ML17331A533

Susquehanna Steam Electric Station, Units 1 & 2, Revision 68 to Final Safety Analysis Report, Summary Table of Contents

ML17331A533
Person / Time
Site:	Susquehanna
Issue date:	10/16/2017
From:	Talen Energy, Susquehanna
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17331A584	List: ML17331A532 ML17331A533 ML17331A534 ML17331A547 ML17331A551 ML17331A553 ML17331A554 ML17331A564 ML18116A085 ML18116A111 ML18116A538 ML18117A090 ML18122A329 ML18122A338 ML18122A369 ML18123A242 ML18123A330 ML18123A485 ML18123A510 ML18124A094 ML18124A109 ML18124A125 ML18124A152 ML18124A200 ML18124A204 ML18298A237 PLA-7636, Redacted - Susquehanna Steam Electric Station, Units 1 & 2, Revision 68 to Final Safety Analysis Report, Chapter 3, Section 3.9 to 3.14, Conformance with NRC General Design Criteria. Part 2 of 2
References
PLA-7636
Download: ML17331A533 (405)

Text

SSES-FSARNIMSRev.60FSARRev.651-iCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANTTABLEOFCONTENTSTEXTSectionTitle1.1Introduction 1.1.1TypeofLicense1.1.2IdentificationofApplicant1.1.3NumberofPlantUnits1.1.4DescriptionofLocation1.1.5TypeofNuclearSteamSupply1.1.6TypeofContainment1.1.7CoreThermalPowerLevels1.1.8ScheduledFuelLoadandOperationData1.1.9FSAROrganization1.2GENERALPLANTDESCRIPTION 1.2.1PrincipalDesignCriteria 1.2.1.1GeneralDesignCriteria1.2.1.2SystemDesignCriteria1.2.1.2.1NuclearSystemCriteria1.2.1.2.2SafetyRelatedSystemsCriteria1.2.1.2.2.1General1.2.1.2.2.2ContainmentandIsolationCriteria1.2.1.2.2.3EmergencyCoreCoolingSystem(ECCS)Criteria1.2.1.2.3ProcessControlSystemsCriteria1.2.1.2.3.1NuclearSystemProcessControlCriteria1.2.1.2.3.2PowerConversionSystemsProcessControlCriteria1.2.1.2.3.3ElectricalPowerSystemProcessControlCriteria1.2.1.2.4ElectricalPowerSystemCriteria1.2.1.2.5FuelHandlingandStorageFacilities1.2.1.2.6AuxiliarySystemsCriteria1.2.1.2.7PowerConversionSystemsCriteria1.2.1.2.8RadioactiveWasteDisposalCriteria1.2.1.2.9ShieldingandAccessControlCriteria1.2.2PlantDescription SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-ii1.2.2.1SiteCharacteristics1.2.2.1.1LocationandSize1.2.2.1.2RoadandRailAccess1.2.2.1.3DescriptionofPlantEnvirons1.2.2.1.3.1GeologyandSoils1.2.2.1.3.2Groundwater1.2.2.1.3.3Hydrology1.2.2.1.3.4Meteorology1.2.2.1.3.5Seismicity1.2.2.2GeneralArrangementofStructuresandEquipment1.2.2.3NuclearSystem1.2.2.3.1ReactorCoreandControlRods1.2.2.3.2ReactorVesselandInternals1.2.2.3.3ReactorRecirculationSystem1.2.2.3.4ResidualHeatRemovalSystem1.2.2.3.5ReactorWaterCleanupSystem(RWCU)1.2.2.4SafetyRelatedSystems1.2.2.4.1ReactorProtectionSystem1.2.2.4.2NeutronMonitoringSystem1.2.2.4.3ControlRodDriveSystem1.2.2.4.4NuclearSystemPressureReliefSystem1.2.2.4.5ReactorCoreIsolationCoolingSystem1.2.2.4.6PrimaryContainment1.2.2.4.7PrimaryContainmentandReactorVesselIsolationControlSystem1.2.2.4.8SecondaryContainment1.2.2.4.9MainSteamlineIsolationValves1.2.2.4.10MainSteamlineFlowRestrictors1.2.2.4.11EmergencyCoreCoolingSystems(ECCS)1.2.2.4.12ResidualHeatRemovalSystem(ContainmentCooling)1.2.2.4.13ControlRodVelocityLimiter1.2.2.4.14ControlRodDriveHousingSupports1.2.2.4.15ReactorBuildingRecirculationandStandbyGasTreatmentSystems1.2.2.4.16StandbyacPowerSupply1.2.2.4.17dcPowerSupply1.2.2.4.18ResidualHeatRemovalServiceWaterSystem1.2.2.4.19EmergencyServiceWaterSystem1.2.2.4.20MainSteamlineRadiationMonitoringSystem1.2.2.4.21ReactorBuildingVentilationRadiationMonitoringSystem1.2.2.4.22NuclearLeakDetectionSystem1.2.2.5InstrumentationandControl1.2.2.5.1NuclearSystemProcessControlandInstrumentation SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-iii1.2.2.5.1.1ReactorManualControlSystem1.2.2.5.1.2RecirculationFlowControlSystem1.2.2.5.1.3NeutronMonitoringSystem1.2.2.5.1.4RefuelingInterlocks1.2.2.5.1.5ReactorVesselInstrumentation1.2.2.5.1.6ProcessComputerSystem1.2.2.5.1.7RemoteShutdownSystem1.2.2.5.2PowerConversionSystemsProcessControlandInstrumentation1.2.2.5.2.1PressureRegulatorandTurbineControl1.2.2.5.2.2FeedwaterSystemControl1.2.2.5.2.3ElectricalPowerSystemControl1.2.2.6ElectricalSystems1.2.2.6.1TransmissionandGenerationSystems1.2.2.6.2ElectricalPowerDistributionSystems1.2.2.7FuelHandlingandStorageSystems1.2.2.7.1NewandSpentFuelStorage1.2.2.7.2FuelPoolCoolingandCleanupSystem1.2.2.7.3FuelHandlingEquipment1.2.2.8CoolingWaterandAuxiliarySystems1.2.2.8.1ServiceWaterSystem1.2.2.8.2ResidualHeatRemovalServiceWaterSystem(RHRSWS)1.2.2.8.3EmergencyServiceWaterSystem(ESWS)1.2.2.8.4ReactorBuildingClosedCoolingWaterSystem1.2.2.8.5TurbineBuildingClosedCoolingWaterSystem(TBCCWS)1.2.2.8.6StandbyLiquidControlSystem1.2.2.8.7FireProtectionSystem1.2.2.8.8PlantHeating,Ventilating,andAir-ConditioningSystems1.2.2.8.9CompressedAirSystem1.2.2.8.10MakeupWaterTreatmentSystem1.2.2.8.11DomesticandSanitaryWaterSystems1.2.2.8.12PlantEquipmentandFloorDrainageSystems1.2.2.8.13ProcessSamplingSystem1.2.2.8.14PlantCommunicationSystem1.2.2.8.15ProcessValveStemLeakoffSystem1.2.2.8.16DieselAuxiliarySystems1.2.2.8.17AuxiliarySteamSystem1.2.2.9PowerConversionSystem1.2.2.9.1Turbine-Generator1.2.2.9.2MainSteamSystem1.2.2.9.3MainCondenser1.2.2.9.4MainCondenserGasRemovalSystem SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-iv1.2.2.9.5SteamSealSystem1.2.2.9.6SteamBypassandPressureControlSystem1.2.2.9.7CirculatingWaterSystem1.2.2.9.8CondensateCleanupSystem1.2.2.9.9CondensateandFeedwaterSystem1.2.2.9.10CondensateandRefuelingWaterStorageandTransferSystem1.2.2.10RadioactiveWasteSystems1.2.2.10.1LiquidRadwasteSystem1.2.2.10.2SolidRadwasteSystem1.2.2.10.3GaseousRadwasteSystem1.2.2.11RadiationMonitoringandControl1.2.2.11.1ProcessRadiationMonitoring1.2.2.11.2AreaRadiationMonitors1.2.2.11.3SiteEnvironsRadiationMonitors1.2.2.11.4LiquidRadwasteSystemControl1.2.2.11.5SolidRadwasteControl1.2.2.11.6GaseousRadwasteSystemControl1.2.2.12Shielding1.2.2.13SteamDryerStorage1.3COMPARISONTABLES 1.3.1ComparisonWithSimilarFacilityDesigns 1.3.1.1NuclearSteamSupplySystemDesignCharacteristics1.3.1.2PowerConversionSystemDesignCharacteristics1.3.1.3EngineeredSafetyFeaturesDesignCharacteristics1.3.1.4ContainmentDesignCharacteristics1.3.1.5RadioactiveWasteManagementSystemsDesignCharacteristics1.3.1.6StructuralDesignCharacteristics1.3.1.7InstrumentationandElectricalSystemsDesignCharacteristics1.3.2ComparisonofFinalandPreliminaryInformation 1.4IDENTIFICATIONOFAGENTSANDCONTRACTORS 1.4.1PennsylvaniaPower&LightCompany(Applicant)1.4.2ArchitectEngineer1.4.3NuclearSteamSupplySystem1.4.4Turbine-GeneratorVendor1.4.5OtherConsultants SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-v1.5REQUIREMENTSFORFURTHERTECHNICALINFORMATION1.5.1DevelopmentofBWRTechnology 1.5.1.1CurrentDevelopmentPrograms1.5.1.1.1CoreSprayDistribution1.5.1.1.2CoreSprayandCoreFloodingHeatTransferEffectiveness1.5.1.1.3VerificationofPressureSuppressionDesign1.5.1.1.4CriticalHeatFluxTesting1.5.1.1.5FuelAssemblyStructuralTesting1.5.2ProgramsConductedDuringOperationsPhase 1.6MATERIALINCORPORATEDBYREFERENCE 1.6.1GeneralElectricTopicalReports1.6.2BechtelTopicalReports1.6.3OtherTopicalReports1.7ELECTRICAL,INSTRUMENTATION,ANDCONTROLDRAWINGS 1.8SYMBOLSANDTERMSUSEDINENGINEERINGANDTEXT 1.8.1TextDefinitionsandAbbreviations1.8.2DrawingIndexandSymbols1.8.3PipingIdentification1.8.4ValveIdentification1.8.5InstrumentIdentification1.8.5.1InstrumentComponents1.8.5.2InstrumentLocation1.8.6ElectricalComponentIdentification 1.8.6.1EquipmentLocationNumbers1.8.6.2SchemeNumbers1.8.6.3SchemeCableNumbers1.8.6.4RacewayNumbers SSES-FSARNIMSRev.60CHAPTER1TABLESNumberTitleFSARRev.651-vi1.3-1ComparisonofNuclearSteamSupplySystemDesignCharacteristics1.3-2ComparisonofPowerConversionSystemDesignCharacteristics 1.3-3ComparisonofEngineeredSafetyFeaturesDesignCharacteristics 1.3-4ComparisonofContainmentDesignCharacteristics 1.3-5RadioactiveWasteManagementSystemsDesignCharacteristics 1.3-6ComparisonofStructuralDesignCharacteristics 1.3-7ComparisonofElectricalPowerSystemsDesignCharacteristics 1.3-8SignificantDesignChangesfromPSARtoFSAR 1.4-1CommercialNuclearReactorsCompleted,UnderConstruction,orinDesignByGeneralElectric1.6-1GeneralElectricTopicalReports 1.6-2BechtelTopicalReports 1.6-3ThisTableHasBeenDeleted 1.6-4OtherTopicalReports 1.7-1ElectricalDrawings 1.8-1SSES-ProjectGlossaryTerms 1.8-2Acronyms 1.8-3TechnicalAbbreviations 1.8-4ThisTableHasBeenIntentionallyLeftBlank 1.8-5DrawingAbbreviations 1.8-6PipingandValveClassIdentification SSES-FSARNIMSRev.60CHAPTER1FIGURESNumberTitleFSARRev.651-vii1.2-1ThisFigurehasbeenReplacedbyDwg.M-220,Sh.11.2-2ThisFigurehasbeenReplacedbyDwg.M-221,Sh.11.2-3ThisFigurehasbeenReplacedbyDwg.M-222,Sh.11.2-4ThisFigurehasbeenReplacedbyDwg.M-223,Sh.1 1.2-5ThisFigurehasbeenReplacedbyDwg.M-224,Sh.11.2-6ThisFigurehasbeenReplacedbyDwg.M-225,Sh.11.2-7ThisFigurehasbeenReplacedbyDwg.M-226,Sh.11.2-8ThisFigurehasbeenReplacedbyDwg.M-227,Sh.11.2-9ThisFigurehasbeenReplacedbyDwg.M-230,Sh.1 1.2-10ThisFigurehasbeenReplacedbyDwg.M-231,Sh.11.2-11ThisFigurehasbeenReplacedbyDwg.M-232,Sh.11.2-12ThisFigurehasbeenReplacedbyDwg.M-233,Sh.11.2-13ThisFigurehasbeenReplacedbyDwg.M-234,Sh.11.2-14ThisFigurehasbeenReplacedbyDwg.M-235,Sh.11.2-15ThisFigurehasbeenReplacedbyDwg.M-236,Sh.11.2-16ThisFigurehasbeenReplacedbyDwg.M-237,Sh.1 1.2-17ThisFigurehasbeenReplacedbyDwg.M-240,Sh.11.2-18ThisFigurehasbeenReplacedbyDwg.M-241,Sh.11.2-19ThisFigurehasbeenReplacedbyDwg.M-242,Sh.11.2-20ThisFigurehasbeenReplacedbyDwg.M-243,Sh.11.2-21ThisFigurehasbeenReplacedbyDwg.M-244,Sh.1 1.2-22ThisFigurehasbeenReplacedbyDwg.M-245,Sh.11.2-23ThisFigurehasbeenReplacedbyDwg.M-246,Sh.1 SSES-FSARNIMSRev.60CHAPTER1FIGURESNumberTitleFSARRev.651-viii1.2-24ThisFigurehasbeenReplacedbyDwg.M-247,Sh.11.2-25ThisFigurehasbeenReplacedbyDwg.M-248,Sh.11.2-26ThisFigurehasbeenReplacedbyDwg.M-249,Sh.11.2-27ThisFigurehasbeenReplacedbyDwg.M-250,Sh.1 1.2-28ThisFigurehasbeenReplacedbyDwg.M-251,Sh.11.2-29ThisFigurehasbeenReplacedbyDwg.M-252,Sh.11.2-30ThisFigurehasbeenReplacedbyDwg.M-253,Sh.11.2-31ThisFigurehasbeenReplacedbyDwg.M-254,Sh.11.2-32ThisFigurehasbeenReplacedbyDwg.M-255,Sh.1 1.2-33ThisFigurehasbeenReplacedbyDwg.M-256,Sh.11.2-34ThisFigurehasbeenReplacedbyDwg.M-257,Sh.11.2-35ThisFigurehasbeenReplacedbyDwg.M-258,Sh.11.2-36ThisFigurehasbeenReplacedbyDwg.M-259,Sh.11.2-37ThisFigurehasbeenReplacedbyDwg.M-260,Sh.1 1.2-38ThisFigurehasbeenReplacedbyDwg.M-261,Sh.11.2-39ThisFigurehasbeenReplacedbyDwg.M-270,Sh.11.2-40ThisFigurehasbeenReplacedbyDwg.M-271,Sh.11.2-41ThisFigurehasbeenReplacedbyDwg.M-272,Sh.11.2-42ThisFigurehasbeenReplacedbyDwg.M-273,Sh.11.2-43ThisFigurehasbeenReplacedbyDwg.M-274,Sh.1 1.2-44ThisFigurehasbeenReplacedbyDwg.M-276,Sh.11.2-45ThisFigurehasbeenReplacedbyDwg.M-280,Sh.1 SSES-FSARNIMSRev.60CHAPTER1FIGURESNumberTitleFSARRev.651-ix1.2-46ThisFigurehasbeenReplacedbyDwg.M-281,Sh.11.2-47ThisFigurehasbeenReplacedbyDwg.M-282,Sh.11.2-48ThisFigurehasbeenReplacedbyDwg.M-284,Sh.11.2-49Unit1-HeatBalanceatRatedPowerwith100x10 6LBm/hrCoreFlow1.2-49-1Unit1-HeatBalanceatRatedPowerwith108x10 6LBm/hrIncreasedCoreFlow1.2-49-2Unit2-HeatBalanceatRatedPowerwith100x10 6LBm/hrCoreFlow1.2-49-3Unit2-HeatBalanceatRatedPowerwith108x10 6LBm/hrIncreasedCoreFlow1.2-50DieselGenerator'E'BuildingGeneralArrangementPlans1.2-51DieselGenerator'E'BuildingGeneralArrangementSectionsSh.21.2-52ThisFigurehasbeenDeleted 1.8-1PipingandInstrumentSymbols1.8-2aP&ID&HVACControlDiagramsLegend&Symbols1.8-2bP&ID&HVACControlDiagramsLegend&Symbols1.8-2cP&IDLegendandSymbols1.8-2dP&IDLegend&Symbols 1.8-3LogicSymbols1.8-4InstrumentSymbol SSES-FSARNIMSRev.60FSARRev.652-iCHAPTER2SITECHARACTERISTICSTABLEOFCONTENTSTEXTSectionTitle2.1GEOGRAPHYANDDEMOGRAPHY 2.1.1SiteLocationandDescription 2.1.1.1SpecificationofLocation2.1.1.2SiteAreaMap2.1.1.3BoundariesforEstablishingEffluentReleaseLimits2.1.2ExclusionAreaAuthorityandControl 2.1.2.1Authority2.1.2.2ControlofActivitiesUnrelatedtoPlantOperation2.1.2.3ArrangementforTrafficControl2.1.2.4AbandonmentorRelocationofRoads2.1.3PopulationDistribution 2.1.3.1PopulationWithin10Miles2.1.3.2PopulationBetween10and50Miles2.1.3.3TransientPopulationBetween0and50Miles2.1.3.3.1SeasonalPopulationBetween0to50Miles2.1.3.3.2DailyTransientPopulation2.1.3.3.3LowPopulationZone2.1.3.4PopulationCenter2.1.3.5PopulationDensity2.1.3.6Thissectionhasbeendeleted2.1.4References 2.2NEARBYINDUSTRIAL,TRANSPORTATION,ANDMILITARYFACILITIES2.2.1LocationsandRoutes 2.2.2Descriptions SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-ii2.2.2.1DescriptionofFacilities2.2.2.2DescriptionsofProductsandMaterials2.2.2.3Pipelines2.2.2.4Waterways2.2.2.5Airports2.2.2.6ProjectionsofIndustrialGrowth2.2.3EvaluationofPotentialAccidents 2.2.3.1DeterminationofDesignBasisEvents2.2.3.1.1Explosions2.2.3.1.1.1HydrogenWaterChemistryStorageTankFarm2.2.3.1.2FlammableVapors2.2.3.1.2.1Twelve-InchNaturalGasPipeline2.2.3.1.2.2Twenty-FourInchGasPipeline2.2.3.1.2.3Thirty-SixInchNaturalGasPipeline2.2.3.1.2.4PropaneCarriers2.2.3.1.2.5SixteenInchNaturalGasPipeline2.2.3.1.3ExposuretoHazardousChemicalReleases2.2.3.1.4Fires2.2.3.1.5CollisionswithIntakeStructure2.2.3.1.6LiquidSpills2.2.3.1.7SubsurfaceGasandWasteStorage2.2.3.2EffectsofDesignBasisEvents2.2.4References 2.3METEOROLOGY 2.3.1RegionalClimatology 2.3.1.1GeneralClimate2.3.1.2RegionalMeteorologicalConditionsforDesignandOperatingBases2.3.1.2.1Hurricanes2.3.1.2.2Tornadoes2.3.1.2.3Thunderstorms2.3.1.2.4Lightning2.3.1.2.5Hail2.3.1.2.6ExtremeWinds2.3.1.2.7FreezingRain2.3.1.2.8Duststorms SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-iii2.3.1.2.9HighAirPollutionPotential2.3.1.2.10Snowpacks2.3.1.2.11DesignBasisTornado2.3.1.2.12UltimateHeatSink2.3.2LocalMeteorology 2.3.2.1NormalandExtremeValuesofMeteorologicalParameters2.3.2.1.1Wind2.3.2.1.2TemperatureandAtmosphericWaterVapor2.3.2.1.3Precipitation2.3.2.1.4FogandSmog2.3.2.1.5Stability2.3.2.2PotentialInfluenceofthePlantanditsFacilitiesonLocalMeteorology2.3.2.3LocalMeteorologicalConditionsforDesignandOperatingBases2.3.3On-SiteMeteorologicalMeasurementsProgram 2.3.3.1LocationandDescriptionoftheTowerSite2.3.3.2TypesofMeasurementsMade2.3.3.3DescriptionofInstruments2.3.3.4DataRecordingSystems2.3.3.5CalibrationandMaintenanceoftheSystem2.3.3.6DataAnalysis2.3.4Short-Term(Accident)DiffusionEstimates 2.3.4.1Short-Term(0-2hours)Releases2.3.4.1.1Direction-IndependentCalculations2.3.4.1.2Direction-DependentCalculations2.3.4.1.3DeterminingAppropriateShort-TermDispersion2.3.4.2LongTermReleases2.3.4.3AnalyticalMethodsforDispersionComputations2.3.5LongTerm(Routine)DiffusionEstimates 2.3.5.1AtmosphericDiffusionModels2.3.5.1.1Straight-LineAirflowModel2.3.5.1.2Terrain/RecirculationConnectionFactors2.3.5.1.3DepositionandDepleted/qs2.3.5.1.4ResultsofLong-TermDiffusionEstimates SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-iv2.3.6References2.4HYDROLOGICENGINEERING2.4.1HydrologicDescription2.4.1.1SiteandFacilities2.4.1.2Hydrosphere2.4.1.2.1RiversandStreams2.4.1.2.2DamsandReservoirs2.4.1.2.3DownstreamWaterUses2.4.2Floods 2.4.2.1FloodHistory2.4.2.1.1FloodRecords2.4.2.1.2TropicalStormAgnes2.4.2.1.3FloodResultingFromIceJams2.4.2.2FloodDesignConsiderations2.4.2.3EffectsofLocalIntensePrecipitation2.4.3ProbableMaximumFlood(PMF)onStreamsandRivers 2.4.3.1ProbableMaximumPrecipitation2.4.3.2PrecipitationLosses2.4.3.3RunoffandStreamCourseModels2.4.3.4ProbableMaximumFloodFlow2.4.3.5WaterLevelDetermination2.4.3.5.1HydraulicCharacteristicsofChannelandOverbank2.4.3.5.2BackwaterCurveCalculations2.4.3.6CoincidentWindWaveActivity 2.4.4PotentialDamFailuresSeismicallyInduced 2.4.4.1DamFailurePermutations2.4.4.2UnsteadyFlowAnalysisofPotentialDamFailures2.4.4.2.1SingularDamFailures2.4.4.2.2MultipleDamFailures-ChemungRiverBasin2.4.4.2.3MultipleDamFailures-EastSusquehannaRiverBasin2.4.4.2.4MultipleDamFailures-LackawannaRiverBasin2.4.4.3WaterLevelatPlantSite SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-v2.4.5ProbableMaximumSurgeandSeicheFlooding2.4.6ProbableMaximumTsunamiFlooding2.4.7IceEffects2.4.8CoolingWaterCanalsandReservoirs 2.4.8.1General2.4.8.2GeneralDescriptionoftheSprayPondSystem2.4.8.3DesignBasesfortheCapacityofSprayPond2.4.8.4HydrologicDesignBasesfortheSprayPondSystem2.4.8.4.1DesignBasisFloodLevel(DBFL)2.4.8.4.2SafeShutdownandOperatingBasisEarthquakes2.4.9ChannelDiversions 2.4.10FloodingProtectionRequirements 2.4.11LowWaterConsiderations 2.4.11.1LowFlowinRiversandStreams2.4.11.1.1LowFlowResultingFromHydrometeorologicalEvents2.4.11.1.2LowFlowResultingfromDamFailures2.4.11.2LowWaterResultingfromSurges,Seiches,orTsunami2.4.11.3HistoricalLowWater2.4.11.4FutureControls2.4.11.4.1LegalConsumptiveUseRestrictions2.4.11.4.2ChangesinConsumptiveUseUpstream2.4.11.5PlantRequirements2.4.11.6HeatSinkDependabilityRequirements2.4.12DispersionDilutionandTravelTimeofAccidentalReleasesofLiquidEffluentsinSurfaceWaters2.4.12.1RiverFlowCharacteristics2.4.12.1.1FlowDuration2.4.12.1.2ExtremeLowFlow2.4.12.1.3TravelTimes2.4.12.2AccidentalReleases2.4.12.3EffluentDilution SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-vi2.4.13Groundwater2.4.13.1DescriptionandOnsiteUse2.4.13.1.1RegionalGroundwaterConditions2.4.13.1.1.1PrimaryAquifersoftheRegionPleistocene-AgeDeposits2.4.13.1.1.2SecondaryAquifersoftheRegionLlewellynFormation2.4.13.1.2LocalGroundwaterConditions2.4.13.1.3OnsiteUseofGroundwater2.4.13.2Sources2.4.13.2.1WaterWellInventory2.4.13.2.2GroundwaterWithdrawal2.4.13.2.3AquiferCharacteristicsandGroundwaterConditionsattheSite2.4.13.2.3.1DataSources2.4.13.2.3.2GroundwaterParametersandMovementattheSite2.4.13.3AccidentsEffects2.4.13.3.1PostulatedAccidentandPotentialFlowPaths2.4.13.3.2DescriptionoftheModelsUsed2.4.13.3.3SelectionofParametersforSLUG3DSimulations2.4.13.3.4NumericalModelSimulationofBuried-ValleyAquifer2.4.13.3.5DiscussionofResultsofAnalysis2.4.13.4DesignBasesforSubsurfaceHydrostaticLoadings2.4.14TechnicalSpecificationandEmergencyOperationRequirements 2.4.15References 2.5GEOLOGY,SEISMOLOGY,ANDGEOTECHNICALENGINEERING 2.5.1BasicGeologicandSeismicInformation 2.5.1.1RegionalGeology2.5.1.1.1PhysiographyandGeomorphology2.5.1.1.2StratigraphyandLithology2.5.1.1.2.1TheAppalachianBasin2.5.1.1.2.2TheValleyandRidgeProvince2.5.1.1.2.3StratigraphicUnitsWithintheSiteVicinity2.5.1.1.3RegionalTectonics2.5.1.1.3.1TectonicProvinces2.5.1.1.3.2StructuralElementswithintheCraton2.5.1.1.3.3StructuralElementsintheSiteVicinity2.5.1.1.3.4RelationshipAmongStructuralElements2.5.1.1.3.5AgeofDeformation SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-vii2.5.1.1.3.5.1RelationshipofLineamentstoRegionalGeology2.5.1.1.4RegionalUpliftandSubsidence2.5.1.1.5NaturalHazards2.5.1.2SiteGeology2.5.1.2.1SitePhysiography2.5.1.2.2SiteLithologyandStratigraphy2.5.1.2.2.1LithologyandStratigraphyintheSiteVicinity2.5.1.2.2.2LithologyandStratigraphyattheSite2.5.1.2.3StructuralGeology2.5.1.2.3.1MajorGeologicStructuresinSiteVicinity2.5.1.2.3.2GeologicStructuresattheSite2.5.1.2.3.3GeologicFeaturesinSurficialMaterialsattheSite2.5.1.2.3.4HazardsfromStorageinLocalGeologicStructures2.5.1.2.4SiteGeologicHistory2.5.1.2.5EngineeringGeologyEvaluation2.5.1.2.5.1GeologicConditionsUnderCategory1Structures2.5.1.2.5.2LandslidePotential2.5.1.2.5.3AreasofPotentialSubsidence,Uplift,orCollapse2.5.1.2.5.4BehaviorofSiteDuringPriorEarthquakes2.5.1.2.5.5ZonesofDeformationorStructuralWeakness2.5.1.2.5.6ZonesofAlterationorIrregularWeathering2.5.1.2.5.7PotentialforUnstableorHazardousRockorSoilConditions2.5.1.2.5.8UnrelievedResidualStressonBedrock2.5.1.2.5.9ConclusionsandSummary2.5.1.2.6SiteGroundwaterConditions2.5.2VibratoryGroundMotion 2.5.2.1Seismicity2.5.2.2GeologicStructuresandTectonicActivity2.5.2.2.1TectonicProvinces2.5.2.2.2TectonicDifferentiationoftheAppalachianOrogen2.5.2.2.3TectonicDifferentiationoftheCraton2.5.2.2.4TectonicDifferentiationoftheMobileBelt2.5.2.3CorrelationofEarthquakeActivitywithGeologicStructuresorTectonicProvinces2.5.2.4MaximumEarthquakePotential2.5.2.5SeismicWaveTransmissionCharacteristics2.5.2.6SafeShutdownEarthquake(SSE)2.5.2.7OperatingBasisEarthquake(OBE)

SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-viii2.5.3SurfaceFaulting2.5.4StabilityofSubsurfaceMaterialsandFoundations2.5.4.1GeologicFeatures2.5.4.1.1AreasofPotentialSubsidence,Uplift,orCollapse2.5.4.1.2PreviousLoadingHistoryoftheFoundationMaterials2.5.4.1.3StructuresandZonesofWeathering,DisturbanceorWeaknessinFoundationMaterials2.5.4.1.4UnrelievedResidualStressesinBedrock2.5.4.1.5PotentialforUnstableorHazardousRockorSoilConditions2.5.4.2PropertiesofSubsurfaceMaterials2.5.4.2.1PropertiesofFoundationRock2.5.4.2.2PropertiesofFoundationSoils2.5.4.3Exploration2.5.4.4GeophysicalSurveys2.5.4.5ExcavationsandBackfill2.5.4.5.1ExtentofSeismicCategoryIExcavations,Fills,andSl opes2.5.4.5.2ExcavationMethodsandDewatering2.5.4.5.2.1ExcavationsinRock2.5.4.5.2.2ExcavationsinSoil2.5.4.5.3BackfillandCompaction2.5.4.5.4BeddingMaterialforSeismicCategoryIPipesandElectricalDuctBanks2.5.4.6GroundwaterConditions2.5.4.7ResponseofSoilandRocktoDynamicLoading2.5.4.7.1ResponseofRocktoDynamicLoading2.5.4.7.2ResponseofSoiltoDynamicLoading2.5.4.7.3SoilStructureInteraction2.5.4.8LiquefactionPotential2.5.4.9EarthquakeDesignBases2.5.4.10StaticStability2.5.4.10.1StaticStabilityofSafety-RelatedStructuresSupportedonRock2.5.4.10.2StaticStabilityofSafety-RelatedStructuresSupportedonSoil2.5.4.11DesignCriteria2.5.4.11.1DesignCriteriaofSafety-RelatedStructuresonRock2.5.4.11.2DesignCriteriaofSafety-RelatedStructuresonSoil2.5.4.12TechniquestoImproveSubsurfaceConditions2.5.4.12.1FoundationsinRock2.5.4.12.2FoundationsinSoil2.5.4.13SubsurfaceInstrumentation2.5.4.13.1InstrumentationforRockFoundations2.5.4.13.2InstrumentationforSoilFoundations SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-ix2.5.4.14ConstructionNotes2.5.5StabilityofSlopes2.5.5.1SlopeCharacteristics2.5.5.1.1GeologicConditions2.5.5.1.2GroundwaterConditions2.5.5.1.3FieldSamplingandTesting2.5.5.1.4LaboratoryTesting2.5.5.1.4.1General2.5.5.1.4.2GrainSizeDistribution2.5.5.1.4.3UnitWeight2.5.5.1.4.4Maximum-MinimumDensities2.5.5.1.4.5RelativeDensity2.5.5.1.4.6StaticTriaxialShearTest2.5.5.1.4.7CyclicTriaxialShearTests2.5.5.2DesignCriteriaandAnalyses2.5.5.2.1DesignCriteriaforSprayPond2.5.5.2.1.1GroundSurfaceAcceleration2.5.5.2.1.2Liquefaction2.5.5.2.1.3SlopeStability2.5.5.2.2DesignAnalysesforSprayPond2.5.5.2.2.1SprayPondSeepageAnalysis2.5.5.2.2.1.1SprayPondSeepageMonitoring2.5.5.2.2.2LiquefactionPotential2.5.5.2.2.2.1MethodofAnalysis2.5.5.2.2.2.2SoilProfilesandPositionsofGroundwaterTable2.5.5.2.2.2.3ShearModuli2.5.5.2.2.2.4CyclicShearStrength2.5.5.2.2.2.5DeterminationofDynamicShearStresses2.5.5.2.2.2.6DesignEarthquake2.5.5.2.2.2.7ResultsofLiquefactionAnalyses2.5.5.2.2.2.7.1LiquefactionPotentialUndertheDesignSSE2.5.5.2.2.2.7.2VariationsofShearModuliandDampingRatiosforEvaluationofLiquefactionPotential2.5.5.2.2.2.7.3ResultsofLiquefactionAnalysesUsingRealEarthquakeRecords2.5.5.2.2.3SlopeStabilityAnalyses2.5.5.2.2.3.1StabilityofRockSlopes2.5.5.2.2.3.2StabilityofSlopesinSoil2.5.5.2.2.4Earthquake-InducedSoilStrainandSettlement2.5.5.3LogsofBorings2.5.5.4CompactedBackfill SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-x2.5.6References2.5AU.S.DEPARTMENTOFTHEINTERIORREPORTONINVESTIGATIONOFANEARTHDISTURBANCEATWILKES-BARRE2.5BCITYOFWILKES-BARREREPORTONANEARTHDISTURBANCE 2.5CBORINGLOGS 2.5C.1SummaryofFieldDensityTestResults2.5C.2ListingsofBoringLogs SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xi2.1-1Thistablehasbeendeleted2.1-2Thistablehasbeendeleted 2.1-3Thistablehasbeendeleted 2.1-4Thistablehasbeendeleted 2.1-5Thistablehasbeendeleted 2.1-6Thistablehasbeendeleted 2.1-7Thistablehasbeendeleted 2.1-8Thistablehasbeendeleted 2.1-9Thistablehasbeendeleted 2.1-10Thistablehasbeendeleted 2.1-11Thistablehasbeendeleted 2.1-12Thistablehasbeendeleted 2.1-13Thistablehasbeendeleted 2.1-14Thistablehasbeendeleted 2.1-15Thistablehasbeendeleted 2.1-16Thistablehasbeendeleted 2.1-17Thistablehasbeenrenumberedto2.1-33 2.1-18Thistablehasbeenrenumberedto2.1-34 2.1-19Thistablehasbeenrenumberedto2.1-39 2.1-20Thistablehasbeenrenumberedto2.1-41 2.1-21Thistablehasbeenrenumberedto2.1-35 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xii2.1-22Thistablehasbeenrenumberedto2.1-362.1-23Thistablehasbeenrenumberedto2.1-37 2.1-24Thistablehasbeenrenumberedto2.1-38 2.1-25Thistablehasbeendeleted 2.1-26Thistablehasbeenrenumberedto2.1-40 2.1-27Thistablehasbeendeleted 2.1-28Thistablehasbeendeleted 2.1-29Thistablehasbeenrenumberedto2.1-43 2.1-30Thistablehasbeenrenumberedto2.1-44 2.1-31Thistablehasbeenrenumberedto2.1-45 2.1-32Thistablehasbeenrenumberedto2.1-46 2.1-33PastPopulationChangesofCountiesWithin20MilesoftheSite 2.1-34PopulationbyResidenceforCountiesWithin20MilesoftheSite 2.1-35PopulationDistribution20100-10MilesDistance(Miles) 2.1-36PopulationDistribution20100-50MilesDistance(Miles) 2.1-37PopulationDistribution20200-10MilesDistance(Miles) 2.1-38PopulationDistribution20200-50MilesDistance(Miles) 2.1-39PopulationDistribution20000-10MilesDistance(Miles) 2.1-40CommunitiesWithin10MilesoftheSite,2000 2.1-41PopulationDistribution20000-50MilesDistance(Miles)

SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xiii2.1-42SeasonalPopulationofCountiesinStudyArea,20002.1-43IndustriesWithin5MilesoftheSite 2.1-44PopulationProjectionsforBerwick,Pennsylvania 2.1-45CumulativePopulationsfor1990and2000 2.1-46CumulativePopulationsfor1990,2000,2010and2020 2.2-1PipelinesWithin5MilesoftheSite 2.2-2ProbabilityofSiteExposurewithAmmonia2.2-3ProbabilityofSiteExposurewithSulfurDioxide2.3-1HurricanesWithin75and150NauticalMilesoftheSusquehannaSitePeriodofRecord1871to19692.3-2ThunderstormDaysforAvoca,PennsylvaniaWilkes-BarreScrantonAirport,PeriodofRecord1956to1974,ValuesareexpressedinDays2.3-3TotalNumberofDaysin5YearsMixingHeights<1500mWindSpeeds<4.0sec-1andNoSignificantPrecipitationForEpisodesLastingatleast2Days2.3-4ThisTableIntentionallyLeftBlank 2.3-5MeanMonthlyValues:SusquehannaSite(1973-1976) 2.3-6LongTermAverageWindSpeedandPrevailingDirectionatWilkes-BarreScrantonAirport,PeriodofRecord:1956-19742.3-7AverageWindSpeedandPrevailingDirectionattheSusquehannaSite,PeriodofRecord(1973-1976)2.3-8WindDirectionPersistence-PasquillA(1973-1976) 2.3-9WindDirectionPersistence-PasquillB(1973-1976) 2.3-10WindDirectionPersistence-PasquillC(1973-1976)

SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xiv2.3-11WindDirectionPersistence-PasquillD(1973-1976)2.3-12WindDirectionPersistence-PasquillE(1973-1976 2.3-13WindDirectionPersistence-PasquillF(1973-1976) 2.3-14WindDirectionPersistence-PasquillG(1973-1976) 2.3-15WindDirectionPersistence-PasquillAll(1973-1976) 2.3-16WindDirectionPersistence-PasquillE,F,&G(1973-1976)2.3-17LongTermTemperature(F)AtWilkes-Barre-ScrantonAirport2.3-18MeanMonthlyTemperature,DewPointTemperatureandRelativeHumidityWilkes-BarreScrantonAirportPeriodofRecord:1956-19742.3-19TemperatureandMoistureDatafortheSusquehannaSite,PeriodofRecord:1973-19762.3-20StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:January1973-19762.3-21StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:February1973-19762.3-22StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:March1973-19762.3-23StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:April1973-19762.3-24StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:May1973-19762.3-25StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:June1973-19762.3-26StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:July1973-1976 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xv2.3-27StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:August1973-19762.3-28StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:September1973-19762.3-29StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:October1973-19762.3-30StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:November1973-19762.3-31StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:December1973-19762.3-32StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:January1973-December19762.3-33LongTermMonthlyPrecipitationData(LiquidEquivalent,InInches)forWilkes-BarreScrantonAirportatAvoca,PA2.3-34ExpectedRainfallbyDurationandRecurrenceIntervalforVicinityofSusquehannaSite(Ref.2.3-20)(Inches)2.3-35ProbableMaximumPrecipitationforVaryingRainfallDurationsandAreas(Ref.2.3-21)(Inches)2.3-36PrecipitationDatafortheSusquehannaSite(InchesofWater)(1973-1976) 2.3-37FrequencyDistributionofPrecipitationDataPeriod:January1973-1976 2.3-38FrequencyDistributionofPrecipitationDataPeriod:February1973-1976 2.3-39FrequencyDistributionofPrecipitationDataPeriod:March1973-1976 2.3-40FrequencyDistributionofPrecipitationDataPeriod:April1973-1976 2.3-41FrequencyDistributionofPrecipitationDataPeriod:May1973-1976 2.3-42FrequencyDistributionofPrecipitationDataPeriod:June1973-1976 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xvi2.3-43FrequencyDistributionofPrecipitationDataPeriod:July1973-19762.3-44FrequencyDistributionofPrecipitationDataPeriod:August1973-1976 2.3-45FrequencyDistributionofPrecipitationDataPeriod:September1973-1976 2.3-46FrequencyDistributionofPrecipitationDataPeriod:October1973-1976 2.3-47FrequencyDistributionofPrecipitationDataPeriod:November1973-1976 2.3-48FrequencyDistributionofPrecipitationDataPeriod:December1973-1976 2.3-49FrequencyDistributionofPrecipitationDataPeriod:January1973-December19762.3-50PrecipitationWindRoseJanuary1973-1976 2.3-51PrecipitationWindRoseFebruary1973-1976 2.3-52PrecipitationWindRoseMarch1973-1976 2.3-53PrecipitationWindRoseApril1973-1976 2.3-54PrecipitationWindRoseMay1973-1976 2.3-55PrecipitationWindRoseJune1973-1976 2.3-56PrecipitationWindRoseJuly1973-1976 2.3-57PrecipitationWindRoseAugust1973-1976 2.3-58PrecipitationWindRoseSeptember1973-1976 2.3-59PrecipitationWindRoseOctober1973-1976 2.3-60PrecipitationWindRoseNovember1973-1976 2.3-61PrecipitationWindRoseDecember1973-1976 2.3-62PrecipitationWindRoseJanuary1973-December1976 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xvii2.3-63HeavyFog(Visibility1/4MileorLess)atAvoca,PA.2.3-64JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassA2.3-65JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassB2.3-66JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassC2.3-67JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassD2.3-68JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassE2.3-69JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassF2.3-70JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassG2.3-71JointFrequency(%)ofWindDirection,WindSpeedandStability,AllStabilityClasses2.3-72MixingHeights(meters) 2.3-73HeightsofMeteorologicalSensors 2.3-74DataRecoveryRates 2.3-75JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003StabilityClass:PasquillA2.3-76JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003StabilityClass:PasquillB SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xviii2.3-77JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillC2.3-78JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillD2.3-79JointWindFrequencyDistributionByStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PaquillE2.3-80JointWindFrequencyDistributionByStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillF2.3-81JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillG2.3-82JointWindFrequencyDistributionbyStabilityClassLowerWindJanuary1,1999throughDecember31,2003,AllClasses2.3-83IntentionallyBlank 2.3-84JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillA2.3-85JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillB2.3-86JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillC2.3-87JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillD2.3-88JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillE2.3-89JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillF2.3-90JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillG SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xix2.3-91JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,AllClasses2.3-92SummaryofShort-TermX/Q(SEC/M3)Resultsat549MEAB 2.3-931999ProbabilityValuesfor1HouratSSESEAB2.3-942000ProbabilityValuesfor1HouratSSESEAB2.3-952001ProbabilityValuesfor1HouratSSESEAB2.3-962002ProbabilityValuesfor1HouratSSESEAB2.3-972003ProbabilityValuesfor1HouratSSESEAB2.3-981999-2003ProbabilityValuesfor1HouratSSESEAB2.3-991999ProbabilityValuesfor1HouratSSESLPZ2.3-1002000ProbabilityValuesfor1HouratSSESLPZ2.3-1012001ProbabilityValuesfor1HouratSSESLPZ2.3-1022002ProbabilityValuesfor1HouratSSESLPZ2.3-1032003ProbabilityValuesfor1HouratSSESLPZ2.3-1041999-2003ProbabilityValuesfor1HouratSSSSLPZ2.3-105SummaryofLong-TermX/G(SEC/M3)Resultsat4827MLPZ 2.3-106DistancesandTerrain/RecirculationCorrectionFactorsforSSES2003LandUseCensusLocations2.3-1071999AverageRelativeConcentration(sec/m 3)andDisposition(m

-2)EstimatesattheSiteBoundary2.3-1082000AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xx2.3-1092001AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1102002AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1112003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1121999-2003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1131999AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1142000AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1152001AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1162002AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1172003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1181999-2003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary.2.3-1191999AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1202000AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1212001AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1222002AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxi2.3-1232003AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1241999-2003AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1251999AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1262000AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1272001AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1282002AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1292003AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1301999-2003AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1311999AtmosphericDispersionEstimatesatSelectedLocations 2.3-1322000AtmosphericDispersionEstimatesatSelectedLocationsl 2.3-1332001AtmosphericDispersionEstimatesatSelectedLocations 2.3-1342002AtmosphericDispersionEstimatesatSelectedLocations 2.3-1352003AtmosphericDispersionEstimatesatSelectedLocations 2.3-1361999-2003AtmosphericDispersionEstimatesatSelectedLocations 2.3-137SSESRelativeConcentrationsNoDecay,UndepletedX/Q(sec/m 3)X/QAccumulationforGroundAverageforthePeriodof01/01/99through12/31/03 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxii2.3-138SSESRelativeConcentrations2.26-DayDecay,UndepletedX/Q(sec/m 3)forGroundDecayedSectorAverageforthePeriodof01/01/99through12/31/032.3-139SSESRelativeConcentrations8-DayDecay,DepletedX/Q(sec/m 3)forGroundDecayedSectorAverageforthePeriodof01/01/99through12/31/032.3-140SSESRelativeDepositionD/Q(m

-2)forthePeriodof01/01/99through12/31/032.4-1ExistingandProposedDamsLocatedintheSusquehannaRiverBasin(ChemungRiverBasin)2.4-2MinorUpstreamDamsandReservoirs 2.4-3WaterUsers 2.4-4HistoricFloodsintheVicinityoftheSusquehannaSteamElectricStation.

2.4-5All-Season24-HourProbableMaximumPrecipitation 2.4-6ProbableMaximumPrecipitationforDurationsLessThan30Min.

2.4-7PeakRunoffRatesfromandMaximumPondingDepthsonRoofsofSafetyRelatedStructuresforLocalAll-SeasonPMP2.4-8Adopted4-HourUnitHydrographsandCharacteristics.

2.4-9SusquehannaRiverBasinRoutingCoefficients 2.4-10Manning"N"ValuesComputedfrom1936Flood 2.4-11SusquehannaRiverFreezeOveratHarrisburg(1870-1955) 2.4-12IceJamFlooding 2.4-13SummaryofFloodRoutingStudies-SprayPond 2.4-14ResultsofWindWaveComputation SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxiii2.4-15MaximumLoadingsResultingfromWind-WaveActivities2.4-16MaximumHydrodynamicLoadingResultingfromEarthquake 2.4-17ThisTablehasbeenDeleted 2.4-18ESWCoolingDutyonSimultaneousLossofAllAuxiliaryPowertoBothUnits2.4-19ThisTableHasBeenDeleted 2.4-20ThisTableHasBeenDeleted 2.4-21RegionalHydrogeologicSection(within20-mileradiusofSusquehannaSES)2.4-22WaterWellDataWithinTwoMilesoftheStation 2.4-23SpringDataWithinTwoMilesoftheStation 2.4-24DataforMajorWaterWells,OtherThanPublicWells,locatedBetween2and10MilesFromtheStation2.4-25DataforPublicSupplyWellsLocatedBetween2and20MilesfromtheStation2.4-26EstimatedGroundwaterWithdrawalin1976WithinTwoMilesoftheStation 2.4-27ProjectionsofFutureGroundwaterWithdrawalWithin2and20MilesoftheStation2.4-28MajorGroundwaterWithdrawal,andPopulationServedbyWaterSupplyCompaniesWithin20-MileArea2.4-29EstimationofTotalGroundwaterWithdrawalin1975Within20MileRadiusoftheStation2.4-30DetailsoftheConstructionofObservationWellsattheSusquehannaSES 2.4-31GroundwaterLevelDataTakenatSusquehannaSES1972through1975 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxiv2.4-32GroundwaterLevelDataTakenatSusquehannaSESin1976and19772.4-33SummaryofPermeabilityTestsofOverburdenandUpperBedrockattheSusquehannaSESPerformedDuringPreviousInvestigations2.4-34SummaryofPermeabilityTestsofOverburdenandUpperBedrockattheSusquehannaSESPerformedforThisInvestigation2.4-35RadionuclideContentoftheTankPostulatedtoRupture-ReactorWaterCleanup(RWCU)PhaseSeparatorTanks-SusquehannaSES2.4-36GroundwaterParameterValuesUsedforSLUG3DSimulationsAccidentAnalysisforSusquehannaSES2.4-37RangeofParameterValuesusedinCalibratedNumericalModelofBuriedValleyAquiferNorthernSideofSusquehannaSES2.4-38EstimatedPeakConcentrationofRadionuclidesinGroundwaterResultingfromPostulatedRuptureofRWCUPhaseSeparatorTank-ResultsofSimulationswithSLUG3DModel-SusquehannaSES2.4-39EstimatedPeakConcentrationofRadionuclidesinGroundwaterinBuriedValleyAquiferResultingfrompostulatedRuptureofRWCUPhaseSeparatorTank-ResultsofSimulationswithSLUG3DModel-SusquehannaSES2.5-1ModifiedMercalliIntensity(Damage)Scale(Abridged) 2.5-2Earthquakelist 2.5-3UnconfinedCompressiveStrengthsofFoundationRock(MahantangoFormation)2.5-4LaboratoryMeasurementsofP-WaveSeismicVelocitiesonRockCorestakenfromReactorandTurbineBuildingAreas2.5-5RepresentativeEngineeringPropertiesofUnweatheredFoundationRockforPrincipalPlantStructures2.5-6P-WaveandS-WaveVelocitiesandComputedDynamicModuli,SprayPondArea SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxv2.5-7Cross-HoleSeismicVelocities,ReactorArea2.5-8ResultsofSettlementMeasurementsTakenonESSWPumphouseBasemat2.5-9SprayPondWaterLevelElevations 2.5-10PermeabilitiesMeasuredinSprayPond 2.5-11PermeabilitiesMeasuredNeartheRailroadBridge 2.5-12CirculationLossesinDrillHolesinSprayPond 2.5-13SoilTestResultsSummary 2.5-14SprayPondSummaryofCyclicConsolidated-UndrainedTriaxial(CR)Tests 2.5-15DesignParametersforSprayPondLiner 2.5-16SprayPond,SummaryofLiquefactionAnalysis 2.5-17EffectofVaryingStandardRelationshipofEffectiveStrainwithDampingandModuliforProfile2,GWT-6652.5-18SprayPondFactorofSafetyasObtainedUsingDifferentEarthquakes 2.5-19ProbableSettlementDuringEarthquake SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxvi2.1-1FigureRenumberedfrom2.1-1to2.1-112.1-2FigureRenumberedfrom2.1-2to2.1-12 2.1-3FigureRenumberedfrom2.1-3to2.1-13 2.1-4FigureRenumberedfrom2.1-4to2.1-14 2.1-5FigureRenumberedfrom2.1-5to2.1-15 2.1-6FigureRenumberedfrom2.1-6to2.1-16 2.1-7FigureRenumberedfrom2.1-7to2.1-17 2.1-8FigureRenumberedfrom2.1-8to2.1-18 2.1-9FigureRenumberedfrom2.1-9to2.1-19 2.1-10FigureRenumberedfrom2.1-10to2.1-20 2.1-11FigureRenumberedfrom2.1-11to2.1-21 2.1-12FigureRenumberedfrom2.1-12to2.1-22 2.1-13FigureRenumberedfrom2.1-13to2.1-27 2.1-14FigureRenumberedfrom2.1-14to2.1-28 2.1-15FigureRenumberedfrom2.1-15to2.1-23 2.1-16FigureRenumberedfrom2.1-16to2.1-24 2.1-17FigureRenumberedfrom2.1-17to2.1-25 2.1-18FigureRenumberedfrom2.1-18to2.1-26 2.1-19Thisfigurehasbeendeleted 2.1-20Thisfigurehasbeendeleted 2.1-21SiteVicinityMap SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxvii2.1-22SiteAreaMap2.1-23PopulationDistribution0-10Miles,2010 2.1-24PopulationDistribution0-50Miles,2010 2.1-25PopulationDistribution0-10Miles,2020 2.1-26PopulationDistribution0-50Miles,2020 2.1-27SeasonalPopulation0-10Miles,2000 2.1-28SeasonalPopulation0-50Miles,2000 2.2-1MajorTransportationRoutesandPipelines 2.2-2AirportandAirlineRouteMap 2.2-3PipelineBreakatElevation700',SteadyStateBreakFlow 2.2-4PipelineBreakatElevation600',SteadyStateBreakFlow 2.3-1TornadoOccurrenceandIntensityinSusquehannaRegion 2.3-2TP25RainfallIntensity-DurationFrequencyCurvesUSDCWB,1955 2.3-3TopographyWithin5Miles 2.3-4-1MaximumTerrainElevationVersusDistanceBySector 2.3-4-2MaximumTerrainElevationVersusDistanceBySector 2.3-4-3MaximumTerrainElevationVersusDistanceBySector 2.3-4-4MaximumTerrainElevationVersusDistanceBySector 2.3-4-5MaximumTerrainElevationVersusDistanceBySector 2.3-4-6MaximumTerrainElevationVersusDistanceBySector SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxviii2.3-4-7MaximumTerrainElevationVersusDistanceBySector2.3-4-8MaximumTerrainElevationVersusDistanceBySector 2.3-5SchematicofInstrumentation 2.3-6OneHourDirectionIndependentX/QattheEAB(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.3-7OneHourDirectionDependentX/QValuesattheEAB(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.3-8OneHourDirectionDependentX/QValuesattheLPZ(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.3-9OneHourDirectionIndependentX/QattheLPZ(WeightedAverageof1999,2000,2001,2002and2003Calculations2.3-10InterpolatedX/QValuesattheLPZ(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.4-1Thisfigurehasbeendeleted 2.4-2Thisfigurehasbeendeleted 2.4-3PlantCompleteShowingStormDrainPipeLayout 2.4-4SusquehannaRiverBasin 2.4-5StageDischargeCurveatLowFlows 2.4-6StageDischargeCurve,DischargeRange1000-37,000CFS 2.4-7WaterUsersontheSusquehannaRiver 2.4-8StageDischargeCurvesatPlantSite 2.4-9FloodProfilesontheSusquehannaRiverattheSite 2.4-10GeneralSiteDrainagePlan SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxix2.4-11SiteDrainageLocationsA&B2.4-12SiteDrainageLocationsC&D 2.4-13SiteDrainageLocationsE&F 2.4-14ProbableMaximumPrecipitationStormPatternandOutlineofSub-Basins,SusquehannaRiveraboveWilkes-Barre,Pennsylvania2.4-15ProbableMaximumPrecipitationonSusquehannaRiverBasinandProbableMaximumFloodHydrographatWilkes-Barre,Pennsylvania2.4-16MapoftheSusquehannaRiver,RiverMiles150-170 2.4-17StageDischargeCurveatSection2-BerwickBridge 2.4-18RiverandWaterSurfaceProfilesofSusquehannaRiverinVicinityofSite 2.4-19CrossSectionsattheEightRiverSectionsNeartheSite 2.4-20CrossSectionofRiveratthePlantSite 2.4-21WindFetch,SusquehannaRiverPMF 2.4-22TiogaDamandHammondDamReservoirAreasandSections 2.4-23SurfaceDrainagePatternsaroundtheSprayPond 2.4-24SprayPondInflowandOutflowHydrograph 2.4-25SprayPondOutletRatingCurves 2.4-26SprayPondElevationAreaStorageCapacityCurves 2.4-27SprayPondEmergencySpillwayWaterSurfaceProfile 2.4-28SprayPondDesignSpectrumforSSE 2.4-29SprayPondDesignSpectrumforOBE 2.4-30DurationCurvesofDailyDischarge SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxx2.4-31TimeofTravel,SusquehannaRiverShickshinnytoDanv ille2.4-32MapofSusquehannaSESShowingGroundwaterContoursinSeptember19772.4-33HydrogeologicCrossSectionfromWesttoEastAlongGroundwaterFlowPathattheSusquehannaSES2.4-34BedrockGeologicMapofAreaWithin20MilesofSusquehannaSES 2.4-35MajorPleistoceneSandandGravelDepositsWithin20MilesofSusquehannaSES2.4-36GeologicMapofAreaWithinTwoMilesoftheStation 2.4-37WaterWellsWithinTwoMilesoftheStation 2.4-38SpringsUsedforWaterSupplyWithinTwoMilesoftheStation 2.4-39MajorWaterWellsTwotoTenMilesfromtheStation,ExceptingPublicSupplyWells2.4-40PublicSupplyWellsTwotoTwentyMilesfromtheStation 2.4-41MapofSusquehannaSESShowingIsopachContoursofOverburdenThickness2.4-42MapofSusquehannaSESShowingTop-of-BedrockContours 2.4-43MapofSusquehannaSESShowingGroundwaterContoursinApril1977 2.4-44LogofBoringandObservationWellConstructionDetails-1200,1200A 2.4-45LogofBoringandObservationWellConstructionDetails-1201 2.4-46LogofBoringandObservationWellConstructionDetails-1204 2.4-47LogofBoringandObservationWellConstructionDetails-1208 2.4-48LogofBoringandObservationWellConstructionDetails-1209A SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxi2.4-49LogofBoringandObservationWellConstructionDetails-12102.4-50MapofSusquehannaSESShowingGroundwaterContoursinJune1971 2.4-51DrawdownCurvesfromPumpingTestsofObservationWells1204and1210 2.4-52RiverIntakeStructure 2.4-53RiverDischargeDiffuser 2.4-54ThisFigureHasBeenReplacedbyDWG.A-12.Sh.1 2.4-54aThisFigureHasBeenDeleted 2.4-55ThisFigureHasBeenReplacedbyDWG.FF62005,Sh.1 2.5-1SiteLocation 2.5-2RegionalPhysiographicMap 2.5-3RegionalGeologicMap 2.5-4LocationofAppalachianBasin 2.5-5RegionalIsopachMaps 2.5-6StratigraphicColumns 2.5-7RegionalTectonicMap 2.5-8aEarthquakeEpicentersandTectonicProvinceBoundariesintheSiteRegion 2.5-8bEarthquakeEpicentersWithin200MilesoftheSite 2.5-9BouguerGravityAnomalyMap 2.5-10GeologicMapoftheBloomsburg-BerwickArea 2.5-11RegionalLandsatLineaments SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxii2.5-12SiteGeologicMap2.5-13PhotographofGeologicFeatureFoundinTurbineBuildingExcavation 2.5-14SiteVicinityGeologicColumn 2.5-15GeologicMapofSprayPondArea 2.5-16ThisFigureHasBeenDeleted 2.5-17ContoursonTopofBedrockSurface 2.5-17aExtentofRockandSoilFoundations 2.5-18GeologicMapofFoundationExcavation 2.5-19GeologicSectionThroughFoundationExcavations 2.5-20aPhotographofGeologicFeaturesExposedinExcavations 2.5-20bPhotographofGeologicFeaturesExposedinExcavations 2.5-20cPhotographofGeologicFeaturesExposedinExcavations 2.5-20dPhotographofGeologicFeaturesExposedinExcavations 2.5-20ePhotographofGeologicFeaturesExposedinExcavations 2.5-20fPhotographofGeologicFeaturesExposedinExcavations 2.5-20gPhotographofGeologicFeaturesExposedinExcavations 2.5-21aSiteGeologicCrossSections 2.5-21bSiteGeologicCrossSections 2.5-22PlotPlan 2.5-22aPlotPlanDetails 2.5-23aLogofBorings SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxiii2.5-23bLogofBorings2.5-23cLogofBorings 2.5-23dLogofBorings 2.5-23eLogofBorings 2.5-23fLogofBorings 2.5-23gLogofBorings 2.5-23hLogofBorings 2.5-23iLogofBorings 2.5-23jLogofBorings 2.5-23kLogofBorings 2.5-23lLogofBorings 2.5-23mLogofBorings 2.5-23nLogofBorings 2.5-23oLogofBorings 2.5-23pLogofBorings 2.5-23qLogofBorings 2.5-23rLogofBorings 2.5-23sLogofBorings 2.5-23tLogofBorings 2.5-24FinalPlantGrades SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxiv2.5-25TectonicMapofAnthraciteRegion2.5-26GeologicSectionofAnthraciteRegion 2.5-27DesignResponseSpectra-SafeShutdownEarthquake 2.5-28DesignResponseSpectra-OperatingBasisEarthquake 2.5-29GeophysicalSurveys 2.5-30SprayPond-GeneralizedCross-Sections 2.5-30aDieselGenerator'E'FuelTank-GeneralizedCross-Sections 2.5-31SprayPond,RangeofGrainSizeCurves 2.5-32RelativeDensityRelatedtoNValueatESSWPumphouseSite 2.5-33"N"ValueVersusElevationatESSWPumphouseSite 2.5-34SprayPond,ConsolidatedDrainedTriaxialTest-MohrCircleDiagram 2.5-35SprayPond,SummaryofCyclicShearTest(CR)Results 2.5-36SprayPond,ShearWaveVelocityDesignCurves 2.5-37LocationandLimitsofExcavationFillandBackfillforClass1Structures 2.5-38LocationofSprayPondwithContoursonTopofRockandWaterTable 2.5-39LateralSoilPressureDiagrams 2.5-40SprayPond,MeasuredandProjectedWaterLevels 2.5-41DetailsofSettlementPinsCastinESSWPumphouseBasemat 2.5-42SprayPond,EarthworkPlan 2.5-43ThisFigureHasBeenReplacedbyDWG.C-63,Sh.1 2.5-44SprayPond,BoringandTestPitsLocationPlan SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxv2.5-45SprayPond,GeneralizedCrossSectionswithLaboratoryTestLocations2.5-46SprayPond,RelativeDensityRelatedto"N"Value 2.5-47SprayPond,RelationshipBetweenSeepageLossandMaximumGroundwaterElevation2.5-48SprayPond,SoilProfilesUsedinLiquefactionAnalysis 2.5-49SprayPond,FactorofSafetyVariationwithGroundwaterTableandDepth 2.5-50SprayPond,MinimumFactorofSafetyAgainstLiquefactionAtSelectedLocations2.5-50AVariationFactorofSafety(F.S)vsChangeofDampingRatio 2.5-51SprayPond,ComparisonofFactorsofSafetyforLiquefactionfortheDesignEarthquakeandSomeRealEarthquakes2.5-52SprayPond,ComparisonofAverageCycleStressAsInducedbyDesignEarthquakeandSomeRealEarthquakes2.5-53SprayPond,AverageShearVariationwithDepth 2.5-54SprayPond,SummaryofPorePressureBuildup 2.5-55SiteWaterTableMap(Preconstruction) 2.5-56ProfileofSlopeNorthofSprayPond 2.5-57SprayPondRelationshipBetweenLinerThickness,LinerPermeabilityandSeepageLoss2.5-58DampingRatioVersusShearStrainofSandinLiquefactionAnalysis 2.5-59SampleLocationsofSoilDensityTests 2.5-60StatisticalAnalysisofFieldDensityTestResults 2.5-61StatisticalAnalysisofSand-Cement-FlyashBeddingandBackfill SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxvi2.5-62ESSWPumphouseFloorPlanEl.685'-6" SSES-FSARTOCRev.62FSARRev.653-iCHAPTER3DESIGNOFSTUCTURES,COMPONENTS,EQUIPMENTSYSTEMSTABLEOFCONTENTSTEXTSectionTitle3.1CONFORMANCEWITHNRCGENERALDESIGNCRITERIA3.1.1SummaryDescription3.1.2CriterionConformance3.1.2.1OverallRequirements(Group1)3.1.2.1.1QualityStandards&Records(Criterion1)3.1.2.1.2DesignBasisforProtectionAgainstNaturalPhenomena(Criterion2)3.1.2.1.3FireProtection(Criterion3)3.1.2.1.4EnvironmentalandDynamicEffectsDesignBases(Criterion4)3.1.2.1.5SharingofStructures,Systems&Components(Criterion5)3.1.2.2ProtectionbyMultipleFissionProductBarriers(GroupII)3.1.2.2.1ReactorDesign(Criterion10)3.1.2.2.2ReactorInherentProtection(Criterion11)3.1.2.2.3SuppressionofReactorPowerOscillations(Criterion12)3.1.2.2.4InstrumentationandControl(Criterion13)3.1.2.2.5ReactorCoolantPressureBoundary(Criterion14)3.1.2.2.6ReactorCoolantSystemDesign(Criterion15)3.1.2.2.7ContainmentDesign(Criterion16)3.1.2.2.8ElectricPowerSystems(Criterion17)3.1.2.2.9InspectionandTestingofElectricPowerSystems(Criterion18)3.1.2.2.10ControlRoom(Criterion19)3.1.2.3Protection&ReactivityControlSystems(GroupIII)3.1.2.3.1ProtectionSystemFunctions(Criterion20)3.1.2.3.2ProtectionSystemReliabilityandTestability(Criterion2l)3.1.2.3.3ProtectionSystemIndependence(Criterion22)3.1.2.3.4ProtectionSystemFailureModes(Criterion23)3.1.2.3.5SeparationofProtectionandControlSystems(Criterion24)3.1.2.3.6ProtectionSystemRequirementsforReactivityControlMalfunctions(Criterion25)3.1.2.3.7ReactivityControlSystemRedundancyandCapability(Criterion26)3.1.2.3.8CombinedReactivityControlSystemsCapability(Criterion27)3.1.2.3.9ReactivityLimits(Criterion28)3.1.2.3.10ProtectionAgainstAnticipatedOperationalOccurrences(Criterion29)3.1.2.4FluidSystems(GroupIV)3.1.2.4.1QualityofReactorCoolantPressureBoundary(Criterion30)

SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-ii3.1.2.4.2FracturePreventionofReactorCoolantPressureBoundary(Criterion31)3.1.2.4.3InspectionofReactorCoolantPressureBoundary(Criterion32)3.1.2.4.4ReactorCoolantMakeup(Criterion33)3.1.2.4.5ResidualHeatRemoval(Criterion34)3.1.2.4.6EmergencyCoreCooling(Criterion35)3.1.2.4.7InspectionofEmergencyCoreCoolingSystem(Criterion36)3.1.2.4.8TestingofEmergencyCoreCoolingSystem(Criterion37)3.1.2.4.9ContainmentHeatRemoval(Criterion38)3.1.2.4.10InspectionofContainmentHeatRemovalSystem(Criterion39)3.1.2.4.11TestingofContainmentHeatRemovalSystem(Criterion40)3.1.2.4.12ContainmentAtmosphereCleanup(Criterion41)3.1.2.4.13InspectionofContainmentAtmosphereCleanupSystems(Criterion42)3.1.2.4.14TestingofContainmentAtmosphereCleanupSystems(Criterion43)3.1.2.4.15CoolingWater(Criterion44)3.1.2.4.16InspectionofCoolingWaterSystem(Criterion45)3.1.2.4.17TestingofCoolingWaterSystem(Criterion46)3.1.2.5ReactorContainment(GroupV)3.1.2.5.1ContainmentDesignBasis(Criterion50)3.1.2.5.2FracturePreventionofContainmentPressureBoundary(Criterion51)3.1.2.5.3CapabilityforContainmentLeakageRateTesting(Criterion52)3.1.2.5.4ProvisionsforContainmentTesting&Inspection(Criterion53)3.1.2.5.5PipingSystemsPenetratingContainment(Criterion54)3.1.2.5.6ReactorCoolantPressureBoundaryPenetratingContainment(Criterion55)3.1.2.5.7PrimaryContainmentIsolation(Criterion56)3.1.2.5.8ClosedSystemIsolationValves(Criterion57)3.1.2.6FuelandRadioactivityControl(GroupVI)3.1.2.6.1ControlofReleaseofRadioactiveMaterialstotheEnvironment(Criterion60)3.1.2.6.2FuelStorageandHandlingandRadioactivityControl(Criterion61)3.1.2.6.3PreventionofCriticalityinFuelStorageandHandling(Criterion62)3.1.2.6.4MonitoringFuelandWasteStorage(Criterion63)3.1.2.6.5MonitoringRadioactivityReleases(Criterion64)3.2CLASSIFICATIONOFSTRUCTURES,COMPONENTSANDSYSTEMS 3.2.1SeismicClassification 3.2.2SystemQualityGroupClassification SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-iii3.2.2.1QualityGroupD(Augmented)3.2.3SystemSafetyClassifications 3.2.3.1SafetyClass13.2.3.1.1DefinitionofSafetyClass13.2.3.2SafetyClass23.2.3.2.1DefinitionofSafetyClass23.2.3.3SafetyClass33.2.3.3.1DefinitionofSafetyClass33.2.3.4OtherStructures,SystemsandComponents3.2.3.4.1DefinitionofOtherStructures,Systems,andComponents3.2.3.4.2DesignRequirementsforOtherStructures,SystemsandComponents3.2.4QualityAssurance 3.2.5CorrelationofSafetyClasseswithIndustryCodes 3.3WINDANDTORNADOLOADINGS 3.3.1WindLoadings 3.3.1.1DesignWindVelocity3.3.1.2DeterminationofAppliedForces3.3.2TornadoLoadings 3.3.2.1ApplicableDesignParameters3.3.2.2DeterminationofForcesonStructures3.3.2.3EffectofFailureofStructuresorComponentsNotDesignedforTornado Loads3.3.2.4Safety-RelatedEquipmentNotProtectedByReinforcedConcrete3.3.3References 3.4WATERLEVEL(FLOOD)DESIGN SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-iv3.5MISSILEPROTECTION3.5.1MissileSelectionandDescription 3.5.1.1InternallyGeneratedMissiles(OutsidePrimaryContainment)3.5.1.1.1RotatingComponentFailureMissiles3.5.1.1.2PressurizedComponentFailureMissiles3.5.1.2InternallyGeneratedMissiles(InsideContainment)3.5.1.2.1RotatingComponentFailureMissiles3.5.1.2.2PressurizedComponentFailureMissiles3.5.1.2.3GravitationallyGeneratedMissiles3.5.1.3TurbineMissiles3.5.1.3.1TurbinePlacementandOrientation3.5.1.3.2MissileIdentificationandCharacteristics3.5.1.3.3ProbabilityAnalysis3.5.1.4MissilesGeneratedbyNaturalPhenomena3.5.1.5SiteProximityMissiles3.5.1.6AircraftHazards3.5.1.6.1AirportOperations3.5.1.6.2AircraftCrashProbability3.5.1.6.3CriticalTargetAreaforthePlant3.5.1.6.4StrikingProbabilities3.5.2SystemstobeProtected 3.5.2.1MissileProtectionDesignPhilosophy3.5.2.2StructuresDesignedtoWithstandMissileEffects3.5.3BarrierDesignProcedures 3.5.4References 3.6PROTECTIONAGAINSTDYNAMICEFFECTSASSOCIATEDWITHTHEPOSTULATEDRUPTUREOFPIPING3.6.1PostulatedPipingFailuresinFluidSystems 3.6.1.1DesignBases3.6.1.2Description3.6.1.2.1MainSteamSystem SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-v3.6.1.2.2FeedwaterSystem3.6.1.2.3HighPressureCoolantInjection(HPCI)System3.6.1.2.4ReactorCoreIsolationCooling(RCIC)System3.6.1.3SafetyEvaluation3.6.2DeterminationofPipeFailureLocationsandDynamicEffectsAssociatedwiththePostulatedPipingFailure3.6.2.1CriteriaUsedtoDeterminePipeBreakandCrackLocationsandtheirConfigurations3.6.2.1.1HighEnergyFluidSystemPipingOtherThanRecirculationSystemPiping3.6.2.1.2ModerateEnergyFluidSystemPipingOtherRecirculationPipingSystem3.6.2.1.3TypesofBreaksandLeakageCracksinFluidSystemPipingOtherThanRecirculationPipingSystem3.6.2.1.4CriteriaforRecirculationSystemPiping(NSSSSupply)3.6.2.1.4.1DefinitionofHighEnergyFluidSystem3.6.2.1.4.2DefinitionofModerateEnergyFluidSystem3.6.2.1.4.3PostulatedPipeBreaks3.6.2.1.4.4ExemptionsfromPipeWhipProtectionRequirements3.6.2.1.4.5LocationforPostulatedPipeBreaks3.6.2.1.4.6TypesofBreakstobePostulatedinFluidSystemPiping3.6.2.1.5HighEnergyFluidSystemsWithandWithoutSufficientCapacitytoDevelopaJetStream3.6.2.2AnalyticalModelstoDefineForcingFunctionsandResponseModels3.6.2.2.1ForPipingOtherThanRecirculationPipingSystem3.6.2.2.2AnalyticMethodstoDefineBlowdownForcingFunctionsandResponseModelsforRecirculationPipingSystem(NSSSSupply)3.6.2.2.2.1AnalyticalMethodstoDefineBlowdownForcingFunctions3.6.2.2.2.2PipeWhipDynamicResponseAnalysesforRecirculationPipingSystem3.6.2.3DynamicAnalysisMethodstoVerifyIntegrityandOperability3.6.2.3.1ForPipingOtherThanRecirculationPipingSystem3.6.2.3.1.1DesignLoadingCombinations3.6.2.3.1.2DesignStressLimits3.6.2.3.2DynamicAnalysisMethodstoVerifyIntegrityandOperabilityforRecirculationPipingSystem(NSSSSupply)3.6.2.3.2.1JetImpingementAnalysesandEffectsonSafetyRelatedComponentsResultingfromPostulatedRupturesoftheRecirculationPipingSystem SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-vi3.6.2.3.2.2PipeWhipEffectsFollowingaPostulatedRuptureoftheRecirculationSystemPiping3.6.2.3.2.3LoadingCombinationsandDesignCriteriaforRecirculationPipingPipeWhipRestraints3.6.2.4GuardPipeAssemblyDesignCriteria3.6.2.5MaterialtobeSubmittedforOperatingLicenseReview3.6.2.5.1ForPipingOtherThanRecirculationPipingSystem3.6.2.5.2ImplementationofCriteriaforPipeBreakandCrackLocationandOrientationforRecirculationPipingSystem(NSSSSUPPLY)3.6.2.5.2.1PostulatedPipeBreaksinRecirculationPipingSystem-InsideContainment3.6.2.5.2.2ImplementationofSpecialProtectionCriteria3.6.2.5.2.3JetEffectsforPostulatedRupturesofRecirculationSystemPiping3.6.3Definitions 3.6.4References 3.6APIPEBREAKOUTSIDECONTAINMENT

SUMMARY

OFANALYSISANDRESULTS3.7aSEISMICDESIGN 3.7a.1SeismicInput 3.7a.1.1DesignResponseSpectra3.7a.1.2DesignTimeHistory3.7a.1.3CriticalDampingValues3.7a.1.4SupportingMediaforSeismicCategoryIStructures3.7a.2SeismicSystemAnalysis 3.7a.2.1SeismicAnalysisMethods3.7a.2.1.1TheEquationsofDynamicEquilibrium3.7a.2.1.2SolutionoftheEquationsofMotionbyModeSuperposition3.7a.2.1.3AnalysisbyResponseSpectrum3.7a.2.1.4SupportDisplacementsinMulti-SupportedStructure3.7a.2.1.5DynamicAnalysisofSeismicCategoryIStructures,Systems,andComponents3.7a.2.1.5.1DynamicAnalysisofPipingSystems SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-vii3.7a.2.1.5.2DynamicAnalysisofEquipment3.7a.2.1.5.2.1DifferentialSeismicMovementofInterconnectedComponents3.7a.2.1.6SeismicQualificationbyTesting3.7a.2.2NaturalFrequenciesandResponseLoads3.7a.2.3ProcedureUsedforModeling3.7a.2.3.1ModelingTechniquesforSeismicCategoryIStructures,Systems,andComponents3.7a.2.3.2ModelingofReactorPressureVesselandInternals3.7a.2.3.3ComparisonofResponses3.7a.2.4SoilStructureInteraction3.7a.2.5DevelopmentofFloorResponseSpectra3.7a.2.6ThreeComponentsofEarthquakeMotion3.7a.2.7CombinationofModelResponses3.7a.2.8InteractionofNon-CategoryIStructureswithSeismicCategoryIStructures3.7a.2.9EffectsofParameterVariationsonFloorResponseSpectra3.7a.2.10UseofConstantVerticalStaticFactors3.7a.2.11MethodsUsedtoAccountforTorsionalEffects3.7a.2.12ComparisonofResponses3.7a.2.13MethodsforSeismicAnalysisofDams3.7a.2.14DeterminationofSeismicCategoryIStructureOverturningMoments3.7a.2.15AnalysisProcedureforDamping3.7a.3SeismicSubsystemAnalysis 3.7a.3.1SeismicAnalysisMethods3.7a.3.2DeterminationofNumberofEarthquakeCycles3.7a.3.3ProcedureUsedforModeling3.7a.3.3.1ModelingofPipingSystems3.7a.3.3.2ModelingofEquipment3.7a.3.3.3LocationofSupportsandRestraints3.7a.3.4BasisofSelectionofFrequencies3.7a.3.5UseofEquivalentStaticLoadMethodofAnalysis3.7a.3.6ThreeComponentsofEarthquakeMotion3.7a.3.6.1ResponseSpectrumMethod3.7a.3.6.2TimeHistoryMethod3.7a.3.7CombinationofModalResponses3.7a.3.8AnalyticalProcedureforPiping3.7a.3.9MultiplySupportedEquipmentandComponentswithDistinctInputs3.7a.3.10UseofConstantVerticalStaticFactors SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-viii3.7a.3.11TorsionalEffectsofEccentricMasses3.7a.3.12BuriedSeismicCategoryIPipingSystemsandTunnels3.7a.3.13InteractionofOtherPipingwithSeismicCategoryIPiping3.7a.3.14SeismicAnalysisforReactorInternals3.7a.3.15AnalysisProceduresforDamping3.7a.4SeismicInstrumentation 3.7a.5References 3.7bSEISMICDESIGN 3.7b.1SeismicInput 3.7b.1.1DesignResponseSpectra3.7b.1.2DesignTimeHistory3.7b.1.3CriticalDampingValues(Non-NSSS)3.7b.1.4SupportingMediaforSeismicCategoryIStructures3.7b.2SeismicSystemAnalysis 3.7b.2.1SeismicAnalysisMethods3.7b.2.1.1FlexibleBaseandFixedBaseContainmentModels3.7b.2.2NaturalFrequenciesandResponseLoads3.7b.2.3ProcedureUsedforModeling3.7b.2.4SoilStructureInteraction3.7b.2.5DevelopmentofFloorResponseSpectra3.7b.2.6ThreeComponentsofEarthquakeMotion3.7b.2.7CombinationofModalResponses3.7b.2.8InteractionofNon-CategoryIStructuresWithSeismicCategoryIStructures3.7b.2.9EffectsofParameterVariationsonFloorResponseSpectra3.7b.2.10UseofConstantVerticalStaticFactors3.7b.2.11MethodsUsedtoAccountforTorsionalEffects3.7b.2.11.1TorsionalAnalysisofDieselGeneratorBuildingA-D&ESSWPumphouse3.7b.2.11.2TorsionalAnalysisoftheReactor/ControlBuilding3.7b.2.12ComparisonofResponses3.7b.2.13MethodsforSeismicAnalysisofDams3.7b.2.14DeterminationofSeismicCategoryIStructureOverturningMoments SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-ix3.7b.2.15AnalysisProcedureforDamping3.7b.3SeismicSubsystemAnalysis 3.7b.3.1SeismicAnalysisMethods3.7b.3.1.1Equipment3.7b.3.1.1.1Analysis3.7b.3.1.1.2DynamicTesting3.7b.3.1.1.3CombinationofAnalysisandDynamicTesting3.7b.3.1.2PipingSystems3.7b.3.1.3ClassIECableTrays3.7b.3.1.4SupportsforSeismicCategoryIHVACDucts3.7b.3.1.5ConcreteBlockMasonryStructures(Blockwalls)3.7b.3.1.6SupportsofSeismicCategoryIElectricalRacewaySystems3.7b.3.1.6.1LoadingCombinations3.7b.3.1.6.2AnalyticalTechniques3.7b.3.1.6.3Damping3.7b.3.1.6.4OperatingBasisEarthquake(OBE)3.7b.3.2DeterminationofNumberofEarthquakeCycles3.7b.3.3ProcedureUsedforModeling3.7b.3.4BasisforSelectionofFrequencies3.7b.3.5UseofEquivalentStaticLoadMethodofAnalysis3.7b.3.6ThreeComponentsofEarthquakeMotion3.7b.3.7CombinationofModalResponses3.7b.3.8AnalyticalProceduresforPiping3.7b.3.9MultipleSupportedEquipmentandComponentswithDistinctInputs3.7b.3.10UseofConstantVerticalStaticFactors3.7b.3.11TorsionalEffectsofEccentricMasses3.7b.3.12BuriedSeismicCategoryIPipingSystemsandTunnels3.7b.3.13InteractionofOtherPipingWithSeismicCategoryIPiping3.7b.3.14SeismicAnalysisforReactorInternals3.7b.3.15AnalysisProcedureforDamping3.7b.4SeismicInstrumentation 3.7b.4.1ComparisonwithNRCRegulatoryGuide1.12,Rev.13.7b.4.1.1TriaxialTime-HistoryAccelerographs3.7b.4.1.2TriaxialPeakAccelerographs3.7b.4.1.3TriaxialSeismicSwitches3.7b.4.1.4TriaxialResponseRecorders SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-x3.7b.4.2DescriptionofInstrumentation3.7b.4.3ControlRoomOperatorNotification3.7b.4.4ComparisonofMeasuredandPredictedResponses3.7b.5References 3.8DESIGNOFCATEGORYISTRUCTURES 3.8.1ConcreteContainment 3.8.1.1DescriptionoftheContainment3.8.1.1.1General3.8.1.1.1.1Dimensions3.8.1.1.2BaseFoundationSlab3.8.1.1.2.1Reinforcement3.8.1.1.2.2LinerPlateandAnchorages3.8.1.1.2.3PedestalandSuppressionChamberColumnBaseLineAnchorages3.8.1.1.3ContainmentWall3.8.1.1.3.1Reinforcement3.8.1.1.3.2LinerPlateandAnchorages3.8.1.1.3.3Penetrations3.8.1.1.3.4InternalContainmentAttachments3.8.1.1.3.5ExternalContainmentAttachments3.8.1.1.3.6SteelComponentsNotBackedbyStructuralConcrete3.8.1.2ApplicableCodes,Standards,&Specifications3.8.1.3Loads&LoadingCombinations3.8.1.3.1General3.8.1.3.2DescriptionofLoads3.8.1.3.2.1DeadLoad3.8.1.3.2.2LiveLoad3.8.1.3.2.3DesignBasisAccidentPressureLoad3.8.1.3.2.4ThermalLoads3.8.1.3.2.5WindandTornadoLoads3.8.1.3.2.6SeismicLoads3.8.1.3.2.7ExternalPressureLoad3.8.1.3.2.8MissileandPipeRuptureLoads3.8.1.4DesignandAnalysisProcedures3.8.1.4.1General3.8.1.4.2ContainmentWall3.8.1.4.3BaseFoundationSlab SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xi3.8.1.4.4AnalysisofAreasAroundEquipmentHatches3.8.1.4.5LinerPlateandAnchorages3.8.1.5StructuralAcceptanceCriteria3.8.1.5.1ReinforcedConcrete3.8.1.5.1.1WorkingStress3.8.1.5.1.2StrengthMethod3.8.1.5.2LinerPlateandAnchorages3.8.1.6Materials,QualityControl,andSpecialConstructionTechniques3.8.1.6.1ConcreteContainment3.8.1.6.2LinerPlate,Anchorages,andAttachments3.8.1.6.2.1Materials3.8.1.6.2.2Welding3.8.1.6.2.3MaterialsTesting3.8.1.6.2.4NondestructiveExaminationofLinerPlateSeamWelds3.8.1.6.2.5QualityControl3.8.1.6.2.6ErectionTolerances3.8.1.7TestingandIn-ServiceSurveillanceRequirements3.8.1.7.1PreoperationalTesting3.8.1.7.1.1StructuralAcceptanceTest3.8.1.7.1.2LeakRateTesting3.8.1.7.2In-ServiceLeakRateTesting3.8.2ASMEClassMCSteelComponentsoftheContainment 3.8.2.1DescriptionoftheASMEClassMCComponents3.8.2.1.1DrywellHeadAssembly3.8.2.1.2EquipmentHatchesandPersonalLock3.8.2.1.3SuppressionChamberAccessHatches3.8.2.1.4CRDRemovalHatch3.8.2.1.5Penetrations3.8.2.2ApplicableCodes,Standards,andSpecifications3.8.2.3LoadsandLoadingCombinations3.8.2.3.1General3.8.2.3.2DescriptionofLoads3.8.2.3.2.1DeadandLiveLoad3.8.2.3.2.2DesignBasisAccidentPressureLoad3.8.2.3.2.3ExternalPressureLoad3.8.2.3.2.4ThermalLoads3.8.2.3.2.5SeismicLoads3.8.2.3.2.5.1DesignBasisLoads SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xii3.8.2.3.2.6MissileandPipeRuptureLoads3.8.2.4DesignandAnalysisProcedures3.8.2.4.1DrywellHeadAssembly3.8.2.4.2AccessHatches3.8.2.4.3PipeandElectricalPenetrations3.8.2.5StructuralAcceptanceCriteria3.8.2.6Materials,QualityControl,andSpecialConstructionTechniques3.8.2.6.1Materials3.8.2.6.1.1General3.8.2.6.1.2DrywellHeadAssembly3.8.2.6.1.3AccessHatches3.8.2.6.1.4Penetrations3.8.2.6.2Welding3.8.2.6.3MaterialsTesting3.8.2.6.4NondestructiveExaminationofWelds3.8.2.6.5QualityControl3.8.2.6.6ErectionTolerances3.8.2.7TestingandIn-serviceInspectionRequirements3.8.2.7.1PreoperationalTesting3.8.2.7.1.1StructuralAcceptanceTest3.8.2.7.1.2LeakRateTesting3.8.2.7.2In-serviceLeakRateTesting3.8.3ContainmentInternalStructures 3.8.3.1DescriptionoftheInternalStructures3.8.3.1.1DrywellFloor3.8.3.1.2ReactorPedestal3.8.3.1.3ReactorShieldWall3.8.3.1.4SuppressionChamberColumns3.8.3.1.5DrywellPlatforms3.8.3.1.6SeismicTrussandSeismicStabilizer3.8.3.1.7ReactorSteamSupplySystemSupports3.8.3.2ApplicableCodes,Standards,andSpecifications3.8.3.3LoadsandLoadingCombinations3.8.3.3.1General3.8.3.3.2DrywellFloorandReactorPedestal3.8.3.3.2.1DescriptionofLoads3.8.3.3.3ReactorShieldWall3.8.3.3.3.1DescriptionofLoads SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xiii3.8.3.3.4SuppressionChamberColumns3.8.3.3.5DrywellPlatforms3.8.3.3.6SeismicTruss3.8.3.4DesignandAnalysisProcedures3.8.3.4.1DrywellFloor3.8.3.4.2DrywellFloorLinerPlateandAnchorages3.8.3.4.3ReactorPedestal3.8.3.4.4ReactorShieldWall3.8.3.4.5SuppressionChamberColumns3.8.3.4.6DrywellPlatforms3.8.3.4.7SeismicTruss3.8.3.5StructuralAcceptanceCriteria3.8.3.5.1ReinforcedConcrete3.8.3.5.2DrywellFloorLinerPlateandAnchorages3.8.3.5.3StructuralSteel3.8.3.6Materials,QualityControl,andSpecialConstructionTechniques3.8.3.6.1ConcreteContainmentInternalStructures3.8.3.6.2DrywellFloorLinerPlate,Anchorages,Attachments3.8.3.6.2.1Materials3.8.3.6.2.2Welding3.8.3.6.2.3NondestructiveExaminationofLinerPlateSeamWelds3.8.3.6.2.4ErectionTolerances3.8.3.6.3ReactorShieldWallandSeismicTruss3.8.3.6.3.1Materials3.8.3.6.3.2WeldingandNondestructiveExaminationofWelds3.8.3.6.3.3MaterialsTesting3.8.3.6.3.4ErectionTolerances3.8.3.6.4SuppressionChamberColumns3.8.3.6.4.1Materials3.8.3.6.4.2Welding3.8.3.6.4.3NondestructiveExaminationofWelds3.8.3.6.4.4FabricationandErectionTolerances3.8.3.6.5DrywellPlatforms3.8.3.6.5.1Materials3.8.3.6.5.2WeldingandNondestructiveExaminationofWelds3.8.3.6.5.3ErectionTolerances3.8.3.6.6QualityControl3.8.3.7TestingandIn-serviceInspectionRequirements3.8.3.7.1PreoperationalTesting3.8.3.7.1.1StructuralAcceptanceTest SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xiv3.8.3.7.1.2LeakRateTesting3.8.3.7.2In-serviceLeakRateTesting3.8.4OtherSeismicCategoryIStructures 3.8.4.1DescriptionoftheStructures3.8.4.2ApplicableCodes,Standards,andSpecifications3.8.4.3LoadsandLoadCombinations3.8.4.3.1DescriptionofLoads3.8.4.3.2LoadCombinations3.8.4.4DesignandAnalysisProcedures3.8.4.5StructuralAcceptanceCriteria3.8.4.6Materials,QualityControl,andSpecialConstructionTechniques3.8.4.6.1ConcreteandReinforcingSteel3.8.4.6.2StructuralSteel3.8.4.6.2.1Materials3.8.4.6.2.2WeldingandNondestructiveTesting3.8.4.6.2.3FabricationandErection3.8.4.6.2.4QualityControl3.8.4.6.3SpecialConstructionTechniques3.8.4.7TestingandIn-serviceInspectionRequirements3.8.4.8ComputerProgramsUsedintheDesignandAnalysisofOtherSeismicCategoryIStructures3.8.5Foundations 3.8.5.1DescriptionoftheFoundations3.8.5.2ApplicableCodes,Standards,andSpecification3.8.5.3LoadsandLoadCombinations3.8.5.4DesignandAnalysisProcedures3.8.5.5StructuralAcceptanceCriteria3.8.5.6Materials,QualityControl,andSpecialConstructionTechniques3.8.5.7TestingandIn-serviceInspectionRequirements3.8ACOMPUTERPROGRAMS 3.8A.1D/SAP3.8A.2ASHSD3.8A.3CECAP3.8A.4CE668 SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xv3.8A.5EASE3.8A.6EO1193.8A.7EO7813.8A.8FINEL3.8A.9ME6203.8A.10SUPERB3.8A.11References3.8BCONCRETE,CONCRETEMATERIALS,QUALITYCONTROL,ANDSPECIALCONSTRUCTIONTECHNIQUES3.8B.1ConcreteandConcreteMaterials-Qualifications3.8B.1.1ConcreteMaterialQualifications3.8B.1.2ConcreteMixDesign3.8B.1.3Grout3.8B.2ConcreteandConcreteMaterials-Batching,Placing,CuringandProtection3.8B.2.1Storage3.8B.2.2Batching,Mixing,andDelivering3.8B.2.3Placing3.8B.2.4Consolidation3.8B.2.5Curing3.8B.2.6HotandColdWeatherConcreting3.8B.3ConcreteandConcreteMaterials-ConstructionTesting 3.8B.4ConcreteReinforcementMaterials-Qualifications 3.8B.5ConcreteReinforcementMaterials-Fabrication 3.8B.5.1BendingReinforcement3.8B.5.2SplicingReinforcement3.8B.5.3PlacingReinforcement3.8B.5.4SpacingReinforcement3.8B.5.5SurfaceCondition3.8B.6ConcreteReinforcementMaterials-ConstructionTesting SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xvi3.8B.7FormworkandConstructionJoints3.8CCONCRETEUNITMASONRY,MASONRYMATERIALSANDQUALITYCONTROL3.8C.1ConcreteUnitMasonryandMasonryMaterials-Qualifications3.8C.2ConcreteUnitMasonryandMasonryMaterials-ConstructionandErection3.8C.3ConcreteUnitMasonryandMasonryMaterials-ConstructionTesting3.9MECHANICALSYSTEMSANDCOMPONENTS 3.9.1SpecialTopicsforMechanicalComponents 3.9.1.1DesignTransients3.9.1.1.1ControlRodDriveTransients3.9.1.1.2CRDHousingandIncoreHousingTransients3.9.1.1.3HydraulicControlUnitTransients3.9.1.1.4CoreSupportandReactorInternalsTransients3.9.1.1.5MainSteamSystemTransients3.9.1.1.6RecirculationSystemTransients3.9.1.1.7ReactorAssemblyTransients3.9.1.1.8MainSteamIsolationValveTransients3.9.1.1.9Safety/ReliefValvesTransients3.9.1.1.10RecirculationFlowControlValveTransients3.9.1.1.11RecirculationPumpTransients3.9.1.1.12RecirculationGateValveTransients3.9.1.2ComputerProgramsUsedinAnalysis3.9.1.2.1ReactorVesselandInternals3.9.1.2.1.1ReactorVessel3.9.1.2.1.1.1CB&IProgram711-"GENOZZ"3.9.1.2.1.1.2CB&IProgram948-"NAPALM"3.9.1.2.1.1.3CB&IProgram10273.9.1.2.1.1.4CB&IProgram8463.9.1.2.1.1.5CB&IProgram781-"KALNINS"3.9.1.2.1.1.6CB&IProgram979-"ASFAST"3.9.1.2.1.1.7CB&IProgram766-"TEMAPR"3.9.1.2.1.1.8CB&IProgram767-"PRINCESS"3.9.1.2.1.1.9CB&IProgram928-"TGRV"3.9.1.2.1.1.10CB&IProgram962-"EO962A" SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xvii3.9.1.2.1.1.11CB&IProgram9843.9.1.2.1.1.12CB&IProgram992-GASP3.9.1.2.1.1.13CB&IProgram1037-"DUNHAM'S"3.9.1.2.1.1.14CB&IProgram13353.9.1.2.1.1.15CB&IPrograms1606and1657-"HAP"3.9.1.2.1.1.16CB&IProgram1634N3.9.1.2.1.2ReactorInternals3.9.1.2.2Piping3.9.1.2.2.1StructuralAnalysisProgramSAP43.9.1.2.2.2ComponentAnalysis/ANSI73.9.1.2.2.3IntegralAttachment/LUGSTR3.9.1.2.2.4PipingAnalysisProgram/PISVS3.9.1.2.2.5ReliefValveDischargePipeForces/RVF0R3.9.1.2.2.6TurbineStopValveClosure/TSFOR3.9.1.2.2.7PipingAnalysisProgram/EZPYP3.9.1.2.2.8PipeWhipAnalysis/PDA3.9.1.2.3RecirculationandECCSPumpsandMotors3.9.1.2.3.1RecirculationPumps3.9.1.2.3.2ECCSPumpsandMotors3.9.1.2.3.2.1StructuralAnalysisProgram/SAPAG3.9.1.2.3.2.2EffectsofFlangeJointConnections/FTFLG013.9.1.2.3.2.3StructuralAnalysisofDischargeHead/ANSYS3.9.1.2.3.2.4BeamElementDataProcessing/POSUM3.9.1.2.4RHRHeatExchanges3.9.1.2.4.1StructuralAnalysisPrograms/SAPAG3.9.1.2.4.2ShellAttachmentParametersandCoefficients/BILRD3.9.1.2.4.3BeamElementDataProcessing/POSUM3.9.1.2.5DynamicLoadsAnalysis3.9.1.2.5.1DynamicAnalysisProgram/DYSEA3.9.1.2.5.2AccelerationResponseSpectrumProgram/SPECA3.9.1.2.5.3FuelSupportLoadsProgram/SEISM3.9.1.3ExperimentalStressAnalysis3.9.1.3.1ExperimentalStressAnalysisofNSSSPipingComponents3.9.1.3.2SeismicCategoryItemsOtherThanNSSS3.9.1.4ConsiderationsforEvaluationoftheFaultedConditions3.9.1.4.1ControlRodDriveSystemComponents3.9.1.4.1.1ControlRodDrives3.9.1.4.1.2HydraulicControlUnit3.9.1.4.2StandardReactorInternalComponents3.9.1.4.2.1CRGuideTube SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xviii3.9.1.4.2.2IncoreHousing3.9.1.4.2.3JetPump3.9.1.4.2.4OrificedFuelSupport3.9.1.4.2.5ControlRodDriveHousing3.9.1.4.3ReactorPressureVesselAssembly3.9.1.4.4CoreSupportStructure3.9.1.4.5MainSteamIsolation,RecirculationGateandSafety/ReliefValves3.9.1.4.6MainSteamandRecirculationPiping3.9.1.4.7NuclearSteamSupplySystemPumps,HeatExchanger,andTurbines3.9.1.4.8ControlRodDriveHousingSupports3.9.1.4.9FuelStorageRacks3.9.1.4.10FuelAssembly(IncludingChannels)3.9.1.4.11RefuelingEquipment3.9.1.4.12SeismicCategoryIItemsOtherThanNSSS3.9.2DynamicTestingandAnalysis 3.9.2.1aPreoperationalVibrationandDynamicEffectsTestingonNSSSPiping3.9.2.1a.1PreoperationalVibrationTesting3.9.2.1a.2SmallAttachedPiping3.9.2.1a.3StartupVibration3.9.2.1a.4OperatingTransientLoads3.9.2.1a.5TestEvaluationandAcceptanceCriteria3.9.2.1a.5.1LevellCriterion3.9.2.1a.5.2Level2Criterion3.9.2.1a.6CorrectiveActions3.9.2.1a.7MeasurementLocations3.9.2.1bPreoperationalThermalVibrationandDynamicEffectsTestingofPipingOtherThanNSSS3.9.2.1b.1PipingDynamicTransientTests3.9.2.1b.2PipingSteadyStateVibrationTesting3.9.2.2aSeismicandHydrodynamicQualificationofSafety-RelatedNSSSMechanicalEquipment3.9.2.2a.1TestsandAnalysisCriteriaandMethods3.9.2.2a.1.1TestInputMotion3.9.2.2a.1.2ApplicationofInputMotion3.9.2.2a.1.3FixtureDesign3.9.2.2a.1.4PrototypeTesting3.9.2.2a.2SeismicandHydrodynamicQualificationofSpecificMechanicalComponents SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xix3.9.2.2a.2.1JetPumps3.9.2.2a.2.2CRDandCRDHousing3.9.2.2a.2.3CoreSupport(OrificedFuelSupportandCRGuideTube)3.9.2.2a.2.4HydraulicControlUnit(HCU)3.9.2.2a.2.5FuelChannels3.9.2.2a.2.6RecirculationPumpandMotorAssembly3.9.2.2a.2.7ECCSPumpandMotorAssembly3.9.2.2a.2.8RCICPumpAssembly3.9.2.2a.2.9RCICTurbineAssembly3.9.2.2a.2.10StandbyLiquidControlPumpandMotorAssembly3.9.2.2a.2.11RHRHeatExchangers3.9.2.2a.2.12SafetyReliefValves(SRV)3.9.2.2a.2.13StandbyLiquidControlTank3.9.2.2a.2.14MainSteamIsolationValves3.9.2.2a.2.15MainSteamSafety/ReliefValves3.9.2.2a.2.16HPCITurbine3.9.2.2a.2.17HPCIPump3.9.2.2bSeismicQualificationTestingofSafetyRelatedNon-NSSSMechanicalEquipment3.9.2.2b.1Safety-RelatedandSafety-ImpactedMechanicalEquipmentOtherThanfortheNSSS3.9.2.2b.1.1DynamicAnalysisWithoutTesting3.9.2.2b.1.2DynamicTesting3.9.2.2b.2Criteria3.9.2.3DynamicResponseofReactorInternalsUnderOperationalFlowTransientsandSteadyStateConditions3.9.2.4ConfirmatoryFlow-InducedVibrationTestingofReactorInternals3.9.2.5DynamicSystemAnalysisoftheReactorInternalsUnderFaultedConditions3.9.2.6CorrelationsofReactorInternalsVibrationTestResultswiththeAnalyticalResults3.9.3ASMECodeClass1,2,and3Components,ComponentSupports,andCoreSupportStructures3.9.3.1LoadingCombinations,DesignTransientsandStressLimits3.9.3.1.1PlantConditions3.9.3.1.1.1NormalCondition3.9.3.1.1.2UpsetCondition3.9.3.1.1.3EmergencyCondition SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xx3.9.3.1.1.4FaultedCondition3.9.3.1.1.5CorrelationofPlantConditionswithEventProbability3.9.3.1.1.6SafetyClassFunctionalCriteria3.9.3.1.1.7CompliancewithRegulatoryGuide1.483.9.3.1.2ReactorVesselAssembly3.9.3.1.3MainSteamPiping3.9.3.1.4RecirculationLoopPiping3.9.3.1.5RecirculationSystemValves3.9.3.1.6RecirculationPump3.9.3.1.7StandbyLiquidControl(SLC)Tank3.9.3.1.8ResidualHeatRemovalHeatExchangers3.9.3.1.9RCICTurbine3.9.3.1.10RCICPump3.9.3.1.11ECCSPumps3.9.3.1.12StandbyLiquidControlPump3.9.3.1.13MainSteamIsolationValvesandSafety/ReliefValves3.9.3.1.14SafetyReliefValvePiping3.9.3.1.15HighPressureCoolantInjection(HPCI)Turbine3.9.3.1.16HighPressureCoolantInjection(HPCI)Pump3.9.3.1.17ReactorWaterClean-up(RWCU)System3.9.3.1.18ThisSectionHasBeenIntentionallyDeleted3.9.3.1.19ASMECodeConstructedItemsNotFurnishedwiththeNSSS3.9.3.2aNSSSPumpandValveOperabilityAssurance3.9.3.2a.1ECCSPumps3.9.3.2a.1.1AnalysisofLoading,Stress,andAccelerationConditions3.9.3.2a.1.2PumpOperationDuringandFollowingFaultedConditionLoading3.9.3.2a.2SLCPumpandMotorAssemblyandRCICPumpAssembly3.9.3.2a.3RCICTurbine3.9.3.2a.4ECCSMotors3.9.3.2a.5NSSSValves3.9.3.2a.5.1MainSteamIsolationValve3.9.3.2a.5.2MainSteamSafety/ReliefValves3.9.3.2a.5.3RecirculationGateValves3.9.3.2a.5.4ExplosiveValves3.9.3.2a.6HPCITurbine3.9.3.2bNon-NSSSPumpandValveOperabilityAssurance3.9.3.2b.1Pumps3.9.3.2b.1.1AnalysisofLoading,Stress,andAccelerationConditions3.9.3.2b.1.2PumpOperationDuringandFollowingSSELoading3.9.3.2b.2Valves SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxi3.9.3.3aDesignandInstallationofNSSSSuppliedPressureReliefDevices3.9.3.3a.1MainSteamSafety/ReliefValves3.9.3.3bDesignandInstallationDetailsforMountingofPressureReliefDevicesinASMECodeClass1and2Systems3.9.3.4ComponentSupports3.9.3.4.1RecirculationPipingSupports3.9.3.4.2ReactorPressureVesselSupportSkirt3.9.3.4.3NSSSFloor-MountedEquipment(Pumps,HeatExchangersandRCICTurbine)3.9.3.4.4SupportsforASMECodeClass1,2and3ActiveComponents3.9.3.4.5HPCITurbine3.9.3.4.6Non-NSSSSupports3.9.3.4.6.1Snubbers3.9.3.4.6.1.1SnubberDesignSpecification3.9.3.4.6.1.2SnubberAnalysisModel3.9.4ControlRodDriveSystem 3.9.4.1DescriptiveInformationonCRDS3.9.4.2ApplicableCRDSDesignSpecifications3.9.4.3DesignLoads,StressLimits,andAllowableDeformation3.9.4.3.1ControlRodDriveHousingSupports3.9.4.4CRDPerformanceAssuranceProgram3.9.5ReactorPressureVesselInternals 3.9.5.1DesignArrangements3.9.5.1.1CoreSupportStructures3.9.5.1.1.1Shroud3.9.5.1.1.2ShroudHeadandSteamSeparatorAssembly3.9.5.1.2CorePlate3.9.5.1.3TopGuide3.9.5.1.4FuelSupport3.9.5.1.5ControlRodGuideTubes3.9.5.1.6JetPumpAssemblies3.9.5.1.7SteamDryers3.9.5.1.8FeedwaterSpargers3.9.5.1.9CoreSprayLines3.9.5.1.10VesselHeadSprayNozzle3.9.5.1.11DifferentialPressureandLiquidControlLine SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxii3.9.5.1.12In-CoreFluxMonitorGuideTubes3.9.5.1.13SurveillanceSampleHolders3.9.5.2DesignLoadingConditions3.9.5.2.1EventstobeEvaluated3.9.5.2.2PressureDifferentialDuringRapidDepressurization3.9.5.2.3RecirculationLineandSteamLineBreak3.9.5.2.3.1AccidentDefinition3.9.5.2.3.2EffectsofInitialReactorPowerandCoreFlow3.9.5.2.4SeismicandHydrodynamicLoads3.9.5.3DesignLoadingCategories3.9.5.4DesignBases3.9.5.4.1SafetyDesignBases3.9.5.4.2PowerGenerationDesignBases3.9.5.4.3ResponseofInternalsDuetoInsideSteamBreakAccident3.9.5.4.4Stress,Deformation,andFatigueLimitsforReactorInternals(ExceptCoreSupportStructure)3.9.5.4.5Stress,Deformation,andFatigueLimitsforCoreSupportStructures3.9.6In-serviceTestingofPumpsandValves 3.9.7References 3.9ACOMPUTERPROGRAMS 3.9A.1ME1013.9A.2ME6323.9A.3ME9123.9A.4ME9133.9A.5References3.10SEISMICQUALIFICATIONSOFCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENT3.10aSEISMICQUALIFICATIONOFSEISMICCATEGORYINSSSINSTRUMENTATIONANDELECTRICALEQUIPMENT3.10a.1SeismicQualificationCriteria 3.10a.1.1SeismicCategoryIEquipmentIdentification3.10a.1.2DynamicDesignCriteria SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxiii3.10a.1.2.1NSSSEquipment3.10a.2MethodsandProceduresforQualifyingElectricalEquipmentandInstrumentation(ExcludingMotorsandValveMountedEquipment)3.10a.2.1MethodsofShowingNSSSEquipmentCompliancewithIEEE344-19713.10a.2.2TestingProceduresforQualifyingElectricalEquipmentandInstrumentation(ExcludingMotorsandValveMountedEquipment)3.10a.2.3QualificationofValveMountedEquipment3.10a.2.4QualificationofNSSSMotors3.10a.3MethodsandProcedureofAnalysisorTestingofSupportsofElectricalEquipmentandInstrumentation3.10a.3.1DynamicAnalysisTestingProceduresandRestraintMeasures3.10a.3.1.1NSSSEquipment(OtherThanMotorsandValveMountedEquipment)3.10a.4OperatingLicenseReview 3.10a.4.1NSSSControlandElectricalEquipment(OtherThanMotorsandValveMountedEquipment)3.10a.4.2NSSSMotors3.10a.4.3ValveMountedEquipment3.10a.5DynamicAnalysisByResponseSpectrumMethod 3.10bSEISMICQUALIFICATIONOFNON-NSSSSUPPLIEDSEISMICCATEGORYIINSTRUMENTATION3.10b.1SeismicQualificationCriteria 3.10b.1.1SeismicCategoryIEquipmentIdentification3.10b.1.2SeismicandHydrodynamicDesignCriteria3.10b.1.2.1FunctionalCriterion3.10b.1.2.2QualificationLevels3.10b.1.2.3InstrumentationSupports3.10b.1.3DeviceQualificationTestCriteria3.10b.2SeismicCategoryIEquipmentQualification 3.10b.3MethodsandProceduresofAnalysisorTestingofSupportsofInstrumentation SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxiv3.10b.4OperatingLicenseReview3.10cSEISMICQUALIFICATIONOFNON-NSSSSEISMICCATEGORYIELECTRICALEQUIPMENT3.10c.1SeismicQualificationCriteria 3.10c.1.1EquipmentLocation3.10c.1.2ResponseSpectrumCurvesfortheElectricalEquipmentandSupports3.10c.1.3SeismicCategoryIElectricalEquipmentLoads3.10c.1.4SafeShutdownEarthquake(SSE)Conditions3.10c.1.5OperatingBasisEarthquake(OBE)Conditions3.10c.1.6PreventionofOverturningandSliding3.10c.2MethodsandProceduresforQualifyingElectricalEquipment 3.10c.2.1SeismicAnalysisMethod3.10c.2.2SeismicQualificationforElectricalEquipmentOperability3.10c.2.3SeismicTestReportAnalysisandMethods3.10c.2.3.1ElectricalEquipmentQualifiedbyTestingandCombinationofTestingandAnalysisMethod3.10c.2.3.2ElectricalEquipmentandSupportsQualifiedbyAnalysisMethod3.10c.2.3.3ElectricalEquipmentQualifiedbySuppliers'Certification3.10c.2.3.4MinimumOperatingVoltageofVoltageRelays3.10c.3MethodsandProceduresofAnalysisorTestingofSupportsofElectricalEquipment3.10c.4OperatingLicenseReview3.11ENVIRONMENTALDESIGNOFMECHANICALANDELECTRICALEQUIPMENT3.11.1EquipmentIdentificationandEnvironmentalConditions 3.11.2QualificationTestandAnalysis 3.11.2.1Class1EEquipmentQualifiedToIEEEStandard323-19713.11.2.2Class1EEquipmentQualifiedtoIEEEStandard323-1974 SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxv3.11.2.3Class1EComponentEnvironmentDesignandQualificationforNormalOperation3.11.2.4Class1EComponentEnvironmentalDesignandQualificationforOperationAfteraDesignBasisAccident3.11.3QualificationTestResults 3.11.4LossofVentilation 3.11.5EstimatedChemical,Physical,andRadiationEnvironment 3.11.5.1SuppressionPool,ResidualHeatRemovalSystem,andEmergencyCoreCoolingSystemWaterQuality3.11.5.2PhysicalEnvironment3.11.5.3RadiationEnvironment3.11.6References 3.11AAppendixHasBeenDeleted 3.12SEPARATIONCRITERIAFORSAFETYRELATEDMECHANICALANDELECTRICALPOWEREQUIPMENT3.12.1Introduction 3.12.2MechanicalSystems 3.12.2.1Criteria3.12.2.1.1GeneralCriteria3.12.2.1.2SystemSeparationCriteria3.12.2.1.3PhysicalSeparationCriteria3.12.2.2SeparationTechniques3.12.3ElectricalSystemsandEquipmentSeparationCriteria 3.12.3.1AffectedSystems3.12.3.2GeneralCriteria3.12.3.3SystemSeparationCriteria3.12.3.4ElectricalPhysicalSeparationCriteria3.12.3.4.1GeneralSeparationCriteria SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxvi3.12.3.4.2SpecificSeparationCriteria3.12.3.4.2.1CablesandRaceways3.12.3.4.2.2StandbyPowerSupply3.12.3.4.2.3DCSystem3.12.3.4.2.4DistributionSystem3.12.3.4.2.5PrimaryContainmentElectricalPenetrations3.12.3.4.2.6MainControlRoomandRelayRoomPanels3.13COMPLIANCEWITHNRCREGULATORYGUIDES 3.13.1Division1,RegulatoryGuides-PowerReactors 3.14LICENSERENEWALPROGRAMS,TLAA,ANDREGULATORYCOMMITMENTS 3.

