Commission of the European Communities DIN Deutsches Institut fur Normung e. V.
Nuclear Standards Catalogue and classification N. Fichtner, K. Becker and M. Bashir
Nuclear Standards Catalogue and classification
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This work was performed for the Commission of the European Communities, Directorate-General Research, Science and Education, Nuclear Plant Safety Division under a study contract granted to the DIN Deutsches Institut fiir N o r m u n g e . V . (Normenausschuß Kerntechnik), Berlin.
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Published for the Commission of the European Communities, Directorate-General Information Market and Innovation, Luxembourg EUR 7135 L E G A L NOTICE Neither the Commission of the European Communities nor any person acting on behalf of the Commission is responsible for the use which might be made of the following information. DK 621.039 : 539.1 : 006 244 Seiten, A 5, brosch. ISBN 3-410-58002-6
© 1 9 8 1 , EGKS, EWG, E A G , Brussel-Luxemburg All rights reserved. No part of this work may be reproduced or utilized in any f o r m or by any means, electrical or mechanical, including photocopying, recording or by any information storage and retrieval system, w i t h o u t written permission f r o m the copyright owner. Zusammengestellt aus der DITR-Datenbank im DIN mit GOLEM (BS 2000) Satzvorbereitung: V T R Verlag fur technische Regelwerke G m b H , Berlin, Rechenzentrum Satzaufbereitung, automatischer Umbruch und Lichtsatz DIGISET: SATZ-RECHEN-ZENTRUM Berlin • Hartmann + Heenemann KG Printed in Germany Druck: Oskar Zach K G , Berlin (West) Buchbinderische Verarbeitung: Reinhart & Wasser, Berlin (West)
Contents Page
Introduction
VII
List of Abbreviations
IX
Organizations and others
IX
Countries
XI
Status Symbols
XI
Classification Index List of standards in order of Classification Index
XII ....
1
Introduction This compilation of all nuclear standards available to the authors by mid 1980 represents the third, carefully revised edition of a catalogue which was first published in 1975 as EUR 5362 entitled "Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants" by M. Bloser, N. Fichtner, and R. Neider. It listed about 1900 documents. A second, updated and more comprehensive edition containing all material available by the end of 1976 appeared 1977 as EUR 5849 with the somewhat modified title "Catalogue and Classification of Technical Safety Standards, Rules and Regulations for Nuclear Power Reactors and Nuclear Fuel Cycle Facilities" by N. Fichtner, K. Becker and M Bashir. It contained 2800 documents, issued by 145 organizations in 31 countries. In this third edition several changes have been made. The title has been condensed. The information has again been carefully up-dated, covering all changes regarding status, withdrawal of old standards, new projects, amendments, revisions, splitting of standards into several parts, combination of several standards into one, etc., as available to the authors by mid 1980. The speed with which information travels varies and requires in many cases rather tedious and cumbersome inquiries. But it is safe to assume that the compilation represents at least the status of the end of 1979 correctly (in some cases changes as late as late-1980 have been considered). Also, the classification scheme has been revised with the goal of better adjustment to changing situations and priorities. Whenever it turned out to be difficult to attribute a standard to a single subject category, multiple listings in all relevant categories have been made As in previous editions, within the subcategories the standards are arranged by organization (in Categorie 2.1 by country) alphabetically and in ascending numerical order. Perhaps most importantly, the physical volume of the compilation was substantially reduced by, for the first time, employing electronic data processing and a light-composing process. This also should reduce the number of errors in manually handling all data, and should make it easier to prepare further up-dated revisions in the future. There is no need to repeat here what already has been said in the introductions of the previous two editions.The purpose and general outline of the catalogue remains the same, namely to provide a current and complete list of all relevant documents from as many countries as possible. Such a compilation should be of great value to those who are developing new standards or harmonizing existing ones, as well as to those who apply them to the construction, operating, licensing, testing, etc., of nuclear facilities, with the practical value of such a list clearly increasing. It covers all relevant areas of power reactors, the fuel cycle, radiation protection, etc., from the basic laws and governmental regulations, regulatory guides, etc., all the way to voluntary industrial standards and codes of pratice, with the implication of decreasing lifetime and legal relevance, but increasing flexibility and technical detail as one moves from the top to the bottom of the "nuclear standards hierarchy" (Fig. 1)
Fig. 1: Hierarchy of Nuclear Standards
VII
Obviously it would far exceed the framework of this introduction to review the current situation of nuclear standardization in various countries, to compare their safety philosophies and technical approaches or to describe various efforts to "harmonize" national nuclear standards into regionally or internationally recognized ones. Only a few facts and trends which help to understand this compilation will, therefore, be briefly mentioned. Both on the national and on the international level, it is now generally accepted that a concise and comprehensive set of nuclear safety standards is required for several reasons, mainly - to simplify, accelerate and standardize the complex licensing process for nuclear facilities, previously primarily for nuclear power plants, but now increasingly also in other areas, such as waste management, reprocessing, non-proliferation and safeguards; - to guarantee the siting, construction, operation and decommissioning of nuclear facilities on a uniformly high safety level according to the latest state of science and technology; and - to take into account excessive public concern about the risks of nuclear power in some of the highly industrialized countries, and improve public acceptance by establishing consensus of all relevant parties involved. There are also several good reasons for the trend of shifting the emphasis from national to international standardization, such as - preventing redundant efforts by expensive and valuable experts (the "cost" of an average nuclear standard including secretariat costs, time and travel of the experts, etc., probably exceeds $ 100.000 in most cases, and may be above one million for large documents); - the increasing across-the-border trade in nuclear fuels, power station components, whole facilities, waste products, etc.; - the large number of nuclear facilities sited close to international borders (for example in Western Europe there are 33, or a quarter of the total number of nuclear power stations planned, under construction or in operation, within 40 km of an international border), and - the need for facilitating nuclear technology transfer to developing countries, keeping in mind that technical standards represent highly condensed know-how,and that the export of nuclear installations from relatively few supplier countries to a large number of user countries is increasing. The efforts for either creating new international standards before there are national ones, or for replacing national ones by a single international, are growing and increasingly successful. (For some recent descriptions of different approaches, see, for example, W. Vinck and W. Essler "Harmonization of Nuclear Regulations in Europe", Nucl. Eng. International., Oct. 1979, p.43 ; K. Becker "ISO International Standard Development for Nuclear Technology", IAEA-CN-39/61, Stockholm 1980, and L Konstantinow et al. "NUSS Program and its Implementation", IAEA-CN-39/53, Stockholm 1980). Therefore, it should be noted with satisfaction that this new compilation contains a larger number of international standards such as the Guides and Codes of Practice developed by the IAEA Nuclear Safety Standards (NUSS) Program; ISO Standards developed by the Technical Committee (TC) 85 "Nuclear Energy" of the International Standards Organization; and Standards of the TC 45 "Nuclear Instrumentation" of the International Electrotechnical Commission (IEC). The compilation also contains some national standards of restricted distribution such as the U.S. RDT (Reactor Development and Technology) Standards developed at ORNL, and the "Weisungsbeschlusse" (guidance codes) of the German independant inspection organization (TUV). It does, however, not contain industrial specification solely for internal use in large cooperations, and rather vague "textbook" documents as they are issued by some organizations. Also, the interpretation of the term "nuclear" has been handled stricter than before, excluding many conventional standards on materials, engineering, etc., even if used in nuclear technology, thus reducing the total number of documents listed to about 2500 (as many documents appear in more than one category, a total of about 4000 entries can be found in this compilation). Care was taken not to change the basic pattern of the classification, but some revisions have been made for clarification, and to adjust to changing situations. It is realized that some classifications, for example in the field of material testing, have been somewhat arbitrary. Best judgement was used in such difficult borderline cases. The remarks used, such as "periodical addenda and revisions provided", "in press", etc., are considered self-explanatory. Lists of abbreviations (countries and institutions; status symbols) follow this introduction.
VIII
An excellent compilation by W.J. Slattery "Index of U.S. Nuclear Standards" (U.S. National Bureau of Standards Publication 483, August 1977) uses a keyword-in-context listing and may, although slightly outdated, be used to supplement this compilation as far as the U.S. standards situation is concerned. Other, earlier U.S. publications, such as a Catalogue of Nuclear Industry Standards (ANSI 1974) and a Compilation of Nuclear Standards (ORNL 1972-73) are, by now, only of historical interest. Unfortunately, the authors have been unable to include the correct English translation of all non-english document titles. In many cases they tried to provide translations, but these should be considered "unofficial" and for guidance only. Whenever possible, the availability of English translations of non-english documents has been indicated. However, as many such translations (also into other languages, such as Spanish, French and Portuguese) are prepared by companies or organizations for their internal use, and their existence and availability is neither announced in the open nor in the "underground" literature, these listings are probably rather incomplete. This introduction is followed by lists of abbreviations for countries and standard-issuing organizations. Of course, with the field still expanding and changing rapidly, the authors anticipate the need for another careful revision of the available material within about two years. All suggestions from readers and users regarding inevitable errors, omissions and other possible improvements are highly appreciated. The assistance of Mr. P. Becker and Mr. Roesler in preparing this compilation is acknowledged with appreciation by the editors.
Berlin, December 1980
Norbert Fichtner Klaus Becker Mohammed Bashir
List of A b b r e v i a t i o n s Organizations and o t h e r s AACC ACI AD AFNOR ANH MRC ANS ANSI ASHRAE ASME ASMW ASNT ASTM AWS B PVC BG BGBI BMI BNS BSI CEA CFR CNBS CNEN CNP CNS CSA
American Association for Contamination Control (USA) American Concrete Institute (USA) Arbeitsgemeinschaft Druckbehalter (DEU) Association Francaise de Normalisation (FRA) Australian National Health and Medical Research Council (AUS) American Nuclear Society (USA) American National Standards Institute (USA) American Society of Heating, Refrigerating and Air-Conditioning Engineers (USA) American Society of Mechanical Engineers (USA) Amt fur Standardisierung, MeBwesen und Warenpriifung (DDR) American Society for Nondestructive Testing (USA) American Society for Testing and Materials (USA) American Welding Society (USA) Boiler and Pressure Vessel Code (USA) Berufsgenossenschaften (DEU) Bundesgesetzblatt (DEU) Bundesministerium des Innern (DEU) Bureau de Normalisation de la Siderurgie (FRA) British Standards Institution (GBR) Commissariat a I'Energie Atomique (FRA) Code of Federal Regulations (USA) Chinese National Bureau of Standards (TWN) Comissao Nacional de Energia Nuclear (BRA) Centro de Normalizacao (PRT) Comite de Normalisation de la Soudure (FRA) Canadian Standard Association (CAN)
IX
DDA Deutscher DampfkesselausschuB (DELI) DEGR Department of the Environment General Regulations (GBR) DERRT Department of the Environment Road and Rail Transport (GBR) DIN Deutsches Institut fur Normung (DEU) EUROVENT European Committee of Air Handling and Air Conditioning Equipment Manufacturers GOST Gosudarstvennyi Komitet Standartov Soveta Ministrov S.S.R. (SUN) IAEA International Atomic Energy Agency ICRP International Commission on Radiological Protection ICRU International Commission on Radiation Units and Measurements IEC International Electrotechnical Commission IEEE Institute of Electrical and Electronics Engineers (USA) IfBT Institut fiir Bautechnik (DEU) ILO International Labour Organization ISO International Organization for Standardization ISO-DIS ISO-Draft International Standard ISO-DP ISO-Draft Proposal ISO-R ISO-Recommendation JEN Junta de Energia Nuclear (ESP) JIS Japanese Standard Association (JPN) KTA Kerntechnischer AusschuB (DEU) LA Lovtidende for Kongeriget (DNK) MB Moniteur Beige (BEL) MSZH Magyar Szabvanyiigyi Hivatal (HUN) MTI Ministry of Trade and Industry (FIN) NARS Nordic Working Group on Reactor Safety NCRP National Council on Radiation Protection and Measurement (USA) NFPA National Fire Protection Association (USA) Nil Nuclear Installation Inspectorate (GBR) NKe NormenausschuB Kerntechnik (DEU) NNI Nederlands Normalisatie instituut (NLD) NPP Nuclear Power Plant OECD Organization for Economic Cooperation and Development ON Osterreichisches Normungsinstitut (AUT) ORNL Oak Ridge National Laboratory (USA) PAEC Pakistan Atomic Energy Commission (PAK) RSK Reaktor-Sicherheitskommission (DEU) SAAEB South African Atomic Energy Board (ZAF) SAAS Staatliches Amt fiir Atomsicherheit und Strahlenschutz (DDR) SEL Stahl-Eisen-Lieferbedingungen (DEU) SEP Stahl-Eisen-Priifblatter (DEU) SEW Stahl-Eisen-Werkstoffblatter (DEU) SFS Swedish Statute Book (SWE) SIS Standardisierungskommissionen Sverige (SWE) SNM Special Nuclear Material SSK Strahlenschutz-Kommission (DEU) TRD Technische Regeln fiir Dampfkessel (DEU) TSE Turk Standardlari Enstitiisu (TUR) UKAEA United Kingdom Atomic Energy Authority (GBR) UL Underwriters Laboratories (USA) USCG United States Coast Guard (USA) USNRC United States Nuclear Regulatory Commission (USA) UVV Unfallverhiitungsvorschriften (DEU) VBG Verband der Berufsgenossenschaften (DEU) VDE Verband Deutscher Elektrotechniker (DEU) VDEh Verein Deutscher Eisenhiittenleute (DEU) VDI Verein Deutscher Ingenieure (DEU) VdS Verband der Sachversicherer (DEU) VdTUV Vereinigung der Technischen Uberwachungsvereine (DEU) VGB Technische Vereinigung der GroBkraftwerksbetreiber (DEU)
Countries AUT BEL BRA CAN CEC CHE CHN CSK DDR DEU DNK ESP FIN FRA GBR HUN INT IRL ITA JPN LUX NLD NZL PAK POL PRT ROM SUN SWE TUR TWN USA VNM YUG ZAF
Austria Belgium Brazil Canada Commission of the European Communities Switzerland China, Peoples Republic of Czechoslovakia German Democratic Republic Germany, Federal Republic of Denmark Spain Finland France United Kingdom Hungary International Ireland Italy Japan Luxemburg Netherlands New Zealand Pakistan Poland Portugal Rumania Union of Soviet Socialist Republics Sweden Turkey Taiwan United States of America Vietnam Yugoslavia South Africa
Status Symbols Amm App Drf Iss Pub Rev Ust
Amendment Approved Draft Issued Published Revision Understudy
XI
Classification I n d e x 1 1.1 1.2
Terms and Classifications General Compilations and Catalogues
2 2.1 2.2
Governmental Laws, Ordinances and Regulations Basic Acts, Regulations, Ordinances, etc. Technical Guides, Criteria, Codes of Good Practice, etc.
3 3.1 3.2 3.3 3.4 3.5
Administrative Procedures General Construction and Operation Decommissioning Qualification, Selection and Training of Personnel Finances and Licensing
4 4.1 4.2 4.3 4.4 4.5 4.6 4.7
Siting and Environmental Protection General Geologic, Seismic and other Considerations Meteorology and Hydrology Non-radiological Environmental Effects Air Pollution, Measurement Water Pollution, Measurement Other Aspects of Environmental Monitoring
5 5.1 5.2 5.3 5.4
Radiation Protection General Radiological Shielding Personnel Monitoring and Protection Devices Stationary Radiation Monitoring Systems
6 6.1 6.2 6.3 6.4 6.5 6.6 6.7
Nuclear Fuel Cycle Mining Enrichment Manufacturing Reprocessing General Aspects of Radioactive Waste Management Treatment of Radioactive Wastes Disposal of Radioactive Wastes
7 7.1 7.2 7.3 7.4 7.4.1 7.4.2 7.4.3 7.4.4
Plant and Reactor Protection General Instrumentation Reactor Protection Systems PlanfProtection Alarm Systems Industrial Security Protection against Fire and Explosions Hazards Emergency Plans
8 8.1 8.2 8.3 8.4 8.5 8.6
Reactor Physics Core and Core Components Critical Experiments, Calculation, Design Reactivity Control, Shut-down Systems Neutron Flux Measurements Fuel Elements and Assemblies Research Reactors
9 9.1 9.2 9.3 94 9.5
Safety and Risk Analysis General Aspects of Safety and Reliability Analysis Boiling Water Reactor Pressurized Water Reactor Gas Cooled Reactor Fast Breeders
X I I
10 10.1 10.2 10.3 10.4 10.5 10.6
Pressure Boundary and Components General and Coolant Circuits Vessels and Boilers Pipes, Tubes and Fittings Pumps and Valves Heater, Heat Exchanger, Pressurizer and Steam Generator Welding
11 11.1 11.2 11.3 11.4 11.5 11.6
Containment General Steel Containment Concrete Containment Leakage Penetrations and Locks Isolation
12 12.1 12.2 123 124 125
Quality Assurance General Construction Operation Cleanliness Protective Coatings, Decontamination
13
Reactor Cooling Systems
14 14 1 14.2 14.3
Ventilation and Air Cleaning General Testing of Systems Filters and Absorbers
15 15.1 15.2 15.3 15.4 155 156 15 7
Nuclear Material Management General Lifting Equipment Handling and Storage Transportation and Packaging Criticality Safety Material Control, Inventory Methods for Analysis, Specifications
16 16.1 16.2 16.3
Electrical Equipment and Systems General Power Sources Insulation and Other Aspects
17 17.1 17.2 17.3 17.4 17.5 17.6 17.7
Testing, Inspection and Surveillance General Pressure Vessels and Boilers Cooling Systems and Components Containment and Installations Electrical Equipment and Instrumentation In-service Surveillance and Recurrent Inspection Pre-operational and Initial Startup Testing
18 18.1 18.2 18.3 18.4 18.5
Material Standards Cooling Systems and Components Pressure Vessels and Boilers Steel Containment Concrete Containment Other Relevant Material Standards
19 19.1 19.2 19.3
Material Test Methods Non-destructive Testing Other Test Methods Metal Test Methods
XIII
1.1
List of standards in order of classification index No. 1
Issuing Body (Country)
Title
Status
(Remarks)
T e r m s anid Classificatio
1.1 General ANS-6.5
ANS
ANS-9 /ANSI N1.1
ANS
ANS-19.2
ANS
ANS-50
ANS
ANSI N15.5 ANSI N15.40
ANSI ANSI
ASTM C 859 BS 1991
ASTM BSI
BS 2597 BS 3455
BSI BSI
BS 3510
BSI
M 60-001
CEA
NF C 01-026
CEA
NF C 01-076
CEA
CNS 3818
CNBS
CNS 3819
CNBS
CNS 3820
CNBS
CNS 3821
CNBS
CNEN NE 0.03
CNEN
NP442
CNP
DIN 2481
DIN
DIN 25401 Teil 1
DIN
DIN 25401 Teil 2 DIN 25401 Teil 3
DIN
DIN 25401 Teil 4
DIN
DIN 25401 Teil 5
DIN
DIN
Glossary of Terms in Shielding and Dosimetry (Issued for Trial Use) Glossary of Terms in Nuclear Science and Technology (Revision of ANSI 1.1-1967) Definition of Reactor Physics Terms and Parameters (Issued for Trial Use) Power Reactor Systems Commitee Glossary of Definitions and Terminology (Issued for Trial Use) Statistical Terminology and Notation Physical Protection of Nuclear Material and Facilities, Definition of Terms (Issued for Comments) Definition of Terms Relating to Nuclear Materials Letter Symbols, Signs and Abbreviations. Part 2: Chemical Engineering, Nuclear Science and Applied Chemistry Glossary of Terms Used in Radiology Glossary of Terms Used in Nuclear Science and Technology A Basic Symbol to Denote the Actual or Potential Presence of Ionizing Radiation Energie nucleaire - Vocabulaire (Nuclear Energy Terminology] Vocabulaire electrotechnique - Groupe 26 Centrales de production d'energie electrique par voie nucleaire Vocabulaire electrotechnique - Groupe 76 Detection et mesure par voie electrique des rayonnements ionisants General Rules for Classification and Numbering System of Nuclear Science Classification and Numbering System of Nuclear Science (Physics and Chemistry] Classification and Numbering System of Nuclear Science (Biology and Medicine) Classification and Numbering System of Nuclear Science (General Engineering) Glossary of Terms in Nuclear Science and Technology (Terms in Portuguese-English-French-German-Spanish) Sinalizacao De Seguranca - Simbolo da radiacao ionizante Warmekraftanlagen, Graphische Symbole (Thermal Power Plants, Graphical Symbols) Kerntechnik; Begriffe, Physikalische und Chemische Grundlagen (Nuclear Technology; Terms and Definitions, Basic Notions of Physics and Chemistry) Kerntechnik; Begriffe, Reaktorauslegung (Nuclear Technology; Terms and Definitions, Reactor Design) Kerntechnik; Begriffe, Reaktortechnik und Betrieb (Nuclear Technology; Terms and Definitions, Reactor Technology and Operation) Kerntechnik; Begriffe, Kernmaterialuberwachung (Nuclear Technology; Terms and Definitions, Nuclear Material Control) Kerntechnik; Begriffe, Brennstoffkreislauf (Nuclear Technology; Terms and Definitions, Fuel Cycle]
Pub
79
App
76
Pub
79
Pub
79
Pub Pub
72 11.79
Pub Pub
78 61
Pub Pub
55 73
Pub
68
Pub
12.74
Pub
74
Pub
71
Iss
7.75
Iss
7.75
Iss
7.75
Iss
7.75
Drf
78
Pub
66
Pub
6.79
Drf
2.79
Drf
2.79
Drf
2.79
Drf
2.79
Drf
2.79
1.1 No.
Issuing Body (Country}
DIN 25401 Teil 6
DIN
DIN 25401 Teil 7
DIN
DIN 25401 Teil 8
DIN
DIN 25404
DIN
DIN 25411
DIN
GO ST 20942 GOST 21440 ICRU Report No. 19 IEC 50(26)
GOST GOST ICRU IEC
IEC 50(65)
IEC
IEC 50(391)
IEC
IEC 50(392)
IEC
IEC 596
IEC
IEEE 380
IEEE
IEEE 505
IEEE
ISO 921
ISO
ISO 921/Add.1
ISO
JIS Z4001 JISZ8101
JIS JIS
JISZ8103 JISZ8115
JIS JIS
JISZ8122 JIS Z8204 JIS Z8205
JIS JIS JIS
MSZ KGST531 MSZ 14345/1 MSZ 14345/2 A 6601 A 9000 SMS 2800 SS-016182
MSZH MSZH MSZH ONORM ONORM SIS SIS
TS 1507 R.G. 5.2
TSE USNRC
R.G. 5.3
USNRC
VDI 3528
VDI
Title (Remarks) Kerntechnik; Begriffe, Isotopentrennung (Nuclear Technology; Terms and Definitions, Isotope Separation) Kerntechnik; Begriffe, Sicherheit kerntechnischer Anlagen (Nuclear Technology; Terms and Definitions, Safety of Nuclear Installations) Kerntechnik; Begriffe, Strahlenschutz (Nuclear Technology; Terms and Definitions, Radiation Protection) Kerntechnik; Formelzeichen (Nuclear Technology; Symbols for Use in Formulae) Kernreaktoren; Sinnbilder (Nuclear Reactors; Graphical Symbols) Kernreaktoren; Bestandteile; Terminologie Kernreaktoren; Klassifikationskriterien Radiation Quantities and Units International Electrotechnical Vocabulary: Nuclear Power Plants for Electric Energy Generation International Electrotechnical Vocabulary: Radiology and Radiological Physics International Electrotechnical Vocabulary: Detection and Measurement of Ionizing Radiation by Electric Means International Electrotechnical Vocabulary: Nuclear Instrumentation - Supplement to Chapter 391 Definitions of Test Method Terms for Semiconductor Radiation Detectors and Scintillation Counting Definitions of Terms Used in IEEE Nuclear Power Generating Station Standards Nomenclature for Generating Station Electric Power Systems Nuclear energy glossary (Under Revision) Nuclear Energy Glossary, Addendum 1 to ISO 921 (Terms in english, french and russian) Glossary of Terms Used in Nuclear Energy Glossary of Terms Used in Quality Control (Available also in English) Glossary of Terms Used in Instrumentation Glossary of Terms Used in Reliability (Available also in English) Glossary of Terms for Contamination Control Instrumentation Symbols Graphical Symbols for Piping (A vailable also in English) Radiation Symbols: Form and Size Nuclear Terminology Nuclear Terminology, Reactor Terms Atomschutz, Begriffe Kerntechnik, Benennungen mit Definitionen Karnenergiordlista (Glossary of Nuclear Energy) Quantities and Units. Nuclear Reactions and Ionizing Radiation Quantities and Units of Atomic and Nuclear Physics Classification of Unirradiated Plutonium and Uranium Scrap Statistical Terminology and Notation for Special Nuclear Materials Control Accountability Regelung und Steuerung von Kernreaktoren; Spezielle Begriffe und Benennungen
Status Drf
2.79
Drf
2.79
Drf
2.79
Pub
9.76
Pub
4.75
Pub Pub Pub Pub
75 75 71 68
Pub
64
Pub
75
Pub
76
Pub
78
Pub
75
Pub
77
Pub
72
Pub
80
Pub Pub
68 63
Pub Pub
78 70
Pub Pub Pub
74 70 59
Pub Pub Pub Iss Pub
77 74 76 8.67 80
Pub
7.79
Iss
12.72
Iss
2.73
Pub
9.72
1.2 No. 1 1.2
*
Issuing Body (Country!
Title
Status
/Remarks)
T e r m s and Classifications C o m p i l a t i o n s and Cataloc ues ACI ACI Publications AD AD-Merkblatter Catalogue des normes francaises AFNOR Publication and Service Catalog of American Nuclear ANS Society Catalog of American National Standards ANSI ASME ASME Publications Catalog ASMW Verzeichnis staatlicher Standards der DDR ASTM Annual ASTM Standards Publications Catalog AWS BMI Handbuch Reaktorsicherheit und Strahlenschutz Teil 1 und 2 British Standards Yearbook BSI DDA Technische Regeln Dampfkessel (TRD] DIN DIN Katalog 1980 mit monatlichen Erganzungsheften GOST Verzeichnis staatlicher Standards der UdSSR IAEA Catalogue of Publications IEC Catalogue of Publications of International Electrotechnical Commission ISO ISO-Catalogue 1980 JIS JIS Yearbook KTA KTA-Verzeichnis Sicherheitstechnischer Regeln NNI NNI Catalogus ONORM ONormen Verzeichnis ORNL Nuclear Standards Transmittal Register over Svensk Standard SIS Regulatory Guide Series; Division 1 to 10 USNRC Code of Federal Regulations; 10 Energy USNRC Verzeichnis der Einzel-Unfallverhutungsvorschriften VBG der BG VDI Verzeichnis der VDI-Richtlinien VdTUV VdTiiV-Merkblatter und VdTuV-Weisungsbeschlusse Kerntechnik
Pub Pub Pub Pub
79 80 80 80
Pub Pub Pub Pub Pub Pub
80 79 79 79 79 80
Pub Pub Pub Pub Pub Pub
80 79 80 77 80 79
Pub Pub Pub Pub Pub Pub Pub Pub Pub Pub
80 79 10.80 78 80 5.80 79 80 79 79
Pub Pub
79 80
2.1 No.
Issuing Body (Country)
Title (Remarks)
2
G o v e r n m e n t a l Laws, Ordinances and Regulations
2.1
Basic A c t s , Re gulatio (A US) (A US) (A US)
Decree of 1966
(BEL)
Decree of 1967
(BEL)
Decree of 1970
(BEL)
Decree of 1972
(BEL)
MB P.3286
(BEL)
MB P.5206
(BEL)
4.118/62 6.189/74 RSC 1952 Ch. 11 RSC 1953 Ch 47 SC 1946 Ch. 37
(BRA) (BRA) (CAN) (CAN) (CAN)
SOR/DORS/74-334
(CAN)
Act of 1959
(CHE)
Art. 24
(CHE)
* *
(CHN)
•
(DDR)
*
(DDR)
•
(DDR)
BGBI. II, S. 41
(DEU)
BGBI. I, S. 173
(DEU)
BGBI. II, S. 173
(DEU)
(CZE)
Status
Ordinances, etc. Atomic Energy Act (1953-1979) Environment Protection (Nuclear Codes) Act 1978 Environment Protection (Alligator Rivers Region) Act 1978 Royal Decree of 17 May 1966 (See "Moniteur Beige ") Royal Decree of 22 May 1967 (See "Moniteur Beige") Royal Decree of 23 December 1970 (See "Moniteur Beige") Royal Decree of 23 May 1972 (See "Moniteur Beige") Loi relative a la protection de la population contre les dangers resultant des radiation ionisantes (See "Moniteur Beige") Arrete royal portant reglement general de la protection de la population et des travailleurs contre ie danger des radiations ionisantes (See "Moniteur Beige") Atomic Law 4.118/62 Atomic Law 6.189/74 Amendment to Act SC 1946 Ch. 37 Amendment to Act SC 1946 Ch. 37 Act Relating to the Development and Control of Atomic Energy (Atomic Energy Control Act) (Amended Several Times) Atomic Energy Control Regulations (Revisions to Act SC 1946 Ch. 37) Loi federale sur I'utilisation pacifique de I'energie atomique et la protection contre les radiations (See "Recueil Officiel") Art. 24 quinquies of the Federal Constitution as Introduced by Federal Order of 20.12.1957 (See "Recueil Officiel") Provisional Decree Concerning Health Protection in Radioactive Work Notification of the Ministries of Chemical Industry and Health Concerning the Control of Radioactive Substances Gesetz iiber die Anwendung der Atomenergie in der DDR - Atomenergiegesetz Verordnung zum Atomenergiegesetz - Einrichtung von Schutzgebieten Verordnung zum Atomenergiegesetz - Haftung fur Strahlenschaden Abfallbeseitigungsgesetz in der Fassung der Bekanntmachung vom 5. Januar 1977 Verordnung zur Ablosung von Verordnungen nach § 24 der Gewerbeordnung vom 27.2.1980; Artikel 1 Verordnung iiber Dampfkesselverordnung - DampfkV) Verordnung zur Ablosung von Verordnungen nach §24 der Gewerbeverordnung vom 27.2.1980; Artikel 4 Verordnung iiber elektrische Anlagen in explosionsgefahrdeten Raumen (ElexV)
Iss Iss
78 78
Iss
5.66
Iss
567
Iss
12.70
Iss
5.72
Iss
4.58
Iss
563
Iss Iss Iss Iss Iss
62 74 52 53 46
Iss
74
Iss
12.59
Iss
12.57
Iss
1.60
Iss
5.56
Iss
3.62
Iss
362
Iss
3.62
Iss
1.77
Iss
2.80
2.80
2.1 No.
Issuing Body (Country}
BGBI. I, S. 173
(DEU)
BGBI. I, S. 173
(DEU)
BGBI. I, S 220
(DEU)
BGBI. I, S 266
(DEU)
BGBI I, S. 273
(DEU)
BGBI. I, S. 306 /BGBI. I, S. 3573
(DEU)
BGBI 1, S. 341 /BGBI. 1, S. 3187 BGBI. 1, S. 721 /BGBI. I, S. 1193 /BGBI. I, S. 373 BGBI. 1, S. 813
(DEU)
BGBI. 1, S.1008
(DEU)
BGBI. I, S. 1017
(DEU)
BGBI. I, S. 1113 /BGBI I, S. 3574
(DEU)
BGBI. I, S. 1119
(DEU)
BGBI. I, S. 1253
(DEU)
BGBI. I, S. 1314 /BGBI. I, S. 613
(DEU)
BGBI I, S. 1502
(DEU)
(DEU) (DEU)
Title
Status
(Remarks)
Verordnung zur Ablosung von Verordnungen nach § 24 der Gewerbeordnung vom 27.2.1980; Artikel 6 Verordnung Liber Anlagen zur Lagerung, Abfullung und Beforderung brennbarer Flussigkeiten zu Lande (Verordnung Liber brennbare Flussigkeiten - VbF| Verordnung zur Ablosung von Verordnungen nach § 24 der Gewerbeordnung vom 27 2.1980; Artikel 2 Verordnung Liber Druckbehalter, Druckgasbehalter und FLillanlagen (Druckbehalterverordnung - DruckbehV) Verordnung Liber die Deckungsvorsorge nach dem Atomgesetz (Atomrechtliche Deckungsvorsorge-Verordnung - AtDeckV] vom 25. Februar 1977 Kostenverordnung zum Atomgesetz vom 24. Marz 1971 Verordnung iiber das Verfahren bei der Genehmigung von Anlagen nach §7 des Atomgesetzes (Atomrechtliche Verfahrensverordnung - AtVfV) vom 18. Februar 1977 Raumordnungsgesetz vom 8. April 1965. zuletzt geandert durch §35 des Bundesnaturschutzgesetzes vom 20. Dezember 1976 Postordnung vom 16. Mai 1963, zuletzt geandert durch Verordnung vom 15. November 1976 Bundes-lmmissionsschutzgesetz - BlmSchG • vom 15. Marz 1974, zuletzt geandert durch Artikel 12 des Gesetzes vom 28 Marz 1980 Gesetz zur Erganzung des Grundgesetzes vom 23. Dezember 1959 Verordnung Liber die Zulassung einer neuen Numerierung der Gefahrenklassen bei der Beforderung gefahrlicher GLiter auf der StraBe vom 22. Juni 1977 Verordnung Liber die Beforderung gefahrlicher GLiter mit Seeschiffen (GefahrgutVSee) vom 5. Juli 1978 Luftverkehrsgesetz (LuftVGI vom 4. November 1968, zuletzt geandert durch §37 des Bundesnaturschutzgesetzes vom 20. Dezember 1976 Verordnung zur EinfLihrung der Verordnung Liber die Beforderung gefahrlicher GLiter auf dem Rhein (ADNR| und Liber die Ausdehnung dieser Verordnung auf die ubrigen BundeswasserstraUen vom 23. November 1971 in der Fassung vom 13. Juni 1977, zuletzt geandert durch die Erste ADNR-Anderungsverordnung vom 27. Dezember 1977 Verwaltungsverfahrensgesetz (VwVfG) vom 25 Mai 1976, zuletzt geandert durch Art. 7 Nr. 4 des Gesetzes vom 2.7.1976 (siehe auch Rundschreiben des Bundesministers des Innern hierzu vom 8. Dezember 1976 - VII 3 130 210/8 -) Gesetz Liber die Aufgaben des Bundes auf dem Gebiet der Seeschiffahrt in der Neufassung vom 30 Juni 1977, geandert durch Artikel 1 des Gesetzes vom 10 Mai 1978 Verordnung Liber die Beforderung gefahrlicher GLiter mit der Eisenbahn (Gefahrengutverordnung-Eisenbahn - GGVE| vom 23. August 1979
Iss
2.80
Iss
2 80
Iss
2.77
Iss
3 71
Iss
2.77
Iss 4 65 Amm 12 76 Iss 5.63 Amm 11.76 Iss 3 74 Amm 12.76 Amm 3.80 Iss 12.59 Iss
6.77
Iss
7.78
Iss 11.68 Amm 12.76 Iss 11.71 Amm 12.77
Iss Amm
5.76 7.76
Iss Amm
6.77 5.78
Iss
8.79
2.1 No.
Issuing Body (Country)
BGBI 1, S. 1509
(DEUI
BGBI. 1, S. 1609
(DEUj
BGBI. 1, S 1885 /BGBI. I, S. 965
(DEU)
BGBI. 1. S 1885
(DEU)
BGBI 1, S. 2044
(DEU)
BGBI 1, S. 2121 /BGBI. I, S. 373
(DEU)
BGBI. 1, S. 2478
(DEU)
BGBI I., S. 2573
(DEU)
BGBI I., S. 2905 /BGBI. 1, S. 184, 269 /BGBI. I. S. 1509
(DEU)
BGBI. I,, S. 3017 /BGBI. I, S. 3341 /BGBI I. S. 373
(DEU)
BGBI. I, S. 3053 /BGBI. I, S. 3281 /BGBI. I, S. 373 /BGBI. I, S. 1556
(DEU)
BGBI. I, S. 3162
(DEU)
BGBI. 1. S 3574
(DEU)
BGBI. III, S. 165 /BGBI. 1, S. 373
(DEU)
BGBI. II, S. 357
(DEU)
BGBI. II. S. 375
(DEU)
Title
Status
(Remarks)
Verordnung iiber die Beforderung gefahrlicher Guter auf der StraSe (GefahrgutVStr) vom 23. August 1979 Verordnung fiber Ausnahmen von der Verordnung iiber die Beforderung gefahrlicher Giiter auf der StralSe (StraBen-Gefahrgutausnahmeverordnung) vom 2. Oktober 1979 Gesetz iiber Betriebsarzte, Sicherheitsingenieure und andere Fachkrafte fur Arbeitssicherheit vom 12. Dezember 1973, zuletzt geandert durch Gesetz vom 12. April 1976 Drittes Gesetz zur Anderung des Atomgesetzes vom 15. Juli 1975 Verordnung zur Einfiihrung der Verordnung iiber die Beforderung gefahrlicher Giiter auf der Mosel vom 20. Dezember 1971 Gesetz uber die Beforderung gefahrlicher Giiter vom 6. August 1975, zuletzt geandert durch Artikel 15 des Gesetzes vom 28. Marz 1980 Verordnung zur Durchfiihrung des Gesetzes zu den Ubereinkommen vom 15. Februar 1972 und 29. Dezember 1972 zur Verhiitung der Meeresverschmutzung durch das Einbringen von Abfallen durch Schiffe und Luftfahrzeuge (Hohe-See-Einbringungsverordnung) vom 7. Dezember 1977 Viertes Gesetz zur Anderung des Atomgesetzes vom 30. August 1976 Verordnung iiber den Schutz vor Schaden durch ionisierende Strahlen (Strahlenschutzverordnung StrlSchV) vom 13. Oktober 1976, zuletzt geandert durch die Verordnung iiber die Beforderung gefahrlicher Giiter auf der StraSe (GefahrgutVStr) vom 23. August 1979 (BGBI. I, S. 1509) Gesetz zur Ordnung des Wasserhaushalts - WHG vom 27. Juli 1957 in der Fassung der Bekanntmachung vom 16. Oktober 1976, zuletzt geandert durch Artikel 7 des Gesetzes vom 28. Marz 1980 Gesetz uber die friedliche Verwendung der Kernenergie und den Schutz gegen ihre Gefahren (Atomgesetz) in der Fassung der Bekanntmachung vom 31. Oktober 1976, zuletzt geandert durch das Gesetz zur Anderung von Kostenvorschriften des Atomgesetzes vom 20. August 1980 Gesetz zur Anderung des Dritten Gesetzes zur Anderung des Atomgesetzes vom 19. Dezember 1975 Gesetz iiber Naturschutz und Landschaftspflege (Bundesnaturschutzgesetz - BNatSchG) vom 20. Dezember 1976 Gesetz zu dem Ubereinkommen vom 15. Februar 1972 und 29. Dezember 1972 zur Verhiitung der Meeresverschmutzung durch das Einbringen von Abfallen durch Schiffe und Luftfahrzeuge vom 11. Februar 1977, zuletzt geandert durch Artikel 11 des Gesetzes vom 28. Marz 1980 Gesetz zu dem Internationalen Ubereinkommen vom 7. Februar 1970 uber den Eisenbahnfrachtverkehr (CIM)vom 26. April 1974 (See also BGBI. II. S. 381, 488, 552) Bekanntmachung iiber den Geltungsbereich des Ubereinkommens iiber die zivilrechtliche Haftung bei der Beforderung von Kernmaterial auf See vom 9.4.1979
Iss
8.79
Iss
10.79
Iss 1273 Amm 4.76 Iss
7.75
Iss
12 71
Iss Amm
8 75 3 80
Iss
12 77
Iss
8.76
Iss 10.76 Amm 12.77 Amm 8.79
Iss 7 57 Amm 12 76 Amm 3.80 Iss 10.76 Amm 12.76 Amm 3.80 Amm 8 80 Iss
12.75
Iss
12.76
Iss Amm
2.77 3.80
Iss
4.74
Iss
4.79
2.1 No.
Issuing Body (Country)
BGBI. II, S. 430
(DEU)
BGBI. II, S. 569
(DEU)
BGBI. II, S. 778 /BGBI. II, S. 150
(DEU)
BGBI. II, S. 957
(DEU)
BGBI II, S. 1286
(DEU)
BGBI. II, S. 1489 /BGBI. II, S. 1190 /BGBI. II, S. 133
(DEU)
BGBI. Ill, GInr. 934-1 /BGBI. I, S. 1506
(DEU)
Act No 94
(DNK)
Act of 1976
(DNK)
Decree No. 192
(DNK)
Ley 25/1964
(ESP)
•
(ESP)
MTI 7/73 MTI 74/77 MTI 75/58 MTI 75/77
MTI (FIN) MTI (FIN) MTI (FIN) MTI (FIN)
Title
Status
(Remarks)
Elfte Verordnung Ciber Ausnahmen von den Vorschriften der Anlagen A und B zum Europaischen Ubereinkommen iiber die internationale Beforderung gefahrlicher Giiter auf der StraFJe (11. ADR-AusnahmeV) vom 18. Mai 1979 mit den vorangehenden Verordnungen (See also BGBI. II, S. 1489) Verordnung iiber die Einfuhrung einer neuen Numerierung der Gefahrenklassen bei der Beforderung gefahrlicher Giiter im internationalen StrafSen- und Eisenbahnverkehr vom 22. Juni 1977 Internationale Ordnung fur die Beforderung gefahrlicher Guter mit der Eisenbahn (RID) in der Fassung der Verordnung iiber die Inkraftsetzung der Neufassung 1977 der Anlage I (RID) des Internationalen Ubereinkommens iiber den Eisenbahnfrachtverkehr (RID-NeufassungsV) vom 9. September 1977, geandert durch die 2. RID-Anderungsverordnung vom 26. Februar 1980 Gesetz zu den Pariser und Briisseler Atomhaftungsiibereinkommen vom 8. Juli 1975 Bekanntmachung iiber den Geltungsbereich des Europaischen Ubereinkommens iiber die internationale Beforderung gefahrlicher Giiter auf der StralSe vom 16. November 1979 (See also BGBI. II, S 1489) Gesetz zu dem Europaischen Ubereinkommen vom 30. September 1957 iiber die internationale Beforderung gefahrlicher Giiter auf der StralSe (ADR| vom 18. August 1969 sowie Anlagen A und B in der Fassung der Verordnung iiber die Inkraftsetzung der Neufassung 1977 der Anlagen A und B zum ADR (ADR-NeufassungsV) vom 4. November 1977, zuletzt geandert durch die 2. ADR-Anderungsverordnung vom 26. Februar 1980 Eisenbahn-Verkehrsordnung, veroffentlicht in der bereinigten Fassung im BGBI. Ill, Gliederungsnummer 934-1, zuletzt geandert durch die 85. Verordnung zur Anderung der Eisenbahn-Verkehrsordnung vom 23. August 1979 Lov om brug m.v. of radioaktive stoffer (See "LA. p. 193") Act of May 12, 1976: Lov om sikkerhedsmaessige og miljomaessige forhold ved stomanlaeg m.v. Bekendtgorelse om sikkerheds foranstaltninger ved brug m.v. af radioaktive stoffer (See "LA. p.545") Ley 25/1964, de 29 de Abril, sobre energia nuclear (Nuclear Energy Act of 29 April, 1964) (See "Boletin Oficial No. 107") Reglamento sobre instalaciones nucleares y radioactivas (Regulation on Nuclear and Radioactive Installations) (See "Boletin Oficial No. 255") MTI 7/73 Atomic Energy Act Amendment
Iss
5.79
Iss
6.77
Iss Amm
9.77 2.80
Iss
7.75
Iss
11.79
Iss 8.69 Amm 11.77 Amm 2.80
Iss Amm
9 38 8.79
Iss
3.53
Iss
5.76
Iss
6.55
Iss
4.64
Iss
7.72
Iss
73
MTI 74/77 Atomic Energy Act Amendment
Iss
77
MTI 75/58 Atomic Energy Statute
Iss
58
MTI 75/77 Atomic Energy Statute Amendment
Iss
77
2.1 No. MTI 356/57
Issuing Body (Country)
Act No. 58-881
MTI (FIN) MTI (FIN) MTI (FIN) (FRA)
Act No. 520
(FRA)
MTI 555/73 MTI 735/70
Act of 1932
(FRA)
Act of 1937
(FRA)
Decret 58.1458
(FRA)
Decret 61.842
(FRA)
Decret 63.1228 /Decret 73.405
(FRA)
Decret 66 450
(FRA)
Decret 73.278
(FRA)
Decret 74 945
(FRA)
Decret 74.1181
(FRA)
Decret 75.306
(FRA)
Decret 75.713
(FRA)
*
(FRA)
•
(FRA)
(FRA)
Title
Status
(Remarks) MTI 356/57 Atomic Energy Act
Iss
57
MTI 555/73 Atomic Energy Statute Amendment
Iss
73
MTI 735/70 Atomic Energy Statute Amendment Act No. 58-881 of September 24, 1958 (Amendment to Act of 1917) (See "Journal Officiel") Act No. 520 of November 21, 1942 (Amendment to Act of 1917) (See "Journal Officiel") Act of April 20, 1932 (Amendment to Act of 1917) (See "Journal Officiel") Loi du 19 decembre 1917 relative aux etablissements dangereux insalubres ou incommodes (Amended Several times. See "Journal Officiel") Decree No. 58-1458 of December 27, 1958 (Amendment to Act of 1917) (See "Journal Officiel") Loi No 61-842 du 2 aout 1961 relative a la lutte contre les pollutions atmospheriques et les odeurs et portant modification de la loi du 19.12.1917 (See "Journal Officiel") Decret 63-1228 du 11 decembre 1963, relatif aux installations nucleaires de base, modifie par le decret 73-405 du 27 mars 1973 (See "Journal Officiel") Principes generaux de protection contre les rayonnements ionisants (See "Journal Officiel") Decret No 73-278 du 13 mars 1973 portant creation d'un conseil superieur de la surete nucleaire et d'un service central de surete des installations nucleaires (See "Journal Officiel") Rejets d'effluents radioactifs gazeux provenant des installations nucleaires de base et des installations nucleaires implantees sur le meme site (See "Journal Officiel") Rejets d'effluents radioactifs liquides provenant d'installations nucleaires (See "Journal Officiel") Protection des travailleurs contre les dangers des rayonnements ionisants dans les installations nucleaires de base (See "Journal Officiel") Decret No 75-713 du 4 aout 1975 instituant un comite interministeriel de la securite nucleaire (See "Journal Officiel") Arrete du 16 decembre 1965 fixant les caracteristiques des accelerateurs de particules en tant qu'installations nucleaires de base Arrete du 6 decembre 1966 fixant les cas dans lesquels les usines de preparation, de fabrication ou de transformation de substances radioactives sont placees hors du champ d'application du decret No 63-1228 d u l l decembre 1963 Arrete du 25 Janvier 1967 fixant les limites au-dela desquelles les installations destinees au stockage, au depot ou a I'utilisation de substances radioactives sont considerees comme installations nucleaires de base
Iss Iss
70 9.58
Iss
11.42
Iss
4.32
Iss
12.17
Iss
12.58
Iss
8.61
Iss 12.63 Amm 3.73 Iss
6.66
Iss
3.73
Iss
11.74
Iss
12.74
Iss
4.75
Iss
12.65
Iss
12.66
Iss
1.67
2.1 No.
Issuing Body (Country)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
*
(FRA)
Title /Remarks) Arrete du 10 aout 1976 relatif aux conditions dans lesquelles doit etre effectuee I'etude preliminaire en vue de la demande d'autorisation de rejet d'etfluents radioactifs gazeux provenant des installations nucleases Arrete du 10 aout 1976 relatif aux rejets d'effluents radioactifs gazeux provenant des installations nucleases et conditions de I'enquete publique prevues par I'article 5 du decret No 74-945 du 6 novembre 1974 Arrete du 10 aout 1976 relatif aux conditions dans lesquelles doit etre effectuee I'etude preliminaire en vue de la demande d'autorisation de rejet d'effluents radioactifs liquides provenant des installations nucleaires Arrete du 10 aout 1976 relatif aux regies generales applicables a la fixation des limites et modalites de rejet des effluents radioactifs liquides provenant des installations nucleaires, choix des mesures de surveillance de leur environnement et modalites de leur controle par le service central de protection contre les rayonnements ionisants, pris en application de I'article 16 du decret no 74-1181 du 31 decembre 1974 Arrete du 10 aout 1976 relatif aux regies propres aux centrales nucleaires de puissance equipees de reacteurs a eau ordinaire applicables aux limites et modalites de rejet de leurs effluents radioactifs liquides, mesures de surveillance de leur environnement et controle par le service central de protection contre les rayonnements ionisants Arrete du 7 juillet 1977 pris en application de I'article 18 du decret No 75-306 du 28 avril 1975, fixant pour les installations nucleaires de base, les seuils et les modalites de signalisation des zones specialement reglementees ou interdites a I'interieur de chaque zone controlee Arrete du 8 juillet 1977 pris en application de I'article 23 du decret No 75-306 du 28 avril 1975, approuvent les methodes de controle elaborees par le service central de protection contre les rayonnements ionisants Arrete du 6 octobre 1977 pris en application de I'article 10 du decret No 75-306 du 28 avril 1975 definissant les caracteristiques de chaque type d'installation nucleaire de base Arrete du 7 octobre 1977 pris en application de I'article 24 du decret No 75-306 du 28 avril 1975, fixant la periodicite des controles effectues dans les installations nucleaires de base Arrete du 10 octobre 1977 pris en application de I'article 40 du decret No 75-306 du 28 avril 1975, fixant les mesures particulieres de securite applicables a certaines installations nucleaires de base Arrete du 11 octobre 1977 pris en application de I'article 40 du decret No 75-306 du 28 avril 1975, fixant les mesures generales de securite applicables aux fluides, dechets radioactifs et combustibles irradies ou non dans les installations nucleaires de base Transport et manutention de matieres dangereuses: annexe a I'arrete du 24 juin 1974
Status Iss
8 76
Iss
8.76
Iss
8.76
Iss
8 76
Iss
8 76
Iss
7.77
Iss
7.77
Iss
10.77
Iss
10 77
Iss
10.77
Iss
10.77
Iss
6.74
2.1 No.
Issuing Body (Country)
*
(FRA)
Act 1954 Act 1965 Act 1969 Act 1971 Reg. No. 780
IGBR) (GBR) (GBR) (GBR) (GBR)
SI 62/2641
DEGR (GBR) DEGR (GBR) DEGR (GBR) DEGR (GBR) DEGR (GBR) DEGR (GBR) DEGR (GBR) DEGR (GBR) DEGR (GBR) DERRT (GBR) DERRT (GBR) DERRT (GBR) DERRT (GBR) (INT)
SI 62/2643 SI 62/2646 SI 62/2649 SI 62/2711 SI 62/2712 SI 62/6710 SI 63/1834 SI 1067 BR 22426 SI 1735 SI 1827
* *
(INT)
(INT) (INT) (INT) 80/836/Euratom
CEC (INT)
Agreement No. 115
ILO (INT) OECD (INT)
10
Title
Status
(Remarks)
Transport de matieres radioactives: arrete du 1er juillet 1966 Atomic Energy Authority Act 1954 Nuclear Installations Act 1965 Nuclear Installations Act 1969 Atomic Energy Authority Act 1971 The Ionizing Radiations (Unsealed Radioactive Substances) Regulations The Radioactive Substances (Civil Defense) Exemption Order 1962 The Radioactive Substances (Test Instruments) Exemption Order 1962 The Radioactive Substances (Storage in Transit) Exemption Order 1962 The Radioactive Substances (Lead) Exemption Order 1962 The Radioactive Substances (Prepared Uranium and Thorium Conpounds) Exemption Order 1962 The Radioactive Substances (Geological Specimens) Exemption Order 1962 The Radioactive Substances (Uranium and Thorium) Exemption Order 1962 The Radioactive Substances (Thorium-X) Exemption Order 1963 The Merchant Shipping 1965 (Dangerous Goods) Rules Amended by 1968 SI 332, and 1972 SI 666 Dangerous Goods and Conditions of Acceptance for Carriage by Freight Train and Passenger Train Radioactive Substances (Carriage by Road) Regulations The Radioactive Substances (Road Transport Workers) Regulations The Nuclear Installations (Insurance Certificate) Regulations Internationales Ubereinkommen uber den Eisenbahnfrachtverkehr (CIM) vom 7. Februar 1970 mit Zusatzprotokoll International Regulation for the Transport of Dangerous Goods by Rail; Version of the Ordernance on the Implementation of the New1977 Issue of Appendix I regarding the International Treaty on Transport of Goods by Rail Paris Agreement of July 29, 1960, on the Third-party. Liability in the Field of Nuclear Energy Brussels Additional Agreement of Jan. 31, 1963, to the Paris Agreement of July 29, 1960 on the Third-Party Liability in the Field of Nuclear Energy Brussels Agreement of Dec. 12, 1971, Regarding the Civil-law. Liability During the Transport of Nuclear Material on Sea Richtlinie des Rates vom 15. Juli 1980 zur Anderung der Richtlinien, mit denen die Grundnormen fur den Gesundheitsschutz der Bevolkerung und der Arbeitskrafte gegen die Gefahren ionisierender Strahlungen festgelegt wurden (Revision of the Basic Regulation 76/579/Euratom) Ubereinkommen Nr. 115 der Internationalen Arbeitsorganisation vom 22. Juni 1960 liber den Schutz der Arbeitnehmer vor ionisierenden Strahlen Bekanntmachung der geanderten Fassung der Grundnormen fur den Strahlenschutz der Organisation fur wirtschaftliche Zusammenarbeit und Entwicklung (OECD)
Iss
7.66
Iss Iss Iss Iss Iss
54 65 69 71 68
Iss
62
Iss
62
\£s
62
Iss
62
Iss
62
Iss
62
Iss
62
Iss
63
Iss Amm Iss
65 72 66
Iss
70
Iss
70
Iss Amm App
65 71 2.70
App 9.77 Amm 10.78
App
7.60
App
1.63
App
12.71
App
7.80
App
6.60
App
4.70
2.1 No.
Issuing Body (Country)
•
IIRLj
Act No. 393
(ITA)
Act No. 933
(ITA)
Act No. 1240
(ITA)
Act No. 1860
(ITA)
Decree No. 185
(ITA)
Decree No. 1704
(ITA)
Cabinet Order No 324
(JPN)
Law No. 166
(JPN)
Law No. 186 Notification No. 21
(JPN) (JPN)
Order of Prime Min. Office No. 83 I.O.(1963)p.227
(JPN) (LUX)
l.0.(1967)p.142
(LUX)
Staatsblad Nr. 82
(NLD)
Staatsblad Nr 403
(NLD)
1965/23
(NZL)
1973/48 1973/51
(NZL) (NZL)
1973/89 1974/116 1974/318
(NZL) (NZL) (NZL)
1977/171
(NZL) PAEC (PAK)
Title
Status
(Remarks)
An tacht urn Fhuinneamh Nuicleach (Nuclear Energie Act 1971) Rules Governing the Location of Nuclear Power Stations and the Production and Use of Electricity (See "Gazzetta Ufficiale No. 224") Act No 933 of 11 August 1960 (See "Gazzetta Ufficiale No. 218") Act No. 1240 of 15 December 1971 (amending Act No. 933) (See 'Gazzetta Ufficiale of 1972") Act No. 1860 of 31 December 1962 (See "Gazzetta Ufficiale No. 27") Decree No. 185 of the President of Republic on the Safety of Installations and the Health Protection of Workers and the Population Against the Hazards of Ionizing Radiations Resulting from Peaceful Use of Nuclear Energy (See "Gazzetta Ufficiale No. 95") Decree No. 1704 of the President of Republic (Amendment to Act No. 1860) (See "Gazzetta Ufficiale No. 112") Executive Order for Law for Regulation of Nuclear Source Material Nuclear Fuel Material and Reactors Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors Atomic Energy Basic Law Notification Concerning Determination of Maximum Permissible Doses, Concentration Pursuant to Provisions Given in Regulation Regulation for the Establishment, Operation of Nuclear Reactors Loi du 25 mars 1963 concernant la protection de la population contre les dangers resultant des radiations ionisantes (Journal Officiel of 10 April 1963, p.227) Reglement grand-ducal du 8 fevrier 1967 portant sur I'execution de la loi du 25 mars 1963 concernant la protection de la population contre les dangers resultant des radiation ionisantes (Journal Officiel of 8 March 1967, p. 142) Wet van 21 februari 1963, houdende regelen met betrekking tot de vrijmaking van kernenergie en de aanwending van radiactieve stoffen en ioniserende stralen uitzendende toestellen (Kernenergiewet) (Staatsblad van net Koninkrijk der Nederlanden 1963, No. 82) Besluit van 4 September 1969 tot uitvoering van de artikelen 16,17,19, eerste lid, en 21 van de Kernenergiewet (Besluit kerinstallaties, splijtstoffen en ersten) (Staatsblad 1969, No. 403} An Act to Consolidate and Amend the Radioactive Substances Act 1949 The Radiation Protection Regulations The Transport of Radioactive Materials Regulations 1973 An Act to Amend the Radiation Protection Act 1965 An Act to Amend the Radiation Protection Act 1965 The Radiation Protection Regulations 1973, Amendment No. 1 An Act to Amend the Radiation Protection Act 1965 Radiation Protection Regulation
Iss
71
Iss
4.75
Iss
8.60
Iss
12.71
Iss
1262
Iss
2.64
Iss
5.66
App
11.57
App
10.57
App App
12.55 9.60
App
12.57
Iss
63
Iss
67
Iss
63
9.69
Iss
9.65
Iss Iss
373 373
Iss Iss Iss
11.73 11.74 12.74
Iss Iss
12.77 70
2.1 No.
*
Issuing Body (Country)
Dz.U.(1968)20
PAEC (PAK) PAEC (PAK) (POL)
Dz.U.(1968)27
(POL)
Resolution 741 Resolution 965
(ROM) (ROM)
Resolution 966
(ROM)
Resolution 1149
(ROM)
Act No. 110/1958
(SWE)
Act No. 306/1956
(SWE)
SFS 1940:383
(SWE)
SFS 1947:385 SFS 1956:306
(SWE) (SWE)
SFS 1958:110 SFS 1958:652
(SWE) (SWE)
SFS 1959:612
(SWE)
SFS 1960:75
(SWE)
SFS 1960:331
(SWE)
SFS 1960:422
(SWE)
SFS 1960:423
(SWE)
SFS 1960:682
(SWE)
SFS 1961:457
(SWE)
SFS 1961:558 SFS 1963:115
(SWE) (SWE)
•
12
Title
Status
(Remarks)
Regulation on Transportation of Radioactive Material
Iss
70
Nuclear Safety and Radiation Protection Ordinance
Iss
72
Decree of Council of Ministers Concerning Occupational Safety and Hygiene in the Application of Ionizing Radiation Decree of the Ministers of Transport and of the Interior Concerning the Road Traffic Regulations Operation of Nuclear Radiation Sources Organizing the Labour Protection and Hygienic and Antiepidemic Measures in the Romanian Peoples Republic - Labour Protection in Case of Handling of Ionizing Rays Approval of the Regulations Concerning the Registration and Supervision of Labour-Accidents and Occupational Diseases as Well as Securing and Utilizing the Fund for Labour Protection- Annex 1, No. 8- Diseases Caused by Ionizing Radiations etc. Annex 2, No 15- Labour Protection in Case of Handling of Radioactive Substances Criteria for the Determination of Working Places With Special Conditions for Which a Supplementary Leave is Granted - Art 2 No. la Workmen Who are Exposed to the Effects of Radioactive Rays Stralskyddslag (Radiation Protection Act) (See "Svensk Forfattingssamling") Lag om raett att utvinna atomenergi m m . atomenergilag (Atomic Energy Act) (See "Svensk Forfattingssamling") Royal Decree Concerning Enforcement of the Law of 17 May 1940 (No. 358) with Certain Provisions for the Protection of the Defence etc. (Security Decree) Building Act (Especially Sections 81, 82 and 136a) Law Concerning the Right to Exploit Atomic Energy etc. (Atomic Energy Act) Radiation Protection Act Royal Decree with Enforcement Directives for the Radiation Protection Act Building Code, with Amendments (Especially Section 17 Subsection 4, Section 24 Subsection 1 and Section 56 subsection 3) Law Concerning Amendment of the Law of 17 May 1940 (No. 358) with Certain Provisions for the Protection of the Defence Law Concerning Safety Measures in the Event of Accidents in Nuclear Facilities etc. Law Concerning Amendment of Text of Sections 7 and 8 of the Atomic Energy Act of 1 June 1956 (No. 306) Law Concerning Amendment of the Radiation Protection Act of 14 March 1958 (No. 110) (Amendment of Sections 23, 26 and 27) Law Concerning Amendment of Section 1 of the Law of 1 June 1956 (No. 306) Concerning the Right to Exploit Atomic Energy etc. (Atomic Energy Act) Royal Decree Concerning Compensation for Participation in Safety Work in the Event of Accidents in Nuclear Facilities etc. Air Freight Decree (Sections 107 - 108) Law Concerning Extended Vacation for Certain Employees in Radiological Occupations
Iss
6.68
Iss
7.68
App App
11.61 12.64
App
12.64
App
5.6
Iss
3.58
Iss
6.56
Iss
40
Iss Iss
47 56
Iss Iss
58 58
Iss
59
Iss
60
Iss
60
Iss
60
Iss
60
Iss
60
Iss
61
Iss Iss
61 63
2.1 Issuing Body
No.
(Country)
SFS 1964:101
(SWE)
SFS 1964:209
(SWE)
SFS 1965:237
(SWE)
SFS SFS SFS SFS
1965:719 1966:202 1968:45 1968:46
(SWE) (SWE) (SWE) (SWE)
SFS 1969:387 SFS 1969:388 SFS 1969:389
(SWE) (SWE) (SWE)
SFS 1970:670
(SWE)
SFS 1970:749
(SWE)
SFS 1971:617
(SWE)
SFS 1971:1154 SFS 1971:1156 SFS 1972:164
(SWE) (SWE) (SWE)
SFS 1972:179
(SWE)
SFS 1973 847
(SWE)
SFS 1973:1004
(SWE)
SFS 1974:35
(SWE)
SFS 1974:38
(SWE)
SFS 1974:80 SFS 1974:115
(SWE) (SWE)
SFS 1974:249
(SWE)
SFS 1974:268
(SWE)
SFS 1974:411
(SWE)
SFS 1974:412
(SWE)
SFS 1974:427
(SWE)
Title
Status
(Remarks)
Law Concerning Amendment of Section 1 of the Law (1963:115) Concerning Extended Vacation for Certain Employees in Radiological Occupations Law concerning Amendment of Sections 7 and 11 of the Atomic Energy Act of 1 June 1956 (No. 306) Royal Decree Concerning Amendment of the Decree of 19 December 1958 (No. 652) with Enforcement Directives for the Radiation Protection Act (Amendment of Sections 1 and 3-5) Law Concerning the Safety on Board Ship Royal Railway Traffic Statut (Chapter 4) Nuclear Liability Act Royal Decree with Proclamations in Accordance with the Nuclear Liability Act of 8 March 1968 (No. 45) Environment Protection Act (with Amendments) Royal Environment Protection Decree Royal Instructions for the National Franchise Board for Environmental Protection (with Amendments) Law Concerning Amendment of the Radiation Protection Act (1958:110) (Amendment of Section 2) Royal Decree with Certain Permissions in Accordance with the Atomic Energy Act (1956:306) Law Concerning Amendment of the Radiation Protection Act (1958:110) (Amendment of Section 29) Law Concerning Ban on Dumping of Waste in Water Royal Dumping Decree Royal Edict with Instructions for the National Board of Occupational Safety and Health (with Amendments) Law Concerning Amendment of the Atomic Energy Act (1956:306) (Amendment of Section 3) Royal Edict with Instructions for the Labour Inspectorate (with Amendments) Law Concerning Amendment of the Radiation Protection Act (1958:110) (Amendment of Sections 2 and 22) Royal Decree Concerning International Road Transport of Hazardous Goods Royal Decree Concerning Amendment of the Decree (1958:652) with Enforcement Directives for the Radiation Protection Act (Amendment of Section 5) Fire Act (Section 21) Edict Concerning Amendment oft Decree (1974:35) Concerning International Road Transport of Hazardous Goods Law Concerning Amendment of Nuclear Liability Act (1968:45) (Amendment of Sections 3, 14 and 15 and New Section 14a) Law Occasioned by the Environment Protection Convention of 19 February 1974 Between Denmark, Finland, Norway and Sweden Royal Decree Concerning Compensation for Participation in Rescue Service etc. Royal Decree Concerning Amendment of the Decree (1961:457) Concerning Compensation for Participation in Safety Work in the Event of Accidents in Nuclear Facilities etc. (Introduction of New Section 6a with Application of Section 21 of the Fire Act (1974:80) and in the Decree (1974:411)) Royal Instructions for the National Power Inspection Board
Iss
64
Iss
64
Iss
65
Iss Iss Iss Iss
65 60 68 68
Iss Iss Iss
69 69 69
Iss
70
Iss
70
Iss
71
Iss Iss Iss
71 71 72
Iss
72
Iss
73
Iss
73
Iss
74
Iss
74
Iss Iss
74 74
Iss
74
Iss
74
Iss
74
Iss
74
Iss
74
13
2.1 No.
Issuing Body (Country)
SFS 1974:429
(SWE)
SFS 1974:430
(SWE)
SFS 1974:610 SFS 1974:706
(SWE) (SWE)
SFS 1974:748
(SWE)
SFS 1974:847
(SWE)
SFS 1974:890 SFS 1974:893
(SWE) (SWE)
SFS 1975:20
(SWE)
SFS 1975:368
(SWE)
SFS 1975:369
(SWE)
SFS 1975:421
(SWE)
SFS 1975:459
(SWE)
SFS 1975:706
(SWE)
SFS 1975:745
(SWE)
SFS 1976:6
(SWE)
SFS 1976:12
(SWE)
SFS 1976:245
(SWE)
SFS 1976:246
(SWE)
SFS 1976:247
(SWE)
SFS 1976:248
(SWE)
SFS 1976:249
(SWE)
14
Title
Status
(Remarks)
Royal Decree Concerning Change of Name of the Swedish Atomic Energy Board Royal Decree concerning Amendment of Decree (1968:46) with Proclamations in Accordance with the Nuclear Liability Act of 8 March 1968 (No 45) (Substitution in Sections 3, 5 and 7 of "Swedish Nuclear Inspection Board" for "Swedish Atomic Energy Board") Law Concerning Domestic Road Transport Royal Decree Concerning Entering into Effect of Certain Part of Nuclear Liability Act Royal Decree concerning International Railway Transport Edict Concerning Amendment of the Royal Railing Traffic Statut (1966:202) Law Concerning Certain Mineral Deposits Royal Decree Concerning Certain Mineral deposits (with Amendment) Edict Concerning Ban on Export of Equipment or Material for Exploitation of Atomic Energy etc. Edict Concerning Date of Effectiveness of Law (1974:249) Concerning Amendment of Nuclear Liability Act (1968:45) Edict Concerning Amendment of Decree (1968:46) with Proclamations in Accordance with the Nuclear Liability Act of 8 March 1968 (No. 45) (Repeal of Section 2) Edict Concerning Certain Fees to be Paid to the National Nuclear Power Inspection Board Law Concerning Amendment of the Building Act (1947:385) (Amendment of, Inter Alia, Section 136a) Law Concerning Amendment of Atomic Energy Act (1956:306) (Amendment of Sections 1-3, 5 and 11-13 and Repeal of Section 14) Law Concerning Amendment of the Law (1974:268) Occasioned by the Environmental Protection Convention of 19 February 1974 Between Denmark, Finland, Norway and Sweden (Amendment of Section 2) Law Concerning Measures against Water Pollution from Ships within the Baltic Sea Area Edict Concerning Supervisory Authority in Accordance with the Provisions fo the Atomic Energy Act (1956:306) etc. Law Concerning Amendment of the Radiation Protection Act (1958:110) (Amendment of Sections 1, 5, 23-25, 28) Edict Concerning Amendment of Decree (1958:652) with Enforcement Directives for the Radiation Protection Act (Modification of Heading, Introduction of two New Sections 4 and 5 and Change of Sections 4 and 5 to Sections 6 and 7) Edict Concerning Certain Fees to be Paid to the National Institute of Radiation Protection Edict Concerning Enforcement of the Law (1974:268) Occasioned by the Environment Protection Convention of 19 February 1974 Between Denmark, Finland, Norway and Sweden Edict Concerning Entering into Effect of the Law (1974:268) Occasioned by the Environment Protection Convention of 19 February 1974 Between Denmark, Finland, Norway and Sweden
Iss
74
Iss
74
Iss Iss
74 74
Iss
74
Iss
74
Iss Iss
74 74
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
76
Iss
76
Iss
76
Iss
76
Iss
76
Iss
76
Iss
76
2.1 No.
Issuing Body (Country)
SFS 1976:409
(SWE)
SFS 1976:481
(SWE)
SFS 1976:570
(SWE)
SFS 1976:960
(SWE)
SFS 1977:140
(SWE)
SFS 1977:173
(SWE)
SFS 1977:231
(SWE)
SFS 1977:254
(SWE)
SFS 1977:277
(SWE)
SFS 1977:288
(SWE)
SFS 1977:328
(SWE)
SFS 1977:481
(SWE)
SFS 1977:1160 SFS 1977:1166 SFS 1978:209
(SWE) (SWE) (SWE)
SFS 1978:254
(SWE)
SFS 1978:255
(SWE)
SFS 1978:281
(SWE)
SFS 1978 282
(SWE)
SFS 1978:335
(SWE)
SFS 1978.686
(SWE)
Title
Status
(Remarks)
Edict Concerning Amendment of the Royal Railing Traffic Statut (1966:202) Edict with Instructions for the National Institute of Radiation Protection Edict Concerning Entering into Effect of the Law (1976:61 Concerning Measures against Water Pollution from Ships within the Baltic Sea Area Edict Concerning Amendment of the Edict (1976.481) with Instructions for the National Institute of Radiation Protection (Amendment of Sections 4, 5, 13, 19, 20 and 23 - 25) Law Concerning Special Permission to Charge Nuclear Reactors with Nuclear Fuel, etc. Edict Concerning Amendment of the Edict (1976:247) Concerning Certain Fees to be Paid to the National Institute of Radiation Protection (Amendment of Section 1) Edict Concerning Amendment of the Instructions (1974:427) for the National Nuclear Power Inspection Board (Amendment of Sections 7 and 8) Edict Concerning Amendment of Edict (1975:20) Concerning Ban on Export of Equipment or Material for Exploitation of Atomic Energy etc. Law Concerning Amendment of the Law (1960:331) Concerning Safety Measures in the Event of Accidents in Nuclear Facilities etc. (Amendment of Section 8) Edict Concerning Amendment of Decree (1961:457) Concerning Compensation for Participation in Safety Work in the Event of Accidents in Nuclear Facilities etc. (Amendment of Sections 2 and 4) Edict Concerning Amendment of the Edict (1976:247) Concerning Certain Fees to be Paid to the National Institute of Radiation Protection (Amendment of Section 1) Law Concerning Amendment of the Law (1963:115) Concerning Extended Vacation for Certain Employees in Radiological Occupations (Amendment of Sections 1 and 3) Working Environment Act Working Environment Edict Edict Concerning Amendment of the Edict (1976:247) Concerning Certain Fees to be Paid to the National Institute of Radiation Protection (Amendment of Section 1) Edict Concerning Amendment of the Radiation Protection Edict (1958:652) (Amendment of Section 4) Edict Concerning Amendment of the Edict (1976:481) with Instructions for the National Institute of Radiation Protection (Amendment of Section 12) Law Concerning Amendment of the Atomic Energy Act (1956:306) (Amendment of Section 2) Law Concerning Amendment of the Law (1940:35) with Certain Provisions for the Protection of the Defence etc. Edict Concerning Amendment of the Decree (1974.35) Concerning International Road Transport of Hazardous Goods Edict Concerning Amendment of the Edict (1975:421) Concerning Certain Fees to be Paid to the National Nuclear Power Inspection Board (Amendment of Sections 1-8.)
Iss
76
Iss
76
Iss
76
Iss
76
Iss
77
Iss
77
Iss
77 77
Iss
77
Iss
77
Iss
77
Iss
77
Iss Iss Iss
77 77 78
Iss
78
Iss
78
Iss
78
Iss
78
Iss
78
Iss
78
15
2.1 No.
Issuing Body (Country)
SFS 1979:119
(SWE)
SFS 1979:335
(SWE)
SFS 1979:353
(SWE)
SSI FS 1977:2
(SWE)
(SWE)
* *
46 CFR 55 46 CFR 146 RSC-1960 10 CFR 20 10 CFR 20 Appendix B 10 CFR 50 10 CFR 50 Appendix A 10 CFR 50 Appendix B 10 CFR 50 Appendix C
(USA) (USA) USCG (USA) USCG (USA) USNRC (USA) USNRC (USA) USNRC (USA) USNRC (USA) USNRC (USA) USNRC (USA) USNRC (USA)
10 CFR 50 Appendix D USNRC (USA) 10 CFR 50 Appendix E USNRC (USA) 10 CFR 50 Appendix F USNRC (USA) 10 CFR 50 Appendix G USNRC (USA) 10 CFR 50 Appendix H USNRC ' (USA) 10 CFR 50 Appendix I USNRC (USA) 10 CFR 50 Appendix J
USNRC (USA) 10 CFR 50 Appendix K USNRC (USA) 10 CFR 50 Appendix L USNRC (USA) 16
Title (Remarks) Edict Concerning Amendment of the Decree (1974:35) Concerning International Road Transport of Hazardous Goods Law Concerning Ban on Right During a Certain Period of Time to Charge Nuclear Reactors with Nuclear Fuel Edict Concerning Amendment of the Edict (1976:247) Concerning Certain Fees to be Paid to the National Institute of Radiation Protection (Amendment of Section 1) Regulations issued by the National Institute of Radiation Protection for the Limitation of the Releases of Radioactive Substances from Nuclear Power Stations Law Concerning Amendment of the Radiation Protection Act (1958:110) (Amendment of Sections 23 and 28) Atomic Energy Act of 1954 Energy Reorganization Act of 1974, Title II Nuclear Power Plant Components Transportation or Storage of Explosives or Other Dangerous Articles or Substances and Combustible Liquids Onboard Vessels Atomic Energy Control Act Standards for Protection against Radiation Concentrations in Air and Water Above Natural Background Domestic Licensing of Production and Utilization Facilities General Design Criteria for Nuclear Power Plants Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants A Guide for the Financial Data and Related Information Required to Establish Financial Qualification for Facility Construction Permits and Operating Licenses (Reserved) Emergency Plans for Production and Utilization Facilities Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities Fracture Toughness Requirements Reactor Vessel Material Survillance Program Requirements Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet Criterion "As Low as Practicable" for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors ECCS Evaluation Models Information Requested by the Attorney General for Antitrust Review Facility License Applications
Status Iss
79
Iss
79
Iss
79
Iss
77
Iss Iss
54 74
No.
Issuing Body (Country)
10 CFR 50 Appendix M USNRC (USA) 10 CFR 50 Appendix N USNRC (USA) 10 CFR 50 Appendix 0
USNRC (USA) 10 CFR 50 Appendix Q USNRC (USA) 10 CFR 51 USNRC (USA) 10 CFR 51 Appendix A USNRC (USA) 10 CFR 55 USNRC (USA) 10 CFR 70 USNRC (USA) 10 CFR 71 USNRC (USA) 10 CFR 71 Appendix A USNRC (USA) 10 CFR 71 Appendix B USNRC (USA) 10 CFR 71 Appendix C USNRC (USA) 10 CFR 71 Appendix D USNRC (USA) 10 CFR 71 Appendix E USNRC (USA) 10 CFR 73 USNRC (USA) 10 CFR 73 Appendix A USNRC (USA) 10 CFR 73 Appendix B USNRC (USA) 10 CFR 73 Appendix C USNRC (USA) 10 CFR 81 USNRC (USA) 10 CFR 100 USNRC (USA) 10 CFR 100 Appendix A USNRC (USA) 10 CFR 110 USNRC (USA) 10 CFR 110 Appendix A USNRC (USA) 10 CFR 110 Appendix B USNRC (USA) 10 CFR 110 Appendix C USNRC (USA) 10 CFR 140 USNRC (USA) 10 CFR 150 USNRC (USA) 10 CFR 160 USNRC (USA) USNRC (USA)
Title
(Remarks)
Standardization of Design; Manufacture of Nuclear Power Reactors; Construction and Operation of Nuclear Power Reactors Manufactured Pursuant to Commission License Standardization of Nuclear Power Plant Designs: Licenses to Construct and Operate Nuclear Power Reactors of Duplicate Design at Multiple Sites Standardization of Design; Staff Review of Standard Designs Pre-application Early Review of Site Suitability Issues Licensing and Regulatory Policy and Procedures for Environmental Protection Requalification Programs for Licensed Operators of Production and Utilization Facilities Operator's Licenses Domestic Licensing of Special Nuclear Material Packaging of Radioactive Material for Transport and Transportation of Radioactive Material under certain Conditions Normal Conditions of Transport Hypothetical Accident Conditions Transport Grouping of Radionuclides Tests for Special Form Licensed Material Quality Assurance Criteria for Shipping Packages for Radioactive Material Physical Protection of Plants and Materials United States Nuclear Regulatory Commission Inspection and Enforcement Regional Offices General Criteria for Security Personnel Licensee Safeguards Contingency Plans Standard Specifications for the Granting of Patent Licenses Reactor Site Criteria Seismic and Geologic Siting Criteria for Nuclear Power Plants Export and Import of Nuclear Equipment and Material List of Nuclear Equipment and Material under NRC Export/Import Licensing Authority List of Foreign Facilities to which Nuclear Equipment May be Exported Pursuant to the General License in § 110.21 (Reserved) Categorization of Nuclear Material Financial Protection Requirements and Indemnity Agreements Exemptions and Continued Regulatory Authority in Agreement States under Section 274 Trespassing on Commission Property National Environmental Policy Act of 1969
Sta
2.1 Issuing Body (Country)
§ § § S
^
Order No. 10-VHXH/NTLC Order No. 62-VHXH/ND Order No. 1065-ND/LD Leg. Series 1952 No. 11
(VNM) (VNM) (VNM)
^
Decree No. 006-66 Decree No. 26-TTP Decree No. 43-SL/GD
^
No.
