ANSI ASME RA-SB-2013 Addenda to Standard for Level 1 Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications.pdf

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1、ASME/ANS RA-Sb2013Addenda toASME/ANS RA-S2008Standard forLevel 1/Large EarlyRelease FrequencyProbabilistic RiskAssessment forNuclear Power PlantApplicationsAN AMERICAN NATIONAL STANDARDA01532Date of Issuance: September 30, 2013ASME is the registered trademark of The American Society of Mechanical En

2、gineers.This code or standard was developed under procedures accredited as meeting the criteria for American NationalStandards. The Standards Committee that approved the code or standard was balanced to assure that individuals fromcompetent and concerned interests have had an opportunity to particip

3、ate. 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, and the public-at-large.ASME does not “approve,” “rate,” or “endorse” any item, construction, proprietary device, o

4、r 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 insure anyone utilizing a standard against liability forinfringement of any applicable letters patent, nor assumes a

5、ny 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, isentirely their own responsibility.Participation by federal agency representative(s) or person(s) affiliated with industry i

6、s 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 with the establishedASME procedures and policies, which precludes the issuance of interpretations by individuals.No p

7、art 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 Mechanical EngineersTwo Park Avenue, New York, NY 10016-5990Copyright 2013 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll

8、 rights reservedPrinted in U.S.A.ASME/ANS RA-Sb2013Following approval by the ASME/ANS RA-S Committee and ASME, and after public review,ASME/ANS RA-Sb2013 was approved by the American National Standards Institute onJuly 1, 2013.Addenda to the 2008 edition of ASME/ANS RA-S are issued in the form of re

9、placement pages.Revisions,additions,anddeletionsareincorporateddirectlyintotheaffectedpages.Itisadvisable,however, thatthis page, theAddenda title andcopyright pages, andall replaced pagesbe retainedfor reference.SUMMARY OF CHANGESThis is the second Addenda to be published to ASME/ANS RA-S2008. This

10、 Standard has beenrevised in its entirety.Replace or insert the pages listed. Changes given below are identified on the pages by a margindesignator, (b), placed next to the affected area.Page Location Changeiii, iii.1 Contents Updated to reflect Addendaiv Foreword Revisedv Preparation on Technical A

11、SME address updatedInquiries to theCommittee on NuclearRisk Managementvivii.1 Roster Updatedviii Preface Deleted1 Part 1 (1) Sections 1-1, 1-2, 1-6, and 1-7, andNonmandatory Appendix 1-A revised(2) Paragraph 1-4.2 corrected by errata(3) Last two paragraphs of paras. 1-1.3.3and 1-3.6.2 inserted by er

12、rata45 Part 2 Section 2-1 title, Sections 2-2 and 2-4, andpara. 2-3.2 revised123 Part 3 Revised in its entirety143 Part 4 Sections 4-1, 4-2, and 4-4, and paras. 4-3.2and 4-3.3 revised228 Part 5 Revised in its entirety273 Part 6 Revised in its entirety287 Part 7 Part 7 title, Section 7-1 title, and S

13、ections7-2 and 7-3 revised301 Part 8 Section 8-1 title and Sections 8-2 and 8-3revised316 Part 9 Revised in its entirety330 Part 10 Paragraph 10-1.3 and Sections 10-2, 10-3,and 10-4 revisedSPECIAL NOTE:The Interpretations to ASME/ANS RA-S, Volume 3, are included in this addenda beginning withpage I-

14、7 for the users convenience.(c)INTENTIONALLY LEFT BLANK(d)CONTENTSForeword ivPreparation of Technical Inquires to the Committee on Nuclear Risk Management . vCommittee Roster . viPreface viiiPART 1 GENERAL REQUIREMENTS FOR A LEVEL 1 PRA, INCLUDING LARGE EARLYRELEASE FREQUENCY 1Section 1-1 Introducti