14.1INTRODUCTION

3.14.2AGINGMANAGEMENTPROGRAMS(AMP)3.14.2.1Area-BasedNSASInspection3.14.2.2BoltingIntegrityProgram3.14.2.3BuriedPipingandTanksInspectionProgram3.14.2.4BuriedPipingSurveillanceProgram3.14.2.5BWRCRDReturnLineNozzleProgram3.14.2.6BWRFeedwaterNozzleProgram3.14.2.7BWRPenetrationsProgram3.14.2.8BWRStressCorrosionCracking(SCC)Program3.14.2.9BWRVesselIDAttachmentWeldsProgram3.14.2.10BWRVesselInternalsProgram3.14.2.11BWRWaterChemistryProgram3.14.2.12ChemistryProgramEffectivenessInspection3.14.2.13ClosedCoolingWaterChemistryProgram3.14.2.14CondensateandRefuelingWaterStorageTanksInspection3.14.2.15ContainmentLeakageRateTestProgram SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxvii3.14.2.16CoolingUnitsInspection3.14.2.17CraneInspectionProgram3.14.2.18FireProtectionProgram3.14.2.19FireWaterSystemProgram3.14.2.20Flow-AcceleratedCorrosion(FAC)Program3.14.2.21FuelOilChemistryProgram3.14.2.22HeatExchangerInspection3.14.2.23InserviceInspection(ISI)Program3.14.2.24InserviceInspection(ISI)Program-IWE3.14.2.25InserviceInspection(ISI)Program-IWF3.14.2.26InserviceInspection(ISI)Program-IWL3.14.2.27LeakChaseChannelMonitoringActivities3.14.2.28LubricatingOilAnalysisProgram3.14.2.29LubricatingOilInspection3.14.2.30NotUsed3.14.2.31MasonryWallProgram3.14.2.32Metal-EnclosedBusInspectionProgram3.14.2.33MonitoringandCollectionSystemInspection3.14.2.34Non-EQCablesandConnectionsUsedinLow-CurrentInstrumentationCircuitsProgram3.14.2.35Non-EQElectricalCablesandConnectionsVisualInspectionProgram3.14.2.36Non-EQInaccessibleMedium-VoltageCablesProgram3.14.2.37Non-EQElectricalCableConnectionsProgram3.14.2.38PipingCorrosionProgram3.14.2.39PreventiveMaintenanceActivities-RCIC/HPCITurbineCasings3.14.2.40ReactorHeadClosureStudsProgram3.14.2.41ReactorVesselSurveillanceProgram3.14.2.42RG1.127Water-ControlStructuresInspection SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxviii3.14.2.43SelectiveLeachingInspection3.14.2.44SmallBoreClass1PipingInspection3.14.2.45StructuresMonitoringProgram3.14.2.46SupplementalPiping/TankInspection3.14.2.47SystemWalkdownProgram3.14.2.48ThermalAgingandNeutronEmbrittlementofCastAusteniticStainlessSteel(CASS)Program3.14.2.49FatigueMonitoringProgram3.14.2.50PreventiveMaintenanceActivities-MainTurbineCasing3.14.2.51FuseHoldersProgram3.14.3EVALUATIONOFTIME-LIMITEDAGINGANALYSES(TLAA) 3.14.3.1ReactorVesselNeutronEmbrittlement3.14.3.2MetalFatigue3.14.3.3Non-Class1ComponentFatigueAnalyses3.14.3.4EnvironmentalQualificationofElectricEquipment3.14.3.5FatigueofPrimaryContainment,AttachedPiping,andComponents3.14.3.6OtherPlant-SpecificTime-LimitedAgingAnalyses3.14.4LICENSERENEWALREGULATORYCOMMITMENTLIST SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxix3.2-1SSESDesignCriteriaSummary3.2-2SummaryofCodesandStandardsforComponentsofWater-CooledNuclearPowerUnitsSuppliedbyAE(orderedpriortoJuly1,1971withtheexceptionofthosecomponentslocatedinsidetheRCPB,andthereactorpressurevessel)3.2-3SummaryofCodesandStandardsforComponentsofWater-CooledNuclearPowerUnitsSuppliedbyAE(orderedafterJuly1,1971)3.2-4CodeGroupDesignations-IndustryCodesandStandardsforMechanicalComponentsSuppliedbytheNSSSVendor3.2-5SummaryofSafetyClassDesignRequirements(Minimum) 3.3-1WindLoadsonStructures 3.3-2TornadoWindProtectedSystemsandTornadoResistantEnclosures 3.5-1ThisTableHasBeenDeleted 3.5-2ProbabilitiesforUnit1TargetsDuetoEachTurbine3.5-3ThisTableHasBeenDeleted 3.5-4Tornado-GeneratedMissileParametersforAllTornado-ResistantStructuresExcepttheDieselGenerator'E'Building3.5-4aTornado-GeneratedMissileParametersforDieselGenerator'E'Building 3.5-5BerwickAirportMovementSummary 3.5-6PlantTargetAreas 3.5-7CalculatedStressforBonnet-SealTypeValves 3.5-8ThisTableHasBeenDeleted 3.5-9ThisTableHasBeenDeleted SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxx3.5-10TurbineSystemReliabilityCriteria3.6-1HighEnergyFluidSystemPiping 3.6-1aModerateEnergyFluidSystemPiping(LocatedinSafety-RelatedStructures)3.6-2SafetyComponentsinCloseProximitytoHighEnergyFluidSystemPiping-(RequiringJetImpingementProtection)PrimaryContainment)3.6-3SafetyComponentsinCloseProximitytoHighEnergyFluidSystemPiping-(RequiringJetImpingementProtection)ReactorBuilding3.6-4RestraintData 3.6-5ComparisonofPDAandNSCCode 3.6-6aSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"A"3.6-6bSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"B"3.6-6cSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"C"3.6-6dSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"D"3.6-6eSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"A"3.6-6fSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"B"3.6-6gSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"C"3.6-6hSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"D" SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxi3.6-7SummaryofStressinHighEnergyASMEClass1Piping-FeedwaterLineInsideContainment-Unit13.6-7aSummaryofStressinHighEnergyASMEClass1Piping-FeedwaterLineInsideContainment-Unit23.6-8SummaryofStressinHighEnergyASMEClass1Piping-HPCISteamSupplyLineInsideContainment-Unit13.6-8aSummaryofStressinHighEnergyASMEClass1Piping-HPCISteamSupplyLineInsideContainment-Unit23.6-9SummaryofStressinHighEnergyASMEClass1Piping-RCICSteamSupplyLineInsideContainment-Unit13.6-9aSummaryofStressinHighEnergyASMEClass1Piping-RCICSteamSupplyLineInsideContainment-Unit23.6-10SummaryofStressinHighEnergyASMEClass1Piping-CoreSprayLineInsideContainment-Unit13.6-10aSummaryofStressinHighEnergyASMEClass1Piping-CoreSprayLineInsideContainment-Unit23.6-11SummaryofStressinHighEnergyASMEClass1Piping-RHRSupplyLineInsideContainment-Unit13.6-11aSummaryofStressinHighEnergyASMEClass1Piping-RHRSupplyLineInsideContainment-Unit23-6-12aSummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainmentUnit1Loop"A"3.6-12a.1SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit13.6-12a.2SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit13.6-12a.3SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit1 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxii3.6-12a.4SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit23.6-12a.5SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit23.6-12a.6SummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainment-Unit2-Loop"A"3.6-12a.7SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit23.6-12bSummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainmentUnit1Loop"B"3.6-12b.1SummaryofStressinHighEnergyASMEClass1Piping-HeadVentLineInsideContainment-Unit13.6-12b.2SummaryofStressinHighEnergyASMEClass1Piping-HeadVentLineInsideContainment-Unit13.6-12b.3SummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainment-Unit2-Loop"B"3.6-12b.4SummaryofStressinHighEnergyASMEClass1Piping-HeadVentLineInsideContainment-Unit23.6-12cSummaryofStressinHighEnergyASMEClass1Piping-HeadSprayLineInsideContainment-Unit13.6-12c.1SummaryofStressinHighEnergyASMEClass1Piping-HeadSprayLineInsideContainment-Unit23.6-12d.1SummaryofStressinHighEnergyASMEClass1Piping-StandbyLiquidControlLineInsideContainment-Unit13.6-12d.2ThisTablehasbeenIntentionallyLeftBlank 3.6-12d.3SummaryofStressinHighEnergyASMEClass1Piping-StandbyLiquidControlLineInsideContainment-Unit2 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxiii3.6-12e.1SummaryofStressinHighEnergyASMEClass1Piping-MSIVDrainLinesInsideContainment-Unit13.6-12e.2SummaryofStressinHighEnergyASMEClass1Piping-MSIVDrainLinesInsideContainment-Unit13.6-12e.3SummaryofStressinHighEnergyASMEClass1Piping-MSIVDrainLinesInsideContainment-Unit23.6-13HighEnergyFluidSystemsWithandWithoutSufficientCapacitytoDevelopaJetStream3.6-14SummaryofStressinHighEnergyASMEClass1Piping-RecirculationPipingSystem-Loop"A"-Unit13.6-15SummaryofStressinHighEnergyASMEClass1Piping-RecirculationPipingSystem-Loop"A"-Unit23.6A-1ComparisonofFlowRatesComputedfromtheTimeDependentMomentumEquation3.6A-2CaseA-SteamTunnelCompartmentVolumes 3.6A-3SteamTunnelFlowAreasCoefficientsandL/A 3.6A-4ForCaseA&CaseB 3.6A-5CaseB-SteamTunnelCompartmentVolumes 3.6A-6SteamTunnelFlowAreasCoefficientsandL/A 3.7a-1CriticalDampingRatiosforDifferentMaterials 3.7a-2Thistablehasbeendeleted 3.7a-3NumberofDynamicResponseCyclesExpectedDuringaSeismicEvent 3.7b-1AmplificationFactorsforGroundSpectra 3.7b-1aThistableHasBeenRenumberedto3.7b-2 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxiv3.7b-2AmplificationFactorsforDieselGenerator'E'Building'sGroundSpectra3.7b-3DampingValuesforNon-NSSSMaterials(PercentofCriticalDamping) 3.7b-4DampingValuesforDieselGenerator'E'Facility3.7b-5StructureFoundationInteractionCoefficients 3.7b-6PropertiesofFoundationMediaforContainmentandESSWPumphouse 3.7b-7NaturalFrequenciesofContainmentBelow33CPS 3.7b-8NaturalFrequenciesoftheReactorandControlBuildingBelow33CPS3.7b-9ESSWPumphouse:FrequenciesWithandWithoutEccentricities 3.7b-10DieselGeneratorA-DBuildingFrequenciesWithandWithoutEccentricities 3.7b-11ComparisonsofTorsionalMomentsBetweenOriginalDesignandtheValuesComputedfromtheResultsof3-DStickModel3.7b-12Thistablehasbeendeleted 3.7b-13Thistablehasbeendeleted 3.8-1ListofApplicableCodes,Standards,Recommendations,andSpecifications 3.8-2LoadCombinationsforPrimaryContainment,DrywellFloor 3.8-2aLoadCombinationsforReactorPedestal 3.8-3LoadCombinationsandAllowableStressesForASMEClassMCComponents3.8-3aComparisonofFSARandSRPLoadCombinationsandAllowableStressesforASMEClassMCComponents3.8-4LoadCombinationfortheReactorShieldWall SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxv3.8-5LoadCombinationsfortheSuppressionChamberColumns3.8-6LoadCombinationsfortheDrywellPlatforms 3.8-7LoadCombinationfortheSeismicTruss 3.8-8LoadCombinationsApplicabletoReactorBuilding 3.8-9LoadCombinationsApplicabletoSeismicCategoryIStructuresOtherThanContainment,ReactorBuildingandDieselGenerator'E'Building3.8-9aLoadCombinationsApplicabletoDieselGenerator'E'Building 3.8-10LoadCombinationsApplicabletoTurbine&RadwasteBuilding 3.8-11ConcreteDesignCompressiveStrengths 3.8-12AllowableStressIncreaseFactorforMasonryStructures 3.8A-1TabulationofMembraneStressResultantsFromtheASHSDProgram 3.8A-2CECAPandHandCalculationComparison-ThermalGradient 3.8A-3ComparisonofCECAPandHandCalculationResults-RealMoment 3.8A-4CECAPandHandCalculationComparison-RealMomentandRealCompressiveLoad3.8A-5ComparisonofResultsfortheRectangularPlatewithaConcentratedLoadattheCenter3.8A-6ComparisonofResultsfortheRectangularPlatewithVariousEdgeConditions3.8A-7ComparisonofStressesforWeldingNeckFlange 3.8A-8ComparisonofStressesforSlip-OnFlange 3.8A-9ComparisonofFinalResultsforHoopForce,N,andMeridionalMoment,M SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxvi3.8A-10MaterialPropertiesoftheConcreteandReinforcingSteelUsedforFINELVerification3.8A-11LoadingHistoryUsedfortheFINELVerification 3.8A-12ComparisonofStressResults 3.8A-13ComparisonofStressResults 3.8A-14ComparisonofResults 3.8B-1MinimumTestingFrequenciesforConcreteMaterialsandConcrete(ExceptfortheDieselGenerator'E'Building)3.8B-2TestingRequirementsforConcreteMaterialsUsedintheDieselGenerator'E'Building3.8B-3TestingRequirementsforConcreteUsedintheDieselGenerator'E'Building 3.9-1TransientsandtheNumberofAssociatedCyclesConsideredintheDesignandFatigueAnalysisoftheRPVAssemblyandInternalTransients3.9-2Introduction 3.9-2Index 3.9-2LoadCombinationandAcceptanceCriteriaforASMECodeClass1,2,and3NSSSPipingandEquipment3.9-2aReactorPressureVesselandShroudSupportAssembly 3.9-2bReactorInternalsandAssociatedEquipment 3.9-2(c)ReactorWaterCleanupHeatExchangers 3.9-2dASMECodeClassIMainSteamPipingandPipeMountedEquipment-HighestStressSummary-Unit13.9-2d.1ASMECodeClassIMainSteamPipingandPipeMountedEquipment-HighestStressSummary-Unit2 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxvii3.9-2eASMECodeClassIRecirculationPipingandPipeMountedEquipment-HighestStressSummary-Unit13.9-2e.1ASMECodeClassIRecirculationPipingandPipeMountedEquipment-HighestStressSummary-Unit23.9-2(f)ThisTableHasBeenIntentionallyLeftBlank 3.9-2gSafety/ReliefValves(MainSteam) 3.9-2(h)MainSteamIsolationValve 3.9-2iRecirculationPump 3.9-2(j)ReactorRecirculationSystemGateValves,DischargeStructural&MechanicalLoadingCriteria3.9-2(k)ThisTableHasBeenIntentionallyLeftBlank 3.9-2LStandbyLiquidControlPump 3.9-2mStandbyLiquidControlTank 3.9-2n(i)RHRPumps(ii)CoreSprayPumps 3.9-2oRHRHeatExchanger 3.9-2(p)RWCUPump 3.9-2qRCICTurbine 3.9-2(r)RCICPump 3.9-2sReactorRefuelingandServicingEquipment 3.9-2tHighPressureCoolantInjectionPump 3.9-2uControlRodDrive(IndexTube) 3.9-2vControlRodDriveHousing SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxviii3.9-2wJetPumps3.9-2aaControlRodGuideTubeFlange 3.9-2abIncoreHousing 3.9-2(ac)ReactorVesselSupportEquipmentCRDHousingSupport 3.9-2(ad)ThisTableHasBeenIntentionallyLeftBlank 3.9-2(ae)HPCITurbineDesignCalculations 3.9-2(af)HighDensitySpentFuelRacks 3.9-3NSSSSeismicCategoryIActivePumpsandValves 3.9-4ApplicableThermalTransients 3.9-5ListofComputerProgramsUsedinBOPMechanicalSystemsandComponents3.9-6DesignLoadingCombinationsForASMECodeClass1,2,and3Components3.9-7DesignCriteriaforASMECodeClassIValves 3.9-8DesignCriteriaforASMECodeClass2and3VesselsDesignedtoNC-3300andND-33003.9-9DesignCriteriaforASMECodeClass2VesselsDesignedtoAlternateRulesofNC-32003.9-10DesignCriteriaforASMECodeClass2and3Piping 3.9-11DesignCriteriaforASMECodeClass2and3Pumps 3.9-12DesignCriteriaforASMECodeClass2and3Valves 3.9-13ThisTableHasBeenIntentionallyLeftBlank SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxix3.9-14DesignLoadingCombinationsforSupportsforASMECodeClass1,2and3Components3.9-15ValveQualificationTestRange 3.9-16ListingofDynamicallyQualifiedEquipment 3.9-17DieselGenerator'A-D'SeismicTestorAnalysisSubmittalChart 3.9-18SummaryComparison-ProjectSpecification-10,"GeneralProjectRequirementsforASeismicDesignandAnalysisofClass1EquipmentandEquipmentSupports"3.9-19ThisTableHasBeenIntentionallyLeftBlank 3.9-20BOPPipingSystemPowerAscensionTesting 3.9A-1ComparisonBetweenSampleProblemandComputerProgramME913Results3.9A-2ComparisonofME912withME643andAnalyticalResults 3.10a-1EssentialElectricalComponentsandInstruments 3.10a-2SeismicQualificationTestSummaryClassIEControlPanelsandLocalPanelsandRacks3.10a-3SummaryofSampleSeismicStaticAnalysisForThreeTypicalCabinets 3.10a-4SeismicDesignVerificationDataSheet 3.10c-1SecondaryUnitSubstationsandPowerTransformers 3.10c-2MotorControlCenters 3.10c-3BatteryMonitorsandFuseBoxes 3.10c-4DCDistributionPanels 3.10c-5BatteryRacks SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xl3.10c-6ElectricalCablePenetration3.10c-7CableTrays"Safeguard" 3.10c-8BatteryChargerRacksandCabinets 3.10c-9LargeInductionMotors4000V 3.10c-10PanelsandTerminationCabinets 3.10c-11BatteryChargers 3.10c-124.16KVSwitchgear 3.10c-13DCControlandLoadCenters 3.10c-14InstrumentACTransformers 3.10c-15AutomaticTransferSwitches 3.10c-16LoadIsolationMotor-GeneratorSets 3.10c-17Non-NSSSandNon-ACRRelaysRequiredtobeEnergized 3.10c-18Invertersand120VACInstrumentPanels 3.11-2ThisTableHasBeenIntentionallyLeftBlank 3.11-3ThisTableHasBeenIntentionallyLeftBlank 3.11-4ThisTableHasBeenIntentionallyLeftBlank 3.11-5ThisTableHasBeenIntentionallyLeftBlank 3.11-6ThisTableHasBeenIntentionallyLeftBlank 3.11-7WaterQuality 3.11-8ThisTableHasBeenIntentionallyLeftBlank 3.12-1ESFDivisionSeparation SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xli3.12-2ChannelSeparation3.12-3MainControlRoomandRelayPanelAnnunciatorandComputerInterfaceDevice3.13-1ComparisonwithRegulatoryGuide1.48 3.14-1LicenseRenewalCommitments SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlii3.2-1CodeClassificationofPipingValves3.2-2MinimumInstrumentLineClassifications 3.5-1ThisFigureHasBeenDeleted 3.5-2ThisFigureHasBeenDeleted 3.5-3ThisFigureHasBeenDeleted 3.5-4ThisFigureHasBeenDeleted 3.5-5ThisFigureHasBeenDeleted 3.5-6ThisFigureHasBeenDeleted 3.5-7ThisFigureHasBeenDeleted 3.5-8ThisFigureHasBeenDeleted 3.5-9Typical900#BonnetSealTypeValve 3.5-10RetainingRingDesignfor900#Bonnet-SealTypeValve 3.6-1AMainSteamLineA 3.6-1BMainSteamLineB 3.6-1CMainSteamLineC 3.6-1DMainSteamLineD 3.6-2FeedwaterSystem 3.6-3HPCISteamSupply 3.6-4RCICSteamSupply 3.6-5CoreSpray SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xliii3.6-6RHRSupply3.6-7RHRReturnLoopA 3.6-8RHRReturnLoopB 3.6-8A.1ReactorWaterCleanup 3.6-8A.2ReactorWaterCleanup 3.6-8A.3ReactorWaterCleanup 3.6-8A.4ReactorWaterCleanup 3.6-8A.5ReactorWaterCleanup 3.6-8BReactorVesselHeadVent 3.6-8CHeadSpray 3.6-8DStandbyLiquidControl 3.6-8EMSIVDrains 3.6-9ThisFigureHasBeenIntentionallyLeftBlank 3.6-10TypicalPipeWhipRestraints 3.6-11PipeWhipRestraintArrangementtoProtectFeedwaterOutsideContainmentIsolationValves3.6-11aMainFeedwaterLinePIPERUPMathematicalModel 3.6-12ForcingFunctionsModelAssociatedwithPipeWhipDynamicAnalysis3.6-12aForcingFunctionsModelAssociatedwithPipeWhipDynamiteAnalysis3.6-13TypicalPipeWhipRestraintConfiguration SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xliv3.6-14RecirculationSystemPostulatedBreakLocationsandRestraintLocations(LOOPAandBSame,UnlessOtherwiseSpecified)3.6-15TypicalRestraintForce-DeflectionCurve 3.6-16BreakLocationsandRestraintsAnalyzed,PDAVerificationProgram 3.6-17-1PipeBreakProtectionforHighEnergyPipingintheReactorBuilding 3.6-17-2PipeBreakProtectionforHighEnergyPipingintheReactorBuilding 3.6-17-3PipeBreakProtectionforHighEnergyPipingintheReactorBuilding 3.6A-1CaseAMSLBinReactorBuilding 3.6A-2PanelandPlatformLocations 3.6A-3CaseAVolumeFlows 3.6A-4CaseAPressureTransient 3.6A-5CaseBMSLBinTurbineBuilding 3.6A-6CaseBVolumeFlows 3.6A-7CaseBPressureTransient 3.6A-8ModelforDouble-EndedGuillotineMSLB3.7a-1ReactorPressureVesselandInternalSeismicModel 3.7a-2DensityofStressReversals 3.7b-1ThisFigureIsADuplicationofFigure2.5-28 3.7b-1aFigurerenumberedfrom3.7B-1Ato3.7B-2 3.7b-2DieselGenerator'E'BuildingDesignResponseSpectraSafeShutdownEarthquakeHorizontalComponent3.7b-2aFigurerenumberedfrom3.7B-2Ato3.7B-4 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlv3.7b-3DesignResponseSpectraSafeShutdownEarthquakeHorizontalComponent3.7b-3aFigurerenumberedfrom3.7B-2Ato3.7B-6 3.7b-3bFigurerenumberedfrom3.7B-3Bto3.7B-7 3.7b-4DieselGenerator'E'BuildingsDesignResponseSpectraSafeShutdownEarthquakeHorizontalComponent3.7b-5SyntheticTimeHistoryNormalizedto1G 3.7b-6DieselGenerator'E'BuildingHorizontalSyntheticTimeHistoryNormalizedto0.1G3.7b-6aFigurerenumberedfrom3.7B-6Ato3.7B-11 3.7b-6bFigurerenumberedfrom3.7B-6Bto3.7B-12 3.7b-6cFigurerenumberedfrom3.7B-6Cto3.7B-13 3.7b-6dFigurerenumberedfrom3.7B-6Dto3.7B-14 3.7b-6eFigurerenumberedfrom3.7B-6Eto3.7B-15 3.7b-6fFigurerenumberedfrom3.7B-6Fto3.7B-16 3.7b-7DieselGenerator'E'BuildingVerticalSyntheticTimeHistoryNormalizedto 0.1G3.7b-8ComparisonofTimeHistoryResponseSpectraandDesignResponseSpectra2%and5%Damping(0.2-30CPS)3.7b-9ComparisonofTimeHistoryResponseSpectraandDesignResponseSpectra3%and7%Damping(0.2-30CPS)3.7b-10ComparisonofTimeHistoryResponseSpectraandDesignResponseSpectra2%and5%Damping(0.2-1.0CPS)

SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlvi3.7b-11DieselGenerator'E'BuildingComparisonofHorizontalTimeHistoryResponseSpectrumandHorizontalDesignResponseSpectrum2%Damping3.7b-12DieselGenerator'E'BuildingComparisonofHorizontalTimeHistoryResponseSpectrumandHorizontalDesignResponseSpectrum5%Damping3.7b-13DieselGenerator'E'BuildingComparisonofHorizontalTimeHistoryResponseSpectrumandHorizontalDesignResponseSpectrum7%Damping3.7b-14DieselGenerator'E'BuildingComparisonofVerticalTimeHistoryResponseSpectrumandVerticalDesignResponseSpectrum2%Damping3.7b-15DieselGenerator'E'BuildingComparisonofVerticalTimeHistoryResponseSpectrumandVerticalDesignResponseSpectrum5%Damping3.7b-16DieselGenerator'E'BuildingComparisonofVerticalTimeHistoryResponseSpectrumandVerticalDesignResponseSpectrum7%Damping3.7b-17HorizontalSeismicModelofContainmentWithFlexibleBase 3.7b-18VerticalSeismicModelofContainmentWithFlexibleBase 3.7b-19E-WSeismicModelofReactorandControlBuilding 3.7b-20N-SSeismicModelofReactorandControlBuilding 3.7b-21VerticalSeismicModelofReactorandControlBuilding 3.7b-22PlanViewofReactorandControlBuilding 3.7b-23CorrelationofVerticalSeismicModelMasspointsofthePhysicalStructure 3.7b-24ContainmentHorizontalModeShapesMode1 3.7b-25ContainmentHorizontalModeShapesMode2 3.7b-26ContainmentHorizontalModeShapesMode4 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlvii3.7b-27ContainmentVerticalModeShapesMode13.7b-28ContainmentVerticalModeShapesMode2 3.7b-29ContainmentVerticalModeShapesMode3 3.7b-30ReactorandControlBuildingE-WModeShapes-Mode1(CranesatPoints32and33)3.7b-31ReactorandControlBuildingE-WModeShapes-Mode2 3.7b-32ReactorandControlBuildingE-WModeShapes-Mode3(CranesatPoints32and33)3.7b-33ReactorandControlBuildingE-WModeShapes-Mode4 3.7b-34ReactorandControlBuildingE-WModeShapes,Mode5 3.7b-35ReactorandControlBuildingN-SModeShapes-Mode1 3.7b-36ReactorandControlBuildingN-SModeShapes-Mode3 3.7b-37ReactorandControlBuildingVerticalModeShapesMode1 3.7b-38ReactorandControlBuildingVerticalModeShapesMode2 3.7b-39ReactorandControlBuildingVerticalModeShapesMode3 3.7b-40ContainmentHorizontalDisplacementsOBE 3.7b-41ContainmentHorizontalDisplacementsSSE 3.7b-42ContainmentVerticalDisplacementsOBE 3.7b-43ContainmentVerticalDisplacementsSSE 3.7b-44ContainmentHorizontalAccelerationsOBE 3.7b-45ContainmentHorizontalAccelerationsSSE 3.7b-46ContainmentVerticalAccelerationsOBE SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlviii3.7b-47ContainmentVerticalAccelerationsSSE3.7b-48ReactorandControlBuildingE-WDisplacementsOBE 3.7b-49ReactorandControlBuildingE-WDisplacementsSSE 3.7b-50ReactorandControlBuildingN-SDisplacementsOBE 3.7b-51ReactorandControlBuildingN-SDisplacementsSSE 3.7b-52ReactorandControlBuildingVerticalDisplacementsOBE 3.7b-53ReactorandControlBuildingVerticalDisplacementsSSE 3.7b-54ReactorandControlBuildingE-WAccelerationsOBE 3.7b-55ReactorandControlBuildingE-WAccelerationsSSE 3.7b-56ReactorandControlBuildingN-SAccelerationsOBE 3.7b-57ReactorandControlBuildingN-SAccelerationsSSE 3.7b-58ReactorandControlBuildingVerticalAccelerationOBE 3.7b-59ReactorandControlBuildingVerticalAccelerationsSSE 3.7b-60ResponseSpectrumatRPVPedestalHorizontalOBE 3.7b-61ResponseSpectrumatRPVPedestalHorizontalSSE 3.7b-62ResponseSpectrumatRPVPedestalVerticalOBE 3.7b-63ResponseSpectrumatRPVPedestalVerticalSSE 3.7b-64ResponseSpectrumatRefuelingAreaE-WOBE 3.7b-65ResponseSpectrumatRefuelingAreaE-WSSE 3.7b-66ResponseSpectrumatRefuelingAreaN-SOBE SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlix3.7b-67ResponseSpectrumatRefuelingAreaN-SSSE3.7b-68ResponseSpectrumatRefuelingAreaVerticalOBE 3.7b-69ResponseSpectrumatRefuelingAreaVerticalSSE 3.7b-70ResponseSpectrumatTopofPedestal(DieselsA-D)E-WOBE 3.7b-71ResponseSpectrumatTopofPedestal(DieselE)E-WOBE 3.7b-72ResponseSpectrumatTopofPedestal(DieselsA-D)E-WSSE 3.7b-73ResponseSpectrumatTopofPedestal(DieselE)E-WSSE 3.7b-74ResponseSpectrumatTopofPedestal(DieselsA-D)N-SOBE 3.7b-75ResponseSpectrumatTopofPedestal(DieselE)N-SOBE 3.7b-76ResponseSpectrumatTopofPedestal(DieselsA-D)N-SSSE 3.7b-77ResponseSpectrumatTopofPedestal(DieselE)N-SSSE 3.7b-78ResponseSpectrumatTopofPedestal(DieselsA-D)VerticalOBE 3.7b-79ResponseSpectrumatTopofPedestalforDieselEVerticalOBE 3.7b-80ResponseSpectrumatTopofPedestal(DieselsA-D)Vertical-SSE 3.7b-81ResponseSpectrumatTopofPedestalforDiesel'E'VerticalSSE 3.7b-82ResponseSpectrumatOperatingFloorofESSWPumphouseE-WOBE 3.7b-83ResponseSpectrumatOperatingFloorofESSWPumphouseE-WSSE 3.7b-84ResponseSpectrumatOperatingFloorofESSWPumphouseN-SOBE 3.7b-85ResponseSpectrumatOperatingFloorofESSWPumphouseN-SSSE 3.7b-86ResponseSpectrumatOperatingFloorofESSWPumphouseVerticalOBE 3.7b-87ResponseSpectrumatOperatingFloorofESSWPumphouseVerticalSSE SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-l3.7b-88ComparisonofDesignandR.G.1.60ResponseSpectraHorizontalOBE3.7b-89ComparisonofDesignandR.G.1.60ResponseSpectraHorizontalSSE 3.7b-90ComparisonofDesignandR.G.1.60ResponseSpectraVerticalOBE 3.7b-90aFigurerenumberedfrom3.7B-90Ato3.7B-71 3.7b-91ComparisonofDesignandR.G.1.60ResponseSpectraVerticalSSE 3.7b-91aFigurerenumberedfrom3.7B-91Ato3.7B-73 3.7b-92DampingV/SZPAforRacewaySystem 3.7b-92aFigurerenumberedfrom3.7B-92Ato3.7B-75 3.7b-93ESSWPumpHouse3-DStickModel 3.7b-93aFigurerenumberedfrom3.7b-93Ato3.7B-77 3.7b-94DieselGenerator'A-D'Building3-DStickModel 3.7b-94aFigurerenumberedfrom3.7B-94Ato3.7B-79 3.7b-95DieselGenerator'E'BuildingSeismicModels 3.7b-95aFigureDeleted

3.7b-96throughFiguresDeleted 3.7b-1263.8-1ThisFigureHasBeenReplacedbyDwg.C-331,Sh.1 3.8-2ThisFigureHasBeenReplacedbyDwg.C-371,Sh.1 3.8-3ThisFigureHasBeenReplacedbyDwg.C-1932,Sh.3 3.8-4ThisFigureHasBeenReplacedbyDwg.C-1932,Sh.4 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-li3.8-5ThisFigureHasBeenReplacedbyDwg.C-1932,Sh.53.8-6ThisFigureHasBeenDeleted 3.8-7ThisFigureHasBeenDeleted 3.8-8ThisFigureHasBeenDeleted 3.8-9PrimaryContainment-DrywellHeadConnection 3.8-10ThisFigureHasBeenReplacedbyDwg.C-284,Sh.1 3.8-11-1ThisFigureHasBeenReplacedbyDwg.C-332,Sh.1 3.8-11-2ThisFigureHasBeenReplacedbyDwg.C-333,Sh.1 3.8-12ThisFigureHasBeenReplacedbyDwg.C-281,Sh.1 3.8-13ThisFigureHasBeenReplacedbyDwg.C-281,Sh.1 3.8-14ThisFigureHasBeenReplacedbyDwg.C-370,Sh.1 3.8-15-1ThisFigureHasBeenReplacedbyDwg.C-334,Sh.1 3.8-15-2ThisFigureHasBeenReplacedbyDwg.C-335,Sh.1 3.8-15-3ThisFigureHasBeenReplacedbyDwg.C-336,Sh.1 3.8-15-4ThisFigureHasBeenReplacedbyDwg.C-337,Sh.1 3.8-15-5ThisFigureHasBeenReplacedbyDwg.C-338,Sh.1 3.8-16-1ThisFigureHasBeenReplacedbyDwg.C-351,Sh.1 3.8-16-2ThisFigureHasBeenReplacedbyDwg.C-352,Sh.1 3.8-16-3ThisFigureHasBeenReplacedbyDwg.C-353,Sh.1 3.8-16-4ThisFigureHasBeenReplacedbyDwg.C-354,Sh.1 3.8-16-5ThisFigureHasBeenReplacedbyDwg.C-355,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lii3.8-16-6ThisFigureHasBeenReplacedbyDwg.C-356,Sh.13.8-16-7ThisFigureHasBeenReplacedbyDwg.C-357,Sh.1 3.8-16-8ThisFigureHasBeenReplacedbyDwg.C-358,Sh.1 3.8-16-9ThisFigureHasBeenReplacedbyDwg.C-359,Sh.1 3.8-16-10ThisFigureHasBeenReplacedbyDwg.C-360,Sh.1 3.8-16-11ThisFigureHasBeenReplacedbyDwg.C-393,Sh.1 3.8-16-12ThisFigureHasBeenReplacedbyDwg.C-394,Sh.1 3.8-16-13ThisFigureHasBeenReplacedbyDwg.C-395,Sh.1 3.8-16-14ThisFigureHasBeenReplacedbyDwg.C-396,Sh.1 3.8-16-15ThisFigureHasBeenReplacedbyDwg.C-397,Sh.1 3.8-16-16ThisFigureHasBeenReplacedbyDwg.C-398,Sh.1 3.8-16-17ThisFigureHasBeenReplacedbyDwg.C-399,Sh.1 3.8-16-18ThisFigureHasBeenReplacedbyDwg.C-400,Sh.1 3.8-17ThisFigureHasBeenReplacedbyDwg.C-282,Sh.1 3.8-18ThisFigureHasBeenReplacedbyDwg.C-285,Sh.1 3.8-19-1ThisFigureHasBeenReplacedbyDwg.C-288,Sh.1 3.8-19-2ThisFigureHasBeenReplacedbyDwg.C-287,Sh.1 3.8-19-3ThisFigureHasBeenReplacedbyDwg.C-283,Sh.1 3.8-20-1SuppressionChamberElectricalPenetrationDetails 3.8-20-2DrywellElectricalPenetrationDetails SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-liii3.8-21ThisFigureHasBeenReplacedbyDwg.C-286,Sh.13.8-22ThisFigureHasBeenReplacedbyDwg.C-291,Sh.1 3.8-23ThisFigureHasBeenReplacedbyDwg.C-278,Sh.1 3.8-24ContainmentWallTemperatureGradients 3.8-25ContainmentWallAnalyticalModelforAxisymmetricLoads 3.8-26DrywellWallAnalyticalModelforNon-AxisymmetricMissileandPostulatedPipeRuptureLoads3.8-27BaseFoundationSlabAnalyticalModel 3.8-28EquipmentHatchAnalyticalModel 3.8-29StructuralAcceptanceTest-PressurizationSequence 3.8-30StructuralAcceptanceTest-LocationsofDeflectionMeasuringDevicesfortheContainment3.8-31StructuralAcceptanceTest-LocationsofDeflectionMeasuringDevicesfortheEquipmentHatch3.8-32ThisFigureHasBeenReplacedbyDwg.C-384,Sh.1 3.8-33ThisFigureHasBeenReplacedbyDwg.C-387,Sh.1 3.8-34StructuralAcceptanceTest-ContainmentAnalyticalModel 3.8-35StructuralAcceptanceTest-EquipmentHatchAnalyticalModel 3.8-36StructuralAcceptanceTest-ComparisonofMeasuredandPredictedDeflectionsfortheContainment3.8-37StructuralAcceptanceTest-ComparisonofMeasuredandPredictedDeflectionfortheEquipmentHatch3.8-38StructuralAcceptanceTest-InsideMeridionalStrainatMid-heightofSuppressionChamberWall SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-liv3.8-39StructuralAcceptanceTest-InsideHoopStrainatMid-heightofSuppressionChamberWall3.8-40StructuralAcceptanceTest-OutsideMeridionalStrainatMid-heightofSuppressionChamberWall3.8-41StructuralAcceptanceTest-OutsideHoopStrainatMid-heightofSuppressionChamberWall3.8-42StructuralAcceptanceTest-OutsideHelicalStrainatMid-heightofSuppressionChamberWall3.8-43StructuralAcceptanceTest-ExternalConcreteSurfaceCracksatMid-heightofDrywellWall3.8-44DrywellHead 3.8-45AnalyticalModelofDrywellHeadAssembly 3.8-46-1ThisFigureHasBeenReplacedbyDwg.C-348,Sh.1 3.8-46-2ThisFigureHasBeenReplacedbyDwg.C-349,Sh.1 3.8-46-3ThisFigureHasBeenReplacedbyDwg.C-350,Sh.1 3.8-47ThisFigureHasBeenReplacedbyDwg.C-293,Sh.1 3.8-48ThisFigureHasBeenReplacedbyDwg.C-340,Sh.1 3.8-49ThisFigureHasBeenReplacedbyDwg.C-341,Sh.1 3.8-50ThisFigureHasBeenReplacedbyDwg.C-376,Sh.1 3.8-51-1ThisFigureHasBeenReplacedbyDwg.C-344,Sh.1 3.8-51-2ThisFigureHasBeenReplacedbyDwg.C-377,Sh.1 3.8-52ThisFigureHasBeenReplacedbyDwg.C-362,Sh.1 3.8-53ThisFigureHasBeenReplacedbyDwg.C-363,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lv3.8-54ThisFigureHasBeenReplacedbyDwg.C-354,Sh.13.8-55ThisFigureHasBeenReplacedbyDwg.C-365,Sh.1 3.8-56ThisFigureHasBeenReplacedbyDwg.C-367,Sh.1 3.8-57ThisFigureHasBeenReplacedbyDwg.C-380,Sh.1 3.8-58TemperatureGradientsforDrywellFloorandReactorPedestal 3.8-59ReactorShieldWallTemperatureGradients 3.8-60DrywellFloorAnalyticalModel 3.8-61AnalyticalModelforReactorPedestalAboveDrywellFloor 3.8-62ReactorShieldWall-EASEProgramAnalyticalModel 3.8-63ReactorShieldWall-AnalyticalModelfor"FINEL"and"ASHSD"Program 3.8-64SuppressionChamberColumns-ASHSDProgramAnalyticalModel 3.8-65SuppressionChamberColumns-SeismicModel 3.8-66SuppressionChamberColumns-"CE668"ProgramAnalyticalModel 3.8-67SeismicTrussAnalyticalModel 3.8-68StructuralAcceptanceTest-ComparisonofMeasuredandPredictedDeflectionsfortheDrywellFloor3.8-69ThisFigureHasBeenReplacedbyDwg.A-11,Sh.1 3.8-70ThisFigureHasBeenReplacedbyDwg.A-12,Sh.1 3.8-71ThisFigureHasBeenReplacedbyDwg.A-13,Sh.1 3.8-72ThisFigureHasBeenReplacedbyDwg.M-203,Sh.1 3.8-73ThisFigureHasBeenReplacedbyDwg.M-204,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lvi3.8-74ThisFigureHasBeenReplacedbyDwg.A-16,Sh.13.8-75ThisFigureHasBeenReplacedbyDwg.A-17,Sh.1 3.8-76ThisFigureHasBeenDeletedSeeFigure3.5-6 3.8-77Reactor,ControlandTurbineBuildingSectionsLookingNorth 3.8-78ReactorBuildingLookingWest 3.8-79ThisFigureHasBeenReplacedbyDwg.M-227,Sh.1 3.8-80ThisFigureHasBeenReplacedbyDwg.M-237,Sh.1 3.8-81ThisFigureHasBeenReplacedbyDwg.M-260,Sh.1 3.8-82ThisFigureHasBeenReplacedbyDwg.M-261,Sh.1 3.8-83ThisFigureHasBeenReplacedbyDwg.M-5200,Sh.1 3.8-84ThisFigureHasBeenReplacedbyDwg.M-5200,Sh.2 3.8-85ThisFigureHasBeenReplacedbyDwg.M-284,Sh.1 3.8-86ThisFigureHasBeenReplacedbyDwg.C-64,Sh.1 3.8-87ThisFigureHasBeenReplacedbyDwg.C-65,Sh.1 3.8-88ThisFigureHasBeenReplacedbyDwg.C-66,Sh.1 3.8-89ThisFigureHasBeenReplacedbyDwg.C-67,Sh.1 3.8-90ThisFigureHasBeenReplacedbyDwg.M-270,Sh.1 3.8-91ThisFigureHasBeenReplacedbyDwg.M-271,Sh.1 3.8-92ThisFigureHasBeenReplacedbyDwg.M-272,Sh.1 3.8-93ThisFigureHasBeenReplacedbyDwg.M-273,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lvii3.8-94ThisFigureHasBeenReplacedbyDwg.M-274,Sh.13.8-95ThisFigureHasBeenReplacedbyDwg.C-795,Sh.1 3.8A-1ThinShellCylinder 3.8A-2LayeredCylinder 3.8A-3GeneralLayoutofCylinder 3.8A-4FiniteElementModel 3.8A-5AxialMoment 3.8A-6CylinderwithHingedEnds 3.8A-7FiniteElementModel 3.8A-8-1ComparisonofResultsforCylindricalShellSubjectedtoanAsymmetricBending3.8A-8-2Comparison(Continued)ofResultsforCylindricalShellSubjectedtoAsymmetricBending3.8A-9ReinforcedConcreteBeam 3.8A-10ReinforcedConcreteBeamandCECAPConcreteElementModel 3.8A-11BeamCross-SectionandInitialStressDistribution 3.8A-12FinalThermalStressDistribution 3.8A-13ReinforcedConcreteBeamandCECAPConcreteElementModel 3.8A-14ReinforcedConcreteBeamandCECAPConcreteElementModel 3.8A-15ReinforcedConcreteBeamandCECAPModel 3.8A-16BeamCross-SectionandStressBlock SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lviii3.8A-17PlateGeometry,Loading,andFiniteElementMeshforRectangularPlatewithaConcentratedLoadattheCenter3.8A-18PlateGeometry,Loading,andFiniteElementMeshforRectangularPlatewithVariousEdgeConditions3.8A-19WeldingNeckFlangeDetail 3.8A-20Slip-OnFlangeDetail 3.8A-21GeometryofTorisphericalandEllipsoidalHeads(FittoCorrespondtoGeometryofEllipsoidalHeadinReference3.8A-9)3.8A-22MeasuredThicknessVariationinExperimentalHeadNo.1(FromReference3.8A-10,Page18)3.8A-23ThicknessVariationinCylinderNo.1(FromReference3.8A-11Fig.4) 3.8A-24AnalyticalModelwithBoundaryConditions 3.8A-25PlotofHoopForceandLongitudinalMovementfromE0781Output3.8A-26PlotofStressinthe(Hoop)DirectionontheInsideSurface(=0 o)(Ref.3.8A-12PageG-14)3.8A-27PlotofStressinthe(Hoop)DirectionontheOutsideSurface(=0 o)(Ref.3.8A-12PageG-11)3.8A-28PlotofStressinthe(Longitudinal)DirectionontheInsideSurface

(=0 o)(Ref.3.8A-12PageG-20)3.8A-29PlotofStressinthe(Longitudinal)DirectionontheOutsideSurface(=0 o)(Ref.3.8A-12PageG-17)3.8A-30PlotofMembraneStress(=0 o)(Ref.3.8A-12PageG-23)3.8A-31DimensionsofCylindricalWaterTank 3.8A-32ExperimentalBeamDimensions SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lix3.8A-33Reference3.8A-14Mesh3.8A-34FinelFiniteElementMesh 3.8A-35-1RegionsofCracking 3.8A-35-2RegionsofCracking(Cont.)

3.8A-36Load-DisplacementCurvesfromFinelVerificationUsingaSimplySupportedBeam3.8A-37FiniteElementModel 3.8A-38FiniteElementModel 3.8A-39TemperatureDistribution 3.8A-40SchematicofTestProblem 3.8A-41FiniteElementLayout 3.8A-42ComparisonofResults 3.8A-43SteelSphere 3.8A-44FiniteElementModel 3.9-1TransientPressureDifferentialsfollowingaSteamLineBreakat105%RatedSteamFlow,100%Recirculation3.9-2TypicalReliefValveTransient 3.9-3ReactorVesselCutaway 3.9-4ReactorInternalsFlowPaths 3.9-5FuelSupportPieces 3.9-6JetPump 3.9-7PressureNodesUsedforDepressurizationAnalysis SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lx3.9A-1TransientTemperatureResponse3.10a-1TypicalVerticalBoard 3.10a-2InstrumentRack 3.10a-3TypicalLocalRack 3.10a-4NEMAType-12Enclosure 3.10a-5-1CabinetInstallationforSeismicandHydrodynamicLoads-SampleCalculation(CabinetH12-P608)3.10a-5-2CabinetInstallationforSeismicandHydrodynamicLoads-SampleCalculation(CabinetH12-P608)3.10a-5-3CabinetInstallationforSeismicandHydrodynamicLoads-SampleCalculation(CabinetH12-P608)3.10a-6CornerPost 3.10a-7PlanViewofPanel 3.10a-8BarrierWithTwoEndPlates 3.10a-9PanelDeflections 3.11-1ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.1 3.11-2ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.2 3.11-3ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.3 3.11-4ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.4 3.11-5ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.5 3.11-6ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.6 3.11-7ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.7 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lxi3.11-8ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.83.11-9ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.9 3.11-10ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.10 3.11-11ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.11 3.11-12ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.12 3.13-1Onelinediagramillustratingrelationshipofloads,penetrationassemblies,andprotectivedevicesforcurvespresentedasFigures3.13-2,3.13-3,&

3.13-83.13-2Time-currentcharacteristiccurvesforovercurrentprotectionof#10copper,containmentpenetrations.3.13-2ATime-CurrentCharacteristicCurvesForOvercurrentProtectionOf#10Copper,ContainmentPenetrations3.13-2BTime-CurrentCharacteristicCurvesForOvercurrentProtectionOf#10Copper,ContainmentPenetrations3.13-3RelationshipOfLoads,PenetrationAssemblies&ProtectiveDevicesforCurvesPresentedinFigures3.13-2,3.13-3,&3.18-83.13-4120VoltACControlCircuits 3.13-5125VoltDCControlCircuits 3.13-6208/120LightingCircuits 3.13-7ReactRecirPump-MaxShortCircuitCapability 3.13-8Time-CurrentCharacteristicCurvesforOvercurrentProtectionof4/0Copper,ContainmentPenetrationsUsedWithHydrogenRecombiners SSES-FSAR TOC Rev. 61 FSAR Rev. 68 4-i CHAPTER 4 REACTOR TABLE OF CONTENTS TEXT Section Title 4.1

SUMMARY

DESCRIPTION

4.1.1 Reactor Vessel 4.1.2 Reactor Internal Components

4.1.2.1 Reactor Core

4.1.2.1.1 General 4.1.2.1.2 Core Configuration 4.1.2.1.3 Fuel Assembly Description 4.1.2.1.3.1 Fuel Rod 4.1.2.1.3.2 Fuel Bundle 4.1.2.1.4 Assembly Support and Control Rod Location

4.1.2.2 Shroud 4.1.2.3 Shroud Head and Steam Separators 4.1.2.4 Steam Dryer Assembly

4.1.3 Reactivity Control Systems

4.1.3.1 Operation 4.1.3.2 Description of Rods

4.1.4 Analysis Techniques

4.1.4.1 Reactor Internal Components 4.1.4.1.1 MASS (Mechanical Analysis of Space Structure) 4.1.4.1.1.1 Program Description 4.1.4.1.1.2 Program Version and Computer 4.1.4.1.1.3 History of Use 4.1.4.1.1.4 Extent of Application 4.1.4.1.2 SNAP (MULTISHELL) 4.1.4.1.2.1 Program Description 4.1.4.1.2.2 Program Version and Computer 4.1.4.1.2.3 History of Use 4.1.4.1.2.4 Extent of Application

4.1.4.1.3 GASP 4.1.4.1.3.1 Program Description SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-ii 4.1.4.1.3.2 Program Version and Computer 4.1.4.1.3.3 History of Use 4.1.4.1.3.4 Extent of Application 4.1.4.1.4 NO HEAT 4.1.4.1.4.1 Program Description 4.1.4.1.4.2 Program Version and Computer 4.1.4.1.4.3 History of Use 4.1.4.1.4.4 Extent of Application

4.1.4.1.5 FINITE 4.1.4.1.5.1 Program Description 4.1.4.1.5.2 Program Version and Computer 4.1.4.1.5.3 History of Use 4.1.4.1.5.4 Extent of Usage

4.1.4.1.6 DYSEA 4.1.4.1.6.1 Program Description 4.1.4.1.6.2 Program Version and Computer 4.1.4.1.6.3 History of Use 4.1.4.1.6.4 Extent of Application 4.1.4.1.7 SHELL 5 4.1.4.1.7.1 Program Description 4.1.4.1.7.2 Program Version and Computer 4.1.4.1.7.3 History of Use 4.1.4.1.7.4 Extent of Application 4.1.4.1.8 HEATER 4.1.4.1.8.1 Program Description 4.1.4.1.8.2 Program Version and Computer 4.1.4.1.8.3 History of Use 4.1.4.1.8.4 Extent of Application 4.1.4.1.9 FAP-71 (Fatigue Analysis Program) 4.1.4.1.9.1 Program Description 4.1.4.1.9.2 Program Version and Computer 4.1.4.1.9.3 History of Use 4.1.4.1.9.4 Extent of Use

4.1.4.1.10 CREEP/PLAST 4.1.4.1.10.1 Program Description 4.1.4.1.10.2 Program Version and Computer 4.1.4.1.10.3 History of Use 4.1.4.1.10.4 Extent of Application 4.1.4.2 Fuel Rod Thermal Analysis 4.1.4.3 Reactor Systems Dynamics 4.1.4.4 Nuclear Engineering Analysis SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-iii 4.1.4.4.1 ESCORE 4.1.4.4.2 CASMO-3G

4.1.4.4.3 SIMULATE-E 4.1.4.5 Neutron Fluence Calculations 4.1.4.6 Thermal Hydraulic Calculations

4.1.5 References

4.2 FUEL SYSTEM DESIGN

4.2.1 Design Bases

4.2.1.1 Fuel Assembly 4.2.1.2 Original Equipment Control Rod Assembly 4.2.1.3 GE Duralife 160C Control Rod Assembly 4.2.1.4 GE Marathon Control Rod Assembly 4.2.1.5 Westinghouse CR 99 Control Rod Assembly

4.2.2 General Design Description

4.2.2.1 Core Cell 4.2.2.2 Fuel Bundle 4.2.2.3 Fuel Assembly 4.2.2.4 Reactivity Control Assembly 4.2.2.4.1 Original Equipment Control Rod Assembly 4.2.2.4.2 Duralife 160C Control Rod Assembly 4.2.2.4.3 GE Marathon Control Rod Assembly 4.2.2.4.4 Westinghouse CR 99 Control Rod Assembly

4.2.3 Design Evaluations

4.2.3.1 Fuel Design Evaluations 4.2.3.2 Results of Control Rod Assembly Design Evaluations 4.2.3.2.1 Original Equipment Control Rod Assembly 4.2.3.2.2 Duralife 160C Control Rod Assembly 4.2.3.2.3 GE Marathon Control Rod Assembly 4.2.3.2.4 Westinghouse CR 99 Control Rod Assembly

4.2.4 Testing and Inspection

4.2.4.1 Fuel Hardware and Assembly SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-iv 4.2.4.2 Enrichment, Burnable Poison, and Absorber Rod Concentrations 4.2.4.3 Surveillance, Inspection and Testing

4.2.5 Operating and Developmental Experience 4.2.6 References

4.3 NUCLEAR DESIGN

4.3.1 Design Bases

4.3.1.1 Safety Design Bases 4.3.2.1 Plant Performance Design Bases

4.3.2 Description

4.3.2.1 Nuclear Design Description 4.3.2.1.1 Core Composition 4.3.2.1.2 Fuel bundle Nuclear Design 4.3.2.2 Power Distributions 4.3.2.2.1 Local Power Distribution 4.3.2.2.2 Radial Power Distribution 4.3.2.2.3 Axial Power Distribution 4.3.2.2.4 Power Distribution Measurements 4.3.2.2.5 Power Distribution Accuracy 4.3.2.3 Reactivity Coefficients 4.3.2.3.1 Void Coefficient 4.3.2.3.2 Moderator Temperature Coefficient 4.3.2.3.3 Doppler Temperature Coefficient 4.3.2.3.4 Power Coefficient 4.3.2.4 Control Requirements 4.3.2.4.1 Shutdown Reactivity 4.3.2.4.2 Reactivity Variations 4.3.2.5 Control Rod Patterns and Reactivity Worths 4.3.2.5.1 RWM Range 4.3.2.5.2 Operating Range 4.3.2.5.3 SCRAM Reactivity 4.3.2.6 Criticality of Reactor During Refueling 4.3.2.7 Stability 4.3.2.8 Vessel Irradiations

4.3.3 Analytical Methods SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-v 4.3.4 Changes 4.3.5 References

4.4 THERMAL AND HYDRAULIC DESIGN

4.4.1 Design Basis

4.4.1.1 Safety Design Bases 4.4.1.2 Power Generation Design Bases 4.4.1.3 Requirements for Steady-State Conditions 4.4.1.4 Requirements for Transient Conditions 4.4.1.5 Summary of Design Bases

4.4.2 Description of Thermal-Hydraulic Design of the Reactor Core

4.4.2.1 Summary Comparison 4.4.2.2 Critical Power Ratio 4.4.2.2.1 Boiling Correlations 4.4.2.3 Thermal Operating Limits 4.4.2.3.1 Design Power Distribution 4.4.2.3.2 Design Linear Heat Generation Rates 4.4.2.4 Void Fraction Distribution 4.4.2.5 Core Coolant Flow Distribution and Orificing Pattern 4.4.2.6 Core Pressure Drop and Hydraulic Loads 4.4.2.6.1 Friction Pressure Drop 4.4.2.6.2 Local Pressure Drop 4.4.2.6.3 Elevation Pressure Drop 4.4.2.6.4 Acceleration Pressure Drop 4.4.2.7 Correlation and Physical Data 4.4.2.7.1 Pressure Drop Correlations 4.4.2.7.2 Void Fraction Correlations 4.4.2.7.3 Heat Transfer Correlation 4.4.2.8 Thermal Effects of Operational Transients 4.4.2.9 Uncertainties in Estimates 4.4.2.10 Flux Tilt Considerations 4.4.2.11 Crud Deposition 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System

4.4.3.1 Plant Configuration Data SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-vi 4.4.3.1.1 Reactor Coolant System Configuration 4.4.3.1.2 Reactor Coolant System Thermal Hydraulic Data 4.4.3.1.3 Reactor Coolant System Geometric Data

4.4.3.2 Operating Restrictions on Pumps 4.4.3.3 Power-Flow Operating Map 4.4.3.3.1 Limits for Normal Operation 4.4.3.3.1.1 Performance Characteristics 4.4.3.3.2 Regions of the Power Flow Map 4.4.3.4 Temperature-Power Operating Map (PWR) 4.4.3.5 Load Following Characteristics 4.4.3.6 Thermal and Hydraulic Characteristics Summary Table

4.4.4 Evaluation

4.4.4.1 Critical Power 4.4.4.2 Core Hydraulics 4.4.4.3 Influence of Power Distributions 4.4.4.4 Core Thermal Response 4.4.4.5 Analytical Methods 4.4.4.5.1 Reactor Model 4.4.4.5.2 System Flow Balances 4.4.4.5.3 System Heat Balances 4.4.4.6 Thermal-Hydraulic Stability Analysis

4.4.4.6.1 Introduction

4.4.4.6.2 Description 4.4.4.6.3 Stability Criteria 4.4.4.6.4 Mathematical Model 4.4.4.6.5 Analytical Confirmation 4.4.4.6.6 Analysis Results

4.4.5 Testing and Verification 4.4.6 Instrumentation Requirements

4.4.6.1 Loose Parts Monitoring

4.4.7 References

4.5 REACTOR MATERIALS

4.5.1 Control Rod System Structural Materials SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-vii 4.5.1.1 Material Specifications 4.5.1.2 Special Materials 4.5.1.3 Processes, Inspections and Tests 4.5.1.4 Control of Delta Ferrite Content 4.5.1.5 Protection of Materials During Fabrication, Shipping and Storage

4.5.2 Reactor Internal Materials

4.5.2.1 Material Specifications 4.5.2.2 Controls on Welding 4.5.2.3 Nondestructive Examination of Wrought Seamless Tubular Products 4.5.2.4 Fabrication and Processing of Austenitic Stainless Steel - Regulatory Guide Conformance 4.5.2.5 Contamination, Protection, and Cleaning of Austenitic Stainless Steel

4.5.3 Control Rod Drive Housing Supports

4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS

4.6.1 Information for CRDS

4.6.1.1 Control Rod Drive System Design 4.6.1.1.1 Design Bases 4.6.1.1.1.1 General Design Bases 4.6.1.1.1.1.1 Safety Design Bases 4.6.1.1.1.1.2 Power Generation Design Basis

4.6.1.1.2 Description 4.6.1.1.2.1 Control Rod Drive Mechanisms 4.6.1.1.2.2 Drive Components 4.6.1.1.2.2.1 Drive Piston 4.6.1.1.2.2.2 Index Tube 4.6.1.1.2.2.3 Collet Assembly 4.6.1.1.2.2.4 Piston Tube 4.6.1.1.2.2.5 Stop Piston 4.6.1.1.2.2.6 Flange and Cylinder Assembly 4.6.1.1.2.2.7 Lock Plug 4.6.1.1.2.3 Materials of Construction 4.6.1.1.2.3.1 Index Tube 4.6.1.1.2.3.2 Coupling Spud 4.6.1.1.2.3.3 Collet Fingers SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-viii 4.6.1.1.2.3.4 Seals and Bushings 4.6.1.1.2.3.5 Summary 4.6.1.1.2.4 Control Rod Drive Hydraulic System 4.6.1.1.2.4.1 Hydraulic Requirements 4.6.1.1.2.4.2 System Description 4.6.1.1.2.4.2.1 Supply Pump 4.6.1.1.2.4.2.2 Accumulator Charging Pressure 4.6.1.1.2.4.2.3 Drive Water Pressure 4.6.1.1.2.4.2.4 Cooling Water Header 4.6.1.1.2.4.2.5 Scram Discharge Volume 4.6.1.1.2.4.3 Hydraulic Control Units 4.6.1.1.2.4.3.1 Insert Drive Valve 4.6.1.1.2.4.3.2 Insert Exhaust Valve 4.6.1.1.2.4.3.3 Withdraw Drive Valve 4.6.1.1.2.4.3.4 Withdraw Exhaust Valve 4.6.1.1.2.4.3.5 Speed Control Units 4.6.1.1.2.4.3.6 Scram Pilot Valves 4.6.1.1.2.4.3.7 Scram Inlet Valve 4.6.1.1.2.4.3.8 Scram Exhaust Valve 4.6.1.1.2.4.3.9 Scram Accumulator 4.6.1.1.2.5 Control Rod Drive System Operation 4.6.1.1.2.5.1 Rod Insertion 4.6.1.1.2.5.2 Rod Withdrawal

4.6.1.1.2.5.3 Scram

4.6.1.1.2.6 Instrumentation 4.6.1.2 Control Rod Drive Housing Supports 4.6.1.2.1 Safety Objective 4.6.1.2.2 Safety Design Bases

4.6.1.2.3 Description

4.6.2 Evaluations of the CRDS

4.6.2.1 Safety Evaluation 4.6.2.1.1 Control Rods 4.6.2.1.1.1 Materials Adequacy Through Design Lifetime 4.6.2.1.1.2 Dimensional and Tolerance Analysis 4.6.2.1.1.3 Thermal Analysis of the Tendency to Warp 4.6.2.1.1.4 Forces for Expulsion 4.6.2.1.1.5 Functional Failure of Critical Components 4.6.2.1.1.6 Precluding Excessive Rates of Reactivity Addition 4.6.2.1.1.7 Effect of Fuel Rod Failure on Control Rod Channel Clearances SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-ix 4.6.2.1.1.8 Mechanical Damage 4.6.2.1.1.9 Evaluation of Control Rod Velocity Limiter 4.6.2.1.2 Control Rod Drives 4.6.2.1.2.1 Evaluation of Scram Time 4.6.2.1.2.2 Analysis of Malfunction Relating to Rod Withdrawal 4.6.2.1.2.2.1 Drive Housing Fails at Attachment Weld 4.6.2.1.2.2.2 Rupture of Hydraulic Line(s) to Drive Housing Flange 4.6.2.1.2.2.2.1 Pressure-under Line Break 4.6.2.1.2.2.2.2 Pressure-over Line Break 4.6.2.1.2.2.3 All Drive Flange Bolts Fail in Tension 4.6.2.1.2.2.4 Weld Joining Flange to Housing Fails in Tension 4.6.2.1.2.2.5 Housing Wall Ruptures 4.6.2.1.2.2.6 Flange Plug Blows Out 4.6.2.1.2.2.7 Ball Check Valve Plug Blows Out 4.6.2.1.2.2.8 Drive Pressure Control Valve Closure (Reactor Pressure, 0 psig) 4.6.2.1.2.2.9 Ball Check Valve Fails to Close Passage to Vessel Ports 4.6.2.1.2.2.10 Hydraulic Control Unit Valve Failures 4.6.2.1.2.2.11 Collet Fingers Fail to Latch 4.6.2.1.2.2.12 Withdrawal Speed Control Valve Failure 4.6.2.1.2.3 Scram Reliability 4.6.2.1.2.4 Control Rod Support and Operation 4.6.2.1.3 Control Rod Drive Housing Supports

4.6.3 Testing and Verification of the CRDs

4.6.3.1 Control Rod Drives 4.6.3.1.1 Testing and Inspection 4.6.3.1.1.1 Development Tests 4.6.3.1.1.2 Factory Quality Control Tests 4.6.3.1.1.3 Operational Tests 4.6.3.1.1.4 Acceptance Tests 4.6.3.1.1.5 Surveillance Tests 4.6.3.1.1.6 Functional Tests 4.6.3.2 Control Rod Drive Housing Supports 4.6.3.2.1 Testing and Inspection

4.6.4 Information for Combined Performance of Reactivity Systems

4.6.4.1 Vulnerability to Common Mode Failures 4.6.4.2 Accidents Taking Credit for Multiple Reactivity Systems

SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-x 4.6.5 Evaluation of Combined Performance 4.6.6 References

SSES-FSAR TOC Rev. 61 CHAPTER 4 TABLES Number Title FSAR Rev. 68 4-xi 4.2-1 Deleted

4.2-2 Deleted

4.2-3 Deleted

4.2-4 Deleted

4.2-5 Deleted

4.2-6 Deleted

4.2-7 Deleted

4.2-8 Deleted

4.2-9 Deleted

4.2-10 Deleted

4.2-11 Deleted

4.2-12 Deleted

4.2-13 Deleted

4.2-14 Fuel Design Characteristics (Nominal)

4.3-1 Reactor Core Characteristics

4.3-2 Susquehanna Unit 1 Core Composition 4.3-3 Susquehanna Unit 2 Core Composition

4.3-4 Summary of BWR/4 and BWR/5 Design Revisions

4.3-5 Calculated Neutron Fluxes (Used to Evaluate Vessel Irradiation)

4.3-6 Calculated Neutron Flux at Core Equivalent Boundary

4.3-7 SSES Lattice Numbers and Corresponding Figures SSES-FSAR TOC Rev. 61 CHAPTER 4 TABLES Number Title FSAR Rev. 68 4-xii 4.4-1 Thermal and Hydraulic Design Characteristics of the Reactor Core

4.4-1a Deleted

4.4-2 Typical Void Distribution

4.4-2a Axial Power Distribution Used to Generate Typical Void and Quality Distributions

4.4-3 Typical Flow Quality Distribution

4.4-4 Typical Core Flow Distribution

4.4-4a Deleted

4.4-5 Deleted

4.4-6 Description of Uncertainties (BWR/4 and BWR/5)

4.4-7 Bypass Flow Paths

4.4-8 Plant Configuration Data

4.4-9 Lengths of Safety Injection Line

NOTE: Additional tables are presented in NEDE 20944/20944-P.

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xiii 4.1-1 Deleted

4.1-2 Steam Dryer Panel

4.1-3 Steam Dryer

4.1-4 Deleted

4.1-5 Deleted

4.1-6 Renumbered to FSAR Figure 4.2-14

4.1-7 Renumbered to FSAR Figure 4.2-20

4.1-8 Renumbered to FSAR Figure 4.2-21

4.2-1 Deleted

4.2-2 Deleted

4.2-3 Deleted

4.2-4 Deleted

4.2-5 Deleted

4.2-6 Deleted

4.2-7 Deleted

4.2-8a Deleted

4.2-8b Deleted

4.2-8c Deleted

4.2-9 Deleted

4.2-10 Deleted

4.2-11 Deleted SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xiv 4.2-12 Deleted

4.2-13 Deleted

4.2-14 This Figure Has Been Deleted

4.2-15 Core Cell (ATRIUMŽ-10 Fuel with Duralife 60C Control Rod)

4.2-15a Core Cell (ATRIUM-10 Fuel with MARATHON Control Rod)

4.2-15B Core Cell (ATRIUM TM-10 Fuel with Ultra-HD Control Rod) 4.2-15C Core Cell (ATRIUM TM-10 Fuel with Westinghouse CR 99 Control Rod) 4.2-16 This Figure Has Been Deleted

4.2-17 Fuel Bundle FANP ATRIUM-10

4.2-18 80 MIL Fuel Channel

4.2-18-1 80 MIL Fuel Channel

4.2-18-2 100 MIL Fuel Channel

4.2-18-3 Advanced Fuel Channel

4.2-19 Correct Fuel Assembly Orientation

4.2-20 Control Rod Assembly Original Equipment

4.2-21 Control Rod Assembly Duralife 160-C (D-160C)

4.2-22 Control Rod Assembly Marathon

4.2-23 Control Rod Assembly Westinghouse CR 99 4.3-1 Unit 1 Core Loading Pattern

4.3-2 Unit 2 Core Loading Pattern

4.3-3 Uranium Depletion as a Function of Exposure, 40% Voids (Typical)

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xv 4.3-4 Plutonium Buildup as a Function of Exposure, 40% Voids (Typical)

4.3-5 Fission Fraction as a Function of Exposure, 40% Voids (Typical)

4.3-6 Delayed Neutron Fraction as a Function of Exposure, 40% Voids (Typical)

4.3-7 Neutron Lifetime as a Functions of Exposure, 40% Voids (Typical)

4.3-8 This Figure Has Been Deleted

4.3-8-1 FRA ANP ATRIUM TM-10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 54

4.3-8-2 This Figure Has Been Deleted

4.3-8-3 FRA ANP ATRIUM TM-10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 55

4.3-8-4 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 50 4.3-8-5 Assembly Type 51 Reload Bundle Description

4.3-8-6 Assembly Type 52 Reload Bundle Description

4.3-8-7 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 49 4.3-8-8 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 49 4.3-8-9 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 47 4.3-8-10 FRA ANP ATRIUM Fuel Axial Enrichment (Nominal) PPL Assembly Type 56 4.3-8-11 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 57 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xvi 4.3-8-12 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 58 4.3-8-13 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 58 4.3-8-14 FRA-ANP ATRIUM TM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 60

4.3-8-15 FRA-ANP ATRIUM TM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 61

4.3-8-16 FRA-ANP ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 62

4.3-8-17 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 63

4.3-8-18 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 64

4.3-8-19 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 65

4.3-8-20 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 66

4.3-8-21 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 67

4.3-8-22 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 68

4.3-8-23 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 69

4.3-8-24 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 70

4.3-8-25 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 71

4.3-8-26 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 72

4.3-8-27 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 73

4.3-8-28 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 74

4.3-8-29 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 75 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xvii 4.3-8-30 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 76

4.3-8-31 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 77

4.3-8-32 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 79 4.3-8-33 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 80 4.3-8-34 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 81 4.3-8-35 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 82 4.3-8-36 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 83 4.3-8-37 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 84 4.3-8-38 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 85 4.3-8-39 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 86 4.3-8-40 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 87 4.3-8-40A ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 87A 4.3-8-41 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 88 4.3-8-42 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 89 4.3-8-43 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 90 4.3-8-44 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 91 4.3-8-45 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 92

4.3-9 This Figure Has Been Deleted 4.3-9-1 This Figure Has Been Deleted

4.3-9-2 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 57 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xviii 4.3-9-3 FANP ATRIUM Fuel Radial Enrichment (Nominal) PPL Lattice Type 58

4.3-9-4 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 59 4.3-9-5 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 60 4.3-9-6 This Figure Has Been Deleted

4.3-9-7 This Figure Has Been Deleted

4.3-9-8 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 69 4.3-9-9 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 70 4.3-9-10 This Figure Has Been Deleted

4.3-9-11 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 52 4.3-9-12 This Figure Has Been Deleted

4.3-9-13 This Figure Has Been Deleted

4.3-9-14 This Figure Has Been Deleted

4.3-9-15 This Figure Has Been Deleted

4.3-9-16 This Figure Has Been Deleted

4.3-9-17 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 61 4.3-9-18 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 62 4.3-9-19 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 71 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xix 4.3-9-20 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 72 4.3-9-21 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 73 4.3-9-22 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 74 4.3-9-23 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 75 4.3-9-24 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 76 4.3-9-25 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 77 4.3-9-26 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 78 4.3-9-27 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 79 4.3-9-28 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 80 4.3-9-29 Update For U1C13 Reload & LEFM Uprate To 3489 MWT Rated Power 4.3-9-30 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 05 4.3-9-31 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 06 4.3-9-32 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 07 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xx 4.3-9-33 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 08 4.3-9-34 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 09 4.3-9-35 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 10 4.3-9-36 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 11 4.3-9-37 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 121 4.3-9-38 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 124 4.3-9-39 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 126 4.3-9-40 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 129 4.3-9-41 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 130 4.3-9-42 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 131 4.3-9-43 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 132 4.3-9-44 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 133 4.3-9-45 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 134 4.3-9-46 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 135 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxi 4.3-9-47 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 136 4.3-9-48 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 137 4.3-9-49 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 138 4.3-9-50 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 139 4.3-9-51 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 140 4.3-9-52 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 141 4.3-9-53 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 142 4.3-9-54 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 143

4.3-9-55 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 144

4.3-9-56 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 145

4.3-9-57 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 146

4.3-9-58 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 147

4.3-9-59 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 148

4.3-9-60 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 149

4.3-9-61 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 150

4.3-9-62 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 151

4.3-9-63 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 152 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxii 4.3-9-64 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 153

4.3-9-65 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 154

4.3-9-66 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 155

4.3-9-67 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 156

4.3-9-68 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 157

4.3-9-69 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 158

4.3-9-70 ATRIUM -10 FUEL Radial Enrichment (Nominal) PPL Lattice Type 159

4.3-9-71 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 160

4.3-9-72 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 161

4.3-9-73 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 162

4.3-9-74 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 163

4.3-9-75 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 164

4.3-9-76 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 165

4.3-9-77 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 166

4.3-9-78 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 167

4.3-9-79 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 168

4.3-9-80 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 169

4.3-9-81 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 170 4.3-9-82 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 171

4.3-9-83 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 172

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxiii 4.3-9-84 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 173

4.3-9-85 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 174

4.3-9-86 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 175

4.3-9-87 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 176

4.3-9-88 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 177

4.3-9-89 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 178

4.3-9-90 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 179

4.3-9-91 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 180

4.3-9-92 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 181

4.3-9-93 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 182

4.3-9-94 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 183

4.3-9-95 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 184

4.3-9-96 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 185

4.3-9-97 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 186 4.3-9-98 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 187 4.3-9-99 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 188 4.3-9-100 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 189 4.3-9-101 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 190 4.3-9-102 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 191 4.3-9-103 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 192 4.3-9-104 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 193 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxiv 4.3-9-105 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 194 4.3-9-106 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 195 4.3-9-107 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 196 4.3-9-108 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 197 4.3-9-109 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 198 4.3-9-110 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 199 4.3-9-111 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 200 4.3-9-112 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 201 4.3-9-113 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 202 4.3-9-114 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 203 4.3-9-115 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 204 4.3-9-116 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 205 4.3-9-117 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 206 4.3-9-118 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 207 4.3-9-119 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 208 4.3-9-120 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 209 4.3-9-121 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 210 4.3-9-122 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 211 4.3-10 This Figure Has Been Deleted 4.3-10-1 This Figure Has Been Deleted

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxv 4.3-10-2 This Figure Has Been Deleted

4.3-10-3 This Figure Has Been Deleted

4.3-10-4 This Figure Has Been Deleted

4.3-10-5 This Figure Has Been Deleted

4.3-10-6 This Figure Has Been Deleted

4.3-10-7 This Figure Has Been Deleted

4.3-11 This Figure Has Been Deleted

4.3-11-1 FANP ATRIUM 10 Fuel Dominant Lattice Hot-Uncontrolled K-Infinity vs Exposure (Typical)

4.3-11-2 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 0 MWD/MTU (Typical)

4.3-11-3 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 15000 MWD/MTU (Typical)

4.3-11-4 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 40000 MWD/MTU (Typical)

4.3-11-5 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 0% Voids 0 MWD/MTU (Typical)

4.3-11-6 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 80% Voids 0 MWD/MTU (Typical)

4.3-11-7 FANP ATRIUM 10 Fuel Dominant Lattice Maximum Hot-Uncontrolled Local Peaking Factor vs Exposure (Typical)

4.3-12 Hot Excess Reactivity vs Exposure (Typical) 4.3-13 Shutdown Margin vs Exposure (Typical)

4.3-14 Vessel Fluence (R,0) Model for Azimuthal Flux Distribution

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxvi 4.3-15 Relative Vessel Flux Variation With Angular Position

4.3-16 Relative Vessel Flux Variation With Elevation

4.3-17 This Figure Has Been Deleted

4.3-18 This Figure Has Been Deleted

4.3-19 This Figure Has Been Deleted

4.3-20 This Figure Has Been Deleted

4.3-21 This Figure Has Been Deleted

4.3-22 This Figure Has Been Deleted

4.3-23 This Figure Has Been Deleted

4.3-24 This Figure Has Been Deleted

4.3-25 This Figure Has Been Deleted

4.3-26 This Figure Has Been Deleted

4.3-27 This Figure Has Been Deleted

4.3-28 This Figure Has Been Deleted

4.3-29 This Figure Has Been Deleted

4.3-30 This Figure Has Been Deleted

4.4-1 Schematic of Reactor Assembly Showing the Bypass Flow Paths

4.4-2 Damping Coefficient Versus Decay Ratio (Second Order Systems)

4.4-3 Hydrodynamic and Core Stability Model for Initial Core

4.4-4 Deleted

4.4-5 Power-Flow Operating Map SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxvii 4.4-6A Deleted

4.4-6B Deleted

4.4-6C Deleted

4.4-7a 10 Cent Rod Reactivity Step at 51.5% Rated Power (Natural Circulation)

4.4-7b 10 psi Pressure Regulator Setpoint Step at 51.5% Rated Power (Natural Circulation)

4.4-7c 6-9 Inch Level Setpoint Step at 51.5% Rated Power (Natural Circulation)

4.4-8a 10 Cent Rod Reactivity Step at 105% Rated Power and 100% Rated Flow 4.4-8b 10 psi Pressure Regulator Setpoint Step at 105% Rated Power and 100% Rated Flow

4.4-8c 6-inch Level Setpoint Step at 105% Rated Power and 100% Rated Flow 4.4-8d 10% Load Demand Step at 105% Rated Power and 100% Rated Flow

4.4-9a 10 Cent Rod Reactivity Step at 68% Rated Power and 51.5% Rated Flow 4.4-9b 10 psi Pressure Regulator Step at 68% Rated Power and 51.5% Rated Flow 4.4-9c 6-inch Water Level Setpoint Step at 60% Rated Power and 51.5%

Rated Flow 4.4-9d 10% Load Demand Step at 68% Rated Power and 51.5% Rated Flow

4.4-10 Deleted

4.6-1 Control Rod to Control Rod Drive Coupling SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxviii 4.6-2 Control Rod Drive Unit

4.6-3 Control Rod Drive Schematic

4.6-4 Control Rod Drive (Cutaway)

4.6-5a Control Rod Drive - Part A

4.6-5b P&ID Control Rod Drive - Part B

4.6-6 Control Rod Drive System Process Diagram and Data

4.6-7 Control Rod Drive Hydraulic Control Unit

4.6-8 Control Rod Drive Housing Support

NOTE: Additional Figures are presented in NEDE 20944/20944-P.

SSES-FSARNIMSRev.60FSARRev.655-iCHAPTER5REACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSTABLEOFCONTENTSTEXTSectionTitle5.1

SUMMARY

DESCRIPTION 5.1.1SchematicFlowDiagram5.1.2PipingandInstrumentationDiagram5.1.3PlanandElevationDrawings5.2INTEGRITYOFREACTORCOOLANTPRESSUREBOUNDARY 5.2.1CompliancewithCodesandCodeCases 5.2.1.1Compliancewith10CFR50,Section50.55a5.2.1.2ApplicableCodeCases5.2.2OverpressureProtection 5.2.2.1DesignBasis 5.2.2.1.1SafetyDesignBases5.2.2.1.2PowerGenerationDesign5.2.2.1.3Discussion5.2.2.1.4SafetyValveCapacity5.2.2.2DesignEvaluation 5.2.2.2.1MethodofAnalysis5.2.2.2.2SystemDesign5.2.2.2.2.1OperatingConditions5.2.2.2.2.2Transients5.2.2.2.2.3Scram5.2.2.2.2.4Safety/ReliefValveTransientAnalysisSpecifications5.2.2.2.2.5SafetyValveCapacity5.2.2.2.3EvaluationofResults5.2.2.2.3.1SafetyValveCapacity SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-ii5.2.2.2.3.2PressureDropinInletandDischarge5.2.2.3Piping&InstrumentDiagrams5.2.2.4EquipmentandComponentDescription5.2.2.4.1Description5.2.2.4.2DesignParameters5.2.2.4.2.1Safety/ReliefValve 5.2.2.5MountingofPressureReliefDevices5.2.2.6ApplicableCodesandClassification5.2.2.7MaterialSpecification5.2.2.8ProcessInstrumentation5.2.2.9SystemReliability5.2.2.10InspectionandTesting5.2.3ReactorCoolantPressureBoundaryMaterials 5.2.3.1MaterialSpecifications5.2.3.2CompatibilitywithReactorCoolant5.2.3.2.1PWRChemistryofReactorCoolant5.2.3.2.2BWRChemistryofReactorCoolant5.2.3.2.3CompatibilityofConstructionMaterialswithReactorCoolant5.2.3.2.4CompatibilityofConstructionMaterialswithExternalInsulationandReactorCoolant5.2.3.3FabricationandProcessingofFerriticMaterials 5.2.3.3.1FractureToughness 5.2.3.3.1.1CompliancewithCodeRequirements5.2.3.3.1.2AcceptableFractureEnergyLevels5.2.3.3.1.3OperatingLimitsDuringHeatup,Cooldown,andCoreOperation5.2.3.3.1.4TemperatureLimitsforISIHydrostaticorLeakPressureTests5.2.3.3.1.5TemperatureLimitsforBoltup5.2.3.3.1.6ReactorVesselAnnealing5.2.3.3.2ControlofWelding SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-iii5.2.3.3.2.1ControlofPreheatTemperatureEmployedforWeldingofLowAlloySteel.RegulatoryGuide1.50(REV.0)5.2.3.3.2.2ControlofElectroslagWeldProperties.RegulatoryGuide1.34(REV.0) 5.2.3.3.2.3WelderQualificationforAreasofLimitedAccessibility.RegulatoryGuide1.71(REV0)5.2.3.3.3NondestructiveExaminationofFerriticTubularProducts5.2.3.4FabricationandProcessingofAusteniticStainlessSteels5.2.3.4.1AvoidanceofStressCorrosionCracking 5.2.3.4.1.1AvoidanceofSignificantSensitization5.2.3.4.1.2ProcessControlstoMinimizeExposuretoContaminants5.2.3.4.1.3ColdWorkedAusteniticStainlessSteels5.2.3.4.2ControlofWelding 5.2.3.4.2.1AvoidanceofHotCracking5.2.3.4.2.2ElectroslagWelds5.2.3.4.2.3WelderQualificationforAreasofLimitedAccessibility.RegulatoryGuide1.71(Rev.0)5.2.3.4.3NondestructiveExaminationofTubularProducts.RegulatoryGuide1.66(Rev.0)5.2.4In-ServiceInspectionandTestingofReactorCoolantPressureBoundary 5.2.4.1SystemBoundarySubjecttoInspection5.2.4.2Accessibility5.2.4.3ExaminationTechniquesandProcedures5.2.4.4InspectionIntervals5.2.4.5EvaluationofExaminationResults5.2.4.6SystemLeakageandHydrostaticPressureTests5.2.4.7AugmentedInserviceInspectiontoProtectAgainstPostulatedPipingFailures5.2.5DetectionofLeakageThroughReactorCoolantPressureBoundary 5.2.5.1LeakageDetectionMethods SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-iv5.2.5.1.1DetectionofAbnormalLeakageWithinthePrimaryContainment(NSS-Systems)5.2.5.1.2DetectionofAbnormalLeakageWithinthePrimaryContainment(Non-NSSS)5.2.5.1.2.1PrimaryContainmentTemperatureMonitoringSystem5.2.5.1.2.2PrimaryContainmentPressureMonitoringSystem5.2.5.1.2.3PrimaryContainmentAtmosphereMonitoring;AirborneRadioactivityMonitoring5.2.5.1.2.3.1SensitivityandResponseTime 5.2.5.1.2.4DrywellFloorDrainSumpMonitoringSystem5.2.5.1.2.4.1SystemDescription5.2.5.1.2.4.2Instrumentation5.2.5.1.2.4.3DrywellEquipmentDrainTankLevelMonitoringSystem5.2.5.1.2.4.4SensitivityandResponseTimeofMeasurement5.2.5.1.2.4.5SignalCorrelationandCalibration5.2.5.1.2.4.6SeismicQualifications5.2.5.1.2.4.7TestingandCalibration5.2.5.1.3DetectionofAbnormalLeakageOutsidethePrimaryContainment 5.2.5.2LeakDetectionDevicesforNSS-System5.2.5.3LimitsforReactorCoolantLeakage5.2.5.3.1TotalLeakageRate5.2.5.3.2NormallyExpectedLeakageRate5.2.5.4UnidentifiedLeakageInsidetheDrywell 5.2.5.4.1UnidentifiedLeakageRate5.2.5.4.2SensitivityandResponseTimes5.2.5.4.3LengthofThrough-WallFlaw5.2.5.4.4MarginsofSafety5.2.5.4.5CriteriatoEvaluatetheAdequacyandMarginoftheLeakDetectionSystem5.2.5.5DifferentiationBetweenIdentifiedandUnidentifiedLeaks5.2.5.6SensitivityandOperabilityTests SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-v5.2.5.7SafetyInterfaces5.2.5.8TestingandCalibration5.2.6References 5.3REACTORVESSEL 5.3.1ReactorVesselMaterials 5.3.1.1MaterialsSpecifications5.3.1.2SpecialProcessesUsedforManufacturingandFabrication5.3.1.3SpecialMethodsforNondestructiveExamination5.3.1.4SpecialControlsforFerriticandAusteniticStainlessSteels5.3.1.4.1ComplianceWithRegulatoryGuides 5.3.1.4.1.1RegulatoryGuide1.31(Rev.1),ControlofStainlessSteelWelding5.3.1.4.1.2RegulatoryGuide1.34(12/72),ControlofElectroslagWeldProperties5.3.1.4.1.2RegulatoryGuide1.34,12/72ControlofElectroslagWeldProperties 5.3.1.4.1.3RegulatoryGuide1.43(5/73),ControlofStainlessSteelWeldCladdingofLow-AlloySteelComponents5.3.1.4.1.4RegulatoryGuide1.44(5/73),ControloftheUseofSensitizedStainlessSteel5.3.1.4.1.5RegulatoryGuide1.50(5/73),ControlofPreheatTemperatureforWeldingLow-AlloySteel5.3.1.4.1.6RegulatoryGuide1.71(12/73),WelderQualificationforAreasofLimitedAccessibility5.3.1.4.1.7RegulatoryGuide1.99(Rev.2),RadiationEmbrittlementofReactorVesselMaterials5.3.1.5FractureToughness 5.3.1.5.1Compliancewith10CFR50AppendixG SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-vi5.3.1.5.1.1IntentofProposedApproach5.3.1.5.1.2OperatingLimitsBasedonFractureToughness5.3.1.5.1.3OperatingLimitsDuringHeatup,Cool-downandCoreOperation5.3.1.5.1.4TemperatureLimitsforISIHydrostaticorLeakPressureTests5.3.1.5.1.5AdjustedReferenceTemperatureForLimitingCoreBeltlineMaterial5.3.1.5.1.6TemperatureLimitsforBoltup5.3.1.5.1.7ReactorVesselAnnealing5.3.1.6MaterialSurveillance 5.3.1.6.1Compliancewith"ReactorVesselMaterialSurveillanceProgramRequirements"5.3.1.6.2NeutronFluxandFluenceCalculations5.3.1.6.3PositioningofSurveillanceCapsulesandMethodofAttachment5.3.1.6.4TimeandNumberofDosimetryMeasurements5.3.1.7ReactorVesselFasteners 5.3.2Pressure-TemperatureLimits 5.3.2.1LimitCurves5.3.2.2OperatingProcedures5.3.3ReactorVesselIntegrity 5.3.3.1Design5.3.3.1.1Description5.3.3.1.1.1ReactorVessel5.3.3.1.1.2ShroudSupport5.3.3.1.1.3ProtectionofClosureStuds5.3.3.1.2SafetyDesignBases5.3.3.1.3PowerGenerationDesignBasis5.3.3.1.4ReactorVesselDesignData5.3.3.1.4.1VesselSupport5.3.3.1.4.2ControlRodDriveHousings5.3.3.1.4.3In-CoreNeutronFluxMonitorHousings5.3.3.1.4.4ReactorVesselInsulation5.3.3.1.4.5ReactorVesselNozzles SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-vii5.3.3.1.4.6MaterialsandInspections5.3.3.1.4.7ReactorVesselSchematic5.3.3.2MaterialsofConstruction5.3.3.3FabricationMethods5.3.3.4InspectionRequirements5.3.3.5ShipmentandInstallation5.3.3.6OperatingConditions5.3.3.7InserviceSurveillance5.3.4References5.4COMPONENTANDSUBSYSTEMDESIGN 5.4.1ReactorRecirculationPumps 5.4.1.1SafetyDesignBases5.4.1.2PowerGenerationDesignBases5.4.1.3Description5.4.1.4SafetyEvaluation5.4.1.5InspectionandTesting5.4.2SteamGenerators(PWR)5.4.3ReactorCoolantPiping5.4.4MainSteamlineFlowRestrictors5.4.4.1SafetyDesignBases5.4.4.2Description5.4.4.3SafetyEvaluation5.4.4.4InspectionandTesting5.4.5MainSteamlineIsolationSystem 5.4.5.1SafetyDesignBases5.4.5.2Description5.4.5.3SafetyEvaluation5.4.5.4InspectionandTesting5.4.6ReactorCoreIsolationCoolingSystem5.4.6.1DesignBases5.4.6.1.1ResidualHeatandIsolation SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-viii5.4.6.1.1.1ResidualHeat5.4.6.1.1.2Isolation5.4.6.1.2Reliability,Operability,andManualOperation 5.4.6.1.2.1ReliabilityandOperability(Alsoseesubsection5.4.6.2.4)5.4.6.1.2.2ManualOperation(Alsoseesubsection5.4.6.2.5.2and5.4.6.2.5.35.4.6.1.3LossofOffsitePower5.4.6.1.4PhysicalDamage5.4.6.1.5Environment5.4.6.2SystemDesign 5.4.6.2.1General 5.4.6.2.1.1Description5.4.6.2.1.2Diagrams5.4.6.2.1.3Interlocks5.4.6.2.2EquipmentandComponentDescription 5.4.6.2.2.1DesignConditions5.4.6.2.2.2DesignParameters5.4.6.2.3ApplicableCodesandClassifications5.4.6.2.4SystemReliabilityConsiderations5.4.6.2.5SystemOperations5.4.6.2.5.1AutomaticOperation5.4.6.2.5.2TestLoopOperation5.4.6.2.5.3SteamCondensing(HotStandby)Operation5.4.6.2.5.4LimitingSingleFailure5.4.6.3PerformanceEvaluation5.4.6.4PreoperationalTesting5.4.6.5SafetyInterfaces5.4.7ResidualHeatRemovalSystem 5.4.7.1DesignBases SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-ix5.4.7.1.1FunctionalDesignBasis5.4.7.1.1.1ResidualHeatRemovalMode(ShutdownCoolingMode)5.4.7.1.1.2LowPressureCoolantInjection(LPCI)Mode5.4.7.1.1.3SuppressionPoolCoolingMode5.4.7.1.1.4ContainmentSprayCoolingMode5.4.7.1.1.5ReactorSteamCondensingMode5.4.7.1.1.6FuelPoolCoolingMode5.4.7.1.2DesignBasisforIsolationofRHRSystemfromReactorCoolantSystem5.4.7.1.3DesignBasisforPressureReliefCapacity5.4.7.1.4DesignBasiswithRespecttoGeneralDesignCriteria55.4.7.1.5DesignBasisforReliabilityandOperability5.4.7.1.6DesignBasisforProtectionfromPhysicalDamage5.4.7.2SystemsDesign 5.4.7.2.1SystemDiagrams5.4.7.2.2EquipmentandComponentDescription5.4.7.2.3ControlsandInstrumentation5.4.7.2.4ApplicableCodesandClassifications5.4.7.2.5ReliabilityConsiderations5.4.7.2.6ManualAction5.4.7.3PerformanceEvaluation 5.4.7.3.1ShutdownWithAllComponentsAvailable5.4.7.3.2ShutdownWithMostLimitingFailure5.4.7.4PreoperationalTesting 5.4.8ReactorWaterCleanupSystem 5.4.8.1DesignBases 5.4.8.1.1SafetyDesignBases5.4.8.1.2PowerGenerationDesignBases5.4.8.2SystemDescription5.4.8.3SystemEvaluation SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-x5.4.9MainSteamLinesandFeedwaterPiping5.4.9.1SafetyDesignBases5.4.9.2PowerGenerationDesignBases5.4.9.3Description5.4.9.4SafetyEvaluation5.4.9.5InspectionandTesting5.4.10Pressurizer5.4.11PressurizerReliefDischargeSystem5.4.12Valves5.4.12.1SafetyDesignBases5.4.12.2Description5.4.12.3SafetyEvaluation5.4.12.4InspectionandTesting5.4.13SafetyandReliefValves 5.4.13.1SafetyDesignBases5.4.13.2Description5.4.13.3SafetyEvaluation5.4.13.4InspectionandTesting5.4.14ComponentSupports 5.4.14.1SafetyDesignBases5.4.14.2Description5.4.14.3SafetyEvaluation5.4.14.4InspectionandTesting5.4.15HighPressureCoolantInjection(HPCI)System5.4.16CoreSpray(CS)System5.4.17StandbyLiquidControl(SLC)System5.4.18References SSES-FSARNIMSRev.60CHAPTER5TABLESNumberTitleFSARRev.655-xi5.1-1DesignandPerformanceCharacteristicsoftheReactorCoolantSystemandItsComponents5.2-1ReactorCoolantPressureBoundaryComponentsCodeCaseInterpretations5.2-2NuclearSystemSafety/ReliefSetPointsUnits1and2 5.2-3DesignTemperature,PressureandMaximumTestPressureforRCPBComponents5.2-4ReactorCoolantPressureBoundaryMaterials 5.2-5BWRWaterChemistry 5.2-6SystemsWhichMayInitiateDuringOverpressureEvent 5.2-7WaterSampleLocations 5.2-8SummaryofIsolation/AlarmofSystemMonitoredandLeakDetectionMethodsUsed5.2-9SequenceofEventsforMSIVIsolationClosure(SeeFigure5.2-13) 5.2.9AThisTableHasBeenDeleted 5.2-10RCPBComponentsinCompliancewith10CFR50.55(a)(2)(ii) 5.2-11IdentifiedLeakagesintotheDrywellEquipmentDrainTank 5.2-12UnidentifiedLeakagesintotheDrywellFloorDrainSump 5.2-13EstimatedMonitorResponses 5.2-14RCPBLeakDetectionMonitorsInsidePrimaryContainmentDrywell 5.3-1aAppendixGMatrixForSusquehannaUnit1 5.3-1bAppendixHMatrixForSusquehannaSESUnit1 SSES-FSARNIMSRev.60CHAPTER5TABLESNumberTitleFSARRev.655-xii5.3-2aAppendixGMatrixForSusquehannaSESUnit25.3-2bAppendixHMatrixForSusquehannaSESUnit2 5.3-3ReactorVesselMaterialSurveillanceProgram-WithdrawalSchedule 5.4-1ThisTableHasBeenDeleted 5.4-2ReactorWaterCleanupSystemEquipmentDesignData 5.4-3RHRReliefValveData 5.4-4RCPBComponentDescription SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xiii5.1-1ThisFigureisDeleted5.1-2CoolantVolumesoftheBoilingWaterReactor 5.1-2A-1ThisFigureisDeleted 5.1-2A-2ThisFigureisDeleted 5.1-2BThisFigureisDeleted 5.1-3ThisFigureisDeleted 5.1-3A-1P&ID-Unit1NuclearBoiler 5.1-3A-2P&ID-Unit1NuclearBoiler 5.1-3BP&ID-Unit1NuclearBoilerVesselInstrumentation 5.1-4-1ReactorCoolantSystemPlan 5.1-4-2ReactorCoolantSystemElevation 5.1-4-3ReactorCoolantSystemElevation 5.2-1ThisFigureisDeleted 5.2-1AThisFigureisDeleted 5.2-2SimulatedSafety/ReliefValveSpringModeCharacteristicUsedforCapacitySizingAnalysis5.2-2ASimulatedSafety/ReliefValveSpringModeCharacteristic 5.2-3ThisFigureisDeleted 5.2-4ThisFigureisDeleted 5.2-5ThisFigureisDeleted 5.2-6SafetyValveLiftVersusTimeCharacteristic SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xiv5.2-7SchematicofSafetyValvewithAuxiliaryActuatingDevice5.2-8TypicalBWRFeedwaterCycle 5.2-9Conductancevs.pHasaFunctionofChlorideConcentrationofAqueousSolutionat25 C5.2-10CalculatedLeakRateVersusCrackLengthasaFunctionofAppliedHoopStress5.2-11AxialThrough-WallCrackLengthDataCorrelation 5.2-12RegionforSpringSafetyModeNominalSetpoint 5.2-13OverpressureProtectionAnalysis(MSIVClosurewithHighFluxScramTrip) 5.2-14OverpressureProtectionAnalysis(MSIVClosurewithHighFluxScramTrip) 5.3-1ReactorVessel 5.3-2FigureDeleted 5.3-3BracketforHolingSurveillanceCapsule 5.3-4aFigureDeleted-SeeUnit1TechSpecFigures3.4.10-1thru3.4.10-35.3-4bFigureDeleted-SeeUnit2TechSpecFigures3.4.10-1thru3.4.10-35.3-4cUnit1PredictedAdjustedReferenceTemperaturevs.EffectiveFullPowerYearsofOperation5.3-4dUnit2PredictedAdjustedReferenceTemperaturevs.EffectiveFullPowerYearsofOperation5.3-5ThisFigureisIntentionallyLeftBlank 5.4-1RecirculationSystemElevationandIsometric 5.4-2AThisFigureHasBeenDeleted SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xv5.4-2b-1ThisFigureHasBeenReplacedbyDwg.M-143,Sh.15.4-2b-2ThisFigureHasBeenReplacedbyDwg.M-143,Sh.2 5.4-2cThisFigureHasBeenReplacedbyDwg.B31-13,Sh.3 5.4-2DThisFigureisDeleted 5.4-3RecirculationPumpHead,NPSH,FlowandEfficiencyCurves 5.4-4aRHRSuctionStrainerDetails 5.4-4bRHRSuctionStrainerDetails 5.4-5OperatingPrincipleofJetPump 5.4-6CoreFloodingCapabilityofRecirculationSystem5.4-7MainSteamLineFlowRestrictorLocation 5.4-8ThisFigureHasBeenDeleted 5.4-9aThisFigureHasBeenReplacedbyDwg.M-149,Sh.1 5.4-9bThisFigureHasBeenReplacedbyDwg.M-150,Sh.1 5.4-10ThisFigureHasBeenReplacedbyDwg.M1-E51-81,Sh.1 5.4-11ThisFigureisIntentionallyLeftBlank 5.4-11-1ThisFigureisIntentionallyLeftBlank 5.4-11-2ThisFigureisIntentionallyLeftBlank 5.4-11-3ThisFigureisIntentionallyLeftBlank 5.4-11-4ThisFigureisIntentionallyLeftBlank 5.4-12ThisFigureisIntentionallyLeftBlank 5.4-12-1ThisFigureisIntentionallyLeftBlank SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xvi5.4-12-2ThisFigureisIntentionallyLeftBlank5.4-13ThisFigureisIntentionallyLeftBlank 5.4-13-1ThisFigureHasBeenReplacedbyDwg.M-151,Sh.1 5.4-13-2ThisFigureHasBeenReplacedbyDwg.M-151,Sh.2 5.4-13-3ThisFigureHasBeenReplacedbyDwg.M-151,Sh.3 5.4-13-4ThisFigureHasBeenReplacedbyDwg.M-151,Sh.4 5.4-14-1ThisFigureHasBeenReplacedbyDwg.M1-E11-3,Sh.1 5.4-14-2ThisFigureHasBeenReplacedbyDwg.M1-E11-3,Sh.2 5.4-15FigureDeleted 5.4-15AThisFigureHasBeenReplacedbyDwg.M1-G33-16,Sh.1 5.4-15BThisFigureHasBeenReplacedbyDwg.M1-G33-18,Sh.1 5.4-16ThisFigureHasBeenIntentionallyLeftBlank 5.4-16-1ThisFigureHasBeenReplacedbyDwg.M1-144,Sh.1 5.4-16-2ThisFigureHasBeenReplacedbyDwg.M1-144,Sh.2 5.4-16-3ThisFigureHasBeenReplacedbyDwg.M1-144,Sh.3 5.4-17AThisFigurehasbeenDeletedbecauseofDuplication(SeeFigure5.4-15a) 5.4-17BThisFigurehasbeenDeletedbecauseofDuplication(SeeFigure5.4-15b) 5.4-18ThisFigureHasBeenReplacedbyDwg.M-145,Sh.1 SSES-FSAR NIMS Rev. 62 FSAR Rev. 68 6-i CHAPTER 6 ENGINEERED SAFETY FEATURES TABLE OF CONTENTS TEXT Section Title 6.0 ENGINEERED SAFETY FEATURES

6.1 ENGINEERED SAFETY FEATURE MATERIALS

6.1.1 Metallic Materials

6.1.1.1 Materials Selection and Fabrication 6.1.1.1.1 NSSS Material Specifications 6.1.1.1.2 Compatibility of NSSS Construction Materials with Core Cooling Water and Containment Sprays 6.1.1.1.3 NSSS Controls for Austenitic Stainless Steel 6.1.1.2 Composition, Compatibility, and Stability of Containment and Core Spray Coolants

6.1.2 Organic Materials

6.1.3 Post-Accident Chemistry

6.2 CONTAINMENT SYSTEMS

6.2.1 Primary Containment Functional Design

6.2.1.1 Pressure Suppression Containment 6.2.1.1.1 Design Basis 6.2.1.1.2 Design Features 6.2.1.1.2.1 Protection from Dynamic Effects 6.2.1.1.2.2 Codes, Standards, and Guides 6.2.1.1.2.3 Functional Capability Tests 6.2.1.1.2.4 External Pressure Loading Conditions 6.2.1.1.2.5 Trapped Water that Cannot Return to Containment Sump 6.2.1.1.2.6 Containment and Subcompartment Atmosphere 6.2.1.1.3 Design Evaluation 6.2.1.1.3.1 Summary Evaluation 6.2.1.1.3.2 Containment Design Parameters 6.2.1.1.3.2.1 Downcomer Vent Flow Loss Coefficient 6.2.1.1.3.2.2 Vacuum Breaker Flow Loss Coefficient SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-ii 6.2.1.1.3.3 Accident Response Analysis 6.2.1.1.3.3.1 Recirculation Line Rupture 6.2.1.1.3.3.1.1 Assumptions for Reactor Blowdown 6.2.1.1.3.3.1.2 Assumptions for Containment Pressurization 6.2.1.1.3.3.1.3 Assumptions for Long-Term Cooling 6.2.1.1.3.3.1.4 Initial Conditions for Accident Analyses 6.2.1.1.3.3.1.5 Short-Term Accident Response 6.2.1.1.3.3.1.6 Long-Term Accident Responses 6.2.1.1.3.3.1.7 Energy Balance During Accident 6.2.1.1.3.3.1.8 Chronology of Accident Events 6.2.1.1.3.3.2 Main Steamline Break 6.2.1.1.3.3.3 Hot Standby Accident Analysis 6.2.1.1.3.3.4 Intermediate Size Breaks 6.2.1.1.3.3.5 Small Size Breaks 6.2.1.1.3.3.5.1 Reactor System Blowdown Considerations 6.2.1.1.3.3.5.2 Containment Response 6.2.1.1.3.3.5.3 Recovery Operations 6.2.1.1.3.3.5.4 Drywell Design Temperature Considerations 6.2.1.1.3.4 Accident Analysis Models 6.2.1.1.3.4.1 Short-Term Pressurization Model 6.2.1.1.3.4.2 Long-Term Cooling Mode 6.2.1.1.3.4.3 Analytical Assumptions 6.2.1.1.3.4.4 Energy Balance Considerations 6.2.1.1.3.4.5 Containment Thermodynamic Conditions 6.2.1.1.3.4.6 Solution of Equations 6.2.1.1.4 Negative Pressure Design Evaluation 6.2.1.1.4.1 Glossary of Terms Used in Subsection 6.2.1.1.4 6.2.1.1.5 Suppression Pool Bypass Effects 6.2.1.1.5.1 Protection Against Bypass Paths 6.2.1.1.5.2 Reactor Blowdown Conditions and Operator Response 6.2.1.1.5.3 Analytical Assumptions 6.2.1.1.5.4 Analytical Results 6.2.1.1.6 Suppression Pool Dynamic Loads 6.2.1.1.7 Asymmetric Loading Conditions 6.2.1.1.8 Containment Environment Control 6.2.1.1.9 Post-Accident Monitoring 6.2.1.2 Containment Subcompartments 6.2.1.3 Mass and Energy Release Analyses for Postulated Loss-of-Coolant Accidents 6.2.1.3.1 Mass and Energy Release Data SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-iii 6.2.1.3.2 Energy Sources 6.2.1.3.3 Reactor Blowdown Model Description 6.2.1.3.4 Effects of Metal-Water Reaction 6.2.1.3.5 Thermal Hydraulic Data for Reactor Analysis

6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures Inside Containment

6.2.1.5 Minimum Containment Pressure Analysis for Performance Capability Studies on Emergency Core Cooling System

6.2.1.6 Testing and Inspection 6.2.1.7 Instrumentation Requirements 6.2.1.8 Response to NRC Generic Letter (GL) 96-06 6.2.1.8.1 Drywell Cooling Water hammer and Two-Phase Flow 6.2.1.8.1.1 Containment Cooling 6.2.1.8.1.2 Containment Integrity 6.2.1.8.1.3 Closed Loop System Overpressurization 6.2.1.8.1.3.1 Reactor Building Closed Cooling Water/Reactor Building Cooling Water (RBCCW/RBCW) 6.2.1.8.1.3.2 Drywell Floor Drain Sump 6.2.1.8.2 Containment Penetration Overpressurization

6.2.2 Containment Heat Removal System

6.2.2.1 Design Basis 6.2.2.2 Containment Cooling System Design 6.2.2.3 Design Evaluation of the Containment Cooling System 6.2.2.3.1 Summary of Containment Cooling Analysis 6.2.2.4 Tests and Inspections 6.2.2.5 Instrumentation Requirements

6.2.3 Secondary Containment Functional Design

6.2.3.1 Design Bases 6.2.3.2 System Design 6.2.3.2.1 Secondary Containment Design 6.2.3.2.2 Secondary Containment Isolation System 6.2.3.2.3 Secondary Containment Bypass Leakage (SCBL) 6.2.3.2.3.1 Water Seals 6.2.3.3 Design Evaluation SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-iv 6.2.3.4 Tests and Inspections 6.2.3.5 Instrumentation Requirements

6.2.4 Containment Isolation System

6.2.4.1 Design Bases 6.2.4.2 System Design 6.2.4.3 Design Evaluation 6.2.4.3.1 Evaluation Against General Design Criterion 54 6.2.4.3.1.1 Operability and Leak Tests 6.2.4.3.2 Evaluation Against General Design Criterion 55 6.2.4.3.2.1 Feedwater Line 6.2.4.3.2.2 Recirculation Pump Seal Water Supply Line 6.2.4.3.2.3 Control Rod Drive Lines 6.2.4.3.2.4 RCIC System Steamlines 6.2.4.3.2.5 Standby Liquid Control System Lines 6.2.4.3.2.6 Reactor Water Cleanup System 6.2.4.3.2.7 HPCI System Steamlines 6.2.4.3.2.8 Main Steamlines 6.2.4.3.2.9 CS Influent Penetrations 6.2.4.3.2.10 RHR Penetrations Connected to the RPV 6.2.4.3.3 Evaluation Against General Design Criterion 56 6.2.4.3.3.1 Containment Purge 6.2.4.3.3.2 RCIC Turbine Exhaust, Vacuum Pump Discharge, and RCIC Pump Minimum Flow Bypass

6.2.4.3.3.3 HPCI Turbine Exhaust and HPCI Pump Minimum Flow Bypass 6.2.4.3.3.4 RCIC and HPCI Turbine Exhaust Vacuum Breaker Lines

6.2.4.3.3.5 Reactor Building Closed Cooling Water and Reactor Building Chilled Water Supplies and Returns

6.2.4.3.3.6 Post-LOCA Atmosphere Sampling Lines 6.2.4.3.3.7 Liquid Radwaste System Equipment and Floor Drains 6.2.4.3.3.8 Suppression Pool Cleanup and Drain 6.2.4.3.3.9 Containment Instrument Gas Supply to Containment Vacuum Relief Valves

6.2.4.3.3.10 Traversing Incore Probe (TIP) Guide Tubes 6.2.4.3.4 Evaluation Against General Design Criterion 57 6.2.4.3.5 Evaluation Against Regulatory Guide 1.11 (Rev. 1)

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-v 6.2.4.3.6 GDC 56 Isolation Provisions With A Single Isolation Valve Outside Containment

6.2.4.3.6.1 Core Spray (CS) Influent Penetrations 6.2.4.3.6.2 Containment Spray and RHR Pump Test and Minimum Flow Lines 6.2.4.3.6.3 HPCI, RCIC, CS, and RHR Pump Suction Lines 6.2.4.3.6.4 RHR Combined Relief Valve Discharge and Heat Exchanger Vent Lines

6.2.4.3.7 Failure Mode and Effects Analyses for Containment Isolation 6.2.4.4 Tests and Inspections

6.2.5 Combustible Gas Control in Containment

6.2.5.1 Design Bases 6.2.5.2 System Design 6.2.5.3 Design Evaluation 6.2.5.4 Test and Inspections 6.2.5.5 Instrumentation Requirements 6.2.5.5.1 Hydrogen Recombiner System 6.2.5.5.2 Containment Hydrogen Purge Subsystem

6.2.5.5.3 Instrumentation Requirements for Primary Containment Atmosphere Monitoring System (Hydrogen and Oxygen Analyzer)

6.2.6 Primary Reactor Containment Leakage Rate Testing 6.2.6.1 Primary Reactor Containment Integrated Leakage Rate Test 6.2.6.2 Primary Containment Penetration Leakage Rate Test 6.2.6.3 Primary Containment Isolation Valve Leakage Rate Tests 6.2.6.4 Scheduling and Reporting of Periodic Tests 6.2.6.5 Special Testing Requirements 6.2.6.5.1 Drywell to Pressure Suppression Chamber Atmosphere Bypass Area Test

6.2.6.5.1.1 High Pressure Leak Test 6.2.6.5.l.2 Low Pressure Leak Test

6.2.7 References

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-vi 6.3 EMERGENCY CORE COOLING SYSTEMS

6.3.1 Design Bases and Summary Description

6.3.1.1 Design Bases 6.3.1.1.1 Performance and Functional Requirements 6.3.1.1.2 Reliability Requirements 6.3.1.1.3 ECCS Requirements for Protection from Physical Damage 6.3.1.1.4 ECCS Environmental Design Basis 6.3.1.2 Summary Descriptions of ECCS 6.3.1.2.1 High Pressure Coolant Injection 6.3.1.2.2 Core Spray 6.3.1.2.3 Low Pressure Coolant Injection 6.3.1.2.4 Automatic Depressurization System

6.3.2 System Design

6.3.2.1 Schematic Piping and Instrumentation Diagrams 6.3.2.2 Equipment and Component Descriptions 6.3.2.2.1 High Pressure Coolant Injection (HPCI) System 6.3.2.2.1.1 NPSH Available with Suction from the Condensate Storage Tank 6.3.2.2.1.2 NPSH Available with Suction from the Suppression Pool 6.3.2.2.2 Automatic Depressurization System (ADS) 6.3.2.2.3 Core Spray (CS) System 6.3.2.2.3.1 NPSH Available for CS 6.3.2.2.4 Low Pressure Coolant Injection (LPCI) System 6.3.2.2.4.1 NPSH Available for RHR 6.3.2.2.5 Discharge Line Fill System 6.3.2.3 Applicable Codes and Classification 6.3.2.4 Materials Specifications and Compatibility 6.3.2.5 System Reliability 6.3.2.6 Protection Provisions 6.3.2.7 Provisions for Performance Testing 6.3.2.8 Manual Actions 6.3.2.9 Position Verification for Manual Valves

6.3.3 ECCS Performance Evaluation

6.3.3.1 ECCS Bases for Technical Specifications 6.3.3.2 Acceptance Criteria for ECCS Performance 6.3.3.3 Single Failure Considerations SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-vii 6.3.3.4 System Performance During the Accident 6.3.3.5 Use of Dual Function Components for ECCS 6.3.3.6 Limits on ECCS System Parameters 6.3.3.7 ECCS Analyses for LOCA 6.3.3.7.1 LOCA Analysis Procedures and Input Variables 6.3.3.7.2 Accident Description 6.3.3.7.3 Break Spectrum Calculations 6.3.3.7.4 Large Recirculation Line Break Calculations 6.3.3.7.5 Transition Recirculation Line Break Calculations 6.3.3.7.6 Small Recirculation Line Break Calculations 6.3.3.7.7 Calculations for Other Break Locations 6.3.3.8 LOCA Analysis Conclusions

6.3.4 Tests and Inspections

6.3.4.1 ECCS Performance Tests 6.3.4.2 Reliability Tests and Inspections 6.3.4.2.1 HPCI Testing 6.3.4.2.2 ADS Testing 6.3.4.2.3 CS Testing 6.3.4.2.4 LPCI Testing

6.3.5 Instrumentation Requirements

6.3.6 NPSHA Margin and Vortex Formation After a Passive Failure in a Water Tight ECCS Pump Room 6.3.7 References

6.4 HABITABILITY SYSTEMS

6.4.1 Design Bases

6.4.2 System Design

6.4.2.1 Control Structure Envelope 6.4.2.2 Ventilation System Design 6.4.2.3 Leaktightness 6.4.2.4 Interaction with Other Zones and Pressure-Containing Equipment 6.4.2.5 Shielding Design

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-viii 6.4.3 System Operational Procedures

6.4.4 Design Evaluations

6.4.4.1 Radiological Protection 6.4.4.2 Toxic Gas Protection

6.4.5 Testing and Inspection

6.4.6 Instrumentation Requirements

6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS

6.5.1 Engineered Safety Feature (ESF) Filter Systems

6.5.1.1 Standby Gas Treatment System (SGTS) 6.5.1.1.1 Design Bases 6.5.1.1.2 System Design 6.5.1.1.3 Design Evaluation 6.5.1.1.4 Tests and Inspections 6.5.1.1.5 Instrument Requirements 6.5.1.1.6 Materials 6.5.1.2 Control Structure Emergency Outside Air Supply System (OV-101) (CSEOASS)

6.5.1.2.1 Design Bases 6.5.1.2.2 System Design 6.5.1.2.3 Design Evaluation 6.5.1.2.4 Tests and Inspections 6.5.1.2.5 Instrumentation Requirements 6.5.1.2.6 Materials

6.5.2 Containment Spray Systems

6.5.3 Fission Product Control System

6.5.3.1 Primary Containment 6.5.3.2 Secondary Containment

6.5.4 Ice Condenser as a Fission Product Cleanup System

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-ix 6.5.5 References

6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS

6.6.1 Components Subject to Examination

6.6.2 Accessibility

6.6.2.1 Piping and Component Welds 6.6.2.2 Insulation Removal 6.6.2.3 Inaccessible Class 3 Piping

6.6.3 Examination Techniques and Procedures

6.6.4 Inspection Intervals

6.6.5 Examination Categories and Requirements

6.6.6 Evaluation of Examination Results

6.6.7 System Pressure Tests

6.6.8 Augmented Inservice Inspection to Protect Against Postulated Piping Failures

6.6.9 Containment Inspections

6.7 MAIN STEAM ISOLATION VALVE LEAKAGE ISOLATED CONDENSER TREATMENT METHOD

6.7.1 Design Bases

6.7.1.1 Safety Criteria 6.7.1.2 Regulatory Acceptance Criteria 6.7.1.3 Leakage Rate Requirements

6.7.2 System Description

6.7.2.1 General Description 6.7.2.1.1 Primary Pathway 6.7.2.1.2 Alternate Pathways SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-x 6.7.2.2 System Operation 6.7.2.3 Equipment Required

6.7.3 System Evaluation

6.7.3.1 Functional Protection Features 6.7.3.2 Effects of Single Active Failures 6.7.3.3 Effects of Seismic Induced Failures 6.7.3.4 Isolation Provisions 6.7.3.5 Leakage Protection Evaluation 6.7.3.6 Failure Mode and Effects Analysis 6.7.3.7 Influence on Other Safety Features 6.7.3.8 Radiological Evaluation

6.7.4 Instrumentation Requirements

6.7.5 Inspection and Testing

APPENDIX 6A Subcompartment Differential Pressure Considerations

APPENDIX 6B Compartment Differential Pressure Analysis Description

6B.1 FLUD Calculational Procedure 6B.1.1 Equation of State 6B.1.2 Compartment Thermodynamic State 6B.1.3 Compartment Initial Conditions 6B.1.4 Air and Vapor Component Flow Rates 6B.2 Energy Transfer Mechanisms 6B.2.1 Blowdown Energy 6B.2.2 Enthalpy Flow 6B.2.3 Compartment Heat Loads 6B.2.4 Unit Coolers 6B.2.5 Energy Balance 6B.2.6 Blowout Panel Activation 6B.2.7 Energy and Mass Conversion 6B.2.8 Eulerian Integration 6B.3 Thermodynamic Properties of Steam, Water, and Air 6B.4 References

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xi 6.1-1a NSSS Supplied Engineered Safety Features Component Materials

6.1-1b Engineered Safety Features Materials

6.1-2 Containment Components-Coating Schedule

6.1-3 Inventory of Qualified and Unqualified Containment Coatings

6.2-1 Containment Design Parameters

6.2-2 Engineered Safety Systems Inputs and Assumptions for Containment Response Analyses

6.2-3 This Table Has Been Deleted

6.2-3a Initial Plant Conditions for DBA-LOCA Containment Response

6.2-4 This Table Has Been Deleted

6.2-4a Input and Assumptions for the Short-Term DBA-LOCA Analysis

6.2-5 This Table Has Been Deleted

6.2-5a Input and Assumptions for the Long-Term DBA-LOCA Analysis

6.2-6 This Table Has Been Deleted 6.2-6a Containment Performance for DBA-LOCA

6.2-7 This Table Has Been Deleted

6.2-8 This Table Has Been Deleted

6.2-9 RPV Break Flow Data For Recirculation Line Break (102% P / 100% F)