Leg. Series 1965 No. 10
(YUG)
Leg. Series 1965 No. 12 Leg. Series 1965 No. 17
(YUG)
Leg. Series 1965 No. 31/1199
(YUG)
Leg. Series 1965 No. 31/1200
(YUG)
Leg. Series 1965 No. 31/1201
(YUG)
Leg Series 1970 No. 20
(YUG)
Leg Series 1970 No. 32 OGSFRY 12/65
(YUG)
18
(YUG)
(YUG)
Title (Remarks) Protection Against Ionizing Radiation Regulations for the Use of Radioactive Substances Regime of Risk Compensation, Sick Leave, Leave of Long Duration, Disability Pension and Compensation for Accidental Death for the Benefit of Staff Steadily Working in Places Using Sources of Ionizing Radiation Regulations for the Use of Trade in, Transfer and Storage of Sources of Ionizing Radiation Safety Standards to be Applied in the Operation of Undertakings Using Sources of Ionizing Radiation Compensation for Occupational Diseases etc. -Diseases Caused by Ionizing Radiation Decree Prohibitting the Employment of Women and Young Persons on Certain Type of Work - Work with Radioactive Radiation and X-Rays Basic Act Concerning Sanitary Inspection (Art 2, 3, 13 and 14) Sources of Ionizing Radiation, Location and Construction Plans for Installations for the Production and Application of Nuclear Energy (Replaced by Act of 30.06 71) Air Traffic Act. (Art 150: Minimum Distance Between Aerodromes and Nuclear Installations) Basic Act Concerning Labour Regulations (Art 37, Subarticle 2 and Art 63, Subarticle 3: Work Subject to Effects of Ionizing Radiation) Regulation Concerning the Permissible Doses of Ionizing Radiation to Which Persons Working With Sources of Such Radiation May be Exposed Regulation Concerning the Technical Training of Persons Working With Sources of Ionizing Radiation and Carrying Out Activities in Connection With Protection Against Such Radiation Regulation Concerning the Putting in Circulation and Handling of Radioactive Substances With an Activity Above a Certain Limit and the Protection Measures Against the Radiation from Such Sources Regulation Concerning the Carriage of Dangerous Goods by Road (Art 2, Class IVb: Radioactive Substances) Public Health Act (Art 3, 31, 51, 52 and 55: Protection Against Ionizing Radiation) Basic Law on Protection Against Radiation
Status Iss Iss Iss
3.66 1.59 4.71
Iss
1.67
Iss
3.67
Iss
6 66
Iss
3.52
Iss Amm
165 6.71
Iss
3.65
Iss
4.65
Iss
6.65
Iss
6.65
Iss
6.65
Iss
4.70
Iss
7.70
Iss
65
2.2 No. 2
Issuing Body (Country)
Title (Remarks)
Status
G o v e r n m e n t a l Laws, O r d i n a n c e s and Regulations
2.2 Technical Guides, Criteria, Codes of Good Practice, etc. ANS-4.1 ANS Criteria for Preparation of Design Bases for Systems that Perform Protective Functions in Nuclear Power Generating Stations ANS-10 2 ANS Recommended Programming Practices to Facilitate Interchange of Digital Computer Programs ANS-15.15 ANS Criteria for the Reactor Safety Systems of Research Reactors ANS-51.1 ANS Nuclear Safety Criteria for the Design of Stationary /ANSI N18.2 Pressurized Water Reactor Plants (See also ANS-51.8) ANS-51.7 ANS Single Failure Criteria for PWR Fluid Systems /ANSI N658 (See also ANS 58.9) ANS-51 8 ANS Nuclear Safety Criteria for the Design of Stationary /ANSI N18.2a Pressurized Water Reactor Plants, Section 2 2 and Section 2 3 (Revision to ANSI NI82) ANS-52.1 ANS Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants ANS-53 1 ANS Nuclear Safety Criteria for the Design of Stationary /ANSI N213 Gas Cooled Reactor Plants ANS-54.1 ANS LMFBR General Design Criteria (Draft for Comments) ANS-58.4 ANS Criteria for Technical Specification for Nuclear Power Stations ANS-58.9 ANS Single Failure Criteria for Light Water Reactor Safety Related Fluid Systems (Revision of ANS 51.7 and ANSI N658) ANSI N101.3 ANSI Guide to Principal Design Criteria Nuclear Fuel Reprocessing Facilities B PVC Sec I ASME Boiler and Pressure Vessel Code; Power Boilers (Regular Addenda and Revisions Provided) B PVC Sec II ASME Boiler and Pressure Vessel Code; Material Specifications, Part A - Ferrous Materials, Part B • Nonferrous Materials, Part C - Welding Rods, Electrodes and Filler Metals (Regular Addenda and Revisions Provided) B PVC Sec.Ill Div.l ASME Boiler and Pressure Vessel Code; Division I: Subsection NB - Class 1 Components, Subsection NC - Class 2 Components, Subsection ND • Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG - Core Support Structures, Appendices (Regular Addenda and Revisions Provided) B PVC Sec III Div II ASME Boiler and Pressure Vessel Code; Code for Concrete Reactor Vessels and Containments (Regular Addenda and Revisions Provided) B PVC Sec.IV ASME Boiler and Pressure Vessel Code; Heating Boilers (Regular Addenda and Revisions Provided) B PVC Sec.V ASME Boiler and Pressure Vessel Code; Nondestructive Examination (Regular Addenda and Revisions Provided) B PVC Sec.VI ASME Boiler and Pressure Vessel Code; Recommended Rules for Care and Operation of Heating Boilers (Regular Addenda and Revisions Provided) B PVC Sec VII ASME Boiler and Pressure Vessel Code; Recommended Rules for Care of Power Boilers (Regular Addenda and Revisions Provided) B PVC Sec.VIM ASME Boiler and Pressure Vessel Code; Pressure Vessels (Regular Addenda and Revision Provided)
Pub
78
Pub
71
Pub
78
App
73
App
76
App
75
Pub
78
Pub Drf
78 4.77
Pub
79
Pub
79
Pub
73
Iss
74
Iss
74
Iss
74
Iss
74
Iss
74
Iss
74
Iss
74
Iss
74
2.2 No.
Issuing Body (Country)
B PVC Sec.lX
ASME
B PVC Sec.X
ASME
B PVC Sec.XI
ASME
BAnz. Nr. 58/80
BMI
BAnz. Nr. 179/76
BMI
BAnz. Nr. 206/77
BMI
BMI RS I-6/76
BMI
BMI RS 11-1
BMI
BMI RS II-5
BMI
GMBI. 1975 S. 602
BMI
GMBI. 1976 S 166
BMI
GMBI. 1976 S. 168
BMI
GMBI. 1976 S. 199
BMI
GMBI. 1976 S. 418
BMI
GMBI. 1976 S. 445
BMI
GMBI. 1977 S. 48
BMI
20
Title
Status
(Remarks)
Boiler and Pressure Vessel Code; Welding and Brazing Qualifications (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Fiberglass-Reinforced Plastic Pressure Vessels (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Rules for Inservice Inspection of Nuclear Power Plant Components (Regular Addenda and Revisions Provided) Grundsatze zur Entsorgungsvorsorge fiir Kernkraftwerke vom 19.3.1980 Richtlinie fiir den Schutz von Kernkraftwerken gegen Druckwellen aus chemischen Reaktionen durch Auslegung der Kernkraftwerke hinsichtlich ihrer Festigkeit und induzierten Schwingungen sowie durch Sicherheitsabstande vom 13.9.1976 Sicherheitskriterien fiir Kernkraftwerke vom 21.10.1977 Richtlinie fiir den Fachkundenachweis von Forschungsreaktorpersonal vom 18.3.1976 Regelung der Rechtsetzungskompetenzen bei der Befbrderung radioaktiver Stoffe und Regelung der Zustandigkeitsverteilung bei der Aufsicht iiber die Beforderung radioaktiver Stoffe Grundsatze fiir die arztliche Uberwachung von . beruflich strahlenexponierten Personen Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Priifung erforderlichen Informationen iiber den Standort, den Sicherheitsbehalter, das Reaktorschutzsystem und den Reaktordruckbehalter vom 30.7.1975 (Withdraw: directions to reactor protection system and reactor pressure vessel, see GMBI. 1977 S. 66 and GMBI. 1977 S. 739) Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Prufung erforderlichen Informationen iiber die Notstromversorgung vom 24.3.1976 Auslegungsrichtlinien und -richtwerte fur Jod-Sorptionsfilter zur Abscheidung von gasformigem Spaltjod in Kernkraftwerken vom 25.2.1976 Richtlinien iiber die Anforderungen an Sicherheitsspezifikationen fur Kernkraftwerke vom 27.4.1976 Merkpostenaufstellung mit Gliederung fiir einen Standardsicherheitsbericht fiir Kernkraftwerke mit Druckwasserreaktor oder Siedewasserreaktor vom 26.7.1976 Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Prufung erforderlichen Informationen iiber die Einbauten des Reaktordruckbehalters und die Einbauten des Sicherheitsbehalters vom 4.8.1976 (withdraw: directions to reactor pressure vessel, see GMBI. 1977 S. 661) Empfehlungen zur Planung von NotfallschutzmaBnahmen durch Betreiber von Kernkraftwerken vom 27.12.1976 (See also GMBI. 1977 S. 664)
Iss
74
Iss
74
Iss
74
Iss
3.80
Iss
9.76
Iss
10 77
Iss
3.76
Iss
78
Iss
7.75
Iss
3.76
Iss
2.76'
Iss
4.76
Iss
7.76
Iss
8.76
Iss
12.76
2.2 No.
Issuing Body (Country)
GMBI. 1977 S. 66 /GMBI. 1977 S. 108
BMI
GMBI. 1977 S. 108
BMI
GMBI. 1977 S. 661
BMI
GMBI. 1977 S. 664
BMI
GMBI. 1977 S. 683
BMI
GMBI. 1977 S. 739
BMI
GMBI. 1977 S. 739
BMI
GMBI 1978 S. 294
BMI
GMBI. 1978 S. 313
BMI
GMBI. 1978 S 342
BMI
GMBI 1978 S 348
BMI
GMBI. 1978 S. 418
BMI
GMBI. 1978 S. 426
BMI
GMBI. 1978 S. 431
BMI
GMBI. 1978 S. 598
BMI
Title (Remarks) Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber das Reaktorschutzsystem vom 20.1.1977, berichtigt am 7.3.1977 Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber den Reaktorkern sowie die Steuer- und Abschaltsysteme vom 22.3.1977 Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fCir Kernkraftwerke zur Prufung erforderlichen Informationen uber die Einbauten des Reaktordruckbehalters vom 12.10.1977 Anderung der Empfehlungen zur Planung von NotfallschutzmalSnahmen durch Betreiber von Kernkraftwerken vom 18.10.1977 (See also GMBI. 1977 S. 48) Rahmenempfehlungen fur den Katastrophenschutz in der Umgebung kerntechnischer Anlagen vom 17.10.1977 Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber das Druckhalte- und Abblasesystem (DWR| vom 21.11.1977 Richtlinien (iber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber den Reaktordruckbehalter vom 25.11.1977 Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen iiber die liiftungstechnischen Anlagen, die Not- und Nachkiihlsysteme einschliefslich Nachkuhlkette und Rohrleitungen, Pumpen und Armaturen des Hauptkiihlkreises vom 17.5.1978 Kontrolle der Eigeniiberwachung radioaktiver Emissionen aus Kernkraftwerken vom 10.5.1978 Richtlinie fur das Verfahren zur Vorbereitung und Durchfiihrung von Instandhaltungs- und Anderungsarbeiten in Kernkraftwerken vom 1.6.1978 Richtlinie fur die physikalische Strahlenschutzkontrolle (§§ 62 und 63 StrlSchVI vom 5.6.1978 Richtlinie fur den Stahlenschutz des Personals bei der Durchfiihrung von Instandhaltungsarbeiten in Kernkraftwerken mit Leichtwasserreaktor: Die wahrend der Planung der Anlage zu treffende Vorsorge, vom 10.7.1978 Genehmigungen gemaU § 20a Strahlenschutzverordnung vom 18.7.1978 Richtlinie fiir den Inhalt der Fachkundepriifung des verantwortlichen Schichtpersonals in Kernkraftwerken vom 10.8.1978 Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Prufung erforderlichen Informationen iiber das Druckabbausystem (DAS) bei Siedewasserreaktoren, die Dampferzeuger und Systeme zur Handhabung und Lagerung sonstiger radioaktiver Stoffe vom 30.10.1978
Status Iss Amm
1.77 377
Iss
3.77
Iss
10.77
Iss
10.77
Iss
10 77
Iss
11.77
Iss
11.77
Iss
5.78
Iss
5.78
Iss
6.78
Iss
6.78
Iss
7.78
Iss
7.78
Iss
8.78
Iss
10.78
21
2.2 No.
Issuing Body (Country)
GMBI 1978 S. 631
BMI
GMBI. 1979 S. 91
BMI
GMBI. 1979 S. 120
BMI
GMBI. 1979 S. 161
BMI
GMBI. 1979 S. 233
BMI
GMBI. 1979 S. 238
BMI
GMBI. 1979 S. 371
BMI
GMBI. 1979 S 668
BMI
GMBI. 1980 S. 90
BMI
GMBI. 1980 S. 92
BMI
Urn we It Nr. 43/75
BMI
Umwelt Nr 61/78
BMI
BS 3895
BSI
BS 4891 DD 13
BSI BSI
DD 15
BSI
DD 16
BSI
22
Title
Status
(Remarks)
Interpretation zu den Sicherheitskriterien fur Kernkraftwerke, Einzelfehlerkonzept, vom 26.10.1978 Genehmigungen gemaB §3 Abs. 1 StrlSchV oder §6 AtG fOr die Zwischenlagerung von abgereichertem bzw. natiirlichem und angereichertem Uran in Form von Uranhexafluorid (UF6); hier: Genehmigungsvoraussetzungen und Auflagen vom 15.2.1979 Richtlinien iiber Pmffristen bei Dichtheitsprufungen an umschlossenen radioaktiven Stoffen vom 23.3.1979 Interpretationen zu den Sicherheitskriterien fur Kernkraftwerke vom 17.5.1979 1. Interpretation zu dem Sicherheitskriterium 2.6: "Einwirkungen von auBen" 2. Interpretation zu dem Sicherheitskriterium 8.5: "Warmeabfuhr aus dem SicherheitseinschluB" Richtlinie fur den Fachkundenachweis von Kernkraftwerkspersonal vom 17.5.1979 Richtlinie fur Programme zur Erhaltung der Fachkunde des verantwortlichen Schichtpersonals in Kernkraftwerken vom 17.5.1979 Allgemeine Berechnungsgrundlagen fur die Strahlenexposition bei radioaktiven Ableitungen mit der Abluft oder in Oberflachengewasser (Richtlinie zu §45 StrlSchV) vom 15.8.79 Richtlinie zur Emissions- und Immissionsuberwachung kerntechnischer Anlagen Interpretationen zu den Sicherheitskriterien fur Kernkraftwerke vom 28.11.1979 1. Interpretation zu dem Sicherheitskriterium 2.2: "Prufbarkeit" 2. Interpretation zu dem Sicherheitskriterium 2.3: "Strahlenbelastung in der Umgebung" 3. Interpretation zu dem Sicherheitskriterium 2.6: "Einwirkungen von auBen" 4. Interpretation zu dem Sicherheitskriterium 2.7: "Brand- und Explosionsschutz" 5. Interpretation zu dem Sicherheitskriterium 4.3: "Nachwarmeabfuhr nach Kiihlmittelverlusten" Richtlinie fur den Inhalt der Fachkundepriifung des verantwortlichen Schichtpersonals in Forschungsreaktoren vom 30.11.1979 Bewertungsdaten fur die Eigenschaften von Kernkraftwerksstandorten aus der Sicht von Reaktorsicherheit und Strahlenschutz vom 11.6.1975 Leitsatze fur die Unterrichtung der Offentlichkeit iiber die Katastrophenschutzplanung in der Umgebung von kerntechnischen Anlagen vom 10.2.1978 Guide to the Design, Testing and Use of Packaging for the Safe Transport of Radioactive Materials A Guide to Quality Assurance Guide on the Assessment of Reliability of Engineering Equipment and Parts Guide on the Production, Flow, Analysis and Interpretation of Reliability data for Engineering Equipment and Parts Guide on the Reliability of Engineering Equipment and Parts. Practical examples of DD 10 to DD 15
Iss
10.78
Iss
2 79
Iss
3.79
Iss
5 79
Iss
5.79
Iss
5.79
Iss
8.79
Iss
79
Iss
11.79
Iss
11.79
Iss
6.75
Iss
2.78
Pub
76
Pub Pub
72 74
Pub
74
Pub
76
2.2 No.
Issuing Body (Country)
M 62-101
CEA
CNEN NE 1.02 CSA Z299.1 CSA Z299.2 CSA Z299.3 CSA Z299.4
CNEN CSA CSA CSA CSA DERRT
•
DERRT
•
DERRT
IAEA 50-C-D
IAEA
IAEA 50-C-G
IAEA
IAEA 50-C-O
IAEA
IAEA 50-C-QA
IAEA
IAEA 50-C-S
IAEA
IAEA50-SG-D1
IAEA
IAEA50-SG-D2 IAEA50-SG-D3
IAEA IAEA
IAEA 50-SG-D4
IAEA
IAEA50-SG-D5
IAEA
IAEA 50-SG-D6
IAEA
IAEA 50-SG-D7A
IAEA
IAEA 50-SG-D8 IAEA50-SG-D9
IAEA IAEA
IAEA50-SG-D10
IAEA
IAEA50-SG-D11 IAEA50-SG-G1
IAEA IAEA
IAEA 50-SG-G2
IAEA
IAEA 50-SG-G3
IAEA
IAEA 50-SG-G4
IAEA
IAEA50-SG-G6
IAEA
IAEA 50-SG-G8
IAEA
IAEA 50-SG-G9
IAEA
Title
Status
(Remarks)
Principes fondamentaux de protection dans la conception et la construction des installations dans lesquelles sont utilisees des sources radioactives non scellees (Basic Principles for Safety in the Design and Construction of Installations in wich Unsealed Radioactive Sources are Used) General Design Criteria for Fuel Reprocessing Plants Quality Assurance Program Requirements Quality Control Program Requirements Quality Verification Program Requirements Inspection Program Requirements Code of Practice for the Carriage of Radioactive Materials by Road Code of Practice for the Storage of Radioactive Material in Transit Code of Practice for Conveyance Through Ports of Radioactive Materials Design for Safety of Nuclear Power Plants, Code of Practice Governmental Organization for the Regulation of Nuclear Power Plants, Code of Practice Safety in Nuclear Power Plant Operation, Including Commissioning and Decommissioning, Code of Practice Quality Assurance for Safety in Nuclear Power Plants, Code of Practice Safety in Nuclear Power Plant Siting, Code of Practice Safety Functions and Component Classification for BWR, PWR and PTR Fire Protection in Nuclear Power Plants Protection Systems and Related Features in Nuclear Power Plants Protection against Internally Generated Missiles and their Secondary Effects in Nuclear Power Plants Man-Induced Events in Relation to Nuclear Power Plant Design Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants Emergency Electrical Power Systems at Nuclear Power Plants Instrumentation and Control of Nuclear Power Plants Design Aspects of Radiological Protection for Operational States of Nuclear Power Plants Fuel Handling and Storage Systems in Nuclear Power Plants General Design Safety Principles Qualifications and Training of Staff of the Regulatory Body for Nuclear Power Plants Information to be Submitted in Support of Licensing Applications for Nuclear Power Plants Conduct of Regulatory Review and Assessment During the Licensing Process for Nuclear Power Plants Inspection and Enforcement by the Regulatory Body for Nuclear Power Plants Preparedness of Public Authorities for Emergencies at Nuclear Power Plants Licences for Nuclear Power Plants: Content, Format and Legal Considerations Establishment and Purpose of Regulations and Guides by the Regulatory Body
Pub
870
Iss Iss Iss Iss Iss Iss
79 78 79 79 79 71
Iss
70
Iss
66
Pub
78
Pub
78
Pub
78
Pub
78
Pub
78
Pub
79
Pub Ust
79
Ust Ust Ust Ust Ust Ust Ust Ust Pub
79
Pub
79
Ust Ust Ust Ust Ust
23
2.2 No.
Issuing Body (Country)
IAEA 50-SG-QA1
IAEA
IAEA 50-SG-QA2
IAEA
IAEA 50-SG-QA3
IAEA
IAEA 50-SG-QA4
IAEA
IAEA 50-SG-QA5
IAEA
IAEA 50-SG-QA6
IAEA
IAEA 50-SG-QA7
IAEA
IAEA 50-SG-QA8
IAEA
IAEA 50-SG-QA10 IAEA 50-SG-QA11
IAEA IAEA
IAEA 50-SG-S1
IAEA
IAEA 50-SG-S2
IAEA
IAEA 50-SG-S3
IAEA
IAEA 50-SG-S4
IAEA
IAEA 50-SG-S5
IAEA
IAEA50-SG-S6
IAEA
IAEA50-SG-S9 IAEA50-SG-S10A
IAEA IAEA
IAEA50-SG-S10B
IAEA
IAEA50-SG-S11
IAEA
IAEA 50-SG-01
IAEA
IAEA 50-SG-02 IAEA 50-SG-03
IAEA IAEA
IAEA 50-SG-04 IAEA 50-SG-05
IAEA IAEA
IAEA 50-SG-06
IAEA
IAEA 50-SG-07 IAEA 50-SG-08
IAEA IAEA
IAEA 50-SG-09
IAEA
IEEE 279 /ANSI N42.7 IEEE 308 /ANSI N41.12 IEEE 381
IEEE
IEEE 565
IEEE
24
IEEE IEEE
Status
Title (Remarks) Preparation of the Quality Assurance Programme for Nuclear Power Plants Quality Assurance Records Systems for Nuclear Power Plants Quality Assurance in the Procurement of Items and Services for Nuclear Power Plants Quality Assurance During Site Construction of Nuclear Power Plants Quality Assurance During Operation of Nuclear Power Plants Quality Assurance in the Design of Nuclear Power Plants Quality Assurance Organization for Nuclear Power Plants Quality Assurance in the Manufacture of Items for Nuclear Power Plants Quality Assurance Auditing for Nuclear Power Plants Quality Assurance in the Procurement, Design and Manufacture of Nuclear Fuel Assemblies Earthquakes and Associated Topics in Relation to Nuclear Power Plant Siting Seismic Analysis and Testing of Nuclear Power Plants Atmospheric Dispersion in Relation to Nuclear Power Plant Siting Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution Extreme Man-Induced Events in Relation to Nuclear Power Plant Siting Hydrological dispersion of Radioactive Material in Relation to Nuclear Power Plant Siting Site Survey for Nuclear Power Plants Determination of Design Basis Floods for Nuclear Power Plants on River Sites Determination of Design Basis Floods for Nuclear Power Plants on Coastal Sites Evaluation of Extreme Meteorological Events for Nuclear Power Plant Siting Staffing of Nuclear Power Plants and Recruitment, Training and Authorization of Operating Personnel In-Service Inspection for Nuclear Power Plants Operational Limits and Conditions for Nuclear Power Plants Commissioning Procedures for Nuclear Power Plants Radiological Protection During Operation of Nuclear Power Plants Preparedness of the Operating Organization for Emergencies at Nuclear Power Plants Maintenance of Nuclear Power Plants Standard Tests of Important Systems and Components in Nuclear Power Plants Management of Nuclear Power Plants for Safe Operation Criteria for Protection Systems for Nuclear Power Generating Stations Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations Standard Criteria for Type Tests of Class 1E Modules Used in Nuclear Power Generating Stations Recommended Practice for the Design of Display and Control Facilities for Central Control Rooms of Nuclear Power Generating Stations
Ust Pub
79
Pub
79
Ust Ust Ust Ust Ust Ust Ust Pub
79
Pub
79
Ust Ust Ust Ust Ust Ust Ust Ust Pub
79
Ust Pub
79
Ust Ust Ust Ust Ust Ust Pub Rev Pub
70 78 74
Pub
77
Pub
77
2.2 No.
Issuing Body (Country)
IEEE 603
IEEE
ISO 1709
ISO
ISO/R 1710
ISO
GSN-01
JEN
GSN-02
JEN
GSN-03
JEN
GSN-04
JEN
GSN-05
JEN
GSN-06
JEN
GSN-07
JEN
GSN-08
JEN
GSN-09
JEN
GSN-10
JEN
GSN-11
JEN
GSN-12
JEN
GSN-13
JEN
Publ. 1
NARS
Publ 3
NARS
NCRP Report No.39
NCRP RSK RSK
Status
Title (Remarks) Trial-Use Standard Criteria for Safety Systems for Nuclear Power Generating Stations Nuclear Energy - Fissile materials - principles of criticality safety in handling and processing Fundamental Principles for Protection in the Design and Construction of Installations for Work on unsealed radioactive materials (Withdrawn 1980) Guia Para Solicitar la Puesta en Marcha de las Instalaciones de Manipulacion o Almacenamiento de Isotopos Radiactivos (2a y 3a Categoria) (Commissioning Application of Radiactive Installations). Cualificaciones y Requisitos Exigidos a los Candidatos a la Obtencion y Uso de Licencias de Operacion de Centrales Nucleares de Potencia. (Requirements for Operators of Nuclear Power Plant) Guia Para el Establecimiento de un Programa de Vigilancia Radiologica Ambiental en las Zonas de Influencia de las Centrales Nucleares. (Enviromental Monitoring Programme) Guia Para la Obtencion del Titulo de Jefe del Servicio de Proteccion contra las Radiaciones. (Requirements for the Radiation Protection Manager) Requisitos Fisico-Psiquicos Exigidos a los Candidatos Para la Obtencion y Uso de Licencias de Operadores y Supervisores de Instalaciones Nucleares y Radiactivas. (Requirements for Supervisors of Nuclear and Radioactive Facilities) Plan de Emergencia en Centrales Nucleares de Potencia (Emergency Plan for Nuclear Power Plants). Criterios Sobre la Seguridad Fisica de las Instalaciones nucleares. (Industrial Security at Nuclear Power Plants) Documentation Para la Solicitud del Persiso de Explotaction Definitiva. (Application to Definitive Operation Permit) Programa de Vigilancia Radiologica Ambiental para Centrales Nucleares de Potencia. (Environmental Monitoring Programme) Guia Para la Elaboracion de informes Anuales de las Instalaciones Radiactivas. (Guide for the Elaboration of Radioactive Installations Annual Reports) Vigilancia de Efluentes Radiactivos Liquidos y. Gaseosos Liberados en Centrales Nucleares de Potencia. (Monitoring of Airborne and Liquid Radioactive Releases form Nuclear Power Plants) Almacenamiento Temporal de Residuos Radiactivos (Temporary Sotorage of Radioactive Wastes) Programa de Pruebas Pre-Nucleares y Nucleares (Programme of Pre-Nuclear and Nuclear Tests) Safety Assessment Documents, Guidelines for the preparation of Safety Assessment Documents for stationary nuclear power plants with water-cooled reactors General Design Criteria, General safety criteria for the design of nuclear power plants with light-water reactors Basic Radiation Protection Criteria RSK-Leitlinien fOr Druckwasserreaktoren (2. Ausgabe) RSK-Leitlinien fur Siedewasserreaktoren
Pub
77
Pub
75
Iss
676
ISS
9.76
Iss
10 76
Iss
4.77
ISS
7.77
Iss
2.79
Iss
3.79
Iss
11.78
Iss
11.78
Drf
79
Drf
79
Drf
79
Drf
79
Pub . 675
Pub
6.75
Pub Pub
71 1.79
Drf
980 25
2.2 No.
Issuing Body (Country!
LBG/1
SAAEB
LBG/2
SAAEB
LBG/3
SAAEB
LBG/4
SAAEB
LBG/16
SAAEB
Ft G. 1.1
USNRC
R.G. 1.2
USNRC
R.G. 1.3
USNRC
R.G. 1.4
USNRC
R.G. 1.5
USNRC
R.G. 1.6
USNRC
R.G. 1.7
USNRC
R.G. 1.8
USNRC
R.G. 1.9
USNRC
R.G. 1.10
USNRC
R.G. 1.11
USNRC
R.G. 1.12
USNRC
R.G. 1.13
USNRC
R.G. 1.14
USNRC
R.G. 1.15
USNRC
R.G. 1.16
USNRC
R.G. 1.17
USNRC
R.G. 1.18
USNRC
26
Title (Remarks) Licensing of Nuclear Installations: A Guide to Requirements for Safety Assessment Licensing of Nuclear Installations: A Guide to the Requirements for Quality Assurance Licensing of Nuclear Installations: A Guide to the Requirements for the Licensing of Operators and Senior Operators for a Nuclear Power Station in the Republic of South Africa Licensing of Nuclear Instalations; A Guide to the Requirements for the Medical Control of Nuclear Licensed Site Personnel Licensing of Nuclear installations: A Guide to the Preliminary Requirements of the Licensing Branch to Establish Safety Criteria Prior to Considering Safety Assessment Net Positiv Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1) Thermal Shock to Reactor Pressure Vessels (Safety Guide 2) Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6) Control of Combustible Gas Concentrations in Containment Following a Loss of Coolant Accident Personnel Selection and Training (Under Revision see also Task No. RS 807-5) Selection, Design, and Qualification of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants Mechanical (Cadweld) Splices in Reinforcing Bars of Category I Concrete Structures Instrument Lines Penetrating Primary Reactor Containment. (Safety Guide 11; Supplement to Safety Guide 11 Backfitting Considerations 2.72) Instrumentation for Earthquakes (Under Revision) Spent Fuel Storage Facility Design Basis (Issued for Comments) Reactor Coolant Pump Flywheel Integrity (Issued for Comments) Testing of Reinforcing Bars for Category I Concrete Structures Reporting'of Operating Information-Appendix A Technical Specifications (Issued for Comments) Protection of Nuclear Plants Against Industrial Sabotage Structural Acceptance Test for Concrete Primary Reactor Containments
Status Iss
5.79
Iss
10.73
Iss
3.79
Iss
12.77
Iss
5.79
Iss
11.70
Iss
11.70
Iss
6.74
Iss
6.74
Iss
3.71
Iss
3.71
Iss
11.78
Iss
5.77
Iss
12.79
Iss
1.73
Iss Amm
3.71 2.72
Iss
4.74
Iss
12.75
Iss
8.75
Iss
12.72
Iss
8.75
Iss
6.73
Iss
12.72
2.2 No.
Issuing Body (Country)
R.G. 1.19
USNRC
R.G. 1.20
USNRC
R.G. 1.21
USNRC
R.G. 1.22
USNRC
R.G. 1.23
USNRC
R.G. 1.24
USNRC
R.G. 1.25
USNRC
R.G. 1.26
USNRC
R.G. 1.27
USNRC
R.G. 1.28
USNRC
R.G. 1.29 R.G. 1.30
USNRC USNRC
R.G. 1.31
USNRC
R.G. 1.32
USNRC
R.G. 1.33
USNRC
R G 1.34 R.G. 1.35
USNRC USNRC
R.G. 1.36
USNRC
R.G. 1.37
USNRC
R.G. 1.38
USNRC
RG. 1.39
USNRC
R.G. 1.40
USNRC
Status
Title (Remarks) Non destructive Examination of Primary Containment Liner Welds (Safety Guide 19) Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Release of Radioactivity in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants Periodic Testing of Protection System Actuation Functions (Safety Guide 22) Onsite Meteorological Programs (Safety Guide 23) Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Gas Storage Tank Failure (Safety Guide 24) Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25; Under Revision) Quality Group Classifications and Standards for Water-, Steam- and Radio-Waste-Containing Components of Nuclear Power Plants (Issued for Comments) Ultimate Heat Sink for Nuclear Power Plants (Issued for Comments) Quality Assurance Program Requirements (Design and Construction) (Issued for Comments) Seismic Design Classification Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) Control of Ferrite Content in Stainless Steel Weld Metal Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants Quality Assurance Program Requirements (Operations) (Under Revision; see also Task No. RS 902-4) Control of Electroslag Weld Properties Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures (Under Revision; see also Task No. SC 810-4) Nonmetallic Thermal Insulation for Austenitic Stainless Steel Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants Housekeeping Requirements for Water-Cooled Nuclear Power Plants Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants
Iss
8.72
Iss
5.76
Iss
6.74
Iss
2.72
Iss
2.72
Iss
3.72
Iss
3.72
Iss
2.76
Iss
1.76
Iss
2.79
Iss Iss
9.78 8.72
Iss
4.78
Iss
277
Iss
2.78
Iss Iss
1272 1.76
Iss
2.73
Iss
3.73
Iss
5.77
Iss
9.77
Iss
3.73
27
2.2 No.
Issuing Body (Country)
R.G. 1.41
USNRC
R.G. 1.42
USNRC
R.G. 1.43
USNRC
R.G. 1.44 R.G. 1.45
USNRC USNRC
R.G. 1.46 R.G. 1.47
USNRC USNRC
R.G. 1.48
USNRC
R.G. 1.49 R.G. 1.50
USNRC USNRC
R.G. 1.51
USNRC
R.G. 1.52
USNRC
R.G. 1.53
USNRC
R.G. 1.54
USNRC
R.G. 1.55 R.G. 1.56
USNRC USNRC
R.G. 1.57
USNRC
R.G. 1.58
USNRC
R.G. 1.59 R.G. 1.60
USNRC USNRC
R.G. 1.61
USNRC
R.G. 1.62 R.G. 1.63
USNRC USNRC
R.G. 1.64
USNRC
R.G. 1.65
USNRC
R.G. 1.66
USNRC
R.G. 1.67 R.G.1.68
USNRC USNRC
R.G. 1.68.1
USNRC
28
Title
Status
(Remarks)
Preoperational Testing of Redundant Onsite Electric Power Systems of Verify Proper Load Group Assignments Interim Licensing Policy on As-Low-As Practicable for Gaseous Radioiodine Release from Light-Water Cooled Nuclear Power Reactors (Withdrawn 3.76) Control Stainless Steel Weld Cladding of Low-Alloy Steel Components Control of the Use of Sensitized Stainless Steel Reactor Coolant Pressure Boundary Leakage Detection Systems Protection Against Pipe Whip Inside Containment Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems Design Limits and Loading Combinations for Seismic Category I Fluid System Components Power Levels of Nuclear Power Plants Control of Preheat Temperature for Welding of Low-Alloy Steel (Under Revision) Inservice Inspection of ASME Code Class 2 and 3 Nuclear Power Plant Components (Withdrawn 7.75) Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light-Water-Cooled Nuclear Power Plants Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants Concrete Placement in Category I Structures Maintenance of Water Purity in Boiling Water Reactors (Issued for Comments) Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Under Revision; see also Task No. RS 901-5) Design Basis Floods for Nuclear Power Plants Design Response Spectra for Seismic Design of Nuclear Power Plants Damping Values for Seismic Design of Nuclear Power Plants Manual Initiation of Protective Actions Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants Quality Assurance Requirements for the Design of Nuclear Power Plants Materials and Inspection for Reactor Vessel Closure Studs Non-destructive Examination of Tubular Products (Withdrawn 10.77) Installation of Overpressure Protective Devices Initial Test Programs for Water-Cooled Nuclear Power Plants Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants
Iss
3.73
Iss
5.73
Iss Iss
5.73 5.73
Iss Iss
5.73 5.73
Iss
5.73
Iss Iss
12.73 5.73
Iss
3.78
Iss
6.73
Iss
6.73
Iss Iss
6.73 7.78
Iss
6.73
Iss
8.73
Iss Iss
8.77 12.73
Iss
10.73
Iss Iss
10.73 7.78
Iss
6.76
Iss
10.73
Iss Iss
10.73 8.78
Iss
1.77
2.2 No.
Issuing Body (Country)
R.G. 1 68.2
USNRC
R.G. 1.69 R.G. 1.70
USNRC USNRC
R.G. 1.70.1
USNRC
R.G. 1.70.2
USNRC
R.G. 1.70.3
USNRC
R.G. 1.70.5
USNRC
R.G 1.70.6
USNRC
R.G. 1 70.7
USNRC
R.G. 1 70.8
USNRC
R.G. 1.70.9
USNRC
R.G. 1.70.10
USNRC
R.G. 1.70.11
USNRC
R.G. 1.70.12
USNRC
R.G. 1.70.13
USNRC
R.G. 1 70.14
USNRC
R.G.1.70.15
USNRC
R.G. 1.70.16
USNRC
R.G. 1.70.17
USNRC
R.G 1.70.18
USNRC
R.G. 170 19
USNRC
Title (Remarks) Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants Concrete Radiation Shields for Nuclear Power Plants Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants Hydrological Considerations for Nuclear Power Plants (See also RG. 1.70) Additional Information: Air Filtration Systems and Containment Sumps for Nuclear Power Plants (See also RG. 1.70/ Additional Information: Radiation Protection (See also R.G. 1.70) Additional Information: Water Level (Flood) Design for Nuclear Power Plants (See also R.G. 1.70) Additional Information: Quality Assurance During Design and Construction (See also R.G. 1.70) Additional Information: Geography and Demography Considerations for Nuclear Power Plants (See also R. G. 1.70) Additional Information: Nearby Industrial Transportation and Military Facilities (See also R. G. 1.70/ Additional Information: Design of Seismic Category I Structures (See also R.G 1.70) Additional Information: Wind and Tornado Loadings (See also R.G. 1.70) Information for Safety Analysis Reports - Quality Assurance During Operations Phase (See also R.G. 1.70) Information for Safety Analysis Reports - Reactor Material (See also R.G. 1.70) Information for Safety Analysis Reports - Code Case Applicable to Reactor Coolant Pressure Boundary Components (See also R.G 1.70/ Information for Safety Analysis Reports -Emergency Planning (See also R.G. 1.70) Information for Safety Analysis Reports-Industrial Security for NPP (See also R.G. 1.70) Information for Safety Analysis Report-Missile Barrier Design Procedures (See also R.G. 1.70) Information for Safety Analysis Reports-Hydrological Engineering (See also R.G. 1.70) Information for Safety Analysis Reports Mechanical System Components (See also R.G. 1.70) Information for Safety Analysis Reports - Steam Generators (See also R.G. 1.70)
Status Iss
7.78
Iss Iss
12.73 11 78
Iss
12.73
Iss
12.73
Iss
1174
Iss
8 74
Iss
11.74
Iss
10 74
Iss
10.74
Iss
11.74
Iss
11.74
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
1.75 29
2.2 No.
Issuing Body (Country}
R.G. 1.70.20
USNRC
R.G. 1.70.21
USNRC
R.G 1 70.22
USNRC
R.G. 1.70.23
USNRC
R.G. 1.70.24
USNRC
R.G. 1.70.25
USNRC
R.G. 1.70.26
USNRC
R.G. 1.70.27
USNRC
R.G. 1.70.28
USNRC
R.G. 1.70.29
USNRC
R.G. 1.70.30
USNRC
R G . 1 70.34
USNRC
R.G. 1.70.35
USNRC
R.G. 1.70.36
USNRC
R.G. 1.70.37
USNRC
R.G. 1.70.38
USNRC
R.G. 1.71
USNRC
R.G. 1.72
USNRC
R.G. 1.73
USNRC
R.G. 1.74 R.G. 1.75 R.G. 1.76
USNRC USNRC USNRC
30
Title (Remarks) Information for Safety Analysis Reports - Reactor Coolant Pressure Boundary Material and Inservice Inspection (See also R.G. 1.70) Information for Safety Analysis Reports - Reactor Vessels (See also R.G. 1.70) Information for Safety Analysis Reports Instrumentation and Controls (See also R.G. 1.70) Information for Safety Analysis Reports - Seismic Qualification of Instrumentation and Electrical Equipment (See also R.G. 1.70) Information for Safety Analysis Reports Environmental Design of Mechanical and Electrical Equipment, Qualification Tests and Analysis (See also R.G. 1.70) Information for Safety Analysis Reports-lnservice Inspection of ASME Code Class 2 and 3 Components (See also R. G. 1.70) Information for Safety Analysis Reports-Metallic Materials for Engineered Safety Features (See also R.G 1.70) Information for Safety Analysis Reports Radioactive Waste Management (See also R.G. 1.70) Information for Safety Analysis Reports - Steam and Feedwater System Materials (See also R.G. 1.70) Information for Safety Analysis Reports Meteorology (See also R.G. 1.70) Information for Safety Analysis Reports - Pump Flywheel Integrity (See also R.G. 1.70) Information for Safety Analysis Reports - Fuel Systems Design (See also R.G. 1.70) Information for Safety Analysis Reports - Internally Generated Missiles (See also R.G. 1.70) Information for Safety Analysis Reports - Electric Power (See also R.G. 1.70) Information for Safety Analysis Reports - Pressurizer Relief Discharge System (See also R.G. 1.70) Information for Safety Analysis Reports - Training (See also R.G. 1.70) Welder Qualification for Areas of Limited Accessibility (Under Revision) Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants Quality Assurance Terms and Definitions Physical Independence of Electric Systems Design Basis Tornado for Nuclear Power Plants
Status Iss
1.75
Iss
1.75
Iss
275
Iss
275
Iss
2.75
Iss
2.75
Iss
2.75
Iss
4.75
Iss Ibl
4.75
Iss
4.75
Iss
75
Iss
5.75
Iss
75
Iss
75
Iss
6.75
Iss
6.75
Iss
12.73
Iss
11.78
Iss
1.74
Iss Iss Iss
2.74 9.78 4.74
2.2 No. R.G. 1.77
Issuing Body (Country) USNRC
R.G. 1.78
USNRC
R.G. 1.79
USNRC
R.G. 1.80
USNRC
R.G. 1.81
USNRC
R.G. 1.82
USNRC
R.G. 1.83
USNRC
R.G. 1.84
USNRC
R.G. 1.85
USNRC
R.G 1.86
USNRC
R G. 1.87
USNRC
R.G. 1.88
USNRC
R.G. 1.89
USNRC
R.G. 1.90
USNRC
R.G. 1.91
USNRC
R.G. 1 92
USNRC
R G 1 93 RG 1.94
USNRC USNRC
R G 1 95
USNRC
R G 1 96
USNRC
R G 1 97
USNRC
R.G. 1.98
USNRC
R.G. 1.99
USNRC
R.G. 1.100
USNRC
R.G. 1 101
USNRC
Title
Status
(Remarks)
Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors Preoperational Testing of Instrument Air Systems (Under Revision) Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants Sumps for Emergency Core Cooling and Containment Spray Systems Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes Design and Fabrication Code Case Acceptability-ASME Section III Division I (Under Revision) Materials Code Case Acceptability-ASME Section III Division I /Under Revision) Termination of Operating Licenses for Nuclear Reactors Guidance for Construction of Class I Components in Elevated-Temperature Reactors (Suplement to ASME Section III Code Classes 1592, 1593, 1594, 1595, and 1596) Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records Qualification of Class 1E Equipment for Nuclear Power Plants (Under Revision) Inservice Inspection of Prestressed Concrete Containment Structures With Grouted Tendons Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants (Issued for Comments) Combining Modal Responses and Spatial Components in Seismic Response Analysis Availability of Electric Power Sources Quality Assurance Requirements of Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Under Revision; see also Task No. 908-5) Protection of Nuclear Power Plant Control Room Operators Against an Accidential Chlorine Release Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (Issued for Comments) Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials Seismic Qualification of Electric Equipment for Nuclear Power Plants Emergency Planning for Nuclear Power Plants (Under Revision)
Iss
574
Iss
674
Iss
9.75
Iss
6.74
Iss
1.75
Iss
674
Iss
7.75
Iss
5.79
Iss
5.79
Iss
6.74
Iss
6.75
Iss
10.76
Iss
11.74
Iss
8.77
Iss
2.78
Iss
2.76
Iss Iss
12.74 4.76
Iss
1 77
Iss
6 76
Iss
8 77
Iss
3.76
Iss
4 77
Iss
8.77
Iss
3.77
31
2.2I No.
Issuing Body (Country}
R.G. 1.102 R.G. 1.103
USNRC USNRC
R.G. 1.104
USNRC
RG 1 105 R.G. 1.106
USNRC USNRC
R.G. 1.107
USNRC
R.G. 1.108
USNRC
R.G. 1.109
USNRC
R.G. 1.110
USNRC
R.G. 1.111
USNRC
R.G. 1.112
USNRC
R.G. 1.113
USNRC
R.G. 1.114
USNRC
RG. 1.115 R.G. 1.116
USNRC USNRC
R.G. 1.117 R G. 1.118
USNRC USNRC
R.G. 1.119
USNRC
R.G. 1.120 R.G. 1.121
USNRC USNRC
R.G. 1.122
USNRC
R.G. 1.123
USNRC
R.G. 1.124
USNRC
R.G. 1.125
USNRC
R.G. 1.126
USNRC
R.G. 1.127
USNRC
R.G. 1.128
USNRC
32
Status
Title
(Remarks)
Flood Protection for Nuclear Power Plants Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments Overhead Crane Handling Systems for Nuclear Power Plants (Withdrawn 8.79) Instrument Setpoints Thermal Overload Protection for Electric Motors on Motor-Operated Valves Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants (Errata Sheet Available) Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (Issued for Comments) Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Release for the Purpose of Implementing Appendix I Guidance on Being Operator at the Controls of a Nuclear Power Plant Protection Against Low Trajectory Turbine Missiles Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems Tornado Design Classification Periodic Testing of Electric Power and Protection Systems Surveillance Program for New Fuel Assembly Designs (Withdrawn 6.77) Fire Protection Guidelines for Nuclear Power Plants Bases for Plugging Degraded PWR Steam Generator Tubes Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants Service Limits and Loading Combination for Class I Linear Type Component Supports Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification Inspection of Water-Control Structures Associated with Nuclear Power Plants Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants
Iss Iss
976 1076
Iss Iss
11.76 3.77
Iss
2.77
Iss
8.77
Iss
10.77
Iss
3.76
Iss
7.77
Iss
5.77
Iss
4.77
Iss
11.76
Iss Iss
777 5.77
Iss Iss
4.78 6.78
Iss Iss
11.77 8.76
Iss
2.78
Iss
7.77
Iss
1.78
Iss
10.78
Iss
3.78
Iss
3.78
Iss
10.78
2.2 No.
Issuing Body (Country)
R.G. 1.129
USNRC
R.G. 1.130
USNRC
R.G. 1.131
USNRC
R.G. 1.132
USNRC
R.G. 1.133
USNRC
R.G. 1.134
USNRC
R.G. 1.135
USNRC
RG. 1.136
USNRC
R.G. 1.137
USNRC
R.G. 1.138
USNRC
R.G. 1.139
USNRC
R.G. 1.140
USNRC
R.G. 1.141
USNRC
R.G. 1.142
USNRC
R.G. 1.143
USNRC
R.G. 1.144
USNRC
R.G. 1.145
USNRC
R.G. 2.1
USNRC
R.G. 2.2
USNRC
RG 23
USNRC
R G 24 RG. 2.5
USNRC USNRC
RG 26
USNRC
RG 31
USNRC
Title /Remarks) Maintenance,-Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants Service Limits and Loading Combinations for Class I Plate-and-Shell-Type Component Supports Qualification Test of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (Under Revision; see also Task No. RS 050-2) Site Investigations for Foundations of Nuclear Power Plants Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (Issued for Comments) Medical Evaluation of Nuclear Power Plants Personnel Requiring Operator Licenses Normal Water Level and Discharge at Nuclear Power Plants (Issued for Comments) Material for Concrete Containments (Under Revision; see also Task No. SC 814-5) Fuel-Oil Systems for Standby Diesel Generators (Under Revision) Laboratory Investigations of Soils for Engineering Analysis and Design of Nuclear Power Plants (Issued for Comments) Guidance for Residual Heat Removal (Issued for Comments) Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants (Under Revision) Containment Isolation Provisions for Fluid Systems (Issued for Comments) Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments! (Issued for Comments) Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (Under Revision) Auditing of Quality Assurance Programs for Nuclear Power Plants Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (Issued for Comments) Shield Test Program for Evaluation of Installed Biological Shielding in Research and Training Reactors Development of Technical Specifications for Experiments in Research Reactors Quality Verification for Plate-Type Uranium-Aluminium Fuel Elements for Use in Research Reactors Review of Experiments for Research Reactors Quality Assurance Program Requirements for Research Reactors Emergency Planing for Research Reactors (Issued for Comments) Use of Borosilicate Class Rashig Rings as a Neutron Absorber in Solutions of Fissile Material
Status Iss
2.78
Iss
10.78
Iss
8.77
Iss
3.79
Iss
9.77
Iss
3.79
Iss
9.77
Iss
10.78
Iss
10.79
Iss
4.78
Iss
5.78
Iss
10 79
Iss
4.78
Iss
4.78
Iss
10.79
Iss
9.80
Iss
8.79
Iss
5 73
Iss
11.73
Iss
7 76
Iss Iss
5 77 10.77
Iss
179
Iss
173
33
2.2 No.
Issuing Body (Country)
R.G. 3.2
USNRC
R.G. 3.3
USNRC
R.G. 3.4
USNRC
R.G. 3.5
USNRC
R.G. 3.6
USNRC
R.G. 3.7
USNRC
R.G. 3.8
USNRC
R.G. 3.9 R.G. 3.10
USNRC USNRC
R.G. 3.11
USNRC
R.G. 3.11.1
USNRC
R.G. 3 12
USNRC
R.G. 3.13
USNRC
R.G. 3.14
USNRC
R.G. 3.15
USNRC
R.G. 3.16
USNRC
R.G 3 17
USNRC
R.G. 3 18
USNRC
R.G. 3.19
USNRC
R.G. 3.20 R.G. 3.21
USNRC USNRC
R.G. 3.22
USNRC
R.G 3.23
USNRC
R.G. 3.24
USNRC
R.G. 3.25
USNRC
R.G. 3.26
USNRC
R.G. 3.27
USNRC
R.G. 3.28
USNRC
34
Status
Title
(Remarks)
Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particles Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants Nuclear Criticality in Safety Operations with Fissionable Materials Outside Reactors Standard Format and Content of License Applications for Uranium Mills (Issued for Comments) Guide to Content of Technical Specifications for Fuel Reprocessing Plants Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants Preparation of Environmental Reports for Uranium Mills (Issued for Comments) Concrete Radiation Shields Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants Design, Construction, and Inspection of Embankment Retention Systems for Uranium Mills Operational Inspection and Surveillance of Embankment Retention Systems for Uranium Mill Tailings (Issued for Comments) General Design Guide for Ventilation Systems of Plutonium Processing and Fuel Fabrication Plants Guide for Acceptable Waste Storage Methods at UF6 Production Plants Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants Standard Format and Content of License Applications for Storage Only of Unirradiated Reactor Fuel and Associated Radioactive Material General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants Earthquake Instrumentation for Fuel Reprocessing Plants Confinement Barriers and Systems for Fuel Reprocessing Plants Reporting of Operating Information for Fuel Reprocessing Plants Process Offgas Systems for Fuel Reprocessing Plants Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing Plants and to Plutonium Processing and Fuel Fabrication Plants Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions Stabilization of Uranium-Thorium Milling Waste Retention Systems Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants Non-destructive Examination of Welds in the Liners of Concrete Barries in Fuel Reprocessing Plants Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants
Iss
1.73
Iss
3.74
Iss
2.78
Iss
11.77
Iss
4.73
Iss
3.73
Iss
978
Iss Iss
6.73 6.73
Iss
12.77
Iss
4.79
Iss
8.73
Iss
10.73
Iss
10.73
Iss
10.73
Iss
1.74
Iss
2.74
Iss
2.74
Iss
2.74
Iss Iss
2.74 3.74
Iss
6.74
Iss
11.74
Iss
12.74
Iss
12.74
Iss
2.75
Iss
5.77
Iss
5.75
2.2 No.
Issuing B o d y (Country!
R.G. 3.29
USNRC
R.G. 3.30
USNRC
R.G. 3 31
USNRC
R.G 3 32
USNRC
R.G. 3.33
USNRC
R.G. 3 34
USNRC
R.G. 3.35
USNRC
R.G. 3.36
USNRC
R.G. 3.37
USNRC
R.G. 3.38
USNRC
R.G. 3.39
USNRC
R.G. 3.40
USNRC
R.G. 3.41
USNRC
R G. 3.42
USNRC
R.G 343
USNRC
R.G. 3.44
USNRC
R.G 4.1
USNRC
R.G. 4.2
USNRC
R.G. 4.3
USNRC
R.G. 4.4
USNRC
R.G. 4 5
USNRC
Title (Remarks! Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants Selection, Application, and Inspection of Protective Coatings (Paints) for Fuel Reprocessing Plants Emergency Water Supply Systems for Fuel Reprocessing Plants General Design Guide for Ventilation Systems for Fuel Reprocessing Plants (Issued for Comments! Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant Non-destructive Examination of Tubular Products for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants (Withdrawn 2 69) Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (Issued for Comments) General Fire Protection Guide for Fuel Reprocessing Plants (Issued for Comments) Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants Validation of Calculational Methods for Nuclear Criticality Safety Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70 Nuclear Criticality Safety in the Storage of Fissile Materials Standard Format and Content for the Safety Analysis Report to be Included in a License Application for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation (Water-Basin Type| Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants (Issued for Comments) Preparation of Environmental Reports for Nuclear Power Stations Measurements of Radionuclides in the Environment Analysis of 1-131 in Milk (Withdrawn 12.76) Reporting Procedures for Mathematical Models Selected to Predict Heated Effluent Dispersion in Natural Water Bodies Measurements of Radionuclides in the Environment Sampling and Analysis of Plutonium in Soil
Status Iss
5.75
Iss
577
Iss
5.77
Iss
9.75
Iss
4.77
Iss
7.79
Iss
7.79
Iss
9 75
Iss
6.76
Iss
176
Iss
12.77
Iss
5.77
Iss
9.79
Iss
4.79
Iss
12.78
Iss
4.75
Iss
7.76
Iss
5.74
Iss
5.74
35
2.2 No.
Issuing Body (Country)
R.G. 4.6
USNRC
R.G. 4.7
USNRC
R.G. 4.8
USNRC
R.G. 4.9
USNRC
R.G. 4.10
USNRC
R.G. 4.11
USNRC
R.G. 4.13
USNRC
R.G. 4.14
USNRC
R.G. 4.15
USNRC
R.G. 4.16
USNRC
R.G. 5.1
USNRC
R.G. 5.2
USNRC
R.G. 5.3
USNRC
R.G. 5.4
USNRC
R.G. 5.5
USNRC
R.G. 5.6
USNRC
R.G. 5.7
USNRC
R.G. 5.8
USNRC
R.G. 5.9
USNRC
R.G. 5.10
USNRC
R.G. 5.11
USNRC
R.G. 5.12
USNRC
R.G. 5.13
USNRC
36
Title (Remarks) Measurements of Radionuclides in the Environment Strontium-89 and Strontium-90 Analysis General Site Suitability Criteria for Nuclear Power Stations Environmental Technical Specifications for Nuclear Power Plants (Issued for Comments) Preparation of Environmental Reports for Commercial Uranium Enrichment Facilities Irreversible and Irretrievable Commitments of Material Resources (Withdrawn 11.77) Terrestrial Environmental Studies for Nuclear Power Stations Performance, Testing, and Procedural Specifications for Thermoluminescene Dosimetry: Environmental Applications Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquids and Airborne Effluents from Uranium Mills Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Airborne Effluents from Nuclear Fuel Processing and Fabrication Plants (Issued for Comments) Serial Numbering of Light-Water Power Reactor Fuel Assemblies Classification of Unirradiated Plutonium and Uranium Scrap Statistical Terminology and Notation for Special Nuclear Materials Control Accountability Standard Analytical Methods for the Measurement of Uranium Tetrafluoride (UF4) and Uranium Hexafluoride (UF6) Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets and Nuclear-Grade Mixed Oxides (U, Pu, 02) Control of Personnel Access to Protected Areas, Vital Areas and Material (Under Revision; see also Task No. SG 909-4) Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Drying and Fluidized Bed Operations Specifications of Ge(Li) Spectroscopy Systems for Material Protection Measurements - Part 1: Data Acquisition Selection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of Special Nuclear Materials Nondestructive Assay of Special Nuclear Material containment in Scrap and Waste General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials (Under Revision) Conduct of Nuclear Material Physical Inventories
Status Iss
5.74
Iss
11.75
Iss
12.75
Iss
10.75
Iss
8.77
Iss
7.77
Iss
4.80
Iss
2.79
Iss
3.78
Iss
12.72
Iss
12.72
Iss
2.73
Iss
2.73
Iss
2.73
Iss
5.73
Iss
6.73
Iss
5.74
Iss
5.74
Iss
7.73
Iss
10.73
Iss
11.73
Iss
11 73
2.2 No.
Issuing Body (Country)
R.G. 5.14
USNRC
R.G. 5.15
USNRC
R.G. 5.16
USNRC
R.G. 5.17 R.G. 5.18
USNRC USNRC
R.G. 5.19
USNRC
R.G. 5.20
USNRC
R.G. 5.21
USNRC
R.G. 5.22
USNRC
R.G. 5.23 R G 5 24
USNRC USNRC
R.G. 5.25
USNRC
R.G. 5.26
USNRC
R.G. 5.27 RG. 5.28
USNRC USNRC
R.G. 5.29
USNRC
R G 5 30
USNRC
R.G. 5.31
USNRC
R.G. 5.32 R.G. 5.33 R.G. 5.34
USNRC USNRC USNRC
R.G. 5 35
USNRC
R.G. 5.36
USNRC
R.G. 5 37 R.G. 5.38
USNRC USNRC
R.G. 5.39
USNRC
R.G. 540
USNRC
R.G. 5.42
USNRC
R G. 5 43 R.G. 5.44
USNRC USNRC
Title
Status
(Remarks)
Visual Surveillance of Individuals in Material Access Areas (Under Revision; see also Task No. SG 910-4) Security Seals for the Protection and Control of Special Nuclear Material Standard Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium Nitrate Solutions and Plutonium Metal (Issued for Comments) Truck Indentification Markings Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control (Under Revision) Methods for the Accountability of Plutonium Nitrate Solutions Training, Equipping, and Qualifying of Guards and Watchmen Nondestructive Uranium-235 Enrichment Assay by Gamma-Ray Spectrometry Assessment of the Assumption of Normality (Employing Individual Observed Values) In-Situ Assay of Plutonium Residual Holdup Analysis and Use of Process Data for the Protection of Special Nuclear Material in Equipment for Wet Process Operations Design Considerations for Minimizing Residual Holdup of Special Nuclear Material Selection of Material Balance Areas and Items Control Areas Special Nuclear Material Doorway Monitors Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials (Under Revision) Nuclear Material Control Systems for Nuclear Power Plants Materials Protection Contingency Measures for Uranium and Plutonium Fuel Manufacturing Plants Specially Designed Vehicle and Armed Guards for Road Shipments of Special Nuclear Material Communication with Transport Vehicles Statistical Evaluation of Material Unaccounted For Nondestructive Assay of Plutonium in Scrap by Spontaneous Fission Detection Calorimetric Assay for Plutonium (Withdrawn 8.77) Recommended Practice for Dealing with Outlying Observations In-Situ Assay of Enriched Uranium Residual Holdup Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma-Ray Spectrometry General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic Distribution, and Impurity Determinations Methods for the Accountability of Plutonium Dioxide Powder Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Dry Process Operations Plant Security Force Duties Perimeter Instrusion Alarm Systems (Under Revision; see also Task No. SG 479-4)
Iss
11.73
Iss
1.74
Iss
575
Iss Iss
1.74 1.74
Iss
1.74
Iss
1.74
Iss
4.74
Iss
4.74
Iss Iss
5.74 674
Iss
6.74
Iss
4.75
Iss Iss
6.74 6.74
Iss
6.75
Iss
6.74
Iss
4.75
Iss Iss Iss
5.75 674 6.74
Iss
6.74
Iss Iss
8.74 9.74
Iss
1274
Iss
12.74
Iss
1.75
Iss Iss
1 75 6.76
37
2.2 No.
Issuing Body (Country)
R.G. 5.45
USNRC
R.G 547
USNRC
R.G. 5.48
USNRC
R.G. 5.49
USNRC
R.G. 5.51
USNRC
R.G. 5.52
USNRC
R.G. 5.53
USNRC
RG. 554
USNRC
R.G. 5.55
USNRC
R.G. 5.56
USNRC
R.G. 5.57
USNRC
R.G. 5.58
USNRC
R.G. 5.60
USNRC
R.G. 7.1
USNRC
R.G. 7.2
USNRC
R.G. 7.3
USNRC
R.G. 7.4
USNRC
R.G. 7.5
USNRC
R.G. 7.6
USNRC
RG. 7.7
USNRC
R.G. 7.8
USNRC
38
Title (Remarks) Standard Format and Content for the Special Nuclear Material Control and Accounting Section of a Special Nuclear Material License Application (Including That for a Uranium Enrichment Facility) Control and Accountability of Plutonium in Waste Material Design Considerations-System for Measuring the Mass of Liquids Internal Transfers of Special Nuclear Material (Issued for Comments) Management Review of Nuclear Material Control and Accounting Systems (Issued for Comments) Standard Format and Content for the Physical Protection Section of a License Application (For Facilities Other Than Nuclear Power Plants) (Revision to Chapter 4 and 18 were issued 7.78; issued for Comments) Qualification, Calibration, and Error Estimation Methods for Non-destructive Assay (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Nuclear Power Plants (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Transportation (Issued for Comments) Shipping and Receiving Control of Special Nuclear Material (Under Revision; see also Task No. SG 908-4) Considerations for Establishing Traceability of Special Nuclear Material Accounting Measurements (Issued for Comments) Standard Format and Content of Licensee Physical Protection Plan for Strategic Special Nuclear Material in Transit Administrative Guide for Packaging and Transporting Radioactive Material Packaging and Transportation of Radioactively Contaminated Biological Materials Procedures for Picking Up and Receiving Packages of Radioactive Material (Issued for Comments) Leakage Tests on Packages for Shipment of Radioactive Materials (Issued for Comments) Administrative Guide for Obtaining Exemptions from Certain NRC Requirements Over Radioactive Material Shipments Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels Administrative Guide for Verifying Compliance with Packaging Requirements for Shipments of Radioactive Materials (Issued for Comments) Load Combinations for the Structural Analysis of Shipping Casks (Issued for Comments)
Status Iss
12.74
Iss
2.75
Iss
2.75
Iss
3 75
Iss
6.75
Iss
6.76
Iss
8.75
Iss
3.78
Iss
3.78
Iss
3.78
Iss
6.76
Iss
11.78
Iss
4.80
Iss
6.74
Iss
6.74
Iss
5.75
Iss
6.75
Iss
5.77
Iss
3.78
Iss
8.77
Iss
5.77
2.2 Issuing Body
No.
(Country)
R.G 7.9
USNRC
R.G. R.G. R.G R.G.
8.1 8.2 83 8.4
USNRC USNRC USNRC USNRC
R.G. 8.5 R.G. 8.6
USNRC USNRC
R.G 8.7 R.G 8.8
USNRC USNRC
R.G. 8.9
USNRC
R.G. 8.10
USNRC
R.G. 8.11 R.G. 8.12
USNRC USNRC
R.G R.G. R.G. R.G.
813 8.14 8.15 8.19
USNRC USNRC USNRC USNRC
R.G. 8.20
USNRC
R.G. 821
USNRC
R.G. 8.22
USNRC
R.G. 8.24
USNRC
R.G. 8.26
USNRC
R.G. 9.1
USNRC
R.G. 9.2
USNRC
R.G 9.3
USNRC
R.G..9.4
USNRC
R.G . 10.1
USNRC
R.G . 10.4
USNRC
Title
Status
(Remarks)
Standard Format and Content of Part 71 Applications for Approval of Packaging of Type B, Large Quantity and Fissile Radioactive Materials (Issued for Comments) Radiation Symbol Administrative Practices in Radiation Monitoring Film Badge Performance Criteria Direct-Reading and Indirect-Reading Pocket Dosimeters Immediate Evacuation Signal Standard Test Procedures for Geiger-Miiller-Counters Occupational Radiation Exposure Records Systems Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as is Reasonably Achievable (Under Revision; see also Task No. OH 507-4) Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable (Nuclear Power Reactors) Applications of Bioassay for Uranium Criticality Accident Alarm Systems (Under Revision; see also Task No. OH 015-4) Instruction Concerning Prenatal Radiation Exposure Personnel Neutron Dosimeters Acceptable Programs for Respiratory Protection Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants-Design Stage Man-Rem Estimates (Issued for Comments) Applications of Bioassay for 1-125 and 1-131 (Under Revision) Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and Manufacturing Plants (Under Revision) Bioassay at Uranium Mills (Under Revision) Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication (Issued for Comments) Application of Bioassay for Fission and Activation Products Regulatory Staff Position Statement on Antitrust Matters Information Needed by the NRC Staff in Connection With Its Antitrust Review of Construction Permit Applications for Nuclear Power Plants Information Needed by the NRC Staff in Connection With Its Antitrust Review of Operating License Applications for Nuclear Power Plants Suggested Format for Cash Flow Statements Submitted as Guarantees of Payment of Retrospective Premiums (Issued for Comments) Compilation of Reporting Requirements for Persons Subject to NRC Regulations (Issued for Comments) Guide for the Preparation of Applications for Licenses to Process Source Material
Iss
3.79
Iss Iss Iss Iss
273 273 2.73 2.73
Iss Iss
273 5.73
Iss Iss
5.73 6.78
Iss
9.73
Iss
5.77
Iss Iss
6.74 12.74
Iss Iss Iss Iss
11.75 8.77 10.76 6.79
Iss
4.78
Iss
5.78
Iss
7.78
Iss
11.78
Iss
9.80
Iss
12.73
Iss
6.76
Iss
10.74
Iss
9.78
Iss
5.77
Iss
3.77
39
2.2 No.
Issuing Body (Country)
Task No. EM 805-5
USNRC
Task No. FP 811-4
USNRC
Task No. FP 818-4
USNRC
Task No. FP 925-5
USNRC
Task No MP 711-4
USNRC
Task No. OH 015-4
USNRC
Task No. OH 507-4
USNRC
Task No. OH 717-4
USNRC
Task No. RH 802-4
USNRC
Task No. RS 050-2
USNRC
Task No. RS 705-4
USNRC
Task No. RS 807-5
USNRC
Task No. RS 809-5
USNRC
Task No. RS 810-5
USNRC
Task No. RS 901-5
USNRC
Task No. RS 902-4
USNRC
Task No. RS 908-5
USNRC
Task No. SC 521-4
USNRC
Task No. SC 704-5
USNRC
40
Title (Remarks) Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants (Proposed R.G.) Safety-Related Permanent Dewatering Systems for Nuclear Power Plants (Proposed R.G.) Standard Format and Content of Licensee Applications, Including Environmental Reports, for In Situ Uranium Solution Extraction (Proposed R.G.) Nuclear Criticality Safety for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate (Proposed R. G.) Standard Format and Content for a Licensee Physical Security Plan for the Protection of Special Nuclear Material of Moderate or Low Stratetic Significance (Proposed R. G.) Criticality Accident Alarm Systems (Proposed R.G. 8.12) Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable (Proposed Revision to R.G. 8.8) Radiation Protection Training for Light-Water-Cooled Nuclear Power Plant Personnel (Proposed R.G.) Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations (Proposed R. G.) Qualification Tests of Electric Cables and Field Splices for Light-Water-Cooled Nuclear Power Plants (Proposed Revision to R.G. 1.131) Lightning Protection for Nuclear Power Plants (Proposed R.G.) Personnel Selection and Training (Proposed Revision to R.G. 1.8) Qualification Test for Cable Penetration Fire Stops for Use in Nuclear Power Plants (Proposed R.G.) Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Proposed R. G.) Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (ProposedRevision to R.G. 1.58) Quality Assurance Program Requirements (Operation) (Proposed Revision to R.G. 1.33) Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations During the Construction Phase of Nuclear Power Plants (Proposed Revision to R.G. 1.94) LWR Core Reloads; Guidance on Applications for Amendments to Operating Licenses and on Refueling and Startup Tests (Proposed R.G.) Functional Specification for Safety-Related Valve Assemblies in Nuclear Power Plants (Proposed R. G.)
Status Iss
2.79
Iss
9.79
Iss
7.80
Iss
1.80
Iss
7.79
Iss
5.80
Iss
3.79
Iss
8.79
Iss
5.79
Iss
8.79
Iss
8.79
Iss
2.79
Iss
7.79
Iss
2.79
Iss
7.79
Iss
8.79
Iss
9.79
Iss
9.79
Iss
2.79
2.2 No.
Issuing B o d y (Country)
Task No. SC 705-4
USNRC
Task No. SC 721-4
USNRC
Task No. SC 807-4
USNRC
Task No. SC 810-4
USNRC
Task No. SC 814-5
USNRC
Task No. SG 479-4
USNRC
Task No. SG 901-4
USNRC
Task No. SG 908-4
USNRC
Task No. SG 909-4
USNRC
Task No. SG 910-4
USNRC
10 CFR 50 Appendix A USNRC 10 CFR 50 Appendix I USNRC
VdTUV Wei 12
VdTUV
VdTUV Wei 13
VdTUV
VdTUV Wei 15
VdTUV
Status
Title (Remarks! Ultrasonic Testing of Reactor Vessel Welds During Inservice Examination (Proposed R. G.) Inservice Inspection Code Case Acceptability ASME Section XI, Division 1 (Proposed R. G.) Determining Prestressing Forces for Inspection of Prestressed Concrete Containments (Proposed R.G. 1.35.1) Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments (Proposed Revision to R.G. 1.35) Materials, Construction, and Testing of Concrete Containments (Articles CC-1000, -2000, and -4000 through -7000 of the "Code for Concrete Reactor Vessels and Containments") (Proposed Revision to R. G. 1.136) Perimeter Intrusion Alarm Systems (Proposed Revision to R.G. 5.44) Reporting of Safeguards Events (Proposed R.G.) Shipping and Receiving Control of Strategic Special Nuclear Material (Proposed Revision to R.G. 5.57) Entry/Exit Control of Protected Areas, Vital Areas, and Material Acces Areas (Proposed Revision to R.G. 5.7) Use of Observation (Visual Surveillance) Techniques in Material Access Areas (Proposed Revision to R. G. 5.14) General Design Criteria for Nuclear Power Plants Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet Criterion "As Low as Practicable" for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents Umsetzung der Empfehlungen der Reaktor-Sicherheitskommission auf ihrer 93. Sitzung am 24.04.74 - Programm zur Untersuchung der SchweiSprobleme bei Reaktordruckbehaltern (Sofortprogramm) - RSK-Leitlinien fur Druckwasserreaktoren (Withdrawn 1.80) Standardgliederung mit Merkposten fur TiiV/GRS-Gutachten fur Kernkraftwerke mit D.ruckoder Siedewasserreaktoren Zusammenstellung der in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen
Iss
5.79
Iss
8.79
Iss
4.79
Iss
4.79
Iss
11.79
Iss
5.79
Iss
10.79
Iss
5.79
Iss
5.79
Iss
5.79
Iss
577
Iss
3.78
41
3.1 No. 3
ANS-10.3 /ANSI N413
ANS ANS ANS
ANS-15.18
ANS
ANS-19.4 /ANSI N652
ANS
ANSI N299
ANSI
ASME JC8-23
ASME /ACI ASME
QA-76-2.2 N45.2.2 QA-76-2.3 N45.2.3
ASME
ASME QA-76-9 /ANSI N45.2.9
ASME
ASME QA-76-12 /ANSI N45.2.12 VBG 1 CNEN NE 1.01 CNEN NE 1.06
ASME
*
DERRT
IAEA 50-C-G
IAEA
IAEA 50-C-O
IAEA
IAEA 50-SG-G4
IAEA
IAEA 50-SG-G6
IAEA
IAEA 50-SG-QA2
IAEA
IAEA 50-SG-QA7
IAEA
IAEA50-SG-QA10 IAEA 50-SG-01
IAEA IAEA
IAEA 50-SG-02 IAEA 50-SG-06
IAEA IAEA
IAEA 50-SG-08
IAEA
IAEA 50-SG-09
IAEA
IEEE 494 /ANSI N41.28
IEEE
GSN-10
JEN
42
Status
(Remarks)
A d m i n i s t r a t i v e Procedures
3.1 General ANS-3.7.2 ANS-10.2
ASME /ANSI ASME /ANSI
Title
Issuing Body (Country)
BG CNEN CNEN
Emergency Control Centers for Nuclear Power Plants Recommended Programming Practices to Facilitate Interchange of Digital Computer Programs Guidelines for the Documentation of Digital Computer Programs (Revision of ANS Std. 2) Standard for Administrative Controls for Research Reactors A Guide for Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification Administrative Controls for Nuclear Fuel Reprocessing Plants Update of Reference Documents Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plant Housekeeping During the Construction Phase of Nuclear Power Plants (Addenda Provided) Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants Allgemeine Vorschriften Licensing of Nuclear Reactor Operators Medical Requirements for Licensing Reactor Operators The Nuclear Installations (Insurance Certificate) Regulations Governmental Organization for the Regulation of Nuclear Power Plants, Code of Practice Safety in Nuclear Power Plant Operation, Including Commissioning and Decommissioning, Code of Practice Inspection and Enforcement by the Regulatory Body for Nuclear Power Plants Preparedness of Public Authorities for Emergencies at Nuclear Power Plants Quality Assurance Records Systems for Nuclear Power Plants Quality Assurance Organization for Nuclear Power Plants Quality Assurance Auditing for Nuclear Power Plants Staffing of Nuclear Power Plants and Recruitment, Training and Authorization of Operating Personnel In-Service Inspection for Nuclear Power Plants Preparedness of the Operating Organization for Emergencies at Nuclear Power Plants Standard Tests of Important Systems and Components in Nuclear Power Plants Management of Nuclear Power Plants for Safe Operation Standard Method for Identification of Documents Related to Class 1E Equipment and Systems for Nuclear Power Generating Stations Guia Para la Elaboracion de informes Anuales de las Instalaciones Radiactivas. (Guide for the Elaboration of Radioactive Installations Annual Reports)
Pub Pub
79 71
App
74
Pub
79
App
76
Pub
76
Drf
9.78
Pub
78
App
73
App
74
Pub
77
Pub Iss Drf
4.77 79 79
Iss Amm Pub
65 71 78
Pub
78
Ust Ust Pub
79
Ust Ust Pub
79
Ust Ust Ust Ust Pub
74
Drf
79
3.1 No.
Issuing B o d y (Country)
Title
S 5201 RDT F 1-2T RDT F 1-3T
ONORM ORNL ORNL
StrahlenpaB - StrahlenpaG gemafc ONORM S 5201 Preparation of System Design Descriptions Preparation of Unusual Occurrence Reports
R.G. 1.70
USNRC
R.G. 1.88
USNRC
R.G. 1.123
USNRC
R.G. 1.144
USNRC
R.G. 4.10
USNRC
R.G. 5.51
USNRC
R.G. 7.5
USNRC
R.G. 9.1
USNRC
R G. 9.2
USNRC
R.G. 9.3
USNRC
R.G. 10.1
USNRC
Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants Collection, Storage, and M aintenance of Nuclear Power Plant Quality Assurance Records Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants Auditing of Quality Assurance Programs for Nuclear Power Plants Irreversible and Irretrievable Commitments of Material Resources (Withdrawn 11.77) M anagement Review of Nuclear M aterial Control and Accounting Systems (Issued for Comme nts) Administrative Guide for Obtaining Exemptions from Certain NRC Requirements Over Radioactive M aterial Shipments Regulatory Staff Position Statement on Antitrust Matters Information Needed by the NRC Staff in Connection With Its Antitrust Review of Construction Permit Applications for Nuclear Power Plants Information Needed by the NRC Staff in Connection With Its Antitrust Review of Operating License Applications for Nuclear Power Plants Compilation of Reporting Requirements for Persons Subject to NRC Regulations (Issued for Comme nts) Licensee Safeguards Contingency Plans Standard Specifications for the Granting of Patent Licenses Export and Import of Nuclear Equipment and Material List of Nuclear Equipment and M aterial under NRC Export/Import Licensing Authority List of Foreign Facilities to which Nuclear Equipment May be Exported Pursuant to the General License in § 110.21 (Reserved) Categorization of Nuclear M aterial Standardgliederung mit M erkposten fur TuV/GRS-Gutachten fur Kernkraftwerke mit Druckoder Siedewasserreaktoren Verwaltungsverfahrensgesetz (VwVfG) vom 25. M ai 1976, zuletzt geandert durch Art. 7 Nr. 4 des Gesetzes vom 2.7.1976 (siehe auch Rundschre ibe n de s Bunde sministe rs de s Innern hie rzu vom 8. De ze mbe r 1976 - V II 3 ■ 130 210/8 -) Paris Agreement of July 29, 1960, on the Third-party Liability in the Field of Nuclear Energy Brussels Additional Agreement of Jan. 31, 1963, to the Paris Agreement of July 29, 1960 on the Third-Party Liability in the Field of Nuclear Energy Brussels Agreement of Dec. 12, 1971, Regarding the Civil-law. Liability During the Transport of Nuclear Material on Sea
10 CFR 73 Appendix C USNRC 10 CFR 81 USNRC 10 CFR 110
USNRC
10 CFR 110 Appendix A USNRC 10 CFR 110 Appendix B USNRC 10 CFR 110 Appendix C USNRC VdTUV Wei 13 VdTUV BGBI. I, S. 1253
(DELI)
(INT) (INT) (INT)
Status
(Remarks) Iss 9.76 Pub 12.75 9.77 Pub Amm 12.77 11.78 Iss Iss
10.76
Iss
777
Iss
9 80
Iss
6.75
Iss
5.77
Iss
12 73
Iss
6 76
Iss
10 74
Iss
5 77
Iss
5 77
Iss Amm
5.76 7.76
App
7.60
App
163
App
12.71
43
Resolution 966
44
(ROM)
Approval of the Regulations Concerning the Registration and Supervision of Labour-Accidents and Occupational Diseases as Well as Securing and Utilizing the Fund for Labour Protection- Annex 1, No. 8- Diseases Caused by Ionizing Radiations etc. Annex 2, No.15- Labour Protection in Case of Handling of Radioactive Substances
App
12.64
3.2 No. 3
Issuing Body (Country)
Title
Status
(Remarks)
A d m i n hstrative Procedu
3.2 C o n s t r u c t i o n and Open ration ANS-3.2 ANS Administrative Controls and Quality Assurance for /ANSI N18.7 the Operational Phase of Nuclear Power Plants (Revision of ANSI N18.7-1972) ANSI N13.2 ANSI Guide for Administrative Practices in Radiation Monitoring ANSI N13.6 ANSI Practice for Occupational Radiation Exposure Records Systems ANSI N14.10.1 ANSI Administrative Guide for Packaging and Transporting Radioactive Materials ANSI N14.10.2 ANSI Administrative Guide for Obtaining Department of Transportation Special Permits for Radioactive Materials for Shipment ANSI N14.10.3 ANSI Administrative Guide for Verifying Compliance with Packaging GMBI. 1978 S. 418 BMI Richtlinie fur den Stahlenschutz des Personals bei der Durchfuhrung von Instandhaltungsarbeiten in Kernkraftwerken mit Leichtwasserreaktor: Die wahrend der Planung der Anlage zu treffende Vorsorge, vom 10.7.1978 DIN 25451 DIN Anforderungen an das Betriebshandbuch; Sicherheitstechnische Anforderungen (Requirements for the Operational Manual; Safety Requirements) (Identical with KTA 1201) IAEA 50-SG-03 IAEA Operational Limits and Conditions for Nuclear Power Plants IAEA 50-SG-04 IAEA Commissioning Procedures for Nuclear Power Plants IAEA 50-SG-05 IAEA Radiological Protection During Operation of Nuclear Power Plants IAEA 50-SG-09 IAEA Management of Nuclear Power Plants for Safe Operation IEEE 494 IEEE Standard Method for Identification of Documents /ANSI N41 28 Related to Class 1E Equipment and Systems for Nuclear Power Generating Stations GSN-08 JEN Documentation Para la Solicitud del Persiso de Explotaction Definitiva. (Application to Definitive Operation Permit) KTA 1201 KTA Anforderungen an das Betriebshandbuch (Requirements for the Operational Manual) KTA 1201 KTA Anforderungen an das Betriebshandbuch (Requirements for the Operational Manual) (Identical with DIN 25451) Publ. 5 Construction Site Emergency Precautions, Guidelines NARS for Information on Internal Emergency Precautions related to a Major Construction Work on a Nuclear Power Plant Site with Reactor(s) in Operation RDT F 4-20T Operation and Maintenance Manuals ORNL R.G. 1.16
USNRC
R.G. 1.39
USNRC
R.G. 1.114
USNRC
R.G. 3.19
USNRC
R.G. 9.2
USNRC
Reporting of Operating Information-Appendix A Technical Specifications (Issued for Comments) Housekeeping Requirements for Water-Cooled Nuclear Power Plants Guidance on Being Operator at the Controls of a Nuclear Power Plant Reporting of Operating Information for Fuel Reprocessing Plants Information Needed by the NRC Staff in Connection With Its Antitrust Review of Construction Permit Applications for Nuclear Power Plants
