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1、W 9006333 0006571 335 = IAEA 50-SG-O3 79 IAEA SAFETY GUIDES Operational Limits and Conditions for Nuclear Power Plants A Safety Guide INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1979 -,-,- IAEA 50-SG-03 77 7006333 000b572 271 CATEGORIES OF IAEA SAFETY SERIES From 1978 onwards lhe various publication
2、s in the Safely Series are divided into four cutegories, as follows: ( 1 ) IAEA Safety Standards. Publications in this category comprise the Agencys safety standards as defined in “The Agencys Safety Standards and Measures”, approved by the Agencys Board of Governors on 25 February 1976 and set fort
3、h in IAEA document INFCIRC/ 18/Rev. 1. They are issued under the authority of the Board of Governors, and are mandatory for the Agencys own operations and for Agency-assisted operations. Such standards comprise the Agencys basic safety standards, the Agencys specialized regulations and the Agencys c
4、odes of practice. The covers are distinguished by the wide red band on the lower half: (2) IAEA Safety Guides. As stated in IAEA document INFCIRC/18/Rev. 1, referred to above, IAEA Safety Guides supplement IAEA Safety Standards and recommend a procedure or procedures that might be followed in implem
5、enting them. They are issued under the authority of the Director General of the Agency. The covers are distinguished by the wide green band on the lower half (3) Recommendations. Publications in this category, containing general recommendations on safety practices, are issued under the authority of
6、the Director General of the Agency. The covers are distinguished by the wide brown band on the lower half: (4) Procedures and Data. Publications in this category contain information on procedures, techniques and criteria pertaining to safety matters. They are issued under the authority of the Direct
7、or General of the Agency. The covers are distinguished by the wide blue band on the lower half: Note: The covers of publications brought out within the framework of the NUSS (Nuclear Safety standards) Programme are distinguished by the wide yellow band on the upper half: I A E A 50-SG-O3 77 = 700b33
8、L 0006573 LO8 OPERATIONAL LIMITS AND CONDITIONS FOR NUCLEAR POWER PLANTS A Safety Guide The following States are Members of the International Atomic Energy Agency: AFGHANISTAN ALBANIA ALGERIA ARGENTINA AUSTRALIA AUSTRIA BANGLADESH BELGIUM BOLIVIA BRAZIL BULGARIA BURMA BYELORUSSIAN SOVIET SOCIALIST R
9、EPUBLIC CANADA CHILE COLOMBIA COSTA RICA CUBA CYPRUS CZECHOSLOVAKIA DEMOCRATIC KAMPUCHEA DEMOCRATIC PEOPLES REPUBLIC OF KOREA DENMARK DOMINICAN REPUBLIC ECUADOR EGYPT EL SALVADOR ETHI OP1 A FINLAND FRANCE GABON GERMAN DEMOCRATIC REPUBLIC GERMANY, FEDERAL REPUBLIC O F GHANA GREECE GUATEMALA HAITI HOL
10、Y SEE HUNGARY ICELAND INDIA INDONESIA I RAN IRAQ IRELAND ISRAEL ITALY IVORY COAST JAMAICA JAPAN JORDAN KENYA KOREA, REPUBLIC O F KUWAIT LEBANON LIBERIA LIBYAN ARAB JAMAHIRIYA LIECHTENSTEIN LUXEMBOURG MADAGASCAR MALAYSIA MALI MAURITIUS MEXICO MONACO MONGOLIA MOROCCO NETHERLANDS NEW ZEALAND NICARAGUA
11、NIGER NIGERIA NORWAY PAKISTAN PANAMA PARAGUAY PERU PHILIPPINES POLAND PORTUGAL QATAR ROMANIA SAUDI ARABIA SENEGAL SIERRA LEONE SINGAPORE SOUTH AFRICA SPAIN SRI LANKA SUDAN SWEDEN SWITZERLAND SYRIAN ARAB REPUBLIC THAILAND TUNISIA TURKEY UGANDA UKRAINIAN SOVIET SOCIALIST UNION OF SOVIET SOCIALIST UNIT
12、ED ARAB EMIRATES UNITED KINGDOM OF GREAT REPUBLIC REPUBLICS BRITAIN AND NORTHERN IRELAND CAMEROON TANZANIA UNITED REPUBLIC OF UNITED REPUBLIC O F UNITED STATES OF AMERICA URUGUAY VENEZUELA VIET NAM YUGOSLAVIA ZAIRE ZAMBIA The Agencys Statute was approved on 23 October 1956 by the Conference on the S
13、tatute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world“
14、. IAEA, 1979 Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International Atomic Energy Agency, Krntner Ring I I, P.O. Box 590, A-IO1 I Vienna, Austria. Printed hy the IAEA in Austria June 1979 IAEA 50-SG-03 79 m 9006333 0006575 T
15、 B O H SAFETY SERIES NOS O-SG-03 OPERATIONAL LIMITS AND CONDITIONS FOR NUCLEAR POWER PLANTS A Safety Guide INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1979 -,-,- IAEA 50-SG-O3 79 9006333 O006576 917 THIS SAFETY GUIDE IS ALSO PUBLISHED IN FRENCH, RUSSIAN AND SPANISH OPERATIONAL LIMITS AND CONDITIONS F
16、OR NUCLEAR POWER PLANTS: A SAFETY GUIDE IAEA, VIENNA, 1979 STI/PUB/53 1 ISBN 92-0-123479-1 -,-,- I A E A 50-SG-O3 79 900b331 O006577 853 FOREWORD by the Director General The demand for energy is continually growing, both in the developed and the developing countries. Traditional sources of energy su
17、ch as oil and gas will probably be exhausted within a few decades, and present world-wide energy demands are already overstraining present capacity. Of the new sources nuclear energy, with its proven technology, is the most significant single reliable source available for closing the energy gap that