6.2-9a This Table Has Been Deleted

6.2-10 RPV Break Flow Data For Main Steam Line Break (102% P / 100% F)

6.2-11 Core Decay Heat Following LOCA for Containment Analysis SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xii 6.2-12 Containment Penetration Data

6.2-12a Data on Instrument Lines Penetrating Containment

6.2-13 Parameters Used for the Evaluation of Combustible Gases in the Containment After a LOCA (HISTORICAL)

6.2-14 Primary Containment Atmosphere Monitoring System (Hydrogen/Oxygen Analyzer) System Level, Failure Mode and Effect Analysis

6.2-15 Evaluation of Potential Secondary Containment Bypass Leakage Pathways

6.2-15a This Table Has Been Deleted

6.2-16 Containment Hydrogen Recombiner System, System Level, Failure Mode and Effect Analysis

6.2-17 Information for the SSES Secondary Containment

6.2-18 Hydrogen Recombiner Design Characteristics

6.2-19 Type A Test Data

6.2-20 This Table Has Been Deleted

6.2-21 System Venting and Draining for Primary Containment Integrated Leakage Rate Test

6.2-22 Leakage Rate Test List

6.2-23 Initial and Boundary Conditions for Inadvertent Spray Actuation Study

6.2-24 Initial and Boundary Conditions For Drywell- Wetwell Bypass Leakage Study

6.2-25 Blowdown Data and Bypass Leakage

6.2-26 Long-term Blowdown Data for a Recirculation Line Break (Case D)

6.2-27 This Table Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xiii 6.3-1 This Table Has Been Renumbered to 6.3-1A

6.3-1A This Table Has Been Deleted

6.3-1B This Table Has Been Deleted

6.3-1B-2 Event Times For Limiting Recirculation Line Break 1.0 Deg Pump Suction Single Failure LPCI Valve Top Peaked Axial Power Distribution 102% Power

4031 Mwt 80 Mlbs/Hr Flow

6.3-2 This Table Has Been Deleted

6.3-3 Summary of Results of LOCA Analysis

6.3-3A This Table Has Been Deleted

6.3-3B This Table Has Been Deleted

6.3-3C Recirculation Line Break Results Highest Pct Cases Atrium Tm -10

6.3-4 This Table Has Been Deleted

6.3-5 Single Failures And Available Systems For Susquehanna

6.3-6 This Table Has Been Deleted

6.3-7 This Table Has Been Deleted 6.3-8 HPCI System Design Pa rameters 6.3-9 Manual Valves in the ECCS

6.3-10 Safety-Related Valves in the Drywell Subject to Spray Impingement

6.4-1 Control Structure Isolation Damper Leakage Characteristics and Closure Times 6.5-1 Engineered Safety Feature Filter System Design Parameters

6.5-2 Engineered Safety Feature Filter Systems Compliance with Recommendations of Regulatory Guide 1.52 SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xiv 6.5-3 Standby Gas Treatment System Failure Mode and Effect Analysis

6.5-4 Recirculation System Failure Mode and Effect Analysis

6.5-5 List of Materials Used in the Standby Gas Treatment System

6.5-6 List of Materials Used in the Emergency Outside Air Supply System

6.5-7 Zone Volumes and Their Estimated Recirculation Airflow Rates

6.7-1 Table Has Been Deleted

6A-1 Table Has Been Deleted

6A-1(a) Reactor Primary System Blowdown Flow Rates and Fluid Enthalpy-Recirculation Outlet Line Break

6A-1(b) Recirc. Outlet Line Break Blowdown Mass Flux Time History

6A-1(c) Reactor Primary System Blowdown Flow Rates and Fluid Enthalpy - Feedwater Line Break

6A-1(d) Feedwater Line Break Blowdown Mass Flux Time History

6A-2 Head Spray Line Break

6A-3 Susquehanna-Compartment Volumes Used in Reactor Vessel Shield Annulus Subcompartment Analysis

6A-4 Susquehanna-Flow Area and Coefficients Used in Reactor Vessel Shield Annulus Subcompartment Analysis

6A-5 Geometry Node Locations

6A-6 RPV Geometry Node Areas for Recirculation Outlet Line Break

6A-7 RPV Geometry Mode Areas for Feedwater Line Break

6A-8 Reactor Primary System Blowdown Flow Rates And Fluid Enthalpy - Recirculation Outlet Line Break

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xv 6.1-1 This Figure Has Been Deleted

6.2-1 Diagram of the Recirculation Line Break Location

6.2-2 Pressure Response for Recirculation Line Break

6.2-3 Temperature Response for Recirculation Line Break

6.2-4 Floor Differential Pressure For Recirculation Line Breaks

6.2-5 Vent Flow for Recirculation Line Break

6.2-6 This Figure Intentionally Left Blank

6.2-6-1 This Figure Has Been Deleted

6.2-6-2 This Figure Has Been Deleted

6.2-6-3 This Figure Has Been Deleted

6.2-7 Drywell Temperature Response - Long-Term

6.2-7-1 This Figure Has Been Deleted

6.2-7-2 This Figure Has Been Deleted

6.2-7-3 This Figure Has Been Deleted

6.2-8 Suppression Pool Temperature Response - Long-Term

6.2-8-1 This Figure Has Been Deleted

6.2-8-2 This Figure Has Been Deleted

6.2-8-3 This Figure Has Been Deleted

6.2-9 RHR Heat Removal Rate

6.2-9-1 This Figure Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xvi 6.2-9-2 This Figure Has Been Deleted

6.2-9-3 This Figure Has Been Deleted

6.2-10 This Figure Has Been Deleted

6.2-11 Pressure Response for Main Steamline Break

6.2-12 Temperature Response for Main Steamline Break

6.2-13 This Figure Intentionally Left Blank

6.2-14 This Figure Has Been Deleted

6.2-15 This Figure Has Been Deleted

6.2-16 Schematic of ECCS Loop

6.2-17 Allowable Leakage Capacity

6.2-18 Vessel Blowdown Rate for Recirculation Line Break

6.2-19 This Figure Deleted For Power Uprate

6.2-20 Vessel Blowdown Rate for Main Steamline Break

6.2-21 This Figure Has Been Deleted 6.2-22 This Figure Has Been Deleted

6.2-23 This Figure Intentionally Left Blank

6.2-24 Secondary Containment Boundary Outline - Unit 1 EL. 645'-0"

6.2-25 Secondary Containment Boundary Outline - Unit 1 EL. 670'-0"

6.2-26 Secondary Containment Boundary Outline - Unit 1 EL. 683'-0"

6.2-27 Secondary Containment Boundary Outline - Unit 1 EL. 719'-0"

6.2-28 Secondary Containment Boundary Outline - Unit 1 EL. 749'-1" SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xvii 6.2-29 Secondary Containment Boundary Outline - Unit 1 EL. 779'-1"

6.2-30 Secondary Containment Boundary Outline - Unit 1 EL. 818'-1"

6.2-31 Secondary Containment Boundary Outline - Unit 1 Section A-A

6.2-32 Secondary Containment Boundary Outline - Unit 1 Section B-B

6.2-33 Secondary Containment Boundary Outline - Unit 1 EL. 799'-1"

6.2-34 Secondary Containment Boundary Outline - Unit 2 EL. 645'-0"

6.2-35 Secondary Containment Boundary Outline - Unit 2 EL. 670'-0"

6.2-36 Secondary Containment Boundary Outline - Unit 2 EL. 683'-0"

6.2-37 Secondary Containment Boundary Outline - Unit 2 EL. 719'-0"

6.2-38 Secondary Containment Boundary Outline - Unit 2 EL. 749'-1"

6.2-39 Secondary Containment Boundary Outline - Unit 2 EL. 779'-1"

6.2-40 Secondary Containment Boundary Outline - Unit 2 EL. 818'-1"

6.2-41 Secondary Containment Boundary Outline - Unit 2 Section A-A

6.2-42 Secondary Containment Boundary Outline - Unit 2 Section B-B

6.2-43 Secondary Containment Boundary Outline - Unit 2 EL. 799'-1"

6.2-44 Containment Penetration Details

6.2-44A Containment Penetration Details

6.2-44B Containment Penetration Details

6.2-44C Containment Penetration Details

6.2-44D Containment Penetration Details

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xviii 6.2-44E Containment Penetration Details

6.2-44F Containment Penetration Details

6.2-44g Containment Penetration Details

6.2-44H Containment Penetration Details

6.2-44i Containment Penetration Details

6.2-44J Containment Penetration Details

6.2-44K Containment Penetration Details

6.2-44L Containment Penetration Details

6.2-44M Containment Penetration Details

6.2-45 This Figure Has Been Deleted

6.2-46 Energy Absorption Rate By the Coolant vs. Time After LOCA

6.2-47 Integrated Energy Absorbed By Coolant vs. Time After LOCA

6.2-48 Figure Deleted

6.2-49 Figure Deleted 6.2-50 Figure Deleted

6.2-51 Figure Deleted

6.2-52 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Zone I and Zone III Isolation

6.2-53 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Normal Plant Operation

6.2-54 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Zone III Isolation

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xix 6.2-55A This Figure Has Been Replaced by Dwg. M-157, Sh. 1

6.2.55B This Figure Has Been Replaced by Dwg. M-157, Sh. 2

6.2.55C This Figure Has Been Replaced by Dwg. M-157, Sh. 3

6.2-56 Drywell to Wetwell Downcomers

6.2-57 This Figure Has Been Deleted

6.2-57-1 Vacuum Breaker - DISC/ARM Assembly Unit 1

6.2-57-2 Vacuum Breaker - DISC/ARM Assembly Unit 2

6.2-57a-1 Containment Personnel Lock Door Penetrations

6.2-57a-2 Containment Personnel Lock Door Penetrations

6.2-57a-3 Containment Personnel Lock Penetrations

6.2-58 Deleted Renumbered To 6.2-58-1 & 6.2-58-2

6.2-58-1 Containment Personnel Lock Door Seals

6.2-58-2 Containment Personnel Lock Door Seals

6.2-59 Personnel Lock Inner Door Tie Downs 6.2-60 Secondary Containment Pressure Transient Post-LOCA

6.2-61 Model for Inadvertent Spray Actuation

6.2-62 Thermal Heat Removal Efficiency of Containment Atmosphere Spray

6.2-63 Drywell Pressure Response For Inadvertent Spray Actuation

6.2-64 Drywell Temperature Response For Inadvertent Spray Actuation

6.2-65 Differential Pressure Experienced Across the Diaphragm Slab During Inadvertent Actuation of the Drywell Spray

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xx 6.2-66A This Figure Has Been Intentionally Left Blank

6.2-66B RWCU Line Penetration

6.2-66C Suppression Pool Purification Line Penetration

6.2-66D This Figure Has Been Intentionally Left Blank

6.2-66E This Figure Has Been Intentionally Left Blank

6.2-66F Reactor Building Closed Cooling Water Line Penetration

6.2-66G Reactor Building Control Rod Drive Seismic Island

6.2-66H RBCCW Supply/Return lines at the Reactor Building to Turbine Building Interface

6.2-67 This Figure Has Been Replaced by Dwg. M-159, Sh. 1

6.2-68 This Figure Deleted For Power Uprate

6.2-69 This Figure Deleted For Power Uprate

6.2-70 Long-Term Energy Release Rate for a Recirculation Line Break

6.2-71 This Figure Has Been Deleted

6.2-72 TIP Guide Tube Isolation Control

6.3-1A This Figure Has Been Replaced by Dwg. M-155, Sh. 1

6.3-1B This Figure Has Been Replaced by Dwg. M-156, Sh. 1

6.3-2 This Figure Has Been Replaced by Dwg. M1-E41-4, Sh. 1

6.3-3 This Figure Has Been Deleted

6.3-3A High Pressure Coolant Injection Pump Speed Characteristics

6.3-4 This Figure Has Been Replaced by Dwg. M-152, Sh. 1

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxi 6.3-5 This Figure Has Been Replaced by Dwg. M1-E21-15, Sh. 1

6.3-6 This Figure Has Been Intentionally Left Blank

6.3-6A This Figure Has Been Intentionally Left Blank

6.3-7 thru These Figures Have Been Intentionally Left Blank

6.3-49

6.3-50 This Figure Has Been Deleted

6.3-51 This Figure Has Been Deleted

6.3-52 This Figure Has Been Deleted

6.3-53 This Figure Has Been Deleted

6.3-54 This Figure Has Been Deleted

6.3-55 This Figure Has Been Deleted

6.3-56 This Figure Has Been Deleted

6.3-57 This Figure Has Been Deleted

6.3-58 This Figure Has Been Deleted 6.3-59 This Figure Has Been Deleted

6.3-60 This Figure Has Been Deleted

6.3-61 This Figure Has Been Deleted

6.3-62 This Figure Has Been Deleted

6.3-63 This Figure Has Been Deleted

6.3-64 This Figure Has Been Deleted

6.3-65 This Figure Has Been Deleted SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxii 6.3-66 This Figure Has Been Deleted

6.3-67 This Figure Has Been Deleted

6.3-68 This Figure Has Been Deleted

6.3-69 This Figure Has Been Deleted

6.3-70 This Figure Has Been Deleted

6.3-71 This Figure Has Been Deleted

6.3-72 This Figure Has Been Deleted

6.3-73 This Figure Has Been Deleted

6.3-74 This Figure Has Been Deleted

6.3-75 This Figure Has Been Deleted

6.3-76 This Figure Has Been Deleted

6.3-77 Pump Characteristic Curves For HPCI Pumps

6.3-78 This Figure Has Been Deleted

6.3-79 This Figure Has Been Renumbered To 6.3-79A

6.3-79A This Figure Has Been Deleted

6.3-79B This Figure Has Been Deleted

6.3-79C Low Pressure Core Spray Flow vs. Head Used in LOCA Analysis (FANP Atrium -10 Fuel)

6.3-80 This Figure Has Been Renumbered To 6.3-80A

6.3-80A This Figure Has Been Deleted

6.3-80B This Figure Has Been Deleted SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxiii 6.3-80C RHR (LPCI) Flow vs. Head Characteristics Use in LOCA Analysis (FANP Atrium 10 fuel) 6.3-81 This Figure Has Been Deleted

6.3-82 This Figure Has Been Deleted

6.3-83 This Figure Has Been Deleted

6.3-84 This Figure Has Been Deleted

6.3-85 This Figure Has Been Deleted

6.3-86 This Figure Has Been Deleted

6.3-87 This Figure Has Been Deleted

6.3-88 This Figure Has Been Deleted

6.3-89 This Figure Has Been Deleted

6.3-90 This Figure Has Been Deleted

6.3-91 This Figure Has Been Deleted

6.3-92 This Figure Has Been Deleted 6.3-93 This Figure Has Been Deleted

6.3-94 This Figure Has Been Deleted

6.3-95 This Figure Has Been Deleted

6.3-96 This Figure Has Been Deleted

6.3-97 This Figure Has Been Deleted

6.3-98 This Figure Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxiv 6.3-99 This Figure Has Been Deleted

6.3-100 This Figure Has Been Deleted

6.3-101 This Figure Has Been Deleted

6.3-102 This Figure Has Been Deleted

6.3-103 This Figure Has Been Deleted

6.3-104 This Figure Has Been Deleted

6.3-105 This Figure Has Been Deleted

6.3-106 This Figure Has Been Deleted

6.3-107 This Figure Has Been Deleted

6.3-108 This Figure Has Been Deleted

6.3-109 This Figure Has Been Deleted

6.3-110 This Figure Has Been Deleted

6.3-111 This Figure Has Been Deleted

6.3-112 This Figure Has Been Deleted 6.3-113 This Figure Has Been Deleted

6.3-114 This Figure Has Been Deleted

6.3-115 This Figure Has Been Deleted

6.3-116 This Figure Has Been Deleted

6.3-117 This Figure Has Been Deleted

6.3-118 Characteristic Curves for Core Spray Pump

6.3-119 Characteristic Curves for LPCI Pump SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxv 6.3-120 Speed Characteristic Curves for HPCI Pumps - Unit 1

6.3-121 Speed Characteristic Curves for HPCI Pumps - Unit 2

6.3-122 This Figure Has Been Deleted

6.3-123 This Figure Has Been Deleted

6.3-124 This Figure Has Been Deleted

6.3-125 This Figure Has Been Deleted

6.3-126 This Figure Has Been Deleted

6.3-127 This Figure Has Been Deleted

6.3-128 This Figure Has Been Deleted

6.3-129 This Figure Has Been Deleted

6.3-130 This Figure Has Been Deleted

6.3-131 This Figure Has Been Deleted

6.3-132 This Figure Has Been Deleted

6.3-133 This Figure Has Been Deleted

6.3-134 This Figure Has Been Deleted

6.3-135 This Figure Has Been Deleted

6.3-136 This Figure Has Been Deleted

6.3-137 This Figure Has Been Deleted

6.3-138 This Figure Has Been Deleted

6.3-139 This Figure Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxvi 6.3-140 This Figure Has Been Deleted

6.3-141 This Figure Has Been Deleted

6.3-142 This Figure Has Been Deleted

6.3-143 This Figure Has Been Deleted

6.3-144 This Figure Has Been Deleted

6.3-145 This Figure Has Been Deleted

6.3-146 This Figure Has Been Deleted

6.3-147 This Figure Has Been Deleted

6.3-148 This Figure Has Been Deleted

6.3-149 This Figure Has Been Deleted

6.3-150 This Figure Has Been Deleted

6.3-151 This Figure Has Been Deleted

6.3-152 This Figure Has Been Deleted

6.3-153 This Figure Has Been Deleted 6.3-154 This Figure Has Been Deleted

6.3-155 This Figure Has Been Deleted

6.3-156 This Figure Has Been Deleted

6.3-157 This Figure Has Been Deleted

6.3-158 This Figure Has Been Deleted

6.3-159 This Figure Has Been Deleted

6.3-160 This Figure Has Been Deleted SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxvii 6.3-161 This Figure Has Been Deleted

6.3-162 This Figure Has Been Deleted

6.3-163 This Figure Has Been Deleted

6.3-164 This Figure Has Been Deleted

6.3-165 This Figure Has Been Deleted

6.3-166 This Figure Has Been Deleted

6.3-167 This Figure Has Been Deleted

6.3-168 This Figure Has Been Deleted

6.3-169 This Figure Has Been Deleted

6.3-170 This Figure Has Been Deleted

6.3-171 This Figure Has Been Deleted

6.3-172 thru 6.3-199 Not Used

6.3-200 Figure Deleted 6.3-201 Limiting TLO Recirculation Line Break Upper Plenum Pressure (Lower)

6.3-202 Limiting TLO Recirculation Line Break Total Break Flow Rate

6.3-203 Limiting TLO Recirculation Line Break Core Inlet Flow Rate

6.3-204 Limiting TLO Recirculation Line Break Core Inlet Flow Rate

6.3-205 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate 6.3-206 Limiting TLO Recirculation Line Break Ads Flow Rate

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxviii 6.3-207 Limiting TLO Recirculation Line Break HPCI Flow Rate

6.3-208 Limiting TLO Recirculation Line Break LPCS Flow Rate

6.3-209 Limiting TLO Recirculation Line Break Intact Loop LPCI Flow Rate

6.3-210 Limiting TLO Recirculation Line Break Broken Loop LPCI Flow Rate

6.3-211 Limiting TLO Recirculation Line Break Upper Downcomer Mixture Level

6.3-212 Limiting TLO Recirculation Line Break Lower Downcomer Mixture Level

6.3-213 Limiting TLO Recirculation Line Break Lower Downcomer Liquid Mass

6.3-214 Limiting TLO Recirculation Line Break Upper Plenum Liquid Mass

6.3-215 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass

6.3-216 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate

6.3-217 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate

6.3-218 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature At The Limiting Node 6.3-219 Limiting TLO Recirculation Line Break Hot Channel Quality At The Limiting Node 6.3-220 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coeff.

at The Limiting Node

6.3-221 Limiting TLO Recirculation Line Break Cladding Temperatures 6.4-1A Control Structure Elevation

6.4-1B Control Structure Envelope Plan - El. 697'-0" and 714'-0"

6.4-1C Control Structure Envelope Control Room Floor Plan EL. 729'-0" Technical Support Center EL. 741'-1"

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxix 6.4-1D Control Structure Envelope Plan EL. 753'-0" & 771'-0"

6.4-1E Control Structure Envelope Plan EL. 783'-0"

6.4-2 Control Room Location Intake and Exhaust Location

6.7-1 This Figure Has Been Deleted

6.7-2 This Figure Has Been Deleted

6.7-3-1 This Figure Has Been Deleted

6.7-3-2 This Figure Has Been Deleted

6.7-3-3 This Figure Has Been Deleted

6.7-3-4 This Figure Has Been Deleted

6.7-4 This Figure Has Been Deleted

6.7-5 This Figure Has Been Deleted

6A-1(a) Reactor Shield Annulus Arrangement

6A-1(b) RPV Shield Wall and Pedestal

6A-2 RPV Shield Annulus Subcompartment Model Schematic 6A-3a Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3b Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3c Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3d Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxx 6A-3e Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3f Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3g Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3h Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3i Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3j Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3k Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3l Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3m This Figure Has Been Deleted

6A-3n This Figure Has Been Deleted 6A-3o This Figure Has Been Deleted

6A-4 Drywell Head Arrangement

6A-5 Head Spray Line Break Geometry

6A-6 Pressure Response in the Drywell Head For a Head Spray Line Break

6A-7 Force Transient on Reactor Pressure Vessel Following A Recirculation Line Break at the Nozzle Safe End

6A-8 Force Transient on Reactor Shield Wall Following A Recirculation Line Break at the Nozzle Safe End SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxxi 6A-9 Resultant Force Transient on RPV Following a Feedwater Line Break at the Nozzle

6A-10 Resultant Force Transient on RPV Following a Feedwater Line Break at the Nozzle

6B-1 Basic FLUD Calculation Flowchart SSES-FSAR Text Rev. 59

FSAR Rev. 65 7-i CHAPTER 7 INSTRUMENTATION AND CONTROLS TABLE OF CONTENTS TEXT Section Title

7.1 INTRODUCTION

7.1.1 Identification of Safety-Related Systems 7.1.1a Identification of Safety-Related Systems Provided with the NSSS

7.1.1a.1 General (NSSS) 7.1.1a.2 Identification of Individual Systems 7.1.1a.3 Classification (NSSS) 7.1.1a.3.1 Safety-Related Systems (NSSS) 7.1.1a.3.2 Power Generation (Non-Safety) Systems (NSSS) 7.1.1a.3.3 Design Basis (NSSS) 7.1.1a.3.4 Specific Regulatory Requirements (NSSS)

7.1.1b Identification of Safety-Related Systems not Provided with the NSSS (Non-NSSS) 7.1.1b.1 Engineered Safety Feature Systems (Non-NSSS) 7.1.1b.2 Engineered Safety Feature Auxiliary Support Systems (Non-NSSS) 7.1.1b.3 Systems Required for Safe Shutdown (Non-NSSS) 7.1.1b.4 Safety-Related Display Instrumentation (Non-NSSS) 7.1.1b.5 Other Systems Required for Safety (Non-NSSS) 7.1.1b.6 Non-NSSS Systems Similar to Plants Which Have an Operating License 7.1.2 Identification of Safety Criteria

7.1.2a.1 Identification of Safety Criteria for NSSS, General 7.1.2a.1.1 Reactor Protection System (RPS) - Instrumentation and Control 7.1.2a.1.1.1 Safety Design Bases 7.1.2a.1.1.1.1 General Functional Requirements 7.1.2a.1.1.1.2 Specific Regulatory Requirements 7.1.2a.1.1.2 Power Generation (Non-Safety) Design Bases 7.1.2a.1.2 Primary Containment and Reactor Vessel Isolation Control System (PCRVICS) - Instrumentation and Controls 7.1.2a.1.2.1 Safety Design Bases SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-ii 7.1.2a.1.2.1.1 General Functional Requirements 7.1.2a.1.2.2 Specific Regulatory Requirements 7.1.2a.1.3 Emergency Core Cooling Systems - Instrumentation and Controls 7.1.2a.1.3.1 Safety Design Bases 7.1.2a.1.3.1.1 General Functional Requirements 7.1.2a.1.3.1.2 Specific Regulatory Requirements 7.1.2a.1.4 Neutron Monitoring System - Instrumentation and Controls 7.1.2a.1.4.1 Source Range Monitor (SRM) Subsystem 7.1.2a.1.4.1.1 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.2 Intermediate Range Monitor (IRM) Subsystem 7.1.2a.1.4.2.1 Safety Design Basis 7.1.2a.1.4.2.2 Specific Regulatory Requirements 7.1.2a.1.4.2.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.3 Local Power Range Monitor (LPRM) Subsystem 7.1.2a.1.4.3.1 Safety Design Bases 7.1.2a.1.4.3.2 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.4 Average Power Range Monitor (APRM) Subsystem 7.1.2a.1.4.4.1 Safety Design Basis 7.1.2a.1.4.4.2 Specific Regulatory Requirements 7.1.2a.1.4.4.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.5 Traversing Incore Probe (TIP) Subsystem 7.1.2a.1.4.5.1 Power Generation Design Bases 7.1.2a.1.4.6 Rod Block Monitor (RBM) Subsystem 7.1.2a.1.4.6.1 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.7 Oscillation Power Range Monitor (OPRM) Subsystem 7.1.2a.1.4.7.1 Safety Design Basis 7.1.2a.1.4.7.2 Specific Regulatory Requirements 7.1.2a.1.4.7.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.5 Refueling Interlocks - Instrumentation and Controls 7.1.2a.1.6 Reactor Manual Control System - Instrumentation and Controls 7.1.2a.1.6.1 Specific Regulatory Requirements 7.1.2a.1.6.2 Power Generation (Non-Safety) Design Bases 7.1.2a.1.7 This Subsection is not used 7.1.2a.1.8 This Subsection is not used 7.1.2a.1.9 This Subsection is not used 7.1.2a.1.10 This Subsection is not used 7.1.2a.1.11 Process Radiation Monitoring System - Instrumentation and Controls 7.1.2a.1.11.1 Main Steamline Radiation Monitoring Subsystem 7.1.2a.1.11.1.1 Safety Design Basis 7.1.2a.1.11.1.2 Specific Regulatory Requirements SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-iii 7.1.2a.1.11.1.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.12 This Subsection is not used 7.1.2a.1.13 This Subsection is not used 7.1.2a.1.14 This Subsection is not used 7.1.2a.1.15 This Subsection is not used 7.1.2a.1.16 This Subsection is not used 7.1.2a.1.17 This Subsection is not used 7.1.2a.1.18 Reactor Core Is olation Cooling (RCIC) Syst em - Instrumentation and Controls 7.1.2a.1.18.1 Safety Design Bases 7.1.2a.1.18.2 Specific Regulatory Requirements 7.1.2a.1.19 Standby Liquid Control System (SLCS) - Instrumentation and Controls 7.1.2a.1.19.1 Safety Design Basis 7.1.2a.1.19.2 Specific Regulatory Requirements 7.1.2a.1.19.3 Power Generation (Non-Safety) Design Basis 7.1.2a.1.20 This Subsection is not used 7.1.2a.1.21 This Subsection is not used 7.1.2a.1.22 This Subsection is not used 7.1.2a.1.23 This Subsection is not used 7.1.2a.1.24 NSSS Leak Detection System - Instrumentation and Controls 7.1.2a.1.24.1 Reactor Coolant Pressure Boundary Leakage Detection 7.1.2a.1.24.1.1 Safety Design Bases 7.1.2a.1.24.1.2 Specific Regulatory Requirements 7.1.2a.1.24.1.3 Power Generation (Non-Safety) Design Basis 7.1.2a.1.25 RHRS - Reactor Shutdown Cooling Subsystem - Instrumentation and Controls 7.1.2a.1.25.1 Safety Design Bases 7.1.2a.1.25.2 Specific Regulatory Requirements 7.1.2a.1.25.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.26 This subsection is not used 7.1.2a.1.27 This subsection is not used 7.1.2a.1.28 This subsection is not used 7.1.2a.1.29 This subsection is not used 7.1.2a.1.30 ATWS Mitigation Capability - Instrumentation and Controls 7.1.2a.1.30.1 Special Event Design Basis 7.1.2a.1.30.2 Specific Regulatory Requirements

7.1.2a.1.31 Safety-Related Display - Instrumentation 7.1.2a.1.31.1 Safety Design Basis 7.1.2a.1.31.2 Specific Regulatory Requirements 7.1.2a.1.31.3 Power Generation (Non-Safety) Design Basis SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-iv 7.1.2a.1.32 This Subsection is not used 7.1.2a.1.33 This Subsection is not used 7.1.2a.1.34 This Subsection is not used 7.1.2a.1.35 RHRS - Containment Spray Cooling System - Instrumentation and Controls 7.1.2a.1.35.1 Safety Design Basis 7.1.2a.1.35.2 Specific Regulatory Requirements 7.1.2a.1.35.3 Power Generation Design Basis 7.1.2a.1.36 This subsection is not used 7.1.2a.1.37 Recirculation Pump Trip (RPT) - Instrumentation and Controls 7.1.2a.1.37.1 Safety Design Bases 7.1.2a.1.37.2 Specific Regulatory Requirements 7.1.2a.1.37.3 Power Generation (Non-Safety) Bases 7.1.2a.1.38 RHRS - Suppression Pool Cooling System - Instrumentation and Controls 7.1.2a.1.38.1 Safety Design Bases 7.1.2a.1.38.2 Specific Regulatory Requirements 7.1.2a.1.38.3 Power Generation (Non-Safety) Design Basis 7.1.2b.1 Identification of Safety Criteria for Non-NSSS, General 7.1.2a.2 Mechanical Systems Separation Criteria 7.1.2a.2.1 General 7.1.2a.2.1.1 Separation Techniques 7.1.2a.2.2 System Separation Criteria 7.1.2a.2.3 Physical Separation 7.1.2a.3 Electrical System Separation Criteria 7.1.2a.3.1 General 7.1.2a.3.1.1 Separation Techniques 7.1.2a.3.2 Identification 7.1.2a.3.3 System Separation Requirements 7.1.2a.3.3.1 Reactor Protection System (RPS) 7.1.2a.3.3.2 Emergency Core Cooling System (ECCS) and Nuclear Steam Supply Shutoff System (NSSSS) 7.1.2a.3.3.3 Steam Leakage Zone 7.1.2a.3.3.4 Su ppression P ool Level Swell Zone 7.1.2a.3.3.5 Penetrations 7.1.2a.3.3.6 Power Generation Control Complex (PGCC) 7.1.2a.3.3.7 Annunciator and Computer 7.1.2a.3.3.8 Conformance to IEEE 384-1974, 1981 7.1.2a.4 NSSS Instrument Errors 7.1.2b.4 Non-NSSS Instrument Errors 7.1.2.5 Conformance to Industry Standards SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-v 7.1.2.5.1 Conformance to IEEE 279-1971 7.1.2.5.2 Conformance to IEEE 308-1974 7.1.2.5.2.1 Conformance to IEEE 308-1980 7.1.2.5.3 Conformance to IEEE 323-1971 7.1.2.5.3.1 Conformance to IEEE 323-1974 7.1.2.5.4 Conformance to IEEE 336-1971 7.1.2.5.4.1 Conformance to IEEE 336-1980 7.1.2.5.5 Conformance to IEEE 338-1971 7.1.2.5.5.1 Conformance to IEEE 338-1977 7.1.2.5.6 Conformance to IEEE 344-1971 7.1.2.5.6.1 Conformance to IEEE 344-1975 7.1.2.5.7 Conformance to IEEE 379-1972 7.1.2.5.7.1 Conformance to IEEE 379-1977 7.1.2.5.8 Conformance to IEEE 384-1974 7.1.2.5.8.1 Conformance to IEEE 384-1981 7.1.2.6 Conformance to Regulatory Guides 7.1.2.6.1 Conformance to Regulatory Guide 1.6 (3/10/71) 7.1.2.6.2 Conformance to Regulatory Guide 1.9 (5/10/71) 7.1.2.6.2.1 Conformance to Regulatory Guide 1.9 (December 1, 1979) 7.1.2.6.3 Conformance to Regulatory Guide 1.11 (3/10/71) 7.1.2.6.4 Conformance to Regulatory Guide 1.22 (2/17/72) 7.1.2.6.5 Conformance to Regulatory Guide 1.29 (6/7/72) 7.1.2.6.5.1 Conformance to Regulatory Guide 1.29 (9/78) 7.1.2.6.6 Conformance to Regulatory Guide 1.30 (8/11/72) 7.1.2.6.7 Conformance to Regulatory Guide 1.32 (8/72) 7.1.2.6.7.1 Conformance to Regulatory Guide 1.32 (2/77) 7.1.2.6.8 Conformance to Regulatory Guide 1.40 (3/16/73) 7.1.2.6.9 Conformance to Regulatory Guide 1.45 (5/73) 7.1.2.6.10 Conformance to Regulatory Guide 1.47 (5/73) 7.1.2.6.11 Conformance to Regulatory Guide 1.53 (6/73) 7.1.2.6.12 Conformance to Regulatory Guide 1.62 (10/73) 7.1.2.6.13 Conformance to Regulatory Guide 1.63 (10/73) 7.1.2.6.14 Conformance to Regulatory Guide 1.68 (11/73) 7.1.2.6.15 Conformance to Regulatory Guide 1.70 (Rev. 2) 7.1.2.6.16 Conformance to Regulatory Guide 1.73 (1/74) 7.1.2.6.17 Conformance to Regulatory Guide 1.75 (1/75) 7.1.2.6.17.1 Conformance to Regulatory Guide 1.75 (9/78) 7.1.2.6.18 Conformance to Regulatory Guide 1.80 (6/74) 7.1.2.6.19 Conformance to Regulatory Guide 1.89 (11/74) 7.1.2.6.20 Conformance to Regulatory Guide 1.96 (6/76) - Rev. 1 7.1.2.6.21 Conformance to Regulatory Guide 1.97 SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-vi 7.1.2.7 Technical Design Bases 7.1.2.8 Safety System Settings

7.2 REACTOR TRIP SYSTEM - (REACTOR PROTECTION SYSTEM) - INSTRUMENTATION AND CONTROLS

7.2.1 Description

7.2.1.1 System Description 7.2.1.1.1 Identification 7.2.1.1.2 Classification 7.2.1.1.3 Power Sources 7.2.1.1.4 Equipment Design 7.2.1.1.4.1 General 7.2.1.1.4.2 Initiating Circuits 7.2.1.1.4.3 Logic 7.2.1.1.4.4 Scram Operating Bypasses 7.2.1.1.4.4.1 Neutron Monitoring System 7.2.1.1.4.4.2 Turbine Stop Valve and Turbine Control Valve Fast Closure 7.2.1.1.4.4.3 Main Steamline Isolation Valves 7.2.1.1.4.4.4 Scram Discharge Volume Level 7.2.1.1.4.4.5 Mode Switch in Shutdown 7.2.1.1.4.4.6 Maintenance, Calibration or Test Bypasses 7.2.1.1.4.4.7 Interlocks 7.2.1.1.4.4.8 RPS Shorting Links (Neutron Monitoring System) 7.2.1.1.4.5 Redundancy and Diversity 7.2.1.1.4.6 Actuated Devices 7.2.1.1.4.7 Separation 7.2.1.1.4.8 Testability 7.2.1.1.5 Environmental Considerations 7.2.1.1.6 Operational Considerations 7.2.1.1.6.1 Reactor Operator Information 7.2.1.1.6.1.1 Indicators 7.2.1.1.6.1.2 Annunciators 7.2.1.1.6.1.3 Computer Alarms 7.2.1.1.6.2 Reactor Operator Controls 7.2.1.1.6.2.1 Mode Switch 7.2.1.1.6.2.2 Safety-Related Portions of Control Systems Which Inhibit or Limit the Response of the Reactivity Control System 7.2.1.1.6.3 Setpoints 7.2.1.1.7 Containment Electrical Penetration Assignment SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-vii 7.2.1.1.8 Cable Spreading Room Description 7.2.1.1.9 Control and Relay Rooms 7.2.1.1.10 Control Boards and Their Contents 7.2.1.1.11 Test Methods that Insure RPS Reliability 7.2.1.1.12 Interlock Circuits to Inhibit Rod Motion as Well as Vary the Protective Function 7.2.1.1.13 ATWS Provisions 7.2.1.2 Design Bases 7.2.1.2.1 Conditions 7.2.1.2.2 Variables 7.2.1.2.3 Sensors 7.2.1.2.4 Operational Limits 7.2.1.2.5 Margin Between Operational Limits 7.2.1.2.6 Levels Requiring Protective Action 7.2.1.2.7 Ranges of Energy Supply and Environmental Conditions 7.2.1.2.8 Unusual Events 7.2.1.2.9 Performance Requirements 7.2.1.3 Final System Drawings

7.2.2 Analysis

7.2.2.1 Reactor Protection System - Instrumentation and Controls 7.2.2.1.1 General Functional Requirements Conformance 7.2.2.1.1.1 Conformance to Design Basis Requirements 7.2.2.1.1.1.1 Design Bases 7.1.2a.1.1.1.1(1) 7.2.2.1.1.1.2 Design Bases 7.1.2a.1.1.1.1(2) 7.2.2.1.1.1.3 Design Bases 7.1.2a.1.1.1.1(3) 7.2.2.1.1.1.4 Design Bases 7.1.2a.1.1.1.1(4) 7.2.2.1.1.1.5 Design Bases 7.1.2a.1.1.1.1(5) 7.2.2.1.1.1.6 Design Bases 7.1.2a.1.1.1.1(6) 7.2.2.1.1.1.7 Design Bases 7.1.2a.1.1.1.1(7a through 7h) 7.2.2.1.1.1.8 Design Bases 7.1.2a.1.1.1.1(8) 7.2.2.1.1.1.9 Other Design Basis Requirements 7.2.2.1.2 Conformance to Specific Regulatory Requirements 7.2.2.1.2.1 Conformance to NRC Regulatory Guides 7.2.2.1.2.1.1 Regulatory Guide 1.11 (1971) 7.2.2.1.2.1.2 Regulatory Guide 1.22 (2/72) 7.2.2.1.2.1.3 Regulatory Guide 1.29 (1972) 7.2.2.1.2.1.4 Regulatory Guide 1.30 (1972) 7.2.2.1.2.1.5 Regulatory Guide 1.47 (5/73) 7.2.2.1.2.1.6 Regulatory Guide 1.53 (6/73)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-viii 7.2.2.1.2.1.7 Regulatory Guide 1.62 (10/73) 7.2.2.1.2.1.8 Regulatory Guide 1.63 (10/73) 7.2.2.1.2.1.9 Regulatory Guide 1.68 (11/73) 7.2.2.1.2.1.10 Regulatory Guide 1.75 (1/75) 7.2.2.1.2.1.11 Regulatory Guide 1.89 (11/74) 7.2.2.1.2.2 Conformance to 10CFR50, Appendix A - General Design Criteria 7.2.2.1.2.2.1 General Design Criterion 1 7.2.2.1.2.2.2 General Design Criterion 2 7.2.2.1.2.2.3 General Design Criterion 3 7.2.2.1.2.2.4 General Design Criterion 4 7.2.2.1.2.2.5 General Design Criterion 5 7.2.2.1.2.2.6 General Design Criterion 10 7.2.2.1.2.2.7 General Design Criterion 12 7.2.2.1.2.2.8 General Design Criterion 13 7.2.2.1.2.2.9 General Design Criterion 15 7.2.2.1.2.2.10 General Design Criterion 19 7.2.2.1.2.2.11 General Design Criterion 20 7.2.2.1.2.2.12 General Design Criterion 21 7.2.2.1.2.2.13 General Design Criterion 22 7.2.2.1.2.2.14 General Design Criterion 23 7.2.2.1.2.2.15 General Design Criterion 24 7.2.2.1.2.2.16 General Design Criterion 25 7.2.2.1.2.2.17 General Design Criterion 29 7.2.2.1.2.3 Conformance with Industry Codes and Standards 7.2.2.1.2.3.1 IEEE 279 (1971) 7.2.2.1.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.2.2.1.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.2.2.1.2.3.1.3 Quality of Components and Modules (IEEE 279-1971, Paragraph 4.3) 7.2.2.1.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.2.2.1.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.2.2.1.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.2.2.1.2.3.1.7 Control and Protection System Interaction (IEEE 279-1971, Paragraph 4.7) 7.2.2.1.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.2.2.1.2.3.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.2.2.1.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.2.2.1.2.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.2.2.1.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-ix 7.2.2.1.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.2.2.1.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.2.2.1.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.2.2.1.2.3.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, Paragraph 4.16) 7.2.2.1.2.3.1.17 Manual Actuation (IEEE 279-1971, Paragraph 4.17) 7.2.2.1.2.3.1.18 Access to Setpoint Adjustments, Calibration, and Test Points (IEEE 279-1971, Paragraph 4.18) 7.2.2.1.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.2.2.1.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.2.2.1.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.2.2.1.2.3.1.22 Identification of Protection Systems (IEEE 279-1971, Pa ragraph 4.22) 7.2.2.1.2.3.2 IEEE 308 - 1974 7.2.2.1.2.3.3 IEEE 317 - 1972

7.2.2.1.2.3.4 This subsection intentionally left blank. 7.2.2.1.2.3.5 IEEE 336 - 1971 7.2.2.1.2.3.6 IEEE 338 - 1971 7.2.2.1.2.3.7 IEEE 344 - 1971 7.2.2.1.2.3.8 IEEE 379 - 1972 7.2.2.1.2.3.9 IEEE 384 - 1974 7.2.2.1.2.4 Conformance to NRC Branch Technical Positions 7.2.2.1.2.4.1 Branch Technical Position EICSB 10 7.2.2.1.2.4.2 Branch Technical Position EICSB 21 7.2.2.1.2.4.3 Branch Technical Position EICSB 22 7.2.2.1.2.4.4 Branch Technical Position EICSB 26 7.2.2.1.3 Additional Design Considerations Analyses 7.2.2.1.3.1 Spurious Rod Withdrawals 7.2.2.1.3.2 Loss of Plant Instrument Air System 7.2.2.1.3.3 Loss-of-Cooling Water to Vital Equipment 7.2.2.1.3.4 Plant Load Rejection 7.2.2.1.3.5 Turbine Trip

7.2.3 Alternate Rod Injection System

7.2.3.1 System Description 7.2.3.1.1 Identification 7.2.3.1.2 Classification 7.2.3.1.3 Power Sources 7.2.3.1.4 Equipment Design 7.2.3.1.4.1 General SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-x 7.2.3.1.4.2 Initiating Circuits 7.2.3.1.4.2.1 Input Parameter Selection 7.2.3.1.4.2.2 Reactor Steam Dome Pressure-High 7.2.3.1.4.2.3 Reactor Vessel Water Level-Low 7.2.3.1.4.2.4 Manual Trip 7.2.3.1.4.3 Logic 7.2.3.1.4.4 ARI Operating and Maintenance Bypasses 7.2.3.1.4.5 Redundancy and Diversity 7.2.3.1.4.6 Actuated Devices 7.2.3.1.4.7 Separation 7.2.3.1.4.8 Testability 7.2.3.1.5 Environmental Considerations 7.2.3.1.6 Operational Considerations 7.2.3.1.6.1 Reactor Operator Information 7.2.3.1.6.1.1 Indicators 7.2.3.1.6.1.2 Annunciators 7.2.3.1.6.1.3 Computer Alarms 7.2.3.1.6.1.3.1 Process Computer System 7.2.3.1.6.1.3.2 Transient Monitoring System 7.2.3.1.6.2 Reactor Operator Controls 7.2.3.1.6.3 Setpoints 7.2.3.1.7 Control Panels 7.2.3.1.8 Test Methods to Ensure ARI Reliability 7.2.3.2 Design Bases 7.2.3.2.1 Operating Conditions 7.2.3.2.2 Variables 7.2.3.2.3 Sensors 7.2.3.2.4 Operational Limits 7.2.3.2.5 Levels Requiring Protection Action 7.2.3.2.6 Ranges of Energy Supply and Environmental Conditions 7.2.3.2.7 Unusual Events 7.2.3.2.8 Performance Requirements 7.2.3.3 Final System Drawings

7.2.4 ARI Analysis

7.2.4.1 ARI General Functional Requirements Conformance 7.2.4.1.1 Conformance to Design Bases Requirements 7.2.4.1.1.1 Design Bases 7.1.2a.1.30 7.2.4.1.1.2 Conformance to Specific Regulatory Requirements 7.2.4.1.1.2.1 Conformance to 10CFR50.62(C)(3)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xi 7.2.4.1.1.2.2 Conformance to NRC Regulatory Guides 7.2.4.1.1.2.2.1 Regulatory Guide 1.22 (February 17, 1972) 7.2.4.1.1.2.2.2 Regulatory Guide 1.30 (August 11, 1972) 7.2.4.1.1.2.2.3 Regulatory Guide 1.53 (June, 1973) 7.2.4.1.1.2.2.4 Regulatory Guide 1.62 (October, 1973) 7.2.4.1.1.2.2.5 Regulatory Guide 1.70 (September, 1975) 7.2.4.1.1.2.2.6 Regulatory Guide 1.75 (January, 1975) 7.2.4.1.1.2.3 Conformance to 10CFR50 Appendix A General Design Criteria 7.2.4.1.1.2.3.1 General Design Criterion 1 7.2.4.1.1.2.3.2 General Design Criterion 2 7.2.4.1.1.2.3.3 General Design Criterion 3 7.2.4.1.1.2.3.4 General Design Criterion 4 7.2.4.1.1.2.3.5 General Design Criterion 13 7.2.4.1.1.2.3.6 General Design Criterion 19 7.2.4.1.1.2.3.7 General Design Criterion 20 7.2.4.1.1.2.3.8 General Design Criterion 21 7.2.4.1.1.2.3.9 General Design Criterion 22 7.2.4.1.1.2.3.10 General Design Criterion 23 7.2.4.1.1.2.3.11 General Design Criterion 24 7.2.4.1.1.2.3.12 General Design Criterion 29 7.2.4.1.1.2.4 Conformance to Industry Standards 7.2.4.1.1.2.4.1 IEEE 279-1971 7.2.4.1.1.2.4.1.1 General Functional Requirements (IEEE 279-1971, Paragraph 4.1) 7.2.4.1.1.2.4.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.2.4.1.1.2.4.1.3 Quality of Components (IEEE 279-1971, Paragraph 4.3) 7.2.4.1.1.2.4.1.4 Equipment Qualific ation (IEEE 279-1971, Paragraph 4.4) 7.2.4.1.1.2.4.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.2.4.1.1.2.4.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.2.4.1.1.2.4.1.7 Control and Protection System Interaction (IEEE 279-1971, Paragraph 4.7) 7.2.4.1.1.2.4.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.2.4.1.1.2.4.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.2.4.1.1.2.4.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.2.4.1.1.2.4.1.11 Channel Bypasses for Removal from (IEEE 279-1971, Paragraph 4.11) 7.2.4.1.1.2.4.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.2.4.1.1.2.4.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.2.4.1.1.2.4.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.2.4.1.1.2.4.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.2.4.1.1.2.4.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xii Paragraph 4.16) 7.2.4.1.1.2.4.1.17 Manual Initiation (IEEE 279-1971, Paragraph 4.17) 7.2.4.1.1.2.4.1.18 Access to Setpoint Adjustments, Calibration, and Test Points (IEEE 279-1971, Paragraph 4.18) 7.2.4.1.1.2.4.1.19 Identification of Protective Actions 7.2.4.1.1.2.4.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.2.4.1.1.2.4.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.2.4.1.1.2.4.1.22 Identification of Protection Systems (IEEE 279-1971, Paragraph 4.22) 7.2.4.1.1.2.4.2 IEEE 336-1971 7.2.4.1.1.2.4.3 IEEE 338-1971 7.2.4.1.1.2.4.4 IEEE 344-1975 7.2.4.1.1.2.4.5 IEEE 384-1981 7.2.4.1.1.2.5 Branch Technical Positions 7.2.4.1.1.2.5.1 EICSB-10 7.2.4.1.1.2.5.2 EICSB-21 7.2.4.1.1.2.5.3 EICSB-22 7.2.4.1.1.2.5.4 EICSB-24

7.3 ENGINEERED SAFETY FEATURE SYSTEMS

7.3.1 Description

7.3.1.1a System Description (NSSS) 7.3.1.1a.1 Emergency Core Cooling Systems (ECCS) Instrumentation and Control 7.3.1.1a.1.1 Network Identification 7.3.1.1a.1.2 Network Power Sources 7.3.1.1a.1.3 High Pressure Coolant Injection (HPCI) System - Instrumentation and Controls 7.3.1.1a.1.3.1 System Identification 7.3.1.1a.1.3.2 Equipment Design 7.3.1.1a.1.3.3 Initiating Circuits 7.3.1.1a.1.3.4 Logic and Sequencing

7.3.1.1a.1.3.5 Bypasses and Interlocks 7.3.1.1a.1.3.6 Redundancy and Diversity 7.3.1.la.1.3.7 Actuated Devices 7.3.1.1a.1.3.8 Separation 7.3.1.1a.1.3.9 Testability 7.3.1.1a.1.3.10 Environmental Considerations 7.3.1.1a.1.3.11 Operational Considerations SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xiii 7.3.1.1a.1.3.11.1 General Information 7.3.1.1a.1.3.11.2 Reactor Operator Information 7.3.1.1a.1.3.11.3 Setpoints 7.3.1.1a.1.4 Automatic Depressurization System (ADS) - Instrumentation and Controls 7.3.1.1a.1.4.1 System Identification 7.3.1.1a.1.4.2 Equipment Design 7.3.1.1a.1.4.3 Initiating Circuits 7.3.1.1a.1.4.4 Logic and Sequencing

7.3.1.1a.1.4.5 Bypasses and Interlocks 7.3.1.1a.1.4.6 Redundancy and Diversity 7.3.1.1a.1.4.7 Actuated Devices 7.3.1.1a.1.4.8 Separation 7.3.1.1a.1.4.9 Testability 7.3.1.1a.1.4.10 Environmental Considerations 7.3.1.1a.1.4.11 Operational Considerations 7.3.1.1a.1.4.11.1 General Information 7.3.1.1a.1.4.11.2 Reactor Operator Information 7.3.1.1a.1.4.11.3 Setpoints 7.3.1.1a.1.5 Core Spray (CS) System - Instrumentation and Controls 7.3.1.1a.1.5.1 System Identification 7.3.1.1a.1.5.2 Equipment Design 7.3.1.1a.1.5.3 Initiating Circuits 7.3.1.1a.1.5.4 Logic and Sequencing

7.3.1.1a.1.5.5 Bypasses and Interlocks 7.3.1.1a.1.5.6 Redundancy and Diversity 7.3.1.1a.1.5.7 Actuated Devices 7.3.1.1a.1.5.8 Separation 7.3.1.1a.1.5.9 Testability 7.3.1.1a.1.5.10 Environmental Considerations 7.3.1.1a.1.5.11 Operational Considerations 7.3.1.1a.1.5.11.1 General Information 7.3.1.1a.1.5.11.2 Reactor Operator Information 7.3.1.1a.1.5.11.3 Setpoints 7.3.1.1a.1.6 Low Pressure Coolant Injection (LPCI) System - Instrumentation and Controls 7.3.1.1a.1.6.1 System Identification 7.3.1.1a.1.6.2 Equipment Design 7.3.1.1a.1.6.3 Initiating Circuits 7.3.1.1a.1.6.4 Logic and Sequencing

7.3.1.1a.1.6.5 Bypasses and Interlocks SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xiv 7.3.1.1a.1.6.6 Redundancy and Diversity 7.3.1.1a.1.6.7 Actuated Devices 7.3.1.1a.1.6.8 Separation 7.3.1.1a.1.6.9 Testability 7.3.1.1a.1.6.10 Environmental Considerations 7.3.1.1a.1.6.11 Operational Considerations 7.3.1.1a.1.6.11.1 General Information 7.3.1.1a.1.6.11.2 Reactor Operator Information 7.3.1.1a.1.6.11.3 Setpoints 7.3.1.1a.2 Primary Containment and Reactor Vessel Isolation Control System - for NSSS Instrumentation and Controls 7.3.1.1a.2.1 System Identification 7.3.1.1a.2.2 System Power Sources 7.3.1.1a.2.3 System Equipment Design 7.3.1.1a.2.4 System Initiating Circuits 7.3.1.1a.2.4.1 Isolation Functions and Settings 7.3.1.1a.2.4.1.1 Reactor Vessel Low Water Level 7.3.1.1a.2.4.1.1.1 Subsystem Identification 7.3.1.1a.2.4.1.1.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.1.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.1.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.1.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.1.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.1.7 Subsystem Testability 7.3.1.1a.2.4.1.2 Main Steamline High Radiation 7.3.1.1a.2.4.1.2.1 Subsystem Identification 7.3.1.1a.2.4.1.2.2 Subsystem Power Sources 7.3.1.1a.2.4.1.2.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.2.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.2.5 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.2.6 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.2.7 Testability 7.3.1.1a.2.4.1.2.8 Environmental Considerations 7.3.1.1a.2.4.1.2.9 Operational Considerations 7.3.1.1a.2.4.1.3 Main Steamline Tunnel High Temperature and Differential Temperature 7.3.1.1a.2.4.1.3.1 Subsystem Identification 7.3.1.1a.2.4.1.3.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.3.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.3.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.3.5 Subsystem Redundancy and Diversity SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xv 7.3.1.1a.2.4.1.3.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.3.7 Subsystem Testability 7.3.1.1a.2.4.1.4 Main Steamline High Flow 7.3.1.1a.2.4.1.4.1 Subsystem Identification 7.3.1.1a.2.4.1.4.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.4.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.4.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.4.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.4.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.4.7 Subsystem Testability 7.3.1.1a.2.4.1.5 Main Turbine Inlet - Low Steam Pressure 7.3.1.1a.2.4.1.5.1 Subsystem Identification 7.3.1.1a.2.4.1.5.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.5.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.5.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.5.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.5.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.5.7 Subsystem Testability 7.3.1.1a.2.4.1.6 Containment Drywell-High Pressure 7.3.1.1a.2.4.1.6.1 Subsystem Identification 7.3.1.1a.2.4.1.6.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.6.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.6.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.6.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.6.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.6.7 Subsystem Testability 7.3.1.1a.2.4.1.7 This Subsection is not used 7.3.1.1a.2.4.1.8 This Subsection is not used 7.3.1.1a.2.4.1.9 Reactor Water Cleanup (RWCU) System - High Differential Flow and High Flow 7.3.1.1a.2.4.1.9.1 Subsystem Identification 7.3.1.1a.2.4.1.9.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.9.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.9.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.9.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.9.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.9.7 Subsystem Testability 7.3.1.1a.2.4.1.10 Reactor Water Cleanup (RWCU) System-Area High Temperature and Differential Temperature 7.3.1.1a.2.4.1.10.1 Subsystem Identification 7.3.1.1a.2.4.1.10.2 Power Supplies SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xvi 7.3.1.1a.2.4.1.10.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.10.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.10.5 Subsystem Redundancy and Diversity

7.3.1.1a.2.4.1.10.6 Subsystem By passes and Interlocks 7.3.1.1a.2.4.1.10.7 Subsystem Testability 7.3.1.1a.2.4.1.11 This subsection has been deleted 7.3.1.1a.2.4.1.12 Main Steamline-Leak Detection 7.3.1.1a.2.4.1.12.1 Subsystem Identification 7.3.1.1a.2.4.1.13 Main Condenser Vacuum Trip 7.3.1.1a.2.4.1.13.1 Subsystem Identification 7.3.1.1a.2.4.1.13.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.13.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.13.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.13.5 Subsystem Redundancy and Diversity

7.3.1.1a.2.4.1.13.6 Subsystem By passes and Interlocks 7.3.1.1a.2.4.1.13.7 Subsystem Testability

7.3.1.1a.2.4.1.14 RHR System High Flow 7.3.1.1a.2.4.1.14.1 Subsystem Identification 7.3.1.1a.2.4.1.14.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.14.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.14.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.14.5 Subsystem Redundancy and Diversity

7.3.1.1a.2.4.1.14.6 Subsystem By passes and Interlocks 7.3.1.1a.2.4.1.14.7 Subsystem Testability 7.3.1.1a.2.4.2 System Instrumentation 7.3.1.1a.2.5 System Logic 7.3.1.1a.2.6 System Sequencing 7.3.1.1a.2.7 System Bypasses and Interlocks 7.3.1.1a.2.8 System Redundancy and Diversity 7.3.1.1a.2.9 System Actuated Devices 7.3.1.1a.2.10 System Separation 7.3.1.1a.2.11 System Testability 7.3.1.1a.2.12 System Environmental Considerations 7.3.1.1a.2.13 System Operational Considerations 7.3.1.1a.2.13.1 General Information 7.3.1.1a.2.13.2 Reactor Operator Information

7.3.1.1a.2.13.3 Setpoints 7.3.1.1a.3 This Subsection is Not Used 7.3.1.1a.4 RHRS/Containment Spray Cooling System - Instrumentation and Controls 7.3.1.1a.4.1 System Identification SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xvii 7.3.1.1a.4.2 Power Sources 7.3.1.1a.4.3 Equipment Design 7.3.1.1a.4.4 Initiating Circuits 7.3.1.1a.4.5 Logic and Sequencing

7.3.1.1a.4.6 Bypasses and Interlocks 7.3.1.1a.4.7 Redundancy and Diversity 7.3.1.1a.4.8 Actuated Devices 7.3.1.1a.4.9 Separation 7.3.1.1a.4.10 Testability 7.3.1.1a.4.11 Environmental Considerations 7.3.1.1a.4.12 Operational Considerations 7.3.1.1a.4.12.1 General Information 7.3.1.1a.4.12.2 Reactor Operator Information

7.3.1.1a.4.12.3 Setpoints 7.3.1.1a.5 RHRS/Suppression Pool Cooling Mode - Instrumentation and Controls 7.3.1.1a.5.1 System Identification 7.3.1.1a.5.2 Power Sources 7.3.1.1a.5.3 Equipment Design 7.3.1.1a.5.4 Initiating Circuits 7.3.1.1a.5.5 Logic and Sequencing

7.3.1.1a.5.6 Bypasses and Interlocks 7.3.1.1a.5.7 Redundancy and Diversity 7.3.1.1a.5.8 Actuated Devices 7.3.1.1a.5.9 Separation 7.3.1.1a.5.10 Testability 7.3.1.1a.5.11 Environmental Considerations 7.3.1.1a.5.12 Operational Considerations 7.3.1.1a.5.12.1 General Information 7.3.1.1a.5.12.2 Reactor Operator Information

7.3.1.1a.5.12.3 Setpoints 7.3.1.1b System Description (Non-NSSS) 7.3.1.1b.1 Primary Containment Isolation Control System for Non-NSSS - Instrumentation and Control 7.3.1.1b.1.1 System Description 7.3.1.1b.1.2 Initiating Circuits and Logic

7.3.1.1b.1.3 Bypasses, Interlocks and Sequencing 7.3.1.1b.1.4 Redundancy and Diversity 7.3.1.1b.1.5 Actuated Devices 7.3.1.1b.1.6 Supporting Systems 7.3.1.1b.1.7 Instrument Sensing Lines SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xviii 7.3.1.1b.2 Combustible Gas Control System 7.3.1.1b.2.1 System Description 7.3.1.1b.2.1.1 Initiating Circuits, Logic, Bypasses, Interlocks and Sequencing 7.3.1.1b.2.1.2 Redundancy and Diversity 7.3.1.1b.2.1.3 Supporting Systems 7.3.1.1b.3 Primary Containment Vacuum Relief - Instrumentation and Control 7.3.1.1b.3.1 System Description 7.3.1.1b.3.2 Initiating Circuits, Logic, Bypasses, Interlocks and Sequencing 7.3.1.1b.3.3 Redundancy and Diversity 7.3.1.1b.3.4 Actuated Devices 7.3.1.1b.4 Standby Gas Treatment System (SGTS) 7.3.1.1b.4.1 Initiating Circuits 7.3.1.1b.4.2 Logic and Sequencing 7.3.1.1b.4.3 Interlocks 7.3.1.1b.4.4 Bypasses

7.3.1.1b.4.5 Redundancy 7.3.1.1b.4.6 Diversity 7.3.1.1b.4.7 Actuated Devices 7.3.1.1b.4.8 Separation 7.3.1.1b.4.9 Supporting Systems 7.3.1.1b.4.10 System Parts Not Required for Safety 7.3.1.1b.5 Reactor Building Recirculation System 7.3.1.1b.5.1 Initiating Circuits 7.3.1.1b.5.2 Logic and Sequencing 7.3.1.1b.5.3 Interlocks 7.3.1.1b.5.4 Bypasses

7.3.1.1b.5.5 Redundancy 7.3.1.1b.5.6 Diversity 7.3.1.1b.5.7 Actuated Devices 7.3.1.1b.5.8 Separation 7.3.1.1b.5.9 Supporting Systems 7.3.1.1b.5.10 System Parts Not Required for Safety 7.3.1.1b.6 Reactor Building Isolation and HVAC Support 7.3.1.1b.6.1 Initiating Circuits 7.3.1.1b.6.2 Logic and Sequencing 7.3.1.1b.6.3 Interlocks 7.3.1.1b.6.4 Bypasses

7.3.1.1b.6.5 Redundancy 7.3.1.1b.6.6 Diversity 7.3.1.1b.6.7 Actuated Devices 7.3.1.1b.6.8 Separation SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xix 7.3.1.1b.6.9 Supporting Systems 7.3.1.1b.6.10 System Parts Not Required for Safety 7.3.1.1b.7 Habitability, Control Room Isolation 7.3.1.1b.7.1 Initiation 7.3.1.1b.7.2 Logic and Sequencing 7.3.1.1b.7.3 Interlocks 7.3.1.1b.7.4 Bypasses

7.3.1.1b.7.5 Redundancy 7.3.1.1b.7.6 Diversity 7.3.1.1b.7.7 Actuated Devices 7.3.1.1b.7.8 Separation 7.3.1.1b.7.9 Supporting Systems 7.3.1.1b.7.10 System Parts Not Required for Safety 7.3.1.1b.8 Auxiliary Support Systems 7.3.1.1b.8.1 Emergency Service Water System - Instrumentation and Control 7.3.1.1b.8.1.1 Initiating Circuits 7.3.1.1b.8.1.2 Logic, Bypasses, Interlocks, and Sequencing 7.3.1.1b.8.1.2.1 Logic Power Source 7.3.1.1b.8.1.2.2 Pump Logic 7.3.1.1b.8.1.2.3 Bypasses 7.3.1.1b.8.1.2.4 Interlocks 7.3.1.1b.8.1.2.5 Sequencing

7.3.1.1b.8.1.3 Redundancy 7.3.1.1b.8.1.4 Actuated Devices 7.3.1.1b.8.1.5 Supporting Systems 7.3.1.1b.8.1.6 ESW Instrumentation Not Required for Safety 7.3.1.1b.8.2 RHR Service Water System - Instrumentation and Controls 7.3.1.1b.8.2.1 Initiation Circuits 7.3.1.1b.8.2.2 Logic, Bypasses, Interlocks, and Sequencing 7.3.1.1b.8.2.2.1 Logic Power Source 7.3.1.1b.8.2.2.2 Pump Control Logic 7.3.1.1b.8.2.2.3 Bypasses 7.3.1.1b.8.2.2.4 Valve Control Logic 7.3.1.1b.8.2.2.5 Interlocks 7.3.1.1b.8.2.3 Actuated Devices 7.3.1.1b.8.2.4 Redundancy and Diversity 7.3.1.1b.8.2.5 Supporting Systems 7.3.1.1b.8.2.6 RHR Service Water Instrumentation Not Required for Safety 7.3.1.1b.8.3 Containment Instrument Gas System - Instrumentation and Control 7.3.1.1b.8.3.1 Initiating Logic and Interlocks 7.3.1.1b.8.3.2 Bypasses, Interlocks and Sequencing SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xx 7.3.1.1b.8.3.3 Redundancy 7.3.1.1b.8.3.4 Containment Instrument Gas Instrumentation Not Required for Safety 7.3.1.1b.8.3.5 Containment Instrument Gas Safety-Related Instrumentation 7.3.1.1b.8.4 Standby Power System 7.3.1.1b.8.5 Heating, Ventilating and Air Conditioning Systems for ESF Areas 7.3.1.1b.8.5.1 SGTS Equipment Room H&V System 7.3.1.1b.8.5.1.1 Initiating Circuits 7.3.1.1b.8.5.1.2 Logic and Sequencing 7.3.1.1b.8.5.1.3 Interlocks 7.3.1.1b.8.5.1.4 Bypasses 7.3.1.1b.8.5.1.5 Redundancy 7.3.1.1b.8.5.1.6 Diversity 7.3.1.1b.8.5.1.7 Actuated Devices 7.3.1.1b.8.5.1.8 Separation 7.3.1.1b.8.5.1.9 Supporting Systems 7.3.1.1b.8.5.1.10 System Parts Not Required for Safety 7.3.1.1b.8.5.2 Diesel Ge nerator Buildings' H&V Systems 7.3.1.1b.8.5.2.1 Initiating Circuits 7.3.1.1b.8.5.2.2 Logic and Sequencing 7.3.1.1b.8.5.2.3 Interlocks 7.3.1.1b.8.5.2.4 Bypasses 7.3.1.1b.8.5.2.5 Redundancy 7.3.1.1b.8.5.2.6 Diversity 7.3.1.1b.8.5.2.7 Actuated Devices 7.3.1.1b.8.5.2.8 Separation 7.3.1.1b.8.5.2.9 Supporting Systems 7.3.1.1b.8.5.2.10 System Parts Not Required for Safety 7.3.1.1b.8.5.3 Engineered Safeguard Service Water Pumphouse Ventilation System 7.3.1.1b.8.5.3.1 Initiating Circuits 7.3.1.1b.8.5.3.2 Logic and Sequencing 7.3.1.1b.8.5.3.3 Interlocks 7.3.1.1b.8.5.3.4 Bypasses 7.3.1.1b.8.5.3.5 Redundancy 7.3.1.1b.8.5.3.6 Diversity 7.3.1.1b.8.5.3.7 Actuated Devices 7.3.1.1b.8.5.3.8 Separation 7.3.1.1b.8.5.3.9 Supporting Systems 7.3.1.1b.8.5.3.10 System Parts Not Required for Safety 7.3.1.1b.8.5.4 ESF Switchgear (SWGR) Rooms Cooling System SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxi 7.3.1.1b.8.5.4.1 Initiating Circuits 7.3.1.1b.8.5.4.2 Logic and Sequencing 7.3.1.1b.8.5.4.3 Interlocks 7.3.1.1b.8.5.4.4 Bypasses 7.3.1.1b.8.5.4.5 Redundancy 7.3.1.1b.8.5.4.6 Diversity 7.3.1.1b.8.5.4.7 Actuated Devices 7.3.1.1b.8.5.4.8 Separation 7.3.1.1b.8.5.4.9 Supporting Systems 7.3.1.1b.8.5.4.10 System Parts Not Required for Safety 7.3.1.1b.8.5.5 Emergency Core Cooling Systems (ECCS) Unit Coolers 7.3.1.1b.8.5.5.1 Initiating Circuits 7.3.1.1b.8.5.5.2 Logic and Sequencing 7.3.1.1b.8.5.5.3 Interlocks 7.3.1.1b.8.5.5.4 Bypasses 7.3.1.1b.8.5.5.5 Redundancy 7.3.1.1b.8.5.5.6 Diversity 7.3.1.1b.8.5.5.7 Actuated Devices 7.3.1.1b.8.5.5.8 Separation 7.3.1.1b.8.5.5.9 Supporting Systems 7.3.1.1b.8.5.5.10 System Parts Not Required for Safety 7.3.1.1b.8.5.6 Drywell Unit Coolers and CRD Area Ventilation Fans 7.3.1.1b.8.5.6.1 Initiating Circuits 7.3.1.1b.8.5.6.2 Logic and Sequencing 7.3.1.1b.8.5.6.3 Interlocks 7.3.1.1b.8.5.6.4 Bypass 7.3.1.1b.8.5.6.5 Redundancy 7.3.1.1b.8.5.6.6 Diversity 7.3.1.1b.8.5.6.7 Actuated Devices 7.3.1.1b.8.5.6.8 Separation 7.3.1.1b.8.5.6.9 Supporting Systems 7.3.1.1b.8.5.6.10 System Parts Not Required for Safety 7.3.1.1b.8.5.7 Control Structure Chilled Water System (CSCWS) 7.3.1.1b.8.5.7.1 Initiating Circuits 7.3.1.1b.8.5.7.2 Logic and Sequencing 7.3.1.1b.8.5.7.3 Interlocks 7.3.1.1b.8.5.7.4 Bypasses 7.3.1.1b.8.5.7.5 Redundancy 7.3.1.1b.8.5.7.6 Diversity 7.3.1.1b.8.5.7.7 Actuated Devices 7.3.1.1b.8.5.7.8 Separation SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxii 7.3.1.1b.8.5.7.9 Supporting Systems 7.3.1.1b.8.5.7.10 System Parts Not Required for Safety 7.3.1.1b.9 Containment Atmosphere Control 7.3.1.2 IEEE 279-1971 Design Basis Information 7.3.1.2.1 Conditions 7.3.1.2.2 Variables 7.3.1.2.3 Numbers of Sensors and Location 7.3.1.2.4 Operational Limits 7.3.1.2.5 Margin Between Operational Limits 7.3.1.2.6 Levels Requiring Protective Action 7.3.1.2.7 Range of Energy Supply and Environmental Conditions of Safety Systems 7.3.1.2.8 Malfunctions, Accidents, and Other Unusual Events Which Could Cause Damage to Safety System 7.3.1.2.9 Minimum Performance Requirements 7.3.1.3 Final System Drawings

7.3.2 Analysis 7.3.2a Analysis of ESFAS Supplied with the NSSS

7.3.2a.1 Emergency Core Cooling Systems - Instrumentation and Controls 7.3.2a.1.1 General Functional Requirement Conformance 7.3.2a.1.2 Specific Regulatory Requirements Conformance 7.3.2a.1.2.1 Regulatory Guides 7.3.2a.1.2.1.1 Regulatory Guide 1.6 (1971) 7.3.2a.1.2.1.2 Regulatory Guide 1.11 (1971) 7.3.2a.1.2.1.3 Regulatory Guide 1.22 (1972) 7.3.2a.1.2.1.4 Regulatory Guide 1.29 (1976) 7.3.2a.1.2.1.5 Regulatory Guide 1.30 (1972) 7.3.2a.1.2.1.6 Regulatory Guide 1.32 (1972) 7.3.2a.1.2.1.7 Regulatory Guide 1.47 (1973) 7.3.2a.1.2.1.8 Regulatory Guide 1.53 (1973) 7.3.2a.1.2.1.9 Regulatory Guide 1.62 (1973) 7.3.2a.1.2.1.10 Regulatory Guide 1.75 (1974) 7.3.2a.1.2.2 10CFR50, Appendix A 7.3.2a.1.2.3 Industry Standards 7.3.2a.1.2.3.1 IEEE 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations 7.3.2a.1.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.3.2a.1.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.3.2a.1.2.3.1.3 Quality of Components (IEEE 279-1971, Paragraph 4.3)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxiii 7.3.2a.1.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.3.2a.1.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.3.2a.1.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.3.2a.1.2.3.1.7 Control and Protection Interaction (IEEE 279-1972, Paragraph 4.7) 7.3.2a.1.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.3.2a.1.2.3.1.9 Capability of Sensor Checks (IEEE 279-1971, Paragraph 4.9)

7.3.2a.1.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.3.2a.1.2.3.1.11 Channel Bypass or Rem oval from Operation (IEEE 279-1971, Paragraph 4.11) 7.3.2a.1.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.3.2a.1.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.3.2a.1.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.3.2a.1.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.3.2a.1.2.3.1.16 Completion of Protective Action Once It Is Initiated (IEEE 279-1971, Paragraph 4.16) 7.3.2a.1.2.3.1.17 Manual Initiation (IEEE 279-1971, Paragraph 4.17) 7.3.2a.1.2.3.1.18 A ccess to Setpoint Ad justments (IEEE 279-1 971, Paragraph 4.18) 7.3.2a.1.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.3.2a.1.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.3.2a.1.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.3.2a.1.2.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.3.2a.1.2.3.2 IEEE 308-1974 7.3.2a.1.2.3.3 IEEE 323-1971 7.3.2a.1.2.3.4 IEEE 338-1971 7.3.2a.1.2.3.5 IEEE 344-1971 7.3.2a.1.2.3.6 IEEE 379-1972 7.3.2a.2 Primary Containment and Reactor Vessel Isolation Control System for NSS Systems - Instrumentation and Controls 7.3.2a.2.1 General Functional Requirement Conformance 7.3.2a.2.2 Specific Regulatory Requirements Conformance 7.3.2a.2.2.1 NRC Regulatory Guides

7.3.2a.2.2.1.1 Regulatory Guide 1.11 (1971) 7.3.2a.2.2.1.2 Regulatory Guide 1.22 (1972) 7.3.2a.2.2.1.3 Regulatory Guide 1.29 (1972) 7.3.2a.2.2.1.4 Regulatory Guide 1.30 (1972) 7.3.2a.2.2.1.5 Regulatory Guide 1.47 (1973) 7.3.2a.2.2.1.6 Regulatory Guide 1.53 (1973) 7.3.2a.2.2.1.7 Regulatory Guide 1.62 (1973) 7.3.2a.2.2.1.8 Regulatory Guide 1.63 (1973)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxiv 7.3.2a.2.2.1.9 Regulatory Guide 1.75 (1975) 7.3.2a.2.2.1.10 Regulatory Guide 1.89 (1974) 7.3.2a.2.2.2 Conformance to 10CFR50, Appendix A 7.3.2a.2.2.3 Industry Codes and Standards 7.3.2a.2.2.3.1 IEEE 279-1971 7.3.2a.2.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.3.2a.2.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.3.2a.2.2.3.1.3 Quality of Components and Modules (IEEE 279-1971, Paragraph 4.3) 7.3.2a.2.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.3.2a.2.2.3.1.5 Channel Integrity (IEEE 279-1971,Paragraph 4.5) 7.3.2a.2.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.3.2a.2.2.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7) 7.3.2a.2.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.3.2a.2.2.3.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.3.2a.2.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.3.2a.2.2.3.1.11 Channel Bypass or Rem oval from Operation (IEEE 279-1971, Paragraph 4.11) 7.3.2a.2.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.3.2a.2.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.3.2a.2.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.3.2a.2.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.3.2a.2.2.3.1.16 Completion of Protection Action Once Initiated (IEEE 279-1971, Paragraph 4.16) 7.3.2a.2.2.3.1.17 Manual Action (IEEE 279-1971, Paragraph 4.17) 7.3.2a.2.2.3.1.18 A ccess to Setpoint Ad justments (IEEE 279-1 971, Paragraph 4.18) 7.3.2a.2.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.3.2a.2.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.3.2a.2.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.3.2a.2.2.3.1.22 Identification of Protection Systems (IEEE 279-1971, Paragraph 4.22) 7.3.2a.2.2.3.2 Conformance to IEEE 308-1974 7.3.2a.2.2.3.3 Conformance to IEEE 323-1971 7.3.2a.2.2.3.4 Conformance to IEEE 338-1971 7.3.2a.2.2.3.5 Conformance to IEEE 344-1971 7.3.2a.2.2.3.6 Conformance to IEEE 379-1972 7.3.2a.3 This Subsection is not used 7.3.2a.4 Containment Spray Cooling System - Instrumentation and Controls 7.3.2a.4.1 General Functional Requirement Conformance SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxv 7.3.2a.4.2 Specific Regulatory Requirements Conformance 7.3.2a.4.3 Conformance to Industry Codes and Standards 7.3.2a.4.3.1 IEEE 279-1971 7.3.2a.4.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.3.2a.4.3.1.2 Single-Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.3.2a.4.3.1.3 Quality Components (IEEE 279-1971, Paragraph 4.3) 7.3.2a.4.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.3.2a.4.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.3.2a.4.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.3.2a.4.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7) 7.3.2a.4.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.3.2a.4.3.1.9 Capability for Sensor Checks (I EEE 279-1971, Paragraph 4.9) 7.3.2a.4.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.3.2a.4.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.3.2a.4.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.3.2a.4.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.3.2a.4.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.3.2a.4.3.1.15 Multiple Trip Settings (IEEE 279-1971, Paragraph 4.15) 7.3.2a.4.3.1.16 Completion of Protection Action Once It is Initiated (IEEE 279-1971, Paragraph 4.16) 7.3.2a.4.3.1.17 Manual Actuation (IEEE 279-1971, Paragraph 4.17) 7.3.2a.4.3.1.18 Access to Setpoint Adjustment (IEEE 279-1971, Pa ragraph 4.18) 7.3.2a.4.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.3.2a.4.3.1.20 Information Readout (I EEE 279-1971, Paragraph 4.20) 7.3.2a.4.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.3.2a.4.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.3.2a.5 Suppression Pool Cooling Mode (RHR) - Instrumentation and Controls 7.3.2a.5.1 General Functional Requirements Conformance 7.3.2a.5.2 Regulatory Requirements Conformance 7.3.2a.5.2.1 Regulatory Guide 1.22 (1972) 7.3.2a.5.2.2 Regulatory Guide 1.29 (1973) 7.3.2a.5.2.3 Regulatory Guide 1.30 (1972) 7.3.2a.5.2.4 Regulatory Guide 1.32 (1972) 7.3.2a.5.2.5 Regulatory Guide 1.47 (1973) 7.3.2a.5.2.6 Regulatory Guide 1.53 (1973) 7.3.2a.5.2.7 Regulatory Guide 1.62 (1973) 7.3.2a.5.2.8 Regulatory Guide 1.63 (1973)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxvi 7.3.2a.5.2.9 Regulatory Guide 1.75 (1975) 7.3.2a.5.3 Conformance to 10CFR50 Appendix A 7.3.2a.5.4 Conformance to Industry Codes and Standards 7.3.2a.5.4.1 IEEE Standard 279(1971) 7.3.2a.5.4.1.1 General Functional Requirements (Paragraph 4.1) 7.3.2a.5.4.1.2 Single Failure Criterion (Paragraph 4.2) 7.3.2a.5.4.1.3 Quality of Components (Paragraph 4.3) 7.3.2a.5.4.1.4 Equipment Qualification (Paragraph 4.4) 7.3.2a.5.4.1.5 Channel Integrity (Paragraph 4.5) 7.3.2a.5.4.1.6 Channel Independence (Paragraph 4.6) 7.3.2a.5.4.1.7 Control and Protection System Interaction (Paragraph 4.7) 7.3.2a.5.4.1.8 Derivation of System Inputs (Paragraph 4.8) 7.3.2a.5.4.1.9 Capability for Sensor Checks (Paragraph 4.9)

7.3.2a.5.4.1.10 Capability for Test and Calibration (Paragraph 4.10) 7.3.2a.5.4.1.11 Channel Bypass or Removal from Operation (Paragraph 4.11), Operating Bypasses (Paragraph 4.12), Indication of Bypasses (Paragraph 4.13) 7.3.2a.5.4.1.12 Access to Means for Bypassing (Paragraph 4.14) 7.3.2a.5.4.1.13 Multiple Setpoint (Paragraph 4.15) 7.3.2a.5.4.1.14 Completion of Protective Action Once Initiated (Paragraph 4.16) 7.3.2a.5.4.1.15 Manual Initiation (Paragraph 4.17) 7.3.2a.5.4.1.16 Access to Setpoint Adjustments (Paragraph 4.18) 7.3.2a.5.4.1.17 Identification of Protective Actions (Paragraph 4.19) 7.3.2a.5.4.1.18 Information Read-Out (Paragraph 4.20) 7.3.2a.5.4.1.19 System Repair (Paragraph 4.21) 7.3.2a.5.4.1.20 Identification (Paragraph 4.22) 7.3.2a.5.4.2 IEEE Standard 308(1974) 7.3.2a.5.4.3 IEEE Standard 338(1971) 7.3.2a.5.4.4 IEEE Standard 379(1972) 7.3.2a.5.4.5 IEEE Standard 384(1974) 7.3.2a.6 Additional Design Considerations Analyses 7.3.2a.6.1 General Plant Safety Analysis 7.3.2a.6.2 Loss of Plant Instrument Air System 7.3.2a.6.3 Loss of Cooling Wa ter to Vital Equipment

7.3.2b Analysis for Non-NSSS Systems

7.3.2b.1 General Design Criteria 7.3.2b.2 Equipment Design Criteria 7.3.2b.3 Failure Modes and Effect Analysis (FMEA) 7.3.2b.3.1 Non-NSSS Containment Isolation Systems SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxvii 7.3.2b.3.2 Combustible Gas Control 7.3.2b.3.3 Primary Containment Vacuum Relief 7.3.2b.3.4 Standby Gas Treatment System 7.3.2b.3.5 Reactor Building Recirculation 7.3.2b.3.6 Reactor Building Isolation 7.3.2b.3.7 Control Room Isolation 7.3.2b.4 Consideration of Plant Contingencies 7.3.2b.4.1 Loss of Instrument Air Systems 7.3.2b.4.2 Loss of Cooling Wa ter to Vital Equipment 7.3.2b.5 Testing Methods and Effects on System Integrity During Testing

7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN

7.4.1 Description

7.4.1.1 Reactor Core Isolation Cooling (RCIC) System - Instrumentation and Controls 7.4.1.1.1 System Identification 7.4.1.1.1.1 Function 7.4.1.1.1.2 Classification 7.4.1.1.2 Power Sources 7.4.1.1.3 Equipment Design 7.4.1.1.3.1 General 7.4.1.1.3.2 Initiating Circuits 7.4.1.1.3.3 Logic and Sequencing 7.4.1.1.3.4 Bypasses and Interlocks 7.4.1.1.3.5 Redundancy & Diversity 7.4.1.1.3.6 Actuated Devices 7.4.1.1.3.7 Separation 7.4.1.1.3.8 Testability 7.4.1.1.4 Environmental Considerations 7.4.1.1.5 Operational Considerations 7.4.1.1.5.1 General Information 7.4.1.1.5.2 Reactor Operator Information 7.4.1.1.5.3 Setpoints 7.4.1.2 Standby Liquid Control System (SLCS) - Instrumentation & Controls 7.4.1.2.1 System Identification 7.4.1.2.1.1 Function 7.4.1.2.1.2 Classification 7.4.1.2.2 Power Sources 7.4.1.2.3 Equipment Design SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxviii 7.4.1.2.3.1 General 7.4.1.2.3.2 Initiating Circuits 7.4.1.2.3.3 Logic and Sequencing 7.4.1.2.3.4 Bypasses and Interlocks 7.4.1.2.3.5 Redundancy and Diversity 7.4.1.2.3.6 Actuated Devices 7.4.1.2.3.7 Separation 7.4.1.2.3.8 Testability 7.4.1.2.4 Environmental Considerations 7.4.1.2.5 Operational Considerations 7.4.1.2.5.1 General Information 7.4.1.2.5.2 Reactor Operator Information 7.4.1.2.5.3 Setpoints 7.4.1.3 RHRS/Reactor Shutdown Cooling Mode - Instrumentation and Controls 7.4.1.3.1 System Identification 7.4.1.3.1.1 Function 7.4.1.3.1.2 Classification 7.4.1.3.2 Power Sources 7.4.1.3.3 Equipment Design 7.4.1.3.3.1 General 7.4.1.3.3.2 Initiating Circuits 7.4.1.3.3.3 Logic and Sequencing 7.4.1.3.3.4 Bypasses and Interlocks 7.4.1.3.3.5 Redundancy and Diversity 7.4.1.3.3.6 Actuated Devices 7.4.1.3.3.7 Separation 7.4.1.3.3.8 Testability 7.4.1.3.4 Environmental Considerations 7.4.1.3.5 Operational Considerations 7.4.1.3.5.1 General Information 7.4.1.3.5.2 Reactor Operator Information 7.4.1.3.5.3 Setpoints 7.4.1.4 Reactor Shutdown from Outside the Control Room (Remote Shutdown) 7.4.1.4.1 Description 7.4.1.4.2 Design Criteria 7.4.1.4.2.1 Postulated Conditions During the Evacuation of the Main Control Room 7.4.1.4.2.2 Design Considerations 7.4.1.4.2.3 Remote Shutdown Functional Capabilities SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxix 7.4.1.4.3 Consideration for Operation of the Remote Shutdown Panel 7.4.1.4.4 Consideration for Operation of the Alternate Control Structure HVAC Panel

7.4.2 Analysis

7.4.2.1 Reactor Core Isolation Cooling (RCIC) System - Instrumentation and Control 7.4.2.1.1 General Functional Requirements Conformance 7.4.2.1.2 Specific Regulatory Requirements Conformance 7.4.2.1.2.1 NRC Regulatory Guides Conformance 7.4.2.1.2.1.1 Regulatory Guide 1.6 7.4.2.1.2.1.2 Regulatory Guide 1.11 7.4.2.1.2.1.3 Regulatory Guide 1.22 7.4.2.1.2.1.4 Regulatory Guide 1.29 7.4.2.1.2.1.5 Regulatory Guide 1.30 7.4.2.1.2.1.6 Regulatory Guide 1.32 7.4.2.1.2.1.7 Regulatory Guide 1.47 7.4.2.1.2.1.8 Regulatory Guide 1.53 7.4.2.1.2.1.9 Regulatory Guide 1.62 7.4.2.1.2.1.10 Regulatory Guide 1.63 7.4.2.1.2.1.11 Regulatory Guide 1.75 7.4.2.1.2.1.12 Regulatory Guide 1.89 7.4.2.1.2.2 NRC Regulations Conformance - 10CFR50 Appendix A Requirements 7.4.2.1.2.2.1 General Design Criterion 13 7.4.2.1.2.2.2 General Design Criterion 20 7.4.2.1.2.2.3 General Design Criterion 21 7.4.2.1.2.2.4 General Design Criterion 22 7.4.2.1.2.2.5 General Design Criterion 29 7.4.2.1.2.2.6 General Design Criterion 34 7.4.2.1.2.2.7 General Design Criterion 37 7.4.2.1.2.3 Conformance to Industry Codes and Standards 7.4.2.1.2.3.1 IEEE 279-1971 7.4.2.1.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.4.2.1.2.3.1.2 Single-Failure Criterio n (IEEE 279-1971, Paragraph 4.2) 7.4.2.1.2.3.1.3 Quality of Components and Modules 7.4.2.1.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.4.2.1.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.4.2.1.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.4.2.1.2.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxx 7.4.2.1.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.4.2.1.2.3.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.4.2.1.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.4.2.1.2.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.4.2.1.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.4.2.1.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.4.2.1.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.4.2.1.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.4.2.1.2.3.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, Paragraph 4.16) 7.4.2.1.2.3.1.17 Manual Actuation (IEEE 279-1971, Paragraph 4.17) 7.4.2.1.2.3.1.18 Access to Setpoint Adjustment (IEEE 279-1971, Paragraph 4.18) 7.4.2.1.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.4.2.1.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.4.2.1.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.4.2.1.2.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.4.2.1.2.3.2 IEEE 308-1974 7.4.2.1.2.3.3 IEEE 323-1971 7.4.2.1.2.3.4 IEEE 338-1971 7.4.2.1.2.3.5 IEEE 344-1971 7.4.2.2 Standby Liquid Control System (SLCS) - Instrumentation and Controls 7.4.2.2.1 General Functional Requirements Conformance 7.4.2.2.2 Specific Regulatory Requirements Conformance 7.4.2.2.2.1 NRC Regulatory Guides Conformance 7.4.2.2.2.1.1 Regulatory Guide 1.6 7.4.2.2.2.1.2 Regulatory Guide 1.11 7.4.2.2.2.1.3 Regulatory Guide 1.22 7.4.2.2.2.1.4 Regulatory Guide 1.29 7.4.2.2.2.1.5 Regulatory Guide 1.30 7.4.2.2.2.1.6 Regulatory Guide 1.32 7.4.2.2.2.1.7 Regulatory Guide 1.47 7.4.2.2.2.1.8 Regulatory Guide 1.53 7.4.2.2.2.1.9 Regulatory Guide 1.62 7.4.2.2.2.1.10 Regulatory Guide 1.63 7.4.2.2.2.1.11 Regulatory Guide 1.89 SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxi 7.4.2.2.2.2 NRC Regulations Conformance-10CFR150 Appendix A Requirements 7.4.2.2.2.2.1 General Design Criterion 13 7.4.2.2.2.2.2 General Design Criterion 29 7.4.2.2.2.3 Conformance to Industry Codes and Standards 7.4.2.2.2.3.1 IEEE 279-1971 7.4.2.2.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.4.2.2.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.4.2.2.2.3.1.3 Quality of Components and Modules (IEEE 279-1971, Paragraph 4.3) 7.4.2.2.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.4.2.2.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.4.2.2.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.4.2.2.2.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7) 7.4.2.2.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.4.2.2.2.3.1.9 Capability of Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.4.2.2.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.4.2.2.2.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.4.2.2.2.3.1.12 Operating Bypass (IEEE 279-1971, Paragraph 4.12) 7.4.2.2.2.3.1.13 Indication of By pass (IEEE279-1971, Paragraph 4.13) 7.4.2.2.2.3.1.14 Access to Means for Bypass (IEEE 279-1971, Paragraph 4.14) 7.4.2.2.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.4.2.2.2.3.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, Paragraph 4.16) 7.4.2.2.2.3.1.17 Manual Initiation (IEEE 279-1971, Paragraph 4.17) 7.4.2.2.2.3.1.18 Access to Setpoint Adjustments, Calibration, and Test Points (IEEE 279-1971, Paragraph 4.18) 7.4.2.2.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.4.2.2.2.3.1.20 Information Read-out (IEEE 279-1971, Paragraph 4.20) 7.4.2.2.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.4.2.2.2.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.4.2.2.2.3.2 IEEE 323-1971 7.4.2.2.2.3.3 IEEE 338-1971 7.4.2.2.2.3.4 IEEE 344-1971 7.4.2.3 Residual Heat Removal System - Reactor Shutdown Cooling Mode Subsystem - Instrumentation and Controls 7.4.2.3.1 General Functional Requirements Conformance 7.4.2.3.2 Specific Regulatory Requirements Conformance SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxii 7.4.2.3.2.1 Conformance to NRC Regulatory Guides 7.4.2.3.2.2 Conformance to NRC Regulations - 10CFR50 Appendix A Requirements 7.4.2.3.2.2.1 General Design Criterion 34 Residual Heat Removal 7.4.2.3.2.3 Conformance to Industry Codes and Standards 7.4.2.4 Reactor Shutdown from Outside the Control Room (Remote Shutdown)

7.4.3 References

7.5 SAFETY-RELATED DISPLAY INSTRUMENTATION (SRDI)

7.5.1a Description

7.5.1a.1 General Description of NSSS Safety - Related Display Instrumentation 7.5.1a.2 Normal Operation 7.5.1a.3 Abnormal Transient Occurrences 7.5.1a.4 Accident Conditions 7.5.1a.4.1 Initial Accident Event 7.5.1a.4.2 Post-Accident Tracking 7.5.1a.4.2.1 Reactor Water Level 7.5.1a.4.2.2 Reactor Pressure 7.5.1a.4.2.3 Reactor Shutdown, Isolation, and Core Cooling Indication 7.5.1a.4.2.3.1 Reactor Operator Information and Observations 7.5.1a.4.2.3.2 System Operation Information - Display Equipment 7.5.1a.4.2.3.3 System Operation Information - Display Equipment Qualification 7.5.1a.4.2.4 Containment Indications

7.5.1b Description of Non-NSSS Safety-Related Displays

7.5.1b.1 Containment Isolation 7.5.1b.2 Combustible Gas Control 7.5.1b.3 Primary Containment Vacuum Relief 7.5.1b.4 Standby Gas Treatment, RX Building Recirculation, and Isolation System 7.5.1b.5 Habitability Systems 7.5.1b.6 Auxiliary Support Systems 7.5.1b.7 Bypass Indication System 7.5.1b.7.1 System Description 7.5.1b.8 Post-Accident Neutron Flux Monitoring System SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxiii 7.5.1b.8.1 This Subsection Has Been Deleted

7.5.2a Analysis of NSSS Safety-Related Displays 7.5.2a.1 General 7.5.2a.1.1 Design Criteria 7.5.2a.1.1.1 Power Generation Control Complex Criteria 7.5.2a.1.1.2 Advance Control Room Design and Operational Criteria 7.5.2a.1.1.2.1 Design Criteria 7.5.2a.1.1.2.2 Operating Criteria 7.5.2a.2 Normal Operation 7.5.2a.3 Abnormal Transient Occurrences 7.5.2a.4 Accident Conditions 7.5.2a.4.1 Initial Accident Event 7.5.2a.4.2 Post-Accident Tracking 7.5.2a.4.3 Safe Shutdown Display 7.5.2a.4.4 Engineered Safety Feature Operation Display 7.5.2a.5 Compliance with Regulatory/Industry Standards 7.5.2a.5.1 Conformance to IEEE 279-1971 7.5.2a.5.1.1 General 7.5.2a.5.1.2 Automatic Initiation of Protective Action (IEEE 279, Paragraph 4.1) 7.5.2a.5.1.3 Single Failure Criterion (IEEE 279, Paragraph 4.2) 7.5.2a.5.1.4 Quality of Indicators (IEEE 279, Paragraph 4.3) 7.5.2a.5.1.5 Equipment Qualification (IEEE 279, Paragraph 4.4) 7.5.2a.5.1.6 Channel Integrity (IEEE 279, Paragraph 4.5) 7.5.2a.5.1.7 Channel Independence (IEEE 279, Paragraph 4.6) 7.5.2a.5.1.8 Control and Protection System Interaction (IEEE 279, Paragraph 4.7) 7.5.2a.5.1.9 Deviation of System Inputs (IEEE 279, Paragraph 4.8) 7.5.2a.5.1.10 Capability for Sensor Checks (IEEE 279, Paragraph 4.9) 7.5.2a.5.1.11 Capability for Test and Calibration (IEEE Paragraph 4.10) 7.5.2a.5.1.12 Channel Bypass (IEEE 279, Paragraph 4.11) 7.5.2a.5.1.13 Operating Bypasses (IEEE 279, Paragraph 4.12) 7.5.2a.5.1.14 Indication of Bypass (IEEE 279, Paragraph 4.13) 7.5.2a.5.1.15 Access to Means for Bypassing (IEEE 279, Paragraph 4.14) 7.5.2a.5.1.16 Multiple Setpoints (IEEE 279, Paragraph 4.15) 7.5.2a.5.1.17 Completion of Protective Action Once it is Initiated (IEEE 279, Paragraph 4.16) 7.5.2a.5.1.18 Manual Actuation (IEEE 279, Paragraph 4.17) 7.5.2a.5.1.19 Access to Setpoints (IEEE 279, Paragraph 4.18) 7.5.2a.5.1.20 Identification of Protective Action (IEEE 279, Paragraph 4.19)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxiv 7.5.2a.5.1.21 Information Read Out (IEEE 279, Paragraph 4.20) 7.5.2a.5.1.22 System Repair (IEEE 279, Paragraph 4.21) 7.5.2a.5.1.23 Identification (IEEE 279, Paragraph 4.22) 7.5.2a.5.2 Conformance with IEEE 323 7.5.2a.5.3 Conformance with IEEE 344 7.5.2a.5.4 Regulatory Guide 1.47 7.5.2a.5.5 Regulatory Guide 1.97 7.5.2a.5.6 10CFR50 Appendix B

7.5.2b Analysis of Non-NSSS Safety-Related Display Instrumentation

7.5.2b.1 Identification, Redundancy, Accuracy 7.5.2b.2 Isolation, Separation 7.5.2b.3 Qualification of Components 7.5.2b.4 Capability for Checking 7.5.2b.5 Analysis of the Bypass Indication System 7.5.2b.6 This Section Has Been Deleted

7.6 ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 7.6.1a Description

7.6.1a.1 Refueling Interlocks System - Instrumentation and Controls 7.6.1a.2 NSSS Process Radiation Monitoring System - Instrumentation and Controls 7.6.1a.3 High Pressure/Low Pressure System Interlock Protection System 7.6.1a.3.1 Function Identification 7.6.1a.3.2 Power Sources 7.6.1a.3.3 Equipment Design 7.6.1a.3.3.1 Circuit Description 7.6.1a.3.3.2 Logic and Sequencing 7.6.1a.3.3.3 Bypasses and Interlocks

7.6.1a.3.3.4 Redundancy 7.6.1a.3.3.5 Actuated Devices 7.6.1a.3.3.6 Separation 7.6.1a.3.3.7 Testability 7.6.1a.3.4 Environmental Considerations 7.6.1a.3.5 Operational Considerations 7.6.1a.3.5.1 General Information 7.6.1a.3.5.2 Reactor Operator Information SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxv 7.6.1a.3.5.3 Setpoints 7.6.1a.4 NSSS Leak Detection System - Instrumentation and Controls 7.6.1a.4.1 System Identification 7.6.1a.4.2 Power Sources 7.6.1a.4.3 Equipment Design 7.6.1a.4.3.1 General 7.6.1a.4.3.2 Main Steamline Leak Detection 7.6.1a.4.3.3 RCIC System Leak Detection 7.6.1a.4.3.3.1 Subsystem Identification 7.6.1a.4.3.3.2 RCIC Area Temperature Monitoring 7.6.1a.4.3.3.2.1 Circuit Description 7.6.1a.4.3.3.2.2 Logic and Sequencing 7.6.1a.4.3.3.2.3 Bypasses and Interlocks 7.6.1a.4.3.3.2.4 Redundancy and Diversity 7.6.1a.4.3.3.3 RCIC Steamline Pressure Monitoring 7.6.1a.4.3.3.3.1 Circuit Description 7.6.1a.4.3.3.3.2 Logic and Sequencing 7.6.1a.4.3.3.3.3 Bypasses and Interlocks 7.6.1a.4.3.3.3.4 Redundancy and Diversity 7.6.1a.4.3.3.4 RCIC Flow Rate Monitoring 7.6.1a.4.3.3.4.1 Circuit Description 7.6.1a.4.3.3.4.2 Logic and Sequencing 7.6.1a.4.3.3.4.3 Bypass and Interlocks 7.6.1a.4.3.3.4.4 Redundancy and Diversity 7.6.1a.4.3.4 Recirculation Pump Leak Detection 7.6.1a.4.3.4.1 Subsystem Identification 7.6.1a.4.3.4.2 Pump Seal Cavity Pressure Monitoring 7.6.1a.4.3.4.2.1 Circuit Description 7.6.1a.4.3.4.2.2 Logic and Sequencing 7.6.1a.4.3.4.2.3 Bypasses and Interlocks 7.6.1a.4.3.4.2.4 Redundancy and Diversity 7.6.1a.4.3.4.3 Liquid Flow Rate Monitoring 7.6.1a.4.3.4.3.1 Circuit Description 7.6.1a.4.3.4.3.2 Logic and Sequencing 7.6.1a.4.3.4.3.3 Bypasses and Interlocks 7.6.1a.4.3.4.3.4 Redundancy and Diversity 7.6.1a.4.3.5 RHR System Leak Detection 7.6.1a.4.3.5.1 Subsystem Identification 7.6.1a.4.3.5.2 RHR Area Temperature Monitoring 7.6.1a.4.3.5.2.1 Circuit Description 7.6.1a.4.3.5.2.2 Logic and Sequencing SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxvi 7.6.1a.4.3.5.2.3 Bypasses and Interlocks 7.6.1a.4.3.5.2.4 Redundancy and Diversity 7.6.1a.4.3.5.3 RHR Flow Rate Monitoring 7.6.1a.4.3.5.3.1 Circuit Description [Unit 2 only]

7.6.1a.4.3.5.3.2 Logic and Sequencing [Unit 2 only]

7.6.1a.4.3.5.3.3 Bypasses and Interlocks [Unit 2 only]

7.6.1a.4.3.5.3.4 Redundancy and Diversity [Unit 2 only]

7.6.1a.4.3.5.4 This Section Has Been Deleted 7.6.1a.4.3.5.5 RHR Pump Room Flood (Water Level) Detection [Unit 1 only]

7.6.1a.4.3.6 Reactor Water Clean-up System Leak Detection 7.6.1a.4.3.7 Safety/Relief Valve Leak Detection 7.6.1a.4.3.7.1 Subsystem Identification 7.6.1a.4.3.7.2 Safety/Relief Valve Discharge Line Temperature Monitoring 7.6.1a.4.3.7.2.1 Description 7.6.1a.4.3.7.2.2 Logic and Sequencing 7.6.1a.4.3.7.2.3 Bypasses and Interlocks 7.6.1a.4.3.8.2.4 Redundancy and Diversity 7.6.1a.4.3.8 HPCI System Leakage Detection 7.6.1a.4.3.8.1 Subsystem Identification 7.6.1a.4.3.8.2 HPCI Area Temperature Monitoring 7.6.1a.4.3.8.2.1 Circuit Description 7.6.1a.4.3.8.2.2 Logic and Sequencing 7.6.1a.4.3.8.2.3 Bypasses and Interlocks 7.6.1a.4.3.8.2.4 Redundancy and Diversity 7.6.1a.4.3.8.3 HPCI Steam Flow Monitoring 7.6.1a.4.3.8.3.1 Description 7.6.1a.4.3.8.3.2 Logic and Sequencing 7.6.1a.4.3.8.3.3 Bypasses and Interlocks 7.6.1a.4.3.8.3.4 Redundancy and Diversity 7.6.1a.4.3.8.4 HPCI Steamline Pressure Monitoring 7.6.1a.4.3.8.4.1 Circuit Description 7.6.1a.4.3.8.4.2 Logic and Sequencing 7.6.1a.4.3.8.4.3 Bypasses and Interlocks 7.6.1a.4.3.8.4.4 Redundancy and Diversity 7.6.1a.4.4 System and Subsystem Separation Criteria 7.6.1a.4.5 System and Subsystem Testability 7.6.1a.4.6 System and Subsystem Environmental Considerations 7.6.1a.4.7 System and Subsystem Operational Considerations 7.6.1a.5 Neutron Monitoring System - Instrumentation and Controls 7.6.1a.5.1 System Identification 7.6.1a.5.2 Power Source SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxvii 7.6.1a.5.3 Source Range Monitor (SRM) Subsystem 7.6.1a.5.4 Intermediate Range Monitor (IRM) Subsystem 7.6.1a.5.4.1 Equipment Design 7.6.1a.5.4.1.1 Description 7.6.1a.5.4.1.1.1 Bypasses and Interlocks 7.6.1a.5.4.1.2 Redundancy 7.6.1a.5.4.1.3 Testability 7.6.1a.5.4.2 Environmental Conditions 7.6.1a.5.4.3 Operational Considerations 7.6.1a.5.5 Local Power Range Monitor (LPRM) Subsystem 7.6.1a.5.5.1 Equipment Design 7.6.1a.5.5.1.1 Description 7.6.1a.5.5.1.2 Bypasses and Interlocks 7.6.1a.5.5.1.3 Redundancy 7.6.1a.5.5.1.4 Testability 7.6.1a.5.5.2 Environmental Considerations 7.6.1a.5.5.3 Operational Considerations 7.6.1a.5.6 Average Power Range Monitor (APRM) Subsystem 7.6.1a.5.6.1 Equipment Design 7.6.1a.5.6.1.1 Description 7.6.1a.5.6.1.2 Bypasses and Interlocks 7.6.1a.5.6.1.3 Redundancy 7.6.1a.5.6.1.4 Testability 7.6.1a.5.6.2 Environmental Considerations 7.6.1a.5.6.3 Operational Considerations 7.6.1a.5.7 Rod Block Monitor (RBM) Subsystem 7.6.1a.5.8 Traversing In-Core Probe Subsystem 7.6.1a.5.9 This Section Intentionally Deleted 7.6.1a.6 Rod Block Trip System - Instrumentation and Controls 7.6.1a.7 Rod Sequence Control System (RSCS) - Instrumentation and Controls 7.6.1a.8 Recirculation Pump Trip (RPT) System - Instrumentation and Controls 7.6.1a.8.1 System Identification 7.6.1a.8.1.1 Safety Classification 7.6.1a.8.1.2 Reference Design 7.5.1a.8.2 Power Sources 7.6.1a.8.3 Equipment Design 7.6.1a.8.3.1 Initiating Circuits 7.6.1a.8.3.2 Logic 7.6.1a.8.3.3 Instrument Piping SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxviii 7.6.1a.8.3.4 Actuated Devices 7.6.1a.8.3.5 Separation 7.6.1a.8.3.6 Testability 7.6.1a.8.4 Environmental Considerations 7.6.1a.8.5 Operational Considerations 7.6.1a.8.5.1 General Information 7.6.1a.8.5.2 Reactor Operator Information 7.6.1a.8.5.3 Setpoints 7.6.1a.8.6 IEEE-279 Design Basis Considerations 7.6.1a.9 Process Computer System-Rod Worth Minimizer (RWM) - Instrumentation and Controls

7.6.1b Description

7.6.1b.1 Containment Monitoring - Instrumentation and Controls 7.6.1b.1.1 Primary Containment Drywell and Suppression Chamber Pressure Monitoring System 7.6.1b.1.1.1 System Identification 7.6.1b.1.1.2 Safety Evaluation 7.6.1b.1.1.3 Power Supply 7.6.1b.1.1.4 Equipment Design

7.6.1b.1.1.5 Redundancy 7.6.1b.1.1.6 Separation 7.6.1b.1.1.7 Operational Considerations 7.6.1b.1.1.8 Environmental Consideration 7.6.1b.1.2 Primary Containment Drywell and Suppression Pool Temperature Monitoring System 7.6.1b.1.2.1 System Identification 7.6.1b.1.2.2 Safety Evaluation 7.6.1b.1.2.3 Power Sources 7.6.1b.1.2.4 Equipment Design 7.6.1b.1.2.4.1 Equipment Design-Containment Temperature 7.6.1b.1.2.4.2 Equipment Design-Suppression Pool Temperature 7.6.1b.1.2.5 Redundancy 7.6.1b.1.2.6 Separation 7.6.1b.1.2.7 Operational Consideration 7.6.1b.1.2.8 Environmental Consideration 7.6.1b.1.3 Suppression Pool Water Level Monitoring System 7.6.1b.1.3.1 System Identification 7.6.1b.1.3.2 Safety Evaluation 7.5.1b.1.3.3 Power Sources SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxix 7.6.1b.1.3.4 Equipment Design 7.6.1b.1.3.5 Redundancy 7.6.1b.1.3.6 Separation 7.6.1b.1.3.7 Operational Considerations 7.6.1b.1.3.8 Environmental Considerations 7.6.1b.1.4 Primary Containment and Suppression Chamber Airborne Particulate Radioactivity Monitoring System - Instrumentation and Controls 7.6.1b.1.5 Primary Containment Radiation Monitoring System (High Range) 7.6.1b.1.5.1 System Identification 7.6.1b.1.5.2 Safety Evaluation 7.6.1b.1.5.3 Power Supply 7.6.1b.1.5.4 Equipment Design

7.6.1b.1.5.5 Redundancy 7.6.1b.1.5.6 Separation 7.6.1b.1.5.7 Operational Considerations 7.6.1b.1.5.8 Environmental Consideration 7.6.1b.1.6 Safety/Relief Valve Position Indication System 7.6.1b.1.6.1 System Identification 7.6.1b.1.6.2 Safety Evaluation 7.6.1b.1.6.3 Power Sources 7.6.1b.1.6.4 Equipment Design

7.6.1b.1.6.5 Redundancy 7.6.1b.1.6.6 Separation 7.6.1b.1.6.7 Operational Considerations 7.6.1b.1.6.8 Environmental Considerations 7.6.1b.2 Non-NSSS Process Radiation Monitoring System - Instrumentation and Controls 7.6.1b.2.1 Refueling Floor Wall Exhaust Radiation Monitoring Subsystem 7.6.1b.2.2 Refueling Floor High Exhaust Radiation Monitoring Subsystem 7.6.1b.2.3 Railroad Access Shaft Exhaust Radiation Monitoring Subsystem 7.6.1b.2.4 Emergency Outside Air Intake Radiation Monitoring Subsystem 7.6.1b.2.5 Standby Gas Treatment System Exhaust Vent Radiation Monitoring Subsystem 7.6.1b.3 Diesel Generator Initiation - Instrumentation and Controls 7.6.1b.3.1 Initiation 7.6.1b.3.2 Logic 7.6.1b.3.3 Bypasses 7.6.1b.4 Drywell Entry Purge - Instrumentation and Controls 7.6.1b.4.1 Initiating Circuits, Logic, and Bypasses 7.6.1b.4.2 Interlocks SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xl 7.6.1b.4.3 Sequencing, Redundancy, and Diversity

7.6.2a Analysis for NSSS - Systems

7.6.2a.1 Refueling Interlocks System - Instrumentation and Controls 7.6.2a.2 Process Radiation Monitoring System - Instrumentation and Controls 7.6.2a.2.1 Main Steamline Radiation Monitoring Subsystem 7.6.2a.2.1.1 General Functional Requirement Conformance 7.6.2a.2.1.2 Specific Regulatory Requirement Conformance 7.6.2a.3 High Pressure/Low Pressure Interlock Protection and Control System 7.6.2a.3.1 General Functional Requirements Conformance 7.6.2a.3.2 Specific Regulatory Requirements Conformance 7.6.2a.3.2.1 General Design Criteria Conformance 7.6.2a.3.2.2 IEEE Standards Conformance 7.6.2a.3.2.2.1 Conformance to IEEE Standard 279-1971 7.6.2a.3.2.2.2 Conformance to IEEE Standard 338-1971 7.6.2a.3.2.2.3 Conformance to IEEE Standard 379-1972 7.6.2a.3.2.3 Regulatory Guide Conformance 7.6.2a.3.2.3.1 Conformance to Regulatory Guide 1.22 7.6.2a.3.2.3.2 Conformance to Regulatory Guide 1.53 7.6.2a.4 NSSS Leak Detection System - Instrumentation and Controls 7.6.2a.4.1 General Functional Requirements Conformance 7.6.2a.4.2 Specific Regulatory Requirements Conformance 7.6.2a.4.2.1 Regulatory Guides Conformance 7.6.2a.4.2.2 Regulation Conformance 7.6.2a.4.2.3 Industry Standards Conformance 7.6.2a.5 Neutron Monitoring System - Instrumentation and Controls 7.6.2a.5.1 Source Range Monitor Subsystem 7.6.2a.5.2 Intermediate Range Monitor Subsystem 7.6.2a.5.2.1 General Functional Requirements Conformance 7.6.2a.5.2.2 Specific Regulatory Requirement Conformance 7.6.2a.5.3 Local Power Range Monitor Subsystem 7.6.2a.5.3.1 General Functional Requirement Conformance 7.6.2a.5.3.2 Specific Regulatory Requirement Conformance 7.6.2a.5.4 Average Power Range Monitor Subsystem 7.6.2a.5.4.1 General Functional Requirement Conformance 7.6.2a.5.4.2 Specific Regulatory Requirement Conformance 7.6.2a.5.5 Rod Block Monitoring Subsystem 7.6.2a.5.6 Traversing In-Core Probe Subsystem (TIPS)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xli 7.6.2a.6 Rod Block Trip - Instrumentation and Controls 7.6.2a.7 Rod Sequence Control System 7.6.2a.8 Recirculation Pump Trip System 7.6.2a.8.1 General Functional Requirements Conformance 7.6.2a.8.2 Specific Regulatory Requirement Conformance (IEEE 279-1971) 7.6.2a.9 Process Computer System-Rod Worth Minimizer (RWM) -Instrumentation and Controls 7.6.2a.10 Additional Design Considerations Analyses 7.6.2a.10.1 General Plant Safety Analyses 7.6.2a.10.2 Cold Water Slug Injection 7.6.2a.10.3 Refueling Accidents 7.6.2a.10.4 Overpressurization of Low Pressure System

7.6.2b Analysis for Non-NSSS Systems

7.6.2b.1 General Functional Requirement Conformance 7.6.2b.2 Specific Requirements Conformance

7.6.3 References

7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY

7.7.1 Description

7.7.1.1 Reactor Vessel - Instrumentation 7.7.1.1.1 System Identification 7.7.1.1.1.1 General 7.7.1.1.1.2 Classification 7.7.1.1.1.3 Reference Design 7.7.1.1.2 Power Sources 7.7.1.1.3 Equipment Design 7.7.1.1.3.1 Circuit Description 7.7.1.1.3.1.1 Reactor Vessel Temperature 7.7.1.1.3.1.2 Reactor Vessel Water Level 7.7.1.1.3.1.3 Reactor Core Hydraulics 7.7.1.1.3.1.4 Reactor Vessel Pressure 7.7.1.1.3.1.5 Reactor Vessel Head Seal Leak Detection 7.7.1.1.3.1.6 Safety/Relief Valve Seal Leak Detection 7.7.1.1.3.1.7 Other Instruments 7.7.1.1.3.2 Testability 7.7.1.1.4 Environmental Considerations SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlii 7.7.1.1.5 Operational Considerations 7.7.1.1.5.1 General Information 7.7.1.1.5.2 Reactor Operator Information 7.7.1.1.5.3 Setpoints 7.7.1.2 Reactor Manual Control System - Instrumentation and Controls 7.7.1.2.1 System Identification 7.7.1.2.1.1 General 7.7.1.2.1.2 Classification 7.7.1.2.1.3 Reference Design 7.7.1.2.2 Power Sources 7.7.1.2.3 Equipment Design 7.7.1.2.3.1 General 7.7.1.2.3.2 Rod Movement Controls 7.7.1.2.3.2.1 Control Rod Drive Control System 7.7.1.2.3.2.1.1 Introduction 7.7.1.2.3.2.1.2 Insert Cycle 7.7.1.2.3.2.1.3 Withdraw Cycle 7.7.1.2.3.2.2 Control Rod Drive - Hydraulic System Control 7.7.1.2.3.2.3 Rod Block Interlocks 7.7.1.2.3.2.4 Testability 7.7.1.2.3.3 Rod Position Information 7.7.1.2.3.3.1 Position Probes