App
76
Pub
69
Pub
72
Pub
73
Pub
73
Pub
75
Iss
7.78
Pub
9.78
Pub
79
Ust Ust Ust Pub
74
Iss
11.78
Drf
10.79
Pub
2.78
Pub
6.75
Pub 1071 Amm 11 78 Iss 8.75 Iss
9.77
Iss
11.76
Iss
2.74
Iss
6.76
45
3.2 No.
Issuing Body (Country)
R.G. 9.3
USNRC
Resolution 741
(ROM)
46
Title
Status
(Remarks)
Information Needed by the NRC Staff in Connection With Its Antitrust Review of Operating License Applications for Nuclear Power Plants Operation of Nuclear Radiation Sources
Iss
10.74
App
11.61
3.3 No. 3
Issuing Body (Country)
Title (Remarks)
Status
A d m i n i s t r a t i v e Procedures
3.3 Decommissioning ANSI N300 ANSI BAnz. Nr. 58/80
BMI
IAEA 50-C-O
IAEA
R G 1 47
USNRC
Design Criteria for Shutdown and Decommissioning of Nuclear Fuel Reprocessing Facilities Grundsatze zur Entsorgungsvorsorge fur Kernkraftwerke vom 19.3.1980 Safety in Nuclear Power Plant Operation, Including Commissioning and Decommissioning, Code of Practice Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems
Pub Iss
75 3.80
Pub
78
Iss
5 73
47
3.4 No. 3
Issuing Body (Country)
(Remarks)
A d m i n i s t r a t i v e Procedu
3.4 Q u a l i f i c a t i o n , S e l e c t i o n and Training of Personnel Guide for Certification of Nuclear Concrete ACI ACI 311.3R Inspection and Testing Personnel AD Herstellung und Priifung von Druckbehaltern; AD-Merkblatt HP 3 SchweiSaufsicht, SchweiBer Herstellung und Priifung von Druckbehaltern; AD AD-Merkblatt HP 4 Priifaufsicht und Priifer fiir zerstorungsfreie Priifung Code de construction des generateurs de vapeur AFNOR E 32-107 Qualification du mode operatoire de soudage ANS Selection and Training of Personnel for Nuclear ANS-3.1 Power Plants ANS-34 ANS Standard for Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear /ANSI N546 Power Plants ANS Nuclear Power Plant Simulators for Use in Operator ANS-3.5 Training ANS ANS-3.7.3 Radiological Emergency Preparedness Drills for Nuclear Power Plants ANS-15.4 ANS Standard for Selection and Training of Personnel for Research Reactors ANSI Qualification of Quality Assurance Program Audit ANSI N45.2.23 Personnel for Nuclear Facilities ANSI Qualifications and Duties for Authorized Nuclear ANSI N626.0 Inspection ANSI Qualifications and Duties for Authorized Inservice ANSI N626.1 Inspection ANSI Qualifications and Duties for Authorized Nuclear ANSI N626 2 Inspection (Concrete) ANSI Qualifications and Duties of Personnel Engaged in ANSI N626.3 ASME Boiler and Pressure Vessel Code, Section III, Division 1 and 2, Certifying ASME ASME QA-76-6 Qualifications of Inspection, Examination and Testing /ANSI N452.6 Personnel for the Construction Phase of Nuclear Power Plants ASNT SNT-TC-1A Non-Destructive Testing Personnel Qualification and Certification AWS WIQC AWS Guide to AWS Welding Inspector Qualification and Certification-including AWS QC1-77 Standard for Qualification and Certification of Welding Inspectors BG Sicherheitsingenieure und andere Fachkrafte fiir VBG 122 Arbeitssicherheit BMI Richtlinie fiir den Fachkundenachweis von BMI RS I-6/76 Forschungsreaktorpersonal vom 18.3.1976 BMI Richtlinie fiir den Inhalt der Fachkundeprufung des GMBI. 1978 S. 431 verantwortlichen Schichtpersonals in Kernkraftwerken vom 10.8.1978 BMI GMBI. 1979 S. 233 Richtlinie fiir den Fachkundenachweis von Kernkraftwerkspersonal vom 17.5.1979 BMI GMBI. 1979 S. 238 Richtlinie fiir Programme zur Erhaltung der Fachkunde des verantwortlichen Schichtpersonals in Kernkraftwerken vom 17.5.1979 GMBI. 1980 S. 92 Richtlinie fur den Inhalt der Fachkundeprufung des BMI verantwortlichen Schichtpersonals in Forschungsreaktoren vom 30.11.1979 CNEN NE 1.01 CNEN Licensing of Nuclear Reactor Operators CNEN NE 1.06 CNEN Medical Requirements for Licensing Reactor Operators Soudage - Qualification des soudeurs et des NF A 88-110 CNS operateurs DIN 8560 DIN Priifung von StahlschweiBern (Examination of welders for welding steel) 48
Status
Title
Pub
75
Pub
4.75
Pub
4.75
Iss
78
Pub
78
App
76
Pub
79
Pub
79
Pub
77
Pub
78
Pub
74
Pub
75
Pub
76
Pub
78
Pub
78
Pub
71
Pub
78
Pub
12.74
Iss
3.76
Iss
8.78
Iss
5.79
Iss
5.79
Iss
11.79
Iss Drf
79 79
Iss Pub
45 1.78
3.4 No.
Issuing Body (Country)
DIN 8561
DIN
DIN 8563 Teil 2
DIN
DIN 54160
DIN
IAEA 50-SG-G1
IAEA
IAEA 50-SG-01
IAEA
GSN-02
JEN
GSN-04
JEN
GSN-05
JEN
LBG/3
SAAEB
R.G. 1.8
USNRC
R.G. 1 58
USNRC
R.G. 1.70.38
USNRC
R.G. 1.71
USNRC
R.G 1.114
USNRC
R.G. 1.134
USNRC
R.G. 3.28
USNRC
R.G 5 20
USNRC
Task No. RS 807-5
USNRC
Task No. RS 810-5
USNRC
Task No. RS 901-5
USNRC
10 CFR 51 Appendix A USNRC Leg. Series 1965 No. 31/1200
(YUG)
Status
Title
1
(Remarks)
Prufung von NE-MetallschweiSern (Examination of welding non-ferrous metals) Sicherung der GCite von SchweilSarbeiten; Anforderungen an den Betrieb (Quality assurance of welded structures; requirements on firms) Zerstorungsfreie Prufung; Anforderungen an Prufpersonal (Non-destructive Testing; Requirements for Testing Personel) (Withdrawn) Qualifications and Training of Staff of the Regulatory Body for Nuclear Power Plants Staffing of Nuclear Power Plants and Recruitment, Training and Authorization of Operating Personnel Cualificaciones y Requisitos Exigidos a los Candidatos a la Obtencion y Uso de Licencias de Operacion de Centrales Nucleares de Potencia. (Requirements for Operators of Nuclear Power Plant) Guia Para la Obtencion del Titulo de Jefe del Servicio de Proteccion contra las Radiaciones. (Requirements for the Radiation Protection Manager) Requisitos Fisico-Psiquicos Exigidos a los Candidatos Para la Obtencion y Uso de Licencias de Operadores y Supervisores de Instalaciones Nucleares y Radiactivas. (Requirements for Supervisors of Nuclear and Radioactive Facilities) Licensing of Nuclear Installations: A Guide to the Requirements for the Licensing of Operators and Senior Operators for a Nuclear Power Station in the Republic of South Africa Personnel Selection and Training (Under Revision see also Task No. RS 807-5) Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Under Revision; see also Task No RS 901-5) Information for Safety Analysis Reports - Training (See also R. G. 1.70) Welder Qualification for Areas of Limited Accessibility (Under Revision) Guidance on Being Operator at the Controls of a Nuclear Power Plant Medical Evaluation of Nuclear Power Plants Personnel Requiring Operator Licenses Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and iri Plutonium Processing and Fuel Fabrication Plants Training, Equipping, and Qualifying of Guards and Watchmen Personnel Selection and Training (Proposed Revision to R.G. 1.8) Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Proposed R.G.) Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Proposed Revision to R.G. 1.58) Requalification Programs for Licensed Operators of Production and Utilization Facilities Regulation Concerning the Technical Training of Persons Working With Sources of Ionizing Radiation and Carrying Out Activities in Connection With Protection Against Such Radiation
Pub
2.74
Pub
10.78
Drf
4.78
Pub
79
Pub
79
ISS
9.76
Iss
4.77
ISS
7.77
Iss
3.79
Iss
5.77
Iss
8.73
Iss
6.75
Iss
12.73
Iss
11.76
Iss
3.79
Iss
5.75
Iss
1.74
Iss
2.79
Iss
279
Iss
779
Iss
6 65
49
3.5 No.
Issuing Body (Country)
3
A d m i n i s t r a t i v e Procedures
3.5
Finances and Licensing
ANSI N14
ANSI
ASME JC7-71 GMBI. 1976 S. 166
ASME /ACI BMI
GMBI. 1976 S. 445
BMI
GMBI. 1978 S. 294
BMI
GMBI 1978 S. 426
BMI
GMBI. 1978 S 598
BMI
CNEN NE 1.04
CNEN
CNEN NE 3.02
CNEN
CNEN NE4.03 IAEA 50-SG-G2
CNEN IAEA
IAEA 50-SG-G3
IAEA
IAEA 50-SG-G8
IAEA
GSN-01
JEN
GSN-08
JEN
LBG/1
SAAEB
LBG/2
SAAEB
50
Status
Title (Remarks)
Administrative Guide for the Liability Insurance Aspects of Shipping Nuclear Materials Owners Certificate of Authorization
Pub Drf
10.78
Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber die Notstromversorgung vom 24.3.1976 Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Priifung erforderlichen Informationen uber die Einbauten des Reaktordruckbehalters und die Einbauten des Sicherheitsbehalters vom 4.8.1976 (withdraw: directions to reactor pressure vessel, see GMBI. 1977 S. 661) Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Priifung erforderlichen Informationen iiber die liiftungstechnischen Anlagen, die Not- und Nachkiihlsysteme emschlieUlich Nachkiihlkette und Rohrleitungen, Pumpen und Armaturen des Hauptkiihlkreises vom 17.5.1978 Genehmigungen gemaS § 20a Strahlenschutzverordnung vom 18.7.1978 Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Priifung erforderlichen Informationen iiber das Druckabbausystem (DAS) bei Siedewasserreaktoren, die Dampferzeuger und Systeme zur Mandhabung und Lagerung sonstiger radioaktiver Stoffe vom 30.10.1978 Licensing of Nuclear Power Reactors (Under Revision) Licensing of Individuals and Institutions for the Inspection and Application of Radiological Protection Measures Licensing of Uranium Mines Information to be Submitted in Support of Licensing Applications for Nuclear Power Plants Conduct of Regulatory Review and Assessment During the Licensing Process for Nuclear Power Plants Licences for Nuclear Power Plants: Content, Format and Legal Considerations Guia Para Solicitar la Puesta en Marcha de las Instalaciones de Manipulacion o Almacenamiento de Isotopos Radiactivos (2a y 3a Categoria) (Commissioning Application of Radiactive Installations). Documentation Para la Solicitud del Persiso de Explotaction Definitiva. (Application to Definitive Operation Permit) Licensing of Nuclear Installations: A Guide to Requirements for Safety Assessment Licensing of Nuclear Installations: A Guide to the Requirements for Quality Assurance
Iss
376
Iss
8.76
Iss
5.78
Iss
7.78
Iss
10.78
Iss
72
Iss
74
Ust Pub
79
74
Ust Ust Iss
>76
Iss
11.78
Iss
5.79
Iss
10.73
3.5 No.
Issuing Body (Country)
LBG/3
SAAEB
LBG/4
SAAEB
LBG/16
SAAEB
R.G. 1.42
USNRC
R.G. 1.86
USNRC
RG. 1.110
USNRC
R.G. 3.5
USNRC
R G. 3.15
USNRC
R.G. 3.24
USNRC
R.G. 3.39
USNRC
R.G. 5.45
USNRC
R.G. 5.52
USNRC
R.G. 5.54
USNRC
R.G. 5.55
USNRC
R.G. 5.56
USNRC
R G 5.60
USNRC
R G. 7.9
USNRC
RG. 9.4
USNRC
RG. 104
USNRC
Title (Remarks) Licensing of Nuclear Installations A Guide to the Requirements for the Licensing of Operators and Senior Operators for a Nuclear Power Station in the Republic of South Africa Licensing of Nuclear Instalations; A Guide to the Requirements for the Medical Control of Nuclear Licensed Site Personnel Licensing of Nuclear Installations: A Guide to the Preliminary Requirements of the Licensing Branch to Establish Safety Criteria Prior to Considering Safety Assessment Interim Licensing Policy on As-Low-As Practicable for Gaseous Radioiodine Release from Light-Water Cooled Nuclear Power Reactors (Withdrawn 3.76) Termination of Operating Licenses for Nuclear Reactors Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (Issued for Comments) Standard Format and Content of License Applications for Uranium Mills (Issued for Comments) Standard Format and Content of License Applications for Storage Only of Unirradiated Reactor Fuel and Associated Radioactive Material Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants Standard Format and Content for the Special Nuclear Material Control and Accounting Section of a Special Nuclear Material License Application (Including That for a Uranium Enrichment Facility) Standard Format and Content for the Physical Protection Section of a License Application (For Facilities Other Than Nuclear Power Plants) (Revision to Chapter 4 and 18 were issued 7.78; issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Nuclear Power Plants (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Transportation (Issued for Comments) Standard Format and Content of Licensee Physical Protection Plan for Strategic Special Nuclear Material in Transit Standard Format and Content of Part 71 Applications for Approval of Packaging of Type B, Large Quantity and Fissile Radioactive Materials (Issued for Comments) Suggested Format for Cash Flow Statements Submitted as Guarantees of Payment of Retrospective Premiums (Issued for Comments) Guide for the Preparation of Applications for Licenses to Process Source Material
Status Iss
3.79
Iss
12.77
iss
5.79
Iss
6.74
Iss
3.76
Iss
11.77
Iss
10.73
Iss
12.74
Iss
1.76
Iss
12.74
Iss
6.76
Iss
3.78
Iss
3.78
Iss
3.78
Iss
480
Iss
379
Iss
9.78
Iss
3.77
51
3.5 No.
Issuing Body (Country)
Task No. FP 818-4
USNRC
Task No. MP 711-4
USNRC
10 CFR 50
USNRC
10 CFR 50 Appendix C USNRC
10 CFR 50 Appendix L
USNRC
10 CFR 50 Appendix M USNRC
10 CFR 50 Appendix N USNRC 10 CFR 50 Appendix 0
USNRC
10 CFR 51
USNRC
10 CFR 55 10 CFR 140
USNRC USNRC
VdTUVWei 15
VdTUV
BGBI. I, S. 266
(DEU)
BGBI. 1, S. 273
(DEU)
52
Title
Status
(Remarks!
Standard Format and Content of Licensee Applications, Including Environmental Reports, for In Situ Uranium Solution Extraction (Proposed R. G) Standard Format and Content for a Licensee Physical Security Plan for the Protection of Special Nuclear Material of Moderate or Low Stratetic Significance (Proposed R. G.) Domestic Licensing of Production and Utilization Facilities A Guide for the Financial Data and Related Information Required to Establish Financial Qualification for Facility Construction Permits and Operating Licenses Information Requested by the Attorney Gfeneral for Antitrust Review Facility License Applications Standardization of Design; Manufacture of Nuclear Power Reactors; Construction and Operation of Nuclear Power Reactors Manufactured Pursuant to Commission License Standardization of Nuclear Power Plant Designs: Licenses to Construct and Operate Nuclear Power Reactors of Duplicate Design at Multiple Sites Standardization of Design; Staff Review of Standard Designs Licensing and Regulatory Policy and Procedures for Environmental Protection Operator's Licenses Financial Protection Requirements and Indemnity Agreements Zusammenstellung der in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Priifung erforderlichen Informationen Kostenverordnung zum Atomgesetz vom 24. Marz 1971 Verordnung iiber das Verfahren bei der Genehmigung von Anlagen nach §7 des Atomgesetzes (Atomrechtliche Verfahrensverordnung - AtVfV) vom 18. Februar 1977
Iss
7.80
Iss
7.79
Iss
3.78
Iss
3.71
Iss
2.77
4.1 No. 4
Issuing Body (Country)
Title
Status
(Remarks)
Siting anid E n v i r o n m e n '
4.1 General ANS-2.7
Pub
11.79
Pub
77
ANS-15.7 /ANSI N379 ANS-18.1 /ANSI N237 ANS-54.7 ANSI N287
ANS
Assessing Capability for Surface Faulting at Nuclear Power Sites, Guidelines (Issued for Comments) Siting for Research Reactors
ANS
Source Term Specification
App
76
ANS ANSI
Ust Pub
76
GMBI. 1975 S. 602
BMI
GMBI. 1977 S 683
BMI
GMBI. 1979 S. 668
BMI
Umwelt Nr. 43/75
BMI
CNEN NE 1.03
CNEN
IAEA 50-C-D
IAEA
IAEA50-C-S
IAEA
IAEA 50-SG-S9 R.G. 1.70.7
IAEA USNRC
R.G. 1.70.8
USNRC
R.G 1 70.24
USNRC
R.G. 1 132
USNRC
R.G. 1.138
USNRC
R.G. 3.8
USNRC
R.G. 3 24
USNRC
R.G. 4.2
USNRC
R.G. 4.7
USNRC
Site Suitability Source Term Criteria for Siting, Design, and Operation of Plants for the Manufacture of Mixed Oxide (UPU) Fuels Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber den Standort, den Sicherheitsbehalter, das Reaktorschutzsystem und den Reaktordruckbehalter vom 30.7.1975 (Withdraw: directions to reactor protection system and reactor pressure vessel, see GMBI. 1977 S. 66 and GMBI. 1977 S. 739) Rahmenempfehlungen fur den Katastrophenschutz in der Umgebung kerntechnischer Anlagen vom 17.10.1977 Richtlinie zur Emissions- und Immissionsiiberwachung kerntechnischer Anlagen Bewertungsdaten fur die Eigenschaften von Kernkraftwerksstandorten aus der Sicht von Reaktorsicherheit und Strahlenschutz vom 11.6.1975 Site Selection for Installation of Power Reactors (Under Revision) Design for Safety of Nuclear Power Plants, Code of Practice Safety in Nuclear Power Plant Siting, Code of Practice Site Survey for Nuclear Power Plants Additional Information: Geography and Demography Considerations for Nuclear Power Plants (See also R. G. 1.70) Additional Information: Nearby Industrial Transportation and Military Facilities (See also R. G. 1.70) Information for Safety Analysis Reports Environmental Design of Mechanical and Electrical Equipment, Qualification Tests and Analysis (See also R.G 1.70) Site Investigations for Foundations of Nuclear Power Plants Laboratory Investigations of Soils for Engineering Analysis and Design of Nuclear Power Plants (Issued for Comments) Preparation of Environmental Reports for Uranium Mills (Issued for Comments) Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation Preparation of Environmental Reports for Nuclear Power Stations General Site Suitability Criteria for Nuclear Power Stations
ANS
Iss
7.75
Iss
10.77
Iss
79
Iss
6.75
Iss
69
Pub
78
Pub
78
Ust Iss
10.74
Iss
10.74
Iss
2.75
Iss
379
Iss
4.78
Iss
9.78
Iss
12.74
Iss
776
Iss
11.75
53
4.1 No.
Issuing B o d y (Country)
R.G. 4.8
USNRC
R.G. 4.9
USNRC
10 CFR 50 Appendix F USNRC 10 CFR 50 Appendix Q USNRC 10 CFR 100 BGBI I, S. 306 /BGBI. I, S 3573
USNRC (DEU)
BGBI. I. S. 3574
(DEL))
Act No. 393
(ITA)
Decree No. 185
(ITA)
Leg Series 1965 No. 12
(YUG)
54
Title (Remarks) Environmental Technical Specifications for Nuclear Power Plants (Issued for Comments) Preparation of Environmental Reports for Commercial Uranium Enrichment Facilities Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities Pre-application Early Review of Site Suitability Issues Reactor Site Criteria Raumordnungsgesetz vom 8. April 1965, zuletzt geandert durch §35 des Bundesnaturschutzgesetzes vom 20. Dezember 1976 Gesetz uber Naturschutz und Landschaftspflege (Bundesnaturschutzgesetz - BNatSchG) vom 20 Dezember 1976 Rules Governing the Location of Nuclear Power Stations and the Production and Use of Electricity (See "Gazzetta Ufficiale No. 224") Decree No. 18 of the President of Republic on the Safety of Installations and the Health Protection of Workers and the Population Against the Hazards of Ionizing Radiations Resulting from Peaceful Use of Nuclear Energy (See "Gazzetta Ufficiale No. 95") Air Traffic Act (Art 150: Minimum Distance Between Aerodromes and Nuclear Installations)
Status Iss
12.75
Iss
10.75
Iss 4.65 Amm 12.76 Iss
1276
Iss
475
Iss
2.64
Iss
3.65
4.2 No. 4
Issuing Body (Country)
Title (Remarks)
Status
Siting an d E n v i r o n m e n '
4.2 Geologic,, Seismic and o t h e r Considerations ANS-22 Earthquake Instrumentation Criteria for Nuclear ANS Power Plants Assessing Capability for Surface Faulting at Nuclear ANS-2.7 ANS Power Sites, Guidelines (Issued for Comments) ANS-2.10 ANS Guidelines for Retrieval, Review, Processing and Evaluation of Records Obtained from Seismic Instrumentation Guidelines for Evaluating Site-Related Geotechnical ANS-2.11 ANS Parameters at Nuclear Power Sites ANS-2.12 Guidelines for Combining Natural Phenomena and ANS Man-Made Hazards at Power Reactor Sites ASME QA-76-20 ASME Supplementary Quality Assurance Requirements for /ANSI N45.2.20 Subsurface Investigation Prior to the Construction Phase of Nuclear Power Plants MCH/MENT 9 CEA Guide de procedures pour les essais sur le site de I'instrumentation des reacteurs nucleaires DIN 25445 DIN Auslegung von Kernkraftwerken gegen seismische Teil 5 Einwirkungen; Seismische Instrumentierung, Sicherheitstechnische Anforderungen (Design of Nuclear Plant against Seismic Effects; Seismic Instrumentation, Safety Requirements] (Identical with KTA 2201.5) IAEA 50-SG-D5 IAEA Man-Induced Events in Relation to Nuclear Power Plant Design IAEA IAEA 50-SG-S1 Earthquakes and Associated Topics in Relation to Nuclear Power Plant Siting IAEA 50-SG-S2 IAEA Seismic Analysis and Testing of Nuclear Power Plants IAEA IAEA 50-SG-S5 Extreme Man-Induced Events in Relation to Nuclear Power Plant Siting IEEE 344 IEEE Seismic Qualification of Class 1 Electric Equipment for Nuclear Power Generating Stations . IfBT Richtlinien fur die Bemessung von Stahlbetonbauteilen von Kernkraftwerken fur auftergewbhnliche auUere Belastungen (Erdbeben, groftere Explosionen, Flugzeugabsturzl ISO/DP 6258 Seismic Design of Nuclear Power Plant ISO KTA Auslegung von Kernkraftwerken gegen seismische KTA 2201.1 Einwirkungen Teil 1: Grundsatze (Design of Nuclear Power Plants Against Seismic Effects Part 1: Basic Principles) (Available also in English) KTA 2201.5 Auslegung von Kernkraftwerken gegen seismische KTA Einwirkungen Teil 5: Seismische Instrumentierung (Design Nuclear Power Plants Against Seismic Effects Part 5: Seismic Instrumentation) (Available also in English; Identical with DIN 25445 Teil 5) RDT F 9-2T ORNL Seismic Requirements for Design of Nuclear Power Plants and Nuclear Test Facilities USNRC Instrumentation for Earthquakes R G 1.12 (Under Revision) USNRC RG. 1.29 Seismic Design Classification R.G. 1.48 USNRC Design Limits and Loading Combinations for Seismic Category I Fluid System Components
Pub
78
Pub
11.79
Pub
79
Pub
78
Pub
78
Pub
979
Pub
75
Pub
2.78
Ust Pub
79
Pub
79
Ust Pub
75
Pub Amm
7.74 8.75
Ust Pub
6.75
Pub
6.77
Pub
1.79
Iss
474
Iss Iss
978 5.73
55
4.2 No.
Issuing Body
(Country!
R.G. 1.60
USNRC
R.G. 1.61
USNRC
R.G. 1.70.9
USNRC
R.G. 1.70.23
USNRC
R.G. 1.91
USNRC
R.G. 1.92
USNRC
R.G. 1.100
USNRC
R.G. 1122
USNRC
R.G. 1.132
USNRC
R.G. 1.138
USNRC
R.G. 3.14
USNRC
10 CFR 100 Appendix A USNRC
56
Title
Status
(Remarks)
Design Response Spectra for Seismic Design of Nuclear Power Plants Damping Values for Seismic Design of Nuclear Power Plants Additional Information: Design of Seismic Category I Structures (See also R.G. J.70) Information for Safety Analysis Reports - Seismic Qualification of Instrumentation and Electrical Equipment (See also R.G. 1.70) Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants (Issued for Comments) Combining Modal Responses and Spatial Components in Seismic Response Analysis Seismic Qualification of Electric Equipment for Nuclear Power Plants Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components Site Investigations for Foundations of Nuclear Power Plants Laboratory Investigations of Soils for Engineering Analysis and Design of Nuclear Power Plants (Issued for Comments) Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants Seismic and Geologic Siting Criteria for Nuclear Power Plants
Iss
12.73
Iss
10.73
Iss
11.74
Iss
2.75
Iss
2.78
Iss
2.76
Iss
8.77
Iss
2.78
Iss
3.79
Iss
4.78
Iss
10.73
4.3 No. 4 4.3
Issuing Body (Country)
Status
Title (Remarks)
Siting and E n v i r o n m e n t a l Protection
M e t e o r o l o g y and H y d r o l o g y Standards for Determining Design Basis Flooding at ANS-2.8 ANS Power Reactor Sites Evaluating Surface-Water Supply for Nuclear Power ANS-2.13 ANS Plants Atmospheric Dispersion in Relation to Nuclear Power IAEA 50-SG-S3 IAEA Plant Siting Hydrological dispersion of Radioactive Material in IAEA 50-SG-S6 IAEA Relation to Nuclear Power Plant Siting Determination of Design Basis Floods for Nuclear IAEA50-SG-S10A IAEA Power Plants on River Sites Determination of Design Basis Floods for Nuclear IAEA50-SG-S10B IAEA Power Plants on Coastal Sites Evaluation of Extreme Meteorological Events for IAEA50-SG-S11 IAEA Nuclear Power Plant Siting R.G 1.23 Onsite Meteorological Programs USNRC (Safety Guide 23) Design Basis Floods for Nuclear Power Plants R.G. 1.59 USNRC R.G. 1.70.1 USNRC Hydrological Considerations for Nuclear Power Plants (See also R.G. 1.70) USNRC Additional Information: Water Level (Flood) Design R.G. 1.70.5 for Nuclear Power Plants (See also R. G. 1.70) Additional Information: Wind and Tornado Loadings R.G. 1.70.10 USNRC (See also R. G. 1.70) USNRC Information for Safety Analysis Reports-Hydrological R.G. 1.70.17 Engineering (See also R.G. 1.70) R.G. 1.70.29 Information for Safety Analysis Reports USNRC Meteorology (See also R.G. 1.70) R.G. 1.76 USNRC Design Basis Tornado for Nuclear Power Plants R.G. 1.102 USNRC Flood Protection for Nuclear Power Plants R.G. 1.117 USNRC Tornado Design Classification R.G. 1.127 USNRC Inspection of Water-Control Structures Associated with Nuclear Power Plants USNRC R.G. 1.132 Site Investigations for Foundations of Nuclear Power Plants USNRC R.G. 1.135 Normal Water Level and Discharge at Nuclear Power Plants (Issued for Comments) Design Basis Floods for Fuel Reprocessing Plants R.G. 3.40 USNRC and for Plutonium Processing and Fuel Fabrication Plants USNRC Safety-Related Permanent Dewatering Systems for Task No. FP 811-4 Nuclear Power Plants (Proposed R.G.) Task No. RS 705-4 Lightning Protection for Nuclear Power Plants USNRC (Proposed R.G.)
App
76
Pub
1279
Ust Ust Ust Ust Ust Iss
2.72
Iss Iss
877 12.73
Iss
8.74
Iss
11.74
Iss
75
Iss
4.75
Iss Iss Iss Iss
4.74 9.76 4.78 3.78
Iss
3.79
Iss
9.77
Iss
12.77
Iss
9.79
Iss
8.79
57
4.4 No. 4
Issuing Body (Country)
Title (Remarks)
S i t i n g and E n v i r o n m e n t a l Protection
4.4 N o n - r a d i o l o g i c a l E n v i r o n m e n t a l Effects ANS-18.4 ANS Aquatic Ecological Survey Guidelines for the Siting, Design, Construction, and Operation of Thermal Power Plants (Issued for Comments) IAEA 50-SG-S4 IAEA Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution R.G. 1.70.7 USNRC Additional Information: Geography and Demography Considerations for Nuclear Power Plants (See also R. G. 1.70) R.G. 4.4 USNRC Reporting Procedures for Mathematical Models Selected to Predict Heated Effluent Dispersion in Natural Water Bodies R.G 4.5 USNRC Measurements of Radionuclides in the Environment Sampling and Analysis of Plutonium in Soil R.G. 4.11 USNRC Terrestrial Environmental Studies for Nuclear Power Stations
58
Status
Pub
11.79
Ust Iss
10.74
Iss
5.74
Iss
5.74
Iss
8.77
4.5 No.
Issuing Body (Country)
Title (Remarks)
4
Siting and E n v i r o n m e n t a l Protection
4.5
Air Pollution, M e a s u r e m e n t
ANSI N13.1
ANSI
ANSI N303
ANSI
GMBI. 1979 S. 371
BMI
BS 5243
BSI
DIN 44801
DIN
DIN 44804
DIN
GO ST 15485 IEC 579
GOST IEC
ISO 2889
ISO
GSN-11
JEN
JIS Z4512
JIS
KTA 1503.1
KTA
TS^3236
TSE
R.G. 1.21
USNRC
R G. 1.42
USNRC
R.G. 1.111
USNRC
R G 1.112
USNRC
R G. 4.14
USNRC
Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities Guide for Control of Gasborne Radioactive Materials at Fuel Reprocessing Facilities Allgemeine Berechnungsgrundlagen fur die Strahlenexposition bei radioaktiven Ableitungen mit der Abluft oder in Oberflachengewasser (Richtlinie zu §45 StrlSchVI vom 15 8.79 General Principles for Sampling Airborne Radioactive Materials Alpha-, Beta- und Alpha-Beta-Kontaminationsmeftgerate und -monitoren (Alpha, Beta and Alpha-Beta Contamination Meters and Monitors] Messen, Steuern, Regeln; Kontaminationsmelsgerate und -monitoren fur radioaktive Aerosole (Measurement and Control; Radioactive Aerosol Contamination Meters and Monitors) Radioaktive Aerosole; Klassifikation Radioactive Aerosol Contamination Meters and Monitors General Principles tor Sampling Airborne Radioactive Materials Vigilancia de Efluentes Radiactivos Liquidos y Gaseosos Liberados en Centrales Nucleares de Potencia. (Monitoring of Airborne and Liquid Radioactive Releases form Nuclear Power Plants) Measuring Methods of Concentration of Airborne Radioactive Particle Messung und Uberwachung der Ableitung gasformiger und aerosolgebundener radioaktiver Stoffe, Teil 1: Messung und Uberwachung der Ableitung radioaktiver Stoffe mit der Kaminabluft bei bestimmungsgemafsem Betrieb (Measurement and Monitoring of Gaseous and Airborne Radioactive Effluents; Part 1: Measurement and Monitoring Radioactive Substance in the Smoke Stack during Normal Operations) (Available also in English) General Principles for Sampling Airborne Radioactive Materials Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Release of Radioactivity in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants Interim Licensing Policy on As-Low-As Practicable for Gaseous Radioiodine Release from Light-Water-Cooled Nuclear Power Reactors (Withdrawn 3.76) Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquids and Airborne Effluents from Uranium Mills
Status
Pub
69
Pub
78
Iss
8.79
Pub
75
Pub
8.78
Pub
8.78
Pub Pub
70 77
Pub
75
Drf
79
Pub
76
Pub
279
Iss
6.74
Iss
7.77
Iss
5.77
Iss
4.80
59
4.5 No.
Issuing Body
(Country)
R.G. 4.16
USNRC
Task No. RH 802-4
USNRC
10 CFR 20 Appendix B USNRC
60
Title
Status
(Remarks}
Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Airborne Effluents from Nuclear Fuel Processing and Fabrication Plants (Issued for Comments) Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations (Proposed R. G.) Concentrations in Air and Water Above Natural Background
Iss
3.78
Iss
5.79
4.6 No. 4
Issuing Body (Country}
Status
Title (Remarks)
Siting and E n v i r o n m e
4.6 W a t e r Pollutioi i , M e a ; ASTM D 1690 ASTM ASTM D 1890
ASTM
ASTM D 1943
ASTM
ASTM D 2038
ASTM
ASTM D 2039 ASTM D 2333 ASTM D 2334
ASTM ASTM ASTM
ASTM D 2459 ASTM D 2460 ASTM D 2461
ASTM ASTM ASTM
ASTM D 2470
ASTM
ASTM D 2476 ASTM D 2577 GMBI. 1979 S. 371
ASTM ASTM BMI
CNS 3822
CNBS
CNS 3823
CNBS
DIN 25416 Teil 1
DIN
DIN 25423 Bbl 1
DIN
DIN 25423 Teil 1
DIN
DIN 25423 Teil 2
DIN
DIN 25423 Teil 3
DIN
Gamma Radioactivity of Industrial Water and Industrial Waste Water, Method for Measurement Beta Particle Radioactivity of Water, Method of Test Alpha Particle Radioactivity of Water, Method for Measurement Radioactive Barium in Industrial Water and Industrial Waste Water, Method of Test Radioactive Manganese in Water, Method of Test Thorium in Water and Waste Water, Method of Test Radioactive Iodine in Industrial Water and Industrial Waste Water, Method of Test Gamma Spectrometry of Water, Method of Test Radionuclides of Radium in Water, Method of Test lron-59 in Water, Method of Test Delayed Neutron-Emitting Fission Products in Nuclear Reactor Coolant Water during Reactor Operation, Method for Measurement Radioactive Tritium in Water, Method of Test Radioactive Cesium in Water, Method of Test Allgemeine Berechnungsgrundlagen fur die Strahlenexposition bei radioaktiven Ableitungen mit der Abluft oder in Oberflachengewasser (Richtlinie zu §45 StrlSchV) vom 15.8.79 Method of Determination for Gross Alpha Radiation in Waste Water Method of Determination for Gross Beta Radiation in Waste Water Anlagen zur Behandlung von radioaktiv kontaminiertem Wasser in Kernkraftwerken; Sicherheitstechnische Anforderungen (Treatment of Radioactive Contaminated Water in Nuclear Power Plants; Safety Requirements) (in Press; Identical with KTA 3603) Probenahme bei der Radioaktivitatsuberwachung der Luff; Hinweise zur Berechnung von Partikelverlusten in Probenahmeleitungen und Hinweise zur Fehlerermittlung anisokinetischer Probenahme • (Sampling Procedures for the Monitoring of Radioactivity in Air; General Aspects for the Calculation of Particle Loss in Sampling Air Ducts, General Aspects for Error Estimates due to Anisokinetic Sampling) Probenahme bei der Radioaktivitatsuberwachung der Luft; Allgemeine Anforderungen (Sampling Procedures for the Monitoring of Radioactivity in Air, General Requirements) Probenahme bei der Radioaktivitatsuberwachung der Luft; Spezielle Anforderungen bei der Probenahme aus Kanalen und Schornsteinen (Sampling Procedures for the Monitoring of Radioactivity in Air; Special Requirements for Sampling from Air Ducts and Smoke Stacks) Probenahme bei der Radioaktivitatsuberwachung der Luft; Probenahmeverfahren (Sampling Procedures for the Monitoring of Radioactivity in Air; Sampling Methods)
Pub Rev Pub Rev Pub Rev Pub
61 67 66 71 66 71 68
Pub Pub Pub
71 68 68
Pub Pub Pub Rev Pub
69 70 61 69 70
Pub Pub Iss
70 69 8.79
Iss
7.75
Iss
7.75
Pub
12.77
Pub
12.77
Pub
1277
Pub
12.77
61
4.6 No.
Issuing Body (Country)
DIN 25465
DIN
GOST 15486
GOST
IAEA50-SG-S6
IAEA
GSN-11
JEN
JISZ4513
JIS
KTA 1504
KTA
KTA 3603
KTA
NCRP Report No.16 NEN2395
NCRP NNI
NEN 2396
NNI
AECP 1058
UKAEA
R.G. 1.21
USNRC
R.G. 1.56
USNRC
R.G. 1.112
USNRC
R.G. 1.113
USNRC
R.G. 1.135
USNRC
R.G. 4.14
USNRC
R.G. 4.16
USNRC
10 CFR 20 Appendix B USNRC
62
Title (Remarks) Messung flussiger radioaktiver Stoffe zur Uberwachung der radioaktiven Ableitungen; Sicherheitstechnische Anforderungen (Measuring Liquid Radioactive Materials for Monitoring Radioactive Discharges; Safety Requirements) (Identical with KTA 1504) Gamma-Radiometer zur Messung der Verunreinigung endloser Gewasser durch radioaktive Isotope Hydrological dispersion of Radioactive Material in Relation to Nuclear Power Plant Siting Vigilancia de Efluentes Radiactivos Liquidos y Gaseosos Liberados en Centrales Nucleares de Potencia. (Monitoring of Airborne and Liquid Radioactive Releases form Nuclear Power Plants) Measuring Methods of Beta-Radioactivity Concentration of Drain Water Messung flussiger radioaktiver Stoffe zur Uberwachung der radioaktiven Ableitungen (Measuring Liquid Radioactive Materials for Monitoring Radioactive Discharges) (Available also in English; Identical with DIN 25465) Anlagen zur Behandlung von radioaktiv kontaminiertem Wasser in Kernkraftwerken (Treatment of Radioactive Contaminated Water in Nuclear Power Plant) (Identical with DIN 25416 Teil 1) Radioactive Waste Disposal in the Ocean Bepaling Van De Beta-Radioactiviteit In Water (Determination of the Beta-Radioactivity in Water) Bepaling Van De Radioactiviteit In Water, Afkomstig Van Isotopen Van De Aardalkalimetalen (Determination of the Radioactivity in Water, Originating from Isotopes of the Alkaline Earth Metals) Drainage of Radioactive Areas (Provisional only) Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Release of Radioactivity in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants Maintenance of Water Purity in Boiling Water Reactors (Issued for Comments) Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from , Light-Water-Cooled Power Reactors Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Release for the Purpose of Implementing Appendix I Normal Water Level and Discharge at Nuclear Power Plants (Issued for Comments) Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquids and Airborne Effluents from Uranium Mills Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Airborne Effluents from Nuclear Fuel Processing and Fabrication Plants (Issued for Comments) Concentrations in Air and Water Above Natural Background
Status Pub
3.79
Pub
70
Ust Drf
79
Pub
77
Pub
6.78
Pub
2.80
Pub
54
Iss
79
Iss
6.74
Iss
7.78
Iss
5.77
Iss
4.77
Iss
9.77
Iss
4.80
Iss
3.78
4.6 No.
Issuing Body (Country)
VdTUV Wei 22
VdTUV
BGBI. I, S. 2478
(DEU)
BGBI. I, S. 3017 /BGBI. I, S. 3341 /BGBI. I, S. 373
(DEU)
BGBI. II. S. 165 /BGBI. I, S. 373
(DEU)
(INT)
Title /Remarks) Anforderungen an die MeUeinrichtungen zur kontinuierlichen Aktivitatsuberwachung der Wasserund Wasserdampf-Kreislaufe in Kernkraftwerken mit Leichtwasserreaktoren Verordnung zur DurchfLihrung des Gesetzes zu den Ubereinkommen vom 15. Februar 1972 und 29. Dezember 1972 zur Verhutung der Meeresverschmutzung durch das Einbringen von Abfallen durch Schiffe und Luftfahrzeuge (Hohe-See-Einbringungsverordnung) vom 7. Dezember 1977 Gesetz zur Ordnung des Wasserhaushalts - WHG vom 27. Juli 1957 in der Fassung der Bekanntmachung vom 16. Oktober 1976, zuletzt geandert durch Artikel 7 des Gesetzes vom 28. Marz 1980 Gesetz zu dem Ubereinkommen vom 15. Februar 1972 und 29. Dezember 1972 zur Verhutung der Meeresverschmutzung durch das Einbringen von Abfallen durch Schiffe und Luftfahrzeuge vom 11. Februar 1977, zuletzt geandert durch Artikel 11 des Gesetzes vom 28. Marz 1980 Brussels Agreement of Dec. 12, 1971, Regarding the Civil-law. Liability During the Transport of Nuclear Material on Sea
Status Iss
5.80
Iss
12.77
Iss 7.57 Amm 12.76 Amm 3.80 Iss Amm
2.77 3.80
App
12.71
63
4.7 No. 4
Issuing Body (Country)
Status
Title
(Remarks)
Siting and E n v i r o n m e n t a l Protection
Other A s p e c t s of Environ m e n t a l M o n i t o r i n g ANHMRC Dose Equivalents, Maximum Permissible Doses and • Dose Limits of Ionising Radiation Calculation and Measurement of Direct and ANS ANS-3.6.1 Scattered Gamma Radiation from LWR Nuclear Power Plants Radiological Control at Research Reactor Facilities ANS-15.11 ANS /ANSI N628 ANS ANS-15.12 Design Objectives for and Monitoring of Systems /ANSI N647 Controlling Research Reactor Effluents ANSI ANSI N13.4 Specification of Portable X- and Gamma Radiation Survey Instruments ANSI ANSI N13.10 Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents ANSI ANSI N545 Environmental Application of Thermoluminescent Dosimetry BMI GMBI. 1978 S. 313 Kontrolle der Eigeniiberwachung radioaktiver Emissionen aus Kernkraftwerken vom 10.5.1978 IAEA IAEA 50-SG-S3 Atmospheric Dispersion in Relation to Nuclear Power Plant Siting ICRP ICRPPubl. 7 Principles of Environmental Monitoring Related to the Handling of Radioactive Materials ICRU ICRU Report No. 22 Measurement of Low-Level Radioactivity ICRU ICRU Report No. 25 Conceptual Basis for the Determination of Dose Equivalent IEC I EC 325 Alpha, Beta and Alpha-Beta Contamination Meters and Monitors IEC IEC 395 Portable X or Gamma Radiation Exposure Rate Meters and Monitors for Use in Radiological Protection IEC 463 IEC Low Energy X or Gamma Radiation Portable Exposure Rate Meters and Monitors for Use in Radiological Protection GSN-03 Guia Para el Establecimiento de un Programa de JEN Vigilancia Radiologica Ambiental en las Zonas de Influencia de las Centrales Nucleares. (Enviromental Monitoring Programme) GSN-09 Programa de Vigilancia Radiologica Ambiental para JEN Centrales Nucleares de Potencia. (Environmental Monitoring Programme) JIS Z4222 JIS General Rules for Geiger-Miiller Counter Tubes JIS Z4309 JIS Ionization Chamber Type Radiation Survey Meters JISZ4310 JIS Geiger-Miiller Counter Tube Type Radiation Survey Meters JIS Z4312 JIS Scintillation Survey Meters for Gamma Rays JISZ4315 JIS Geiger-Miiller Counter Type Hand-Foot Monitors JIS Z4316 JIS Radioactive Dust Monitors JIS Z4317 JIS Gas Flow Counter Type Survey Meters for Radioactive Surface Contamination JIS JIS Z4318 Gas Filled Counter Type Survey Meters for Radioactive Surface Contamination JIS JIS Z4319 Counters for Geiger-Miiller Tubes JIS Z4321 Thallium-Activated Sodium Jodide Scintillator for JIS Radiation Detection JIS Z4601 Radioactive Dust Samplers JIS Protection Against Neutron Radiation NCRP NCRP Report No.38 Tritium Measurement Techniques NCRP Report No.47 NCRP NCRP NCRP Report No.50 Environmental Radiation Measurements NCRP Report No.52 NCRP Cesium-137 from the Environment to Man: Metabolism and Dose
4.7
64
Iss
69
Drf
79
Pub
77
Pub
77
Pub Rev Pub
71 77 74
Pub
75
Iss
5.78
Ust Pub
65
Pub Pub
72 76
Pub
70
Pub
72
Pub
74
Iss
10.76
Iss
11.78
Pub Pub Pub
77 76 76
Pub Pub Pub Pub
76 77 78 76
Pub
76
Pub Pub
77 77
Pub Pub Pub Pub Pub
78 71 76 76 77
4.7 No.
Issuing Body (Country!
NCRP Report No.59 R.G. 1.21
NCRP USNRC
R.G. 1.109
USNRC
R.G. 1.111
USNRC
R.G. 1.112
USNRC
R.G. 1.113
USNRC
R.G 4.1
USNRC
R.G. 4.2
USNRC
R.G. 4.3
USNRC
R.G. 4.6
USNRC
R.G. 4.9
USNRC
R.G. 4.13
USNRC
R.G. 4.15
USNRC
R.G. 8.2 R.G. 8.9
USNRC USNRC
R.G. 8.11 R.G. 8.13 R.G. 8.22
USNRC USNRC USNRC
VdTUVWei 21
VdTUV
Title (Remarks) Operational Radiation Safety Program Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Release of Radioactivity in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Release for the Purpose of Implementing Appendix I Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants (Issued for Comments) Preparation of Environmental Reports for Nuclear Power Stations Measurements of Radionuclides in the Environment Analysis of 1-131 in Milk (Withdrawn 12.76) Measurements of Radionuclides in the Environment Strontium-89 and Strontium-90 Analysis Preparation of Environmental Reports for Commercial Uranium Enrichment Facilities Performance, Testing, and Procedural Specifications for Thermoluminescene Dosimetry: Environmental Applications Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment Administrative Practices in Radiation Monitoring Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program Applications of Bioassay for Uranium Instruction Concerning Prenatal Radiation Exposure Bioassay at Uranium Mills (Under Revision) Erfassung und Begrenzung von Jod-131-Emissionen aus dem Sekundarkreis von Kernkraftwerken mit Druckwasserreaktoren im bestimmungsgemaUen Betrieb
Status
Iss
6.74
Iss
10.77
Iss
7.77
Iss
5.77
Iss
4.77
Iss
4.75
Iss
7.76
Iss
5.74
Iss
10.75
Iss
7.77
Iss
2.79
Iss Iss
2.73 9.73
Iss Iss Iss
6.74 11.75 7.78
Iss
10.78
65
5.1 No.
Issuing Body (Country)
5
Radiation Protection
5.1
General
* ANS-3.6.1 ANS-37.1 ANS-6.5 ANS-6.61 ANS-1511 /ANSI N628 ANS-18.1 /ANSI N237 ANSI N2.1 ANSI N7.1a /ANSI N508 ANSI N12.1 ANSI N13.1
Status
ANHMRC Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores ANS Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plants ANS Facilities and Medical Care for on Site Nuclear Power Plant Radiological Emergencies ANS Glossary of Terms in Shielding and Dosimetry (Issued for Trial Use) ANS Calculation and Measurement of Direct and Scattered Gamma Radiation from Nuclear Power Plants ANS Radiological Control at Research Reactor Facilities
Iss
75
Drf
79
Drf
1078
ANS ANSI ANSI ANSI ANSI
ANSI N13.2
ANSI
ANSI N13.4
ANSI
ANSI N13.8 ANSI N13.12
ANSI ANSI
ANSI N42.5
ANSI
ANSI N42.6
ANSI
ANSI N42.13
ANSI
ANSI N42.14
ANSI
ANSI N303
ANSI
ANSI N320
ANSI
ANSI N323
ANSI
ASTM C 638 /ANSI N649
ASTM
ASTM E 184
ASTM
ASTM E 521
ASTM
ASTM E 560
ASTM
ASTM E 635
ASTM
ZH1-202
BG
66
Title (Remarks)
Pub
79
Pub
79
Pub
77
Source Term Specification
App
76
Radiation Symbol Protection from Radiation and Other Hazards in Uranium Milling and Concentrating Fissile Material Symbol Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities Guide for Administrative Practices in Radiation Monitoring Specification of Portable X- and Gamma Radiation Survey Instruments Radiation Protection in Uranium Mines Operation Control of Radioactive Surface Contamination on Materials. Equipment and Apparatus to be Released for Uncontroled Use Base for GM Counter Tubes
Pub Pub
69 69
Pub Pub
71 69
Pub
69
Pub Rev Pub Pub
71 77 73 79
Pub Rev Pub
71 77 78
Pub
78
Pub
78
Pub
78
Interrelationship of Quartz-Fiber Electrometer Type Dosimeters and Companion Dosimeter Charges Calibration and Usage of "Dose Calibrator" Ionization Chambers for the Assay of Radionuclides Calibration and Usage of Germanium Detectors for Measurement of Gamma-Ray Emmission of Radionuclides Guide for Control of Gasborne Radioactive Materials at Fuel Reprocessing Facilities Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation Radiation Protection Instrumentation Test and Calibration Descriptive Nomenclature of Constituents of Aggregates for Radiation Shielding Concrete (Reapproved) Effects of High-Energy Radiation on the Mechanical Properties of Metallic Materials Recommended Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation Rec. Pract. for Relating Dosimetry Results From A Reactor Vessel Surveillance Capsule to the Neutron Fluence Levels At and Through the Pressure Vessel Wall Predicting Radiation Effects in Water cooled Reactor Pressure Vessel Richtlinien: Umschlossene Radioaktive Stoffe
Pub
79
Pub
77
Pub App
73 2.79
Pub
62
Pub
77
Pub
75
Ust
5.1 No.
Issuing Beidy /Country)
GMBI 1978 S 348
BM!
GMBI 1979 S. 120
BMI
BS 2597 BS3510
BSI BSI
BS 3890
BSI
BS 4094
BSI
BS 5243
BSI
NF C 01-076
CEA
NF M 60-101
CEA
NF M 60-103
CEA
80/836/Euratom
CEC
CNEN NE 3.01
CNEN
CNEN NE 3.02
CNEN
CNEN NE 3 03
CNEN
DIN 6818 Teil 1 DIN 25400
DIN
DIN 25401 Teil 8
DIN
DIN 25426 Teil 1
DIN
DIN 25426 Teil 2
DIN
DIN 25426 Teil 4
DIN
DIN 25430
DIN
DIN
Status
Title
1
(Remarks)
Richtlinie fur die physikalische Strahlenschutzkontrolle (§§ 62 und 63 StrlSchV) vom 56.1978 Richtlinien iiber Pruffristen bei Dichtheitspriifungen an umschlossenen radioaktiven Stoffen vom 233.1979 Glossary of Terms Used in Radiology A Basic Symbol to Denote the Actual or Potential Presence of Ionizing Radiation General Recommendations for the Testing, Calibration and Processing of Radiation Monitoring Films Recommendation for Data on Shielding from Ionizing Radiation General Principles for Sampling Airborne Radioactive Materials Vocabulaire electrotechnique - Groupe 76 Detection et mesure par voie electrique des rayonnements ionisants Signalisation des rayonnements ionisants - Schema de base (Basic Principles for Ionizing Radiation Warning) Signalisation des rayonnements ionisants - Bandes de balisage pour la delimitation de zones particulieres pouvant presenter des risques radiologiques (Ionizing Radiation Warning: Identification Marking of Special Zone Presenting Radiation Risks) Richtlinie des Rates vom 15. Juli 1980 zur Anderung der Richtlinien, mit denen die Grundnormen fur den Gesundheitsschutz der Bevolkerung und der Arbeitskrafte gegen die Gefahren ionisierender Strahlungen festgelegt wurden (Revision of the Basic Regulation 76/579/Euratom) Basic Radiological Protection (Under Revision) Licensing of Individuals and Institutions for the Inspection and Application of Radiological Protection Measures Radiological Protection in the Thorium and Uranium Cycle Strahlenschutzdosimeter; Allgemeine Regeln (Radiation Protection Dosimeters; General) Warnzeichen fur ionisierende Strahlung (Warning Symbol for Ionizing Radiation) Kerntechnik; Begriffe, Strahlenschutz (Nuclear Technology; Terms and Definitions, Radiation Protection) Umschlossene radioaktive Stoffe; Anforderungen und Klassifikation (Sealed radioactive sources; requirements and classification) Umschlossene radioaktive Stoffe; Anforderungen an radioaktive Stoffe in besonderer Form (Sealed radioactive sources; special form radioactive material, requirements) Umschlossene radioaktive Stoffe; Dichtheitspriifungen wahrend des Umgangs (Sealed radioactive sources; leakage test methods for recurrent inspections) Sicherheitskennzeichnung im Strahlenschutz (Radiation Warning Signs in Radiation Protection)
Iss
678
Iss
379
Pub Pub
55 68
Pub
65
Pub
66
Pub
75
Pub
71
Pub
12.72
Pub
7 76
App
7.80
Iss
73
Iss
74
Iss
75
Pub
12.76
Pub
5.66
Drf
279
Pub
2.77
Pub
4.79
Pub
4 77
Pub
8 78
67
5.1 No.
Issuing Body
Title
(Country)
(Remarks)
DIN 44420
DIN
DIN 44422
DIN
DIN 44423
DIN ■
GOST GOST GOST GOST GOST
12631 14105 14336 15484 16950
GOST GOST GOST GOST GOST
GOST 18298
GOST
GOST 19465
GOST
GOST 19868
. GOST
GOST 21785 IAEA50-SG-D9
GOST IAEA
IAEA 50-SG-S4
IAEA
IAEA 50-SG-S9 IAEA 50-SG-05
IAEA IAEA
ICRP Publ. 10
ICRP
ICRP Publ. 10a
ICRP
ICRP Publ. 11
ICRP
ICRP Publ. 12
ICRP
ICRP Publ. 14 ICRP Publ. 15
ICRP ICRP
ICRP Publ 21 ICRP Publ. 22
ICRP ICRP
ICRP Publ. 23
ICRP
ICRP Publ. 24 ICRP Publ. 26
ICRP ICRP
ICRP Publ. 28
ICRP
ICRP Publ. 29
ICRP
ICRP ICRP ICRU ICRU ICRU ICRU
Publ. 30 Publ. 31 Report No. Report No. Report No. Report No.
10b 10c 19 19s
ICRP ICRP ICRU ICRU ICRU ICRU
ICRU Report No. 20
ICRU
ICRU Report No. 21
ICRU
ICRU Report No. 22
ICRU
68
Begriffe aus der M eGtechnik fur ionisierende Strahlung (Definition of Terms, Used in Ionizing Radiation M easuring Practice) StrahlungsmeSsonden; HauptmalSe (Probe for Ionizing Radiation, M ain Dimensions) Probenschalchen fur radioaktive Stoffe (Planchets for Radioactive Samples) Qualitatsfaktor der ionisierenden Strahlen Strahlungsdetektoren; Klassifikation Radioisotopengerate; Aufbau der Symbole Ionisierende Strahlungen; Klassifikation Erzeugnisse der Strahlenschutztechnik; Terminologie, Klassifikation Strahlungsfestigkeit von Apparaten, Zubehorteilen und Werkstoffen Polymerer Schutzanstrich fur die Verbesserung der Strahlungsumstande Spektrometrische Linearverstarker fur Halbleiterdetektoren von ionisierenden Strahlungen Technologische Strahlenschutzausrustungen Design Aspects of Radiological Protection for Operational States of Nuclear Power Plants Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution Site Survey for Nuclear Power Plants Radiological Protection During Operation of Nuclear Power Plants Evaluation of Radiation Doses to Body Tissues from Internal Contamination due to Occupational Exposure The Assessment of Internal Contamination Resulting from Recurrent or Prolonged Uptakes A Review of the Radiosensitivity of the Tissues in Bone General Principles of M onitoring for Radiation Protection of Workers Radiosensitivity and Spatial Distribution of Dose Protection Against Ionizing Radiation from External Sources Supplement to Publication No. 15 Implications of Commission Recommendations that Doses be Kept as Low as Readily Achievable Reference M an: Anatomical, Physiological and Metabolic Characteristics Radiation Protection in Uranium and other M ines Recommendations of the International Commission on Radiological Protection The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers Radionuclide Release into the Environment: Assessment of Doses to M an Limits for Intakes of Radionuclides by Workers Biological Effects of Inhaled Radionuclides Physical Aspects of Irradiation Radioactivity Radiation Quantities and Units Dose Equivalent (Supplement to ICRU Report No. 19) Radiation Protection Instrumentation and Its Application Radiation Dosimetry: Electrons with Initial Energies Between 1 and 50 M eV Measurement of Low-Level Radioactivity
Status Pub
7.66
Pub
4.71
Pub
8.63
Pub Pub Pub Pub Pub
67 76 76 74 71
Pub
72
Pub
74
Pub
74
Pub Ust
76
Ust Ust Ust
Pub
67
Pub
69
Pub
71
Pub
77
Pub
78
Pub
79
Pub Pub Pub Pub Pub Pub
79 80 64 63 71 73
Pub
72
Pub
72
Pub
72
5.1 No.
Issuing Body (Country)
ICRU Report No. 25
ICRU
ICRU Report No. 28
ICRU
IEC 50(65)
IEC
IEC 50(3911
IEC
IEC 50(392)
IEC
IEC 181
IEC
IEC 181A IEC 181 B ISO 361 ISO/DP 5568 GSN-04
IEC IEC ISO ISO JEN
GSN-09
JEN
MSZKGST531 MSZ 62 NCRP Report No.3
MSZH MSZH NCRP
NCRP Report No 22
NCRP
NCRP NCRP NCRP NCRP
No.38 No.39 No.47 No.52
NCRP NCRP NCRP NCRP
NCRP Report No.55
NCRP
NCRP Report No.57
NCRP
NCRP Report No.59 NCRP Report No.60
NCRP NCRP
NEN 1848
NNI
Report Report Report Report
OECD
A 6601 SS 016182
ONORM PAEC PAEC SIS
TS 1507 R G. 1 24
TSE USNRC
Title
Status
(Remarks)
Conceptual Basis for the Determination of Dose Equivalent Basic Aspects of High Energy Particle Interactions and Radiation Dosimetry International Electrotechnical Vocabulary: Radiology and Radiological Physics International Electrotechnical Vocabulary: Detection and Measurement of Ionizing Radiation by Electric Means International Electrotechnical Vocabulary: Nuclear Instrumentation - Supplement to Chapter 391 Index of Electrical Measuring Apparatus Used in Connection with Ionizing Radiation First Supplement to IEC 181 Second Supplement to IEC 181 Basic ionizing radiation symbol Proposal for a Fissile Material Symbol Guia Para la Obtencion del Titulo de Jefe del Servicio de Proteccion contra las Radiaciones (Requirements for the Radiation Protection Manager) Programa de Vigilancia Radiologica Ambiental para Centrales Nucleares de Potencia. (Environmental Monitoring Programme) Radiation Symbols: Form and Size Protection against Radioisotope Radiation Control and Removal of Radioactive Contamination in Laboratories Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupacional Exposures Protection Against Neutron Radiation Basic Radiation Protection Criteria Tritium Measurement Techniques Cesium-137 from the Environment to Man: Metabolism and Dose Protection of the Thyroid Gland in the Event of Release of Radioiodine Instrumentation and Monitoring Methods for Radiation Protection Operational Radiation Safety Program Physical, Chemical, and Biological Properties of Radiocerium Relevant to Radiation Protection • Guidelines Buitenmiddellijnen Van Cilindrische Stralings Meetsondes (External Diameters of Cylindrical Radiation Probes) Bekanntmachung der geanderten Fassung der Grundnormen fOr den Strahlenschutz der Organisation fur wirtschaftliche Zusammenarbeit und Entwicklung (OECD) Atomschutz, Begriffe Radiation Protection Regulation Nuclear Safety and Radiation Protection Ordinance Quantities and Units. Nuclear Reactions and Ionizing Radiation Quantities and Units of Atomic and Nuclear Physics Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Gas Storage Tank Failure (Safety Guide 24)
Pub
76
Pub
78
Pub
64
Pub
75
Pub
76
Pub
64
Pub Pub Pub Drf Iss
65 65 75 75 4.77
Iss
11 78
Pub Pub Pub
77 78 51
Pub
59
Pub Pub Pub Pub
71 71 76 77
Pub
77
Pub
78
App
4.70
Iss Iss Iss Pub
8.67 70 72 779
Iss
3.72
69
5.1 Issuing Body
No.
(Country)
R.G. 1.25
USNRC
R.G. 1.70.3
USNRC
R.G. 1.98
USNRC
R.G. 3 33
USNRC
R.G. 3.34
USNRC
R.G. 3.35
USNRC
R.G. R.G. R.G. R.G.
8.1 82 87 8.8
USNRC USNRC USNRC USNRC
R.G. 8.9
USNRC
R.G. 8.10
USNRC
R.G. 8.11 R.G. 8.13 R.G. 8.20
USNRC USNRC USNRC
Task No. OH 507-4
USNRC
10 CFR 20 VdTUVWei 26
USNRC VdTUV
MB P.3286
(BEL)
•
(CZE)
BGBI. I, S. 721 /BGBI. I, S. 1193 /BGBI. I, S. 373 BGBI. I, S. 2905 /BGBI. I, S. 184, 269 /BGBI. I. S. 1509
(DEU)
70
(DEU)
Title (Remarks) Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25; Under Revision) Additional Information: Radiation Protection (See also R.G. 1.70) Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant Radiation Symbol Administrative Practices in Radiation Monitoring Occupational Radiation Exposure Records Systems Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as is Reasonably Achievable (Under Revision; see also Task No. OH 507-4) Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable (Nuclear Power Reactors) Applications of Bioassay for Uranium Instruction Concerning Prenatal Radiation Exposure Applications of Bioassay for 1-125 and 1-131 (Under Revision) Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable (Proposed Revision to R.G. 8.8) Standards for Protection against Radiation Rahmenpriifvorschrift fiir die Eignungspriifung von MelSeinrichtungen zur Strahlungsiiberwachung Loi relative a la protection de la population contre les dangers resultant des radiation ionisantes (See "Moniteur Beige "I Notification of the Ministries of Chemical Industry and Health Concerning the Control of Radioactive Substances Bundes-lmmissionsschutzgesetz - BlmSchG - vom 15. Marz 1974, zuletzt geandert durch Artikel 12 des Gesetzes vom 28. Marz 1980 Verordnung uber den Schutz vor Schaden durch ionisierende Strahlen (Strahlenschutzverordnung StrlSchV) vom 13. Oktober 1976, zuletzt geandert durch die Verordnung uber die Beforderung gefahrlicher Guter auf der StralSe (GefahrgutVStr) vom 23. August 1979 (BGBI. I, S 1509)
Status Iss
3.72
Iss
11.74
Iss
3.76
Iss
4.77
Iss
7.79
Iss
7.79
Iss Iss Iss Iss
2.73 2.73 5.73 678
Iss
9.73
Iss
5.77
Iss Iss Iss
6.74 11.75 4.78
Iss
3.79
Iss
9.79
Iss
4.58
Iss
5.56
Iss 3 74 Amm 12.76 Amm 3.80 Iss 10.76 Amm 12.77 Amm 8.79
5.1 No.
Issuing Body (Country}
Decree No. 185
(ITA)
I.O.(1963)p.227
I LUX)
l.0.(1967)p.142
(LUX)
SSI FS 1977:2
(SWE)
Decree No. 006-66 Leg. Series 1970 No. 32 OGSFRY 12/65
(VNM) (YUG) (YUG)
Status
Title
(Remarks)
Decree No. 185 of the President of Republic on the Safety of Installations and the Health Protection of Workers and the Population Against the Hazards of Ionizing Radiations Resulting from Peaceful Use of Nuclear Energy (See "Gazzetta Ufficiale No. 95") Loi du 25 mars 1963 concernant la protection de la population contre les dangers resultant des radiations ionisantes (Journal Officiel of 10 April 1963, p227) Reglement grand-ducal du 8 fevrier 1967 portant sur I'execution de la loi du 25 mars 1963 concernant la protection de la population contre les dangers resultant des radiation ionisantes (Journal Officiel of 8 March 1967, p. 142/ Regulations Issued by the National Institute of Radiation Protection for the Limitation ot the Releases of Radioactive Substances from Nuclear Power Stations Protection Against Ionizing Radiation Public Health Act (Art 3, 31, 51, 52 and 55: Protection Against Ionizing Radiation) Basic Law on Protection Against Radiation
Iss
264
Iss
63
Iss
67
Iss
77
Iss Iss
366 770
Iss
65
71
5.2 No. 5
Issuing Body (Country)
Status
Radiation Protection
5.2 Radiological S h i e l d i n g ACI 349 ACI ANS-6.3 /ANSI N18.9 ANS-6.4
ANS
ANS-11.13 /ANSI N101.6 ASTM C 637 /ANSI N648
ANS
BS 3909 BS 4094
BSI BSI
BS4513 Chapitre I
BSI CEA
Chapitre II
CEA
Chapitre III
CEA
Chapitre IV
CEA
Chapitre V
CEA
Chapitre VI
CEA
M 62-200
CEA
M 62-202
CEA
NF M 60-001
CEA
NF M 62-002
CEA
NF M 62-003
CEA
NF M 62-004
CEA
NF M 62-005
CEA
NF M 62-006
CEA
*
CEA
ANS
ASTM
DIN 25407 Teil 1
DIN
DIN 25407 Teil 1 Bbl
DIN
72
Title (Remarks)
Code Requirements for Nuclear Safety Related Concrete Structures Program for Testing Biological Shielding in Nuclear Reactor Plants Guidelines on the Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants Concrete Radiation Shields Specification for Aggregats for Radiation-Shielding Concrete (Reapproved) Ingot Lead for Radiation Shielding Recommendation for Data on Shielding from Ionizing Radiation Lead Bricks for Radiation Shielding Elements constitutifs d'enceintes blindees (See "Catalogue de materiel normalise") Elements constitutifs d'enceintes etanches (See "Catalogue de materiel normalise") Manipulation (See "Catalogue de materiel normalise ") Enceintes de confinement (See "Catalogue de materiel normalise") Enceintes blindees et moyens de vision (See "Catalogue de materiel normalise ") Chateaux de plomb et elements de transfert proteges (See "Catalogue de materiel normalise") Enceintes de confinement - Classification des enceintes selon leur etancheite Enceintes de confinement - Caracteristiques des reseaux de ventilation Elements constitutifs d'enceintes blindees - briques a chevrons en plomb antimonie (Shielding Materials: Lead/Antimonie Bricks) Elements constitutifs d'enceintes blindees Encadrements en plomb antimonie (Shielding Materials: Lead/Antimony Frames) Elements constitutifs d'enceintes blindees Bouchons en plomb antimonie (Shielding Materials: Lead/Antimony Plugs) Elements constitutifs d'enceintes blindees - Hublots en verre au plomb (Shielding Materials: Lead/Glass Windows) Elements constitutifs d'enceintes blindees Bouchons a rotule en plomb antimonie (Shielding Materials: Lead/Antimony Plugs with Swirel Joints) Elements constitutifs d'enceintes blindees - Poteaux a chevrons en plomb antimonie (Shielding Materials: Lead/Antimony Suare Posts) Catalogue de materiel normalise "Protection-Manipulation-Detection-Surete" Abschirmwande gegen ionisierende Strahlung; Bleibausteine (Walls Shielding Against Ionizing Radiation; Lead Bricks) Abschirmwande gegen ionisierende Strahlung; Bleibausteine, Hinweise fur die Verwendung (Walls Shielding Against Ionizing Radiation; Lead Bricks; Recomendations for Use)
Pub
76
App
72
App
77
App
72
Pub App
73 2.79
Pub Pub
65 66
Pub Iss
69
Iss Iss Iss Ust Ust Iss
74
Iss
78
Pub
2.70
Pub
6.71
Pub
6.71
Pub
12.72
Pub
6.71
Pub
6.71
Pub
2.74
Pub
2.74
5.2 No.
Issuing Body (Country)
DIN 25407 Teil 2
DIN
DIN 25407 Teil 2 Bbl
DIN
DIN 25413
DIN
DIN 25427 Teil 1
DIN
DIN 25427 Teil 2
DIN
JIS Z4415 MSZ KGST237
JIS MSZH
MSZ 14348
MSZH
AESS(R)44/70000 AESS(R)10338 AESS(R)11753
UKAEA UKAEA UKAEA
AESS(R)11756 R.G. 1.69 R.G. 1 99
UKAEA USNRC USNRC
R.G. 2.1
USNRC
R.G. 3.9 R.G. 3.27
USNRC USNRC
Task No. EM 805-5
USNRC
Title (Remarks) Abschirmwande gegen ionisierende Strahlung; Spezielle Bauelemente (Walls Shielding Against Ionizing Radiation; Special Construction Elements) Abschirmwande gegen ionisierende Strahlung; Spezielle Bauelemente, Hinweise fiir die Verwendung (Walls Shielding Against Ionizing Radiation; Special Construction Elements; Recommendations for Use) Klassifikation von Betonen nach Elementanteilen bei Verwendung zur Neutronenabschirmung (Classification of Concretes for Neutron Shielding with Respect to Atomic Composition) Auslegung von zweifach geknickten gasgefiillten Kanalen in Abschirmwanden aus Beton gegen Gammastrahlung; Begriffe und Voraussetzungen (Design of Gas-Filled Double-Blend Ducts in Concrete-Shields against Gamma Radiation, Definitions and Conditions) Auslegung von zweifach geknickten gasgefiillten Kanalen in Abschirmwanden aus Beton gegen Gammastrahlung; Bemessung des Kanals und der Eisenverstarkung bei Punktquellenstrahlung und kollimierter Strahlung (Design of Gas-Filled Double-Bend Ducts in Concrete-Shields against Gamma Radiation; Proportionment of the Duct and the Embedded Iron-Layers for Point Source Radiation and Collimated Radiation) Beta Ray Absorber Technical Requirements on Lead Ball and Joint and Plug for Radiation Shielding Lead-Brick for Radiation Shielding. Technical Requirements Shielding Glass Concrete Shielding Bricks Concrete for Shielding (Ordinary Portland Cement and Normal Aggregate) Concrete for Shielding (Barytes) Concrete Radiation Shields for Nuclear Power Plants Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials Shield Test Program for Evaluation of Installed Biological Shielding in Research and Training Reactors Concrete Radiation Shields Non-destructive Examination of Welds in the Liners of Concrete Barries in Fuel Reprocessing Plants Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants (Proposed R.G.)
Status Pub
12.74
Pub
12.74
Pub
3.76
Pub
10.77
Pub
10.77
Pub Pub
74 75
Pub
77
Iss Iss Iss
77 64 61
Iss Iss Iss
60 12.73 4.77
Iss
5.73
Iss Iss
6.73 5.77
Iss
279
73
5.3 Issuing Body (Country}
No. 5
Status
Title (Remarks)
Radiation Protection
Personne I M o n i t o r i n g and Protection Devices ANHMRC Revised Radiation Protection Standards for * Individuals Exposed to Ionising Radiation « ANHMRC Dose Equivalents, Maximum Permissible Doses and Dose Limits of Ionising Radiation * ANHMRC Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores Facilities and Medical Care for on Site Nuclear ANS-3.7.1 ANS Power Plant Radiological Emergencies Protection from Radiation and Other Hazards in ANSI N7.1a ANSI Uranium Milling and Concentrating /ANSI N508 Performance Specifications for Direct Reading and ANSI ANSI N13.5 Indirect Reading Pocket Dosimeters for X- and Gamma Radiation Film Badge Performance Criteria ANSI N13.7 ANSI Radiation Protection in Uranium Mines Operation ANSI N13.8 ANSI Criteria for Testing Personnel Dosimetry Performance ANSI N13.11 ANSI Performance Specifications for Personnel Neutron ANSI N319 ANSI Dosimeters 5.3
ANSI N322
ANSI
ASTM C 852 ZH1-204
ASTM BG
ZH1-283
BG
VBG 1 BMI RS II-5
BG BMI
GMBI. 1978 S. 418
BMI
BS 3385
BSI
BS 3654 Chapitre VII
BSI CEA
Chapitre VIII
CEA
Chapitre IX
CEA
M 60-511 NF M 60-501
CEA CEA
•
CEA
SI 1827
DERRT
DIN 6816
DIN
DIN 6818 Teil 1
DIN
74
Inspection and Test Specifications for Direct and Indirect Reading Pocket Dosimeters Design Criteria for Plutonium Gloveboxes Richtlinien zum Schutze gegen ionisierende Strahlen bei Verwendung und Lagerung offener Radioaktiver Stoffe Merkblatt fur das Arbeiten mit offenen Radioaktiven Stoffen Allgemeine Vorschriften Grundsatze fur die arztliche Clberwachung von beruflich strahlenexponierten Personen Richtlinie fur den Stahlenschutz des Personals bei der Durchfuhrung von Instandhaltungsarbeiten in Kernkraftwerken mit Leichtwasserreaktor: Die wahrend der Planung der Anlage zu treffende Vorsorge, vom 10.7.1978 Direct Reading Pocket Type Electroscope Exposure Meters Film Badges for Personnel Radiation Monitoring Vetements de protection (See "Catalogue de materiel normalise") Protections contre I'incendie - Protections diverses (See "Catalogue de materiel normalise") Detection et mesure des rayonnements (See "Catalogue de materiel normalise ") Appareils de mesure dosimetriques Appareils de mesure dosimetriques Styloexposimetres a lecture directe (sans chargeur incorpore) (Direct Reading Pocket Dosimeters without Charging Unit) Catalogue de materiel normalise "Protection-Manipulation-Detection-Surete" The Radioactive Substances (Road Transport Workers) Regulations Filmdosimeterie nach dem filteranalytischen Verfahren zur Strahlenschutzuberwachung (Filteranalytic Method of Film Dosimetry for Personnel Monitoring) Strahlenschutzdosimeter; Allgemeine Regeln (Radiation Protection Dosimeters; General)
Iss
67
Iss
69
Iss
75
Drf
10.78
Pub
69
Pub
72
Pub Pub Pub Pub
72 73 79 76
Pub
75
Pub Ust
77
Ust Pub Iss
4.77 78
Iss
7.78
Pub
73
Pub Iss
63
Ust Ust Iss
2.69
Iss
70
Pub
3.64
Pub
12.76
5.3 No.
Issuing Body (Country)
DIN 6818 Teil 2
DIN
DIN 6818 Teil 3
DIN
DIN 6818 Teil 4
DIN
DIN 6818 Teil 5
DIN
DIN 25400
DIN
DIN 25406 Teil 1
DIN
DIN 25430
DIN
GOST 14337 GOST 14642
GOST GOST
GOST GOST GOST GOST
GOST GOST GOST GOST
18177 18325 20441 20858
GOST 21785 ICRU Report No. 25
GOST ICRU
IEC405
IEC
IEC504
IEC
Agreement No. 115
ILO
ISO 1757 ISO 1758
ISO ISO
ISO 1759
ISO
ISO/DP 5568 ISO/R 1757 JIS Z4308 JIS Z4311 JIS Z4323 JIS Z4415 JIS Z4808 JIS Z4809 JISZ4810
ISO ISO JIS JIS JIS JIS JIS JIS JIS
Title
Status
(Remarks)
Strahlenschutzdosimeter; Direkt ablesbare lonisationskammer-Stabdosimeter fur Gamma- und Rontgenstrahlen (Radiation Protection Dosimeters; Direct Reading Ionization Chamber Pocket Dosimeters for Gamma and X-rays) Strahlenschutzdosimeter; Nicht direkt ablesbare lonisationskammer-Stabdosimeter fur Gamma- und Rontgenstrahlen (Radiation Protection Dosimeters; Not-Direct Reading Ionization Chamber Pocket Dosimeters for Gamma and X-rays Strahlenschutzdosimeter; Tragbare lonisationskammerdosimeter fiir Gamma- und Rontgenstrahlen (Radiation Protection Dosimeters; Portable Ion Chamber Dosimeters for Gamma and X-radiation) Strahlenschutzdosimeter; Zahlrohr-Dosisleistungsmesser fur Gamma- und Rontgenstrahlen (Radiation Protection Dosimeters; Exposure Ratemeters with Gas Proportional Counters and Geiger-Miiller-Counters for Gamma- and X-rays) Warnzeichen fur ionisierende Strahlung (Warning Symbol for Ionizing Radiation) Schleusen am Reaktorsicherheitsbehalter von Kernkraftwerken; Personenschleusen, Sicherheitstechnische Anforderungen (Locks at Reactor Safety Containments of Nuclear Power Plants; Personal Locks, Safety Requirements) (Identical with KTA 3402) Sicherheitskennzeichnung im Strahlenschutz (Radiation Warning Signs in Radiation Protection) Mefkjerate fur ionisierende Strahlen Funktionsbaugruppen; Blocke und Vorrichtungen von Geraten zur Messung ionisierender Strahlen Halbleiterdetektoren ionisierender Strahlungen Erzeugnisse der Schutztechnik; Spezialmbbel Dosimetrische Gerate: Kennwerte Spektrometrische Szintillationseinheiten fiir den Nachweis von Rontgen- und Gammastrahlen Technologische Strahlenschutzausriistungen Conceptual Basis for the Determination of Dose Equivalent Nuclear Instruments: Constructional Requirements to Afford Personal Protection Against Ionizing Radiation Hand and/or Foot Contamination Monitors and Warning Assemblies Ubereinkommen Nr. 115 der I n t e r n a t i o n a l Arbeitsorganisation vom 22. Juni 1960 iiber den Schutz der Arbeitnehmer vor ionisierenden Strahlen Personal Photographie Dosimeters Direct-Reading Electroscope-Type Pocket Exposure Meters Indirect-Reading Capacitor-Type Pocket Exposure Meters and Accessory Electrometers Proposal for a Fissile Material Symbol Personal Photographic Dosimeters Pocket Chambers and Dosimeters Personal Exposure Alarm Meters X and Gamma Rays Film Badge Cases for X and Gamma Rays Beta Ray Absorber Glove Box for Handling of Radioactive Substance Protective Clothing for Radioactive Contamination Rubber Gloves for Handling of Unsealed Radioisotopes
Pub
3.79
Pub
3.79
Pub
11.79
Pub
379
Pub
5.66
Pub
4.77
Pub
8.78
Pub Pub
69 69
Pub Pub Pub Pub
72 73 75 75
Pub Pub
76 76
Pub
72
Pub
75
App
6.60
Pub Pub
80 76
Pub
76
Drf Pub Pub Pub Pub Pub Pub Pub Pub
75 71 75 78 74 74 75 75 61
75
5.3 No.
Issuing Body (Country)
JIS Z4811
JIS
KTA 3402
KTA
MSZ 14333 NCRP Report No.22
MSZH NCRP
NCRP Report No.38 NCRP Report No.46 NCRP Report No.52
NCRP NCRP NCRP
NCRP Report No.53
NCRP
NCRP Report No.55
NCRP
NCRP Report No 59 NEN 2384
NCRP NNI
NEN 2386
NNI
NEN 2387
NNI
NEN 2388
NNI
S5201 LBG/4
ONORM SAAEB
AESS AESS AESS AESS AESS AESS AESS
35/34950 35/38940 35/39390 35/55030 35/55350 35/55555 35/55686
UKAEA UKAEA UKAEA UKAEA UKAEA UKAEA UKAEA
AESS 35/55700 R.G. 1.95
UKAEA USNRC
R.G. 1.109
USNRC
R.G. 1.134
USNRC
R.G. R.G. R.G. R.G.