18、 is likely, according to the experts, to be upon us by the turn of the century. During the past 25 years, 19 countries have constructed nuclear power plants. More than 200 power reactors are now in operation, a further 150 are planned, and, in the longer term, nuclear energy is expected to play an i
19、ncreasingly important role in the development of energy programmes throughout the world. Since its inception the nuclear energy industry has maintained a safety record second to none. Recognizing the importance of this aspect of nuclear power and wishing to ensure the continuation of this record, th
20、e International Atomic Energy Agency established a wide-ranging programme to provide the Member States with guidance on the many aspects of safety associated with thermal neutron nuclear power reactors. The programme, at present involving the preparation and publication of about 50 books in the form
21、 of Codes of Practice and Safety Guides, has become known as the NUSS programme (the letters being an acronym for Nuclear Safety Standards). The publications are being produced in the Agencys Safety Series and each one will be made available in separate English, French, Russian and Spanish versions.
22、 They will be revised as necessary in the light of experience to keep their contents up to date. The task envisaged in this programme is a considerable and taxing one, entailing numerous meetings for drafting, reviewing, amending, consolidating and approving the documents. The Agency wishes to thank
23、 all those Member States that have so generously provided experts and material, and those many individuals, named in the published Lists of Participants, who have given their time and efforts to help in implementing the programme. Sincere gratitude is also expressed to the international organization
24、s that have participated in the work. The Codes of Practice and Safety Guides are recommendations issued by the Agency for use by Member States in the context of their own nuclear safety requirements. A Member State wishing to enter into an agreement with the Agency for the Agencys assistance in con
25、nection with the siting, construction, -,-,- IAEA 50-SG-03 79 9006333 000b578 79T m commissioning, operation or decommissioning of a nuclear power plant will be required to follow those parts of the Codes of Practice and Safety Guides that pertain to the activities covered by the agreement. However,
26、 it is recognized that the final decisions and legal responsibilities in any licensing procedures always rest with the Member State. The NUSS publications presuppose a single national framework within which the various parties, such as the regulatory body, the applicant/licensee and the supplier or
27、manufacturer, perform their tasks. Where more than one Member State is involved, however, it is understood that certain modifications to the procedures described may be necessary in accordance with national practice and with the relevant agreements concluded between the States and between the variou
28、s organizations concerned. The Codes and Guides are written in such a form as would enable a Member State, should it so decide, to make the contents of such documents directly applicable to activities under its jurisdiction. Therefore, consistent with accepted practice for codes and guides, and in a
29、ccordance with a proposal of the Senior Advisory Group, “shall” and “should” are used to distinguish for the potential user between a firm requirement and a desirable option. The task of ensuring an adequate and safe supply of energy for coming generations, and thereby contributing to their well-bei
30、ng and standard of life, is a matter of concern to us all. It is hoped that the publication presented here, together with the others being produced under the aegis of the NUSS programme, will be of use in this task. STATEMENT by the Senior Advisory Group The Agencys plans for establishing Codes of P
31、ractice and Safety Guides for nuclear power plants have been set out in IAEA document GC(XVIII)/526/Mod.l. The programme, referred to as the NUSS programme, deals with radiological safety and is at present limited to land-based stationary plants with thermal neutron reactors designed for the product
32、ion of power. The present publication is brought out within this framework. A Senior Advisory Group (SAG), set up by the Director General in September 1974 to implement the programme, selected five topics to be covered by Codes of Practice and drew up a provisional list of subjects for Safety Guides
33、 supporting the five Codes. The SAG was entrusted with the task of supervising, reviewing and advising on the project at all stages and approving draft documents for onward transmission to the Director General. One Technical Review Committee (TRC), composed of experts from Member States, was created