7.7.1.2.3.3.2 Position Indication Electronics 7.7.1.2.3.3.3 System Operation 7.7.1.2.4 Environmental Considerations 7.7.1.2.5 Operational Considerations 7.7.1.2.5.1 General Information 7.7.1.2.5.2 Reactor Operator Information 7.7.1.2.5.3 Setpoints 7.7.1.2.6 Rod Block Sub-Trip System of RMCS 7.7.1.2.6.1 Grouping of Channels 7.7.1.2.6.2 Rod Block Functions 7.7.1.2.6.3 Rod Block Bypasses 7.7.1.2.6.4 Rod Block Interlocks 7.7.1.2.6.5 Redundancy 7.7.1.2.6.6 Testability 7.7.1.2.6.7 Environmental Considerations 7.7.1.2.6.8 Operational Considerations 7.7.1.2.7 Rod Sequence Control System (RSCS) - Subsystem of RMCS Instrumentation Controls 7.7.1.2.7.1 System Identification SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xliii 7.7.1.2.7.2 Power Sources 7.7.1.2.7.3 Equipment Design 7.7.1.2.7.3.1 General Description 7.7.1.2.7.3.2 Inputs 7.7.1.2.7.3.3 Outputs 7.7.1.2.7.3.4 Description of Function Blocks 7.7.1.2.7.3.4.1 Rod Pattern Controller (RPC) 7.7.1.2.7.3.4.2 Substitute Position Generator 7.7.1.2.7.3.4.3 Operator Display 7.7.1.2.7.3.4.4 Tester 7.7.1.2.7.3.4.5 Bypassed Rod Identifier 7.7.1.2.7.3.4.6 Logic Rules 7.7.1.2.7.3.4.7 Buffering 7.7.1.2.7.3.4.8 RSCS Rod Insertion Block Bypass Mode 7.7.1.2.7.4 Environmental Considerations 7.7.1.2.7.5 Operational Considerations 7.7.1.2.7.6 Separation 7.7.1.2.8 Rod Worth Minimizer (RWM) - Instrumentation and Controls 7.7.1.2.8.1 System Identification 7.7.1.2.8.2 Power Sources 7.7.1.2.8.3 Equipment Design 7.7.1.2.8.4 System Interface Relationship 7.7.1.2.8.5 Operational Considerations 7.7.1.3 Recirculation Flow Control System - Instrumentation and Controls 7.7.1.3.1 System Identification 7.7.1.3.1.1 General 7.7.1.3.1.2 Classification 7.7.1.3.1.3 Reference Design 7.7.1.3.2 Power Sources 7.7.1.3.3 Equipment Design 7.7.1.3.3.1 General 7.7.1.3.3.2 Pump Drive Motor Control 7.7.1.3.3.2.1 ATWS Trip 7.7.1.3.3.3 High Frequency Motor - Generator (HFMG) Set 7.7.1.3.3.4 Speed Control 7.7.1.3.3.4.1 Digital Integrated Control System - Reactor Recirculation Pump Speed 7.7.1.3.3.4.2 Modes of Speed Control Operation 7.7.1.3.3.4.3 Speed Limiters and Rundown 7.7.1.3.3.4.4 Recirculation Loop Starting Sequence 7.7.1.3.3.5 Testability SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xliv 7.7.1.3.4 Environmental Considerations 7.7.1.3.5 Operational Considerations 7.7.1.3.5.1 General Information 7.7.1.3.5.2 Reactor Operator Information 7.7.1.3.5.3 Setpoints 7.7.1.4 Feedwater Control System - Instrumentation and Controls 7.7.1.4.1 System Identification 7.7.1.4.1.1 General 7.7.1.4.1.2 Classification 7.7.1.4.1.3 Reference Design 7.7.1.4.2 Power Sources 7.7.1.4.3 Equipment Design 7.7.1.4.3.1 General 7.7.1.4.3.2 Reactor Vessel Water Level Measurement 7.7.1.4.3.3 Steam Flow Measurement 7.7.1.4.3.4 Feedwater Flow Measurement 7.7.1.4.3.5 Feedwater/Level Control 7.7.1.4.3.5.1 Interlocks 7.7.1.4.3.6 Turbine-Driven Feedwater Pump Control 7.7.1.4.3.7 Testability 7.7.1.4.4 Environmental Considerations 7.7.1.4.5 Operational Considerations 7.7.1.4.5.1 General Information 7.7.1.4.5.2 Reactor Operator Information 7.7.1.4.5.3 Setpoints 7.7.1.5 Pressure Regulator and Turbine-Generator Control System 7.7.1.5.1 Power Generation Design Bases 7.7.1.5.2 Power Sources 7.7.1.5.3 Equipment Design 7.7.1.5.3.1 System Description 7.7.1.5.3.2 Steam Pressure Control 7.7.1.5.3.3 Steam Bypass System 7.7.1.5.3.4 Turbine Speed System/Load Control System 7.7.1.5.3.5 Turbine Generator to Reactor Protection System Interface 7.7.1.5.3.6 Turbine Generator to Main Steam Isolation System Interface 7.7.1.5.3.7 Inspection and Testing 7.7.1.5.4 Environmental Considerations 7.7.1.5.5 Operational Considerations 7.7.1.6 Neutron Monitoring System - Traversing In-Core Probe (TIP) Subsystem - Instrumentation and Controls SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlv 7.7.1.6.1 System Identification 7.7.1.6.1.1 General 7.7.1.6.1.2 Classification 7.7.1.6.1.3 Reference Design 7.7.1.6.2 Power Sources 7.7.1.6.3 Equipment Design 7.7.1.6.3.1 General 7.7.1.6.3.2 Equipment Arrangement 7.7.1.6.3.3 Testability 7.7.1.6.4 Environmental Considerations 7.7.1.6.5 Operational Considerations 7.7.1.7 Plant Integrated Computer System and Reactor Data Analysis System (RDAS) - Instrumentation 7.7.1.7.1 System Identification 7.7.1.7.1.1 General Objectives 7.7.1.7.1.2 Classification 7.7.1.7.1.3 Reference Design 7.7.1.7.2 Power Sources 7.7.1.7.3.1 System Description 7.7.1.7.3.1.1 Reactor Data Analysis System 7.7.1.7.3.2 Testability 7.7.1.7.4 Environmental Considerations 7.7.1.7.5 Operational Considerations 7.7.1.7.5.1 General Information 7.7.1.7.5.2 Reactor Operator Information 7.7.1.8 Reactor Water Cleanup (RWCU) System - Instrumentation and Controls 7.7.1.8.1 System Identification 7.7.1.8.1.1 General 7.7.1.8.1.2 Classification 7.7.1.8.1.3 Reference Design 7.7.1.8.2 Power Sources 7.7.1.8.3 Equipment Design 7.7.1.8.3.1 General 7.7.1.8.3.2 Circuit Description 7.7.1.8.3.3 Testability 7.7.1.8.4 Environmental Considerations 7.7.1.8.5 Operational Considerations 7.7.1.8.5.1 General Information 7.7.1.8.5.2 Reactor Operator Information 7.7.1.8.5.3 Setpoints SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlvi 7.7.1.9 Transient Monitoring System for Startup Testing 7.7.1.9.1 Transient Monitoring System (TMS) Description 7.7.1.9.2 Piping Thermal Expansion and Vibration Measurement 7.7.1.10 Refueling Interlocks System - Instrumentation and Controls 7.7.1.10.1 System Identification 7.7.1.10.2 Power Sources 7.7.1.10.3 Equipment Design 7.7.1.10.3.1 Circuit Description 7.7.1.10.3.2 Logic and Sequencing

7.7.1.10.3.3 Bypasses and Interlocks 7.7.1.10.3.4 Redundancy and Diversity 7.7.1.10.3.5 Actuated Devices 7.7.1.10.3.6 Separation 7.7.1.10.3.7 Testability 7.7.1.10.4 Environmental Considerations 7.7.1.10.5 Operational Considerations 7.7.1.10.5.1 General Information 7.7.1.10.5.2 Reactor Operator Information 7.7.1.10.5.3 Setpoints 7.7.1.11 Neutron Monitoring System - Rod Block Monitor (RBM) Subsystem 7.7.1.11.1 Equipment Design 7.7.1.11.1.1 Description 7.7.1.11.1.2 Rod Block Trip Function 7.7.1.11.1.3 Bypasses

7.7.1.11.1.4 Redundancy 7.7.1.11.1.5 Testability 7.7.1.11.2 Environmental Considerations 7.7.1.11.3 Operational Considerations 7.7.1.12 Nuclear Pressure Relief System 7.7.1.12.1 System Identification 7.7.1.12.2 Equipment Design 7.7.1.12.3 Initiating Circuits 7.7.1.12.4 Logic and Sequencing 7.7.1.12.5 Bypasses and Interlocks 7.7.1.12.6 Redundancy and Diversity 7.7.1.12.7 Actuated Devices 7.7.1.12.8 Separation 7.7.1.12.9 Testability 7.7.1.12.10 Environmental Considerations 7.7.1.12.11 Operational Considerations 7.7.1.12.11.1 General Information SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlvii 7.7.1.12.11.2 Operational Information 7.7.1.13 Neutron Monitoring System - Source Range Monitor (SRM)

Subsystem 7.7.1.13.1 Equipment Design 7.7.1.13.1.1 Description

7.7.1.13.1.1.1 Bypasses and Interlocks 7.7.1.13.1.2 Redundancy and Diversity 7.7.1.13.1.3 Testability 7.7.1.13.2 Environmental Considerations 7.7.1.13.3 Operational Considerations 7.7.1.14 Loose Parts Monitoring System

7.7.2 Analysis

7.7.2.1 Reactor Vessel - Instrumentation 7.7.2.1.1 General Functional Requirements Conformance 7.7.2.1.2 Specific Regulatory Requirements Conformance 7.7.2.2 Reactor Manual Control System - Instrumentation and Controls 7.7.2.2.1 General Functional Requirements Conformance 7.7.2.2.2 Specific Regulatory Requirements 7.7.2.2.3 Rod Block Trip - Instrumentation and Controls 7.7.2.2.3.1 General Functional Requirements Conformance 7.7.2.2.3.2 Specific Regulatory Requirement Conformance 7.7.2.2.4 Rod Sequence Control System 7.7.2.2.4.1 Conformance to General Functional Requirements 7.7.2.2.4.2 Conformance to Specific Regulatory Requirement 7.7.2.2.5 Rod Worth Minimizer (RWM) - Instrumentation and Controls 7.7.2.2.5.1 General Functional Requirements Conformance 7.7.2.2.5.2 Specific Regulatory Requirements Conformance 7.7.2.3 Recirculation Flow Control System - Instrumentation and Controls 7.7.2.3.1 General Functional Requirements Conformance 7.7.2.3.2 Specific Regulatory Requirements 7.7.2.4 Feedwater Control System (Turbine-Driven Pumps) - Instrumentation and Controls 7.7.2.4.1 General Functional Requirements Conformance 7.7.2.4.2 Specific Regulatory Requirements Conformance 7.7.2.5 Pressure Regulatory and Turbine-Generator System Instrumentation and Controls 7.7.2.5.1 General Functional Requirements Conformance 7.7.2.5.2 Specific Regulatory Requirements Conformance 7.7.2.6 Neutron Monitoring System Traversing In-Core Probe Subsystem SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlviii (TIP) - Instrumentation and Controls 7.7.2.6.1 General Functional Requirement Conformance 7.7.2.6.2 Specific Regulatory Requirement Conformance 7.7.2.7 Plant Computer System - Instrumentation 7.7.2.7.1 General Functional Requirements 7.7.2.7.2 Specific Regulatory Requirements Conformance 7.7.2.8 Reactor Water Cleanup System - Instrumentation and Controls 7.7.2.8.1 General Functional Requirement Conformance 7.7.2.8.2 Specific Regulatory Requirements Conformance 7.7.2.9 Transient Monitoring System Analysis 7.7.2.9.1 TMS Safety-Related Functions 7.7.2.9.1.1 TMS Safety-Related System Isolation 7.7.2.9.1.2 TMS Wiring Separation 7.7.2.10 Refueling Interlocks System - Instrumentation and Controls 7.7.2.10.1 General Functional Requirements Conformance 7.7.2.10.2 Specific Regulatory Requirements Conformance 7.7.2.11 Rod Block Monitor Subsystem 7.7.2.11.1 General Functional Requirement Conformance 7.7.2.11.2 Specific Regulatory Requirement Conformance 7.7.2.12 Nuclear Pressure Relief System - Instrumentation and Controls 7.7.2.12.1 General Functional Requirements Conformance 7.7.2.12.2 Specific Regulatory Requirements 7.7.2.13 Neutron Monitoring System - Instrumentation and Controls 7.7.2.13.1 Source Range Monitor Subsystem 7.7.2.13.1.1 General Functional Requirement Conformance 7.7.2.13.1.2 Specific Regulatory Requirements Conformance

7.7.3 References

SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-xlix 7.1-1 Responsibility

7.1-2 Similarity to Licensed Reactors

7.1-3 Codes and Standards Applicability Matrix

7.1-4 Reactor Protection System Codes and Standards

7.1-5 Primary Containment and Reactor Vessel Isolation Control System Codes and Standards

7.1-6 High Pressure ECCS (HPCI, ADS A, ADS B Network) Codes and Standards

7.1-7 Low Pressure ECCS (CS, RHR Network) Codes and Standards

7.1-8 Process Radiation Moni toring Codes and Standards

7.1-9 Leak Detection System Codes and Standards

7.1-10 Reactor Protection System Sensor Suffix Letters and Division Allocation

7.1-11 Four Division Grouping for Neutron Monitoring System

7.1-12 Emergency Core Cooling System and RCIC Sensor Suffix Letters and Division Allocation

7.2-1 Reactor Protection System Instrumentation Specifications

7.2-2 Channels Required for Functional Performance of RPS

7.2-3 ATWS Recirculation Pump Trip and Alternate Rod Injection Instrumentation Specifications

7.2-4 Channels Required for Functional Performance of ARI 7.3-1 High Pressure Coolant Injection System-Instrument Specifications and Channels

7.3-2 Automatic Depressurization System-Instrument Specifications and SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-l Channels 7.3-3 Core Spray System-Instrument Specifications and Channels

7.3-4 Low Pressure Coolant Injection-Instrument Specification and Channels 7.3-5 Primary Containment and Reactor Vessel Isolation Control System Instrumentation Specifications

7.3-6 This Table Has Been Deleted

7.3-7 This Table Has Been Deleted

7.3-8 This Table Has Been Deleted

7.3-9 This Table Has Been Deleted

7.3-10 This Table Has Been Deleted

7.3-11 This Table Has Been Deleted

7.3-12 This Table Has Been Deleted

7.3-13 ESFAS Actuated Equipment Standby Gas Treatment System

7.3-14 ESFAS Actuated Equipment Recirculation System, Reactor Building Isolation Dampers, and Reactor Building Non-Safety

Related Equipment

7.3-15 ESFAS Actuated Equipment Control Structure Emergency Outside Air Supply System

7.3-16 ESFAS Actuated Equipment Battery Rooms Exhaust System

7.3-17 General Notes for Tables 7.3-13 Through 7.3-16 7.3-18 Standby Gas Treatment System (SGTS) Failure Mode and Effects Analysis 7.3-19 Reactor Building Recirculation System Failure Mode and Effects SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-li Analysis 7.3-20 Failure Mode and Effects Analysis Primary Containment Isolation Control System Fan Non-NSS Systems

7.3-21 Emergency Outside Air Supply System (EOASS) Failure Mode and Effects Analysis

7.3-22 Computer Room Cooling System (CRCS) Failure Mode and Effects Analysis 7.3-23 Control Structure H&V System (CSHVS) Failure Mode and Effects Analysis 7.3-24 Control Structure Chilled Water System (CSCWS) Failure Mode and Effects Analysis

7.3-25 Battery Rooms Exhaust System Failure Mode and Effects Analysis

7.3-26 Control Room Floor Cooling System (CRFCS) Failure Mode and Effects Analysis

7.3-27 This Table Has Been Deleted

7.3-28 Reactor Protection System Response Times

7.3-29 Isolation System Instrumentation Response Time

7.3-30 Emergency Core Cooling System Response Times

7.4-1 This Table Has Been Deleted

7.4-2 RHRS Shutdown Cooling Bypasses and Interlocks

7.4-3 Remote Shutdown Panel Instrumentation

7.4-4 Alternate Control Structure HVAC Control Panel

7.5-1 Safety Related Display Instrumentation

7.5-2 Safety Related Display Instrumentation-Habitability (Emergency SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-lii Outside Air System/Control Structure HVAC)

7.5-3 Safety Related Display Instrumentation-Containment and Suppression Pool Instrumentation

7.5-4 Safety Related Display Instrumentation-Standby Gas Treatment System, RX Building Recirculation and Isolation System

7.5-5 Safety Related Display Instrumentation-Emergency Service Water System 7.5-6 Safety Related Display Instrumentation-RHR Service Water System and Spray Pond

7.5-7 Safety Related Display Instrumentation-Containment Instrument Gas System

7.5-7a Safety Related Display Instrumentation Standby Liquid Control System 7.5-8 Bypass Indication System for Non-NSSS Systems

7.6-1 (This table has been intentionally left blank)

7.6-2 (This table has been intentionally left blank)

7.6-3 IRM Trips

7.6-4 LPRM System Trips

7.6-5 APRM System Trips

7.6-6 (This table has been intentionally left blank)

7.6-7 OPRM System Trip

7.6-8 This Table Has Been Deleted

7.6-9 Suppression Pool Temperature Sensor Locations

7.6-10 End-of-Cycle Recirculation Pump Trip System Response Time SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-liii 7.7-1 CRD Hydraulic System Process Indicators

7.7-2 Refueling Interlock Effectiveness

7.7-3 RBM System Trips

7.7-4 IRM Trips

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-liv 7.2-1-1 This Figure has been replaced by Dwg. M1-C72-2, Sh. 1

7.2-1-2 This Figure has been replaced by Dwg. M1-C72-2, Sh. 2

7.2-1-3 This Figure has been replaced by Dwg. M1-C72-2, Sh. 3

7.2-1-4 This Figure has been replaced by Dwg. M1-C72-2, Sh. 4

7.2-2 Reactor Protection System Scram Functions

7.2-3 Arrangement of Channels and Logics

7.2-4 Actuators and Actuator Logics

7.2-5 Logic in One Trip System

7.2-6 Relationship Between Neutron Monitoring System and Reactor Protection System

7.2-7 Configuration for Turbine Stop Valve Closure Reactor Trip

7.2-8 Configuration for Main Steamline Isolation Reactor Trip

7.2-9 Block Diagram - RPS Protective Circuit - Electrical Protection Assembly (EPA)

7.2-10 ARI Trip System Logic

7.2-11 This Figure Intentionally Deleted

7.3-1 This Figure Has been Deleted

7.3-2 Isolation Control System for Main Steamline Isolation Valves

7.3-3 Isolation Control System Using Motor-Operated Valves

7.3-4 Main Steamline Isolation Valve Schematic

7.3-5-1 Initiation Logic - ADS, CS, RHR

7.3-5-2 ADS Initiation Logic SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lv 7.3-5-3 Unit 2 ADS Initiation Logic

7.3-6 Initiation Logic - HPCI, RCIC

7.3-7-1 This Figure has been replaced by Dwg. M1-E41-65, Sh. 1

7.3-7-2 This Figure has been replaced by Dwg. M1-E41-65, Sh. 2

7.3-7-3 This Figure has been replaced by Dwg. M1-E41-65, Sh. 3

7.3-7-4 This Figure has been replaced by Dwg. M1-E41-65, Sh. 4

7.3-7-5 This Figure has been replaced by Dwg. M1-E41-65, Sh. 5

7.3-8-1 This Figure has been replaced by Dwg. M1-B21-92, Sh. 1

7.3-8-2 This Figure has been replaced by Dwg. M1-B21-92, Sh. 2

7.3-8-3 This Figure has been replaced by Dwg. M1-B21-92, Sh. 3

7.3-8-4 This Figure has been replaced by Dwg. M1-B21-92, Sh. 4

7.3-8-5 This Figure has been replaced by Dwg. M1-B21-92, Sh. 5

7.3-8-6 This Figure has been replaced by Dwg. M1-B21-92, Sh. 6

7.3-9-1 This Figure has been replaced by Dwg. M1-E21-3, Sh. 1

7.3-9-2 This Figure has been replaced by Dwg. M1-E21-3, Sh. 2

7.3-9-3 This Figure has been replaced by Dwg. M1-E21-3, Sh. 3

7.3-10-1 This Figure has been replaced by Dwg. M1-E11-51, Sh. 1

7.3-10-2 This Figure has been replaced by Dwg. M1-E11-51, Sh. 2 7.3-10-3 This Figure has been replaced by Dwg. M1-E11-51, Sh. 3

7.3-10-4 This Figure has been replaced by Dwg. M1-E11-51, Sh. 4

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lvi 7.3-10-5 This Figure has been replaced by Dwg. M1-E11-51, Sh. 5

7.3-11-1 This Figure has been replaced by Dwg. M1-D12-1, Sh. 1

7.3-11-2 This Figure has been replaced by Dwg. M1-D12-1, Sh. 2

7.3-11-3 This Figure has been replaced by Dwg. M1-D12-1, Sh. 3

7.3-11-4 This Figure has been replaced by Dwg. M1-D12-1, Sh. 4

7.3-11-5 This Figure has been replaced by Dwg. M1-D12-1, Sh. 5

7.4-1 This Figure has been replaced by Dwgs. M-149, Sh. 1 & M-150, Sh. 1 7.4-2-1 This Figure has been replaced by Dwg. M1-E51-80, Sh. 1

7.4-2-2 This Figure has been replaced by Dwg. M1-E51-80, Sh. 2

7.4-2-3 This Figure has been replaced by Dwg. M1-E51-80, Sh. 3

7.4-2-4 This Figure has been replaced by Dwg. M1-E51-80, Sh. 4

7.4-3 This Figure has been replaced by Dwg. M-148, Sh. 1

7.4-4 This Figure has been replaced by Dwg. M1-C41-31, Sh. 1

7.5-1-1 This Figure Has Been Deleted

7.5-1-2 This Figure Has Been Deleted

7.5-1-3 This Figure Has Been Deleted

7.5-1-4 This Figure Has Been Deleted

7.5-1-5 This Figure Has Been Deleted 7.5-1-6 This Figure Has Been Deleted

7.5-2-1 This Figure Has Been Deleted

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lvii 7.5-2-2 This Figure Has Been Deleted

7.5-2-3 This Figure Has Been Deleted

7.5-3 Neutron Flux at Primary Shield

7.6-1 Recirculation Pump Leak Detection Block Diagram

7.6-2 RHR Area Temperature Monitoring System Block Diagram

7.6-3 Vessel Penetrations for Nuclear Instrumentation

7.6-4-1 This Figure has been replaced by Dwg. M1-C51-35, Sh. 1

7.6-4-2 This Figure has been replaced by Dwg. M1-C51-35, Sh. 2

7.6-5 SRM/IRM Neutron Monitoring Unit

7.6-6 Detector Drive System Schematic

7.6-7-1 This Figure has been replaced by Dwg. M1-C51-2, Sh. 1

7.6-7-2 This Figure has been replaced by Dwg. M1-C51-2, Sh. 2

7.6-7-3 This Figure has been replaced by Dwg. M1-C51-2, Sh. 3

7.6-7-4 This Figure has been replaced by Dwg. M1-C51-2, Sh. 4

7.6-7-5 This Figure has been replaced by Dwg. M1-C51-2, Sh. 5

7.6-7-6 This Figure has been replaced by Dwg. M1-C51-2, Sh. 6

7.6-7-7 This Figure has been replaced by Dwg. M1-C51-2, Sh. 7

7.6-8 Functional Block Diagram of SRM Channel

7.6-9 Functional Block Diagram of IRM Channel

7.6-10 Power Range Monitor Det ector Assembly Location

7.6-11-1 Refer to Figure 5.4-2A SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lviii 7.6-11-2 This Figure has been replaced by Dwg. M1-B31-13, Sh. 2

7.6-11-3 This Figure has been replaced by Dwg. M1-B31-13, Sh. 3

7.6-12 APRM Circuit Arrangement for Reactor Protection System Input

7.6-13 Ranges of Neutron Monitoring System

7.7-1 Water Level Range Definition

7.7-2-1 Control Rod Drive Hydraulic System - FCD

7.7-2-2 Control Rod Drive Hydraulic System - FCD

7.7-2-3 Control Rod Drive Hydraulic System - FCD

7.7-2-4 Control Rod Drive Hydraulic System - FCD

7.7-2-5 Control Rod Drive Hydraulic System - FCD

7.7-2-6 Control Rod Drive Hydraulic System - FCD

7.7-2-7 Control Rod Drive Hydraulic System - FCD

7.7-3-1 This Figure has been replaced by Dwg. M1-C12-90, Sh. 4

7.7-3-2 This Figure has been replaced by Dwg. M1-C12-110, Sh. 8

7.7-4 Reactor Manual Control System Operation

7.7-5 Reactor Manual Control Self-Test Provisions

7.7-6 Eleven-Wire Position Probe

7.7-7-1 This Figure has been replaced by Dwg. M1-B31-189, Sh. 1 7.7-7-2 This Figure has been replaced by Dwg. M1-B31-189, Sh. 2

7.7-7-3 This Figure has been replaced by Dwg. M1-B31-189, Sh. 3

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lix 7.7-7-4 This Figure has been replaced by Dwg. M1-B31-189, Sh. 4

7.7-7-5 This Figure has been replaced by Dwg. M1-B31-189, Sh. 5

7.7-7-6 ATWS Recirculation Pump Trip Logic

7.7-8 Recirculation Flow Control Illustration

7.7-8a This Figure has been deleted

7.7-9 This Figure has been replaced by Dwg. M1-C32-3, Sh. 1

7.7-10 Detector Drive System Schematic

7.7-11 This Figure has been replaced by Dwg. M1-G33-143, Sh. 1

7.7-12 This Figure has been deleted

7.7-13 This Figure has been replaced by Dwg. A-105, Sh. 1

7.7-13a Control room Panel Safety Relat ed Display Instr. Plant Operator Interface

7.7-14 Traversing In-Core Probe Assembly

7.7-15 Main Turbine Control System Block Diagram

7.7-16 Assignment of LPRM Input to RBM System

7.7-17 Unit 1, RBM Response to Control Rod Motion (Channels A and C)

7.7-18 Unit 1, RBM Response to Control Rod Motion (Channels B and D) 7.7-19 Unit 2, Typical RBM Channel Responses, Old Versus New LPRM Assignment (No Failed LPRMS)

SSES-FSARTOCRev.60FSARRev.658-iCHAPTER8ELECTRICPOWERTABLEOFCONTENTSTEXTSectionTitle

8.1INTRODUCTION

8.1.1General 8.1.2UtilityPowerGridandOffsitePowerSystems 8.1.3OnsitePowerSystems 8.1.4SafetyRelatedLoads 8.1.5DesignBases 8.1.5.1SafetyDesignBases 8.1.6RegulatoryGuidesandIEEEStandards 8.1.6.1CompliancewithRegulatoryGuides8.1.6.2CompliancewithIEEE338,344,and3878.2OFFSITEPOWERSYSTEM 8.2.1Description 8.2.1.1TransmissionSystem8.2.1.2TransmissionInterconnection8.2.1.3Switchyards8.2.1.3.1StartupTransformers#10and#208.2.1.3.2SusquehannaUnit#1230kVMainTransformerLeads8.2.1.3.3Susquehanna230kVSwitchyard8.2.1.3.4SusquehannaUnit#2500kVMainTransformerLeads8.2.1.3.5Susquehanna500kVSwitchyard8.2.1.3.6MontourandMountain230kVSwitchyards8.2.1.4OffsitePowerSystemMonitoring 8.2.1.5IndustryStandards8.2.2Analysis SSES-FSARTOCRev.60CHAPTER8TEXTSectionTitleFSARRev.658-ii8.2.2.1GridAvailability8.2.2.2StabilityAnalysisAPPENDIX8.2ARELIABILITYPRINCIPLESANDSTANDARDSFORPLANNINGBULKELECTRICSUPPLYSYSTEMOFMAACGROUP8.3ONSITEPOWERSYSTEMS 8.3.1ACPowerSystems 8.3.1.1Description8.3.1.2Non-Class1EACSystem8.3.1.2.1Operation8.3.1.2.2Non-Class1EEquipmentCapacities8.3.1.3Class1EACPowerSystem8.3.1.3.1PowerSupplyFeeders8.3.1.3.2PowerFeederCables8.3.1.3.3BusArrangements8.3.1.3.4LoadsSuppliedfromEachBus8.3.1.3.5Class1EIsolatedSwingBus8.3.1.3.6ManualandAutomaticInterconnectionsBetweenBuses,BusesandLoads,andBusesandSupplies8.3.1.3.7InterconnectionsBetweenSafetyRelatedandNon-SafetyRelatedBuses,Non-SafetyRelatedLoads,andSafetyRelatedBuses8.3.1.3.8RedundantBusSeparation8.3.1.3.9Class1EEquipmentCapacities8.3.1.3.10AutomaticLoadingandLoadShedding8.3.1.3.11SafetyRelatedEquipmentIdentification8.3.1.3.12InstrumentationandControlSystemfortheApplicablePowerSystemsWiththeAssignedPowerSupplyIdentified8.3.1.3.13ElectricCircuitProtectionSystems8.3.1.3.14TestingoftheACSystemDuringPowerOperation8.3.1.3.15Class1ELoadsNotTestableDuringPowerOperations8.3.1.4StandbyPowerSupply8.3.1.4.1AutomaticStartingInitiatingCircuits8.3.1.4.2DieselStartingMechanismandSystem8.3.1.4.3AlarmandTrippingDevice8.3.1.4.4BreakerInterlocks8.3.1.4.5ControlPermissive8.3.1.4.6LoadingCircuits SSES-FSARTOCRev.60CHAPTER8TEXTSectionTitleFSARRev.658-iii8.3.1.4.7Testing8.3.1.4.8FuelOilStorageandTransferSystem8.3.1.4.9DieselGeneratorCoolingandHeating8.3.1.4.10InstrumentationandControlSystemsforStandbyPowerSupply8.3.1.4.11TestProgram8.3.1.4.11.1Class1EEquipmentIdentification8.3.1.4.11.2VendorQualificationTechniquesandDocumentation8.3.1.4.11.3PerformanceinServiceEnvironment8.3.1.4.11.4PeriodicTest8.3.1.4.12ControlandAlarmLogic8.3.1.5ElectricalEquipmentLayout8.3.1.6ReactorProtectionSystemPowerSupply8.3.1.7Class1E120VACInstrumentationandControlPowerSupply8.3.1.8Non-Class1EInstrumentandVitalACPowerSupply8.3.1.9DesignCriteriaforClass1EEquipment8.3.1.10Safety-RelatedLogicandSchematicDiagrams8.3.1.11Analysis8.3.1.11.1GeneralDesignCriteriaandRegulatoryGuideCompliance8.3.1.11.2SafetyRelatedEquipmentExposedtoAccidentEnvironment8.3.1.11.3PhysicalIdentificationofSafetyRelatedEquipment8.3.1.11.4IndependenceofRedundantSystemsSeparationCriteria8.3.1.11.5AdministrativeResponsibilitiesandControlsforEnsuringSeparationCriteria8.3.2DCPowerSystems 8.3.2.1Description8.3.2.1.1Class1EDCPowerSystem8.3.2.1.1.1125VDCSubsystems8.3.2.1.1.2250VDCSubsystems8.3.2.1.1.324VDCSubsystems8.3.2.1.1.4Class1EStationBatteriesandBatteryChargers 8.3.2.1.1.5Class1EDCSystemEquipmentRatings8.3.2.1.1.6Inspection,Maintenance,andTesting8.3.2.1.1.7SeparationandVentilation8.3.2.1.1.8Non-Class1EDCSystem8.3.2.2Analysis8.3.2.2.1CompliancewithGeneralDesignCriteria,RegulatoryGuides,andIEEEStandards8.3.2.2.2PhysicalIdentificationofSafetyRelatedEquipment8.3.2.2.3IndependenceofRedundantSystems SSES-FSARTOCRev.60CHAPTER8TEXTSectionTitleFSARRev.658-iv8.3.3FireProtectionforCableSystems8.3.3.1CableDeratingandCableTrayFill8.3.3.2FireDetectionforCableSystems8.3.3.3FireBarriersandSeparationBetweenRedundantTrays8.3.3.4FireStops SSES-FSARTOCRev.60CHAPTER8TABLESNumberTitleFSARRev.658-v8.1-1MotorOperatedValvesWithThermalOverloadContinuouslyBypassedDuringPlantOperation8.1-2AffiliatedandNon-Class1ECircuitsThatConnecttoClass1EPowerSupplies8.1-3Non-Class1EAnnunciatorandComputerInterfaceDevices 8.1-4DivisionalorAffiliatedLoadsSuppliedFromClass1EChannelCorD4.16kVBuss8.1-5ContainmentRadiationMonitorsSuppliedfromClass1ESystem 8.2-1SusquehannaUnit#1&#2StabilityCaseList(SummerLightLoadConditions)8.3-1AssignmentofESFandSelectedNon-ESFLoadstoDieselGeneratorsandESSBuses8.3-1aDieselGeneratorLoading(Note1),DieselGeneratorsA,B,CandDInService,Unit-DesignBasisAccident;Unit2-ForcedShutdown8.3-1bSupplementtoTable8.3-1 8.3-1cDieselGeneratorELoading,DieselGeneratorEInServiceforAorBorCorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-2DieselGeneratorLoading,DieselAUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-2aDieselGeneratorELoading,DieselAUnavailable,DieselGeneratorESubstitutedforDieselBorCorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-3DieselGeneratorLoading,DieselBUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-3aDieselGeneratorLoadingE,DieselBUnavailable,DieselGeneratorESubstitutedforDieselAorCorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown SSES-FSARTOCRev.60CHAPTER8TABLESNumberTitleFSARRev.658-vi8.3-4DieselGeneratorLoading,DieselCUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-4aDieselGeneratorELoading,DieselCUnavailable,DieselGeneratorESubstitutedforDieselAorBorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-5DieselGeneratorLoading,DieselDUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-5aDieselGeneratorELoading,DieselDUnavailable,DieselGeneratorESubstitutedforDieselAorBorC,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-6A125VoltDCLoadCycle through 8.3-6I8.3-6J125VDCBatteryDutyLoadProfiles 8.3-7AUnit1250VDCLoadCycleDiv.I(1D650) 8.3-7BUnit1250VDCLoadCycleDiv.II(1D660) 8.3-7CUnit2250VDCLoadCycleDiv.I(2D650) 8.3-7DUnit2250VDCLoadCycleDiv.II(2D660) 8.3-7E250VDCBatteryDutyLoadProfiles 8.3-824VoltDCLoadCycle8.3-9ACPowerFailureModeEffectsAnalysis8.3-10RoutingTable 8.3-11ThisTableHasBeenDeleted 8.3-12ThisTableHasBeenDeleted SSES-FSARTOCRev.60CHAPTER8TABLESNumberTitleFSARRev.658-vii8.3-13ThisTableHasBeenDeleted8.3-14ThisTableHasBeenDeleted 8.3-15ThisTableHasBeenDeleted 8.3-16DieselGeneratorAutoStartCircuitFailureEffectsAnalysis(1) 8.3-17125VDCControlPowerSourceforNon-Class1E13.8kVand4.16kVSwitchgear8.3-18125VDCControlPowerSourceForNon-Class1E480VL.C.

8.3-19125VDCControlPowerSourceForClass1E4.16kVSwitchgear 8.3-20125VDCControlPowerSourceForClass1E480VLC 8.3-21FailureModeandEffectAnalysis-125VDCSystem(4Channels) 8.3-22FailureModeandEffectAnalysis-250VDCSystem(2Divisions) 8.3-23FailureModeandEffectAnalysis-24VDCSystem(2Divisions) 8.3-24CommonMode-CommonCauseFailureAnalysis-AutoTransferSwitch 8.3-25SeparationMethodsandRequirementsWithinJunctionBoxesandFieldInstalledPullBoxes SSES-FSARTOCRev.60CHAPTER8FIGURESNumberTitleFSARRev.658-viii8.2-1ThisFigureHasBeenReplacedbyDrawingD159760,Sh.18.2-2BulkPowerSupplySysteminVicinityofSusquehannaSteamElectricStation8.2-3TransmissionSystem 8.2-4MontourandMountainSwitchyardsOneLineDiagram 8.3-1-1ThisFigureHasBeenReplacedbyDrawingE-1,Sh.1 8.3-1-2ThisFigureHasBeenReplacedbyDrawingE-1,Sh.1A 8.3-1-2aThisFigureHasBeenReplacedbyDrawingE-1,Sh.2 8.3-2ThisFigureHasBeenReplacedbyDrawingE-4,Sh.2 8.3-2APreferredPowerSuppliestoDieselGeneratorEClass1EPowerSystem 8.3-3ThisFigureHasBeenReplacedbyDrawingE-5,Sh.1 8.3-4ThisFigureHasBeenReplacedbyDrawingE-5,Sh.2 8.3-4AThisFigureHasBeenReplacedbyDrawingE-5,Sh.5 8.3-5ThisFigureHasBeenReplacedbyDrawingE-11,Sh.1 8.3-5AThisFigureHasBeenReplacedbyDrawingE-11,Sh.11 8.3-6ThisFigureHasBeenReplacedbyDrawingE-13,Sh.1 8.3-7ThisFigureHasBeenReplacedbyDrawingE-8,Sh.4 8.3-8ThisFigureHasBeenReplacedbyDrawingE-8,Sh.8 8.3-9480VoltSwingBuses 8.3-10ThisFigureHasBeenReplacedbyDrawingM-260,Sh.1 8.3-10AThisFigureHasBeenReplacedbyDrawingM-261,Sh.1 SSES-FSARTOCRev.60CHAPTER8FIGURESNumberTitleFSARRev.658-ix8.3-10BThisFigureHasBeenReplacedbyDrawingM-5200,Sh.18.3-11ThisFigureHasBeenReplacedbyDrawingE-31,Sh.8 8.3-12ThisFigureHasBeenReplacedbyDrawingE-31,Sh.9 8.3-13SingleLineDiagramfor480VoltSwingBusSystem 8.3-14SwingBusAutoTransforSwitchControlSchematic 8.3-15ThisFigureHasBeenReplacedbyDrawingE-31,Sh.5

SSES-FSARTOCRev.61FSARRev.6510-iCHAPTER10STEAMANDPOWERCONVERSIONSYSTEMTABLEOFCONTENTSTEXTSectionTitle10.1

SUMMARY

DESCRIPTION 10.2TURBINE-GENERATOR 10.2.1DesignBases 10.2.2Description 10.2.2.1Turbine10.2.2.2GeneratorandExciter10.2.2.3ProtectiveValvesFunctions10.2.2.4ExtractionSystemCheckValves10.2.2.5ControlSystem10.2.2.6OverspeedProtection10.2.2.7TurbineShellDiaphragms10.2.2.8Turbine-GeneratorLoadFollowingCapability10.2.3TurbineDiskIntegrity 10.2.3.1MaterialSelection10.2.3.2FractureToughness10.2.3.3High-TemperatureProperties10.2.3.4TurbineDesign10.2.3.5Pre-serviceInspection10.2.3.6InserviceInspection10.2.4Evaluation 10.2.5References 10.3MAINSTEAMSUPPLYSYSTEM 10.3.1DesignBases 10.3.2Description10.3.3Evaluation SSES-FSARTOCRev.61CHAPTER10TEXTSectionTitleFSARRev.6510-ii10.3.4InspectionandTestingRequirements10.3.5WaterChemistry(PWR) 10.3.6SteamandFeedwaterSystemMaterials 10.3.6.1FractureToughness10.3.6.2MaterialSelectionandFabrication10.4OTHERFEATURESOFTHESTEAMANDPOWERCONVERSIONSYSTEM10.4.1MainCondenser 10.4.1.1DesignBases10.4.1.2Description 10.4.1.3SafetyEvaluation10.4.1.3.1RadioactiveGases10.4.1.3.2CondenserLeakage10.4.1.3.3CirculatingWaterSystemRupture10.4.1.4TestsandInspections10.4.1.5ControlsandInstrumentation10.4.1.5.1Condenser10.4.1.5.2CondensateContamination10.4.2MainCondenserEvacuationSystem 10.4.2.1DesignBases10.4.2.2SystemDescription10.4.2.3SafetyEvaluation10.4.2.4TestsandInspections10.4.2.5ControlsandInstrumentation10.4.3SteamSealSystem 10.4.3.1DesignBases10.4.3.2Description10.4.3.3SafetyEvaluation SSES-FSARTOCRev.61CHAPTER10TEXTSectionTitleFSARRev.6510-iii10.4.3.4TestsandInspections10.4.3.5ControlsandInstrumentation10.4.4TurbineBypassSystem 10.4.4.1DesignBases10.4.4.2SystemDescription10.4.4.3SafetyEvaluation10.4.4.4TestsandInspections10.4.4.5ControlsandInstrumentation10.4.5CirculatingWaterSystem 10.4.5.1DesignBases10.4.5.2SystemDescription10.4.5.3SafetyEvaluation10.4.5.4TestsandInspections 10.4.5.5ControlsandInstrumentation10.4.6CondensateCleanupSystem 10.4.6.1DesignBases10.4.6.2SystemDescription10.4.6.2.1CondensateDemineralizers10.4.6.2.2SupportingSystems10.4.6.3SafetyEvaluation10.4.6.4TestsandInspections10.4.6.5ControlsandInstrumentation10.4.7CondensateandFeedwater 10.4.7.1DesignBases10.4.7.2SystemDescription10.4.7.3SafetyEvaluation10.4.7.4TestsandInspections10.4.7.5ControlsandInstrumentation10.4.8SteamGeneratorBlowdownSystem(PWR) 10.4.9AuxiliaryFeedwaterSystem(PWR)

SSES-FSARTOCRev.61CHAPTER10TEXTSectionTitleFSARRev.6510-iv10.4.10ExtractionSteamandFeedwaterHeaterDrainandVentSystem10.4.10.1DesignBasis10.4.10.2SystemDescription10.4.10.3SafetyEvaluation10.4.10.4TestsandInspections10.4.10.5ControlsandInstrumentation10.4.11AuxiliarySteamSystem 10.4.11.1DesignBases10.4.11.2SystemDescription10.4.11.3SafetyEvaluation10.4.11.4TestandInspections10.4.11.5InstrumentationApplication SSES-FSARTOCRev.61CHAPTER10TABLESNumberTitleFSARRev.6510-v10.1-1Unit1-SummaryofTypicalDesignandPerformanceCharacteristicsofPowerConversionSystem10.1-1aUnit2-SummaryofTypicalDesignandPerformanceCharacteristicsofPowerConversionSystem10.2-1TurbineOverspeedProtection 10.4-1CondenserDesignParameters 10.4-2ThisTableHasBeenDeleted 10.4-3CirculatingWaterQualityDesignParametersUsedfortheCondensateCleanup10.4-4ThisTableHasBeenDeleted10.4-5ThisTableHasBeenDeleted10.4-6DesignConditionsforFeedwaterHeaters SSES-FSARTOCRev.61CHAPTER10FIGURESNumberTitleFSARRev.6510-vi10.1-1ThisFigureHasBeenDeleted10.1-1aGuaranteedFlowUnit1 10.1-1bGuaranteedFlowUnit2 10.1-2ThisFigureHasBeenDeleted 10.1-2aValvesWideOpen(VWO)Unit1 10.1-2bValvesWideOpen(VWO)Unit2 10.2-1TurbineStopValveClosureCharacteristic 10.2-2TurbineControlValveFastClosureCharacteristic 10.2-3MechanicalOverspeedTrip 10.2-4ThisFigurehasbeenreplacedbyDwg.M2H-54,Sh.1 10.2-5ThisFigurehasbeenreplacedbyDwg.M2J-101,Sh.5 10.2-6RateSensitivePower/LoadUnbalanceCircuit 10.2-7ThisFigureHasBeenDeleted 10.2-8ThisFigureHasBeenDeleted 10.2-9ThisFigureHasBeenDeleted 10.2-10ThisFigureHasBeenDeleted 10.2-11BulkHydrogenSystem 10.4-1-1ThisFigurehasbeenreplacedbyDwg.M-101,Sh.1 10.4-1-1aThisFigurehasbeenreplacedbyDwg.M-2101,Sh.1 SSES-FSARTOCRev.61CHAPTER10FIGURESNumberTitleFSARRev.6510-vii10.4-1-2ThisFigurehasbeenreplacedbyDwg.M-101,Sh.210.4-1-2aThisFigurehasbeenreplacedbyDwg.M-2101,Sh.2 10.4-1-3ThisFigurehasbeenreplacedbyDwg.M-101,Sh.3 10.4-1-3aThisFigurehasbeenreplacedbyDwg.M-2101,Sh.3 10.4-2ThisFigureHasBeenRenumberedTo10.4-2-1 10.4-2-1ThisFigurehasbeenreplacedbyDwg.M-116,Sh.1 10.4-2-2ThisFigurehasbeenreplacedbyDwg.M-116,Sh.2 10.4-2-3ThisFigurehasbeenreplacedbyDwg.M-116,Sh.3 10.4-3ThisFigureHasBeenRenumberedTo10.4-2-2 10.4-4ThisFigureHasBeenDeleted 10.4-4-1ThisFigurehasbeenreplacedbyDwg.M-105,Sh.1 10.4-4-2ThisFigurehasbeenreplacedbyDwg.M-105,Sh.2 10.4-4-3ThisFigurehasbeenreplacedbyDwg.M-105,Sh.3 10.4-4-4ThisFigurehasbeenreplacedbyDwg.M-105,Sh.4 10.4-5ThisFigureHasBeenRenumberedTo10.4-5-1 10.4-5-1ThisFigurehasbeenreplacedbyDwg.M-106,Sh.1 10.4-5-2ThisFigurehasbeenreplacedbyDwg.M-106,Sh.2 10.4-5-2AThisFigurehasbeenreplacedbyDwg.M-2106,Sh.2 10.4-5-3ThisFigurehasbeenreplacedbyDwg.M-106,Sh.3 10.4-5-3AThisFigurehasbeenreplacedbyDwg.M-2106,Sh.3 SSES-FSARTOCRev.61CHAPTER10FIGURESNumberTitleFSARRev.6510-viii10.4-5-4ThisFigurehasbeenreplacedbyDwg.M-106,Sh.410.4-5-4AThisFigurehasbeenreplacedbyDwg.M-2106,Sh.4 10.4-5-5ThisFigurehasbeenreplacedbyDwg.M-106,Sh.5 10.4-6-1ThisFigurehasbeenreplacedbyDwg.M-102,Sh.1 10.4-6-1aThisFigurehasbeenreplacedbyDwg.M-2102,Sh.1 10.4-6-2ThisFigurehasbeenreplacedbyDwg.M-102,Sh.2 10.4-6-2aThisFigurehasbeenreplacedbyDwg.M-2102,Sh.2 10.4-6-3ThisFigurehasbeenreplacedbyDwg.M-102,Sh.3 10.4-6-3aThisFigurehasbeenreplacedbyDwg.M-2102,Sh.3 10.4-7ThisFigurehasbeenreplacedbyDwg.M-103,Sh.1 10.4-8ThisFigurehasbeenreplacedbyDwg.M-104,Sh.1 10.4-9ThisFigureHasBeenRenumberedTo10.4-9-1 10.4-9-1ThisFigurehasbeenreplacedbyDwg.M-107,Sh.1 10.4-9-2ThisFigurehasbeenreplacedbyDwg.M-107,Sh.2 10.4-9-3ThisFigurehasbeenreplacedbyDwg.M-107,Sh.3 10.4-9-4ThisFigurehasbeenreplacedbyDwg.M-107,Sh.4 SSES-FSARTOCRev.59FSARRev.6511-iCHAPTER11RADIATIONWASTEMANAGEMENTTABLEOFCONTENTSTEXTSectionTitle11.1SOURCETERMS 11.1.1FissionProducts 11.1.1.1NobleRadiogasFissionProducts11.1.1.2RadiohalogenFissionProducts11.1.1.3OtherFissionProducts11.1.1.4Nomenclature11.1.2ActivationProducts 11.1.2.1CoolantActivationProducts11.1.2.2NoncoolantActivationProducts11.1.3Tritium 11.1.4CoreInventory,FuelExperienceandDepressurizationSpiking 11.1.4.1CoreInventory11.1.4.2FuelExperience11.1.4.3DepressurizationSpiking11.1.5ProcessLeakageSources 11.1.6OtherReleases 11.1.7References 11.2LIQUIDWASTEMANAGEMENTSYSTEMS 11.2.1DesignBases 11.2.2SystemDescriptions 11.2.2.1General11.2.2.2LiquidRadwasteProcessingSubsystem SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-ii11.2.2.3LiquidRadwasteChemicalProcessingSubsystem11.2.2.4LiquidRadwasteLaundryDrainProcessingSubsystem11.2.3RadioactiveReleases 11.2.4EstimatedDoses 11.3GASEOUSWASTEMANAGEMENTSYSTEMS 11.3.1DesignBases11.3.2SystemDescriptions11.3.2.1OffgasSystem 11.3.2.1.1ProcessFlowDescription 11.3.2.1.2ActivatedCarbonHoldupTime 11.3.2.1.3DetonationResistance 11.3.2.2ComponentDescription 11.3.2.2.1RecombinerSystem11.3.2.2.2ActivatedCarbonAdsorberSystem11.3.2.2.3InletHEPAFilter11.3.2.2.4WaterRemoval/TemperatureReductionAssembly11.3.2.2.5GuardBeds11.3.2.2.6MainCharcoalAdsorberBed11.3.2.2.7OutletHEPAFilter11.3.2.2.8InstrumentationandControl11.3.2.2.9LeakageofGasesfromOffgasSystem11.3.2.3TypicalOperatingModes 11.3.2.3.1Standby11.3.2.3.2Prestart11.3.2.3.3NormalOperation11.3.2.3.4Startup11.3.2.3.5EquipmentMalfunction11.3.2.4OtherRadioactiveGasSources SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-iii11.3.2.4.1PrimaryandSecondaryContainment11.3.2.4.2RadwasteBuilding11.3.2.4.3TurbineBuilding11.3.3RadioactiveReleases 11.3.4EstimatedDoses 11.3.5References11.4SOLIDWASTEMANAGEMENTSYSTEM11.4.1DesignBases 11.4.2SystemDescription 11.4.2.1General11.4.2.2WetSolidWastes11.4.2.3DrySoildWaste11.4.3References 11.5PROCESSANDEFFLUENTRADIOLOGICALMONITORINGANDSAMPLINGSYSTEMS11.5.1DesignBases 11.5.1.1DesignObjectives11.5.1.2DesignCriteria11.5.2ProcessandEffluentRadiologicalMonitoringSystemDescription 11.5.2.1ContinuousProcessandEffluentMonitorSystems 11.5.2.1.1ReactorBuildingVentStackExhaustMonitorandSampleRMS11.5.2.1.2TurbineBuildingandRadwasteVentStackExhaustMonitorandSampleRMS11.5.2.1.3StandbyGasTreatmentSystemVentStackExhaustMonitorandSampleRMS11.5.2.1.4StandbyGasTreatmentVentExhaustRadiationMonitoringSystem11.5.2.1.5RefuelingFloorWallExhaustDuctRadiationMonitoringSystem SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-iv11.5.2.1.6RefuelingFloorExhaustDuctHighRadiationMonitoringSystemMonitoringSystem(Unit1Only)11.5.2.1.7RailroadAccessExhaustDuctRadiationMonitoringSystem(Unit1only)11.5.2.1.8ControlStructureOutsideAirIntakeRadiationMonitoringSystem11.5.2.1.9LiquidRadwasteEffluentRMSDHRemovalRadiationMonitoringSystem11.5.2.1.10ServiceWaterDischarge/SupplementalDHRemovalRadiationMonitoringSystem11.5.2.1.11OffgasPretreatmentRadiationMonitoringSystem11.5.2.1.12MainSteamlineRadiationMonitoringSystem11.5.2.1.13RHRServiceWaterRadiationMonitoringSystem11.5.2.1.14ReactorBuildingClosedCoolingWaterRadiationMonitoringSystem11.5.2.2RoutineSampling11.5.2.2.1AnalyticalProcedures11.5.3EffluentMonitoringandSampling 11.5.3.1ContainmentAtmosphere11.5.3.2ReactorBuilding11.5.3.3EffluentDischargePaths11.5.3.4PlantEnvironsMeasurement11.5.4ProcessMonitoringandSampling 11.5.4.1ProcessMonitoringandSamplingSystems 11.5.4.1.1PlantRadwasteEffluentRMS11.5.4.1.2ServiceWaterDischarge/SupplementalDHRemovalRMS11.5.4.1.3OffgasPretreatmentRMS11.5.4.1.4MainSteamlineRMS11.5.4.1.5RHRServiceWaterRMSMonitoringSystem11.5.4.1.6ReactorBuildingClosedCoolingWaterRMS11.5.4.2RadioactiveWasteProcessMonitoringandSamplingSystems11.6LOWLEVELRADWASTEHOLDINGFACILITY(LLRWHF) 11.6.1DesignBasis 11.6.2LowLevelRadwasteHoldingFacilityDescription 11.6.3LLRWHFWasteDescriptionandCapacity SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-v11.6.4LLRWHFSourceTerm11.6.5Containers 11.6.6ContainerShieldingforTransportandStorage 11.6.7CraneLoadingandUnloadingSystem11.6.7.1LLRWHF30-TonCraneOperation11.6.7.2LinerStorageinVault11.6.7.3LinerRetrievalinVault11.6.7.4MobileCraneOperation11.6.8HealthandSafetyRequirements 11.6.9FloorDrainSystem 11.6.10LLRWHFHVACSystem11.6.10.1GeneralFunctionsandControls11.6.10.2StorageAreaVentilationSystem11.6.10.3ControlRoomHVACSystem11.6.10.4BatteryChargingStationHeatingandVentilatingSystem11.6.10.5SprinklerValveHouseHeatingSystems11.6.10.6TruckBayVehicleFumeExhaustSystem11.6.10.7InspectionStationVentilation11.6.10.8AirInlets11.6.11EffluentMonitoring 11.6.12ElectricalSystems 11.6.12.1480VoltDistributionSystem11.6.12.2GroundingSystem11.6.12.3LightingSystem11.6.12.4CommunicationSystem11.6.12.5CableandRacewaySystem11.6.13ControlPanels 11.6.14RadiationZoning 11.6.15RadiationMonitoringSystem SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-vi11.6.16Shielding11.6.17Security 11.6.18FireProtectionSystemOperatingDescription 11.6.18.1DryPipeSprinklerSystems11.6.18.2InfraRedSmokeDetectionSystems11.6.18.3PhotoElectricSmokeDetectionSystem11.6.18.4TruckBaySmokeDetectionSystem11.6.18.5FireAlarmSystem11.6.19ExposuretoOperatingPersonnel 11.6.20EnvironmentalConsequencesofOperationoftheLow-LevelRadioactiveWasteHoldingFacility11.6.21LinerInspections 11.6.22SafetyAnalysis 11.6.22.1HandlingandStorageAccidents 11.6.22.1.1ContainerDropfromaTransportVehicle11.6.22.1.2HandlingandStorageAccidentsInsidetheDawStorageVaultandOpenArea11.6.22.1.3DroppingaHeavyComponentOntotheSolidifiedWasteStorageVault11.6.22.1.4DroppingaLLRWContainerIntoSolidifiedWasteStorageCell11.6.22.1.5Collisions-SolidifiedWasteContainerHandling11.6.22.1.6ShieldedLinerStorageModuleAccidents11.6.22.2OtherAccidents 11.6.22.2.1Fires11.6.22.2.2Freezes11.6.22.2.3Tornadoes11.6.22.2.4FloodsandSeismicEvents11.6.22.2.5Sabotage11.6.22.2.6LossofOff-SitePower11.6.22.3Summary SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-vii11.6.23References11.7INDEPENDENTSPENTFUELSTORAGEINSTALLATION(ISFSI) 11.7.1DesignBasis11.7.2NUHOMSHorizontalModularDryStorageSystemDescription(NUHOMSSystem)11.7.3ISFSISourceTerms11.7.3.1RadiationSourceTerm 11.7.3.2AirborneRadioactiveMaterialSourceTerm11.7.4DryShieldedCanister(DSC) 11.7.5HorizontalStorageModule(HSM) 11.7.6TransportEquipment11.7.6.1On-SiteTransferCask11.7.6.2.TransferTrailer11.7.7NUHOMSSystemOperation11.7.7.1On-SiteTransferCask(TC)Preparation11.7.7.2PlacementofDSCinCask11.7.7.3FillTC/DSCAnnuluswithWaterandSeal11.7.7.4TCMovementtotheCaskStoragePit11.7.7.5DSCSpentFuelLoading11.7.7.6DSCTopShieldPlugPlacement11.7.7.7LiftingTCfromPool11.7.7.8InnerDSCTopCoverPlate11.7.7.9DSCDryingandBackfilling11.7.7.10OuterDSCTopCoverPlate11.7.7.11TC/DSCAnnulusDrainingandTooCoverPlatePlacement11.7.7.12PlacementofTConTransferTrailer11.7.7.13TransportofTCtoHSM11.7.7.14TC/HSMPreparation11.7.7.15LoadingDSCintoHSM11.7.7.16SpentFuelStorage11.7.7.17SpentFuelRetrieval SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-viii11.7.8RadiologicalAssessment11.7.8.1Introduction11.7.8.2Dose11.7.8.3ISFSIControlledArea11.7.8.4FullyLoadedISFSIDoseAssessment11.7.9SiteSpecificEvaluations11.7.9.1AverageAmbientAirTemperatureandTemperatureExtremes11.7.9.2EarthquakeIntensity/SeismicAcceleration11.7.9.3Flooding11.7.9.4TornadoWindPressureandMissiles 11.7.9.5Snow11.7.9.6Lightning11.7.9.7FireandExplosion11.7.10HeavyLoads 11.7.11AuxiliarySystems11.7.11.1ElectricalSystems11.7.11.2Instrumentation SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-ix11.1-1NobleRadiogasSourceTerms11.1-2HalogenRadioisotopesinReactorWaterandSteam 11.1-3OtherFissionProductRadioisotopesinReactorWater 11.1-4CoolantActivationProductsinReactorWaterandSteam 11.1-5NoncoolantActivationProductsinReactorWater 11.1-6DepressurizationSpikingActivity95thPercentileCumulativeProbability 11.2-1ExpectedDailyInputsandActivitiestotheLiquidWasteManagementSystemFromTwoUnits11.2-2ExpectedBatchedInputstotheLiquidRadwasteSystemFromtheSolidRadwasteSystemForNormalOperationofTwoUnits11.2-3LiquidWasteManagementSystemComponentDescription 11.2-4LiquidRadwasteSystemFlows(RefertoFig.11.2-8) 11.2-5ExpectedRadionuclideActivityInventoriesofLiquidRadwasteSystemComponents(CuriesPerComponent)(2)(3)11.2-6DesignBasisRadionuclideActivityInventoriesofLiquidRadwasteSystemComponents(CuriesPerComponent)(2)(3)11.2-7ThisTableHasBeenDeleted11.2-8AssumptionsandParametersUsedForEvaluationofRadioactiveReleases 11.2-9ExpectedRadionuclideActivityConcentrationsInReactorCoolantandMainSteamUsedForEvaluationofRadioactiveReleases(1)11.2-10RadwasteSystemFlowRatesandStreamActivitiesUsedforEvaluationofRadioactiveReleases SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-x11.2-11ExpectedHoldupTimesForCollection,Processing,andDischargeUsedforEvaluationofRadioactiveReleases11.2-12DecontaminationFactorsUsedForEvaluationofRadioactiveReleases 11.2-13ExpectedYearlyActivityReleasedFromLiquidRadwasteManagementSystemsUsedForEvaluationofComplianceWithAppendixIof10CFR50(Ci/yr/site)11.2-14CalculatedExpectedEffluentActivityConcentrationsforEvaluationofRadioactiveReleasestotheSusquehannaRiver11.2-15InputDataforAquaticDoseCalculations 11.2-16TanksOutsidePrimaryContainmentWhichContainPotentiallyRadioactiveLiquids(1)11.3-1AnnualGaseousReleasesPerUnit11.3-2AssumptionsandParametersUsedForEvaluationofGaseousReleases 11.3-3Thistablehasbeendeleted 11.3-4FilterTrainsUsedtoControlGaseousEffluents 11.3-5OffGasSystemMajorEquipmentDescription 11.3-6OffGasSystemEquipmentMalfunctionAnalysis 11.3-7InputDataForAtmosphericDoseCalculations 11.3-8OffGasSystemFlows(RefertoFig.11.3-1)(PPH1SCFM) 11.3-9Thistablehasbeendeleted 11.3-10ComparisonofIndividualDosesfromExpectedGaseousEffluentReleaseswith10CFR50,AppendixIDesignObjectives11.3-11ComparisonofExpectedRadionuclideConcentrationsintheEnvironmentfromRoutineAtmosphericReleasesto10CFR20Limits SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-xi11.4-1InputstotheSolidRadwasteCollectionSystemForBothUnits11.4-2DrySolidWasteAmountFromGas,LaundryDrainFilters,andMaintenanceActivities11.4-3SolidWasteManagementSystemComponentDescription 11.4-4SolidWasteManagementSystemFlows(RefertoFig.11.4-3) 11.4-5ExpectedInventoriesofRadioactiveMaterialsinComponentsoftheSolidRadwasteSystem(2)11.4-6DesignInventoriesofRadioactiveMaterialsinComponentsoftheSolidWasteManagementSystem(Curies)(2)11.4-7ThisTableHasBeenDeleted11.4-8ThisTableHasBeenDeleted 11.4-9ExpectedInventoriesOfRadioactiveMaterialsInWasteShippingCasks 11.4-10DesignInventoriesOfRadioactiveMaterialsInWasteShippingCasks(1,2)11.5-1ProcessandEffluentRadiationMonitoringSystems 11.5-2RadiologicalAnalysisSummaryofRoutineEffluentSampling 11.5-3CompositionandConcentrationofNuclidesinRoutineEffluentSamples 11.6-1DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoaContainerDropfromaTransportVehicle(Reference11.6-7)11.6-2DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoDroppingaHeavyComponentOntotheSolidifiedWasteStorageVault(Reference11.6-11)11.6-3DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoanUnspecifiedIncendiaryEventInvolving100%ofDAW(Reference11.6-4)

SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-xii11.6-4DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoLossofOff-SitePowertotheLLRWHF(Reference11.6-5)11.6-5DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoMobileShieldedStorageModuleWithoutLid(Reference11.6-6)

SSES-FSARTOCRev.59CHAPTER11FIGURESNumberTitleFSARRev.6511-xiii11.1-1NobleRadiogasDecayConstantExponentFrequencyHistogram11.1-2RadiohalogenDecayConstantExponentFrequencyHistogram 11.1-3NobelRadiogasVersusI-131Leakage 11.2-1ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-39 11.2-2ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-40 11.2-3ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-41 11.2-4ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-42 11.2-5ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-43 11.2-6ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-1 11.2-7ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-9 11.2-8LiquidRadwasteManagementSystemFlowDiagram 11.2-9ThisFigureHasBeenRenumberedto11.2-9-1 11.2-9-1ThisFigurehasbeenreplacedbyDwg.M-162,Sh.1 11.2-9-2ThisFigurehasbeenreplacedbyDwg.M-162,Sh.2 11.2-9-3ThisFigurehasbeenreplacedbyDwg.M-162,Sh.3 11.2-10ThisFigureHasBeenRenumberedto11.2-9-2 11.2-11ThisFigureHasBeenRenumberedto11.2-11-1 11.2-11-1ThisFigurehasbeenreplacedbyDwg.M-163,Sh.1 11.2-11-2ThisFigurehasbeenreplacedbyDwg.M-163,Sh.2 11.2-11-3ThisFigurehasbeenreplacedbyDwg.M-163,Sh.3 SSES-FSARTOCRev.59CHAPTER11FIGURESNumberTitleFSARRev.6511-xiv11.2-12ThisFigurehasbeenreplacedbyDwg.M-164,Sh.111.2-13LiquidWasteManagementScheme 11.2-14TypicalMobileProcessingSystemFlowDiagram 11.3-1OffgasSystemProcessFlowDiagram 11.3-2AThisFigureHasBeenRenumberedto11.3-2A-1 11.3-2A-1ThisFigurehasbeenreplacedbyDwg.M-169,Sh.1 11.3-2A-2ThisFigurehasbeenreplacedbyDwg.M-169,Sh.2 11.3-2A-3ThisFigurehasbeenreplacedbyDwg.M-169,Sh.3 11.3-2A-4ThisFigurehasbeenreplacedbyDwg.M-169,Sh.4 11.3-2BThisFigureHasBeenRenumberedto11.3-2A-2 11.3-2CThisFigureHasBeenRenumberedto11.3-2C-1 11.3-2C-1ThisFigurehasbeenreplacedbyDwg.M-2169,Sh.1 11.3-2C-2ThisFigurehasbeenreplacedbyDwg.M-2169,Sh.2 11.3-2DThisFigureHasBeenRenumberedto11.3-2D-1 11.3-2D-1ThisFigurehasbeenreplacedbyDwg.M-2171,Sh.1 11.3-2D-2ThisFigurehasbeenreplacedbyDwg.M-2171,Sh.2 11.3-3ThisFigureHasBeenRenumberedto11.3-3-1 11.3-3-1P&IDAmbientTemperatureCharcoalOffgasTreatmentSystem 11.3-3-2P&IDAmbientTemperatureCharcoalOffgasTreatmentSystem 11.3-4ReleasePointsLocationsandDetails 11.4-1ThisFigureHasBeenRenumberedto11.4-1-1 SSES-FSARTOCRev.59CHAPTER11FIGURESNumberTitleFSARRev.6511-xv11.4-1-1ThisFigurehasbeenreplacedbyDwg.M-166,Sh.111.4-1-2ThisFigurehasbeenreplacedbyDwg.M-166,Sh.2 11.4-2ThisFigureHasBeenRenumberedto11.4-2-1 11.4-2-1ThisFigurehasbeenreplacedbyDwg.M-167,Sh.1 11.4-2-2ThisFigurehasbeenreplacedbyDwg.M-167,Sh.2 11.4-3SolidWasteManagementSystemFlowDiagram 11.6-1ThisFigurehasbeenreplacedbyDwg.B1P-005,Sh.1 11.6-2ThisFigurehasbeenreplacedbyDwg.B1N-100,Sh.1 11.6-3ShieldBellAssembly 11.6-4ThisFigureHasBeenDeleted SSES-FSARTextRev.59FSARRev.6512-iCHAPTER12RADIATIONPROTECTIONTABLEOFCONTENTSTEXTSectionTitle12.1ENSURINGTHATOCCUPATIONALRADIATIONEXPOSURESAREASLOWASREASONABLYACHIEVABLE(ALARA)12.1.1PolicyConsiderations 12.1.1.1ManagementPolicy12.1.1.2ManagementResponsibilities12.1.1.3PolicyImplementation12.1.2DesignConsiderations 12.1.2.2EquipmentGeneralDesignConsiderationsforALARA12.1.2.3FacilityLayoutGeneralDesignConsiderationsforALARA12.1.2.4ALARADesignReview12.1.3OperationalConsiderations 12.1.3.1ProcedureDevelopment12.1.3.1.1ALARAProcedures12.1.3.1.2StationProcedures12.1.3.2StationOrganization12.1.3.3OperatingExperience12.1.3.4ExposureReduction12.1.4References 12.2RADIATIONSOURCES 12.2.1ContainedSources 12.2.1.1Drywell12.2.1.1.1ReactorCore12.2.1.1.2ReactorCoolantSystem 12.2.1.1.3PrimarySteamSystem12.2.1.2ReactorBuilding12.2.1.2.1ReactorWaterCleanupSystem SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-ii12.2.1.2.2SpentFuelHandlingandTransfer12.2.1.2.3ResidualHeatRemovalSystem12.2.1.2.4ReactorCoreIsolationCoolingSystem12.2.1.2.5HighPressureCoolantInjectionSystem12.2.1.2.6CoreSpraySystems12.2.1.3RefuelingFacilities12.2.1.3.1SpentFuelStorageandTransfer12.2.1.3.2SpentFuelPoolCoolingAndCleanupSystem12.2.1.4TurbineBuilding12.2.1.4.1PrimarySteamandPowerConversionSystems12.2.1.4.2CondensateSystem12.2.1.4.3OffgasSystemRecombiner12.2.1.5RadwasteBuilding12.2.1.5.1LiquidRadwasteSystems12.2.1.5.2SolidRadwasteSystem12.2.1.5.3AmbientCharcoalOffgasTreatmentSystem12.2.1.6SourcesResultingfromDesignBasisAccidents12.2.1.7SiteBoundaryN-16ShineDose12.2.1.8StoredRadioactivity12.2.1.9SpecialSources12.2.2AirborneRadioactiveMaterialSources 12.2.2.1SourcesofAirborneRadioactivity12.2.2.2ProductionofAirborneMaterials12.2.2.3LocationsofSourcesofAirborneRadioactivity12.2.2.4ControlofAirborneRadioactivity12.2.2.5MethodologyforEstimatingtheConcentrationofAirborneRadioactiveMaterialWithinthePlant12.2.2.6EstimationofTotalAirborneReleases12.2.2.7DistributionofAirborneReleases12.2.2.8EstimatedAirborneRadioactiveMaterial12.2.2.9ChangestoSourceDataSincePSAR12.3RADIATIONPROTECTIONDESIGNFEATURES 12.3.1FacilityDesignFeatures 12.3.1.1CommonEquipmentandComponentDesignsforALARA12.3.1.2CommonFacilityandLayoutDesignsforALARA SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-iii12.3.1.3RadiationZoningandAccessControl12.3.1.4ControlofActivatedCorrosionProducts12.3.2Shielding 12.3.2.1DesignObjectives12.3.2.2GeneralShieldingDesign12.3.2.2.1ReactorBuildingShieldingDesign12.3.2.2.2ReactorBuildingInteriorShieldingDesign12.3.2.2.3RadwasteBuildingShieldingDesign12.3.2.2.4TurbineBuildingShieldingDesign12.3.2.2.5ControlRoomShieldingDesign12.3.2.2.6DieselGeneratorBuildingShieldingDesign12.3.2.2.7MiscellaneousPlantAreasandPlantYardAreas12.3.2.2.8CountingRoomShielding12.3.2.3ShieldingCalculationalMethods12.3.3Ventilation 12.3.3.1DesignObjectives12.3.3.2DesignCriteria12.3.3.3DesignGuidelines12.3.3.3.1GuidelinestoMinimizeAirborneRadioactivity12.3.3.3.2GuidelinestoControlAirborneRadioactivity12.3.3.3.3GuidelinestoMinimizePersonnelExposurefromHVACEquipment12.3.3.4DesignDescription12.3.4AreaRadiationandAirborneRadioactivityMonitoringInstrumentation 12.3.4.1AreaRadiationMonitoring12.3.4.1.1CriteriaforAreaMonitorSelection12.3.4.1.2CriteriaforLocationofAreaMonitors12.3.4.1.3SystemDescription(AreaRadiationMonitoring)General12.3.4.1.4AreaRadiationMonitoringInstrumentation12.3.4.1.5SafetyEvaluation12.3.4.1.6CalibrationMethodandTestability12.3.4.2AirborneRadioactivityMonitoring12.3.5References SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-iv12.4DOSEASSESSMENT12.4.1DirectRadiationDoseEstimatesforExposuresWithinthePlant 12.4.1.1DefinitionofCategoriesUsedinExposureEstimates12.4.1.2ExposureEstimateMethodology12.4.1.3ResultsofAnnualDirectRadiationDoseEstimates12.4.1.3.1RoutineOperationsDoseEstimate12.4.1.3.2RoutineMaintenanceDoseEstimate12.4.1.3.3In-ServiceInspectionDoseEstimate12.4.1.3.4SpecialMaintenanceDoseEstimate12.4.1.3.5WasteProcessingDoseEstimate12.4.1.3.6RefuelingDoseEstimate12.4.1.3.7HealthPhysicsDoseEstimate12.4.1.3.8SummaryofDirectRadiationDoseEstimates12.4.1.3.9MethodsforEstimatingDoses12.4.2AirborneRadioactivityDoseEstimatesforExposuresWithinthePlant 12.4.3ExposuresatLocationsOutsidePlantStructures 12.4.3.1DirectRadiationDoseEstimatesOutsideStructures12.4.3.2AirborneRadioactivityDoseEstimatesOutsideStructures12.4.4References 12.5HEALTHPHYSICSPROGRAM 12.5.1Organization 12.5.1.1Introduction12.5.1.2HealthPhysicsOrganizationandResponsibilities12.5.1.3Authority12.5.1.4ExperienceandQualification12.5.2Facilities,Equipment,&Instrumentation 12.5.2.1HealthPhysicsFacilities12.5.2.1.1HealthPhysicsOfficeFacilities12.5.2.1.2ControlledZoneAccess/EgressFacilities12.5.2.1.3LocalChangeFacilities SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-v12.5.2.1.4DecontaminationFacilities12.5.2.1.4.1PersonnelDecontaminationFacilities12.5.2.1.4.2EquipmentDecontaminationFacilities12.5.2.1.5RespiratoryProtectionFacilities12.5.2.1.6LaundryFacilities12.5.2.1.7InstrumentationFacilities12.5.2.1.8CountRoomFacilities12.5.2.1.9Chemistry/RadiochemistryFacilities12.5.2.1.10RestrictedAreaAccess/EgressFacilities12.5.2.2HealthPhysicsEquipment12.5.2.2.1ProtectiveClothing12.5.2.2.2RespiratoryProtectiveEquipment12.5.2.2.3AirSamplingEquipment12.5.2.2.3.1ContinuousAirMonitors12.5.2.2.3.2PortableAirSamplers12.5.2.2.3.3BreathingZoneSamplers12.5.2.2.3.4SamplingMedia12.5.2.2.3.5SpecialAirSampling12.5.2.2.4PersonnelDosimetry12.5.2.2.5MiscellaneousEquipment12.5.2.3HealthPhysicsInstrumentation12.5.2.3.1CountingRoomInstrumentation12.5.2.3.2PortableRadiationSurvey/Monitoring12.5.2.3.3ContaminationInstrumentation12.5.2.3.4SpecialInstrumentation12.5.3Procedures 12.5.3.1ControlofAccessandStayTimein12.5.3.1.1PhysicalControls12.5.3.1.1.1SecurityCheckPoints12.5.3.1.1.2SecurityDoors12.5.3.1.1.3PostingandLocking12.5.3.1.1.4Surveillance12.5.3.1.2AdministrativeControls12.5.3.1.2.1Training12.5.3.1.2.2RadiationWorkPermit12.5.3.1.2.3ReportingRequirement12.5.3.1.2.4IndependentReview12.5.3.1.2.5ProcedureReview SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-vi12.5.3.2AssuringthatOccupationalRadiationExposure(ORE)willbeasLowasReasonablyAchievable(ALARA)12.5.3.2.1ALARAProceduresCommontoExternalandInternalExposure12.5.3.2.1.1Training12.5.3.2.1.2RadiationWorkPermit12.5.3.2.1.3WorkScheduling12.5.3.2.1.4ReportingRequirements12.5.3.2.1.5InternalProgramReviews12.5.3.2.1.6ExposureGoals12.5.3.2.1.7JobPre-Planning12.5.3.2.1.8Worker'sRecommendations12.5.3.2.1.9AdministrativeLimits12.5.3.2.2ExternalALARA12.5.3.2.2.1DoseRecording12.5.3.2.2.2CategorizationofExposures12.5.3.2.2.3WorkTimeEvaluation12.5.3.2.2.4SpecialAlarmsandInstruments12.5.3.2.2.5TemporaryShielding12.5.3.2.2.6SpecialToolsandApparatus12.5.3.2.3InternalALARA12.5.3.2.3.1EngineeringControls12.5.3.2.3.2RespiratoryProtection12.5.3.2.3.3PreWorkAirSurveys12.5.3.2.3.4SpecialAirSampling12.5.3.2.3.5RoutineAirSampling12.5.3.2.3.6ControlofAreaandEquipmentContaminationLevels12.5.3.2.3.7AirborneExposureEvaluation12.5.3.3RadiationSurveys12.5.3.3.1RadiationSurveyProgramControls12.5.3.3.1.1RecordReview12.5.3.3.1.2IndependentReviews12.5.3.3.1.3SurveyorWorkRotation12.5.3.3.1.4Training12.5.3.3.2RadiationSurveyProgram12.5.3.3.2.1InstrumentSelection12.5.3.3.2.2RoutineRadiationAreaSurveys12.5.3.3.2.3HighRadiationAreaSurveys12.5.3.3.2.4VeryHighRadiationAreaSurveys12.5.3.3.2.5Non-RadiationAreaSurveys12.5.3.3.2.6RadiationWorkPermitSurveys12.5.3.3.2.7SpecialRadiationSurveys SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-vii12.5.3.3.2.8RadiationSurveyRecords12.5.3.4ContaminationSurveyProcedures12.5.3.4.1PersonnelContaminationSurveys12.5.3.4.1.1FriskerSurvey12.5.3.4.1.2NasalSwab12.5.3.4.1.3IntakeProcedures12.5.3.4.1.4Wound,Cut,AbrasionSurveys12.5.3.4.2EquipmentContaminationSurveys12.5.3.4.2.1ContaminatedAreaEquipmentSurveys12.5.3.4.2.2PersonalItemSurveys12.5.3.4.2.3ProtectiveClothingSurveys12.5.3.4.2.4RespiratoryProtectionDeviceSurveys12.5.3.4.2.5SurveysInvolvingReceipt/ShipmentofRadioactiveMaterial12.5.3.4.3SurfaceContaminationSurveys12.5.3.4.3.1ControlledAccessAreas12.5.3.4.3.2Non-ControlledZoneAreas12.5.3.4.3.3Implementation,Review,andReportingPractices12.5.3.5AirborneRadioactiveMaterial12.5.3.5.1PhysicalControls12.5.3.5.1.1AirFlowPatterns12.5.3.5.1.2ContaminationConfinement12.5.3.5.1.3AirExhaust12.5.3.5.1.4PostingandLocking12.5.3.5.2AdministrativeControls12.5.3.5.2.1HealthPhysicsReview12.5.3.5.2.2HealthPhysicsInvestigation12.5.3.5.2.3RWPProcedures12.5.3.5.3AirSamplingEquipment12.5.3.5.4AirborneConcentrationSampling12.5.3.5.4.1RoutineSampling12.5.3.5.4.2SpecialAirSampling12.5.3.5.5AirSampleEvaluation12.5.3.5.5.1ParticulateInitialEvaluation12.5.3.5.5.2SubsequentParticulateEvaluations12.5.3.5.5.3GaseousEvaluations12.5.3.5.6RespiratoryProtection12.5.3.5.6.1TrainingandFitting12.5.3.5.6.2WrittenProcedures12.5.3.5.6.3SelectionofEquipment12.5.3.5.6.4IssueandUse SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-viii12.5.3.5.6.5Cleaning,Decontamination,Inspection,Maintenance,SanitizingandStorage12.5.3.5.6.6QualityControls12.5.3.5.6.7SurveillanceofWorkAreaConditions12.5.3.5.6.8EvaluationofProgramEffectiveness12.5.3.5.6.9MedicalSurveillance12.5.3.5.7HandlingofRadioactiveMaterial12.5.3.5.7.1UnsealedMaterial12.5.3.5.7.2SealedMaterials12.5.3.6PersonnelMonitoring12.5.3.6.1ExternalPersonnelMonitoring12.5.3.6.1.1PersonnelDosimetryEvaluation12.5.3.6.1.2AdministrativeExposureControl12.5.3.6.1.3MethodsofRecordingandReporting12.5.3.6.2InternalRadiationExposureAssessment12.5.3.6.2.1BioassayMethods12.5.3.6.2.2AdministrativeControls12.5.3.6.2.3CriteriaforParticipationorSelection12.5.3.6.2.4EvaluationandReporting12.5.3.7HealthPhysicsTrainingPrograms12.5.3.7.1ProgramControls12.5.3.7.1.1HealthPhysicsTrainingProgramReview12.5.3.7.1.2AccessControl12.5.3.7.1.3Retraining/ReplacementTraining12.5.3.7.2TrainingPrograms12.5.3.7.2.1LevelITraining12.5.3.7.2.2LevelIITraining12.5.3.7.2.3RespiratoryProtectionTraining12.5.3.7.2.4HealthPhysicsTechnicianInitialTrainingProgram12.5.3.7.2.5HealthPhysicsTechnicianRetrainingProgram SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-ix12.2-1BasicReactorData12.2-2CoreRegionDescriptionUsedinCalculationstoDetermineRadialFluxDistributionatReactorCoreMidplane12.2-3MaterialCompositiontoDetermineRadialFluxDistributionsatReactorCoreMidplane12.2-4CalculatedGammaRayandNeutronFluxesatOutsideSurfaceofRPV 12.2-5CalculatedGammaRayandNeutronFluxesatOutsideSurfaceofPrimaryShield12.2-6ReactorWaterCleanupSystemN-16ShieldingSourceTerms 12.2-7ReactorWaterCleanupFilterDemineralizerShieldingSourceTerms 12.2-8ReactorWaterCleanupBackwashReceivingTankShieldingSourceTerms12.2-9ThisTableHasBeenDeleted 12.2-9A1Activity(Curies)perFullCoreofATRIUM-10Fuel 12.2-9A2Activity(Curies)perSingleAssemblyofATRIUM-10Fuel 12.2-10ResidualHeatRemovalSystemShieldingSourceTerms 12.2-11SteamN-16ShieldingSourceTermsforTurbineandReactorBuildingEquipment12.2-12FuelPoolSystemShieldingSourceTerms 12.2-13FuelPoolFilterDemineralizerShieldingSourceTerms 12.2-14FuelPoolWaterCleanupBackwashReceivingTankShieldingSourceTerms12.2-15CondensateShieldingSourceTerms 12.2-16CondensateDemineralizerShieldingSourceTerms SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-x12.2-17Off-gasLinefromSJAEtoRecombinerShieldingSourceTerms12.2-18Off-gasPrimaryRecombinerShieldingSourceTerms 12.2-19Off-gasLinefromRecombinertoCharcoalSystemShieldingSourceTerms12.2-20CharcoalOff-gasSystemInlet-HEPAFilterShieldingSourceTerms 12.2-21Off-gasAmbientCharcoalFreonChillerShieldingSourceTerms12.2-22Off-gasCharcoalGuardBedShieldingSourceTerms 12.2-23Off-gasCharcoalBedsShieldingSourceTerms 12.2-24Off-gasPost-HEPAFilterShieldingSourceTerms 12.2-25Post-LOCAPrimaryContainmentActivity 12.2-26Post-LOCASecondaryContainmentActivity 12.2-27Post-LOCAStandbyGasTreatmentCharcoalFilterActivity 12.2-28IsotopicInventoryofN-16forTurbineOperatingFloorComponents 12.2-29CondensateStorageTankSourceTerms 12.2-30EstimatedAirborneRadioactiveReleasesPriortoTreatment(Curies/Year)12.2-31EstimatedDistributionofAirborneRadioactiveReleases 12.2-32TurbineBuildingAirborneSourceDescriptions 12.2-33ReactorBuildingAirborneSourceDescriptions 12.2-34RadwasteBuildingAirborneSourceDescriptions 12.2-35EstimatedAirborneConcentrationsintheTurbineBuildingandFractionofDACs SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-xi12.2-36EstimatedAirborneConcentrationsintheReactorBuildingandFractionofDACs12.2-37EstimatedAirborneConcentrationsintheRadwasteBuildingandFractionofDACs12.2-38TurbineBuildingShieldingDesignRadiationSourceDescription 12.2-39ReactorBuildingShieldingDesignRadiationSourceDescription 12.2-40RadwasteBuildingShieldingDesignRadiationSourceTerms 12.2-41MaterialCompositionoftheTIPSystemComponentsAsUsedinActivationCalculations12.2-42TraversingIncoreProbeDetectorDecayGammaActivitiesinMEV/Secof0.001gofU-23512.2-43TraversingIncoreProbeDetectorDecayGammaActivitiesofMaterialsintheDetector(ExcludingU-235)inMicrocuriesintheIrradiatedDetector12.2-44DecayGammaActivitiesofMaterialsintheCableinMicrocuriesperInchofIrradiatedCable.12.2-45UltrasonicResinCleanerShieldingSourceTerms 12.2-46CondensateFilterVesselShieldingSourceTerms 12.2-47CondensateFilterVesselBackwashShieldingSourceTerms 12.2-48CondensateFilterVesselBackwashReceivingTankShieldingSourceTerms12.3-1PlantRadiationZoneDescription 12.3-2ListofComputerCodesUsedinShieldingDesignCalculations 12.3-3Thistablehasbeendeleted SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-xii12.3-4Thistablehasbeendeleted12.3-5Thistablehasbeendeleted 12.3-6Thistablehasbeendeleted 12.3-7AreaRadiationMonitoringSystem 12.4-1SummaryofHistoricalDataUsedinCompilationofExposuresReceivedatOperatingBoilingWaterReactors12.4-2OccupationalExposuresByJobFunctionforOperatingBoilingWaterReactors12.4-3ExposureEstimatesfortheTurbineBuildingandControlStructure 12.4-4ExposureEstimatesfortheReactorBuilding 12.4-5ExposureEstimatesfortheRadwasteBuilding 12.4-6EstimatedExposureforOperatorsinResidenceinControlRooms 12.4-7SummaryofRoutineOperationsExposureEstimate 12.4-8EstimateofExpectedMaintenanceMan-hoursforVariousTypesofEquipment12.4-9SummaryofIn-PlantDirectRadiationExposureEstimates 12.4-10EstimatedTurbineBuildingInhalationExposuresDuetoAirborneRadioactivity12.4-11EstimatedReactorBuildingInhalationExposuresDuetoAirborneRadioactivity12.4-12EstimatedRadwasteBuildingInhalationExposuresDuetoAirborneRadioactivity12.4-13ThisTableHasBeenDeleted SSES-FSARTextRev.59CHAPTER12FIGURESNumberTitleFSARRev.6512-xiii12.3-1TypicalShieldingArrangementforLiquidRadwasteFiltersandValveGallery12.3-2TypicalShieldingArrangementforRadwasteDemineralizer 12.3-3TypicalShieldingArrangementforCharcoalandParticulateFilter 12.3-4TypicalShieldingArrangementforOff-gasRecombiners 12.3-5TypicalShieldingArrangementforRadwasteTanksandPumps 12.3-6TypicalShieldingArrangementforRadwasteEvaporator 12.3-7TypicalShieldingArrangementforSampleStation 12.3-8ShieldingandRadiationZoningDrawingControlBuildingEL.656'-0"to714'-0"12.3-9ShieldingandRadiationZoningDrawingControlBuildingEL.729'-1"to783'-0"12.3-10ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.656'-0"12.3-11ShieldingandRadiationZoningDrawingTurbineBuildingEL.676'-0" 12.3-12ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.699'-0"12.3-13ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.714'-0"12.3-14ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.729'-0"12.3-15ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.762'-0"12.3-16ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.645-'0" SSES-FSARTextRev.59CHAPTER12FIGURESNumberTitleFSARRev.6512-xiv12.3-17ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.670'-0"12.3-18ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.683'-0"12.3-19ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.719'-0"12.3-20ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.749'-1"12.3-21ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.779'-1"12.3-22ShieldingandRadiationZoningDrawingReactorBuildingEL.799'-1" 12.3-23ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.818'-1"12.3-24ShieldingandRadiationZoningDrawingRadwasteBuildingEL.646'-0" 12.3-25ShieldingandRadiationZoningDrawingRadwasteBuildingEL.660'-0" 12.3-26ShieldingandRadiationZoningDrawingRadwasteBuilding-Unit1EL.676'-0"12.3-27ShieldingandRadiationDrawingRadwasteBuildingEL.691'-6" 12.3-28LLRWHoldingFacilityInterimRadiationZoningandAreaRadiationMonitorLocations12.3-29ScaledIsometricofControlBuildingwithRelationshiptoContainment 12.3-30-1P&IDAreaRadiationMonitoringandMeteorologicalInstruments 12.3-30-2P&IDAreaRadiationMonitoringandMeteorologicalInstruments 12.4-1EstimatedTurbineShineDoseRates 12.5-1HealthPhysicsOrganization SSES-FSAR TOC Rev. 61 FSAR Rev. 68 13-i CHAPTER 13 CONDUCT OF OPERATIONS TABLE OF CONTENTS TEXT Section Title

13.1 ORGANIZATIONAL STRUCTURE

13.1.1 Management and Technical Support Organization

13.1.1.1 Design and Operating Responsibilities 13.1.1.1.1 Design and Construction Activities (Project Phase) (HISTORICAL) 13.1.1.1.2 Preoperational Activities (HISTORICAL) 13.1.1.1.3 Technical Support for Operations: General Office Personnel Responsibilities and Authorities 13.1.1.2 Organizational Arrangement: General Office 13.1.1.3 Qualification Requirements for Personnel in the Off-Site Organization

13.1.2 Operating Organization

13.1.2.1 Plant Organization 13.1.2.2 Plant Personnel Responsibilities and Authorities 13.1.2.3 Operating Shift Crews

13.1.3 Qualification Requirements for Nuclear Plant (On-Site) Personnel

13.1.3.1 Minimum Required Qualifications 13.1.3.1.1 Qualifications of Personnel Who Cannot Be Directly Cross-Referenced to ANSI/ANS 3.1-1978 13.1.3.2 Qualifications of Incumbent Plant Personnel

13.2 TRAINING PROGRAM

13.2.1 Plant Personnel Training Program 13.2.1.1 Pre Licensing Program Description 13.2.1.1.1 Initial Plant Staff Training 13.2.1.1.2 Operations Section Training Program 13.2.1.1.2.1 Initial Cold License Training 13.2.1.1.2.2 Non-Licensed Operator Training Program 13.2.1.1.3 Maintenance Section Training Program 13.2.1.1.4 Technical Section Training Program

SSES-FSAR TOC Rev. 61 CHAPTER 13 TEXT Section Title FSAR Rev. 68 13-ii 13.2.1.1.4.1 Chemistry Personnel 13.2.1.1.4.2 Instrumentation & Control Personnel 13.2.1.1.4.3 Reactor Engineering Personnel 13.2.1.1.5 Health Physics Training Program 13.2.1.1.6 General Employee Training 13.2.1.1.7 Fire Safety Training

13.2.2 Requalification and Replacement Training

13.2.2.1 Licensed Operator Requalification Program 13.2.2.1.1 Curriculum

13.2.2.1.2 Evaluations 13.2.2.1.3 Accelerated Retraining 13.2.2.1.4 Absence From Licensed Duties 13.2.2.1.5 Disability of Licensed Individuals 13.2.2.2 Continuing Training for Non-licensed Personnel 13.2.2.2.1 Continuing Training for Non-licensed Operators 13.2.2.2.2 Continuing Training for Maintenance Personnel 13.2.2.2.3 Continuing Training for Technical Section Personnel 13.2.2.3 Replacement Training 13.2.2.3.1 NRC Licensed Operator Replacement 13.2.2.3.2 Non-Licensed Operator Replacement Training 13.2.2.3.3 Technical Personnel Replacement Training 13.2.2.3.4 Engineering Support Personnel Replacement Training 13.2.2.4 Records 13.2.2.5 Responsible Individual

13.3 EMERGENCY PLAN

13.4 REVIEW AND AUDIT

13.4.1 Plant Operations Review Committee

13.4.1.1 Organization

13.4.1.2 Meetings 13.4.1.3 Responsibility 13.4.1.4 Authority

13.4.2 Nuclear Safety Review Board

13.4.2.1 Charter SSES-FSAR TOC Rev. 61 CHAPTER 13 TEXT Section Title FSAR Rev. 68 13-iii 13.4.2.2 Membership 13.4.2.3 Sub-Committees

13.4.2.4 Consultants 13.4.2.5 Meeting Frequency 13.4.2.6 Quorum 13.4.2.7 Records 13.4.2.8 Responsibility 13.4.2.9 NSRB Audit Program 13.4.2.10 Authority

13.4.3 Audit Program

13.4.4 Process Control Program (PCP)

13.4.5 Technical Review and Control

13.5 PLANT PROCEDURES

13.5.1 Administrative Procedures 13.5.1.1 Procedure Conformance 13.5.1.2 Preparation of Procedures 13.5.1.3 Procedures

13.5.2 Operating and Maintenance Procedures

13.5.2.1 Control Room Operating Procedures 13.5.2.1.1 Operating Procedures 13.5.2.1.2 General Plant Procedures 13.5.2.1.3 Off-Normal Procedures 13.5.2.1.4 Emergency Procedures 13.5.2.1.5 Alarm Response Procedures 13.5.2.1.6 Temporary Procedures 13.5.2.2 Additional Operating and Maintenance Procedures 13.5.2.2.1 Chemistry Procedures 13.5.2.2.2 Emergency Plan Procedures 13.5.2.2.3 Environmental Surveillance Procedures 13.5.2.2.4 Health Physics Procedures 13.5.2.2.5 Instrument and Control Procedures 13.5.2.2.6 Maintenance Procedures 13.5.2.2.7 Procurement and Material Control Procedures 13.5.2.2.8 Radwaste Management Procedures SSES-FSAR TOC Rev. 61 CHAPTER 13 TEXT Section Title FSAR Rev. 68 13-iv 13.5.2.2.9 Reactor Engineering Procedures 13.5.2.2.10 Records Procedures 13.5.2.2.11 Security Procedures 13.5.2.2.12 Surveillance Procedures 13.5.2.2.13 Fire Protection Procedures

13.6 INDUSTRIAL SECURITY

SSES-FSAR TOC Rev. 61 CHAPTER 13 TABLES Number Title FSAR Rev. 68 13-v 13.1-1 Resumes of Key General Office Personnel

13.1-2 Resumes of Key Plant Personnel

13.1-3 (Deleted)

SSES-FSAR TOC Rev. 61 CHAPTER 13 FIGURES Number Title FSAR Rev. 68 13-vi 13.1-1 Talen Energy Corporation Management Organization Applicable to Susquehanna SES

13.1-1a Deleted

13.1-1b Deleted

13.1-2 Susquehanna Nuclear, LLC, Off-Site Organization

13.1-2a Deleted

13.1-2b Deleted

13.1-2c Deleted

13.1-2d Deleted

13.1-2e Deleted

13.1-2f Deleted

13.1-2g Deleted

13.1-3 Susquehanna Nuclear, LLC, On-Site Organization

13.1-3a Deleted

13.1-3b Deleted

13.1-3c Deleted

13.1-3d Deleted

13.1-4 Deleted

13.1-4a Deleted 13.1-4b Deleted

13.1-4c Deleted SSES-FSAR TOC Rev. 61 CHAPTER 13 FIGURES Number Title FSAR Rev. 68 13-vii 13.1-4d Deleted

13.1-5 Deleted

13.5-1 Deleted

13.5-2 Main Control Room

SSES-FSARTextRev.51CHAPTER14FSARRev.6514-iINITIALTESTSPROGRAMTABLEOFCONTENTSTEXTSectionTitle14.1SPECIFICINFORMATIONTOBEINCLUDEDINPRELIMINARYSAFETYANALYSISREPORTS14.2SPECIFICINFORMATIONTOBEINCLUDEDINFINALSAFETYANALYSISREPORT14.2.1SummaryOfTestProgramandObjectives14.2.1.1PreoperationalTestProgram14.2.1.2StartupTestProgram14.2.2OrganizationandStaffing14.2.2.1PlantStaff14.2.2.2IntegratedStartupGroupOrganizationandResponsibilities14.2.2.2.1ISGSupervisor 14.2.2.2.2AssistantISGSupervisor 14.2.2.2.3GroupLeaders14.2.2.2.4ISGCoordinator14.2.2.2.5ISGSpecialistsSupervisor 14.2.2.2.6ISGScheduledSupervisor14.2.2.2.7RecordControlGroupSupervisor14.2.2.2.8GEISGSiteRepresentative 14.2.2.2.9Responsibilities14.2.2.3PlantOperationsReviewCommittee14.2.2.4TestReviewBoard14.2.3TestProcedures14.2.3.1ProcedurePreparation14.2.3.2ProcedureReviewandApproval14.2.4ConductofTestProgram14.2.4.1TestPerformance14.2.4.2TestPrerequisites14.2.4.3ProcedureModifications 14.2.4.4DesignProblems14.2.4.5ControlofRework,Modifications,andRepairs SSES-FSARTextRev.51CHAPTER14FSARRev.6514-iiSectionTitle14.2.4.6TestPhasePrerequisites14.2.5Review,Evaluation,andApprovalofTestResults14.2.5.1IndividualTestResults14.2.5.2MajorTestPhase-TestResults14.2.5.3PowerAscensionTesting-TestResults14.2.6TestRecords14.2.7ConformanceofTestProgramsWithRegulatoryGuides14.2.8UtilizationofReactorOperatingandTestingExperienceIntheDevelopmentofTheTestProgram14.2.9TrialUseofPlantOperatingandEmergencyProcedures14.2.10InitialFuelLoadingandInitialCriticality14.2.11TestProgramSchedule 14.2.12IndividualTestDescriptions14.2.12.1Unit1PreoperationalTestProcedureAbstracts14.2.12.2Unit1StartupTestProgramProcedureAbstracts14.2.12.3RequestedUnit1AcceptanceTestProcedureAbstracts14.2.12.4Unit2PreoperationalTestProcedureAbstracts 14.2.12.5Unit2AcceptanceTestProcedureAbstracts14.2.12.6Unit2StartupTestProgramProcedureAbstracts14.3POWERUPRATETESTPROGRAM14.3.1SummaryofPowerUprateTestProgramandObjectives14.3.2OrganizationandStaffing14.3.2.1TestReviewCommittee14.3.2.2PowerUprateProjectTestGroup14.3.3TestProcedures SSES-FSARTextRev.51CHAPTER14FSARRev.6514-iiiSectionTitle14.3.4ConductofTestProgram14.3.4.1TestPerformance14.3.4.2TestPrerequisites 14.3.4.3ProcedureModifications14.3.4.4DesignProblems14.3.4.5ControlorRework,Modifications,andRepairs 14.3.4.6TestPhasePrerequisites14.3.5Review,Evaluation,andApprovalofTestResults 14.3.5.1IndividualTestResults14.3.5.2MajorTestPhases-TestResults 14.3.5.3PowerAscensionTesting-TestResults14.3.6TestRecords14.3.7IndividualTestDescriptions14.3.7.1ChemistryTests14.3.7.2Test2-Radiological14.3.7.3Test3-FuelLoading14.3.7.4Test4-FullCoreShutdownMargin 14.3.7.5Test5-ControlRodDrive(CRD) 14.3.7.6Test11-LPRMCalibration14.3.7.7Test12-APRMCalibration14.3.7.8Test14-RCICSystem 14.3.7.9Test15-HPCISystem14.3.7.10Test18-TIPUncertainty14.3.7.11Test19-ThermalLimitsEvaluation 14.3.7.12Test22-PressureRegulator 14.3.7.13Test23-FeedwaterSystem14.3.7.14Test24-TurbineValveSurveillance14.3.7.15Test25-MainSteamIsolationValves 14.3.7.16Test29-RecirculationFlowControlSystem14.3.7.17Test32-ContainmentAtmosphereCooling14.3.7.18Test35-RecirculationSystemFlowCalibration 14.3.7.19Test37-GaseousRadwasteSystem14.3.7.20Test42-I&CSurveillance14.3.7.21Test43-SteadyStateDataCollection 14.3.7.22Test45-MainSteamHighFlow 14.3.7.23Test46-MainSteamLineHighTunnelTemperature14.3.7.24Test47-RecirculationSingleLoopOperation14.3.7.25Test48-LoosePartsMonitor 14.3.7.26Test49-MainSteamLineRadiationMonitor14.3.7.27Test50-CoreSprayLeakDetection14.3.7.28Test61-Unit1ReactorRecirculationHydraulicResponseTest SSES-FSARTextRev.51CHAPTER14FSARRev.6514-ivTABLESNumberTitle14.2-1PreoperationalTestProcedures14.2-2AcceptanceTestProcedures14.2-3StartupTestProcedures 14.2-4MajorTestPhaseandTestPlateauSchedule-TestConditionSequence14.2-5ControlRodDriveSystemStartupTests14.2-6Unit2PreoperationalTestProcedures14.2-7Unit2AcceptanceTest14.3-1PowerUprateTestProcedures 14.3-2TestPlateauandTestConditionDefinition SSES-FSARTextRev.51CHAPTER14FSARRev.6514-vFIGURESNumberTitle14.2-1IntegratedStartupGroupOrganization14.2-2APreoperationalTestProcedureStandardFormat14.2-2BStartupTestProcedureStandardFormat-Unit1 14.2-2CStartupTestProcedureStandardFormat-Unit214.2-3InitialTestProgramSchedule14.2-4aUnit1PreoperationalTestSequence14.2-4bUnit2PreoperationalTestSequence14.2-5-1IndividualStartupTestSequence-Unit1 14.2-5-2IndividualStartupTestSequence-Unit114.2-5-3IndividualStartupTestSequence-Unit214.2-5-4IndividualStartupTestSequence-Unit214.2-6-1PowerFlowMapandStartupTestConditions14.2-6-2PowerFlowMapandPowerTestConditions 14.2-7RCICAcceptanceCriteriaCurvesForCapacityandActuationTime SSES-FSAR Text Rev. 62 FSAR Rev. 68 15-i CHAPTER 15 ACCIDENT ANALYSIS TABLE OF CONTENTS TEXT Section Title 15.0 ACCIDENT ANALYSES

15.0.1 Analytical Objective

15.0.2 Analytical Categories

15.0.3 Event Evaluation

15.0.3.1 Identification of Causes and Frequency Classification 15.0.3.1.1 Unacceptable Results for Incidents of Moderate Frequency (Anticipated (Expected) Operational Transients) 15.0.3.1.2 Unacceptable Results for Infrequent Incidents (Abnormal (Unexpected) Operational Transients) 15.0.3.1.3 Unacceptable Results for Limiting Faults (Design Basis (Postulated) Accidents) 15.0.3.2 Sequence of Events and Systems Operations 15.0.3.2.1 Single Failures or Operator Errors

15.0.3.2.1.1 General 15.0.3.2.1.2 Initiating Event Analysis 15.0.3.2.1.3 Single Active Component Failure or Single Operator Failure Analysis 15.0.3.3 Core and System Performance 15.0.3.3.1 Introduction 15.0.3.3.2 Input Parameters and Initial Conditions for Analyzed Events 15.0.3.3.3 Initial Power/Flow Operating Constraints 15.0.3.3.4 Results 15.0.3.5 Barrier Performance 15.0.3.6 Radiological Consequences

15.0.4 Nuclear Safety Operational Analysis (NSQA) Relationship

15.0.5 References

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-ii 15.1 DECREASE IN REACTOR COOLANT TEMPERATURE

15.1.1 Loss of Feedwater Heating 15.1.1.1 Identification of Causes and Frequency Classification 15.1.1.1.1 Identification of Causes 15.1.1.1.2 Frequency Classification 15.1.1.2 Sequence of Events and Systems Operation 15.1.1.2.1 Sequence of Events 15.1.1.2.1.1 Identification of Operator Actions 15.1.1.2.2 Systems Operation 15.1.1.2.3 The Effect of Single Failures and Operator Errors 15.1.1.3 Core and System Performance 15.1.1.3.1 Mathematical Model 15.1.1.3.2 Input Parameters and Initial Conditions 15.1.1.3.3 Results 15.1.1.3.4 Considerations of Uncertainties 15.1.1.4 Barrier Performance 15.1.1.5 Radiological Consequences

15.1.2 Feedwater Controller Failure-Maximum Demand

15.1.2.1 Identification of Causes and Frequency Classification 15.1.2.1.1 Identification of Causes 15.1.2.1.2 Frequency Classification 15.1.2.2 Sequence of Events and Systems Operation 15.1.2.2.1 Sequence of Events 15.1.2.2.1.1 Identification of Operator Actions 15.1.2.2.2 Systems Operation 15.1.2.2.3 The Effect of Single Failures and Operator Errors 15.1.2.3 Core and System Performance 15.1.2.3.1 Mathematical Model 15.1.2.3.2 Input Parameters and Initial Conditions 15.1.2.3.3 Results 15.1.2.3.4 Consideration of Uncertainties 15.1.2.4 Barrier Performance 15.1.2.5 Radiological Consequences 15.1.3 Pressure Regulator Failure - Open

15.1.3.1 Identification of Causes and Frequency Classification 15.1.3.1.1 Identification of Causes SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-iii 15.1.3.1.2 Frequency Classification 15.1.3.2 Sequence of Events and Systems Operation 15.1.3.2.1 Sequence of Events 15.1.3.2.1.1 Identification of Operator Actions 15.1.3.2.2 Systems Operation 15.1.3.2.3 The Effect of Single Failures and Operator Errors 15.1.3.3 Core and System Performance 15.1.3.3.1 Mathematical Model 15.1.3.3.2 Input Parameters and Initial Conditions 15.1.3.3.3 Results 15.1.3.3.4 Consideration of Uncertainties 15.1.3.4 Barrier Performance 15.1.3.5 Radiological Consequences

15.1.4 Inadvertent Safety/Relief Valve Opening

15.1.4.1 Identification of Causes and Frequency Classification 15.1.4.1.1 Identification of Causes 15.1.4.1.2 Frequency Classification 15.1.4.2 Sequence of Events and Systems Operation 15.1.4.2.1 Sequence of Events 15.1.4.2.1.1 Identification of Operator Actions 15.1.4.2.2 Systems Operation 15.1.4.2.3 The Effect of Single Failures and Operator Errors 15.1.4.3 Core and System Performance 15.1.4.3.1 Mathematical Model 15.1.4.3.2 Input Parameters and Initial Conditions 15.1.4.3.3 Qualitative Results 15.1.4.4 Barrier Performance 15.1.4.5 Radiological Consequences

15.1.5 Spectrum of Steam System Piping Failures Inside and Outside of Containment In A PWR

15.1.6 Inadvertent RHR Shutdown Cooling Operation

15.1.6.1 Identification of Causes and Frequency Classification 15.1.6.1.1 Identification of Causes 15.1.6.1.2 Frequency Classification 15.1.6.2 Sequence of Events and Systems Operation 15.1.6.2.1 Sequence of Events SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-iv 15.1.6.2.2 System Operation 15.1.6.2.3 Effect of Single Failures and Operator Action 15.1.6.3 Core and System Performance 15.1.6.4 Barrier Performance 15.1.6.5 Radiological Consequences

15.1.7 References

15.2 INCREASE IN REACTOR PRESSURE

15.2.1 Pressure Regulator Failure - Closed

15.2.1.1 Identification of Causes and Frequency Classification 15.2.1.1.1 Identification of Causes 15.2.1.1.2 Frequency Classification 1.5.2.1.2 Sequence of Events and System Operation 15.2.1.2.1 Sequence of Events 15.2.1.2.1.1 Identification of Operator Actions 15.2.1.2.2 Systems Operation 15.2.1.2.3 The Effect of Single Failures and Operator Errors 15.2.1.3 Core and System Performance 15.2.1.3.1 Mathematical Model 15.2.1.3.2 Input Parameters and Initial Conditions 15.2.1.3.3 Results 15.2.1.3.4 Consideration of Uncertainties 15.2.1.4 Barrier Performance 15.2.1.5 Radiological Consequences

15.2.2 Generator Load Rejection

15.2.2.1 Identification of Causes and Frequency Classification 15.2.2.1.1 Identification of Causes 15.2.2.1.2 Frequency Classification 15.2.2.1.2.1 Generator Load Rejection Without Without Bypass 15.2.2.2 Sequence of Events and System Operation 15.2.2.2.1 Sequence of Events 15.2.2.2.1.1 Generator Load Rejection-Turbine Control Valve Fast Closure with Bypass Operable 15.2.2.2.1.2 Generator Load Rejection with Failure of Bypass 15.2.2.2.1.3 Identification of Operator Actions 15.2.2.2.2 System Operation SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-v 15.2.2.2.2.1 Generator Load Rejection with Bypass Operable 15.2.2.2.2.2 Generator Load Rejection with Failure of Bypass 15.2.2.2.3 The Effect of Single Failures and Operator Errors 15.2.2.3 Core and System Performance 15.2.2.3.1 Mathematical Model 15.2.2.3.2 Input Parameters and Initial Conditions 15.2.2.3.3 Results 15.2.2.3.3.1 Generator Load Rejection with Bypass 15.2.2.3.3.2 Generator Load Rejection with Failure of Bypass 15.2.2.3.4 Consideration of Uncertainties 15.2.2.4 Barrier Performance 15.2.2.4.1 Generator Load Rejection with Bypass Operable 15.2.2.4.2 Generator Load Rejection with Failure of Bypass 15.2.2.5 Radiological Consequences

15.2.3 Turbine Trip

15.2.3.1 Identification of Causes and Frequency Classification 15.2.3.1.1 Identification of Causes 15.2.3.1.2 Frequency Classification 15.2.3.1.2.1 Turbine Trip 15.2.3.2 Sequence of Events and Systems Operation 15.2.3.2.1 Sequence of Events 15.2.3.2.1.1 Turbine Trip with Bypass Operable 15.2.3.2.1.2 Turbine Trip with Failure of the Bypass 15.2.3.2.1.3 Identification of Operator Actions 15.2.3.2.2 Systems Operation 15.2.3.2.2.1 Turbine Trip with Bypass Operable 15.2.3.2.2.2 Turbine Trip with Failure of the Bypass 15.2.3.2.2.3 Turbine Trip at Low Power with Failure of the Bypass 15.2.3.2.3 The Effect of Single Failures and Operators Errors 15.2.3.2.3.1 Turbine Trips at Power Levels Greater Than 30%

15.2.3.2.3.2 Turbine Trips at Power Levels Less Than 30%

15.2.3.3 Core and System Performance 15.2.3.3.1 Mathematical Model 15.2.3.3.2 Input Parameters and Initial Conditions 15.2.3.3.3 Results 15.2.3.3.3.1 Turbine Trip with Bypass Operable 15.2.3.3.3.2 Turbine Trip with Failure of Bypass 15.2.3.3.3.3 Turbine Trip with Bypass Valve Failure, Low Power 15.2.3.3.4 Considerations of Uncertainties SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-vi 15.2.3.4 Barrier Performance 15.2.3.4.1 Turbine Trip with Bypass Operable 15.2.3.4.2 Turbine Trip with Failure of the Bypass 15.2.3.4.2.1 Turbine Trip with Failure of Bypass at Low Power 15.2.3.5 Radiological Consequences

15.2.4 MSIV Closures

15.2.4.1 Identification of Causes and Frequency Classification 15.2.4.1.1 Identification of Causes 15.2.4.1.2 Frequency Classification 15.2.4.1.2.1 Closure of All Main Steam Isolation Valves 15.2.4.1.2.2 Closure of One Main Steam Isolation Valve 15.2.4.2 Sequence of Events and Systems Operation 15.2.4.2.1 Sequence of Events 15.2.4.2.1.1 Identification of Operator Actions 15.2.4.2.2 Systems Operation 15.2.4.2.2.1 Closure of All Main Steam Isolation Valves 15.2.4.2.2.2 Closure of One Main Steam Isolation Valve 15.2.4.2.3 The Effect of Single Failures and Operator Errors 15.2.4.3 Core and System Performance 15.2.4.3.1 Mathematical Model 15.2.4.3.2 Input Parameters and Initial Conditions 15.2.4.3.3 Results 15.2.4.3.3.1 Closure of All Main Steam Isolation Valves 15.2.4.3.3.2 Closure of One Main Steam Isolation Valve 15.2.4.3.4 Considerations of Uncertainties 15.2.4.4 Barrier Performance 15.2.4.4.1 Closure of All Main Steam Isolation Valves 15.2.4.4.2 Closure of One Main Steam Isolation Valve 15.2.4.5 Radiological Consequences

15.2.5 Loss of Condenser Vacuum

15.2.5.1 Identification of Causes and Frequency Classification 15.2.5.1.1 Identification of Causes 15.2.5.1.2 Frequency Classification 15.2.5.2 Sequence of Events and Systems Operation 15.2.5.2.1 Sequence of Events 15.2.5.2.1.1 Identification of Operator Actions 15.2.5.2.2 Systems Operation SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-vii 15.2.5.2.3 The Effect of Single Failures and Operator Errors 15.2.5.3 Core and System Performance 15.2.5.3.1 Mathematical Model 15.2.5.3.2 Input Parameters and Initial Conditions 15.2.5.3.3 Results 15.2.5.3.4 Considerations of Uncertainties 15.2.5.4 Barrier Performance 15.2.5.5 Radiological Consequences

15.2.6 Loss of AC Power

15.2.6.1 Identification of Causes and Frequency Classification 15.2.6.1.1 Identification of Causes 15.2.6.1.1.1 Loss of Auxiliary Power Transformer 15.2.6.1.1.2 Loss of All Grid Connections 15.2.6.1.2 Frequency Classification 15.2.6.1.2.1 Loss of Auxiliary Power Transformer 15.2.6.1.2.2 Loss of All Grid Connections 15.2.6.2 Sequence of Events and Systems Operation 15.2.6.2.1 Sequence of Events 15.2.6.2.1.1 Loss of Auxiliary Power Transformer 15.2.6.2.1.2 Loss of All Grid Connections 15.2.6.2.1.3 Identification of Operator Actions 15.2.6.2.2 Systems Operation 15.2.6.2.2.1 Loss of Auxiliary Power Transformer 15.2.6.2.2.2 Loss of All Grid Connections 15.2.6.2.3 The Effect of Single Failures and Operator Errors 15.2.6.3 Core and System Performance 15.2.6.3.1 Mathematical Model 15.2.6.3.2 Input Parameters and Initial Conditions 15.2.6.3.2.1 Loss of Auxiliary Power Transformer 15.2.6.3.2.2 Loss of All Grid Connections 15.2.6.3.3 Results 15.2.6.3.3.1 Loss of Auxiliary Power Transformer 15.2.6.3.3.2 Loss of All Grid Connections 15.2.6.3.4 Consideration of Uncertainties 15.2.6.4 Barrier Performance 15.2.6.4.1 Loss of Auxiliary Power Transformer 15.2.6.4.2 Loss of All Grid Connections 15.2.6.5 Radiological Consequences