USNRC USNRC USNRC USNRC
76
8.3 8.5 8.7 8.8
Title
Status
(Remarks)
Synthetic Rubber Boots for Handling of Unsealed Radioisotopes Schleusen am Reaktorsicherheitsbehalter von Kernkraftwerken - Personenschleusen (Locks in the Containment of Nuclear Power Plants, Personnel-Locks) (Available also in English; Identical with DIN 25406 Teil I) Testing of Personnel Gamma Dosimeters at Site Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupacional Exposures Protection Against Neutron Radiation Alpha-Emitting Particles in Lungs Cesium-137 from the Environment to Man: Metabolism and Dose Review of NCRP Radiation Dose Limit for Embryo and Fetus in Occupationally Exposed Women Protection of the Thyroid Gland in the Event of Release of Radioiodine Operational Radiation Safety Program Richtlijnen Voor Draagbare Monitors (Rules for Portable Monitors) Richtlijnen Voor Zakelektroscopen Voor Controle Van Persoonlijke (Rules for Pocket Electroscopes for Personal Monitoring) Richtlijnen Voor Condensatorvaten En Bijbehoerende Elektrometers Voor Controle Van Persoonlijke Bestralingsdoses (Rules for Condensor Type Ionization Chambers and Accessory Electrometers for Personal Monitoring) Richtlijnen Voor Filmdosismeters Voor Controle Van Persoonlijke Bestralingsdoses (Rules for Film Badges Personal Monitoring) StrahlenpaS - StrahlenpaS gemaS ONORM S 5201 Licensing of Nuclear Instalations; A Guide to the Requirements for the Medical Control of Nuclear Licensed Site Personnel Jackets, PVC, Unsupported Suits, Combination, PVC Unsupported Trousers, PVC, Unsupported Blouses, Air Line, Hooded, PVC, Unsupported Hoods, Air Line, PVC, Unsupported Oversuits and Overhoods, PVC, Unsupported Top Half, for Two Piece Pressurised Suit, PVC, Unsupported Suits, Pressurised, Unsupported PVC Protection of Nuclear Power Plant Control Room Operators Against an Accidential Chlorine Release Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I Medical Evaluation of Nuclear Power Plants Personnel Requiring Operator Licenses Film Badge Performance Criteria Immediate Evacuation Signal Occupational Radiation Exposure Records Systems Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as is Reasonably Achievable (Under Revision; see also Task No. OH 507-4)
Pub
61
Pub
11.76
Pub Pub
78 59
Pub Pub Pub
71 75 77
Pub
77
Pub
77
Iss Iss
9.76 12.77
Iss Iss Iss Iss Iss Iss Iss
79 77 77 77 77 77 77
Iss Iss
79 1.77
Iss
10.77
Iss
3.79
Iss Iss Iss Iss
2.73 2.73 5.73 6.78
5.3 No.
Issuing Body (Country)
R.G. 8 10
USNRC
R.G. 8.14 R.G. 8.15 R.G 8.19
USNRC USNRC USNRC
R.G. 8.21
USNRC
R G 8.22
USNRC
R.G. 8.24
USNRC
Task No. OH 507-4
USNRC
Task No. OH 717-4
USNRC
Task No. OH 902-1
USNRC
•
(CHN)
BGBI. 1, S. 1885 /BGBI. 1, S. 965
(DEU)
Dz.U.(1968)20
(POL}
Resolution 965
(ROM)
Resolution 966
(ROM)
Resolution 1149
(ROM)
Decree No. 43-SL/GD
(VNM)
Order No. 1065-ND/LD
(VNM)
Leg Series 1952 No. 11
(YUG)
Title (Remarks) Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable (Nuclear Power Reactors) Personnel Neutron Dosimeters Acceptable Programs for Respiratory Protection Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants-Design Stage Man-Rem Estimates (Issued for Comments) Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and Manufacturing Plants (Under Revision) Bioassay at Uranium Mills (Under Revision) Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication (Issued for Comments) Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable (Proposed Revision to R.G. 8.8) Radiation Protection Training for Light-Water-Cooled Nuclear Power Plant Personnel (Proposed R. G.) Instruction Concerning Risk from Occupational Radiation Exposure (Proposed R.G.) Provisional Decree Concerning Health Protection in Radioactive Work Gesetz iiber Betriebsarzte, Sicherheitsingenieure und andere Fachkrafte fur Arbeitssicherheit vom 12. Dezember 1973, zuletzt geandert durch Gesetz vom 12. April 1976 Decree of Council of Ministers Concerning Occupational Safety and Hygiene in the Application of Ionizing Radiation Organizing the Labour Protection and Hygienic and Antiepidemic Measures in the Romanian Peoples Republic - Labour Protection in Case of Handling of Ionizing Rays Approval of the Regulations Concerning the Registration and Supervision of Labour-Accidents and Occupational Diseases as Well as Securing and Utilizing the Fund for Labour Protection- Annex 1, No. 8- Diseases Caused by Ionizing Radiations etc. Annex 2, No.15- Labour Protection in Case of Handling of Radioactive Substances Criteria for the Determination of Working Places With Special Conditions for Which a Supplementary Leave is Granted - Art 2 No. 1a Workmen Who are Exposed to the Effects of Radioactive Rays Regime of Risk Compensation, Sick Leave, Leave of Long Duration, Disability Pension and Compensation for Accidental Death for the Benefit of Staff Steadily Working in Places Using Sources of Ionizing Radiation Compensation for Occupational Diseases etc. -Diseases Caused by Ionizing Radiation Decree Prohibitting the Employment of Women and Young Persons on Certain Type of Work - Work with Radioactive Radiation and X-Rays
Status Iss
5.77
Iss Iss Iss
8.77 10.76 6.79
Iss
578
Iss
778
Iss
11.78
Iss
3.79
Iss
8.79
Iss
580
Iss
1.60
Iss 1273 Amm 4.76 Iss
6.68
App
12.64
App
12.64
App
5.68
Iss
4.71
Iss
6.66
Iss
352
77
5.3 No.
Issuing Body (Country!
Leg. Series 1965 No. 17
(YUG)
Leg. Series 1965 No. 31/1199
(YUG)
78
Title
Status
(Remarks!
Basic Act Concerning Labour Regulations (Art 37, Subarticle 2 and Art 63, Subarticle 3: Work Subject to Effects of Ionizing Radiation) Regulation Concerning the Permissible Doses of Ionizing Radiation to Which Persons Working With Sources of Such Radiation May be Exposed
Iss
4.65
Iss
6.65
5.4 No. 5
Issuing Body (Country}
Title
Status
(Remarks)
Radiation Protection
5.4 S t a t i o n a r y Radiation M o n i t o r i n g S y s t e m s ANS-6.6.1 ANS Calculation and Measurement of Direct and Scattered Gamma Radiation from Nuclear Power Plants ANSI N13.3 ANSI Dosimetry for Criticality Accidents ANSI N13.4 Specification of Portable X- and Gamma Radiation ANSI Survey Instruments ANSI N13.10 ANSI Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents ANSI N42.5 ANSI Base for GM Counter Tubes ANSI N42.6
ANSI
ANSI N323
ANSI
ANSI N343
ANSI
ASTM E 170 ASTM E 482
ASTM ASTM
ASTM E 522
ASTM
ASTM E 526
ASTM
BS 3775 BS 3890
BSI BSI
MCH/MENT 5
CEA
NF M 60-552
CEA
DIN 25458
DIN
DIN 44421
DIN
DIN 44424
DIN
DIN 44426 Teil 1
DIN
DIN 44426 Teil 2
DIN
DIN 44427
DIN
Interrelationship of Quartz-Fiber Electrometer Type Dosimeters and Companion Dosimeter Charges Radiation Protection Instrumentation Test and Calibration Internal Dosimetry Techniques for Fission and Activation Products Standard definitions of terms relating to dosimetry Recommended Practice for Neutron Dosimetry for Reactor Pressure Vessel Surveillance Method of Calibration of Germanium Detectors for Measurement of Gamma-Ray Emission Rates of Radionuclides Recommended Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results Counting Trays (Planchets) for Radioactive Assay General Recommendations for the Testing, Calibration and Processing of Radiation Monitoring Films Caracteristiques et methodes d'essais des detecteurs de rayonnement Jauges a radioelements - Appareils destines a etre installes a poste fixe (Radioisotope-Gauges: Devices for Permanent Installation) Ortsfestes System zur Uberwachung von Ortsdosisleistungen innerhalb von Kernkraftwerken; Sicherheitstechnische Anforderungen (Stationary System for the Surveillance of Local Dose-Rates within Nuclear Power Stations; Safety Requirements! (Identical with KTA 1501) Zahlrohrsockel und Zahlrohrfassung bis 3 kV; HauptmaSe (Counting Tube Base and Counting Tube Holder up to 3 kV; Principal Dimensions! Steckverbindung fur Zahlrohre; AnschlulSmaUe, Anforderungen (Socket for Counting Tubes; Dimensions, Requirements) Steuersystem fur StrahlungsmelSgerate und ihre Zusatzgerate; Grundlagen (Control-System for Electrical Measuring Instruments Used in Connection with Ionizing Radiation! Steuersystem fur StrahlungsmeUgerate und ihre Zusatzgerate; Nachrichtengabe durch mechanische Kontakte (Control-System for Electrical Measuring Instruments Used in Connection with Ionizing Radiation) Prufstrahler zur Funktionskontrolle von Dosisleistungsmessern (Test Source for Checking Dose Rate Meters)
Pub
79
Pub Pub Rev Pub
69 71 77 74
Pub Rev Pub
71 77 78
Pub
77
Pub
78
Pub Pub
76 76
Pub
78
Pub
77
Pub Pub
64 65
Pub
76
Pub
8.75
Pub
8.78
Pub
7.78
Pub
4.66
Pub
8 68
Pub
8.68
Pub
8 72
79
5.4 No.
Issuing Body (Country)
DIN 44801
DIN
DIN 44804
DIN
GOST 12736 GOST 12736 GOST 12915
GOST GOST GOST
GOST GOST GOST GOST
13021 14105 14337 14639
GOST GOST GOST GOST
GOST 14641
GOST
GOST 14642
GOST
GOST 15546 GOST 15944 GOST 16314
GOST GOST GOST
GOST 16551 GOST 16839
GOST GOST
GOST 17038
GOST
GOST 17064
GOST
GOST 17134 GOST 17135
GOST GOST
GOST 17137
GOST
GOST 17226
GOST
GOST 17355-71 GOST 17414
GOST GOST
GOST 17415
GOST
GOST 17416
GOST
GOST 17615
GOST
GOST 17619
GOST
GOST 18166
GOST
GOST 18171
GOST
GOST 18177 GOST 18229
GOST GOST
GOST 18230
GOST
GOST 18398
GOST
80
Title
Status
(Remarks)
Alpha-, Beta- und Alpha-Beta-KontaminationsmeSgerate und -monitoren (Alpha, Beta and Alpha-Beta Contamination Meters and Monitors) Messen, Steuern, Regeln; KontaminationsmeBgerate und -monitoren fur radioaktive Aerosole (Measurement and Control; Radioactive Aerosol Contamination Meters and Monitors) Vereinheitlichte Szintillation-Plastdetektoren Detektoreinheiten von Stilben-Monokristallen Detektoreinheiten fur ionisierende Strahlen; Zylindrische Detektoreinheiten Gammaresonanz-Kassiteritanalysatoren Strahlungsdetektoren; Klassifikation MeSgerate fur ionisierende Strahlen Szintillationsdetektoren ionisierender Strahlungen auf der Grundlage von Anthrazen-Monokristallen Detektoreinheiten von Thallium-aktivierten Natriumjodid-Monokristallen Funktionsbaugruppen; Blocke und Vorrichtungen von Geraten zur Messung ionisierender Strahlen Dosimetrische Gerate Detektoren fur ionisierende Strahlen; Klassifikation Detektoren fur ionisierende Strahlen; Gasentladungszahlrohre Gamma- und Rontgenstrahlen-Spektrometer Baugruppen zum Nachweis szintillierender lonenstrahlen Szintillierende Detektoren fur ionisierende Strahlen; Messung der Szintillationscharakteristik Hauptfunktionsgruppen, Gerate und Hilfsmechanismen fur Gamma-Apparate Relaisartige Radioisotopenanlagen Halbleiterdetektoren; Messung ionisierender Strahlungen Strahlungskontrollsysteme; Steuerung und Schutz bei Kernreaktoren Exposimeter fur Gamma- und Rontgenstrahlen mit einer Quantenenergie von 8-480 f j Dosimetrische und radiometrische Instrumente Gerate zum Nachweis ionisierender Strahlungen; Koronazahler Gerate zum Nachweis ionisierender Strahlungen; Elektrische Geiger-Muller-Zahler Gerate zum Nachweis ionisierender Strahlungen; Geiger-Muller-lmpulszahler Gerate zum Nachweis ionisierender Strahlungen; Halbleiter Gerate zum Nachweis ionisierender Strahlungen; Halbleiter Gerate zum Nachweis ionisierender Strahlungen; Ionisierende Blocke Halbleiterdetektoren fur ionisierende Strahlungen; Klassifikationsmerkmale Halbleiterdetektoren ionisierender Strahlungen Ladungsempfindliche spektrometrische Vorverstarker zu Halbleiterdetektoren ionisierender Strahlungen Speisequellen spektrometrischer Halbleiterdetektoren fur ionisierende Strahlen Gerate zum Nachweis ionisierender Strahlungen; Germaniumdetektoren
Pub
8.78
Pub
8.78
Pub Pub Pub
67 74 67
Pub Pub Pub Pub
71 76 69 74
Pub
74
Pub
69
Pub Pub Pub
73 70 70
Pub Pub
71 71
Pub
71
Pub
71
Pub Pub
71 71
Pub
71
Pub
71
Pub Pub
71 71
Pub
72
Pub
72
Pub
72
Pub
72
Pub
72
Pub
72
Pub Pub
72 72
Pub
72
Pub
73
5.4 No.
Issuing Body (Country)
GOST 18695
GOST
GOST 19154
GOST
GOST 19155
GOST
GOST 19189
GOST
GOST 19868
GOST
GOST 20441 GOST 20858
GOST GOST
GOST 21635
GOST
GOST 21636
GOST
GOST 21637
GOST
GOST 21766
GOST
GOST 22462 ICRU Report No. 20
GOST ICRU
ICRU Report No. 21
ICRU
ICRU Report No. 22 ICRU Report No 28
ICRU ICRU
IEC 248-2
IEC
IEC 256
IEC
IEC 325
IEC
IEC 395
IEC
IEC 412 IEC 421
IEC IEC
IEC 460
IEC
IEC 463
IEC
IEC 504
IEC
IEC 515
IEC
Title
Status
(Remarks)
Spektrometrische Einrichtungen zur Messung ionisierender Strahlungen Elektrische Eingangs- und Ausgangssignale von Geraten zur Messung ionisierender Strahlungen, ihre funktionellen Einheiten und Baugruppen Elektrische Speisequellen und -kreise fur Gerate zur Messung ionisierender Strahlungen, ihre Funktionseinheiten und Baugruppen Gasionisierungsdetektoren fur ionisierende Strahlungen Spektrometrische Linearverstarker fur Halbleiterdetektoren von ionisierenden Strahlungen Dosimetrische Gerate: Kennwerte Spektrometrische Szintillationseinheiten fur den Nachweis von Rontgen- und Gammastrahlen Detektoren ionisierender Strahlungen; Neutronenstrom- und Neutronenimpulsgasionisierungskammern Detektoren ionisierender Strahlungen; Neutronenstrom- und Neutronenimpulsgasionisierungskammern; Messung der Neutronenempfindlichkeit Detektoren ionisierender Strahlungen; Neutronenstrom- und Neutronenimpulsgasionisierungskammern; Messung der Gammastrahlenempfindlichkeit Gerate fur die Strahlenschutzkontrolle in Kernkraftwerken Rontgenradiometrische Analysatoren Radiation Protection Instrumentation and Its Application Radiation Dosimetry: Electrons with Initial Energies Between 1 and 50 MeV Measurement of Low-Level Radioactivity Basic Aspects of High Energy Particle Interactions and Radiation Dosimetry Dimensions of Planchets Used in Nuclear Instrumentation for Radioactive Assay; Part 2: Flat and Dish-Type Planchets External Diameters of Cylindrical Radiation Probes Containing Geiger-Muller or Proportional Counter Tubes or Scintillation Detectors Alpha, Beta and Alpha-Beta Contamination Meters and Monitors Portable X or Gamma Radiation Exposure Rate Meters and Monitors for Use in Radiological Protection Standard Dimensions of Scintillators Portable Prospecting Radiation Meters with Geiger-Muller Counter Tube (Linear Scale Instruments! Portable Prospecting Radiation Meters with Gamma-Ray Scintillation Detectors Low Energy X or Gamma Radiation Portable Exposure Rate Meters and Monitors for Use in Radiological Protection Hand and/or Foot Contamination Monitors and Warning Assemblies Radiation Detectors for the Instrumentation and Protection of Nuclear Reactors; Characteristics and Test Methods
Pub
73
Pub
73
Pub
73
Pub
73
Pub
74
Pub Pub
75 75
Pub
76
Pub
76
Pub
76
Pub
76
Pub Pub
77 72
Pub
72
Pub Pub
72 78
Pub
79
Pub
67
Pub
70
Pub
72
Pub Pub
73 73
Pub
74
Pub
74
Pub
75
Pub
75
81
5.4 Issuing Body (Country)
No. IEC 532 I EC 579
IEC IEC
IEC 582 IEC 596
IEC IEC
IEEE 497
IEEE
ISO 1758
ISO
ISO 1759
ISO
JIS Z4202
JIS
JIS Z4222 JIS Z4304
JIS JIS
JIS JIS JIS JIS
Z4307 Z4308 Z4309 Z4310
JIS JIS JIS JIS
JIS Z4311 JIS Z4312 JIS Z4313
JIS JIS JIS
JIS JIS JIS JIS
Z4314 Z4315 Z4316 Z4317
JIS JIS JIS JIS
JISZ4318
JIS
JISZ4319 JIS Z4320
JIS JIS
JIS Z4321
JIS
JIS Z4402 JIS Z4411
JIS JIS
JIS Z4509 KTA 1501
JIS KTA
MSZ 14341
MSZH
NCRP Report No.25
NCRP
NCRP Report No.53
NCRP
NCRP Report No.57
NCRP
S5230 R.G. 1.21
ONORM USNRC
82
Title
Status
(Remarks)
Installed Exposure Rate Meters, Warning Assemblies and Monitors for X or Gamma Radiation of Energy between 80 KeV and 3 MeV Radioactive Aerosol Contamination Meters and Monitors Dimensions of Vials for Liquid Scintillation Counting Definitions of Test Method Terms for Semiconductor Radiation Detectors and Scintillation Counting Trial-Use Standard Criteria for Post Accident Monitoring Instrumentation for Nuclear Power Generating Stations Direct-Reading Electroscope-Type Pocket Exposure Meters Indirect-Reading Capacitor-Type Pocket Exposure Meters and Accessory Electrometers End Window Geiger-Muller Counter Tubes for Beta Ray Survey Meters General Rules for Geiger-Muller Counter Tubes Scintillation Counter Type Survey Meters for Radioactive Surface Contamination Ionization Chamber Type Radon Scopes Pocket Chambers and Dosimeters Ionization Chamber Type Radiation Survey Meters Geiger-Muller Counter Tube Type Radiation Survey Meters Personal Exposure Alarm Meters X and Gamma Rays Scintillation Survey Meters for Gamma Rays Boron Coated Neutron Pocket Chambers and Dosimeters Fluoro Glass Dosimeter for X and Gamma Rays Geiger-Muller Counter Type Hand-Foot Monitors Radioactive Dust Monitors Gas Flow Counter Type Survey Meters for Radioactive Surface Contamination Gas Filled Counter Type Survey Meters for Radioactive Surface Contamination Counters for Geiger-Muller Tubes Thermoluminescence Dosimeters for X and Gamma Rays Thallium-Activated Sodium Jodide Scintillator for Radiation Detection Vial for Scintillation Counter Stabilized D.C. High Voltage Supplies for Radiation Detection Instruments Method of Handling X and Gamma Ray Film Badges Ortsfestes System zur Uberwachung von Ortsdosisleistungen innerhalb von Kernkraftwerken (Stationary System for the Surveillance of Local Dose-Rates within the Nuclear Power Station) (Available also in English; Identical with DIN 25458/ Dosimetry for External X-, Beta- and Gamma Radiation Measurement of Absorbed Dose of Neutrons and of Mixtures of Neutrons Review of NCRP Radiation Dose Limit for Embryo and Fetus in Occupationally Exposed Women Instrumentation and Monitoring Methods for Radiation Protection Strahlenschutzdosimeter; Allgemeine Regeln Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Release of Radioactivity in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants
Pub
76
Pub
77
Pub Pub
77 78
Pub
77
Pub
76
Pub
76
Pub
77
Pub Pub
77 76
Pub Pub Pub Pub
75 75 76 76
Pub Pub Pub
78 76 75
Pub Pub Pub Pub
76 77 78 76
Pub
76
Pub Pub
77 76
Pub
77
Pub Pub
68 75
Pub Pub
78 10.77
Pub
72
Pub
61
Pub
77
Pub Iss Iss
78 4.79 6.74
5.4 No.
Issuing Body
(Country)
R.G. 1.97
USNRC
R.G. 1.109
USNRC
R.G. 8.4
USNRC
R G. 8.6
USNRC
R G. 8.26
USNRC
VdTUV Wei 22
VdTUV
Title
Status
(Remarks)
Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I Direct-Reading and Indirect-Reading Pocket Dosimeters Standard Test Procedures for Geiger-Muller-Counters Application of Bioassay for Fission and Activation Products Anforderungen an die Mefteinrichtungen zur kontinuierlichen Aktivitatsuberwachung der Wasserund Wasserdampf-Kreislaufe in Kernkraftwerken mit Leichtwasserreaktoren
Iss
8.77
Iss
10.77
Iss
2.73
Iss
5.73
Iss
9.80
Iss
5.80
83
6.1 No.
Issuing Body (Country)
6
Nuclear Fuel Cycle
6.1
Mining
• ANSI N7 1a /ANSI N508 ANSI N13.8 ANSI N313 CNEN NE4.01 CNEN NE4.03 IEC201 IEC 253 IEC 421 IEC 460 IEC 576 IEC 600 R.G. 3.5 R.G. 3.8 R.G. 3.11 R.G. 3.11.1
R.G. 3.23 R.G. 4.14 Task No RH 802-4
84
Title (Remarks)
ANHMRC Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores Protection from Radiation and Other Hazards in ANSI Uranium Milling and Concentrating Radiation Protection in Uranium Mines Operation ANSI Stabilization of Uranium-Thorium Milling Waste ANSI Retention Systems CNEN Applicability of Law 4.118 to Nuclear Minerals and Ores CNEN Licensing of Uranium Mines IEC Power Sources for Portable Prospecting Equipment for Radioactive Materials IEC Power Supply for Air and Land Vehicle-Mounted Prospection Equipment for Radioactive Materials IEC Portable Prospecting Radiation Meters with Geiger-Muller Counter Tube (Linear Scale Instruments) IEC Portable Prospecting Radiation Meters with Gamma-Ray Scintillation Detectors IEC Portable Bore-Hole Logging Equipment (down to 300 m): General Characteristics IEC Equipment for Minehead Assay and Sorting by Container USNRC Standard Format and Content of License Applications for Uranium Mills (Issued for Comments) USNRC Preparation of Environmental Reports for Uranium Mills (Issued for Comments) USNRC Design, Construction, and Inspection of Embankment Retention Systems for Uranium Mills USNRC Operational Inspection and Surveillance of Embankment Retention Systems for Uranium Mill Tailings (Issued for Comments) USNRC Stabilization of Uranium-Thorium Milling Waste Retention Systems USNRC Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquids and Airborne Effluents from Uranium Mills USNRC Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations (Proposed R. G.)
Status
Iss
75
Pub
69
Pub Pub
73 74
Iss
65
list Pub
65
Pub
67
Pub
73
Pub
74
Pub
77
Pub
79
Iss
11.77
Iss
9.78
Iss
12.77
Iss
4.79
Iss
11.74
Iss
4.80
Iss
5.79
6.2 Issuing Body
No. 6
(Country)
Title
Status
(Remarks)
Nuclear Fuel Cycle
6.2 Enrichment ASTM C 787
ASTM
CNEN NE 1.10 RDT E 13-3T RDT E 13-4T R.G. 3.25
CNEN ORNL ORNL USNRC
R.G 4.9
USNRC
R.G 5.21
USNRC
R.G 5.45
USNRC
R.G. 8.24
USNRC
Specification for Uranium Hexafluoride for Enrichment Contents of S.A.R for Fuel Enrichment Plants Fast Flux Test Facility Uranyl Nitrate Solution Fast Flux Test Facility Plutonium Nitrate Solution Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities Preparation of Environmental Reports for Commercial Uranium Enrichment Facilities Nondestructive Uranium-235 Enrichment Assay by Gamma-Ray Spectrometry Standard Format and Content for the Special Nuclear Material Control and Accounting Section of a Special Nuclear Material License Application (Including That for a Uranium Enrichment Facility) Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication (Issued for Comments)
Pub
76
Ust Pub Pub Iss
6.71 6.71 12.74
Iss
10.75
Iss
4.74
Iss
12.74
Iss
11.78
85
6.3 No. 6
Issuing Body (Country)
Title (Remarks)
Status
Nuclear Fuel Cycle
6.3 Manufacturing ANSI N7.2 ANSI ANSI N15.9
ANSI
ANSI N287
ANSI
ANSI N290
ANSI
CNEN NE 1.09
CNEN
ISO 1709
ISO
RDTE 13-1T
ORNL
RDT E 13-2T
ORNL
RDTE 13-5T RDT E 13-6T
ORNL ORNL
RDT E 13-7T RDTE 13-8T
ORNL ORNL
RDT E 13-9T RDT E 13-10T RDT E 13-1 IT RDT E 13-12T RDTE 13-13T RDT E 13-15T
ORNL ORNL ORNL ORNL ORNL ORNL
RDT E 13-16T RDTF 11-4T
ORNL ORNL
RDTF 11-5T
ORNL
RDTF 11-6T
ORNL
R G. 3.7
USNRC
R.G. 3.21
USNRC
R.G. 3.29
USNRC
R.G. 3.34
USNRC
R.G. 3.36
USNRC
R.G. 3.39
USNRC
R.G. 3.40
USNRC
Radiation Protection in Nuclear Reactor Fuel Fabrication Plants Nuclear Materials Control Systems for Fuel Fabrication Plants Criteria for Siting, Design, and Operation of Plants for the Manufacture of Mixed Oxide (UPU) Fuels Design, Construction and Operation of Ventilation Systems for Mixed Oxide (U, PU) Fuel Fabrication Plants Contents of S.A.R. for Fuel Elements Fabrication Plants Nuclear Energy - Fissile materials - principles of criticality safety in handling and processing Fast Flux Test Facility Ceramic Grade Plutonium Dioxide Ceramic Grade Uranium Dioxide Fast Flux Test Facility Driver Fuel Pin Fast Flux Test Facility Driver Fuel Pin Mixed Oxide Fuel Pellet Fast Flux Test Facility Driver Fuel Pin Insulator Pellet Fast Flux Test Facility Driver Fuel Pin Seamless Cladding Tube Fast Flux Test Facility Driver Fuel Pin End Caps Fast Flux Test Facility Driver Fuel Pin Reflectors Fast Flux Test Facility Driver Fuel Pin Plenum Spacer FasfFlux Test Facility Driver Fuel Pin Plenum Spring Fast Flux Test Facility Driver Fuel Pin Wrap Wire Fuel Assemblies for Pressurized Water Reactors Driver Fuel Assembly Determination of a Figure of Merit for Pu02-U02 Fuel Pellet Homogeneity by Use of an Electron Microprobe Determination of Fuel Pellet Homogeneity by Alpha-Autoradiography Ceramographic Preparation of Mixed Oxide Fuel Pellets Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing Plants and to Plutonium Processing and Fuel Fabrication Plants Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant Non-destructive Examination of Tubular Products for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants /Withdrawn 2.69) Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants
Pub
63
Pub
75
Pub
76
Pub
79
Ust Pub
75
Pub
6.71
Pub 6.71 Amm 12.74 Pub 6.71 Pub 6.71 Amm 12.74 671 Pub Pub 671 Pub Pub Pub Pub Pub Pub Amm Pub Pub
6.71 6.71 6.71 6.71 6.71 7.71 5.72 9.77 9.72
Pub
5.75
Pub
1.73
Iss
3.73
Iss
3.74
Iss
5.75
Iss
7.79
Iss
1.76
Iss
12.77
6.3 No. R.G. 4.16
Issuing Body (Country) USNRC
R G. 5.30
USNRC
R.G. 8.21
USNRC
R.G. 8.24
USNRC
Title (Remarks) Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Airborne Effluents from Nuclear Fuel Processing and Fabrication Plants (Issued for Comments) Materials Protection Contingency Measures for Uranium and Plutonium Fuel Manufacturing Plants Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and Manufacturing Plants (Under Revision) Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication (Issued for Comments)
Status Iss
3.78
Iss
6.74
Iss
5.78
Iss
11.78
87
6.4 No. 6
Issuing B o d y (Country)
Status
Nuclear Fuel Cycle
6.4 Reprocessing ANS-8.9
ANS
ANSI N15.13
ANSI
ANSI N46.2.11
ANSI
ANSI N46.2.13
ANSI
ANSI N101.3
ANSI
ANSI N299
ANSI
ANSI N300
ANSI
ANSI N303
ANSI
ANSI N304 ANSI N305
ANSI ANSI
CNEN NE 1.02 CNEN NE 1.08 BAnz. Nr. 132/1975
CNEN CNEN SSK
R.G. 3.3
USNRC
R.G. 3.6
USNRC
R G. 3.7
USNRC
R.G. 3.10
USNRC
R.G. 3.12
USNRC
R.G. 3.14
USNRC
R.G. 3.16
USNRC
R.G. 3.17
USNRC
R.G. 3.18
USNRC
R.G. 3.19
USNRC
R.G. 3.20 R.G. 3.21
USNRC USNRC
R.G. 3.22
USNRC
R.G. 3.26
USNRC
R.G. 3.27
USNRC
R.G. 3.28
USNRC
88
Title (Remarks)
Nuclear Criticality Safety Guide for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate Nuclear Material Control Systems for Fuel Processing Facilities (a Guide to Practice) Quality Assurance Requirements for the Design of Nuclear Fuel Reprocessing Facilities Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Fuel Reprocessing Facilities Guide to Principal Design Criteria Nuclear Fuel Reprocessing Facilities Administrative Controls for Nuclear Fuel Reprocessing Plants Design Criteria for Shutdown and Decommissioning of Nuclear Fuel Reprocessing Facilities Guide for Control of Gasborne Radioactive Materials at Fuel Reprocessing Facilities Fire Protection for Fuel Reprocessing Facilities Design Objectives for Highly Radioactive Solid Material Handling and Storage Facilities in a Reprocessing Plant General Design Criteria for Fuel Reprocessing Plants Contents of S.A.R. for Fuel Reprocessing Plants Abtrennung von Krypton-85 aus den Abgasen von Wiederaufarbeitungsanlagen vom 2.7.1975 Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants Guide to Content of Technical Specifications for Fuel Reprocessing Plants Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants General Design Guide for Ventilation Systems of Plutonium Processing and Fuel Fabrication Plants Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants Earthquake Instrumentation for Fuel Reprocessing Plants Confinement Barriers and Systems for Fuel Reprocessing Plants Reporting of Operating Information for Fuel Reprocessing Plants Process Offgas Systems for Fuel Reprocessing Plants Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing Plants and to Plutonium Processing and Fuel Fabrication Plants Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants Non-destructive Examination of Welds in the Liners of Concrete Barries in Fuel Reprocessing Plants Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants
Pub
78
Pub
74
Pub
77
Pub
77
Pub
73
Pub
76
Pub
75
Pub
78
Pub Pub
78 75
Iss Drf Iss
79 79 7.75
Iss
3.74
Iss
4.73
Iss
3.73
Iss
6.73
Iss
8.73
Iss
10.73
Iss
1.74
Iss
2.74
Iss
2.74
Iss
2.74
Iss Iss
2.74 3.74
Iss
6.74
Iss
2.75
Iss
5.77
Iss
5.75
6.4 No.
Issuing B o d y (Country)
R.G. 3.29
USNRC
R.G. 3.31
USNRC
R.G. 3.32
USNRC
R.G. 3.33
USNRC
R.G. 3 35
USNRC
R.G. 3.36
USNRC
R.G 3 37
USNRC
R.G. 3.38
USNRC
R.G. 3.40
USNRC
Task No. FP 818-4
USNRC
Task No. FP 925-5
USNRC
10 CFR 50 Appendix F USNRC
Title
Status
(Remarks)
Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants Emergency Water Supply Systems for Fuel Reprocessing Plants General Design Guide for Ventilation Systems for Fuel Reprocessing Plants (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant Non-destructive Examination of Tubular Products for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants (Withdrawn 2.69) Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (Issued for Comments) General Fire Protection Guide for Fuel Reprocessing Plants (Issued for Comments) Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants Standard Format and Content of Licensee Applications, Including Environmental Reports, for In Situ Uranium Solution Extraction (Proposed R. G) Nuclear Criticality Safety for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate (Proposed R. G) Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities
Iss
5.75
Iss
5.77
Iss
975
Iss
4.77
Iss
779
Iss
9.75
Iss
6.76
Iss
1277
Iss
7.80
Iss
1.80
89
6.5 No. 6
Issuing B o d y (Country)
Title (Remarks)
Nuclea r Fuel Cycle
6.5 Genera I A s p e c t s of Radioactive W a s t e M a n a g e m e n t GCR Plant Liquid Radwaste System ANS ANS-53.24 Design Criteria for the Solid Radwaste Processing ANS-55.1 ANS System of BWR, PWR, and HTGR (Draft for Comments) ANS-55.4 ANS Design Criteria for Gaseous Radioactive Waste Processing Systems for LWRs ANS-55.6 ANS Liquid Radioactive Waste Processing System for Light Water Reactor Plants ANS-57.2 ANS Design Objectives for Light Water Reactor Spent /ANSI N210 Fuel Facilities at Nuclear Power Stations ANSI N5.8 ANSI Definitions of Radioactive Waste Categories ANSI N14.3 ANSI Packaging and Transportation of Radioactively Contaminated Biological Materials ANSI N14.9.1 ANSI Packaging Liquid Radioactive Wastes from Nuclear Power Plants ANSI N15.1 ANSI Classification of Unirradiated Uranium Scrap ANSI N15.10 ANSI Classification of Unirradiated Plutonium Scrap ANSI N313 Stabilization of Uranium-Thorium Milling Waste ANSI Retention Systems ASTM C 853 ASTM Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste GOST 17606 GOST Radioaktiver Abfall und Entaktivierung GOST 20286 GOST Radioaktive Verunreinigungen und Entaktivierung Long-term Leach Testing of Radioactive Waste ISO/DIS6961 ISO Solidification Products ISO/DIS 6962 ISO Standard Method for Testing the Irradiation Stability of Solidified Radioactive Waste ISO/DP 6963 ISO Soxhlet Leach Test Procedure for Testing of Solidified Radioactive Waste Products GSN-12 JEN Almacenamiento Temporal de Residuos Radiactivos. (Temporary Sotorage of Radioactive Wastes) JIS Z4902 JIS The Bins for Solid Radioactive Waste in Door MSZ 14344 Radioactive Wastes: Terms, Waste Categories, MSZH Management R.G. 1.21 USNRC Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Release of Radioactivity in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants R.G. 1.70.27 USNRC Information for Safety Analysis Reports Radioactive Waste Management (See also R.G. 1.70) R.G. 1.110 USNRC Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (Issued for Comments) R.G. 1.143 USNRC Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (Under Revision) R.G. 3.13 USNRC Guide for Acceptable Waste Storage Methods at UF6 Production Plants R.G. 3.23 USNRC Stabilization of Uranium-Thorium Milling Waste Retention Systems R.G. 7.2 USNRC Packaging and Transportation of Radioactively Contaminated Biological Materials 10 CFR 50 Appendix F USNRC Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities BGBI. I, S. 41 (DEU) Abfallbeseitigungsgesetz in der Fassung der Bekanntmachung vom 5. Januar 1977 90
Status
Ust Drf
2.79
Pub
79
Pub
79
App
76
Pub Pub
67 73
Pub
76
Pub Pub Pub
70 72 74
Pub
77
Pub Pub Drf
72 74 79
Drf
80
Ust Drf
79
Pub Pub
60 74
Iss
6.74
Iss
4.75
Iss
3.76
Iss
10.79
Iss
10.73
Iss
11.74
Iss
6.74
Iss
1.77
6.5 No.
Issuing Body (Country)
BGBI. I, S. 2478
(DEL))
BGBI. II, S. 165 /BGBI. I, S. 373
(DEL))
Title (Remarks) Verordnung zur Durchführung des Gesetzes zu den Ubereinkommen vom 15. Februar 1972 und 29. Dezember 1972 zur Verhiitung der Meeresverschmutzung durch das Einbringen von Abfallen durch Schiffe und Luftfahrzeuge (Hohe-See-Einbringungsverordnung] vom 7. Dezember 1977 Gesetz zu dem Ubereinkommen vom 15. Februar 1972 und 29. Dezember 1972 zur Verhiitung der Meeresverschmutzung durch das Einbringen von Abfallen durch Schiffe und Luftfahrzeuge vom 11. Februar 1977, zuletzt geandert durch Artikel 11 des Gesetzes vom 28. März 1980
Status Iss
Iss Amm
12.77
2.77 3.80
91
6.6 No. 6
Issuing B o d y (Country)
Status
Nuclear Fuel Cycle
6.6 Treatmemt of Radioacti ANS-55.1 ANS ANS-55.2 /ANSI N199 ANS-55.3 /ANSI N197 ANS-55.4
ANS
ANS-55.6
ANS
DIN 25416 Teil 1
DIN
KTA 3603
KTA
RDTE11-1T R.G. 3.10
ORNL USNRC
92
Title (Remarks)
ANS ANS
Design Criteria for the Solid Radwaste Processing System of BWR, PWR, and HTGR (Draft for Comments) Liquid Radioactive Waste Processing System for Pressurized Water Reactor Plants Boiling Water Reactor Liquid Radioactive Waste Processing System Design Criteria for Gaseous Radioactive Waste Processing Systems for LWRs Liquid Radioactive Waste Processing System for Light Water Reactor Plants Anlagen zur Behandlung von radioaktiv kontaminiertem Wasser in Kernkraftwerken; Sicherheitstechnische Anforderungen (Treatment of Radioactive Contaminated Water in Nuclear Power Plants; Safety Requirements) (in Press; Identical with KTA 3603) Anlagen zur Behandlung von radioaktiv kontaminiertem Wasser in Kernkraftwerken (Treatment of Radioactive Contaminated Water in Nuclear Power Plant) (Identical with DIN 25416 Teil 1) Ion Exchanger, Non-Regenerative Type Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants
Drf
2.79
App
76
App
76
Pub
79
Pub
79
Pub
2.80
Pub Iss
5.72 6.73
6.7 No. 6
Issuing Body (Country)
Title (Remarks)
Status
Nuclear Fuel Cycle
6.7 Disposal of Radioactive W a s t e s NCRP Report No.12 NCRP Recommendations for the Disposal of Carbon-14 Wastes NCRP Report No.16 NCRP Radioactive Waste Disposal in the Ocean AECP 71 UKAEA Sea Disposal Packages for Radioactive Waste
Pub
53
Pub Iss
54 71
93
7.1 No. 1
Issuing Body (Country)
Status
Plant and Reactor Protection
7.1 General ANS-4.1
ANS
ANS-10.2
ANS
ANS-15.15
ANS
ANS-51.1 /ANSI N18.2
ANS
ANS-51.7 /ANSI N658 ANS-51.8 /ANSI N18.2a
ANS
ANS-51.10
ANS
ANS-52.1
ANS
ANS-53.1 /ANSI N213 ANS-54.6
ANS
ANS-54.10
ANS
ANS-56.3 /ANSI N193 ANS-58.2
ANS
ANS
ANS
ANS
ANS-58.3 /ANSI N182 ANS-58.4
ANS
ANS-58.9
ANS
ANS-59.1
ANS
ANS-59.3 /ANSI N187 ANSI N278.1
ANS
ASME OM-75-2
ASME
B PVC Sec.lll Div.l
ASME
BAnz. Nr 206/77
BMI
GMBI. 1976 S. 199
BMI
94
Title (Remarks)
ANS
ANSI
Criteria for Preparation of Design Bases for Systems that Perform Protective Functions in Nuclear Power Generating Stations Recommended Programming Practices to Facilitate Interchange of Digital Computer Programs Criteria for the Reactor Safety Systems of Research Reactors Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants (See also ANS-51.8) Single Failure Criteria for PWR Fluid Systems (See also ANS 58.9) Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, Section 2.2 and Section 2.3 (Revision to ANSI N18.2) Design Criteria for Auxiliary Feedwater Systems for PWR Plants Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants Nuclear Safety Criteria for the Design of Stationary Gas Cooled Reactor Plants LMFBR Safety Classification and Related Requirements (Draft for Comments) Probability Requirements for Accident Prevention in LMFBRs Overpressure Protection of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary Design Basis for Protection of Nuclear Power Plants Against Effects of Postulated Pipe Rupture Physical Protection for Systems and Components Important to Safety Criteria for Technical Specification for Nuclear Power Stations Single Failure Criteria for Light Water Reactor Safety Related Fluid Systems (Revision of ANS 51.7 and ANSI N658) Safety Related Cooling Water Systems in Nuclear Power Plants Safety-Related Control Air Systems Functional Specification Standard for Self-Operated and Power-Operated Safety-Related Valves Vibration Systems - Monitoring and Testing Requirements Boiler and Pressure Vessel Code; Division I: Subsection NB - Class 1 Components, Subsection NC - Class 2 Components, Subsection ND Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG - Core Support Structures, Appendices (Regular Addenda and Revisions Provided) Sicherheitskriterien fur Kernkraftwerke vom 21.10.1977 Richtlinien uber die Anforderungen an Sicherheitsspezifikationen fur Kernkraftwerke vom 27.4.1976
Pub
78
Pub
71
Pub
78
App
73
App
76
App
75
App
11.79
Pub
78
Pub Drf
78 1.79
Ust Pub
77
Pub
79
Pub
77
Pub
79
Pub
79
Pub
10.79
Pub
77
Pub
75
Ust Iss
74
Iss
10.77
Iss
4.76
7.1 No.
Issuing Body (Country)
GMBI. 1978 S. 631
BMI
GMBI. 1979 S. 161
BMI
GMBI. 1980 S. 90
BMI
Umwelt Nr. 43/75
BMI
M 62-101
CEA
DIN 25401 Teil 7
DIN
DIN 25417 Teil 1
DIN
DIN 25419 Teil 1
DIN
DIN 25419 Teil 2
DIN
30ST 17138
GOST
GOST 18298
GOST
IAEA 50-C-D
IAEA
IAEA 50-C-O
IAEA
IAEA 50-SG-D3
IAEA
AEA 50-SG-D4
IAEA
IAEA 50 SG-D11 IAEA 50-SG-03
IAEA IAEA
EC 639
IEC
Status
Title (Remarks) Interpretation zu den Sicherheitskriterien fur Kernkraftwerke, Einzelfehlerkonzept, vom 26.10.1978 Interpretationen zu den Sicherheitskriterien fur Kernkraftwerke vom 17.5.1979 1. Interpretation zu dem Sicherheitskriterium 2.6: "Einwirkungen von auBen" 2. Interpretation zu dem Sicherheitskriterium 8 5: "Warmeabfuhr aus dem SicherheitseinschlulS" Interpretationen zu den Sicherheitskriterien fur Kernkraftwerke vom 28.11.1979 1. Interpretation zu dem Sicherheitskriterium 2.2: "Prufbarkeit" 2. Interpretation zu dem Sicherheitskriterium 2.3: "Strahlenbelastung in der Umgebung" 3. Interpretation zu dem Sicherheitskriterium 2 6: "Einwirkungen von auBen" 4. Interpretation zu dem Sicherheitskriterium 2.7: "Brand- und Explosionsschutz" 5. Interpretation zu dem Sicherheitskriterium 4.3: "Nachwarmeabfuhr nach Kuhlmittelverlusten" Bewertungsdaten fur die Eigenschaften von Kernkraftwerksstandorten aus der Sicht von Reaktorsicherheit und Strahlenschutz vom 11.6.1975 Principes fondamentaux de protection dans la conception et la construction des installations dans lesquelles sont utilisees des sources radioactives non scellees (Basic Principles for Safety in the Design and Construction of Installations in wich Unsealed Radioactive Sources are Used) Kerntechnik; Begriffe, Sicherheit kerntechnischer Anlagen (Nuclear Technology; Terms and Definitions, Safety of Nuclear Installations! Ubergeordnete Anforderungen an die elektrische Energieversorgung des Sicherheitssystems; Einblockanlagen, Sicherheitstechnische Anforderungen (General Requirements for Electrical Power Supply to Safety Systems for Nuclear Power Generating Stations; Single-Unit Stations, Safety Requirements) (Identical with KTA 3701.1) Storfallablauf analyse; Storfallablauf diagramm, Methode und Bildzeichen (Incident Sequence Analysis; Event Tree, Method and Graphical Symbols) Storfallablaufanalyse; Auswertung des Storfallablaufdiagramms mit Hilfe der Wahrscheinlichkeitsrechnung (Incident Sequence Analysis; Event Tree, Probabilistic Evaluation) Gerat fur die Kontrolle der Dichtheit des Mantels von warmeabstrahlenden Elementen von Kernreaktoren Strahlungsfestigkeit von Apparaten, Zubehorteilen und Werkstoffen Design for Safety of Nuclear Power Plants, Code of Practice Safety in Nuclear Power Plant Operation, Including Commissioning and Decommissioning, Code of Practice Protection Systems and Related Features in Nuclear Power Plants Protection against Internally Generated Missiles and their Secondary Effects in Nuclear Power Plants General Design Safety Principles Operational Limits and Conditions for Nuclear Power Plants Use of Protection System for Non-Safety Purpose
Iss
1078
Iss
579
Iss
1179
Iss
6.75
Pub
8 70
Drf
2.79
Pub
12.78
Pub
6.77
Pub
2.79
Pub
71
Pub
72
Pub
78
Pub
78
Ust Ust Ust Pub
79
Pub
79 95
7.1 No.
Title
Issuing Body (Country)
IEEE 279 /ANSI N42.7 IEEE 352 /ANSI N41.4 IEEE 565
IEEE
RDT C 16-2T
ORNL
Criteria for Protection Systems for Nuclear Power Generating Stations Guide for Reliability Analysis of Nuclear Power Generating Station Protection Systems Recommended Practice for the Design of Display and Control Facilities for Central Control Rooms of Nuclear Power Generating Stations Reliability Requirements in the Design and Operation of Safety Systems for Nuclear Power Generating Stations Trial-Use Standard Criteria for Safety Systems for Nuclear Power Generating Stations Richtlinien fur die Bemessung von Stahlbetonbauteilen von Kernkraftwerken ftir auSergewohnliche aulJere Belastungen (Erdbeben, groUere Explosionen, Flugzeugabsturz) Auslegung von Kernkraftwerken gegen seismische Einwirkungen Teil 1: Grundsatze (Design of Nuclear Power Plants Against Seismic Effects Part 1: Basic Principles) (Available also in English) Komponenten des Primarkreises von Leichtwasserreaktoren Teil 2: Auslegung, Konstruktion und Berechnung (Components for the Primary Circuit of Light Water Reactors Part 2: Design, Construction and Calculation) Ubergeordnete Anforderungen an die elektrische Energieversorgung des Sicherheitssystems in Kernkraftwerken Teil 1: Einblockanlagen (General Requirements for Electrical Power Supply to Safety Systems for Nuclear Power Plants Part 1: Single-Unit Stations) (Available also in English; Identical with DIN 25417 Teil I) Supplementary Criteria and Requirements for RDT Reactor Plant Protection Systems Protection System Logic
IEEE 577
IEEE
IEEE 603
IEEE
*
IfBT
KTA 2201.1
KTA
KTA 3201.2
KTA
KTA 3701.1
KTA
RDTC16-1T
ORNL
RDTC16-3T
ORNL
PPS Buffers
RDT C 16-4T
ORNL
Protection System Comparator
RDTC17-8T
ORNL
Annunciators for Control Systems
AECP1058
UKAEA
R.G. 1.22
USNRC
R.G. 1.26
USNRC
R.G. 1.32
USNRC
Drainage of Radioactive Areas (Provisional only) Periodic Testing of Protection System Actuation Functions (Safety Guide 22) Quality Group Classifications and Standards for Water-, Steam- and Radio-Waste-Containing Components of Nuclear Power Plants (Issued for Comments) Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants Reactor Coolant Pressure Boundary Leakage Detection Systems Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems Power Levels of Nuclear Power Plants Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems
IEEE IEEE
R.G. 1.45
USNRC
R.G. 1.47
USNRC
R.G. 1.49 R.G. 1.53
USNRC USNRC
96
Status
(Remarks) Pub Rev Pub
70 78 75
Pub
77
Pub
76
Pub
77
Pub Amm
7 74 8.75
Pub
6.75
Pub
10.80
Pub
6.78
Pub
12.69
4.72 Pub Amm 6.73 Pub 10.71 Amm 12.71 4.72 Pub Amm 6.73 Pub 10.72 Amm 8.73 Iss 79 Iss
2.72
Iss
2.76
Iss
2.77
Iss
5.73
Iss
5.73
Iss Iss
12.73 6.73
7.1 No.
Issuing Body (Country)
R.G. 1.57
USNRC
R.G. 1.62 R.G. 1.67 R.G. 1.70.16
USNRC USNRC USNRC
R.G. 1.70.37
USNRC
R.G. 1.84
USNRC
R.G. 1.142
USNRC
R.G. 3.22
USNRC
R G 3.24
USNRC
R.G. 5.26
USNRC
VDI 2180 Blatt 1 VDI 2180 Blatt 2
VDI
VDI 2180 Blatt 3
VDI
VDI 2180 Blatt 4
VDI
VDI 2180 Blatt 5
VDI
VDI 2180 Blatt 6
VDI
VDI 2180 Blatt 7
VDI
VDI 3551
VDI
VDI 3558
VDI
VdTUV Wei 8
VdTUV
VdTUV Wei 27
VdTUV
Order No 62-VHXH/ND Leg. Series 1965 No. 31/1200
(VNM)
VDI
(YUG)
Title
Status
(Remarks)
Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components Manual Initiation of Protective Actions Installation of Overpressure Protective Devices Information for Safety Analysis Report-Missile Barrier Design Procedures (See also R.G 1 70) Information for Safety Analysis Reports - Pressurizer Relief Discharge System (See also R.G 1.70) Design and Fabrication Code Case Acceptability-ASME Section III Division I (Under Revision) Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments) (Issued for Comments) Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation Selection of Material Balance Areas and Items Control Areas Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen; Moglichkeiten der Signalverarbeitung Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen; Planung und Aufbau von Sicherungseinrichtungen Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen; Prufung von Sicherungseinrichtungen Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen; Hilfsenergieversorgung der Einrichtungen zum Messen, Steuern und Regeln Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen; Bauliche und installationstechnische MaBnahmen zur Funktionssicherung von MeS-, Steuer- und Regeleinrichtungen in Ausnahmezustanden Sicherung von Anlagen der Verfahrenstechnik; Einfuhrung, Begriffe, Erklarungen; Katalog der Gesetze, Vorschriften, Richtlinien Empfehlungen zur Storsicherheit der Signaliibertragung beim Einsatz von ProzeBrechnern Projektierung von ProzefJrechnersystemen mit Redundanz zur Erhohung der Verfiigbarkeit einer Automatisierungsanlage AulJere Bauwerksabdichtungen in kerntechnischen Anlagen Auslegung, Konstruktion und Prufung von Rohrausschlagsicherungen in kerntechnischen Anlagen Safety Standards to be Applied in the Operation of Undertakings Using Sources of Ionizing Radiation Regulation Concerning the Technical Training of Persons Working With Sources of Ionizing Radiation and Carrying Out Activities in Connection With Protection Against Such Radiation
Iss
6 73
Iss Iss Iss
10.73 10.73 75
Iss
6.75
Iss
5.79
Iss
4.78
Iss
6.74
Iss
12.74
Iss
4.75
Pub
12.65
Pub
12.65
Pub
10.67
Pub
10.67
Pub
1.68
Pub
2 69
Pub
8 71
Pub
10 76
Drf
12 77
Iss
12.76
Iss
11.79
Iss
3.67
Iss
6.65
97
7.2 No. 7
Issuing Body (Country}
Status
Plant and Reactor P r o t e c t i o n
7.2 Instrumentation NFC 77-100 AFNOR ANS-2.2
ANS
ANSI N42.4
ANSI
ANSI N317
ANSI
ANSI N320
ANSI
ANSI N544
ANSI
BS 4877
BSI
BS 5251
BSI
BS5548
BSI
MCH/MENT 5
CEA
MCH/MENT 6
CEA
MCH/MENT 7
CEA
MCH/MENT 8
CEA
MCH/MENT 9
CEA
MCH/MENT 10
CEA
MCH/MENT 11
CEA
MCH/MENT 12 NF M 60-501
CEA CEA
SI 62/2643
DEGR
DIN 25445 Teil 5
DIN
DIN 44429
DIN
DIN 44800
DIN
GO ST 13539
GOST
GOST 13540
GOST
GOST 14345
GOST
98
Title (Remarks)
Systeme modulaire (^'instrumentation pour le traitement de I'information - Systeme CALMAC Earthquake Instrumentation Criteria for Nuclear Power Plants High Voltage Connectors for Nuclear Instruments Inplant Plutonium Monitoring, Performance Criteria for Instrumentation Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation Signal Connectors for Nuclear Instruments Recommendations for General Principles of Nuclear Reactor Instrumentation Analogue Voltage Ranges and Logic Levels for Mains Operated Nuclear Instruments Specification for Radiation Detectors for the Instrumentation and Protection of Nuclear Reactors: Characteristics and Test Methods Caracteristiques et methodes d'essais des detecteurs de rayonnement Maintenabilite mise en oeuvre et procedure d'introduction dans les contrats Susceptibilite du materiel d'electronique nucleaire a impulsions aux parasites Caracteristiques et methodes d'essais des sous ensembles a fluctuations Guide de procedures pour les essais sur le site de I'instrumentation des reacteurs nucleaires Caracteristiques et methodes d'essais des reactimetres Caracteristiques et methodes d'essais des ictometres Microlaquages, microphonic Appareils de mesure dosimetriques Styloexposimetres a lecture directe (sans chargeur incorpore) (Direct Reading Pocket Dosimeters without Charging Unit) The Radioactive Substances (Test Instruments) Exemption Order 1962 Auslegung von Kernkraftwerken gegen seismische Einwirkungen; Seismische Instrumentierung, Sicherheitstechnische Anforderungen (Design of Nuclear Plant against Seismic Effects; Seismic Instrumentation, Safety Requirements) (Identical with KTA 2201.5) Versorgungsspannungen fur netzbetriebene StrahlungsmeBgerate (Supply Voltages for Mains Operated Nuclear Instruments) Analogspannungsbereiche und Digitalpegel fur netzbetriebene Strahlungsmefsgerate (Analogue Voltage Ranges and Logic Levels for Mains Operated Nuclear Instruments) Stabilisierte Hochspannungs-Speiseeinheiten der Typen 592 und 593 fur elektronische Gerate der Kernphysik Stabilisierte NV-Speiseeinheiten des Typs 591 fur elektronische Gerate der Kernphysik Hochspannungs-Steckverbindungen fur den kernphysikalischen Geratebau
Iss
77
Pub
78
Pub Rev Pub
71 78 78
Pub
79
Pub Rev Pub
73 79 72
Pub
75
Pub
78
Pub
76
Pub
78
Pub
72
Pub
74
Pub
75
Pub
76
Pub
77
Pub
78
Iss
62
Pub
2.78
Pub
7.74
Pub
8.75
Pub
74
Pub
74
Pub
69
7.2 No.
Issuing Body (Country)
GOST 14847
GOST
GOST 16328 GOST 16417
GOST GOST
IAEA 50-SG-D8 lEC 181
IAEA lEC
lEC 181A lEC 181B lEC 248
lEC lEC lEC
lEC 248-2
lEC
lEC 248A
lEC
lEC 293
lEC
lEC 313
lEC
lEC 323
lEC
I EC 482
lEC
I EC 498
lEC
IEC516
lEC
lEC 547
lEC
lEC 552
lEC
IEC640 IEC643
lEC lEC
IEEE 500
IEEE
IEEE 583
IEEE
JIS Z4601 JIS Z8103 JIS Z8204 KTA 2201.5
JIS JIS JIS KTA
RDT C 1-1T
ORNL
RDT C 2-3T
ORNL
RDT C 4-4T RDT C4-5T
ORNL ORNL
RDTC4-6T
ORNL
RDT C 4-7T
ORNL
Title
Status
(Remarks)
Radioelektronische Apparatur fur den kerntechnischen Geratebau; Blocke, Stiitzen, Gestelle, Gehause Thermoelektrische Radioisotopen-Generatoren Hochspannungs-Steckverbindungen fur den kerntechnischen Geratebau Instrumentation and Control of Nuclear Power Plants Index of Electrical Measuring Apparatus Used in Connection with Ionizing Radiation First Supplement to lEC 181 Second Supplement to lEC 181 External Diameter of Planchets Used in Nuclear Electronic Instruments Dimensions of Planchets Used in Nuclear Instrumentation for Radioactive Assay; Part 2: Flat and Dish-Type Planchets First Supplement: Height Dimensions of " w e l l " Pattern Planchets Supply Voltages for Transistorized Nuclear Instruments Coaxial Cable Connections Used in Nuclear Instrumentation Analogue Voltage Ranges and Logic Levels for Mains Operated Nuclear Instruments Dimensions of Electronic Instrument Modules (for Nuclear Electronic Instruments) High-Voltage Coaxial Connectors Used in Nuclear Instrumentation A Modular Instrumentation System for Data Handling; CAMAC System Modular Plug-In Unit and Standard 19-Inch Rack Mounting Unit Based on NIM Standard CAMAC - Organization of Multi-Crate Systems. Specification of the Branch-Highway and CAMAC Crate Controller Type A1 Serial Highway Interface System (CAMAC) Application of Digital Computers to Nuclear Reactor Instrumentation and Control Guide to Collection and Presentation of Electrical, Electronic and Sensing Component Reliability Data for NPGS Computer Automated Measurement and Control (CAMAC) Radioactive Dust Samplers Glossary of Terms Used in Instrumentation Instrumentation Symbols Auslegung von Kernkraftwerken gegen seismische Einwirkungen Teil 5: Seismische Instrumentierung (Design Nuclear Power Plants Against Seismic Effects Part 5: Seismic Instrumentation) (Available also in English; Identical with DIN 25445 Teil 5) Instrumentation and Control Equipment Grounding and Shielding Practices Time Response Test for Sheathed, Mineral Insulated Thermocouple Assembly Venturi Flow Tube for Liquid Sodium Permanent Magnet Flowmeter for Liquid-Metal Piping Systems In-Core Permanent-Magnet Flow-Through-Type Flowmeter for Liquid Metal Service Eddy-Current Probe Type Flow Sensor for Liquid Metal Service
Pub
69
Pub Pub
70 70
Ust Pub
64
Pub Pub Pub
65 65 67
Pub
79
Pub
73
Pub
68
Pub
69
Pub
70
Pub
75
Pub
75
Pub
75
Pub
76
Pub
77
App App
78 78
Pub
78
Pub
75
Pub Pub Pub Pub
78 78 70 6.77
Pub Amm Pub
1.73 1.75 6.72
Pub Pub
8 74 4.74
Pub 4.73 Amm 11.74 Pub 6.73
99
7.2 No.
Issuing Body (Country)
RDT C 5-1T
ORNL
RDT C 5-2T
ORNL
RDTC6-1T
ORNL
RDT C 6-2T
ORNL
RDT C 6-3T
ORNL
RDTC7-15T
ORNL
RDTC7-16T
ORNL
RDTC 7-17T RDTC7-18T
ORNL ORNL
RDT C 8-2T
ORNL
RDT C 8-4T
ORNL
RDT C 8-5T
ORNL
RDT C 8-6T RDT C 8-8T
ORNL ORNL
RDTC 10-1T RDTC 10-5T
ORNL ORNL
RDT C 17-4T
ORNL
RDT C 17-9T RDTE8-13T
ORNL ORNL
SEN 434000
SIS
R.G. 1.11
USNRC
R.G. 1.12
USNRC
R.G. 1.30
USNRC
R.G. 1.70.22
USNRC
R.G. 1.70.23
USNRC
R.G. 1.80
USNRC
100
Title
Status
(Remarks)
Inductive Level Measurement Sensor for Use in Liquid Metal Resistive Level Measurement Sensor for Use in Liquid Metal NaK-Transmission High-Temperature Pressure Transmitter for Liquid Metal Service Differential Pressure Transmitter, Pneumatic or Electric Output Signal Liquid Metal Pressure Measurement System, Flush-Mounted, Eddy Current Type, Inductive, Absolute or Gage Thermocouple Connectors and Thermocouple Connector Panels Thermocouple Assemblies, Magnesium Oxide Insulated, Stainless Steel Sheathed Platinum Resistance Thermometer Thermowell Systems for Liquid Metal Service Liquid Sodium Bearing Film Thickness, Variable Reluctance Transducer, Proximity Measurement System Electrical Continuity-Type Liquid Metal Leak Detector Electrochemical Oxygen Meter for Service in Liquid Sodium Hydrogen Meter for Service in Liquid Sodium Specimen Equilibration Device (or Multipurpose Sampler) for the Analysis of Nonmetals in Liquid Sodium Thermocouple Signal Transmitter Eddy-Current Flowmeter Power Supply and Signal Conditioning Electronics General Instrumentation Foil-Shieled Instrumentation Cable Oxygen-Hydrogen Meter Module for Service in Liquid Sodium Nukleara Matinstrument. Oversikt av Normer. Internationella Rekommendationers Giltighet som Svensk Standard (Nuclear Instruments. Suvey of Standards. International Recommendations' Validity as Swedish Standards) Instrument Lines Penetrating Primary Reactor Containment. (Safety Guide 11; Supplement to Safety Guide 11 Backfitting Considerations 2.72) Instrumentation for Earthquakes (Under Revision) Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) Information for Safety Analysis Reports Instrumentation and Controls (See also R.G. 1.70) Information for Safety Analysis Reports - Seismic Qualification of Instrumentation and Electrical Equipment (See also R.G. 1.70) Preoperational Testing of Instrument Air Systems (Under Revision)
Pub
3.75
Pub 4.70 Amm 10.71 Pub 3.71 Amm 6.74 Pub 4.74 Pub 10.70 Amm 10.71 Pub 1.72 Amm 1.73 Pub 11.76 Pub Pub Amm Pub
4.75 8.72 5.74 1.76
Pub 10.72 Amm 6.73 Pub 1.72 Pub Pub
5.77 7.77
Pub Pub
1.79 2.73
Pub Amm Pub Pub
2.72 5.73 6.74 1.72
Pub
4.76
Iss Amm
3.71 2.72
Iss
4.74
Iss
8.72
Iss
2.75
Iss
2.75
Iss
6.74
7.2 No.
Issuing Body (Country)
R.G. 197
USNRC
R.G. 1.105 R.G. 1.106
USNRC USNRC
R.G. 3.17
USNRC
VDI 2184
VDI
VDI 2191
VDI
VDI 2192
VDI
VDI 2600 Blatt 1 VDI 2600 Blatt 2
VDI VDI
VDI 2600 Blatt 3
VDI
VDI 2600 Blatt 4
VDI
VDI 2600 Blatt 5
VDI
VDI 2600 Blatt 6
VDI
VDI 2620 Blatt 1 VDI 2620 Blatt 2
VDI VDI
VDI 3540 Blatt 1 VDI 3540 Blatt 2
VDI
VDI 3552 VDI 3557
VDI VDI
VDI
Title
Status
(Remarks)
Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident Instrument Setpoints Thermal Overload Protection for Electric Motors on Motor-Operated Valves Earthquake Instrumentation for Fuel Reprocessing Plants MeBumformer fur Druck; Beschreibung und Untersuchung MeBumformer fur Temperatur; Beschreibung und Untersuchung MeBumformer fur GroBen der Starkstromtechnik; Beschreibung und Untersuchung Metrologie (MeBtechnik); Inhaltsverzeichnisse und Gesamtstichwortverzeichnis der Blatter 2 bis 6 Metrologie (MeBtechnik); Inhaltsverzeichnis und Gesamtstichwortverzeichnis der Blatter 2 bis 6, Grundbegriffe Metrologie (Me6technik|; Inhaltsverzeichnisse und Gesamtstichwortverzeichnis der Blatter 2 bis 6; Geratetechnische Begriffe Metrologie (MeBtechnikl; Inhaltsverzeichnisse und Gesamtstichwortverzeichnis der Blatter 2 bis 6; Begriffe zur Beschreibung der Eigenschaften von MeSeinrichtungen Metrologie (MeBtechnik); Inhaltsverzeichnisse und Gesamtstichwortverzeichnis der Blatter 2 bis 6; Begriffe zur Darstellung der Wirkungsweise von MeBeinrichtungen Metrologie (MeBtechnik); Inhaltsverzeichnisse und Gesamtstichwortverzeichnis der Blatter 2 bis 6; Benennung von MeBeinrichtungen Fortpflanzung von Fehlergrenzen bei Messungen; Grundlagen Fortpflanzung von Fehlergrenzen bei Messungen; Grundlagen; Beispiele zur Fortpflanzung von Fehlern und Fehlergrenzen Zuverlassigkeit von MeB-, Steuer- und Regelgeraten; Erfassung von Ausfalldaten Zuverlassigkeit von MeB-, Steuer- und Regelgeraten; Erfassung von Ausfalldaten; Klimaklassen fur Gerate und Zubehor Leistungkriterien von ProzeSrechensystemen • Bedienpult fur ProzeBrechner in verfahrenstechnischen Anlagen (in Press)
Iss
8.77
Iss Iss
11.76 3.77
Iss
2.74
Pub
1.76
Pub
9.77
Pub
9.72
Pub
11.73
Pub
11.73
Pub
11.73
Pub
11.73
Pub
11.73
Pub
11.73
Pub
1.73
Pub
1.74
Pub
8.75
Pub
12.75
Pub
1.77
101
7.3 No. 7
Issuing Body
Title
(Country}
Plant and Reactor P r o t e c t i o n
7.3 Reacto r Protection Syste ms ANS Criteria for Remote Shutdown for LWRs ANS-58.6 (Combination ofANS-51.9 and ANS-52.5) BMI Richtlinien uber die in atomrechtlichen GMBI 1977 S. 66 /GMBI. 1977 S 108 Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen liber das Reaktorschutzsystem vom 20.1.1977, berichtigt am 7.3.1977 DIN 25434 DIN Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen; Sicherheitstechnische Anforderungen (Reactor Protection System and Monitoring of Safety Devices; Safety Engineering Requirements) (Identical with KTA 3501) GOST 17137 GOST Strahlungskontrollsysteme; Steuerung und Schutz bei Kernreaktoren GOST 17605 GOST Kernreaktoren; Automatisierte Kontroll- und Steuersysteme GOST 21933 GOST Systeme fur die Reaktorinnenkontrolle GOST 21935 GOST Systeme fur die Reaktorinnenkontrolle; Klassifikationskriterien IEC231 IEC General Principles of Nuclear Reactor Instrumentation IEC231A IEC First Supplement IEC231B IEC Second Supplement: Principles of Instrumentation of Direct Cycle Boiling Water Power Reactors IEC231C IEC Third Supplement: Instrumentation of Gas-Cooled Graphite-Moderated Reactors IEC 231D IEC Fourth Supplement: Principles of Instrumentation for Pressurized Water Reactors IEC231E IEC Fifth Supplement: Principles of Instrumentation of High Temperature Indirect Cycle Gas-Cooled Power Reactors IEC231F IEC Sixth Supplement: Steam Generating, Direct Cycle, Heavy-Water Moderated Reactors IEC 231G IEC Seventh Supplement: Liquid-Metal Cooled Fast Reactors IEC 232 IEC General Characteristics of Nuclear Reactor Instrumentation IEC 515 IEC Radiation Detectors for the Instrumentation and Protection of Nuclear Reactors; Characteristics and Test Methods IEC 568 IEC In-Core Instrumentation for Neutron Fluence Rate (Flux) Measurements in Power Reactors IEC 643 IEC Application of Digital Computers to Nuclear Reactor Instrumentation and Control KTA 3501 KTA Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen (Reactor Protection System and Monitoring of Safety Devices) KTA 3501 KTA Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen (Reactor Protection System and Monitoring of Safety Devices) (Available also in English; Identical with DIN 25434) RDTC 16-1T ORNL Supplementary Criteria and Requirements for RDT Reactor Plant Protection Systems RDT C 16-2T ORNL Protection System Logic RDTC 16-3T
ORNL
PPS Buffers
RDTC 16-4T
ORNL
Protection System Comparator
102
Status
(Remarks)
Drf
2.79
Iss Amm
1.77 377
Pub
10.77
Pub
71
Pub
72
Pub Pub
76 76
Pub
67
Pub Pub
69 72
Pub
74
Pub
75
Pub
77
Pub
77
Pub
77
Pub
66
Pub
75
Pub
77
App
78
Drf
1080
Pub
3.77
Pub
12.69
Pub 4.72 Amm 6.73 Pub 10.71 Amm 12.71 Pub 4.72 Amm 6.73
7.3 No.
Issuing Body
(Country)
SEN 434100
SIS
TS 2596
TSE
VDI 3527 VDI 3528
VDI VDI
Title
Status
(Remarks/
Karnreaktorinstrumentering. Oversikt av Normer. Internationella Rekommendationers Giltighet som Svensk Standard (Nuclear Reactor Instrumentation Survey of Standards. International Recommendations Validity as Swedish Standards) General Characteristics of Nuclear Reactor Instrumentation Kernreaktor-Regelung; Sinnbilder Regelung und Steuerung von Kernreaktoren; Spezielle Begriffe und Benennungen
Pub
4 76
Pub Pub
5.67 9.72
103
7.4 No. 7
Issuing Body (Country)
Title (Remarks)
Plant and Reactor Protection
7.4 Plant Protection IEEE 603 IEEE RDTE1-6T
ORNL
Trial-Use Standard Criteria for Safety Systems for Nuclear Power Generating Stations Automatic Spring-Loaded Safety Valves
10CFR73
USNRC
Physical Protection of Plants and Materials
104
Status
Pub
77
Pub 3.72 Amm 173
7.4.1 No.
Issuing Body
Title
(Country)
7
Plant and Reactor P r o t e c t i o n
7.4
Plant Protection
7.4.1 A l a r m S y s t e m s ANS-8.3 ANS /ANSI N16.2 BS 3510 BSI GOST 17925 IEC 532
GOST IEC
KTA 3901 KTA 3901.1
KTA KTA
R.G. 5.27 R.G. 5.44
USNRC USNRC
R.G. 8.12
USNRC
Task No. OH 015-4
USNRC
Task No. SG 479-4
USNRC
Status
(Remarks!
Criticality Accident Alarm System (Revision of ANSI NI6.2-I969) A Basic Symbol to Denote the Actual or Potential Presence of Ionizing Radiation Zeichen fur Strahlungsgefahr Installed Exposure Rate Meters, Warning Assemblies and Monitors for X or Gamma Radiation of Energy between 80 KeV and 3 MeV Kommunikationsmittel fur Kernkraftwerke Alarmanlagen, Personensuchanlagen und Fernmeldeverbindungen in und von Kernkraftwerken; Teil 1: Einblockanlagen (Alarm Systems, Personnel Call Systems and Telecommunications inside and from Nuclear Power Plants; Part 1: Single-Unit Stations) Special Nuclear Material Doorway Monitors Perimeter Instrusion Alarm Systems (Under Revision; see also Task No. SG 479-4) Criticality Accident Alarm Systems (Under Revision; see also Task No. OH 015-4) Criticality Accident Alarm Systems (Proposed R. G. 8.12) Perimeter Intrusion Alarm Systems (Proposed Revision to R.G. 5.44)
App
10.79
Pub
68
Pub Pub
72 76
Drf Pub
2.80 3.77
Iss Iss
6 74 6 76
Iss
12.74
Iss
5.80
Iss
5.79
105
7.4.2 No.
Issuing Body (Country)
Title (Remarks)
7
Plant and Reactor Protection
7.4
Plant Protection
7.4.2 Industrial S e c u r i t y ANS ANS-2.12 ANS-3.3 /ANSI N18.17 ANSI N15.40
ANS
Chapitre V
CEA
CNEN NE2.01
CNEN
IAEA50-SG-D5
IAEA
ANSI
IAEA50-SG-S5
IAEA
GSN-07
JEN
R.G. 1.17
USNRC
R.G. 1.70.15
USNRC
R.G. 5.7
USNRC
R.G. 5.12
USNRC
R.G. 5.14
USNRC
R.G. 5.15
USNRC
R.G. 5.20
USNRC
R.G. 5.31
USNRC
R.G. 5.43 R.G. 5.54
USNRC USNRC
R.G. 5.55
USNRC
Task No. SG 901-4
USNRC
Task No. SG 909-4
USNRC
Task No. SG 910-4
USNRC
10 CFR 73 Appendix B USNRC
106
Guidelines for Combining Natural Phenomena and Man-Made Hazards at Power Reactor Sites Industrial Security for Nuclear Power Plants Physical Protection of Nuclear Material and Facilities, Definition of Terms (Issued for Comments) Enceintes blindees et moyens de vision (See "Catalogue de materiel normalise") Physical Protection of Nuclear Materials and Facilities Man-Induced Events in Relation to Nuclear Power Plant Design Extreme Man-Induced Events in Relation to Nuclear Power Plant Siting Criterios Sobre la Seguridad Fisica de las Instalaciones nucleares. (Industrial Security at Nuclear Power Plants) Protection of Nuclear Plants Against Industrial Sabotage Information for Safety Analysis Reports-Industrial Security for NPP (See also R.G. 1.70) Control of Personnel Access to Protected Areas, Vital Areas and Material (Under Revision; see also Task No. SG 909-4) General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials (Under Revision) Visual Surveillance of Individuals in Material Access Areas (Under Revision; see also Task No. SG 910-4/ Security Seals for the Protection and Control of Special Nuclear Material Training, Equipping, and Qualifying of Guards and Watchmen Specially Designed Vehicle and Armed Guards for Road Shipments of Special Nuclear Material Plant Security Force Duties Standard Format and Content of Safeguards Contingency Plans for Nuclear Power Plants (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities (Issued for Comments) Reporting of Safeguards Events (Proposed R. G.) Entry/Exit Control of Protected Areas, Vital Areas, and Material Acces Areas (Proposed Revision to R.G. 5.7) Use of Observation (Visual Surveillance) Techniques in Material Access Areas (Proposed Revision to R. G. 5.14) General Criteria for Security Personnel
Status
Pub
78
App
73
Pub
11.79
Ust Iss
77
Ust Ust Iss
3.79
Iss
6.73
Iss
75
Iss
6.73
Iss
11.73
Iss
11.73
Iss
1.74
Iss
1.74
Iss
4.75
Iss Iss
1.75 3.78
Iss
3.78
Iss
1079
Iss
5.79
Iss
579
7.4.3 No.
Issuing Body
(Country)
7
Plant and Reactor P r o t e c t i o n
7.4
Plant Protection
Title
Status
(Remarks!