15、on . 1Section 1-2 Acronyms and Definitions . 9Section 1-3 Risk Assessment Application Process . 21Section 1-4 Risk Assessment Technical Requirements . 27Section 1-5 PRA Configuration Control 29Section 1-6 Peer Review . 30Section 1-7 References . 33Nonmandatory Appendix1-A PRA Maintenance, PRA Upgrad

16、e, and the Advisability of PeerReview . 35PART 2 REQUIREMENTS FOR INTERNAL-EVENTS AT-POWER PRA 45Section 2-1 Overview of Internal-Events At-Power PRA Requirements 45Section 2-2 Internal-Events PRA Technical Elements and Requirements . 46Section 2-3 Peer Review for Internal Events At-Power 119Section

17、 2-4 References . 121PART 3 REQUIREMENTS FOR INTERNAL FLOOD AT-POWER PRA . 123Section 3-1 Overview of Internal Flood At-Power PRA Requirements . 123Section 3-2 Internal Flood PRA Technical Elements and Requirements 124Section 3-3 Peer Review for Internal Flood At-Power PRA 141Section 3-4 References

18、. 142PART 4 REQUIREMENTS FOR INTERNAL FIRES AT-POWER PRA 143Section 4-1 Risk Assessment Technical Requirements for Internal Fires At-Power 143Section 4-2 Fire PRA Technical Elements and Requirements 146Section 4-3 Peer Review for the Internal Fire Analysis 208Section 4-4 References . 211Nonmandatory

19、 Appendix4-A Fire PRA Methodology 212PART 5 REQUIREMENTS FOR SEISMIC EVENTS AT-POWER PRA . 228Section 5-1 Overview of Seismic-PRA Requirements At-Power 228Section 5-2 Technical Requirements for Seismic PRA At-Power . 230Section 5-3 Peer Review for Seismic Events PRA At-Power . 265Section 5-4 Referen

20、ces . 266Nonmandatory Appendix5-A Seismic Probabilistic Risk Assessment Methodology: Primer 268PART 6 REQUIREMENTS FOR SCREENING AND CONSERVATIVE ANALYSIS OFOTHER HAZARDS AT-POWER . 273Section 6-1 Approach for Screening and Conservative Analysis . 273Section 6-2 Technical Requirements for Screening

21、and Conservative Analysis . 274iiiSection 6-3 Peer Review for Screening and Conservative Analysis 280Section 6-4 References . 281Nonmandatory Appendix6-A List of Hazards Requiring Consideration . 282PART 7 REQUIREMENTS FOR HIGH-WIND EVENTS AT-POWER PRA. 287Section 7-1 Overview of High-Wind At-Power

22、PRA Requirements 287Section 7-2 Technical Requirements for High-Wind Events At-Power PRA . 288Section 7-3 Peer Review for High-Wind At-Power PRA . 299Section 7-4 References . 300PART 8 REQUIREMENTS FOR EXTERNAL FLOOD EVENTS AT-POWER PRA . 301Section 8-1 Overview of External Flood At-Power PRA Requir

23、ements . 301Section 8-2 Technical Requirements for External Flood Events At-Power PRA . 302Section 8-3 Peer Review for External Flood At-Power PRA . 314Section 8-4 References . 315PART 9 REQUIREMENTS FOR OTHER HAZARDS AT-POWER PRA . 316Section 9-1 Overview of Requirements for Other Hazards At-Power

24、PRA . 316Section 9-2 Technical Requirements for Other Hazards At-Power PRA 318Section 9-3 Peer Review for Other Hazards At-Power PRA . 328Section 9-4 References . 329PART 10 SEISMIC MARGIN ASSESSMENT REQUIREMENTS AT-POWER 330Section 10-1 Overview of Requirements for Seismic Margins At-Power . 330Sec

25、tion 10-2 Technical Requirements for Seismic Margin At-Power . 331Section 10-3 Peer Review for Seismic Margins At-Power . 341Section 10-4 References . 342Nonmandatory Appendices10-A Seismic Margin Assessment Methodology: Primer 34310-B Seismic Margin Assessment Applications Guidance, IncludingSeismi

