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1RegulatoryGuide1.157,“Best-EstimateCalculationsofEmergencyCoreCoolingSystemPerformance,”describesacceptablemodels,correlations,data,modelevaluationprocedures,andmethodsformeetingthespecificrequirementsforarealisticorbest-estimatecalculationofECCSperformanceduringaloss-of-coolantaccident.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;orbyemailtoDistribution@nrc.gov.ElectroniccopiesofthisguideandotherrecentlyissuedguidesareavailablethroughtheNRC’spublicWebsiteundertheRegulatoryGuidesdocumentcollectionoftheNRC’sElectronicReadingRoomat’sAgencywideDocumentsAccessandManagementSystem(ADAMS)at(DraftswereissuedasDG-1096,datedDecember2000,andDG-1120,datedDecember2002)TRANSIENTANDACCIDENTANALYSISMETHODSA.INTRODUCTIONInTitle10,Part50,oftheCodeofFederalRegulations(10CFRPart50),“DomesticLicensingofProductionandUtilizationFacilities,”Section50.34,“ContentsofApplications;TechnicalInformation”(10CFR50.34),specifiesthefollowingrequirementsregardingapplicationsforconstructionpermitsand/orlicensestooperateafacility:(1)Safetyanalysisreportsmustanalyzethedesignandperformanceofstructures,systems,andcomponents,andtheiradequacyforthepreventionofaccidentsandmitigationoftheconsequencesofaccidents.(2)Analysisandevaluationofemergencycorecoolingsystem(ECCS)coolingperformancefollowingpostulatedloss-of-coolantaccidents(LOCAs)mustbeperformedinaccordancewiththerequirementsof10CFR50.46.(3)Thetechnicalspecificationsforthefacilitymustbebasedonthesafetyanalysisandpreparedinaccordancewiththerequirementsof10CFR50.36.ThisregulatoryguidedescribesaprocessthatthestaffoftheU.S.NuclearRegulatoryCommission(NRC)considersacceptableforuseindevelopingandassessingevaluationmodelsthatmaybeusedtoanalyzetransientandaccidentbehaviorthatiswithinthedesignbasisofanuclearpowerplant.EvaluationmodelsthattheNRChaspreviouslyapprovedwillremainacceptableandneednotberevisedtoconformwiththeguidancegiveninthisregulatoryguide.1RG1.203,Page2Chapter15oftheNRC’s“StandardReviewPlan(SRP)fortheReviewofSafetyAnalysisReportsforNuclearPowerPlants”(NUREG-0800,Ref.1)andthe“StandardFormatandContentofSafetyAnalysisReportsforNuclearPowerPlants”(RegulatoryGuide1.70,Ref.2)describeasubsetofthetransientandaccidenteventsthatmustbeconsideredinthesafetyanalysesrequiredby10CFR50.34.Sections15.1through15.6oftheSRPalsodiscussmanyoftheseevents.Thisregulatoryguideisintendedtoprovideguidanceforuseindevelopingandassessingevaluationmodelsforaccidentandtransientanalyses.Anadditionalbenefitisthatevaluationmodelsthataredevelopedusingtheseguidelineswillprovideamorereliableframeworkforrisk-informedregulationandabasisforestimatingtheuncertaintyinunderstandingtransientandaccidentbehavior.Towardthatend,theDiscussionsectionofthisguideaddressesthefundamentalfeaturesoftransientandaccidentanalysismethods.Next,theRegulatoryPositionsectiondescribesamulti-stepprocessfordevelopingandassessingevaluationmodels,andprovidesguidanceonrelatedsubjects,suchasqualityassurance,documentation,generalpurposecodes,andagradedapproachtotheprocess.TheImplementationsectionthenspecifiesthetargetaudienceforwhomthisguideisintended,aswellastheextenttowhichthisguideapplies,andtheRegulatoryAnalysissectionpresentsthestaff’srelatedrationaleandconclusion.Forconvenience,thisguidealsoinclud
本文标题:RG1.203 瞬态与事故分析方法 2005
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