7.4.3 Protection against Fire and Explosions Hazards Generic Requirements for Light Water Nuclear ANS-594 ANS Power Plant Fire Protection Fire Protection for Fuel Reprocessing Facilities ANSI N304 ANSI Fire Protection Practice for Facilities Handling ANSI N693 ANSI /NFPA 801 Radioactive Materials Explosionsschutz-Richtlinien BG 11 BG Richtlinie fiir den Schutz von Kernkraftwerken gegen BAnz. Nr. 179/76 BMI Druckwellen aus chemischen Reaktionen durch Auslegung der Kernkraftwerke hinsichtlich ihrer 4c Festigkeit und induzierten Schwingungen sowie durch Sicherheitsabstande vom 13.9.1976 DIN EN 54 DIN Bestandteile automatischer Brandmeldeanlagen; Teil 1 Einleitung (Components of automatic fire detection systems; introduction) DIN EN 54 DIN Bestandteile automatischer Brandmeldeanlagen; Teil 5 Warmemelder, Punktformige Melder mit einem Element, mit statischer Ansprechschwelle (Components of automatic fire detection systems; heat sensitive detectors, point detectors containing a static element) DIN EN 54 DIN Bestandteile automatischer Brandmeldeanlagen; Teil 6 Warmemelder, punktformige Differentialmelder ohne Element mit statischer Ansprechschwelle (Components of automatic fire detection systems; heat sensitive detectors, rate of rise point detectors without a static element) DIN EN 54 DIN Bestandteile automatischer Brandmeldeanlagen; Teil 7 Punktformige Rauchmelder, Rauchmelder nach dem Streulicht-, Durchlicht- oder lonisationsprinzip (Components of automatic fire detection systems; point type smoke detectors, detectors using scattered light, transmitted light or ionization) DIN EN 54 DIN Bestandteile automatischer Brandmeldeanlagen; Teil 8 Warmemelder mit hohen Ansprechtemperaturen (Components of automatic fire detection systems; high temperature heat detectors) DIN EN 54 DIN Bestandteile automatischer Brandmeldeanlagen; Teil 9 Erprobungstest (Components of automatic fire detection systems; fire sensitivity test) DIN 4102 DIN Brandverhalten von Baustoffen und Bauteilen; Bbl 1 Inhaltsverzeichnisse (Behaviour of building materials and components in fire; indexes) DIN 4102 DIN Brandverhalten von Baustoffen und Bauteilen; Teil 1 Baustoffe, Begriffe, Anforderungen und Priifungen (Behaviour of building materials and components in fire; building materials, definitions, requirements and tests) DIN 4102 DIN Brandverhalten von Baustoffen und Bauteilen; Teil 2 Begriffe, Anforderungen und Priifungen (Behaviour of building materials and components in fire; building components, definitions, requirements and tests) DIN 4102 DIN Brandverhalten von Baustoffen und Bauteilen; Teil 3 Brandwande und nichttragende AuBenwande, Begriffe, Anforderungen und Priifungen (Behaviour of building materials and components in fire; firewalls and non loadbearing external walls, definitions, requirements and tests)
Pub
79
Pub Pub
78 76
Pub Iss
65 9 76
Pub
4.77
Pub
4.77
Drf
178
Drf
4.79
Drf
4.79
Drf
4 79
Pub
2.78
Pub
9.77
Pub
9 77
Pub
9.77
107
7.4.3 No.
Issuing Body (Country)
DIN 4102 Teil 4
DIN
DIN 4102 Teil 4
DIN
DIN 4102 Teil 5
DIN
DIN 4102 Teil 6
DIN
DIN 4102 Teil 7
DIN
DIN 4102 Teil 8
DIN
DIN 14675
DIN
DIN 18230 Teil 1
DIN
DIN 18230 Teil 1 Bbl 1
DIN
DIN 18230 Teil 2
DIN
DIN 18232 Teil 1
DIN
IAEA 50-SG-D2 IAEA50-SG-S5
IAEA IAEA
•
IfBT
ISO 3956
ISO
RDTM 17-1T
ORNL
NUREG-75/087
USNRC
108
Title (Remarks) Brandverhalten von Baustoffen und Bauteilen; Einreihung in die Begriffe (Behaviour of building materials and structures in fire; classification with respect to definitions) Brandverhalten von Baustoffen und Bauteilen; Zusammenstellung und Anwendung klassifizierter Baustoffe, Bauteile und Sonderbauteile (Behaviour of building materials and components in fire; synopsis and application of classified building materials, building components and special building components (with respect to their definitions)) Brandverhalten von Baustoffen und Bauteilen; Feuerschutzabschliisse, Abschlusse in Fahrschachtwanden und gegen Feuer widerstandsfahige Verglasungen, Begriffe, Anforderungen und Prufungen (Behaviour of building materials and components in fire; firebarriers, barriers in lift wells and against fire resistant glazings, definitions, requirements and tests) Brandverhalten von Baustoffen und Bauteilen; Luftungsleitungen, Begriffe, Anforderungen und Prufungen (Behaviour of building materials and components in fire; ventilation ducts, definitions, requirements and tests) Brandverhalten von Baustoffen und Bauteilen; Bedachungen, Begriffe, Anforderungen und Prufungen (Behaviour of building materials and components in fire; roofing, definitions, requirements and tests) Brandverhalten von Baustoffen und Bauteilen; Kleinpriifstand (Behaviour of building materials and components in fire; small test furnace) Brandmeldeanlagen; Aufbau (Fire Alarm Systems; Design, Erection) Baulicher Brandschutz im Industriebau; Erforderliche Feuerwiderstandsdauer (Fire safety in industrial construction; necessary durability of fire resistance) Baulicher Brandschutz im Industriebau; Erforderliche Feuerwiderstandsdauer, Abbrandfaktoren m und Heizwerte (Fire safety in industrial construction; necessary durability of fire resistance, burning factors m and calorific potentials) Baulicher Brandschutz im Industriebau; Ermittlung des Abbrandfaktors m (Fire safety in industrial construction; determination of the burning factor m) Baulicher Brandschutz; Rauch- und Warmeabzugsanlagen, Begriffe und Anwendung (Fire safety in building; smoke and heat control installations, terms and application) Fire Protection in Nuclear Power Plants Extreme Man-Induced Events in Relation to Nuclear Power Plant Siting Bau- und Prufgrundsatze fur Absperrvorrichtungen gegen Feuer und Rauch in Luftungsleitungen, Institut fur Bautechnik Principles of Structural fire-Engineering Design with Special Regard to the Connection Between Real Fire Resistance Test Sodium Carbonate, Low-Chloride Fire Extinguishing Agent USNRC-Standard Review Plan, Section 9.5.1 "Fire Protection System"
Status Pub
2.70
Drf
3.78
Pub
9.77
Pub
9.77
Pub
9.77
Drf
9.77
Pub
4.79
Drf
8.78
Drf
8.78
Drf
8.78
Drf
8.78
Pub Ust
79
Pub
12.71
Drf
11.75
Pub 12.73 Amm 4.74 Iss 5.76
7.4.3 No.
Issuing Body (Country)
R.G. 1.7
USNRC
R.G. 1.78
USNRC
R.G 1.91
USNRC
R.G. 1.120 R.G 3 7
USNRC USNRC
R.G. 3.16
USNRC
R.G. 3.38
USNRC
* FJGBI. I, S 173
VDS (DEU)
BGBI. I, S. 173
(DEU)
Title (Remarks) Control of Combustible Gas Concentrations in Containment Following a Loss of Coolant Accident Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants (Issued for Comments) Fire Protection Guidelines for Nuclear Power Plants Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants General Fire Protection Guide for Fuel Reprocessing Plants (Issued for Comments) Richtlinien fur den Brandschutz in Kernkraftwerken Verordnung zur Ablosung von Verordnungen nach S 24 der Gewerbeordnung vom 27.2.1980; Artikel 6 Verordnung iiber Anlagen zur Lagerung, Abfiillung und Beforderung brennbarer Flussigkeiten zu Lande (Verordnung uber brennbare Flussigkeiten - VbF) Verordnung zur Ablosung von Verordnungen nach §24 der Gewerbeverordnung vom 27.2.1980; Artikel 4 Verordnung iiber elektrische Anlagen in explosionsgefahrdeten Raumen (ElexV)
Status Iss
11.78
Iss
6.74
Iss
2.78
Iss Iss
11.77 3.73
Iss
1.74
Iss
6.76
Iss Iss
9.76 2 80
Iss
2.80
109
7.4.4 No.
Issuing B o d y (Country!
Title (Remarks)
Status
Plant and Reactor P r o t e c t i o n 7.4
Plant Protection
7.4.4 E m e r g e n c y Plans ANHMRC Emergency Reference Levels for Major Radiation • Accidents ANS-2.12 ANS Guidelines for Combining Natural Phenomena and Man-Made Hazards at Power Reactor Sites ANS-3.7.1 ANS Facilities and Medical Care for on Site Nuclear Power Plant Radiological Emergencies ANS-3.7.2 ANS Emergency Control Centers for Nuclear Power Plants ANS-3.7.3 ANS Radiological Emergency Preparedness Drills for Nuclear Power Plants ANS-15.16 ANS Emergency Planning for Research Reactors ANS-58.3 ANS Physical Protection for Systems and Components /ANSI N182 Important to Safety ANSI N2.3 ANSI Immediate Evacuation Signal for Use in Industrial Installations ANSI N13.3 ANSI Dosimetry for Criticality Accidents ANSI N320 ANSI Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation GMBI. 1977 S. 48 BMI Empfehlungen zur Planung von NotfallschutzmaBnahmen durch Betreiber von Kernkraftwerken vom 27.12.1976 (See also GMBI. 1977 S. 664) GMBI. 1977 S. 664 Anderung der Empfehlungen zur Planung von BMI NotfallschutzmaBnahmen durch Betreiber von Kernkraftwerken vom 18.10.1977 (See also GMBI. 1977 S. 48) GMBI. 1977 S. 683 BMI Rahmenempfehlungen fur den Katastrophenschutz in der Umgebung kerntechnischer Anlagen vom 17.10.1977 Umwelt Nr. 61/78 BMI Leitsatze fur die Unterrichtung der Qffentlichkeit iiber die Katastrophenschutzplanung in der Umgebung von kerntechnischen Anlagen vom 10.2.1978 IAEA 50-SG-D7A IAEA Emergency Electrical Power Systems at Nuclear Power Plants IAEA 50-SG-G6 IAEA Preparedness of Public Authorities for Emergencies at Nuclear Power Plants IAEA50-SG-S4 IAEA Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution IAEA 50-SG-06 IAEA Preparedness of the Operating Organization for Emergencies at Nuclear Power Plants IEEE 497 IEEE Trial-Use Standard Criteria for Post Accident Monitoring Instrumentation for Nuclear Power Generating Stations GSN-06 JEN Plan de Emergencia en Centrales Nucleares de Potencia (Emergency Plan for Nuclear Power Plants). Publ. 4 NARS Internal Emergency Plan Requirements and Recommendations for the Internal Emergency Plan for Stationary Nuclear Power Plants NARS Construction Site Emergency Precautions, Guidelines Publ. 5 for Information on Internal Emergency Precautions related to a Major Construction Work on a Nuclear Power Plant Site with Reactor(s) in Operation NCRP Report No.55 NCRP Protection of the Thyroid Gland in the Event of Release of Radioiodine R.G. 1.3 USNRC Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors 110
Iss Pub Drf
73 78 10.78
Pub Pub
79 79
Pub Pub
78 77
Pub
67
Pub Pub
69 79
Iss
12.76
Iss
10.77
Iss
10.77
Iss
2.78
Ust Ust Ust Ust Pub
77
Iss
2.79
Pub
6.75
Pub
6.75
Pub
77
Iss
6.74
7.4.4 No.
Issuing B o d y (Country)
R.G. 1.4
USNRC
R.G. 1.5
USNRC
R.G. 1.24
USNRC
R.G. 1.25
USNRC
R.G. 1.52
USNRC
R.G. 1.70.14
USNRC
R.G 179
USNRC
R.G. 1.81
USNRC
R.G. 1.82
USNRC
R.G. 1.93 R.G. 1.95
USNRC USNRC
R.G 1.97
USNRC
R.G. 1.98
USNRC
R.G. 1.101
USNRC
R.G. 1.102 R.G. 1.113
USNRC USNRC
R.G. 1.145
USNRC
R.G. 2.6
USNRC
R.G 3 33
USNRC
R.G. 3 34
USNRC
R G. 3.35
USNRC
Title
Status
(Remarks)
Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5/ Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Gas Storage Tank Failure (Safety Guide 24/ Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25; Under Revision) Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light-Water-Cooled Nuclear Power Plants Information for Safety Analysis Reports - Emergency Planning (See also R G 1.70) Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants Sumps for Emergency Core Cooling and Containment Spray Systems Availability of Electric Power Sources Protection of Nuclear Power Plant Control Room Operators Against an Accidential Chlorine Release Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (Issued for Comments) Emergency Planning for Nuclear Power Piants (Under Revision) Flood Protection for Nuclear Power Plants Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Release for the Purpose of Implementing Appendix I Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (Issued for Comments) Emergency Planing for Research Reactors (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant
Iss
6 74
Iss
3.71
Iss
3 72
Iss
3.72
Iss
3.78
Iss
75
Iss
9.75
Iss
1.75
Iss
6.74
Iss Iss
12.74 1.77
Iss
8.77
Iss
3.76
Iss
3.77
Iss Iss
9.76 4.77
Iss
8.79
Iss
1.79
Iss
4.77
Iss
7.79
Iss
7.79
111
7.4.4 No. R.G. 3.42
Issuing Body (Country)
USNRC
R.G. 8.5 USNRC 10 CFR 50 Appendix E USNRC VdTUVWei 23
112
VdTUV
Title
Status
(Remarks)
Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70 Immediate Evacuation Signal Emergency Plans for Production and Utilization Facilities Verhinderung von zündfahigen Wasserstoffkonzentrationen in der Sicherheitsbehalteratmosphare von Kernkraftwerken mit Druckwasserreaktoren nach einem Kuhlmittelverluststorfall
Iss
9.79
Iss
2.73
Iss
10 78
8.1 No. 8
Issuing Body (Country)
Title
Status
(Remarks)
Reactor Physics
8.1 Core and Core C o m p o n ents Boiler and Pressure Vessel Code; Division I: B PVC Sec.lll Div.l ASME Subsection NB - Class 1 Components. Subsection NC • Class 2 Components, Subsection ND Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG - Core Support Structures, Appendices (Regular Addenda and Revisions Provided) Richtlinien iiber die in atomrechtlichen GMBI. 1977 S 108 BMI Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber den Reaktorkern sowie die Steuer- und Abschaltsysteme vom 22 3.1977 DIN 25437 Auslegung der Reaktorkerne von gasgekiihlten DIN Teil 1 Hochtemperaturreaktoren; Berechnung der Helium-Stoffwerte, Sicherheitstechnische Anforderungen (Reactor Core Design for High-Temperature-Gas Cooled Reactors; Calculation of the Properties of Helium, Safety Requirements) (Identical with KTA 3102 I) Neutronengeneratoren GOST GOST 19353 IAEA Core Management, Fuel Handling and Associated IAEA 50-SG-010 Services Auslegung der Reaktorkerne von Druck- und KTA 3101 1 KTA Siedewasserreaktoren Teil 1: Thermohydraulische Auslegung (Reactor Core Design for Pressurized Water and Boiling Water Reactors Part 1: Thermo-hydraulic Design) Auslegung der Reaktorkerne von gasgekiihlten KTA KTA 3102.1 Hochtemperaturreaktoren Teil 1: Berechnung der Helium-Stoffwerte (Reactor Core Design for High-Temperature Gas-Cooled Reactors Part 1: Calculation of the Properties of Helium) (Available also in English; Identical with DIN 25437 Teil 1} Auslegung der Reaktorkerne von gasgekiihlten KTA KTA 3102.3 Hochtemperaturreaktoren Teil 3: Reibungsdruckverlust in Kugelhaufen (Reactor Core Design for High-Temperature Gas-Cooled Reactors Part 3; Frictional-pressure-Loss in pebble-bed) RDT E 6-1T ORNL Near-lsotropic Petroleum-Coke Based Graphites for High Temperature Gas-Cooled Reactor Core Components RDT E 6-5T ORNL Collapsible-Rotor, Roller-Nut Control Rod Drive Mechanism for Sodium Service RDT E 6-19T ORNL Radial Reflector Assembly for Liquid Metal Fast Breeder Reactors RDT E 6-20T ORNL Austenitic Stainless Steel Hexagonal Duct Tubes for Core Components and Assemblies RDT E 6-24T ORNL Interim Decay Storage for Sodium-Cooled Reactors RDT E 6-38T ORNL Low Friction Hard Surfaces for Core Components RDT E 6-40T
ORNL
R.G. 1.20
USNR
R.G. 1.70.12
USNR
Piston Rings of High Strength Alloys for Core Components for Liquid Metal Service Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing Information for Safety Analysis Reports - Reactor Material (See also R.G. 1.70)
Iss
74
Iss
377
Pub
7 79
Pub
74
Pub
2 80
Pub
6.78
Drf
10.80
Pub
10 77
Pub Amm Pub
3 71 9 74 3 78
Pub
5.76
Pub Pub Amm Pub
4 73 5 73 973 5.74
Iss
576
Iss
75
113
8.1 No.
Issuing Body (Country)
R.G. 1.82
USNRC
R.G. 1.124
USNRC
Task No. SC 521-4
USNRC
114
Title
Status
(Remarks)
Sumps for Emergency Core Cooling and Containment Spray Systems Service Limits and Loading Combination for Class I Linear Type Component Supports LWR Core Reloads; Guidance on Applications for Amendments to Operating Licenses and on Refueling and Startup Tests (Proposed /?. G.)
Iss
6 74
Iss
1.78
Iss
9.79
8.2 No. 8
Issuing Body (Country)
Status
Title
(Remarks)
Reactor Physics
8.2 Critical Experiments, C, ANS ANS-1 /ANSI N405 ANS ANS-5.1 /ANSI N18.6 ANS ANS-61.1 /ANSI N666 ANS ANS-19.1 /ANSI N411 ANS ANS-19.4 /ANSI N652 ANS-19.5
ANS
DIN 25401 Teil 2 DIN 25401 Teil 3
DIN
DIN 25405
DIN
DIN 25437 Teil 1
DIN
KTA 3101.1
KTA
KTA 3102.1
KTA
KTA 3102.3
KTA
RDT E 6-25T
ORNL
RDT E 6-33T
ORNL
DIN
RDT E 16-1T
ORNL
VDI 3528
VDI
Safety Guide for the Performance of Critical Experiments Decay Energy Release Rates Following Shutdown of Uranium-Fueled Thermal Reactors Neutron and Gamma-Ray Flux-to-Dose-Rate Factors
App
75
Pub
10.79
Pub
77
Nuclear Data Sets for Reactor Design Calculations
App
75
A Guide for Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification Requirements for Reference Reactor Physics Measurements Kerntechnik; Begriffe, Reaktorauslegung (Nuclear Technology; Terms and Definitions, Reactor Design) Kerntechnik; Begriffe, Reaktortechnik und Betrieb (Nuclear Technology; Terms and Definitions, Reactor Technology and Operation) Gesichtspunkte fur eine sichere Auslegung von thermischen Reaktoren bezuglich des Reaktivitatsverhaltens (Aspects of a Safe Design of Thermal Reactors with Regard to their Reactivity Behaviour) Auslegung der Reaktorkerne von gasgekiihlten Hochtemperaturreaktoren; Berechnung der Helium-Stoffwerte, Sicherheitstechnische Anforderungen (Reactor Core Design for High-Temperature-Gas Cooled Reactors; Calculation of the Properties of Helium, Safety Requirements) (Identical with KTA 3102.1) Auslegung der Reaktorkerne von Druck- und Siedewasserreaktoren Teil 1: Thermohydraulische Auslegung (Reactor Core Design for Pressurized Water and Boiling Water Reactors Part 1: Thermo-hydraulic Design) Auslegung der Reaktorkerne von gasgekiihlten Hochtemperaturreaktoren Teil 1: Berechnung der Helium-Stoffwerte (Reactor Core Design for High-Temperature Gas-Cooled Reactors Part 1: Calculation of the Properties of Helium) (Available also in English; Identical with DIN 25437 Teil 1) Auslegung der Reaktorkerne von gasgekiihlten Hochtemperaturreaktoren Teil 3; Reibungsdruckverlust in Kugelhaufen (Reactor Core Design for High-Temperature Gas-Cooled Reactors Part 3: Frictional-pressure-Loss in pebble-bed) Control Rod Absorber Pin for Liquid Metal Fast Reactors Control Rod Assembly for Liquid Metal Fast Breeder Reactors Test Vehicles for Transient Reactor Test Facility (TREAT) Experiments Containing Sodium Regelung und Steuerung von Kernreaktoren; Spezielle Begriffe und Benennungen
App
76
Pub
78
Drf
279
Drf
2.79
Pub
670
Pub
779
Pub
2.80
Pub
6.78
Drf
10.80
Pub Amm Pub Amm Pub
9.76 1.77 3.77 6.78 8.74
Pub
9.72
115
8.3 No. 8
Issuing Body (Country)
(Remarks)
Reactor Physics
8.3 Reactivity C o n t r o l , Shut- d o w n S y s t e m s The Determination of Neutron Reaction Rate ANS ANS-19.3 Distributions and Reactivity of Nuclear Reactors /ANSI N412 Criteria for Remote Shutdown for LWRs ANS ANS-58.6 (Combination ofANS-51.9 and ANS-52.5) Reporting Irradiation Results on Graphite ASTM ASTM C 625 (Under Revision) /ANSI K90.8 Estimating the Thermal Neutron Absorption cross ASTM ASTM C 626 /ANSI K90.10 Section of Nuclear Graphite Recommended Practice for Testing Graphite and ASTM ASTM C 781 /ANSI N590 Boronated Graphite for HTGR's Practice for Reporting Dosimetry Results on Nuclear ASTM ASTM E 525 Graphite GMBI. 1977 S. 108 BMI Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber den Reaktorkern sowie die Steuer- und Abschaltsysteme vom 22.3.1977 MCH/MENT 10 CEA Caracteristiques et methodes d'essais des reactimetres DIN 25405 DIN Gesichtspunkte fur eine sichere Auslegung von thermischen Reaktoren bezuglich des Reaktivitatsverhaltens (Aspects of a Safe Design of Thermal Reactors with Regard to their Reactivity Behaviour) DIN DIN 25442 Ermittlung der Abschaltreaktivitat; Sicherheitstechnische Anforderungen (Evaluating of the Shutdown Reactivity; Safety Requirements) (Identical with KTA 3104) GOST GOST 17605 Kernreaktoren; Automatisierte Kontroll- und Steuersysteme GOST GOST 21935 Systeme fur die Reaktorinnenkontrolle; Klassifikationskriterien KTA KTA3104 Ermittlung der Abschaltreaktivitat (Evaluation of Shutdown Reactivity) (Identical with DIN 25442) SIS SS-4369003 Karnenergianlaggningar - Reaktoravstallning da det centrala kontrollrummet ar otillgangligt (Nuclear power stations - Reactor shutdown without access to the main control room) R.G. 1.68.2 USNRC Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants USNRC R.G. 1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors USNRC R.G. 1.81 Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants VDI VDI 3527 Kernreaktor-Regelung; Sinnbilder VDI VDI 3528 Regelung und Steuerung von Kernreaktoren; Spezielle Begriffe und Benennungen VdTUV VdTOVWei 11 Sicherstellung ausreichender Abschaltreaktivitat bei Leichtwasserreaktoren VdTUV VdTUV Wei 24 Auslegung von Steuerstabsteuerungen in Leichtwasserreaktoren
116
Status
Title
App Drf
75 2.79
Pub
72
Pub Rev Pub
71 77 77
Pub
74
Iss
3.77
Pub
76
Pub
670
Pub
6.80
Pub
72
Pub
76
Pub
10.79
Pub
180
Iss
7.78
Iss
5.74
Iss
1.75
Pub Pub
5.67 9.72
Iss
3.77
Iss
11.78
8.4 No. 8
Issuing Body (Country)
Title
Status
(Remarks)
Reactor Physics
8.4 N e u t r o n Flux M e a s u r e m ents ANS Neutron and Gamma-Ray Flux-to-Dose-Rate Factors ANS-6.1.1 /ANSI N666 ANS-8.6 Safety in Conducting Subcritical ANS /ANSI N16.3 Neutron-Multiplication Measurements In-Situ (Revision of ANSI N16.3-1969) The Determination of Neutron Reaction Rate ANS-193 ANS /ANSI N412 Distributions and Reactivity of Nuclear Reactors ANS-19.3.4 ANS The Determination of Thermal Energy Deposition /ANSI N676 Rates in Nuclear Reactors ANS-195 ANS Requirements for Reference Reactor Physics Measurements ANSI N343 ANSI Internal Dosimetry Techniques for Fission and Activation Products ANSI PTC 32.2 ANSI Methods of Measuring the Performance of Nuclear Reactor Fuel in Light Water Reactors ASTM E 262 ASTM Determining Thermal Neutron Flux by Radioactivation Techniques ASTM E 263 ASTM Determining Fast-Neutron Flux by Radioactivation of Iron ASTM E 264 ASTM Determining Fast-Neutron Flux by Radioactivation of Nickel ASTM E 265 ASTM Determining Fast-Neutron Flux by Radioactivation of Sulfur ASTM E 266 ASTM Determining Fast-Neutron Flux by Radioactivation of Aluminium ASTM E 343 ASTM Test for Fast-Neutron Flux by Analysis of Molybdenum-99 Activity from Uranium-238 Fission ASTM E 393 ASTM Measuring Fast-Neutron Flux by Analysis of Barium-140 Produced by Uranium-238 Fission ASTM E 402 ASTM Measuring Fast-Neutron Flux by Radioactivation of Titanium ASTM ASTM E418 Fast-Neutron Flux Measurements by Track-Etch Technique ASTM E 481 ASTM Neutron Flux Density by Radioactivation of Cobalt and Silver, Measuring ASTM E 496 ASTM Test for Neutron Flux Density and Average Energy from 3H(d,n)4He Neutron Generators by Radioactivation Techniques ASTM E 523 ASTM Test for Fast-Neutron Flux Density by Radioactivation BS 5552 BSI Code of Practice for In-Core Instrumentation for Neutron Fluence Rate (Flux) Measurements in Power Reactors IEC 568 IEC In-Core Instrumentation for Neutron Fluence Rate (Flux) Measurements in Power Reactors MSZ 14350 MSZH Neutron Flux Density Measurement with Long Counter MSZ 14353 MSZH Neutron Flux Density Measurement by Activation Method for Radiation Protection Purposes NCRP Report N 0.25 NCRP Measurement of Absorbed Dose of Neutrons and of Mixtures of Neutrons RDT C 10-3T ORNL Multiple Input Preamplifier/Discriminator for Use with Neutron Counters RDT C 15-2T ORNL Wide-Range (10 Decade) Neutron Flux Monitoring Channel RDT C 15-3T ORNL Current Pulse Preamplifiers for Use with Fission Counters
Pub
77
App
75
App
75
App
76
Pub
78
Pub
78
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub Rev Pub
72 78 73
Pub
76
Pub
73
Pub
78
Pub
73
Pub
76
Pub
78
Pub
77
Pub
78
Pub
79
Pub
61
Pub
12.75
Pub
2.71
8.71 Pub Amm 10.74
117
8.4 No. RDTC 15-5T
Issuing Body (Country)
Title
ORNL
Fission Type Neutron Detector Assembly
RDT C 15-6T
ORNL
RDTC 15-7T
ORNL
RDTC 15-8T
ORNL
RDT C 15-10T
ORNL
RDTC 15-11T R.G. 8.26
ORNL USNRC
Logarithmic Mean Square Voltage (MSV) Intermediate Range Neutron Flux Monitoring System Gamma Compensated Ionization Chamber Assembly (Fixed Electrical Compensation) Direct Current Power Range Neutron Flux Monitoring System Logarithmic Count Rate Source Range Neutron Flux Monitoring System BF 3 Gamma Tolerant Neutron Detector Tubes Application of Bioassay for Fission and Activation Products
118
Status
(Remarks)
Pub 12 71 Amm 10.73 Pub 7.71 Pub Amm Pub
7.71 3.74 7.71
Pub
7.71
Pub Iss
12.75 9.80
8.5 No. 8
Issuing Body (Country)
Title
Status
(Remarks)
Reactor Physics
8.5 Fuel Elements and A s s e m b l i e s ANS-15.2 ANS Quality Control for Plate-Type Uranium-Aluminium /ANSI N398 Fuel Elements HTGR New Fuel Facilities ANS-53.17 ANS ANS-54.2 ANS Design Bases for Ex-Vessel Storage Facilities for LMFBR Spent Fuel ANS-57.2 Design Objectives for Light Water Reactor Spent ANS /ANSI N210 Fuel Facilities at Nuclear Power Stations ANS-57.5 Light Water Reactors Fuel Assembly Mechanical ANS Design and Evaluation Fuel Assembly Identification ANS-578 ANS Methods of Measuring the Performance of Nuclear Reactor Fuel in Light Water Reactors Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear Grade Boron Carbide Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear Grade Aluminium Oxide and Aluminium Oxide-Boron Carbide Composite Pellets Design and Quality Assurance Practices for Nuclear Fuel Rods Recommended Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties Kerntechnische Anlagen; Lagerbecken fur Brennelementbiindel von wassergekiihlten Leistungsreaktoren (Nuclear Facilities; Pool Facility for Fuel Assemblies for Watercooled Power Reactors) Kennzeichnung von Brennelementen fur Leistungsreaktoren (Fuel Assembly Identification for Nuclear Power Reactors) Quality Assurance in the Procurement, Design and Manufacture of Nuclear Fuel Assemblies Core Management, Fuel Handling and Associated Services Control Rod Absorber Pin for Liquid Metal Fast Reactors Absorber Pin Boron Carbide Pellet Control Rod Assembly for Liquid Metal Fast Breeder Reactors Shielded Shipping Cask for Spent Reactor Fuel Elements Fast Flux Test Facility Ceramic Grade Plutonium Dioxide Ceramic Grade Uranium Dioxide
ANSI PTC 32 2
ANSI
ASTM C 791
ASTM
ASTM C 809
ASTM
ASTM C 934
ASTM
ASTM E 560
ASTM
DIN 25428
DIN
DIN 25433
DIN
IAEA 50-SG-QA11
IAEA
IAEA 50-SG-010
IAEA
RDT E 6-25T
ORNL
RDT E 6-30T RDT E 6-33T
ORNL ORNL
RDT E 12-4T
ORNL
RDTE 13-1T
ORNL
RDTE 13-2T
ORNL
RDT E 13-5T RDT E 13-6T
ORNL ORNL
RDT E 13-7T RDT E 13-8T
ORNL ORNL
RDT E 13-9T RDT E 13-10T RDTE 13-11T RDT E 13 12T RDT E 13-13T RDTE 13-15T
ORNL ORNL ORNL ORNL ORNL ORNL
Fast Flux Test Facility Driver Fuel Pin Fast Flux Test Facility Driver Fuel Pin Mixed Oxide Fuel Pellet Fast Flux Test Facility Driver Fuel Pin Insulator Pellet Fast Flux Test Facility Driver Fuel Pin Seamless Cladding Tube Fast Flux Test Facility Driver Fuel Pin End Caps Fast Flux Test Facility Driver Fuel Pin Reflectors Fast Flux Test Facility Driver Fuel Pin Plenum Spacer Fast Flux Test Facility Driver Fuel Pin Plenum Spring Fast Flux Test Facility Driver Fuel Pin Wrap Wire Fuel Assemblies for Pressuri zed Water Reactors
RDT E 13-16T
ORNL
Driver Fuel Assembly
App
74
Ust Ust App
76
Pub
78
Pub Rev
78 10.79
Pub
75
Pub
76
Pub
80
Pub
72
Pub
876
Pub
7.78
Ust
Pub 976 Amm 1 77 Pub 9.76 377 Pub Amm 678 Pub 873 Amm 1273 671 Pub 671 Pub Amm 1274 Pub 6.71 Pub 671 Amm 12.74 671 Pub Pub 6.71 Pub Pub Pub Pub Pub Pub Amm Pub
671 6.71 6.71 6.71 6.71 7.71 5.72 977 119
8.5 No.
Issuing Body (Country)
RDT F 11-4T
ORNL
RDT F 11-5T
ORNL
RDT F 11-6T
ORNL
RDT M 14-2T R.G. 1.13
ORNL USNRC
R.G. 1.70.34
USNRC
R.G. 1.119
USNRC
R.G. 1.126
USNRC
R.G. 2.3
USNRC
R.G. 3.24
USNRC
R.G. 5.1
USNRC
VdTUV Wei 28
VdTUV
120
Title
Status
(Remarks)
Determination of a Figure of Merit for Pu02-U02 Fuel Pellet Homogeneity by Use of an Electron Microprobe Determination of Fuel Pellet Homogeneity by Alpha-Autoradiography Ceramographic Preparation of Mixed Oxide Fuel Pellets Fuel and Control Assembly Tag Gas Spent Fuel Storage Facility Design Basis (Issued for Comments) Information for Safety Analysis Reports - Fuel Systems Design (See also R.G. 1.70) Surveillance Program for New Fuel Assembly Designs (Withdrawn 6.77) An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification Quality Verification for Plate-Type Uranium-Aluminium Fuel Elements for Use in Research Reactors Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation Serial Numbering of Light-Water Power Reactor Fuel Assemblies Lagerung von Brennelementbundeln im Lagerbecken wassergekuhlter Leistungsreaktoren (see also DIN 25428)
Pub
9.72
Pub
5.75
Pub
1.73
Pub Iss
10.72 12.75
Iss
5.75
Iss
3.78
Iss
7.76
Iss
12.74
Iss
12.72
Iss
11.79
8.6 No. 8
Issuing B o d y (Country)
Title (Remarks)
Status
Reactor Physics
8.6 Research Reactors ANS ANS-14.1 /ANSI N394 ANS ANS-15.1 /ANSI N378 ANS ANS-15.3 /ANSI N399 ANS ANS-15.4
Operation of Fast Pulse Reactors
App
75
Standard for the Development of Technical Specifications for Research Reactors Records and Reports for Research Reactors
App
74
App
74
Pub
77
App
74
ANS-15.6 /ANSI N401 ANS-15.7 /ANSI N379 ANS-15.8 /ANSI N402 ANS-15.11 /ANSI N628 ANS-15.12 /ANSI N647 ANS-15.15
ANS
Standard for Selection and Training of Personnel for Research Reactors Review of Experiments for Research Reactors
ANS
Siting for Research Reactors
Pub
77
Quality Assurance Program Requirements for Research Reactors Radiological Control at Research Reactor Facilities
App
76
Pub
77
Pub
77
Pub
78
ANS-15.16 ANS-15.18
ANS ANS
Pub Pub
78 79
BMI RS I-6/76
BMI
GMBI. 1980 S 92
BMI
R.G. 2.1
USNRC
R.G. 2.2
USNRC
Design Objectives for and Monitoring of Systems Controlling Research Reactor Effluents Criteria for the Reactor Safety Systems of Research Reactors Emergency Planning for Research Reactors Standard for Administrative Controls for Research Reactors Richtlinie fur den Fachkundenachweis von Forschungsreaktorpersonal vom 18.3.1976 Richtlinie fur den Inhalt der Fachkundepriifung des verantwortlichen Schichtpersonals in Forschungsreaktoren vom 30.11.1979 Shield Test Program for Evaluation of Installed Biological Shielding in Research and Training Reactors Development of Technical Specifications for Experiments in Research Reactors Quality Verification for Plate-Type Uranium-Aluminium Fuel Elements for Use in Research Reactors Review of Experiments for Research Reactors Quality Assurance Program Requirements for Research Reactors Emergency Planing for Research Reactors (Issued for Comments)
ANS ANS ANS ANS
R.G. 2.3
USNRC
R.G. 2.4 R.G. 2.5
USNRC USNRC
R.G. 2.6
USNRC
Iss
3.76
Iss
11.79
Iss
5.73
Iss
11.73
Iss
776
Iss Iss
5.77 10.77
Iss
1.79
121
9.1 No. 9
Issuing B o d y (Country)
Title (Remarks)
Safety and Risk Analysis
9.1 General A s p e c t s of Safety and Reliability Analysis ANS-2.10 ANS Guidelines for Retrieval, Review, Processing and Evaluation of Records Obtained from Seismic Instrumentation ANS-15.15 ANS Criteria for the Reactor Safety Systems of Research Reactors ANS-18.20 ANS Nuclear Plant Reliability Data Collection Reporting /ANSI N524 ANS-54.6 ANS LMFBR Safety Classification and Related Requirements (Draft for Comments) ANS Single Failure Criteria for Light Water Reactor Safety ANS-58.9 Related Fluid Systems (Revision of ANS 51.7 and ANSI N6S8) BAnz. Nr. 206/77 BMI Sicherheitskriterien fur Kernkraftwerke vom 21.10.1977 BMI Richtlinien uber die Anforderungen an GMBI. 1976 S. 199 Sicherheitsspezifikationen fur Kernkraftwerke vom 27.4.1976 BMI Merkpostenaufstellung mit Gliederung fur einen GMBI. 1976 S. 418 Standardsicherheitsbericht fur Kernkraftwerke mit Druckwasserreaktor oder Siedewasserreaktor vom 26.7.1976 BMI Interpretation zu den Sicherheitskriterien fur GMBI. 1978 S. 631 Kernkraftwerke, Einzelfehlerkonzept, vom 26.10.1978 GMBI. 1979 S. 161 BMI Interpretationen zu den Sicherheitskriterien fur Kernkraftwerke vom 17.5.1979 1. Interpretation zu dem Sicherheitskriterium 2.6: "Einwirkungen von auBen" 2. Interpretation zu dem Sicherheitskriterium 8.5: "Warmeabfuhr aus dem SicherheitseinschluB" GMBI. 1980 S. 90 BMI Interpretationen zu den Sicherheitskriterien fur Kernkraftwerke vom 28.11.1979 1. Interpretation zu dem Sicherheitskriterium 2.2: "Prufbarkeit" 2. Interpretation zu dem Sicherheitskriterium 2.3: "Strahlenbelastung in der Umgebung" 3. Interpretation zu dem Sicherheitskriterium 2.6: "Einwirkungen von auBen" 4. Interpretation zu dem Sicherheitskriterium 2.7: "Brand- und Explosionsschutz" 5. Interpretation zu dem Sicherheitskriterium 4.3: "Nachwarmeabfuhr nach Kuhlmittelverlusten" Umwelt Nr. 43/75 BMI Bewertungsdaten fur die Eigenschaften von Kernkraftwerksstandorten aus der Sicht von Reaktorsicherheit und Strahlenschutz vom 11.6.1975 DD 13 BSI Guide on the Assessment of Reliability of Engineering Equipment and Parts DD 15 BSI Guide on the Production, Flow, Analysis and Interpretation of Reliability data for Engineering Equipment and Parts DD 16 BSI Guide on the Reliability of Engineering Equipment and Parts. Practical examples of DD 10 to DD 15 M 62-101 CEA Principes fondamentaux de protection dans la conception et la construction des installations dans lesquelles sont utilisees des sources radioactives non scellees (Basic Principles for Safety in the Design and Construction of Installations in wich Unsealed Radioactive Sources are Used)
122
Status
Pub
79
Pub
78
App
76
Drf Pub
1.79 79
Iss
10.77
Iss
4.76
Iss
7.76
Iss
10.78
Iss
5.79
Iss
11.79
Iss
6.75
Pub
74
Pub
74
Pub
76
Pub
8.70
9.1 No.
Issuing Body (Country)
DIN 25419 Teil 1
DIN
DIN 25419 Teil 2
DIN
DIN 25424
DIN
DIN 25448
DIN
IAEA 50-C-D
IAEA
IAEA 50-SG-D1
IAEA
IAEA 50-SG-D11 IAEA 50-SG-03
IAEA IAEA
IEEE 352 /ANSI N41.4 IEEE 379 /ANSI N41.2 IEEE 384
IEEE
IEEE 500
IEEE
IEEE 577
IEEE
ISO/DIS 6527 ISO/R 1710
ISO ISO
JIS Z8115
JIS
KTA 2201.1
KTA
Publ. 2
NARS
RDT F 2-9T
ORNL RSK RSK
LBG/1
SAAEB
R.G. 1.26
USNRC
R.G. 1.53
USNRC
R.G. 1.59 R.G. 1 60
USNRC USNRC
R.G. 1.70
USNRC
IEEE
.
IEEE
Title
Status
(Remarks)
Storfallablauf analyse; Storfallablaufdiagramm, Methode und Bildzeichen (Incident Sequence Analysis; Event Tree, Method and Graphical Symbols) Storfallablaufanalyse; Auswertung des Storfallablaufdiagramms mit Hilfe der Wahrscheinlichkeitsrechnung (Incident Sequence Analysis; Event Tree, Probabilistic Evaluation! Fehlerbaumanalyse; Methode und Bildzeichen (Fault Tree Analysis; Method and Symbols] Ausfalleffektanalyse (Failure Mode and Effects Analysis) Design for Safety of Nuclear Power Plants, Code of Practice Safety Functions and Component Classification for BWR, PWR and PTR General Design Safety Principles Operational Limits and Conditions for Nuclear Power Plants Guide for Reliability Analysis of Nuclear Power Generating Station Protection Systems The Application of Single Failure Criteria to Nuclear Power Generating Station Class 1E Systems Standard Criteria for Independence of Class 1E Equipment and Circuits Guide to Collection and Presentation of Electrical, Electronic and Sensing Component Reliability Data for NPGS Reliability Requirements in the Design and Operation of Safety Systems for Nuclear Power Generating Stations Reliability Data Exchange Fundamental Principles for Protection in the Design and Construction of Installations for Work on unsealed radioactive materials (Withdrawn 1980) Glossary of Terms Used in Reliability (Available also in English) Auslegung von Kernkraftwerken gegen seismische Einwirkungen Teil 1: Grundsatze (Design of Nuclear Power Plants Against Seismic Effects Part 1: Basic Principles) (Available also in English) Cause- Consequence Diagrams A Graphical Method for Description and Analysis of Event Sequences after Failures in Complex Process Systems Reliability Assurance RSK-Leitlinien fur Siedewasserreaktoren RSK-Leitlinien fur Druckwasserreaktoren (2. Ausgabe) Licensing of Nuclear Installations: A Guide to Requirements for Safety Assessment Quality Group Classifications and Standards for Water-, Steam- and Radio-Waste-Containing Components of Nuclear Power Plants (Issued for Comments) Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems Design Basis Floods for Nuclear Power Plants Design Response Spectra for Seismic Design of Nuclear Power Plants Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants
Pub
677
Pub
2.79
Pub
6.77
Pub
6.80
Pub
78
Pub
79
Ust Pub
79
Pub
75
Pub
77
Pub
77
Pub
78
Pub
76
Drf
80
Pub
70
Pub
6.75
Pub
675
Pub Drf Pub
6.74 9.80 1.79
Iss
5.79
Iss
2.76
Iss
6.73
Iss Iss
877 12.73
Iss
11.78
123
9.1 No.
Issuing Body (Country)
R.G. 1.70.1
USNRC
R.G. 1.70.2
USNRC
R.G. 1.70.3
USNRC
R.G. 1.70.5
USNRC
R.G. 1.70.6
USNRC
R.G. 1.70.7
USNRC
R.G. 1.70.8
USNRC
R.G. 1.70.9
USNRC
R.G. 1.70.10
USNRC
R.G. 1.70.11
USNRC
R.G. 1.70.12
USNRC
R.G. 1.70.13
USNRC
R.G. 1.70.14
USNRC
R.G. 1.70.15
USNRC
R.G. 1.70.16
USNRC
R.G. 1.70.17
USNRC
R.G. 1.70.18
USNRC
R.G. 1 70.19
USNRC
R.G. 1.70.20
USNRC
R.G. 1.70.21
USNRC
124
Title (Remarks) Hydrological Considerations for Nuclear Power Plants (See also R.G. 1.70) Additional Information: Air Filtration Systems and Containment Sumps for Nuclear Power Plants (See also R.G. 1.70) Additional Information: Radiation Protection (See also R.G. 1.70) Additional Information: Water Level (Flood) Design for Nuclear Power Plants (See also R.G. 1.70) Additional Information: Quality Assurance During Design and Construction (See also R.G. 1.70) Additional Information: Geography and Demography Considerations for Nuclear Power Plants (See also R.G. 1.70) Additional Information: Nearby Industrial Transportation and Military Facilities (See also R.G. 1.70) Additional Information: Design of Seismic Category I Structures (See also R.G. 1.70) Additional Information: Wind and Tornado Loadings (See also R.G. 1.70) Information for Safety Analysis Reports - Quality Assurance During Operations Phase (See also R.G. 1.70) Information for Safety Analysis Reports - Reactor Material (See also R.G. 1.70) Information for Safety Analysis Reports - Code Case Applicable to Reactor Coolant Pressure Boundary Components (See also R.G. 1.70) Information for Safety Analysis Reports - Emergency Planning (See also R.G. 1.70) Information for Safety Analysis Reports-Industrial Security for NPP (See also R.G. 1.70) Information for Safety Analysis Report-Missile Barrier Design Procedures (See also R.G. 1.70) Information for Safety Analysis Reports-Hydrological Engineering (See also R.G. 1.70) Information for Safety Analysis Reports Mechanical System Components (See also R.G. 1.70) Information for Safety Analysis Reports - Steam Generators (See also R.G. 1.70) Information for Safety Analysis Reports - Reactor Coolant Pressure Boundary Material and Inservice Inspection (See also R.G. 1.70) Information for Safety Analysis Reports - Reactor Vessels (See also R.G. 1.70)
Status Iss
12.73
Iss
12.73
Iss
11.74
Iss
8.74
Iss
11.74
Iss
10.74
Iss
10.74
Iss
11.74
Iss
11.74
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
75
Iss
1.75
Iss
1.75
Iss
1.75
9.1 No.
Issuing Body (Country)
R.G. 1.70.22
USNRC
R.G. 1.70.23
USNRC
R.G. 1.70.24
USNRC
R.G. 1.70.25
USNRC
R.G. 1.70.26
USNRC
R.G. 1.70.27
USNRC
R.G. 1.70.28
USNRC
R.G. 1.70.29
USNRC
R.G. 1.70.30
USNRC
R.G. 1.70.34
USNRC
R.G. 1.70.35
USNRC
R.G. 1.70.36
USNRC
R.G. 1.70.37
USNRC
R.G. 1.70.38
USNRC
R.G. 1.78
USNRC
R.G. 3.25
USNRC
R.G. 3.26
USNRC
R.G. 3.33
USNRC
R.G. 3 34
USNRC
R.G. 3.35
USNRC
10 CFR 50 Appendix K USNRC
Title (Remarks) Information for Safety Analysis Reports Instrumentation and Controls (See also R. G 1.70) Information for Safety Analysis Reports • Seismic Qualification of Instrumentation and Electrical Equipment (See also R.G. 1.70) Information for Safety Analysis Reports Environmental Design of Mechanical and Electrical Equipment, Qualification Tests and Analysis (See also R.G. 1.70) Information for Safety Analysis Reports-lnservice Inspection of ASME Code Class 2 and 3 Components (See also R. G. 1.70) Information for Safety Analysis Reports-Metallic Materials for Engineered Safety Features (See also R. G 1.70) Information for Safety Analysis Reports Radioactive Waste Management (See also R.G. 1.70/ Information for Safety Analysis Reports - Steam and Feedwater System Materials (See also R. G 1.70) Information for Safety Analysis Reports Meteorology (See also R. G 1.70) Information for Safety Analysis Reports - Pump Flywheel Integrity (See also R.G. 1.70) Information for Safety Analysis Reports - Fuel Systems Design (See also R. G 1.70/ Information for Safety Analysis Reports - Internally Generated Missiles (See also R.G. 1.70) Information for Safety Analysis Reports - Electric Power (See also R.G 1.70/ Information for Safety Analysis Reports - Pressurizer Relief Discharge System (See also R.G. 1.70/ Information for Safety Analysis Reports - Training (See also R.G. 1.70) Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant ECCS Evaluation Models
Status Iss
2.75
Iss
2.75
Iss
2.75
Iss
2.75
Iss
2.75
Iss
4.75
Iss
4.75
Iss
4 75
Iss
75
Iss
5.75
Iss
75
Iss
75
Iss
6.75
Iss
6.75
Iss
6.74
Iss
12 74
Iss
2.75
Iss
4 77
Iss
7 79
Iss
7.79
125
9.1 No. VDI 3540 Blatt 1 VdTUVWei 13
126
Issuing Body (Country)
VDI VdTUV
Title
Status
(Remarks)
Zuverlässigkeit von Meß-, Steuer- und Regelgeraten; Erfassung von Ausfalldaten Standardgliederung mit Merkposten für TuV/GRS-Gutachten fur Kernkraftwerke mit Druckoder Siedewasserreaktoren
Pub
8.75
Iss
5.77
9.2 No. 9
Issuing Body (Country}
Title (Remarks)
Status
Safety and Risk Analysis
9.2 Boiling W a t e r Reactor ANS-52.1 ANS ANS-56.4
ANS
IEC 231B
IEC
KTA 3101.1
KTA
* R.G. 1.3
RSK USNRC
R.G. 1.5
USNRC
R.G. 1.25
USNRC
R.G. 1.96
USNRC
R.G 198
USNRC
Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants Pressure and Temperature Transient Analysis for Light Water Reactor Containments (Issued for Comments) Second Supplement: Principles of Instrumentation of Direct Cycle Boiling Water Power Reactors Auslegung der Reaktorkerne von Druck- und Siedewasserreaktoren Teil 1: Thermohydraulische Auslegung (Reactor Core Design for Pressurized Water and Boiling Water Reactors Part 1: Thermo-hydraulic Design) RSK-Leitlinien fur Siedewasserreaktoren Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25; Under Revision) Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (Issued for Comments)
Pub
78
Pub
11.79
Pub
72
Pub
2 80
Drf Iss
9 80 6.74
Iss
3.71
Iss
3.72
Iss
6 76
Iss
3.76
127
9.3 No. 9
Issuing Body (Country)
Title
Safety and Risk Analysis
9.3 Pressurized W a t e r Reactor ANS-51.1 ANS Nuclear Safety Criteria for the Design of Stationary /ANSI N18.2 Pressurized Water Reactor Plants (See also ANS-518) ANS-51.7 ANS Single Failure Criteria for PWR Fluid Systems /ANSI N658 (See also ANS 58 9) ANS-518 ANS Nuclear Safety Criteria for the Design of Stationary /ANSI N18.2a Pressurized Water Reactor Plants, Section 2.2 and Section 2.3 (Revision to ANSI N18.2) ANS-51.10 ANS Design Criteria for Auxiliary Feedwater Systems for PWR Plants ANS-56.4 ANS Pressure and Temperature Transient Analysis for Light Water Reactor Containments (Issued for Comments) IEC231D IEC Fourth Supplement: Principles of Instrumentation for Pressurized Water Reactors KTA 3101.1 KTA Auslegung der Reaktorkerne von Druck-und Siedewasserreaktoren Teil 1: Thermohydraulische Auslegung (Reactor Core Design for Pressurized Water and Boiling Water Reactors Part 1: Thermo-hydraulic Design) RSK RSK-Leitlinien fur Druckwasserreaktoren (2. Ausgabe) R.G. 1.4 USNRC Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors R.G. 124 USNRC Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Gas Storage Tank Failure (Safety Guide 24) R.G. 1.25 USNRC Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25; Under Revision) R.G. 177 USNRC Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors R.G. 1.121 USNRC Bases for Plugging Degraded PWR Steam Generator Tubes VdTUV Wei 23 VdTUV Verhinderung von ziindfahigen Wasserstoffkonzentrationen in der Sicherheitsbehalteratmosphare von Kernkraftwerken mit Druckwasserreaktoren nach einem Kuhlmittelverluststorfall
128
Status
(Remarks)
App
73
App
76
App
75
App
11.79
Pub
11.79
Pub
75
Pub
2 80
Pub
1.79
Iss
6.74
Iss
3.72
Iss
3.72
Iss
5 74
Iss
8 76
Iss
10.78
9.4 No. 9
Issuing B o d y (Country)
Title (Remarks)
Status
Safety and Risk Analysis
9.4 Gas Cooled Reactor ANS-53.1 ANS /ANSI N213 ANS-53.13 ANS ANS-53.14
ANS
ANS-53.15
ANS
ANS-53.16
ANS
ANS-53.17 ANS-53.18
ANS ANS
ANS-53 21 IEC 231C
ANS IEC
IEC 231E
IEC
KTA 3102.1
KTA
KTA 3102.3
KTA
Nuclear Safety Criteria for the Design of Stationary Gas Cooled Reactor Plants Design Criteria for the Helium Purification System of Gas-Cooled Reactor Plants (Draft for Comments) Design Criteria for the Helium Storage Systems of Gas-Cooled Reactor Plants (Draft for Comments) Design Criteria for the Reactor Cooling Water System of Gas-Cooled Reaktor Plants Design Criteria for the Service Water System of Gas-Cooled Reactor Plants HTGR New Fuel Facilities GCR Plant Liquid Nitrogen System (Draft for Comments) GCR Plant Other Structures Third Supplement: Instrumentation of Gas-Cooled Graphite-Moderated Reactors Fifth Supplement: Principles of Instrumentation of High Temperature Indirect Cycle Gas Cooled Power Reactors Auslegung der Reaktorkerne von gasgekiihlten Hochtemperaturreaktoren Teil 1: Berechnung der Helium-Stoffwerte (Reactor Core Design for High-Temperature Gas-Cooled Reactors Part 1: Calculation of the Properties of Helium) (Available also in English; Identical with DIN 25437 Teil 1) Auslegung der Reaktorkerne von gasgekiihlten Hochtemperaturreaktoren Teil 3: Reibungsdruckverlust in Kugelhaufen (Reactor Core Design for High-Temperature Gas-Cooled Reactors Part 3: Frictional-pressure-Loss in pebble-bed)
Pub
78
Drf
8 78
Drf
8 78
Ust Ust Drf
8.78
Ust Pub
4.75 74
Pub
77
Pub
6 78
Drf
10.80
129
9.5 No. 9
Issuing Body (Country)
Status
(Remarks)
Safety arid Ris k Analysis
9.5 Fast Breeders ANS-54.1
ANS
ANS-54.2
ANS
ANS-54.3 ANS-54.6
ANS ANS
ANS-54.10
ANS
IEC 45A(CO)40
IEC
IEC 231G
IEC
RDT A 1-5T
ORNL
130
Title
LMFBR General Design Criteria (Draft for Comments) Design Bases tor Ex-Vessel Storage Facilities for LMFBR Spent Fuel Principal Design Criteria for LMFBR Containments LMFBR Safety Classification and Related Requirements (Draft for Comments) Probability Requirements for Accident Prevention in LMFBRs Principles of Instrumentation of Liquid-Metal Cooled Fast Reactors Seventh Supplement: Liquid-Metal Cooled Fast Reactors Purity Requirements for Operating Sodium Reactor Systems
Drf
4.77
Ust Ust Drf
1.79
Ust Drf
1.79
Pub
77
Pub
3.76
10.1 No. 10
Issuing B o d y (Country)
Status
Title (Remarks)
Pressure Boundary and C o m p o n e n t s
10.1 General and Coolant Ci rcuits Design Criteria for Auxiliary Feedwater Systems for ANS ANS-51.10 PWR Plants ANS-53.15 Design Criteria for the Reactor Cooling Water ANS System of Gas-Cooled Reaktor Plants ANS-53.16 Design Criteria for the Service Water System of ANS Gas-Cooled Reactor Plants ANS-53.19 GCR Plant Chilled Water System ANS ANS-53.20 ANS GCR Plant Secondary Coolant System ANS-563 ANS Overpressure Protection of Low Pressure Systems /ANSI N193 Connected to the Reactor Coolant Pressure Boundary ANS-58.2 Design Basis for Protection of Nuclear Power Plants ANS Against Effects of Postulated Pipe Rupture ANS-58.9 Single Failure Criteria for Light Water Reactor Safety ANS Related Fluid Systems (Revision of ANS 51 7 and ANSI N658) ANS-59.1 Safety Related Cooling Water Systems in Nuclear ANS Power Plants ASME QA-76-2.1 ASME Cleaning of Fluid Systems and Associated /ANSI N45.2.1 Components for Nuclear Power Plants (For Public Review and Comments) Boiler and Pressure Vessel Code; Division I: B PVC Sec.lll Div.l ASME Subsection NB - Class 1 Components, Subsection NC - Class 2 Components, Subsection ND Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG - Core Support Structures, Appendices (Regular Addenda and Revisions Provided) GMBI. 1977 S. 739 Richtlinien iiber die in atomrechtlichen BMI Genehmigungsverfahren fur Kernkraftwerke zur PrCifung erforderlichen Informationen iiber das Druckhalte- und Abblasesystem (DWR) vom 21.11.1977 Richtlinien uber die in atomrechtlichen GMBI 1978 S. 294 BMI Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen iiber die liiftungstechnischen Anlagen, die Not- und Nachkiihlsysteme einschliefslich Nachkiihlkette und Rohrleitungen, Pumpen und Armaturen des Hauptkiihlkreises vom 17.5.1978 CSA CSA N285.1 General and Construction Requirements for CANDU Nuclear Power Plant Components CSA N285 4 CSA Periodic Inspection of CANDU Nuclear Power Plant Components DIN 25410 DIN Kerntechnische Anlagen; Oberflachensauberkeit von Teil 2 Bauteilen, Reinigung und Konservierung von Kreislaufsystemen einschlieSlich zugehoriger Komponenten (Nuclear Facilities; Surface Cleanliness of Components, Cleaning and Preserving of Fluid Systems and Associated Components) GOST 17924 GOST Kontrolle und Dichtigkeit der Hiillen von warmeabgebenden Elementen der Kernreaktoren GOST 21441 GOST Kernreaktoren; Montage von Warmetrennelementen; Klassifikationskriterien IAEA 50-SG-D1 IAEA Safety Functions and Component Classification for BWR, PWR and PTR IAEA IAEA 50-SG-D6 Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants ISO/DP 7126 ISO Pressure Boundaries of Primary Circuits: Material
App
11.79
Ust Ust Ust Ust Pub
1.75 1.75 77
Pub
79
Pub
79
Pub
10.79
Drf
1.78
Iss
74
Iss
11.77
Iss
5.78
App
75
App
75
Pub
2.77
Pub
72
Pub
75
Pub
79
Ust Ust 131
10.1 No.
Issuing Body
(Country)
KTA 3201.1
KTA
KTA 3201.2
KTA
KTA 3201.3
KTA
RDT A 1-1T RDT E 3-12T RDT E 8-18T
ORNL ORNL ORNL
RDT E 15-2NB-T
ORNL
RDT E 15-2NC-T
ORNL
RDTE 15-2ND-T
ORNL
RDT E 15-2NE-T
ORNL
RDT F 7-3T
ORNL
RDTF8-1T RDT F 9-4T
ORNL ORNL
RDT F 9-5T
ORNL
RDTM5-19T
ORNL
RDT M 7-23T
ORNL
RDT M 7-24T RDT M 12-1T
ORNL ORNL
RDT M 12-2T
ORNL
RDT M 12-3T
ORNL
RDTM12-4T
ORNL
RDT M 12-5T
ORNL
RDT M 12-6T
ORNL
*
RSK
132
Title
Status
(Remarks)
Komponenten des Primarkreises von Leichtwasserreaktoren Teil 1: Werkstoffe (Components for the Primary Circuit of Light Water Reactors Part 1: Materials) Komponenten des Primarkreises von Leichtwasserreaktoren Teil 2: Auslegung, Konstruktion und Berechnung (Components for the Primary Circuit of Light Water Reactors Part 2: Design, Construction and Calculation) Komponenten des Primarkreises von Leichtwasserreaktoren Teil 3: Herstellung (Components for the Primary Circuit of Light Water Reactors Part 3: Manufacturing) Coolant Composition in Pressurized Water Reactors Radioactive Gas Compressors Threaded Fasteners for Nuclear Components Class 1 Nuclear Components (Supplement to ASME Boiler and Pressure Vessel Code, Section III, Subsections NCA and NB) Class 2 Nuclear Components (Supplement to ASME Boiler and Pressure Vessel Code, Section Mi, Subsections NCA and NC) Class 3 Nuclear Components (Supplement to ASME Boiler and Pressure Vessel Code, Section III, Subsections NCA and ND) Class MC Nuclear Components (Supplement to ASME Boiler and Pressure Vessel Code, Section III, Subsections NA and NE) Marking of Components and Parts Preloaded Threaded Fasteners and Closures Requirements for Construction of Class 1 Elevated Temperature Nuclear System Components (Supplement to ASME Code Cases 1592, 1593, 1594, 1595 and 1596) Guidelines and Procedures for Design of Nuclear System Components at Elevated Temperature Austenitic Stainless Steel Plate, Sheet and Strip for Core Components Austenitic Stainless Steel Bar for Core Components Austenitic Stainless Steel Wire for Core Components Test Requirements for Thermal Insulating Materials for Use on Austenitic Stainless Steel Calcium Silicate Block and Pipe Thermal Insulation (ASTM C 533 with additional requirements) Mineral Fiber Hydraulic-Setting Thermal Insulating and Finishing Cement (ASTM C 449 with additional requirements) Reflective Insulation Thermal Insulation, Flexible or Molded, High Temperature, Low Conductivity Mineral Fiber Thermal Insulation, High-Temperature, Rigid, Flexible and Loose Fill (ASTM C 612 with additional requirements) Rahmenspezifikation - Basissicherheit von druckfiihrenden Komponenten, Behalter, Apparate, Rohrleitungen, Pumpen und Armaturen (Anhang zu RSK-Leitlinien Druckwasserreaktor vom 1/79)
Pub
2.79
Pub
10.80
Pub
10.79
Pub 10.71 8.73 Pub Pub 7.79 Amm 2.80 Pub 3.78 Pub
6.78
Pub
6.78
Pub
8.75
Pub 6.75 Amm 10.78 Pub 11.76 Pub 4.77 Amm 11.78 Pub
9.74
Pub
3.73
3.73 Pub Amm 4.74 3.73 Pub Pub 10.72 671 Pub Amm 11.72 Pub 1071 Amm 11.72 1.72 Pub Amm 10.74 Pub 5.72 Amm 473 3.73 Pub Pub
4.79
10.1 No.
Issuing Body (Country)
R.G. 1.26
USNRC
R.G. 1.37
USNRC
R.G. 1.45
USNRC
R.G. 1.48
USNRC
R.G. 1.70.13
USNRC
R G. 1.70.18
USNRC
R.G. 1.70.35
USNRC
R.G. 1.84
USNRC
R G 1 87
USNRC
R.G. 1.115 R.G. 1.116
USNRC USNRC
R G 1 124
USNRC
R.G. 1.125
USNRC
R G. 1.127
USNRC
R G. 1.133
USNRC
R.G. 3.31
USNRC
VDI 2184
VDI
VDI 2191
VDI
VdTUV SV 100
VdTUV
VdTUV Wei 1
VdTUV
VdTUV Wei 9
VdTUV
VdTUV Wei 10
VdTUV
Title (Remarks) Quality Group Classifications and Standards tor Water-, Steam- and Radio-Waste-Containing Components of Nuclear Power Plants (Issued for Comments) Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants Reactor Coolant Pressure Boundary Leakage Detection Systems Design Limits and Loading Combinations for Seismic Category I Fluid System Components Information for Safety Analysis Reports - Code Case Applicable to Reactor Coolant Pressure Boundary Components (See also R.G. 1.70) Information for Safety Analysis Reports Mechanical System Components (See also R. G. 1.70) Information for Safety Analysis Reports - Internally Generated Missiles (See also R G 1.70) Design and Fabrication Code Case Acceptability-ASME Section III Division I (Under Revision) Guidance for Construction of Class I Components in Elevated-Temperature Reactors (Suplement to ASME Section III Code Classes 1592, 1593, 1594, 1595, and 1596) Protection Against Low Trajectory Turbine Missiles Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems Service Limits and Loading Combination for Class I Linear Type Component Supports Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants Inspection of Water-Control Structures Associated with Nuclear Power Plants Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (Issued for Comments) Emergency Water Supply Systems for Fuel Reprocessing Plants MeSumformer fur Druck; Beschreibung und Untersuchung Mefsumformer fur Temperatur; Beschreibung und Untersuchung Allgemeines Blatt: Richtlinien fur die Bauteilprufung von Sicherheitseinrichtungen gegen Druckiiberschreitung Sicherheitsbeiwerte fur die Auslegung von Primarkreiskomponenten in Druck- und Siedewasserreaktoren (Withdrawn 11.79) Gultigkeit von Spezifikationen fur Komponenten der druckfiihrenden UmschlieRung des Reaktorkiihlmittels fur Kernkraftwerke mit Leichtwasserreaktoren Priifumfang fur Hebezeuge in kerntechnischen Anlagen - Wiederkehrende Prufungen
Status Iss
2.76
Iss
3 73
Iss
5 73
Iss
5.73
Iss
75
Iss
75
Iss
75
Iss
5.79
Iss
6.75
Iss Iss
7.77 5.77
Iss
1 78
Iss
10.78
Iss
3 78
Iss
9 77
Iss
5.77
Pub
1.76
Pub
9 77
Pub
9.74
Iss
6 79
Iss
5 77
133
10.1 No.
Issuing Body (Country)
VdTUV Wei 19
VdTUV
VdTUV Wei 22
VdTUV
VdTUV 454
VdTUV
134
Title (Remarks) Verkniipfung des Brennelementbeckenkuhlsystems mit dem Not- und Nachkiihlsystem bei Druckwasserreaktoren der KWU Anforderungen an die Me&einrichtungen zur kontinuierlichen Aktivitätsüberwachung der Wasserund Wasserdampf-Kreislaufe in Kernkraftwerken mit Leichtwasserreaktoren Empfehlungen für die Behandlung von Speisewasserbehaltern als Bestandteil von Dampfkesselanlagen
Status Iss
12.77
Iss
5.80
Pub
3.76
10.2 No. 10
Title
Issuing B o d y (Country)
Status
(Remarks)
Pressure Boundary and C o m p o n e n t s
10.2 Vessels and Boilers AD-Merkblatt A 1
AD
AD-Merkblatt A 2 AD-Merkblatt A 3
AD AD
AD-Merkblatt A 4
AD
AD-Merkblatt A 5
AD
AD-Merkblatt A 5 Anl.1 AD AD-Merkblatt B 0 AD-Merkblatt B 1
AD AD
AD-Merkblatt B 2
AD
AD-Merkblatt B 3
AD
AD-Merkblatt B 5
AD
AD-Merkblatt B 6
AD
AD-Merkblatt B 7 AD-Merkblatt B 8 AD-Merkblatt B 9
AD AD AD
AD-Merkblatt B 10
AD
AD-Merkblatt B 11
AD
AD-Merkblatt B 13
AD
AD-Merkblatt BP 0
AD
AD-Merkblatt G 1
AD
AD-Merkblatt G 1 Anl.1 AD AD-Merkblatt H 1
AD
AD-Merkblatt HP 3
AD
AD-Merkblatt HP 4
AD
AD-Merkblatt HP 5/1
AD
AD-Merkblatt HP 5/2
AD
AD-Merkblatt HP 5/3
AD
AD-Merkblatt N 1
AD
Ausriistung von Druckbehaltern; Sicherheitseinrichtungen gegen Druckiiberschreitung - Berstsicherungen Ausriistung von Druckbehaltern; Sicherheitsventile Ausriistung von Druckbehaltern; Bau, Ausriistung und Priifung von Warmwasserbereitern mit Gebrauchswassertemperaturen bis etwa 95 ~C Ausriistung von Druckbehaltern, Gehause von Armaturen Ausriistung von Druckbehaltern; Offnungen und Verschliisse an Druckbehaltern Ausrustung von Druckbehaltern; Hinweise fur die Anordnung von Mannlochern und Besichtigungsoffnungen Berechnung von Druckbehaltern Berechnung von Druckbehaltern; Zylindrische Mantel und Kugeln unter innerem Uberdruck Berechnung von Druckbehaltern; Kegelformige Mantel unter innerem und auBerem Uberdruck Berechnung von Druckbehaltern; Gewolbte Boden unter innerem und auBerem Uberdruck Berechnung von Druckbehaltern; Ebene Boden und Platten nebst Verankerungen Berechnung von Druckbehaltern; Zylindrische Mantel unter auBerem Uberdruck Berechnung von Druckbehaltern; Schrauben Berechnung von Druckbehaltern; Flansche Berechnung von Druckbehaltern; Ausschnitte in Zylindern, Kegeln und Kugeln unter Innendruck Berechnung von Druckbehaltern; Dickwandige zylindrische Mantel unter innerem Uberdruck Berechnung von Druckbehaltern; Rohre unter innerem und auBerem Uberdruck Berechnung von Druckbehaltern; Einwandige Balgkompensatoren Betrieb und Priifung von Druckbehaltern; Allgemeine Grundsatze fur Betrieb und Priifung AD-Regelwerk; Aufbau, Anwendung, Verfahrensrichtlinien Zusammenstellung wichtiger im AD-Regelwerk verwendeter DIN-Normen Herstellung von Druckbehaltern; SchweiBen von Druckbehaltern aus Stahl Herstellung und Priifung von Druckbehaltern; SchweiBaufsicht, SchweiSer Herstellung und Priifung von Druckbehaltern; Priifaufsicht und Priifer fur zerstorungsfreie Priifung Herstellung und Priifung von Druckbehaltern; Herstellung und Priifung der Verbindungen; Arbeitstechnische Grundsatze Herstellung und Priifung von Druckbehaltern; Herstellung und Priifung der Verbindungen; Arbeitspriifung an SchweiSnahten Herstellung und Priifung von Druckbehaltern; Herstellung und Priifung der Verbindungen; Zerstorungsfreie Priifung der SchweiBnahte Druckbehalter aus glasfaserverstarkten Kunststoffen (GFK) (vorlaufiges AD-Merkblatt)
Pub
6.77
Pub Pub
9.68 462
Pub
5.76
Pub
9.75
Pub
9.75
Pub Pub
277 2.77
Pub
2.77
Pub
2.77
Pub
2.77
Pub
2.77
Pub Pub Pub
2.77 2.77 2.77
Pub
2.77
Pub
2.77
Pub
2.77
Pub
10.77
Pub
9.71
Pub
10.70
Pub
4.68
Pub
4.75
Pub
4.75
Pub
4.75
Pub
12.77
Pub
12.77
Pub
4.69
135
10.2 No.
Issuing Body (Country)
AD-Merkblatt S 1
AD
NF A 49-200
AFNOR
NF A 49-212
AFNOR
NF A 49-213
AFNOR
NF A 49-214
AFNOR
Pr A 49-217
AFNOI
B PVC Seel
ASME
B PVC Sec.lll Div.ll
ASME
B PVC Sec.IV
ASME
B PVC Sec.VI
ASME
B PVC Sec.VII
ASME
B PVC Sec.VIII
ASME
ASTM A 487
ASTM
ASTM A 508
ASTM
ASTM A 541
ASTM
ASTM E 526
ASTM
ASTM E 560
ASTM
ASTM E 635
ASTM
GMBI. 1977 S. 661
BMI
GMBI. 1977 S. 739
BMI
NF A 36-201
BNS
136
Title
Status
(Remarks)
Abgrenzung zwischen der Berechnung gegen vorwiegend ruhende Innendruckbeanspruchung und der Berechnung gegen Schwellbeanspruchung Tubes en acier - Tubes sans soudure pour chaudieres et appareils a pression - Controles par ultrasons - Classes de controle et modalites d'application Tubes en acier - Tubes sans soudure en aciers non allies utilises aux temperatures moyennement elevees - Dimensions (avec tolerances normales) Conditions techniques de livraison Tubes en acier - Tubes sans soudures en aciers non allies et allies ferritiques utilises aux temperatures elevees - Dimensions (avec tolerances normales) Conditions techniques de livraison Tubes en acier sans soudure en aciers austenitiques utilises aux temperatures elevees - Dimensions (avec tolerances normales) - Conditions techniques de livraison Tubes sans soudure pour echangeurs de chaleur Aciers inoxydables austenitiques et ferritiques Dimensions - Conditions techniques de livraison Boiler and Pressure Vessel Code; Power Boilers (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Code for Concrete Reactor Vessels and Containments (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Heating Boilers (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Recommended Rules for Care and Operation of Heating Boilers (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Recommended Rules for Care of Power Boilers (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Pressure Vessels (Regular Addenda and Revision Provided) Specification for Low Alloy Steel Castings Suitable for Pressure Service Specification for Quenched and Tempered Vacuum Treated Carbon and Alloy Steel Forgings for Pressure Vessels Specification for Quenched and Tempered Carbon and Alloy Steel, Forgings for Pressure Vessel Components Recommended Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results Rec. Pract. for Relating Dosimetry Results From A Reactor Vessel Surveillance Capsule to the Neutron Fluence Levels At and Through the Pressure Vessel Wall Predicting Radiation Effects in Water cooled Reactor Pressure Vessel Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber die Einbauten des Reaktordruckbehalters vom 12.10.1977 Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber den Reaktordruckbehalter vom 25.11.1977 Toles en aciers soudables a haute limite d'elasticite - Nuances et qualites
Pub
9.73
Iss
77
Iss
79
Iss
79
Iss
78
Iss
74
Iss
74
Iss
74
Iss
74
Iss
74
Pub
76
Pub
77
Pub
76
Pub
77
Pub
75
Iss
10.77
Iss
11.77
Iss
75
10.2 No.
Issuing Body (Country)
NF A 36-205
BNS
NF A 36-206
BNS
NF A 36-207
BNS
NF A 36-208
BNS
NF A 36-209
BNS
Pr A 36-210
BNS
BS 3915
BSI
BS 4975
BSI
CEA G 14
CEA
CEAG 15 SR-Sicherheitsventile Blatt 1
CEA DDA
SR-Vorwarmer
DDA
TRD TRD TRD TRD
100 300 301 301 Anl. 1
DDA DDA DDA DDA
TRD 301 Anl. 2 TRD 303
DDA DDA
TRD 304 TRD 305
DDA DDA
TRD 306 TRD 309 TRD 320
DDA DDA DDA
TRD 401 TRD 402
DDA DDA
TRD 403 TRD 601 Blatt 1
DDA DDA
TRD 601 Blatt 2
DDA
TRD 602 Blatt 1 TRD 602 Blatt 2
DDA
TRD 603 Blatt 2
DDA
DDA
Title
Status
(Remarks)
Toles pour chaudieres et appareils a pression Aciers non allies Toles pour chaudieres et appareils a pression Aciers non allies au Mo, au Mn-Mo et au Cr-Mo Toles en aciers a haute limite d'elasticite pour chaudieres et appareils a pression - Nuances et qualites Toles en aciers non allies et allies au nickel pour appareils a pression a basses temperatures Toles en aciers inoxydables austenitiques pour appareils a pression a basses et tres basses temperatures Toles pour chaudieres et appareils a pression Aciers allies a haute limite d'elasticite Carbon and Low Alloy Steel Pressure Vessels for Primary Circuits of Nuclear Reactors Prestressed Concrete Pressure Vessels for Nuclear Reactors Normalisation des teintes conventionelles des tuyauteries Raccordement par brides pour vide Sicherheitstechnische Richtlinien fur Sicherheitseinrichtungen gegen Druckiiberschreitung fur den Hochdruckbereich Sicherheitstechnische Richtlinien fur Abgas-Wasservorwarmer Allgemeine Grundsatze fur Werkstoffe Festigkeitsberechnung von Dampfkesseln Zylinderschalen unter innerem Uberdruck Berechnung auf Wechselbeanspruchung durch schwellenden Innendruck bzw. durch kombinierte Innendruck- und Temperaturanderungen Berechnung von Rohrbogen Kugelschalen und gewolbte Boden unter innerem und unter auSerem Uberdruck Gewolbte Flammrohrboden Ebene Wandungen, Verankerungen und Versteifungstrager Zylinderformige Schalen unter auSerem Uberdruck Schrauben Glatte Vierkantrohre und Teilkammern unter innerem Uberdruck Ausrustung fur Dampferzeuger Ausrustung von Dampfkesselanlagen mit HeiSwassererzeuger Aufstellung von Hochdruck-Dampfkesselanlagen Betrieb der Dampfkesselanlagen; Teil I - Allgemeine Anweisung fur den Betreiber von Dampfkesselanlagen (Hochdruckdampfkessel) Betrieb der Dampfkesselanlagen; Teil II Allgemeine Anweisung fur die Wartung von Dampfkesselanlagen - Betriebsvorschriften fur Hochdruckdampfkessel Eingeschrankte Beaufsichtigung von Dampfkesselanlagen mit Hochdruckdampferzeugern Eingeschrankte Beaufsichtigung von Dampfkesselanlagen mit HochdruckheiBwassererzeugern Zeitweiliger Betrieb einer Hochdruckheifswassererzeugungsanlage mit herabgesetzter Vorlauftemperatur ohne Beaufsichtigung
Iss
78
Iss
78
Iss
79
Iss
78
Iss
76
Pub
65
Pub
73
Ust Iss Pub
73 372
Pub
10.66
Pub Pub Pub Pub
4.75 4.75 4.75 4.75
Pub Pub
10.76 5.76
Pub Pub
8.64 6.77
Pub Pub Pub
677 6.65 4.75
Pub Pub
4.73 5.76
Pub Pub
4.73 6.77
Pub
6.77
Pub
4.73
Pub
4.73
Pub
5 74
137
10.2 No.
Issuing Body (Country)
TRD 603 Blattl
DDA
TRD 604 Blatt 1
DDA
TRD 604 Blatt 2
DDA
TRD 701
DDA
TRD 702
DDA DIN
IAEA 126
IAEA
ISO/R 831 RDT E 10-3T
ISO ORNL
RDTE 10-4T RDTE 10-7T
ORNL ORNL RSK
• R.G. 1.2
USNRC
R.G. 1.67 R.G. 1.70.21
USNRC USNRC
R.G. 1.99
USNRC
R.G. 1.103
USNRC
VdTUV 355
VdTUV
VdTUV 357 VdTUV 359 VdTUV 362
VdTUV VdTOV VdTUV
VdTUV 364
VdTUV
VdTUV 367-76/3
VdTUV
VdTUV 451-64/3
VdTUV
VdTUV 451-67/11 VdTUV 451-67/12
VdTUV VdTUV
VdTUV 451-68/1 VdTUV 451-71/1
VdTUV VdTUV
VdTUV 451-72/2
VdTUV
138
Title (Remarks) Zeitweiliger Betrieb eines Hochdruckdampferzeugers mit herabgesetztem Betriebsdruck ohne Beaufsichtigung Betrieb von Dampfkesselanlagen mit Hochdruckdampferzeugern ohne standige Beaufsichtigung Betrieb von Dampfkesselanlagen mit HochdruckheilSwassererzeugern ohne standige Beaufsichtigung Dampferzeuger mit einem zulassigen Betriebsiiberdruck bis 0,5 bar (Niederdruckdampferzeuger) HeiBwassererzeuger mit einer zulassigen Vorlauftemperatur bis 110 °C (NiederdruckheiBwassererzeuger) Reaktordruckbehalter aus Spannbeton (Study for a Standard) Basis Structural Design Philosophy and Safety of Concrete Pressure Vessels Rules for Construction of Stationary Boilers Tank - Liquid Metal Service Accumulators, Pressure Vessel, Class 2 Blowdown Suppression Tank Rahmenspezifikation - Basissicherheit von druckfuhrenden Komponenten, Behalter, Apparate, Rohrleitungen, Pumpen und Armaturen (Anhang zu RSK-Leitlinien Druckwasserreaktor vom 1/79) Thermal Shock to Reactor Pressure Vessels (Safety Guide 2) Installation of Overpressure Protective Devices Information for Safety Analysis Reports - Reactor Vessels (See also R.G. 1.70) Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments Anforderungen an Druckbehalter, die durch Reaktionswarme, Dampf oder heiBe Flussigkeiten beheizt werden und Dampf oder HeiBwasser zur Abgabe erzeugen Schraubverbindungen Richtlinien fur Schalendruckbehalter Richtlinien zur Durchfuhrung, Auswertung und Beurteilung von Dehnungsmessungen Zerstorungsfreie Wiederholungsprufung von Druckbehaltern aus Stahl fur zyanhaltige Gase Beriicksichtigung von rohrfdrmigen Ausschnittverstarkungen bei Klopperboden im Bereich zwischen 0,6 x Da u. 0,89 x Da Ein- und AnschweiBen einzelner Teile an Kesseltrommeln ohne Warmebehandlung Berechnung innenliegender Wendekammern AnschweiBen kleiner Teile an Sammler, Rohre und Gehause von Armaturen ohne Warmebehandlung Herstellung gasdicht geschweiBter Rohrwande Richtlinien fur die Beurteilung von Kesselkonstruktionen (Die Festlegungen in Nr. 1: Flammrohr Rauchrohrkessel und ahnliche Konstruktionen - sind ungultig. Hierfur gilt das VdTuV-Merkblatt 451-76/1) Behandlung von TrenngefaBen
Status Pub
5.74
Pub
5.76
Pub
5.76
Pub
10.76
Pub
10.76
Drf
6.72
Pub Pub Pub Amm Pub Pub Pub
70 68 9.71 5.74 3.73 5.72 4.79
Iss
11.70
Iss Iss
10.73 1.75
Iss
4.77
Iss
10.76
Pub
9.68
Pub Pub Pub
12.69 4.71 4.72
Pub
1.73
Pub
6.76
Pub
5.65
Pub Pub
1.68 1.68
Pub Pub
5.68 8.71
Pub
8.72
10.2 No. VdTUV 451-72/3
Issuing B o d y (Country) VdTUV
VdTUV 451-77/3
VdTUV
VdTUV 454
VdTUV
BGBI. I, S. 173
(DEU)
BGBI. I, S. 173
(DEL)}
Title
Status
(Remarks}
Gehause von Dampfkessel-Armaturen aus Kupferlegierungen Befestigung von Rohren in Trommeln von Wasserrohrkesseln durch Walz-Schweißverbindungen ohne nachtragliche Warmebehandlung Empfehlungen für die Behandlung von SpeisewasserbehaTtern als Bestandteil von Dampfkesselanlagen Verordnung zur Ablosung von Verordnungen nach 5 24 der Gewerbeordnung vom 27.2.1980; Artikel 2 Verordnung uber Druckbehalter, Druckgasbehalter und Füllanlagen (Druckbehalterverordnung - DruckbehV) Verordnung zur Ablosung von Verordnungen nach § 24 der Gewerbeordnung vom 27.2.1980; Artikel 1 Verordnung uber Dampfkesselverordnung - DampfkV)
Pub
8.72
Pub
1077
Pub
3.76
Iss
2.80
Iss
280
139
10.3 No. 10
Issuing Body (Country)
Title
Pressure Bou ndary and C o m p o n e n t s
10.3 Pipes, Tubes and Fittings ASME: OM-75-2 ASME Vibration Systems - Monitoring and Testing Requirements B PVC Sec.lll Div.l ASME Boiler and Pressure Vessel Code; Division I: Subsection NB - Class 1 Components, Subsection NC - Class 2 Components, Subsection ND Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG - Core Support Structures, Appendices (Regular Addenda and Revisions Provided) ASTM A 53 ASTM Specitication tor Welded and Seamless Pipe ASTM A 106 ASTM Specification for Seamless Carbon Steel Pipe for High-Temperature Service ASTM A 134 ASTM Specification for Electric-Fusion (A) Welded Steel Plate Pipe (Sizes 16 Inches and over) ASTM A 135 ASTM Specification for Electric-Resistance Welded Steel Pipe ASTM A 178 ASTM Specification for Electric-Resistance-Welded Carbon Steel Boiler Tubes ASTM A 179 ASTM Specification for Seamless Cold-Drawn Low-Carbon Steel Heat Exchanger and Condenser Tubes ASTM A 181 ASTM Specification for Forged or Rolled Steel Pipe Flanges, Forged Fittings and Valves and Perts for General Service ASTM A 192 ASTM Specification for Seamless Carbon Steel Boiler Tubes for High-Pressure Service ASTM A 210 ASTM Specification for Seamless Medium-Carbon Steel Boiler and Super-Heater Tubes ASTM A 213 ASTM Specification for Seamless Ferritic and Austenitic Alloy-Steel Boiler, Super-Heater and Heat Exchanger Tubes ASTM A 226 ASTM Specification for Electric-Resistance-Welded Carbon Steel Boiler and Super-Heater Tubes for High-Pressure Service ASTM A 249 ASTM Specification for Welded Austenitic Stainless Steel Boiler, Super-Heater, Heat Exchanger and Condenser Tubes ASTM A 269 ASTM Specification for Seamless and Welded Austenitic Stainless Steel Tubing for General Service ASTM A 312 ASTM Specification for Seamless and Welded Austenitic Stainless Steel Pipe ASTM A 333 ASTM Specification for Seamless and Welded Steel Pipe for Low Temperature Service ASTM A 334 ASTM Specification for Seamless Ferritic Alloy Steel Pipe for High-Temperature Service ASTM A 350 ASTM Specification for Forged or Rolled Carbon and Alloy Steel Flanges, Forged Fittings and Valves, and Parts for Low Temperature Service ASTM A 358 ASTM Specification for Electric-Fission-Welded Austenitic Chromium-Nickel Alloy Steel Pipes for High-Temperature Service ASTM A 369 ASTM Specification for Ferritic Alloy Steel Forged and Bored Pipe for High-Temperature Service ASTM A 403 ASTM Specification for Wrought Austenitic Stainless Steel Piping Fittings ASTM A 409 ASTM Specification for Welded Large outside Diameter Light-Wall Austenitic Chromium-Nickel Alloy Steel Pipe for Corrosive or High-Temperature Service 140
Status
(Remarks)
