ASME RA-S-2008 Standard for Level 1 Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications (Includes Interpretations Volume 1)《核电站设施用1级 大型_1.pdf

1、Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant ApplicationsAN AMERICAN NATIONAL STANDARDASME/ANS RA-S2008(Revision of ASME RA-S2002)ASME/ANS RA-S2008(Revision of ASME RA-S2002)Standard forLevel 1/Large EarlyRelease FrequencyProbabilistic Risk

2、Assessment forNuclear Power PlantApplicationsAN AMERICAN NATIONAL STANDARDThe 2008 edition of this Standard is being issued with an automatic addenda subscription service.The use of addenda allows revisions made in response to public review comments or committeeactions to be published as necessary.

3、The next edition of this Standard is scheduled for publicationin 2010.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. Interpretations are published on the ASME Web site under the Committee Pages athttp:/cstools.asme.org. Interpretations are a

4、lso included with each edition and addenda.ASME is the registered trademark of The American Society of Mechanical Engineers.This code or standard was developed under procedures accredited as meeting the criteria for American NationalStandards. The Standards Committee that approved the code or standa

5、rd was balanced to assure that individuals fromcompetent and concerned interests have had an opportunity to participate. The proposed code or standard was madeavailable for public review and comment that provides an opportunity for additional public input from industry, academia,regulatory agencies,

6、 and the public-at-large.ASME does not “approve,” “rate,” or “endorse” any item, construction, proprietary device, or activity.ASME does not take any position with respect to the validity of any patent rights asserted in connection with anyitems mentioned in this document, and does not undertake to

7、insure anyone utilizing a standard against liability forinfringement of any applicable letters patent, nor assumes any such liability. Users of a code or standard are expresslyadvised that determination of the validity of any such patent rights, and the risk of infringement of such rights, isentirel

8、y their own responsibility.Participation by federal agency representative(s) or person(s) affiliated with industry is not to be interpreted asgovernment or industry endorsement of this code or standard.ASME accepts responsibility for only those interpretations of this document issued in accordance w

9、ith the establishedASME procedures and policies, which precludes the issuance of interpretations by individuals.No part of this document may be reproduced in any form,in an electronic retrieval system or otherwise,without the prior written permission of the publisher.The American Society of Mechanic

10、al EngineersThree Park Avenue, New York, NY 10016-5990Copyright 2008 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reservedPrinted in U.S.A.CONTENTSForeword ivPreparation of Technical Inquires to the Committee on Nuclear Risk Management . vCommittee Roster . viPreface viiiPART 1 LEVEL 1 A

11、ND LERF PROBABILISTIC RISK ASSESSMENT GENERALREQUIREMENTS . 1Section 1-1 Introduction 1Section 1-2 Acronyms and Definitions 7Section 1-3 Risk Assessment Application Process . 20Section 1-4 Risk Assessment Technical Requirements 26Section 1-5 PRA Configuration Control . 28Section 1-6 Peer Review . 29

12、Section 1-7 References . 31Section 1-8 For Further Reading 32Nonmandatory Appendix1-A PRA Maintenance, PRA Upgrade, and the Advisability of Peer Review 33PART 2 INTERNAL EVENTS AT POWER PROBABILISTIC RISK ASSESSMENTREQUIREMENTS . 39Section 2-1 Risk Assessment Technical Requirements for Internal Even

13、ts at Power . 39Section 2-2 Peer Review for Internal Events at Power . 119Section 2-3 References . 121PART 3 FIRES AT POWER PROBABILISTIC RISK ASSESSMENT REQUIREMENTS 122Section 3-1 Risk Assessment Technical Requirements for Fire Events at Power . 122Section 3-2 Peer Review for Fire PRA at Power . 1

14、86Section 3-3 References . 189Nonmandatory Appendix3-A FPRA Methodology 190PART 4 EXTERNAL EVENTS AT POWER PROBABLISTIC RISK ASSESSMENTREQUIREMENTS . 205Section 4-1 Risk Assessment Technical Requirements for External Events at Power . 205Section 4-2 Peer Review for External Events at Power . 273Sect

15、ion 4-3 Documentation Requirements for External Events at Power 275Section 4-4 References . 276Nonmandatory Appendices4-A List of External Events Requiring Consideration . 2804-B Seismic Probabilistic Risk Assessment Methodology: Primer . 2834-C Seismic Margin Assessment Methodology: Primer . 2884-D

16、 Seismic Margin Assessment Applications Guidance, Including SeismicMargin Assessment With Enhancements 295PART 5 LOW POWER AND SHUTDOWN PRAN/ATo be supplied N/AiiiFOREWORDThe ASME Board on Nuclear Codes and Standards (BNCS) and American Nuclear Society(ANS) Standards Board mutually agreed in 2004 to

17、 form a Nuclear Risk Management CoordinatingCommittee (NRMCC). This committee was chartered to coordinate and harmonize Standardsactivities related to probabilistic risk assessment (PRA) between the two Standards developmentorganizations (SDO). A key activity resulting from NRMCC was the development