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-viii 15.2.7 Loss of Feedwater Flow

15.2.7.1 Identification of Causes and Frequency Classification 15.2.7.1.1 Identification of Causes 15.2.7.1.2 Frequency Classification 15.2.7.2 Sequence of Events and Systems Operation 15.2.7.2.1 Sequence of Events 15.2.7.2.1.1 Identification of Operator Actions 15.2.7.2.2 Systems Operation 15.2.7.2.3 The Effect of Single Failures and Operator Errors 15.2.7.3 Core and System Performance 15.2.7.3.1 Mathematical Model 15.2.7.3.2 Input Parameters and Initial Conditions 15.2.7.3.3 Results 15.2.7.3.4 Considerations of Uncertainties 15.2.7.4 Barrier Performance 15.2.7.5 Radiological Consequences

15.2.8 Feedwater Line Break

15.2.9 Failure of RHR Shutdown Cooling

15.2.9.1 Identification of Causes and Frequency Classification 15.2.9.1.1 Identification of Causes 15.2.9.1.2 Frequency Classification 15.2.9.2 Sequence of Events and System Operation 15.2.9.2.1 Sequence of Events 15.2.9.2.1.1 Identification of Operator Actions 15.2.9.2.2 System Operation 15.2.9.2.3 The Effect of Single Failures and Operator Errors 15.2.9.3 Core and System Performance 15.2.9.3.1 Methods, Assumptions, and Conditions 15.2.9.3.2 Results 15.2.9.3.2.1 Full Power to Approximately 100 psig 15.2.9.3.2.2 Approximately 100 psig to Cold Shutdown 15.2.9.4 Barrier Performance 15.2.9.5 Radiological Consequences

15.2.10 References

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-ix 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE

15.3.1 Recirculation Pump Trip

15.3.1.1 Identification of Causes and Frequency Classification 15.3.1.1.1 Identification of Causes 15.3.1.1.2 Frequency Classification 15.3.1.1.2.1 Trip of One Recirculation Pump 15.3.1.1.2.2 Trip of Two Recirculation Pumps 15.3.1.2 Sequence of Events and Systems Operation 15.3.1.2.1 Sequence of Events 15.3.1.2.1.1 Trip of One Recirculation Pump 15.3.1.2.1.2 Trip of Two Recirculation Pumps 15.3.1.2.1.3 Identification of Operator Actions 15.3.1.2.1.3.1 Trip of One Recirculation Pump 15.3.1.2.1.3.2 Trip of Two Recirculation Pumps 15.3.1.2.2 Systems Operation 15.3.1.2.2.1 Trip of One Recirculation Pump 15.3.1.2.2.2 Trip of Two Recirculation Pumps 15.3.1.2.3 The Effect of Single Failures and Operator Errors 15.3.1.2.3.1 Trip of One Recirculation Pump 15.3.1.2.3.2 Trip of Two Recirculation Pumps 15.3.1.3 Core and System Performance 15.3.1.3.1 Mathematical Model 15.3.1.3.2 Input Parameters and Initial Conditions 15.3.1.3.3 Results 15.3.1.3.3.1 Trip of One Recirculation Pump 15.3.1.3.3.2 Trip of Two Recirculation Pumps 15.3.1.3.4 Consideration of Uncertainties 15.3.1.4 Barrier Performance 15.3.1.4.1 Trip of One Recirculation Pump 15.3.1.4.2 Trip of Two Recirculation Pumps 15.3.1.5 Radiological Consequences

15.3.2 Recirculation Flow Control Failure - Decreasing Flow

15.3.2.1 Identification of Causes and Frequency Classification 15.3.2.1.1 Identification of Causes 15.3.2.1.2 Frequency Classification 15.3.2.2 Sequence of Events and Systems Operation 15.3.2.2.1 Sequence of Events SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-x 15.3.2.2.1.1 Failure of One Speed Control Loop Including Failure of the Redundant Control Processor (CP) Pair 15.3.2.2.1.2 Identification of Operator Actions 15.3.2.2.2 Systems Operation 15.3.2.2.3 The Effect of Single Failures and Operator Errors 15.3.2.3 Core and System Performance 15.3.2.3.1 Mathematical Model 15.3.2.3.2 Input Parameters and Initial Conditions 15.3.2.3.3 Results 15.3.2.3.4 Consideration of Uncertainties 15.3.2.4 Barrier Performance 15.3.2.5 Radiological Consequences

15.3.3 Recirculation Pump Seizure

15.3.3.1 Identification of Causes and Frequency Classification 15.3.3.1.1 Identification of Causes 15.3.3.1.2 Frequency Classification 15.3.3.2 Sequence of Events and Systems Operations 15.3.3.2.1 Sequence of Events 15.3.3.2.1.1 Identification of Operator Actions 15.3.3.2.2 Systems Operation 15.3.3.2.3 The Effect of Single Failures and Operator Errors 15.3.3.3 Core and System Performance 15.3.3.3.1 Mathematical Model 15.3.3.3.2 Input Parameters and Initial Conditions 15.3.3.3.3 Results 15.3.3.3.4 Considerations of Uncertainties 15.3.3.4 Barrier Performance 15.3.3.5 Radiological Consequences 15.3.3.5.1 Design Basis Analysis 15.3.3.5.2 Realistic Analysis

15.3.4 Recirculation Pump Shaft Break

15.3.4.1 Identification of Causes and Frequency Classification 15.3.4.1.1 Identification of Causes 15.3.4.1.2 Frequency Classification 15.3.4.2 Sequence of Events and Systems Operations 15.3.4.2.1 Sequence of Events 15.3.4.2.1.1 Identification of Operator Actions SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xi 15.3.4.2.2 Systems Operation 15.3.4.2.3 The Effect of Single Failures and Operator Errors 15.3.4.3 Core and System Performance 15.3.4.3.1 Qualitative Results 15.3.4.4 Barrier Performance 15.3.4.5 Radiological Consequences

15.3.5 References

15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES

15.4.1 Rod Withdrawal Error - Low Power

15.4.1.1 Control Rod Removal Error During Refueling 15.4.1.1.1 Identification of Causes and Frequency Classification 15.4.1.1.2 Sequence of Events and Systems Operation 15.4.1.1.2.1 Initial Control Rod Removal 15.4.1.1.2.2 Fuel Movement With Control Rod Removed 15.4.1.1.2.3 Control Rod Removal Without Fuel Removal 15.4.1.1.2.4 Identification of Operator Actions 15.4.1.1.2.5 Effect of Single Failure and Operator Errors 15.4.1.1.3 Core and System Performances 15.4.1.1.4 Barrier Performance 15.4.1.1.5 Radiological Consequences 15.4.1.2 Continuous Rod Withdrawal During Reactor Startup 15.4.1.2.1 Identification of Causes and Frequency Classification 15.4.1.2.2 Sequence of Events and Systems Operation 15.4.1.2.2.1 Sequence of Events 15.4.1.2.2.2 Identification of Operator Actions 15.4.1.2.2.3 Effects of Single Failure and Operator Errors 15.4.1.2.3 Core and System Performance 15.4.1.2.4 Barrier Performance 15.4.1.2.5 Radiological Consequences

15.4.2 Rod Withdrawal Error-at Power

15.4.2.1 Identification of Causes and Frequency Classifications 15.4.2.1.1 Identification of Causes 15.4.2.1.2 Frequency Classification 15.4.2.2 Sequence of Events and Systems Operation 15.4.2.2.1 Sequence of Events SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xii 15.4.2.2.2 System Operations 15.4.2.2.3 Effect of Single Failure and Operator Errors 15.4.2.3 Core and System Performance 15.4.2.3.1 Mathematical Model 15.4.2.3.2 Input Parameters and Initial Conditions 15.4.2.3.2.1 REM System Operation 15.4.2.3.3 Results 15.4.2.3.4 Considerations of Uncertainties 15.4.2.4 Barrier Performance 15.4.2.5 Radiological Consequences

15.4.3 Control Rod Maloperation (System Malfunction or Operator Error)

15.4.4 Abnormal Startup of Idle Recirculation Pump

15.4.4.1 Identification of Causes and Frequency Classification 15.4.4.1.1 Identification of Causes 15.4.4.1.1.1 Normal Restart of Recirculation Pump at Power 15.4.4.1.1.2 Abnormal Startup of Idle Recirculation Pump 15.4.4.2 Sequence of Events and Systems Operation 15.4.4.2.1 Sequence of Events 15.4.4.2.1.1 Operator Actions 15.4.4.2.2 Systems Operation 15.4.4.2.3 The Effect of Single Failures and Operator Errors 15.4.4.3 Core and System Performance 15.4.4.3.1 Mathematical Model 15.4.4.3.2 Input Parameters and Initial Conditions 15.4.4.3.3 Results 15.4.4.3.4 Consideration of Uncertainties 15.4.4.4 Barrier Performance 15.4.4.5 Radiological Consequences

15.4.5 Recirculation Flow Control Failure with Increasing Flow

15.4.5.1 Identification of Causes and Frequency Classification 15.4.5.1.1 Identification of Causes 15.4.5.1.2 Frequency Classification 15.4.5.2 Sequence of Events and Systems Operation 15.4.5.2.1 Sequence of Events 15.4.5.2.1.1 Identification of Operator Actions 15.4.5.2.2 Systems Operation SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xiii 15.4.5.2.3 The Effect of Single Failures and Operator Errors 15.4.5.3 Core and System Performance 15.4.5.3.1 Mathematical Model 15.4.5.3.2 Input Parameters and Initial Conditions 15.4.5.3.3 Results 15.4.5.3.4 Considerations of Uncertainties 15.4.5.4 Barrier Performance 15.4.5.5 Radiological Consequences

15.4.6 Chemical and Volume Control System Malfunctions

15.4.7 Misplaced Bundle Accident

15.4.7.1 Identification of Causes and Frequency Classification 15.4.7.1.1 Identification of Causes 15.4.7.1.2 Frequency of Occurrence 15.4.7.2 Sequence of Events and Systems Operation 15.4.7.2.1 Effect of Single Failure and Operator Errors 15.4.7.3 Core and System Performance 15.4.7.3.1 Mathematical Model 15.4.7.3.2 Input Parameters and Initial Conditions 15.4.7.3.3 Results 15.4.7.3.4 Considerations of Uncertainties 15.4.7.4 Barrier Performance 15.4.7.5 Radiological Consequences

15.4.8 Spectrum of Rod Ejection Assemblies

15.4.9 Control Rod Drop Accident (CRDA)

15.4.9.1 Identification of Causes and Frequency Classification 15.4.9.1.1 Identification of Causes 15.4.9.1.2 Frequency of Classification 15.4.9.2 Sequence of Events and System Operation 15.4.9.2.1 Sequence of Events 15.4.9.2.2 Systems Operation 15.4.9.2.3 Effect of Single Failures and Operator Errors 15.4.9.3 Core and System Performance 15.4.9.3.1 Mathematical Model 15.4.9.3.2 Input Parameters and Initial Conditions 15.4.9.3.3 Results SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xiv 15.4.9.4 Barrier Performance 15.4.9.5 Radiological Consequences 15.4.9.5.1 Design Basis Analysis 15.4.9.5.2 Realistic Analysis

15.4.10 References

15.5 INCREASE IN REACTOR COOLANT INVENTORY

15.5.1 Inadvertent HPCI Startup

15.5.1.1 Identification of Causes and Frequency Classification 15.5.1.1.1 Identification of Causes 15.5.1.1.2 Frequency Classification 15.5.1.2 Sequence of Events and Systems Operation 15.5.1.2.1 Sequence of Events 15.5.1.2.1.1 Identification of Operator Actions 15.5.1.2.2 System Operation 15.5.1.2.3 The Effect of Single Failures and Operator Errors 15.5.1.3 Core and System Performance 15.5.1.3.1 Mathematical Model 15.5.1.3.2 Input Parameter and Initial Conditions 15.5.1.3.3 Results 15.5.1.3.4 Consideration of Uncertainties 15.5.1.4 Barrier Performance 15.5.1.5 Radiological Consequences

15.5.2 Chemical Volume Control System Malfunction (or Operator Error)

15.5.3 BWR Transients Which Increase Reactor Coolant Inventory

15.5.4 References

15.6 DECREASE IN REACTOR COOLANT INVENTORY

15.6.1 Inadvertent Safety Relief Valve Opening 15.6.2 Instrument Line Break

15.6.2.1 Identification of Causes and Frequency Classification 15.6.2.1.1 Identification of Causes SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xv 15.6.2.1.1.1 Event Description 15.6.2.1.2 Frequency Classification 15.6.2.2 Sequence of Events and Systems Operation 15.6.2.2.1 Sequence of Events 15.6.2.2.1.1 Identification of Operator Actions 15.6.2.2.2 System Operation 15.6.2.2.3 The Effect of Single Failures and Operator Errors 15.6.2.3 Core and System Performance 15.6.2.3.1 Qualitative Summary - Results 15.6.2.3.2 Quantitative Results 15.6.2.3.3 Considerations of Uncertainties 15.6.2.4 Barrier Performance 15.6.2.5 Radiological Consequences 15.6.2.5.1 Design Basis Analysis 15.6.2.5.2 Realistic Analysis 15.6.2.5.3 Results

15.6.3 Steam Generator Tube Failure

15.6.4 Steam System Piping Break Outside Containment

15.6.4.1 Identification of Causes and Frequency Classification 15.6.4.1.1 Identification of Causes 15.6.4.1.2 Frequency Classification 15.6.4.2 Sequence of Events and Systems Operation 15.6.4.2.1 Sequence of Events 15.6.4.2.1.1 Identification of Operator Actions 15.6.4.2.2 Systems Operation 15.6.4.2.3 The Effect of Single Failures and Operator Errors 15.6.4.3 Core and System Performance 15.6.4.3.1 Input Parameters and Initial Conditions 15.6.4.3.2 Results 15.6.4.3.3 Considerations of Uncertainties 15.6.4.4 Barrier Performance 15.6.4.5 Radiological Consequences 15.6.4.5.1 Design Basis Analysis 15.6.4.5.2 Realistic Analysis 15.6.4.5.3 Results

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xvi 15.6.5 Loss-Of-Coolant Accidents (Resulting From Spectrum of Postulated Piping Breaks Within The Reactor Coolant Pressure Boundary) -

Inside Containment

15.6.5.1 Identification of Causes and Frequency Classification 15.6.5.1.1 Identification of Causes 15.6.5.1.2 Frequency Classification 15.6.5.2 Sequence of Events and Systems Operation 15.6.5.2.1 Sequence of Events 15.6.5.2.1.1 Identification of Operator Actions 15.6.5.2.2 Systems Operations 15.6.5.2.3 The Effect of Single Failures and Operator Errors 15.6.5.3 Core and System Performance 15.6.5.3.1 Mathematical Model 15.6.5.3.2 Input Parameters and Initial Conditions 15.6.5.3.3 Results 15.6.5.3.4 Consideration of Uncertainties 15.6.5.4 Barrier Performance 15.6.5.5 Radiological Consequences 15.6.5.5.1 Design Basis Analysis 15.6.5.5.1.1 Fission Product Release from Fuel 15.6.5.5.1.2 Fission Product Transport to the Environment 15.6.5.5.2 Realistic Analysis 15.6.5.5.2.1 Fission Product Release from Fuel 15.6.5.5.2.2 Fission Product Transport to the Environment 15.6.5.5.3 Results 15.6.5.5.3.1 Offsite Exposure 15.6.5.5.3.2 Control Room Doses

15.6.6 Feedwater Line Break-Outside Containment

15.6.6.1 Identification of Causes and Frequency Classification 15.6.6.1.1 Identification of Causes 15.6.6.1.2 Frequency Classification 15.6.6.2 Sequence of Events and Systems Operation 15.6.6.2.1 Sequence of Events 15.6.6.2.1.1 Identification of Operator Actions 15.6.6.2.2 Systems Operations 15.6.6.2.3 The Effect of Single Failures and Operator Errors 15.6.6.3 Core and System Performance 15.6.6.3.1 Qualitative Summary SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xvii 15.6.6.3.2 Qualitative Results 15.6.6.3.3 Consideration of Uncertainties 15.6.6.4 Barrier Performance 15.6.6.5 Radiological Consequences 15.6.6.5.1 Design Basis Analysis 15.6.6.5.2 Realistic Analysis 15.6.6.5.3 Fission Product Release 15.6.6.5.4 Fission Product Transport to the Environment 15.6.6.5.5 Results

15.6.7 References

15.7 RADIOACTIVE RELEASE FROM SUBSYSTEMS AND COMPONENTS

15.7.1 Gaseous Radwaste System Leak or Failure

15.7.1.1 Ambient Charcoal Offgas Treatment System Failure 15.7.1.1.1 Identification of Causes and Frequency Classification 15.7.1.1.1.1 Identification of Causes 15.7.1.1.1.2 Frequency Classification 15.7.1.1.2 Sequence of Events and System Operation 15.7.1.1.2.1 Sequence of Events 15.7.1.1.2.2 Identification of Operator Actions 15.7.1.1.2.3 Systems Operation 15.7.1.1.2.4 The Effects of Single Failures and Operator Errors 15.7.1.1.3 Core and System Performance 15.7.1.1.4 Barrier Performance 15.7.1.1.5 Radiological Consequences 15.7.1.1.5.1 Design Basis Analysis 15.7.1.1.5.2 Realistic Analysis 15.7.1.1.5.3 Results 15.7.1.2 Malfunction of Main Turbine Gland Sealing System 15.7.1.2.1 Identification of Causes and Frequency Classification 15.7.1.2.1.1 Identification of Causes 15.7.1.2.1.2 Frequency Classification 15.7.1.2.2 Sequence of Events and System Operation 15.7.1.2.2.1 Sequence of Events 15.7.1.2.2.2 Identification of Operator Actions 15.7.1.2.2.3 System Operation 15.7.1.2.3 Core and System Performance SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xviii 15.7.1.2.4 Barrier Analysis 15.7.1.2.5 Radiological Consequences 15.7.1.3 Failure of Air Ejector Lines 15.7.1.3.1 Identification of Causes and Frequency Classification 15.7.1.3.2 Sequence of Events and Systems Operation 15.7.1.3.3 Core and System Performance 15.7.1.3.4 Barrier Analysis 15.7.1.3.5 Radiological Consequences 15.7.1.3.5.1 Design Basis Analysis 15.7.1.3.5.2 Realistic Analysis 15.7.1.3.5.3 Fission Product Release 15.7.1.3.5.4 Fission Product Transport to the Environment 15.7.1.3.5.5 Results

15.7.2 Liquid Radwaste System Failure

15.7.2.1 Miscellaneous Small Releases Outside Containment

15.7.3 Postulated Radioactive Releases Due To Liquid Radwaste Tank Failure 15.7.3.1 Identification of Causes and Frequency Classification 15.7.3.1.1 Identification of Causes 15.7.3.1.2 Frequency Classification 15.7.3.2 Sequence of Events and Systems Operation 15.7.3.3 Core and System Performance 15.7.3.4 Barrier Performance 15.7.3.5 Radiological Consequences 15.7.3.5.1 Design Basis Analysis 15.7.3.5.2 Realistic Analysis

15.7.4 Fuel and Equipment Handling Accidents

15.7.4.1 Identification of Causes and Frequency Classification 15.7.4.1.1 Identification of Causes 15.7.4.1.2 Frequency Classification 15.7.4.2 Sequence of Events and Systems Operation 15.7.4.2.1 Sequence of Events 15.7.4.2.2 Identification of Operator Actions 15.7.4.2.3 System Operation 15.7.4.2.4 The Effects of Single Failures and Operator Errors SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xix 15.7.4.3 Core and System Performance 15.7.4.3.1 Mathematical Model 15.7.4.3.2 Input Parameters and Initial Conditions 15.4.7.3.3 Results 15.7.4.3.3.1 Energy Available 15.7.4.3.3.2 Energy Loss Per Impact 15.7.4.3.3.3 Fuel Rod Failures 15.7.4.3.3.3.1 First Impact Failures 15.7.4.3.3.3.2 Second Impact Failures 15.7.4.3.3.3.3 Total Failures 15.7.4.4 Barrier Performance 15.7.4.5 Radiological Consequences 15.7.4.5.1 Design Basis Analysis 15.7.4.5.1.1 Fission Product Release from Fuel 15.7.4.5.1.2 Fission Product Transport to the Environment 15.7.4.5.1.3 Results 15.7.4.5.2 Realistic Analysis 15.7.4.5.2.1 Fission Product Release from Fuel 15.7.4.5.2.2 Fission Product Transport to the Environment 15.7.4.5.2.3 Results

15.7.5 Spent Fuel Cask Drop Accident

15.7.6 References

15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS)

15.8.1 Causes, Frequency Classification, Initiating Events, Acceptance Criteria, Mathematical Models, Input Parameters, and Initial Conditions 15.8.1.1 Identification of Causes 15.8.1.2 Frequency Classification 15.8.1.3 Initiating Events 15.8.1.4 Acceptance Criteria 15.8.1.4.1 Peak Clad Temperature and Vessel Pressure Associated with Initial Pressurization Transient 15.8.1.4.2 Peak Suppression Pool Temperature and Containment Pressure 15.8.1.4.3 Fuel Integrity Under Unstable Operation 15.8.1.4.4 Radiological Consequences and Long-Term Shutdown and Cooling Capability 15.8.1.5 Mathematical Models SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xx 15.8.1.6 Input Parameters and Initial Conditions

15.8.2 Inadvertent Control Rod Withdrawal

15.8.3 Loss of Feedwater (LOFW)

15.8.4 Loss of Offsite Power (LOOP)

15.8.5 Loss of Electrical Load

15.8.6 Loss of Condenser Vacuum

15.8.7 Turbine Trip

15.8.8 Closure of Main Steam Line Isolation Valves 15.8.8.1 Sequence of Events, Systems Operation, and Operator Actions 15.8.8.2 Results

15.8.9 Pressure Regulator Failure-Open 15.8.9.1 Sequence of Events, Systems Operation, and Operator Actions 15.8.9.2 Results

15.8.10 Feedwater Controller Failure-Open (FWCFO)

15.8.11 Inadvertent Opening of a S/R Valve

15.8.12 References

15.9 STATION BLACKOUT (SBO)

15.9.0 Coping Assessment for the Susquehanna Steam Electric Station During a Station Blackout

15.9.1 References

15A Nuclear Safety Operational Analysis (NOSA) (A System Level/Qualitative Type Plant FMEA)

15A.1 OBJECTIVES

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxi 15A.1.1 General Objectives

15A.1.2 Specific Objectives

15A.2 APPROACH TO OPERATIONAL NUCLEAR SAFETY

15A.2.1 General Philosophy

15A.2.2 Specific Philosophy

15A.2.2.1 Consistency of the Analysis

15A.2.3 Comprehensiveness of the Analysis

15A.2.4 Systematic Approach of the Analysis

15A.2.5 Relationship of Nuclear Safety Operational Analysis to Safety Analyses of Chapter 15

15A.2.6 Relationship Between NSOA and Operational Requirements, Technical Specifications, Design Basis, and SACF Aspects

15A.2.7 Unacceptable Results Criteria

15A.2.8 General Nuclear Safety Operational Criteria

15A.3 METHOD OF ANALYSIS

15A.3.1 General Approach

15A.3.2 BWR Operating States

15A.3.3 Selection of Events for Analysis

15A.3.3.1 Planned Operations 15A.3.3.2 Anticipated (Expected) Operational Transients 15A.3.3.3 Abnormal (Unexpected) Operational Transients 15A.3.3.4 Accidents 15A.3.3.5 Additional Special Plant Capability Events

15A.3.4 Applicability of Events to Operating States SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxii 15A.3.5 Rules for Event Analysis

15A.3.6 Steps in an Operational Analysis

15A.4 DISPLAY OF OPERATIONAL ANALYSIS RESULTS

15A.4.1 General

15A.4.2 Protection Sequence and Safety System Auxiliary Diagrams

15A.5 BASES FOR SELECTING SURVEILLANCE TEST FREQUENCIES

15A.5.1 Normal Surveillance Test Frequencies

15A.5.2 Allowable Repair Times

15A.5.3 Repair Time Rule

15A.6 OPERATIONAL ANALYSES

15A.6.1 Safety System Auxiliaries

15A.6.2 Planned (Normal) Operations

15A.6.2.1 General 15A.6.2.2 Event Definitions 15A.6.2.3 Required Safety Actions/Related Unacceptable Results 15A.6.2.3.1 Radioactive Material Release Control 15A.6.2.3.2 Core Coolant Flow Rate Control 15A.6.2.3.3 Core Power Level Control 15A.6.2.3.4 Core Neutron Flux Distribution Control 15A.6.2.3.5 Reactor Vessel Water Level Control 15A.6.2.3.6 Reactor Vessel Pressure Control 15A.6.2.3.7 Nuclear System Temperature Control 15A.6.2.3.8 Nuclear System Water Quality Control 15A.6.2.3.9 Nuclear System Leakage Control 15A.6.2.3.10 Core Reactivity Control 15A.6.2.3.11 Control Rod Worth Control 15A.6.2.3.12 Refueling Restriction 15A.6.2.3.13 Containment & Reactor Building Pressure and Temperature Control SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxiii 15A.6.2.3.14 Stored Fuel Shielding, Cooling, and Reactivity Control 15A.6.2.4 Operational Safety Evaluations

15A.6.3 Anticipated (Expected) Operational Transients

15A.6.3.1 General 15A.6.3.2 Required Safety Actions/Related Unacceptable Result 15A.6.3.3 Event Definitions & Operational Safety Evaluations

15A.6.4 Abnormal (Unexpected) Operational Transients

15A.6.4.1 General 15A.6.4.2 Required Safety Actions/Related Unacceptable Results 15A.6.4.3 Event Definition & Operational Safety Evaluation

15A.6.5 Design Basis (Postulated) Accidents

15A.6.5.1 General 15A.6.5.2 Required Safety Actions/Unacceptable Results 15A.6.5.3 Event Definition and Operational Safety Evaluations

15A.6.6 Special (Plant Capability) Events

15A.6.6.1 General 15A.6.6.2 Required Safety Action/Unacceptable Results 15A.6.6.3 Event Definitions and Operational Safety Evaluation

15A.7 REMAINDER OF NSQA

15A.8 CONCLUSIONS

15A.9 LIST OF REFERENCES

15B ACCIDENT DOSE MODEL DESCRIPTIONS

15B.1 OFFSITE DOSE MODEL 15B.1.1 Total Body Gamma Dose

15B.1.2 Thyroid Inhalation Dose

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxiv 15B.1.3 Beta Skin Dose

15B.2 CONTROL ROOM DOSE MODEL

15B.3 REFERENCES

APPENDIX 15C SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 FINAL SAFETY ANALYSIS REPORT - CYCLE SPECIFIC DATA

APPENDIX 15D SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 FINAL SAFETY ANALYSIS REPORT - CYCLE SPECIFIC DATA

APPENDIX 15E INITIAL CORE FOR SSES UNITS 1 AND 2 NON-LIMITING EVENTS SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxv 15.0-1 15.0-1A 15.0-2 15.0-3 15.0-4 15.0-5 SECTION15.0 - All Tables have been moved to Appendix 15C and D 15.1-1 15.1-2 15.1-3 15.1-4 15.1-5 15.1-6 15-1-7 Sequence or Events for Inadvertent Safety Relief Valve Opening Safety Relief Valve Opening Event Activity Above Suppression Pool (Curies)

Safety Relief Valve Opening Event Activity Release to Environs (Curies) Safety Relief Valve Opening Event Radiological Doses (REM-TEDE) These Tables Are not Used These Tables Are not Used These Tables Are not Used 15.2-1 15.2-2 15.2-3 15.2-4 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 15.2-15 15.2-16 SECTION 15.2 - All Tables have been moved to Appendix 15C and D 15.3-1 15.3-2 15.3-3 SECTION 15 All Tables have been moved to Appendix 15C and D 15.4-1 15.4-2 15.4-3 15.4-4 15.4-5 15.4-6 15.4-7 15.4-8 15.4-9 15.4-10 15.4-11 15.4-12 15.4-13 15.4-14 15.4-15 15.4-16 Sequence of Events for Control Rod Drop Accident Control Rod Drop Accident - Design Basis Analysis-Airborne Activity in Condense (2000 Failed Rods) Control Rod Drop Accident - Design Basis Analysis-Airborne Activity in Condenser (30 Failed Rods) Control Rod Drop Accident - Design Basis Analysis- Activity Released to Environs (2000 Failed Rods) Control Rod Drop Accident - Design Basis Analysis- Activity Released to Environs (30 Failed Rods) Control Rod Drop Accident - Activity Airborne in Condenser (Realistic Analysis) (2000 Rods) Control Rod Drop Accident - Activity Airborne in Condenser (Realistic Analysis) (30 Rods) Control Rod Drop Accident - Activity Released to Environs (Realistic Analysis) (2000 Rods) Control Rod Drop Accident - Activity Released to Environs (Realistic Analysis) (30 Rods) Control Rod Accident Radiological Effects Design Basis Case and Realistic Case Control Rod Drop Accident - Parameters to be Tabulated for Postulated Accident Analysis Sequence of Events for Misloaded Bundle/Accident/Sequence of Events for Rotated Bundle Accident These Tables are not Used These Tables are not Used These Tables are not Used These Tables are not Used

SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxvi 15.5-1 This Table Has Been Deleted

15.6-1 Sequence of Events for Instrument Line Break 15.6-2 Mass Releases-Instrument Line Break 15.6-3 Instrument Line Break Activity Released to the Environment (Curies) 15.6-4 Instrument Line Break Inside Secondary Containment Radiological Consequences 15.6-5 Instrument Line Break Accident - Parameters for Postulated Accident Analysis 15.6-6 Sequence of Events for Steam Line Break Outside Containment 15.6-7 Steam Line Break Accident Activity Released to the Environment (Curies) (Design Basis Analysis) 15.6-8 Steam Line Break Accident Activity Released to the Environment (Curies) (Realistic Analysis) 15.6-9 Steam Line Break Outside Containment Radiological Doses (rem) 15.6-10 Steam Line Break Accident - Parameters to be Tabulated for Postulated Accident Analyses 15.6-11 Loss of Coolant Accident - Activity Airborne in Primary Containment (Curies) (Design Basis Analysis) 15.6-12 This Table Has Been Intentionally Left Blank 15.6-13 Loss of Coolant Accident - Activity Airborne in Reactor Building (Curies) (Design Basis Analysis) 15.6-14 Loss of Coolant Accident - Activity Released to Environment (Curies) (Design Basis Analysis) 15.6-15 Loss of Coolant Accident - Activity Airborne in Primary Containment (Curies) (Realistic Analysis) 15.6-16 Loss of Coolant Accident - Activity Airborne in Reactor Building (Curies) (Realistic Analysis) 15.6-17 Loss of Coolant Accident - Activity Released to Environment (Curies) (Realistic Analysis) 15.6-18 Loss-of-Coolant Accident - Summary of Offsite Doses 15.6-19 This Table Has Been Intentionally Left Blank 15.6-20 This Table Has Been Intentionally Left Blank 15.6-21 Loss-of-Coolant Accident - Summary of Control Room Operator Doses (Design Basis Analysis) 15.6-22 Loss-of-Coolant Accident - Parameters for Postulated Accident Analysis 15.6-23 Sequence of Events for Feedwater Line Break Outside Containment 15.6-24 Feedwater Line Break Accident - Parameters for Postulated Accident Analyses 15.6-25 Feedwater Line Break Activity Released to Environment (Curies)

SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxvii 15.6-26 Feedwater Line Break Outside Containment Radiological Doses (rem) 15.7-1 Sequence of Events for Main Condenser Offgas Treatment System Failure 15.7-2 Activity Inventory Stored in Offgas Treatment System Activity Released to the Environs (curies) (Design Basis Analysis) 15.7-3 Activity Inventory Stored in Offgas Treatment System Activity Released to the Environs (curies) (Realistic Analysis) 15.7-4 Main Condenser Offgas Treatment System Failure Radiological Effects 15.7-5 Offgas Treatment System Failure Parameters for Postulated Accident Analysis 15.7-6 Failure of Air Ejector Lines Activity Released to the Environment (curies/sec) 15.7-7 Failure of Steam Jet Air Ejector Lines Radiological Consequences 15.7-8 Failure of Air Ejector Lines Parameters for Postulated Accident Analysis 15.7-9 RWCU Phase Separator Tank Failure Activity Release to Environment 15.7-10 RWCU Phase Separator Tank Failure Radiological Effects 15.7-11 RWCU Phase Separator Tank Failure 15.7-12 Refueling Accidents Activity Airborne in Reactor Building (Curies) (Design Basis Analysis) 15.7-13 Refueling Accidents Activity Released to Environment (Curies) (Design Basis Analysis) 15.7-14 Refueling Accidents - Activity Airborne in Reactor Building (Realistic Analysis) 15.7-15 Refueling Accidents - Activity Released to Environs (Realistic Analysis) 15.7-16 Refueling Accidents - Radiological Effects 15.7-16A Refueling Accidents with Additional Assembly (LUA) - Radiological Effects 15.7-17 Refueling Accidents - Parameters to be Tabulated for Postulated Accident Analyses 15.7-18 Sequence of Events for SJAE Failure

15.8-1 Input Parameters for ATWS Analysis 15.8-2 This Table Has Been Deleted 15.8-3 Input Operating Conditions for ATWS Analysis 15.8-4 This Table Has Been Deleted 15.8-5 Sequence of Events for MSIV Closure ATWS 15.8-6 This Table Has Been Deleted 15.8-7 Results for MSIV Closure ATWS Event 15.8-8 This Table Has Been Deleted 15.8-9 Sequence of Events for Prego ATWS 15.8-10 This Table Has Been Deleted 15.8-11 Results for Prego ATWS Event SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxviii 15.8-12 This Table Has Been Deleted 15.9-1 Unit 1 Station Blackout Instrumentation List 15.9-2 Unit 2 Station Blackout Instrumentation List 15A.2-1 Planned (Normal) Operation Cross-Correlation References 15A.2-2 Anticipated (Expected) Operational Transients Cross-Correlation References 15A.2-3 Abnormal (Unexpected) Operational Transients Cross-Correlation References 15A.2-4 Design Basis (Postulated) Accidents Cross-Correlation References 15A.2-5 Special (Plant Capability) Events Cross-Correlation References 15A.2-6 Plant Event Category: Planned (Normal) Operation Unacceptable Results Criteria 15A.2-7 Plant Event Category: Anticipated (Expected) Operational Transients Unacceptable Results Criteria 15A.2-8 Plant Event Category: Abnormal (Unexpected) Operational Transients Unacceptable Results Criteria 15A.2-9 Plant Event Category: Design Basis (Postulated) Accidents Unacceptable Result Criteria 15A.2-10 Plant Event Category: Special (Plant Capability) Events Unacceptable Results Considerations 15A.3-1 BWR Operating States 15A.6-1 Plant Events Applicable in Each BWR Operating State Planned (Normal)

Operation 15A.6-2 Plant Events Applicable in Each BWR Operating State Anticipated (Expected) Operational Transients 15A.6-3 Plant Events Applicable in Each BWR Operating State Abnormal (Unexpected) Operational Transients 15A.6-4 Plant Events Applicable in Each BWR Operating State Design Basis (Postulated) Accidents 15A.6-5 Plant Events Applicable in Each BWR Operating State Special (Plant Capability) Events 15.B-1 Control Room Atmospheric Dispersion Factors For Design Basis Accidents - X/Q 15B-2 Physical Data for Isotopes 15B-3 Breathing Rates 15B-4 This Table Has Been Deleted 15C.0-1 Results Summary of Transient Events Unit 1 15C.0-1A This Table Has Been Deleted 15C.0-2 Input Parameters and Initial Conditions for Transients Unit 1 15C.0-3 MCPR Fuel Cladding Integrity Safety Limit (All Fuel) Unit 1 SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxix 15C.0-4 Unit 1 Minimum MCPR Requirement For Single Loop Operation & 2 Loop Operation 15C.0-5 Average Scram Insertion Times Unit 1

15C.1.1-1 Sequence of Events for Loss of Feedwater Heating Unit 1 15C.1.2-1 Sequence of Events for Feedwater Controller Failure, Maximum Demand Unit 1 15C.1.3-1 Sequence of Events for Pressure Regulator Failure - Open Unit 1

15C.2.2-1 Sequence of Events for Generator Load Rejection Without Bypass and Turbine Trip Without Bypass Unit 1

15C.3.3-1 Pump Seizure Accident from Two Loop Operation Sequence of Events Unit 1 15C.3.3-2 Pump Seizure Accident from Single Loop Operation Sequence of Events Unit 1 15C.3.3-3 This Table Has Been Deleted 15C.3.3-4 This Table Has Been Deleted 15C.3.3-5 This Table Has Been Deleted 15C.3.3-6 This Table Has Been Deleted 15C.3.3-7 This Table Has Been Deleted 15C.3.3-8 This Table Has Been Deleted

15C.4.2-1 Sequence of Events - RWE Drift in Power Range Unit 1 15C.4.5-1 Sequence of Events for Recirculation Flow Controller Failure Unit 1 15C.4.7-1 Unit 1 Sequence of Events for Misloaded Bundle Accident 15C.4.9-1 Sequence of Events for Control Rod Drop Accident Unit 1 15C.4.9-2 Control Rod Drop Accident Unit 1 15C.4.9-3 This Table Has Been Deleted 15C.4.9-4 This Table Has Been Deleted 15C.4.9-5 This Table Has Been Deleted 15C.4.9-6 This Table Has Been Deleted 15C.4.9-7 This Table Has Been Deleted 15C.4.9-8 This Table Has Been Deleted 15D.0-1 Results Summary of Transient Events Unit 2 15D.0-1A This Table Has Been Deleted 15D.0-2 Input Parameters and Initial Conditions for Transients Unit 2 15D.0-3 MCPR Fuel Cladding Integrity Safety Limit (All Fuel) Unit 2 15D.0-4 Unit 2 Minimum MCPR Requirement for Single Loop Operation &

Minimum MCPR Requirement for 2 Loop Operation 15D.0-5 Average Scram Insertion Times Unit 2 SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxx 15D.1.1-1 Sequence of Events for Loss of Feedwater Heating Unit 2 15D.1.2-1 Sequence of Events for Feedwater Controller Failure, Maximum Demand Unit 2 15D.1.3-1 Sequence of Events for Pressure Regulator Failure - Open Unit 2

15D.2.2-1 Sequence of Events for Generator Load Rejection Without Bypass and Turbine Trip Without Bypass Unit 2

15D.3.3-1 Pump Seizure Accident from Two Loop Operation Sequence of Events Unit 2 15D.3.3-2 Pump Seizure Accident from Single Loop Operation Sequence of Events Unit 2 15D.3.3-3 This table has been deleted 15D.3.3-4 This table has been deleted 15D.3.3-5 This table has been deleted 15D.3.3-6 This table has been deleted 15D.3.3-7 This table has been deleted 15D.3.3-8 This table has been deleted

15D.4.2-1 Sequence of Events - RWE Drift in Power Range Unit 2 15D.4.5-1 Sequence of Events for Recirculation Flow Controller Failure Unit 2 15D.4.7-1 Sequence of Events for Misloaded Bundle Accident Unit 2 15D.4.9-1 Sequence of Events for Control Rod Drop Accident Unit 2 15D.4.9-2 Control Rod Drop Accident Unit 2 15D.4.9-3 This Table Has Been Deleted 15D.4.9-4 This Table Has Been Deleted 15D.4.9-5 This Table Has Been Deleted 15D.4.9-6 This Table Has Been Deleted 15D.4.9-7 This Table Has Been Deleted 15D.4.9-8 This Table Has Been Deleted

15E.0-1 Results Summary of Transient Events Units 1 and 2 Non-Limiting Events (Values are for the Initial Cores Only) 15E.0-2 Input Parameters and Initial Conditions for Transients Units 1 and 2 Initial Cycles 15E.1.1-1 Operator Actions When Reactor Scram is Incurred 15E.1.4-1 Sequence of Events for Inadvertent Safety Relief Valve Opening 15E-1-4-2 Safety Relief Valve Opening Event Activity Above Suppression Pool (curies)

SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxxi 15E-1-4-3 Safety Relief Valve Opening Event Activity Released to the Environs (curies) 15E-1-4-4 Safety Relief Valve Opening Event Offsite Radiological Doses (rems) 15E.1.6-1 Sequence of Events for Inadvertent RHR Shutdown Cooling Operation

15E.2.2-1 Sequence of Events for Figure 15E2.2-1 Generator Load Rejection, Bypass On 15E.2.3-1 Sequence of Events for Turbine Trip With Bypass Operable Figure 15E.2.3-1 15E.2.4-1 Sequence of Events for MSIV Closure, Figure 15E.2.4-1 15E.2.4-2 This table has been deleted 15E.2.4-3 This table has been deleted 15E.2.4-4 This table has been deleted 15E.2.5-1 Typical Rates of Decay for Condenser Vacuum 15E.2.5-2 Loss of Condenser Vacuum Sequence of Events for Figure 15E.2.5-1 15E.2.5-3 Trips Signals Associated With Loss of Condenser Vacuum 15E.2.6-1 Loss of Auxiliary Power Sequence of Events for Figure 15E.2.6-1 15E.2.6-2 Loss of All Grid Connections Sequence of Events for Figure 15E.2.6-2 15E.2.7-1 Loss of Feedwater Flow Sequence of Events for Figure 15E.2.7-1 15E.2.9-1 Sequence of Events for Failure of RHR Shutdown Cooling 15E.2.9-2 Input Parameters for Evaluation of Failure of RHR Shutdown Cooling

15E.3.1-1 Sequence of Events for Trip of One Recirculation Pump 15E.3.1-2 Sequence of Events for Trip of Two Recirculation Pumps

15E.4.4-1 Sequence of Events Abnormal Startup of Idle Recirculation Pump for Figure 15E.4.4-1 15E.5.1-1 Sequence of Events for Inadvertent Startup of HPCI

SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxii 15.0-1 15.0-2 15.0-3a 15.0-3b SECTION 15.0 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.1-1 15.1-2 15.1-3 15.1-4 SECTION 15.1 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.2-1 15.2-2 15.2-3 15.2-4 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 15.2-15 SECTION 15.2 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.3-1 15.3-2 15.3-3 SECTION 15.3 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.4-1 15.4-2 15.4-3 15.4-4 15.4-5 15.4-6 15.4-7 15.4-8 15.4-9 Leakage Path for Control Rod Drop Accident SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E 15.5-1 This Figure Has Been Renumbered to 15E.5.1-1

15.6-1 Leakage Path for Instrument Line Break 15.6-2 Steam Flow Schematic for Steam Break Outside Containment SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxiii 15.6-3 Leakage Flow for LOCA 15.6-4 Leakage Path for Feedwater Line Break Outside Containment

15.7-1 Leakage Path for Refueling Accidents

15A.2-1 Possible Inconsistencies in the Selection of Nuclear Safety Operational Requirements 15A.2-2 Methods Used to Derive NSO Requirements System and Sub-System Level Qualitative FMEA and Design Basis Confirmation Audits and Tech.

Specs. 15A.4-1 Format for Protection Sequence Diagrams 15A.4-2 Format for Safety System Auxiliary Diagrams 15A.4-3 Format for Commonality of Auxiliary Diagrams 15A.6-1 Safety System Auxiliaries 15A.6-2 Safety System Auxiliaries 15A.6-3 Safety Action Sequences for Planned Operations in State A 15A.6-4 Safety Action Sequences for Planned Operations in State B 15A.6-5 Safety Action Sequences for Planned Operations in State C 15A.6-6 Safety Action Sequences for Planned Operations in State D 15A.6-7 Protection Sequence for Manual or Inadvertent Scram 15A.6-8 Protection Sequence for Loss of Plant Instrument Air System 15A.6-9 Protection Sequence for Inadvertent Start-Up of HPCI's Pump 15A.6-10 Protection Sequences for Inadvertent Start-Up of Idle Recirculation Loop Pump 15A.6-11 Protection Sequence for Recirculation Loop Flow Control Failure - Maximum Demand 15A.6-12 Protection Sequence for Recirculation Loop Flow Control Failure -

Decreasing 15A.6-13 Recirculation Loop Pump Trip - One or Both 15A.6-14a Protection Sequences for Isolation of All Main Steamlines 15A.6-14b Protection Sequences for Isolation of the One Main Steamline 15A.6-15 Protection Sequences for Inadvertent Opening of a Safety/Relief Valve 15A.6-16 Protection Sequence for Control Rod Withdrawal Error - Startup and Refueling Operation 15A.6-17 Protection Sequence for Control Rod Withdrawal Error - Power Operation 15A.6-18 Protection Sequences for RHR'S - Loss of Shutdown Cooling Failure 15A.6-19 RHR'S - Shutdown Cooling Failure - Increased Cooling 15A.6-20 Protection Sequences for Loss of Feedwater Flow 15A.6-21 Protection Sequence for Loss of a Feedwater Heater 15A.6-22 Protection Sequences for Feedwater Controller Failure - Maximum Demand SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxiv 15A.6-23 Protection Sequences for Pressure Regulator Failure - Open 15A.6-24 Protection Sequence for Pressure Regulator Failure - Closed 15A.6-25 Protection Sequences for Main Turbine Trip with Bypass 15A.6-26 Protection Sequences for Loss of Main Condenser Vacuum 15A.6-27 Protection Sequences for Main Generator Trip with Bypass 15A.6-28 Protection Sequence for Loss of Normal AC Power - Aux Transformer Failure 15A.6-29 Protection Sequences for Loss of Normal AC Power - Grid Connection Loss 15A.6-30 Protection Sequences Main Generator Trip - Without Bypass 15A.6-31 Protection Sequences Main Turbine Trip - With Bypass Failure 15A.6-32 Protection Sequence for Inadvertent Loading and Operations of Fuel Assembly in Improper Position 15A.6-33 This Figure Has Been Intentionally Left Blank 15A.6-34 This Figure Has Been Intentionally Left Blank 15A.6-35 This Figure Has Been Intentionally Left Blank 15A.6-36 This Figure Has Been Intentionally Left Blank 15A.6-37 This Figure Has Been Intentionally Left Blank 15A.6-38 Protection Sequences for Recirculation Loop Pump Seizure 15A.6-39 Protection Sequence for Recirculation Loop Pump Shaft Break 15A.6-40 Protection Sequences for Control Rod Drop Accident 15A.6-41 Protection Sequences for Fuel Handling Accident 15A.6-42 Protection Sequences for Loss-of-Coolant Piping Breaks in RCPB - Inside Containment 15A.6-43 Protection Sequences for Liquid, Steam, Large, Small Piping Breaks Outside Containment 15A.6-44 This Figure Has Been Intentionally Left Blank 15A.6-45 This Figure Has Been Intentionally Left Blank 15A.6-46 Protection Sequences for Gaseous Radwaste System Leak or Failure 15A.6-47 Protection Sequence for Off-Gas Treatment System Failure 15A.6-48 Protection Sequence for Liquid Radwaste System Leak or Failure 15A.6-49 Protection Sequence for Liquid Radwaste System Storage Tank Failure 15A.6-50 Protection Sequence for Spend Fuel Cask Drop 15A.6-51 Protection Sequence for Reactor Shutdown - From Anticipated Transient Without Scram 15A.6-52 Protection Sequences for Reactor Shutdown - From Outside Main Control Room 15A.6-53 Protection Sequence for Reactor Shutdown - Without Control Rods 15A.6-54 Figure Deleted 15A.6-54-1 Commonality of Auxiliary Systems - DC Power Systems (125/250 Volts) 15A.6-54-2 Event Identification For Figure 15A.6-54, Page 1 of 2 SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxv 15A.6-54-3 Event Identification For Figure 15A.6-54, Page 2 of 2 15A.6-55 Figure Deleted 15A.6-55-1 Commonality of Auxiliary Systems - AC Power Systems (120/480/4160 Volts) 15A.6-55-2 Event Identification For Figure 15A.6-55, Page 1 of 2 15A.6-55-3 Event Identification For Figure 15A.6-55, Page 2 of 2 15A.6-56 Figure Deleted 15A.6-56-1 Commonality of Auxiliary Systems - Equipment Area Coding System 15A.6-56-2 Event Identification For Figure 15A.6-56 15A.6-57 Figure Deleted 15A.6-57-1 Commonality of Auxiliary Systems - Plant Service Water System 15A.6-57-2 Event Identification For Figure 15A.6-57 15A.6-58 Commonality of Auxiliary Systems - RHR Service Water System 15A.6-59 Figure Deleted 15A.6-59-1 Commonality of Auxiliary Systems - Suppression Pool Storage 15A.6-59-2 Event Identification For Figure 15A.6-59 15A.6-60 Figure Deleted 15A.6-61 Figure Deleted 15A.6-62 Figure Deleted 15A.6-63 Figure Deleted 15A.6-64 Figure Deleted 15A.6.65 Figure Deleted

15C.0-1 This Figure Has Been Deleted 15C.1.2-1-1 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-2 Susquehanna Feedwater controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-3 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-4 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-5 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.3-1-1 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15C.1.3-1-2 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.1.3-1-3 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.1.3-1-4 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.1.3-1-5 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.2.2-1-1 Susquehanna Generator Load Reject Without Bypass and Turbine Trip SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxvi Without Bypass 15C.2.2-1-2 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.2.2-1-3 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.2.2-1-4 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.2.2-1-5 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.3.3-1 Pump Seizure Accident Two Loop Operation (101/108) 15C.3.3-2 Pump Seizure Accident Single Loop Operation (76/52) 15C.4.5-1-1 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-2 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-3 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-4 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-5 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.9-1 This Figure Has Been Deleted

15D.0-1 This Figure Has Been Deleted 15D.1.2-1-1 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-2 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-3 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-4 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-5 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.3-1-1 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15D.1.3-1-2 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15D.1.3-1-3 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15D.1.3-1-4 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxvii MWt 15D.1.3-1-5 Pressure Regulator Failure - Steam Flow at 130% of Rated 15D.2.2-1-1 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-2 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-3 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-4 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-5 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.3.3-1 Pump Seizure Accident Two Loop Operation (101/108) 15D.3.3-2 Pump Seizure Accident Single Loop Operation (76/52) 15D.4.5-1-1 This Figure Has Been Deleted 15D.4.5-1-2 This Figure Has Been Deleted 15D.4.5-1-3 This Figure Has Been Deleted 15D.4.5-1-4 This Figure Has Been Deleted 15D.4.5-1-5 This Figure Has Been Deleted 15D.4.9-1 This Figure Has Been Deleted

15E.0-1 Typical Power/Flow Map 15E.0-2 Scram Position and Reactivity Characteristics 15E.2.2-1 Susquehanna Generator Load Rejection, With Bypass On 15E.2.3-1 Turbine Trip, Trip Scram, Bypass and RPT On 15E.2.4-1 Three-Second Closure of All MSIV's With Position Switch Scram Trip 15E.2.5-1 Loss of Condenser Vacuum at 2 Inches Per Second 15E.2.6-1 Loss of Auxiliary Power Transformer 15E.2.6-2 Loss of All Grid Connections 15E.2.7-1 Loss of All Feedwater Flow 15E.2.7-2 Loss of Feedwater Core Power, Heat Flux and Core Flow 15E.2.7-3 Loss of Feedwater, Feedwater Flow Steam Flow and RCIC Flow 15E.2.9-1-1 ADS/RHR Cooling Loops 15E.2.9-1-2 Notes for Figure 15E.2.9-1-1 15E.2.9-1-3 Notes for Figure 15E.2.9-1-1 15E.2.9-2 Summary of Paths Available to Achieve Cold Shutdown 15E.2.9-3 Vessel Temperature and Pressure Versus Time (Activity C1 or C2) 15E.2.9-4 Suppression Pool Temperature Versus Time (90 Service Water Temperature) Capacity C1 or C2 15E.2.9-5 Activity C1 Alternate Shutdown Cooling Path Utilizing RHR Loop B 15E.2.9-6 Activity C2 Alternate Shutdown Cooling Path Utilizing RHR Loop A SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxviii 15E.3.1-1 Trip of One Recirculation Pump Motor 15E.3.1-2 Trip of Both Recirculation Pump Motors 15E.4.4-1 Startup of Idle Recirculation Loop Pump

15E.5.1-1 Inadvertent Startup of HPCI SSES-FSARTOCRev.58FSARRev.6516-iCHAPTER16TECHNICALSPECIFICATIONSTABLEOFCONTENTSTEXTSectionTitle16.1PRELIMINARYTECHNICALSPECIFICATIONS 16.2PROPOSEDFINALTECHNICALSPECIFICATIONS 16.3TECHNICALREQUIREMENTSMANUALS SSES-FSAR TOC Rev. 65 FSAR Rev. 68 17-i CHAPTER 17 QUALITY ASSURANCE TABLE OF CONTENTS TEXT Section Title 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION

17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE

17.2.0 Introduction

17.2.1 Organization

17.2.1.1 Chief Nuclear Officer 17.2.1.2 Site Vice President 17.2.1.3 Plant Manager 17.2.1.4 General Manager-Nuclear Engineering 17.2.1.5 General Manager-Operations 17.2.1.6 Manager-Special Projects 17.2.1.7 Manager-Nuclear Oversight 17.2.1.8 Manager-Performance Improvement 17.2.1.9 Manager-Nuclear Design Engineering 17.2.1.10 Manager-Nuclear Fuels and Analysis 17.2.1.11 Manager-Nuclear Maintenance 17.2.1.12 Manager-Nuclear Operations 17.2.1.13 Manager-Nuclear Regulatory Affairs 17.2.1.14 Manager-Nuclear Security 17.2.1.15 Manager-Nuclear Training 17.2.1.16 Manager-Radiation Protection 17.2.1.17 Manager-Station Engineering 17.2.1.18 General Manager-Work Management 17.2.1.19 Manager-Plant Chemistry/Environment 17.2.1.20 PPL Electric Utilities 17.2.1.21 Talen Energy Corporation 17.2.1.22 General Manager-Programs 17.2.1.23 Manager-Engineering Programs 17.2.1.24 General Manager-Maintenance

SSES-FSAR TOC Rev. 65 CHAPTER 17 TEXT Section Title FSAR Rev. 68 17-ii 17.2.2 Quality Assurance Program

17.2.3 Design Control

17.2.4 Procurement Document Control

17.2.5 Instructions, Procedures, and Drawings

17.2.6 Document Control

17.2.7 Control of Purchased Material, Equipment, and Services

17.2.8 Identification and Control of Materials, Parts, and Components

17.2.9 Control of Special Processes

17.2.10 Inspection

17.2.11 Test Control

17.2.12 Control of Measuring and Test Equipment

17.2.13 Handling, Storage, and Shipping

17.2.14 Inspection, Test, and Operating Status

17.2.15 Nonconforming Materials, Parts, or Components

17.2.16 Corrective Action

17.2.17 Quality Assurance Records

17.2.18 Audits

SSES-FSAR TOC Rev. 65 CHAPTER 17 TABLES Number Title FSAR Rev. 68 17-iii 17.2-1 Quality Assurance Program Description Compliance Matrix

17.2-2 Operational Policy Statement Cross Reference Matrix with 10CFR50 Appendix B Criteria

SSES-FSAR TOC Rev. 65 CHAPTER 17 FIGURES Number Title FSAR Rev. 68 17-iv 17.2-1 Hierarchy of Operational Quality Assurance Documents

17.2-2 Talen Energy Corporation Management Organization Applicable to Susquehanna SES

17.2-3 Susquehanna Nuclear, LLC Management Organization

17.2-4 Nuclear Oversight Organization

SSES-FSARTOCRev.59FSARRev.6518-iCHAPTER18RESPONSESTOTMIRELATEDREQUIREMENTSTABLEOFCONTENTSTEXTSectionTitle18.0RESPONSESTOTMIRELATEDREQUIREMENTS18.1RESPONSETOREQUIREMENTSINNUREG 073718.1.1ShiftTechnicalAdvisor(I.A.1.1) 18.1.1.1StatementofRequirement18.1.1.2Interpretation18.1.1.3StatementofResponse18.1.2ShiftSupervisorResponsibilities(I.A.1.2)18.1.3ShiftManning(I.A.1.3)18.1.3.1StatementofRequirement18.1.3.2Interpretation18.1.3.3StatementofResponse18.1.4ImmediateUpgradingOfReactorOperatorandSeniorReactorOperatorTrainingandQualifications(I.A.2.1)18.1.4.1StatementofRequirement18.1.4.2Interpretation18.1.4.3StatementofResponse18.1.5AdministrationofTrainingPrograms(I.A.2.3) 18.1.5.1StatementofRequirement18.1.5.2Interpretation18.1.5.3StatementofResponse18.1.6ReviseScopeAndCriteriaforLicensingExaminations(I.A.3.1) 18.1.6.1StatementofRequirement18.1.6.2Interpretation 18.1.6.3StatementofResponse SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-ii18.1.7EvaluationOfOrganizationandManagement(I.B.1.2)18.1.7.1StatementofRequirement18.1.7.2Interpretation18.1.7.3StatementofResponse18.1.8Short-TermAccidentandProcedureReview(I.C.1) 18.1.8.1StatementofRequirement18.1.8.2Interpretation18.1.8.3StatementofResponse18.1.9ShiftReliefandTurnoverProcedures(I.C.2)18.1.10ShiftSupervisorResponsibility(I.C.3)18.1.11ControlRoomAccess(I.C.4)18.1.12FeedbackOfOperatingExperience(I.C.5)18.1.12.1StatementofRequirement18.1.12.2Interpretation18.1.12.3StatementofResponse18.1.13VerifyCorrectPerformanceofOperatingActivities(I.C.6) 18.1.13.1StatementofRequirement18.1.13.2Interpretation18.1.13.3StatementofResponse18.1.14NSSSVendorReviewofProcedures(I.C.7)18.1.15PilotMonitoringofSelectedEmergencyProceduresforNearTermOperatingLicenses(I.C.8)18.1.16ControlRoomDesignReview(I.D.1)18.1.16.1StatementofRequirement18.1.16.2Interpretation18.1.16.3StatementofResponse18.1.17PlantSafetyParameterDisplaySystem(I.D.2) 18.1.17.1StatementofRequirement SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-iii18.1.17.1.1Function18.1.17.1.2Location18.1.17.1.3Size18.1.17.1.4Staffing18.1.17.1.5DisplayConsideration18.1.17.1.6DesignCriteria18.1.17.2Interpretation18.1.17.3StatementofResponse18.1.18TrainingDuringLow-PowerTesting(I.G.1)18.1.19ReactorCoolantSystemVents(II.B.1)18.1.19.1StatementofRequirement18.1.19.2Interpretation18.1.19.3StatementofResponse18.1.20PlantShielding(II.B.2) 18.1.20.1StatementofRequirement 18.1.20.1.1DocumentationRequiredforVitalAreaAccess18.1.20.1.2DocumentationRequiredforEquipmentQualification18.1.20.2Interpretation 18.1.20.2.1SourceTerms18.1.20.2.2Post-AccidentSystems18.1.20.2.3EquipmentQualification18.1.20.3StatementofResponse 18.1.20.3.1Introduction18.1.20.3.2DesignReviewBases18.1.20.3.2.1SystemsSelectedforShieldingReview 18.1.20.3.2.1.1CoreSpray,HPCI,RCICandRHR(LPCIMode)18.1.20.3.2.1.2RHR(ShutdownCoolingMode)18.1.20.3.2.1.3RHR(SuppressionPoolCoolingMode)18.1.20.3.2.1.4RHR(ContainmentSprayMode)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-iv18.1.20.3.2.1.5CRDHydraulicSystem18.1.20.3.2.1.6RWCUSystem18.1.20.3.2.1.7LiquidRadwasteSystem18.1.20.3.2.1.8ThisSubsectionIsNotUsed18.1.20.3.2.1.9SamplingSystems18.1.20.3.2.1.10StandbyGasTreatmentSystem18.1.20.3.2.1.11ContainmentAtmosphere(Drywell)18.1.20.3.2.1.12SuppressionPool(Wetwell)18.1.20.3.2.2RadioactiveSourceReleaseFractions18.1.20.3.2.3SourceTermQuantification18.1.20.3.2.3.1DecayTime18.1.20.3.2.3.2DilutionVolume18.1.20.3.2.4System/SourceSummary18.1.20.3.2.5DoseIntegrationFactorsforPersonnel18.1.20.3.3ShieldingReviewMethodology 18.1.20.3.3.1RadiationDoseCalculationModel18.1.20.3.3.2Post-AccidentRadiationZoneMaps18.1.20.3.3.3PersonnelRadiationExposureGuidelines18.1.20.3.3.4VitalAreaIdentificationandAccess18.1.20.3.3.4.1VitalAreaClarification18.1.20.3.3.4.2VitalAreaAccess18.1.20.3.4Results 18.1.20.3.4.1PostAccidentRadiationLevels18.1.20.3.4.2IntegratedPersonnelExposures18.1.20.3.4.3ReactorBuildingAccessibility18.1.20.3.4.4ControlBuildingAccessibility18.1.21Post-AccidentSampling(II.B.3) 18.1.21.1StatementofCommitment 18.1.21.2.1Introduction18.1.21.2.1SystemDescription SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-v18.1.21.2.2SamplePoints18.1.21.2.3IsolationValvesandSampleLines18.1.21.2.4PipingStation18.1.21.3.2.4SampleStationandControlPanels 18.1.21.2.5.1GasSampler18.1.21.2.5.2LiquidSampler18.1.21.2.5.3SampleStationVentilation18.1.21.2.5.4SampleStationSump18.1.21.2.5.5SampleHandlingToolsandTransportContainers 18.1.21.2.5.6SampleStationPowerSupply18.1.21.2.6DescriptionofSamplePreparation/ChemistryandNuclearCountingFacilities18.1.21.2.7SummaryDescriptionofProcedures18.1.21.2.7.1Chemical/RadiochemicalProcedures 18.1.21.2.7.1.1Introduction18.1.21.27.2.1SamplePreparation18.1.21.2.7.2SystemTestingandOperatingTraining 18.1.22TrainingForMitigatingCoreDamage(II.B.4) 18.1.22.1StatementofRequirement18.1.22.2Interpretation18.1.22.3StatementofResponse18.1.23ReliefandSafetyValveTestRequirements(II.D.1) 18.1.23.1StatementofRequirement18.1.23.2Interpretation18.1.23.3StatementofResponse18.1.24Safety/ReliefValvePositionIndication(II.D.3)18.1.24.1StatementofRequirement18.1.24.2Interpretation18.1.24.3StatementofResponse SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-vi18.1.25AuxiliaryFeedwaterSystemEvaluation(II.E.1.1)18.1.26AuxiliaryFeedwaterSystemInitiationAndFlow(II.E.1.2)18.1.27EmergencyPowerforPressurizerHeaters(II.E.3.1)18.1.28DedicatedHydrogenPenetrations(II.E.4.1)18.1.28.1StatementofRequirement18.1.28.2Interpretation18.1.28.3StatementofResponse18.1.29ContainmentIsolationDependability(II.E.4.2) 18.1.29.1StatementofRequirement18.1.29.2Interpretation18.1.29.3StatementofResponse18.1.30Accident-MonitoringInstrumentation(II.F.1) 18.1.30.1StatementofRequirement 18.1.30.1.1NobleGasEffluentMonitor18.1.30.1.2SamplingandAnalysisofPlantEffluents18.1.30.1.3ContainmentHigh-RangeRadiationMonitor18.1.30.1.4ContainmentPressureMonitor18.1.30.1.5ContainmentWaterLevelMonitor18.1.30.1.6ContainmentHydrogenMonitor18.1.30.2Interpretation18.1.30.3StatementofResponse18.1.30.3.1NobleGasEffluentMonitor18.1.30.3.2SamplingandAnalysisofPlantEffluents18.1.30.3.3ContainmentHigh-RangeRadiationMonitor18.1.30.3.4ContainmentPressureMonitor18.1.30.3.5ContainmentWaterLevelMonitor18.1.30.3.6ContainmentHydrogenMonitor18.1.31InstrumentforDetectionofInadequateCoreCooling(II.F.2) 18.1.31.1StatementofRequirement18.1.31.2Interpretation SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-vii18.1.31.3StatementofResponse18.1.31.3.1Introduction18.1.31.3.2ReactorWaterLevelInstrumentationReport18.1.31.3.3InadequateCoreCoolingReport18.1.31.3.4Conclusion18.1.32EmergencyPowerforPressurizerEquipment(II.G.1)18.1.33ReviewESFValves(II.K.1.5)18.1.34OperabilityStatus(II.K.1.10)18.1.35TripPressurizerLow-LevelCoincidentSignalBistables(II.K.1.17) 18.1.36OperatorTrainingforPromptManualReactorTrip(II.K.1.20)18.1.37AutomaticSafetyGradeAnticipatoryReactorTrip(II.K.1.21)18.1.38AuxiliaryHeatRemovalSystemProcedures(II.K.1.22)18.1.39ReactorVesselLevelProcedures(II.K.1.23)18.1.40CommissionOrdersOnBabcockandWilcoxPlants(II.K.2)18.1.41AutomaticPower-OperatedReliefValveIsolationSystem(II.K.3.1)18.1.42ReportOnPower-OperatedReliefValveFailures(II.K.3.2)18.1.43ReportingSafety/ReliefValveFailuresandChallenges(II.K.3.3)18.1.44AutomaticTripofReactorCoolantPumpsDuringALOCA(II.K.3.5)18.1.45EvaluationofPower-OperatedReliefValveOpeningProbability(II.K.3.7)18.1.46ProportionalIntegralDerivativeControllerModification(II.K.3.9)18.1.47ProposedAnticipatoryTripModification(II.K.3.10)18.1.48Power-OperatedReliefValveFailureRate(II.K.3.11)18.1.49AnticipatoryReactorTriponTurbineTrip(II.K.3.12)18.1.50SeparationOfHighPressureCoolantInjectionandReactorCoreIsolationCoolingSystemInitiationLevels(II.K.3.13)18.1.50.1StatementofRequirement18.1.50.2Interpretation18.1.50.3StatementofResponse18.1.51ModifyBreak-DetectionLogictoPreventSpuriousIsolationofHighPressureCoolantInjectionandReactorCoreIsolationCooling(II.K.3.15)18.1.51.1StatementofRequirement18.1.51.2Interpretation18.1.51.3StatementofResponse18.1.52ReductionofChallengesandFailuresofReliefValves(II.K.3.16)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-viii18.1.52.1StatementofRequirement18.1.52.2Interpretation18.1.52.3StatementofResponse18.1.53ReportOnOutagesOfEmergencyCoreCoolingSystems(II.K.3.17)18.1.53.1StatementofRequirement18.1.53.2Interpretation18.1.53.3StatementofResponse18.1.54ModificationofAutomaticDepressurizationSystemLogic(II.K.3.18) 18.1.54.1StatementofRequirement18.1.54.2Interpretation18.1.54.3StatementofResponse18.1.55RestartofCoreSprayAndLowPressureCoolantInjectionSystems(II.K.3.21)18.1.55.1StatementofRequirement18.1.55.2Interpretation18.1.55.3StatementofResponse18.1.56AutomaticSwitchoverofReactorCoreIsolationCoolingSystemSuction(II.K.3.22)18.1.56.1StatementofRequirement18.1.56.2Interpretation18.1.56.3StatementofResponse18.1.57ConfirmAdequacyofSpaceCoolingForHighPressureCoolantInjectionandReactorCoreIsolationCoolingSystems(II.K.3.24)18.1.57.1StatementofRequirement18.1.57.2Interpretation18.1.57.3StatementofResponse18.1.58EffectofLossofAlternating-CurrentPoweronRecirculationPumpSeals(II.K.3.25)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-ix18.1.58.1StatementofRequirement18.1.58.2Interpretation18.1.58.3StatementofResponse18.1.59ProvideACommonReferenceLevelforVesselLevelInstrumentation(II.K.3.27)18.1.59.1StatementofRequirement18.1.59.2Interpretation18.1.59.3StatementofResponse18.1.60VerifyQualificationofAccumulatorsonAutomaticDepressurizationSystemValves(II.K.3.28)18.1.60.1StatementofRequirement18.1.60.2Interpretation18.1.60.3StatementofResponse18.1.61RevisedSmall-BreakLossofCoolantAccidentMethods(II.K.3.30) 18.1.61.1StatementofRequirement18.1.61.2Interpretation18.1.61.3StatementofResponse18.1.62Plant-SpecificCalculationsToShowCompliancewith10CFRPart50.46(II.K.3.31)18.1.62.1StatementofRequirement18.1.62.2Interpretation18.1.62.3StatementofResponse18.1.63EvaluationofAnticipatedTransientswithSingleFailureToVerifyNoFuelCladdingFailure(II.K.3.44)18.1.63.1StatementofRequirement18.1.63.2Interpretation18.1.63.3StatementofResponse18.1.64EvaluationofDepressurizationWithOtherThanTheAutomaticDepressurizationSystem(II.K.3.45)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-x18.1.64.1StatementofRequirement18.1.64.2Interpretation18.1.64.3StatementofResponse18.1.65MichelsenConcerns(II.K.3.46) 18.1.65.1StatementofRequirement18.1.65.2Interpretation18.1.65.3StatementofResponse18.1.66EmergencyPreparedness-ShortTerm(III.A.1.1)18.1.67UpgradeEmergencySupportFacilities(III.A.1.2)18.1.67.1StatementofRequirement18.1.67.2Interpretation18.1.67.3StatementofResponse18.1.68EmergencyPreparedness-LongTerm(III.A.2) 18.1.68.1StatementofRequirement18.1.68.2Interpretation18.1.68.3StatementofResponse18.1.69IntegrityOfSystemsOutsideContainmentLikelyToContainRadioactiveMaterial(III.D.1.1)18.1.69.1StatementofRequirement18.1.69.2Interpretation18.1.69.3StatementofResponse18.1.70InplantIodineRadiationMonitoring(III.D.3.3)18.1.70.1StatementofRequirement18.1.70.2Interpretation18.1.70.3StatementofResponse18.1.71ControlRoomHabitabilityRequirements(III.D.3.4) 18.1.71.1StatementofRequirement SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xi18.1.71.1.1RequirementsforLicenseesthatMeetCriteria18.1.71.1.2RequirementsforLicenseesthatDoNotMeetCriteria18.1.71.1.3DocumentationandImplementation18.1.71.2Interpretation18.1.71.3StatementofResponse18.1.72References 18.2RESPONSETOREQUIREMENTSINNUREG069418.2.1ShiftTechnicalAdvisor(I.A.1.1)18.2.2ShiftSupervisorAdministrativeDuties(I.A.1.2)18.2.2.1StatementofRequirement18.2.2.2Interpretation18.2.2.3StatementofResponse18.2.3ShiftManning(I.A.1.3)18.2.4ImmediateUpgradingOfOperatorAndSeniorOperatorTrainingAndQualification(I.A.2.1)18.2.5ReviseScopeAndCriteriaForLicensingExaminations(I.A.3.1)18.2.6EvaluationOfOrganizationAndManagementImprovementsOfNear-TermOperatingLicenseApplicants(I.B.1.2)18.2.6.1StatementofRequirement18.2.6.2Interpretation18.2.6.3StatementofResponse18.2.7Short-TermAccidentAnalysisAndProcedureRevision(I.C.1)18.2.8ShiftReliefAndTurnoverProcedures(I.C.2)18.2.8.1StatementofRequirement18.2.8.2Interpretation18.2.8.3StatementofResponse18.2.9ShiftSupervisorResponsibilities(I.C.3) 18.2.9.1StatementofRequirement18.2.9.2Interpretation18.2.9.3StatementofResponse SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xii18.2.10ControlRoomAccess(I.C.4)18.2.10.1StatementofRequirement18.2.10.2Interpretation18.2.10.3StatementofResponse18.2.11ProceduresForFeedbackOfOperatingExperienceToPlantStaff (I.C.5)18.2.12NSSSVendorReviewOfProcedures(I.C.7)18.2.12.1StatementofRequirement18.2.12.2Interpretation18.2.12.3StatementofResponse18.2.13PilotMonitoringOfSelectedEmergencyProceduresNear-TermOperatingLicenseApplicants(I.C.8)18.2.13.1StatementofRequirement18.2.13.2Interpretation18.2.13.3StatementofResponse18.2.14ControlRoomDesign(I.D.1)18.2.15TrainingDuringLowPowerTesting(I.G.1)18.2.15.1StatementofRequirement18.2.15.2Interpretation18.2.15.3StatementofResponse18.2.16ReactorCoolantSystemVents(II.B.1)18.2.17PlantShielding(II.B.2)18.2.18Post-AccidentSampling(II.B.3)18.2.19TrainingForMitigatingCoreDamage(II.B.4)18.2.20ReliefAndSafetyValveTestRequirements(II.D.1)18.2.21ReliefAndSafetyValvePositionIndication(II.D.3)18.2.22ContainmentIsolationDependability(II.E.4.2)18.2.23AdditionalAccidentMonitoringInstrumentation(II.F.1)18.2.24InadequateCoreCoolingInstruments(II.F.2)18.2.25AssuranceOfProperESFFunctioning(II.K.1.5)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xiii18.2.25.1StatementofRequirement18.2.25.2Interpretation18.2.25.3StatementofResponse18.2.26SafetyRelatedSystemOperabilityStatus(II.K.1.10) 18.2.26.1StatementofRequirement18.2.26.2Interpretation18.2.26.3StatementofResponse18.2.27TripPressurizerLow-LevelCoincidentSignalBistables(II.K.1.17)18.2.28OperatorTrainingForPromptManualReactorTrip(II.K.1.20)18.2.29AutomaticSafetyGradeAnticipatoryTrip(II.K.1.21)18.2.30AuxiliaryHeatRemovalSystemsOperatingProcedures(II.K.1.22)18.2.30.1StatementofRequirement18.2.30.2Interpretation18.2.30.3StatementofResponse18.2.31ReactorLevelInstrumentation(II.K.1.23) 18.2.31.1StatementofRequirement18.2.31.2Interpretation18.2.31.3StatementofResponse18.2.32CommissionOrdersOnBabcockAndWilcoxPlants(II.K.2)18.2.33ReportingRequirementsForSafety/ReliefValveFailuresOrChallenges(II.K.3.3)18.2.33.1StatementofRequirement18.2.33.2Interpretation18.2.33.3StatementofResponse18.2.34ProportionalIntegralDerivativeController(II.K.3.9)18.2.35AnticipatoryReactorTripModification(II.K.3.10)18.2.36PowerOperatedReliefValveFailureRate(II.K.3.11)18.2.37AnticipatoryReactorTriponTurbineTrip(II.K.3.12)18.2.38EmergencyPreparedness-ShortTerm(II.A.1.1)18.2.38.1StatementofRequirement18.2.38.2Interpretation SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xiv18.2.38.3StatementofResponse18.2.39UpgradeEmergencySupportFacilities(III.A.1.2)18.2.40PrimaryCoolantSourcesOutsideContainment(III.D.1.1)18.2.41InplantRadiationMonitoring(III.D.3.3)18.2.42ControlRoomHabitability(III.D.3.4)

SSES-FSARTOCRev.59CHAPTER18TABLESNumberTitleFSARRev.6518-xv18.1-1InterimRequiredShiftStaffing18.1-2InitialCoreIsotopicInventory 18.1-3PostAccidentRadiationZoneClassification 18.1-4VitalAreas 18.1-5PrincipalDoseRateContributorsinPlantArea 18.1-6ThisTableHasBeenDeleted 18.1-7ThisTableHasBeenDeleted 18.1-8TrainingCriteriaforMitigatingCoreDamage 18.1-9MitigatingCoreDamageCourseOutline 18.1-10ContainmentIsolationActuationProvision 18.1-11ThisTableHasBeenDeleted 18.1-12Actuation/IsolationSignalCodesandCorrespondingActuatingSwitches18.1-13MeteorologicalInformation 18.1-14ThisTableHasBeenDeleted 18.1-15ThisTableHasBeenDeleted 18.1-16ThisTableHasBeenDeleted 18.1-17InformationRequiredforControlRoomHabitabilityEvaluation 18.1-18PossibleICCDetectionDevices 18.2-1TestingProgramOutline SSES-FSARTOCRev.59CHAPTER18FIGURESNumberTitleFSARRev.6518-xvi18.1-1RadiationLevelsfortheSitePlan18.1-2RadiationLevelsfortheSitePlanElevations646'-0,"645'0,"and656'-0"18.1-3RadiationLevelsforElevations670'-0"and676'-0" 18.1-4RadiationLevelsforElevations683'-0,"699'-0,"714'-0,"and716'-3"18.1-5RadiationLevelsforElevations719'-1,"729'-0,"and741'-1"18.1-6RadiationLevelsforElevations749'-1,"754'-0,"762'-0,"771'-0,"and783'-0"18.1-7RadiationLevelsforElevations779'-1,"799'-1,"and806'-0" 18.1-8RadiationLevelsforElevations818'-1"and872'-41/2" 18.1-9ThisFigureHasBeenDeleted 18.1-10ThisFigureHasBeenDeleted 18.1-11ThisFigureHasBeenDeleted 18.1-12TypicalHPCIRCICSteamlineBreakDetectionLogic 18.1-13TypicalReactorWaterLevelDisplay 18.1-14DowncomerWaterLevelHistory 18.1-15WaterLevelasanIndicatorofCoreOverheating 18.1-16CladdingTemperatureSensitivitytoCoreRecoveryTime

SSES-FSARNIMSRev.60FSARRev.651-iCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANTTABLEOFCONTENTSTEXTSectionTitle1.1Introduction 1.1.1TypeofLicense1.1.2IdentificationofApplicant1.1.3NumberofPlantUnits1.1.4DescriptionofLocation1.1.5TypeofNuclearSteamSupply1.1.6TypeofContainment1.1.7CoreThermalPowerLevels1.1.8ScheduledFuelLoadandOperationData1.1.9FSAROrganization1.2GENERALPLANTDESCRIPTION 1.2.1PrincipalDesignCriteria 1.2.1.1GeneralDesignCriteria1.2.1.2SystemDesignCriteria1.2.1.2.1NuclearSystemCriteria1.2.1.2.2SafetyRelatedSystemsCriteria1.2.1.2.2.1General1.2.1.2.2.2ContainmentandIsolationCriteria1.2.1.2.2.3EmergencyCoreCoolingSystem(ECCS)Criteria1.2.1.2.3ProcessControlSystemsCriteria1.2.1.2.3.1NuclearSystemProcessControlCriteria1.2.1.2.3.2PowerConversionSystemsProcessControlCriteria1.2.1.2.3.3ElectricalPowerSystemProcessControlCriteria1.2.1.2.4ElectricalPowerSystemCriteria1.2.1.2.5FuelHandlingandStorageFacilities1.2.1.2.6AuxiliarySystemsCriteria1.2.1.2.7PowerConversionSystemsCriteria1.2.1.2.8RadioactiveWasteDisposalCriteria1.2.1.2.9ShieldingandAccessControlCriteria1.2.2PlantDescription SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-ii1.2.2.1SiteCharacteristics1.2.2.1.1LocationandSize1.2.2.1.2RoadandRailAccess1.2.2.1.3DescriptionofPlantEnvirons1.2.2.1.3.1GeologyandSoils1.2.2.1.3.2Groundwater1.2.2.1.3.3Hydrology1.2.2.1.3.4Meteorology1.2.2.1.3.5Seismicity1.2.2.2GeneralArrangementofStructuresandEquipment1.2.2.3NuclearSystem1.2.2.3.1ReactorCoreandControlRods1.2.2.3.2ReactorVesselandInternals1.2.2.3.3ReactorRecirculationSystem1.2.2.3.4ResidualHeatRemovalSystem1.2.2.3.5ReactorWaterCleanupSystem(RWCU)1.2.2.4SafetyRelatedSystems1.2.2.4.1ReactorProtectionSystem1.2.2.4.2NeutronMonitoringSystem1.2.2.4.3ControlRodDriveSystem1.2.2.4.4NuclearSystemPressureReliefSystem1.2.2.4.5ReactorCoreIsolationCoolingSystem1.2.2.4.6PrimaryContainment1.2.2.4.7PrimaryContainmentandReactorVesselIsolationControlSystem1.2.2.4.8SecondaryContainment1.2.2.4.9MainSteamlineIsolationValves1.2.2.4.10MainSteamlineFlowRestrictors1.2.2.4.11EmergencyCoreCoolingSystems(ECCS)1.2.2.4.12ResidualHeatRemovalSystem(ContainmentCooling)1.2.2.4.13ControlRodVelocityLimiter1.2.2.4.14ControlRodDriveHousingSupports1.2.2.4.15ReactorBuildingRecirculationandStandbyGasTreatmentSystems1.2.2.4.16StandbyacPowerSupply1.2.2.4.17dcPowerSupply1.2.2.4.18ResidualHeatRemovalServiceWaterSystem1.2.2.4.19EmergencyServiceWaterSystem1.2.2.4.20MainSteamlineRadiationMonitoringSystem1.2.2.4.21ReactorBuildingVentilationRadiationMonitoringSystem1.2.2.4.22NuclearLeakDetectionSystem1.2.2.5InstrumentationandControl1.2.2.5.1NuclearSystemProcessControlandInstrumentation SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-iii1.2.2.5.1.1ReactorManualControlSystem1.2.2.5.1.2RecirculationFlowControlSystem1.2.2.5.1.3NeutronMonitoringSystem1.2.2.5.1.4RefuelingInterlocks1.2.2.5.1.5ReactorVesselInstrumentation1.2.2.5.1.6ProcessComputerSystem1.2.2.5.1.7RemoteShutdownSystem1.2.2.5.2PowerConversionSystemsProcessControlandInstrumentation1.2.2.5.2.1PressureRegulatorandTurbineControl1.2.2.5.2.2FeedwaterSystemControl1.2.2.5.2.3ElectricalPowerSystemControl1.2.2.6ElectricalSystems1.2.2.6.1TransmissionandGenerationSystems1.2.2.6.2ElectricalPowerDistributionSystems1.2.2.7FuelHandlingandStorageSystems1.2.2.7.1NewandSpentFuelStorage1.2.2.7.2FuelPoolCoolingandCleanupSystem1.2.2.7.3FuelHandlingEquipment1.2.2.8CoolingWaterandAuxiliarySystems1.2.2.8.1ServiceWaterSystem1.2.2.8.2ResidualHeatRemovalServiceWaterSystem(RHRSWS)1.2.2.8.3EmergencyServiceWaterSystem(ESWS)1.2.2.8.4ReactorBuildingClosedCoolingWaterSystem1.2.2.8.5TurbineBuildingClosedCoolingWaterSystem(TBCCWS)1.2.2.8.6StandbyLiquidControlSystem1.2.2.8.7FireProtectionSystem1.2.2.8.8PlantHeating,Ventilating,andAir-ConditioningSystems1.2.2.8.9CompressedAirSystem1.2.2.8.10MakeupWaterTreatmentSystem1.2.2.8.11DomesticandSanitaryWaterSystems1.2.2.8.12PlantEquipmentandFloorDrainageSystems1.2.2.8.13ProcessSamplingSystem1.2.2.8.14PlantCommunicationSystem1.2.2.8.15ProcessValveStemLeakoffSystem1.2.2.8.16DieselAuxiliarySystems1.2.2.8.17AuxiliarySteamSystem1.2.2.9PowerConversionSystem1.2.2.9.1Turbine-Generator1.2.2.9.2MainSteamSystem1.2.2.9.3MainCondenser1.2.2.9.4MainCondenserGasRemovalSystem SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-iv1.2.2.9.5SteamSealSystem1.2.2.9.6SteamBypassandPressureControlSystem1.2.2.9.7CirculatingWaterSystem1.2.2.9.8CondensateCleanupSystem1.2.2.9.9CondensateandFeedwaterSystem1.2.2.9.10CondensateandRefuelingWaterStorageandTransferSystem1.2.2.10RadioactiveWasteSystems1.2.2.10.1LiquidRadwasteSystem1.2.2.10.2SolidRadwasteSystem1.2.2.10.3GaseousRadwasteSystem1.2.2.11RadiationMonitoringandControl1.2.2.11.1ProcessRadiationMonitoring1.2.2.11.2AreaRadiationMonitors1.2.2.11.3SiteEnvironsRadiationMonitors1.2.2.11.4LiquidRadwasteSystemControl1.2.2.11.5SolidRadwasteControl1.2.2.11.6GaseousRadwasteSystemControl1.2.2.12Shielding1.2.2.13SteamDryerStorage1.3COMPARISONTABLES 1.3.1ComparisonWithSimilarFacilityDesigns 1.3.1.1NuclearSteamSupplySystemDesignCharacteristics1.3.1.2PowerConversionSystemDesignCharacteristics1.3.1.3EngineeredSafetyFeaturesDesignCharacteristics1.3.1.4ContainmentDesignCharacteristics1.3.1.5RadioactiveWasteManagementSystemsDesignCharacteristics1.3.1.6StructuralDesignCharacteristics1.3.1.7InstrumentationandElectricalSystemsDesignCharacteristics1.3.2ComparisonofFinalandPreliminaryInformation 1.4IDENTIFICATIONOFAGENTSANDCONTRACTORS 1.4.1PennsylvaniaPower&LightCompany(Applicant)1.4.2ArchitectEngineer1.4.3NuclearSteamSupplySystem1.4.4Turbine-GeneratorVendor1.4.5OtherConsultants SSES-FSARNIMSRev.60CHAPTER1TEXTSectionTitleFSARRev.651-v1.5REQUIREMENTSFORFURTHERTECHNICALINFORMATION1.5.1DevelopmentofBWRTechnology 1.5.1.1CurrentDevelopmentPrograms1.5.1.1.1CoreSprayDistribution1.5.1.1.2CoreSprayandCoreFloodingHeatTransferEffectiveness1.5.1.1.3VerificationofPressureSuppressionDesign1.5.1.1.4CriticalHeatFluxTesting1.5.1.1.5FuelAssemblyStructuralTesting1.5.2ProgramsConductedDuringOperationsPhase 1.6MATERIALINCORPORATEDBYREFERENCE 1.6.1GeneralElectricTopicalReports1.6.2BechtelTopicalReports1.6.3OtherTopicalReports1.7ELECTRICAL,INSTRUMENTATION,ANDCONTROLDRAWINGS 1.8SYMBOLSANDTERMSUSEDINENGINEERINGANDTEXT 1.8.1TextDefinitionsandAbbreviations1.8.2DrawingIndexandSymbols1.8.3PipingIdentification1.8.4ValveIdentification1.8.5InstrumentIdentification1.8.5.1InstrumentComponents1.8.5.2InstrumentLocation1.8.6ElectricalComponentIdentification 1.8.6.1EquipmentLocationNumbers1.8.6.2SchemeNumbers1.8.6.3SchemeCableNumbers1.8.6.4RacewayNumbers SSES-FSARNIMSRev.60CHAPTER1TABLESNumberTitleFSARRev.651-vi1.3-1ComparisonofNuclearSteamSupplySystemDesignCharacteristics1.3-2ComparisonofPowerConversionSystemDesignCharacteristics 1.3-3ComparisonofEngineeredSafetyFeaturesDesignCharacteristics 1.3-4ComparisonofContainmentDesignCharacteristics 1.3-5RadioactiveWasteManagementSystemsDesignCharacteristics 1.3-6ComparisonofStructuralDesignCharacteristics 1.3-7ComparisonofElectricalPowerSystemsDesignCharacteristics 1.3-8SignificantDesignChangesfromPSARtoFSAR 1.4-1CommercialNuclearReactorsCompleted,UnderConstruction,orinDesignByGeneralElectric1.6-1GeneralElectricTopicalReports 1.6-2BechtelTopicalReports 1.6-3ThisTableHasBeenDeleted 1.6-4OtherTopicalReports 1.7-1ElectricalDrawings 1.8-1SSES-ProjectGlossaryTerms 1.8-2Acronyms 1.8-3TechnicalAbbreviations 1.8-4ThisTableHasBeenIntentionallyLeftBlank 1.8-5DrawingAbbreviations 1.8-6PipingandValveClassIdentification SSES-FSARNIMSRev.60CHAPTER1FIGURESNumberTitleFSARRev.651-vii1.2-1ThisFigurehasbeenReplacedbyDwg.M-220,Sh.11.2-2ThisFigurehasbeenReplacedbyDwg.M-221,Sh.11.2-3ThisFigurehasbeenReplacedbyDwg.M-222,Sh.11.2-4ThisFigurehasbeenReplacedbyDwg.M-223,Sh.1 1.2-5ThisFigurehasbeenReplacedbyDwg.M-224,Sh.11.2-6ThisFigurehasbeenReplacedbyDwg.M-225,Sh.11.2-7ThisFigurehasbeenReplacedbyDwg.M-226,Sh.11.2-8ThisFigurehasbeenReplacedbyDwg.M-227,Sh.11.2-9ThisFigurehasbeenReplacedbyDwg.M-230,Sh.1 1.2-10ThisFigurehasbeenReplacedbyDwg.M-231,Sh.11.2-11ThisFigurehasbeenReplacedbyDwg.M-232,Sh.11.2-12ThisFigurehasbeenReplacedbyDwg.M-233,Sh.11.2-13ThisFigurehasbeenReplacedbyDwg.M-234,Sh.11.2-14ThisFigurehasbeenReplacedbyDwg.M-235,Sh.11.2-15ThisFigurehasbeenReplacedbyDwg.M-236,Sh.11.2-16ThisFigurehasbeenReplacedbyDwg.M-237,Sh.1 1.2-17ThisFigurehasbeenReplacedbyDwg.M-240,Sh.11.2-18ThisFigurehasbeenReplacedbyDwg.M-241,Sh.11.2-19ThisFigurehasbeenReplacedbyDwg.M-242,Sh.11.2-20ThisFigurehasbeenReplacedbyDwg.M-243,Sh.11.2-21ThisFigurehasbeenReplacedbyDwg.M-244,Sh.1 1.2-22ThisFigurehasbeenReplacedbyDwg.M-245,Sh.11.2-23ThisFigurehasbeenReplacedbyDwg.M-246,Sh.1 SSES-FSARNIMSRev.60CHAPTER1FIGURESNumberTitleFSARRev.651-viii1.2-24ThisFigurehasbeenReplacedbyDwg.M-247,Sh.11.2-25ThisFigurehasbeenReplacedbyDwg.M-248,Sh.11.2-26ThisFigurehasbeenReplacedbyDwg.M-249,Sh.11.2-27ThisFigurehasbeenReplacedbyDwg.M-250,Sh.1 1.2-28ThisFigurehasbeenReplacedbyDwg.M-251,Sh.11.2-29ThisFigurehasbeenReplacedbyDwg.M-252,Sh.11.2-30ThisFigurehasbeenReplacedbyDwg.M-253,Sh.11.2-31ThisFigurehasbeenReplacedbyDwg.M-254,Sh.11.2-32ThisFigurehasbeenReplacedbyDwg.M-255,Sh.1 1.2-33ThisFigurehasbeenReplacedbyDwg.M-256,Sh.11.2-34ThisFigurehasbeenReplacedbyDwg.M-257,Sh.11.2-35ThisFigurehasbeenReplacedbyDwg.M-258,Sh.11.2-36ThisFigurehasbeenReplacedbyDwg.M-259,Sh.11.2-37ThisFigurehasbeenReplacedbyDwg.M-260,Sh.1 1.2-38ThisFigurehasbeenReplacedbyDwg.M-261,Sh.11.2-39ThisFigurehasbeenReplacedbyDwg.M-270,Sh.11.2-40ThisFigurehasbeenReplacedbyDwg.M-271,Sh.11.2-41ThisFigurehasbeenReplacedbyDwg.M-272,Sh.11.2-42ThisFigurehasbeenReplacedbyDwg.M-273,Sh.11.2-43ThisFigurehasbeenReplacedbyDwg.M-274,Sh.1 1.2-44ThisFigurehasbeenReplacedbyDwg.M-276,Sh.11.2-45ThisFigurehasbeenReplacedbyDwg.M-280,Sh.1 SSES-FSARNIMSRev.60CHAPTER1FIGURESNumberTitleFSARRev.651-ix1.2-46ThisFigurehasbeenReplacedbyDwg.M-281,Sh.11.2-47ThisFigurehasbeenReplacedbyDwg.M-282,Sh.11.2-48ThisFigurehasbeenReplacedbyDwg.M-284,Sh.11.2-49Unit1-HeatBalanceatRatedPowerwith100x10 6LBm/hrCoreFlow1.2-49-1Unit1-HeatBalanceatRatedPowerwith108x10 6LBm/hrIncreasedCoreFlow1.2-49-2Unit2-HeatBalanceatRatedPowerwith100x10 6LBm/hrCoreFlow1.2-49-3Unit2-HeatBalanceatRatedPowerwith108x10 6LBm/hrIncreasedCoreFlow1.2-50DieselGenerator'E'BuildingGeneralArrangementPlans1.2-51DieselGenerator'E'BuildingGeneralArrangementSectionsSh.21.2-52ThisFigurehasbeenDeleted 1.8-1PipingandInstrumentSymbols1.8-2aP&ID&HVACControlDiagramsLegend&Symbols1.8-2bP&ID&HVACControlDiagramsLegend&Symbols1.8-2cP&IDLegendandSymbols1.8-2dP&IDLegend&Symbols 1.8-3LogicSymbols1.8-4InstrumentSymbol SSES-FSARNIMSRev.60FSARRev.652-iCHAPTER2SITECHARACTERISTICSTABLEOFCONTENTSTEXTSectionTitle2.1GEOGRAPHYANDDEMOGRAPHY 2.1.1SiteLocationandDescription 2.1.1.1SpecificationofLocation2.1.1.2SiteAreaMap2.1.1.3BoundariesforEstablishingEffluentReleaseLimits2.1.2ExclusionAreaAuthorityandControl 2.1.2.1Authority2.1.2.2ControlofActivitiesUnrelatedtoPlantOperation2.1.2.3ArrangementforTrafficControl2.1.2.4AbandonmentorRelocationofRoads2.1.3PopulationDistribution 2.1.3.1PopulationWithin10Miles2.1.3.2PopulationBetween10and50Miles2.1.3.3TransientPopulationBetween0and50Miles2.1.3.3.1SeasonalPopulationBetween0to50Miles2.1.3.3.2DailyTransientPopulation2.1.3.3.3LowPopulationZone2.1.3.4PopulationCenter2.1.3.5PopulationDensity2.1.3.6Thissectionhasbeendeleted2.1.4References 2.2NEARBYINDUSTRIAL,TRANSPORTATION,ANDMILITARYFACILITIES2.2.1LocationsandRoutes 2.2.2Descriptions SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-ii2.2.2.1DescriptionofFacilities2.2.2.2DescriptionsofProductsandMaterials2.2.2.3Pipelines2.2.2.4Waterways2.2.2.5Airports2.2.2.6ProjectionsofIndustrialGrowth2.2.3EvaluationofPotentialAccidents 2.2.3.1DeterminationofDesignBasisEvents2.2.3.1.1Explosions2.2.3.1.1.1HydrogenWaterChemistryStorageTankFarm2.2.3.1.2FlammableVapors2.2.3.1.2.1Twelve-InchNaturalGasPipeline2.2.3.1.2.2Twenty-FourInchGasPipeline2.2.3.1.2.3Thirty-SixInchNaturalGasPipeline2.2.3.1.2.4PropaneCarriers2.2.3.1.2.5SixteenInchNaturalGasPipeline2.2.3.1.3ExposuretoHazardousChemicalReleases2.2.3.1.4Fires2.2.3.1.5CollisionswithIntakeStructure2.2.3.1.6LiquidSpills2.2.3.1.7SubsurfaceGasandWasteStorage2.2.3.2EffectsofDesignBasisEvents2.2.4References 2.3METEOROLOGY 2.3.1RegionalClimatology 2.3.1.1GeneralClimate2.3.1.2RegionalMeteorologicalConditionsforDesignandOperatingBases2.3.1.2.1Hurricanes2.3.1.2.2Tornadoes2.3.1.2.3Thunderstorms2.3.1.2.4Lightning2.3.1.2.5Hail2.3.1.2.6ExtremeWinds2.3.1.2.7FreezingRain2.3.1.2.8Duststorms SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-iii2.3.1.2.9HighAirPollutionPotential2.3.1.2.10Snowpacks2.3.1.2.11DesignBasisTornado2.3.1.2.12UltimateHeatSink2.3.2LocalMeteorology 2.3.2.1NormalandExtremeValuesofMeteorologicalParameters2.3.2.1.1Wind2.3.2.1.2TemperatureandAtmosphericWaterVapor2.3.2.1.3Precipitation2.3.2.1.4FogandSmog2.3.2.1.5Stability2.3.2.2PotentialInfluenceofthePlantanditsFacilitiesonLocalMeteorology2.3.2.3LocalMeteorologicalConditionsforDesignandOperatingBases2.3.3On-SiteMeteorologicalMeasurementsProgram 2.3.3.1LocationandDescriptionoftheTowerSite2.3.3.2TypesofMeasurementsMade2.3.3.3DescriptionofInstruments2.3.3.4DataRecordingSystems2.3.3.5CalibrationandMaintenanceoftheSystem2.3.3.6DataAnalysis2.3.4Short-Term(Accident)DiffusionEstimates 2.3.4.1Short-Term(0-2hours)Releases2.3.4.1.1Direction-IndependentCalculations2.3.4.1.2Direction-DependentCalculations2.3.4.1.3DeterminingAppropriateShort-TermDispersion2.3.4.2LongTermReleases2.3.4.3AnalyticalMethodsforDispersionComputations2.3.5LongTerm(Routine)DiffusionEstimates 2.3.5.1AtmosphericDiffusionModels2.3.5.1.1Straight-LineAirflowModel2.3.5.1.2Terrain/RecirculationConnectionFactors2.3.5.1.3DepositionandDepleted/qs2.3.5.1.4ResultsofLong-TermDiffusionEstimates SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-iv2.3.6References2.4HYDROLOGICENGINEERING2.4.1HydrologicDescription2.4.1.1SiteandFacilities2.4.1.2Hydrosphere2.4.1.2.1RiversandStreams2.4.1.2.2DamsandReservoirs2.4.1.2.3DownstreamWaterUses2.4.2Floods 2.4.2.1FloodHistory2.4.2.1.1FloodRecords2.4.2.1.2TropicalStormAgnes2.4.2.1.3FloodResultingFromIceJams2.4.2.2FloodDesignConsiderations2.4.2.3EffectsofLocalIntensePrecipitation2.4.3ProbableMaximumFlood(PMF)onStreamsandRivers 2.4.3.1ProbableMaximumPrecipitation2.4.3.2PrecipitationLosses2.4.3.3RunoffandStreamCourseModels2.4.3.4ProbableMaximumFloodFlow2.4.3.5WaterLevelDetermination2.4.3.5.1HydraulicCharacteristicsofChannelandOverbank2.4.3.5.2BackwaterCurveCalculations2.4.3.6CoincidentWindWaveActivity 2.4.4PotentialDamFailuresSeismicallyInduced 2.4.4.1DamFailurePermutations2.4.4.2UnsteadyFlowAnalysisofPotentialDamFailures2.4.4.2.1SingularDamFailures2.4.4.2.2MultipleDamFailures-ChemungRiverBasin2.4.4.2.3MultipleDamFailures-EastSusquehannaRiverBasin2.4.4.2.4MultipleDamFailures-LackawannaRiverBasin2.4.4.3WaterLevelatPlantSite SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-v2.4.5ProbableMaximumSurgeandSeicheFlooding2.4.6ProbableMaximumTsunamiFlooding2.4.7IceEffects2.4.8CoolingWaterCanalsandReservoirs 2.4.8.1General2.4.8.2GeneralDescriptionoftheSprayPondSystem2.4.8.3DesignBasesfortheCapacityofSprayPond2.4.8.4HydrologicDesignBasesfortheSprayPondSystem2.4.8.4.1DesignBasisFloodLevel(DBFL)2.4.8.4.2SafeShutdownandOperatingBasisEarthquakes2.4.9ChannelDiversions 2.4.10FloodingProtectionRequirements 2.4.11LowWaterConsiderations 2.4.11.1LowFlowinRiversandStreams2.4.11.1.1LowFlowResultingFromHydrometeorologicalEvents2.4.11.1.2LowFlowResultingfromDamFailures2.4.11.2LowWaterResultingfromSurges,Seiches,orTsunami2.4.11.3HistoricalLowWater2.4.11.4FutureControls2.4.11.4.1LegalConsumptiveUseRestrictions2.4.11.4.2ChangesinConsumptiveUseUpstream2.4.11.5PlantRequirements2.4.11.6HeatSinkDependabilityRequirements2.4.12DispersionDilutionandTravelTimeofAccidentalReleasesofLiquidEffluentsinSurfaceWaters2.4.12.1RiverFlowCharacteristics2.4.12.1.1FlowDuration2.4.12.1.2ExtremeLowFlow2.4.12.1.3TravelTimes2.4.12.2AccidentalReleases2.4.12.3EffluentDilution SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-vi2.4.13Groundwater2.4.13.1DescriptionandOnsiteUse2.4.13.1.1RegionalGroundwaterConditions2.4.13.1.1.1PrimaryAquifersoftheRegionPleistocene-AgeDeposits2.4.13.1.1.2SecondaryAquifersoftheRegionLlewellynFormation2.4.13.1.2LocalGroundwaterConditions2.4.13.1.3OnsiteUseofGroundwater2.4.13.2Sources2.4.13.2.1WaterWellInventory2.4.13.2.2GroundwaterWithdrawal2.4.13.2.3AquiferCharacteristicsandGroundwaterConditionsattheSite2.4.13.2.3.1DataSources2.4.13.2.3.2GroundwaterParametersandMovementattheSite2.4.13.3AccidentsEffects2.4.13.3.1PostulatedAccidentandPotentialFlowPaths2.4.13.3.2DescriptionoftheModelsUsed2.4.13.3.3SelectionofParametersforSLUG3DSimulations2.4.13.3.4NumericalModelSimulationofBuried-ValleyAquifer2.4.13.3.5DiscussionofResultsofAnalysis2.4.13.4DesignBasesforSubsurfaceHydrostaticLoadings2.4.14TechnicalSpecificationandEmergencyOperationRequirements 2.4.15References 2.5GEOLOGY,SEISMOLOGY,ANDGEOTECHNICALENGINEERING 2.5.1BasicGeologicandSeismicInformation 2.5.1.1RegionalGeology2.5.1.1.1PhysiographyandGeomorphology2.5.1.1.2StratigraphyandLithology2.5.1.1.2.1TheAppalachianBasin2.5.1.1.2.2TheValleyandRidgeProvince2.5.1.1.2.3StratigraphicUnitsWithintheSiteVicinity2.5.1.1.3RegionalTectonics2.5.1.1.3.1TectonicProvinces2.5.1.1.3.2StructuralElementswithintheCraton2.5.1.1.3.3StructuralElementsintheSiteVicinity2.5.1.1.3.4RelationshipAmongStructuralElements2.5.1.1.3.5AgeofDeformation SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-vii2.5.1.1.3.5.1RelationshipofLineamentstoRegionalGeology2.5.1.1.4RegionalUpliftandSubsidence2.5.1.1.5NaturalHazards2.5.1.2SiteGeology2.5.1.2.1SitePhysiography2.5.1.2.2SiteLithologyandStratigraphy2.5.1.2.2.1LithologyandStratigraphyintheSiteVicinity2.5.1.2.2.2LithologyandStratigraphyattheSite2.5.1.2.3StructuralGeology2.5.1.2.3.1MajorGeologicStructuresinSiteVicinity2.5.1.2.3.2GeologicStructuresattheSite2.5.1.2.3.3GeologicFeaturesinSurficialMaterialsattheSite2.5.1.2.3.4HazardsfromStorageinLocalGeologicStructures2.5.1.2.4SiteGeologicHistory2.5.1.2.5EngineeringGeologyEvaluation2.5.1.2.5.1GeologicConditionsUnderCategory1Structures2.5.1.2.5.2LandslidePotential2.5.1.2.5.3AreasofPotentialSubsidence,Uplift,orCollapse2.5.1.2.5.4BehaviorofSiteDuringPriorEarthquakes2.5.1.2.5.5ZonesofDeformationorStructuralWeakness2.5.1.2.5.6ZonesofAlterationorIrregularWeathering2.5.1.2.5.7PotentialforUnstableorHazardousRockorSoilConditions2.5.1.2.5.8UnrelievedResidualStressonBedrock2.5.1.2.5.9ConclusionsandSummary2.5.1.2.6SiteGroundwaterConditions2.5.2VibratoryGroundMotion 2.5.2.1Seismicity2.5.2.2GeologicStructuresandTectonicActivity2.5.2.2.1TectonicProvinces2.5.2.2.2TectonicDifferentiationoftheAppalachianOrogen2.5.2.2.3TectonicDifferentiationoftheCraton2.5.2.2.4TectonicDifferentiationoftheMobileBelt2.5.2.3CorrelationofEarthquakeActivitywithGeologicStructuresorTectonicProvinces2.5.2.4MaximumEarthquakePotential2.5.2.5SeismicWaveTransmissionCharacteristics2.5.2.6SafeShutdownEarthquake(SSE)2.5.2.7OperatingBasisEarthquake(OBE)

SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-viii2.5.3SurfaceFaulting2.5.4StabilityofSubsurfaceMaterialsandFoundations2.5.4.1GeologicFeatures2.5.4.1.1AreasofPotentialSubsidence,Uplift,orCollapse2.5.4.1.2PreviousLoadingHistoryoftheFoundationMaterials2.5.4.1.3StructuresandZonesofWeathering,DisturbanceorWeaknessinFoundationMaterials2.5.4.1.4UnrelievedResidualStressesinBedrock2.5.4.1.5PotentialforUnstableorHazardousRockorSoilConditions2.5.4.2PropertiesofSubsurfaceMaterials2.5.4.2.1PropertiesofFoundationRock2.5.4.2.2PropertiesofFoundationSoils2.5.4.3Exploration2.5.4.4GeophysicalSurveys2.5.4.5ExcavationsandBackfill2.5.4.5.1ExtentofSeismicCategoryIExcavations,Fills,andSl opes2.5.4.5.2ExcavationMethodsandDewatering2.5.4.5.2.1ExcavationsinRock2.5.4.5.2.2ExcavationsinSoil2.5.4.5.3BackfillandCompaction2.5.4.5.4BeddingMaterialforSeismicCategoryIPipesandElectricalDuctBanks2.5.4.6GroundwaterConditions2.5.4.7ResponseofSoilandRocktoDynamicLoading2.5.4.7.1ResponseofRocktoDynamicLoading2.5.4.7.2ResponseofSoiltoDynamicLoading2.5.4.7.3SoilStructureInteraction2.5.4.8LiquefactionPotential2.5.4.9EarthquakeDesignBases2.5.4.10StaticStability2.5.4.10.1StaticStabilityofSafety-RelatedStructuresSupportedonRock2.5.4.10.2StaticStabilityofSafety-RelatedStructuresSupportedonSoil2.5.4.11DesignCriteria2.5.4.11.1DesignCriteriaofSafety-RelatedStructuresonRock2.5.4.11.2DesignCriteriaofSafety-RelatedStructuresonSoil2.5.4.12TechniquestoImproveSubsurfaceConditions2.5.4.12.1FoundationsinRock2.5.4.12.2FoundationsinSoil2.5.4.13SubsurfaceInstrumentation2.5.4.13.1InstrumentationforRockFoundations2.5.4.13.2InstrumentationforSoilFoundations SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-ix2.5.4.14ConstructionNotes2.5.5StabilityofSlopes2.5.5.1SlopeCharacteristics2.5.5.1.1GeologicConditions2.5.5.1.2GroundwaterConditions2.5.5.1.3FieldSamplingandTesting2.5.5.1.4LaboratoryTesting2.5.5.1.4.1General2.5.5.1.4.2GrainSizeDistribution2.5.5.1.4.3UnitWeight2.5.5.1.4.4Maximum-MinimumDensities2.5.5.1.4.5RelativeDensity2.5.5.1.4.6StaticTriaxialShearTest2.5.5.1.4.7CyclicTriaxialShearTests2.5.5.2DesignCriteriaandAnalyses2.5.5.2.1DesignCriteriaforSprayPond2.5.5.2.1.1GroundSurfaceAcceleration2.5.5.2.1.2Liquefaction2.5.5.2.1.3SlopeStability2.5.5.2.2DesignAnalysesforSprayPond2.5.5.2.2.1SprayPondSeepageAnalysis2.5.5.2.2.1.1SprayPondSeepageMonitoring2.5.5.2.2.2LiquefactionPotential2.5.5.2.2.2.1MethodofAnalysis2.5.5.2.2.2.2SoilProfilesandPositionsofGroundwaterTable2.5.5.2.2.2.3ShearModuli2.5.5.2.2.2.4CyclicShearStrength2.5.5.2.2.2.5DeterminationofDynamicShearStresses2.5.5.2.2.2.6DesignEarthquake2.5.5.2.2.2.7ResultsofLiquefactionAnalyses2.5.5.2.2.2.7.1LiquefactionPotentialUndertheDesignSSE2.5.5.2.2.2.7.2VariationsofShearModuliandDampingRatiosforEvaluationofLiquefactionPotential2.5.5.2.2.2.7.3ResultsofLiquefactionAnalysesUsingRealEarthquakeRecords2.5.5.2.2.3SlopeStabilityAnalyses2.5.5.2.2.3.1StabilityofRockSlopes2.5.5.2.2.3.2StabilityofSlopesinSoil2.5.5.2.2.4Earthquake-InducedSoilStrainandSettlement2.5.5.3LogsofBorings2.5.5.4CompactedBackfill SSES-FSARNIMSRev.60CHAPTER2TEXTSectionTitleFSARRev.652-x2.5.6References2.5AU.S.DEPARTMENTOFTHEINTERIORREPORTONINVESTIGATIONOFANEARTHDISTURBANCEATWILKES-BARRE2.5BCITYOFWILKES-BARREREPORTONANEARTHDISTURBANCE 2.5CBORINGLOGS 2.5C.1SummaryofFieldDensityTestResults2.5C.2ListingsofBoringLogs SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xi2.1-1Thistablehasbeendeleted2.1-2Thistablehasbeendeleted 2.1-3Thistablehasbeendeleted 2.1-4Thistablehasbeendeleted 2.1-5Thistablehasbeendeleted 2.1-6Thistablehasbeendeleted 2.1-7Thistablehasbeendeleted 2.1-8Thistablehasbeendeleted 2.1-9Thistablehasbeendeleted 2.1-10Thistablehasbeendeleted 2.1-11Thistablehasbeendeleted 2.1-12Thistablehasbeendeleted 2.1-13Thistablehasbeendeleted 2.1-14Thistablehasbeendeleted 2.1-15Thistablehasbeendeleted 2.1-16Thistablehasbeendeleted 2.1-17Thistablehasbeenrenumberedto2.1-33 2.1-18Thistablehasbeenrenumberedto2.1-34 2.1-19Thistablehasbeenrenumberedto2.1-39 2.1-20Thistablehasbeenrenumberedto2.1-41 2.1-21Thistablehasbeenrenumberedto2.1-35 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xii2.1-22Thistablehasbeenrenumberedto2.1-362.1-23Thistablehasbeenrenumberedto2.1-37 2.1-24Thistablehasbeenrenumberedto2.1-38 2.1-25Thistablehasbeendeleted 2.1-26Thistablehasbeenrenumberedto2.1-40 2.1-27Thistablehasbeendeleted 2.1-28Thistablehasbeendeleted 2.1-29Thistablehasbeenrenumberedto2.1-43 2.1-30Thistablehasbeenrenumberedto2.1-44 2.1-31Thistablehasbeenrenumberedto2.1-45 2.1-32Thistablehasbeenrenumberedto2.1-46 2.1-33PastPopulationChangesofCountiesWithin20MilesoftheSite 2.1-34PopulationbyResidenceforCountiesWithin20MilesoftheSite 2.1-35PopulationDistribution20100-10MilesDistance(Miles) 2.1-36PopulationDistribution20100-50MilesDistance(Miles) 2.1-37PopulationDistribution20200-10MilesDistance(Miles) 2.1-38PopulationDistribution20200-50MilesDistance(Miles) 2.1-39PopulationDistribution20000-10MilesDistance(Miles) 2.1-40CommunitiesWithin10MilesoftheSite,2000 2.1-41PopulationDistribution20000-50MilesDistance(Miles)

SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xiii2.1-42SeasonalPopulationofCountiesinStudyArea,20002.1-43IndustriesWithin5MilesoftheSite 2.1-44PopulationProjectionsforBerwick,Pennsylvania 2.1-45CumulativePopulationsfor1990and2000 2.1-46CumulativePopulationsfor1990,2000,2010and2020 2.2-1PipelinesWithin5MilesoftheSite 2.2-2ProbabilityofSiteExposurewithAmmonia2.2-3ProbabilityofSiteExposurewithSulfurDioxide2.3-1HurricanesWithin75and150NauticalMilesoftheSusquehannaSitePeriodofRecord1871to19692.3-2ThunderstormDaysforAvoca,PennsylvaniaWilkes-BarreScrantonAirport,PeriodofRecord1956to1974,ValuesareexpressedinDays2.3-3TotalNumberofDaysin5YearsMixingHeights<1500mWindSpeeds<4.0sec-1andNoSignificantPrecipitationForEpisodesLastingatleast2Days2.3-4ThisTableIntentionallyLeftBlank 2.3-5MeanMonthlyValues:SusquehannaSite(1973-1976) 2.3-6LongTermAverageWindSpeedandPrevailingDirectionatWilkes-BarreScrantonAirport,PeriodofRecord:1956-19742.3-7AverageWindSpeedandPrevailingDirectionattheSusquehannaSite,PeriodofRecord(1973-1976)2.3-8WindDirectionPersistence-PasquillA(1973-1976) 2.3-9WindDirectionPersistence-PasquillB(1973-1976) 2.3-10WindDirectionPersistence-PasquillC(1973-1976)

SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xiv2.3-11WindDirectionPersistence-PasquillD(1973-1976)2.3-12WindDirectionPersistence-PasquillE(1973-1976 2.3-13WindDirectionPersistence-PasquillF(1973-1976) 2.3-14WindDirectionPersistence-PasquillG(1973-1976) 2.3-15WindDirectionPersistence-PasquillAll(1973-1976) 2.3-16WindDirectionPersistence-PasquillE,F,&G(1973-1976)2.3-17LongTermTemperature(F)AtWilkes-Barre-ScrantonAirport2.3-18MeanMonthlyTemperature,DewPointTemperatureandRelativeHumidityWilkes-BarreScrantonAirportPeriodofRecord:1956-19742.3-19TemperatureandMoistureDatafortheSusquehannaSite,PeriodofRecord:1973-19762.3-20StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:January1973-19762.3-21StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:February1973-19762.3-22StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:March1973-19762.3-23StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:April1973-19762.3-24StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:May1973-19762.3-25StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:June1973-19762.3-26StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:July1973-1976 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xv2.3-27StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:August1973-19762.3-28StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:September1973-19762.3-29StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:October1973-19762.3-30StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:November1973-19762.3-31StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:December1973-19762.3-32StatisticsandDiurnalVariationofMeteorologicalParametersDataPeriod:January1973-December19762.3-33LongTermMonthlyPrecipitationData(LiquidEquivalent,InInches)forWilkes-BarreScrantonAirportatAvoca,PA2.3-34ExpectedRainfallbyDurationandRecurrenceIntervalforVicinityofSusquehannaSite(Ref.2.3-20)(Inches)2.3-35ProbableMaximumPrecipitationforVaryingRainfallDurationsandAreas(Ref.2.3-21)(Inches)2.3-36PrecipitationDatafortheSusquehannaSite(InchesofWater)(1973-1976) 2.3-37FrequencyDistributionofPrecipitationDataPeriod:January1973-1976 2.3-38FrequencyDistributionofPrecipitationDataPeriod:February1973-1976 2.3-39FrequencyDistributionofPrecipitationDataPeriod:March1973-1976 2.3-40FrequencyDistributionofPrecipitationDataPeriod:April1973-1976 2.3-41FrequencyDistributionofPrecipitationDataPeriod:May1973-1976 2.3-42FrequencyDistributionofPrecipitationDataPeriod:June1973-1976 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xvi2.3-43FrequencyDistributionofPrecipitationDataPeriod:July1973-19762.3-44FrequencyDistributionofPrecipitationDataPeriod:August1973-1976 2.3-45FrequencyDistributionofPrecipitationDataPeriod:September1973-1976 2.3-46FrequencyDistributionofPrecipitationDataPeriod:October1973-1976 2.3-47FrequencyDistributionofPrecipitationDataPeriod:November1973-1976 2.3-48FrequencyDistributionofPrecipitationDataPeriod:December1973-1976 2.3-49FrequencyDistributionofPrecipitationDataPeriod:January1973-December19762.3-50PrecipitationWindRoseJanuary1973-1976 2.3-51PrecipitationWindRoseFebruary1973-1976 2.3-52PrecipitationWindRoseMarch1973-1976 2.3-53PrecipitationWindRoseApril1973-1976 2.3-54PrecipitationWindRoseMay1973-1976 2.3-55PrecipitationWindRoseJune1973-1976 2.3-56PrecipitationWindRoseJuly1973-1976 2.3-57PrecipitationWindRoseAugust1973-1976 2.3-58PrecipitationWindRoseSeptember1973-1976 2.3-59PrecipitationWindRoseOctober1973-1976 2.3-60PrecipitationWindRoseNovember1973-1976 2.3-61PrecipitationWindRoseDecember1973-1976 2.3-62PrecipitationWindRoseJanuary1973-December1976 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xvii2.3-63HeavyFog(Visibility1/4MileorLess)atAvoca,PA.2.3-64JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassA2.3-65JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassB2.3-66JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassC2.3-67JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassD2.3-68JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassE2.3-69JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassF2.3-70JointFrequency(%)ofWindDirection,WindSpeedandStability,StabilityClassG2.3-71JointFrequency(%)ofWindDirection,WindSpeedandStability,AllStabilityClasses2.3-72MixingHeights(meters) 2.3-73HeightsofMeteorologicalSensors 2.3-74DataRecoveryRates 2.3-75JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003StabilityClass:PasquillA2.3-76JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003StabilityClass:PasquillB SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xviii2.3-77JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillC2.3-78JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillD2.3-79JointWindFrequencyDistributionByStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PaquillE2.3-80JointWindFrequencyDistributionByStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillF2.3-81JointWindFrequencyDistributionbyStabilityClass,LowerWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillG2.3-82JointWindFrequencyDistributionbyStabilityClassLowerWindJanuary1,1999throughDecember31,2003,AllClasses2.3-83IntentionallyBlank 2.3-84JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillA2.3-85JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillB2.3-86JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillC2.3-87JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillD2.3-88JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillE2.3-89JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillF2.3-90JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,StabilityClass:PasquillG SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xix2.3-91JointWindFrequencyDistributionbyStabilityClass,UpperWindJanuary1,1999throughDecember31,2003,AllClasses2.3-92SummaryofShort-TermX/Q(SEC/M3)Resultsat549MEAB 2.3-931999ProbabilityValuesfor1HouratSSESEAB2.3-942000ProbabilityValuesfor1HouratSSESEAB2.3-952001ProbabilityValuesfor1HouratSSESEAB2.3-962002ProbabilityValuesfor1HouratSSESEAB2.3-972003ProbabilityValuesfor1HouratSSESEAB2.3-981999-2003ProbabilityValuesfor1HouratSSESEAB2.3-991999ProbabilityValuesfor1HouratSSESLPZ2.3-1002000ProbabilityValuesfor1HouratSSESLPZ2.3-1012001ProbabilityValuesfor1HouratSSESLPZ2.3-1022002ProbabilityValuesfor1HouratSSESLPZ2.3-1032003ProbabilityValuesfor1HouratSSESLPZ2.3-1041999-2003ProbabilityValuesfor1HouratSSSSLPZ2.3-105SummaryofLong-TermX/G(SEC/M3)Resultsat4827MLPZ 2.3-106DistancesandTerrain/RecirculationCorrectionFactorsforSSES2003LandUseCensusLocations2.3-1071999AverageRelativeConcentration(sec/m 3)andDisposition(m

-2)EstimatesattheSiteBoundary2.3-1082000AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xx2.3-1092001AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1102002AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1112003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1121999-2003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheSiteBoundary2.3-1131999AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1142000AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1152001AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1162002AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1172003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary2.3-1181999-2003AverageRelativeConcentration(sec/m 3)andDeposition(m

-2)EstimatesattheExclusionAreaBoundary.2.3-1191999AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1202000AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1212001AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1222002AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxi2.3-1232003AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1241999-2003AtmosphericDispersionEstimatesforNearestResidenceandVegetableGarden2.3-1251999AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1262000AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1272001AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1282002AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1292003AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1301999-2003AtmosphericDispersionEstimatesforNearestMeatAnimal,DairyLocationsandSpecialReceptors2.3-1311999AtmosphericDispersionEstimatesatSelectedLocations 2.3-1322000AtmosphericDispersionEstimatesatSelectedLocationsl 2.3-1332001AtmosphericDispersionEstimatesatSelectedLocations 2.3-1342002AtmosphericDispersionEstimatesatSelectedLocations 2.3-1352003AtmosphericDispersionEstimatesatSelectedLocations 2.3-1361999-2003AtmosphericDispersionEstimatesatSelectedLocations 2.3-137SSESRelativeConcentrationsNoDecay,UndepletedX/Q(sec/m 3)X/QAccumulationforGroundAverageforthePeriodof01/01/99through12/31/03 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxii2.3-138SSESRelativeConcentrations2.26-DayDecay,UndepletedX/Q(sec/m 3)forGroundDecayedSectorAverageforthePeriodof01/01/99through12/31/032.3-139SSESRelativeConcentrations8-DayDecay,DepletedX/Q(sec/m 3)forGroundDecayedSectorAverageforthePeriodof01/01/99through12/31/032.3-140SSESRelativeDepositionD/Q(m

-2)forthePeriodof01/01/99through12/31/032.4-1ExistingandProposedDamsLocatedintheSusquehannaRiverBasin(ChemungRiverBasin)2.4-2MinorUpstreamDamsandReservoirs 2.4-3WaterUsers 2.4-4HistoricFloodsintheVicinityoftheSusquehannaSteamElectricStation.