Ust Iss
74
Pub Pub
77 77
Pub
74
Pub
73
Pub
75
Pub
75
Pub
77
Pub
75
Pub
76
Pub
76
Pub
75
Pub
77
Pub
76
Pub
76
Pub
77
Pub
77
Pub
77
Pub
77
Pub
76
Pub
77
Pub
77
10.3 No.
Issuing Body (Country/
ASTM A 420
ASTM
ASTM A 426
ASTM
ASTM A 430
ASTM
ASTM A 450
ASTM
ASTM A 451
ASTM
ASTM A 452
ASTM
ASTM A 498
ASTM
ASTM A 632
ASTM
ASTM A 652
ASTM
ASTM A 655
ASTM
ASTM A 691
ASTM
AWS D10.4
AWS
AWS D10.6
AWS
AWS D10 8
AWS
AWS D10.9
AWS
TRD 301 Anl 2 DIN 25408
DDA DIN
JIS Z8205
JIS
RDT C4-5T
ORNL
RDT C4-8T RDT E 7-4T
ORNL ORNL
RDT F 6-11T
ORNL
RDT M 2-3T
ORNL
RDT M 2-5T
ORNL
RDT M 2-12T
ORNL
RDT M 3-4T
ORNL
RDT M 3 9T
ORNL
Title
Status
(Remarks)
Specification for Factory Made Wrought Carbon Steel and Alloy Steel Welding Fittings of Seamless or Welded Construction for Low Temperature Service Specification for Centrifugally Cast Ferritic Alloy Steel Pipe for High-Temperature Service Specification for Austenitic Steel Forged and Bored Pipe for High-Temperature Service General Requirements for Carbon, Ferritic, Alloy and Austenitic Alloy Steel Tubes Specification for Centrifugally Cast Austenitic Steel Pipe for High-Temperature Service Specification for Centrifugally Cast Austenitic Cold-Wrought Pipe for High-Temperature Service Specification for Seamless and Welded Carbon, Ferritic and Austenitic Alloy Steel Heat Exchanger Tubes with Integral Fins Specification for Seamless and Welded Austenic Stainless Steel Tubing (Small-Diameter) for General Service Specification for Special Requirements for Wrought Steel Welding Fittings for Nuclear and other Special Applications Specification for Special Requirements for Pipe and Tubing for Nuclear and other Special Applications Carbon and Alloy Steel Pipe, Electric Fusion-Welded for High Pressure Service at High Temperature Welding of Austenitic Chromium-Nickel Steel Piping and Tubing Gas Tungsten Arc-Welding of Titanium Piping and Tubing Recommended Practices for Welding of Chromium-Molybdenum Steel Piping and Tubing Standard for Qualification of Welding Procedures and Welders for Piping and Tubing Berechnung von Rohrbogen Kerntechnische Anlagen; Rohrleitungen, Auslegung, Herstellung, Priifung (Nuclear Facilities; Piping, Design, Manufacturing, Testing] (For trial use and comments) Graphical Symbols for Piping (Available also in English) Permanent Magnet Flowmeter for Liquid Metal Piping Systems Orifice Assemblies for Nuclear Systems Mixing Component for Liquid Metal Piping Systems Fabrication and Installation of Piping Subassemblies for Liquid Metal Service Carbon and Alloy Steel Welding Fittings (ASMS SA-234 with additional requirements) Austenitic Stainless Steel Welding Fittings (ASME SA-403 with additional requirements) Nickel-Molybdenum-Chromium Alloy Welding Fittings (ASME SA-403 with additional requirements) Nickel Alloy Seamless Tubes (ASME SB-163 with additional requirements) Nickel-lron-Chromium Alloy Seamless Pipe and Tubing (ASME SB-407 with additional requirements)
Pub
77
Pub
76
Pub
77
Pub
76
Pub
77
Pub
75
Pub Rev
68 73
Pub
76
Pub
77
Pub
77
Pub
77
Pub
66
Pub
73
Pub
78
Pub
69
Pub Pub
10.76 8.76
Pub
59
Pub
4 74
Pub 8 73 Pub 11.71 Amm 6.74 Pub 8 71 Amm 6 73 Pub 8.79 Pub
8.79
Pub
8 79
Pub
8.79
Pub
4.76
141
10.3 No.
Issuing Body (Country)
RDT M 3-10T
ORNL
RDTM 3-17T
ORNL
RDT M 3-18T
ORNL
RDT M 3-27T
ORNL
RDT M 3-28T
ORNL
RDT M 3-29T
ORNL
RDT M 3-30T
ORNL
RDT M 3-33T
ORNL
RDT M 3-34T
ORNL
•
RSK
R.G. 1.46 R.G. 1.66
USNRC USNRC
R.G. 1.72
USNRC
R.G. 1.83
USNRC
R.G. 1.84
USNRC
R.G. 1.87
USNRC
R.G. 1.121
USNRC
R.G. 3.36
USNRC
SEP 1915
VDEh
SEP 1918
VDEh
SEP 1919
VDEh
VdTUV Wei 25
VdTUV
VdTUV 451-68/1
VdTUV
142
Title (Remarks) Nickel-Molybdenum-Chromium Alloy Seamless Pipe and Tubes (ASME SB-167 with additional requirements) Nickel-Molybdenum-Chromium Alloy Welded Pipe (ASME SA-358 with additional requirements) Nickel-Molybdenum-Chromium Alloy Seamless Tubes (ASME SB-163 with additional requirements) Seamless and Welded Small Diameter Austenitic Stainless Steel Tubing (ASTM A 632 with additional requirements) Austenitic Stainless Steel and Superalloy Tubing for BRP Core Components Nickel-Chromium-Molybdenum-Columbium Alloy Seamless Tubes (AMS 5589 with additional requirements) Nickel-Chromium-Molybdenum-Columbium Alloy Seamless Tubes (AMS 5590 with additional requirements) 2-1/4%-Chromium, 1°/o-Molybdenum Alloy Steel Seamless Tubes (ASME SA-213 with additional requirements) Pipe and Tubing for Nuclear and Other Special Applications (ASME SA-655 with additional requirements) Rahmenspezifikation - Basissicherheit von druckfiihrenden Komponenten, Behalter, Apparate, Rohrleitungen, Pumpen und Armaturen (Anhang zu RSK-Leitlinien Druckwasserreaktor vom 1/79) Protection Against Pipe Whip Inside Containment Non-destructive Examination of Tubular Products (Withdrawn 10.77) Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes Design and Fabrication Code Case Acceptability-ASME Section III Division I (Under Revision) Guidance for Construction of Class I Components in Elevated-Temperature Reactors (Suplement to ASME Section III Code Classes 1592, 1593, 1594, 1595, and 1596) Bases for Plugging Degraded PWR Steam Generator Tubes Non-destructive Examination of Tubular Products for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants (Withdrawn 2.69) Ultraschallprufung auf Langsfehler von Rohren aus warmfesten Stahlen Ultraschallprufung auf Querfehler von Rohren aus warmfesten Stahlen Ultraschallprufung auf Doppelungen von Rohren aus warmfesten Stahlen Drucktragende Teile von Armaturen aus StahlguB in der druckfiihrenden UmschliefJung des Primarkuhlmittels von Kernkraftwerken mit Leichtwasserreaktoren Herstellung gasdicht geschweiBter Rohrwande
Status Pub
4.76
Pub
8 79
Pub
8 79
Pub
8.79
Pub
11.77
Pub
4.76
Pub
4.76
Pub
8.79
Pub 12.77 Amm 2.78 Pub
4.79
Iss
5.73
Iss
11.78
Iss
7.75
Iss
5.79
Iss
6.75
Iss
8.76
Pub
6.77
Pub
7.77
Pub
7.77
Iss
3.80
Pub
5 68
10.3 No.
Issuing Body (Country)
VdTUV 451-77/3
VdTUV
VdTUV 1001 "' _
VdTUV
VdTUV Blatt VdTUV Blatt
1151 1 1151 2
VdTUV
VdTUV 1152
VdTUV
VdTUV 1155
VdTUV
VdTUV
Title (Remarks) Befestigung von Rohren in Trommeln von Wasserrohrkessein durch Walz-Schweiftverbindungen ohne nachtragliche Warmebehandlung Richtlinie uber Prüfungen beim Bau von Gashochdruckleitungen durch den TuV-Sachverstandigen Richtlinien fur Verfahrenspriifungen an geschweilSten Rohren aus ferritischen Stahlen Richtlinien fur Verfahrensprufungen an geschweiftten Rohren aus austenitischen Stahlen, NE-Metallen und NE-Metall-Legierungen Hinweise fur Schweiljverbindungen an nichtartgleichen Werkstoffen Hersteller von geschweiftten Rohren
Status Pub
10 77
Pub
11.77
Pub
878
Pub
9.77
Pub
5.73
Pub
2.75
143
10.4 No. 10
(Country)
(Remarks)
Pressure Boundary and C o m p o n e n t s
10.4 Pumps and Valves ANSI N278.1 ANSI
Functional Specification Standard for Self-Operated and Power-Operated Safety-Related Valves Performance Testing of Safety Valves Specification for Forged or Rolled Steel Pipe Flanges, Forged Fittings and Valves and Perts for General Service Specification for Forged or Rolled Carbon and Alloy Steel Flanges, Forged Fittings and Valves, and Parts for Low Temperature Service Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fiir Kernkraftwerke zur Priifung erforderlichen Informationen liber die liiftungstechnischen Anlagen, die Not- und Nachkuhlsysteme emschlieSlich Nachkuhlkette und Rohrleitungen, Pumpen und Armaturen des Hauptkuhlkreises vom 17.5.1978 Armaturengehause Richtlinien fiir die Bauteilprufung von Armaturen Kerntechnische Anlagen; Armaturen, Werkstoffe, Herstellung, Prufung (Nuclear Facilities; Valves Materials, Manufacture, Testing) (For trial use and comments) Kerntechnische Anlagen; Armaturen, Vorprufunterlagen und Dokumentation (Nuclear Facilities; Valves, Preliminary Test Documents) Bau- und Priifgrundsatze fiir Absperrvorrichtungen gegen Feuer und Rauch in Liiftungsleitungen, Institut fiir Bautechnik Automatic Spring-Loaded Safety Valves
ASME OM-75-6 ASTM A 181
ASME ASTM
ASTM A 350
ASTM
GMBI. 1978 S. 294
BMI
TRD 110 TRD 110 Anl. 1 DIN 25418 Teil 1
DDA DDA DIN
DIN 25418 Teil 2
DIN
•
IfBT
RDT E 1-6T
ORNL
RDT E 1-9T
ORNL
RDT E 1-12T
ORNL
Stainless Steel Gate Valves, Manual and Power Operated Stainless Steel Check Valves
RDT E 1-13T
ORNL
Valve, Isolation, Butterfly Type
RDT E 1-18T RDT E 1-19T RDT E 1-21T
ORNL ORNL ORNL
RDT E 1-25T RDT E 1-31T
ORNL ORNL
Class 1 Valves for Liquid Metal Service Class 2 Valves for Liquid Metal Service Stainless Steel Globe and Angle Valves, Manual and Power Operated Instrument Valves Carbon Steel Isolation Valves
RDT E 1-36T
ORNL
RDTE3-1T
ORNL
RDT E 3-2T
ORNL
RDT E 3-3T
ORNL
RDT E 3-6T
ORNL
RDT E 3-7T
ORNL
Floor Valve, Reactor Refueling and Maintenance for LMFBR Vertical, Canned or Wet Motor-Driven Single-Stage Centrifugal Pump Centrifugal, Free-Surface, Sodium Pump with Electrical Drive Vertical, Shaft-Sealed, Motor-Driven, Single-Stage Centrifugal Pump Horizontal, Electric Motor-Driven, Single-Stage Centrifugal Pump Reciprocating Positive Displacement Pump
RDT E 3-9T
ORNL
Electromagnetic Pump for Liquid Metal Service
144
Status
Title
Issuing Body
Pub
75
Pub
77
Pub
77
Iss
5.78
Pub Pub Pub
5.74 5.74 4.76
Drf
2.77
Pub
12.71
Pub Amm Pub Amm Pub Amm Pub Amm Pub Pub Pub
372 1.73 372 5.74 3.72 5.74 8.72 5.74 5.75 674 3.72
Pub Pub Amm Pub Amm Pub Amm Pub Amm Pub Amm Pub Amm Pub Amm Pub Amm
4.72 4.73 5.74 6.72 6.74 6.72 5.74 5.71 6.74 7.72 5.74 2.72 5.74 372 5.74 3.71 5.74
10.4 No.
Issuing Body (Country)
*
RSK
RG 11
USNRC
RG. 1.14
USNRC
R.G. 1.67 R.G. 1.70.30
USNRC USNRC
R.G. 1.73
USNRC
R.G. 1.87
USNRC
R.G. 1.96
USNRC
R.G. 1.106
USNRC
Task No. SC 704-5
USNRC
VdTUV GW-SV
VdTUV
VdTUV SV 100
VdTUV
VdTUV SV 100/2
VdTUV
VdTUV SV 100/3
VdTUV
VdTUV SV 100/4
VdTUV
VdTUV Wei 5 VdTUV Wei 17
VdTUV VdTUV
VdTUV 451-67/12
VdTUV
Title
Status
(Remarks)
Rahmenspezifikation - Basissicherheit von druckfiihrenden Komponenten, Behalter, Apparate, Rohrleitungen, Pumpen und Armaturen (Anhang zu RSK-Leitlinien Druckwasserreaktor vom 1/79| Net Positiv Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1) Reactor Coolant Pump Flywheel Integrity (Issued for Comments) Installation of Overpressure Protective Devices Information for Safety Analysis Reports -Pump Flywheel Integrity (See also R.G. 1.70) Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants Guidance for Construction of Class I Components in Elevated-Temperature Reactors (Suplement to ASME Section III Code Classes 1592, 1593, 1594, 1595, and 15961 Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants Thermal Overload Protection for Electric Motors on Motor-Operated Valves Functional Specification for Safety-Related Valve Assemblies in Nuclear Power Plants (Proposed R.G.) Grundwerk Sicherheitsventile (Das Grundwerk enthalt samtliche bisher erschienenen Merkblatter über bauteilgeprüfte Sicherheitsventile - z.Z. ca. 325 Blatt) Allgemeines Blatt: Richtlinien fur die Bauteilprufung von Sicherheitseinrichtungen gegen Druckuberschreitung Bemessungsvorschlag fur Sicherheitsventile fur Gase in flussigem Zustand Hinweise fur die Prufung von Sicherheitseinrichtungen gegen Druckuberschreitung am Einbauort Kunststoffe und Elastomere in Sicherheitsventilen Elastomere Innenliegende Absperr-Sicherheits-Armatur Anwendung und Prufung von GuBteilen fur Pumpengehause im Primarkreis von Kernkraftwerken mit Leichtwasserreaktoren aus dem Werkstoff GS 18 NiMoCr 37 (Withdrawn 5.79) Anschwei&en kleiner Teile an Sammler, Rohre und Gehause von Armaturen ohne Warmebehandlung
Pub
4.79
Iss
11.70
Iss
8.75
Iss Iss
10.73 75
Iss
1.74
Iss
6.75
Iss
6.76
Iss
3 77
Iss
2.79
Pub
9.74
Pub
1.73
Pub
7.74
Pub
1.78
Iss
9 80
Pub
1.68
145
10.5 Issuing Body (Country)
No. 10
Title (Remarks)
Pressure Boundary and C o m p o n e n t s
10.5 Heater,, Heat Exchanger,, Pressurizer and S t e a m Generator E 32-101 AFNOR Code de construction des generateurs de vapeur Partie I: Generalites - Essais hydrauliques AFNOR E 32-102 Code de construction des generateurs de vapeur Partie II: Materiaux E 32-105 AFNOR Code de construction des generateurs de vapeur Partie V: Fabrication AFNOR Code de construction des generateurs de vapeur E 32-106 Partie VI: Robinetterie - Pompes de circulation Appareils de surveillance, d'alarme et de securite E 32-107 AFNOR Code de construction des generateurs de vapeur Qualification du mode operatoire de soudage NF E 32-103 AFNOR Code de construction des generateurs de vapeur Partie III: Calcul de resistance des elements soumis a une pression interieure ASTM A 356 ASTM Specification for Heavy-Walled Carbon and Low Alloy Steel Casting for Steam Turbines BMI GMBI. 1978 S. 598 Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber das Druckabbausystem (DAS) bei Siedewasserreaktoren, die Dampferzeuger und Systeme zur Handhabung und Lagerung sonstiger radioaktiver Stoffe vom 30.10.1978 RDT E4-1T ORNL Steam Generator for Pressurized Water Reactors RDT E 4-2T ORNL Heat Exchanger, Class 1, Water-to-Water, Straight or U-Tube RDT E 4-5T ORNL Forced-Circulation Cold Trap Assembly for Removal of Sodium Impurities RDT E 4-6T ORNL Intermediate Heat Exchanger for Liquid Metal Systems RDT E 4-7T ORNL Sodium to Air Heat Exchanger RDT E4-13T
ORNL
Freeze Vent for Sodium Service
RDT E 4-14T
ORNL
Vapor Trap Assemblies for Sodium Service
RDT E4-16T RDT E4-17T
ORNL ORNL
RDTE4-18T
ORNL
RDT E 4-20T
ORNL
Sodium-Heated Steam Generator Heat Exchanger, Class 2, Water-to-Water, Straight or U-Tube Air-Cooled Heat Exchanger for Nuclear Steam-Supplied Systems Heat Exchanger for Gas Cooler
RDT E 5-2T
ORNL
R.G. 1.67 R.G. 1.70.19
USNRC USNRC
R.G. 1.70.37
USNRC
R.G. 1.83
USNRC
R.G. 1.87
USNRC
VDI 3501
VDI
146
Status
Electric Heater and Connector Assembly for Pressurizer for Pressurized Water Reactors Installation of Overpressure Protective Devices Information for Safety Analysis Reports - Steam Generators (See also R.G. 1.70) Information for Safety Analysis Reports - Pressurizer Relief Discharge System (See also R.G. 1.70) Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes Guidance for Construction of Class I Components in Elevated-Temperature Reactors (Suplement to ASME Section III Code Classes 1592, 1593, 1594, 1595, and 1596) Dampferzeuger-Regelung, Brennstoff- und Verbrennungsluft-Regelung
Iss
77
Iss
77
Iss
78
Iss
75
Iss
78
Iss
78
Pub
77
Iss
1078
Pub Pub
12.71 6.73
Pub
1.76
574 Pub Amm 4.75 6.71 Pub Amm 1.74 2.71 Pub Amm 12.71 4.72 Pub Amm 1.74 2.74 Pub 7.71 Pub Pub
3.71
5.72 Pub Amm 10.73 5.72 Pub Iss Iss
10.73 1.75
Iss
6.75
Iss
7.75
Iss
675
Pub
2.62
10.5 No. VDI 3506 Blatt 1 VDI 3507 VdTUV Wei 14
Issuing Body
(Country)
Title
Status
(Remarks)
VDI
Speisewasser-Regelung fur Durchlaufdampferzeuger
Pub
8.68
VDI VdTUV
Abnahme von Regelanlagen fur Dampferzeuger Druckspeicherintegritat
Pub Iss
11.66 3 79
147
10.6 Issuing Body (Country)
No. 10
Status
(Remarks)
Pressure Boundary and
10.6 W e l d i n g AD-Merkblatt H 1
AD
E 32-107
AFNOR
B PVC Sec.lX
ASME
ASTM A 216 /ANSI G37 2 AWS B1.0 AWS D1.1 AWS D10.4
ASTM /ANSI AWS AWS AWS
AWS D10.6
AWS
AWS D10.8
AWS
AWS D10.9
AWS
AWS D12.1 AWS WIQC
AWS AWS
A 81-350
CNS
NF A 81-300
CNS
NF A 81-301
CNS
NF A 81-302
CNS
NF A 81-303
CNS
NF A 81-304
CNS
NF A 81-305
CNS
NF A 81-306
CNS
NF A 81-307
CNS
NF A 81-309
CNS
NF A 81-310
CNS
148
Title
Herstellung von Druckbehaltern; SchweiBen von Druckbehaltern aus Stahl Code de construction des generateurs de vapeur Qualification du mode operatoire de soudage Boiler and Pressure Vessel Code; Welding and Brazing Qualifications (Regular Addenda and Revisions Provided) Specification for Carbon-Steel Castings Suitable for Fusion Welding for High-Temperature-Service Guide for the Nondestructive Inspection of Welds Structural Welding Code-Steel Welding of Austenitic Chromium-Nickel Steel Piping and Tubing Gas Tungsten Arc-Welding of Titanium Piping and Tubing Recommended Practices for Welding of Chromium-Molybdenum Steel Piping and Tubing Standard for Qualification of Welding Procedures and Welders for Piping and Tubing Reinforcing Steel Welding Code Guide to AWS Welding Inspector Qualification and Certification-including AWS QC1-77 Standard for Qualification and Certification of Welding Inspectors Produits siderurgiques - Methode conventionnelle d'essai de fissuration sur implants a entaille circulate Produits d'apport - Electrodes pour soudage electrique a Tare - Terminologie Electrodes metalliques enrobees pour soudage manuel electrique a Tare des aciers et alliages Caracteristiques dimensionnelles - Essais geometriques et physiques - Conditionnement et marquage Electrodes metalliques enrobees pour soudage manuel electrique a Tare des aciers non allies Caracteristiques dimensionnelles Electrodes metalliques enrobees pour soudage manuel electrique a Tare - Execution d'un depot de metal fondu - Essais de durete Electrodes enrobees pour soudage manuel a Tare Execution d'un depot de metal fondu en vue de I'analyse chimique Electrodes enrobees pour soudage manuel a Tare Execution d'un depot de metal fondu et dosage de I'hydrogene diffusible Electrodes enrobees - Determination du rendement et du coefficient de depot Procede de soudage avec fil electrode - Execution d'un depot de metal fondu et dosage de I'hydrogene diffusible Electrodes metalliques enrobees pour soudage manuel electrique a Tare des aciers non allies ou faiblement allies - Produits d'apport Fil electrode nu pour soudage a Tare sous protection gazeuse de I'acier doux - Dimensions des fils
Pub
4.68
Iss
78
Iss
74
Pub
77
Pub Pub Pub
77 79 66
Pub
73
Pub
78
Pub
69
Pub Pub
75 78
Iss
77
Iss
45
Iss
79
Iss
75
Iss
79
Iss
69
Iss
75
Iss
75
Iss
77
Iss
75
Iss
69
10.6 No.
Issuing Body (Country)
NF A 81-321
CNS
NF A 81-331
CNS
NF A 81-340
CNS
NF A 81-341
CNS
NF A 81-343
CNS
NF A 81-344
CNS
NF A 81-345
CNS
NF A 81-346
CNS
NF A 81-347
CNS
NF A 81-348
CNS
NF A 81-510
CNS
NF A 81-900
CNS
NF A 88-010
CNS
NF A 88-110
CNS
TRD 201
DDA
DIN 8560
DIN
DIN 8561
DIN
DIN 8562
DIN
DIN 8563 Teil 1
DIN
Title
Status
(Remarks}
Metaux d'apport pour soudage, brasage et soudo-brasage - Baguettes et fils non enrobes Caracteristiques dimensionnelles Aluminium et alliages d'aluminium - Soudage Produits d'apport Electrodes metalliques enrobees pour le soudage manuel electrique a Tare deposant un metal a haute limite d'elasticite - Symbolisation - Produits d'apport Electrodes metalliques enrobees pour le soudage manuel electrique a Tare deposant un metal a haute limite d'elasticite - Essais mecaniques - Analyse chimique - Essais geometriques et physiques Electrodes metalliques enrobees pour le soudage manuel electrique a I'arc deposant un metal inoxydable et refractaire - Symbolisation - Produits d'apport Electrodes metalliques enrobees pour le soudage manuel electriques a I'arc deposant un metal inoxydable et refractaire - Analyse chimique - Essais mecaniques, geometriques et physiques Electrodes metalliques enrobees pour le soudage manuel electrique a I'arc deposant un metal resistant a chaud - Symbolisation - Produits d'apport Electrodes metalliques enrobees pour le soudage manuel electrique a I'arc deposant un metal resistant a chaud - Analyse chimique - Essais mecaniques, geometriques et physiques Electrodes metalliques enrobees pour le soudage manuel electrique a I'arc deposant un metal pour utilisation a basses temperatures - SymbolisationProduits d'apport Electrodes metalliques enrobees pour le soudage manuel electrique a I'arc deposant un metal pour utilisation a basses temperatures - Essais mecaniques - Analyse chimique - Essais geometriques et physiques Fils electrodes nus, pleins ou fourres pour soudage a I'arc des aciers non allies ou faiblement allies Dimensions des bobines, jantes et couronnes Aluminium et alliages d'aluminium - Soudage Emploi et controle des flux decapants Positions fondamentales d'execution des soudures et definition des angles de rotation et d'inclinaison pour les soudures rectilignes - Valeurs de ces angles pour le soudage manuel des aciers doux et faiblement allies a haute resistance avec electrodes enrobees Soudage - Qualification des soudeurs et des operateurs SchweiBen von Bauteilen aus Stahl - Fertigung Priifung Prufung von StahlschweiBern (Examination of welders for welding steel) Prufung von NE-Metallschweilsern (Examination of welding non-ferrous metals) SchweifJen im Behalterbau; Behalter aus metallischen Werkstoffen, Schweilstechnische Grundsatze (Welding of containers; containers of metallic materials, general specifications) Sicherung der Gute von SchweiSarbeiten; Allgemeine Grundsatze (Quality assurance of welded structures; fundamentals)
Iss
79
Iss
73
Iss
79
Iss
79
Iss
79
Iss
79
Iss
79
Iss
79
Iss
79
Iss
79
Iss
78
Iss
73
Iss
76
Iss
45
Pub
4.73
Pub
1.78
Pub
2.74
Pub
1.75
Pub
10.78
149
10.6 No.
Issuing Body (Country)
DIN 8563 Teil 2
DIN
DIN 8563 Teil 3
DIN
DIN 8563 Teil 4
DIN
DIN 8564 Teil 1
DIN
DIN 50120 Teil 1
DIN
DIN 50120 Teil 2
DIN
DIN 50121 Teil 1
DIN
DIN 50121 Teil 2
DIN
DIN 50121 Teil 3
DIN
DIN 50123
DIN
DIN 50124
DIN
ISO 2553 ISO/R 617
ISO ISO
ISO/R 626 ISO/R 627
ISO ISO
ISO/R 637
ISO
RDT F 6-2T
ORr>
150
Title
Status
(Remarks)
Sicherung der Giite von ! chweiBarbeiten; Anforderungen an den Butrieb (Quality assurance of welded structures; requirements on firms) Sicherung der Giite von SchweiBarbeiten; SchmelzschweiBverbindungen an Stahl, Anforderungen, Bewertungsgruppen (Quality assurance of welded structures; fusion-welded joints in steel, requirements, classification) Sicherung der Giite von SchweiBarbeiten; SchmelzschweiBverbindungen an Stahl, Anforderungsklassen (Quality safeguarding of welded structures; fusion-welded joints in steel, categories of service requirements) SchweiSen im Rohrleitungsbau; Rohrleitungen aus Stahl, Herstellung, SchweiBnahtpriifung (Welding of pipelines; steel pipelines; manufacturing, testing of welds) Priifung von Stahl; Zugversuch an SchweiSverbindungen, SchmelzgeschweiBte Stumpfnahte (Testing of steel; tensile test on fusion welded butt joints) Priifung von Stahl; Zugversuch an SchweilSverbindungen, PreBgeschweiBte Stumpfnahte (Testing of steel; tensile test on welded joints, pressure welded butt joints) Priifung metallischer Werkstoffe; Technologischer Biegeversuch an SchweilSverbindungen und SchweiBplattierungen, SchmelzschweiBverbindungen (Testing of metallic materials; technological bend test on welded joints, fusion welded joints) Priifung metallischer Werkstoffe; Technologischer Biegeversuch an SchweilSverbindungen und SchweiBplattierungen, PreBschweiBverbindungen (Testing of metallic materials; technological bend test on welded joints; pressure welded joints) Priifung metallischer Werkstoffe; Technologischer Biegeversuch an SchweiSverbindungen und SchweiBplattierungen, SchmelzschweiSplattierungen (Testing of metallic materials; technological bend test on welded platings) Priifung von Nichteisenmetallen; Zugversuch an SchweiSverbindungen, SchmelzgeschweiBte Stumpfnahte (Testing of non-ferrous metals; tensile test on fusion welded butt joints) Priifung metallischer Werkstoffe; Scherzugversuch an Widerstandspunkt-, Widerstandsbuckel- und SchmelzpunktschweiBverbindungen (Testing of metallic materials; shear tension test on spot joints, projection joints by resistance and fusion welding) Welds: Symbolic Representation on Drawings Calculation of Rectangular Symmetrical Fillet Welds Staically Loated in such a Way that the Transverse Section is not under any Normal Stress Strenght Calculation of Butt Welded Joints Fundamental Welding Positions and Definitions of Rotation and Slope for Straight Welds Methods of Test for Determining the Mechanical Properties of Weld Metal Deposited by Filler Rods for Gas Welding Mild Steels and Low Alloy High Tensile Steels Welding of Reactor Core Components and Test Assemblies
Pub
10.78
Pub
1.79
Pub
1076
Pub
4.72
Pub
9.75
Pub
8.78
Pub
1.78
Pub
1.78
Pub
1.78
Pub
4.77
Pub
4.77
Pub Pub
74 67
Pub Pub
67 67
Pub
75
Pub
7.73
10.6 No.
Issuing Body (Country)
RDTF6-5T
ORNL
RDT F 6-6T
ORNL
RDTM1-1T
ORNL
RDTM1-2T
ORNL
RDTM1-3T
ORNL
RDTM1-4T
ORNL
RDTM1-5T
ORNL
RDTM1-6T
ORNL
RDTM1-9T
ORNL
RDT M MOT
ORNL
RDTM1-11T
ORNL
RDTM1-15T
ORNL
RDTM1-17T
ORNL
RDTM1-19T
ORNL
RDTM1-20T
ORNL
RDTM1-21T
ORNL
RDTM1-22T
ORNL
RDTM1-23T
ORNL
R G. 1.19
USNRC
R.G. 1.31
USNRC
RG. 1.34 R G. 1 43
USNRC USNRC
RG. 1.50
USNRC
RG 1.71
USNRC
R.G. 3.27
USNRC
R.G. 3.28
USNRC
R G. 3.29
USNRC
Title (Remarks) Welding and Brazing Qualifications (Supplement to ASME Boiler and Pressure Vessel Code, Section IX) Welding of Structural Components (AWS D1.1 with additional requirements) Stainless Steel Covered Welding Electrodes (ASME SFA-5.4 with additional requirements) Stainless Steel Welding Rods and Bare Electrodes (ASME SFA-5 9 with additional requirements) Mild Steel Covered Welding Electrodes (ASME SFA-5.1 with additional requirements) Low Alloy Steel Covered Welding Electrodes (ASME SFA-55 with additional requirements) Welding Rods and Electrodes, Surfacing (AWS AS. 13 with additional requirements) Mild Steel Electrodes for Gas Metal-Arc Welding (ASME SFA-5.18 with additional requirements) Brazing Filler Metal (ASME SFA-5.8 with additional requirements) Nickel and Nickel-Alloy Covered Welding Electrodes (ASME SFA-5.11 with additional requirements) Nickel and Nickel-Alloy Bare Welding Rods and Electrodes (ASME SFA-5.14 with additional requirements) Nickel-Molybdenum-Chromium Alloy Bare Welding Rods and Electrodes Bare Carbon Steel Electrodes and Fluxes for Submerged Arc Welding (ASME SFA-5.17 with additional requirements) Nickel-Chromium-Molybdenum-Columbium Bare Welding Rods and Electrodes Mild Steel Electrodes for Flux-Cored Arc Welding (ASME SFA-5.20 with additional requirements) Consumable Welding Inserts Bare Low-Alloy Steel Electrodes and Fluxes for Submerged Arc Welding (ASME SFA-5.23 with additional requirements) 2-1/4%-Chromium, 1%-Molybdenum Alloy Bare Welding Rods and Electrodes Non destructive Examination of Primary Containment Liner Welds (Safety Guide 19) Control of Ferrite Content in Stainless Steel Weld Metal Control of Electroslag Weld Properties Control Stainless Steel Weld Cladding of Low-Alloy Steel Components Control of Preheat Temperature for Welding of Low-Alloy Steel (Under Revision) Welder Qualification for Areas of Limited Accessibility (Under Revision) Non-destructive Examination of Welds in the Liners of Concrete Barries in Fuel Reprocessing Plants Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants
Status Pub
1.80
Pub
6.73
Pub
8 79
Pub
10 78
Pub
8.79
Pub
8.79
Pub
8.79
Pub
3.77
Pub » Pub
8 79
Pub
5.77
Pub
4 77
Pub
3.77
Pub
8.79
Pub
8.79
8.79
Pub 3 75 Amm 5.75 Pub 11.77 Pub
3.77
Iss
8.72
Iss
4 78
Iss Iss
12.72 5 73
Iss
5.73
Iss
12 73
Iss
5 77
Iss
5.75
Iss
5 75
151
10.6 No.
Issuing B o d y (Country)
VdTUV GW-SZW
VdTUV
VdTUV Wei 12
VdTUV
VdTUV 451-74/1 VdTUV 1152
VdTUV VdTUV
VdTUV 1153
VdTUV
VdTUV 1156
VdTUV
152
Title
Status
(Remarks)
Grundwerk: Kernblätter für Schweißzusätze (z.Z. ca. 2000 Blatt) Umsetzung der Empfehlungen der Reaktor-Sicherheitskommission auf ihrer 93. Sitzung am 24.04.74 - Programm zur Untersuchung der Schweißprobleme bei Reaktordruckbehaltern (Sofortprogramm) - RSK-Leitlinien für Druckwasserreaktoren (Withdrawn 1.80) Warmebehandlung von SchweiSverbindungen Hinweise für Schweißverbindungen an nichtartgleichen Werkstoffen Richtlinien fur die Eignungsprufung von SchweiSzusatzwerkstoffen Verfahrensprufungen für die Hartauftragschweißung (Panzern)
Pub Pub
974 5.73
Pub
11.77
Pub
11.78
11.1 No. 11
Issuing Body (Country)
Title (Remarks)
Status
Containment
11.1 General ANS-54.3 ANS-56.4
ANS ANS
ANS-56.5
ANS
ANS-56.6
ANS
ANS-56.7
ANS
B PVC Sec III Div .1
ASME
GMBI. 1976 S. 445
BMI
RDTE8-18T
ORNL
R.G. 1.7
USNRC
R.G. 1.122
USNRC
VdTUV Wei 8
VdTUV
VdTUV Wei 31
VdTUV
Principal Design Criteria for LMFBR Containments Pressure and Temperature Transient Analysis for Light Water Reactor Containments (Issued for Comments) PWR and BWR Containment Spray System Design Criteria Pressurized Water Reactor Containment Ventilation Systems Boiling Water Reactor Containment Ventilation Systems Boiler and Pressure Vessel Code; Division I: Subsection NB - Class 1 Components, Subsection NC - Class 2 Components, Subsection ND Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG - Core Support Structures, Appendices (Regular Addenda and Revisions Provided) Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber die Einbauten des Reaktordruckbehalters und die Einbauten des Sicherheitsbehalters vom 4.8.1976 (withdraw: directions to reactor pressure vessel, see GMBI. 1977 S. 661) Threaded Fasteners for Nuclear Components Control of Combustible Gas Concentrations in Containment Following a Loss of Coolant Accident Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components Aufiere Bauwerksabdichtungen in kerntechnischen Anlagen Behandlung von Gefugeanzeigen bei der Magnetpulverpriifung in SchweiBgut und WarmeeinflulSzonen von Reaktorsicherheitsbehaltern und Komponenten der auSeren Systeme (in press)
Ust Pub
11.79
Pub
11.79
App
78
App
78
Iss
74
Iss
8.76
Pub 7.79 Amm 2.80 Iss 11.78 Iss
2.78
Iss
12.76
153
11.2 No. 11
Issuing B o d y (Country)
Status
Containment
11.2 Steel C o n t a i n m e n t GMBI. 1975 S. 602 BMI
BS 4208
BSI
DIN 25449
DIN
KTA 3401.1
KTA
KTA3401 2
KTA
KTA 3401.3
KTA
KTA 3401.4
KTA
RDT E 10-8T R.G. 1.57
ORNL USNRC
154
Title (Remarks)
Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber den Standort, den Sicherheitsbehalter, das Reaktorschutzsystem und den Reaktordruckbehalter vom 30.7.1975 (Withdraw: directions to reactor protection system and reactor pressure vessel, see GMBI. 1977 S. 66 and GMBI. 1977 S. 739) Carbon and Low Alloy Steel. Containment Structures for Stationary Nuclear Power Reactors Auslegung der Stahlbetonbauteile von Kernkraftwerken unter Belastung aus inneren Storfallen (Design Criteria for Structure Concrete Against Loadings Resulting due to Accidents Inside Nuclear Power Plants) Reaktorsicherheitsbehalter aus Stahl Teil 1: Werkstoffe (Steel Reactor Containment Part 1: Materials) Reaktorsicherheitsbehalter aus Stahl Teil 2: Auslegung, Konstruktion und Berechnung (Steel Reactor Containment Part 2: Design, Construction and Calculation) Reaktorsicherheitsbehalter aus Stahl Teil 3: Herstellung (Steel Reactor Containment Part 3: Manufacturing) Reaktorsicherheitsbehalter aus Stahl Teil 4: Wiederkehrende Priifungen (Steel Reactor Containment Part 4: Inservice Inspections) Steel Containment Vessel Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components
Iss
Pub
7.75
67
Drf
10.79
Pub
6.80
Pub
6.80
Pub
10.79
Drf
10.80
Pub Iss
12.73 6.73
11.3 No. 11
Issuing B o d y (Country)
Status
Title (Remarks)
Containment
11.3 Concrete C o n t a i n m e n t ACI ACI 311 3R ACI 318 ACI 349
ACI ACI
ASME JC 8-18
ASME /ACI ASME /ACI ASME /ACI ASME
ASME JC 8-23 ASME JC 8-53 B PVC Sec III Div.ll BS 4975
BSI
CSA N287 1
CSA
CSA N287 2
CSA
CSA N287 4
CSA
DIN 25449
DIN
•
DIN
IAEA 126
IAEA
R.G. 1.10
USNRC
R.G. 1 55 R.G. 1 103
USNRC USNRC
R G 1 107
USNRC
R.G. 1.136
USNRC
Task No. SC 814-5
USNRC
Guide for Certification of Nuclear Concrete Inspection and Testing Personnel Building Code Requirements for Reinforced Concrete Code Requirements for Nuclear Safety Related Concrete Structures Concrete Requirements
Pub
75
Pub Pub
77 76
Drf
6.78
Update of Reference Documents
Drf
9.78
Use of SA-216 Material for Containment
Drf
878
Boiler and Pressure Vessel Code; Code for Concrete Reactor Vessels and Containments (Regular Addenda and Revisions Provided) Prestressed Concrete Pressure Vessels for Nuclear Reactors General Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants Material Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants Construction, Fabrication and Installation Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants Auslegung der Stahlbetonbauteile von Kernkraftwerken unter Belastung aus inneren Storfallen (Design Criteria for Structure Concrete Against Loadings Resulting due to Accidents Inside Nuclear Power Plants) Reaktordruckbehalter aus Spannbeton (Study for a Standard) Basis Structural Design Philosophy and Safety of Concrete Pressure Vessels Mechanical (Cadweld) Splices in Reinforcing Bars of Category I Concrete Structures Concrete Placement in Category I Structures Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures Material for Concrete Containments (Under Revision; see also Task No. SC 814-5) Materials, Construction, and Testing of Concrete Containments (Articles CC-1000, -2000, and -4000 through -7000 of the "Code for Concrete Reactor Vessels and Containments") (Proposed Revision to R.G 1.136)
Iss
74
Pub
73
App
77
App
76
App
77
Drf
10.79
Drf
6.72
Pub
70
Iss
1.73
Iss Iss
6.73 1076
Iss
2.77
Iss
1078
Iss
11.79
155
11.4 No. 11
Issuing Body (Country)
Status
(Remarks)
Containment
11.4 Leakage ASME JC 8-76 CSA N287.6
ASME /ACI CSA
DIN 25436
DIN
KTA 3405
KTA
10 CFR 50 Appendix J
USNRC
156
Title
Water Soundness Test
Drf
Pre-operational Proof and Leakage Rate Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants Integrale Leckratenpriifung des Sicherheitsbehalters, mit der Absolutdruckmethode (Identical with KTA 3405) Integrale Leckratenpriifung des Sicherheitsbehalters mit der Absolutdruckmethode (Integral Test for Leakage Rate of the Containment by Absolute Pressure Method) (Identical with DIN 25436) Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors
App
75
Pub
7.80
Pub
2.79
10.78
11.5 No.
Issuing B o d y (Country)
11
Containment
11.5
Penetrations and Locks
DIN 25406 Teil 1
DIN
DIN 25406 Teil 2
DIN
DIN 25431
DIN
DIN 25438
DIN
IEEE 317
IEEE
KTA 3402
KTA
KTA 3403
KTA
KTA 3404
KTA
KTA 3409
KTA
RDT P3-1T
ORNL
R.G.1.63
USNRC
R.G. 1.70.2
USNRC
Status
Title
(Remarks)
Schleusen am Reaktorsicherheitsbehalter von Kernkraftwerken; Personenschleusen, Sicherheitstechnische Anforderungen (Locks at Reactor Safety Containments of Nuclear Power Plants; Personal Locks, Safety Requirements) (Identical with KTA 3402) Schleusen am Reaktorsicherheitsbehalter von Kernkraftwerken; Materialschleusen, Sicherheitstechnische Anforderungen (Locks at Reactor Safety Containments of Nuclear Power Plants; Material Locks, Safety Requirements) (Identical with KTA 3409) Kabeldurchfiihrungen im Reaktor-Sicherheitsbehalter; Sicherheitstechnische Anforderungen (Electric Penetration Assemblies in Containment Structures; Safety Requirements) (in Press; Identical with KTA 3403) AbschlieBung der den Reaktorsicherheitsbehalter durchdringenden Rohrleitungen im Falle einer Freisetzung von radioaktiven Stoffen innerhalb des Reaktorsicherheitsbehalters (Sealing of the Containment Penetrating Piping in the Case of Release of Radioactivity within the Containment) (Identical with KTA 3404) Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations Schleusen am Reaktorsicherheitsbehalter von Kernkraftwerken - Personenschleusen (Locks in the Containment of Nuclear Power Plants, Personnel-Locks) (Available also in English; Identical with DIN 25406 Teil I) Kabeldurchfuhrungen im Reaktorsicherheitsbehalter von Kernkraftwerken (Electric Cable Penetrations in Containment of Nuclear Power Plant) (Identical with DIN 25431) AbschlieBung der den Reaktorsicherheitsbehalter durchdringenden Rohrleitungen im Falle einer Freisetzung von radioaktiven Stoffen innerhalb des Reaktorsicherheitsbehalters (Sealing of the ' Containment Penetrating Piping in the Case of Release of Radioactive Material within the Containment) (Identical with DIN 25438) Schleusen am Reaktorsicherheitsbehalter von Kernkraftwerken - Materialschleusen (Locks in the Containment of Nuclear Power Plants, Material-Locks) (Identical with DIN 25406 Teil 2) Electric Penetration Assemblies in Containment Structures (IEEE 317 with additional requirements) Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants Additional Information: Air Filtration Systems and Containment Sumps for Nuclear Power Plants (See also R.G. 1.70)
Pub
4.77
Pub
2.80
Drf
7.77
Pub
76
Pub
11.76
Pub
10.80
Drf
6.77
Pub
679
Pub
179
Iss
7.78
Iss
12.73
157
11.5 RG 5.12
158
USNRC
General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials (Under Revision)
Iss
11.73
11.6 No. 11
Issuing B o d y (Country)
Title
Status
/Remarks)
Containment
11.6 Isolation ANS-562 /ANSI N271 RDT E 1-13T
ANS
Containment Isolation Provisions for Fluid Systems
App
ORNL
Valve, Isolation, Butterfly Type
RDT E 1-31T
ORNL
Carbon Steel Isolation Valves
RDT M 12-1T
ORNL
RDT M 12-2T
ORNL
RDT M 12-3T
ORNL
RDT M 12-4T
ORNL
Test Requirements for Thermal Insulating Materials for Use on Austenitic Stainless Steel Calcium Silicate Block and Pipe Thermal Insulation (ASTM C 533 with additional requirements) Mineral Fiber Hydraulic-Setting Thermal Insulating and Finishing Cement (ASTM C 449 with additional requirements) Reflective Insulation
872 Pub Amm 5.74 4 73 Pub Amm 5.74 Pub 10.72
RDT M 12-5T
ORNL
RDT M 12 6T
ORNL
R.G. 1.141
USNRC
VDE 0304 Teil 1
VDE
Thermal Insulation, Flexible or Molded, High Temperature, Low Conductivity Mineral Fiber Thermal Insulation, High-Temperature, Rigid, Flexible and Loose Fill (ASTM C 612 with additional requirements) Containment Isolation Provisions for Fluid Systems (Issued for Comments) Bestimmungen fur Priifverfahren zur Beurteilung des thermischen Verhaltens fester Isolierstoffe
76
6 71 Pub Amm 11 72 Pub 10.71 Amm 11.72 Pub 1.72 Amm 10.74 5.72 Pub Amm 473 373 Pub Iss
4.78
Pub
7.59
159
12.1 No. 12
Issuing Body (Country) Quality Assurance
12.1 General M 63-001
AFNOR
ANS-15.8 /ANSI N402 ANSI N45.2
ANS
ANSI N45.2.23
ANSI
ANSI N46.2
ANSI
ASME JC 8-9
ASME /ACI ASME
ASME NQA-1
ANSI
ASME /ANSI ASME /ANSI
QA-76-2 N45.2 QA-76-9 N45.29
ASME
ASME /ANSI ASME /ANSI ASME /ANSI
QA-76-10 N45.2.10 QA-76-12 N45.2.12 QA-76-13 N45.2.13
ASME
ASME QA-76-20 /ANSI N45.2 20
ASME
BS 4891 BS 5882
BSI BSI
CSA N285.1
CSA
CSA Z299.1 CSA Z299 2 CSA Z299.3 IAEA 50-C-QA
CSA CSA CSA IAEA
IAEA50-SG-QA1
IAEA
IAEA 50-SG-QA2
IAEA
IAEA 50-SG-QA3
IAEA
IAEA 50-SG-QA7
IAEA
IAEA 50-SG-QA8
IAEA
IAEA50-SG-QA10 IAEA 50-SG-QA11
IAEA IAEA
ISO 6215 JIS Z8101
ISO JIS
ASME
ASME ASME
KTA 1401
KTA
RDT F 2-2
ORNL
160
Status
Title (Remarks/
Energie nucleaire - Assurance de la qualite des centrales nucleaires Quality Assurance Program Requirements for Research Reactors Quality Assurance Program Requirements for Nuclear Facilities Qualification of Quality Assurance Program Audit Personnel for Nuclear Facilities Quality Assurance Program Requirements for Post Nuclear Fuel Cycle Facilities Material Manufacturers Quality System Program Quality Assurance Program Requirements for Nuclear Power Plants Quality Assurance Program Requirements for Nuclear Facilities Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants Quality Assurance Terms and Definitions (Under Revision) Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants (Under Revision) Supplementary Quality Assurance Requirements for Subsurface Investigation Prior to the Construction Phase of Nuclear Power Plants A Guide to Quality Assurance Total Quality Assurance Programme for Nuclear Power Plants General and Construction Requirements for CANDU Nuclear Power Plant Components Quality Assurance Program Requirements Quality Control Program Requirements Quality Verification Program Requirements Quality Assurance for Safety in Nuclear Power Plants, Code of Practice Preparation of the Quality Assurance Programme for Nuclear Power Plants Quality Assurance Records Systems for Nuclear Power Plants Quality Assurance in the Procurement of Items and Services for Nuclear Power Plants Quality Assurance Organization for Nuclear Power Plants Quality Assurance in the Manufacture of Items for Nuclear Power Plants Quality Assurance Auditing for Nuclear Power Plants Quality Assurance in the Procurement, Design and Manufacture of Nuclear Fuel Assemblies Nuclear Power Plants - Quality Assurance Glossary of Terms Used in Quality Control (Available also in English) Allgemeine Anforderungen an die Qualitatssicherung (General Requirements for Quality Assurance) Quality Assurance Program Requirements
Ust App
76
Pub
77
Pub
78
Pub
78
Drf
6.78
Iss
1079
Pub
77
App
74
App
73
Pub
77
App
76
Pub
9.79
Pub Pub
72 80
App
75
Iss Iss Iss Pub
78 79 79 78
Ust Pub
79
Pub
79
Ust Ust Ust Ust Pub Pub
80 63
Pub
2.80
Pub Amm
8.73 9.79
12.1 No.
Issuing Body (Country)
RDT F 2-4T LBG/2
ORNL SAAEB
RG. 1.38
USNRC
RG. 1.74 RG. 1.88
USNRC USNRC
RG. 1.116
USNRC
R G 1 123
USNRC
RG. 1.144
USNRC
RG. 2.5
USNRC
RG. 3.3
USNRC
10 CFR 50 Appendix B USNRC
Title
Status
(Remarks)
Quality Verification Program Requirements Licensing of Nuclear Installations: A Guide to the Requirements for Quality Assurance Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants Quality Assurance Terms and Definitions Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants Auditing of Quality Assurance Programs for Nuclear Power Plants Quality Assurance Program Requirements for Research Reactors Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
Pub Iss
12.74 10.73
Iss
5.77
Iss Iss
2.74 10.76
Iss
5.77
Iss
7 77
Iss
9 80
Iss
10.77
Iss
3.74
161
12.2 No. 12
Issuing Body /Country)
Status
Quality Assurance
12.2 C o n s t r u c t i o n ANSI N46.2 11
ANSI
ANSI N46.2.13
ANSI
ASME QA-76-2.3 /ANSI N45.2.3
ASME
ASME QA-76-5 /ANSI N45.2 5
ASME
ASME QA-76-6 /ANSI N45.2.6
ASME
ASME QA-76-8 /ANSI N452.8
ASME
ASME QA-76-11 /ANSI N45.2.11
ASME
BS 5882
BSI
CSA N285.1
CSA
IAEA 50-SG-QA4
IAEA
IAEA 50-SG-QA6
IAEA
R.G. 1.28
USNRC
R.G. 1.64
USNRC
R.G. 1.70.6
USNRC
R.G. 1 94
USNRC
Task No. RS 908-5
USNRC
162
Title (Remarks)
Quality Assurance Requirements for the Design of Nuclear Fuel Reprocessing Facilities Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Fuel Reprocessing Facilities Housekeeping During the Construction Phase of Nuclear Power Plants (Addenda Provided) Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel, Soils and Foundation During the Construction Phase of Nuclear Power Plants Qualifications of Inspection, Examination and Testing Personnel for the Construction Phase of Nuclear Power Plants Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants Quality Assurance Requirements for the Design of Nuclear Power Plants (Under Revision) Total Quality Assurance Programme for Nuclear Power Plants General and Construction Requirements for CANDU Nuclear Power Plant Components Quality Assurance During Site Construction of Nuclear Power Plants Quality Assurance in the Design of Nuclear Power Plants Quality Assurance Program Requirements (Design and Construction) (Issued for Comments) Quality Assurance Requirements for the Design of Nuclear Power Plants Additional Information: Quality Assurance During Design and Construction (See also R.G. 1.70) Quality Assurance Requirements of Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Under Revision; see also Task No. 908-5) Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations During the Construction Phase of Nuclear Power Plants (Proposed Revision to R.G. 1.94)
Pub
77
Pub
77
App
73
Pub
78
Pub
78
App
75
App
74
Pub
80
App
75
Ust Ust Iss
2.79
Iss
6.76
Iss
11.74
Iss
4.76
Iss
9.79
12.3 No. 12
Issuing Body (Country)
Title (Remarks!
Status
Quality A s s u r a n c e
12.3 O p e r a t i o n ANS-3.2 /ANSI N18.7
ANS
ANS-14.1 /ANSI N394 ANSI N46.2.13
ANSI
ANS
BS 5882
BSI
DIN 25451
DIN
IAEA 50SG-QA5
IAEA
KTA 1201
KTA
KTA 1201
KTA
R.G. 1.33
USNRC
R.G.1.39
USNRC
R.G. 1.70.11
USNRC
R.G. 4.15
USNRC
Task No. RS 902-4
USNRC
Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants (Revision of ANSI N18.7-1972) Operation of Fast Pulse Reactors
App
76
App
75
Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Fuel Reprocessing Facilities Total Quality Assurance Programme for Nuclear Power Plants Anforderungen an das Betriebshandbuch; Sicherheitstechnische Anforderungen (Requirements for the Operational Manual; Safety Requirements! (Identical with KTA 1201) Quality Assurance During Operation of Nuclear Power Plants Anforderungen an das Betriebshandbuch (Requirements for the Operational Manual) (Identical with DIN 25451) Anforderungen an das Betriebshandbuch (Requirements for the Operational Manual) Quality Assurance Program Requirements (Operations) (Under Revision; see also Task No. RS 902-4/ Housekeeping Requirements for Water-Cooled Nuclear Power Plants Information for Safety Analysis Reports - Quality Assurance During Operations Phase (See also R.G. 1.70) Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment Quality Assurance Program Requirements (Operation) (Proposed Revision to R.G. 1.33)
Pub
77
Pub
80
Pub
9.78
Ust Pub
278
Drf
10.79
Iss
278
Iss
9.77
Iss
75
Iss
2.79
Iss
8.79
163
12.4 No. 12
Issuing Body (Country)
Status
(Remarks)
Quality A:ssurance
12.4 Cleanliness ASME QA-76-2.1 /ANSI N45.2.1
ASME
DIN 25410
DIN
DIN 25410 Teil 1
DIN
DIN 25410 Teil 2
DIN
DIN 25410 Teil 3
DIN
DIN 25410 Teil 4
DIN
DIN 53781
DIN
RDT A 1-5T
ORNL
RDTF 5-1T
ORNL
RDT F 5-9T R.G. 1.37
ORNL USNRC
164
Title
Cleaning of Fluid Systems and Associated Components for Nuclear Power Plants (For Public Review and Comments) Kerntechnische Anlagen; Oberflachensauberkeit von Bauteilen (Nuclear Facilities; Surface Cleanliness of Components) Kerntechnische Anlagen; Oberflachensauberkeit von Bauteilen, Sauberkeitsstufen (Nuclear Facilities; Clean Conditions of Components, Classes of Clean Condition) Kerntechnische Anlagen; Oberflachensauberkeit von Bauteilen, Reinigung und Konservierung von Kreislaufsystemen emschlieSlich zugehoriger Komponenten (Nuclear Facilities; Surface Cleanliness of Components, Cleaning and Preserving of Fluid Systems and Associated Components) Kerntechnische Anlagen; Oberflachensauberkeit von Bauteilen, Anforderungen an die Verpackung (Nuclear Facilities; Clean Conditions of Components, Requirements for Packaging) Kerntechnische Anlagen; Oberflachensauberkeit von Bauteilen, MaRnahmen auf der Baustelle (Nuclear Facilities; Clean Conditions of Components, Measures on the Building Site) Priifung von Beschichtungsstoffen; Verfahren zur Priifung der Bestandigkeit von Beschichtungen gegen ionisierende Strahlung in kerntechnischen Anlagen Purity Requirements for Operating Sodium Reactor Systems Cleaning and Cleanliness Requirements for Nuclear Components Sodium Removal Processes Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants
Drf
1.78
Pub
6.74
Drf
10.79
Pub
2.77
Pub
8.79
Pub
8.79
Pub
4.80
Pub
3.76
Pub
1.78
Pub Iss
4.77 3.73
12.5 No. 12
Issuing Body (Country)
Status
Title
(Remarks)
Quality A;ssurance
12.5 Protectives Coatings, De ANSI N13.12 ANSI ANSI N101.2
ANSI
ANSI N101 4
ANSI
ANSI N512 ASTM D 3911
ANSI ASTM
ASTM D 3912
ASTM
ASTM D 3913
ASTM
BS 4247
BSI
BS 4247 Part 1
BSI
BS 4247 Part II DIN 25415 Teil 1
BSI DIN
DIN 25415 Teil 2
DIN
GOST 9.036
GOST
GOST 9.037
GOST
GOST 9.059
GOST
GOST 19465
GOST
JIS Z4317
JIS
JISZ4318
JIS
JIS Z4507
JIS
JIS Z8122 NCRP Report No.3
JIS NCRP
AECP 68
UKAE,
Control of Radioactive Surface Contamination on Materials. Equipment and Apparatus to be Released for Uncontroled Use Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities Quality Assurance for Protective Coatings Applied to Nuclear Facilities Protective Coatings (Paints) for the Nuclear Industry Evaluation of Coatings Used in Light Water Nuclear Power Plants at Simulated Loss of Coolant Accident (LOCA) Conditions, Test Method Determining the Chemical Resistance of Coatings Used in Light Water Nuclear Power Plants Evaluating the Physical Properties of Coatings Used in Light Water Nuclear Power Plants, Test Method The Assessment of Surface Materials for Use in Radioactive Areas Method of Test for the Measurement and Evaluation of the Decontamination Factor Guide of the Selection of Materials Dekontamination von radioaktiv kontaminierten Oberflachen; Verfahren zur Prufung und Bewertung der Dekontaminierbarkeit (Decontamination of Radioactive Contaminated Surfaces; Method of Test for Ease of Decontamination and Interpretation of Results) (For trial use and comments; Available also in English) Dekontamination von radioaktiv kontaminierten Oberflachen; Bestimmung der Oberflachenkontamination (Decontamination of Radioactive Contaminated Surfaces; Determination of Surface Contamination) (Available also in English) Einheitliches System des Korrosions- und Alterungsschutzes; Strahlenresistente polymere Schutziiberziige; Klassifikation und Bezeichnungen nach Betriebsbedingungen Einheitliches System des Korrosions- und Alterungsschutzes; Entaktivierende polymere Schutziiberziige; Klassifikation und Bezeichnung nach Betriebsbedingungen Einheitliches System des Korrosions- und Alterungsschutzes; Schiitzende, isolierende, entaktivierende und akkumulierende Polymeruberzuge; Klassifikation und Bezeichnungen Polymerer Schutzanstrich fur die Verbesserung der Strahlungsumstande Gas Flow Counter Type Survey Meters for Radioactive Surface Contamination Gas Filled Counter Type Survey Meters for Radioactive Surface Contamination Testing and Calculating Methods of Contamination and Decontamination Index of Radioactive Surface Contamination Glossary of Terms for Contamination Control Control and Removal of Radioactive Contamination in Laboratories Coatings and Their Application (Under Revision)
Pub
79
Pub
72
Pub
72
Pub Pub
74 80
Pub
80
Pub
80
Pub Rev Pub Pub
67 6 79 69 10.80
Pub
4.77
Pub
74
Pub
74
Pub
75
Pub
74
Pub
76
Pub
76
Pub
75
Pub Pub
74 51
Iss
71
165
12.5 No.
Issuing Body (Country)
AECP 1002
UKAEA
AECP 1057
UKAEA
AESS 6066 Part 1
UKAEA
R.G. 1.54
USNRC
R.G. 3.21
USNRC
R G. 3.30
USNRC
166
Title
Status
(Remarks)
The Coating of Surfaces Requiring Decontamination (Under Revision) Radioactive Decontamination (Provisional only) Surface Materials for Use in Radioactive Areas Methods of Testing for Decontamination Factor Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing Plants and to Plutonium Processing and Fuel Fabrication Plants Selection, Application, and Inspection of Protective Coatings (Paints) for Fuel Reprocessing Plants
Iss
69
Iss
79
Iss
76
Iss
6.73
Iss
3.74
Iss
5 77
13 No.
Issuing Body (Country)
Title
Status
(Remarks)
13 Reactor Cooling S y s t e m s Decay Energy Release Rates Following Shutdown of ANS-5.1 ANS Uranium-Fueled Thermal Reactors /ANSI N18.6 Design Criteria for Auxiliary Feedwater Systems for ANS-51.10 ANS PWR Plants ANS ANS-53.13 Design Criteria for the Helium Purification System of Gas-Cooled Reactor Plants (Draft for Comments) ANS-53.14 Design Criteria for the Helium Storage Systems of ANS Gas-Cooled Reactor Plants (Draft for Comments) ANS-53.15 Design Criteria for the Reactor Cooling Water ANS System of Gas-Cooled Reaktor Plants ANS-53.19 GCR Plant Chilled Water System ANS ANS-53.20 GCR Plant Secondary Coolant System ANS ANS-56.5 PWR and BWR Containment Spray System Design ANS Criteria ANS-59.1 Safety Related Cooling Water Systems in Nuclear ANS Power Plants BMI GMBI. 1978 S. 294 Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Prufung erforderlichen Informationen uber die liiftungstechnischen Anlagen, die Not- und Nachkuhlsysteme einschlieUlich Nachkuhlkette und Rohrleitungen, Pumpen und Armaturen des Hauptkuhlkreises vom 17.5.1978 IAEA IAEA 50-SG-D6 Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants USNRC-Standard Review Plan, Section 9.2 2 USNRC PSRP-9.2.2 "Reactor Auxiliary Cooling Water System" (Proposed Revision) R.G. 1.1 Net Positiv Suction Head for Emergency Core USNRC Cooling and Containment Heat Removal System Pumps (Safety Guide 1) R.G 1.27 USNRC Ultimate Heat Sink for Nuclear Power Plants (Issued for Comments) R.G. 1.68.1 USNRC Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants R.G. 1.79 USNRC Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors R.G. 1.82 USNRC Sumps for Emergency Core Cooling and Containment Spray Systems R.G. 1.139 USNRC Guidance for Residual Heat Removal (Issued for Comments) 10 CFR 50 Appendix K USNRC ECCS Evaluation Models VdTUV Wei 19 VdTUV Verkniipfung des Brennelementbeckenkuhlsystems mit dem Not- und Nachkuhlsystem bei Druckwasserreaktoren der KWU
Pub
10.79
App
11.79
Drf
8.78
Drf
8.78
Ust Ust Ust Pub
1.75 1.75 11.79
Pub
10.79
Iss
5.78
Ust Iss
10.79
Iss
11.70
Iss
1.76
Iss
1.77
Iss
9.75
Iss
6.74
Iss
5.78
Iss
1277
167
14.1 No.
Issuing Body (Country)
14
V e n t i l a t i o n and Air Cle;
14.1
General
ANS-56.6
ANS
ANS-56.7
ANS
ANSI N290
ANSI
ANSI N509
ANSI
B PVC Sec.lll Div.1
ASME
GMBI 1978 S. 294
BMI
DIN 1946 Teil 1 DIN 25414
DIN
GOST 15485 KTA 3601
GOST KTA
RDT E 9-7T
ORNL
BAnz. Nr. 132/1975
SSK
AECP 1054 R.G. 1.52
UKAEA USNRC
R.G 1.70.2
USNRC
R.G. 1.140
USNRC
R.G. 3.12
USNRC
168
DIN
Title (Remarks)
Pressurized Water Reactor Containment Ventilation Systems Boiling Water Reactor Containment Ventilation Systems Design, Construction and Operation of Ventilation Systems for Mixed Oxide (U, PU) Fuel Fabrication Plants Nuclear Power Plant Air Cleaning Units and Components (Under Revision) Boiler and Pressure Vessel Code; Division I: Subsection NB - Class 1 Components, Subsection NC - Class 2 Components, Subsection ND Class 3 Components, Subsection NE - Class MC Components, Subsection NF - Component Supports, Subsection NG • Core Support Structures, Appendices (Regular Addenda and Revisions Provided) Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber die luftungstechnischen Anlagen, die Not- und Nachkuhlsysteme einschlie&lich Nachkuhlkette und Rohrleitungen, Pumpen und Armaturen des Hauptkiihlkreises vom 17.5.1978 Raumlufttechnik, Grundlagen (Room Ventilation Technic, Fundamentals) Luftungstechnische Anlagen in Kernkraftwerken; Sicherheitstechnische Anforderungen (Ventilating Systems in Nuclear Power Plants, Safety Requirements) (Identical with KTA 3601) Radioaktive Aerosole; Klassifikation Luftungstechnische Anlagen in Kernkraftwerken (Ventilating Systems in Nuclear Power Plants) (Identical with DIN 25414) Fans, Blowers, and Compressors for Dry Gas Circulation Abtrennung von Krypton-85 aus den Abgasen von Wiederaufarbeitungsanlagen vom 2.7.1975 Radioactive Ventilation Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light-Water-Cooled Nuclear Power Plants Additional Information: Air Filtration Systems and Containment Sumps for Nuclear Power Plants (See also R.G. 1.70) Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants (Under Revision) General Design Guide for Ventilation Systems of Plutonium Processing and Fuel Fabrication Plants
Status
App
78
App
78
Pub
79
App
76
Iss
74
Iss
5.78
Drf
6.79
Drf
12.79
Pub Drf
70 10.79
Pub
4.73
Iss
7.75
Iss Iss
79 3.78
Iss
12.73
Iss
10.79
Iss
8.73
14.1 No.
Issuing Body
(Country)
RG. 3.32
USNRC
VDI 2051 VDI 3673 VDI 3801
VDI VDI VDI
Title
Status
(Remarks)
General Design Guide for Ventilation Systems for Fuel Reprocessing Plants (Issued for Comments} Lüftung von Laboratorien Druckentlastung von Staubexplosionen Betreiben von Raumlufttechnischen Anlagen (in Press)
Iss
9.75
Pub Pub Drf
9.66 6.75
169
14.2 No.
Issuing Body (Country)
Title
Status
(Remarks)
14
Ventilatiion and Air Cleaning Testing of S y s t e m s AACC CS-6T AACC Testing and Certification of "Particulate Clean" Rooms ANSI N101.1 ANSI Efficiency Testing of Air Cleaning Systems Containing Devices for Removal of Particles ANSI N510 ANSI Testing of Nuclear Air-Cleaning Systems (Under Revision) ASHRAE 52-68 ASHRAE Method of Testing Air Cleaning Devices Used in General Ventilation for Removing Particulate Matter DIN 4102 DIN Brandverhalten von Baustoffen und Bauteilen; Teil 6 Liiftungsleitungen, Begriffe, Anforderungen und Priifungen (Behaviour of building materials and components in fire; ventilation ducts, definitions, requirements and tests) DIN 25414 DIN Liiftungstechnische Anlagen in Kernkraftwerken; Sicherheitstechnische Anforderungen (Ventilating Systems in Nuclear Power Plants, Safety Requirements) (Identical with KTA 3601) IfBT Bau- und Priifgrundsatze fur Absperrvorrichtungen gegen Feuer und Rauch in Luftungsleitungen, Institut fur Bautechnik KTA Liiftungstechnische Anlagen in Kernkraftwerken KTA 3601 (Ventilating Systems in Nuclear Power Plants) (Identical with DIN 25414) USNRC Design, Testing, and Maintenance Criteria for R.G. 1.52 Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light-Water-Cooled Nuclear Power Plants R.G. 1.140 USNRC Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants (Under Revision) USNRC Efficiency Testing of Air-Cleaning Systems R.G. 3.2 Containing Devices for Removal of Particles VDI 2044 VDI Abnahme- und Leistungsversuche an Ventilatoren 14.2
170
Pub
80
Pub
72
App
75
Pub
69
Pub
9.77
Drf
12.79
Pub
12.71
Drf
10.79
Iss
3.78
Iss
10.79
Iss
1.73
Pub
10.66
14.3 No. 14
Issuing Body (Country)
Title
Status
(Remarks)
V e n t i l a t i o n and Air Cleaning
14.3 Filters and A b s o r b e r s NF X44-0 AFNOR
Iss
72
ANSI N509
App
76
GMBI. 1976 S. 168
BS 3928 DIN 8558 Teil 1
DIN 24184 DIN 24185 Teil 1 DIN 24185 Teil 2
EUROVENT4/4 JIS Z4812 RDT E 9-1T RDT E 11-2T RDTM 16-1T RDT M 16-3T BAnz. Nr. 8/1977 AESS 30/93402
AESS 30/93450
AESS 30/93700 AESS(NF)30/93470 AESS(NF)30/94325 UL586 R.G. 1.140
R.G. 3.2
Methode de mesure de I'efficacite des filtres au moyen d'un aerosol d'uranine (fluoresceinel Nuclear Power Plant Air Cleaning Units and Components (Under Revision) BMI Auslegungsrichtlinien und -richtwerte fur Jod-Sorptionsfilter zur Abscheidung von gasformigem Spaltjod in Kernkraftwerken vom 25.2.1976 BSI Sodium Flame Test for Air Filters Gestaltung und Ausfiihrung von DIN SchweiSverbindungen; Behalter und Apparate aus Stahl fur die chemische Industrie (Design and performance of welded joints; steel pressure vessels and apparatus used in chemical industry] DIN Typpriifung von Schwebstoffiltern (Type test of high efficiency submicron particulate airfilter) DIN Luftfilter fur die allgemeine Liiftungstechnik; Begriffe, Einheiten (Air filter for the general ventilation technic; definitions, units) DIN Priifung von Luftfiltern fur die allgemeine Luftungstechnik; Filterklassen, Einteilung, Kennzeichnung, Priifung (Type test of air filters for the general ventilation technic; filterclassification, identification, test) EUROVENT Sodium Chloride Aerosol Test for Filters Using Flame Photometric Technique JIS HEPA Filters for Radioactive Aerosols ORNL HEPA Filters ORNL Filter for Sodium Service ORNL Gas-Phase Adsorbents for Trapping Radioactive Iodine and Iodine Compounds ORNL HEPA Filter Medium, Glass Fiber (MIL-F-51079 with modifications and additional requirements) SSK BackfittingmaSnahmen fur die Jodfilterung von Kernkraftwerken vom 10.12.1976 UKAEA Filter Inserts High Efficiency Particulate Air (HEPA), Non Combustible Glass Fibre Paper 25 to 500 Litres per Second (Formerly AESS 12050) UKAEA Filters, High Efficiency Particulate Air (HEPA), Non Combustible Glass Fibre Paper 5 and 25 Litres per Second (Formerly AESS 12051) UKAEA Spark Arrestors UKAEA High Efficiency Low Temperature Filter Inserts (Formerly AESS 30/93320/7) UKAEA Filter Unit, High Efficiency Particulate Air (HEPA), Non Combustible, Glass Fibre Paper Insert with Spark Arrestor. 350 Litres per Second UL High Efficiency Air Filter Units USNRC Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants (Under Revision) Efficiency Testing of Air-Cleaning Systems USNRC Containing Devices for Removal of Particles ANSI
Iss
2.76
Pub Drf
69 4.79
Pub
10.74
Pub
10.80
Pub
10.80
Pub
12.76
Pub Pub Pub Pub
75 8.74 1.73 12.77
Pub
3.74
Iss
1.77
Iss
76
Iss
77
Iss Iss
76 76
Iss
78
Pub Iss
77 10.79
Iss
1.73
171
15.1 Issuing Body (Country)
No. 15
Nuclear Material Mana
15.1 General ANSI N12.1 ANSI N15.8
ANSI ANSI
ANSI N15.26
ANSI
ANSI N46.2
ANSI
ASTM C 859 ASTM E 669 CNEN NE2.01
ASTM ASTM CNEN
SI 62/2641
DEGR
DIN 25400
DIN
DIN 25401 Teil 5 DIN 25401 Teil 6
DIN
DIN 25425 Teil 1 DIN 25425 Teil 2
DIN
DIN 25428
DIN
GOST 20286 GO ST 22574 ISO 3925
GOST GOST ISO
ISO/DP 5568 R.G. 5.30
ISO USNRC
Task No. MP 711-4
USNRC
10CFR 70 VdTUV Wei 28
USNRC VdTUV
172
Status
Title (Remarks)
DIN
DIN
Fissile Material Symbol Nuclear Material Control Systems for Nuclear Power Reactors Physical Protection of Special Nuclear Materials Within a Facility (Withdrawn 10.79) Quality Assurance Program Requirements for Post Nuclear Fuel Cycle Facilities Definition of Terms Relating to Nuclear Materials Master Matrix for Nuclear Fuel Cycle Standards Physical Protection of Nuclear Materials and Facilities The Radioactive Substances (Civil Defense) Exemption Order 1962 Warnzeichen fur ionisierende Strahlung (Warning Symbol for Ionizing Radiation) Kerntechnik; Begriffe, Brennstoffkreislauf (Nuclear Technology; Terms and Definitions, Fuel Cycle) Kerntechnik; Begriffe, Isotopentrennung (Nuclear Technology; Terms and Definitions, Isotope Separation) Radionuklidlaboratorien; Regeln fur die Auslegung (Radioisotope Laboratories; Rules for Design) Radionuklidlaboratorien; SchutzmaBnahmen beim Umgang mit offenen radioaktiven Stoffen (Radioisotope Laboratories; Protective Measures when Handling Unsealed Radioactive Sources) Kerntechnische Anlagen; Lagerbecken fiir Brennelementbiindel von wassergekiihlten Leistungsreaktoren (Nuclear Facilities; Pool Facility for Fuel Assemblies for Watercooled Power Reactors) Radioaktive Verunreinigungen und Entaktivierung Spaltbares Kernmaterial Unsealed Radioactive Substances - Identification and Certification Proposal for a Fissile Material Symbol Materials Protection Contingency Measures for Uranium and Plutonium Fuel Manufacturing Plants Standard Format and Content for a Licensee Physical Security Plan for the Protection of Special Nuclear Material of Moderate or Low Stratetic Significance (Proposed R.G.) Domestic Licensing of Special Nuclear Material Lagerung von Brennelementbundeln im Lagerbecken wassergekuhlter Leistungsreaktoren (see also DIN 25428)
Pub Pub
71 74
Pub
76
Pub
78
Pub Pub Iss
78 79 77
Iss
62
Pub
5.66
Drf
2.79
Drf
2.79
Pub
3.77
Drf
3.79
Pub
8.76
Pub Pub Pub
74 77 78
Drf Iss
75 6.74
Iss
7.79
Iss
11.79
15.2 No. 15
Issuing Body (Country)
Status
Title (Remarks)
Nuclear Material M a n a g e m e n t
15.2 Lifting E q u i p m e n t ANSI N14.6 ANSI ASME QA-76-15 ASME /ANSI N45.2.15 KTA 3902 KTA RDT F 8-6T
ORNL
RDT M 13-1T RDT M 14-1T
ORNL ORNL
R.G. 1.104
USNRC
R.G. 7.3
USNRC
RG.74
USNRC
VdTUV Wei 2
VdTUV
VdTUV Wei 4
VdTUV
VdTUV Wei 20
VdTUV
Shipping Cask Lugs and Associated Lifting Devices Hoisting, Reggings, and Transporting of Items for Nuclear Power Plants Hebezeuge in kerntechnischen Anlagen (Lifting Equipment for Nuclear Facilities] (Available also in English) Hoisting and Rigging of Critical Components and Related Equipment Sodium Purchase Specifications Sodium Cover Gas - Purchase Specifications Overhead Crane Handling Systems for Nuclear Power Plants (Withdrawn 8 79) Procedures for Picking Up and Receiving Packages of Radioactive Material (Issued for Comments) Leakage Tests on Packages for Shipment of Radioactive Materials (Issued for Comments) Absturz einer Last, auch wenn das Hebezeug den erhohten Anforderungen der KTA-Regel "Hebezeuge in kerntechnischen Anlagen" entspricht (See also KTA 3902) Priifumfang fur Hebezeuge in kerntechnischen Anlagen - Wiederkehrende Priifungen Absturz eines Hebezeuges
Pub Ust
78
Pub
6.78
Pub
180
Pub Pub Amm
9.73 7.72 1.75
Iss
5.75
Iss
6.75
Iss
10.80
Iss
5.76
Iss
2.78
173
15.3 No. 15
Issuing Body (Country)
Title (Remarks)
Status
Nuclear Material Management
15.3 Handling and Storage ANS-8.7 /ANSI N16.5 ANS-57.2 /ANSI N210 ANSI N14.6 ANSI N305 ASME /ANSI ASTM ASTM
QA-76-2.2 N45.2.2 C 852 E 309
ANS ANS ANSI ANSI ASME ASTM ASTM
GMBI. 1978 S. 598
BMI
GMBI. 1979 S. 91
BMI
BS 3598
BSI
SI 62/2646
DEGR
*
DERRT
DIN 25409 Bbl
DIN
DIN 25409 Teil 1
DIN
DIN 25409 Teil 2
DIN
DIN 25409 Teil 3
DIN
DIN 25409 Teil 4
DIN
174
Guide for Nuclear Criticality Safety in the Storage of Fissile Materials Design Objectives for Light Water Reactor Spent Fuel Facilities at Nuclear Power Stations Shipping Cask Lugs and Associated Lifting Devices Design Objectives for Highly Radioactive Solid Material Handling and Storage Facilities in a Reprocessing Plant Packaging, Shipping, Receiving, Storage and Handling of Items tor Nuclear Power Plant Design Criteria for Plutonium Gloveboxes Recommended Practice for Eddy Current Testing of Steel Tubular Products with Magnetic Saturation Richtlinien uber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen uber das Druckabbausystem (DAS) bei Siedewasserreaktoren, die Dampferzeuger und Systeme zur Handhabung und Lagerung sonstiger radioaktiver Stoffe vom 30.10.1978 Genehmigungen gemaB §3 Abs. 1 StrlSchV oder 56 AtG fur die Zwischenlagerung von abgereichertem bzw. naturlichem und angereichertem Uran in Form von Uranhexafluorid (UF6); hier: Genehmigungsvoraussetzungen und Auflagen vom 15.2.1979 Recommendations for Criticality Safety in Handling and Processing Fissile Materials The Radioactive Substances (Storage in Transit) Exemption Order 1962 Code of Practice for the Storage of Radioactive Material in Transit Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Hinweise fur die Verwendung (Remote Handling Devices for Use behind Shielding Walls; Recommendations for Use) Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Ferngreifer, MaBe (Remote Handling Devices for Use behind Shielding Walls; Remote Handling Tongs; Dimensions) Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Parallel-Manipulatoren mit 3 Gelenken, MaBe (Remote Handling Devices for Use behind Shielding Walls; Master-Slave Manipulators with three Hinges; Dimensions) Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Parallel-Manipulatoren in Teleskopbauart, MaBe (Remote Handling Devices for Use behind Shielding Walls; Telescopic Master-Slave Manipulators; Dimensions) Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Parallel-Manipulatoren in Teleskopbauart, Anforderungen (Remote Handling Devices for Use behind Shielding Walls; Telescopic Master-Slave Manipulators, Requirements)
App
75
App
76
Pub Pub
78 75
Pub
78
Pub Pub
77 77
Iss
10.78
Iss
2.79
Pub
70
Iss
62
Iss
70
Pub
11.74
Pub
11.74
Pub
11.74
Pub
11.74
Pub
2.77
15.3 No.
Issuing Body (Country)
DIN 25409 Teil 5
DIN
DIN 25409 Teil 6
DIN
DIN 25409 Teil 7
DIN
DIN 25409 Teil 8
DIN
DIN 25412 Teil 1
DIN
DIN 25412 Teil 1 Bbl.