18、 of PRA Stan-dards structured around the Levels of PRA (i.e., Level 1, Level 2, Level 3) to be jointly issued bythe two societies.The scope of the initial issue of the ASME RA-S standard included Level 1 and Large EarlyRelease Frequency (LERF) for internal events at power. In parallel with the devel

19、opment of ASMERA-S, ANS was developing companion PRA Standards covering external events, internal fire,and low power and shutdown conditions. These Standards are ANSI/ANS-58.212003, ANSI/ANS-58.232007, and ANS-58.22 (in development), respectively. ANS-58.22 will be added onceit is approved as a revi

20、sion or addendum. The three existing Standards are assembled togetheras a revision to ASME RA-S. Consequently, this revision to ASME RA-S is being issued with therevised identity of ASME/ANS RA-S2008.A major objective of the combined Standard is to ensure consistency in format, organization,language

21、, and level of detail of the Standard. In assembling the component Standards the followingcriteria were used:(a) the requirements in the Standards would not be revised or modified(b) no new requirements would be included(c) the numbering scheme of the technical requirements would be preserved(d) the

22、 common requirements across the Standards would be consolidated into a single place(e) the commentary and nonmandatory requirements would be retainedImplementation of the consensus process for this Standard revealed that preserving the exactsame requirements from the component Standards created cert

23、ain technical issues that will needto be addressed in a revision or addendum of ASME/ANS RA-S2008.During the development of the ASME RA-S and the ANS companion, titled PRA Standardsfor Internal Fires, External Events, and Low Power and Shutdown Conditions, concerns wereraised by stakeholder organiza

24、tions and SDOs with respect to stability and consistency in require-ments between the Standards. Thus, a key objective of this Standard is to improve consistencyand foster stability by enabling future changes to be applied across the various PRA scopes thatpreviously existed as separate Standards. I

25、t is anticipated that efficiencies and improvements willresult from maintaining, interpreting, and implementing one PRA Standard as opposed to fourseparate Standards. Additionally, the identification of common processes in general requirementssections for such areas as PRA configuration control, pee

26、r review, maintenance versus upgrade,and use in risk-informed applications can now be provided, which further supports consistencyand stability. Using a single committee responsible for this Standard provides a single point ofresponse to inquiries and places the expertise necessary to address and co

27、ordinate activities ina single cognizant group supported by responsible technical societies. In addition, this Standardis intended to determine the technical adequacy of a PRA such that the PRA can be used indecision making.The Committee on Nuclear Risk Management (CNRM) operates under procedures ac

28、creditedby the American National Standards Institute (ANSI) as meeting the criteria of consensus proce-dures for American National Standards. The initial Standard was approved by the ASME Boardon Nuclear Codes and Standards and subsequently approved by ANSI on April 9, 2008.CNRM is responsible for e

29、nsuring that this Standard is maintained and revised as necessaryfollowing its original publication. This includes appropriate coordination with and linkage toother Standards under development for related risk-informed applications.ivPREPARATION OF TECHNICAL INQUIRIES TOTHE COMMITTEE ON NUCLEAR RISK

30、 MANAGEMENTINTRODUCTIONThe ASME Committee on Nuclear Risk Managementwill consider written requests for interpretations andrevisions to risk management standards and develop-ment of new requirements as dictated by technologicaldevelopment. The Committees activities in this latterregard are limited st

31、rictly to interpretations of therequirements, or to the consideration of revisions to therequirements on the basis of new data or technology.As a matter of published policy, ASME does not approve,certify, rate, or endorse any item, construction, proprie-tary device, or activity, and accordingly, inq

32、uiries requir-ing such consideration will be returned. Moreover,ASME does not act as a consultant on specific engi-neering problems or on the general application or under-standing of the Standard requirements. If, based on theinquiry information submitted, it is the opinion of theCommittee that the

33、inquirer should seek assistance, theinquiry will be returned with the recommendation thatsuch assistance be obtained. All inquiries that do notprovide the information needed for the Committees fullunderstanding will be returned.INQUIRY FORMATInquiries shall be limited strictly to interpretations oft

34、he requirements, or to the consideration of revisions tothe present requirements on the basis of new data ortechnology. Inquiries shall be submitted in the followingformat:(a) Scope. The inquiry shall involve a single require-ment or closely related requirements. An inquiry letterconcerning unrelate

35、d subjects will be returned.v(b) Background. State the purpose of the inquiry,which would be either to obtain an interpretation of theStandard requirement or to propose consideration of arevision to the present requirements. Provide conciselythe information needed for the Committees under-standing o

36、f the inquiry (with sketches as necessary),being sure to include references to the applicable stan-dard edition, addenda, part, appendix, paragraph, fig-ure, or table.(c) Inquiry Structure. The inquiry shall be stated in acondensed and precise question format, omitting super-fluous background inform

