RG1.207 考虑到轻水堆环境对金属部件寿命减短效应影响的的疲劳分析评价导则 2007

TheU.S.NuclearRegulatoryCommission(NRC)issuesregulatoryguidestodescribeandmakeavailabletothepublicmethodsthattheNRCstaffconsidersacceptableforuseinimplementingspecificpartsoftheagency’sregulations,techniquesthatthestaffusesinevaluatingspecificproblemsorpostulatedaccidents,anddatathatthestaffneedinreviewingapplicationsforpermitsandlicenses.Regulatoryguidesarenotsubstitutesforregulations,andcompliancewiththemisnotrequired.MethodsandsolutionsthatdifferfromthosesetforthinregulatoryguideswillbedeemedacceptableiftheyprovideabasisforthefindingsrequiredfortheissuanceorcontinuanceofapermitorlicensebytheCommission.Thisguidewasissuedafterconsiderationofcommentsreceivedfromthepublic.TheNRCstaffencouragesandwelcomescommentsandsuggestionsinconnectionwithimprovementstopublishedregulatoryguides,aswellasitemsforinclusioninregulatoryguidesthatarecurrentlybeingdeveloped.TheNRCstaffwillreviseexistingguides,asappropriate,toaccommodatecommentsandtoreflectnewinformationorexperience.WrittencommentsmaybesubmittedtotheRulesandDirectivesBranch,OfficeofAdministration,U.S.NuclearRegulatoryCommission,Washington,DC20555-0001.Regulatoryguidesareissuedin10broaddivisions:1,PowerReactors;2,ResearchandTestReactors;3,FuelsandMaterialsFacilities;4,EnvironmentalandSiting;5,MaterialsandPlantProtection;6,Products;7,Transportation;8,OccupationalHealth;9,AntitrustandFinancialReview;and10,General.Requestsforsinglecopiesofdraftoractiveregulatoryguides(whichmaybereproduced)shouldbemadetotheU.S.NuclearRegulatoryCommission,Washington,DC20555,Attention:ReproductionandDistributionServicesSection,orbyfaxto(301)415-2289;[e-mail]ideandotherrecentlyissuedguidesareavailablethroughtheNRC’spublicWebsiteundertheRegulatoryGuidesdocumentcollectionoftheNRC’sElectronicReadingRoomat’sAgencywideDocumentsAccessandManagementSystem(ADAMS)at(DraftwasissuedasDG-1144,datedJuly2006)GUIDELINESFOREVALUATINGFATIGUEANALYSESINCORPORATINGTHELIFEREDUCTIONOFMETALCOMPONENTSDUETOTHEEFFECTSOFTHELIGHT-WATERREACTORENVIRONMENTFORNEWREACTORSA.INTRODUCTIONInAppendixA,“GeneralDesignCriteriaforNuclearPowerPlants,”toTitle10,Part50,oftheCodeofFederalRegulations(10CFRPart50),“DomesticLicensingofProductionandUtilizationFacilities”(Ref.1),GeneralDesignCriterion(GDC)1,“QualityStandardsandRecords,”requires,inpart,thatstructures,systems,andcomponentsthatareimportanttosafetyshallbedesigned,fabricated,erected,andtestedtoqualitystandardscommensuratewiththeimportanceofthesafetyfunctionperformed.Inaddition,GDC30,“QualityofReactorCoolantPressureBoundary,”requires,inpart,thatcomponentsthatarepartofthereactorcoolantpressureboundaryshallbedesigned,fabricated,erected,andtestedtothehighestpracticalqualitystandards.Augmentingthosedesigncriteria,10CFR50.55a,“CodesandStandards,”endorsestheAmericanSocietyofMechanicalEngineers(ASME)BoilerandPressureVesselCode(Ref.2)fordesignofsafety-relatedsystemsandcomponents.Inparticular,Section50.55a(c),“ReactorCoolantPressureBoundary,”requires,inpart,thatcomponentsofthereactorcoolantpressureboundarymustmeettherequirementsforClass1componentsinSectionIII,“RulesforConstructionofNuclearPowerPlantComponents,”oftheASMECode,exceptasprovidedinthatsection.RG1.207,Page2Specifically,theASMEClass1requirementscontainprovisions,includingfatiguedesigncurves,fordeterminingacomponent’ssuitabilityforcyclicservice.Thesefatiguedesigncurvesarebasedonstrain-controlledtestsperformedonsmallpolishedspecimens,atroomtemperature,inairenvironments.Thus,thesecurvesdonotaddresstheimpactofthereactorcoolantsystemenvironmentonthecomponentsofthereactorcoolantpressureboundary.ThisregulatoryguideprovidesguidanceforuseindeterminingtheacceptablefatiguelifeofASMEpressureboundarycomponents,withconsiderationofthelight-waterreactor(LWR)environment.Insodoing,thisguidedescribesamethodthatthestaffoftheU.S.NuclearRegulatoryCommission(NRC)considersacceptabletosupportreviewsofapplicationsthattheagencyexpectstoreceivefornewnuclearreactorconstructionpermitsoroperatinglicensesunder10CFRPart50;designcertificationsunder10CFRPart52,“EarlySitePermits;StandardDesignCertifications;andCombinedLicensesforNuclearPowerPlants”(Ref.3);andcombinedlicensesunder10CFRPart52thatdonotreferenceastandarddesign.Becauseofsignificantconservatisminquantifyingotherplant-relatedvariables(suchascyclicbehavior,includingstressandloadingrates)involvedincumulativefatiguelifecalculations,thedesignofthecurrentfleetofreactorsissatisfactory.Thisregulatoryguidecontainsinformationcollectionsthatarecoveredbytherequirementsof10CFRParts50and52,whichtheOfficeofManagementandBudget(OMB)approvedunderOMBcontrolnumbers3150-0011and3150-0151,respectively.TheNRCmayneitherconductnorsponsor,andapersonisnotrequiredtorespondto,aninformationcollectionrequestorrequirementunlesstherequestingdocumentdispl