RG1.154 电站特定热冲击安全分析报告的格式与内容 1987

U.S.NUCLEARREGULATORYCOMMISSIONJanuary1987/REGULATORYGUIDEOFFICEOFNUCLEARREGULATORYRESEARCHREGULATORYGUIDE1.154(TaskSI502-41FORMATANDCONTENTOFPLANT-SPECIFICPRESSURIZEDTHERMALSHOCKSAFETYANALYSISREPORTSFORPRESSURIZEDWATERREACTORSUSNRCREGULATORYGUIDESTheguidesareissuedinthefollowingtenbroaddivisions:RegulatoryGuidesareissuedtodescribeandmakeavailabletothePublicmethodsacceptabletotheNRCstaffofimplementing1.PowerReactors6.ProductsspeclficpartsoftheCommisslon*~regulationstodelineatetech-2.ResearchandTestReactors7.Transportationniquesusedbythestaffinevaluatingspecific'problemsorPostu-3.FuelsandMaterialsFacilities8.OccupationalHealthiatedaccidentsortoprovideguidancetoapplicants.Regulatory4.EnvironmentalandSiting9.AntitrustandFinancialReviewGuidesareno{substitutesforregulationsandcompliancewith5.MaterialsandPlantProtection10.Generalthemisnotrequired.~ethodsandsolutionsherentfromthosesetoutintheguideswillbeacceptableiftheyprovideabasisforthefindingsrequisitetotheissuanceorcontinuanceofapermitorCopiesoflssuedguidesmaybepurchasedfromtheGovernmentlicensebytheCommission.PrintingOfficeatthecurrentGPOprice.InformationoncurrentGPOpricesmaybeobtainedbycontactingtheSuperintendentofThisguidewasissuedafterconsiderationofcommentsreceivedfromDocumentsU.S.GovernmentPrintingOfficePostOfficeBoxthepublicCommentsandsuggestionsforImprovementsinthese37082,waihington.DC20013-7082,telephoni(202)275-2060orguidesareencouragedatalltimesandguideswillberevised,as(202)275-2171.appropriatetoaccommodatecommhntsandtoreflectnewinform*tlonorexp;rience.IssuedguidesmayalsobepurchasedfromtheNationalTechnicalWrittencommentsmaybesubmittedtotheRulesandProceduresInformationServiceonastandingorderbasis.DetailsonthisBranchDRRADM,U.S.NuclearRegulatoryCommission,servicemaybeobtainedbywritingNTIS.5285RonRoyalRoad.~ashtnbton.~d20555.Springfield.VA22161.TableofContentsINTRODUCTION............................BackgroundandPurposeofThisGuide..............ObjectivesofPlant-SpecificPTSSafetyAnalysisReports....StaffReviewofPlant-SpecificPTSSafetyAnalysisReportsandAcceptanceCriteriaTorContinuedOperation.........RecommendedFormat.......................CHAPTER1OVERALLAPPROACH.SCOPEOFANALYSIS.ANDREPORTORGANIZATION......................CHAPTER2PLANTDATA........................2.1SystemsPertinenttoPTS...............2.2Reactorvessel...........................................2.3Fluence.............2.4InserviceInspectionResults2.5PlantOperatingExperience...............2.6OperatingProcedures................./CHAPTER3DETERMINATIONOFDETAILEDPTSSEQUENCESFORANALYSES.........................3.1ApproachUsed.....................3.2SequenceDelineation......................3.2.1DevelopmentofClassesofInitiators3.2.2IdentificationofImportantInitiatorVariations..................3.2.3DefinitionofPotentialTransients.........ResultingfromEachInitiator3.3OperatorEffects...................3.4SequenceQuantification...............3.4.1InitiatingEvents...............3.4.2EquipmentFailures..............3.4.3OperatorActions................................3.5EventTreeCollapse..............3.5.1SpecificSequences3.5.2ResidualGroups................PagevviviiiiiiTab1eofContents(Continued)PageCHAPTER4THERMAL-HYDRAULICANALYSIS................4.1Thermal-HydraulicAnalysisPlan...........4.2Thermal-HydraulicModel..............4.3Simp1ifiedAnalysisMethods.............4.4ThermalStratificationEffects............4.5Thermal-HydraulicAnalysisResults..........CHAPTER5FRACTUREMECHANICSANALYSIS...............CHAPTER6INTEGRATIONOFANALYSES.................CHAPTER7SENSITIVITYANDUNCERTAINTYANALYSESOFTHROUGH-WALLCRACKFREQUENCY........................7.1SensitivityAnalysis.................7.2UncertaintyAnalysis.................7.2.1ParameterUncertainties............7.2.2ModelingUncertainties(Biases)........CHAPTER8EFFECTOFCORRECTIVEACTIONSONVESSELTHROUGH-WALLCRACKFREQUENCY.....................8.1FluxReductionProgram................8.2OperatingProceduresandTrainingProgram.....................Improvements8.3InserviceInspectionandNondestructiveExaminationProgram.................8.4PlantModifications.................8.5InSituAnnealing..................CHAPTER9FURTHERANALYSES....................CHAPTER10RESULTSANDCONCLUSIONSREGARDINGPTSANALYSES......10..1SummaryofAnalysis.................10.2BasisforContinuedOperation............REFERENCES.............................REGULATORYANALYSIS.........................INTRODUCTION/BackgroundandPurposeofThisGuideThepressurizedthermalshock(PTS)rule,§50.61of10CFRPart50issuedonJuly23,1985(50FR29937),establishesascreeningcriterionbasedonreactorvesselnil-ductility-transitiontemperature(RTNDT)ThescreeningcriterionwasestablishedafterextensiveindustryandNRCanalysesregardingthelikelihoodofvesselfailureduetoPTSeventsinpressurizedwaterreactors(PWRs).TheanalyseswereappliedgenericallyandcontainedconservativeassumptionstomaketheresultsboundingforanyPWR.Basedontheresults,theNRCconcludedthattheriskduetoPTSeventsisacceptableatanyplantsolongastheRTpTSXofthereactorpressurevesselremainsbe1owthescreeningcriteri