DIN
DIN 25412 Teil 2 DIN 25425 Teil 2
DIN
DIN 25428
DIN
GOST 21470
GOST
GOST 21471
GOST
IAEA 50-SG-D10
IAEA
NCRP Report No .30 AECP 59
NCRP UKAEA
AESS 44/23370
UKAEA
AESS(NF|34/39900 R.G. 1.13
UKAEA USNRC
R G. 1.25
USNRC
R.G. 1.38
USNRC
R.G 1.104
USNRC
DIN
Title
Status
(Remarks)
Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Parallel-Manipulatoren mit 3 Gelenken, Anforderungen (Remote Handling Devices for Use behind Shielding Walls; Master-Slave Manipulators with three Pivots, Requirements! Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Ferngreifer, Anforderungen (Remote Handling Devices for Use behind Shielding Walls; Remote Handling Tools, Specifications) Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Kraftmanipulatoren mit elektrischen Antrieben, Anforderungen und Priifungen (Remote Handling Devices for Use behind Shielding Walls; Power Manipulators, Requirements and Tests) Fernbedienungsgerate zum Arbeiten hinter Schutzwanden; Kraftmanipulatoren, Bedienteile, Anordnung und Kennzeichnung (Remote Handling Devices for Use behind Shielding Walls; Power Manipulators, Operating Devices, Arrangement and Designation) Laboreinrichtungen; Handschuhkasten, MaSe und Anforderungen (Glove Boxes; Dimensions and Requirements) Laboreinrichtungen; Handschuhkasten, Mafie und Anforderungen, Beispiele fur Zusatzausrustungen (Glove Boxes; Accessories) Laboreinrichtungen; Handschuhkasten, Dichtheitsprufung (Glove Boxes; Leak Test) Radionuklidlaboratorien; SchutzmaBnahmen beim Umgang mit offenen radioaktiven Stoffen (Radioisotope Laboratories; Protective Measures when Handling Unsealed Radioactive Sources) Kerntechnische Anlagen; Lagerbecken fur Brennelementbiindel von wassergekiihlten Leistungsreaktoren (Nuclear Facilities; Pool Facility for Fuel Assemblies for Watercooled Power Reactors) Transportcontainer fOr ausgebrannte Brennelementengruppen von Kernenergiereaktoren Innencontainer und Kapseln fur ausgebrannte Brennelementengruppen von Kernenergiereaktoren Fuel Handling and Storage Systems in Nuclear Power Plants Safe Handling of Radioactive Materials Glove Boxes - Unshielded (Under Revision) Beaded Ambidexterous Lead Loaded Gloves for Glove Boxes Uranium Hexafluoride Container Design No 0236 Spent Fuel Storage Facility Design Basis (Issued for Comments) Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25, Under Revision) Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants Overhead Crane Handling Systems for Nuclear Power Plants (Withdrawn 8.79)
Pub
2.77
Pub
678
Drf
5.78
Drf
6.79
Pub
3.77
Pub
12.76
Pub
6.78
Drf
3.79
Pub
876
Pub
76
Pub
76
Ust Pub Iss
64 75
Iss
77
Iss Iss
76 12.75
Iss
3.72
Iss
5.77
175
15.3 No.
Issuing Body (Country}
R.G. 3.15
USNRC
R.G. 3.24
USNRC
R.G. 3.44
USNRC
Vd IUV Wei 28
VdTUV
Leg. Series 1965 No. 31/1201
(YUG)
176
Title
Status
(Remarks)
Standard Format and Content of License Applications for Storage Only of Unirradiated Reactor Fuel and Associated Radioactive Material Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation Standard Format and Content for the Safety Analysis Report to be Included in a License Application for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation (Water-Basin Type) Lagerung von Brennelementbundeln im Lagerbecken wassergekiihlter Leistungsreaktoren (see also DIN 25428) Regulation Concerning the Putting in Circulation and Handling of Radioactive Substances With an Activity Above a Certain Limit and the Protection Measures Against the Radiation from Such Sources
Iss
10.73
Iss
12.74
Iss
12.78
Iss
11.79
Iss
6.65
15.4 No. 15
Issuing Body (Country)
Title
Status
(Remarks/
Nuclear Materi al M a n a g e m e n t
15.4 T r a n s p o r t a t i o n and Packaging ANSI N14 ANSI Administrative Guide for the Liability Insurance Aspects of Shipping Nuclear Materials ANSI N14.1 Packaging of Uranium Hexafluoride for Transport ANSI ANSI N14.3 Packaging and Transportation of Radioactively ANSI Contaminated Biological Materials ANSI N14 5 ANSI Leakage Tests on Packages for Shipment of Radioactive Materials ANSI N14.7 ANSI Guide to Design and Use of Shipping Packages for Type A Quantities of Radioactive Liquids ANSI N14.9.1 ANSI Packaging Liquid Radioactive Wastes from Nuclear Power Plants ANSI N14.10.1 Administrative Guide for Packaging and Transporting ANSI Radioactive Materials ANSI N14.10 2 Administrative Guide for Obtaining Department of ANSI Transportation Special Permits for Radioactive Materials for Shipment ANSI N14.10.3 ANSI Administrative Guide for Verifying Compliance with Packaging ANSI N15.17 ANSI Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of SNM ANSI N679 ANSI Manuals for Use, Maintenance and Inspection of Type B Radioactive Materials Packaging ASME QA-76-2 2 ASME Packaging, Shipping, Receiving, Storage and /ANSI N45.2.2 Handling of Items for Nuclear Power Plant BMI RS 11-1 BMI Regelung der Rechtsetzungskompetenzen bei der Beforderung radioaktiver Stoffe und Regelung der Zustandigkeitsverteilung bei der Aufsicht uber die Beforderung radioaktiver Stoffe BS 3895 BSI Guide to the Design, Testing and Use of Packaging for the Safe Transport of Radioactive Materials CEA CEA IG 5 Norme d'identification des emballages contenant du plutonium, de I'uranium ou du thorium NF M 60-301 CEA Emballages pour matieres radioactives - Essai d'etancheite au contenu (Leakage Test for Packages Containing Radioactive Material] CNEN NE 5.01 CNEN Transport of Radioactive Materials CNEN NE 5.02 CNEN Design and Tests of Packaging of Radioactive Materials SI 62/2646 DEGR The Radioactive Substances (Storage in Transit) Exemption Order 1962 SI 1067 DEGR The Merchant Shipping 1965 (Dangerous Goods) Rules Amended by 1968 SI 332, and 1972 SI 666 BR 22426 DERRT Dangerous Goods and Conditions of Acceptance for Carriage by Freight Train and Passenger Train DERRT SI 1735 Radioactive Substances (Carriage by Road) Regulations DERRT SI 1827 The Radioactive Substances (Road Transport Workers) Regulations . DERRT Code of Practice for the Carriage of Radioactive Materials by Road Code of Practice for Conveyance Through Ports of DERRT Radioactive Materials DERRT Code of Practice for the Storage of Radioactive Material in Transit GOST 20.38.309 Komplexsystem allgemeiner technischer GOST Forderungen; Transportverpackungskomplexe fur ausgebrannte warmeabgebende Kernreaktorelemente
Pub
74
Pub Pub
71 73
Pub
77
Pub
75
Pub
76
Pub
73
Pub
73
Pub
75
Pub
75
Pub
76
Pub
78
Pub
76
Pub
64
Pub
12.77
Ust Ust 62 Iss Amm Iss
65 72 66
Iss
70
Iss
70
Iss
71
Iss
66
Iss
70
Pub
77
177
15.4 No.
Issuing Body (Country)
GOST 12916
GOST
GOST 21470
GOST
GOST 21471
GOST
IAEA 6
IAEA
ISO 2855
ISO
ISO/DP 7195
ISO
MSZ 14343 MSZ 14346 RDT E 12-4T
MSZH MSZH ORNL
RDT E 12-5T RDTE 12-6T RDT F 7-2T
ORNL ORNL ORNL
RDT F 8-7T
ORNL
RDT F 8-9T
ORNL
RDTF8-11T TS 2969
ORNL PAEC TSE
AECP 71 AECP 1006
UKAEA UKAEA
AECP 1023
UKAEA
AECP 1030
UKAEA
AECP 1040
UKAEA
AECP 1042
UKAEA
AECP 1052
UKAEA
AECP 1056 Part 1
UKAEA
AESS 6060
UKAEA
AESS 6067
UKAEA
R.G. 1.38
USNRC
R.G. 1.91
USNRC
R.G. 5.10
USNRC
178
Title (Remarks) Transportverpackungskomplexe fur radioaktive Stoffe; Klassifikation, Terminologie Transportcontainer fur ausgebrannte Brennelementengruppen von Kernenergiereaktoren Innencontainer und Kapseln fur ausgebrannte Brennelementengruppen von Kernenergiereaktoren Regulations for the Safe Transport of Radioactive Materials (Under Revision) Radioactive Materials - Packagings - Test for Contents Leakage and Radiation Leakage International Guide to the Packaging of Uranium Hexafluoride for Transport Packaging of Radioactive Materials Safe Transport of Radioactive Materials Shielded Shipping Cask for Spent Reactor Fuel Elements Operating Manuals for Fuel Shipping Containers Ancillary Features of Irradiated Fuel Shipping Casks Packaging, Packing, and Marking of Components for Shipment and Storage Transportation of Critical Components and Equipment Design Basis for Fuel and Irradiations Experiment Resistance to Shock and Vibration in Truck Transport Fuel Shipping Container Tiedown for Truck Transport Regulation on Transportation of Radioactive Material Radioactive Materials-Packaging-Tests for Contents Leakage and Radiation Leakage Sea Disposal Packages for Radioactive Waste Securing Radioactive Material Packages to Transport Vehicles Requirements for Timber and Cadmium Used in Wood/Cadmium Shielding, for Fissile Material Transport Packaging (Under Revision) Labelling and Marking of Packages for the Transport of Radioactive Materials Placarding of Road Vehicles Carrying Radioactive Materials Provision of Transport Packaging for Radioactive Materials (Under Revision) Type 'B' Packaging for Radioactive Materials Using Removable Head Drums as Outer Containers (Under Revision) Shielding Integrity Testing of Radioactive Material Transport Packaging - Gamma Shielding Fibreboard Cases and Internal Fitments for Radioactive Material Type 'A' Packaging (Under Revision) Testing the Integrity of Packaging Radiation Shielding by Scanning with Radiation Source and Detector Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants (Issued for Comments) Selection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of Special Nuclear Materials
Status Pub
75
Pub
76
Pub
76
Pub
73
Pub
76
Ust Pub 74 74 Pub Pub 8.73 Amm 12.73 Pub 1.75 Pub 1.79 Pub 9.75 Amm 1.76 Pub 1.76 Pub
2.75
Pub Iss
1.75 70
Iss Iss
71 79
Iss
71
Iss
77
Iss
77
Iss
69
Iss
73
Iss
77
Iss
73
Iss
77
Iss
5.77
Iss
2.78
Iss
7.73
15.4 No.
Issuing Body (Country)
R.G. 5.15
USNRC
R.G. 5.31
USNRC
R.G. 5.32 R.G. 5 56
USNRC USNRC
R.G. 5 57
USNRC
R.G. 5.60
USNRC
R.G. 7.1
USNRC
R.G. 7.2
USNRC
R.G. 7.5
USNRC
R.G. 7.6
USNRC
R.G. 7.7
USNRC
R.G. 7.8
USNRC
R.G. 7 9
USNRC
Task No. SG 908-4
USNRC
10 CFR 71
USNRC
10 10 10 10 10
CFR CFR CFR CFR CFR
71 71 71 71 71
Appendix Appendix Appendix Appendix Appendix
A B C D E
USNRC USNRC USNRC USNRC USNRC
MB P.5206
(BEL)
BGBI. I. S 341 /BGBI. I, S. 3187 BGBI I, S. 1008
(DEU)
BGBI. I. S. 1017
(DEU)
BGBI I, S. 1113 /BGBI I, S 3574
(DEU)
(DEU)
Title
Status
(Remarks)
Security Seals for the Protection and Control of Special Nuclear Material Specially Designed Vehicle and Armed Guards for Road Shipments of Special Nuclear Material Communication with Transport Vehicles Standard Format and Content of Safeguards Contingency Plans for Transportation (Issued for Comments) Shipping and Receiving Control of Special Nuclear Material (Under Revision; see also Task No SG 908-4) Standard Format and Content of Licensee Physical Protection Plan for Strategic Special Nuclear Material in Transit Administrative Guide for Packaging and Transporting Radioactive Material Packaging and Transportation of Radioactively Contaminated Biological Materials Administrative Guide for Obtaining Exemptions from Certain NRC Requirements Over Radioactive Material Shipments Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels Administrative Guide for Verifying Compliance with Packaging Requirements for Shipments of Radioactive Materials (Issued for Comments) Load Combinations for the Structural Analysis of Shipping Casks (Issued for Comments) Standard Format and Content of Part 71 Applications for Approval of Packaging of Type B, Large Quantity and Fissile Radioactive Materials /Issued for Comments) Shipping and Receiving Control of Strategic Special Nuclear Material (Proposed Revision to R.G. 5.57) Packaging of Radioactive Material for Transport and Transportation of Radioactive Material under certain Conditions Normal Conditions of Transport Hypothetical Accident Conditions Transport Grouping of Radionuclides Tests for Special Form Licensed Material Quality Assurance Criteria for Shipping Packages for Radioactive Material Arrete royal portant reglement general de la protection de la population et des travailleurs contre ie danger des radiations ionisantes (See "Moniteur Beige") Postordnung »om 16. Mai 1963, zuletzt geandert durch Verordnung vom 15. November 1976 Verordnung uber die Zulassung einer neuen Numerierung der Gefahrenklassen bei der Beforderung gefahrlicher Guter auf der StraBe vom 22. Juni 1977 Verordnung fiber die Beforderung gefahrlicher Guter mit Seeschiffen (GefahrgutVSee) vom 5. Juli 1978 Luftverkehrsgesetz (LuftVG) vom 4. November 1968, zuletzt geandert durch §37 des Bundesnaturscfiutzgesetzes vom 20. Dezember 1976
Iss
1.74
Iss
4.75
Iss Iss
5 75 3.78
Iss
6.76
Iss
4 80
Iss
674
Iss
6.74
Iss
5.77
Iss
378
Iss
8.77
Iss
5.77
Iss
3.79
Iss
5.79
Iss
5.63
Iss 5.63 Amm 11.76 Iss 6.77
Iss
778
Iss 11.68 Amm 12 76
179
15.4 No.
Issuing Body (Country)
BGBI I, S. 1119
IDEU)
BGBI. I, S. 1314 /BGBI. I, S. 613
(DEU)
BGBI. 1. S. 1502
IDEU)
BGBI. 1. S. 1509
(DEU)
BGBI. 1, S. 1609
(DEU)
BGBI. 1. S. 2044
(DEU)
BGBI. 1, S. 2121 /BGBI. I, S. 373
(DEU)
BGBI. II , S. 357
(DEU)
BGBI. II , S. 375
(DEU)
BGBI. II, S. 430
(DEU)
BGBI. II, S. 569
(DEU)
BGBI. II, S. 778 /BGBI. II, S. 150
(DEU)
BGBI. II, S. 1286
(DEU)
180
Title
Status
(Remarks)
Verordnung zur Einfiihrung der Verordnung fiber die Beforderung gefahrlicher GOter auf dem Rhein (ADNR) und uber die Ausdehnung dieser Verordnung auf die librigen Bundeswasserstraften vom 23. November 1971 in der Fassung vom 13. Juni 1977, zuletzt geandert durch die Erste ADNR-Anderungsverordnung vom 27. Dezember 1977 Gesetz uber die Aufgaben des Bundes auf dem Gebiet der Seeschiffahrt in der Neufassung vom 30. Juni 1977, geandert durch Artikel 1 des Gesetzes vom 10. Mai 1978 Verordnung uber die Beforderung gefahrlicher Guter mit der Eisenbahn (Gefahrengutverordnung-Eisenbahn - GGVE) vom 23. August 1979 Verordnung uber die Beforderung gefahrlicher Guter auf der StralSe (GefahrgutVStr) vom 23. August 1979 Verordnung uber Ausnahmen von der Verordnung uber die Beforderung gefahrlicher Guter auf der StraSe (StraRen-Gefahrgutausnahmeverordnung) vom 2. Oktober 1979 Verordnung zur Einfuhrung der Verordnung uber die Beforderung gefahrlicher Guter auf der Mosel vom 20. Dezember 1971 Gesetz uber die Beforderung gefahrlicher Guter vom 6. August 1975, zuletzt geandert durch Artikel 15 des Gesetzes vom 28. Marz 1980 Gesetz zu dem Internationalen Ubereinkommen vom 7. Februar 1970 uber den Eisenbahnfrachtverkehr (CIM) vom 26. April 1974 (See also BGBI. II. S. 381, 488, 552) Bekanntmachung uber den Geltungsbereich des Ubereinkommens iiber die zivilrechtliche Haftung bei der Beforderung von Kernmaterial auf See vom 9.4.1979 Elfte Verordnung uber Ausnahmen von den Vorschriften der Anlagen A und B zum Europaischen Ubereinkommen iiber die internationale Beforderung gefahrlicher Guter auf der StraBe (11. ADR-AusnahmeV) vom 18. Mai 1979 mit den vorangehenden Verordnungen (See also BGBI. II, S. 1489) Verordnung uber die Einfuhrung einer neuen Numerierung der Gefahrenklassen bei der Beforderung gefahrlicher Guter im internationalen StraSen- und Eisenbahnverkehr vom 22. Juni 1977 Internationale Ordnung fur die Beforderung gefahrlicher Guter mit der Eisenbahn (RID) in der Fassung der Verordnung fiber die Inkraftsetzung der Neufassung 1977 der Anlage I (RID) des Internationalen Ubereinkommens fiber den Eisenbahnfrachtverkehr (RID-NeufassungsV) vom 9. September 1977, geandert durch die 2. RID-Anderungsverordnung vom 26. Februar 1980 Bekanntmachung fiber den Geltungsbereich des Europaischen Ubereinkommens fiber die internationale Beforderung gefahrlicher GOter auf der StraSe vom 16. November 1979 (See also BGBI. II, S. 1489)
Iss 11.71 Amm 12.77
Iss Amm
6.77 5.78
Iss
8.79
Iss
8.79
Iss
10.79
Iss
12.71
Iss Amm
8 75 3.80
Iss
4.74
Iss
4.79
Iss
5.79
Iss
6.77
Iss Amm
9.77 2.80
Iss
11.79
15.4 No.
Issuing Body (Country)
BGBI. II, S. 1489 /BGBI. II, S. 1190 /BGBI. II, S. 133
(DEU)
BGBI. Ill, Glnr. 934-1 /BGBI. I, S. 1506
(DEU)
(INT) (INT)
Dz.U.(1968)27
(POL)
Order No 10-VHXH/NTLC Leg. Series 1970 No 20
(VNM) (YUG)
Title (Remarks) Gesetz zu dem Europaischen Ubereinkommen vom 30. September 1957 iiber die internationale Beforderung gefahrlicher Guter auf der StralSe (ADR) vom 18. August 1969 sowie Anlagen A und B in der Fassung der Verordnung iiber die Inkraftsetzung der Neufassung 1977 der Anlagen A und B zum ADR (ADR-NeutassungsV) vom 4. November 1977, zuletzt geandert durch die 2. ADR-Anderungsverordnung vom 26. Februar 1980 Eisenbahn-Verkehrsordnung, veroffentlicht in der bereinigten Fassung im BGBI. Ill, Gliederungsnummer 934-1, zuletzt geandert durch die 85. Verordnung zur Anderung der Eisenbahn-Verkehrsordnung vom 23. August 1979 Internationales Ubereinkommen iiber den Eisenbahnfrachtverkehr (CIM) vom 7. Februar 1970 mit Zusatzprotokoll International Regulation tor the Transport of Dangerous Goods by Rail; Version of the Ordernance on the Implementation of the New1977 Issue of Appendix I regarding the International Treaty on Transport of Goods by Rail Decree of the Ministers of Transport and of the Interior Concerning the Road Traffic Regulations Regulations for the Use of Trade in, Transfer and Storage of Sources of Ionizing Radiation Regulation Concerning the Carriage of Dangerous Goods by Road (Art 2, Class IVb: Radioactive Substances)
Status Iss 869 Amm 11.77 Amm 2.80
Iss Amm
9.38 8.79
App
2.70
App 9.77 Amm 10.78
Iss
768
Iss
1.67
Iss
470
181
15.5 No.
Title
Issuing Body (Country}
15
Nuclear Material M a n a g e m e n t
15.5
Criticality Safety
ANS-1 /ANSI N405 ANS-8.1 /ANSI N16.1
ANS
ANS-8.3 /ANSI N162 ANS-8.5 /ANSI N16.4
ANS
ANS-87 /ANSI N16.5 ANS-8.9
ANS
ANS
ANS
ANS
ANS-8.10 /ANSI N16.8 ANS-8.11 /ANSI N169 ANS-8.12
ANS
BS 3598
BSI
DIN 25403 Teil 1
DIN
DIN 25403 Teil 2
DIN
DIN 25403 Teil 3
DIN
DIN 25403 Teil 4
DIN
DIN 25403 Teil 5
DIN
182
ANS ANS
Status
(Remarks)
Safety Guide for the Performance of Critical Experiments Nuclear Criticality Safety in Operations With Fissionable Materials Outside Reactors (Revision of ANSI N16.1-I969) Criticality Accident Alarm System (Revision of ANSI N16.2-I969) Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material (Revision of ANSI N16.4-1971) Guide for Nuclear Criticality Safety in the Storage of Fissile Materials Nuclear Criticality Safety Guide for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate Criteria for Nuclear Criticality Safety Controls in Operations Where Shielding Protects Personnel Calculational Methods for Nuclear Criticality Safety Nuclear Criticality Control and Safety of Homogeneous Plutonium-Uranium Fuel Mixtures Outside Reactors Recommendations for Criticality Safety in Handling and Processing Fissile Materials Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Grundsatze (Criticality Safety in Processing and Handling Fissile Materials; Principles) Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Kritikalitatsdaten fur Uran 235-Metall-Leichtwasser-Mischungen (Criticality Safety in Processing and Handling Fissile Materials; Criticality Data for Uranium 235 Metal Light-Water-Mixtures) Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Kritikalitatsdaten fur Plutonium 239-Metall-Leichtwasser-Mischungen (Criticality Safety in Processing and Handling Fissile Materials; Criticality Data for Plutonium 239 Metal Light-Water-Mixtures) Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Kritikalitatsdaten fur Uran 235-Dioxid-Leichtwasser-Mischungen (Criticality Safety in Processing and Handling Fissile Materials; Criticality Data for Uranium 235 Dioxide Light-Water-Mixtures) Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Kritikalitatsdaten fur Plutonium 239-Dioxid-Leichtwasser-Mischungen (Criticality Safety in Processing and Handling Fissile Materials; Criticality Data for Plutonium 239-Dioxide Light-Water-Mixtures)
App
75
App
75
App
10.79
App
79
App
75
Pub
78
App
75
App
75
Pub
78
Pub
70
Drf
11.80
Pub
8.75
Pub
8.75
Pub
1.77
Pub
1.77
15.5 No.
Issuing B o d y (Country)
DIN 25403 Teil 6
DIN
DIN 25403 Teil 7
DIN
DIN 25421
DIN
ISO 1709
ISO
R.G. 3.1
USNRC
R.G. 3 4
USNRC
R.G. 3.41
USNRC
R.G. 3.43
USNRC
R.G. 8 12
USNRC
Task No. FP 925-5
USNRC
Task No OH 015-4
USNRC
Title
Status
(Remarks)
Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Kritikalitatsdaten fur Plutonium 239-Nitrat-Leichtwasser-Mischungen (Criticality safety in Processing and Handling Fissile Materials; Criticality Data for Plutonium 239 Nitrate Light-Water-Mixtures] Kritikalitatssicherheit bei der Herstellung und Handhabung von Kernbrennstoffen; Kritikalitatsdaten fur niedrig angereicherte Urandioxid-Stabgitter in Wasser(Criticality Safety in Processing and Handling Fissile Materials; Criticality Data for Low Enriched Uranium Dioxid Lattices in Water) Kritikalitatssicherheit bei der Anwendung von Borosilicatglas-Raschigringen als Neutronenabsorber in Spaltstofflosungen (Criticality safety of Borosilicate Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material) Nuclear Energy - Fissile materials - principles of criticality safety in handling and processing Use of Borosilicate-Class Rashig Rings as a Neutron Absorber in Solutions of Fissile Material Nuclear Criticality in Safety Operations with Fissionable Materials Outside Reactors Validation of Calculational Methods for Nuclear Criticality Safety Nuclear Criticality Safety in the Storage of Fissile Materials Criticality Accident Alarm Systems (Under Revision; see also Task No. OH 015-4) Nuclear Criticality Safety for Pipe Intersections Containing Aqueous Solutions of Enriched Uranyl Nitrate (Proposed R. G) Criticality Accident Alarm Systems (Proposed R.G. 8.12/
Pub
1.77
Pub
11.80
Pub
180
Pub
75
Iss
1 73
Iss
278
Iss
5.77
Iss
4.79
Iss
1274
Iss
1 80
Iss
580
183
15.6 No. 15
Title
Issuing Body (Country) Nuclear Material M a n a g e m e n t
15.6 Material C o n t r o l , Inventory ANS-57.8 Fuel Assembly Identification ANS ANSI N15.2
ANSI
ANSI N15.3 ANSI N15.5 ANSI N15.6
ANSI ANSI ANSI
ANSI N15.7
ANSI
ANSI N15.8
ANSI
ANSI N15.9
ANSI
ANSI N15.11 ANSI N15.13
ANSI ANSI
ANSI N15.15
ANSI
ANSI N15.16
ANSI
ANSI N15.17
ANSI
ANSI N15.18
ANSI
ANSI N15.19
ANSI
ANSI N15.20 ANSI N15.22
ANSI ANSI
ANSI N15.23
ANSI
ANSI N317
ANSI
ASTM C 853
ASTM
CNEN NE2.01
CNEN
CNEN NE 2.02 DIN 25401 Teil 4
CNEN DIN
DIN 25433
DIN
GOST 22574 ISO 3925
GOST ISO
RDT E 12-7T
ORNL
R.G. 5.2
USNRC
R.G. 5.3
USNRC
184
Status
(Remarks)
Record and Reporting Units for Nuclear Materials Control Physical Inventories of Nuclear Fuel Statistical Terminology and Notation Analytical Standards for Accountability of Uranium Tetrafluoride Analytical Procedures for Accountability of Uranium Hexafluoride Nuclear Material Control Systems for Nuclear Power Reactors Nuclear Materials Control Systems for Fuel Fabrication Plants Auditing Nuclear Material Statements Nuclear Material Control Systems for Fuel Processing Facilities (a Guide to Practice) Assessment of the Assumption of Normality (Employing Individual Observed Values) Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control Concepts and Principles for the Statistical Evaluation of Shipper-Receiver Differences in the Transfer of SNM Mass Calibration Techniques for Nuclear Materials Control Volume Calibration Techniques for Nuclear Materials Control Radiometric Calibration Techniques Calibration Techniques for the Calorimetric Assay of Plutonium Bearing Solids Applied to Nuclear Materials Control Guide to the Nondestructive Assay of 235U Content of Unpoisoned Low-Enrichment Uranium Fuel Rods Inplant Plutonium Monitoring, Performance Criteria for Instrumentation Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste Physical Protection of Nuclear Materials and Facilities Control and Accountability of Nuclear Materials Kerntechnik; Begriffe, Kernmaterialuberwachung (Nuclear Technology; Terms and Definitions, Nuclear Material Control) Kennzeichnung von Brennelementen fur Leistungsreaktoren (Fuel Assembly Identification for Nuclear Power Reactors) Spaltbares Kemmaterial Unsealed Radioactive Substances - Identification and Certification Inspection and Preventive Maintenance of Fuel Shipping Containers Classification of Unirradiated Plutonium and Uranium Scrap Statistical Terminology and Notation for Special Nuclear Materials Control Accountability
Pub Rev Pub
78 10.79 71
Pub Pub Pub
72 72 72
Pub
72
Pub'
74
Pub
75
Pub Pub
73 74
Pub
76
Pub
74
Pub
75
Pub
75
Pub
75
Pub Pub
75 75
Pub
79
Pub
78
Pub
77
Iss
77
Drf Drf
79 279
Pub
7.78
Pub Pub
77 78
Pub
1.75
Iss
12.72
Iss
2.73
15.6 No.
Issuing Body (Country)
R.G. 5.7
USNRC
R.G. 5 8
USNRC
R.G. 5.9
USNRC
R.G. 5.11
USNRC
R.G. 5.12
USNRC
R.G. 5.13 R.G. 5.15
USNRC USNRC
R.G. 5.18
USNRC
R.G. 5.19
USNRC
R.G. 5.22
USNRC
R.G. 5.23 R.G. 5.24
USNRC USNRC
R.G. 5.25
USNRC
R.G. 5.26
USNRC
R.G. 5 27 R.G. 5 28
USNRC USNRC
R.G. 5.29
USNRC
R.G. 5.33 R.G. 5.36
USNRC USNRC
R.G. 5.37 R.G. 5.40
USNRC USNRC
R.G. 5.42
USNRC
R.G. 5.49
USNRC
R.G 5 51
USNRC
R.G. 5 53
USNRC
R.G 5.54
USNRC
R.G. 5 55
USNRC
Title
Status
(Remarks)
Control of Personnel Access to Protected Areas, Vital Areas and Material (Under Revision; see also Task No. SG 909-4) Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Drying and Fluidized Bed Operations Specifications of Ge(Li) Spectroscopy Systems for Material Protection Measurements • Part 1: Data Acquisition Nondestructive Assay of Special Nuclear Material containment in Scrap and Waste General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials (Under Revision) Conduct of Nuclear Material Physical Inventories Security Seals for the Protection and Control of Special Nuclear Material Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control (Under Revision) Methods for the Accountability of Plutonium Nitrate Solutions Assessment of the Assumption of Normality (Employing Individual Observed Values) In-Situ Assay of Plutonium Residual Holdup Analysis and Use of Process Data for the Protection of Special Nuclear Material in Equipment for Wet Process Operations Design Considerations for Minimizing Residual Holdup of Special Nuclear Material Selection of Material Balance Areas and Items Control Areas Special Nuclear Material Doorway Monitors Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials (Under Revision) Nuclear Material Control Systems for Nuclear Power Plants Statistical Evaluation of Material Unaccounted For Recommended Practice for Dealing with Outlying Observations In-Situ Assay of Enriched Uranium Residual Holdup Methods for the Accountability of Plutonium Dioxide Powder Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Dry Process Operations Internal Transfers of Special Nuclear Material (Issued for Comments) Management Review of Nuclear Material Control and Accounting Systems (Issued for Comments) Qualification, Calibration, and Error Estimation Methods for Non-destructive Assay (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Nuclear Power Plants (Issued for Comments) Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities (Issued for Comments)
Iss
6.73
Iss
5.74
Iss
5.74
Iss
10.73
Iss
11.73
Iss Iss
11.73 1.74
Iss
1.74
Iss
1.74
Iss
4.74
Iss Iss
5.74 6.74
Iss
6.74
Iss
4.75
Iss Iss
6 74 6 74
Iss
6.75
Iss Iss
6.74 6.74
Iss Iss
8.74 12.74
Iss
1.75
Iss
3.75
Iss
6.75
Iss
8.75
Iss
3.78
Iss
3.78
185
15.6 No.
Issuing Body (Country)
R.G. 5.57
USNRC
R.G. 5.58
USNRC
R.G. 7.7
USNRC
Task No. SG 901-4
USNRC
Task No. SG 908-4
USNRC
Task No. SG 909-4
USNRC
'
(CZE)
Title (Remarks) Shipping and Receiving Control of Special Nuclear Material (Under Revision; see also Task No SG 908-4) Considerations for Establishing Traceability of Special Nuclear Material Accounting Measurements (Issued for Comments) Administrative Guide for Verifying Compliance with Packaging Requirements for Shipments of Radioactive Materials (Issued for Comments) Reporting of Safeguards Events (Proposed R.G.) Shipping and Receiving Control of Strategic Special Nuclear Material (Proposed Revision to R.G. 5.57) Entry/Exit Control of Protected Areas, Vital Areas, and Material Acces Areas (Proposed Revision to R.G. 5.7) Notification of the Ministries of Chemical Industry and Health Concerning the Control of Radioactive Substances
Status Iss
6.76
Iss
11.78
Iss
8 77
Iss
10.79
Iss
5 79
Iss
5.79
Iss
5.56
15.7 No. 15
Issuing Body (Country)
Title
Status
(Remarks)
Nuclear Material M a n a g e m e n t
15.7 M e t h o d s for Analysis S p e c i f i c a t i o n s ANSI N15.1 Classification of Unirradiated Jranium Scrap ANSI ANSI Analytical Standards for Accountability of Uranium ANSI N15.6 Tetrafluoride Analytical Procedures for Accountability of Uranium ANSI ANSI N15.7 Hexafluoride ANSI Classification of Unirradiated Plutonium Scrap ANSI N15.10 ANSI N15.16 Limit of Error Concepts and Principles of Calculation ANSI in Nuclear Materials Control ANSI N15.18 Mass Calibration Techniques for Nuclear Materials ANSI Control ANSI ANSI N15.19 Volume Calibration Techniques for Nuclear Materials Control ANSI N15.20 ANSI Radiometric Calibration Techniques ANSI ANSI N15.22 Calibration Techniques for the Calorimetric Assay of Plutonium Bearing Solids Applied to Nuclear Materials Control ANSI ANSI N15.23 Guide to the Nondestructive Assay of 235U Content of Unpoisoned Low-Enrichment Uranium Fuel Rods ASTM C 696 ASTM Chemical Mass Spectrometric. Spectrochemical /ANSI N103 Analysis of Nuclear-Grade Uranium Dioxide Powder Pellet ASTM C 697 ASTM Chemical Mass Spectrometric, Spectrochemical /ANSI N104 Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets ASTM ASTM C 698 Chemical Mass Spectrometric, Spectrochemical /ANSI N139 Analysis of Nuclear-Grade Mixed Oxide ((U, Pu) O2) ASTM ASTM C 699 Methods for Chemical, Mass Spectrometric and /ANSI N140 Spectrochemical Analysis of, and Physical Tests on Beryllium Oxide Powder ASTM ASTM C 708 Specification for Nuclear-Grade Beryllium Oxide /ANSI N138 Powder ASTM ASTM C 750 Specification for Nuclear Grade Boron Carbide /ANSI N569 Powder (Under Revision) ASTM ASTM C 751 Specification for Nuclear Grade Boron Carbide Pellets /ANSI N722 (Under Revision) ASTM ASTM C 752 Specification for Nuclear Grade Silver Indium /ANSI N571 Cadmium Alloy (Reaffirmed 12.77) ASTM ASTM C 753 Specification for Nuclear Grade Sinterable Uranium Dioxide Powder ASTM C 757 ASTM Standard Specification for Nuclear Grade Sinterable /ANSI N568 Plutonium Dioxide Powder ASTM C 758 ASTM Chemical Mass Spectrometric, Spectrochemical /ANSI N572 Nuclear and Radiochemical Analysis of Nuclear Grade Plutonium Metal ASTM ASTM C 759 Chemical Mass Spectrometric, Spectrochemical /ANSI N573 Nuclear and Radiochemical Analysis of Nuclear Grade Plutonium Nitrate Solution ASTM ASTM C 760 Method for Chemical and Spectrochemical Analysis /ANSI N574 of Nuclear Grade Silver-lndium-Cadmium-Alloys ASTM C 761 ASTM Method for Chemical Mass Spectrometric and /ANSI N575 Spectrochemical Nuclear and Radiochemical Analysis of Uranium Hexafluoride ASTM ASTM C 776 Specification for Sintered Uranium Dioxide pellets ASTM C 784 ASTM Aluminium Oxide/Boron Carbide Composite Pellets, Specification ASTM C 787 ASTM Specification for Uranium Hexafluoride for Enrichment
Pub Pub
70 72
Pub
72
Pub Pub
72 74
Pub
75
Pub
75
Pub Pub
75 75
Pub
79
Pub Rev
77 1 79
Pub Rev
77 1.79
Pub Rev Pub Rev
77 1.79 72 1.79
Pub Rev Pub
72 77 74
Pub
75
Pub App
73 74
Pub
78
Pub Rev Pub Rev
74 12.78 73 79
Pub Rev
73 79
Pub Rev Pub
74 79 77
Pub Pub
76 76
Pub
76
187
15.7 No.
Issuing Body (Country)
ASTM C 788
ASTM
ASTM C 791
ASTM
ASTM C 799
ASTM
ASTM C 809
ASTM
ASTM C 833
ASTM
ASTM C 853
ASTM
ASTM C 886
ASTM
ASTM E 217
ASTM
ASTM E 219
ASTM
ASTM E 244
ASTM
ASTM E 267
ASTM
ASTM E 320
ASTM
ASTM E 321
ASTM
ASTM E 402
ASTM
ASTM E 495
ASTM
SI 62/2649
DEGR
SI 62/2711
DEGR
SI 62/2712
DEGR
SI 62/6710
DEGR
SI 63/1834
DEGR
DIN 25401 Teil 6
DIN
GO ST 14930 GOST 19647
GOST GOST
IEC 583
IEC
ISO/DP 7097
ISO
RDT F 2-6T
ORNL
RDT F 2-8T
ORNL
RDT F 11-1T R.G. 1.126
ORNL USNRC
Title
Status
(Remarks)
Specification for Nuclear Grade Uranyl Nitrate Solution Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear Grade Boron Carbide Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear Grade Uranyl Nitrate Solutions Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear Grade Aluminium Oxide and Aluminium Oxide-Boron Carbide Composite Pellets Specification for Sintered (Uranium-Plutonium) Dioxide Pellets Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste Scleroscope Hardness Testing of Fine-Grained Carbon and Graphite Materials Test for Uranium by Controled-Potential Coulometry Test for Atom Percent Fission in Uranium Fuel (Radiochemical Method) Test for Atom Percent Fission in Uranium and Plutonium Fuel (Mass Spectrometric Method) Test for Uranium and Plutonium Concentrations and Isotopic Abundances Radiochemical Determination of Cesium-137 in Nuclear Fuel Solutions Test for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method) Spectrographic Analysis of Uranium Oxide (UsOa) by Gallium Oxide-Carrier Technique Spectrophotometric Determination of Fission Zirconium in Irradiated Nuclear Fuels The Radioactive Substances (Lead) Exemption Order 1962 The Radioactive Substances (Prepared Uranium and Thorium Conpounds) Exemption Order 1962 The Radioactive Substances (Geological Specimens) Exemption Order 1962 The Radioactive Substances (Uranium and Thorium) Exemption Order 1962 The Radioactive Substances (Thorium-X) Exemption Order 1963 Kerntechnik; Begriffe, Isotopentrennung (Nuclear Technology; Terms and Definitions, Isotope Separation) Radioaktive Stoffe; Technische Kennwerte Mittel und Verfahren der rontgenradiometrischen Analyse Dimensions of Test Tubes Made of Glass or Plastics for Radioactivity Measurements Determination on Uranium in Reactor Fuel Solutions and in Uranium Product Solution-Ferrous Sulphate Reduction/Potassium Dichromate Oxidation Titrimetric Method Qualification and Control of Analytical Chemistry Laboratories for Mixed Oxide Fuel Analysis Qualification and Control of Analytical Chemistry Laboratories for Control Rod Absorber Material Analysis Analytical Chemistry Methods for Mixed Oxide Fuel An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification
Pub
76
Pub
75
Pub
78
Pub
76
Pub
76
Pub
77
Pub
78
Pub Rev Pub Rev Pub
70 78 69 74 74
Pub
78
Pub
70
Pub
75
Pub Rev Pub
70 76 78
Iss
62
Iss
62
Iss
62
Iss
62
Iss
63
Drf
2.79
Pub Pub
69 74
Pub
77
Ust
Pub
3.79
Pub
12.78
Pub Iss
5.77 3.78
15.7 No.
Issuing Body (Country)
R.G. 5.4
USNRC
R.G. 5.5
USNRC
R.G. 5.6
USNRC
RG 5.11
USNRC
R G. 5.16
USNRC
RG. 5 19
USNRC
R G. 5.21
USNRC
R.G. 5.23 R.G. 5.24
USNRC USNRC
R.G 5.34
USNRC
R.G. 5 35
USNRC
R.G. 5.38
USNRC
R.G. 5.39
USNRC
R G. 5.40
USNRC
R.G. 5 42
USNRC
R.G. 5.47
USNRC
R.G. 5.48
USNRC
R.G. 5.53
USNRC
Title (Remarks) Standard Analytical Methods for the Measurement of Uranium Tetrafluoride (UF4) and Uranium Hexafluoride (UF6) Standard Methods for Chemical. Mass Spectrometry, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets and Nuclear-Grade Mixed Oxides (U, Pu, 02) Nondestructive Assay of Special Nuclear Material containment in Scrap and Waste Standard Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium Nitrate Solutions and Plutonium Metal (Issued for Comments) Methods for the Accountability of Plutonium Nitrate Solutions Nondestructive Uranium-235 Enrichment Assay by Gamma-Ray Spectrometry In-Situ Assay of Plutonium Residual Holdup Analysis and Use of Process Data for the Protection of Special Nuclear Material in Equipment for Wet Process Operations Nondestructive Assay of Plutonium in Scrap by Spontaneous Fission Detection Calorimetric Assay for Plutonium (Withdrawn 8.77) Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma-Ray Spectrometry General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic Distribution, and Impurity Determinations Methods for the Accountability of Plutonium Dioxide Powder Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Dry Process Operations Control and Accountability of Plutonium in Waste Material Design Considerations-System for Measuring the Mass of Liquids Qualification, Calibration, and Error Estimation Methods for Non-destructive Assay (Issued for Comments)
Status Iss
2.73
Iss
2.73
Iss
5.73
Iss
10 73
Iss
5 75
Iss
1 74
Iss
4.74
Iss Iss
5.74 6 74
Iss
6.74
Iss
9.74
Iss
12.74
Iss
12.74
Iss
1.75
Iss
2.75
Iss
2.75
Iss
8 75
189
16.1 No. 16
Title
Issuing Body (Country) Electrical E q u i p m e n t and S y s t e m s
16.1 General ANSI N42.4
ANSI
High Voltage Connectors for Nuclear Instruments
ASTM E 240
ASTM
ASTM E 452 NF C 61-303 DIN 25431
ASTM CEA DIN
DIN 25434
DIN
DIN 44426 Teil 1
DIN
DIN 44426 Teil 2
DIN
IAEA50-SG-D8 IEC 323
IAEA IEC
I EC 527
IEC
IEEE 308 /ANSI N41.12 IEEE 323
IEEE
IEEE 334 /ANSI N41.9 IEEE 336 /ANSI N45.2.4
IEEE
Specification for Sheathed Electrical Resistance Heaters for Nuclear or Other Spezialized Service Calibration of Refractory Metal Thermocouples Prises de courant et prolongateurs 10/16 a 250 V Kabeldurchfiihrungen im Reaktor-Sicherheitsbehalter; Sicherheitstechnische Anforderungen (Electric Penetration Assemblies in Containment Structures; Safety Requirements) (in Press; Identical with KTA 3403) Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen; Sicherheitstechnische Anforderungen (Reactor Protection System and Monitoring of Safety Devices; Safety Engineering Requirements) (Identical with KTA 3501) Steuersystem fur Strahlungsmefigerate und ihre Zusatzgerate; Grundlagen (Control-System for Electrical Measuring Instruments Used in Connection with Ionizing Radiation) Steuersystem fur StrahlungsmeBgerate und ihre Zusatzgerate; Nachrichtengabe durch mechanische Kontakte (Control-System for Electrical Measuring Instruments Used in Connection with Ionizing Radiation) Instrumentation and Control of Nuclear Power Plants Analogue Voltage Ranges and Logic Levels for Mains Operated Nuclear Instruments Direct Current Amplifiers; Characteristics and Test Methods Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations Standard for Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations Standard for Type Tests of Continuous-Duty Class 1E Motors for Nuclear Power Generating Stations Installation Inspection and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations Seismic Qualification of Class 1 Electric Equipment for Nuclear Power Generating Stations The Application of Single Failure Criteria to Nuclear Power Generating Station Class 1E Systems Standard Criteria for Type Tests of Class 1E Modules Used in Nuclear Power Generating Stations Guide for Type Test of Class 1 Electric Valve Operators for Nuclear Power Generating Stations Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations Standard Criteria for Independence of Class 1E Equipment and Circuits Guide for Planning of Pre-Operational Testing Programs for Class 1E Power Systems for Nuclear Power Generating Stations Trial-Use Guide for Class 1E Control Switchboards for Nuclear Power Generating Stations (Trial-Use Standard)
IEEE
IEEE
IEEE 344
IEEE
IEEE 379 /ANSI N41 2 IEEE 381
IEEE
IEEE 382
IEEE
IEEE 383
IEEE
IEEE 384
IEEE
IEEE 415
IEEE
IEEE 420
IEEE
190
Status
(Remarks)
IEEE
Pub Rev Pub
71 78 71
Pub Pub
77 71
Pub
1077
Pub
8.68
Pub
8.68
Ust Pub
70
Pub
75
Pub
74
Pub
74
Pub
74
Pub
77
Pub
75
Pub
77
Pub
77
Pub
72
Pub
77
Pub
77
Pub
76
Pub
73
16.1 No.
Issuing B o d y (Country)
IEEE 422
IEEE
IEEE 494 /ANSI N41.28
IEEE
IEEE 505
IEEE
KTA 3403
KTA
KTA 3501
KTA
KTA 3501
KTA
RDTE4 19T
ORNL
R G. 1 6
USNRC
R.G. 1 30
USNRC
R.G. 1.32
USNRC
R.G. 1.40
USNRC
R.G. 1.63
USNRC
R.G. 1.70.23
USNRC
R G. 1 70.24
USNRC
R G 1 73
USNRC
R G. 1 75 R G 1 81
USNRC USNRC
R G. 1 89
USNRC
RG 1.100
USNRC
R.G 1106
USNRC
R.G. 1.118
USNRC
R.G. 1.131
USNRC
Title (Remarks! Guide for the Design and Installation of Cable Systems in Power Generating Stations Standard Method tor Identification of Documents Related to Class 1E Equipment and Systems for Nuclear Power Generating Stations Nomenclature for Generating Station Electric Power Systems Kabeldurchfiihrungen im Reaktorsicherheitsbehalter von Kernkraftwerken (Electric Cable Penetrations in Containment of Nuclear Power Plant) (Identical with DIN 25431) Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen (Reactor Protection System and Monitoring of Safety Devicesl Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen (Reactor Protection System and Monitoring of Safety Devicesl (Available also in English; Identical with DIN 25434) Plugging Temperature Indicator Assembly for Sodium Service Independence Between Redundant Standby (Onsitel Power Sources and Between Their Distribution Systems (Safety Guide 6) Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants Electric Penetration Assemblies in Containment Structujes for Light-Water-Cooled Nuclear Power Plants Information for Safety Analysis Reports -Seismic Qualification of Instrumentation and Electrical Equipment (See also R.G. 1.70) Information for Safety Analysis Reports Environmental Design of Mechanical and Electrical Equipment, Qualification Tests and Analysis (See also R.G. 1.70) Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants Physical Independence of Electric Systems Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants Qualification of Class 1E Equipment for Nuclear Power Plants (Under Revision) Seismic Qualification of Electric Equipment for Nuclear Power Plants Thermal Overload Protection for Electric Motors on Motor-Operated Valves Periodic Testing of Electric Power and Protection Systems Qualification Test of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (Under Revision; see also Task No. RS 050-2)
Status Pub
77
Pub
74
Pub
77
Pub
10 80
Drf
10 80
Pub
3.77
Pub
4 75
Iss
3 71
Iss
8 72
Iss
2.77
Iss
3.73
Iss
7 78
Iss
2 75
Iss
2.75
Iss
174
Iss Iss
9 78 1 75
Iss
1174
Iss
8.77
Iss
3.77
Iss
6.78
Iss
8.77
191
16.1 No.
Issuing Body (Country/
Task No. RS 050-2
USNRC
VDI 2192
VDI
192
Title
Status
/Remarks)
Qualification Tests of Electric Cables and Field Splices for Light-Water-Cooled Nuclear Power Plants (Proposed Revision to R.G. 1.131) Meßumformer für Größen der Starkstromtechnik; Beschreibung und Untersuchung
Iss
8.79
Pub
9 72
16.2 No. 16
Issuing Body (Country)
Title (Remarks)
Status
Electrical E q u i p m e n t and S y s t e m s
16.2 Power Sources ANS-59.51 ANS /ANSI N195 GMBI. 1976 S. 166 BMI
DIN 25417 Teil 1
DIN
DIN 25467 Teil 1
DIN
IAEA 50-SG-D7A
IAEA
IEC 201
IEC
IEC 253
IEC
IEC 293
IEC
IEC 293A
IEC
IEEE 308 /ANSI N41.12 IEEE 323
IEEE
IEEE 387
IEEE
IEEE 450 /ANSI N41.15
IEEE
IEEE 484 /ANSI N41.24
IEEE
JIS Z4411
JIS
KTA 3701.1
KTA
KTA 3702.1
KTA
R.G 1 6
USNRC
IEEE
Fuel Oil Systems tor Emergency Diesel Generators
App
76
Richtlinien iiber die in atomrechtlichen Genehmigungsverfahren fur Kernkraftwerke zur Priifung erforderlichen Informationen iiber die Notstromversorgung vom 24.3.1976 Ubergeordnete Anforderungen an die elektrische Energieversorgung des Sicherheitssystems; Einblockanlagen, Sicherheitstechnische Anforderungen (General Requirements for Electrical Power Supply to Safety Systems for Nuclear Power Generating Stations; Single-Unit Stations, Safety Requirements) (Identical with KTA 3701.1) Notstromerzeugungsanlagen mit Dieselaggregaten; Auslegung, Sicherheitstechnische Anforderungen (Emergency Diesel Generators; Design, Safety Requirements] (Identical with KTA 3702.1) Emergency Electrical Power Systems at Nuclear Power Plants Power Sources for Portable Prospecting Equipment for Radioactive Materials Power Supply for Air and Land Vehicle-Mounted Prospection Equipment for Radioactive Materials Supply Voltages for Transistorized Nuclear Instruments First Supplement: Stabilized D.C. Power Supplies Tolerances of Voltages Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations Standard for Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations Recommended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Substations Recommended Practice for Installation Design and Installation of Large Lead Storage Batteries for Generating Stations and Substations Stabilized D.C. High Voltage Supplies for Radiation Detection Instruments Ubergeordnete Anforderungen an die elektrische Energieversorgung des Sicherheitssystems in Kernkraftwerken Teil 1: Einblockanlagen (General Requirements for Electrical Power Supply to Safety Systems for Nuclear Power Plants Part 1: Single-Unit Stations) (Available also in English; Identical with DIN 25417 Teil 1) Notstromerzeugungsanlagen mit Dieselaggregaten Teil 1: Auslegung (Emergency Diesel Generators Part 1: Design) (Identical with DIN 25467 Teil I) Independence Between Redundant Standby (Onsitel Power Sources and Between Their Distribution Systems (Safety Guide 6)
Iss
3.76
Pub
12.78
Drf
8.79
Ust Pub
65
Pub
67
Pub
68
Pub
70
Pub
74
Pub
74
Pub
77
Pub
75
Pub
75
Pub
75
Pub
6.78
Pub
680
Iss
371
193
16.2 No.
Issuing Body (Country)
R.G. 1.9
USNRC
R.G. 1.41
USNRC
R.G. 1.70.36
USNRC
R.G. 1.93 R.G. 1 108
USNRC USNRC
R.G. 1.128
USNRC
R.G 1 129
USNRC
R G 1 137
USNRC
VDI 2180 Blatt 5
VDI
VdTUV Wei 16
VdTUV
194
Title
Status
(Remarks)
Selection, Design, and Qualification of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants Preoperational Testing of Redundant Onsite Electric Power Systems of Verify Proper Load Group Assignments Information for Safety Analysis Reports - Electric Power (See also R.G. 1.70) Availability of Electric Power Sources Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants (Errata Sheet Available) Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants Fuel-Oil Systems for Standby Diesel Generators (Under Revision) Sicherung von Anlagen der Verfahrenstechnik; Einfiihrung, Begriffe, Erklarungen; Hilfsenergieversorgung der Einrichtungen zum Messen, Steuern und Regeln Typpriifung von Dieselmotoren fur Notstrom- und Notspeiseaggregate in Kernkraftwerken und fur Dieselmotoren mit vergleichbarer sicherheitstechnischer Bedeutung in anderen kerntechnischen Anlagen (100-Stunden-Qualifikationslauf)
Iss
12 79
Iss
373
Iss
75
Iss Iss
12.74 8.77
Iss
10.78
Iss
2 78
Iss
10.79
Pub
168
Iss
7.77
16.3 No. 16
Issuing Body (Country)
Title (Remarks!
Status
Electrical E q u i p m e n t and S y s t e m s
16.3 Insulation and Other A s p e c t s BS 5251 BSI Analogue Voltage Ranges and Logic Levels for Mains Operated Nuclear Instruments DIN 44429 DIN Versorgungsspannungen fur netzbetriebene StrahlungsmeBgerate (Supply Voltages for Mains Operated Nuclear Instruments) DIN 44800 DIN Analogspannungsbereiche und Digitalpegel fur netzbetriebene StrahlungsmeUgerate (Analogue Voltage Ranges and Logic Levels for Mains Operated Nuclear Instruments) IEC313 IEC Coaxial Cable Connections Used in Nuclear Instrumentation I EC 498 High-Voltage Coaxial Connectors Used in Nuclear IEC Instrumentation IEEE 422 Guide for the Design and Installation of Cable IEEE Systems in Power Generating Stations Determination of Insulation Compaction in Ceramic RDTC 2-1T ORNL Insulated Conductors RDT C 7-3T ORNL Thermocouple Material, Copper and Constantan, Sclid Conductor (Bare, Fiberglass Insulated, and Sheathed Over Fiberglass Insulation] RDT C 7-4T Thermocouple Material, Copper-Constantan, ORNL Mineral-Oxide Insulated, Sheathed RDT C 7-5T Thermocouple Material, Chromel-P and Alumel, Solid ORNL Conductor (Bare, Fiberglass Insulated, and Sheathed Over Fiberglass Insulation) Thermocouple Material and Thermocouple Assembly, RDT C 7-6T ORNL Chrcmel-P versus Alumel, Stainless Steel Sheathed, Magnesium Oxide Insulated High-Temperature Electrical Connectors and RDT C 17-1T ORNL Hermetic Seals RDT C 17-5T ORNL Metal-Sheathed, Mineral-Insulated Cable Bulk Material RDT C 17-9T ORNL Foil-Shieled Instrumentation Cable Ceramic Electrical Insulators RDT C 18-1T ORNL Metal-Sheathed, Mineral-Insulated Electrical RDT P4-3T ORNL Resistance Heater VDE Bestimmungen fur das Errichten von VDE 0101 Starkstromanlagen mit Nennspannungen von 1 kV und dariiber VDE Leitsatze fur die Bemessung von Starkstromanlagen VDE 0103 auf mechanische und thermische KurzschlufJfestigkeit Bestimmungen fur den Betrieb von VDE 0105/1 VDE Starkstromanlagen - Allgemeine Bestimmungen Vorschriften fur Erdungen in Wechselstromanlagen VDE 0141 VDE fiir Nennspannungen von 1 kV und dariiber Bestimmungen fiir die Errichtung elektrischer VDE 0165 VDE Anlagen in explosionsgefahrdeten Betriebsstatten Vorschriften fiir schlagwetter- und VDE VDE 0170 explosionsgeschiitzte elektrische Betriebsmittel VDE 0250 VDE Vorschriften fiir isolierte Starkstromleitungen VDE 0255
VDE
Bestimmungen fiir Kabel mit massegetrankter Papierisolierung und Metallmantel fiir Starkstromanlagen (ausgenommen Gasdruck- und Olkabel)
Pub
75
Pub
7.74
Pub
8.75
Pub
69
Pub
75
Pub
77
Pub Amm Pub
8.70 9.73 9.76
Pub Amm Pub
4.70 1.73 1.73
Pub Amm
2.75 2.76
Pub
3.70
Pub Amm Pub Pub Pub
273 4.74 6.74 8.74 3.75
Pub
4.71
Pub
5.74
Pub
5.75
Pub
7.76
Pub
869
Pub
2.61
Pub 3.69 Amm 677 Pub 11.72
195
16.3 No.
Issuing Body (Country)
VDE 0265
VDE
VDE 0271
VDE
VDE 0284
VDE
VDE 0303
VDE
VDE 0303 Teil 1 VDE 0303 Teil 2
VDE
VDE 0303 Teil 3
Status
(Remarks)
VDE
Vorschriften für Kabel mit Gummi- oder Kunststoffisolierung sowie mit Bleimantel fur Starkstromanlagen Vorschriften fur Kabel mit Gummiisolierung und Gummimantel Oder mit Kunststoffisolierung und Kunststoffmantel fiir Starkstromanlagen Vorschriften fur mineralisolierte Starkstromleitungen mit Kupfermantel Bestimmungen für elektrische Priifungen von Isolierstoffen Bestimmung der Kriechstromfestigkeit bei Betriebsspannungen bis 1000 V Bestimmung der elektrischen Durchschlagspannung und Durchschlagfestigkeit bei technischen Frequenzen Bestimmung der elektrischen Widerstandswerte (Spezifischer Durchgangswiderstand, Widerstand zwischen Spopselj, Oberflachenwiderstand) Bestimmung der Lichtbogenfestigkeit
Pub
10.55
VDE
Bestimmung der elektrolytischen Korrosionswirkung
Pub
3 68
VDE
Bestimmung des Verhaltens unter Einwirkung von Glimmentladungen Bestimmungen fiir Prufverfahren zur Beurteilung des thermischen Verhaltens fester Isolierstoffe Bestimmung thermischer Kenngrößen von festen Isolierstoffen Bestimmung des Verhaltens von Isolierstoffen nach langandauernder Warmeeinwirkung Regeln für elektrische Meßgeräte VDE-Bestimmungen fiir elektronische Meßgeräte und Regler Teil 1: Schutzmaßnahmen fiir elektronische Meßgerate Regeln fiir Prufgerate und Prufverfahren Leitsätze für die Durchfuhrung von Prufungen an isolierten Leitungen und Kabeln
Pub
9 74
VDE VDE
VDE 0303 Teil 5 VDE 0303 Teil 6 VDE 0303 Teil 7 VDE 0304 Teil 1 VDE 0304 Teil 1 VDE 0304 Teil 2 VDE 0410 VDE 0411
VDE VDE
VDE 0470 VDE 0472
VDE VDE
196
Title
VDE VDE VDE
Pub
4.75
Pub Amm
3.69 2 76
Pub
8 61
Pub
10 76
Pub
1174
Pub
3 67
Pub
7.59
Pub
7.59
Pub
7.59
Pub Pub
10.76 10.73
Pub Pub
1.61 9.71
17.1 Issuing Body (Country)
No. 17
Status
Title (Remarks)
T e s t i n g , Inspection and Surveillance
17.1 General ANSI N626.0 ASME JC 7-47 ASME QA-76-6 /ANSI N45.2.6
ANSI ASME /ACI ASME
ASME QA-76-8 /ANSI N45.2.8
ASME
ASTM E 105
ASTM
ASTM E 329
ASTM
BS 6000
BSI
BS 6001
BSI
CNEN NE 3.02
CNEN
CNEN NE 5.02
CNEN
CSA N285.1
CSA
CSA N2854
CSA
CSA Z299 4 SI 62/2643
CSA DEGR
DIN 25415 Teil 1
DIN
DIN 50049
DIN
IAEA 50-SG-G4
IAEA
IAEA 50-SG-07 IAEA 50-SG-08
IAEA IAEA
ICRU Report No. 10f
ICRU
RDT E 1-36T
ORNL
RDT F 2-7T RDT F 3-2T RDT F 3-1 IT
ORNL ORNL ORNL
RDT F 3-15T
ORNL
RDT F 6-2T
ORNL
Qualifications and Duties for Authorized Nuclear Inspection Inspection and Testing Agency
Pub
74
Qualifications of Inspection, Examination and Testing Personnel for the Construction Phase of Nuclear Power Plants Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants Recommended Practice for Probability Sampling of Materials Recommended Practice for Inspection and Testing Agencies for Concrete and Steel as used in Construction Guide to the Use of BS 6001. Sampling Procedures and Tables for Inspection by Attributes Sampling Procedures and Tables for Inspection by Attributes Licensing of Individuals and Institutions for the Inspection and Application of Radiological Protection Measures Design and Tests of Packaging of Radioactive Materials General and Construction Requirements for CANDU Nuclear Power Plant Components Periodic Inspection of CANDU Nuclear Power Plant Components Inspection Program Requirements The Radioactive Substances (Test Instruments) Exemption Order 1962 Dekontamination von radioaktiv kontaminierten Oberflachen; Verfahren zur Priifung und Bewertung der Dekontaminierbarkeit (Decontamination of Radioactive Contaminated Surfaces; Method of Test for Ease of Decontamination and Interpretation of Results) (For trial use and comments; Available also in English) Bescheinigungen uber Werkstoffpriifungen • (Certificates on material tests) (Available also in English) Inspection and Enforcement by the Regulatory Body for Nuclear Power Plants Maintenance of Nuclear Power Plants Standard Tests of Important Systems and Components in Nuclear Power Plants Methods of Evaluating Radiological Equipment and Materials Floor Valve, Reactor Refueling and Maintenance for LMFBR Acceptance Sampling Plans Calibration Program Requirements Mass Spectrometer Helium Leak Detection for Instruments and Small Components Requirements for Inspection of Dimensional Characteristics Welding of Reactor Core Components and Test Assemblies
Pub
78
App
75
Pub
75
Pub
77
Pub
72
Pub
72
Iss
74
Ust
Ust App
75
App
75
Iss Iss
79 62
Pub
1080
Pub
7.72
Ust Ust Ust Pub
63
Pub 6.72 Amm 6.74 Pub 11.73 Pub 2.73 Pub 2.72 Pub
8.73
Pub
7 73
197
17.1 No.
Issuing Body (Country)
Title
RDT F 7-3T
ORNL
Marking of Components and Parts
R.G. 1.26
USNRC
R.G. 1.34 R.G. 1.58
USNRC USNRC
R.G 1 70.24
USNRC
R.G. 1.116
USNRC
R G 1.130
USNRC
Task No. RS 901 -5
USNRC
VDE 0304 Teil 1 VdTUV Wei 29 VdTUV Wei 30
VDE
VdTUV 1255
VdTUV
VdTUV 1265
VdTUV
Quality Group Classifications and Standards for Water-, Steam- and Radio-Waste-Containing Components of Nuclear Power Plants (Issued for Comments) Control of Electroslag Weld Properties Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Under Revision; see also Task No. RS 901-5) Information for Safety Analysis Reports Environmental Design of Mechanical and Electrical Equipment, Qualification Tests and Analysis (See also R.G. 1.70) Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems Service Limits and Loading Combinations for Class I Plate-and-Shell-Type Component Supports Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Proposed Revision to R.G. 1.58) Bestimmungen fur Priifverfahren zur Beurteilung des thermischen Verhaltens fester Isolierstoffe Priifung der Bau-und Fertigungsdokumentation Vorgehensweise bei der Abwicklung von Materialqualitatsfallen bei Komponenten Grundsatze fur die Begutachtung von Werkstoffen fur iiberwachungsbedurftige Anlagen durch die Technische Uberwachung Ausstellen von Abnahmepriifzeugnissen A und C nach DIN 50049 Abschnitt 3.1 fur Werkstoffpriifungen (See also DIN 50049)
198
VdTUV VdTUV
Status
(Remarks)
Pub 6 75 Amm 10.78 Iss 2 76
Iss Iss
12 72 8.73
Iss
2.75
Iss
5.77
Iss
10.78
Iss
7.79
Pub
7 59
Iss Iss
180 180
Pub
2.74
Pub
6.74
17.2 No.
Issuing B o d y (Country)
17
T e s t i n g , Inspection and Surveillance
17.2
Pressure Vessels and B oilers
AD-Merkblatt BP 0
AD
AD-Merkblatt BP 1
AD
AD-Merkblatt H 3
AD
AD-Merkblatt HP 0
AD
AD-Merkblatt HP 1
AD
AD-Merkblatt HP 2/1
AD
AD-Merkblatt HP 2/1 Anl.1 AD-Merkblatt HP 3
AD
AD-Merkblatt HP 4
AD
AD-Merkblatt HP 5/1
AD
AD-Merkblatt HP 5/2
AD
AD-Merkblatt HP 5/3
AD
AD-Merkblatt HP 20
AD
E 32-106
AFNOI
ANSI N626.3
ANSI
B PVC Sec.VI
ASME
B PVC Sec.VII
ASME
ASTM E 185
ASTM
ASTM E 482
ASTM
ASTM E 509
ASTM
ASTM E 526
ASTM
ASTM F 112 TRD 110 Anl. 1 TRD 500 TRD 501
ASTM DDA DDA DDA
AD
Status
Title (Remarks)
Betrieb und Priifung von Druckbehaltern; Allgemeine Grundsatze fur Betrieb und Priifung Betrieb und Priifung von Druckbehaltern; Abnahmepriifung Herstellung von Druckbehaltern; Priifung von Fertigteilen aus Stahlblech Herstellung und Priifung von Druckbehaltern; Allgemeine Grundsatze fur Auslegung, Herstellung und erstmalige Priifung Herstellung und Priifung von Druckbehaltern; Auslegung und Priifung Herstellung und Priifung von Druckbehaltern; Verfahrenspriifung fur Fiigeverfahten. Verfahrenspriifung fur SchweilSverbindungen Herstellung und Prufung von Druckbehaltern; Abgrenzung des Geltungsbereiches fiir Stahl Herstellung und Prufung von Druckbehaltern; SchweiSaufsicht, SchweilSer Herstellung und Prufung von Druckbehaltern; Priifaufsicht und Priifer fiir zerstorungsfreie Prufung Herstellung und Prufung von Druckbehaltern; Herstellung und Prufung der Verbindungen; Arbeitstechnische Grundsatze Herstellung und Prufung von Druckbehaltern; Herstellung und Priifung der Verbindungen; Arbeitspriifung an SchweiSnahten Herstellung und Priifung von Druckbehaltern; Herstellung und Prufung der Verbindungen; Zerstorungsfreie Prufung der SchweiBnahte Herstellung und Priifung von Druckbehaltern; Erstmalige Prufung von Druckbehaltern; Baupriifung und Druckprufung Code de construction des generateurs de vapeur Partie VI: Robinetterie - Pompes de circulation Appareils de surveillance, d'alarme et de securite Qualifications and Duties of Personnel Engaged in ASME Boiler and Pressure Vessel Code, Section III, Division 1 and 2, Certifying Boiler and Pressure Vessel Code; Recommended Rules for Care and Operation of Heating Boilers (Regular Addenda and Revisions Provided) Boiler and Pressure Vessel Code; Recommended Rules for Care of Power Boilers (Regular Addenda and Revisions Provided) Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels Recommended Practice for Neutron Dosimetry for Reactor Pressure Vessel Surveillance Recommended Guide for In-Service Annealing of Water-Cooled Nuclear Reactor Vessels Recommended Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results Method of Test for Sealability of Enveloped Gaskets Richtlinien fiir die Bauteilpriifung von Armaturen Prufung von Dampfkesselanlagen Prufung der Hochdruckdampfkesselanlagen
Pub
10.77
Pub
10.77
Pub
7.69
Pub
12.77
Pub
10.77
Pub
12 77
Pub
2 77
Pub
4.75
Pub
4,75
Pub
4 75
Pub
12.77
Pub
12 77
Pub
10.77
Iss
75
Pub
78
Iss
74
Iss
74
Pub
73
Pub
76
Pub
74
Pub
77
Pub Pub Pub Pub
74 5.74 10.78 7.68
199
17.2 No.
Issuing Body (Country)
TRD 501 Anl. 1
DDA
TRD 502
DDA
TRD 503
DDA
TRD 506 Blatt 1 TRD 507 TRD 508
DDA
TRD 508 Anl. 1
DDA
IAEA 109
IAEA
ISO/R 1106
ISO
R.G. 1.99
USNRC
Task No. SC 705-4
USNRC
DDA DDA
10 CFR 50 Appendix H USNRC VdTUV 351 VdTUV 353
VdTUV VdTUV
VdTUV 354
VdTUV
VdTUV 358
VdTUV
VdTUV 362
VdTUV
VdTUV 364
VdTUV
VdTUV 451-71/1
VdTUV
VdTUV 451-78/1
VdTUV
BGBI. I, S. 173
IDEU)
BGBI. I, S. 173
(DEU)
200
Title
Status
(Remarks)
Richtlinie fur das Verfahren der Bauartzulassung nach § 14 und der Baumusterpriifung nach § 19 der Dampfkesselverordnung Vorpriifung der Unterlagen des Erlaubnisantrags, Prufung der Bemessung der druckfiihrenden Teile und der Konstruktion Prufung vor Inbetriebnahme, Baupriifung und Wasserdruckpriifung Richtlinie fur die innere Prufung im Rahmen der wiederkehrenden Prufungen von Dampfkesseln Wiederkehrende Prufungen, Wasserdruckpriifung Zusatzliche Prufungen an Bauteilen, berechnet mit zeitabhangigen Festigkeitskennwerten Zusatzliche Prufungen an Bauteilen, Verfahren zur Berechnung von Bauteilen mit zeitabhangigen Festigkeitskennwerten Periodic Inspection of Nuclear Reactor Steel Pressure Vessels Recommended Parctice for Radiographic Inspection of Fusion Welded Butt Joints for Steel Plates up to 50 mm (2 in) Thick Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials Ultrasonic Testing of Reactor Vessel Welds During Inservice Examination (Proposed R. G.) Reactor Vessel Material Survillance Program Requirements Prufung von Druckbehaltern mit Auskleidung Prufung von Druckbehaltern - Hinweise fur Sachverstandige - Bl. 1, 2, 3, 4 - und Anlage 1 bis 6 Richtlinien fiir die Bauteilprufung von Klammerschrauben Vorbereitung und Durchfiihrung von Druckprufungen - Hinweise Richtlinien zur Durchftihrung, Auswertung und Beurteilung von Dehnungsmessungen Zerstorungsfreie Wiederholungspriifung von Druckbehaltern aus Stahl fiir zyanhaltige Gase Richtlinien fiir die Beurteilung von Kesselkonstruktionen (Die Festlegungen in Nr. 1: Flammrohr Rauchrohrkessel und ahnliche Konstruktionen - sind ungultig. Hierfiir gilt das VdTuV-Merkblatt 451-76/1) Oberflachengefiigeuntersuchung zeitstandbeanspruchter Bauteile gemaB TRD 508 (See also TRD 508) Verordnung zur Ablosung von Verordnungen nach § 24 der Gewerbeordnung vom 27.2.1980; Artikel 1 Verordnung iiber Dampfkesselverordnung - DampfkV) Verordnung zur Ablosung von Verordnungen nach § 24 der Gewerbeordnung vom 27.2.1980; Artikel 2 Verordnung iiber Druckbehalter, Druckgasbehalter und Fiillanlagen (Druckbehalterverordnung - DruckbehV)
Pub
10.78
Pub
10.78
Pub
1078
Pub
6.75
Pub Pub
1078 10.78
Pub
10.78
Pub
69
Iss
4.77
Iss
5.79
Pub Pub
1.67 12.75
Pub
9.68
Pub
3.70
Pub
4.72
Pub
1.73
Pub
8.71
Pub
7.78
Iss
2.80
Iss
2.80
17.3 No. 17
Issuing Body (Country)
Title
Status
/Remarks)
T e s t i n g , Inspection and Surveillance
17.3 Cooling S y s t e m s and C o m p o n e n t s ANSI N626 3 ANSI Qualifications and Duties of Personnel Engaged in ASME Boiler and Pressure Vessel Code, Section III, Division 1 and 2, Certifying ASTM E 213 ASTM Recommended Practice for Ultrasonic Inspection of Metal Pipe and Tubing ASTM E 309 ASTM Recommended Practice for Eddy Current Testing of Steel Tubular Products with Magnetic Saturation DIN 3440 DIN Temperaturregel- und -begrenzungseinrichtungen fur Warmeerzeugungsanlagen DIN 25408 DIN Kemtechnische Anlagen; Rohrleitungen, Auslegung, Herstellung, Priifung (Nuclear Facilities; Piping, Design, Manufacturing, Testing) (For trial use and comments) DIN 25418 DIN Kemtechnische Anlagen; Armaturen, Werkstoffe, Teil 1 Herstellung, Priifung (Nuclear Facilities; Valves Materials, Manufacture, Testing) (For trial use and comments) DIN 25418 Kemtechnische Anlagen; Armaturen, DIN Teil 2 Vorpriifunterlagen und Dokumentation (Nuclear Facilities; Valves, Preliminary Test Documents) GOST 17924 GOST Kontrolle und Dichtigkeit der Hiillen von warmeabgebenden Elementen der Kernreaktoren ISO/DP 7126 ISO Pressure Boundaries of Primary Circuits: Material ISO/R 947 ISO Recommended Practice for Radiographic Inspection of Circumferential Fusion Welded Butt Joints for Steel Pipes up to 50 mm (2 in) Wall Thickness KTA 3201 1 KTA Komponenten des Primarkreises von Leichtwasserreaktoren Teil 1: Werkstoffe (Components for the Primary Circuit of Light Water Reactors Part 1: Materials) KTA 3201.3 KTA Komponenten des Primarkreises von Leichtwasserreaktoren Teil 3: Herstellung (Components for the Primary Circuit of Light Water Reactors Part 3: Manufacturing) RDT A 1-1T ORNL Coolant Composition in Pressurized Water Reactors RDT F 3-7T ORNL Inspection Requirements for Materials Used in Reactor Coolant System Wear Applications RDT F 3-10T ORNL Non-destructive Examination of Reactor Core Components RDT M 12-1T ORNL Test Requirements for Thermal Insulating Materials for Use on Austenitic Stainless Steel R.G. 1.45 USNRC Reactor Coolant Pressure Boundary Leakage Detection Systems R.G. 1.133 USNRC Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (Issued for Comments) SEP 1915 VDEh Ultraschallpriifung auf Langsfehler von Rohren aus warmfesten Stahlen SEP 1918 VDEh Ultraschallpriifung auf Querfehler von Rohren aus warmfesten Stahlen VDEh SEP 1919 Ultraschallpriifung auf Doppelungen von Rohren aus warmfesten Stahlen VdTUV SV 100/3 VdTUV Hinweise fur die Priifung von Sicherheitseinrichtungen gegen Druckiiberschreitung am Einbauort VdTUV Wei 9 VdTUV Giiltigkeit von Spezifikationen fur Komponenten der druckfiihrenden Umschlielsung des Reaktorkiihlmittels fiir Kernkraftwerke mit Leichtwasserreaktoren
Pub
78
Pub
77
Pub
77
Pub
4.76
Pub
8.76
Pub
4.76
Drf
2.77
Pub
72
Ust Pub
69
Pub
2.79
Pub
10.79
Pub Pub
10.71 10.67
Pub 8.77 Amm 4.79 Pub 10.72 Iss
5.73
Iss
9.77
Pub
6.77
Pub
7.77
Pub
7.77
Pub
7.74
Iss
6 79
201
17.3 No.
Issuing Body (Country}
VdTUV Wei 10
VdTUV
VdTUV Wei 17
VdTUV
VdTUV Wei 19
VdTUV
VdTUV 451-75/2
VdTUV
VdTUV 1001
VdTUV
VdTUV Blatt VdTUV Blatt
VdTUV
202
1151 1 1151 2
VdTUV
Title
Status
(Remarks)
Prufumfang fur Hebezeuge in kerntechnischen Anlagen - Wiederkehrende Priifungen Anwendung und Priifung von GulMeilen fur Pumpengehause im Primarkreis von Kernkraftwerken mit Leichtwasserreaktoren aus dem Werkstoff GS 18 NiMoCr37 (Withdrawn 5.79) Verkniipfung des Brennelementbeckenkuhlsystems mit dem Not- und Nachkiihlsystem bei Druckwasserreaktoren der KWU Priifung von Temperaturregel- u. begrenzungseinrichtungen fur Warmeerzeugungsanlagen nach DIN 3440 (See also DIN 3440) Richtlinie iiber Priifungen beim Bau von Gashochdruckleitungen durch den TiiV-Sachverstandigen Richtlinien fur Verfahrenspriifungen an geschweiSten Rohren aus ferritischen Stahlen Richtlinien fur Verfahrensprufungen an geschweiBten Rohren aus austenitischen Stahlen, NE-Metallen und NE-Metall-Legierungen
