RG1.084 ASME第III卷设计制造和材料规范案例可接受性 2007

TheU.S.NuclearRegulatoryCommission(NRC)issuesregulatoryguidestodescribeandmakeavailabletothepublicmethodsthattheNRCstaffconsidersacceptableforuseinimplementingspecificpartsoftheagency’sregulations,techniquesthatthestaffusesinevaluatingspecificproblemsorpostulatedaccidents,anddatathatthestaffneedsinreviewingapplicationsforpermitsandlicenses.Regulatoryguidesarenotsubstitutesforregulations,andcompliancewiththemisnotrequired.MethodsandsolutionsthatdifferfromthosesetforthinregulatoryguideswillbedeemedacceptableiftheyprovideabasisforthefindingsrequiredfortheissuanceorcontinuanceofapermitorlicensebytheCommission.Thisguidewasissuedafterconsiderationofcommentsreceivedfromthepublic.Regulatoryguidesareissuedin10broaddivisions:1,PowerReactors;2,ResearchandTestReactors;3,FuelsandMaterialsFacilities;4,EnvironmentalandSiting;5,MaterialsandPlantProtection;6,Products;7,Transportation;8,OccupationalHealth;9,AntitrustandFinancialReview;and10,General.ElectroniccopiesofthisguideandotherrecentlyissuedguidesareavailablethroughtheNRC’spublicWebsiteundertheRegulatoryGuidesdocumentcollectionoftheNRC’sElectronicReadingRoomat’sAgencywideDocumentsAccessandManagementSystem(ADAMS)at(DraftwasissuedasDG-1133,datedOctober2006)DESIGN,FABRICATION,ANDMATERIALSCODECASEACCEPTABILITY,ASMESECTIONIIIA.INTRODUCTIONGeneralDesignCriterion(GDC)1,“QualityStandardsandRecords,”ofAppendixA,“GeneralDesignCriteriaforNuclearPowerPlants,”toTitle10,Part50,oftheCodeofFederalRegulations(10CFRPart50),“DomesticLicensingofProductionandUtilizationFacilities”(Ref.1),requires,inpart,thatstructures,systems,andcomponentsimportanttosafetybedesigned,fabricated,erected,andtestedtoqualitystandardscommensuratewiththeimportanceofthesafetyfunctiontobeperformed.Wheregenerallyrecognizedcodesandstandardsareused,Criterion1requiresthattheybeidentifiedandevaluatedtodeterminetheirapplicability,adequacy,andsufficiencyandbesupplementedormodifiedasnecessarytoensureaqualityproductinkeepingwiththerequiredsafetyfunction.Criterion30,“QualityofReactorCoolantPressureBoundary,”ofAppendixAto10CFRPart50requires,inpart,thatcomponentsthatarepartofthereactorcoolantpressureboundarybedesigned,fabricated,erected,andtestedtothehighestpracticalqualitystandards.AppendixB,“QualityAssuranceCriteriaforNuclearPowerPlantsandFuelProcessingPlants,”to10CFRPart50requires,inpart,thatmeasuresbeestablishedforthecontrolofspecialprocessingofmaterialsandthatpropertestingbeperformed.RG1.84,Rev.34,Page2ProvisionsoftheAmericanSocietyofMechanicalEngineers(ASME)BoilerandPressureVessel(BPV)Codehavebeenusedsince1971asonepartoftheframeworktoestablishthenecessarydesign,fabrication,construction,testing,andperformancerequirementsforstructures,systems,andcomponentsimportanttosafety.Amongotherthings,ASMEstandardscommitteesdevelopimprovedmethodsfortheconstructionandinserviceinspection(ISI)ofASMEClass1,2,3,MC(metalcontainment),andCC(concretecontainment)nuclearpowerplantcomponents.AbroadspectrumofstakeholdersparticipateintheASMEprocess,whichhelpstoensurethatthevariousinterestsareconsidered.Theregulationin10CFR50.55a(c),“ReactorCoolantPressureBoundary,”requires,inpart,thatcomponentsofthereactorcoolantpressureboundarymustbedesigned,fabricated,erected,andtestedinaccordancewiththerequirementsforClass1componentsofSectionIII,“RulesforConstructionofNuclearPowerPlantComponents,”oftheASMEBPVCode(Ref.2)orequivalentqualitystandards.TheASMEpublishesaneweditionoftheBPVCode,whichincludesSectionIII,every3years,andnewaddendaeveryyear.ThelatesteditionsandaddendaofSectionIIIthattheU.S.NuclearRegulatoryCommission(NRC)hasapprovedforusearereferencedin10CFR50.55a(b).TheASMEalsopublishesCodeCasesquarterly.CodeCasesprovidealternativesdevelopedandapprovedbyASME.ThisregulatoryguideidentifiestheCodeCasesthathavebeendeterminedbytheNRCtobeacceptablealternativestoapplicablepartsofSectionIII.SectionIIICodeCasesnotyetendorsedbytheNRCmaybeimplementedthrough10CFR50.55a(a)(3),whichpermitstheuseofalternativestotheCoderequirementsreferencedin10CFR50.55aprovidedthattheproposedalternativesresultinanacceptablelevelofqualityandsafety,andthattheiruseisauthorizedbytheDirectoroftheOfficeofNuclearReactorRegulation.TheASMECodeisincorporatedbyreferenceinto10CFR50.55a.CodeCasesapprovedbytheNRCprovideanacceptablevoluntaryalternativetothemandatoryASMECodeprovisions.Therefore,theNRCwillamend10CFR50.55atoincorporatebyreferencethenewCodeCasesandrevisionstoexistingCodeCaseslistedinthisguide,andtostatetherequirementsgoverningtheuseofCodeCases.BecauseofcontinuingchangeinthestatusofCodeCases,thestaffplansperiodicupdatesto10CFR50.55aandthisguidetoaccommodatenewCodeCasesandanyrevisionsofexistingCodeCases.1ExceptforCodeCasespertainingtohigh-temperaturegas-cooledreactors;certainrequirementsinSectionIII,Division2,notendorsedbytheNRC;liquidmetal;andsu