2.4-5All-Season24-HourProbableMaximumPrecipitation 2.4-6ProbableMaximumPrecipitationforDurationsLessThan30Min.

2.4-7PeakRunoffRatesfromandMaximumPondingDepthsonRoofsofSafetyRelatedStructuresforLocalAll-SeasonPMP2.4-8Adopted4-HourUnitHydrographsandCharacteristics.

2.4-9SusquehannaRiverBasinRoutingCoefficients 2.4-10Manning"N"ValuesComputedfrom1936Flood 2.4-11SusquehannaRiverFreezeOveratHarrisburg(1870-1955) 2.4-12IceJamFlooding 2.4-13SummaryofFloodRoutingStudies-SprayPond 2.4-14ResultsofWindWaveComputation SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxiii2.4-15MaximumLoadingsResultingfromWind-WaveActivities2.4-16MaximumHydrodynamicLoadingResultingfromEarthquake 2.4-17ThisTablehasbeenDeleted 2.4-18ESWCoolingDutyonSimultaneousLossofAllAuxiliaryPowertoBothUnits2.4-19ThisTableHasBeenDeleted 2.4-20ThisTableHasBeenDeleted 2.4-21RegionalHydrogeologicSection(within20-mileradiusofSusquehannaSES)2.4-22WaterWellDataWithinTwoMilesoftheStation 2.4-23SpringDataWithinTwoMilesoftheStation 2.4-24DataforMajorWaterWells,OtherThanPublicWells,locatedBetween2and10MilesFromtheStation2.4-25DataforPublicSupplyWellsLocatedBetween2and20MilesfromtheStation2.4-26EstimatedGroundwaterWithdrawalin1976WithinTwoMilesoftheStation 2.4-27ProjectionsofFutureGroundwaterWithdrawalWithin2and20MilesoftheStation2.4-28MajorGroundwaterWithdrawal,andPopulationServedbyWaterSupplyCompaniesWithin20-MileArea2.4-29EstimationofTotalGroundwaterWithdrawalin1975Within20MileRadiusoftheStation2.4-30DetailsoftheConstructionofObservationWellsattheSusquehannaSES 2.4-31GroundwaterLevelDataTakenatSusquehannaSES1972through1975 SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxiv2.4-32GroundwaterLevelDataTakenatSusquehannaSESin1976and19772.4-33SummaryofPermeabilityTestsofOverburdenandUpperBedrockattheSusquehannaSESPerformedDuringPreviousInvestigations2.4-34SummaryofPermeabilityTestsofOverburdenandUpperBedrockattheSusquehannaSESPerformedforThisInvestigation2.4-35RadionuclideContentoftheTankPostulatedtoRupture-ReactorWaterCleanup(RWCU)PhaseSeparatorTanks-SusquehannaSES2.4-36GroundwaterParameterValuesUsedforSLUG3DSimulationsAccidentAnalysisforSusquehannaSES2.4-37RangeofParameterValuesusedinCalibratedNumericalModelofBuriedValleyAquiferNorthernSideofSusquehannaSES2.4-38EstimatedPeakConcentrationofRadionuclidesinGroundwaterResultingfromPostulatedRuptureofRWCUPhaseSeparatorTank-ResultsofSimulationswithSLUG3DModel-SusquehannaSES2.4-39EstimatedPeakConcentrationofRadionuclidesinGroundwaterinBuriedValleyAquiferResultingfrompostulatedRuptureofRWCUPhaseSeparatorTank-ResultsofSimulationswithSLUG3DModel-SusquehannaSES2.5-1ModifiedMercalliIntensity(Damage)Scale(Abridged) 2.5-2Earthquakelist 2.5-3UnconfinedCompressiveStrengthsofFoundationRock(MahantangoFormation)2.5-4LaboratoryMeasurementsofP-WaveSeismicVelocitiesonRockCorestakenfromReactorandTurbineBuildingAreas2.5-5RepresentativeEngineeringPropertiesofUnweatheredFoundationRockforPrincipalPlantStructures2.5-6P-WaveandS-WaveVelocitiesandComputedDynamicModuli,SprayPondArea SSES-FSARNIMSRev.60CHAPTER2TABLESNumberTitleFSARRev.652-xxv2.5-7Cross-HoleSeismicVelocities,ReactorArea2.5-8ResultsofSettlementMeasurementsTakenonESSWPumphouseBasemat2.5-9SprayPondWaterLevelElevations 2.5-10PermeabilitiesMeasuredinSprayPond 2.5-11PermeabilitiesMeasuredNeartheRailroadBridge 2.5-12CirculationLossesinDrillHolesinSprayPond 2.5-13SoilTestResultsSummary 2.5-14SprayPondSummaryofCyclicConsolidated-UndrainedTriaxial(CR)Tests 2.5-15DesignParametersforSprayPondLiner 2.5-16SprayPond,SummaryofLiquefactionAnalysis 2.5-17EffectofVaryingStandardRelationshipofEffectiveStrainwithDampingandModuliforProfile2,GWT-6652.5-18SprayPondFactorofSafetyasObtainedUsingDifferentEarthquakes 2.5-19ProbableSettlementDuringEarthquake SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxvi2.1-1FigureRenumberedfrom2.1-1to2.1-112.1-2FigureRenumberedfrom2.1-2to2.1-12 2.1-3FigureRenumberedfrom2.1-3to2.1-13 2.1-4FigureRenumberedfrom2.1-4to2.1-14 2.1-5FigureRenumberedfrom2.1-5to2.1-15 2.1-6FigureRenumberedfrom2.1-6to2.1-16 2.1-7FigureRenumberedfrom2.1-7to2.1-17 2.1-8FigureRenumberedfrom2.1-8to2.1-18 2.1-9FigureRenumberedfrom2.1-9to2.1-19 2.1-10FigureRenumberedfrom2.1-10to2.1-20 2.1-11FigureRenumberedfrom2.1-11to2.1-21 2.1-12FigureRenumberedfrom2.1-12to2.1-22 2.1-13FigureRenumberedfrom2.1-13to2.1-27 2.1-14FigureRenumberedfrom2.1-14to2.1-28 2.1-15FigureRenumberedfrom2.1-15to2.1-23 2.1-16FigureRenumberedfrom2.1-16to2.1-24 2.1-17FigureRenumberedfrom2.1-17to2.1-25 2.1-18FigureRenumberedfrom2.1-18to2.1-26 2.1-19Thisfigurehasbeendeleted 2.1-20Thisfigurehasbeendeleted 2.1-21SiteVicinityMap SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxvii2.1-22SiteAreaMap2.1-23PopulationDistribution0-10Miles,2010 2.1-24PopulationDistribution0-50Miles,2010 2.1-25PopulationDistribution0-10Miles,2020 2.1-26PopulationDistribution0-50Miles,2020 2.1-27SeasonalPopulation0-10Miles,2000 2.1-28SeasonalPopulation0-50Miles,2000 2.2-1MajorTransportationRoutesandPipelines 2.2-2AirportandAirlineRouteMap 2.2-3PipelineBreakatElevation700',SteadyStateBreakFlow 2.2-4PipelineBreakatElevation600',SteadyStateBreakFlow 2.3-1TornadoOccurrenceandIntensityinSusquehannaRegion 2.3-2TP25RainfallIntensity-DurationFrequencyCurvesUSDCWB,1955 2.3-3TopographyWithin5Miles 2.3-4-1MaximumTerrainElevationVersusDistanceBySector 2.3-4-2MaximumTerrainElevationVersusDistanceBySector 2.3-4-3MaximumTerrainElevationVersusDistanceBySector 2.3-4-4MaximumTerrainElevationVersusDistanceBySector 2.3-4-5MaximumTerrainElevationVersusDistanceBySector 2.3-4-6MaximumTerrainElevationVersusDistanceBySector SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxviii2.3-4-7MaximumTerrainElevationVersusDistanceBySector2.3-4-8MaximumTerrainElevationVersusDistanceBySector 2.3-5SchematicofInstrumentation 2.3-6OneHourDirectionIndependentX/QattheEAB(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.3-7OneHourDirectionDependentX/QValuesattheEAB(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.3-8OneHourDirectionDependentX/QValuesattheLPZ(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.3-9OneHourDirectionIndependentX/QattheLPZ(WeightedAverageof1999,2000,2001,2002and2003Calculations2.3-10InterpolatedX/QValuesattheLPZ(WeightedAverageof1999,2000,2001,2002and2003Calculations)2.4-1Thisfigurehasbeendeleted 2.4-2Thisfigurehasbeendeleted 2.4-3PlantCompleteShowingStormDrainPipeLayout 2.4-4SusquehannaRiverBasin 2.4-5StageDischargeCurveatLowFlows 2.4-6StageDischargeCurve,DischargeRange1000-37,000CFS 2.4-7WaterUsersontheSusquehannaRiver 2.4-8StageDischargeCurvesatPlantSite 2.4-9FloodProfilesontheSusquehannaRiverattheSite 2.4-10GeneralSiteDrainagePlan SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxix2.4-11SiteDrainageLocationsA&B2.4-12SiteDrainageLocationsC&D 2.4-13SiteDrainageLocationsE&F 2.4-14ProbableMaximumPrecipitationStormPatternandOutlineofSub-Basins,SusquehannaRiveraboveWilkes-Barre,Pennsylvania2.4-15ProbableMaximumPrecipitationonSusquehannaRiverBasinandProbableMaximumFloodHydrographatWilkes-Barre,Pennsylvania2.4-16MapoftheSusquehannaRiver,RiverMiles150-170 2.4-17StageDischargeCurveatSection2-BerwickBridge 2.4-18RiverandWaterSurfaceProfilesofSusquehannaRiverinVicinityofSite 2.4-19CrossSectionsattheEightRiverSectionsNeartheSite 2.4-20CrossSectionofRiveratthePlantSite 2.4-21WindFetch,SusquehannaRiverPMF 2.4-22TiogaDamandHammondDamReservoirAreasandSections 2.4-23SurfaceDrainagePatternsaroundtheSprayPond 2.4-24SprayPondInflowandOutflowHydrograph 2.4-25SprayPondOutletRatingCurves 2.4-26SprayPondElevationAreaStorageCapacityCurves 2.4-27SprayPondEmergencySpillwayWaterSurfaceProfile 2.4-28SprayPondDesignSpectrumforSSE 2.4-29SprayPondDesignSpectrumforOBE 2.4-30DurationCurvesofDailyDischarge SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxx2.4-31TimeofTravel,SusquehannaRiverShickshinnytoDanv ille2.4-32MapofSusquehannaSESShowingGroundwaterContoursinSeptember19772.4-33HydrogeologicCrossSectionfromWesttoEastAlongGroundwaterFlowPathattheSusquehannaSES2.4-34BedrockGeologicMapofAreaWithin20MilesofSusquehannaSES 2.4-35MajorPleistoceneSandandGravelDepositsWithin20MilesofSusquehannaSES2.4-36GeologicMapofAreaWithinTwoMilesoftheStation 2.4-37WaterWellsWithinTwoMilesoftheStation 2.4-38SpringsUsedforWaterSupplyWithinTwoMilesoftheStation 2.4-39MajorWaterWellsTwotoTenMilesfromtheStation,ExceptingPublicSupplyWells2.4-40PublicSupplyWellsTwotoTwentyMilesfromtheStation 2.4-41MapofSusquehannaSESShowingIsopachContoursofOverburdenThickness2.4-42MapofSusquehannaSESShowingTop-of-BedrockContours 2.4-43MapofSusquehannaSESShowingGroundwaterContoursinApril1977 2.4-44LogofBoringandObservationWellConstructionDetails-1200,1200A 2.4-45LogofBoringandObservationWellConstructionDetails-1201 2.4-46LogofBoringandObservationWellConstructionDetails-1204 2.4-47LogofBoringandObservationWellConstructionDetails-1208 2.4-48LogofBoringandObservationWellConstructionDetails-1209A SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxi2.4-49LogofBoringandObservationWellConstructionDetails-12102.4-50MapofSusquehannaSESShowingGroundwaterContoursinJune1971 2.4-51DrawdownCurvesfromPumpingTestsofObservationWells1204and1210 2.4-52RiverIntakeStructure 2.4-53RiverDischargeDiffuser 2.4-54ThisFigureHasBeenReplacedbyDWG.A-12.Sh.1 2.4-54aThisFigureHasBeenDeleted 2.4-55ThisFigureHasBeenReplacedbyDWG.FF62005,Sh.1 2.5-1SiteLocation 2.5-2RegionalPhysiographicMap 2.5-3RegionalGeologicMap 2.5-4LocationofAppalachianBasin 2.5-5RegionalIsopachMaps 2.5-6StratigraphicColumns 2.5-7RegionalTectonicMap 2.5-8aEarthquakeEpicentersandTectonicProvinceBoundariesintheSiteRegion 2.5-8bEarthquakeEpicentersWithin200MilesoftheSite 2.5-9BouguerGravityAnomalyMap 2.5-10GeologicMapoftheBloomsburg-BerwickArea 2.5-11RegionalLandsatLineaments SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxii2.5-12SiteGeologicMap2.5-13PhotographofGeologicFeatureFoundinTurbineBuildingExcavation 2.5-14SiteVicinityGeologicColumn 2.5-15GeologicMapofSprayPondArea 2.5-16ThisFigureHasBeenDeleted 2.5-17ContoursonTopofBedrockSurface 2.5-17aExtentofRockandSoilFoundations 2.5-18GeologicMapofFoundationExcavation 2.5-19GeologicSectionThroughFoundationExcavations 2.5-20aPhotographofGeologicFeaturesExposedinExcavations 2.5-20bPhotographofGeologicFeaturesExposedinExcavations 2.5-20cPhotographofGeologicFeaturesExposedinExcavations 2.5-20dPhotographofGeologicFeaturesExposedinExcavations 2.5-20ePhotographofGeologicFeaturesExposedinExcavations 2.5-20fPhotographofGeologicFeaturesExposedinExcavations 2.5-20gPhotographofGeologicFeaturesExposedinExcavations 2.5-21aSiteGeologicCrossSections 2.5-21bSiteGeologicCrossSections 2.5-22PlotPlan 2.5-22aPlotPlanDetails 2.5-23aLogofBorings SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxiii2.5-23bLogofBorings2.5-23cLogofBorings 2.5-23dLogofBorings 2.5-23eLogofBorings 2.5-23fLogofBorings 2.5-23gLogofBorings 2.5-23hLogofBorings 2.5-23iLogofBorings 2.5-23jLogofBorings 2.5-23kLogofBorings 2.5-23lLogofBorings 2.5-23mLogofBorings 2.5-23nLogofBorings 2.5-23oLogofBorings 2.5-23pLogofBorings 2.5-23qLogofBorings 2.5-23rLogofBorings 2.5-23sLogofBorings 2.5-23tLogofBorings 2.5-24FinalPlantGrades SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxiv2.5-25TectonicMapofAnthraciteRegion2.5-26GeologicSectionofAnthraciteRegion 2.5-27DesignResponseSpectra-SafeShutdownEarthquake 2.5-28DesignResponseSpectra-OperatingBasisEarthquake 2.5-29GeophysicalSurveys 2.5-30SprayPond-GeneralizedCross-Sections 2.5-30aDieselGenerator'E'FuelTank-GeneralizedCross-Sections 2.5-31SprayPond,RangeofGrainSizeCurves 2.5-32RelativeDensityRelatedtoNValueatESSWPumphouseSite 2.5-33"N"ValueVersusElevationatESSWPumphouseSite 2.5-34SprayPond,ConsolidatedDrainedTriaxialTest-MohrCircleDiagram 2.5-35SprayPond,SummaryofCyclicShearTest(CR)Results 2.5-36SprayPond,ShearWaveVelocityDesignCurves 2.5-37LocationandLimitsofExcavationFillandBackfillforClass1Structures 2.5-38LocationofSprayPondwithContoursonTopofRockandWaterTable 2.5-39LateralSoilPressureDiagrams 2.5-40SprayPond,MeasuredandProjectedWaterLevels 2.5-41DetailsofSettlementPinsCastinESSWPumphouseBasemat 2.5-42SprayPond,EarthworkPlan 2.5-43ThisFigureHasBeenReplacedbyDWG.C-63,Sh.1 2.5-44SprayPond,BoringandTestPitsLocationPlan SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxv2.5-45SprayPond,GeneralizedCrossSectionswithLaboratoryTestLocations2.5-46SprayPond,RelativeDensityRelatedto"N"Value 2.5-47SprayPond,RelationshipBetweenSeepageLossandMaximumGroundwaterElevation2.5-48SprayPond,SoilProfilesUsedinLiquefactionAnalysis 2.5-49SprayPond,FactorofSafetyVariationwithGroundwaterTableandDepth 2.5-50SprayPond,MinimumFactorofSafetyAgainstLiquefactionAtSelectedLocations2.5-50AVariationFactorofSafety(F.S)vsChangeofDampingRatio 2.5-51SprayPond,ComparisonofFactorsofSafetyforLiquefactionfortheDesignEarthquakeandSomeRealEarthquakes2.5-52SprayPond,ComparisonofAverageCycleStressAsInducedbyDesignEarthquakeandSomeRealEarthquakes2.5-53SprayPond,AverageShearVariationwithDepth 2.5-54SprayPond,SummaryofPorePressureBuildup 2.5-55SiteWaterTableMap(Preconstruction) 2.5-56ProfileofSlopeNorthofSprayPond 2.5-57SprayPondRelationshipBetweenLinerThickness,LinerPermeabilityandSeepageLoss2.5-58DampingRatioVersusShearStrainofSandinLiquefactionAnalysis 2.5-59SampleLocationsofSoilDensityTests 2.5-60StatisticalAnalysisofFieldDensityTestResults 2.5-61StatisticalAnalysisofSand-Cement-FlyashBeddingandBackfill SSES-FSARNIMSRev.60CHAPTER2FIGURESNumberTitleFSARRev.652-xxxvi2.5-62ESSWPumphouseFloorPlanEl.685'-6" SSES-FSARTOCRev.62FSARRev.653-iCHAPTER3DESIGNOFSTUCTURES,COMPONENTS,EQUIPMENTSYSTEMSTABLEOFCONTENTSTEXTSectionTitle3.1CONFORMANCEWITHNRCGENERALDESIGNCRITERIA3.1.1SummaryDescription3.1.2CriterionConformance3.1.2.1OverallRequirements(Group1)3.1.2.1.1QualityStandards&Records(Criterion1)3.1.2.1.2DesignBasisforProtectionAgainstNaturalPhenomena(Criterion2)3.1.2.1.3FireProtection(Criterion3)3.1.2.1.4EnvironmentalandDynamicEffectsDesignBases(Criterion4)3.1.2.1.5SharingofStructures,Systems&Components(Criterion5)3.1.2.2ProtectionbyMultipleFissionProductBarriers(GroupII)3.1.2.2.1ReactorDesign(Criterion10)3.1.2.2.2ReactorInherentProtection(Criterion11)3.1.2.2.3SuppressionofReactorPowerOscillations(Criterion12)3.1.2.2.4InstrumentationandControl(Criterion13)3.1.2.2.5ReactorCoolantPressureBoundary(Criterion14)3.1.2.2.6ReactorCoolantSystemDesign(Criterion15)3.1.2.2.7ContainmentDesign(Criterion16)3.1.2.2.8ElectricPowerSystems(Criterion17)3.1.2.2.9InspectionandTestingofElectricPowerSystems(Criterion18)3.1.2.2.10ControlRoom(Criterion19)3.1.2.3Protection&ReactivityControlSystems(GroupIII)3.1.2.3.1ProtectionSystemFunctions(Criterion20)3.1.2.3.2ProtectionSystemReliabilityandTestability(Criterion2l)3.1.2.3.3ProtectionSystemIndependence(Criterion22)3.1.2.3.4ProtectionSystemFailureModes(Criterion23)3.1.2.3.5SeparationofProtectionandControlSystems(Criterion24)3.1.2.3.6ProtectionSystemRequirementsforReactivityControlMalfunctions(Criterion25)3.1.2.3.7ReactivityControlSystemRedundancyandCapability(Criterion26)3.1.2.3.8CombinedReactivityControlSystemsCapability(Criterion27)3.1.2.3.9ReactivityLimits(Criterion28)3.1.2.3.10ProtectionAgainstAnticipatedOperationalOccurrences(Criterion29)3.1.2.4FluidSystems(GroupIV)3.1.2.4.1QualityofReactorCoolantPressureBoundary(Criterion30)

SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-ii3.1.2.4.2FracturePreventionofReactorCoolantPressureBoundary(Criterion31)3.1.2.4.3InspectionofReactorCoolantPressureBoundary(Criterion32)3.1.2.4.4ReactorCoolantMakeup(Criterion33)3.1.2.4.5ResidualHeatRemoval(Criterion34)3.1.2.4.6EmergencyCoreCooling(Criterion35)3.1.2.4.7InspectionofEmergencyCoreCoolingSystem(Criterion36)3.1.2.4.8TestingofEmergencyCoreCoolingSystem(Criterion37)3.1.2.4.9ContainmentHeatRemoval(Criterion38)3.1.2.4.10InspectionofContainmentHeatRemovalSystem(Criterion39)3.1.2.4.11TestingofContainmentHeatRemovalSystem(Criterion40)3.1.2.4.12ContainmentAtmosphereCleanup(Criterion41)3.1.2.4.13InspectionofContainmentAtmosphereCleanupSystems(Criterion42)3.1.2.4.14TestingofContainmentAtmosphereCleanupSystems(Criterion43)3.1.2.4.15CoolingWater(Criterion44)3.1.2.4.16InspectionofCoolingWaterSystem(Criterion45)3.1.2.4.17TestingofCoolingWaterSystem(Criterion46)3.1.2.5ReactorContainment(GroupV)3.1.2.5.1ContainmentDesignBasis(Criterion50)3.1.2.5.2FracturePreventionofContainmentPressureBoundary(Criterion51)3.1.2.5.3CapabilityforContainmentLeakageRateTesting(Criterion52)3.1.2.5.4ProvisionsforContainmentTesting&Inspection(Criterion53)3.1.2.5.5PipingSystemsPenetratingContainment(Criterion54)3.1.2.5.6ReactorCoolantPressureBoundaryPenetratingContainment(Criterion55)3.1.2.5.7PrimaryContainmentIsolation(Criterion56)3.1.2.5.8ClosedSystemIsolationValves(Criterion57)3.1.2.6FuelandRadioactivityControl(GroupVI)3.1.2.6.1ControlofReleaseofRadioactiveMaterialstotheEnvironment(Criterion60)3.1.2.6.2FuelStorageandHandlingandRadioactivityControl(Criterion61)3.1.2.6.3PreventionofCriticalityinFuelStorageandHandling(Criterion62)3.1.2.6.4MonitoringFuelandWasteStorage(Criterion63)3.1.2.6.5MonitoringRadioactivityReleases(Criterion64)3.2CLASSIFICATIONOFSTRUCTURES,COMPONENTSANDSYSTEMS 3.2.1SeismicClassification 3.2.2SystemQualityGroupClassification SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-iii3.2.2.1QualityGroupD(Augmented)3.2.3SystemSafetyClassifications 3.2.3.1SafetyClass13.2.3.1.1DefinitionofSafetyClass13.2.3.2SafetyClass23.2.3.2.1DefinitionofSafetyClass23.2.3.3SafetyClass33.2.3.3.1DefinitionofSafetyClass33.2.3.4OtherStructures,SystemsandComponents3.2.3.4.1DefinitionofOtherStructures,Systems,andComponents3.2.3.4.2DesignRequirementsforOtherStructures,SystemsandComponents3.2.4QualityAssurance 3.2.5CorrelationofSafetyClasseswithIndustryCodes 3.3WINDANDTORNADOLOADINGS 3.3.1WindLoadings 3.3.1.1DesignWindVelocity3.3.1.2DeterminationofAppliedForces3.3.2TornadoLoadings 3.3.2.1ApplicableDesignParameters3.3.2.2DeterminationofForcesonStructures3.3.2.3EffectofFailureofStructuresorComponentsNotDesignedforTornado Loads3.3.2.4Safety-RelatedEquipmentNotProtectedByReinforcedConcrete3.3.3References 3.4WATERLEVEL(FLOOD)DESIGN SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-iv3.5MISSILEPROTECTION3.5.1MissileSelectionandDescription 3.5.1.1InternallyGeneratedMissiles(OutsidePrimaryContainment)3.5.1.1.1RotatingComponentFailureMissiles3.5.1.1.2PressurizedComponentFailureMissiles3.5.1.2InternallyGeneratedMissiles(InsideContainment)3.5.1.2.1RotatingComponentFailureMissiles3.5.1.2.2PressurizedComponentFailureMissiles3.5.1.2.3GravitationallyGeneratedMissiles3.5.1.3TurbineMissiles3.5.1.3.1TurbinePlacementandOrientation3.5.1.3.2MissileIdentificationandCharacteristics3.5.1.3.3ProbabilityAnalysis3.5.1.4MissilesGeneratedbyNaturalPhenomena3.5.1.5SiteProximityMissiles3.5.1.6AircraftHazards3.5.1.6.1AirportOperations3.5.1.6.2AircraftCrashProbability3.5.1.6.3CriticalTargetAreaforthePlant3.5.1.6.4StrikingProbabilities3.5.2SystemstobeProtected 3.5.2.1MissileProtectionDesignPhilosophy3.5.2.2StructuresDesignedtoWithstandMissileEffects3.5.3BarrierDesignProcedures 3.5.4References 3.6PROTECTIONAGAINSTDYNAMICEFFECTSASSOCIATEDWITHTHEPOSTULATEDRUPTUREOFPIPING3.6.1PostulatedPipingFailuresinFluidSystems 3.6.1.1DesignBases3.6.1.2Description3.6.1.2.1MainSteamSystem SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-v3.6.1.2.2FeedwaterSystem3.6.1.2.3HighPressureCoolantInjection(HPCI)System3.6.1.2.4ReactorCoreIsolationCooling(RCIC)System3.6.1.3SafetyEvaluation3.6.2DeterminationofPipeFailureLocationsandDynamicEffectsAssociatedwiththePostulatedPipingFailure3.6.2.1CriteriaUsedtoDeterminePipeBreakandCrackLocationsandtheirConfigurations3.6.2.1.1HighEnergyFluidSystemPipingOtherThanRecirculationSystemPiping3.6.2.1.2ModerateEnergyFluidSystemPipingOtherRecirculationPipingSystem3.6.2.1.3TypesofBreaksandLeakageCracksinFluidSystemPipingOtherThanRecirculationPipingSystem3.6.2.1.4CriteriaforRecirculationSystemPiping(NSSSSupply)3.6.2.1.4.1DefinitionofHighEnergyFluidSystem3.6.2.1.4.2DefinitionofModerateEnergyFluidSystem3.6.2.1.4.3PostulatedPipeBreaks3.6.2.1.4.4ExemptionsfromPipeWhipProtectionRequirements3.6.2.1.4.5LocationforPostulatedPipeBreaks3.6.2.1.4.6TypesofBreakstobePostulatedinFluidSystemPiping3.6.2.1.5HighEnergyFluidSystemsWithandWithoutSufficientCapacitytoDevelopaJetStream3.6.2.2AnalyticalModelstoDefineForcingFunctionsandResponseModels3.6.2.2.1ForPipingOtherThanRecirculationPipingSystem3.6.2.2.2AnalyticMethodstoDefineBlowdownForcingFunctionsandResponseModelsforRecirculationPipingSystem(NSSSSupply)3.6.2.2.2.1AnalyticalMethodstoDefineBlowdownForcingFunctions3.6.2.2.2.2PipeWhipDynamicResponseAnalysesforRecirculationPipingSystem3.6.2.3DynamicAnalysisMethodstoVerifyIntegrityandOperability3.6.2.3.1ForPipingOtherThanRecirculationPipingSystem3.6.2.3.1.1DesignLoadingCombinations3.6.2.3.1.2DesignStressLimits3.6.2.3.2DynamicAnalysisMethodstoVerifyIntegrityandOperabilityforRecirculationPipingSystem(NSSSSupply)3.6.2.3.2.1JetImpingementAnalysesandEffectsonSafetyRelatedComponentsResultingfromPostulatedRupturesoftheRecirculationPipingSystem SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-vi3.6.2.3.2.2PipeWhipEffectsFollowingaPostulatedRuptureoftheRecirculationSystemPiping3.6.2.3.2.3LoadingCombinationsandDesignCriteriaforRecirculationPipingPipeWhipRestraints3.6.2.4GuardPipeAssemblyDesignCriteria3.6.2.5MaterialtobeSubmittedforOperatingLicenseReview3.6.2.5.1ForPipingOtherThanRecirculationPipingSystem3.6.2.5.2ImplementationofCriteriaforPipeBreakandCrackLocationandOrientationforRecirculationPipingSystem(NSSSSUPPLY)3.6.2.5.2.1PostulatedPipeBreaksinRecirculationPipingSystem-InsideContainment3.6.2.5.2.2ImplementationofSpecialProtectionCriteria3.6.2.5.2.3JetEffectsforPostulatedRupturesofRecirculationSystemPiping3.6.3Definitions 3.6.4References 3.6APIPEBREAKOUTSIDECONTAINMENT

SUMMARY

OFANALYSISANDRESULTS3.7aSEISMICDESIGN 3.7a.1SeismicInput 3.7a.1.1DesignResponseSpectra3.7a.1.2DesignTimeHistory3.7a.1.3CriticalDampingValues3.7a.1.4SupportingMediaforSeismicCategoryIStructures3.7a.2SeismicSystemAnalysis 3.7a.2.1SeismicAnalysisMethods3.7a.2.1.1TheEquationsofDynamicEquilibrium3.7a.2.1.2SolutionoftheEquationsofMotionbyModeSuperposition3.7a.2.1.3AnalysisbyResponseSpectrum3.7a.2.1.4SupportDisplacementsinMulti-SupportedStructure3.7a.2.1.5DynamicAnalysisofSeismicCategoryIStructures,Systems,andComponents3.7a.2.1.5.1DynamicAnalysisofPipingSystems SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-vii3.7a.2.1.5.2DynamicAnalysisofEquipment3.7a.2.1.5.2.1DifferentialSeismicMovementofInterconnectedComponents3.7a.2.1.6SeismicQualificationbyTesting3.7a.2.2NaturalFrequenciesandResponseLoads3.7a.2.3ProcedureUsedforModeling3.7a.2.3.1ModelingTechniquesforSeismicCategoryIStructures,Systems,andComponents3.7a.2.3.2ModelingofReactorPressureVesselandInternals3.7a.2.3.3ComparisonofResponses3.7a.2.4SoilStructureInteraction3.7a.2.5DevelopmentofFloorResponseSpectra3.7a.2.6ThreeComponentsofEarthquakeMotion3.7a.2.7CombinationofModelResponses3.7a.2.8InteractionofNon-CategoryIStructureswithSeismicCategoryIStructures3.7a.2.9EffectsofParameterVariationsonFloorResponseSpectra3.7a.2.10UseofConstantVerticalStaticFactors3.7a.2.11MethodsUsedtoAccountforTorsionalEffects3.7a.2.12ComparisonofResponses3.7a.2.13MethodsforSeismicAnalysisofDams3.7a.2.14DeterminationofSeismicCategoryIStructureOverturningMoments3.7a.2.15AnalysisProcedureforDamping3.7a.3SeismicSubsystemAnalysis 3.7a.3.1SeismicAnalysisMethods3.7a.3.2DeterminationofNumberofEarthquakeCycles3.7a.3.3ProcedureUsedforModeling3.7a.3.3.1ModelingofPipingSystems3.7a.3.3.2ModelingofEquipment3.7a.3.3.3LocationofSupportsandRestraints3.7a.3.4BasisofSelectionofFrequencies3.7a.3.5UseofEquivalentStaticLoadMethodofAnalysis3.7a.3.6ThreeComponentsofEarthquakeMotion3.7a.3.6.1ResponseSpectrumMethod3.7a.3.6.2TimeHistoryMethod3.7a.3.7CombinationofModalResponses3.7a.3.8AnalyticalProcedureforPiping3.7a.3.9MultiplySupportedEquipmentandComponentswithDistinctInputs3.7a.3.10UseofConstantVerticalStaticFactors SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-viii3.7a.3.11TorsionalEffectsofEccentricMasses3.7a.3.12BuriedSeismicCategoryIPipingSystemsandTunnels3.7a.3.13InteractionofOtherPipingwithSeismicCategoryIPiping3.7a.3.14SeismicAnalysisforReactorInternals3.7a.3.15AnalysisProceduresforDamping3.7a.4SeismicInstrumentation 3.7a.5References 3.7bSEISMICDESIGN 3.7b.1SeismicInput 3.7b.1.1DesignResponseSpectra3.7b.1.2DesignTimeHistory3.7b.1.3CriticalDampingValues(Non-NSSS)3.7b.1.4SupportingMediaforSeismicCategoryIStructures3.7b.2SeismicSystemAnalysis 3.7b.2.1SeismicAnalysisMethods3.7b.2.1.1FlexibleBaseandFixedBaseContainmentModels3.7b.2.2NaturalFrequenciesandResponseLoads3.7b.2.3ProcedureUsedforModeling3.7b.2.4SoilStructureInteraction3.7b.2.5DevelopmentofFloorResponseSpectra3.7b.2.6ThreeComponentsofEarthquakeMotion3.7b.2.7CombinationofModalResponses3.7b.2.8InteractionofNon-CategoryIStructuresWithSeismicCategoryIStructures3.7b.2.9EffectsofParameterVariationsonFloorResponseSpectra3.7b.2.10UseofConstantVerticalStaticFactors3.7b.2.11MethodsUsedtoAccountforTorsionalEffects3.7b.2.11.1TorsionalAnalysisofDieselGeneratorBuildingA-D&ESSWPumphouse3.7b.2.11.2TorsionalAnalysisoftheReactor/ControlBuilding3.7b.2.12ComparisonofResponses3.7b.2.13MethodsforSeismicAnalysisofDams3.7b.2.14DeterminationofSeismicCategoryIStructureOverturningMoments SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-ix3.7b.2.15AnalysisProcedureforDamping3.7b.3SeismicSubsystemAnalysis 3.7b.3.1SeismicAnalysisMethods3.7b.3.1.1Equipment3.7b.3.1.1.1Analysis3.7b.3.1.1.2DynamicTesting3.7b.3.1.1.3CombinationofAnalysisandDynamicTesting3.7b.3.1.2PipingSystems3.7b.3.1.3ClassIECableTrays3.7b.3.1.4SupportsforSeismicCategoryIHVACDucts3.7b.3.1.5ConcreteBlockMasonryStructures(Blockwalls)3.7b.3.1.6SupportsofSeismicCategoryIElectricalRacewaySystems3.7b.3.1.6.1LoadingCombinations3.7b.3.1.6.2AnalyticalTechniques3.7b.3.1.6.3Damping3.7b.3.1.6.4OperatingBasisEarthquake(OBE)3.7b.3.2DeterminationofNumberofEarthquakeCycles3.7b.3.3ProcedureUsedforModeling3.7b.3.4BasisforSelectionofFrequencies3.7b.3.5UseofEquivalentStaticLoadMethodofAnalysis3.7b.3.6ThreeComponentsofEarthquakeMotion3.7b.3.7CombinationofModalResponses3.7b.3.8AnalyticalProceduresforPiping3.7b.3.9MultipleSupportedEquipmentandComponentswithDistinctInputs3.7b.3.10UseofConstantVerticalStaticFactors3.7b.3.11TorsionalEffectsofEccentricMasses3.7b.3.12BuriedSeismicCategoryIPipingSystemsandTunnels3.7b.3.13InteractionofOtherPipingWithSeismicCategoryIPiping3.7b.3.14SeismicAnalysisforReactorInternals3.7b.3.15AnalysisProcedureforDamping3.7b.4SeismicInstrumentation 3.7b.4.1ComparisonwithNRCRegulatoryGuide1.12,Rev.13.7b.4.1.1TriaxialTime-HistoryAccelerographs3.7b.4.1.2TriaxialPeakAccelerographs3.7b.4.1.3TriaxialSeismicSwitches3.7b.4.1.4TriaxialResponseRecorders SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-x3.7b.4.2DescriptionofInstrumentation3.7b.4.3ControlRoomOperatorNotification3.7b.4.4ComparisonofMeasuredandPredictedResponses3.7b.5References 3.8DESIGNOFCATEGORYISTRUCTURES 3.8.1ConcreteContainment 3.8.1.1DescriptionoftheContainment3.8.1.1.1General3.8.1.1.1.1Dimensions3.8.1.1.2BaseFoundationSlab3.8.1.1.2.1Reinforcement3.8.1.1.2.2LinerPlateandAnchorages3.8.1.1.2.3PedestalandSuppressionChamberColumnBaseLineAnchorages3.8.1.1.3ContainmentWall3.8.1.1.3.1Reinforcement3.8.1.1.3.2LinerPlateandAnchorages3.8.1.1.3.3Penetrations3.8.1.1.3.4InternalContainmentAttachments3.8.1.1.3.5ExternalContainmentAttachments3.8.1.1.3.6SteelComponentsNotBackedbyStructuralConcrete3.8.1.2ApplicableCodes,Standards,&Specifications3.8.1.3Loads&LoadingCombinations3.8.1.3.1General3.8.1.3.2DescriptionofLoads3.8.1.3.2.1DeadLoad3.8.1.3.2.2LiveLoad3.8.1.3.2.3DesignBasisAccidentPressureLoad3.8.1.3.2.4ThermalLoads3.8.1.3.2.5WindandTornadoLoads3.8.1.3.2.6SeismicLoads3.8.1.3.2.7ExternalPressureLoad3.8.1.3.2.8MissileandPipeRuptureLoads3.8.1.4DesignandAnalysisProcedures3.8.1.4.1General3.8.1.4.2ContainmentWall3.8.1.4.3BaseFoundationSlab SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xi3.8.1.4.4AnalysisofAreasAroundEquipmentHatches3.8.1.4.5LinerPlateandAnchorages3.8.1.5StructuralAcceptanceCriteria3.8.1.5.1ReinforcedConcrete3.8.1.5.1.1WorkingStress3.8.1.5.1.2StrengthMethod3.8.1.5.2LinerPlateandAnchorages3.8.1.6Materials,QualityControl,andSpecialConstructionTechniques3.8.1.6.1ConcreteContainment3.8.1.6.2LinerPlate,Anchorages,andAttachments3.8.1.6.2.1Materials3.8.1.6.2.2Welding3.8.1.6.2.3MaterialsTesting3.8.1.6.2.4NondestructiveExaminationofLinerPlateSeamWelds3.8.1.6.2.5QualityControl3.8.1.6.2.6ErectionTolerances3.8.1.7TestingandIn-ServiceSurveillanceRequirements3.8.1.7.1PreoperationalTesting3.8.1.7.1.1StructuralAcceptanceTest3.8.1.7.1.2LeakRateTesting3.8.1.7.2In-ServiceLeakRateTesting3.8.2ASMEClassMCSteelComponentsoftheContainment 3.8.2.1DescriptionoftheASMEClassMCComponents3.8.2.1.1DrywellHeadAssembly3.8.2.1.2EquipmentHatchesandPersonalLock3.8.2.1.3SuppressionChamberAccessHatches3.8.2.1.4CRDRemovalHatch3.8.2.1.5Penetrations3.8.2.2ApplicableCodes,Standards,andSpecifications3.8.2.3LoadsandLoadingCombinations3.8.2.3.1General3.8.2.3.2DescriptionofLoads3.8.2.3.2.1DeadandLiveLoad3.8.2.3.2.2DesignBasisAccidentPressureLoad3.8.2.3.2.3ExternalPressureLoad3.8.2.3.2.4ThermalLoads3.8.2.3.2.5SeismicLoads3.8.2.3.2.5.1DesignBasisLoads SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xii3.8.2.3.2.6MissileandPipeRuptureLoads3.8.2.4DesignandAnalysisProcedures3.8.2.4.1DrywellHeadAssembly3.8.2.4.2AccessHatches3.8.2.4.3PipeandElectricalPenetrations3.8.2.5StructuralAcceptanceCriteria3.8.2.6Materials,QualityControl,andSpecialConstructionTechniques3.8.2.6.1Materials3.8.2.6.1.1General3.8.2.6.1.2DrywellHeadAssembly3.8.2.6.1.3AccessHatches3.8.2.6.1.4Penetrations3.8.2.6.2Welding3.8.2.6.3MaterialsTesting3.8.2.6.4NondestructiveExaminationofWelds3.8.2.6.5QualityControl3.8.2.6.6ErectionTolerances3.8.2.7TestingandIn-serviceInspectionRequirements3.8.2.7.1PreoperationalTesting3.8.2.7.1.1StructuralAcceptanceTest3.8.2.7.1.2LeakRateTesting3.8.2.7.2In-serviceLeakRateTesting3.8.3ContainmentInternalStructures 3.8.3.1DescriptionoftheInternalStructures3.8.3.1.1DrywellFloor3.8.3.1.2ReactorPedestal3.8.3.1.3ReactorShieldWall3.8.3.1.4SuppressionChamberColumns3.8.3.1.5DrywellPlatforms3.8.3.1.6SeismicTrussandSeismicStabilizer3.8.3.1.7ReactorSteamSupplySystemSupports3.8.3.2ApplicableCodes,Standards,andSpecifications3.8.3.3LoadsandLoadingCombinations3.8.3.3.1General3.8.3.3.2DrywellFloorandReactorPedestal3.8.3.3.2.1DescriptionofLoads3.8.3.3.3ReactorShieldWall3.8.3.3.3.1DescriptionofLoads SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xiii3.8.3.3.4SuppressionChamberColumns3.8.3.3.5DrywellPlatforms3.8.3.3.6SeismicTruss3.8.3.4DesignandAnalysisProcedures3.8.3.4.1DrywellFloor3.8.3.4.2DrywellFloorLinerPlateandAnchorages3.8.3.4.3ReactorPedestal3.8.3.4.4ReactorShieldWall3.8.3.4.5SuppressionChamberColumns3.8.3.4.6DrywellPlatforms3.8.3.4.7SeismicTruss3.8.3.5StructuralAcceptanceCriteria3.8.3.5.1ReinforcedConcrete3.8.3.5.2DrywellFloorLinerPlateandAnchorages3.8.3.5.3StructuralSteel3.8.3.6Materials,QualityControl,andSpecialConstructionTechniques3.8.3.6.1ConcreteContainmentInternalStructures3.8.3.6.2DrywellFloorLinerPlate,Anchorages,Attachments3.8.3.6.2.1Materials3.8.3.6.2.2Welding3.8.3.6.2.3NondestructiveExaminationofLinerPlateSeamWelds3.8.3.6.2.4ErectionTolerances3.8.3.6.3ReactorShieldWallandSeismicTruss3.8.3.6.3.1Materials3.8.3.6.3.2WeldingandNondestructiveExaminationofWelds3.8.3.6.3.3MaterialsTesting3.8.3.6.3.4ErectionTolerances3.8.3.6.4SuppressionChamberColumns3.8.3.6.4.1Materials3.8.3.6.4.2Welding3.8.3.6.4.3NondestructiveExaminationofWelds3.8.3.6.4.4FabricationandErectionTolerances3.8.3.6.5DrywellPlatforms3.8.3.6.5.1Materials3.8.3.6.5.2WeldingandNondestructiveExaminationofWelds3.8.3.6.5.3ErectionTolerances3.8.3.6.6QualityControl3.8.3.7TestingandIn-serviceInspectionRequirements3.8.3.7.1PreoperationalTesting3.8.3.7.1.1StructuralAcceptanceTest SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xiv3.8.3.7.1.2LeakRateTesting3.8.3.7.2In-serviceLeakRateTesting3.8.4OtherSeismicCategoryIStructures 3.8.4.1DescriptionoftheStructures3.8.4.2ApplicableCodes,Standards,andSpecifications3.8.4.3LoadsandLoadCombinations3.8.4.3.1DescriptionofLoads3.8.4.3.2LoadCombinations3.8.4.4DesignandAnalysisProcedures3.8.4.5StructuralAcceptanceCriteria3.8.4.6Materials,QualityControl,andSpecialConstructionTechniques3.8.4.6.1ConcreteandReinforcingSteel3.8.4.6.2StructuralSteel3.8.4.6.2.1Materials3.8.4.6.2.2WeldingandNondestructiveTesting3.8.4.6.2.3FabricationandErection3.8.4.6.2.4QualityControl3.8.4.6.3SpecialConstructionTechniques3.8.4.7TestingandIn-serviceInspectionRequirements3.8.4.8ComputerProgramsUsedintheDesignandAnalysisofOtherSeismicCategoryIStructures3.8.5Foundations 3.8.5.1DescriptionoftheFoundations3.8.5.2ApplicableCodes,Standards,andSpecification3.8.5.3LoadsandLoadCombinations3.8.5.4DesignandAnalysisProcedures3.8.5.5StructuralAcceptanceCriteria3.8.5.6Materials,QualityControl,andSpecialConstructionTechniques3.8.5.7TestingandIn-serviceInspectionRequirements3.8ACOMPUTERPROGRAMS 3.8A.1D/SAP3.8A.2ASHSD3.8A.3CECAP3.8A.4CE668 SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xv3.8A.5EASE3.8A.6EO1193.8A.7EO7813.8A.8FINEL3.8A.9ME6203.8A.10SUPERB3.8A.11References3.8BCONCRETE,CONCRETEMATERIALS,QUALITYCONTROL,ANDSPECIALCONSTRUCTIONTECHNIQUES3.8B.1ConcreteandConcreteMaterials-Qualifications3.8B.1.1ConcreteMaterialQualifications3.8B.1.2ConcreteMixDesign3.8B.1.3Grout3.8B.2ConcreteandConcreteMaterials-Batching,Placing,CuringandProtection3.8B.2.1Storage3.8B.2.2Batching,Mixing,andDelivering3.8B.2.3Placing3.8B.2.4Consolidation3.8B.2.5Curing3.8B.2.6HotandColdWeatherConcreting3.8B.3ConcreteandConcreteMaterials-ConstructionTesting 3.8B.4ConcreteReinforcementMaterials-Qualifications 3.8B.5ConcreteReinforcementMaterials-Fabrication 3.8B.5.1BendingReinforcement3.8B.5.2SplicingReinforcement3.8B.5.3PlacingReinforcement3.8B.5.4SpacingReinforcement3.8B.5.5SurfaceCondition3.8B.6ConcreteReinforcementMaterials-ConstructionTesting SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xvi3.8B.7FormworkandConstructionJoints3.8CCONCRETEUNITMASONRY,MASONRYMATERIALSANDQUALITYCONTROL3.8C.1ConcreteUnitMasonryandMasonryMaterials-Qualifications3.8C.2ConcreteUnitMasonryandMasonryMaterials-ConstructionandErection3.8C.3ConcreteUnitMasonryandMasonryMaterials-ConstructionTesting3.9MECHANICALSYSTEMSANDCOMPONENTS 3.9.1SpecialTopicsforMechanicalComponents 3.9.1.1DesignTransients3.9.1.1.1ControlRodDriveTransients3.9.1.1.2CRDHousingandIncoreHousingTransients3.9.1.1.3HydraulicControlUnitTransients3.9.1.1.4CoreSupportandReactorInternalsTransients3.9.1.1.5MainSteamSystemTransients3.9.1.1.6RecirculationSystemTransients3.9.1.1.7ReactorAssemblyTransients3.9.1.1.8MainSteamIsolationValveTransients3.9.1.1.9Safety/ReliefValvesTransients3.9.1.1.10RecirculationFlowControlValveTransients3.9.1.1.11RecirculationPumpTransients3.9.1.1.12RecirculationGateValveTransients3.9.1.2ComputerProgramsUsedinAnalysis3.9.1.2.1ReactorVesselandInternals3.9.1.2.1.1ReactorVessel3.9.1.2.1.1.1CB&IProgram711-"GENOZZ"3.9.1.2.1.1.2CB&IProgram948-"NAPALM"3.9.1.2.1.1.3CB&IProgram10273.9.1.2.1.1.4CB&IProgram8463.9.1.2.1.1.5CB&IProgram781-"KALNINS"3.9.1.2.1.1.6CB&IProgram979-"ASFAST"3.9.1.2.1.1.7CB&IProgram766-"TEMAPR"3.9.1.2.1.1.8CB&IProgram767-"PRINCESS"3.9.1.2.1.1.9CB&IProgram928-"TGRV"3.9.1.2.1.1.10CB&IProgram962-"EO962A" SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xvii3.9.1.2.1.1.11CB&IProgram9843.9.1.2.1.1.12CB&IProgram992-GASP3.9.1.2.1.1.13CB&IProgram1037-"DUNHAM'S"3.9.1.2.1.1.14CB&IProgram13353.9.1.2.1.1.15CB&IPrograms1606and1657-"HAP"3.9.1.2.1.1.16CB&IProgram1634N3.9.1.2.1.2ReactorInternals3.9.1.2.2Piping3.9.1.2.2.1StructuralAnalysisProgramSAP43.9.1.2.2.2ComponentAnalysis/ANSI73.9.1.2.2.3IntegralAttachment/LUGSTR3.9.1.2.2.4PipingAnalysisProgram/PISVS3.9.1.2.2.5ReliefValveDischargePipeForces/RVF0R3.9.1.2.2.6TurbineStopValveClosure/TSFOR3.9.1.2.2.7PipingAnalysisProgram/EZPYP3.9.1.2.2.8PipeWhipAnalysis/PDA3.9.1.2.3RecirculationandECCSPumpsandMotors3.9.1.2.3.1RecirculationPumps3.9.1.2.3.2ECCSPumpsandMotors3.9.1.2.3.2.1StructuralAnalysisProgram/SAPAG3.9.1.2.3.2.2EffectsofFlangeJointConnections/FTFLG013.9.1.2.3.2.3StructuralAnalysisofDischargeHead/ANSYS3.9.1.2.3.2.4BeamElementDataProcessing/POSUM3.9.1.2.4RHRHeatExchanges3.9.1.2.4.1StructuralAnalysisPrograms/SAPAG3.9.1.2.4.2ShellAttachmentParametersandCoefficients/BILRD3.9.1.2.4.3BeamElementDataProcessing/POSUM3.9.1.2.5DynamicLoadsAnalysis3.9.1.2.5.1DynamicAnalysisProgram/DYSEA3.9.1.2.5.2AccelerationResponseSpectrumProgram/SPECA3.9.1.2.5.3FuelSupportLoadsProgram/SEISM3.9.1.3ExperimentalStressAnalysis3.9.1.3.1ExperimentalStressAnalysisofNSSSPipingComponents3.9.1.3.2SeismicCategoryItemsOtherThanNSSS3.9.1.4ConsiderationsforEvaluationoftheFaultedConditions3.9.1.4.1ControlRodDriveSystemComponents3.9.1.4.1.1ControlRodDrives3.9.1.4.1.2HydraulicControlUnit3.9.1.4.2StandardReactorInternalComponents3.9.1.4.2.1CRGuideTube SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xviii3.9.1.4.2.2IncoreHousing3.9.1.4.2.3JetPump3.9.1.4.2.4OrificedFuelSupport3.9.1.4.2.5ControlRodDriveHousing3.9.1.4.3ReactorPressureVesselAssembly3.9.1.4.4CoreSupportStructure3.9.1.4.5MainSteamIsolation,RecirculationGateandSafety/ReliefValves3.9.1.4.6MainSteamandRecirculationPiping3.9.1.4.7NuclearSteamSupplySystemPumps,HeatExchanger,andTurbines3.9.1.4.8ControlRodDriveHousingSupports3.9.1.4.9FuelStorageRacks3.9.1.4.10FuelAssembly(IncludingChannels)3.9.1.4.11RefuelingEquipment3.9.1.4.12SeismicCategoryIItemsOtherThanNSSS3.9.2DynamicTestingandAnalysis 3.9.2.1aPreoperationalVibrationandDynamicEffectsTestingonNSSSPiping3.9.2.1a.1PreoperationalVibrationTesting3.9.2.1a.2SmallAttachedPiping3.9.2.1a.3StartupVibration3.9.2.1a.4OperatingTransientLoads3.9.2.1a.5TestEvaluationandAcceptanceCriteria3.9.2.1a.5.1LevellCriterion3.9.2.1a.5.2Level2Criterion3.9.2.1a.6CorrectiveActions3.9.2.1a.7MeasurementLocations3.9.2.1bPreoperationalThermalVibrationandDynamicEffectsTestingofPipingOtherThanNSSS3.9.2.1b.1PipingDynamicTransientTests3.9.2.1b.2PipingSteadyStateVibrationTesting3.9.2.2aSeismicandHydrodynamicQualificationofSafety-RelatedNSSSMechanicalEquipment3.9.2.2a.1TestsandAnalysisCriteriaandMethods3.9.2.2a.1.1TestInputMotion3.9.2.2a.1.2ApplicationofInputMotion3.9.2.2a.1.3FixtureDesign3.9.2.2a.1.4PrototypeTesting3.9.2.2a.2SeismicandHydrodynamicQualificationofSpecificMechanicalComponents SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xix3.9.2.2a.2.1JetPumps3.9.2.2a.2.2CRDandCRDHousing3.9.2.2a.2.3CoreSupport(OrificedFuelSupportandCRGuideTube)3.9.2.2a.2.4HydraulicControlUnit(HCU)3.9.2.2a.2.5FuelChannels3.9.2.2a.2.6RecirculationPumpandMotorAssembly3.9.2.2a.2.7ECCSPumpandMotorAssembly3.9.2.2a.2.8RCICPumpAssembly3.9.2.2a.2.9RCICTurbineAssembly3.9.2.2a.2.10StandbyLiquidControlPumpandMotorAssembly3.9.2.2a.2.11RHRHeatExchangers3.9.2.2a.2.12SafetyReliefValves(SRV)3.9.2.2a.2.13StandbyLiquidControlTank3.9.2.2a.2.14MainSteamIsolationValves3.9.2.2a.2.15MainSteamSafety/ReliefValves3.9.2.2a.2.16HPCITurbine3.9.2.2a.2.17HPCIPump3.9.2.2bSeismicQualificationTestingofSafetyRelatedNon-NSSSMechanicalEquipment3.9.2.2b.1Safety-RelatedandSafety-ImpactedMechanicalEquipmentOtherThanfortheNSSS3.9.2.2b.1.1DynamicAnalysisWithoutTesting3.9.2.2b.1.2DynamicTesting3.9.2.2b.2Criteria3.9.2.3DynamicResponseofReactorInternalsUnderOperationalFlowTransientsandSteadyStateConditions3.9.2.4ConfirmatoryFlow-InducedVibrationTestingofReactorInternals3.9.2.5DynamicSystemAnalysisoftheReactorInternalsUnderFaultedConditions3.9.2.6CorrelationsofReactorInternalsVibrationTestResultswiththeAnalyticalResults3.9.3ASMECodeClass1,2,and3Components,ComponentSupports,andCoreSupportStructures3.9.3.1LoadingCombinations,DesignTransientsandStressLimits3.9.3.1.1PlantConditions3.9.3.1.1.1NormalCondition3.9.3.1.1.2UpsetCondition3.9.3.1.1.3EmergencyCondition SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xx3.9.3.1.1.4FaultedCondition3.9.3.1.1.5CorrelationofPlantConditionswithEventProbability3.9.3.1.1.6SafetyClassFunctionalCriteria3.9.3.1.1.7CompliancewithRegulatoryGuide1.483.9.3.1.2ReactorVesselAssembly3.9.3.1.3MainSteamPiping3.9.3.1.4RecirculationLoopPiping3.9.3.1.5RecirculationSystemValves3.9.3.1.6RecirculationPump3.9.3.1.7StandbyLiquidControl(SLC)Tank3.9.3.1.8ResidualHeatRemovalHeatExchangers3.9.3.1.9RCICTurbine3.9.3.1.10RCICPump3.9.3.1.11ECCSPumps3.9.3.1.12StandbyLiquidControlPump3.9.3.1.13MainSteamIsolationValvesandSafety/ReliefValves3.9.3.1.14SafetyReliefValvePiping3.9.3.1.15HighPressureCoolantInjection(HPCI)Turbine3.9.3.1.16HighPressureCoolantInjection(HPCI)Pump3.9.3.1.17ReactorWaterClean-up(RWCU)System3.9.3.1.18ThisSectionHasBeenIntentionallyDeleted3.9.3.1.19ASMECodeConstructedItemsNotFurnishedwiththeNSSS3.9.3.2aNSSSPumpandValveOperabilityAssurance3.9.3.2a.1ECCSPumps3.9.3.2a.1.1AnalysisofLoading,Stress,andAccelerationConditions3.9.3.2a.1.2PumpOperationDuringandFollowingFaultedConditionLoading3.9.3.2a.2SLCPumpandMotorAssemblyandRCICPumpAssembly3.9.3.2a.3RCICTurbine3.9.3.2a.4ECCSMotors3.9.3.2a.5NSSSValves3.9.3.2a.5.1MainSteamIsolationValve3.9.3.2a.5.2MainSteamSafety/ReliefValves3.9.3.2a.5.3RecirculationGateValves3.9.3.2a.5.4ExplosiveValves3.9.3.2a.6HPCITurbine3.9.3.2bNon-NSSSPumpandValveOperabilityAssurance3.9.3.2b.1Pumps3.9.3.2b.1.1AnalysisofLoading,Stress,andAccelerationConditions3.9.3.2b.1.2PumpOperationDuringandFollowingSSELoading3.9.3.2b.2Valves SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxi3.9.3.3aDesignandInstallationofNSSSSuppliedPressureReliefDevices3.9.3.3a.1MainSteamSafety/ReliefValves3.9.3.3bDesignandInstallationDetailsforMountingofPressureReliefDevicesinASMECodeClass1and2Systems3.9.3.4ComponentSupports3.9.3.4.1RecirculationPipingSupports3.9.3.4.2ReactorPressureVesselSupportSkirt3.9.3.4.3NSSSFloor-MountedEquipment(Pumps,HeatExchangersandRCICTurbine)3.9.3.4.4SupportsforASMECodeClass1,2and3ActiveComponents3.9.3.4.5HPCITurbine3.9.3.4.6Non-NSSSSupports3.9.3.4.6.1Snubbers3.9.3.4.6.1.1SnubberDesignSpecification3.9.3.4.6.1.2SnubberAnalysisModel3.9.4ControlRodDriveSystem 3.9.4.1DescriptiveInformationonCRDS3.9.4.2ApplicableCRDSDesignSpecifications3.9.4.3DesignLoads,StressLimits,andAllowableDeformation3.9.4.3.1ControlRodDriveHousingSupports3.9.4.4CRDPerformanceAssuranceProgram3.9.5ReactorPressureVesselInternals 3.9.5.1DesignArrangements3.9.5.1.1CoreSupportStructures3.9.5.1.1.1Shroud3.9.5.1.1.2ShroudHeadandSteamSeparatorAssembly3.9.5.1.2CorePlate3.9.5.1.3TopGuide3.9.5.1.4FuelSupport3.9.5.1.5ControlRodGuideTubes3.9.5.1.6JetPumpAssemblies3.9.5.1.7SteamDryers3.9.5.1.8FeedwaterSpargers3.9.5.1.9CoreSprayLines3.9.5.1.10VesselHeadSprayNozzle3.9.5.1.11DifferentialPressureandLiquidControlLine SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxii3.9.5.1.12In-CoreFluxMonitorGuideTubes3.9.5.1.13SurveillanceSampleHolders3.9.5.2DesignLoadingConditions3.9.5.2.1EventstobeEvaluated3.9.5.2.2PressureDifferentialDuringRapidDepressurization3.9.5.2.3RecirculationLineandSteamLineBreak3.9.5.2.3.1AccidentDefinition3.9.5.2.3.2EffectsofInitialReactorPowerandCoreFlow3.9.5.2.4SeismicandHydrodynamicLoads3.9.5.3DesignLoadingCategories3.9.5.4DesignBases3.9.5.4.1SafetyDesignBases3.9.5.4.2PowerGenerationDesignBases3.9.5.4.3ResponseofInternalsDuetoInsideSteamBreakAccident3.9.5.4.4Stress,Deformation,andFatigueLimitsforReactorInternals(ExceptCoreSupportStructure)3.9.5.4.5Stress,Deformation,andFatigueLimitsforCoreSupportStructures3.9.6In-serviceTestingofPumpsandValves 3.9.7References 3.9ACOMPUTERPROGRAMS 3.9A.1ME1013.9A.2ME6323.9A.3ME9123.9A.4ME9133.9A.5References3.10SEISMICQUALIFICATIONSOFCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENT3.10aSEISMICQUALIFICATIONOFSEISMICCATEGORYINSSSINSTRUMENTATIONANDELECTRICALEQUIPMENT3.10a.1SeismicQualificationCriteria 3.10a.1.1SeismicCategoryIEquipmentIdentification3.10a.1.2DynamicDesignCriteria SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxiii3.10a.1.2.1NSSSEquipment3.10a.2MethodsandProceduresforQualifyingElectricalEquipmentandInstrumentation(ExcludingMotorsandValveMountedEquipment)3.10a.2.1MethodsofShowingNSSSEquipmentCompliancewithIEEE344-19713.10a.2.2TestingProceduresforQualifyingElectricalEquipmentandInstrumentation(ExcludingMotorsandValveMountedEquipment)3.10a.2.3QualificationofValveMountedEquipment3.10a.2.4QualificationofNSSSMotors3.10a.3MethodsandProcedureofAnalysisorTestingofSupportsofElectricalEquipmentandInstrumentation3.10a.3.1DynamicAnalysisTestingProceduresandRestraintMeasures3.10a.3.1.1NSSSEquipment(OtherThanMotorsandValveMountedEquipment)3.10a.4OperatingLicenseReview 3.10a.4.1NSSSControlandElectricalEquipment(OtherThanMotorsandValveMountedEquipment)3.10a.4.2NSSSMotors3.10a.4.3ValveMountedEquipment3.10a.5DynamicAnalysisByResponseSpectrumMethod 3.10bSEISMICQUALIFICATIONOFNON-NSSSSUPPLIEDSEISMICCATEGORYIINSTRUMENTATION3.10b.1SeismicQualificationCriteria 3.10b.1.1SeismicCategoryIEquipmentIdentification3.10b.1.2SeismicandHydrodynamicDesignCriteria3.10b.1.2.1FunctionalCriterion3.10b.1.2.2QualificationLevels3.10b.1.2.3InstrumentationSupports3.10b.1.3DeviceQualificationTestCriteria3.10b.2SeismicCategoryIEquipmentQualification 3.10b.3MethodsandProceduresofAnalysisorTestingofSupportsofInstrumentation SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxiv3.10b.4OperatingLicenseReview3.10cSEISMICQUALIFICATIONOFNON-NSSSSEISMICCATEGORYIELECTRICALEQUIPMENT3.10c.1SeismicQualificationCriteria 3.10c.1.1EquipmentLocation3.10c.1.2ResponseSpectrumCurvesfortheElectricalEquipmentandSupports3.10c.1.3SeismicCategoryIElectricalEquipmentLoads3.10c.1.4SafeShutdownEarthquake(SSE)Conditions3.10c.1.5OperatingBasisEarthquake(OBE)Conditions3.10c.1.6PreventionofOverturningandSliding3.10c.2MethodsandProceduresforQualifyingElectricalEquipment 3.10c.2.1SeismicAnalysisMethod3.10c.2.2SeismicQualificationforElectricalEquipmentOperability3.10c.2.3SeismicTestReportAnalysisandMethods3.10c.2.3.1ElectricalEquipmentQualifiedbyTestingandCombinationofTestingandAnalysisMethod3.10c.2.3.2ElectricalEquipmentandSupportsQualifiedbyAnalysisMethod3.10c.2.3.3ElectricalEquipmentQualifiedbySuppliers'Certification3.10c.2.3.4MinimumOperatingVoltageofVoltageRelays3.10c.3MethodsandProceduresofAnalysisorTestingofSupportsofElectricalEquipment3.10c.4OperatingLicenseReview3.11ENVIRONMENTALDESIGNOFMECHANICALANDELECTRICALEQUIPMENT3.11.1EquipmentIdentificationandEnvironmentalConditions 3.11.2QualificationTestandAnalysis 3.11.2.1Class1EEquipmentQualifiedToIEEEStandard323-19713.11.2.2Class1EEquipmentQualifiedtoIEEEStandard323-1974 SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxv3.11.2.3Class1EComponentEnvironmentDesignandQualificationforNormalOperation3.11.2.4Class1EComponentEnvironmentalDesignandQualificationforOperationAfteraDesignBasisAccident3.11.3QualificationTestResults 3.11.4LossofVentilation 3.11.5EstimatedChemical,Physical,andRadiationEnvironment 3.11.5.1SuppressionPool,ResidualHeatRemovalSystem,andEmergencyCoreCoolingSystemWaterQuality3.11.5.2PhysicalEnvironment3.11.5.3RadiationEnvironment3.11.6References 3.11AAppendixHasBeenDeleted 3.12SEPARATIONCRITERIAFORSAFETYRELATEDMECHANICALANDELECTRICALPOWEREQUIPMENT3.12.1Introduction 3.12.2MechanicalSystems 3.12.2.1Criteria3.12.2.1.1GeneralCriteria3.12.2.1.2SystemSeparationCriteria3.12.2.1.3PhysicalSeparationCriteria3.12.2.2SeparationTechniques3.12.3ElectricalSystemsandEquipmentSeparationCriteria 3.12.3.1AffectedSystems3.12.3.2GeneralCriteria3.12.3.3SystemSeparationCriteria3.12.3.4ElectricalPhysicalSeparationCriteria3.12.3.4.1GeneralSeparationCriteria SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxvi3.12.3.4.2SpecificSeparationCriteria3.12.3.4.2.1CablesandRaceways3.12.3.4.2.2StandbyPowerSupply3.12.3.4.2.3DCSystem3.12.3.4.2.4DistributionSystem3.12.3.4.2.5PrimaryContainmentElectricalPenetrations3.12.3.4.2.6MainControlRoomandRelayRoomPanels3.13COMPLIANCEWITHNRCREGULATORYGUIDES 3.13.1Division1,RegulatoryGuides-PowerReactors 3.14LICENSERENEWALPROGRAMS,TLAA,ANDREGULATORYCOMMITMENTS 3.

14.1INTRODUCTION

3.14.2AGINGMANAGEMENTPROGRAMS(AMP)3.14.2.1Area-BasedNSASInspection3.14.2.2BoltingIntegrityProgram3.14.2.3BuriedPipingandTanksInspectionProgram3.14.2.4BuriedPipingSurveillanceProgram3.14.2.5BWRCRDReturnLineNozzleProgram3.14.2.6BWRFeedwaterNozzleProgram3.14.2.7BWRPenetrationsProgram3.14.2.8BWRStressCorrosionCracking(SCC)Program3.14.2.9BWRVesselIDAttachmentWeldsProgram3.14.2.10BWRVesselInternalsProgram3.14.2.11BWRWaterChemistryProgram3.14.2.12ChemistryProgramEffectivenessInspection3.14.2.13ClosedCoolingWaterChemistryProgram3.14.2.14CondensateandRefuelingWaterStorageTanksInspection3.14.2.15ContainmentLeakageRateTestProgram SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxvii3.14.2.16CoolingUnitsInspection3.14.2.17CraneInspectionProgram3.14.2.18FireProtectionProgram3.14.2.19FireWaterSystemProgram3.14.2.20Flow-AcceleratedCorrosion(FAC)Program3.14.2.21FuelOilChemistryProgram3.14.2.22HeatExchangerInspection3.14.2.23InserviceInspection(ISI)Program3.14.2.24InserviceInspection(ISI)Program-IWE3.14.2.25InserviceInspection(ISI)Program-IWF3.14.2.26InserviceInspection(ISI)Program-IWL3.14.2.27LeakChaseChannelMonitoringActivities3.14.2.28LubricatingOilAnalysisProgram3.14.2.29LubricatingOilInspection3.14.2.30NotUsed3.14.2.31MasonryWallProgram3.14.2.32Metal-EnclosedBusInspectionProgram3.14.2.33MonitoringandCollectionSystemInspection3.14.2.34Non-EQCablesandConnectionsUsedinLow-CurrentInstrumentationCircuitsProgram3.14.2.35Non-EQElectricalCablesandConnectionsVisualInspectionProgram3.14.2.36Non-EQInaccessibleMedium-VoltageCablesProgram3.14.2.37Non-EQElectricalCableConnectionsProgram3.14.2.38PipingCorrosionProgram3.14.2.39PreventiveMaintenanceActivities-RCIC/HPCITurbineCasings3.14.2.40ReactorHeadClosureStudsProgram3.14.2.41ReactorVesselSurveillanceProgram3.14.2.42RG1.127Water-ControlStructuresInspection SSES-FSARTOCRev.62CHAPTER3TEXTSectionTitleFSARRev.653-xxviii3.14.2.43SelectiveLeachingInspection3.14.2.44SmallBoreClass1PipingInspection3.14.2.45StructuresMonitoringProgram3.14.2.46SupplementalPiping/TankInspection3.14.2.47SystemWalkdownProgram3.14.2.48ThermalAgingandNeutronEmbrittlementofCastAusteniticStainlessSteel(CASS)Program3.14.2.49FatigueMonitoringProgram3.14.2.50PreventiveMaintenanceActivities-MainTurbineCasing3.14.2.51FuseHoldersProgram3.14.3EVALUATIONOFTIME-LIMITEDAGINGANALYSES(TLAA) 3.14.3.1ReactorVesselNeutronEmbrittlement3.14.3.2MetalFatigue3.14.3.3Non-Class1ComponentFatigueAnalyses3.14.3.4EnvironmentalQualificationofElectricEquipment3.14.3.5FatigueofPrimaryContainment,AttachedPiping,andComponents3.14.3.6OtherPlant-SpecificTime-LimitedAgingAnalyses3.14.4LICENSERENEWALREGULATORYCOMMITMENTLIST SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxix3.2-1SSESDesignCriteriaSummary3.2-2SummaryofCodesandStandardsforComponentsofWater-CooledNuclearPowerUnitsSuppliedbyAE(orderedpriortoJuly1,1971withtheexceptionofthosecomponentslocatedinsidetheRCPB,andthereactorpressurevessel)3.2-3SummaryofCodesandStandardsforComponentsofWater-CooledNuclearPowerUnitsSuppliedbyAE(orderedafterJuly1,1971)3.2-4CodeGroupDesignations-IndustryCodesandStandardsforMechanicalComponentsSuppliedbytheNSSSVendor3.2-5SummaryofSafetyClassDesignRequirements(Minimum) 3.3-1WindLoadsonStructures 3.3-2TornadoWindProtectedSystemsandTornadoResistantEnclosures 3.5-1ThisTableHasBeenDeleted 3.5-2ProbabilitiesforUnit1TargetsDuetoEachTurbine3.5-3ThisTableHasBeenDeleted 3.5-4Tornado-GeneratedMissileParametersforAllTornado-ResistantStructuresExcepttheDieselGenerator'E'Building3.5-4aTornado-GeneratedMissileParametersforDieselGenerator'E'Building 3.5-5BerwickAirportMovementSummary 3.5-6PlantTargetAreas 3.5-7CalculatedStressforBonnet-SealTypeValves 3.5-8ThisTableHasBeenDeleted 3.5-9ThisTableHasBeenDeleted SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxx3.5-10TurbineSystemReliabilityCriteria3.6-1HighEnergyFluidSystemPiping 3.6-1aModerateEnergyFluidSystemPiping(LocatedinSafety-RelatedStructures)3.6-2SafetyComponentsinCloseProximitytoHighEnergyFluidSystemPiping-(RequiringJetImpingementProtection)PrimaryContainment)3.6-3SafetyComponentsinCloseProximitytoHighEnergyFluidSystemPiping-(RequiringJetImpingementProtection)ReactorBuilding3.6-4RestraintData 3.6-5ComparisonofPDAandNSCCode 3.6-6aSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"A"3.6-6bSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"B"3.6-6cSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"C"3.6-6dSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit1-Line"D"3.6-6eSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"A"3.6-6fSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"B"3.6-6gSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"C"3.6-6hSummaryofStressinHighEnergyASMEClass1Piping-MainSteamLineInsideContainment-Unit2-Line"D" SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxi3.6-7SummaryofStressinHighEnergyASMEClass1Piping-FeedwaterLineInsideContainment-Unit13.6-7aSummaryofStressinHighEnergyASMEClass1Piping-FeedwaterLineInsideContainment-Unit23.6-8SummaryofStressinHighEnergyASMEClass1Piping-HPCISteamSupplyLineInsideContainment-Unit13.6-8aSummaryofStressinHighEnergyASMEClass1Piping-HPCISteamSupplyLineInsideContainment-Unit23.6-9SummaryofStressinHighEnergyASMEClass1Piping-RCICSteamSupplyLineInsideContainment-Unit13.6-9aSummaryofStressinHighEnergyASMEClass1Piping-RCICSteamSupplyLineInsideContainment-Unit23.6-10SummaryofStressinHighEnergyASMEClass1Piping-CoreSprayLineInsideContainment-Unit13.6-10aSummaryofStressinHighEnergyASMEClass1Piping-CoreSprayLineInsideContainment-Unit23.6-11SummaryofStressinHighEnergyASMEClass1Piping-RHRSupplyLineInsideContainment-Unit13.6-11aSummaryofStressinHighEnergyASMEClass1Piping-RHRSupplyLineInsideContainment-Unit23-6-12aSummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainmentUnit1Loop"A"3.6-12a.1SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit13.6-12a.2SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit13.6-12a.3SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit1 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxii3.6-12a.4SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit23.6-12a.5SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit23.6-12a.6SummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainment-Unit2-Loop"A"3.6-12a.7SummaryofStressinHighEnergyASMEClass1Piping-ReactorWaterCleanUpLineInsideContainment-Unit23.6-12bSummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainmentUnit1Loop"B"3.6-12b.1SummaryofStressinHighEnergyASMEClass1Piping-HeadVentLineInsideContainment-Unit13.6-12b.2SummaryofStressinHighEnergyASMEClass1Piping-HeadVentLineInsideContainment-Unit13.6-12b.3SummaryofStressinHighEnergyASMEClass1Piping-RHRReturnLineInsideContainment-Unit2-Loop"B"3.6-12b.4SummaryofStressinHighEnergyASMEClass1Piping-HeadVentLineInsideContainment-Unit23.6-12cSummaryofStressinHighEnergyASMEClass1Piping-HeadSprayLineInsideContainment-Unit13.6-12c.1SummaryofStressinHighEnergyASMEClass1Piping-HeadSprayLineInsideContainment-Unit23.6-12d.1SummaryofStressinHighEnergyASMEClass1Piping-StandbyLiquidControlLineInsideContainment-Unit13.6-12d.2ThisTablehasbeenIntentionallyLeftBlank 3.6-12d.3SummaryofStressinHighEnergyASMEClass1Piping-StandbyLiquidControlLineInsideContainment-Unit2 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxiii3.6-12e.1SummaryofStressinHighEnergyASMEClass1Piping-MSIVDrainLinesInsideContainment-Unit13.6-12e.2SummaryofStressinHighEnergyASMEClass1Piping-MSIVDrainLinesInsideContainment-Unit13.6-12e.3SummaryofStressinHighEnergyASMEClass1Piping-MSIVDrainLinesInsideContainment-Unit23.6-13HighEnergyFluidSystemsWithandWithoutSufficientCapacitytoDevelopaJetStream3.6-14SummaryofStressinHighEnergyASMEClass1Piping-RecirculationPipingSystem-Loop"A"-Unit13.6-15SummaryofStressinHighEnergyASMEClass1Piping-RecirculationPipingSystem-Loop"A"-Unit23.6A-1ComparisonofFlowRatesComputedfromtheTimeDependentMomentumEquation3.6A-2CaseA-SteamTunnelCompartmentVolumes 3.6A-3SteamTunnelFlowAreasCoefficientsandL/A 3.6A-4ForCaseA&CaseB 3.6A-5CaseB-SteamTunnelCompartmentVolumes 3.6A-6SteamTunnelFlowAreasCoefficientsandL/A 3.7a-1CriticalDampingRatiosforDifferentMaterials 3.7a-2Thistablehasbeendeleted 3.7a-3NumberofDynamicResponseCyclesExpectedDuringaSeismicEvent 3.7b-1AmplificationFactorsforGroundSpectra 3.7b-1aThistableHasBeenRenumberedto3.7b-2 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxiv3.7b-2AmplificationFactorsforDieselGenerator'E'Building'sGroundSpectra3.7b-3DampingValuesforNon-NSSSMaterials(PercentofCriticalDamping) 3.7b-4DampingValuesforDieselGenerator'E'Facility3.7b-5StructureFoundationInteractionCoefficients 3.7b-6PropertiesofFoundationMediaforContainmentandESSWPumphouse 3.7b-7NaturalFrequenciesofContainmentBelow33CPS 3.7b-8NaturalFrequenciesoftheReactorandControlBuildingBelow33CPS3.7b-9ESSWPumphouse:FrequenciesWithandWithoutEccentricities 3.7b-10DieselGeneratorA-DBuildingFrequenciesWithandWithoutEccentricities 3.7b-11ComparisonsofTorsionalMomentsBetweenOriginalDesignandtheValuesComputedfromtheResultsof3-DStickModel3.7b-12Thistablehasbeendeleted 3.7b-13Thistablehasbeendeleted 3.8-1ListofApplicableCodes,Standards,Recommendations,andSpecifications 3.8-2LoadCombinationsforPrimaryContainment,DrywellFloor 3.8-2aLoadCombinationsforReactorPedestal 3.8-3LoadCombinationsandAllowableStressesForASMEClassMCComponents3.8-3aComparisonofFSARandSRPLoadCombinationsandAllowableStressesforASMEClassMCComponents3.8-4LoadCombinationfortheReactorShieldWall SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxv3.8-5LoadCombinationsfortheSuppressionChamberColumns3.8-6LoadCombinationsfortheDrywellPlatforms 3.8-7LoadCombinationfortheSeismicTruss 3.8-8LoadCombinationsApplicabletoReactorBuilding 3.8-9LoadCombinationsApplicabletoSeismicCategoryIStructuresOtherThanContainment,ReactorBuildingandDieselGenerator'E'Building3.8-9aLoadCombinationsApplicabletoDieselGenerator'E'Building 3.8-10LoadCombinationsApplicabletoTurbine&RadwasteBuilding 3.8-11ConcreteDesignCompressiveStrengths 3.8-12AllowableStressIncreaseFactorforMasonryStructures 3.8A-1TabulationofMembraneStressResultantsFromtheASHSDProgram 3.8A-2CECAPandHandCalculationComparison-ThermalGradient 3.8A-3ComparisonofCECAPandHandCalculationResults-RealMoment 3.8A-4CECAPandHandCalculationComparison-RealMomentandRealCompressiveLoad3.8A-5ComparisonofResultsfortheRectangularPlatewithaConcentratedLoadattheCenter3.8A-6ComparisonofResultsfortheRectangularPlatewithVariousEdgeConditions3.8A-7ComparisonofStressesforWeldingNeckFlange 3.8A-8ComparisonofStressesforSlip-OnFlange 3.8A-9ComparisonofFinalResultsforHoopForce,N,andMeridionalMoment,M SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxvi3.8A-10MaterialPropertiesoftheConcreteandReinforcingSteelUsedforFINELVerification3.8A-11LoadingHistoryUsedfortheFINELVerification 3.8A-12ComparisonofStressResults 3.8A-13ComparisonofStressResults 3.8A-14ComparisonofResults 3.8B-1MinimumTestingFrequenciesforConcreteMaterialsandConcrete(ExceptfortheDieselGenerator'E'Building)3.8B-2TestingRequirementsforConcreteMaterialsUsedintheDieselGenerator'E'Building3.8B-3TestingRequirementsforConcreteUsedintheDieselGenerator'E'Building 3.9-1TransientsandtheNumberofAssociatedCyclesConsideredintheDesignandFatigueAnalysisoftheRPVAssemblyandInternalTransients3.9-2Introduction 3.9-2Index 3.9-2LoadCombinationandAcceptanceCriteriaforASMECodeClass1,2,and3NSSSPipingandEquipment3.9-2aReactorPressureVesselandShroudSupportAssembly 3.9-2bReactorInternalsandAssociatedEquipment 3.9-2(c)ReactorWaterCleanupHeatExchangers 3.9-2dASMECodeClassIMainSteamPipingandPipeMountedEquipment-HighestStressSummary-Unit13.9-2d.1ASMECodeClassIMainSteamPipingandPipeMountedEquipment-HighestStressSummary-Unit2 SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxvii3.9-2eASMECodeClassIRecirculationPipingandPipeMountedEquipment-HighestStressSummary-Unit13.9-2e.1ASMECodeClassIRecirculationPipingandPipeMountedEquipment-HighestStressSummary-Unit23.9-2(f)ThisTableHasBeenIntentionallyLeftBlank 3.9-2gSafety/ReliefValves(MainSteam) 3.9-2(h)MainSteamIsolationValve 3.9-2iRecirculationPump 3.9-2(j)ReactorRecirculationSystemGateValves,DischargeStructural&MechanicalLoadingCriteria3.9-2(k)ThisTableHasBeenIntentionallyLeftBlank 3.9-2LStandbyLiquidControlPump 3.9-2mStandbyLiquidControlTank 3.9-2n(i)RHRPumps(ii)CoreSprayPumps 3.9-2oRHRHeatExchanger 3.9-2(p)RWCUPump 3.9-2qRCICTurbine 3.9-2(r)RCICPump 3.9-2sReactorRefuelingandServicingEquipment 3.9-2tHighPressureCoolantInjectionPump 3.9-2uControlRodDrive(IndexTube) 3.9-2vControlRodDriveHousing SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxviii3.9-2wJetPumps3.9-2aaControlRodGuideTubeFlange 3.9-2abIncoreHousing 3.9-2(ac)ReactorVesselSupportEquipmentCRDHousingSupport 3.9-2(ad)ThisTableHasBeenIntentionallyLeftBlank 3.9-2(ae)HPCITurbineDesignCalculations 3.9-2(af)HighDensitySpentFuelRacks 3.9-3NSSSSeismicCategoryIActivePumpsandValves 3.9-4ApplicableThermalTransients 3.9-5ListofComputerProgramsUsedinBOPMechanicalSystemsandComponents3.9-6DesignLoadingCombinationsForASMECodeClass1,2,and3Components3.9-7DesignCriteriaforASMECodeClassIValves 3.9-8DesignCriteriaforASMECodeClass2and3VesselsDesignedtoNC-3300andND-33003.9-9DesignCriteriaforASMECodeClass2VesselsDesignedtoAlternateRulesofNC-32003.9-10DesignCriteriaforASMECodeClass2and3Piping 3.9-11DesignCriteriaforASMECodeClass2and3Pumps 3.9-12DesignCriteriaforASMECodeClass2and3Valves 3.9-13ThisTableHasBeenIntentionallyLeftBlank SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xxxix3.9-14DesignLoadingCombinationsforSupportsforASMECodeClass1,2and3Components3.9-15ValveQualificationTestRange 3.9-16ListingofDynamicallyQualifiedEquipment 3.9-17DieselGenerator'A-D'SeismicTestorAnalysisSubmittalChart 3.9-18SummaryComparison-ProjectSpecification-10,"GeneralProjectRequirementsforASeismicDesignandAnalysisofClass1EquipmentandEquipmentSupports"3.9-19ThisTableHasBeenIntentionallyLeftBlank 3.9-20BOPPipingSystemPowerAscensionTesting 3.9A-1ComparisonBetweenSampleProblemandComputerProgramME913Results3.9A-2ComparisonofME912withME643andAnalyticalResults 3.10a-1EssentialElectricalComponentsandInstruments 3.10a-2SeismicQualificationTestSummaryClassIEControlPanelsandLocalPanelsandRacks3.10a-3SummaryofSampleSeismicStaticAnalysisForThreeTypicalCabinets 3.10a-4SeismicDesignVerificationDataSheet 3.10c-1SecondaryUnitSubstationsandPowerTransformers 3.10c-2MotorControlCenters 3.10c-3BatteryMonitorsandFuseBoxes 3.10c-4DCDistributionPanels 3.10c-5BatteryRacks SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xl3.10c-6ElectricalCablePenetration3.10c-7CableTrays"Safeguard" 3.10c-8BatteryChargerRacksandCabinets 3.10c-9LargeInductionMotors4000V 3.10c-10PanelsandTerminationCabinets 3.10c-11BatteryChargers 3.10c-124.16KVSwitchgear 3.10c-13DCControlandLoadCenters 3.10c-14InstrumentACTransformers 3.10c-15AutomaticTransferSwitches 3.10c-16LoadIsolationMotor-GeneratorSets 3.10c-17Non-NSSSandNon-ACRRelaysRequiredtobeEnergized 3.10c-18Invertersand120VACInstrumentPanels 3.11-2ThisTableHasBeenIntentionallyLeftBlank 3.11-3ThisTableHasBeenIntentionallyLeftBlank 3.11-4ThisTableHasBeenIntentionallyLeftBlank 3.11-5ThisTableHasBeenIntentionallyLeftBlank 3.11-6ThisTableHasBeenIntentionallyLeftBlank 3.11-7WaterQuality 3.11-8ThisTableHasBeenIntentionallyLeftBlank 3.12-1ESFDivisionSeparation SSES-FSARTOCRev.62CHAPTER3TABLESNumberTitleFSARRev.653-xli3.12-2ChannelSeparation3.12-3MainControlRoomandRelayPanelAnnunciatorandComputerInterfaceDevice3.13-1ComparisonwithRegulatoryGuide1.48 3.14-1LicenseRenewalCommitments SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlii3.2-1CodeClassificationofPipingValves3.2-2MinimumInstrumentLineClassifications 3.5-1ThisFigureHasBeenDeleted 3.5-2ThisFigureHasBeenDeleted 3.5-3ThisFigureHasBeenDeleted 3.5-4ThisFigureHasBeenDeleted 3.5-5ThisFigureHasBeenDeleted 3.5-6ThisFigureHasBeenDeleted 3.5-7ThisFigureHasBeenDeleted 3.5-8ThisFigureHasBeenDeleted 3.5-9Typical900#BonnetSealTypeValve 3.5-10RetainingRingDesignfor900#Bonnet-SealTypeValve 3.6-1AMainSteamLineA 3.6-1BMainSteamLineB 3.6-1CMainSteamLineC 3.6-1DMainSteamLineD 3.6-2FeedwaterSystem 3.6-3HPCISteamSupply 3.6-4RCICSteamSupply 3.6-5CoreSpray SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xliii3.6-6RHRSupply3.6-7RHRReturnLoopA 3.6-8RHRReturnLoopB 3.6-8A.1ReactorWaterCleanup 3.6-8A.2ReactorWaterCleanup 3.6-8A.3ReactorWaterCleanup 3.6-8A.4ReactorWaterCleanup 3.6-8A.5ReactorWaterCleanup 3.6-8BReactorVesselHeadVent 3.6-8CHeadSpray 3.6-8DStandbyLiquidControl 3.6-8EMSIVDrains 3.6-9ThisFigureHasBeenIntentionallyLeftBlank 3.6-10TypicalPipeWhipRestraints 3.6-11PipeWhipRestraintArrangementtoProtectFeedwaterOutsideContainmentIsolationValves3.6-11aMainFeedwaterLinePIPERUPMathematicalModel 3.6-12ForcingFunctionsModelAssociatedwithPipeWhipDynamicAnalysis3.6-12aForcingFunctionsModelAssociatedwithPipeWhipDynamiteAnalysis3.6-13TypicalPipeWhipRestraintConfiguration SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xliv3.6-14RecirculationSystemPostulatedBreakLocationsandRestraintLocations(LOOPAandBSame,UnlessOtherwiseSpecified)3.6-15TypicalRestraintForce-DeflectionCurve 3.6-16BreakLocationsandRestraintsAnalyzed,PDAVerificationProgram 3.6-17-1PipeBreakProtectionforHighEnergyPipingintheReactorBuilding 3.6-17-2PipeBreakProtectionforHighEnergyPipingintheReactorBuilding 3.6-17-3PipeBreakProtectionforHighEnergyPipingintheReactorBuilding 3.6A-1CaseAMSLBinReactorBuilding 3.6A-2PanelandPlatformLocations 3.6A-3CaseAVolumeFlows 3.6A-4CaseAPressureTransient 3.6A-5CaseBMSLBinTurbineBuilding 3.6A-6CaseBVolumeFlows 3.6A-7CaseBPressureTransient 3.6A-8ModelforDouble-EndedGuillotineMSLB3.7a-1ReactorPressureVesselandInternalSeismicModel 3.7a-2DensityofStressReversals 3.7b-1ThisFigureIsADuplicationofFigure2.5-28 3.7b-1aFigurerenumberedfrom3.7B-1Ato3.7B-2 3.7b-2DieselGenerator'E'BuildingDesignResponseSpectraSafeShutdownEarthquakeHorizontalComponent3.7b-2aFigurerenumberedfrom3.7B-2Ato3.7B-4 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlv3.7b-3DesignResponseSpectraSafeShutdownEarthquakeHorizontalComponent3.7b-3aFigurerenumberedfrom3.7B-2Ato3.7B-6 3.7b-3bFigurerenumberedfrom3.7B-3Bto3.7B-7 3.7b-4DieselGenerator'E'BuildingsDesignResponseSpectraSafeShutdownEarthquakeHorizontalComponent3.7b-5SyntheticTimeHistoryNormalizedto1G 3.7b-6DieselGenerator'E'BuildingHorizontalSyntheticTimeHistoryNormalizedto0.1G3.7b-6aFigurerenumberedfrom3.7B-6Ato3.7B-11 3.7b-6bFigurerenumberedfrom3.7B-6Bto3.7B-12 3.7b-6cFigurerenumberedfrom3.7B-6Cto3.7B-13 3.7b-6dFigurerenumberedfrom3.7B-6Dto3.7B-14 3.7b-6eFigurerenumberedfrom3.7B-6Eto3.7B-15 3.7b-6fFigurerenumberedfrom3.7B-6Fto3.7B-16 3.7b-7DieselGenerator'E'BuildingVerticalSyntheticTimeHistoryNormalizedto 0.1G3.7b-8ComparisonofTimeHistoryResponseSpectraandDesignResponseSpectra2%and5%Damping(0.2-30CPS)3.7b-9ComparisonofTimeHistoryResponseSpectraandDesignResponseSpectra3%and7%Damping(0.2-30CPS)3.7b-10ComparisonofTimeHistoryResponseSpectraandDesignResponseSpectra2%and5%Damping(0.2-1.0CPS)

SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlvi3.7b-11DieselGenerator'E'BuildingComparisonofHorizontalTimeHistoryResponseSpectrumandHorizontalDesignResponseSpectrum2%Damping3.7b-12DieselGenerator'E'BuildingComparisonofHorizontalTimeHistoryResponseSpectrumandHorizontalDesignResponseSpectrum5%Damping3.7b-13DieselGenerator'E'BuildingComparisonofHorizontalTimeHistoryResponseSpectrumandHorizontalDesignResponseSpectrum7%Damping3.7b-14DieselGenerator'E'BuildingComparisonofVerticalTimeHistoryResponseSpectrumandVerticalDesignResponseSpectrum2%Damping3.7b-15DieselGenerator'E'BuildingComparisonofVerticalTimeHistoryResponseSpectrumandVerticalDesignResponseSpectrum5%Damping3.7b-16DieselGenerator'E'BuildingComparisonofVerticalTimeHistoryResponseSpectrumandVerticalDesignResponseSpectrum7%Damping3.7b-17HorizontalSeismicModelofContainmentWithFlexibleBase 3.7b-18VerticalSeismicModelofContainmentWithFlexibleBase 3.7b-19E-WSeismicModelofReactorandControlBuilding 3.7b-20N-SSeismicModelofReactorandControlBuilding 3.7b-21VerticalSeismicModelofReactorandControlBuilding 3.7b-22PlanViewofReactorandControlBuilding 3.7b-23CorrelationofVerticalSeismicModelMasspointsofthePhysicalStructure 3.7b-24ContainmentHorizontalModeShapesMode1 3.7b-25ContainmentHorizontalModeShapesMode2 3.7b-26ContainmentHorizontalModeShapesMode4 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlvii3.7b-27ContainmentVerticalModeShapesMode13.7b-28ContainmentVerticalModeShapesMode2 3.7b-29ContainmentVerticalModeShapesMode3 3.7b-30ReactorandControlBuildingE-WModeShapes-Mode1(CranesatPoints32and33)3.7b-31ReactorandControlBuildingE-WModeShapes-Mode2 3.7b-32ReactorandControlBuildingE-WModeShapes-Mode3(CranesatPoints32and33)3.7b-33ReactorandControlBuildingE-WModeShapes-Mode4 3.7b-34ReactorandControlBuildingE-WModeShapes,Mode5 3.7b-35ReactorandControlBuildingN-SModeShapes-Mode1 3.7b-36ReactorandControlBuildingN-SModeShapes-Mode3 3.7b-37ReactorandControlBuildingVerticalModeShapesMode1 3.7b-38ReactorandControlBuildingVerticalModeShapesMode2 3.7b-39ReactorandControlBuildingVerticalModeShapesMode3 3.7b-40ContainmentHorizontalDisplacementsOBE 3.7b-41ContainmentHorizontalDisplacementsSSE 3.7b-42ContainmentVerticalDisplacementsOBE 3.7b-43ContainmentVerticalDisplacementsSSE 3.7b-44ContainmentHorizontalAccelerationsOBE 3.7b-45ContainmentHorizontalAccelerationsSSE 3.7b-46ContainmentVerticalAccelerationsOBE SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlviii3.7b-47ContainmentVerticalAccelerationsSSE3.7b-48ReactorandControlBuildingE-WDisplacementsOBE 3.7b-49ReactorandControlBuildingE-WDisplacementsSSE 3.7b-50ReactorandControlBuildingN-SDisplacementsOBE 3.7b-51ReactorandControlBuildingN-SDisplacementsSSE 3.7b-52ReactorandControlBuildingVerticalDisplacementsOBE 3.7b-53ReactorandControlBuildingVerticalDisplacementsSSE 3.7b-54ReactorandControlBuildingE-WAccelerationsOBE 3.7b-55ReactorandControlBuildingE-WAccelerationsSSE 3.7b-56ReactorandControlBuildingN-SAccelerationsOBE 3.7b-57ReactorandControlBuildingN-SAccelerationsSSE 3.7b-58ReactorandControlBuildingVerticalAccelerationOBE 3.7b-59ReactorandControlBuildingVerticalAccelerationsSSE 3.7b-60ResponseSpectrumatRPVPedestalHorizontalOBE 3.7b-61ResponseSpectrumatRPVPedestalHorizontalSSE 3.7b-62ResponseSpectrumatRPVPedestalVerticalOBE 3.7b-63ResponseSpectrumatRPVPedestalVerticalSSE 3.7b-64ResponseSpectrumatRefuelingAreaE-WOBE 3.7b-65ResponseSpectrumatRefuelingAreaE-WSSE 3.7b-66ResponseSpectrumatRefuelingAreaN-SOBE SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-xlix3.7b-67ResponseSpectrumatRefuelingAreaN-SSSE3.7b-68ResponseSpectrumatRefuelingAreaVerticalOBE 3.7b-69ResponseSpectrumatRefuelingAreaVerticalSSE 3.7b-70ResponseSpectrumatTopofPedestal(DieselsA-D)E-WOBE 3.7b-71ResponseSpectrumatTopofPedestal(DieselE)E-WOBE 3.7b-72ResponseSpectrumatTopofPedestal(DieselsA-D)E-WSSE 3.7b-73ResponseSpectrumatTopofPedestal(DieselE)E-WSSE 3.7b-74ResponseSpectrumatTopofPedestal(DieselsA-D)N-SOBE 3.7b-75ResponseSpectrumatTopofPedestal(DieselE)N-SOBE 3.7b-76ResponseSpectrumatTopofPedestal(DieselsA-D)N-SSSE 3.7b-77ResponseSpectrumatTopofPedestal(DieselE)N-SSSE 3.7b-78ResponseSpectrumatTopofPedestal(DieselsA-D)VerticalOBE 3.7b-79ResponseSpectrumatTopofPedestalforDieselEVerticalOBE 3.7b-80ResponseSpectrumatTopofPedestal(DieselsA-D)Vertical-SSE 3.7b-81ResponseSpectrumatTopofPedestalforDiesel'E'VerticalSSE 3.7b-82ResponseSpectrumatOperatingFloorofESSWPumphouseE-WOBE 3.7b-83ResponseSpectrumatOperatingFloorofESSWPumphouseE-WSSE 3.7b-84ResponseSpectrumatOperatingFloorofESSWPumphouseN-SOBE 3.7b-85ResponseSpectrumatOperatingFloorofESSWPumphouseN-SSSE 3.7b-86ResponseSpectrumatOperatingFloorofESSWPumphouseVerticalOBE 3.7b-87ResponseSpectrumatOperatingFloorofESSWPumphouseVerticalSSE SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-l3.7b-88ComparisonofDesignandR.G.1.60ResponseSpectraHorizontalOBE3.7b-89ComparisonofDesignandR.G.1.60ResponseSpectraHorizontalSSE 3.7b-90ComparisonofDesignandR.G.1.60ResponseSpectraVerticalOBE 3.7b-90aFigurerenumberedfrom3.7B-90Ato3.7B-71 3.7b-91ComparisonofDesignandR.G.1.60ResponseSpectraVerticalSSE 3.7b-91aFigurerenumberedfrom3.7B-91Ato3.7B-73 3.7b-92DampingV/SZPAforRacewaySystem 3.7b-92aFigurerenumberedfrom3.7B-92Ato3.7B-75 3.7b-93ESSWPumpHouse3-DStickModel 3.7b-93aFigurerenumberedfrom3.7b-93Ato3.7B-77 3.7b-94DieselGenerator'A-D'Building3-DStickModel 3.7b-94aFigurerenumberedfrom3.7B-94Ato3.7B-79 3.7b-95DieselGenerator'E'BuildingSeismicModels 3.7b-95aFigureDeleted

3.7b-96throughFiguresDeleted 3.7b-1263.8-1ThisFigureHasBeenReplacedbyDwg.C-331,Sh.1 3.8-2ThisFigureHasBeenReplacedbyDwg.C-371,Sh.1 3.8-3ThisFigureHasBeenReplacedbyDwg.C-1932,Sh.3 3.8-4ThisFigureHasBeenReplacedbyDwg.C-1932,Sh.4 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-li3.8-5ThisFigureHasBeenReplacedbyDwg.C-1932,Sh.53.8-6ThisFigureHasBeenDeleted 3.8-7ThisFigureHasBeenDeleted 3.8-8ThisFigureHasBeenDeleted 3.8-9PrimaryContainment-DrywellHeadConnection 3.8-10ThisFigureHasBeenReplacedbyDwg.C-284,Sh.1 3.8-11-1ThisFigureHasBeenReplacedbyDwg.C-332,Sh.1 3.8-11-2ThisFigureHasBeenReplacedbyDwg.C-333,Sh.1 3.8-12ThisFigureHasBeenReplacedbyDwg.C-281,Sh.1 3.8-13ThisFigureHasBeenReplacedbyDwg.C-281,Sh.1 3.8-14ThisFigureHasBeenReplacedbyDwg.C-370,Sh.1 3.8-15-1ThisFigureHasBeenReplacedbyDwg.C-334,Sh.1 3.8-15-2ThisFigureHasBeenReplacedbyDwg.C-335,Sh.1 3.8-15-3ThisFigureHasBeenReplacedbyDwg.C-336,Sh.1 3.8-15-4ThisFigureHasBeenReplacedbyDwg.C-337,Sh.1 3.8-15-5ThisFigureHasBeenReplacedbyDwg.C-338,Sh.1 3.8-16-1ThisFigureHasBeenReplacedbyDwg.C-351,Sh.1 3.8-16-2ThisFigureHasBeenReplacedbyDwg.C-352,Sh.1 3.8-16-3ThisFigureHasBeenReplacedbyDwg.C-353,Sh.1 3.8-16-4ThisFigureHasBeenReplacedbyDwg.C-354,Sh.1 3.8-16-5ThisFigureHasBeenReplacedbyDwg.C-355,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lii3.8-16-6ThisFigureHasBeenReplacedbyDwg.C-356,Sh.13.8-16-7ThisFigureHasBeenReplacedbyDwg.C-357,Sh.1 3.8-16-8ThisFigureHasBeenReplacedbyDwg.C-358,Sh.1 3.8-16-9ThisFigureHasBeenReplacedbyDwg.C-359,Sh.1 3.8-16-10ThisFigureHasBeenReplacedbyDwg.C-360,Sh.1 3.8-16-11ThisFigureHasBeenReplacedbyDwg.C-393,Sh.1 3.8-16-12ThisFigureHasBeenReplacedbyDwg.C-394,Sh.1 3.8-16-13ThisFigureHasBeenReplacedbyDwg.C-395,Sh.1 3.8-16-14ThisFigureHasBeenReplacedbyDwg.C-396,Sh.1 3.8-16-15ThisFigureHasBeenReplacedbyDwg.C-397,Sh.1 3.8-16-16ThisFigureHasBeenReplacedbyDwg.C-398,Sh.1 3.8-16-17ThisFigureHasBeenReplacedbyDwg.C-399,Sh.1 3.8-16-18ThisFigureHasBeenReplacedbyDwg.C-400,Sh.1 3.8-17ThisFigureHasBeenReplacedbyDwg.C-282,Sh.1 3.8-18ThisFigureHasBeenReplacedbyDwg.C-285,Sh.1 3.8-19-1ThisFigureHasBeenReplacedbyDwg.C-288,Sh.1 3.8-19-2ThisFigureHasBeenReplacedbyDwg.C-287,Sh.1 3.8-19-3ThisFigureHasBeenReplacedbyDwg.C-283,Sh.1 3.8-20-1SuppressionChamberElectricalPenetrationDetails 3.8-20-2DrywellElectricalPenetrationDetails SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-liii3.8-21ThisFigureHasBeenReplacedbyDwg.C-286,Sh.13.8-22ThisFigureHasBeenReplacedbyDwg.C-291,Sh.1 3.8-23ThisFigureHasBeenReplacedbyDwg.C-278,Sh.1 3.8-24ContainmentWallTemperatureGradients 3.8-25ContainmentWallAnalyticalModelforAxisymmetricLoads 3.8-26DrywellWallAnalyticalModelforNon-AxisymmetricMissileandPostulatedPipeRuptureLoads3.8-27BaseFoundationSlabAnalyticalModel 3.8-28EquipmentHatchAnalyticalModel 3.8-29StructuralAcceptanceTest-PressurizationSequence 3.8-30StructuralAcceptanceTest-LocationsofDeflectionMeasuringDevicesfortheContainment3.8-31StructuralAcceptanceTest-LocationsofDeflectionMeasuringDevicesfortheEquipmentHatch3.8-32ThisFigureHasBeenReplacedbyDwg.C-384,Sh.1 3.8-33ThisFigureHasBeenReplacedbyDwg.C-387,Sh.1 3.8-34StructuralAcceptanceTest-ContainmentAnalyticalModel 3.8-35StructuralAcceptanceTest-EquipmentHatchAnalyticalModel 3.8-36StructuralAcceptanceTest-ComparisonofMeasuredandPredictedDeflectionsfortheContainment3.8-37StructuralAcceptanceTest-ComparisonofMeasuredandPredictedDeflectionfortheEquipmentHatch3.8-38StructuralAcceptanceTest-InsideMeridionalStrainatMid-heightofSuppressionChamberWall SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-liv3.8-39StructuralAcceptanceTest-InsideHoopStrainatMid-heightofSuppressionChamberWall3.8-40StructuralAcceptanceTest-OutsideMeridionalStrainatMid-heightofSuppressionChamberWall3.8-41StructuralAcceptanceTest-OutsideHoopStrainatMid-heightofSuppressionChamberWall3.8-42StructuralAcceptanceTest-OutsideHelicalStrainatMid-heightofSuppressionChamberWall3.8-43StructuralAcceptanceTest-ExternalConcreteSurfaceCracksatMid-heightofDrywellWall3.8-44DrywellHead 3.8-45AnalyticalModelofDrywellHeadAssembly 3.8-46-1ThisFigureHasBeenReplacedbyDwg.C-348,Sh.1 3.8-46-2ThisFigureHasBeenReplacedbyDwg.C-349,Sh.1 3.8-46-3ThisFigureHasBeenReplacedbyDwg.C-350,Sh.1 3.8-47ThisFigureHasBeenReplacedbyDwg.C-293,Sh.1 3.8-48ThisFigureHasBeenReplacedbyDwg.C-340,Sh.1 3.8-49ThisFigureHasBeenReplacedbyDwg.C-341,Sh.1 3.8-50ThisFigureHasBeenReplacedbyDwg.C-376,Sh.1 3.8-51-1ThisFigureHasBeenReplacedbyDwg.C-344,Sh.1 3.8-51-2ThisFigureHasBeenReplacedbyDwg.C-377,Sh.1 3.8-52ThisFigureHasBeenReplacedbyDwg.C-362,Sh.1 3.8-53ThisFigureHasBeenReplacedbyDwg.C-363,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lv3.8-54ThisFigureHasBeenReplacedbyDwg.C-354,Sh.13.8-55ThisFigureHasBeenReplacedbyDwg.C-365,Sh.1 3.8-56ThisFigureHasBeenReplacedbyDwg.C-367,Sh.1 3.8-57ThisFigureHasBeenReplacedbyDwg.C-380,Sh.1 3.8-58TemperatureGradientsforDrywellFloorandReactorPedestal 3.8-59ReactorShieldWallTemperatureGradients 3.8-60DrywellFloorAnalyticalModel 3.8-61AnalyticalModelforReactorPedestalAboveDrywellFloor 3.8-62ReactorShieldWall-EASEProgramAnalyticalModel 3.8-63ReactorShieldWall-AnalyticalModelfor"FINEL"and"ASHSD"Program 3.8-64SuppressionChamberColumns-ASHSDProgramAnalyticalModel 3.8-65SuppressionChamberColumns-SeismicModel 3.8-66SuppressionChamberColumns-"CE668"ProgramAnalyticalModel 3.8-67SeismicTrussAnalyticalModel 3.8-68StructuralAcceptanceTest-ComparisonofMeasuredandPredictedDeflectionsfortheDrywellFloor3.8-69ThisFigureHasBeenReplacedbyDwg.A-11,Sh.1 3.8-70ThisFigureHasBeenReplacedbyDwg.A-12,Sh.1 3.8-71ThisFigureHasBeenReplacedbyDwg.A-13,Sh.1 3.8-72ThisFigureHasBeenReplacedbyDwg.M-203,Sh.1 3.8-73ThisFigureHasBeenReplacedbyDwg.M-204,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lvi3.8-74ThisFigureHasBeenReplacedbyDwg.A-16,Sh.13.8-75ThisFigureHasBeenReplacedbyDwg.A-17,Sh.1 3.8-76ThisFigureHasBeenDeletedSeeFigure3.5-6 3.8-77Reactor,ControlandTurbineBuildingSectionsLookingNorth 3.8-78ReactorBuildingLookingWest 3.8-79ThisFigureHasBeenReplacedbyDwg.M-227,Sh.1 3.8-80ThisFigureHasBeenReplacedbyDwg.M-237,Sh.1 3.8-81ThisFigureHasBeenReplacedbyDwg.M-260,Sh.1 3.8-82ThisFigureHasBeenReplacedbyDwg.M-261,Sh.1 3.8-83ThisFigureHasBeenReplacedbyDwg.M-5200,Sh.1 3.8-84ThisFigureHasBeenReplacedbyDwg.M-5200,Sh.2 3.8-85ThisFigureHasBeenReplacedbyDwg.M-284,Sh.1 3.8-86ThisFigureHasBeenReplacedbyDwg.C-64,Sh.1 3.8-87ThisFigureHasBeenReplacedbyDwg.C-65,Sh.1 3.8-88ThisFigureHasBeenReplacedbyDwg.C-66,Sh.1 3.8-89ThisFigureHasBeenReplacedbyDwg.C-67,Sh.1 3.8-90ThisFigureHasBeenReplacedbyDwg.M-270,Sh.1 3.8-91ThisFigureHasBeenReplacedbyDwg.M-271,Sh.1 3.8-92ThisFigureHasBeenReplacedbyDwg.M-272,Sh.1 3.8-93ThisFigureHasBeenReplacedbyDwg.M-273,Sh.1 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lvii3.8-94ThisFigureHasBeenReplacedbyDwg.M-274,Sh.13.8-95ThisFigureHasBeenReplacedbyDwg.C-795,Sh.1 3.8A-1ThinShellCylinder 3.8A-2LayeredCylinder 3.8A-3GeneralLayoutofCylinder 3.8A-4FiniteElementModel 3.8A-5AxialMoment 3.8A-6CylinderwithHingedEnds 3.8A-7FiniteElementModel 3.8A-8-1ComparisonofResultsforCylindricalShellSubjectedtoanAsymmetricBending3.8A-8-2Comparison(Continued)ofResultsforCylindricalShellSubjectedtoAsymmetricBending3.8A-9ReinforcedConcreteBeam 3.8A-10ReinforcedConcreteBeamandCECAPConcreteElementModel 3.8A-11BeamCross-SectionandInitialStressDistribution 3.8A-12FinalThermalStressDistribution 3.8A-13ReinforcedConcreteBeamandCECAPConcreteElementModel 3.8A-14ReinforcedConcreteBeamandCECAPConcreteElementModel 3.8A-15ReinforcedConcreteBeamandCECAPModel 3.8A-16BeamCross-SectionandStressBlock SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lviii3.8A-17PlateGeometry,Loading,andFiniteElementMeshforRectangularPlatewithaConcentratedLoadattheCenter3.8A-18PlateGeometry,Loading,andFiniteElementMeshforRectangularPlatewithVariousEdgeConditions3.8A-19WeldingNeckFlangeDetail 3.8A-20Slip-OnFlangeDetail 3.8A-21GeometryofTorisphericalandEllipsoidalHeads(FittoCorrespondtoGeometryofEllipsoidalHeadinReference3.8A-9)3.8A-22MeasuredThicknessVariationinExperimentalHeadNo.1(FromReference3.8A-10,Page18)3.8A-23ThicknessVariationinCylinderNo.1(FromReference3.8A-11Fig.4) 3.8A-24AnalyticalModelwithBoundaryConditions 3.8A-25PlotofHoopForceandLongitudinalMovementfromE0781Output3.8A-26PlotofStressinthe(Hoop)DirectionontheInsideSurface(=0 o)(Ref.3.8A-12PageG-14)3.8A-27PlotofStressinthe(Hoop)DirectionontheOutsideSurface(=0 o)(Ref.3.8A-12PageG-11)3.8A-28PlotofStressinthe(Longitudinal)DirectionontheInsideSurface

(=0 o)(Ref.3.8A-12PageG-20)3.8A-29PlotofStressinthe(Longitudinal)DirectionontheOutsideSurface(=0 o)(Ref.3.8A-12PageG-17)3.8A-30PlotofMembraneStress(=0 o)(Ref.3.8A-12PageG-23)3.8A-31DimensionsofCylindricalWaterTank 3.8A-32ExperimentalBeamDimensions SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lix3.8A-33Reference3.8A-14Mesh3.8A-34FinelFiniteElementMesh 3.8A-35-1RegionsofCracking 3.8A-35-2RegionsofCracking(Cont.)

