RG1.029 抗震设计分级 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-1156,datedOctober2006)SEISMICDESIGNCLASSIFICATIONA.INTRODUCTIONGeneralDesignCriterion(GDC)2,“DesignBasesforProtectionAgainstNaturalPhenomena,”ofAppendixA,“GeneralDesignCriteriaforNuclearPowerPlants,”toTitle10,Part50,oftheCodeofFederalRegulations(10CFRPart50),“DomesticLicensingofProductionandUtilizationFacilities”(Ref.1),requiresthatnuclearpowerplantstructures,systems,andcomponents(SSCs)importanttosafetymustbedesignedtowithstandtheeffectsofearthquakeswithoutlossofcapabilitytoperformtheirsafetyfunctions.Towardthatend,AppendixB,“QualityAssuranceCriteriaforNuclearPowerPlantsandFuelReprocessingPlants,”to10CFRPart50establishesqualityassurancerequirementsforthedesign,construction,andoperationofnuclearpowerplantSSCsthatpreventormitigatetheconsequencesofpostulatedaccidentsthatcouldcauseunduerisktothehealthandsafetyofthepublic.ThepertinentrequirementsofAppendixBapplytoallactivitiesaffectingthesafety-relatedfunctionsofthoseSSCs.AppendixSto10CFRPart50appliestoapplicantsforadesigncertificationorcombinedlicensepursuantto110CFRPart52,“EarlySitePermits;StandardDesignCertifications;andCombinedLicensesforNuclearPowerPlants,”oraconstructionpermitoroperatinglicensepursuantto10CFRPart50onorafterJanuary10,1997.However,theearthquakeengineeringcriteriainSectionVIofAppendixA,“SeismicandGeologicSitingCriteriaforNuclearPowerPlants,”to10CFRPart100,“ReactorSiteCriteria”(Ref.2),continuetoapplytooperatinglicenseapplicantsorholderswhoseconstructionpermitwasissuedbeforeJanuary10,1997.Dosevaluessetforthin10CFRPart100,“ReactorSiteCriteria”(Ref.2),continuetoapplytooperatinglicense2applicantsorholderswhoseconstructionpermitswereissuedbeforeJanuary10,1997.However,applicationof10CFR50.67,“Accidentsourceterm,”withthealternativesourcetermsidentifiedinthelatesteditionofRegulatoryGuide1.183,“AlternativeRadiologicalSourceTermsforEvaluatingDesign-BasisAccidentsatNuclearPowerReactors”(Ref.3),isavoluntaryoptiontomeetthenewpositionsinthisregulatoryguidance.Rev.4ofRG1.29,Page2Inaddition,AppendixS,“EarthquakeEngineeringCriteriaforNuclearPowerPlants,”to10CFRPart50,requiresthatallnuclearpowerplantsmustbedesignedsothatcertainSSCsremainfunctionalifthesafe-shutdownearthquakegroundmotion(SSE)occurs.Theseplantfeatures1arethosenecessarytoensure(1)theintegrityofthereactorcoolantpressureboundary,(2)thecapabilitytoshutdownthereactorandmaintainitinasafeshutdowncondition,or(3)thecapabilitytopreventormitigatetheconsequencesofaccidentsthatcouldresultinpotentialoffsiteexposurescomparabletotheguidelineexposuresof10CFR50.34(a)(1)or10CFR100.11.2ThisguidedescribesamethodthatthestaffoftheU.S.NuclearRegulatoryCommission(NRC)considersacceptableforuseinidentifyingandclassifyingthosefeaturesoflight-water-reactor(LWR)nuclearpowerplantsthatmustbedesignedtowithstandtheeffectsoftheSSE.Thisregulatoryguiderelatestoinformationcollectionsthatarecoveredbytherequirementsof10CFRPart50and10CFRPart100,whichtheOffi