Iss
5.77
Iss
12.77
Pub
8.75
Pub
11.77
Pub
8.78
Pub
9.77
17.4 No.
Issuing Body (Country)
17
Title
Status
(Remarks)
Testing, Inspection and Surveillance
17.4 C o n t a i n m e n t and Instal ations ANS-6.3 ANS Program for Testing Biological Shielding in Nuclear /ANSI N18.9 Reactor Plants Leakage-Rate Testing of Containment Structures for ANS-7.60 ANS Nuclear Reactors /ANSI N45.4 ANSI N626.2 ANSI Qualifications and Duties for Authorized Nuclear Inspection (Concrete) ASME JC7-47 ASME Inspection and Testing Agency /ACI ASME JC8-6 Inspection of Devision 2 Metal Parts ASME /ACI ASME JC 8-76 ASME Water Soundness Test /ACI ASME QA-76-5 ASME Supplementary Quality Assurance Requirements for /ANSI N45.2.5 Installation, Inspection and Testing of Structural Concrete and Structural Steel, Soils and Foundation During the Construction Phase of Nuclear Power Plants ASTM E 329 ASTM Recommended Practice for Inspection and Testing Agencies for Concrete and Steel as used in Construction CSA N287.4 CSA Construction, Fabrication and Installation Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants CSA CSA N287.6 Preoperational Proof and Leakage Rate Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants CSA N287.7 CSA In-Service Testing and Examination Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants DIN 25436 DIN Integrale Leckratenpriifung des Sicherheitsbehalters, mit der Absolutdruckmethode (Identical with KTA 3405) ISO/R 947 ISO Recommended Practice for Radiographic Inspection of Circumferential Fusion Welded Butt Joints for Steel Pipes up to 50 mm (2 in) Wall Thickness ISO/R 1106 ISO Recommended Parctice for Radiographic Inspection of Fusion Welded Butt Joints for Steel Plates up to 50 mm (2 in) Thick KTA 3401 4 KTA Reaktorsicherheitsbehalter aus Stahl Teil 4: Wiederkehrende Priifungen (Steel Reactor Containment Part 4: Inservice Inspections) • KTA Integrale Leckratenpriifung des Sicherheitsbehalters KTA 3405 mit der Absolutdruckmethode (Integral Test for Leakage Rate of the Containment by Absolute Pressure Method) (Identical with DIN 25436) USNRC Mechanical (Cadweld) Splices in Reinforcing Bars of R.G. 1.10 Category I Concrete Structures USNRC Testing of Reinforcing Bars for Category I Concrete R G 1.15 Structures USNRC Structural Acceptance Test for Concrete Primary R.G. 1.18 Reactor Containments USNRC Non destructive Examination of Primary Containment R.G. 1.19 Liner Welds (Safety Guide 19) USNRC Inservice Inspection of Ungrouted Tendons in R.G. 1 35 Prestressed Concrete Containment Structures (Under Revision; see also Task No SC 810-4) USNRC Inservice Inspection of Prestressed Concrete R G. 1 90 Containment Structures With Grouted Tendons
App
72
App
72
Pub
76
Ust Drf
5.78
Drf
10 78
Pub
78
Pub
77
App
77
App
75
App
75
Pub
7.80
Pub
69
Pub
69
Drf
10.80
Pub
2.79
Iss
1.73
Iss
12 72
Iss
12.72
Iss
8.72
Iss
1.76
Iss
8 77
203
17.4 No.
Issuing Body (Country)
R.G. 1.94
USNRC
R.G. 1.130
USNRC
R.G. 3.11
USNRC
R.G. 3.11.1
USNRC
Task No. RS 809-5
USNRC
Task No. RS 908-5
USNRC
Task No SC 807-4
USNRC
Task No. SC 810-4
USNRC
VdTUV SV 100/3
VdTUV
VdTUV Wei 4
VdTUV
204
Title (Remarks) Quality Assurance Requirements of Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Under Revision; see also Task No. 908-5) Service Limits and Loading Combinations for Class I Plate-and-Shell-Type Component Supports Design, Construction, and Inspection of Embankment Retention Systems for Uranium Mills Operational Inspection and Surveillance of Embankment Retention Systems for Uranium Mill Tailings (Issued for Comments) Qualification Test for Cable Penetration Fire Stops for Use in Nuclear Power Plants (Proposed R. G.) Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations During the Construction Phase of Nuclear Power Plants (Proposed Revision to R.G. 1.94) Determining Prestressing Forces for Inspection of Prestressed Concrete Containments (Proposed R.G. 1.35.1) Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments (Proposed Revision to R.G. 1.35) Hinweise fur die Priifung von Sicherheitseinrichtungen gegen Druckuberschreitung am Einbauort Prufumfang fur Hebezeuge in kerntechnischen Anlagen - Wiederkehrende Prufungen
Status Iss
4.76
Iss
10.78
Iss
12.77
Iss
4.79
Iss
7.79
Iss
9.79
Iss
4.79
Iss
4.79
Pub
7.74
Iss
5.76
17.5 No. 17
Issuing Body (Country) T e s t i n g , Inspection and S
Title (Remarks)
Status
lance
17.5 Electrica I E q u i p m e n t and I n s t r u m e n t a t i o n ANSI N13.5 ANSI Performance Specifications for Direct Reading and Indirect Reading Pocket Dosimeters for X- and Gamma Radiation ANSI N13.10 ANSI Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents ANSI N13.11 ANSI Criteria for Testing Personnel Dosimetry Performance ANSI N42.13 ANSI Calibration and Usage of "Dose Calibrator" Ionization Chambers for the Assay of Radionuclides ANSI N42.14 ANSI Calibration and Usage of Germanium Detectors for Measurement of Gamma-Ray Emmission of Radionuclides ANSI N320 ANSI Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation ANSI N322 ANSI Inspection and Test Specifications for Direct and Indirect Reading Pocket Dosimeters ANSI N323 ANSI Radiation Protection Instrumentation Test and Calibration BS5548 BSI Specification for Radiation Detectors for the Instrumentation and Protection of Nuclear Reactors: Characteristics and Test Methods NF M 60-502 CEA Exposimetres et dosimetres - Methodes generales d'essais (Exposure Meters and Dosimeters: General Methods of Testing) DIN 25409 DIN Fernbedienungsgerate zum Arbeiten hinter Teil 7 Schutzwanden; Kraftmanipulatoren mit elektrischen Antrieben, Anforderungen und Prufungen (Remote Handling Devices for Use behind Shielding Walls; Power Manipulators, Requirements and Tests) DIN 25412 Laboreinrichtungen; Handschuhkasten, DIN Teil 2 Dichtheitsprijfung (Glove Boxes; Leak Test) DIN 25434 Reaktorschutzsystem und Uberwachung von DIN Sicherheitseinrichtungen; Sicherheitstechnische Anforderungen (Reactor Protection System and Monitoring of Safety Devices; Safety Engineering Requirements) (Identical with KTA 3501) DIN 44426 Steuersystem fiir Strahlungsmeftgerate und ihre DIN Teil 1 Zusatzgerate; Grundlagen (Control-System for Electrical Measuring Instruments Used in Connection with Ionizing Radiation) DIN 44426 Steuersystem fiir StrahlungsmeUgerate und ihre DIN Teil 2 Zusatzgerate; Nachrichtengabe durch mechanische Kontakte (Control-System for Electrical Measuring Instruments Used in Connection with Ionizing Radiation) DIN 44427 DIN Prufstrahler zur Funktionskontrolle von Dosisleistungsmessern (Test Source for Checking Dose Rate Meters) DIN 44802 Messen, Steuern, Regeln; Priifverfahren fiir DIN Verstarker und Vorverstarker fiir Halbleiterdetektoren fiir lonisierende Strahlen (Measurement and Control, Test Procedure for Amplifiers and Pre-Amplifiers for Semiconductor Detectors for Ionizing Radiation) IEC 295 IEC DC. Periodmeters: Characteristics and Test Methods
Pub
72
Pub
74
Pub
79
Pub
78
Pub
78
Pub
79
Pub
75
Pub
77
Pub
78
Pub
79
Drf
5.78
Pub
6.78
Pub
10.77
Pub
8.68
Pub
8.68
Pub
8.72
Pub
10.78
Pub
69
205
17.5 No.
Issuing Body (Country)
IEC 333
IEC
IEC 340
IEC
IEC 430
IEC
IEC 462
IEC
IEC 515
IEC
IEC 527
IEC
IEC 583
IEC
IEC 596
IEC
IEEE 300
IEEE
IEEE 301 /ANSI N42.2 IEEE 309 IEEE 325
IEEE IEEE IEEE
IEEE 334 /ANSI N41.9 IEEE 336 /ANSI N45.2.4
IEEE
IEEE 382
IEEE
IEEE 383
IEEE
IEEE 415
IEEE
IEEE 450 /ANSI N41.15
IEEE
IEEE 498
IEEE
IEEE 645
IEEE
IEEE 680
IEEE
ISO 4071
ISO
JIS Z4201 JISZ4511
JIS JIS
KTA 3501
KTA
KTA 3501
KTA
MSZ 14333
MSZH
206
IEEE
Title
Status
(Remarks/
Test Procedures for Semiconductor Detectors for Ionizing Radiation Test Procedures for Amplifiers and Preamplifiers for Semiconductor Detectors for Ionizing Radiation Test Procedures for Germanium Gamma-Ray Detectors Standard Test Procedures for Photomultiplier Tubes for Scintillation Counting Radiation Detectors for the Instrumentation and Protection of Nuclear Reactors; Characteristics and Test Methods Direct Current Amplifiers; Characteristics and Test Methods Dimensions of Test Tubes Made of Glass or Plastics for Radioactivity Measurements Definitions of Test Method Terms for Semiconductor Radiation Detectors and Scintillation Counting Test Procedure for Semiconductor Radiation Detectors Test Procedure for Amplifiers and Preamplifiers for Semiconductor Radiation Detectors Test Procedure for Geiger-Muller Counters Test Procedures for Germanium Gamma-Ray Detectors Standard for Type Tests of Continuous-Duty Class 1E Motors for Nuclear Power Generating Stations Installation Inspection and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations Guide for Type Test of Class 1 Electric Valve Operators for Nuclear Power Generating Stations Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations Guide for Planning of Pre-Operational Testing Programs for Class 1E Power Systems for Nuclear Power Generating Stations Recommended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Substations Supplementary Requirements for Calibration and Control of Measuring and Test Equipment Used in the Construction and Maintenance of Nuclear Power Generating Stations Test Procedures for High Purity Germanium Detectors for Ionizing Radiation Germanium Semiconductor Detector Gamma-Ray Efficiency. Determination Using a Standard Marinelli (Reentrant) Beaker Geometry Exposure Meters and Dosimeters - General Methods for Testing Testing Method for Geiger-Muller Counter Tubes Methods of Calibration for Radiation Exposure Meters Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen (Reactor Protection System and Monitoring of Safety Devices) Reaktorschutzsystem und Uberwachung von Sicherheitseinrichtungen (Reactor Protection System and Monitoring of Safety Devices) (Available also in English; Identical with DIN 25434) Testing of Personnel Gamma Dosimeters at Site
Pub
70
Pub
78
Pub
73
Pub
74
Pub
75
Pub
75
Pub
77
Pub
78
Pub Rev Pub
69 74 76
Pub Pub Rev Pub
70 71 77 74
Pub
77
Pub
72
Pub
77
Pub
76
Pub
75
Pub
75
Pub
77
Pub
78
Pub
78
Pub Pub
77 75
Drf
10.80
Pub
3.77
Pub
78
17.5 No.
Issuing B o d y (Country)
RDTC2-3T
ORNL
RDT F 3-39T
ORNL
R.G. 1.9
USNRC
R G. 1.30
USNRC
R G 1.40
USNRC
R G. 1.41
USNRC
R.G. 1.70.24
USNRC
R.G. 1.73
USNRC
R.G. 1 89
USNRC
R.G. 1.108
USNRC
R.G. 1.118
USNRC
R.G. 1.128
USNRC
R.G. 1.129
USNRC
R.G. 1.131
USNRC
R.G. 4.13
USNRC
R.G 86
USNRC
Task No. RS 050 2
USNRC
VDI 2180 Blatt 4
VDI
VdTUV 451-75/2
VdTUV
Title
Status
(Remarks)
Time Response Test for Sheathed, Mineral Insulated Thermocouple Assembly Testing of High Temperature Cable for Nuclear Detectors Selection, Design, and Qualification of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants Preoperational Testing of Redundant Onsite Electric Power Systems of Verify Proper Load Group Assignments Information for Safety Analysis Reports Environmental Design of Mechanical and Electrical Equipment, Qualification Tests and Analysis (See also R.G. 1.70) Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants Qualification of Class 1E Equipment for Nuclear Power Plants (Under Revision) Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants (Errata Sheet Available) Periodic Testing of Electric Power and Protection Systems Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants Qualification Test of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (Under Revision; see also Task No RS 050-2) Performance, Testing, and Procedural Specifications for Thermoluminescene Dosimetry: Environmental Applications Standard Test Procedures for Geiger-Miiller- Counters Qualification Tests of Electric Cables and Field Splices for Light-Water-Cooled Nuclear Power Plants (Proposed Revision to R.G. 1.131) Sicherung von Anlagen der Verfahrenstechnik; Einfiihrung, Begriffe, Erklarungen; Priifung von Sicherungseinrichtungen Prufung von Temperaturregel- u. begrenzungseinrichtungen fur Warmeerzeugungsanlagen nach DIN 3440 (See also DIN 3440)
Pub
6.72
Pub
8.71
Iss
12.79
Iss
8 72
Iss
3 73
Iss
3.73
Iss
2.75
Iss
1 74
Iss
11 74
Iss
8.77
Iss
6.78
Iss
10.78
Iss
2.78
Iss
8.77
Iss
7.77
Iss
5.73
Iss
8.79
Pub
10 67
Pub
8.75
207
17.6 No. 17
Issuing Body (Country)
Title (Remarks)
Status
T e s t i n g , Inspection and Surveillance
17.6
In-service Surveillance and Recurrent Inspection ANSI Qualifications and Duties for Authorized Inservice Inspection ASME B PVC Sec.XI Boiler and Pressure Vessel Code; Rules for Inservice Inspection of Nuclear Power Plant Components (Regular Addenda and Revisions Provided) ASTM ASTM E 482 Recommended Practice for Neutron Dosimetry for Reactor Pressure Vessel Surveillance ASTM ASTM E 509 Recommended Guide for In-Service Annealing of Water-Cooled Nuclear Reactor Vessels BMI GMBI. 1978 S. 342 Richtlinie fur das Verfahren zur Vorbereitung und Durchfiihrung von Instandhaltungs- und Anderungsarbeiten in Kernkraftwerken vom 1.6 1978 CSA CSA N285.4 Periodic Inspection of CANDU Nuclear Power Plant Components CSA Pre-operational Proof and Leakage Rate Testing CSA N287 6 Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants CSA CSA N287.7 In-Service Testing and Examination Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants CSA CSA Z299.4 Inspection Program Requirements DIN DIN 25435 Kerntechnische Anlagen; Wiederkehrende Teil 1 Prufungen, Mechanisierte Ultraschallpriifung (Nuclear Facilities; Inservice Inspections, Remote-Controlled Ultrasonic Inspection) DIN DIN 25435 Kerntechnische Anlagen; Wiederkehrende Teil 2 Prufungen, Magnetpulverpriifung (Nuclear Facilities; Inservice Inspections, Magnetic Particle Methode) DIN DIN 25435 Kerntechnische Anlagen; Wiederkehrende Teil 3 Prufungen, Druckpriifung (Nuclear Facilities; Inservice Inspections, Pressure Test) DIN DIN 25435 Kerntechnische Anlagen; Wiederkehrende Teil 4 Prufungen, Sichtprufung (Nuclear Installations; Inservice Inspections, Visual Inspection) IAEA IAEA 50-SG-02 In-Service Inspection for Nuclear Power Plants IAEA IAEA 50-SG-08 Standard Tests of Important Systems and Components in Nuclear Power Plants IEEE 338 Criteria for the Periodic Testing of Nuclear Power IEEE Generating Station Safety Systems Visual In-Service Inspection System and Associated ORNL RDTE8-12T Equipment for the Reactor Enclosure System Periodic Testing of Protection System Actuation USNRC R.G. 1.22 Functions (Safety Guide 22) USNRC R.G. 1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures (Under Revision; see also Task No. SC 810-4) USNRC inservice Inspection of ASME Code R.G. 1.51 Class 2 and 3 Nuclear Power Plant Components (Withdrawn 7.75) USNRC R.G. 1.70.20 Information for Safety Analysis Reports - Reactor Coolant Pressure Boundary Material and Inservice Inspection (See also R.G. 1.70) USNRC R.G. 1.70.25 Information for Safety Analysis Reports-lnservice Inspection of ASME Code Class 2 and 3 Components (See also R.G. 1.70) R.G. 1 83 USNRC Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes ANSI N626.1
208
Pub
75
Iss
74
Pub
76
Pub
74
Iss
6.78
App
75
App
75
App
75
Iss Pub
79 8.79
Pub
879
Pub
2.80
Pub
8.79
Ust Ust Pub
77
Pub
7.73
Iss
2.72
Iss
1.76
Iss
1.75
Iss
2.75
Iss
7.75
17.6 No.
Issuing Body (Country)
R.G. 1.90
USNRC
R.G. 1.108
USNRC
R.G. 1.127
USNRC
R.G. 3 22
USNRC
Task No. SC 721-4
USNRC
Task No. SC 810-4
USNRC
VdTUV Wei 10
VdTUV
Title (Remarks) Inservice Inspection of Prestressed Concrete Containment Structures With Grouted Tendons Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants (Errata Sheet Available) Inspection of Water-Control Structures Associated with Nuclear Power Plants Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions Inservice Inspection Code Case Acceptability ASME Section XI. Division 1 (Proposed R G) Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments (Proposed Revision to R.G. 1.35) Priifumfang fur Hebezeuge in kerntechnischen Anlagen - Wiederkehrende Priifungen
Status Iss
877
Iss
8.77
Iss
3.78
Iss
6.74
Iss
8.79
Iss
479
Iss
5.77
209
17.7 No. 17
Issuing Body (Country)
Title (Remarks)
T e s t i n g , Inspection a n d Surveillance
17.7 Pre-operational a n d Initial S t a r t u p Testing Calibration and Usage of "Dose Calibrator" ANSI ANSI N42.13 Ionization Chambers for the Assay of Radionuclides ANSI N42.14 Calibration and Usage of Germanium Detectors for ANSI Measurement of Gamma-Ray Emmission of Radionuclides ASME OM-75-2 Vibration Systems - Monitoring and Testing ASME Requirements ASME ASME OM-75-6 Performance Testing of Safety Valves DIN 25418 DIN Kerntechnische Anlagen; Armaturen, Teil 2 Vorpriifunterlagen und Dokumentation (Nuclear Facilities; Valves, Preliminary Test Documents) IAEA IAEA 50-SG-QA4 Quality Assurance During Site Construction of Nuclear Power Plants IAEA 50-SG-04 Commissioning Procedures for Nuclear Power Plants IAEA IEEE IEEE 415 Guide for Planning of Pre-Operational Testing Programs for Class 1E Power Systems for Nuclear Power Generating Stations GSN-13 JEN Programa de Pruebas Pre-Nucleares y Nucleares. (Programme of Pre-Nuclear and Nuclear Tests) R.G. 1.20 USNRC Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing R.G. 1.41 USNRC Preoperational Testing of Redundant Onsite Electric Power Systems of Verify Proper Load Group Assignments R.G. 1.68 USNRC Initial Test Programs for Water-Cooled Nuclear Power Plants R.G. 1.68.1 USNRC Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants R.G. 1.68.2 USNRC Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants R.G. 1.73 USNRC Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants R.G. 1.79 USNRC Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors R.G. 1.80 USNRC Preoperational Testing of Instrument Air Systems (Under Revision)
210
Status
Pub
78
Pub
78
Ust Ust Drf
2 77
Ust Ust Pub
76
Drf
79
Iss
5.76
Iss
3 73
Iss
8.78
Iss
177
Iss
7.78
Iss
1.74
Iss
9 75
Iss
6.74
18.1 No. 18
Issuing Body (Country)
Status
Title (Remarks)
Material S t a n d a r d s
18.1 Cooling S y s t e m s and C o m p o n e n t s B PVC Sec.ll ASME Boiler and Pressure Vessel Code; Material Specifications, Part A • Ferrous Materials, Part B Nonferrous Materials, Part C - Welding Rods, Electrodes and Filler Metals (Regular Addenda and Revisions Provided) ASTM A 336 ASTM Alloy Steel Forgings Pressure and High Temperature Parts ASTM A 409 ASTM Specification for Welded Large outside Diameter Light-Wall Austenitic Chromium.Nickel Alloy Steel Pipe for Corrosive or High-Temperature Service ASTM A 608 ASTM Specification for Centrifugally Cast Iron-Chromium-Nickel in High Alloy Tubing for Pressure Application at High Temperature ASTM A 637 ASTM Specification for Precipitation Hardening Nickel Alloy Bars, Forgings, and Forging Stock for High-Temperature Service ASTM A 638 ASTM Specification for Precipitation Hardening Iron-Base Super Alloy Bars, Forgings and Forging Stock for High-Temperature Service ASTM A 639 ASTM Specification for Precipitation Hardening Cobalt Containing Alloy Bars, Forgings. and Forging Stock for High-Temperature Service DIN 25418 DIN Kerntechnische Anlagen; Armaturen, Werkstoffe, Teil 1 Hersiellung, Prufung (Nuclear Facilities; Valves Materials, Manufacture, Testing) (For trial use and comments) DIN Kerntechnische Anlagen; Armaturen, DIN 25418 Teil 2 Vorprufunterlagen und Dokumentation (Nuclear Facilities; Valves, Preliminary Test Documents) KTA KTA 3201.1 Komponenten des Primarkreises von Leichtwasserreaktoren Teil 1; Werkstoffe (Components for the Primary Circuit of Light Water Reactors Part 1: Materials) Komponenten des Primarkreises von KTA 3201.3 KTA Leichtwasserreaktoren Teil 3: Herstellung (Components for the Primary Circuit of Light Water Reactors Part 3; Manufacturing) RDT M 2-3T ORNL Carbon and Alloy Steel Welding Fittings (ASME SA-234 with additional requirements) RDT M 2-5T ORNL Austenitic Stainless Steel Welding Fittings (ASME SA-403 with additional requirements) RDT M 2-6T ORNL Martensitic Stainless Steel (Type 403) Forgings (ASME SA-182 with additional requirements) Nickel-Molybdenum-Chromium Alloy Forgings ORNL RDT M 2-11T (ASME SA-182 with additional requirements) RDT M 2-12T Nickel-Molybdenum-Chromium Alloy Welding ORNL Fittings (ASME SA-403 with additional requirements) RDT M 2-15T Nickel-Chromium Alloy Bars, Forgings and Forging ORNL Stock (ASME SA-637 with additional requirements) RDT M 2-18T ORNL Precipitation Hardening Nickel Alloy Bars, Forgings and Forging Stock for High-Temperature Service (ASTM A 637 with additional requirements) RDT M 2 19T 2-1/4°/o-Chromium, 1%-Molybdenum Alloy Steel ORNL Tubesheet Forgings (ASME SA-336 with additional requirements) RDT M 2-20T ORNL Nickel Alloy Forgings (ASME SB-564 with additional requirements)
74
Pub
77
Pub
77
Pub Rev
70 76
Pub
76
Pub
76
Pub
76
Pub
4.76
Drf
2.77
Pub
2.79
Pub
10.79
Pub
8.79
Pub
8.79
Pub
8.79
Pub
8.79
Pub
8.79
Pub
7.79
Pub
8 79
Pub
8.79
Pub
8 79
211
18.1 No.
Issuing Body (Country)
RDT M 2-21T
ORNL
RDT M 3-4T
ORNL
RDT M 3-9T
ORNL
RDTM 3-10T
ORNL
RDTM 3-17T
ORNL
RDTM 3-18T
ORNL
RDT M 3-27T
ORNL
RDT M 3-28T
ORNL
RDT M 3-29T
ORNL
RDT M 3-30T
ORNL
RDT M 3-33T
ORNL
RDT M 3-34T
ORNL
RDT M 4-3T RDT M 4-5T
ORNL ORNL
RDT M 4-6T
ORNL
RDT M 5-19T
ORNL
RDT M 7-23T
ORNL
RDT M 7-24T RDT M 8-1T
ORNL ORNL
R.G. 1.70.20
USNRC
R.G. 1.70 28
USNRC
R.G. 1.85
USNRC
SEW 409
VDEh
SEW 550 SEW 590-61 SEW 640
VDEh VDEh VDEh
212
Title
Status
(Remarks)
Forgings and Bars for Nuclear and Other Special Applications (ASME SA-654 with additional requirements) Nickel Alloy Seamless Tubes (ASME SB-163 with additional requirements) Nickel-lron-Chromium Alloy Seamless Pipe and Tubing (ASME SB-407 with additional requirements) Nickel-Molybdenum-Chromium Alloy Seamless Pipe and Tubes (ASME SB-167 with additional requirements) Nickel-Molybdenum-Chromium Alloy Welded Pipe (ASME SA-358 with additional requirements) Nickel-Molybdenum-Chromium Alloy Seamless Tubes (ASME SB-163 with additional requirements) Seamless and Welded Small Diameter Austenitic Stainless Steel Tubing (ASTM A 632 with additional requirements) Austenitic Stainless Steel and Superalloy Tubing for BRP Core Components Nickel-Chromium-Molybdenum-Columbium Alloy Seamless Tubes (AMS 5589 with additional requirements) Nickel-Chromium-Molybdenum-Columbium Alloy Seamless Tubes (AMS 5590 with additional requirements) 2-1/4%-Chromium, 1%-Molybdenum Alloy Steel Seamless Tubes (ASME SA-213 with additional requirements) Pipe and Tubing for Nuclear and Other Special Applications (ASME SA-655 with additional requirements) Cobalt-Chromium Alloy Castings Nickel-Molybdenum-Chromium Alloy Castings (ASTM A 494 with additional requirements) Steel Castings for Nuclear and Other Special Applications (ASME SA-613 with additional requirements) Austenitic Stainless Steel Plate, Sheet and Strip for Core Components Austenitic Stainless Steel Bar for Core Components Austenitic Stainless Steel Wire for Core Components Helical Age-Hardenable Nickel-Chromium-lron Alloy Springs Information for Safety Analysis Reports - Reactor Coolant Pressure Boundary Material and Inservice Inspection (See also R. G 1.70) Information for Safety Analysis Reports - Steam and Feedwater System Materials (See also R. G 1.70) Materials Code Case Acceptability-ASME Section III Division I (Under Revision) Korrosionsbestandige SchweiSplattierungen fur Kernenergieanlagen Stahle fur groftere Schmiedestiicke Druckwasserstoffbestandige Stahle Stahle fur Bauteile im Primarkreislauf von Kernenergie-Erzeugungsanlagen
Pub
12.77
Pub
8.79
Pub
4.76
Pub
4.76
Pub
879
Pub
8.79
Pub
8.79
Pub
11.77
Pub
4.76
Pub
4.76
Pub
8.79
Pub 12.77 Amm 2.78 Pub Pub
7.75 4.76
Pub
12.77
Pub
3.73
Pub Amm Pub Pub
3.73 4.74 3.73 5.75
Iss
1.75
Iss
4.75
Iss
5.79
Pub
3.72
Pub Pub Pub
876 12.61 575
18.1 No.
Issuing Body (Country)
SEW 640 Bbl 1
VDEh
VdTUV GW-WB VdTUV Wei 18
VdTUV VdTUV
VdTUV 1153
VdTUV
VdTUV 1156
VdTUV
Status
Title (Remarks) Stähle für Schrauben und Muttern größerer Abmessungen fur eine Verwendung bei mäßig erhohten Temperaturen als Bauteile im Primarkreislauf von Kernenergie-Erzeugungsanlagen Grundwerk Werkstoffblatter ca. 180 Blatt Einsatz hoherfester Feinkornbaustahle in Kernkraftwerken Richtlinien für die Eignungspriifung von Schweißzusatzwerkstoffen Verfahrenspriifungen fur die Hartauftragschweißung (Panzern)
Pub
1.78
Iss
7.77
Pub
11.77
Pub
11.78
213
18.2 No. 18
Issuing B o d y (Country)
Title (Remarks)
Material S t a n d a r d s
18.2 Pressu re Vessel s and Boiilers AD-Merkblatt H 3 Herstellung von Druckbehaltern; Priifung von AD Fertigteilen aus Stahlblech AD-Merkblatt HP 2/1 Herstellung und Priifung von Druckbehaltern; AD Anl.1 Abgrenzung des Geltungsbereiches fur Stahl AD-Merkblatt HP 7/1 Herstellung und Priifung von Druckbehaltern; AD Warmebehandlung, Allgemeine Grundsatze AD-Merkblatt HP 7/2 Herstellung und Priifung von Druckbehaltern; AD Warmebehandlung, Ferritische Stahle AD-Merkblatt HP 7/3 Herstellung und Priifung von Druckbehaltern; AD Warmebehandlung, Austenitische Stahle AD-Merkblatt W 0 Werkstoffe fur Druckbehalter; Allgemeine AD Grundsatze fiir Werkstoffe AD-Merkblatt W 1 Werkstoffe fur Druckbehalter; Unlegierte und AD legierte Stahle fiir Bleche AD-Merkblatt W 2 AD Werkstoffe fiir Druckbehalter; Austenitische Stahle AD AD-Merkblatt W 3 / 1 Werkstoffe fiir Druckbehalter; GuSeisenwerkstoffe Gulieisen mit Lamellengraphit (GrauguB) unlegiert und niedriglegiert AD-Merkblatt W 3/2 AD Werkstoffe fiir Druckbehalter; GulSeisenwerkstoffe GuBeisen mit Kugelgraphit unlegiert und niedriglegiert AD-Merkblatt W 3 / 3 AD Werkstoffe fiir Druckbehalter; GuBeisenwerkstoffe Austenitisches GuBeisen mit Lamellengraphit AD-Merkblatt W 4 AD Werkstoffe fiir Druckbehalter; Rohre aus unlegierten und legierten Stahlen als Bestandteile von Druckbehaltern AD AD-Merkblatt W 4 Werkstoffe fur Druckbehalter; Anlage 1 zum Anl.1 AD-Merkblatt W 4 AD-Merkblatt W 5 AD Werkstoffe fiir Druckbehalter; StahlgufJ AD-Merkblatt W 6 / 1 AD Werkstoffe fiir Druckbehalter; Aluminium und Aluminiumlegierungen, Knetwerkstoffe AD AD-Merkblatt W 7 Werkstoffe fiir Druckbehalter; Schrauben und Muttern aus Stahl AD Werkstoffe fur Druckbehalter; Plattierte Stahlbleche AD-Merkblatt W 8 AD AD-Merkblatt W 10 Werkstoffe fiir Druckbehalter; Werkstoffe fiir tiefe Temperaturen, Eisenwerkstoffe AD Werkstoffe fur Druckbehalter; Nahtlose Hohlkorper AD-Merkblatt W 12 aus unlegierten und legierten Stahlen fiir Druckbehaltermantel AD-Merkblatt W 13 AD Werkstoffe fur Druckbehalter; Unlegierte und legierte Stahle fiir gewalzte Teile und Schmiedestiicke E 32-102 AFNOR Code de construction des generateurs de vapeur Partie II: Materiaux B PVC Sec.ll ASME Boiler and Pressure Vessel Code; Material Specifications, Part A - Ferrous Materials, Part B Nonferrous Materials, Part C - Welding Rods, Electrodes and Filler Metals (Regular Addenda and Revisions Provided) B PVC Sec.X ASME Boiler and Pressure Vessel Code; Fiberglass-Reinforced Plastic Pressure Vessels (Regular Addenda and Revisions Provided) ASTM A 20 ASTM Steel Plates for Pressure Vessels ASTM A 204 ASTM Specification for Molybdenum Alloy-Steel Plate for Pressure Vessels ASTM ASTM A 217 Specification for Alloy Steel Castings for Pressure Containing Parts Suitable for High-Temperature
Service
214
Status
Pub
7.69
Pub
2 77
Pub
4.75
Pub
12 77
Pub
4.75
Pub
5.74
Pub
6.77
Pub Pub
12 77 3.68
Pub
5.74
Pub
4.70
Pub
9.64
Pub
4.69
Pub Pub
2.73 6.72
Pub
12.78
Pub Pub
12.75 11.76
Pub
6.77
Pub
9.73
Iss
77
Iss
74
Iss
74
Pub Pub
77 74
Pub
77
18.2 No.
Issuing Body (Country)
ASTM A 240
ASTM
ASTM A 285
ASTM
ASTM A 299
ASTM
ASTM A 302
ASTM
ASTM A 336
ASTM
ASTM A 352
ASTM
ASTM A 387
ASTM
ASTM A 442
ASTM
ASTM A 453
ASTM
ASTM A 473
ASTM
ASTM A 479
ASTM
ASTM A 487
ASTM
ASTM A 508
ASTM
ASTM A 515
ASTM
ASTM A 516
ASTM
ASTM A 517
ASTM
ASTM A 533
ASTM
ASTM A 537
ASTM
ASTM A 541
ASTM
ASTM A 542
ASTM
ASTM A 553
ASTM
ASTM A 605
ASTM
ASTM A 608
ASTM
ASTM A 637
ASTM
Title
Status
(Remarks)
Specification for Corrosion, Resisting Chromium and Chromium-Nickel Steel Plate. Sheet and Strip for Fusion Elded Unfired Pressure Vessels Specification for Low and Intermediate Tensile Strength Carbon Steel Plates for Pressure Vessels Specification for Carbon Manganese Silicon Steel Plates for Pressure Vessels Specification for Manganese-Molybdenum and Manganese-Molybdenum-Nickel Alloy Steel Plates for Pressure Vessels Alloy Steel Forgings Pressure and High Temperature Parts Ferritic Steel Castings for Pressure Containing Parts, Suitable High-Temperature Service Specification for Chromium-Molybdenum Alloy Steel Plates for Pressure Vessels Specification for Carbon Steel Plates with Improved Transition Properties for Pressure Vessels Specification for High Strength, High Temperature Bolting Materials, with Expansion Coefficients Comparable with Austenitic Steel Specification for Stainless and Heat Resisting Steel Forgings Specification for Stainless and Heat Resisting Steel Bars and Shapes for Use in Boiler and other Pressure Vessels Specification for Low Alloy Steel Castings Suitable for Pressure Service Specification for Quenched and Tempered Vacuum Treated Carbon and Alloy Steel Forgings for Pressure Vessels Specification for Carbon Steel Plates for Pressure Vessels for Intermediate and Higher Temperature Service Specification for Carbon Steel Plates for Pressure Vessels for Moderate and Lower Temperature Service Specification for High-Strength Alloy Steel Plates, Quenched and Tempered, for Pressure Vessels Manganese-Molybdenum and Manganese-Molybdenum-Nickel Alloy Steel Plates, Quenched and Tempered for Pressure Vessels Carbon-Manganese-Silicon Steel Plates, Heat Treated, for Pressure Vessels Specification for Quenched and Tempered Carbon and Alloy Steel, Forgings for Pressure Vessel Components Specification for Chromium-Molybdenum Alloy Steel Plates, Quenched and Tempered, for Pressure Vessels Specification for Eight and Nine Percent Nickel Alloy Steel Plate, Quenched and Tempered, for Pressure Vessels Standard Specification for Nickel-Cobalt-Molybdenum Chromium Alloy Steel Plates, Quenched and Tempered, tor Pressure Vessels Specification for Centrifugally Cast Iron-Chromium-Nickel in High Alloy Tubing for Pressure Application at High Temperature Specification for Precipitation Hardening Nickel Alloy Bars, Forgings, and Forging Stock for High-Temperature Service
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
76
Pub
77
Pub
76
Pub
77
Pub
74
Pub
77
Pub
77
Pub
77
Pub
77
Pub
76
Pub
77
Pub
74
Pub Rev
72 77
Pub Rev
70 76
Pub
76
215
18.2 Issuing Body (Country)
No. ASTM A 638
ASTM
ASTM A 639
ASTM
TRD TRD TRD TRD
100 101 103 104
DDA DDA DDA DDA
TRD 105
DDA
TRD 106 TRD 107 TRD 108
DDA DDA DDA
TRD 202 R.G. 1.65
DDA USNRC
R.G. 1.70.12
USNRC
R.G. 1.70.20
USNRC
R.G. 1.70.28
USNRC
R.G. 1.99
USNRC
R.G. 1.121
USNRC
10 CFR 50 Appendix H USNRC SEL 072 SEL 075 SEL 096
VDEh VDEh VDEh
SEW 088
VDEh
SEW 089-70 SEW 400 SEW 409
VDEh VDEh VDEh
SEW 550 SEW 590-61 SEW 640
VDEh VDEh VDEh
SEW 640 Bbl 1
VDEh
VdTUV GW-WB VdTUV Wei 18
VdTUV VdTUV
216
Title
Status
(Remarks)
Specification for Precipitation Hardening Iron-Base Super Alloy Bars, Forgings and Forging Stock for High-Temperature Service Specification for Precipitation Hardening Cobalt Containing Alloy Bars, Forgings, and Forging Stock for High-Temperature Service Allgemeine Grundsatze fur Werkstoffe Bleche, PreS- und KLimpelteile StahlguU Schiisse, Trommeln und ahnliche Hohlkorper ohne LangsschweiBnaht mit einem lichten Durchmesser von 600 mm und mehr aus Stahl Nahtlose Sammelrohre, Sammler und ahnliche Hohlkorper, mit einem lichten Durchmesser unter 600 mm Schrauben und Muttern aus Stahl Kesselteile aus Formstahl und Schmiedestiicken Gufteisen mit Lamellengraphit und GuISeisen mit Kugelgraphit Priifung von Fertigteilen aus Stahlblech Materials and Inspection for Reactor Vessel Closure Studs Information for Safety Analysis Reports - Reactor Material (See also R.G. 1.70) Information for Safety Analysis Reports - Reactor Coolant Pressure Boundary Material and Inservice Inspection (See also R. G. 1.70) Information for Safety Analysis Reports - Steam and Feedwater System Materials (See also R. G. 1.70) Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials Bases for Plugging Degraded PWR Steam Generator Tubes Reactor Vessel Material Survillance Program Requirements Ultraschallgepriiftes Grobblech Plattierte Stahlbleche Blech, Band und Breitflachstahl mit verbesserten Eigenschaften fur Beanspruchungen senkrecht zur Erzeugnisoberflache SchweiBgeeignete Feinkornbaustahle, Richtlinien fiir die Verarbeitung, besonders fiir das SchweiBen SchweiSbare Feinkornbaustahle, Giitevorschriften Nichtrostende Walz- und Schmiedestahle Korrosionsbestandige SchweiBplattierungen fiir Kernenergieanlagen Stahle fiir grolsere Schmiedestiicke Druckwasserstoffbestandige Stahle Stahle fiir Bauteile im Primarkreislauf von Kernenergie-Erzeugungsanlagen Stahle fur Schrauben und Muttern grofJerer Abmessungen fiir eine Verwendung bei malSig erhohten Temperaturen als Bauteile im Primarkreislauf von Kernenergie-Erzeugungsanlagen Grundwerk Werkstoffblatter ca. 180 Blatt Einsatz hoherfester Feinkornbaustahle in Kernkraftwerken
Pub
76
Pub
76
Pub Pub Pub Pub
4.75 5.74 670 271
Pub
4.73
Pub Pub Pub
6.77 5.74 578
Pub Iss
2.71 10.73
Iss
75
Iss
1.75
Iss
4.75
Iss
4.77
Iss
8.76
Pub
12.77
Pub
5.74
Pub
10.76
Pub Pub Pub
7.70 12.73 3.72
Pub Pub Pub
8.76 12.61 5.75
Pub
1.78
Iss
7.77
18.3 No.
Issuing Body (Country)
18
Material S t a n d a r d s
18.3
Steel C o n t a i n m e n t
B PVC Sec.ll
ASME
ASTM A 440 BS 4208
ASTM BSI
ISO/DP 7126 ISO/R 630 ISO/R 683/I
ISO ISO ISO
ISO/R 683/II
ISO
ISO/R 683/III
ISO
ISO/R 683/IV
ISO
ISO/R 683/V
ISO
ISO/R 683/VI
ISO
ISO/R 683/VII
ISO
ISO/R 683/VIII
ISO
ISO/R 683/IX
ISO
ISO/R 683/X
ISO
ISO/R 683/XI
ISO
KTA 3401.1
KTA
KTA 3401.3
KTA
SEL072 SEL075 SEL096
VDEh VDEh VDEh
SEW 088
VDEh
SEW 089-70 SEW 400 VdTUV Wei 18
VDEh VDEh VdTUV
Status
Title (Remarks)
Boiler and Pressure Vessel Code; Material Specifications, Part A - Ferrous Materials, Part B Nonferrous Materials, Part C - Welding Rods, Electrodes and Filler Metals (Regular Addenda and Revisions Provided) Specification for High-Strength Structural Steel Carbon and Low Alloy Steel. Containment Structures for Stationary Nuclear Power Reactors Pressure Boundaries of Primary Circuits: Material Structural Steels Heat-Treated Steels, Alloy Steels and Free Cutting Steels Part 1: Quenched and Tempered Unalloyed Steels Heat-Treated Steels, Alloy Steels and Free Cutting Steels Part 2: Wrought, Quenched and Tempered Steels with 1 % Chromium and 0,2% Molybdenum Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 3: Wrought Quenched and Tempered Unalloyed Steel with Controlled Sulphur Content Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 4: Wrought Quenched and Tempered Steels with 1 % Chromium and 0,2% Molybdenum and Controlled Sulphur Content Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 5: Wrought Quenched and Tempered Manganese Steels Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 6: Wrought Quenched and Tempered Steels with 3% Chromium and 0,5% Molybdenum Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 7: Wrought Quenched and Tempered Chromium Steels Heat Treated Steels, Alloy Steels and Free-Cutting Steels Part 8: Wrought Quenched and Tempered Chromium-Nickel Molybdenum Steels Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 9: Wrought Free-Cutting Steels Heat-Treated Steels, Alloy Steels and Free-Cutting Steels Part 10: Wrought Nitriding Steels Heat-Treated Steels, Alloy Steel and Free-Cutting Steels Part 11: Wrought Case Hardening Steels Reaktorsicherheitsbehalter aus Stahl Teil 1: Werkstoffe (Steel Reactor Containment Part 1: Materials! Reaktorsicherheitsbehalter aus Stahl Teil 3: Herstellung (Steel Reactor Containment Part 3: Manufacturing) Ultraschallgepriiftes Grobblech Plattierte Stahlbleche Blech, Band und Breitflachstahl mit verbesserten Eigenschaften fur Beanspruchungen senkrecht zur Erzeugnisoberflache SchweiSgeeignete Feinkornbaustahle, Richtlinien fur die Verarbeitung, besonders fur das SchweifJen SchweiSbare Feinkornbaustahle, Gutevorschriften Nichtrostende Walz- und Schmiedestahle Einsatz hoherfester Feinkornbaustahle in Kernkraftwerken
Iss
74
Pub Pub
77 67
Ust Pub Pub
67 68
Pub
68
Pub
70
Pub
70
Pub
70
Pub
70
Pub
70
Pub
70
Pub
70
Pub
75
Pub
70
Pub
6.80
Pub
10 79
Pub
12.77
Pub
5.74
Pub
10.76
Pub Pub Iss
7 70 12.73 7 77
217
18.4 No. 18
Issuing Body (Country) Material Standards
18.4 Concrete C o n t a i n m e n t ASME ASME JC 8-18 /ACI ASME ASME JC 8-53 /ACI ASTM ASTM C 637 /ANSI N648 ASTM C 638 /ANSI N649
ASTM
CSA N287.2
CSA
CSA N287.4
CSA
DIN 25413
DIN
R.G. 1.55 R.G. 1.107
USNRC USNRC
R.G. 1.136
USNRC
Task No SC 814-5
USNRC
218
Status
Title (Remarks)
Concrete Requirements
Drf
6.78
Use of SA-216 Material for Containment
Drf
878
Specification for Aggregats for Radiation-Shielding Concrete (Reapproved) Descriptive Nomenclature of Constituents of Aggregates for Radiation Shielding Concrete (Reapproved) Material Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants Construction, Fabrication and Installation Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants Klassifikation von Betonen nach Elementanteilen bei Verwendung zur Neutronenabschirmung (Classification of Concretes for Neutron Shielding with Respect to Atomic Composition) Concrete Placement in Category I Structures Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures Material for Concrete Containments (Under Revision; see also Task No. SC 814-5) Materials, Construction, and Testing of Concrete Containments (Articles CC-1000, -2000, and -4000 through -7000 of the "Code for Concrete Reactor Vessels and Containments") (Proposed Revision to R.G. 1.136)
Pub App
73 279
Pub App
73 2.79
App
76
App
77
Pub
376
Iss Iss
6.73 2.77
Iss
10.78
Iss
11.79
18.5 No. 18
Issuing Body (Country)
Status
Title
/Remarks)
Material S t a n d a r d s
18.5
Other Relevant M a t e r i a l S t a n d a r d s Boiler and Pressure Vessel Code; Material BPVCSecll ASME Specifications, Part A - Ferrous Materials, Part B Nonferrous Materials, Part C - Welding Rods, Electrodes and Filler Metals (Regular Addenda and Revisions Provided) Specification for Alloy-Steel and Stainless Steel ASTM A 193 ASTM Bolting Materials for High-Temperature Service Specification for Carbon and Alloy-Steel Nuts for ASTM A 194 ASTM Bolts for High-Pressure and High Temperature Service ASTM A 216 /ANSI G37.2 ASTM A 217
ASTM /ANSI ASTM
ASTM A 263
ASTM
ASTM A 264
ASTM
ASTM A 265
ASTM
ASTM A 276
ASTM
ASTM A 320
ASTM
ASTM A 351
ASTM
ASTM A 356
ASTM
ASTM A 494 ASTM A 540
ASTM ASTM
ASTM A 564
ASTM
ASTM A 607
ASTM
ASTM A 613
ASTM
ASTM A 614
ASTM
ASTM A 647
ASTM
ASTM A 654
ASTM
ASTM D 3911
ASTM
ASTM D 3912
ASTM
ASTM D 3913
ASTM
ASTM E 105
ASTM
Specification for Carbon-Steel Castings Suitable for Fusion Welding for High-Temperature-Service Specification for Alloy Steel Castings for Pressure Containing Parts Suitable for High-Temperature Service Specification for Corrosion-Resisting Chromium-Steel Clad Plate, Sheet, and Strip Specification for Stainless Chromium-Nickel-Steel Clad Plate, Sheet, and Strip Specification for Nickel and Nickel-Base Alloy Clad Steel Plate Specification for Stainless and Heat Resisting Steel-Bars and Shapes Specification for Alioy Steel Bolting-Materials for Low Temperature Service Specification for Ferritic and Austenitic Steel Castings for High-Temperature Service Specification for Heavy-Walled Carbon and Low Alloy Steel Casting for Steam Turbines Specification for Nickel and Nickel Alloy Castings Specification for Alloy Steel Bolting Materials for Special Applications Specification for Hot-Rolled and Cold Finished Pecipitation-Hardening-Stainless and Heat-Resisting Steel Bars and Shapes Specification for Steel Sheet and Strip Hot Rolled and Cold-Rolled, High-Strength, Low-Alloy Columbium and/or Vanadium Specification for Special Requirements for Steel Castings for Nuclear and other Special Applications Specification for Special Requirements for Bolting Material for Nuclear and other Special Applications Specification for Special Requirements for Steel Plates for Nuclear and other Applications Specification for Special Requirements for Forgings and Bars for Nuclear and other Applications Evaluation of Coatings Used in Light Water Nuclear Power Plants at Simulated Loss of Coolant Accident (LOCA) Conditions, Test Method Determining the Chemical Resistance of Coatings Used in Light Water Nuclear Power Plants Evaluating the Physical Properties of Coatings Used in Light Water Nuclear Power Plants, Test Method Recommended Practice for Probability Sampling of Materials
Iss
74
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub
77
Pub Pub
76 77
Pub
74
Pub
75
Pub
76
Pub
76
Pub
77
Pub
77
Pub
80
Pub
80
Pub
80
Pub
75
219
18.5 No.
Issuing Body (Country)
ASTM E419
ASTM
ASTM E 560
ASTM
BS 3909 BS 4247
BSI BSI
BS4247 Part II BS4513 Chapitre VII
BSI BSI CEA
MCH/MENT 7
CEA
•
CEA
DIN 17155 Teil 1
DIN
DIN 17155 Teil 2
DIN
DIN 17155 Teil 2 Bbl
DIN
DIN 17440
DIN
DIN 50049
DIN
GOST 18298
GOST
JIS Z4808 JIS Z4809 JISZ4810
JIS JIS JIS
JIS Z4811
JIS
MSZ 14348
MSZH
RDT C 7-3T
ORNL
RDT C 7-4T
ORNL
RDT C 7-5T
ORNL
RDT C 7-6T
ORNL
RDT C 7-7T
ORNL
RDTC 17-5T
ORNL
RDT M 5-4T
ORNL
RDT M 5-7T
ORNL
220
Title (Remarks) Guide for Selection of Neutron Activation Detector Materials Recommended Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties Ingot Lead for Radiation Shielding The Assessment of Surface Materials for Use in Radioactive Areas Guide of the Selection of Materials Lead Bricks for Radiation Shielding Vetements de protection (See "Catalogue de materiel normalise") Susceptibilite du materiel d'electronique nucleaire a impulsions aux parasites Catalogue de materiel normalise "Protection-Manipulation-Detection-Surete" Kesselbleche; Technische Lieferbedingungen (Boilerplates; technical conditions of delivery) (Available also in English) Kesselbleche; Giitevorschriften fur die verwendeten Stahle (Boilerplates; quality specifications) (Available also in English) Kesselbleche; Langzeit-Warmfestigkeitswerte (Boilerplates; longterm creep and stress-rupture properties) (Available also in English) Nichtrostende Stahle; Giitevorschriften (Stainless Steels; quality specifications) (Available also in English) Bescheinigungen iiber Werkstoffprufungen (Certificates on material tests) (Available also in English) Strahlungsfestigkeit von Apparaten, Zubehorteilen und Werkstoffen Glove Box for Handling of Radioactive Substance Protective Clothing for Radioactive Contamination Rubber Gloves for Handling of Unsealed Radioisotopes Synthetic Rubber Boots for Handling of Unsealed Radioisotopes Lead-Brick for Radiation Shielding. Technical Requirements Thermocouple Material, Copper and Constantan, Sclid Conductor (Bare, Fiberglass Insulated, and Sheathed Over Fiberglass Insulation) Thermocouple Material, Copper-Constantan, Mineral-Oxide Insulated, Sheathed Thermocouple Material, Chromel-P and Alumel, Solid Conductor (Bare, Fiberglass Insulated, and Sheathed Over Fiberglass Insulation) Thermocouple Material and Thermocouple Assembly, Chrcmel-P versus Alumel, Stainless Steel Sheathed, Magnesium Oxide Insulated Thermocouple Materials, Platinum and Platinum 10 Percent Rhodium Wires, Noninsulated, Standard Grade Metal-Sheathed, Mineral-Insulated Cable Bulk Material Nickel-Chromium-lron Alloy Plate, Sheet and Strip (ASME SB-168 with additional requirements) Nickel-Iron-Chromium Alloy Plate, Sheet and Strip (ASME SB-409 with additional requirements)
Status Pub
73
Pub
72
Pub
65
Pub Pub Iss
69 69
Pub
72
Pub
1.59
Pub
1.59
Pub
6 69
Pub
12.72
Pub
7.72
Pub
72
Pub Pub Pub
75 75 61
Pub
61
Pub
77
Pub
9.76
Pub Amm Pub
4.70 1.73 1.73
Pub Amm
2.75 2.76
8.72 Pub Amm 11.74 Pub Amm Pub
2.73 4.74 8.79
Pub
8.79
18.5 No.
Issuing Body (Country)
RDT M 5-8T
ORNL
RDT M 5-20T
ORNL
RDT M 5-21T
ORNL
RDT M 5-23T
ORNL
RDT M 6-1T
ORNL
RDT M 6-2T
ORNL
RDT M 6-3T
ORNL
RDT M 6-4T
ORNL
RDT M 6-5T
ORNL
RDT M 6-6T
ORNL
RDT M 7-1T
ORNL
RDT M 7-3T
ORNL
RDT M 7-4T
ORNL
RDT M 7-6T
ORNL
RDTM 7-7T RDT M 7-10T
ORNL ORNL
RDT M 7-11T
ORNL
AESS 6060
UKAEA
AESS(R)10338 AESS(R|11753
UKAEA UKAEA
AESS|R)11756 R.G. 1.31
UKAEA USNRC
R G 1 34 R.G. 1.36
USNRC USNRC
R.G. 1.43
USNRC
R.G. 1.44 R G 1.70.12
USNRC USNRC
R.G. 1 70 26
USNRC
Title
Status
(Remarks)
Nickel-Molybdenum-Chromium Alloy Sheet and Plate (ASME SB-434 with additional requirements) Nickel-Chromium-Molybdenum-Cnlumbium Alloy Plate, Sheet and Strip (AMS 5597 with additional requirements) Nickel-Chromium-Molybdenum-Columbium Alloy Plate, Sheet and Strip (AMS 5596 with additional requirements) Steel Plates for Nuclear and Other Special Applications (ASME SA-647 with additional requirements) Alloy Steel Bolting Material for Low-Temperature Service (ASME SA-320 with additional requirements) Mechanical Locking Devices Alloy Steel Bolting Material for High-Temperature Service (ASME SA-193 with additional requirements) Alloy Steel Nuts for Bolting for High-Pressure and High-Temperature Service (ASME SA-194 with additional requirements) Alloy Steel Bolting Material for Special Applications (ASME SA-540 with additional requirements) High-Strength, High-Temperature Bolting Materials (ASME SA-453 with additional requirements) Martensitic Stainless Steel (Type 403) Bars (ASTM A 276 with additional requirements) Alloy Steel Bars and Shapes (ASME SA-479 with additional requirements) Nickel-Chromium-Iron Alloy Rod and Bar (ASME SB-166 with additional requirements) Precipitation-Hardening Stainless Steel Bars, Shapes, and Forgings (ASME SA-564 with additional requirements) Cobalt-Chromium Alloy Bars and Shapes Nickel-Iron-Chromium Alloy Rod and Bar (ASME SB-408 with additional requirements) Nickel-Molybdenum-Chromium Alloy Rod and Bar (ASME SB-336 with additional requirements) Fibreboard Cases and Internal Fitments for Radioactive Material Type 'A' Packaging (Under Revision) Concrete Shielding Bricks Concrete for Shielding (Ordinary Portland Cement and Normal Aggregate) Concrete for Shielding (Barytes) Control of Ferrite Content in Stainless Steel Weld Metal Control of Electroslag Weld Properties Nonmetallic Thermal Insulation for Austenitic Stainless Steel Control Stainless Steel Weld Cladding of Low-Alloy Steel Components Control of the Use of Sensitized Stainless Steel Information for Safety Analysis Reports - Reactor Material (See also R. G. 1.70) Information for Safety Analysis Reports-Metallic Materials for Engineered Safety Features (See also R.G. 1.70)
Pub
8.79
Pub 875 Amm 11.75 Pub
4.75
Pub
9.77
Pub
7.79
Pub 3.69 Amm 10.71 Pub 7.79 Pub
7.79
Pub
7.79
Pub
7.79
Pub
8.79
Pub
8.79
Pub
8.79
Pub
8.79
Pub Pub
4.75 8.79
Pub
476
Iss
73
Iss Iss
64 61
Iss Iss
60 4.78
Iss Iss
1272 2.73
Iss
5.73
Iss Iss
5.73 75
Iss
275
221
18.5 No.
Issuing Body (Country)
R.G. 1.85
USNRC
R.G. 3.37
USNRC
R.G. 7.6
USNRC
R.G. 7.8
USNRC
10 CFR 50 Appendix G USNRC SEW 510 VDEh SEW 515
VDEh
VdTUV 352-67/1
VdTUV
VdTUV 1255
VdTUV
VdTUV 1265
VdTUV
222
Title (Remarks) Materials Code Case Acceptability-ASME Section III Division I (Under Revision) Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (Issued for Comments) Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels Load Combinations for the Structural Analysis of Shipping Casks (Issued for Comments) Fracture Toughness Requirements VergiitungsstahlgufJ fur GuSstucke mit Wanddicken bis 100 mm VergutungsstahlguB fur GuBstucke mit Wanddicken iiber 100 mm Anwendung von 1%-Dehngrenzen nach der Vornorm DIN 17440 (See also DIN 17440/ Grundsatze fur die Begutachtung von Werkstoffen fur uberwachungsbedurftige Anlagen durch die Technische Uberwachung Ausstellen von Abnahmeprufzeugnissen A und C nach DIN 50049 Abschnitt 3.1 fur Werkstoffpriifungen (See also DIN 50049)
Status Iss
5.79
Iss
9 75
Iss
3 78
Iss
5 77
Pub
10 77
Pub
10.77
Pub
3 67
Pub
2.74
Pub
6.74
19.1 No. 19
Issuing Body (Country)
Title (Remarks)
Status
Material Test M e t h o d s
19.1 N o n - d e s t r u c t i v e Testing AD-Merkblatt HP 5/3 AD
SNT-TC-1A Supplement B SNT-TC-1A Supplement D SNT-TC-1A Supplement E ASTM A 275
ASNT
Herstellung und Priifung von Druckbehaltern; Herstellung und Priifung der Verbindungen; Zerstorungsfreie Priifung der SchweifSnahte Herstellung und Priifung von Druckbehaltern; Verfahrenstechnische Mindestanforderung fur die zerstorungsfreien Priifverfahren Boiler and Pressure Vessel Code; Nondestructive Examination (Regular Addenda and Revisions Provided) Ultra Sonic Testing Method Non-Destructive Testing Personnel Qualification and Certification Magnetic Particle Method
ASNT
Liquid Penetrant Testing Method
ASNT
Eddy Current Testing Method
ASTM
ASTM A 388
ASTM
ASTM A 435
ASTM
ASTM A 577
ASTM
ASTM A 578
ASTM
ASTM A 609
ASTM
ASTM A 745
ASTM
ASTM ASTM ASTM ASTM ASTM
E 94 E 109 E 138 E 142 E 164
ASTM ASTM ASTM ASTM ASTM
ASTM E 165 ASTM E 213
ASTM ASTM
ASTM E 309
ASTM
ASTM E 390
ASTM
ASTM E 446
ASTM
AWS B1.0 DIN 25435 Teil 1
AWS DIN
DIN 25435 Teil 2
DIN
Method of Magnetic Particle Testing and Inspection of Heavy Steel Forgings Ultra Sonic Recommended Practice for Examination of Heavy Steel Forgings Method and Specification for Ultra Sonic Testing and Inspection of Steel Plates for Pressure Vessels Specification for Ultrasonic, Shear Wave Inspection of Steel Plates Straight-Beam Ultra Sonic Examination of Plain and Clad Steel Plates for Special Application Standard Specification for Longitudinal Beam, Ultra Sonic Inspection of Carbon and Low Alloy Steel-Castings Practice for Ultrasonic Examination of Austenitic Steel Forgings Recommended Practice for Radiographic Testing Dry Power Magnetic Particle Inspection Wet Magnetic Particle Inspection Controlling Quality of Radiographic Testing Method for Ultra Sonic Contact Inspection of Weldments Liquid Penetrant Inspection Recommended Practice for Ultrasonic Inspection of Metal Pipe and Tubing Recommended Practice for Eddy Current Testing of Steel Tubular Products with Magnetic Saturation Standard Reference Radiographs for Steel Fusion Welds Standard Referance Radiographs for Steel Castings up to 2 Inches in Thickness Guide for the Nondestructive Inspection of Welds Kerntechnische Anlagen; Wiederkehrende Prufungen, Mechanisierte Ultraschallpriifung (Nuclear Facilities; Inservice Inspections, Remote-Controlled Ultrasonic Inspection) Kerntechnische Anlagen; Wiederkehrende Prufungen, Magnetpulverpriifung (Nuclear Facilities; Inservice Inspections, Magnetic Particle Methode)
AD-Merkblatt HP 5/3 Anl.1
AD
B PVC Sec.V
ASME
SNT-TC Supplement C ASNT SNT-TC-1A ASNT
Pub
12 77
Pub
4.75
Iss
74
Pub Pub
71 71
Pub
71
Pub
77
Pub
77
Pub
75
Pub
77
Pub
77
Pub Rev
70 75
Pub
77
Pub Pub Pub Pub Pub
77 76 76 77 74
Pub Pub
75 77
Pub
77
Pub
75
Pub
75
Pub Pub
77 879
Pub
1.79
223
19.1 No.
Issuing Body (Country)
DIN 54112
DIN
DIN 54116 Teil 1
DIN
DIN 54116 Teil 2
DIN
DIN 54119
DIN
DIN 54119
DIN
DIN 54124 Teil 1
DIN
DIN 54131 Teil 1
DIN
DIN 54132
DIN
DIN 54140 Teil 1
DIN
DIN 54150
DIN
DIN 54160
DIN
ISO/R 947
ISO
ISO/R 1106
ISO
RDT F 3-6T
ORNL
R.G. 1.19
USNRC
R.G. 1.66
USNRC
224
Title (Remarks) Zerstorungsfreie Priifung; Filme, Aufnahmefolien, Kassetten fur Aufnahmen mit Rontgen- und Gammastrahlen, Ma Re (Non-destructive testing; films, exposure screens, cassettes for X- and gamma ray radiographs, dimensions) Zerstorungsfreie Priifverfahren: Betrachtung von Durchstrahlungsaufnahmen, Betrachtungsbedingungen (Non-destructive testing; film viewing, viewing conditions) Zerstorungsfreie Priifverfahren; Betrachtung von Durchstrahlungsaufnahmen, Betrachtungsgerate (Non-destructive testing; viewing films, film viewing boxes) Zerstorungsfreie Priifung; Ultraschallprufung, Begriffe (Non-destructive testing; ultrasonic testing, definitions) Zerstorungsfreie Priifung; Ultraschallprufung, Begriffe (Non-destructive testing; ultrasonic testing; definitions) Zerstorungsfreie Priifung; Kontrolle von Priifeinrichtungen mit Ultraschall-lmpuls-Echo-Geraten, Kontrolle am Priifort (Non-destructive testing; control of test equipment with ultrasonic echo instruments, control at the test place) Zerstorungsfreie Priifung; Magnetisierungsgerate fur die Magnetpulverpriifung, Transportable Gerate auSer Handgerate, stationare Gerate (Non-destructive testing; magnetizing equipment for magnetic particle inspection, stationary and transportable equipment except transportable magnetic yoke) Zerstorungsfreie Priifung; Bestimmung der Eigenschaften von Prufmittel fur die Magnetpulverpriifung (Non-destructive testing; determination of properties of the means of testing for the magnetic-particle-method) Zerstorungsfreie Priifung; Induktive Verfahren (Wirbelstromverfahren), Allgemeines (Non-destructive testing; electromagnetic methods (eddy current methods), generalities) Zerstorungsfreie Priifung; Abdruckverfahren fur die Oberflachenpriifung (Replica-Technik) (Non-destructive testing; impression methods for surface examination (replica-technique)) Zerstorungsfreie Priifung; Anforderungen an Priifpersonal (Non-destructive Testing; Requirements for Testing Personel) (Withdrawn) Recommended Practice for Radiographic Inspection of Circumferential Fusion Welded Butt Joints for Steel Pipes up to 50 mm (2 in) Wall Thickness Recommended Practice for Radiographic Inspection of Fusion Welded Butt Joints for Steel Plates up to 50 mm (2 in) Thick Nondestructive Examination (Supplement to ASME Boiler and Pressure Vessel Code, Section V) Non destructive Examination of Primary Containment Liner Welds (Safety Guide 19) Non-destructive Examination of Tubular Products (Withdrawn 10.77)
Status Pub
8 77
Pub
10.73
Pub
12.76
Drf
1.80
Pub
1.64
Drf
3.79
Pub
7.75
Drf
7.78
Pub
4.76
Pub
8.77
Drf
4.78
Pub
69
Pub
69
Pub
3.79
Iss
8.72
19.1 No.
Issuing Body (Country)
R.G 3 27
USNRC
R.G. 3.36
USNRC
SEP 1915
VDEh
SEP 1918
VDEh
SEP 1919
VDEh
SEP 1922
VDEh
VdTUV Wei 10
VdTUV
VdTUV Wei 31
VdTUV
VdTUV 364
VdTUV
Title (Remarks) Non-destructive Examination of Welds in the Liners of Concrete Barries in Fuel Reprocessing Plants Non-desltuutive Examination of Tubular Products for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants (Withdrawn 2 69) Ultraschallpriifung auf Langsfehler von Rohren aus warmfesten Stahlen Ultraschallpriifung auf Querfehler von Rohren aus warmfesten Stahlen Ultraschallpriifung auf Doppelungen von Rohren aus warmfesten Stahlen Ultraschallpriifung von Gußstücken aus ferritischem Stahl Prüfumfang für Hebezeuge in kerntechnischen Anlagen - Wiederkehrende Priifungen Behandlung von Gefiigeanzeigen bei der Magnetpulverpriifung in Schweißgut und Warmeeinflußzonen von Reaktorsicherheitsbehaltern und Komponenten der äußeren Systeme (in press) Zerstorungsfreie Wiederholungspriifung von Druckbehaltern aus Stahl fur zyanhaltige Gase
Status Iss
5.77
Pub
6.77
Pub
7.77
Pub
7.77
Pub
6 77
Iss
5.77
Pub
1.73
225
19.2 No. 19
Issuing Body (Country)
Status
Material Test M e t h o d s
19.2 Other Test M e t h o d s ASTM ASTM C 558 /ANSI K90.1 ASTM ASTM C 625 /ANSI K90 8 ASTM ASTM C 626 /ANSI K90.10 ASTM ASTM C 781 /ANSI N590 ASTM ASTM C 816 ASTM ASTM C817 ASTM C818
ASTM
ASTM C 886
ASTM
ASTM E 521
ASTM
ASTM E 525
ASTM
ASTM E 531
ASTM
ASTM F 112 BS 4247 Part I
ASTM BSI
DIN 25415 Teil 1
DIN
DIN 25415 Teil 2
DIN
DIN 25435 Teil 3
DIN
DIN 25435 Teil 4
DIN
DIN 53750
DIN
DIN 53750
DIN
DIN 53781
DIN
ISO 2855
ISO
JIS Z4501 JIS Z4504
JIS JIS
226
Title (Remarks)
Measurement of Latice Spacing of Nuclear Graphite Pulse Reporting Irradiation Results on Graphite (Under Revision) Estimating the Thermal Neutron Absorption cross Section of Nuclear Graphite Recommended Practice for Testing Graphite and Boronated Graphite for HTGR's Method of Test for Total Boron in Graphite Spectrochemical Analysis of Nuclear Graphite by the Powder DC. Arc Technique Method of Test for Boron Oxide in Boronated Graphite Scleroscope Hardness Testing of Fine-Grained Carbon and Graphite Materials Recommended Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation Practice for Reporting Dosimetry Results on Nuclear Graphite Surveillance Testing of High Temperature Nuclear Component Materials, Recommended Practice Method of Test for Sealability of Enveloped Gaskets Method of Test for the Measurement and Evaluation of the Decontamination Factor Dekontamination von radioaktiv kontaminierten Oberflachen; Verfahren zur Prufung und Bewertung der Dekontaminierbarkeit (Decontamination of Radioactive Contaminated Surfaces; Method of Test for Ease of Decontamination and Interpretation of Results) (For trial use and comments; Available also in English) Dekontamination von radioaktiv kontaminierten Oberflachen; Bestimmung der Oberflachenkontamination (Decontamination of Radioactive Contaminated Surfaces; Determination of Surface Contamination) (Available also in English) Kerntechnische Anlagen; Wiederkehrende Priifungen, Druckpriifung (Nuclear Facilities; Inservice Inspections, Pressure Test) Kerntechnische Anlagen; Wiederkehrende Priifungen, Sichtpriifung (Nuclear Installations; Inservice Inspections, Visual Inspection) Werkstoffprufung; Verfahren zur Bestrahlung mit energiereichen Strahlen (Testing of materials; methods for exposure to high energy radiation) Werkstoffprufung; Verfahren zur Bestrahlung mit energiereichen Strahlen (Testing of materials; methods for exposure to high energy radiation) Prufung von Beschichtungsstoffen; Verfahren zur Prufung der Bestandigkeit von Beschichtungen gegen ionisierende Strahlung in kerntechnischen Anlagen Radioactive Materials - Packagings - Test for Contents Leakage and Radiation Leakage Testing Method of Lead Equivalent for X Ray Smear Testing Methods for Radioactive Surface Contamination (Available also in English)
Pub Rev Pub
69 75 72
Pub Rev Pub
71 77 77
Pub Drf
77 11.77
Drf
11.77
Pub
78
Pub
77
Pub
74
Pub
76
Pub Pub Rev Pub
74 67 679 10.80
Pub
4.77
Pub
2.80
Pub
8.79
Pub
7.70
Pub
7.70
Pub
480
Pub
76
Pub Pub
75 75
19.2 No.
Issuing Body (Country)
JIS Z4507
JIS
JIS Z4508
JIS
RDT F 3-40T
ORNL
RDT F 11-2T
ORNL
RDT M 12-1T
ORNL
R G. 7.4
USNRC
Title (Remarks) Testing and Calculating Methods of Contamination and Decontamination Index of Radioactive Surface Contamination Testing Method of Scattering-Ratio of Low-Backscattering Materials Methods for the Analysis of Sodium and Cover Gas Analytical Chemistry Methods for Boron Carbide Absorber Material Test Requirements for Thermal Insulating Materials for Use on Austenitic Stainless Steel Leakage Tests on Packages for Shipment of Radioactive Materials (Issued for Comments)
Status Pub Pub
75 74
Pub 1.76 Amm 11.78 Pub 7 77 Pub
10 72
Iss
6 75
227
19.3 No.
Issuing Body /Country)
Title
Status
(Remarks)
19 Material Test Methods 19.3 Metal Test Methods ASTM A 275
ASTM
ASTM A 370 ASTM A 388
ASTM ASTM
ASTM A 577
ASTM
ASTM A 578
ASTM
ASTM A 609
ASTM
ASTM A 745
ASTM
ASTM E 8 ASTM E 21
ASTM ASTM
ASTM E 23 ASTM E 184
ASTM ASTM
ASTM E 208
ASTM
ASTM E 213
ASTM
ASTM E 390
ASTM
ASTM E 399
ASTM
ASTM E 436 ASTM E 446
ASTM ASTM
ASTM G 28
ASTM
TRD 202 DIN 50120 Teil 1
DDA DIN
DIN 50120 Teil 2
DIN
DIN 50121 Teil 1
DIN
DIN 50121 Teil 2
DIN
DIN 50121 Teil 3
DIN
228
Method of Magnetic Particle Testing and Inspection of Heavy Steel Forgings Mechanical Testing of Steel Products Ultra Sonic Recommended Practice for Examination of Heavy Steel Forgings Specification for Ultrasonic, Shear Wave Inspection of Steel Plates Straight-Beam Ultra Sonic Examination of Plain and Clad Steel Plates for Special Application Standard Specification for Longitudinal Beam, Ultra Sonic Inspection of Carbon and Low Alloy Steel-Castings Practice for Ultrasonic Examination of Austenitic Steel Forgings Tension Testing of Metallic Materials Elevatec Temperature Tension Tests of Metallic Materials Notched Bar Impact Testing of Metallic Materials Effects of High-Energy Radiation on the Mechanical Properties of Metallic Materials Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels Recommended Practice for Ultrasonic Inspection of Metal Pipe and Tubing Standard Reference Radiographs for Steel Fusion Welds Tentative Method of Test for Plain Strain Fracture Toughness of Metallic Materials Drop-Weight Tear Tests of Ferritic Steels Standard Referance Radiographs for Steel Castings up to 2 Inches in Thickness Test for Detecting Susceptibility to Intergranular Attack in Wrought Nickel-Rich, Chromium Bearing Alloys Prufung von Fertigteilen aus Stahlblech Prufung von Stahl; Zugversuch an SchweiSverbindungen, SchmelzgeschweiSte Stumpfnahte (Testing of steel; tensile test on fusion welded butt joints) Prufung von Stahl; Zugversuch an SchweiSverbindungen, PreSgeschweiBte Stumpfnahte (Testing of steel; tensile test on welded joints, pressure welded butt joints) Prufung metallischer Werkstoffe; Technologischer Biegeversuch an SchweiSverbindungen und SchweiSplattierungen, SchmelzschweiSverbindungen (Testing of metallic materials; technological bend test on welded joints, fusion welded joints) Prufung metallischer Werkstoffe; Technologischer Biegeversuch an SchweiSverbindungen und SchweiSplattierungen, PreSschweifJverbindungen (Testing of metallic materials; technological bend test on welded joints; pressure welded joints) Prufung metallischer Werkstoffe; Technologischer Biegeversuch an SchweiSverbindungen und SchweiBplattierungen, SchmelzschweiSplattierungen (Testing of metallic materials; technological bend test on welded platings)
Pub
77
Pub Pub
75 77
Pub
77
Pub
77
Pub Rev
70 75
Pub
77
Pub Pub
69 70
Pub Pub
72 62
Pub
69
Pub
77
Pub
75
Pub
78
Pub Pub
74 75
Pub
72
Pub Pub
2.71 9.75
Pub
8.78
Pub
1.78
Pub
1.78
Pub
1.78
19.3 No.
Issuing Body (Country)
DIN 50123
DIN
DIN 50124
DIN
DIN 53750
DIN
ISO 82 ISO 83 ISO 89 ISO 136 ISO 144 ISO/R 79 ISO/R 80
ISO ISO ISO ISO ISO ISO ISO
ISO/R ISO/R ISO/R ISO/R
81 84 85 86
ISO ISO ISO ISO
ISO/R 87
ISO
ISO/R 88
ISO
ISO/R ISO/R ISO/R ISO/R ISO/R ISO/R ISO/R
145 148 165 166 167 202 203
ISO ISO ISO ISO ISO ISO ISO
ISO/R 204
ISO
ISO/R 206
ISO
ISO/R 374 ISO/R 375 ISO/R 637
ISO ISO ISO
ISO/R 642
ISO
ISO/R 643
ISO
ISO/R 783
ISO
ISO/R 1014
ISO
ISO/R 1099 ISO/R 1143 RDT F 11 3T
ISO ISO ORNL
SEP 1325
VDEh
Title
Status
(Remarks)
Priifung von Nichteisenmetallen; Zugversuch an SchweiSverbindungen, SchmelzgeschweilMe Stumpfnahte (Testing of non-ferrous metals; tensile test on fusion welded butt joints) Priifung metallischer Werkstoffe; Scherzugversuch an Widerstandspunkt-, Widerstandsbuckel- und Schmelzpunktschweillverbindungen (Testing of metallic materials; shear tension test on spot joints, projection joints by resistance and fusion welding) Werkstoffpriifung; Verfahren zur Bestrahlung mit energiereichen Strahlen (Testing of materials; methods for exposure to high energy radiation! Tensile Testing of Steel Charpy Impact Test (U-Notch) for Steel Tensile Testing of Steel Wire Simple Torsion Testing of Steel Wire Reverse Band Testing of Steel Wire Brinell Hardness Test for Steel Rockwell Hardness Test (B and C Scales) for Steel. 2nd Edition Vickers Hardness Test for Steel (Load 5 to 1 kgf) Izod Impact Test for Steel Bend Test for Steel Tensile Testing of Steel Sheet and Strip less than 3 mm and not less than 0,5 mm thick Simple Bend Testing of Steel Sheet and Strip less than 3 mm thick Reserve Bend Testing of Steel Sheet and Strip less than 3 mm thick Wrapping Test of Steel Wire Beam Impact Test (V-Notch) for Steel Flanging Test on Steel Tubes Drift Expanding Test on Steel Tubes Bend Test on Steel Tubes Flattering Test on Steel Tubes Interrupted Creep Testing of Steel at Elevated Temperatures (Load and Temperature Interrupted) Non-Interrupted Creep Testing of Steel at Elevated Temperatures Creep Stress Rupture Testing of Steel at Elecated Temperatures Ring Expanding Test on Steel Tubes Tensile Testing of Steel Tubes Methods of Test for Determining the Mechanical Properties of Weld Metal Deposited by Filler Rods for Gas Welding Mild Steels and Low Alloy High Tensile Steels Hardenability Test by End Quenching Steel (Jominy Test) Micrographic Determination of the Austenitic Grain Size of Steel Mechanical Testing of Steel at Elevated Temperatures - Determination of Lower Yiel Stress and Proof Stress and Proving Test Rockwell Superficial Hardness Test (N and Scales) for Steel Axial Coad Fatigue Test Rotating Bar Bending Fatigue Testing Analytical Chemistry Methods for Metallic Core Components Ermiitlung der Sprodbruch-Ubergangstemperatur (NDT) im Fallgewichtversuch nach Pellini
Pub
4.77
Pub
477
Pub
7.70
Pub Pub Pub Pub Pub Pub Pub
74 76 74 72 73 68 68
Pub Pub Pub Pub
67 59 59 74
Pub
59
Pub
59
Pub Pub Pub Pub Pub Pub Pub
60 60 60 60 60 61 61
Pub
61
Pub
61
Pub Pub Pub
64 74 75
Pub
67
Pub
67
Pub
68
Pub
75
Pub Pub Pub Amm Drf
75 75 9 75 4 77 78
229
19.3 No.
Issuing Body (Country)
SEP 1570
VDEh
SEP 1805
VDEh
SEP 1922
VDEh
VdTUV 1060 VdTUV 1256
VdTUV VdTUV
VdTUV 1257
VdTUV
VdTUV 1258
VdTUV
VdTUV 1259 VdTUV 1260
VdTUV VdTUV
VdTUV 1261
VdTUV
VdTUV 1262
VdTUV
VdTUV 1263
VdTUV
VdTUV 1264
VdTUV
VdTUV 1266
VdTUV
230
Title
Status
(Remarks)
Mikroskopische Prufung von Stahlen auf nichtmetallische Einschlusse mit Bildreihen Probenahme und Probenvorbereitung fur die Stiickanalyse bei Stahlen Ultraschallpriifung von GuBstiicken aus ferritischem Stahl Richtlinien fur die Durchfuhrung des Stresstests Priifplan fur die Begutachtung von Walz- und Schmiedestahlen einschlieBlich der Feinkornbaustahle mit feritisch-perlitischem Gefuge (normalgegluht), Zwischenstufengefiige und/oder Vergiitungsgefuge (luft- oder fliissigkeitsvergiitet) Priifplan fur die Begutachtung von nichtrostenden. umwandlungsfreien Chromstahlen (Walz- und Schmiedestahle) Priifplan fur die Begutachtung von austenitischen Walz- und Schmiedestahlen Priifplan fur die Begutachtung von StahlguE Priifplan fur die Begutachtung von GuBeisen-Werkstoffen mit Kugelgraphit und von austenitischen GuBeisen-Werkstoffen mit Lamellengraphit oder Kugelgraphit Priifplan fur die Begutachtung von GuBeisen-Werkstoffen mit Lamellengraphit Priifplan fur die Begutachtung von Aluminium, Kupfer, Nickel und deren Legierungen (geknetet, gepreSt, gewalzt oder geschmiedet) Vereinbarung zur Begutachtung von Erzeugnissen (Band, Blech, Breitflachstahl), die mit geregelter Temperaturfuhrung beim und nach dem Walzen hergestellt werden, zum Nachweis der Gleichwertigkeit mit dem Normalgluhen Priifplan fur die Begutachtung von plattierten Stahlen (Walz- und Sprengplattieren) Priifplan von abbrennstumpfgeschweiBten Flanschen und Ringen
Pub
871
Pub
3.76
Pub
6.77
Pub Pub
877 2.74
Pub
2.74
Pub
2.74
Pub Pub
2.74 2.74
Pub
2.74
Pub
2.74
Pub
3.76
Pub
6 76
Pub
5.78
ISBN 3-410-58002-6