3.8A-36Load-DisplacementCurvesfromFinelVerificationUsingaSimplySupportedBeam3.8A-37FiniteElementModel 3.8A-38FiniteElementModel 3.8A-39TemperatureDistribution 3.8A-40SchematicofTestProblem 3.8A-41FiniteElementLayout 3.8A-42ComparisonofResults 3.8A-43SteelSphere 3.8A-44FiniteElementModel 3.9-1TransientPressureDifferentialsfollowingaSteamLineBreakat105%RatedSteamFlow,100%Recirculation3.9-2TypicalReliefValveTransient 3.9-3ReactorVesselCutaway 3.9-4ReactorInternalsFlowPaths 3.9-5FuelSupportPieces 3.9-6JetPump 3.9-7PressureNodesUsedforDepressurizationAnalysis SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lx3.9A-1TransientTemperatureResponse3.10a-1TypicalVerticalBoard 3.10a-2InstrumentRack 3.10a-3TypicalLocalRack 3.10a-4NEMAType-12Enclosure 3.10a-5-1CabinetInstallationforSeismicandHydrodynamicLoads-SampleCalculation(CabinetH12-P608)3.10a-5-2CabinetInstallationforSeismicandHydrodynamicLoads-SampleCalculation(CabinetH12-P608)3.10a-5-3CabinetInstallationforSeismicandHydrodynamicLoads-SampleCalculation(CabinetH12-P608)3.10a-6CornerPost 3.10a-7PlanViewofPanel 3.10a-8BarrierWithTwoEndPlates 3.10a-9PanelDeflections 3.11-1ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.1 3.11-2ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.2 3.11-3ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.3 3.11-4ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.4 3.11-5ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.5 3.11-6ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.6 3.11-7ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.7 SSES-FSARTOCRev.62CHAPTER3FIGURESNumberTitleFSARRev.653-lxi3.11-8ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.83.11-9ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.9 3.11-10ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.10 3.11-11ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.11 3.11-12ThisFigureHasBeenReplacedbyDwg.C-1815,Sh.12 3.13-1Onelinediagramillustratingrelationshipofloads,penetrationassemblies,andprotectivedevicesforcurvespresentedasFigures3.13-2,3.13-3,&

3.13-83.13-2Time-currentcharacteristiccurvesforovercurrentprotectionof#10copper,containmentpenetrations.3.13-2ATime-CurrentCharacteristicCurvesForOvercurrentProtectionOf#10Copper,ContainmentPenetrations3.13-2BTime-CurrentCharacteristicCurvesForOvercurrentProtectionOf#10Copper,ContainmentPenetrations3.13-3RelationshipOfLoads,PenetrationAssemblies&ProtectiveDevicesforCurvesPresentedinFigures3.13-2,3.13-3,&3.18-83.13-4120VoltACControlCircuits 3.13-5125VoltDCControlCircuits 3.13-6208/120LightingCircuits 3.13-7ReactRecirPump-MaxShortCircuitCapability 3.13-8Time-CurrentCharacteristicCurvesforOvercurrentProtectionof4/0Copper,ContainmentPenetrationsUsedWithHydrogenRecombiners SSES-FSAR TOC Rev. 61 FSAR Rev. 68 4-i CHAPTER 4 REACTOR TABLE OF CONTENTS TEXT Section Title 4.1

SUMMARY

DESCRIPTION

4.1.1 Reactor Vessel 4.1.2 Reactor Internal Components

4.1.2.1 Reactor Core

4.1.2.1.1 General 4.1.2.1.2 Core Configuration 4.1.2.1.3 Fuel Assembly Description 4.1.2.1.3.1 Fuel Rod 4.1.2.1.3.2 Fuel Bundle 4.1.2.1.4 Assembly Support and Control Rod Location

4.1.2.2 Shroud 4.1.2.3 Shroud Head and Steam Separators 4.1.2.4 Steam Dryer Assembly

4.1.3 Reactivity Control Systems

4.1.3.1 Operation 4.1.3.2 Description of Rods

4.1.4 Analysis Techniques

4.1.4.1 Reactor Internal Components 4.1.4.1.1 MASS (Mechanical Analysis of Space Structure) 4.1.4.1.1.1 Program Description 4.1.4.1.1.2 Program Version and Computer 4.1.4.1.1.3 History of Use 4.1.4.1.1.4 Extent of Application 4.1.4.1.2 SNAP (MULTISHELL) 4.1.4.1.2.1 Program Description 4.1.4.1.2.2 Program Version and Computer 4.1.4.1.2.3 History of Use 4.1.4.1.2.4 Extent of Application

4.1.4.1.3 GASP 4.1.4.1.3.1 Program Description SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-ii 4.1.4.1.3.2 Program Version and Computer 4.1.4.1.3.3 History of Use 4.1.4.1.3.4 Extent of Application 4.1.4.1.4 NO HEAT 4.1.4.1.4.1 Program Description 4.1.4.1.4.2 Program Version and Computer 4.1.4.1.4.3 History of Use 4.1.4.1.4.4 Extent of Application

4.1.4.1.5 FINITE 4.1.4.1.5.1 Program Description 4.1.4.1.5.2 Program Version and Computer 4.1.4.1.5.3 History of Use 4.1.4.1.5.4 Extent of Usage

4.1.4.1.6 DYSEA 4.1.4.1.6.1 Program Description 4.1.4.1.6.2 Program Version and Computer 4.1.4.1.6.3 History of Use 4.1.4.1.6.4 Extent of Application 4.1.4.1.7 SHELL 5 4.1.4.1.7.1 Program Description 4.1.4.1.7.2 Program Version and Computer 4.1.4.1.7.3 History of Use 4.1.4.1.7.4 Extent of Application 4.1.4.1.8 HEATER 4.1.4.1.8.1 Program Description 4.1.4.1.8.2 Program Version and Computer 4.1.4.1.8.3 History of Use 4.1.4.1.8.4 Extent of Application 4.1.4.1.9 FAP-71 (Fatigue Analysis Program) 4.1.4.1.9.1 Program Description 4.1.4.1.9.2 Program Version and Computer 4.1.4.1.9.3 History of Use 4.1.4.1.9.4 Extent of Use

4.1.4.1.10 CREEP/PLAST 4.1.4.1.10.1 Program Description 4.1.4.1.10.2 Program Version and Computer 4.1.4.1.10.3 History of Use 4.1.4.1.10.4 Extent of Application 4.1.4.2 Fuel Rod Thermal Analysis 4.1.4.3 Reactor Systems Dynamics 4.1.4.4 Nuclear Engineering Analysis SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-iii 4.1.4.4.1 ESCORE 4.1.4.4.2 CASMO-3G

4.1.4.4.3 SIMULATE-E 4.1.4.5 Neutron Fluence Calculations 4.1.4.6 Thermal Hydraulic Calculations

4.1.5 References

4.2 FUEL SYSTEM DESIGN

4.2.1 Design Bases

4.2.1.1 Fuel Assembly 4.2.1.2 Original Equipment Control Rod Assembly 4.2.1.3 GE Duralife 160C Control Rod Assembly 4.2.1.4 GE Marathon Control Rod Assembly 4.2.1.5 Westinghouse CR 99 Control Rod Assembly

4.2.2 General Design Description

4.2.2.1 Core Cell 4.2.2.2 Fuel Bundle 4.2.2.3 Fuel Assembly 4.2.2.4 Reactivity Control Assembly 4.2.2.4.1 Original Equipment Control Rod Assembly 4.2.2.4.2 Duralife 160C Control Rod Assembly 4.2.2.4.3 GE Marathon Control Rod Assembly 4.2.2.4.4 Westinghouse CR 99 Control Rod Assembly

4.2.3 Design Evaluations

4.2.3.1 Fuel Design Evaluations 4.2.3.2 Results of Control Rod Assembly Design Evaluations 4.2.3.2.1 Original Equipment Control Rod Assembly 4.2.3.2.2 Duralife 160C Control Rod Assembly 4.2.3.2.3 GE Marathon Control Rod Assembly 4.2.3.2.4 Westinghouse CR 99 Control Rod Assembly

4.2.4 Testing and Inspection

4.2.4.1 Fuel Hardware and Assembly SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-iv 4.2.4.2 Enrichment, Burnable Poison, and Absorber Rod Concentrations 4.2.4.3 Surveillance, Inspection and Testing

4.2.5 Operating and Developmental Experience 4.2.6 References

4.3 NUCLEAR DESIGN

4.3.1 Design Bases

4.3.1.1 Safety Design Bases 4.3.2.1 Plant Performance Design Bases

4.3.2 Description

4.3.2.1 Nuclear Design Description 4.3.2.1.1 Core Composition 4.3.2.1.2 Fuel bundle Nuclear Design 4.3.2.2 Power Distributions 4.3.2.2.1 Local Power Distribution 4.3.2.2.2 Radial Power Distribution 4.3.2.2.3 Axial Power Distribution 4.3.2.2.4 Power Distribution Measurements 4.3.2.2.5 Power Distribution Accuracy 4.3.2.3 Reactivity Coefficients 4.3.2.3.1 Void Coefficient 4.3.2.3.2 Moderator Temperature Coefficient 4.3.2.3.3 Doppler Temperature Coefficient 4.3.2.3.4 Power Coefficient 4.3.2.4 Control Requirements 4.3.2.4.1 Shutdown Reactivity 4.3.2.4.2 Reactivity Variations 4.3.2.5 Control Rod Patterns and Reactivity Worths 4.3.2.5.1 RWM Range 4.3.2.5.2 Operating Range 4.3.2.5.3 SCRAM Reactivity 4.3.2.6 Criticality of Reactor During Refueling 4.3.2.7 Stability 4.3.2.8 Vessel Irradiations

4.3.3 Analytical Methods SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-v 4.3.4 Changes 4.3.5 References

4.4 THERMAL AND HYDRAULIC DESIGN

4.4.1 Design Basis

4.4.1.1 Safety Design Bases 4.4.1.2 Power Generation Design Bases 4.4.1.3 Requirements for Steady-State Conditions 4.4.1.4 Requirements for Transient Conditions 4.4.1.5 Summary of Design Bases

4.4.2 Description of Thermal-Hydraulic Design of the Reactor Core

4.4.2.1 Summary Comparison 4.4.2.2 Critical Power Ratio 4.4.2.2.1 Boiling Correlations 4.4.2.3 Thermal Operating Limits 4.4.2.3.1 Design Power Distribution 4.4.2.3.2 Design Linear Heat Generation Rates 4.4.2.4 Void Fraction Distribution 4.4.2.5 Core Coolant Flow Distribution and Orificing Pattern 4.4.2.6 Core Pressure Drop and Hydraulic Loads 4.4.2.6.1 Friction Pressure Drop 4.4.2.6.2 Local Pressure Drop 4.4.2.6.3 Elevation Pressure Drop 4.4.2.6.4 Acceleration Pressure Drop 4.4.2.7 Correlation and Physical Data 4.4.2.7.1 Pressure Drop Correlations 4.4.2.7.2 Void Fraction Correlations 4.4.2.7.3 Heat Transfer Correlation 4.4.2.8 Thermal Effects of Operational Transients 4.4.2.9 Uncertainties in Estimates 4.4.2.10 Flux Tilt Considerations 4.4.2.11 Crud Deposition 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System

4.4.3.1 Plant Configuration Data SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-vi 4.4.3.1.1 Reactor Coolant System Configuration 4.4.3.1.2 Reactor Coolant System Thermal Hydraulic Data 4.4.3.1.3 Reactor Coolant System Geometric Data

4.4.3.2 Operating Restrictions on Pumps 4.4.3.3 Power-Flow Operating Map 4.4.3.3.1 Limits for Normal Operation 4.4.3.3.1.1 Performance Characteristics 4.4.3.3.2 Regions of the Power Flow Map 4.4.3.4 Temperature-Power Operating Map (PWR) 4.4.3.5 Load Following Characteristics 4.4.3.6 Thermal and Hydraulic Characteristics Summary Table

4.4.4 Evaluation

4.4.4.1 Critical Power 4.4.4.2 Core Hydraulics 4.4.4.3 Influence of Power Distributions 4.4.4.4 Core Thermal Response 4.4.4.5 Analytical Methods 4.4.4.5.1 Reactor Model 4.4.4.5.2 System Flow Balances 4.4.4.5.3 System Heat Balances 4.4.4.6 Thermal-Hydraulic Stability Analysis

4.4.4.6.1 Introduction

4.4.4.6.2 Description 4.4.4.6.3 Stability Criteria 4.4.4.6.4 Mathematical Model 4.4.4.6.5 Analytical Confirmation 4.4.4.6.6 Analysis Results

4.4.5 Testing and Verification 4.4.6 Instrumentation Requirements

4.4.6.1 Loose Parts Monitoring

4.4.7 References

4.5 REACTOR MATERIALS

4.5.1 Control Rod System Structural Materials SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-vii 4.5.1.1 Material Specifications 4.5.1.2 Special Materials 4.5.1.3 Processes, Inspections and Tests 4.5.1.4 Control of Delta Ferrite Content 4.5.1.5 Protection of Materials During Fabrication, Shipping and Storage

4.5.2 Reactor Internal Materials

4.5.2.1 Material Specifications 4.5.2.2 Controls on Welding 4.5.2.3 Nondestructive Examination of Wrought Seamless Tubular Products 4.5.2.4 Fabrication and Processing of Austenitic Stainless Steel - Regulatory Guide Conformance 4.5.2.5 Contamination, Protection, and Cleaning of Austenitic Stainless Steel

4.5.3 Control Rod Drive Housing Supports

4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS

4.6.1 Information for CRDS

4.6.1.1 Control Rod Drive System Design 4.6.1.1.1 Design Bases 4.6.1.1.1.1 General Design Bases 4.6.1.1.1.1.1 Safety Design Bases 4.6.1.1.1.1.2 Power Generation Design Basis

4.6.1.1.2 Description 4.6.1.1.2.1 Control Rod Drive Mechanisms 4.6.1.1.2.2 Drive Components 4.6.1.1.2.2.1 Drive Piston 4.6.1.1.2.2.2 Index Tube 4.6.1.1.2.2.3 Collet Assembly 4.6.1.1.2.2.4 Piston Tube 4.6.1.1.2.2.5 Stop Piston 4.6.1.1.2.2.6 Flange and Cylinder Assembly 4.6.1.1.2.2.7 Lock Plug 4.6.1.1.2.3 Materials of Construction 4.6.1.1.2.3.1 Index Tube 4.6.1.1.2.3.2 Coupling Spud 4.6.1.1.2.3.3 Collet Fingers SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-viii 4.6.1.1.2.3.4 Seals and Bushings 4.6.1.1.2.3.5 Summary 4.6.1.1.2.4 Control Rod Drive Hydraulic System 4.6.1.1.2.4.1 Hydraulic Requirements 4.6.1.1.2.4.2 System Description 4.6.1.1.2.4.2.1 Supply Pump 4.6.1.1.2.4.2.2 Accumulator Charging Pressure 4.6.1.1.2.4.2.3 Drive Water Pressure 4.6.1.1.2.4.2.4 Cooling Water Header 4.6.1.1.2.4.2.5 Scram Discharge Volume 4.6.1.1.2.4.3 Hydraulic Control Units 4.6.1.1.2.4.3.1 Insert Drive Valve 4.6.1.1.2.4.3.2 Insert Exhaust Valve 4.6.1.1.2.4.3.3 Withdraw Drive Valve 4.6.1.1.2.4.3.4 Withdraw Exhaust Valve 4.6.1.1.2.4.3.5 Speed Control Units 4.6.1.1.2.4.3.6 Scram Pilot Valves 4.6.1.1.2.4.3.7 Scram Inlet Valve 4.6.1.1.2.4.3.8 Scram Exhaust Valve 4.6.1.1.2.4.3.9 Scram Accumulator 4.6.1.1.2.5 Control Rod Drive System Operation 4.6.1.1.2.5.1 Rod Insertion 4.6.1.1.2.5.2 Rod Withdrawal

4.6.1.1.2.5.3 Scram

4.6.1.1.2.6 Instrumentation 4.6.1.2 Control Rod Drive Housing Supports 4.6.1.2.1 Safety Objective 4.6.1.2.2 Safety Design Bases

4.6.1.2.3 Description

4.6.2 Evaluations of the CRDS

4.6.2.1 Safety Evaluation 4.6.2.1.1 Control Rods 4.6.2.1.1.1 Materials Adequacy Through Design Lifetime 4.6.2.1.1.2 Dimensional and Tolerance Analysis 4.6.2.1.1.3 Thermal Analysis of the Tendency to Warp 4.6.2.1.1.4 Forces for Expulsion 4.6.2.1.1.5 Functional Failure of Critical Components 4.6.2.1.1.6 Precluding Excessive Rates of Reactivity Addition 4.6.2.1.1.7 Effect of Fuel Rod Failure on Control Rod Channel Clearances SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-ix 4.6.2.1.1.8 Mechanical Damage 4.6.2.1.1.9 Evaluation of Control Rod Velocity Limiter 4.6.2.1.2 Control Rod Drives 4.6.2.1.2.1 Evaluation of Scram Time 4.6.2.1.2.2 Analysis of Malfunction Relating to Rod Withdrawal 4.6.2.1.2.2.1 Drive Housing Fails at Attachment Weld 4.6.2.1.2.2.2 Rupture of Hydraulic Line(s) to Drive Housing Flange 4.6.2.1.2.2.2.1 Pressure-under Line Break 4.6.2.1.2.2.2.2 Pressure-over Line Break 4.6.2.1.2.2.3 All Drive Flange Bolts Fail in Tension 4.6.2.1.2.2.4 Weld Joining Flange to Housing Fails in Tension 4.6.2.1.2.2.5 Housing Wall Ruptures 4.6.2.1.2.2.6 Flange Plug Blows Out 4.6.2.1.2.2.7 Ball Check Valve Plug Blows Out 4.6.2.1.2.2.8 Drive Pressure Control Valve Closure (Reactor Pressure, 0 psig) 4.6.2.1.2.2.9 Ball Check Valve Fails to Close Passage to Vessel Ports 4.6.2.1.2.2.10 Hydraulic Control Unit Valve Failures 4.6.2.1.2.2.11 Collet Fingers Fail to Latch 4.6.2.1.2.2.12 Withdrawal Speed Control Valve Failure 4.6.2.1.2.3 Scram Reliability 4.6.2.1.2.4 Control Rod Support and Operation 4.6.2.1.3 Control Rod Drive Housing Supports

4.6.3 Testing and Verification of the CRDs

4.6.3.1 Control Rod Drives 4.6.3.1.1 Testing and Inspection 4.6.3.1.1.1 Development Tests 4.6.3.1.1.2 Factory Quality Control Tests 4.6.3.1.1.3 Operational Tests 4.6.3.1.1.4 Acceptance Tests 4.6.3.1.1.5 Surveillance Tests 4.6.3.1.1.6 Functional Tests 4.6.3.2 Control Rod Drive Housing Supports 4.6.3.2.1 Testing and Inspection

4.6.4 Information for Combined Performance of Reactivity Systems

4.6.4.1 Vulnerability to Common Mode Failures 4.6.4.2 Accidents Taking Credit for Multiple Reactivity Systems

SSES-FSAR TOC Rev. 61 CHAPTER 4 TEXT Section Title FSAR Rev. 68 4-x 4.6.5 Evaluation of Combined Performance 4.6.6 References

SSES-FSAR TOC Rev. 61 CHAPTER 4 TABLES Number Title FSAR Rev. 68 4-xi 4.2-1 Deleted

4.2-2 Deleted

4.2-3 Deleted

4.2-4 Deleted

4.2-5 Deleted

4.2-6 Deleted

4.2-7 Deleted

4.2-8 Deleted

4.2-9 Deleted

4.2-10 Deleted

4.2-11 Deleted

4.2-12 Deleted

4.2-13 Deleted

4.2-14 Fuel Design Characteristics (Nominal)

4.3-1 Reactor Core Characteristics

4.3-2 Susquehanna Unit 1 Core Composition 4.3-3 Susquehanna Unit 2 Core Composition

4.3-4 Summary of BWR/4 and BWR/5 Design Revisions

4.3-5 Calculated Neutron Fluxes (Used to Evaluate Vessel Irradiation)

4.3-6 Calculated Neutron Flux at Core Equivalent Boundary

4.3-7 SSES Lattice Numbers and Corresponding Figures SSES-FSAR TOC Rev. 61 CHAPTER 4 TABLES Number Title FSAR Rev. 68 4-xii 4.4-1 Thermal and Hydraulic Design Characteristics of the Reactor Core

4.4-1a Deleted

4.4-2 Typical Void Distribution

4.4-2a Axial Power Distribution Used to Generate Typical Void and Quality Distributions

4.4-3 Typical Flow Quality Distribution

4.4-4 Typical Core Flow Distribution

4.4-4a Deleted

4.4-5 Deleted

4.4-6 Description of Uncertainties (BWR/4 and BWR/5)

4.4-7 Bypass Flow Paths

4.4-8 Plant Configuration Data

4.4-9 Lengths of Safety Injection Line

NOTE: Additional tables are presented in NEDE 20944/20944-P.

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xiii 4.1-1 Deleted

4.1-2 Steam Dryer Panel

4.1-3 Steam Dryer

4.1-4 Deleted

4.1-5 Deleted

4.1-6 Renumbered to FSAR Figure 4.2-14

4.1-7 Renumbered to FSAR Figure 4.2-20

4.1-8 Renumbered to FSAR Figure 4.2-21

4.2-1 Deleted

4.2-2 Deleted

4.2-3 Deleted

4.2-4 Deleted

4.2-5 Deleted

4.2-6 Deleted

4.2-7 Deleted

4.2-8a Deleted

4.2-8b Deleted

4.2-8c Deleted

4.2-9 Deleted

4.2-10 Deleted

4.2-11 Deleted SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xiv 4.2-12 Deleted

4.2-13 Deleted

4.2-14 This Figure Has Been Deleted

4.2-15 Core Cell (ATRIUMŽ-10 Fuel with Duralife 60C Control Rod)

4.2-15a Core Cell (ATRIUM-10 Fuel with MARATHON Control Rod)

4.2-15B Core Cell (ATRIUM TM-10 Fuel with Ultra-HD Control Rod) 4.2-15C Core Cell (ATRIUM TM-10 Fuel with Westinghouse CR 99 Control Rod) 4.2-16 This Figure Has Been Deleted

4.2-17 Fuel Bundle FANP ATRIUM-10

4.2-18 80 MIL Fuel Channel

4.2-18-1 80 MIL Fuel Channel

4.2-18-2 100 MIL Fuel Channel

4.2-18-3 Advanced Fuel Channel

4.2-19 Correct Fuel Assembly Orientation

4.2-20 Control Rod Assembly Original Equipment

4.2-21 Control Rod Assembly Duralife 160-C (D-160C)

4.2-22 Control Rod Assembly Marathon

4.2-23 Control Rod Assembly Westinghouse CR 99 4.3-1 Unit 1 Core Loading Pattern

4.3-2 Unit 2 Core Loading Pattern

4.3-3 Uranium Depletion as a Function of Exposure, 40% Voids (Typical)

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xv 4.3-4 Plutonium Buildup as a Function of Exposure, 40% Voids (Typical)

4.3-5 Fission Fraction as a Function of Exposure, 40% Voids (Typical)

4.3-6 Delayed Neutron Fraction as a Function of Exposure, 40% Voids (Typical)

4.3-7 Neutron Lifetime as a Functions of Exposure, 40% Voids (Typical)

4.3-8 This Figure Has Been Deleted

4.3-8-1 FRA ANP ATRIUM TM-10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 54

4.3-8-2 This Figure Has Been Deleted

4.3-8-3 FRA ANP ATRIUM TM-10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 55

4.3-8-4 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 50 4.3-8-5 Assembly Type 51 Reload Bundle Description

4.3-8-6 Assembly Type 52 Reload Bundle Description

4.3-8-7 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 49 4.3-8-8 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 49 4.3-8-9 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 47 4.3-8-10 FRA ANP ATRIUM Fuel Axial Enrichment (Nominal) PPL Assembly Type 56 4.3-8-11 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 57 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xvi 4.3-8-12 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 58 4.3-8-13 FRA ANP ATRIUM 10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 58 4.3-8-14 FRA-ANP ATRIUM TM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 60

4.3-8-15 FRA-ANP ATRIUM TM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 61

4.3-8-16 FRA-ANP ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 62

4.3-8-17 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 63

4.3-8-18 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 64

4.3-8-19 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 65

4.3-8-20 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 66

4.3-8-21 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 67

4.3-8-22 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 68

4.3-8-23 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 69

4.3-8-24 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 70

4.3-8-25 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 71

4.3-8-26 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 72

4.3-8-27 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 73

4.3-8-28 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 74

4.3-8-29 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 75 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xvii 4.3-8-30 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 76

4.3-8-31 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 77

4.3-8-32 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 79 4.3-8-33 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 80 4.3-8-34 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 81 4.3-8-35 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 82 4.3-8-36 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 83 4.3-8-37 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 84 4.3-8-38 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 85 4.3-8-39 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 86 4.3-8-40 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 87 4.3-8-40A ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 87A 4.3-8-41 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 88 4.3-8-42 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 89 4.3-8-43 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 90 4.3-8-44 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 91 4.3-8-45 ATRIUM -10 Fuel Axial Enrichment (Nominal) PPL Assembly Type 92

4.3-9 This Figure Has Been Deleted 4.3-9-1 This Figure Has Been Deleted

4.3-9-2 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 57 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xviii 4.3-9-3 FANP ATRIUM Fuel Radial Enrichment (Nominal) PPL Lattice Type 58

4.3-9-4 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 59 4.3-9-5 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 60 4.3-9-6 This Figure Has Been Deleted

4.3-9-7 This Figure Has Been Deleted

4.3-9-8 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 69 4.3-9-9 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 70 4.3-9-10 This Figure Has Been Deleted

4.3-9-11 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 52 4.3-9-12 This Figure Has Been Deleted

4.3-9-13 This Figure Has Been Deleted

4.3-9-14 This Figure Has Been Deleted

4.3-9-15 This Figure Has Been Deleted

4.3-9-16 This Figure Has Been Deleted

4.3-9-17 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 61 4.3-9-18 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 62 4.3-9-19 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 71 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xix 4.3-9-20 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 72 4.3-9-21 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 73 4.3-9-22 FANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 74 4.3-9-23 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 75 4.3-9-24 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 76 4.3-9-25 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 77 4.3-9-26 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 78 4.3-9-27 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 79 4.3-9-28 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 80 4.3-9-29 Update For U1C13 Reload & LEFM Uprate To 3489 MWT Rated Power 4.3-9-30 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 05 4.3-9-31 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 06 4.3-9-32 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 07 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xx 4.3-9-33 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 08 4.3-9-34 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 09 4.3-9-35 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 10 4.3-9-36 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 11 4.3-9-37 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 121 4.3-9-38 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 124 4.3-9-39 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 126 4.3-9-40 FRA ANP ATRIUM 10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 129 4.3-9-41 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 130 4.3-9-42 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 131 4.3-9-43 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 132 4.3-9-44 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 133 4.3-9-45 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 134 4.3-9-46 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 135 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxi 4.3-9-47 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 136 4.3-9-48 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 137 4.3-9-49 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 138 4.3-9-50 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 139 4.3-9-51 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 140 4.3-9-52 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 141 4.3-9-53 FRA ANP ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 142 4.3-9-54 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 143

4.3-9-55 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 144

4.3-9-56 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 145

4.3-9-57 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 146

4.3-9-58 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 147

4.3-9-59 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 148

4.3-9-60 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 149

4.3-9-61 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 150

4.3-9-62 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 151

4.3-9-63 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 152 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxii 4.3-9-64 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 153

4.3-9-65 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 154

4.3-9-66 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 155

4.3-9-67 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 156

4.3-9-68 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 157

4.3-9-69 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 158

4.3-9-70 ATRIUM -10 FUEL Radial Enrichment (Nominal) PPL Lattice Type 159

4.3-9-71 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 160

4.3-9-72 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 161

4.3-9-73 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 162

4.3-9-74 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 163

4.3-9-75 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 164

4.3-9-76 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 165

4.3-9-77 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 166

4.3-9-78 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 167

4.3-9-79 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 168

4.3-9-80 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 169

4.3-9-81 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 170 4.3-9-82 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 171

4.3-9-83 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 172

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxiii 4.3-9-84 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 173

4.3-9-85 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 174

4.3-9-86 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 175

4.3-9-87 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 176

4.3-9-88 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 177

4.3-9-89 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 178

4.3-9-90 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 179

4.3-9-91 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 180

4.3-9-92 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 181

4.3-9-93 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 182

4.3-9-94 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 183

4.3-9-95 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 184

4.3-9-96 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 185

4.3-9-97 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 186 4.3-9-98 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 187 4.3-9-99 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 188 4.3-9-100 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 189 4.3-9-101 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 190 4.3-9-102 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 191 4.3-9-103 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 192 4.3-9-104 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 193 SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxiv 4.3-9-105 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 194 4.3-9-106 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 195 4.3-9-107 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 196 4.3-9-108 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 197 4.3-9-109 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 198 4.3-9-110 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 199 4.3-9-111 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 200 4.3-9-112 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 201 4.3-9-113 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 202 4.3-9-114 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 203 4.3-9-115 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 204 4.3-9-116 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 205 4.3-9-117 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 206 4.3-9-118 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 207 4.3-9-119 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 208 4.3-9-120 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 209 4.3-9-121 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 210 4.3-9-122 ATRIUM -10 Fuel Radial Enrichment (Nominal) PPL Lattice Type 211 4.3-10 This Figure Has Been Deleted 4.3-10-1 This Figure Has Been Deleted

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxv 4.3-10-2 This Figure Has Been Deleted

4.3-10-3 This Figure Has Been Deleted

4.3-10-4 This Figure Has Been Deleted

4.3-10-5 This Figure Has Been Deleted

4.3-10-6 This Figure Has Been Deleted

4.3-10-7 This Figure Has Been Deleted

4.3-11 This Figure Has Been Deleted

4.3-11-1 FANP ATRIUM 10 Fuel Dominant Lattice Hot-Uncontrolled K-Infinity vs Exposure (Typical)

4.3-11-2 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 0 MWD/MTU (Typical)

4.3-11-3 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 15000 MWD/MTU (Typical)

4.3-11-4 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 40000 MWD/MTU (Typical)

4.3-11-5 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 0% Voids 0 MWD/MTU (Typical)

4.3-11-6 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 80% Voids 0 MWD/MTU (Typical)

4.3-11-7 FANP ATRIUM 10 Fuel Dominant Lattice Maximum Hot-Uncontrolled Local Peaking Factor vs Exposure (Typical)

4.3-12 Hot Excess Reactivity vs Exposure (Typical) 4.3-13 Shutdown Margin vs Exposure (Typical)

4.3-14 Vessel Fluence (R,0) Model for Azimuthal Flux Distribution

SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxvi 4.3-15 Relative Vessel Flux Variation With Angular Position

4.3-16 Relative Vessel Flux Variation With Elevation

4.3-17 This Figure Has Been Deleted

4.3-18 This Figure Has Been Deleted

4.3-19 This Figure Has Been Deleted

4.3-20 This Figure Has Been Deleted

4.3-21 This Figure Has Been Deleted

4.3-22 This Figure Has Been Deleted

4.3-23 This Figure Has Been Deleted

4.3-24 This Figure Has Been Deleted

4.3-25 This Figure Has Been Deleted

4.3-26 This Figure Has Been Deleted

4.3-27 This Figure Has Been Deleted

4.3-28 This Figure Has Been Deleted

4.3-29 This Figure Has Been Deleted

4.3-30 This Figure Has Been Deleted

4.4-1 Schematic of Reactor Assembly Showing the Bypass Flow Paths

4.4-2 Damping Coefficient Versus Decay Ratio (Second Order Systems)

4.4-3 Hydrodynamic and Core Stability Model for Initial Core

4.4-4 Deleted

4.4-5 Power-Flow Operating Map SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxvii 4.4-6A Deleted

4.4-6B Deleted

4.4-6C Deleted

4.4-7a 10 Cent Rod Reactivity Step at 51.5% Rated Power (Natural Circulation)

4.4-7b 10 psi Pressure Regulator Setpoint Step at 51.5% Rated Power (Natural Circulation)

4.4-7c 6-9 Inch Level Setpoint Step at 51.5% Rated Power (Natural Circulation)

4.4-8a 10 Cent Rod Reactivity Step at 105% Rated Power and 100% Rated Flow 4.4-8b 10 psi Pressure Regulator Setpoint Step at 105% Rated Power and 100% Rated Flow

4.4-8c 6-inch Level Setpoint Step at 105% Rated Power and 100% Rated Flow 4.4-8d 10% Load Demand Step at 105% Rated Power and 100% Rated Flow

4.4-9a 10 Cent Rod Reactivity Step at 68% Rated Power and 51.5% Rated Flow 4.4-9b 10 psi Pressure Regulator Step at 68% Rated Power and 51.5% Rated Flow 4.4-9c 6-inch Water Level Setpoint Step at 60% Rated Power and 51.5%

Rated Flow 4.4-9d 10% Load Demand Step at 68% Rated Power and 51.5% Rated Flow

4.4-10 Deleted

4.6-1 Control Rod to Control Rod Drive Coupling SSES-FSAR TOC Rev. 61 CHAPTER 4 FIGURES Number Title FSAR Rev. 68 4-xxviii 4.6-2 Control Rod Drive Unit

4.6-3 Control Rod Drive Schematic

4.6-4 Control Rod Drive (Cutaway)

4.6-5a Control Rod Drive - Part A

4.6-5b P&ID Control Rod Drive - Part B

4.6-6 Control Rod Drive System Process Diagram and Data

4.6-7 Control Rod Drive Hydraulic Control Unit

4.6-8 Control Rod Drive Housing Support

NOTE: Additional Figures are presented in NEDE 20944/20944-P.

SSES-FSARNIMSRev.60FSARRev.655-iCHAPTER5REACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSTABLEOFCONTENTSTEXTSectionTitle5.1

SUMMARY

DESCRIPTION 5.1.1SchematicFlowDiagram5.1.2PipingandInstrumentationDiagram5.1.3PlanandElevationDrawings5.2INTEGRITYOFREACTORCOOLANTPRESSUREBOUNDARY 5.2.1CompliancewithCodesandCodeCases 5.2.1.1Compliancewith10CFR50,Section50.55a5.2.1.2ApplicableCodeCases5.2.2OverpressureProtection 5.2.2.1DesignBasis 5.2.2.1.1SafetyDesignBases5.2.2.1.2PowerGenerationDesign5.2.2.1.3Discussion5.2.2.1.4SafetyValveCapacity5.2.2.2DesignEvaluation 5.2.2.2.1MethodofAnalysis5.2.2.2.2SystemDesign5.2.2.2.2.1OperatingConditions5.2.2.2.2.2Transients5.2.2.2.2.3Scram5.2.2.2.2.4Safety/ReliefValveTransientAnalysisSpecifications5.2.2.2.2.5SafetyValveCapacity5.2.2.2.3EvaluationofResults5.2.2.2.3.1SafetyValveCapacity SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-ii5.2.2.2.3.2PressureDropinInletandDischarge5.2.2.3Piping&InstrumentDiagrams5.2.2.4EquipmentandComponentDescription5.2.2.4.1Description5.2.2.4.2DesignParameters5.2.2.4.2.1Safety/ReliefValve 5.2.2.5MountingofPressureReliefDevices5.2.2.6ApplicableCodesandClassification5.2.2.7MaterialSpecification5.2.2.8ProcessInstrumentation5.2.2.9SystemReliability5.2.2.10InspectionandTesting5.2.3ReactorCoolantPressureBoundaryMaterials 5.2.3.1MaterialSpecifications5.2.3.2CompatibilitywithReactorCoolant5.2.3.2.1PWRChemistryofReactorCoolant5.2.3.2.2BWRChemistryofReactorCoolant5.2.3.2.3CompatibilityofConstructionMaterialswithReactorCoolant5.2.3.2.4CompatibilityofConstructionMaterialswithExternalInsulationandReactorCoolant5.2.3.3FabricationandProcessingofFerriticMaterials 5.2.3.3.1FractureToughness 5.2.3.3.1.1CompliancewithCodeRequirements5.2.3.3.1.2AcceptableFractureEnergyLevels5.2.3.3.1.3OperatingLimitsDuringHeatup,Cooldown,andCoreOperation5.2.3.3.1.4TemperatureLimitsforISIHydrostaticorLeakPressureTests5.2.3.3.1.5TemperatureLimitsforBoltup5.2.3.3.1.6ReactorVesselAnnealing5.2.3.3.2ControlofWelding SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-iii5.2.3.3.2.1ControlofPreheatTemperatureEmployedforWeldingofLowAlloySteel.RegulatoryGuide1.50(REV.0)5.2.3.3.2.2ControlofElectroslagWeldProperties.RegulatoryGuide1.34(REV.0) 5.2.3.3.2.3WelderQualificationforAreasofLimitedAccessibility.RegulatoryGuide1.71(REV0)5.2.3.3.3NondestructiveExaminationofFerriticTubularProducts5.2.3.4FabricationandProcessingofAusteniticStainlessSteels5.2.3.4.1AvoidanceofStressCorrosionCracking 5.2.3.4.1.1AvoidanceofSignificantSensitization5.2.3.4.1.2ProcessControlstoMinimizeExposuretoContaminants5.2.3.4.1.3ColdWorkedAusteniticStainlessSteels5.2.3.4.2ControlofWelding 5.2.3.4.2.1AvoidanceofHotCracking5.2.3.4.2.2ElectroslagWelds5.2.3.4.2.3WelderQualificationforAreasofLimitedAccessibility.RegulatoryGuide1.71(Rev.0)5.2.3.4.3NondestructiveExaminationofTubularProducts.RegulatoryGuide1.66(Rev.0)5.2.4In-ServiceInspectionandTestingofReactorCoolantPressureBoundary 5.2.4.1SystemBoundarySubjecttoInspection5.2.4.2Accessibility5.2.4.3ExaminationTechniquesandProcedures5.2.4.4InspectionIntervals5.2.4.5EvaluationofExaminationResults5.2.4.6SystemLeakageandHydrostaticPressureTests5.2.4.7AugmentedInserviceInspectiontoProtectAgainstPostulatedPipingFailures5.2.5DetectionofLeakageThroughReactorCoolantPressureBoundary 5.2.5.1LeakageDetectionMethods SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-iv5.2.5.1.1DetectionofAbnormalLeakageWithinthePrimaryContainment(NSS-Systems)5.2.5.1.2DetectionofAbnormalLeakageWithinthePrimaryContainment(Non-NSSS)5.2.5.1.2.1PrimaryContainmentTemperatureMonitoringSystem5.2.5.1.2.2PrimaryContainmentPressureMonitoringSystem5.2.5.1.2.3PrimaryContainmentAtmosphereMonitoring;AirborneRadioactivityMonitoring5.2.5.1.2.3.1SensitivityandResponseTime 5.2.5.1.2.4DrywellFloorDrainSumpMonitoringSystem5.2.5.1.2.4.1SystemDescription5.2.5.1.2.4.2Instrumentation5.2.5.1.2.4.3DrywellEquipmentDrainTankLevelMonitoringSystem5.2.5.1.2.4.4SensitivityandResponseTimeofMeasurement5.2.5.1.2.4.5SignalCorrelationandCalibration5.2.5.1.2.4.6SeismicQualifications5.2.5.1.2.4.7TestingandCalibration5.2.5.1.3DetectionofAbnormalLeakageOutsidethePrimaryContainment 5.2.5.2LeakDetectionDevicesforNSS-System5.2.5.3LimitsforReactorCoolantLeakage5.2.5.3.1TotalLeakageRate5.2.5.3.2NormallyExpectedLeakageRate5.2.5.4UnidentifiedLeakageInsidetheDrywell 5.2.5.4.1UnidentifiedLeakageRate5.2.5.4.2SensitivityandResponseTimes5.2.5.4.3LengthofThrough-WallFlaw5.2.5.4.4MarginsofSafety5.2.5.4.5CriteriatoEvaluatetheAdequacyandMarginoftheLeakDetectionSystem5.2.5.5DifferentiationBetweenIdentifiedandUnidentifiedLeaks5.2.5.6SensitivityandOperabilityTests SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-v5.2.5.7SafetyInterfaces5.2.5.8TestingandCalibration5.2.6References 5.3REACTORVESSEL 5.3.1ReactorVesselMaterials 5.3.1.1MaterialsSpecifications5.3.1.2SpecialProcessesUsedforManufacturingandFabrication5.3.1.3SpecialMethodsforNondestructiveExamination5.3.1.4SpecialControlsforFerriticandAusteniticStainlessSteels5.3.1.4.1ComplianceWithRegulatoryGuides 5.3.1.4.1.1RegulatoryGuide1.31(Rev.1),ControlofStainlessSteelWelding5.3.1.4.1.2RegulatoryGuide1.34(12/72),ControlofElectroslagWeldProperties5.3.1.4.1.2RegulatoryGuide1.34,12/72ControlofElectroslagWeldProperties 5.3.1.4.1.3RegulatoryGuide1.43(5/73),ControlofStainlessSteelWeldCladdingofLow-AlloySteelComponents5.3.1.4.1.4RegulatoryGuide1.44(5/73),ControloftheUseofSensitizedStainlessSteel5.3.1.4.1.5RegulatoryGuide1.50(5/73),ControlofPreheatTemperatureforWeldingLow-AlloySteel5.3.1.4.1.6RegulatoryGuide1.71(12/73),WelderQualificationforAreasofLimitedAccessibility5.3.1.4.1.7RegulatoryGuide1.99(Rev.2),RadiationEmbrittlementofReactorVesselMaterials5.3.1.5FractureToughness 5.3.1.5.1Compliancewith10CFR50AppendixG SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-vi5.3.1.5.1.1IntentofProposedApproach5.3.1.5.1.2OperatingLimitsBasedonFractureToughness5.3.1.5.1.3OperatingLimitsDuringHeatup,Cool-downandCoreOperation5.3.1.5.1.4TemperatureLimitsforISIHydrostaticorLeakPressureTests5.3.1.5.1.5AdjustedReferenceTemperatureForLimitingCoreBeltlineMaterial5.3.1.5.1.6TemperatureLimitsforBoltup5.3.1.5.1.7ReactorVesselAnnealing5.3.1.6MaterialSurveillance 5.3.1.6.1Compliancewith"ReactorVesselMaterialSurveillanceProgramRequirements"5.3.1.6.2NeutronFluxandFluenceCalculations5.3.1.6.3PositioningofSurveillanceCapsulesandMethodofAttachment5.3.1.6.4TimeandNumberofDosimetryMeasurements5.3.1.7ReactorVesselFasteners 5.3.2Pressure-TemperatureLimits 5.3.2.1LimitCurves5.3.2.2OperatingProcedures5.3.3ReactorVesselIntegrity 5.3.3.1Design5.3.3.1.1Description5.3.3.1.1.1ReactorVessel5.3.3.1.1.2ShroudSupport5.3.3.1.1.3ProtectionofClosureStuds5.3.3.1.2SafetyDesignBases5.3.3.1.3PowerGenerationDesignBasis5.3.3.1.4ReactorVesselDesignData5.3.3.1.4.1VesselSupport5.3.3.1.4.2ControlRodDriveHousings5.3.3.1.4.3In-CoreNeutronFluxMonitorHousings5.3.3.1.4.4ReactorVesselInsulation5.3.3.1.4.5ReactorVesselNozzles SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-vii5.3.3.1.4.6MaterialsandInspections5.3.3.1.4.7ReactorVesselSchematic5.3.3.2MaterialsofConstruction5.3.3.3FabricationMethods5.3.3.4InspectionRequirements5.3.3.5ShipmentandInstallation5.3.3.6OperatingConditions5.3.3.7InserviceSurveillance5.3.4References5.4COMPONENTANDSUBSYSTEMDESIGN 5.4.1ReactorRecirculationPumps 5.4.1.1SafetyDesignBases5.4.1.2PowerGenerationDesignBases5.4.1.3Description5.4.1.4SafetyEvaluation5.4.1.5InspectionandTesting5.4.2SteamGenerators(PWR)5.4.3ReactorCoolantPiping5.4.4MainSteamlineFlowRestrictors5.4.4.1SafetyDesignBases5.4.4.2Description5.4.4.3SafetyEvaluation5.4.4.4InspectionandTesting5.4.5MainSteamlineIsolationSystem 5.4.5.1SafetyDesignBases5.4.5.2Description5.4.5.3SafetyEvaluation5.4.5.4InspectionandTesting5.4.6ReactorCoreIsolationCoolingSystem5.4.6.1DesignBases5.4.6.1.1ResidualHeatandIsolation SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-viii5.4.6.1.1.1ResidualHeat5.4.6.1.1.2Isolation5.4.6.1.2Reliability,Operability,andManualOperation 5.4.6.1.2.1ReliabilityandOperability(Alsoseesubsection5.4.6.2.4)5.4.6.1.2.2ManualOperation(Alsoseesubsection5.4.6.2.5.2and5.4.6.2.5.35.4.6.1.3LossofOffsitePower5.4.6.1.4PhysicalDamage5.4.6.1.5Environment5.4.6.2SystemDesign 5.4.6.2.1General 5.4.6.2.1.1Description5.4.6.2.1.2Diagrams5.4.6.2.1.3Interlocks5.4.6.2.2EquipmentandComponentDescription 5.4.6.2.2.1DesignConditions5.4.6.2.2.2DesignParameters5.4.6.2.3ApplicableCodesandClassifications5.4.6.2.4SystemReliabilityConsiderations5.4.6.2.5SystemOperations5.4.6.2.5.1AutomaticOperation5.4.6.2.5.2TestLoopOperation5.4.6.2.5.3SteamCondensing(HotStandby)Operation5.4.6.2.5.4LimitingSingleFailure5.4.6.3PerformanceEvaluation5.4.6.4PreoperationalTesting5.4.6.5SafetyInterfaces5.4.7ResidualHeatRemovalSystem 5.4.7.1DesignBases SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-ix5.4.7.1.1FunctionalDesignBasis5.4.7.1.1.1ResidualHeatRemovalMode(ShutdownCoolingMode)5.4.7.1.1.2LowPressureCoolantInjection(LPCI)Mode5.4.7.1.1.3SuppressionPoolCoolingMode5.4.7.1.1.4ContainmentSprayCoolingMode5.4.7.1.1.5ReactorSteamCondensingMode5.4.7.1.1.6FuelPoolCoolingMode5.4.7.1.2DesignBasisforIsolationofRHRSystemfromReactorCoolantSystem5.4.7.1.3DesignBasisforPressureReliefCapacity5.4.7.1.4DesignBasiswithRespecttoGeneralDesignCriteria55.4.7.1.5DesignBasisforReliabilityandOperability5.4.7.1.6DesignBasisforProtectionfromPhysicalDamage5.4.7.2SystemsDesign 5.4.7.2.1SystemDiagrams5.4.7.2.2EquipmentandComponentDescription5.4.7.2.3ControlsandInstrumentation5.4.7.2.4ApplicableCodesandClassifications5.4.7.2.5ReliabilityConsiderations5.4.7.2.6ManualAction5.4.7.3PerformanceEvaluation 5.4.7.3.1ShutdownWithAllComponentsAvailable5.4.7.3.2ShutdownWithMostLimitingFailure5.4.7.4PreoperationalTesting 5.4.8ReactorWaterCleanupSystem 5.4.8.1DesignBases 5.4.8.1.1SafetyDesignBases5.4.8.1.2PowerGenerationDesignBases5.4.8.2SystemDescription5.4.8.3SystemEvaluation SSES-FSARNIMSRev.60CHAPTER5TEXTSectionTitleFSARRev.655-x5.4.9MainSteamLinesandFeedwaterPiping5.4.9.1SafetyDesignBases5.4.9.2PowerGenerationDesignBases5.4.9.3Description5.4.9.4SafetyEvaluation5.4.9.5InspectionandTesting5.4.10Pressurizer5.4.11PressurizerReliefDischargeSystem5.4.12Valves5.4.12.1SafetyDesignBases5.4.12.2Description5.4.12.3SafetyEvaluation5.4.12.4InspectionandTesting5.4.13SafetyandReliefValves 5.4.13.1SafetyDesignBases5.4.13.2Description5.4.13.3SafetyEvaluation5.4.13.4InspectionandTesting5.4.14ComponentSupports 5.4.14.1SafetyDesignBases5.4.14.2Description5.4.14.3SafetyEvaluation5.4.14.4InspectionandTesting5.4.15HighPressureCoolantInjection(HPCI)System5.4.16CoreSpray(CS)System5.4.17StandbyLiquidControl(SLC)System5.4.18References SSES-FSARNIMSRev.60CHAPTER5TABLESNumberTitleFSARRev.655-xi5.1-1DesignandPerformanceCharacteristicsoftheReactorCoolantSystemandItsComponents5.2-1ReactorCoolantPressureBoundaryComponentsCodeCaseInterpretations5.2-2NuclearSystemSafety/ReliefSetPointsUnits1and2 5.2-3DesignTemperature,PressureandMaximumTestPressureforRCPBComponents5.2-4ReactorCoolantPressureBoundaryMaterials 5.2-5BWRWaterChemistry 5.2-6SystemsWhichMayInitiateDuringOverpressureEvent 5.2-7WaterSampleLocations 5.2-8SummaryofIsolation/AlarmofSystemMonitoredandLeakDetectionMethodsUsed5.2-9SequenceofEventsforMSIVIsolationClosure(SeeFigure5.2-13) 5.2.9AThisTableHasBeenDeleted 5.2-10RCPBComponentsinCompliancewith10CFR50.55(a)(2)(ii) 5.2-11IdentifiedLeakagesintotheDrywellEquipmentDrainTank 5.2-12UnidentifiedLeakagesintotheDrywellFloorDrainSump 5.2-13EstimatedMonitorResponses 5.2-14RCPBLeakDetectionMonitorsInsidePrimaryContainmentDrywell 5.3-1aAppendixGMatrixForSusquehannaUnit1 5.3-1bAppendixHMatrixForSusquehannaSESUnit1 SSES-FSARNIMSRev.60CHAPTER5TABLESNumberTitleFSARRev.655-xii5.3-2aAppendixGMatrixForSusquehannaSESUnit25.3-2bAppendixHMatrixForSusquehannaSESUnit2 5.3-3ReactorVesselMaterialSurveillanceProgram-WithdrawalSchedule 5.4-1ThisTableHasBeenDeleted 5.4-2ReactorWaterCleanupSystemEquipmentDesignData 5.4-3RHRReliefValveData 5.4-4RCPBComponentDescription SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xiii5.1-1ThisFigureisDeleted5.1-2CoolantVolumesoftheBoilingWaterReactor 5.1-2A-1ThisFigureisDeleted 5.1-2A-2ThisFigureisDeleted 5.1-2BThisFigureisDeleted 5.1-3ThisFigureisDeleted 5.1-3A-1P&ID-Unit1NuclearBoiler 5.1-3A-2P&ID-Unit1NuclearBoiler 5.1-3BP&ID-Unit1NuclearBoilerVesselInstrumentation 5.1-4-1ReactorCoolantSystemPlan 5.1-4-2ReactorCoolantSystemElevation 5.1-4-3ReactorCoolantSystemElevation 5.2-1ThisFigureisDeleted 5.2-1AThisFigureisDeleted 5.2-2SimulatedSafety/ReliefValveSpringModeCharacteristicUsedforCapacitySizingAnalysis5.2-2ASimulatedSafety/ReliefValveSpringModeCharacteristic 5.2-3ThisFigureisDeleted 5.2-4ThisFigureisDeleted 5.2-5ThisFigureisDeleted 5.2-6SafetyValveLiftVersusTimeCharacteristic SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xiv5.2-7SchematicofSafetyValvewithAuxiliaryActuatingDevice5.2-8TypicalBWRFeedwaterCycle 5.2-9Conductancevs.pHasaFunctionofChlorideConcentrationofAqueousSolutionat25 C5.2-10CalculatedLeakRateVersusCrackLengthasaFunctionofAppliedHoopStress5.2-11AxialThrough-WallCrackLengthDataCorrelation 5.2-12RegionforSpringSafetyModeNominalSetpoint 5.2-13OverpressureProtectionAnalysis(MSIVClosurewithHighFluxScramTrip) 5.2-14OverpressureProtectionAnalysis(MSIVClosurewithHighFluxScramTrip) 5.3-1ReactorVessel 5.3-2FigureDeleted 5.3-3BracketforHolingSurveillanceCapsule 5.3-4aFigureDeleted-SeeUnit1TechSpecFigures3.4.10-1thru3.4.10-35.3-4bFigureDeleted-SeeUnit2TechSpecFigures3.4.10-1thru3.4.10-35.3-4cUnit1PredictedAdjustedReferenceTemperaturevs.EffectiveFullPowerYearsofOperation5.3-4dUnit2PredictedAdjustedReferenceTemperaturevs.EffectiveFullPowerYearsofOperation5.3-5ThisFigureisIntentionallyLeftBlank 5.4-1RecirculationSystemElevationandIsometric 5.4-2AThisFigureHasBeenDeleted SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xv5.4-2b-1ThisFigureHasBeenReplacedbyDwg.M-143,Sh.15.4-2b-2ThisFigureHasBeenReplacedbyDwg.M-143,Sh.2 5.4-2cThisFigureHasBeenReplacedbyDwg.B31-13,Sh.3 5.4-2DThisFigureisDeleted 5.4-3RecirculationPumpHead,NPSH,FlowandEfficiencyCurves 5.4-4aRHRSuctionStrainerDetails 5.4-4bRHRSuctionStrainerDetails 5.4-5OperatingPrincipleofJetPump 5.4-6CoreFloodingCapabilityofRecirculationSystem5.4-7MainSteamLineFlowRestrictorLocation 5.4-8ThisFigureHasBeenDeleted 5.4-9aThisFigureHasBeenReplacedbyDwg.M-149,Sh.1 5.4-9bThisFigureHasBeenReplacedbyDwg.M-150,Sh.1 5.4-10ThisFigureHasBeenReplacedbyDwg.M1-E51-81,Sh.1 5.4-11ThisFigureisIntentionallyLeftBlank 5.4-11-1ThisFigureisIntentionallyLeftBlank 5.4-11-2ThisFigureisIntentionallyLeftBlank 5.4-11-3ThisFigureisIntentionallyLeftBlank 5.4-11-4ThisFigureisIntentionallyLeftBlank 5.4-12ThisFigureisIntentionallyLeftBlank 5.4-12-1ThisFigureisIntentionallyLeftBlank SSES-FSARNIMSRev.60CHAPTER5FIGURESNumberTitleFSARRev.655-xvi5.4-12-2ThisFigureisIntentionallyLeftBlank5.4-13ThisFigureisIntentionallyLeftBlank 5.4-13-1ThisFigureHasBeenReplacedbyDwg.M-151,Sh.1 5.4-13-2ThisFigureHasBeenReplacedbyDwg.M-151,Sh.2 5.4-13-3ThisFigureHasBeenReplacedbyDwg.M-151,Sh.3 5.4-13-4ThisFigureHasBeenReplacedbyDwg.M-151,Sh.4 5.4-14-1ThisFigureHasBeenReplacedbyDwg.M1-E11-3,Sh.1 5.4-14-2ThisFigureHasBeenReplacedbyDwg.M1-E11-3,Sh.2 5.4-15FigureDeleted 5.4-15AThisFigureHasBeenReplacedbyDwg.M1-G33-16,Sh.1 5.4-15BThisFigureHasBeenReplacedbyDwg.M1-G33-18,Sh.1 5.4-16ThisFigureHasBeenIntentionallyLeftBlank 5.4-16-1ThisFigureHasBeenReplacedbyDwg.M1-144,Sh.1 5.4-16-2ThisFigureHasBeenReplacedbyDwg.M1-144,Sh.2 5.4-16-3ThisFigureHasBeenReplacedbyDwg.M1-144,Sh.3 5.4-17AThisFigurehasbeenDeletedbecauseofDuplication(SeeFigure5.4-15a) 5.4-17BThisFigurehasbeenDeletedbecauseofDuplication(SeeFigure5.4-15b) 5.4-18ThisFigureHasBeenReplacedbyDwg.M-145,Sh.1 SSES-FSAR NIMS Rev. 62 FSAR Rev. 68 6-i CHAPTER 6 ENGINEERED SAFETY FEATURES TABLE OF CONTENTS TEXT Section Title 6.0 ENGINEERED SAFETY FEATURES

6.1 ENGINEERED SAFETY FEATURE MATERIALS

6.1.1 Metallic Materials

6.1.1.1 Materials Selection and Fabrication 6.1.1.1.1 NSSS Material Specifications 6.1.1.1.2 Compatibility of NSSS Construction Materials with Core Cooling Water and Containment Sprays 6.1.1.1.3 NSSS Controls for Austenitic Stainless Steel 6.1.1.2 Composition, Compatibility, and Stability of Containment and Core Spray Coolants

6.1.2 Organic Materials

6.1.3 Post-Accident Chemistry

6.2 CONTAINMENT SYSTEMS

6.2.1 Primary Containment Functional Design

6.2.1.1 Pressure Suppression Containment 6.2.1.1.1 Design Basis 6.2.1.1.2 Design Features 6.2.1.1.2.1 Protection from Dynamic Effects 6.2.1.1.2.2 Codes, Standards, and Guides 6.2.1.1.2.3 Functional Capability Tests 6.2.1.1.2.4 External Pressure Loading Conditions 6.2.1.1.2.5 Trapped Water that Cannot Return to Containment Sump 6.2.1.1.2.6 Containment and Subcompartment Atmosphere 6.2.1.1.3 Design Evaluation 6.2.1.1.3.1 Summary Evaluation 6.2.1.1.3.2 Containment Design Parameters 6.2.1.1.3.2.1 Downcomer Vent Flow Loss Coefficient 6.2.1.1.3.2.2 Vacuum Breaker Flow Loss Coefficient SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-ii 6.2.1.1.3.3 Accident Response Analysis 6.2.1.1.3.3.1 Recirculation Line Rupture 6.2.1.1.3.3.1.1 Assumptions for Reactor Blowdown 6.2.1.1.3.3.1.2 Assumptions for Containment Pressurization 6.2.1.1.3.3.1.3 Assumptions for Long-Term Cooling 6.2.1.1.3.3.1.4 Initial Conditions for Accident Analyses 6.2.1.1.3.3.1.5 Short-Term Accident Response 6.2.1.1.3.3.1.6 Long-Term Accident Responses 6.2.1.1.3.3.1.7 Energy Balance During Accident 6.2.1.1.3.3.1.8 Chronology of Accident Events 6.2.1.1.3.3.2 Main Steamline Break 6.2.1.1.3.3.3 Hot Standby Accident Analysis 6.2.1.1.3.3.4 Intermediate Size Breaks 6.2.1.1.3.3.5 Small Size Breaks 6.2.1.1.3.3.5.1 Reactor System Blowdown Considerations 6.2.1.1.3.3.5.2 Containment Response 6.2.1.1.3.3.5.3 Recovery Operations 6.2.1.1.3.3.5.4 Drywell Design Temperature Considerations 6.2.1.1.3.4 Accident Analysis Models 6.2.1.1.3.4.1 Short-Term Pressurization Model 6.2.1.1.3.4.2 Long-Term Cooling Mode 6.2.1.1.3.4.3 Analytical Assumptions 6.2.1.1.3.4.4 Energy Balance Considerations 6.2.1.1.3.4.5 Containment Thermodynamic Conditions 6.2.1.1.3.4.6 Solution of Equations 6.2.1.1.4 Negative Pressure Design Evaluation 6.2.1.1.4.1 Glossary of Terms Used in Subsection 6.2.1.1.4 6.2.1.1.5 Suppression Pool Bypass Effects 6.2.1.1.5.1 Protection Against Bypass Paths 6.2.1.1.5.2 Reactor Blowdown Conditions and Operator Response 6.2.1.1.5.3 Analytical Assumptions 6.2.1.1.5.4 Analytical Results 6.2.1.1.6 Suppression Pool Dynamic Loads 6.2.1.1.7 Asymmetric Loading Conditions 6.2.1.1.8 Containment Environment Control 6.2.1.1.9 Post-Accident Monitoring 6.2.1.2 Containment Subcompartments 6.2.1.3 Mass and Energy Release Analyses for Postulated Loss-of-Coolant Accidents 6.2.1.3.1 Mass and Energy Release Data SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-iii 6.2.1.3.2 Energy Sources 6.2.1.3.3 Reactor Blowdown Model Description 6.2.1.3.4 Effects of Metal-Water Reaction 6.2.1.3.5 Thermal Hydraulic Data for Reactor Analysis

6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures Inside Containment

6.2.1.5 Minimum Containment Pressure Analysis for Performance Capability Studies on Emergency Core Cooling System

6.2.1.6 Testing and Inspection 6.2.1.7 Instrumentation Requirements 6.2.1.8 Response to NRC Generic Letter (GL) 96-06 6.2.1.8.1 Drywell Cooling Water hammer and Two-Phase Flow 6.2.1.8.1.1 Containment Cooling 6.2.1.8.1.2 Containment Integrity 6.2.1.8.1.3 Closed Loop System Overpressurization 6.2.1.8.1.3.1 Reactor Building Closed Cooling Water/Reactor Building Cooling Water (RBCCW/RBCW) 6.2.1.8.1.3.2 Drywell Floor Drain Sump 6.2.1.8.2 Containment Penetration Overpressurization

6.2.2 Containment Heat Removal System

6.2.2.1 Design Basis 6.2.2.2 Containment Cooling System Design 6.2.2.3 Design Evaluation of the Containment Cooling System 6.2.2.3.1 Summary of Containment Cooling Analysis 6.2.2.4 Tests and Inspections 6.2.2.5 Instrumentation Requirements

6.2.3 Secondary Containment Functional Design

6.2.3.1 Design Bases 6.2.3.2 System Design 6.2.3.2.1 Secondary Containment Design 6.2.3.2.2 Secondary Containment Isolation System 6.2.3.2.3 Secondary Containment Bypass Leakage (SCBL) 6.2.3.2.3.1 Water Seals 6.2.3.3 Design Evaluation SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-iv 6.2.3.4 Tests and Inspections 6.2.3.5 Instrumentation Requirements

6.2.4 Containment Isolation System

6.2.4.1 Design Bases 6.2.4.2 System Design 6.2.4.3 Design Evaluation 6.2.4.3.1 Evaluation Against General Design Criterion 54 6.2.4.3.1.1 Operability and Leak Tests 6.2.4.3.2 Evaluation Against General Design Criterion 55 6.2.4.3.2.1 Feedwater Line 6.2.4.3.2.2 Recirculation Pump Seal Water Supply Line 6.2.4.3.2.3 Control Rod Drive Lines 6.2.4.3.2.4 RCIC System Steamlines 6.2.4.3.2.5 Standby Liquid Control System Lines 6.2.4.3.2.6 Reactor Water Cleanup System 6.2.4.3.2.7 HPCI System Steamlines 6.2.4.3.2.8 Main Steamlines 6.2.4.3.2.9 CS Influent Penetrations 6.2.4.3.2.10 RHR Penetrations Connected to the RPV 6.2.4.3.3 Evaluation Against General Design Criterion 56 6.2.4.3.3.1 Containment Purge 6.2.4.3.3.2 RCIC Turbine Exhaust, Vacuum Pump Discharge, and RCIC Pump Minimum Flow Bypass

6.2.4.3.3.3 HPCI Turbine Exhaust and HPCI Pump Minimum Flow Bypass 6.2.4.3.3.4 RCIC and HPCI Turbine Exhaust Vacuum Breaker Lines

6.2.4.3.3.5 Reactor Building Closed Cooling Water and Reactor Building Chilled Water Supplies and Returns

6.2.4.3.3.6 Post-LOCA Atmosphere Sampling Lines 6.2.4.3.3.7 Liquid Radwaste System Equipment and Floor Drains 6.2.4.3.3.8 Suppression Pool Cleanup and Drain 6.2.4.3.3.9 Containment Instrument Gas Supply to Containment Vacuum Relief Valves

6.2.4.3.3.10 Traversing Incore Probe (TIP) Guide Tubes 6.2.4.3.4 Evaluation Against General Design Criterion 57 6.2.4.3.5 Evaluation Against Regulatory Guide 1.11 (Rev. 1)

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-v 6.2.4.3.6 GDC 56 Isolation Provisions With A Single Isolation Valve Outside Containment

6.2.4.3.6.1 Core Spray (CS) Influent Penetrations 6.2.4.3.6.2 Containment Spray and RHR Pump Test and Minimum Flow Lines 6.2.4.3.6.3 HPCI, RCIC, CS, and RHR Pump Suction Lines 6.2.4.3.6.4 RHR Combined Relief Valve Discharge and Heat Exchanger Vent Lines

6.2.4.3.7 Failure Mode and Effects Analyses for Containment Isolation 6.2.4.4 Tests and Inspections

6.2.5 Combustible Gas Control in Containment

6.2.5.1 Design Bases 6.2.5.2 System Design 6.2.5.3 Design Evaluation 6.2.5.4 Test and Inspections 6.2.5.5 Instrumentation Requirements 6.2.5.5.1 Hydrogen Recombiner System 6.2.5.5.2 Containment Hydrogen Purge Subsystem

6.2.5.5.3 Instrumentation Requirements for Primary Containment Atmosphere Monitoring System (Hydrogen and Oxygen Analyzer)

6.2.6 Primary Reactor Containment Leakage Rate Testing 6.2.6.1 Primary Reactor Containment Integrated Leakage Rate Test 6.2.6.2 Primary Containment Penetration Leakage Rate Test 6.2.6.3 Primary Containment Isolation Valve Leakage Rate Tests 6.2.6.4 Scheduling and Reporting of Periodic Tests 6.2.6.5 Special Testing Requirements 6.2.6.5.1 Drywell to Pressure Suppression Chamber Atmosphere Bypass Area Test

6.2.6.5.1.1 High Pressure Leak Test 6.2.6.5.l.2 Low Pressure Leak Test

6.2.7 References

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-vi 6.3 EMERGENCY CORE COOLING SYSTEMS

6.3.1 Design Bases and Summary Description

6.3.1.1 Design Bases 6.3.1.1.1 Performance and Functional Requirements 6.3.1.1.2 Reliability Requirements 6.3.1.1.3 ECCS Requirements for Protection from Physical Damage 6.3.1.1.4 ECCS Environmental Design Basis 6.3.1.2 Summary Descriptions of ECCS 6.3.1.2.1 High Pressure Coolant Injection 6.3.1.2.2 Core Spray 6.3.1.2.3 Low Pressure Coolant Injection 6.3.1.2.4 Automatic Depressurization System

6.3.2 System Design

6.3.2.1 Schematic Piping and Instrumentation Diagrams 6.3.2.2 Equipment and Component Descriptions 6.3.2.2.1 High Pressure Coolant Injection (HPCI) System 6.3.2.2.1.1 NPSH Available with Suction from the Condensate Storage Tank 6.3.2.2.1.2 NPSH Available with Suction from the Suppression Pool 6.3.2.2.2 Automatic Depressurization System (ADS) 6.3.2.2.3 Core Spray (CS) System 6.3.2.2.3.1 NPSH Available for CS 6.3.2.2.4 Low Pressure Coolant Injection (LPCI) System 6.3.2.2.4.1 NPSH Available for RHR 6.3.2.2.5 Discharge Line Fill System 6.3.2.3 Applicable Codes and Classification 6.3.2.4 Materials Specifications and Compatibility 6.3.2.5 System Reliability 6.3.2.6 Protection Provisions 6.3.2.7 Provisions for Performance Testing 6.3.2.8 Manual Actions 6.3.2.9 Position Verification for Manual Valves

6.3.3 ECCS Performance Evaluation

6.3.3.1 ECCS Bases for Technical Specifications 6.3.3.2 Acceptance Criteria for ECCS Performance 6.3.3.3 Single Failure Considerations SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-vii 6.3.3.4 System Performance During the Accident 6.3.3.5 Use of Dual Function Components for ECCS 6.3.3.6 Limits on ECCS System Parameters 6.3.3.7 ECCS Analyses for LOCA 6.3.3.7.1 LOCA Analysis Procedures and Input Variables 6.3.3.7.2 Accident Description 6.3.3.7.3 Break Spectrum Calculations 6.3.3.7.4 Large Recirculation Line Break Calculations 6.3.3.7.5 Transition Recirculation Line Break Calculations 6.3.3.7.6 Small Recirculation Line Break Calculations 6.3.3.7.7 Calculations for Other Break Locations 6.3.3.8 LOCA Analysis Conclusions

6.3.4 Tests and Inspections

6.3.4.1 ECCS Performance Tests 6.3.4.2 Reliability Tests and Inspections 6.3.4.2.1 HPCI Testing 6.3.4.2.2 ADS Testing 6.3.4.2.3 CS Testing 6.3.4.2.4 LPCI Testing

6.3.5 Instrumentation Requirements

6.3.6 NPSHA Margin and Vortex Formation After a Passive Failure in a Water Tight ECCS Pump Room 6.3.7 References

6.4 HABITABILITY SYSTEMS

6.4.1 Design Bases

6.4.2 System Design

6.4.2.1 Control Structure Envelope 6.4.2.2 Ventilation System Design 6.4.2.3 Leaktightness 6.4.2.4 Interaction with Other Zones and Pressure-Containing Equipment 6.4.2.5 Shielding Design

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-viii 6.4.3 System Operational Procedures

6.4.4 Design Evaluations

6.4.4.1 Radiological Protection 6.4.4.2 Toxic Gas Protection

6.4.5 Testing and Inspection

6.4.6 Instrumentation Requirements

6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS

6.5.1 Engineered Safety Feature (ESF) Filter Systems

6.5.1.1 Standby Gas Treatment System (SGTS) 6.5.1.1.1 Design Bases 6.5.1.1.2 System Design 6.5.1.1.3 Design Evaluation 6.5.1.1.4 Tests and Inspections 6.5.1.1.5 Instrument Requirements 6.5.1.1.6 Materials 6.5.1.2 Control Structure Emergency Outside Air Supply System (OV-101) (CSEOASS)

6.5.1.2.1 Design Bases 6.5.1.2.2 System Design 6.5.1.2.3 Design Evaluation 6.5.1.2.4 Tests and Inspections 6.5.1.2.5 Instrumentation Requirements 6.5.1.2.6 Materials

6.5.2 Containment Spray Systems

6.5.3 Fission Product Control System

6.5.3.1 Primary Containment 6.5.3.2 Secondary Containment

6.5.4 Ice Condenser as a Fission Product Cleanup System

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-ix 6.5.5 References

6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS

6.6.1 Components Subject to Examination

6.6.2 Accessibility

6.6.2.1 Piping and Component Welds 6.6.2.2 Insulation Removal 6.6.2.3 Inaccessible Class 3 Piping

6.6.3 Examination Techniques and Procedures

6.6.4 Inspection Intervals

6.6.5 Examination Categories and Requirements

6.6.6 Evaluation of Examination Results

6.6.7 System Pressure Tests

6.6.8 Augmented Inservice Inspection to Protect Against Postulated Piping Failures

6.6.9 Containment Inspections

6.7 MAIN STEAM ISOLATION VALVE LEAKAGE ISOLATED CONDENSER TREATMENT METHOD

6.7.1 Design Bases

6.7.1.1 Safety Criteria 6.7.1.2 Regulatory Acceptance Criteria 6.7.1.3 Leakage Rate Requirements

6.7.2 System Description

6.7.2.1 General Description 6.7.2.1.1 Primary Pathway 6.7.2.1.2 Alternate Pathways SSES-FSAR NIMS Rev. 61 CHAPTER 6 TEXT Section Title FSAR Rev. 65 6-x 6.7.2.2 System Operation 6.7.2.3 Equipment Required

6.7.3 System Evaluation

6.7.3.1 Functional Protection Features 6.7.3.2 Effects of Single Active Failures 6.7.3.3 Effects of Seismic Induced Failures 6.7.3.4 Isolation Provisions 6.7.3.5 Leakage Protection Evaluation 6.7.3.6 Failure Mode and Effects Analysis 6.7.3.7 Influence on Other Safety Features 6.7.3.8 Radiological Evaluation

6.7.4 Instrumentation Requirements

6.7.5 Inspection and Testing

APPENDIX 6A Subcompartment Differential Pressure Considerations

APPENDIX 6B Compartment Differential Pressure Analysis Description

6B.1 FLUD Calculational Procedure 6B.1.1 Equation of State 6B.1.2 Compartment Thermodynamic State 6B.1.3 Compartment Initial Conditions 6B.1.4 Air and Vapor Component Flow Rates 6B.2 Energy Transfer Mechanisms 6B.2.1 Blowdown Energy 6B.2.2 Enthalpy Flow 6B.2.3 Compartment Heat Loads 6B.2.4 Unit Coolers 6B.2.5 Energy Balance 6B.2.6 Blowout Panel Activation 6B.2.7 Energy and Mass Conversion 6B.2.8 Eulerian Integration 6B.3 Thermodynamic Properties of Steam, Water, and Air 6B.4 References

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xi 6.1-1a NSSS Supplied Engineered Safety Features Component Materials

6.1-1b Engineered Safety Features Materials

6.1-2 Containment Components-Coating Schedule

6.1-3 Inventory of Qualified and Unqualified Containment Coatings

6.2-1 Containment Design Parameters

6.2-2 Engineered Safety Systems Inputs and Assumptions for Containment Response Analyses

6.2-3 This Table Has Been Deleted

6.2-3a Initial Plant Conditions for DBA-LOCA Containment Response

6.2-4 This Table Has Been Deleted

6.2-4a Input and Assumptions for the Short-Term DBA-LOCA Analysis

6.2-5 This Table Has Been Deleted

6.2-5a Input and Assumptions for the Long-Term DBA-LOCA Analysis

6.2-6 This Table Has Been Deleted 6.2-6a Containment Performance for DBA-LOCA

6.2-7 This Table Has Been Deleted

6.2-8 This Table Has Been Deleted

6.2-9 RPV Break Flow Data For Recirculation Line Break (102% P / 100% F)

6.2-9a This Table Has Been Deleted

6.2-10 RPV Break Flow Data For Main Steam Line Break (102% P / 100% F)

6.2-11 Core Decay Heat Following LOCA for Containment Analysis SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xii 6.2-12 Containment Penetration Data

6.2-12a Data on Instrument Lines Penetrating Containment

6.2-13 Parameters Used for the Evaluation of Combustible Gases in the Containment After a LOCA (HISTORICAL)

6.2-14 Primary Containment Atmosphere Monitoring System (Hydrogen/Oxygen Analyzer) System Level, Failure Mode and Effect Analysis

6.2-15 Evaluation of Potential Secondary Containment Bypass Leakage Pathways

6.2-15a This Table Has Been Deleted

6.2-16 Containment Hydrogen Recombiner System, System Level, Failure Mode and Effect Analysis

6.2-17 Information for the SSES Secondary Containment

6.2-18 Hydrogen Recombiner Design Characteristics

6.2-19 Type A Test Data

6.2-20 This Table Has Been Deleted

6.2-21 System Venting and Draining for Primary Containment Integrated Leakage Rate Test

6.2-22 Leakage Rate Test List

6.2-23 Initial and Boundary Conditions for Inadvertent Spray Actuation Study

6.2-24 Initial and Boundary Conditions For Drywell- Wetwell Bypass Leakage Study

6.2-25 Blowdown Data and Bypass Leakage

6.2-26 Long-term Blowdown Data for a Recirculation Line Break (Case D)

6.2-27 This Table Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xiii 6.3-1 This Table Has Been Renumbered to 6.3-1A

6.3-1A This Table Has Been Deleted

6.3-1B This Table Has Been Deleted

6.3-1B-2 Event Times For Limiting Recirculation Line Break 1.0 Deg Pump Suction Single Failure LPCI Valve Top Peaked Axial Power Distribution 102% Power

4031 Mwt 80 Mlbs/Hr Flow

6.3-2 This Table Has Been Deleted

6.3-3 Summary of Results of LOCA Analysis

6.3-3A This Table Has Been Deleted

6.3-3B This Table Has Been Deleted

6.3-3C Recirculation Line Break Results Highest Pct Cases Atrium Tm -10

6.3-4 This Table Has Been Deleted

6.3-5 Single Failures And Available Systems For Susquehanna

6.3-6 This Table Has Been Deleted

6.3-7 This Table Has Been Deleted 6.3-8 HPCI System Design Pa rameters 6.3-9 Manual Valves in the ECCS

6.3-10 Safety-Related Valves in the Drywell Subject to Spray Impingement

6.4-1 Control Structure Isolation Damper Leakage Characteristics and Closure Times 6.5-1 Engineered Safety Feature Filter System Design Parameters

6.5-2 Engineered Safety Feature Filter Systems Compliance with Recommendations of Regulatory Guide 1.52 SSES-FSAR NIMS Rev. 61 CHAPTER 6 TABLES Number Title FSAR Rev. 65 6-xiv 6.5-3 Standby Gas Treatment System Failure Mode and Effect Analysis

6.5-4 Recirculation System Failure Mode and Effect Analysis

6.5-5 List of Materials Used in the Standby Gas Treatment System

6.5-6 List of Materials Used in the Emergency Outside Air Supply System

6.5-7 Zone Volumes and Their Estimated Recirculation Airflow Rates

6.7-1 Table Has Been Deleted

6A-1 Table Has Been Deleted

6A-1(a) Reactor Primary System Blowdown Flow Rates and Fluid Enthalpy-Recirculation Outlet Line Break

6A-1(b) Recirc. Outlet Line Break Blowdown Mass Flux Time History

6A-1(c) Reactor Primary System Blowdown Flow Rates and Fluid Enthalpy - Feedwater Line Break

6A-1(d) Feedwater Line Break Blowdown Mass Flux Time History

6A-2 Head Spray Line Break

6A-3 Susquehanna-Compartment Volumes Used in Reactor Vessel Shield Annulus Subcompartment Analysis

6A-4 Susquehanna-Flow Area and Coefficients Used in Reactor Vessel Shield Annulus Subcompartment Analysis

6A-5 Geometry Node Locations

6A-6 RPV Geometry Node Areas for Recirculation Outlet Line Break

6A-7 RPV Geometry Mode Areas for Feedwater Line Break

6A-8 Reactor Primary System Blowdown Flow Rates And Fluid Enthalpy - Recirculation Outlet Line Break

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xv 6.1-1 This Figure Has Been Deleted

6.2-1 Diagram of the Recirculation Line Break Location

6.2-2 Pressure Response for Recirculation Line Break

6.2-3 Temperature Response for Recirculation Line Break

6.2-4 Floor Differential Pressure For Recirculation Line Breaks

6.2-5 Vent Flow for Recirculation Line Break

6.2-6 This Figure Intentionally Left Blank

6.2-6-1 This Figure Has Been Deleted

6.2-6-2 This Figure Has Been Deleted

6.2-6-3 This Figure Has Been Deleted

6.2-7 Drywell Temperature Response - Long-Term

6.2-7-1 This Figure Has Been Deleted

6.2-7-2 This Figure Has Been Deleted

6.2-7-3 This Figure Has Been Deleted

6.2-8 Suppression Pool Temperature Response - Long-Term

6.2-8-1 This Figure Has Been Deleted

6.2-8-2 This Figure Has Been Deleted

6.2-8-3 This Figure Has Been Deleted

6.2-9 RHR Heat Removal Rate

6.2-9-1 This Figure Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xvi 6.2-9-2 This Figure Has Been Deleted

6.2-9-3 This Figure Has Been Deleted

6.2-10 This Figure Has Been Deleted

6.2-11 Pressure Response for Main Steamline Break

6.2-12 Temperature Response for Main Steamline Break

6.2-13 This Figure Intentionally Left Blank

6.2-14 This Figure Has Been Deleted

6.2-15 This Figure Has Been Deleted

6.2-16 Schematic of ECCS Loop

6.2-17 Allowable Leakage Capacity

6.2-18 Vessel Blowdown Rate for Recirculation Line Break

6.2-19 This Figure Deleted For Power Uprate

6.2-20 Vessel Blowdown Rate for Main Steamline Break

6.2-21 This Figure Has Been Deleted 6.2-22 This Figure Has Been Deleted

6.2-23 This Figure Intentionally Left Blank

6.2-24 Secondary Containment Boundary Outline - Unit 1 EL. 645'-0"

6.2-25 Secondary Containment Boundary Outline - Unit 1 EL. 670'-0"

6.2-26 Secondary Containment Boundary Outline - Unit 1 EL. 683'-0"

6.2-27 Secondary Containment Boundary Outline - Unit 1 EL. 719'-0"

6.2-28 Secondary Containment Boundary Outline - Unit 1 EL. 749'-1" SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xvii 6.2-29 Secondary Containment Boundary Outline - Unit 1 EL. 779'-1"

6.2-30 Secondary Containment Boundary Outline - Unit 1 EL. 818'-1"

6.2-31 Secondary Containment Boundary Outline - Unit 1 Section A-A

6.2-32 Secondary Containment Boundary Outline - Unit 1 Section B-B

6.2-33 Secondary Containment Boundary Outline - Unit 1 EL. 799'-1"

6.2-34 Secondary Containment Boundary Outline - Unit 2 EL. 645'-0"

6.2-35 Secondary Containment Boundary Outline - Unit 2 EL. 670'-0"

6.2-36 Secondary Containment Boundary Outline - Unit 2 EL. 683'-0"

6.2-37 Secondary Containment Boundary Outline - Unit 2 EL. 719'-0"

6.2-38 Secondary Containment Boundary Outline - Unit 2 EL. 749'-1"

6.2-39 Secondary Containment Boundary Outline - Unit 2 EL. 779'-1"

6.2-40 Secondary Containment Boundary Outline - Unit 2 EL. 818'-1"

6.2-41 Secondary Containment Boundary Outline - Unit 2 Section A-A

6.2-42 Secondary Containment Boundary Outline - Unit 2 Section B-B

6.2-43 Secondary Containment Boundary Outline - Unit 2 EL. 799'-1"

6.2-44 Containment Penetration Details

6.2-44A Containment Penetration Details

6.2-44B Containment Penetration Details

6.2-44C Containment Penetration Details

6.2-44D Containment Penetration Details

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xviii 6.2-44E Containment Penetration Details

6.2-44F Containment Penetration Details

6.2-44g Containment Penetration Details

6.2-44H Containment Penetration Details

6.2-44i Containment Penetration Details

6.2-44J Containment Penetration Details

6.2-44K Containment Penetration Details

6.2-44L Containment Penetration Details

6.2-44M Containment Penetration Details

6.2-45 This Figure Has Been Deleted

6.2-46 Energy Absorption Rate By the Coolant vs. Time After LOCA

6.2-47 Integrated Energy Absorbed By Coolant vs. Time After LOCA

6.2-48 Figure Deleted

6.2-49 Figure Deleted 6.2-50 Figure Deleted

6.2-51 Figure Deleted

6.2-52 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Zone I and Zone III Isolation

6.2-53 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Normal Plant Operation

6.2-54 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Zone III Isolation

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xix 6.2-55A This Figure Has Been Replaced by Dwg. M-157, Sh. 1

6.2.55B This Figure Has Been Replaced by Dwg. M-157, Sh. 2

6.2.55C This Figure Has Been Replaced by Dwg. M-157, Sh. 3

6.2-56 Drywell to Wetwell Downcomers

6.2-57 This Figure Has Been Deleted

6.2-57-1 Vacuum Breaker - DISC/ARM Assembly Unit 1

6.2-57-2 Vacuum Breaker - DISC/ARM Assembly Unit 2

6.2-57a-1 Containment Personnel Lock Door Penetrations

6.2-57a-2 Containment Personnel Lock Door Penetrations

6.2-57a-3 Containment Personnel Lock Penetrations

6.2-58 Deleted Renumbered To 6.2-58-1 & 6.2-58-2

6.2-58-1 Containment Personnel Lock Door Seals

6.2-58-2 Containment Personnel Lock Door Seals

6.2-59 Personnel Lock Inner Door Tie Downs 6.2-60 Secondary Containment Pressure Transient Post-LOCA

6.2-61 Model for Inadvertent Spray Actuation

6.2-62 Thermal Heat Removal Efficiency of Containment Atmosphere Spray

6.2-63 Drywell Pressure Response For Inadvertent Spray Actuation

6.2-64 Drywell Temperature Response For Inadvertent Spray Actuation

6.2-65 Differential Pressure Experienced Across the Diaphragm Slab During Inadvertent Actuation of the Drywell Spray

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xx 6.2-66A This Figure Has Been Intentionally Left Blank

6.2-66B RWCU Line Penetration

6.2-66C Suppression Pool Purification Line Penetration

6.2-66D This Figure Has Been Intentionally Left Blank

6.2-66E This Figure Has Been Intentionally Left Blank

6.2-66F Reactor Building Closed Cooling Water Line Penetration

6.2-66G Reactor Building Control Rod Drive Seismic Island

6.2-66H RBCCW Supply/Return lines at the Reactor Building to Turbine Building Interface

6.2-67 This Figure Has Been Replaced by Dwg. M-159, Sh. 1

6.2-68 This Figure Deleted For Power Uprate

6.2-69 This Figure Deleted For Power Uprate

6.2-70 Long-Term Energy Release Rate for a Recirculation Line Break

6.2-71 This Figure Has Been Deleted

6.2-72 TIP Guide Tube Isolation Control

6.3-1A This Figure Has Been Replaced by Dwg. M-155, Sh. 1

6.3-1B This Figure Has Been Replaced by Dwg. M-156, Sh. 1

6.3-2 This Figure Has Been Replaced by Dwg. M1-E41-4, Sh. 1

6.3-3 This Figure Has Been Deleted

6.3-3A High Pressure Coolant Injection Pump Speed Characteristics

6.3-4 This Figure Has Been Replaced by Dwg. M-152, Sh. 1

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxi 6.3-5 This Figure Has Been Replaced by Dwg. M1-E21-15, Sh. 1

6.3-6 This Figure Has Been Intentionally Left Blank

6.3-6A This Figure Has Been Intentionally Left Blank

6.3-7 thru These Figures Have Been Intentionally Left Blank

6.3-49

6.3-50 This Figure Has Been Deleted

6.3-51 This Figure Has Been Deleted

6.3-52 This Figure Has Been Deleted

6.3-53 This Figure Has Been Deleted

6.3-54 This Figure Has Been Deleted

6.3-55 This Figure Has Been Deleted

6.3-56 This Figure Has Been Deleted

6.3-57 This Figure Has Been Deleted

6.3-58 This Figure Has Been Deleted 6.3-59 This Figure Has Been Deleted

6.3-60 This Figure Has Been Deleted

6.3-61 This Figure Has Been Deleted

6.3-62 This Figure Has Been Deleted

6.3-63 This Figure Has Been Deleted

6.3-64 This Figure Has Been Deleted

6.3-65 This Figure Has Been Deleted SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxii 6.3-66 This Figure Has Been Deleted

6.3-67 This Figure Has Been Deleted

6.3-68 This Figure Has Been Deleted

6.3-69 This Figure Has Been Deleted

6.3-70 This Figure Has Been Deleted

6.3-71 This Figure Has Been Deleted

6.3-72 This Figure Has Been Deleted

6.3-73 This Figure Has Been Deleted

6.3-74 This Figure Has Been Deleted

6.3-75 This Figure Has Been Deleted

6.3-76 This Figure Has Been Deleted

6.3-77 Pump Characteristic Curves For HPCI Pumps

6.3-78 This Figure Has Been Deleted

6.3-79 This Figure Has Been Renumbered To 6.3-79A

6.3-79A This Figure Has Been Deleted

6.3-79B This Figure Has Been Deleted

6.3-79C Low Pressure Core Spray Flow vs. Head Used in LOCA Analysis (FANP Atrium -10 Fuel)

6.3-80 This Figure Has Been Renumbered To 6.3-80A

6.3-80A This Figure Has Been Deleted

6.3-80B This Figure Has Been Deleted SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxiii 6.3-80C RHR (LPCI) Flow vs. Head Characteristics Use in LOCA Analysis (FANP Atrium 10 fuel) 6.3-81 This Figure Has Been Deleted

6.3-82 This Figure Has Been Deleted

6.3-83 This Figure Has Been Deleted

6.3-84 This Figure Has Been Deleted

6.3-85 This Figure Has Been Deleted

6.3-86 This Figure Has Been Deleted

6.3-87 This Figure Has Been Deleted

6.3-88 This Figure Has Been Deleted

6.3-89 This Figure Has Been Deleted

6.3-90 This Figure Has Been Deleted

6.3-91 This Figure Has Been Deleted

6.3-92 This Figure Has Been Deleted 6.3-93 This Figure Has Been Deleted

6.3-94 This Figure Has Been Deleted

6.3-95 This Figure Has Been Deleted

6.3-96 This Figure Has Been Deleted

6.3-97 This Figure Has Been Deleted

6.3-98 This Figure Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxiv 6.3-99 This Figure Has Been Deleted

6.3-100 This Figure Has Been Deleted

6.3-101 This Figure Has Been Deleted

6.3-102 This Figure Has Been Deleted

6.3-103 This Figure Has Been Deleted

6.3-104 This Figure Has Been Deleted

6.3-105 This Figure Has Been Deleted

6.3-106 This Figure Has Been Deleted

6.3-107 This Figure Has Been Deleted

6.3-108 This Figure Has Been Deleted

6.3-109 This Figure Has Been Deleted

6.3-110 This Figure Has Been Deleted

6.3-111 This Figure Has Been Deleted

6.3-112 This Figure Has Been Deleted 6.3-113 This Figure Has Been Deleted

6.3-114 This Figure Has Been Deleted

6.3-115 This Figure Has Been Deleted

6.3-116 This Figure Has Been Deleted

6.3-117 This Figure Has Been Deleted

6.3-118 Characteristic Curves for Core Spray Pump

6.3-119 Characteristic Curves for LPCI Pump SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxv 6.3-120 Speed Characteristic Curves for HPCI Pumps - Unit 1

6.3-121 Speed Characteristic Curves for HPCI Pumps - Unit 2

6.3-122 This Figure Has Been Deleted

6.3-123 This Figure Has Been Deleted

6.3-124 This Figure Has Been Deleted

6.3-125 This Figure Has Been Deleted

6.3-126 This Figure Has Been Deleted

6.3-127 This Figure Has Been Deleted

6.3-128 This Figure Has Been Deleted

6.3-129 This Figure Has Been Deleted

6.3-130 This Figure Has Been Deleted

6.3-131 This Figure Has Been Deleted

6.3-132 This Figure Has Been Deleted

6.3-133 This Figure Has Been Deleted

6.3-134 This Figure Has Been Deleted

6.3-135 This Figure Has Been Deleted

6.3-136 This Figure Has Been Deleted

6.3-137 This Figure Has Been Deleted

6.3-138 This Figure Has Been Deleted

6.3-139 This Figure Has Been Deleted

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxvi 6.3-140 This Figure Has Been Deleted

6.3-141 This Figure Has Been Deleted

6.3-142 This Figure Has Been Deleted

6.3-143 This Figure Has Been Deleted

6.3-144 This Figure Has Been Deleted

6.3-145 This Figure Has Been Deleted

6.3-146 This Figure Has Been Deleted

6.3-147 This Figure Has Been Deleted

6.3-148 This Figure Has Been Deleted

6.3-149 This Figure Has Been Deleted

6.3-150 This Figure Has Been Deleted

6.3-151 This Figure Has Been Deleted

6.3-152 This Figure Has Been Deleted

6.3-153 This Figure Has Been Deleted 6.3-154 This Figure Has Been Deleted

6.3-155 This Figure Has Been Deleted

6.3-156 This Figure Has Been Deleted

6.3-157 This Figure Has Been Deleted

6.3-158 This Figure Has Been Deleted

6.3-159 This Figure Has Been Deleted

6.3-160 This Figure Has Been Deleted SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxvii 6.3-161 This Figure Has Been Deleted

6.3-162 This Figure Has Been Deleted

6.3-163 This Figure Has Been Deleted

6.3-164 This Figure Has Been Deleted

6.3-165 This Figure Has Been Deleted

6.3-166 This Figure Has Been Deleted

6.3-167 This Figure Has Been Deleted

6.3-168 This Figure Has Been Deleted

6.3-169 This Figure Has Been Deleted

6.3-170 This Figure Has Been Deleted

6.3-171 This Figure Has Been Deleted

6.3-172 thru 6.3-199 Not Used

6.3-200 Figure Deleted 6.3-201 Limiting TLO Recirculation Line Break Upper Plenum Pressure (Lower)

6.3-202 Limiting TLO Recirculation Line Break Total Break Flow Rate

6.3-203 Limiting TLO Recirculation Line Break Core Inlet Flow Rate

6.3-204 Limiting TLO Recirculation Line Break Core Inlet Flow Rate

6.3-205 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate 6.3-206 Limiting TLO Recirculation Line Break Ads Flow Rate

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxviii 6.3-207 Limiting TLO Recirculation Line Break HPCI Flow Rate

6.3-208 Limiting TLO Recirculation Line Break LPCS Flow Rate

6.3-209 Limiting TLO Recirculation Line Break Intact Loop LPCI Flow Rate

6.3-210 Limiting TLO Recirculation Line Break Broken Loop LPCI Flow Rate

6.3-211 Limiting TLO Recirculation Line Break Upper Downcomer Mixture Level

6.3-212 Limiting TLO Recirculation Line Break Lower Downcomer Mixture Level

6.3-213 Limiting TLO Recirculation Line Break Lower Downcomer Liquid Mass

6.3-214 Limiting TLO Recirculation Line Break Upper Plenum Liquid Mass

6.3-215 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass

6.3-216 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate

6.3-217 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate

6.3-218 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature At The Limiting Node 6.3-219 Limiting TLO Recirculation Line Break Hot Channel Quality At The Limiting Node 6.3-220 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coeff.

at The Limiting Node

6.3-221 Limiting TLO Recirculation Line Break Cladding Temperatures 6.4-1A Control Structure Elevation

6.4-1B Control Structure Envelope Plan - El. 697'-0" and 714'-0"

6.4-1C Control Structure Envelope Control Room Floor Plan EL. 729'-0" Technical Support Center EL. 741'-1"

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxix 6.4-1D Control Structure Envelope Plan EL. 753'-0" & 771'-0"

6.4-1E Control Structure Envelope Plan EL. 783'-0"

6.4-2 Control Room Location Intake and Exhaust Location

6.7-1 This Figure Has Been Deleted

6.7-2 This Figure Has Been Deleted

6.7-3-1 This Figure Has Been Deleted

6.7-3-2 This Figure Has Been Deleted

6.7-3-3 This Figure Has Been Deleted

6.7-3-4 This Figure Has Been Deleted

6.7-4 This Figure Has Been Deleted

6.7-5 This Figure Has Been Deleted

6A-1(a) Reactor Shield Annulus Arrangement

6A-1(b) RPV Shield Wall and Pedestal

6A-2 RPV Shield Annulus Subcompartment Model Schematic 6A-3a Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3b Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3c Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3d Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxx 6A-3e Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3f Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End

6A-3g Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3h Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3i Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3j Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3k Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3l Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End

6A-3m This Figure Has Been Deleted

6A-3n This Figure Has Been Deleted 6A-3o This Figure Has Been Deleted

6A-4 Drywell Head Arrangement

6A-5 Head Spray Line Break Geometry

6A-6 Pressure Response in the Drywell Head For a Head Spray Line Break

6A-7 Force Transient on Reactor Pressure Vessel Following A Recirculation Line Break at the Nozzle Safe End

6A-8 Force Transient on Reactor Shield Wall Following A Recirculation Line Break at the Nozzle Safe End SSES-FSAR NIMS Rev. 61 CHAPTER 6 FIGURES Number Title FSAR Rev. 65 6-xxxi 6A-9 Resultant Force Transient on RPV Following a Feedwater Line Break at the Nozzle

6A-10 Resultant Force Transient on RPV Following a Feedwater Line Break at the Nozzle

6B-1 Basic FLUD Calculation Flowchart SSES-FSAR Text Rev. 59

FSAR Rev. 65 7-i CHAPTER 7 INSTRUMENTATION AND CONTROLS TABLE OF CONTENTS TEXT Section Title

7.1 INTRODUCTION

7.1.1 Identification of Safety-Related Systems 7.1.1a Identification of Safety-Related Systems Provided with the NSSS

7.1.1a.1 General (NSSS) 7.1.1a.2 Identification of Individual Systems 7.1.1a.3 Classification (NSSS) 7.1.1a.3.1 Safety-Related Systems (NSSS) 7.1.1a.3.2 Power Generation (Non-Safety) Systems (NSSS) 7.1.1a.3.3 Design Basis (NSSS) 7.1.1a.3.4 Specific Regulatory Requirements (NSSS)

7.1.1b Identification of Safety-Related Systems not Provided with the NSSS (Non-NSSS) 7.1.1b.1 Engineered Safety Feature Systems (Non-NSSS) 7.1.1b.2 Engineered Safety Feature Auxiliary Support Systems (Non-NSSS) 7.1.1b.3 Systems Required for Safe Shutdown (Non-NSSS) 7.1.1b.4 Safety-Related Display Instrumentation (Non-NSSS) 7.1.1b.5 Other Systems Required for Safety (Non-NSSS) 7.1.1b.6 Non-NSSS Systems Similar to Plants Which Have an Operating License 7.1.2 Identification of Safety Criteria

7.1.2a.1 Identification of Safety Criteria for NSSS, General 7.1.2a.1.1 Reactor Protection System (RPS) - Instrumentation and Control 7.1.2a.1.1.1 Safety Design Bases 7.1.2a.1.1.1.1 General Functional Requirements 7.1.2a.1.1.1.2 Specific Regulatory Requirements 7.1.2a.1.1.2 Power Generation (Non-Safety) Design Bases 7.1.2a.1.2 Primary Containment and Reactor Vessel Isolation Control System (PCRVICS) - Instrumentation and Controls 7.1.2a.1.2.1 Safety Design Bases SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-ii 7.1.2a.1.2.1.1 General Functional Requirements 7.1.2a.1.2.2 Specific Regulatory Requirements 7.1.2a.1.3 Emergency Core Cooling Systems - Instrumentation and Controls 7.1.2a.1.3.1 Safety Design Bases 7.1.2a.1.3.1.1 General Functional Requirements 7.1.2a.1.3.1.2 Specific Regulatory Requirements 7.1.2a.1.4 Neutron Monitoring System - Instrumentation and Controls 7.1.2a.1.4.1 Source Range Monitor (SRM) Subsystem 7.1.2a.1.4.1.1 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.2 Intermediate Range Monitor (IRM) Subsystem 7.1.2a.1.4.2.1 Safety Design Basis 7.1.2a.1.4.2.2 Specific Regulatory Requirements 7.1.2a.1.4.2.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.3 Local Power Range Monitor (LPRM) Subsystem 7.1.2a.1.4.3.1 Safety Design Bases 7.1.2a.1.4.3.2 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.4 Average Power Range Monitor (APRM) Subsystem 7.1.2a.1.4.4.1 Safety Design Basis 7.1.2a.1.4.4.2 Specific Regulatory Requirements 7.1.2a.1.4.4.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.5 Traversing Incore Probe (TIP) Subsystem 7.1.2a.1.4.5.1 Power Generation Design Bases 7.1.2a.1.4.6 Rod Block Monitor (RBM) Subsystem 7.1.2a.1.4.6.1 Power Generation (Non-Safety) Design Bases 7.1.2a.1.4.7 Oscillation Power Range Monitor (OPRM) Subsystem 7.1.2a.1.4.7.1 Safety Design Basis 7.1.2a.1.4.7.2 Specific Regulatory Requirements 7.1.2a.1.4.7.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.5 Refueling Interlocks - Instrumentation and Controls 7.1.2a.1.6 Reactor Manual Control System - Instrumentation and Controls 7.1.2a.1.6.1 Specific Regulatory Requirements 7.1.2a.1.6.2 Power Generation (Non-Safety) Design Bases 7.1.2a.1.7 This Subsection is not used 7.1.2a.1.8 This Subsection is not used 7.1.2a.1.9 This Subsection is not used 7.1.2a.1.10 This Subsection is not used 7.1.2a.1.11 Process Radiation Monitoring System - Instrumentation and Controls 7.1.2a.1.11.1 Main Steamline Radiation Monitoring Subsystem 7.1.2a.1.11.1.1 Safety Design Basis 7.1.2a.1.11.1.2 Specific Regulatory Requirements SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-iii 7.1.2a.1.11.1.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.12 This Subsection is not used 7.1.2a.1.13 This Subsection is not used 7.1.2a.1.14 This Subsection is not used 7.1.2a.1.15 This Subsection is not used 7.1.2a.1.16 This Subsection is not used 7.1.2a.1.17 This Subsection is not used 7.1.2a.1.18 Reactor Core Is olation Cooling (RCIC) Syst em - Instrumentation and Controls 7.1.2a.1.18.1 Safety Design Bases 7.1.2a.1.18.2 Specific Regulatory Requirements 7.1.2a.1.19 Standby Liquid Control System (SLCS) - Instrumentation and Controls 7.1.2a.1.19.1 Safety Design Basis 7.1.2a.1.19.2 Specific Regulatory Requirements 7.1.2a.1.19.3 Power Generation (Non-Safety) Design Basis 7.1.2a.1.20 This Subsection is not used 7.1.2a.1.21 This Subsection is not used 7.1.2a.1.22 This Subsection is not used 7.1.2a.1.23 This Subsection is not used 7.1.2a.1.24 NSSS Leak Detection System - Instrumentation and Controls 7.1.2a.1.24.1 Reactor Coolant Pressure Boundary Leakage Detection 7.1.2a.1.24.1.1 Safety Design Bases 7.1.2a.1.24.1.2 Specific Regulatory Requirements 7.1.2a.1.24.1.3 Power Generation (Non-Safety) Design Basis 7.1.2a.1.25 RHRS - Reactor Shutdown Cooling Subsystem - Instrumentation and Controls 7.1.2a.1.25.1 Safety Design Bases 7.1.2a.1.25.2 Specific Regulatory Requirements 7.1.2a.1.25.3 Power Generation (Non-Safety) Design Bases 7.1.2a.1.26 This subsection is not used 7.1.2a.1.27 This subsection is not used 7.1.2a.1.28 This subsection is not used 7.1.2a.1.29 This subsection is not used 7.1.2a.1.30 ATWS Mitigation Capability - Instrumentation and Controls 7.1.2a.1.30.1 Special Event Design Basis 7.1.2a.1.30.2 Specific Regulatory Requirements

7.1.2a.1.31 Safety-Related Display - Instrumentation 7.1.2a.1.31.1 Safety Design Basis 7.1.2a.1.31.2 Specific Regulatory Requirements 7.1.2a.1.31.3 Power Generation (Non-Safety) Design Basis SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-iv 7.1.2a.1.32 This Subsection is not used 7.1.2a.1.33 This Subsection is not used 7.1.2a.1.34 This Subsection is not used 7.1.2a.1.35 RHRS - Containment Spray Cooling System - Instrumentation and Controls 7.1.2a.1.35.1 Safety Design Basis 7.1.2a.1.35.2 Specific Regulatory Requirements 7.1.2a.1.35.3 Power Generation Design Basis 7.1.2a.1.36 This subsection is not used 7.1.2a.1.37 Recirculation Pump Trip (RPT) - Instrumentation and Controls 7.1.2a.1.37.1 Safety Design Bases 7.1.2a.1.37.2 Specific Regulatory Requirements 7.1.2a.1.37.3 Power Generation (Non-Safety) Bases 7.1.2a.1.38 RHRS - Suppression Pool Cooling System - Instrumentation and Controls 7.1.2a.1.38.1 Safety Design Bases 7.1.2a.1.38.2 Specific Regulatory Requirements 7.1.2a.1.38.3 Power Generation (Non-Safety) Design Basis 7.1.2b.1 Identification of Safety Criteria for Non-NSSS, General 7.1.2a.2 Mechanical Systems Separation Criteria 7.1.2a.2.1 General 7.1.2a.2.1.1 Separation Techniques 7.1.2a.2.2 System Separation Criteria 7.1.2a.2.3 Physical Separation 7.1.2a.3 Electrical System Separation Criteria 7.1.2a.3.1 General 7.1.2a.3.1.1 Separation Techniques 7.1.2a.3.2 Identification 7.1.2a.3.3 System Separation Requirements 7.1.2a.3.3.1 Reactor Protection System (RPS) 7.1.2a.3.3.2 Emergency Core Cooling System (ECCS) and Nuclear Steam Supply Shutoff System (NSSSS) 7.1.2a.3.3.3 Steam Leakage Zone 7.1.2a.3.3.4 Su ppression P ool Level Swell Zone 7.1.2a.3.3.5 Penetrations 7.1.2a.3.3.6 Power Generation Control Complex (PGCC) 7.1.2a.3.3.7 Annunciator and Computer 7.1.2a.3.3.8 Conformance to IEEE 384-1974, 1981 7.1.2a.4 NSSS Instrument Errors 7.1.2b.4 Non-NSSS Instrument Errors 7.1.2.5 Conformance to Industry Standards SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-v 7.1.2.5.1 Conformance to IEEE 279-1971 7.1.2.5.2 Conformance to IEEE 308-1974 7.1.2.5.2.1 Conformance to IEEE 308-1980 7.1.2.5.3 Conformance to IEEE 323-1971 7.1.2.5.3.1 Conformance to IEEE 323-1974 7.1.2.5.4 Conformance to IEEE 336-1971 7.1.2.5.4.1 Conformance to IEEE 336-1980 7.1.2.5.5 Conformance to IEEE 338-1971 7.1.2.5.5.1 Conformance to IEEE 338-1977 7.1.2.5.6 Conformance to IEEE 344-1971 7.1.2.5.6.1 Conformance to IEEE 344-1975 7.1.2.5.7 Conformance to IEEE 379-1972 7.1.2.5.7.1 Conformance to IEEE 379-1977 7.1.2.5.8 Conformance to IEEE 384-1974 7.1.2.5.8.1 Conformance to IEEE 384-1981 7.1.2.6 Conformance to Regulatory Guides 7.1.2.6.1 Conformance to Regulatory Guide 1.6 (3/10/71) 7.1.2.6.2 Conformance to Regulatory Guide 1.9 (5/10/71) 7.1.2.6.2.1 Conformance to Regulatory Guide 1.9 (December 1, 1979) 7.1.2.6.3 Conformance to Regulatory Guide 1.11 (3/10/71) 7.1.2.6.4 Conformance to Regulatory Guide 1.22 (2/17/72) 7.1.2.6.5 Conformance to Regulatory Guide 1.29 (6/7/72) 7.1.2.6.5.1 Conformance to Regulatory Guide 1.29 (9/78) 7.1.2.6.6 Conformance to Regulatory Guide 1.30 (8/11/72) 7.1.2.6.7 Conformance to Regulatory Guide 1.32 (8/72) 7.1.2.6.7.1 Conformance to Regulatory Guide 1.32 (2/77) 7.1.2.6.8 Conformance to Regulatory Guide 1.40 (3/16/73) 7.1.2.6.9 Conformance to Regulatory Guide 1.45 (5/73) 7.1.2.6.10 Conformance to Regulatory Guide 1.47 (5/73) 7.1.2.6.11 Conformance to Regulatory Guide 1.53 (6/73) 7.1.2.6.12 Conformance to Regulatory Guide 1.62 (10/73) 7.1.2.6.13 Conformance to Regulatory Guide 1.63 (10/73) 7.1.2.6.14 Conformance to Regulatory Guide 1.68 (11/73) 7.1.2.6.15 Conformance to Regulatory Guide 1.70 (Rev. 2) 7.1.2.6.16 Conformance to Regulatory Guide 1.73 (1/74) 7.1.2.6.17 Conformance to Regulatory Guide 1.75 (1/75) 7.1.2.6.17.1 Conformance to Regulatory Guide 1.75 (9/78) 7.1.2.6.18 Conformance to Regulatory Guide 1.80 (6/74) 7.1.2.6.19 Conformance to Regulatory Guide 1.89 (11/74) 7.1.2.6.20 Conformance to Regulatory Guide 1.96 (6/76) - Rev. 1 7.1.2.6.21 Conformance to Regulatory Guide 1.97 SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-vi 7.1.2.7 Technical Design Bases 7.1.2.8 Safety System Settings

