NUREG/CR-6850, Volume 1 - NRC

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NPPNPSHNQ cableNRCP&IDPEPMPMMAPORVPRAPSFPTSPVCPWRQ cableRBMKRCICRCPRCSRDATRESRHRRI/PBRPSRWSTNuclear Power PlantNet Positive Suction HeadNon-Qualified (IEEE-383) cableNuclear Regulatory CommissionPiping and Instrumentation DiagramPolyethylenePreventive MaintenancePolymethyl MethacrylatePower Operated Relief ValveProbabilistic Risk AssessmentPerformance Shaping FactorPressurized Thermal ShockPolyvinyl ChloridePressurized Water ReactorQualified (IEEE-383) cableReactor Bolshoy Moshchnosty Kanalny (high-power channel reactor)Reactor Core Isolation CoolingReactor Coolant PumpReactor Coolant SystemComputer program for Bayesian analysisThe Office of Nuclear Regulatory Research (at NRC)Residual Heat RemovalRisk-Informed / Performance-BasedReactor Protection SystemRefueling Water Storage Tankxxiv
SCBASDPSGTRSISMASOSOVSRVSSDSSELSUTT/GTGBTSPUATVCTVTTVVERXLPEZOISelf-Contained Breathing ApparatusSignificance Determination ProcessSteam Generator Tube RuptureSafety InjectionSeismic Margin AssessmentSpurious OperationSolenoid Operated ValveSafety Relief ValveSafe ShutdownSafe Shutdown Equipment ListStart-up TransformerTurbine/GeneratorTurbine-Generator BuildingTransfer Switch PanelUnit Auxiliary TransformerVolume Control TankValtion Teknillinen Tutkimuskeskus (Technical Research Centre of Finland)The Soviet (and now, Russian Federation) designation for light waterpressurized reactorCross-Linked PolyethyleneZone of Influencexxv
Page 1: EPRI 1011989NUREG/CR-6850Final Repo
Page 5: CITATIONSThis report was prepared b
Page 9 and 10: CONTENTS1 INTRODUCTION ............
Page 11: LIST OF FIGURESFigure 1 Overview of
Page 15 and 16: PREFACEThis report is presented in
Page 17: BDetailed Fire Scenario AnalysisTAS
Page 21: ACKNOWLEDGMENTSThis work benefited
Page 24 and 25: CWPEDGEFEIEOPEPREPRIFEDBFEPFHACircu
Page 29 and 30: 1INTRODUCTION1.1 BackgroundOver the
Page 31 and 32: IntroductionNote that this report d
Page 33 and 34: IntroductionDevelopment Teams then
Page 35 and 36: IntroductionThe fire risk analysis
Page 37: Introduction1.6 Report StructureThi
Page 40 and 41: Overview of the Fire PRA Methodolog
Page 50 and 51: Conclusions and Closing Remarksconf
Page 52 and 53: Conclusions and Closing RemarksFutu
Page 54 and 55: Conclusions and Closing Remarks•
Page 56 and 57: Conclusions and Closing RemarksThe
Page 58 and 59: Conclusions and Closing Remarks3.3.
Page 60 and 61: Conclusions and Closing Remarks3.4
Page 62 and 63: Conclusions and Closing Remarks•
Page 64 and 65: Conclusions and Closing Remarks3.6
Page 67: Printed on recycled paperFederal Re

NUREG/CR-6850, Volume 1 - NRC

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