37、ation, and, where appro-priate, composed in such a way that “yes“ or “no“(perhaps with provisos) would be an acceptable reply.This inquiry statement should be technically and editori-ally correct.(d) Proposed Reply. State what it is believed that theStandard requires. If, in the inquirers opinion, a

38、 revisionto the Standard is needed, recommended wording shallbe provided.(e) The inquiry shall be submitted in typewrittenform; however, legible, handwritten inquiries will beconsidered.(f) The inquiry shall include name, telephone number,and mailing address of the inquirer.(g) The inquiry shall be

39、submitted to the followingaddress:Secretary, Committee on Nuclear RiskManagementThe American Society of Mechanical EngineersThree Park AvenueNew York, NY 10016-5990ASME/ANS RA-S COMMITTEEStandard for Level 1/LERF Probabilistic Risk Assessment forNuclear Power Plant Applications(The following is the

40、roster of the Committee at the time of approval of this Standard.)ASME Combined Standard Project TeamC. R. Grantom, Chair, South Texas Project Nuclear Operating Co.T. Lazar, The American Society of Mechanical EngineersS. A. Bernsen, IndividualM. Drouin, U.S. Nuclear Regulatory CommissionASME Cross-C

41、utting Issues Project TeamD. E. True, Chair, ERIN Engineering and ResearchT. Lazar, The American Society of Mechanical EngineersR. E. Bradley, Nuclear Energy InstituteK. Canavan, Electric Power Research InstituteJ. R. Chapman, ScientechC. R. Grantom, South Texas Project Nuclear Operating Co.ASME Com

42、mittee on Nuclear Risk ManagementC. R. Grantom, Chair, South Texas Project Nuclear Operating Co.T. A. Meyer, Vice Chair, Westinghouse Electric Co.T. Lazar, The American Society of Mechanical EngineersS. A. Bernsen, IndividualR. E. Bradley, Nuclear Energy InstituteH. D. Brewer, Duke EnergyK. Brook, B

43、ritish EnergyR. J. Budnitz, Lawrence Berkeley National LaboratoryJ. R. Chapman, ScientechM. Drouin, U.S. Nuclear Regulatory CommissionK. N. Flemming, KNF Consulting ServicesH. A. Hackerott, OPPD: Nuclear Engineering DivisionASME Subcommittee on ApplicationsB. D. Sloane, Chair, ERIN Engineering and R

44、esearchI. B. Wall, Vice Chair, Electric Power Research InstituteS. A. Bernsen, IndividualR. E. Bradley, Nuclear Energy InstituteK. Brook, British EnergyM. P. Carr, Southern California Edison, SONGSH. A. Hackerott, OPPD: Nuclear Engineering DivisionR. A. Hill, ERIN Engineering and ResearchASME Subcom

45、mittee on TechnologyH. D. Brewer, Chair, Duke EnergyS. H. Levinson, Vice Chair, AREVA NP, Inc.R. J. Budnitz, Lawrence Berkeley National LaboratoryK. Canavan, Electric Power Research InstituteJ. R. Chapman, ScientechM. Drouin, U.S. Nuclear Regulatory CommissionK. N. Flemming, KNF Consulting ServicesD

46、. W. Henneke, General ElectricS. Kojima, Computer Software Development Co.viD. W. Henneke, General ElectricD. T. McLaughlin, Westinghouse Electric Co.P. F. Nelson, UNAMM. K. Ravindra, IndividualG. A. Krueger, Exelon Corp.S. H. Levinson, AREVA NP, Inc.D. N. Miskiewicz, Progress EnergyG. W. Parry, U.S

47、. Nuclear Regulatory CommissionD. J. Wakefield, ABS ConsultingI. B. Wall, Electric Power Research InstituteS. Kojima, Computer Software Development Co.I. B. Kouzmina, International Atomic Energy AgencyG. A. Krueger, Exelon Corp.S. H. Levinson, AREVA NP, Inc.P. F. Nelson, UNAMR. E. Schneider, Westing

48、house Electric Co.B. D. Sloane, ERIN Engineering and ResearchD. E. True, ERIN Engineering and ResearchR. A. Hill, Alternate, ERIN Engineering and ResearchI. B. Wall, Electric Power Research InstituteG. G. Wilks, Nuclear Electric InsuranceG. L. Zigler, Alion Science and TechnologyE. Kichev, Kozloduy

49、Nuclear Power PlantI. B. Kouzmina, International Atomic Energy AgencyG. A. Krueger, Exelon Corp.D. T. McLaughlin, Westinghouse Electric Co.T. A. Meyer, Westinghouse Electric Co.G. W. Parry, U.S. Nuclear Regulatory CommissionT. A. Wheeler, Sandia National LaboratoriesJ. L. Lachance, Sandia National LaboratoriesD. N. Miskiewicz, Progress EnergyP. F. Nelson, UNAMM. K. Ravindra, IndividualR. E. Schneider, Westinghouse Electric Co.D. W. Stillwell, South Texas Project Nuclear Operating Co.D. E. True, ERIN Engineering and ResearchD. J. Wakefield, ABS ConsultingASME Special Committe