26、c Margin Assessment With Enhancements . 350iii.1INTENTIONALLY LEFT BLANKiii.2(b) FOREWORDThe ASME Board on Nuclear Codes and Standards (BNCS) and American Nuclear Society(ANS)StandardsBoardmutuallyagreedin2004toformaNuclearRiskManagementCoordinatingCommittee (NRMCC), in which the following additiona

27、l organizations participate: BrookhavenNational Laboratory (BNL), Boiling Water Reactor Owners Group (BWROG), Electric PowerResearch Institute (EPRI), Institute of Electrical and Electronics Engineers (IEEE), National Aero-nautics and Space Administration (NASA), Nuclear Energy Institute (NEI), Pres

28、surized WaterReactorOwners Group(PWROG),U.S. DepartmentofEnergy (DoE),andU.S. NuclearRegulatoryCommission (USNRC). This committee was chartered to coordinate and harmonize standardsactivitiesrelatedto probabilisticriskassessment(PRA) fornuclearpowerplantsand othernuclearinstallations among all inter

29、ested standards development organizations and other interestedparties. Implementing a proposal by NRMCC, ASME and ANS formed a Joint Committee onNuclear Risk Management (JCNRM) to develop and maintain PRA standards. The JCNRM oper-atesunderproceduresaccreditedbytheAmericanNationalStandardsInstitute(

30、ANSI)asmeetingthe criteria of consensus procedures for American National Standards.In 2002, ASME issued an initial PRA standard whose scope was Level 1 and large early releasefrequency(LERF) forinternaleventsat-power forlight-water-reactor(LWR) nuclearpowerplants.In 2003 and 2007, the ANS issued two

31、 other PRA standards, whose scopes were external hazardsand internal fires at-power for LWR nuclear power plants. In 2008, the three standards werecombined into one standard, ASME/ANS RA-S2008, under the joint auspices of ASME andANS. A revision, ASME/ANS RA-Sa2009 Addenda (a), was issued in 2009. T

32、he JCNRM cameinto existence after Addenda (a) was issued. This Addenda, ASME/ANS RA-Sb2013 Addenda(b), is a second revision; it supersedes all previous revisions. JCNRM is responsible for ensuringthatthisStandardismaintainedandrevised,asnecessary.Thisresponsibilityincludesappropriatecoordination wit

33、h and linkage to other standards under development for related risk-informedapplications.Users of this Standard are invited to provide feedback to improve its usefulness for inclusionin the next edition of this Standard, which is currently under development and planned to beissuedin2015.TheJCNRMhold

34、stwoformalmeetingsperyearandusersareinvitedtoparticipate.Additional information about the JCNRM can be found on its Committee Page athttp:/ cstools.asme.org/.ivPREPARATION OF TECHNICAL INQUIRIES TOTHE COMMITTEE ON NUCLEAR RISK MANAGEMENTINTRODUCTIONThe ASME Committee on Nuclear Risk Managementwill c

35、onsider 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 strictly to interpretations of therequirements, or to the consideration of r

36、evisions to therequirements on the basis of new data or technology.Asamatterofpublishedpolicy,ASMEdoesnotapprove,certify, rate, or endorse any item, construction, proprie-tarydevice,oractivity,andaccordingly,inquiriesrequir-ing such consideration will be returned. Moreover,ASME does not act as a con

37、sultant on specific engi-neeringproblemsoronthegeneralapplicationorunder-standing of the Standard requirements. If, based on theinquiry information submitted, it is the opinion of theCommittee that the inquirer should seek assistance, theinquiry will be returned with the recommendation thatsuch assi

38、stance be obtained. All inquiries that do notprovidethe informationneededforthe Committeesfullunderstanding will be returned.INQUIRY FORMATInquiries shall be limited strictly to interpretations ofthe requirements, or to the consideration of revisions tothe present requirements on the basis of new da

