RG1.161 反应堆压力容器夏比冲击评估 1995

U.S.NUCLEARREGULATORYCOMMISSIONREGULATORYGIOFFICEOFNUCLEARREGULATORYRESEARCHREGULATORYGUIDE1.161(DraftwasDG-1023)EVALUATIONOFREACTORPRESSUREVESSELSWITHCHARPYUPPER-SHELFENERGYLESSTHAN50FT-LB.USNRCnEGUIATOUGUIDESRegulatoryGuidesareIssuedtodescribeandmakeavailabletotheptuIbiosuchInformationasmethodsacceptabletotheNROstaffforImplementingspecificpartsoftheCommission'sregulations,techniquesusedbythestaffinevaluatingspecificproblemsorpostulatedaccidents,anddataneededbytheNRCstaffInItsreviewofapplicationsforpermitsandlicenses.Regulatoryguidesarenotsubstitutesforregulations,andcompliancewiththemIsnotrequired.MethodsandsolutionsdifferentfromthosesetoutIntheguldeswillbeacceptableIftheyprovideabasisforthefindingsrequIsitetotheIssuanceorcontinuanceofapermitorlicensebytheCommission.ThisguidewasIssuedafterconsiderationofcommentsreceivedfromthepublic.CommentsandsuggestionsforImprovementsintheseguldesareencouragedatalltimes,andguideswii=berevised,asapprprrate,toaccommodatecommentsandtoreflectnewInformationorexperience.June1995UIDEWrittencommentsmaybesubmittedtotheRulesReviewandDirectivesBranch,DFRPS,ADM,U.S.NuclearRegulatoryConrvnsslon,Washington,DC20555-0001.TheguidesareIssuedInthefollowingtenbroaddivisions:1.PowerReactorsS.Products2.ResearchandTestReactors7.Transportation3.FuelsandMaterialsFacilities8.OccupationalHealth4.EnvironmentalandSiting:.AntitrustandFinancialReview5.MaterialsandPlantProtection10.GeneralSinglecopiesofregulatoryguidesmaybeobtainedfreeofchargebywritingtheOfficeofAdministration,Attention:DistributionandServicesSection,U.S.NuclearRegulatoryCommission,Washington,DC206565-0001;orbyfaxat(301)415-2260.IssuedguidesmayalsobepurchasedfromtheNationalTechnicalInformatlonServiceonastandingorderbasis.DetailsonthisservicemaybeobtainedbywritingNTIS,5285PortRoyalRoad,Springfield,VA22161.CONTENTS*A.INTRODUCTION..............................................................................1B.DISCUSSION..................................................................................INOMENCLATURE..............................................................................2C.REGULATORYPOSITION.......................................................................31.ACCEPTANCECRITERIA................................................................31.1LevclAmndBConditions...........................................................31.2LeveCCondition.................................................................31.3LevelDCondition.................................................................42.ANALYSISMETHODS...................................................................42.1LevelAmndBConditions...........................................................42.2LevelCCondition.................................................................72.3LevelDCondition.................................................................83.MATERIALPROPERTIES................................................................83.1WeldsMadeUsingLinde80Flux....................................................93.2GenericReactorPressureVesselWelds...............................................93.3ReactorPressureVesselBase(Plate)Materials.........................................94.TRANSIENTSELECTION...............................................................II4.1Plant-SpecificTransients..........................................................I4.2BoundingTransients..............................................................1D.IMPLEMENTATION...........................................................................11REFERENCES........................................................................................12APPENDIXA:Examples.............................................................................A-1APPENDIXB:ComputationofStressIntensityFactors......................................................B-lREGULATORYANALYSIS............................................................................R-lm.°A.INTRODUCTIONAppendix0.FractureToughnessRequirementsto10CFRPart50,Domestic.LicensingofProductionandUtilizationFacilities,requires,inpart,thatthereactorvesselbetlinematerials..musthaveCharpyupper-shelfnergyofnolessthan75fl-lb(102J)initiallyandmustmaintainuppr-shelfenergythroughoutthelifeofthevesselofnolessthan50ft-lb(68J),unlessitisdemotratedinamannerapprovedbytheDirector,OfficeofNuclearReactorRegulation,thatlowervaluesofupper-shelfenergywillprovidemarginofsafetyagainstfractureequivalenttothoserequiredbyAppe.ndx0oftheASMECode.'Charpyuppcr-shelfenergyisdefinedinASTME185-79(Ref.1)and-82WR2),whichareincorporatedbyreferenceinAppendixKLReactorVesselMaterialSurveillanceProgramRequirementsto10CFRPart50.ThisguidedescribesgeneralproceduresacceptabletotheNRCstafffordemonstratingequivalencetothemarginsofsafetyinAppendix0oftheASMECode(Ref.3).SeveralexamplesusingtheseprocduresarepresentedinAppendixAtothisguideandinmoredetailinNUREG/CR-6023Ref.4).ThisregulatoryguidecontainsinformationcollectionsthataresubjecttothePaperworkReductionActof1980(44U.SC.3501e