RG1.085 ASME第III卷第1部分材料规范案例可接受性 2005

Revision31May1999RegulatoryGuide1.85MaterialsCodeCaseAcceptabilityASMESectionIII,Division1(DraftwasissuedasDG-1049)[DivisionIndex|RegulatoryGuideIndex|NRCHomePage]PublicationInformationTableofContentsoA.INTRODUCTIONoB.DISCUSSIONoC.REGULATORYPOSITION1.ACCEPTABLECODECASESa.Materials-OrientedCodeCases(CodeCaseNumber,DateofASMEApproval,3andtitle)(1)CodeCasesInvolvingPlate(2)CodeCasesInvolvingPipeandTubes(3)CodeCasesInvolvingBarsandForgings(4)CodeCasesInvolvingGeneralUsageb.Testing-orientedCodeCases(1)CodeCaseInvolvingPlates(2)CodeCaseInvolvingBarsandForgings(3)CodeCaseInvolvingPipeandTubes(4)CodeCaseInvolvingGeneralUsage2.ANNULLEDCODECASES3.REVISEDCODECASES4.UNACCEPTABLECODECASESoD.IMPLEMENTATIONoAPPENDIX:NUMERICALLISTINGOFCODECASESoVALUE/IMPACTSTATEMENTA.INTRODUCTIONSection50.55a,CodesandStandards,of10CFRPart50,DomesticLicensingofProductionandUtilizationFacilities,requires,inpart,thatcomponentsofthereactorcoolantpressureboundarybedesigned,fabricated,erected,andtestedinaccordancewiththerequirementsforClass1componentsofSectionIII,NuclearPowerPlantComponents,1(1)oftheAmericanSocietyofMechanicalEngineers(ASME)BoilerandPressureVesselCodeorequivalentqualitystandards.Footnote6to10CFR50.55astatesthattheuseofspecificCodeCasesmaybeauthorizedbytheCommissionuponrequestpursuantto10CFR50.55a(a)(3),whichrequiresthatproposedalternativestothedescribedrequirementsorportionsthereofprovideanacceptablelevelofqualityandsafety.GeneralDesignCriterion1,QualityStandardsandRecords,ofAppendixA,GeneralDesignCriteriaforNuclearPowerPlants,to10CFRPart50requires,inpart,thatstructures,systems,andcomponentsimportanttosafetybedesigned,fabricated,erected,andtestedtoqualitystandardscommensuratewiththeimportanceofthesafetyfunctiontobeperformed.Wheregenerallyrecognizedcodesandstandardsareused,Criterion1requiresthattheybeidentifiedandevaluatedtodeterminetheirapplicability,adequacy,andsufficiencyandbesupplementedormodifiedasnecessarytoensureaqualityproductinkeepingwiththerequiredsafetyfunction.Criterion30,QualityofReactorCoolantPressureBoundary,ofthesameappendixrequires,inpart,thatcomponentsthatarepartofthereactorcoolantpressureboundarybedesigned,fabricated,erected,andtestedtothehighestqualitystandardspractical.AppendixB,QualityAssuranceCriteriaforNuclearPowerPlantsandFuelReprocessingPlants,to10CFRPart50requires,inpart,thatmeasuresbeestablishedforthecontrolofspecialprocessingofmaterialsandthatpropertestingbeperformed.ThisregulatoryguideliststhoseSectionIIIASMECodeCasesorientedtomaterialsandtestingthataregenerallyacceptabletotheNRCstaffforimplementationinthelicensingoflight-water-coolednuclearpowerplants.ThisguideisbeingrevisedtoupdatetheNRCstaffpositionsonnewCodeCases,revisedCodeCases,andannulledCodeCasessubsequenttoRevision30oftheguideinOctober1994.Thisregulatoryguidecontainsnoinformationcollectionactivitiesand,therefore,isnotsubjecttotherequirementsofthePaperworkReductionActof1980(44U.S.C.3501etseq.).B.DISCUSSIONTheBoilerandPressureVesselCommitteeoftheASMEpublishesadocumententitledCodeCases.1Generally,theindividualCodeCasesthatmakeupthisdocumentexplaintheintentofCoderulesorprovideforalternativerequirementsunderspecialcircumstances.MostCodeCasesareeventuallysupersededbyrevisiontotheCodeandthenareannulledbyactionoftheASME.Insuchcases,theintentoftheannulledCodeCasebecomespartoftherevisedCode,andthereforecontinueduseoftheCodeCaseintentissanctionedundertherulesoftheCode.Inothercases,theCodeCaseisannulledbecauseitisnolongeracceptableorthereisnofurtherrequirementforit.ACodeCasethatwasapprovedforaparticularsituationandnotforagenericapplicationshouldbeusedonlyforconstructionoftheapprovedsituationbecauseannulmentofsuchaCodeCasecouldresultinconstructionthatwouldnotmeetCoderequirements.TheCodeCaseslistedinthisguidearelimitedtothosecasesapplicabletoSectionIIIthatareorientedtowardmaterialsandtesting.AllpublishedCodeCasesintheareaofmaterialsandtestingthatareapplicabletoSectionIIIoftheCodeandwereineffectonMay12,1994,*werereviewedforinclusioninthisguide.InadditiontothelistingofacceptableCodeCases,thisrevisionoftheguideincludeslistingsof(1)CodeCasesthatwereidentifiedasacceptableinapriorversionofthisregulatoryguideandthatwereannulledaftertheoriginalissuanceofthisguide(June1974)and(2)CodeCasesthatwereidentifiedasacceptableinapriorversionofthisregulatoryguideandthatweresupersededbyrevisedCodeCasesaftertheoriginalissuanceofthisguide(June1974).CodeCasesthatarenotlistedhereinareeithernotendorsedorwillrequiresupplementaryprovisionsonanindividualbasistoattainendorsementstatus.TheendorsementofaCodeCasebythisguideconstitutesacceptanceofitstechnicalpositionforapplicationsnotprecludedbyregulatoryorotherrequirementsorbytherecommendationsinthisorotherregulatoryguides.ContingentendorsementisindicatedinRegulatoryPositionC.1.aforspecificcases.However,itistheresponsibilityoftheusertomakecertainthatnoregulatoryrequirementsareviolatedandthattherearenoconflictswithotherrecommendedlimitationsresultingfromCodeCaseusage.AcceptanceorendorsementbytheNRCstaffappliesonlytothoseCod