39、ta ortechnology.Inquiriesshallbesubmittedinthefollowingformat:(a) Scope. The inquiry shall involve a single require-ment or closely related requirements. An inquiry letterconcerning unrelated subjects will be returned.v(b) Background. State the purpose of the inquiry,which would be either to obtain

40、an interpretation of theStandard requirement or to propose consideration of arevision to the present requirements. Provide conciselythe information needed for the Committees under-standing of the inquiry (with sketches as necessary),being sure to include references to the applicable stan-dard editio

41、n, 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 information, and, where appro-priate, composed in such a way that “yes“ or “no“(perhaps with provisos) would be an a

42、cceptable reply.Thisinquirystatementshouldbetechnicallyandeditori-ally correct.(d) Proposed Reply. State what it is believed that theStandardrequires.If,intheinquirersopinion,arevisionto the Standard is needed, recommended wording shallbe provided.(e) The inquiry shall be submitted in typewrittenfor

43、m; however, legible, handwritten inquiries will beconsidered.(f) Theinquiryshallincludename,telephonenumber,and mailing address of the inquirer.(g) The inquiry shall be submitted to the followingaddress:Secretary, Committee on Nuclear RiskManagementThe American Society of Mechanical EngineersTwo Par

44、k AvenueNew York, NY 10016-5990(b)(b)ASME/ANS RA-S COMMITTEEStandard for Level 1/LERF Probabilistic Risk Assessment forNuclear Power Plant Applications(The following is the roster of the Committee at the time of approval of this Standard.)ASME Standards Committee on Nuclear Risk Management (CNRM)C.

45、R. Grantom, Chair, South Texas Project Nuclear Operating Co.P. F. Nelson, Vice Chair, UNAMO. Martinez, Secretary, The American Society of MechanicalEngineersS. A. Bernsen, IndividualR. E. Bradley, Nuclear Energy InstituteV. K. Anderson, Alternate, Nuclear Energy InstituteR. J. Budnitz, Lawrence Berk

46、eley National LaboratoryJ. R. Chapman, ScientechM. Drouin, U.S. Nuclear Regulatory CommissionK. N. Flemming, KNF Consulting ServicesH. A. Hackerott, OPPD: Nuclear Engineering DivisionD. W. Henneke, General ElectricE. A. Hughes, Etranco, Inc.ANS Risk-Informed Standards Consensus Committee (RISC)R. J.

47、 Budnitz, Chair, Lawrence Berkeley National LaboratoryP. Schroeder, Secretary, American Nuclear SocietyP. J. Amico, Hughes Associates, Inc.B. Najafi, Alternate, SAICR. A. Bari, Brookhaven National LaboratoryR. E. Bradley, Nuclear Energy InstituteA. L. Camp, Los Alamos National LaboratoryM. Drouin, U

48、.S. Nuclear Regulatory CommissionD. J. Finnicum, Westinghouse Electric Co.B. R. Baron, Alternate, Westinghouse Electric Co.D. W. Henneke, General ElectricR. A. Hill, ERIN Engineering and Research, Inc.D. E. True, Alternate, ERIN Engineering and Research, Inc.G. Hughes, Etranco, Inc.K. L. Kiper, Next

49、Era EnergyG. A. Krueger, Exelon Corp.ASME CNRM Subcommittee on Standards Maintenance (SC-SM)K. L. Kiper, Chair, NextEra EnergyS. H. Levinson, Vice Chair, AREVA NP, Inc.I. B. Wall, Vice Chair, ConsultantP. J. Amico, Hughes Associates, Inc.M. Carr, Southern California EdisonD. J. Finnicum, Westinghouse Electric Co.J. Gaertner, Electric Power Research InstituteH. A. Hackerott, OPPD: Nuclear Engineering DivisionD. C. Hance, Electric Power Research InstituteD. G. Harrison, U.S. Nuclear Regulatory CommissionT. G. Hook, Arizona Public ServiceS. Kojima, ConsultantviK. L. Kiper, Ne