34、 for each of the topics covered by the Codes of Practice. -,-,- IAEA 50-SG-O3 79 m 9006331 0006579 626 = In accordance with the procedure outlined in the above-mentioned IAEA document, the Codes of Practice and Safety Guides, which are based on docu- mentation and experience from various national sy
35、stems and practices, are first drafted by expert worgng groups consisting of two or three experts from Member States together with Agency staff members. They are then reviewed and revised by the appropriate TRC. In this undertaking use is made of both published and unpublished material, such as answ
36、ers to questionnaires, submitted by Member States. The draft documents, as revised by the TRCs, are placed before the SAG. After acceptance by the SAG, English, French, Russian and Spanish versions are sent to Member States for comments. When changes and additions have been made by the TRCs in the l
37、ight of these comments, and after further review by the SAG, the drafts are transmitted to the Director General, who submits them, as and when appropriate, to the Board of Governors for approval before final publication. The five Codes of Practice cover the following topics: Governmental organizatio
38、n for the regulation of nuclear power plants Safety in nuclear power plant siting Design for safety of nuclear power plants Safety in nuclear power plant operation Quality assurance for safety in nuclear power plants. These five Codes establish the objectives and minimum requirements that should be
39、fulfilled to provide adequate safety in the operation of nuclear power plants. The Safety Guides are issued to describe and make available to Member States acceptable methods of implementing specific parts of the relevant Codes of Practice. Methods and solutions varying from those set out in these G
40、uides may be acceptable, if they provide at least comparable assurance that nuclear power plants can be operated without undue risk to the health and safety of the general public and site personnel. Although these Codes of Practice and Safety Guides establish an essential basis for safety, they may
41、not be sufficient or entirely applicable. Other safety documents published by the Agency should be consulted as necessary. In some cases, in response to particular circumstances, additional require- ments may need to be met. Moreover, there will be special aspects which have to be assessed by expert
42、s on a case-bycase basis. Physical security of fissile and radioactive materials and of a nuclear power plant as a whole is mentioned where appropriate but is not treated in detail. Non-radiological aspects of industrial safety and environmental protection are not explicitly considered. -,-,- IAEA 5
43、0-SG-O3 79 9006333 O006580 348 When an appendix is included it is considered to be an integral part of the document and to have the same status as that assigned to the main text of the document. On the other hand annexes, footnotes, lists of participants and bibliographies are only included to provi
44、de information or practical examples that might be help- ful to the user. Lists of additional bibliographical material may in some cases be available at the Agency. A list of relevant definitions appears in each book. These publications are intended for use, as appropriate, by regulatory bodies and
45、others concerned in Member States. To fully comprehend their contents, it is essential that the other relevant Codes of Practice and Safety Guides be taken into account. -,-,- I A E A 50-SG-O3 79 900b331 000b581 284 CONTENTS 1. INTRODUCTION 1 1.1. General 1 1.2. Scope 1 2. CONCEPT OF OPERATIONAL LIM
46、ITS AND CONDITIONS 2 3. CONTENTS OF OPERATIONAL LIMITS AND CONDITIONS . 4 3.1. 3.2. 3.3. 3.4. General 4 Safety limits . 5 3.2.1. General 3.2.2. Fuel and fuel cladding temperatures 3.2.3. Reactor coolant system pressure Safety system settings 6 3.3.1. General 3.3.2. Typical parameters requiring safet
47、y system settings Limits and conditions for normal operation 7 3.4.1. General 3.4.2. Reactor coolant system temperature 3.4.3. Reactor coolant system pressure 3.4.4. Reactor power 3.4.5. Reactor coolant chemical quality 3.4.6. Pressure relief and safety valves 3.4.7. Emergency cooling systems 3.4.8.
48、 Moderator and cover gas system 3.4.9. Steam generators 3.4.1 O. Reactor coolant system leakage 3.4.1 1. Reactor coolant radioactivity 3.4.12. Ultimate heat sink 3.4.13. Negative reactivity requirements 3.4.14. Reactivity coefficients 3.4.15. Reactivity control logic 3.4,16. Positive reactivity insertion rates 3.4. i 7. Reactor core neutron flux monitoring 3.4.18. Reactivity control devices 3.4.19. Reactivity differences 3.4.20. Liquid poison systems 3.4.21. Reactor protection and other safety system instrumentation -,-,- *