7.2 REACTOR TRIP SYSTEM - (REACTOR PROTECTION SYSTEM) - INSTRUMENTATION AND CONTROLS

7.2.1 Description

7.2.1.1 System Description 7.2.1.1.1 Identification 7.2.1.1.2 Classification 7.2.1.1.3 Power Sources 7.2.1.1.4 Equipment Design 7.2.1.1.4.1 General 7.2.1.1.4.2 Initiating Circuits 7.2.1.1.4.3 Logic 7.2.1.1.4.4 Scram Operating Bypasses 7.2.1.1.4.4.1 Neutron Monitoring System 7.2.1.1.4.4.2 Turbine Stop Valve and Turbine Control Valve Fast Closure 7.2.1.1.4.4.3 Main Steamline Isolation Valves 7.2.1.1.4.4.4 Scram Discharge Volume Level 7.2.1.1.4.4.5 Mode Switch in Shutdown 7.2.1.1.4.4.6 Maintenance, Calibration or Test Bypasses 7.2.1.1.4.4.7 Interlocks 7.2.1.1.4.4.8 RPS Shorting Links (Neutron Monitoring System) 7.2.1.1.4.5 Redundancy and Diversity 7.2.1.1.4.6 Actuated Devices 7.2.1.1.4.7 Separation 7.2.1.1.4.8 Testability 7.2.1.1.5 Environmental Considerations 7.2.1.1.6 Operational Considerations 7.2.1.1.6.1 Reactor Operator Information 7.2.1.1.6.1.1 Indicators 7.2.1.1.6.1.2 Annunciators 7.2.1.1.6.1.3 Computer Alarms 7.2.1.1.6.2 Reactor Operator Controls 7.2.1.1.6.2.1 Mode Switch 7.2.1.1.6.2.2 Safety-Related Portions of Control Systems Which Inhibit or Limit the Response of the Reactivity Control System 7.2.1.1.6.3 Setpoints 7.2.1.1.7 Containment Electrical Penetration Assignment SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-vii 7.2.1.1.8 Cable Spreading Room Description 7.2.1.1.9 Control and Relay Rooms 7.2.1.1.10 Control Boards and Their Contents 7.2.1.1.11 Test Methods that Insure RPS Reliability 7.2.1.1.12 Interlock Circuits to Inhibit Rod Motion as Well as Vary the Protective Function 7.2.1.1.13 ATWS Provisions 7.2.1.2 Design Bases 7.2.1.2.1 Conditions 7.2.1.2.2 Variables 7.2.1.2.3 Sensors 7.2.1.2.4 Operational Limits 7.2.1.2.5 Margin Between Operational Limits 7.2.1.2.6 Levels Requiring Protective Action 7.2.1.2.7 Ranges of Energy Supply and Environmental Conditions 7.2.1.2.8 Unusual Events 7.2.1.2.9 Performance Requirements 7.2.1.3 Final System Drawings

7.2.2 Analysis

7.2.2.1 Reactor Protection System - Instrumentation and Controls 7.2.2.1.1 General Functional Requirements Conformance 7.2.2.1.1.1 Conformance to Design Basis Requirements 7.2.2.1.1.1.1 Design Bases 7.1.2a.1.1.1.1(1) 7.2.2.1.1.1.2 Design Bases 7.1.2a.1.1.1.1(2) 7.2.2.1.1.1.3 Design Bases 7.1.2a.1.1.1.1(3) 7.2.2.1.1.1.4 Design Bases 7.1.2a.1.1.1.1(4) 7.2.2.1.1.1.5 Design Bases 7.1.2a.1.1.1.1(5) 7.2.2.1.1.1.6 Design Bases 7.1.2a.1.1.1.1(6) 7.2.2.1.1.1.7 Design Bases 7.1.2a.1.1.1.1(7a through 7h) 7.2.2.1.1.1.8 Design Bases 7.1.2a.1.1.1.1(8) 7.2.2.1.1.1.9 Other Design Basis Requirements 7.2.2.1.2 Conformance to Specific Regulatory Requirements 7.2.2.1.2.1 Conformance to NRC Regulatory Guides 7.2.2.1.2.1.1 Regulatory Guide 1.11 (1971) 7.2.2.1.2.1.2 Regulatory Guide 1.22 (2/72) 7.2.2.1.2.1.3 Regulatory Guide 1.29 (1972) 7.2.2.1.2.1.4 Regulatory Guide 1.30 (1972) 7.2.2.1.2.1.5 Regulatory Guide 1.47 (5/73) 7.2.2.1.2.1.6 Regulatory Guide 1.53 (6/73)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-viii 7.2.2.1.2.1.7 Regulatory Guide 1.62 (10/73) 7.2.2.1.2.1.8 Regulatory Guide 1.63 (10/73) 7.2.2.1.2.1.9 Regulatory Guide 1.68 (11/73) 7.2.2.1.2.1.10 Regulatory Guide 1.75 (1/75) 7.2.2.1.2.1.11 Regulatory Guide 1.89 (11/74) 7.2.2.1.2.2 Conformance to 10CFR50, Appendix A - General Design Criteria 7.2.2.1.2.2.1 General Design Criterion 1 7.2.2.1.2.2.2 General Design Criterion 2 7.2.2.1.2.2.3 General Design Criterion 3 7.2.2.1.2.2.4 General Design Criterion 4 7.2.2.1.2.2.5 General Design Criterion 5 7.2.2.1.2.2.6 General Design Criterion 10 7.2.2.1.2.2.7 General Design Criterion 12 7.2.2.1.2.2.8 General Design Criterion 13 7.2.2.1.2.2.9 General Design Criterion 15 7.2.2.1.2.2.10 General Design Criterion 19 7.2.2.1.2.2.11 General Design Criterion 20 7.2.2.1.2.2.12 General Design Criterion 21 7.2.2.1.2.2.13 General Design Criterion 22 7.2.2.1.2.2.14 General Design Criterion 23 7.2.2.1.2.2.15 General Design Criterion 24 7.2.2.1.2.2.16 General Design Criterion 25 7.2.2.1.2.2.17 General Design Criterion 29 7.2.2.1.2.3 Conformance with Industry Codes and Standards 7.2.2.1.2.3.1 IEEE 279 (1971) 7.2.2.1.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.2.2.1.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.2.2.1.2.3.1.3 Quality of Components and Modules (IEEE 279-1971, Paragraph 4.3) 7.2.2.1.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.2.2.1.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.2.2.1.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.2.2.1.2.3.1.7 Control and Protection System Interaction (IEEE 279-1971, Paragraph 4.7) 7.2.2.1.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.2.2.1.2.3.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.2.2.1.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.2.2.1.2.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.2.2.1.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-ix 7.2.2.1.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.2.2.1.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.2.2.1.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.2.2.1.2.3.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, Paragraph 4.16) 7.2.2.1.2.3.1.17 Manual Actuation (IEEE 279-1971, Paragraph 4.17) 7.2.2.1.2.3.1.18 Access to Setpoint Adjustments, Calibration, and Test Points (IEEE 279-1971, Paragraph 4.18) 7.2.2.1.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.2.2.1.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.2.2.1.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.2.2.1.2.3.1.22 Identification of Protection Systems (IEEE 279-1971, Pa ragraph 4.22) 7.2.2.1.2.3.2 IEEE 308 - 1974 7.2.2.1.2.3.3 IEEE 317 - 1972

7.2.2.1.2.3.4 This subsection intentionally left blank. 7.2.2.1.2.3.5 IEEE 336 - 1971 7.2.2.1.2.3.6 IEEE 338 - 1971 7.2.2.1.2.3.7 IEEE 344 - 1971 7.2.2.1.2.3.8 IEEE 379 - 1972 7.2.2.1.2.3.9 IEEE 384 - 1974 7.2.2.1.2.4 Conformance to NRC Branch Technical Positions 7.2.2.1.2.4.1 Branch Technical Position EICSB 10 7.2.2.1.2.4.2 Branch Technical Position EICSB 21 7.2.2.1.2.4.3 Branch Technical Position EICSB 22 7.2.2.1.2.4.4 Branch Technical Position EICSB 26 7.2.2.1.3 Additional Design Considerations Analyses 7.2.2.1.3.1 Spurious Rod Withdrawals 7.2.2.1.3.2 Loss of Plant Instrument Air System 7.2.2.1.3.3 Loss-of-Cooling Water to Vital Equipment 7.2.2.1.3.4 Plant Load Rejection 7.2.2.1.3.5 Turbine Trip

7.2.3 Alternate Rod Injection System

7.2.3.1 System Description 7.2.3.1.1 Identification 7.2.3.1.2 Classification 7.2.3.1.3 Power Sources 7.2.3.1.4 Equipment Design 7.2.3.1.4.1 General SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-x 7.2.3.1.4.2 Initiating Circuits 7.2.3.1.4.2.1 Input Parameter Selection 7.2.3.1.4.2.2 Reactor Steam Dome Pressure-High 7.2.3.1.4.2.3 Reactor Vessel Water Level-Low 7.2.3.1.4.2.4 Manual Trip 7.2.3.1.4.3 Logic 7.2.3.1.4.4 ARI Operating and Maintenance Bypasses 7.2.3.1.4.5 Redundancy and Diversity 7.2.3.1.4.6 Actuated Devices 7.2.3.1.4.7 Separation 7.2.3.1.4.8 Testability 7.2.3.1.5 Environmental Considerations 7.2.3.1.6 Operational Considerations 7.2.3.1.6.1 Reactor Operator Information 7.2.3.1.6.1.1 Indicators 7.2.3.1.6.1.2 Annunciators 7.2.3.1.6.1.3 Computer Alarms 7.2.3.1.6.1.3.1 Process Computer System 7.2.3.1.6.1.3.2 Transient Monitoring System 7.2.3.1.6.2 Reactor Operator Controls 7.2.3.1.6.3 Setpoints 7.2.3.1.7 Control Panels 7.2.3.1.8 Test Methods to Ensure ARI Reliability 7.2.3.2 Design Bases 7.2.3.2.1 Operating Conditions 7.2.3.2.2 Variables 7.2.3.2.3 Sensors 7.2.3.2.4 Operational Limits 7.2.3.2.5 Levels Requiring Protection Action 7.2.3.2.6 Ranges of Energy Supply and Environmental Conditions 7.2.3.2.7 Unusual Events 7.2.3.2.8 Performance Requirements 7.2.3.3 Final System Drawings

7.2.4 ARI Analysis

7.2.4.1 ARI General Functional Requirements Conformance 7.2.4.1.1 Conformance to Design Bases Requirements 7.2.4.1.1.1 Design Bases 7.1.2a.1.30 7.2.4.1.1.2 Conformance to Specific Regulatory Requirements 7.2.4.1.1.2.1 Conformance to 10CFR50.62(C)(3)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xi 7.2.4.1.1.2.2 Conformance to NRC Regulatory Guides 7.2.4.1.1.2.2.1 Regulatory Guide 1.22 (February 17, 1972) 7.2.4.1.1.2.2.2 Regulatory Guide 1.30 (August 11, 1972) 7.2.4.1.1.2.2.3 Regulatory Guide 1.53 (June, 1973) 7.2.4.1.1.2.2.4 Regulatory Guide 1.62 (October, 1973) 7.2.4.1.1.2.2.5 Regulatory Guide 1.70 (September, 1975) 7.2.4.1.1.2.2.6 Regulatory Guide 1.75 (January, 1975) 7.2.4.1.1.2.3 Conformance to 10CFR50 Appendix A General Design Criteria 7.2.4.1.1.2.3.1 General Design Criterion 1 7.2.4.1.1.2.3.2 General Design Criterion 2 7.2.4.1.1.2.3.3 General Design Criterion 3 7.2.4.1.1.2.3.4 General Design Criterion 4 7.2.4.1.1.2.3.5 General Design Criterion 13 7.2.4.1.1.2.3.6 General Design Criterion 19 7.2.4.1.1.2.3.7 General Design Criterion 20 7.2.4.1.1.2.3.8 General Design Criterion 21 7.2.4.1.1.2.3.9 General Design Criterion 22 7.2.4.1.1.2.3.10 General Design Criterion 23 7.2.4.1.1.2.3.11 General Design Criterion 24 7.2.4.1.1.2.3.12 General Design Criterion 29 7.2.4.1.1.2.4 Conformance to Industry Standards 7.2.4.1.1.2.4.1 IEEE 279-1971 7.2.4.1.1.2.4.1.1 General Functional Requirements (IEEE 279-1971, Paragraph 4.1) 7.2.4.1.1.2.4.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.2.4.1.1.2.4.1.3 Quality of Components (IEEE 279-1971, Paragraph 4.3) 7.2.4.1.1.2.4.1.4 Equipment Qualific ation (IEEE 279-1971, Paragraph 4.4) 7.2.4.1.1.2.4.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.2.4.1.1.2.4.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.2.4.1.1.2.4.1.7 Control and Protection System Interaction (IEEE 279-1971, Paragraph 4.7) 7.2.4.1.1.2.4.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.2.4.1.1.2.4.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.2.4.1.1.2.4.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.2.4.1.1.2.4.1.11 Channel Bypasses for Removal from (IEEE 279-1971, Paragraph 4.11) 7.2.4.1.1.2.4.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.2.4.1.1.2.4.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.2.4.1.1.2.4.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.2.4.1.1.2.4.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.2.4.1.1.2.4.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xii Paragraph 4.16) 7.2.4.1.1.2.4.1.17 Manual Initiation (IEEE 279-1971, Paragraph 4.17) 7.2.4.1.1.2.4.1.18 Access to Setpoint Adjustments, Calibration, and Test Points (IEEE 279-1971, Paragraph 4.18) 7.2.4.1.1.2.4.1.19 Identification of Protective Actions 7.2.4.1.1.2.4.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.2.4.1.1.2.4.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.2.4.1.1.2.4.1.22 Identification of Protection Systems (IEEE 279-1971, Paragraph 4.22) 7.2.4.1.1.2.4.2 IEEE 336-1971 7.2.4.1.1.2.4.3 IEEE 338-1971 7.2.4.1.1.2.4.4 IEEE 344-1975 7.2.4.1.1.2.4.5 IEEE 384-1981 7.2.4.1.1.2.5 Branch Technical Positions 7.2.4.1.1.2.5.1 EICSB-10 7.2.4.1.1.2.5.2 EICSB-21 7.2.4.1.1.2.5.3 EICSB-22 7.2.4.1.1.2.5.4 EICSB-24

7.3 ENGINEERED SAFETY FEATURE SYSTEMS

7.3.1 Description

7.3.1.1a System Description (NSSS) 7.3.1.1a.1 Emergency Core Cooling Systems (ECCS) Instrumentation and Control 7.3.1.1a.1.1 Network Identification 7.3.1.1a.1.2 Network Power Sources 7.3.1.1a.1.3 High Pressure Coolant Injection (HPCI) System - Instrumentation and Controls 7.3.1.1a.1.3.1 System Identification 7.3.1.1a.1.3.2 Equipment Design 7.3.1.1a.1.3.3 Initiating Circuits 7.3.1.1a.1.3.4 Logic and Sequencing

7.3.1.1a.1.3.5 Bypasses and Interlocks 7.3.1.1a.1.3.6 Redundancy and Diversity 7.3.1.la.1.3.7 Actuated Devices 7.3.1.1a.1.3.8 Separation 7.3.1.1a.1.3.9 Testability 7.3.1.1a.1.3.10 Environmental Considerations 7.3.1.1a.1.3.11 Operational Considerations SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xiii 7.3.1.1a.1.3.11.1 General Information 7.3.1.1a.1.3.11.2 Reactor Operator Information 7.3.1.1a.1.3.11.3 Setpoints 7.3.1.1a.1.4 Automatic Depressurization System (ADS) - Instrumentation and Controls 7.3.1.1a.1.4.1 System Identification 7.3.1.1a.1.4.2 Equipment Design 7.3.1.1a.1.4.3 Initiating Circuits 7.3.1.1a.1.4.4 Logic and Sequencing

7.3.1.1a.1.4.5 Bypasses and Interlocks 7.3.1.1a.1.4.6 Redundancy and Diversity 7.3.1.1a.1.4.7 Actuated Devices 7.3.1.1a.1.4.8 Separation 7.3.1.1a.1.4.9 Testability 7.3.1.1a.1.4.10 Environmental Considerations 7.3.1.1a.1.4.11 Operational Considerations 7.3.1.1a.1.4.11.1 General Information 7.3.1.1a.1.4.11.2 Reactor Operator Information 7.3.1.1a.1.4.11.3 Setpoints 7.3.1.1a.1.5 Core Spray (CS) System - Instrumentation and Controls 7.3.1.1a.1.5.1 System Identification 7.3.1.1a.1.5.2 Equipment Design 7.3.1.1a.1.5.3 Initiating Circuits 7.3.1.1a.1.5.4 Logic and Sequencing

7.3.1.1a.1.5.5 Bypasses and Interlocks 7.3.1.1a.1.5.6 Redundancy and Diversity 7.3.1.1a.1.5.7 Actuated Devices 7.3.1.1a.1.5.8 Separation 7.3.1.1a.1.5.9 Testability 7.3.1.1a.1.5.10 Environmental Considerations 7.3.1.1a.1.5.11 Operational Considerations 7.3.1.1a.1.5.11.1 General Information 7.3.1.1a.1.5.11.2 Reactor Operator Information 7.3.1.1a.1.5.11.3 Setpoints 7.3.1.1a.1.6 Low Pressure Coolant Injection (LPCI) System - Instrumentation and Controls 7.3.1.1a.1.6.1 System Identification 7.3.1.1a.1.6.2 Equipment Design 7.3.1.1a.1.6.3 Initiating Circuits 7.3.1.1a.1.6.4 Logic and Sequencing

7.3.1.1a.1.6.5 Bypasses and Interlocks SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xiv 7.3.1.1a.1.6.6 Redundancy and Diversity 7.3.1.1a.1.6.7 Actuated Devices 7.3.1.1a.1.6.8 Separation 7.3.1.1a.1.6.9 Testability 7.3.1.1a.1.6.10 Environmental Considerations 7.3.1.1a.1.6.11 Operational Considerations 7.3.1.1a.1.6.11.1 General Information 7.3.1.1a.1.6.11.2 Reactor Operator Information 7.3.1.1a.1.6.11.3 Setpoints 7.3.1.1a.2 Primary Containment and Reactor Vessel Isolation Control System - for NSSS Instrumentation and Controls 7.3.1.1a.2.1 System Identification 7.3.1.1a.2.2 System Power Sources 7.3.1.1a.2.3 System Equipment Design 7.3.1.1a.2.4 System Initiating Circuits 7.3.1.1a.2.4.1 Isolation Functions and Settings 7.3.1.1a.2.4.1.1 Reactor Vessel Low Water Level 7.3.1.1a.2.4.1.1.1 Subsystem Identification 7.3.1.1a.2.4.1.1.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.1.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.1.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.1.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.1.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.1.7 Subsystem Testability 7.3.1.1a.2.4.1.2 Main Steamline High Radiation 7.3.1.1a.2.4.1.2.1 Subsystem Identification 7.3.1.1a.2.4.1.2.2 Subsystem Power Sources 7.3.1.1a.2.4.1.2.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.2.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.2.5 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.2.6 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.2.7 Testability 7.3.1.1a.2.4.1.2.8 Environmental Considerations 7.3.1.1a.2.4.1.2.9 Operational Considerations 7.3.1.1a.2.4.1.3 Main Steamline Tunnel High Temperature and Differential Temperature 7.3.1.1a.2.4.1.3.1 Subsystem Identification 7.3.1.1a.2.4.1.3.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.3.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.3.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.3.5 Subsystem Redundancy and Diversity SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xv 7.3.1.1a.2.4.1.3.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.3.7 Subsystem Testability 7.3.1.1a.2.4.1.4 Main Steamline High Flow 7.3.1.1a.2.4.1.4.1 Subsystem Identification 7.3.1.1a.2.4.1.4.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.4.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.4.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.4.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.4.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.4.7 Subsystem Testability 7.3.1.1a.2.4.1.5 Main Turbine Inlet - Low Steam Pressure 7.3.1.1a.2.4.1.5.1 Subsystem Identification 7.3.1.1a.2.4.1.5.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.5.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.5.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.5.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.5.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.5.7 Subsystem Testability 7.3.1.1a.2.4.1.6 Containment Drywell-High Pressure 7.3.1.1a.2.4.1.6.1 Subsystem Identification 7.3.1.1a.2.4.1.6.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.6.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.6.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.6.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.6.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.6.7 Subsystem Testability 7.3.1.1a.2.4.1.7 This Subsection is not used 7.3.1.1a.2.4.1.8 This Subsection is not used 7.3.1.1a.2.4.1.9 Reactor Water Cleanup (RWCU) System - High Differential Flow and High Flow 7.3.1.1a.2.4.1.9.1 Subsystem Identification 7.3.1.1a.2.4.1.9.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.9.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.9.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.9.5 Subsystem Redundancy and Diversity 7.3.1.1a.2.4.1.9.6 Subsystem Bypasses and Interlocks 7.3.1.1a.2.4.1.9.7 Subsystem Testability 7.3.1.1a.2.4.1.10 Reactor Water Cleanup (RWCU) System-Area High Temperature and Differential Temperature 7.3.1.1a.2.4.1.10.1 Subsystem Identification 7.3.1.1a.2.4.1.10.2 Power Supplies SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xvi 7.3.1.1a.2.4.1.10.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.10.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.10.5 Subsystem Redundancy and Diversity

7.3.1.1a.2.4.1.10.6 Subsystem By passes and Interlocks 7.3.1.1a.2.4.1.10.7 Subsystem Testability 7.3.1.1a.2.4.1.11 This subsection has been deleted 7.3.1.1a.2.4.1.12 Main Steamline-Leak Detection 7.3.1.1a.2.4.1.12.1 Subsystem Identification 7.3.1.1a.2.4.1.13 Main Condenser Vacuum Trip 7.3.1.1a.2.4.1.13.1 Subsystem Identification 7.3.1.1a.2.4.1.13.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.13.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.13.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.13.5 Subsystem Redundancy and Diversity

7.3.1.1a.2.4.1.13.6 Subsystem By passes and Interlocks 7.3.1.1a.2.4.1.13.7 Subsystem Testability

7.3.1.1a.2.4.1.14 RHR System High Flow 7.3.1.1a.2.4.1.14.1 Subsystem Identification 7.3.1.1a.2.4.1.14.2 Subsystem Power Supplies 7.3.1.1a.2.4.1.14.3 Subsystem Initiating Circuits 7.3.1.1a.2.4.1.14.4 Subsystem Logic and Sequencing 7.3.1.1a.2.4.1.14.5 Subsystem Redundancy and Diversity

7.3.1.1a.2.4.1.14.6 Subsystem By passes and Interlocks 7.3.1.1a.2.4.1.14.7 Subsystem Testability 7.3.1.1a.2.4.2 System Instrumentation 7.3.1.1a.2.5 System Logic 7.3.1.1a.2.6 System Sequencing 7.3.1.1a.2.7 System Bypasses and Interlocks 7.3.1.1a.2.8 System Redundancy and Diversity 7.3.1.1a.2.9 System Actuated Devices 7.3.1.1a.2.10 System Separation 7.3.1.1a.2.11 System Testability 7.3.1.1a.2.12 System Environmental Considerations 7.3.1.1a.2.13 System Operational Considerations 7.3.1.1a.2.13.1 General Information 7.3.1.1a.2.13.2 Reactor Operator Information

7.3.1.1a.2.13.3 Setpoints 7.3.1.1a.3 This Subsection is Not Used 7.3.1.1a.4 RHRS/Containment Spray Cooling System - Instrumentation and Controls 7.3.1.1a.4.1 System Identification SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xvii 7.3.1.1a.4.2 Power Sources 7.3.1.1a.4.3 Equipment Design 7.3.1.1a.4.4 Initiating Circuits 7.3.1.1a.4.5 Logic and Sequencing

7.3.1.1a.4.6 Bypasses and Interlocks 7.3.1.1a.4.7 Redundancy and Diversity 7.3.1.1a.4.8 Actuated Devices 7.3.1.1a.4.9 Separation 7.3.1.1a.4.10 Testability 7.3.1.1a.4.11 Environmental Considerations 7.3.1.1a.4.12 Operational Considerations 7.3.1.1a.4.12.1 General Information 7.3.1.1a.4.12.2 Reactor Operator Information

7.3.1.1a.4.12.3 Setpoints 7.3.1.1a.5 RHRS/Suppression Pool Cooling Mode - Instrumentation and Controls 7.3.1.1a.5.1 System Identification 7.3.1.1a.5.2 Power Sources 7.3.1.1a.5.3 Equipment Design 7.3.1.1a.5.4 Initiating Circuits 7.3.1.1a.5.5 Logic and Sequencing

7.3.1.1a.5.6 Bypasses and Interlocks 7.3.1.1a.5.7 Redundancy and Diversity 7.3.1.1a.5.8 Actuated Devices 7.3.1.1a.5.9 Separation 7.3.1.1a.5.10 Testability 7.3.1.1a.5.11 Environmental Considerations 7.3.1.1a.5.12 Operational Considerations 7.3.1.1a.5.12.1 General Information 7.3.1.1a.5.12.2 Reactor Operator Information

7.3.1.1a.5.12.3 Setpoints 7.3.1.1b System Description (Non-NSSS) 7.3.1.1b.1 Primary Containment Isolation Control System for Non-NSSS - Instrumentation and Control 7.3.1.1b.1.1 System Description 7.3.1.1b.1.2 Initiating Circuits and Logic

7.3.1.1b.1.3 Bypasses, Interlocks and Sequencing 7.3.1.1b.1.4 Redundancy and Diversity 7.3.1.1b.1.5 Actuated Devices 7.3.1.1b.1.6 Supporting Systems 7.3.1.1b.1.7 Instrument Sensing Lines SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xviii 7.3.1.1b.2 Combustible Gas Control System 7.3.1.1b.2.1 System Description 7.3.1.1b.2.1.1 Initiating Circuits, Logic, Bypasses, Interlocks and Sequencing 7.3.1.1b.2.1.2 Redundancy and Diversity 7.3.1.1b.2.1.3 Supporting Systems 7.3.1.1b.3 Primary Containment Vacuum Relief - Instrumentation and Control 7.3.1.1b.3.1 System Description 7.3.1.1b.3.2 Initiating Circuits, Logic, Bypasses, Interlocks and Sequencing 7.3.1.1b.3.3 Redundancy and Diversity 7.3.1.1b.3.4 Actuated Devices 7.3.1.1b.4 Standby Gas Treatment System (SGTS) 7.3.1.1b.4.1 Initiating Circuits 7.3.1.1b.4.2 Logic and Sequencing 7.3.1.1b.4.3 Interlocks 7.3.1.1b.4.4 Bypasses

7.3.1.1b.4.5 Redundancy 7.3.1.1b.4.6 Diversity 7.3.1.1b.4.7 Actuated Devices 7.3.1.1b.4.8 Separation 7.3.1.1b.4.9 Supporting Systems 7.3.1.1b.4.10 System Parts Not Required for Safety 7.3.1.1b.5 Reactor Building Recirculation System 7.3.1.1b.5.1 Initiating Circuits 7.3.1.1b.5.2 Logic and Sequencing 7.3.1.1b.5.3 Interlocks 7.3.1.1b.5.4 Bypasses

7.3.1.1b.5.5 Redundancy 7.3.1.1b.5.6 Diversity 7.3.1.1b.5.7 Actuated Devices 7.3.1.1b.5.8 Separation 7.3.1.1b.5.9 Supporting Systems 7.3.1.1b.5.10 System Parts Not Required for Safety 7.3.1.1b.6 Reactor Building Isolation and HVAC Support 7.3.1.1b.6.1 Initiating Circuits 7.3.1.1b.6.2 Logic and Sequencing 7.3.1.1b.6.3 Interlocks 7.3.1.1b.6.4 Bypasses

7.3.1.1b.6.5 Redundancy 7.3.1.1b.6.6 Diversity 7.3.1.1b.6.7 Actuated Devices 7.3.1.1b.6.8 Separation SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xix 7.3.1.1b.6.9 Supporting Systems 7.3.1.1b.6.10 System Parts Not Required for Safety 7.3.1.1b.7 Habitability, Control Room Isolation 7.3.1.1b.7.1 Initiation 7.3.1.1b.7.2 Logic and Sequencing 7.3.1.1b.7.3 Interlocks 7.3.1.1b.7.4 Bypasses

7.3.1.1b.7.5 Redundancy 7.3.1.1b.7.6 Diversity 7.3.1.1b.7.7 Actuated Devices 7.3.1.1b.7.8 Separation 7.3.1.1b.7.9 Supporting Systems 7.3.1.1b.7.10 System Parts Not Required for Safety 7.3.1.1b.8 Auxiliary Support Systems 7.3.1.1b.8.1 Emergency Service Water System - Instrumentation and Control 7.3.1.1b.8.1.1 Initiating Circuits 7.3.1.1b.8.1.2 Logic, Bypasses, Interlocks, and Sequencing 7.3.1.1b.8.1.2.1 Logic Power Source 7.3.1.1b.8.1.2.2 Pump Logic 7.3.1.1b.8.1.2.3 Bypasses 7.3.1.1b.8.1.2.4 Interlocks 7.3.1.1b.8.1.2.5 Sequencing

7.3.1.1b.8.1.3 Redundancy 7.3.1.1b.8.1.4 Actuated Devices 7.3.1.1b.8.1.5 Supporting Systems 7.3.1.1b.8.1.6 ESW Instrumentation Not Required for Safety 7.3.1.1b.8.2 RHR Service Water System - Instrumentation and Controls 7.3.1.1b.8.2.1 Initiation Circuits 7.3.1.1b.8.2.2 Logic, Bypasses, Interlocks, and Sequencing 7.3.1.1b.8.2.2.1 Logic Power Source 7.3.1.1b.8.2.2.2 Pump Control Logic 7.3.1.1b.8.2.2.3 Bypasses 7.3.1.1b.8.2.2.4 Valve Control Logic 7.3.1.1b.8.2.2.5 Interlocks 7.3.1.1b.8.2.3 Actuated Devices 7.3.1.1b.8.2.4 Redundancy and Diversity 7.3.1.1b.8.2.5 Supporting Systems 7.3.1.1b.8.2.6 RHR Service Water Instrumentation Not Required for Safety 7.3.1.1b.8.3 Containment Instrument Gas System - Instrumentation and Control 7.3.1.1b.8.3.1 Initiating Logic and Interlocks 7.3.1.1b.8.3.2 Bypasses, Interlocks and Sequencing SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xx 7.3.1.1b.8.3.3 Redundancy 7.3.1.1b.8.3.4 Containment Instrument Gas Instrumentation Not Required for Safety 7.3.1.1b.8.3.5 Containment Instrument Gas Safety-Related Instrumentation 7.3.1.1b.8.4 Standby Power System 7.3.1.1b.8.5 Heating, Ventilating and Air Conditioning Systems for ESF Areas 7.3.1.1b.8.5.1 SGTS Equipment Room H&V System 7.3.1.1b.8.5.1.1 Initiating Circuits 7.3.1.1b.8.5.1.2 Logic and Sequencing 7.3.1.1b.8.5.1.3 Interlocks 7.3.1.1b.8.5.1.4 Bypasses 7.3.1.1b.8.5.1.5 Redundancy 7.3.1.1b.8.5.1.6 Diversity 7.3.1.1b.8.5.1.7 Actuated Devices 7.3.1.1b.8.5.1.8 Separation 7.3.1.1b.8.5.1.9 Supporting Systems 7.3.1.1b.8.5.1.10 System Parts Not Required for Safety 7.3.1.1b.8.5.2 Diesel Ge nerator Buildings' H&V Systems 7.3.1.1b.8.5.2.1 Initiating Circuits 7.3.1.1b.8.5.2.2 Logic and Sequencing 7.3.1.1b.8.5.2.3 Interlocks 7.3.1.1b.8.5.2.4 Bypasses 7.3.1.1b.8.5.2.5 Redundancy 7.3.1.1b.8.5.2.6 Diversity 7.3.1.1b.8.5.2.7 Actuated Devices 7.3.1.1b.8.5.2.8 Separation 7.3.1.1b.8.5.2.9 Supporting Systems 7.3.1.1b.8.5.2.10 System Parts Not Required for Safety 7.3.1.1b.8.5.3 Engineered Safeguard Service Water Pumphouse Ventilation System 7.3.1.1b.8.5.3.1 Initiating Circuits 7.3.1.1b.8.5.3.2 Logic and Sequencing 7.3.1.1b.8.5.3.3 Interlocks 7.3.1.1b.8.5.3.4 Bypasses 7.3.1.1b.8.5.3.5 Redundancy 7.3.1.1b.8.5.3.6 Diversity 7.3.1.1b.8.5.3.7 Actuated Devices 7.3.1.1b.8.5.3.8 Separation 7.3.1.1b.8.5.3.9 Supporting Systems 7.3.1.1b.8.5.3.10 System Parts Not Required for Safety 7.3.1.1b.8.5.4 ESF Switchgear (SWGR) Rooms Cooling System SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxi 7.3.1.1b.8.5.4.1 Initiating Circuits 7.3.1.1b.8.5.4.2 Logic and Sequencing 7.3.1.1b.8.5.4.3 Interlocks 7.3.1.1b.8.5.4.4 Bypasses 7.3.1.1b.8.5.4.5 Redundancy 7.3.1.1b.8.5.4.6 Diversity 7.3.1.1b.8.5.4.7 Actuated Devices 7.3.1.1b.8.5.4.8 Separation 7.3.1.1b.8.5.4.9 Supporting Systems 7.3.1.1b.8.5.4.10 System Parts Not Required for Safety 7.3.1.1b.8.5.5 Emergency Core Cooling Systems (ECCS) Unit Coolers 7.3.1.1b.8.5.5.1 Initiating Circuits 7.3.1.1b.8.5.5.2 Logic and Sequencing 7.3.1.1b.8.5.5.3 Interlocks 7.3.1.1b.8.5.5.4 Bypasses 7.3.1.1b.8.5.5.5 Redundancy 7.3.1.1b.8.5.5.6 Diversity 7.3.1.1b.8.5.5.7 Actuated Devices 7.3.1.1b.8.5.5.8 Separation 7.3.1.1b.8.5.5.9 Supporting Systems 7.3.1.1b.8.5.5.10 System Parts Not Required for Safety 7.3.1.1b.8.5.6 Drywell Unit Coolers and CRD Area Ventilation Fans 7.3.1.1b.8.5.6.1 Initiating Circuits 7.3.1.1b.8.5.6.2 Logic and Sequencing 7.3.1.1b.8.5.6.3 Interlocks 7.3.1.1b.8.5.6.4 Bypass 7.3.1.1b.8.5.6.5 Redundancy 7.3.1.1b.8.5.6.6 Diversity 7.3.1.1b.8.5.6.7 Actuated Devices 7.3.1.1b.8.5.6.8 Separation 7.3.1.1b.8.5.6.9 Supporting Systems 7.3.1.1b.8.5.6.10 System Parts Not Required for Safety 7.3.1.1b.8.5.7 Control Structure Chilled Water System (CSCWS) 7.3.1.1b.8.5.7.1 Initiating Circuits 7.3.1.1b.8.5.7.2 Logic and Sequencing 7.3.1.1b.8.5.7.3 Interlocks 7.3.1.1b.8.5.7.4 Bypasses 7.3.1.1b.8.5.7.5 Redundancy 7.3.1.1b.8.5.7.6 Diversity 7.3.1.1b.8.5.7.7 Actuated Devices 7.3.1.1b.8.5.7.8 Separation SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxii 7.3.1.1b.8.5.7.9 Supporting Systems 7.3.1.1b.8.5.7.10 System Parts Not Required for Safety 7.3.1.1b.9 Containment Atmosphere Control 7.3.1.2 IEEE 279-1971 Design Basis Information 7.3.1.2.1 Conditions 7.3.1.2.2 Variables 7.3.1.2.3 Numbers of Sensors and Location 7.3.1.2.4 Operational Limits 7.3.1.2.5 Margin Between Operational Limits 7.3.1.2.6 Levels Requiring Protective Action 7.3.1.2.7 Range of Energy Supply and Environmental Conditions of Safety Systems 7.3.1.2.8 Malfunctions, Accidents, and Other Unusual Events Which Could Cause Damage to Safety System 7.3.1.2.9 Minimum Performance Requirements 7.3.1.3 Final System Drawings

7.3.2 Analysis 7.3.2a Analysis of ESFAS Supplied with the NSSS

7.3.2a.1 Emergency Core Cooling Systems - Instrumentation and Controls 7.3.2a.1.1 General Functional Requirement Conformance 7.3.2a.1.2 Specific Regulatory Requirements Conformance 7.3.2a.1.2.1 Regulatory Guides 7.3.2a.1.2.1.1 Regulatory Guide 1.6 (1971) 7.3.2a.1.2.1.2 Regulatory Guide 1.11 (1971) 7.3.2a.1.2.1.3 Regulatory Guide 1.22 (1972) 7.3.2a.1.2.1.4 Regulatory Guide 1.29 (1976) 7.3.2a.1.2.1.5 Regulatory Guide 1.30 (1972) 7.3.2a.1.2.1.6 Regulatory Guide 1.32 (1972) 7.3.2a.1.2.1.7 Regulatory Guide 1.47 (1973) 7.3.2a.1.2.1.8 Regulatory Guide 1.53 (1973) 7.3.2a.1.2.1.9 Regulatory Guide 1.62 (1973) 7.3.2a.1.2.1.10 Regulatory Guide 1.75 (1974) 7.3.2a.1.2.2 10CFR50, Appendix A 7.3.2a.1.2.3 Industry Standards 7.3.2a.1.2.3.1 IEEE 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations 7.3.2a.1.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.3.2a.1.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.3.2a.1.2.3.1.3 Quality of Components (IEEE 279-1971, Paragraph 4.3)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxiii 7.3.2a.1.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.3.2a.1.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.3.2a.1.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.3.2a.1.2.3.1.7 Control and Protection Interaction (IEEE 279-1972, Paragraph 4.7) 7.3.2a.1.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.3.2a.1.2.3.1.9 Capability of Sensor Checks (IEEE 279-1971, Paragraph 4.9)

7.3.2a.1.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.3.2a.1.2.3.1.11 Channel Bypass or Rem oval from Operation (IEEE 279-1971, Paragraph 4.11) 7.3.2a.1.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.3.2a.1.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.3.2a.1.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.3.2a.1.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.3.2a.1.2.3.1.16 Completion of Protective Action Once It Is Initiated (IEEE 279-1971, Paragraph 4.16) 7.3.2a.1.2.3.1.17 Manual Initiation (IEEE 279-1971, Paragraph 4.17) 7.3.2a.1.2.3.1.18 A ccess to Setpoint Ad justments (IEEE 279-1 971, Paragraph 4.18) 7.3.2a.1.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.3.2a.1.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.3.2a.1.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.3.2a.1.2.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.3.2a.1.2.3.2 IEEE 308-1974 7.3.2a.1.2.3.3 IEEE 323-1971 7.3.2a.1.2.3.4 IEEE 338-1971 7.3.2a.1.2.3.5 IEEE 344-1971 7.3.2a.1.2.3.6 IEEE 379-1972 7.3.2a.2 Primary Containment and Reactor Vessel Isolation Control System for NSS Systems - Instrumentation and Controls 7.3.2a.2.1 General Functional Requirement Conformance 7.3.2a.2.2 Specific Regulatory Requirements Conformance 7.3.2a.2.2.1 NRC Regulatory Guides

7.3.2a.2.2.1.1 Regulatory Guide 1.11 (1971) 7.3.2a.2.2.1.2 Regulatory Guide 1.22 (1972) 7.3.2a.2.2.1.3 Regulatory Guide 1.29 (1972) 7.3.2a.2.2.1.4 Regulatory Guide 1.30 (1972) 7.3.2a.2.2.1.5 Regulatory Guide 1.47 (1973) 7.3.2a.2.2.1.6 Regulatory Guide 1.53 (1973) 7.3.2a.2.2.1.7 Regulatory Guide 1.62 (1973) 7.3.2a.2.2.1.8 Regulatory Guide 1.63 (1973)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxiv 7.3.2a.2.2.1.9 Regulatory Guide 1.75 (1975) 7.3.2a.2.2.1.10 Regulatory Guide 1.89 (1974) 7.3.2a.2.2.2 Conformance to 10CFR50, Appendix A 7.3.2a.2.2.3 Industry Codes and Standards 7.3.2a.2.2.3.1 IEEE 279-1971 7.3.2a.2.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.3.2a.2.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.3.2a.2.2.3.1.3 Quality of Components and Modules (IEEE 279-1971, Paragraph 4.3) 7.3.2a.2.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.3.2a.2.2.3.1.5 Channel Integrity (IEEE 279-1971,Paragraph 4.5) 7.3.2a.2.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.3.2a.2.2.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7) 7.3.2a.2.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.3.2a.2.2.3.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.3.2a.2.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.3.2a.2.2.3.1.11 Channel Bypass or Rem oval from Operation (IEEE 279-1971, Paragraph 4.11) 7.3.2a.2.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.3.2a.2.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.3.2a.2.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.3.2a.2.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.3.2a.2.2.3.1.16 Completion of Protection Action Once Initiated (IEEE 279-1971, Paragraph 4.16) 7.3.2a.2.2.3.1.17 Manual Action (IEEE 279-1971, Paragraph 4.17) 7.3.2a.2.2.3.1.18 A ccess to Setpoint Ad justments (IEEE 279-1 971, Paragraph 4.18) 7.3.2a.2.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.3.2a.2.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.3.2a.2.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.3.2a.2.2.3.1.22 Identification of Protection Systems (IEEE 279-1971, Paragraph 4.22) 7.3.2a.2.2.3.2 Conformance to IEEE 308-1974 7.3.2a.2.2.3.3 Conformance to IEEE 323-1971 7.3.2a.2.2.3.4 Conformance to IEEE 338-1971 7.3.2a.2.2.3.5 Conformance to IEEE 344-1971 7.3.2a.2.2.3.6 Conformance to IEEE 379-1972 7.3.2a.3 This Subsection is not used 7.3.2a.4 Containment Spray Cooling System - Instrumentation and Controls 7.3.2a.4.1 General Functional Requirement Conformance SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxv 7.3.2a.4.2 Specific Regulatory Requirements Conformance 7.3.2a.4.3 Conformance to Industry Codes and Standards 7.3.2a.4.3.1 IEEE 279-1971 7.3.2a.4.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.3.2a.4.3.1.2 Single-Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.3.2a.4.3.1.3 Quality Components (IEEE 279-1971, Paragraph 4.3) 7.3.2a.4.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.3.2a.4.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.3.2a.4.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.3.2a.4.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7) 7.3.2a.4.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.3.2a.4.3.1.9 Capability for Sensor Checks (I EEE 279-1971, Paragraph 4.9) 7.3.2a.4.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.3.2a.4.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.3.2a.4.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.3.2a.4.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.3.2a.4.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.3.2a.4.3.1.15 Multiple Trip Settings (IEEE 279-1971, Paragraph 4.15) 7.3.2a.4.3.1.16 Completion of Protection Action Once It is Initiated (IEEE 279-1971, Paragraph 4.16) 7.3.2a.4.3.1.17 Manual Actuation (IEEE 279-1971, Paragraph 4.17) 7.3.2a.4.3.1.18 Access to Setpoint Adjustment (IEEE 279-1971, Pa ragraph 4.18) 7.3.2a.4.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.3.2a.4.3.1.20 Information Readout (I EEE 279-1971, Paragraph 4.20) 7.3.2a.4.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.3.2a.4.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.3.2a.5 Suppression Pool Cooling Mode (RHR) - Instrumentation and Controls 7.3.2a.5.1 General Functional Requirements Conformance 7.3.2a.5.2 Regulatory Requirements Conformance 7.3.2a.5.2.1 Regulatory Guide 1.22 (1972) 7.3.2a.5.2.2 Regulatory Guide 1.29 (1973) 7.3.2a.5.2.3 Regulatory Guide 1.30 (1972) 7.3.2a.5.2.4 Regulatory Guide 1.32 (1972) 7.3.2a.5.2.5 Regulatory Guide 1.47 (1973) 7.3.2a.5.2.6 Regulatory Guide 1.53 (1973) 7.3.2a.5.2.7 Regulatory Guide 1.62 (1973) 7.3.2a.5.2.8 Regulatory Guide 1.63 (1973)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxvi 7.3.2a.5.2.9 Regulatory Guide 1.75 (1975) 7.3.2a.5.3 Conformance to 10CFR50 Appendix A 7.3.2a.5.4 Conformance to Industry Codes and Standards 7.3.2a.5.4.1 IEEE Standard 279(1971) 7.3.2a.5.4.1.1 General Functional Requirements (Paragraph 4.1) 7.3.2a.5.4.1.2 Single Failure Criterion (Paragraph 4.2) 7.3.2a.5.4.1.3 Quality of Components (Paragraph 4.3) 7.3.2a.5.4.1.4 Equipment Qualification (Paragraph 4.4) 7.3.2a.5.4.1.5 Channel Integrity (Paragraph 4.5) 7.3.2a.5.4.1.6 Channel Independence (Paragraph 4.6) 7.3.2a.5.4.1.7 Control and Protection System Interaction (Paragraph 4.7) 7.3.2a.5.4.1.8 Derivation of System Inputs (Paragraph 4.8) 7.3.2a.5.4.1.9 Capability for Sensor Checks (Paragraph 4.9)

7.3.2a.5.4.1.10 Capability for Test and Calibration (Paragraph 4.10) 7.3.2a.5.4.1.11 Channel Bypass or Removal from Operation (Paragraph 4.11), Operating Bypasses (Paragraph 4.12), Indication of Bypasses (Paragraph 4.13) 7.3.2a.5.4.1.12 Access to Means for Bypassing (Paragraph 4.14) 7.3.2a.5.4.1.13 Multiple Setpoint (Paragraph 4.15) 7.3.2a.5.4.1.14 Completion of Protective Action Once Initiated (Paragraph 4.16) 7.3.2a.5.4.1.15 Manual Initiation (Paragraph 4.17) 7.3.2a.5.4.1.16 Access to Setpoint Adjustments (Paragraph 4.18) 7.3.2a.5.4.1.17 Identification of Protective Actions (Paragraph 4.19) 7.3.2a.5.4.1.18 Information Read-Out (Paragraph 4.20) 7.3.2a.5.4.1.19 System Repair (Paragraph 4.21) 7.3.2a.5.4.1.20 Identification (Paragraph 4.22) 7.3.2a.5.4.2 IEEE Standard 308(1974) 7.3.2a.5.4.3 IEEE Standard 338(1971) 7.3.2a.5.4.4 IEEE Standard 379(1972) 7.3.2a.5.4.5 IEEE Standard 384(1974) 7.3.2a.6 Additional Design Considerations Analyses 7.3.2a.6.1 General Plant Safety Analysis 7.3.2a.6.2 Loss of Plant Instrument Air System 7.3.2a.6.3 Loss of Cooling Wa ter to Vital Equipment

7.3.2b Analysis for Non-NSSS Systems

7.3.2b.1 General Design Criteria 7.3.2b.2 Equipment Design Criteria 7.3.2b.3 Failure Modes and Effect Analysis (FMEA) 7.3.2b.3.1 Non-NSSS Containment Isolation Systems SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxvii 7.3.2b.3.2 Combustible Gas Control 7.3.2b.3.3 Primary Containment Vacuum Relief 7.3.2b.3.4 Standby Gas Treatment System 7.3.2b.3.5 Reactor Building Recirculation 7.3.2b.3.6 Reactor Building Isolation 7.3.2b.3.7 Control Room Isolation 7.3.2b.4 Consideration of Plant Contingencies 7.3.2b.4.1 Loss of Instrument Air Systems 7.3.2b.4.2 Loss of Cooling Wa ter to Vital Equipment 7.3.2b.5 Testing Methods and Effects on System Integrity During Testing

7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN

7.4.1 Description

7.4.1.1 Reactor Core Isolation Cooling (RCIC) System - Instrumentation and Controls 7.4.1.1.1 System Identification 7.4.1.1.1.1 Function 7.4.1.1.1.2 Classification 7.4.1.1.2 Power Sources 7.4.1.1.3 Equipment Design 7.4.1.1.3.1 General 7.4.1.1.3.2 Initiating Circuits 7.4.1.1.3.3 Logic and Sequencing 7.4.1.1.3.4 Bypasses and Interlocks 7.4.1.1.3.5 Redundancy & Diversity 7.4.1.1.3.6 Actuated Devices 7.4.1.1.3.7 Separation 7.4.1.1.3.8 Testability 7.4.1.1.4 Environmental Considerations 7.4.1.1.5 Operational Considerations 7.4.1.1.5.1 General Information 7.4.1.1.5.2 Reactor Operator Information 7.4.1.1.5.3 Setpoints 7.4.1.2 Standby Liquid Control System (SLCS) - Instrumentation & Controls 7.4.1.2.1 System Identification 7.4.1.2.1.1 Function 7.4.1.2.1.2 Classification 7.4.1.2.2 Power Sources 7.4.1.2.3 Equipment Design SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxviii 7.4.1.2.3.1 General 7.4.1.2.3.2 Initiating Circuits 7.4.1.2.3.3 Logic and Sequencing 7.4.1.2.3.4 Bypasses and Interlocks 7.4.1.2.3.5 Redundancy and Diversity 7.4.1.2.3.6 Actuated Devices 7.4.1.2.3.7 Separation 7.4.1.2.3.8 Testability 7.4.1.2.4 Environmental Considerations 7.4.1.2.5 Operational Considerations 7.4.1.2.5.1 General Information 7.4.1.2.5.2 Reactor Operator Information 7.4.1.2.5.3 Setpoints 7.4.1.3 RHRS/Reactor Shutdown Cooling Mode - Instrumentation and Controls 7.4.1.3.1 System Identification 7.4.1.3.1.1 Function 7.4.1.3.1.2 Classification 7.4.1.3.2 Power Sources 7.4.1.3.3 Equipment Design 7.4.1.3.3.1 General 7.4.1.3.3.2 Initiating Circuits 7.4.1.3.3.3 Logic and Sequencing 7.4.1.3.3.4 Bypasses and Interlocks 7.4.1.3.3.5 Redundancy and Diversity 7.4.1.3.3.6 Actuated Devices 7.4.1.3.3.7 Separation 7.4.1.3.3.8 Testability 7.4.1.3.4 Environmental Considerations 7.4.1.3.5 Operational Considerations 7.4.1.3.5.1 General Information 7.4.1.3.5.2 Reactor Operator Information 7.4.1.3.5.3 Setpoints 7.4.1.4 Reactor Shutdown from Outside the Control Room (Remote Shutdown) 7.4.1.4.1 Description 7.4.1.4.2 Design Criteria 7.4.1.4.2.1 Postulated Conditions During the Evacuation of the Main Control Room 7.4.1.4.2.2 Design Considerations 7.4.1.4.2.3 Remote Shutdown Functional Capabilities SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxix 7.4.1.4.3 Consideration for Operation of the Remote Shutdown Panel 7.4.1.4.4 Consideration for Operation of the Alternate Control Structure HVAC Panel

7.4.2 Analysis

7.4.2.1 Reactor Core Isolation Cooling (RCIC) System - Instrumentation and Control 7.4.2.1.1 General Functional Requirements Conformance 7.4.2.1.2 Specific Regulatory Requirements Conformance 7.4.2.1.2.1 NRC Regulatory Guides Conformance 7.4.2.1.2.1.1 Regulatory Guide 1.6 7.4.2.1.2.1.2 Regulatory Guide 1.11 7.4.2.1.2.1.3 Regulatory Guide 1.22 7.4.2.1.2.1.4 Regulatory Guide 1.29 7.4.2.1.2.1.5 Regulatory Guide 1.30 7.4.2.1.2.1.6 Regulatory Guide 1.32 7.4.2.1.2.1.7 Regulatory Guide 1.47 7.4.2.1.2.1.8 Regulatory Guide 1.53 7.4.2.1.2.1.9 Regulatory Guide 1.62 7.4.2.1.2.1.10 Regulatory Guide 1.63 7.4.2.1.2.1.11 Regulatory Guide 1.75 7.4.2.1.2.1.12 Regulatory Guide 1.89 7.4.2.1.2.2 NRC Regulations Conformance - 10CFR50 Appendix A Requirements 7.4.2.1.2.2.1 General Design Criterion 13 7.4.2.1.2.2.2 General Design Criterion 20 7.4.2.1.2.2.3 General Design Criterion 21 7.4.2.1.2.2.4 General Design Criterion 22 7.4.2.1.2.2.5 General Design Criterion 29 7.4.2.1.2.2.6 General Design Criterion 34 7.4.2.1.2.2.7 General Design Criterion 37 7.4.2.1.2.3 Conformance to Industry Codes and Standards 7.4.2.1.2.3.1 IEEE 279-1971 7.4.2.1.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.4.2.1.2.3.1.2 Single-Failure Criterio n (IEEE 279-1971, Paragraph 4.2) 7.4.2.1.2.3.1.3 Quality of Components and Modules 7.4.2.1.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.4.2.1.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.4.2.1.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.4.2.1.2.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxx 7.4.2.1.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.4.2.1.2.3.1.9 Capability for Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.4.2.1.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.4.2.1.2.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.4.2.1.2.3.1.12 Operating Bypasses (IEEE 279-1971, Paragraph 4.12) 7.4.2.1.2.3.1.13 Indication of Bypasses (IEEE 279-1971, Paragraph 4.13) 7.4.2.1.2.3.1.14 Access to Means for Bypassing (IEEE 279-1971, Paragraph 4.14) 7.4.2.1.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.4.2.1.2.3.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, Paragraph 4.16) 7.4.2.1.2.3.1.17 Manual Actuation (IEEE 279-1971, Paragraph 4.17) 7.4.2.1.2.3.1.18 Access to Setpoint Adjustment (IEEE 279-1971, Paragraph 4.18) 7.4.2.1.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.4.2.1.2.3.1.20 Information Readout (IEEE 279-1971, Paragraph 4.20) 7.4.2.1.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.4.2.1.2.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.4.2.1.2.3.2 IEEE 308-1974 7.4.2.1.2.3.3 IEEE 323-1971 7.4.2.1.2.3.4 IEEE 338-1971 7.4.2.1.2.3.5 IEEE 344-1971 7.4.2.2 Standby Liquid Control System (SLCS) - Instrumentation and Controls 7.4.2.2.1 General Functional Requirements Conformance 7.4.2.2.2 Specific Regulatory Requirements Conformance 7.4.2.2.2.1 NRC Regulatory Guides Conformance 7.4.2.2.2.1.1 Regulatory Guide 1.6 7.4.2.2.2.1.2 Regulatory Guide 1.11 7.4.2.2.2.1.3 Regulatory Guide 1.22 7.4.2.2.2.1.4 Regulatory Guide 1.29 7.4.2.2.2.1.5 Regulatory Guide 1.30 7.4.2.2.2.1.6 Regulatory Guide 1.32 7.4.2.2.2.1.7 Regulatory Guide 1.47 7.4.2.2.2.1.8 Regulatory Guide 1.53 7.4.2.2.2.1.9 Regulatory Guide 1.62 7.4.2.2.2.1.10 Regulatory Guide 1.63 7.4.2.2.2.1.11 Regulatory Guide 1.89 SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxi 7.4.2.2.2.2 NRC Regulations Conformance-10CFR150 Appendix A Requirements 7.4.2.2.2.2.1 General Design Criterion 13 7.4.2.2.2.2.2 General Design Criterion 29 7.4.2.2.2.3 Conformance to Industry Codes and Standards 7.4.2.2.2.3.1 IEEE 279-1971 7.4.2.2.2.3.1.1 General Functional Requirement (IEEE 279-1971, Paragraph 4.1) 7.4.2.2.2.3.1.2 Single Failure Criterion (IEEE 279-1971, Paragraph 4.2) 7.4.2.2.2.3.1.3 Quality of Components and Modules (IEEE 279-1971, Paragraph 4.3) 7.4.2.2.2.3.1.4 Equipment Qualification (IEEE 279-1971, Paragraph 4.4) 7.4.2.2.2.3.1.5 Channel Integrity (IEEE 279-1971, Paragraph 4.5) 7.4.2.2.2.3.1.6 Channel Independence (IEEE 279-1971, Paragraph 4.6) 7.4.2.2.2.3.1.7 Control and Protection Interaction (IEEE 279-1971, Paragraph 4.7) 7.4.2.2.2.3.1.8 Derivation of System Inputs (IEEE 279-1971, Paragraph 4.8) 7.4.2.2.2.3.1.9 Capability of Sensor Checks (IEEE 279-1971, Paragraph 4.9) 7.4.2.2.2.3.1.10 Capability for Test and Calibration (IEEE 279-1971, Paragraph 4.10) 7.4.2.2.2.3.1.11 Channel Bypass or Removal from Operation (IEEE 279-1971, Paragraph 4.11) 7.4.2.2.2.3.1.12 Operating Bypass (IEEE 279-1971, Paragraph 4.12) 7.4.2.2.2.3.1.13 Indication of By pass (IEEE279-1971, Paragraph 4.13) 7.4.2.2.2.3.1.14 Access to Means for Bypass (IEEE 279-1971, Paragraph 4.14) 7.4.2.2.2.3.1.15 Multiple Setpoints (IEEE 279-1971, Paragraph 4.15) 7.4.2.2.2.3.1.16 Completion of Protective Act ion Once it is Initiated (IEEE 279-1971, Paragraph 4.16) 7.4.2.2.2.3.1.17 Manual Initiation (IEEE 279-1971, Paragraph 4.17) 7.4.2.2.2.3.1.18 Access to Setpoint Adjustments, Calibration, and Test Points (IEEE 279-1971, Paragraph 4.18) 7.4.2.2.2.3.1.19 Identification of Protective Actions (IEEE 279-1971, Paragraph 4.19) 7.4.2.2.2.3.1.20 Information Read-out (IEEE 279-1971, Paragraph 4.20) 7.4.2.2.2.3.1.21 System Repair (IEEE 279-1971, Paragraph 4.21) 7.4.2.2.2.3.1.22 Identification (IEEE 279-1971, Paragraph 4.22) 7.4.2.2.2.3.2 IEEE 323-1971 7.4.2.2.2.3.3 IEEE 338-1971 7.4.2.2.2.3.4 IEEE 344-1971 7.4.2.3 Residual Heat Removal System - Reactor Shutdown Cooling Mode Subsystem - Instrumentation and Controls 7.4.2.3.1 General Functional Requirements Conformance 7.4.2.3.2 Specific Regulatory Requirements Conformance SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxii 7.4.2.3.2.1 Conformance to NRC Regulatory Guides 7.4.2.3.2.2 Conformance to NRC Regulations - 10CFR50 Appendix A Requirements 7.4.2.3.2.2.1 General Design Criterion 34 Residual Heat Removal 7.4.2.3.2.3 Conformance to Industry Codes and Standards 7.4.2.4 Reactor Shutdown from Outside the Control Room (Remote Shutdown)

7.4.3 References

7.5 SAFETY-RELATED DISPLAY INSTRUMENTATION (SRDI)

7.5.1a Description

7.5.1a.1 General Description of NSSS Safety - Related Display Instrumentation 7.5.1a.2 Normal Operation 7.5.1a.3 Abnormal Transient Occurrences 7.5.1a.4 Accident Conditions 7.5.1a.4.1 Initial Accident Event 7.5.1a.4.2 Post-Accident Tracking 7.5.1a.4.2.1 Reactor Water Level 7.5.1a.4.2.2 Reactor Pressure 7.5.1a.4.2.3 Reactor Shutdown, Isolation, and Core Cooling Indication 7.5.1a.4.2.3.1 Reactor Operator Information and Observations 7.5.1a.4.2.3.2 System Operation Information - Display Equipment 7.5.1a.4.2.3.3 System Operation Information - Display Equipment Qualification 7.5.1a.4.2.4 Containment Indications

7.5.1b Description of Non-NSSS Safety-Related Displays

7.5.1b.1 Containment Isolation 7.5.1b.2 Combustible Gas Control 7.5.1b.3 Primary Containment Vacuum Relief 7.5.1b.4 Standby Gas Treatment, RX Building Recirculation, and Isolation System 7.5.1b.5 Habitability Systems 7.5.1b.6 Auxiliary Support Systems 7.5.1b.7 Bypass Indication System 7.5.1b.7.1 System Description 7.5.1b.8 Post-Accident Neutron Flux Monitoring System SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxiii 7.5.1b.8.1 This Subsection Has Been Deleted

7.5.2a Analysis of NSSS Safety-Related Displays 7.5.2a.1 General 7.5.2a.1.1 Design Criteria 7.5.2a.1.1.1 Power Generation Control Complex Criteria 7.5.2a.1.1.2 Advance Control Room Design and Operational Criteria 7.5.2a.1.1.2.1 Design Criteria 7.5.2a.1.1.2.2 Operating Criteria 7.5.2a.2 Normal Operation 7.5.2a.3 Abnormal Transient Occurrences 7.5.2a.4 Accident Conditions 7.5.2a.4.1 Initial Accident Event 7.5.2a.4.2 Post-Accident Tracking 7.5.2a.4.3 Safe Shutdown Display 7.5.2a.4.4 Engineered Safety Feature Operation Display 7.5.2a.5 Compliance with Regulatory/Industry Standards 7.5.2a.5.1 Conformance to IEEE 279-1971 7.5.2a.5.1.1 General 7.5.2a.5.1.2 Automatic Initiation of Protective Action (IEEE 279, Paragraph 4.1) 7.5.2a.5.1.3 Single Failure Criterion (IEEE 279, Paragraph 4.2) 7.5.2a.5.1.4 Quality of Indicators (IEEE 279, Paragraph 4.3) 7.5.2a.5.1.5 Equipment Qualification (IEEE 279, Paragraph 4.4) 7.5.2a.5.1.6 Channel Integrity (IEEE 279, Paragraph 4.5) 7.5.2a.5.1.7 Channel Independence (IEEE 279, Paragraph 4.6) 7.5.2a.5.1.8 Control and Protection System Interaction (IEEE 279, Paragraph 4.7) 7.5.2a.5.1.9 Deviation of System Inputs (IEEE 279, Paragraph 4.8) 7.5.2a.5.1.10 Capability for Sensor Checks (IEEE 279, Paragraph 4.9) 7.5.2a.5.1.11 Capability for Test and Calibration (IEEE Paragraph 4.10) 7.5.2a.5.1.12 Channel Bypass (IEEE 279, Paragraph 4.11) 7.5.2a.5.1.13 Operating Bypasses (IEEE 279, Paragraph 4.12) 7.5.2a.5.1.14 Indication of Bypass (IEEE 279, Paragraph 4.13) 7.5.2a.5.1.15 Access to Means for Bypassing (IEEE 279, Paragraph 4.14) 7.5.2a.5.1.16 Multiple Setpoints (IEEE 279, Paragraph 4.15) 7.5.2a.5.1.17 Completion of Protective Action Once it is Initiated (IEEE 279, Paragraph 4.16) 7.5.2a.5.1.18 Manual Actuation (IEEE 279, Paragraph 4.17) 7.5.2a.5.1.19 Access to Setpoints (IEEE 279, Paragraph 4.18) 7.5.2a.5.1.20 Identification of Protective Action (IEEE 279, Paragraph 4.19)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxiv 7.5.2a.5.1.21 Information Read Out (IEEE 279, Paragraph 4.20) 7.5.2a.5.1.22 System Repair (IEEE 279, Paragraph 4.21) 7.5.2a.5.1.23 Identification (IEEE 279, Paragraph 4.22) 7.5.2a.5.2 Conformance with IEEE 323 7.5.2a.5.3 Conformance with IEEE 344 7.5.2a.5.4 Regulatory Guide 1.47 7.5.2a.5.5 Regulatory Guide 1.97 7.5.2a.5.6 10CFR50 Appendix B

7.5.2b Analysis of Non-NSSS Safety-Related Display Instrumentation

7.5.2b.1 Identification, Redundancy, Accuracy 7.5.2b.2 Isolation, Separation 7.5.2b.3 Qualification of Components 7.5.2b.4 Capability for Checking 7.5.2b.5 Analysis of the Bypass Indication System 7.5.2b.6 This Section Has Been Deleted

7.6 ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 7.6.1a Description

7.6.1a.1 Refueling Interlocks System - Instrumentation and Controls 7.6.1a.2 NSSS Process Radiation Monitoring System - Instrumentation and Controls 7.6.1a.3 High Pressure/Low Pressure System Interlock Protection System 7.6.1a.3.1 Function Identification 7.6.1a.3.2 Power Sources 7.6.1a.3.3 Equipment Design 7.6.1a.3.3.1 Circuit Description 7.6.1a.3.3.2 Logic and Sequencing 7.6.1a.3.3.3 Bypasses and Interlocks

7.6.1a.3.3.4 Redundancy 7.6.1a.3.3.5 Actuated Devices 7.6.1a.3.3.6 Separation 7.6.1a.3.3.7 Testability 7.6.1a.3.4 Environmental Considerations 7.6.1a.3.5 Operational Considerations 7.6.1a.3.5.1 General Information 7.6.1a.3.5.2 Reactor Operator Information SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxv 7.6.1a.3.5.3 Setpoints 7.6.1a.4 NSSS Leak Detection System - Instrumentation and Controls 7.6.1a.4.1 System Identification 7.6.1a.4.2 Power Sources 7.6.1a.4.3 Equipment Design 7.6.1a.4.3.1 General 7.6.1a.4.3.2 Main Steamline Leak Detection 7.6.1a.4.3.3 RCIC System Leak Detection 7.6.1a.4.3.3.1 Subsystem Identification 7.6.1a.4.3.3.2 RCIC Area Temperature Monitoring 7.6.1a.4.3.3.2.1 Circuit Description 7.6.1a.4.3.3.2.2 Logic and Sequencing 7.6.1a.4.3.3.2.3 Bypasses and Interlocks 7.6.1a.4.3.3.2.4 Redundancy and Diversity 7.6.1a.4.3.3.3 RCIC Steamline Pressure Monitoring 7.6.1a.4.3.3.3.1 Circuit Description 7.6.1a.4.3.3.3.2 Logic and Sequencing 7.6.1a.4.3.3.3.3 Bypasses and Interlocks 7.6.1a.4.3.3.3.4 Redundancy and Diversity 7.6.1a.4.3.3.4 RCIC Flow Rate Monitoring 7.6.1a.4.3.3.4.1 Circuit Description 7.6.1a.4.3.3.4.2 Logic and Sequencing 7.6.1a.4.3.3.4.3 Bypass and Interlocks 7.6.1a.4.3.3.4.4 Redundancy and Diversity 7.6.1a.4.3.4 Recirculation Pump Leak Detection 7.6.1a.4.3.4.1 Subsystem Identification 7.6.1a.4.3.4.2 Pump Seal Cavity Pressure Monitoring 7.6.1a.4.3.4.2.1 Circuit Description 7.6.1a.4.3.4.2.2 Logic and Sequencing 7.6.1a.4.3.4.2.3 Bypasses and Interlocks 7.6.1a.4.3.4.2.4 Redundancy and Diversity 7.6.1a.4.3.4.3 Liquid Flow Rate Monitoring 7.6.1a.4.3.4.3.1 Circuit Description 7.6.1a.4.3.4.3.2 Logic and Sequencing 7.6.1a.4.3.4.3.3 Bypasses and Interlocks 7.6.1a.4.3.4.3.4 Redundancy and Diversity 7.6.1a.4.3.5 RHR System Leak Detection 7.6.1a.4.3.5.1 Subsystem Identification 7.6.1a.4.3.5.2 RHR Area Temperature Monitoring 7.6.1a.4.3.5.2.1 Circuit Description 7.6.1a.4.3.5.2.2 Logic and Sequencing SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxvi 7.6.1a.4.3.5.2.3 Bypasses and Interlocks 7.6.1a.4.3.5.2.4 Redundancy and Diversity 7.6.1a.4.3.5.3 RHR Flow Rate Monitoring 7.6.1a.4.3.5.3.1 Circuit Description [Unit 2 only]

7.6.1a.4.3.5.3.2 Logic and Sequencing [Unit 2 only]

7.6.1a.4.3.5.3.3 Bypasses and Interlocks [Unit 2 only]

7.6.1a.4.3.5.3.4 Redundancy and Diversity [Unit 2 only]

7.6.1a.4.3.5.4 This Section Has Been Deleted 7.6.1a.4.3.5.5 RHR Pump Room Flood (Water Level) Detection [Unit 1 only]

7.6.1a.4.3.6 Reactor Water Clean-up System Leak Detection 7.6.1a.4.3.7 Safety/Relief Valve Leak Detection 7.6.1a.4.3.7.1 Subsystem Identification 7.6.1a.4.3.7.2 Safety/Relief Valve Discharge Line Temperature Monitoring 7.6.1a.4.3.7.2.1 Description 7.6.1a.4.3.7.2.2 Logic and Sequencing 7.6.1a.4.3.7.2.3 Bypasses and Interlocks 7.6.1a.4.3.8.2.4 Redundancy and Diversity 7.6.1a.4.3.8 HPCI System Leakage Detection 7.6.1a.4.3.8.1 Subsystem Identification 7.6.1a.4.3.8.2 HPCI Area Temperature Monitoring 7.6.1a.4.3.8.2.1 Circuit Description 7.6.1a.4.3.8.2.2 Logic and Sequencing 7.6.1a.4.3.8.2.3 Bypasses and Interlocks 7.6.1a.4.3.8.2.4 Redundancy and Diversity 7.6.1a.4.3.8.3 HPCI Steam Flow Monitoring 7.6.1a.4.3.8.3.1 Description 7.6.1a.4.3.8.3.2 Logic and Sequencing 7.6.1a.4.3.8.3.3 Bypasses and Interlocks 7.6.1a.4.3.8.3.4 Redundancy and Diversity 7.6.1a.4.3.8.4 HPCI Steamline Pressure Monitoring 7.6.1a.4.3.8.4.1 Circuit Description 7.6.1a.4.3.8.4.2 Logic and Sequencing 7.6.1a.4.3.8.4.3 Bypasses and Interlocks 7.6.1a.4.3.8.4.4 Redundancy and Diversity 7.6.1a.4.4 System and Subsystem Separation Criteria 7.6.1a.4.5 System and Subsystem Testability 7.6.1a.4.6 System and Subsystem Environmental Considerations 7.6.1a.4.7 System and Subsystem Operational Considerations 7.6.1a.5 Neutron Monitoring System - Instrumentation and Controls 7.6.1a.5.1 System Identification 7.6.1a.5.2 Power Source SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxvii 7.6.1a.5.3 Source Range Monitor (SRM) Subsystem 7.6.1a.5.4 Intermediate Range Monitor (IRM) Subsystem 7.6.1a.5.4.1 Equipment Design 7.6.1a.5.4.1.1 Description 7.6.1a.5.4.1.1.1 Bypasses and Interlocks 7.6.1a.5.4.1.2 Redundancy 7.6.1a.5.4.1.3 Testability 7.6.1a.5.4.2 Environmental Conditions 7.6.1a.5.4.3 Operational Considerations 7.6.1a.5.5 Local Power Range Monitor (LPRM) Subsystem 7.6.1a.5.5.1 Equipment Design 7.6.1a.5.5.1.1 Description 7.6.1a.5.5.1.2 Bypasses and Interlocks 7.6.1a.5.5.1.3 Redundancy 7.6.1a.5.5.1.4 Testability 7.6.1a.5.5.2 Environmental Considerations 7.6.1a.5.5.3 Operational Considerations 7.6.1a.5.6 Average Power Range Monitor (APRM) Subsystem 7.6.1a.5.6.1 Equipment Design 7.6.1a.5.6.1.1 Description 7.6.1a.5.6.1.2 Bypasses and Interlocks 7.6.1a.5.6.1.3 Redundancy 7.6.1a.5.6.1.4 Testability 7.6.1a.5.6.2 Environmental Considerations 7.6.1a.5.6.3 Operational Considerations 7.6.1a.5.7 Rod Block Monitor (RBM) Subsystem 7.6.1a.5.8 Traversing In-Core Probe Subsystem 7.6.1a.5.9 This Section Intentionally Deleted 7.6.1a.6 Rod Block Trip System - Instrumentation and Controls 7.6.1a.7 Rod Sequence Control System (RSCS) - Instrumentation and Controls 7.6.1a.8 Recirculation Pump Trip (RPT) System - Instrumentation and Controls 7.6.1a.8.1 System Identification 7.6.1a.8.1.1 Safety Classification 7.6.1a.8.1.2 Reference Design 7.5.1a.8.2 Power Sources 7.6.1a.8.3 Equipment Design 7.6.1a.8.3.1 Initiating Circuits 7.6.1a.8.3.2 Logic 7.6.1a.8.3.3 Instrument Piping SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxviii 7.6.1a.8.3.4 Actuated Devices 7.6.1a.8.3.5 Separation 7.6.1a.8.3.6 Testability 7.6.1a.8.4 Environmental Considerations 7.6.1a.8.5 Operational Considerations 7.6.1a.8.5.1 General Information 7.6.1a.8.5.2 Reactor Operator Information 7.6.1a.8.5.3 Setpoints 7.6.1a.8.6 IEEE-279 Design Basis Considerations 7.6.1a.9 Process Computer System-Rod Worth Minimizer (RWM) - Instrumentation and Controls

7.6.1b Description

7.6.1b.1 Containment Monitoring - Instrumentation and Controls 7.6.1b.1.1 Primary Containment Drywell and Suppression Chamber Pressure Monitoring System 7.6.1b.1.1.1 System Identification 7.6.1b.1.1.2 Safety Evaluation 7.6.1b.1.1.3 Power Supply 7.6.1b.1.1.4 Equipment Design

7.6.1b.1.1.5 Redundancy 7.6.1b.1.1.6 Separation 7.6.1b.1.1.7 Operational Considerations 7.6.1b.1.1.8 Environmental Consideration 7.6.1b.1.2 Primary Containment Drywell and Suppression Pool Temperature Monitoring System 7.6.1b.1.2.1 System Identification 7.6.1b.1.2.2 Safety Evaluation 7.6.1b.1.2.3 Power Sources 7.6.1b.1.2.4 Equipment Design 7.6.1b.1.2.4.1 Equipment Design-Containment Temperature 7.6.1b.1.2.4.2 Equipment Design-Suppression Pool Temperature 7.6.1b.1.2.5 Redundancy 7.6.1b.1.2.6 Separation 7.6.1b.1.2.7 Operational Consideration 7.6.1b.1.2.8 Environmental Consideration 7.6.1b.1.3 Suppression Pool Water Level Monitoring System 7.6.1b.1.3.1 System Identification 7.6.1b.1.3.2 Safety Evaluation 7.5.1b.1.3.3 Power Sources SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xxxix 7.6.1b.1.3.4 Equipment Design 7.6.1b.1.3.5 Redundancy 7.6.1b.1.3.6 Separation 7.6.1b.1.3.7 Operational Considerations 7.6.1b.1.3.8 Environmental Considerations 7.6.1b.1.4 Primary Containment and Suppression Chamber Airborne Particulate Radioactivity Monitoring System - Instrumentation and Controls 7.6.1b.1.5 Primary Containment Radiation Monitoring System (High Range) 7.6.1b.1.5.1 System Identification 7.6.1b.1.5.2 Safety Evaluation 7.6.1b.1.5.3 Power Supply 7.6.1b.1.5.4 Equipment Design

7.6.1b.1.5.5 Redundancy 7.6.1b.1.5.6 Separation 7.6.1b.1.5.7 Operational Considerations 7.6.1b.1.5.8 Environmental Consideration 7.6.1b.1.6 Safety/Relief Valve Position Indication System 7.6.1b.1.6.1 System Identification 7.6.1b.1.6.2 Safety Evaluation 7.6.1b.1.6.3 Power Sources 7.6.1b.1.6.4 Equipment Design

7.6.1b.1.6.5 Redundancy 7.6.1b.1.6.6 Separation 7.6.1b.1.6.7 Operational Considerations 7.6.1b.1.6.8 Environmental Considerations 7.6.1b.2 Non-NSSS Process Radiation Monitoring System - Instrumentation and Controls 7.6.1b.2.1 Refueling Floor Wall Exhaust Radiation Monitoring Subsystem 7.6.1b.2.2 Refueling Floor High Exhaust Radiation Monitoring Subsystem 7.6.1b.2.3 Railroad Access Shaft Exhaust Radiation Monitoring Subsystem 7.6.1b.2.4 Emergency Outside Air Intake Radiation Monitoring Subsystem 7.6.1b.2.5 Standby Gas Treatment System Exhaust Vent Radiation Monitoring Subsystem 7.6.1b.3 Diesel Generator Initiation - Instrumentation and Controls 7.6.1b.3.1 Initiation 7.6.1b.3.2 Logic 7.6.1b.3.3 Bypasses 7.6.1b.4 Drywell Entry Purge - Instrumentation and Controls 7.6.1b.4.1 Initiating Circuits, Logic, and Bypasses 7.6.1b.4.2 Interlocks SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xl 7.6.1b.4.3 Sequencing, Redundancy, and Diversity

7.6.2a Analysis for NSSS - Systems

7.6.2a.1 Refueling Interlocks System - Instrumentation and Controls 7.6.2a.2 Process Radiation Monitoring System - Instrumentation and Controls 7.6.2a.2.1 Main Steamline Radiation Monitoring Subsystem 7.6.2a.2.1.1 General Functional Requirement Conformance 7.6.2a.2.1.2 Specific Regulatory Requirement Conformance 7.6.2a.3 High Pressure/Low Pressure Interlock Protection and Control System 7.6.2a.3.1 General Functional Requirements Conformance 7.6.2a.3.2 Specific Regulatory Requirements Conformance 7.6.2a.3.2.1 General Design Criteria Conformance 7.6.2a.3.2.2 IEEE Standards Conformance 7.6.2a.3.2.2.1 Conformance to IEEE Standard 279-1971 7.6.2a.3.2.2.2 Conformance to IEEE Standard 338-1971 7.6.2a.3.2.2.3 Conformance to IEEE Standard 379-1972 7.6.2a.3.2.3 Regulatory Guide Conformance 7.6.2a.3.2.3.1 Conformance to Regulatory Guide 1.22 7.6.2a.3.2.3.2 Conformance to Regulatory Guide 1.53 7.6.2a.4 NSSS Leak Detection System - Instrumentation and Controls 7.6.2a.4.1 General Functional Requirements Conformance 7.6.2a.4.2 Specific Regulatory Requirements Conformance 7.6.2a.4.2.1 Regulatory Guides Conformance 7.6.2a.4.2.2 Regulation Conformance 7.6.2a.4.2.3 Industry Standards Conformance 7.6.2a.5 Neutron Monitoring System - Instrumentation and Controls 7.6.2a.5.1 Source Range Monitor Subsystem 7.6.2a.5.2 Intermediate Range Monitor Subsystem 7.6.2a.5.2.1 General Functional Requirements Conformance 7.6.2a.5.2.2 Specific Regulatory Requirement Conformance 7.6.2a.5.3 Local Power Range Monitor Subsystem 7.6.2a.5.3.1 General Functional Requirement Conformance 7.6.2a.5.3.2 Specific Regulatory Requirement Conformance 7.6.2a.5.4 Average Power Range Monitor Subsystem 7.6.2a.5.4.1 General Functional Requirement Conformance 7.6.2a.5.4.2 Specific Regulatory Requirement Conformance 7.6.2a.5.5 Rod Block Monitoring Subsystem 7.6.2a.5.6 Traversing In-Core Probe Subsystem (TIPS)

SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xli 7.6.2a.6 Rod Block Trip - Instrumentation and Controls 7.6.2a.7 Rod Sequence Control System 7.6.2a.8 Recirculation Pump Trip System 7.6.2a.8.1 General Functional Requirements Conformance 7.6.2a.8.2 Specific Regulatory Requirement Conformance (IEEE 279-1971) 7.6.2a.9 Process Computer System-Rod Worth Minimizer (RWM) -Instrumentation and Controls 7.6.2a.10 Additional Design Considerations Analyses 7.6.2a.10.1 General Plant Safety Analyses 7.6.2a.10.2 Cold Water Slug Injection 7.6.2a.10.3 Refueling Accidents 7.6.2a.10.4 Overpressurization of Low Pressure System

7.6.2b Analysis for Non-NSSS Systems

7.6.2b.1 General Functional Requirement Conformance 7.6.2b.2 Specific Requirements Conformance

7.6.3 References

7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY

7.7.1 Description

7.7.1.1 Reactor Vessel - Instrumentation 7.7.1.1.1 System Identification 7.7.1.1.1.1 General 7.7.1.1.1.2 Classification 7.7.1.1.1.3 Reference Design 7.7.1.1.2 Power Sources 7.7.1.1.3 Equipment Design 7.7.1.1.3.1 Circuit Description 7.7.1.1.3.1.1 Reactor Vessel Temperature 7.7.1.1.3.1.2 Reactor Vessel Water Level 7.7.1.1.3.1.3 Reactor Core Hydraulics 7.7.1.1.3.1.4 Reactor Vessel Pressure 7.7.1.1.3.1.5 Reactor Vessel Head Seal Leak Detection 7.7.1.1.3.1.6 Safety/Relief Valve Seal Leak Detection 7.7.1.1.3.1.7 Other Instruments 7.7.1.1.3.2 Testability 7.7.1.1.4 Environmental Considerations SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlii 7.7.1.1.5 Operational Considerations 7.7.1.1.5.1 General Information 7.7.1.1.5.2 Reactor Operator Information 7.7.1.1.5.3 Setpoints 7.7.1.2 Reactor Manual Control System - Instrumentation and Controls 7.7.1.2.1 System Identification 7.7.1.2.1.1 General 7.7.1.2.1.2 Classification 7.7.1.2.1.3 Reference Design 7.7.1.2.2 Power Sources 7.7.1.2.3 Equipment Design 7.7.1.2.3.1 General 7.7.1.2.3.2 Rod Movement Controls 7.7.1.2.3.2.1 Control Rod Drive Control System 7.7.1.2.3.2.1.1 Introduction 7.7.1.2.3.2.1.2 Insert Cycle 7.7.1.2.3.2.1.3 Withdraw Cycle 7.7.1.2.3.2.2 Control Rod Drive - Hydraulic System Control 7.7.1.2.3.2.3 Rod Block Interlocks 7.7.1.2.3.2.4 Testability 7.7.1.2.3.3 Rod Position Information 7.7.1.2.3.3.1 Position Probes

7.7.1.2.3.3.2 Position Indication Electronics 7.7.1.2.3.3.3 System Operation 7.7.1.2.4 Environmental Considerations 7.7.1.2.5 Operational Considerations 7.7.1.2.5.1 General Information 7.7.1.2.5.2 Reactor Operator Information 7.7.1.2.5.3 Setpoints 7.7.1.2.6 Rod Block Sub-Trip System of RMCS 7.7.1.2.6.1 Grouping of Channels 7.7.1.2.6.2 Rod Block Functions 7.7.1.2.6.3 Rod Block Bypasses 7.7.1.2.6.4 Rod Block Interlocks 7.7.1.2.6.5 Redundancy 7.7.1.2.6.6 Testability 7.7.1.2.6.7 Environmental Considerations 7.7.1.2.6.8 Operational Considerations 7.7.1.2.7 Rod Sequence Control System (RSCS) - Subsystem of RMCS Instrumentation Controls 7.7.1.2.7.1 System Identification SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xliii 7.7.1.2.7.2 Power Sources 7.7.1.2.7.3 Equipment Design 7.7.1.2.7.3.1 General Description 7.7.1.2.7.3.2 Inputs 7.7.1.2.7.3.3 Outputs 7.7.1.2.7.3.4 Description of Function Blocks 7.7.1.2.7.3.4.1 Rod Pattern Controller (RPC) 7.7.1.2.7.3.4.2 Substitute Position Generator 7.7.1.2.7.3.4.3 Operator Display 7.7.1.2.7.3.4.4 Tester 7.7.1.2.7.3.4.5 Bypassed Rod Identifier 7.7.1.2.7.3.4.6 Logic Rules 7.7.1.2.7.3.4.7 Buffering 7.7.1.2.7.3.4.8 RSCS Rod Insertion Block Bypass Mode 7.7.1.2.7.4 Environmental Considerations 7.7.1.2.7.5 Operational Considerations 7.7.1.2.7.6 Separation 7.7.1.2.8 Rod Worth Minimizer (RWM) - Instrumentation and Controls 7.7.1.2.8.1 System Identification 7.7.1.2.8.2 Power Sources 7.7.1.2.8.3 Equipment Design 7.7.1.2.8.4 System Interface Relationship 7.7.1.2.8.5 Operational Considerations 7.7.1.3 Recirculation Flow Control System - Instrumentation and Controls 7.7.1.3.1 System Identification 7.7.1.3.1.1 General 7.7.1.3.1.2 Classification 7.7.1.3.1.3 Reference Design 7.7.1.3.2 Power Sources 7.7.1.3.3 Equipment Design 7.7.1.3.3.1 General 7.7.1.3.3.2 Pump Drive Motor Control 7.7.1.3.3.2.1 ATWS Trip 7.7.1.3.3.3 High Frequency Motor - Generator (HFMG) Set 7.7.1.3.3.4 Speed Control 7.7.1.3.3.4.1 Digital Integrated Control System - Reactor Recirculation Pump Speed 7.7.1.3.3.4.2 Modes of Speed Control Operation 7.7.1.3.3.4.3 Speed Limiters and Rundown 7.7.1.3.3.4.4 Recirculation Loop Starting Sequence 7.7.1.3.3.5 Testability SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xliv 7.7.1.3.4 Environmental Considerations 7.7.1.3.5 Operational Considerations 7.7.1.3.5.1 General Information 7.7.1.3.5.2 Reactor Operator Information 7.7.1.3.5.3 Setpoints 7.7.1.4 Feedwater Control System - Instrumentation and Controls 7.7.1.4.1 System Identification 7.7.1.4.1.1 General 7.7.1.4.1.2 Classification 7.7.1.4.1.3 Reference Design 7.7.1.4.2 Power Sources 7.7.1.4.3 Equipment Design 7.7.1.4.3.1 General 7.7.1.4.3.2 Reactor Vessel Water Level Measurement 7.7.1.4.3.3 Steam Flow Measurement 7.7.1.4.3.4 Feedwater Flow Measurement 7.7.1.4.3.5 Feedwater/Level Control 7.7.1.4.3.5.1 Interlocks 7.7.1.4.3.6 Turbine-Driven Feedwater Pump Control 7.7.1.4.3.7 Testability 7.7.1.4.4 Environmental Considerations 7.7.1.4.5 Operational Considerations 7.7.1.4.5.1 General Information 7.7.1.4.5.2 Reactor Operator Information 7.7.1.4.5.3 Setpoints 7.7.1.5 Pressure Regulator and Turbine-Generator Control System 7.7.1.5.1 Power Generation Design Bases 7.7.1.5.2 Power Sources 7.7.1.5.3 Equipment Design 7.7.1.5.3.1 System Description 7.7.1.5.3.2 Steam Pressure Control 7.7.1.5.3.3 Steam Bypass System 7.7.1.5.3.4 Turbine Speed System/Load Control System 7.7.1.5.3.5 Turbine Generator to Reactor Protection System Interface 7.7.1.5.3.6 Turbine Generator to Main Steam Isolation System Interface 7.7.1.5.3.7 Inspection and Testing 7.7.1.5.4 Environmental Considerations 7.7.1.5.5 Operational Considerations 7.7.1.6 Neutron Monitoring System - Traversing In-Core Probe (TIP) Subsystem - Instrumentation and Controls SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlv 7.7.1.6.1 System Identification 7.7.1.6.1.1 General 7.7.1.6.1.2 Classification 7.7.1.6.1.3 Reference Design 7.7.1.6.2 Power Sources 7.7.1.6.3 Equipment Design 7.7.1.6.3.1 General 7.7.1.6.3.2 Equipment Arrangement 7.7.1.6.3.3 Testability 7.7.1.6.4 Environmental Considerations 7.7.1.6.5 Operational Considerations 7.7.1.7 Plant Integrated Computer System and Reactor Data Analysis System (RDAS) - Instrumentation 7.7.1.7.1 System Identification 7.7.1.7.1.1 General Objectives 7.7.1.7.1.2 Classification 7.7.1.7.1.3 Reference Design 7.7.1.7.2 Power Sources 7.7.1.7.3.1 System Description 7.7.1.7.3.1.1 Reactor Data Analysis System 7.7.1.7.3.2 Testability 7.7.1.7.4 Environmental Considerations 7.7.1.7.5 Operational Considerations 7.7.1.7.5.1 General Information 7.7.1.7.5.2 Reactor Operator Information 7.7.1.8 Reactor Water Cleanup (RWCU) System - Instrumentation and Controls 7.7.1.8.1 System Identification 7.7.1.8.1.1 General 7.7.1.8.1.2 Classification 7.7.1.8.1.3 Reference Design 7.7.1.8.2 Power Sources 7.7.1.8.3 Equipment Design 7.7.1.8.3.1 General 7.7.1.8.3.2 Circuit Description 7.7.1.8.3.3 Testability 7.7.1.8.4 Environmental Considerations 7.7.1.8.5 Operational Considerations 7.7.1.8.5.1 General Information 7.7.1.8.5.2 Reactor Operator Information 7.7.1.8.5.3 Setpoints SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlvi 7.7.1.9 Transient Monitoring System for Startup Testing 7.7.1.9.1 Transient Monitoring System (TMS) Description 7.7.1.9.2 Piping Thermal Expansion and Vibration Measurement 7.7.1.10 Refueling Interlocks System - Instrumentation and Controls 7.7.1.10.1 System Identification 7.7.1.10.2 Power Sources 7.7.1.10.3 Equipment Design 7.7.1.10.3.1 Circuit Description 7.7.1.10.3.2 Logic and Sequencing

7.7.1.10.3.3 Bypasses and Interlocks 7.7.1.10.3.4 Redundancy and Diversity 7.7.1.10.3.5 Actuated Devices 7.7.1.10.3.6 Separation 7.7.1.10.3.7 Testability 7.7.1.10.4 Environmental Considerations 7.7.1.10.5 Operational Considerations 7.7.1.10.5.1 General Information 7.7.1.10.5.2 Reactor Operator Information 7.7.1.10.5.3 Setpoints 7.7.1.11 Neutron Monitoring System - Rod Block Monitor (RBM) Subsystem 7.7.1.11.1 Equipment Design 7.7.1.11.1.1 Description 7.7.1.11.1.2 Rod Block Trip Function 7.7.1.11.1.3 Bypasses

7.7.1.11.1.4 Redundancy 7.7.1.11.1.5 Testability 7.7.1.11.2 Environmental Considerations 7.7.1.11.3 Operational Considerations 7.7.1.12 Nuclear Pressure Relief System 7.7.1.12.1 System Identification 7.7.1.12.2 Equipment Design 7.7.1.12.3 Initiating Circuits 7.7.1.12.4 Logic and Sequencing 7.7.1.12.5 Bypasses and Interlocks 7.7.1.12.6 Redundancy and Diversity 7.7.1.12.7 Actuated Devices 7.7.1.12.8 Separation 7.7.1.12.9 Testability 7.7.1.12.10 Environmental Considerations 7.7.1.12.11 Operational Considerations 7.7.1.12.11.1 General Information SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlvii 7.7.1.12.11.2 Operational Information 7.7.1.13 Neutron Monitoring System - Source Range Monitor (SRM)

Subsystem 7.7.1.13.1 Equipment Design 7.7.1.13.1.1 Description

7.7.1.13.1.1.1 Bypasses and Interlocks 7.7.1.13.1.2 Redundancy and Diversity 7.7.1.13.1.3 Testability 7.7.1.13.2 Environmental Considerations 7.7.1.13.3 Operational Considerations 7.7.1.14 Loose Parts Monitoring System

7.7.2 Analysis

7.7.2.1 Reactor Vessel - Instrumentation 7.7.2.1.1 General Functional Requirements Conformance 7.7.2.1.2 Specific Regulatory Requirements Conformance 7.7.2.2 Reactor Manual Control System - Instrumentation and Controls 7.7.2.2.1 General Functional Requirements Conformance 7.7.2.2.2 Specific Regulatory Requirements 7.7.2.2.3 Rod Block Trip - Instrumentation and Controls 7.7.2.2.3.1 General Functional Requirements Conformance 7.7.2.2.3.2 Specific Regulatory Requirement Conformance 7.7.2.2.4 Rod Sequence Control System 7.7.2.2.4.1 Conformance to General Functional Requirements 7.7.2.2.4.2 Conformance to Specific Regulatory Requirement 7.7.2.2.5 Rod Worth Minimizer (RWM) - Instrumentation and Controls 7.7.2.2.5.1 General Functional Requirements Conformance 7.7.2.2.5.2 Specific Regulatory Requirements Conformance 7.7.2.3 Recirculation Flow Control System - Instrumentation and Controls 7.7.2.3.1 General Functional Requirements Conformance 7.7.2.3.2 Specific Regulatory Requirements 7.7.2.4 Feedwater Control System (Turbine-Driven Pumps) - Instrumentation and Controls 7.7.2.4.1 General Functional Requirements Conformance 7.7.2.4.2 Specific Regulatory Requirements Conformance 7.7.2.5 Pressure Regulatory and Turbine-Generator System Instrumentation and Controls 7.7.2.5.1 General Functional Requirements Conformance 7.7.2.5.2 Specific Regulatory Requirements Conformance 7.7.2.6 Neutron Monitoring System Traversing In-Core Probe Subsystem SSES-FSAR Text Rev. 59 CHAPTER 7 TEXT Section Title FSAR Rev. 65 7-xlviii (TIP) - Instrumentation and Controls 7.7.2.6.1 General Functional Requirement Conformance 7.7.2.6.2 Specific Regulatory Requirement Conformance 7.7.2.7 Plant Computer System - Instrumentation 7.7.2.7.1 General Functional Requirements 7.7.2.7.2 Specific Regulatory Requirements Conformance 7.7.2.8 Reactor Water Cleanup System - Instrumentation and Controls 7.7.2.8.1 General Functional Requirement Conformance 7.7.2.8.2 Specific Regulatory Requirements Conformance 7.7.2.9 Transient Monitoring System Analysis 7.7.2.9.1 TMS Safety-Related Functions 7.7.2.9.1.1 TMS Safety-Related System Isolation 7.7.2.9.1.2 TMS Wiring Separation 7.7.2.10 Refueling Interlocks System - Instrumentation and Controls 7.7.2.10.1 General Functional Requirements Conformance 7.7.2.10.2 Specific Regulatory Requirements Conformance 7.7.2.11 Rod Block Monitor Subsystem 7.7.2.11.1 General Functional Requirement Conformance 7.7.2.11.2 Specific Regulatory Requirement Conformance 7.7.2.12 Nuclear Pressure Relief System - Instrumentation and Controls 7.7.2.12.1 General Functional Requirements Conformance 7.7.2.12.2 Specific Regulatory Requirements 7.7.2.13 Neutron Monitoring System - Instrumentation and Controls 7.7.2.13.1 Source Range Monitor Subsystem 7.7.2.13.1.1 General Functional Requirement Conformance 7.7.2.13.1.2 Specific Regulatory Requirements Conformance

7.7.3 References

SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-xlix 7.1-1 Responsibility

7.1-2 Similarity to Licensed Reactors

7.1-3 Codes and Standards Applicability Matrix

7.1-4 Reactor Protection System Codes and Standards

7.1-5 Primary Containment and Reactor Vessel Isolation Control System Codes and Standards

7.1-6 High Pressure ECCS (HPCI, ADS A, ADS B Network) Codes and Standards

7.1-7 Low Pressure ECCS (CS, RHR Network) Codes and Standards

7.1-8 Process Radiation Moni toring Codes and Standards

7.1-9 Leak Detection System Codes and Standards

7.1-10 Reactor Protection System Sensor Suffix Letters and Division Allocation

7.1-11 Four Division Grouping for Neutron Monitoring System

7.1-12 Emergency Core Cooling System and RCIC Sensor Suffix Letters and Division Allocation

7.2-1 Reactor Protection System Instrumentation Specifications

7.2-2 Channels Required for Functional Performance of RPS

7.2-3 ATWS Recirculation Pump Trip and Alternate Rod Injection Instrumentation Specifications

7.2-4 Channels Required for Functional Performance of ARI 7.3-1 High Pressure Coolant Injection System-Instrument Specifications and Channels

7.3-2 Automatic Depressurization System-Instrument Specifications and SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-l Channels 7.3-3 Core Spray System-Instrument Specifications and Channels

7.3-4 Low Pressure Coolant Injection-Instrument Specification and Channels 7.3-5 Primary Containment and Reactor Vessel Isolation Control System Instrumentation Specifications

7.3-6 This Table Has Been Deleted

7.3-7 This Table Has Been Deleted

7.3-8 This Table Has Been Deleted

7.3-9 This Table Has Been Deleted

7.3-10 This Table Has Been Deleted

7.3-11 This Table Has Been Deleted

7.3-12 This Table Has Been Deleted

7.3-13 ESFAS Actuated Equipment Standby Gas Treatment System

7.3-14 ESFAS Actuated Equipment Recirculation System, Reactor Building Isolation Dampers, and Reactor Building Non-Safety

Related Equipment

7.3-15 ESFAS Actuated Equipment Control Structure Emergency Outside Air Supply System

7.3-16 ESFAS Actuated Equipment Battery Rooms Exhaust System

7.3-17 General Notes for Tables 7.3-13 Through 7.3-16 7.3-18 Standby Gas Treatment System (SGTS) Failure Mode and Effects Analysis 7.3-19 Reactor Building Recirculation System Failure Mode and Effects SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-li Analysis 7.3-20 Failure Mode and Effects Analysis Primary Containment Isolation Control System Fan Non-NSS Systems

7.3-21 Emergency Outside Air Supply System (EOASS) Failure Mode and Effects Analysis

7.3-22 Computer Room Cooling System (CRCS) Failure Mode and Effects Analysis 7.3-23 Control Structure H&V System (CSHVS) Failure Mode and Effects Analysis 7.3-24 Control Structure Chilled Water System (CSCWS) Failure Mode and Effects Analysis

7.3-25 Battery Rooms Exhaust System Failure Mode and Effects Analysis

7.3-26 Control Room Floor Cooling System (CRFCS) Failure Mode and Effects Analysis

7.3-27 This Table Has Been Deleted

7.3-28 Reactor Protection System Response Times

7.3-29 Isolation System Instrumentation Response Time

7.3-30 Emergency Core Cooling System Response Times

7.4-1 This Table Has Been Deleted

7.4-2 RHRS Shutdown Cooling Bypasses and Interlocks

7.4-3 Remote Shutdown Panel Instrumentation

7.4-4 Alternate Control Structure HVAC Control Panel

7.5-1 Safety Related Display Instrumentation

7.5-2 Safety Related Display Instrumentation-Habitability (Emergency SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-lii Outside Air System/Control Structure HVAC)

7.5-3 Safety Related Display Instrumentation-Containment and Suppression Pool Instrumentation

7.5-4 Safety Related Display Instrumentation-Standby Gas Treatment System, RX Building Recirculation and Isolation System

7.5-5 Safety Related Display Instrumentation-Emergency Service Water System 7.5-6 Safety Related Display Instrumentation-RHR Service Water System and Spray Pond

7.5-7 Safety Related Display Instrumentation-Containment Instrument Gas System

7.5-7a Safety Related Display Instrumentation Standby Liquid Control System 7.5-8 Bypass Indication System for Non-NSSS Systems

7.6-1 (This table has been intentionally left blank)

7.6-2 (This table has been intentionally left blank)

7.6-3 IRM Trips

7.6-4 LPRM System Trips

7.6-5 APRM System Trips

7.6-6 (This table has been intentionally left blank)

7.6-7 OPRM System Trip

7.6-8 This Table Has Been Deleted

7.6-9 Suppression Pool Temperature Sensor Locations

7.6-10 End-of-Cycle Recirculation Pump Trip System Response Time SSES-FSAR Text Rev. 59 CHAPTER 7 TABLES Number Title FSAR Rev. 65 7-liii 7.7-1 CRD Hydraulic System Process Indicators

7.7-2 Refueling Interlock Effectiveness

7.7-3 RBM System Trips

7.7-4 IRM Trips

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-liv 7.2-1-1 This Figure has been replaced by Dwg. M1-C72-2, Sh. 1

7.2-1-2 This Figure has been replaced by Dwg. M1-C72-2, Sh. 2

7.2-1-3 This Figure has been replaced by Dwg. M1-C72-2, Sh. 3

7.2-1-4 This Figure has been replaced by Dwg. M1-C72-2, Sh. 4

7.2-2 Reactor Protection System Scram Functions

7.2-3 Arrangement of Channels and Logics

7.2-4 Actuators and Actuator Logics

7.2-5 Logic in One Trip System

7.2-6 Relationship Between Neutron Monitoring System and Reactor Protection System

7.2-7 Configuration for Turbine Stop Valve Closure Reactor Trip

7.2-8 Configuration for Main Steamline Isolation Reactor Trip

7.2-9 Block Diagram - RPS Protective Circuit - Electrical Protection Assembly (EPA)

7.2-10 ARI Trip System Logic

7.2-11 This Figure Intentionally Deleted

7.3-1 This Figure Has been Deleted

7.3-2 Isolation Control System for Main Steamline Isolation Valves

7.3-3 Isolation Control System Using Motor-Operated Valves

7.3-4 Main Steamline Isolation Valve Schematic

7.3-5-1 Initiation Logic - ADS, CS, RHR

7.3-5-2 ADS Initiation Logic SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lv 7.3-5-3 Unit 2 ADS Initiation Logic

7.3-6 Initiation Logic - HPCI, RCIC

7.3-7-1 This Figure has been replaced by Dwg. M1-E41-65, Sh. 1

7.3-7-2 This Figure has been replaced by Dwg. M1-E41-65, Sh. 2

7.3-7-3 This Figure has been replaced by Dwg. M1-E41-65, Sh. 3

7.3-7-4 This Figure has been replaced by Dwg. M1-E41-65, Sh. 4

7.3-7-5 This Figure has been replaced by Dwg. M1-E41-65, Sh. 5

7.3-8-1 This Figure has been replaced by Dwg. M1-B21-92, Sh. 1

7.3-8-2 This Figure has been replaced by Dwg. M1-B21-92, Sh. 2

7.3-8-3 This Figure has been replaced by Dwg. M1-B21-92, Sh. 3

7.3-8-4 This Figure has been replaced by Dwg. M1-B21-92, Sh. 4

7.3-8-5 This Figure has been replaced by Dwg. M1-B21-92, Sh. 5

7.3-8-6 This Figure has been replaced by Dwg. M1-B21-92, Sh. 6

7.3-9-1 This Figure has been replaced by Dwg. M1-E21-3, Sh. 1

7.3-9-2 This Figure has been replaced by Dwg. M1-E21-3, Sh. 2

7.3-9-3 This Figure has been replaced by Dwg. M1-E21-3, Sh. 3

7.3-10-1 This Figure has been replaced by Dwg. M1-E11-51, Sh. 1

7.3-10-2 This Figure has been replaced by Dwg. M1-E11-51, Sh. 2 7.3-10-3 This Figure has been replaced by Dwg. M1-E11-51, Sh. 3

7.3-10-4 This Figure has been replaced by Dwg. M1-E11-51, Sh. 4

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lvi 7.3-10-5 This Figure has been replaced by Dwg. M1-E11-51, Sh. 5

7.3-11-1 This Figure has been replaced by Dwg. M1-D12-1, Sh. 1

7.3-11-2 This Figure has been replaced by Dwg. M1-D12-1, Sh. 2

7.3-11-3 This Figure has been replaced by Dwg. M1-D12-1, Sh. 3

7.3-11-4 This Figure has been replaced by Dwg. M1-D12-1, Sh. 4

7.3-11-5 This Figure has been replaced by Dwg. M1-D12-1, Sh. 5

7.4-1 This Figure has been replaced by Dwgs. M-149, Sh. 1 & M-150, Sh. 1 7.4-2-1 This Figure has been replaced by Dwg. M1-E51-80, Sh. 1

7.4-2-2 This Figure has been replaced by Dwg. M1-E51-80, Sh. 2

7.4-2-3 This Figure has been replaced by Dwg. M1-E51-80, Sh. 3

7.4-2-4 This Figure has been replaced by Dwg. M1-E51-80, Sh. 4

7.4-3 This Figure has been replaced by Dwg. M-148, Sh. 1

7.4-4 This Figure has been replaced by Dwg. M1-C41-31, Sh. 1

7.5-1-1 This Figure Has Been Deleted

7.5-1-2 This Figure Has Been Deleted

7.5-1-3 This Figure Has Been Deleted

7.5-1-4 This Figure Has Been Deleted

7.5-1-5 This Figure Has Been Deleted 7.5-1-6 This Figure Has Been Deleted

7.5-2-1 This Figure Has Been Deleted

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lvii 7.5-2-2 This Figure Has Been Deleted

7.5-2-3 This Figure Has Been Deleted

7.5-3 Neutron Flux at Primary Shield

7.6-1 Recirculation Pump Leak Detection Block Diagram 7.6-2 RHR Area Temperature Monitoring System Block Diagram 7.6-3 Vessel Penetrations for Nuclear Instrumentation

7.6-4-1 This Figure has been replaced by Dwg. M1-C51-35, Sh. 1

7.6-4-2 This Figure has been replaced by Dwg. M1-C51-35, Sh. 2

7.6-5 SRM/IRM Neutron Monitoring Unit

7.6-6 Detector Drive System Schematic

7.6-7-1 This Figure has been replaced by Dwg. M1-C51-2, Sh. 1

7.6-7-2 This Figure has been replaced by Dwg. M1-C51-2, Sh. 2

7.6-7-3 This Figure has been replaced by Dwg. M1-C51-2, Sh. 3

7.6-7-4 This Figure has been replaced by Dwg. M1-C51-2, Sh. 4

7.6-7-5 This Figure has been replaced by Dwg. M1-C51-2, Sh. 5

7.6-7-6 This Figure has been replaced by Dwg. M1-C51-2, Sh. 6

7.6-7-7 This Figure has been replaced by Dwg. M1-C51-2, Sh. 7

7.6-8 Functional Block Diagram of SRM Channel

7.6-9 Functional Block Diagram of IRM Channel

7.6-10 Power Range Monitor Det ector Assembly Location

7.6-11-1 Refer to Figure 5.4-2A SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lviii 7.6-11-2 This Figure has been replaced by Dwg. M1-B31-13, Sh. 2

7.6-11-3 This Figure has been replaced by Dwg. M1-B31-13, Sh. 3

7.6-12 APRM Circuit Arrangement for Reactor Protection System Input

7.6-13 Ranges of Neutron Monitoring System

7.7-1 Water Level Range Definition

7.7-2-1 Control Rod Drive Hydraulic System - FCD

7.7-2-2 Control Rod Drive Hydraulic System - FCD

7.7-2-3 Control Rod Drive Hydraulic System - FCD

7.7-2-4 Control Rod Drive Hydraulic System - FCD

7.7-2-5 Control Rod Drive Hydraulic System - FCD

7.7-2-6 Control Rod Drive Hydraulic System - FCD

7.7-2-7 Control Rod Drive Hydraulic System - FCD

7.7-3-1 This Figure has been replaced by Dwg. M1-C12-90, Sh. 4

7.7-3-2 This Figure has been replaced by Dwg. M1-C12-110, Sh. 8

7.7-4 Reactor Manual Control System Operation

7.7-5 Reactor Manual Control Self-Test Provisions

7.7-6 Eleven-Wire Position Probe

7.7-7-1 This Figure has been replaced by Dwg. M1-B31-189, Sh. 1 7.7-7-2 This Figure has been replaced by Dwg. M1-B31-189, Sh. 2

7.7-7-3 This Figure has been replaced by Dwg. M1-B31-189, Sh. 3

SSES-FSAR Text Rev. 59 CHAPTER 7 FIGURES Number Title FSAR Rev. 65 7-lix 7.7-7-4 This Figure has been replaced by Dwg. M1-B31-189, Sh. 4

7.7-7-5 This Figure has been replaced by Dwg. M1-B31-189, Sh. 5

7.7-7-6 ATWS Recirculation Pump Trip Logic

7.7-8 Recirculation Flow Control Illustration

7.7-8a This Figure has been deleted

7.7-9 This Figure has been replaced by Dwg. M1-C32-3, Sh. 1

7.7-10 Detector Drive System Schematic

7.7-11 This Figure has been replaced by Dwg. M1-G33-143, Sh. 1

7.7-12 This Figure has been deleted

7.7-13 This Figure has been replaced by Dwg. A-105, Sh. 1

7.7-13a Control room Panel Safety Relat ed Display Instr. Plant Operator Interface

7.7-14 Traversing In-Core Probe Assembly

7.7-15 Main Turbine Control System Block Diagram 7.7-16 Assignment of LPRM Input to RBM System

7.7-17 Unit 1, RBM Response to Control Rod Motion (Channels A and C)

7.7-18 Unit 1, RBM Response to Control Rod Motion (Channels B and D) 7.7-19 Unit 2, Typical RBM Channel Responses, Old Versus New LPRM Assignment (No Failed LPRMS)

SSES-FSARTOCRev.60FSARRev.658-iCHAPTER8ELECTRICPOWERTABLEOFCONTENTSTEXTSectionTitle

8.1INTRODUCTION

8.1.1General 8.1.2UtilityPowerGridandOffsitePowerSystems 8.1.3OnsitePowerSystems 8.1.4SafetyRelatedLoads 8.1.5DesignBases 8.1.5.1SafetyDesignBases 8.1.6RegulatoryGuidesandIEEEStandards 8.1.6.1CompliancewithRegulatoryGuides8.1.6.2CompliancewithIEEE338,344,and3878.2OFFSITEPOWERSYSTEM 8.2.1Description 8.2.1.1TransmissionSystem8.2.1.2TransmissionInterconnection8.2.1.3Switchyards8.2.1.3.1StartupTransformers#10and#208.2.1.3.2SusquehannaUnit#1230kVMainTransformerLeads8.2.1.3.3Susquehanna230kVSwitchyard8.2.1.3.4SusquehannaUnit#2500kVMainTransformerLeads8.2.1.3.5Susquehanna500kVSwitchyard8.2.1.3.6MontourandMountain230kVSwitchyards8.2.1.4OffsitePowerSystemMonitoring 8.2.1.5IndustryStandards8.2.2Analysis SSES-FSARTOCRev.60CHAPTER8TEXTSectionTitleFSARRev.658-ii8.2.2.1GridAvailability8.2.2.2StabilityAnalysisAPPENDIX8.2ARELIABILITYPRINCIPLESANDSTANDARDSFORPLANNINGBULKELECTRICSUPPLYSYSTEMOFMAACGROUP8.3ONSITEPOWERSYSTEMS 8.3.1ACPowerSystems 8.3.1.1Description8.3.1.2Non-Class1EACSystem8.3.1.2.1Operation8.3.1.2.2Non-Class1EEquipmentCapacities8.3.1.3Class1EACPowerSystem8.3.1.3.1PowerSupplyFeeders8.3.1.3.2PowerFeederCables8.3.1.3.3BusArrangements8.3.1.3.4LoadsSuppliedfromEachBus8.3.1.3.5Class1EIsolatedSwingBus8.3.1.3.6ManualandAutomaticInterconnectionsBetweenBuses,BusesandLoads,andBusesandSupplies8.3.1.3.7InterconnectionsBetweenSafetyRelatedandNon-SafetyRelatedBuses,Non-SafetyRelatedLoads,andSafetyRelatedBuses8.3.1.3.8RedundantBusSeparation8.3.1.3.9Class1EEquipmentCapacities8.3.1.3.10AutomaticLoadingandLoadShedding8.3.1.3.11SafetyRelatedEquipmentIdentification8.3.1.3.12InstrumentationandControlSystemfortheApplicablePowerSystemsWiththeAssignedPowerSupplyIdentified8.3.1.3.13ElectricCircuitProtectionSystems8.3.1.3.14TestingoftheACSystemDuringPowerOperation8.3.1.3.15Class1ELoadsNotTestableDuringPowerOperations8.3.1.4StandbyPowerSupply8.3.1.4.1AutomaticStartingInitiatingCircuits8.3.1.4.2DieselStartingMechanismandSystem8.3.1.4.3AlarmandTrippingDevice8.3.1.4.4BreakerInterlocks8.3.1.4.5ControlPermissive8.3.1.4.6LoadingCircuits SSES-FSARTOCRev.60CHAPTER8TEXTSectionTitleFSARRev.658-iii8.3.1.4.7Testing8.3.1.4.8FuelOilStorageandTransferSystem8.3.1.4.9DieselGeneratorCoolingandHeating8.3.1.4.10InstrumentationandControlSystemsforStandbyPowerSupply8.3.1.4.11TestProgram8.3.1.4.11.1Class1EEquipmentIdentification8.3.1.4.11.2VendorQualificationTechniquesandDocumentation8.3.1.4.11.3PerformanceinServiceEnvironment8.3.1.4.11.4PeriodicTest8.3.1.4.12ControlandAlarmLogic8.3.1.5ElectricalEquipmentLayout8.3.1.6ReactorProtectionSystemPowerSupply8.3.1.7Class1E120VACInstrumentationandControlPowerSupply8.3.1.8Non-Class1EInstrumentandVitalACPowerSupply8.3.1.9DesignCriteriaforClass1EEquipment8.3.1.10Safety-RelatedLogicandSchematicDiagrams8.3.1.11Analysis8.3.1.11.1GeneralDesignCriteriaandRegulatoryGuideCompliance8.3.1.11.2SafetyRelatedEquipmentExposedtoAccidentEnvironment8.3.1.11.3PhysicalIdentificationofSafetyRelatedEquipment8.3.1.11.4IndependenceofRedundantSystemsSeparationCriteria8.3.1.11.5AdministrativeResponsibilitiesandControlsforEnsuringSeparationCriteria8.3.2DCPowerSystems 8.3.2.1Description8.3.2.1.1Class1EDCPowerSystem8.3.2.1.1.1125VDCSubsystems8.3.2.1.1.2250VDCSubsystems8.3.2.1.1.324VDCSubsystems8.3.2.1.1.4Class1EStationBatteriesandBatteryChargers 8.3.2.1.1.5Class1EDCSystemEquipmentRatings8.3.2.1.1.6Inspection,Maintenance,andTesting8.3.2.1.1.7SeparationandVentilation8.3.2.1.1.8Non-Class1EDCSystem8.3.2.2Analysis8.3.2.2.1CompliancewithGeneralDesignCriteria,RegulatoryGuides,andIEEEStandards8.3.2.2.2PhysicalIdentificationofSafetyRelatedEquipment8.3.2.2.3IndependenceofRedundantSystems SSES-FSARTOCRev.60CHAPTER8TEXTSectionTitleFSARRev.658-iv8.3.3FireProtectionforCableSystems8.3.3.1CableDeratingandCableTrayFill8.3.3.2FireDetectionforCableSystems8.3.3.3FireBarriersandSeparationBetweenRedundantTrays8.3.3.4FireStops SSES-FSARTOCRev.60CHAPTER8TABLESNumberTitleFSARRev.658-v8.1-1MotorOperatedValvesWithThermalOverloadContinuouslyBypassedDuringPlantOperation8.1-2AffiliatedandNon-Class1ECircuitsThatConnecttoClass1EPowerSupplies8.1-3Non-Class1EAnnunciatorandComputerInterfaceDevices 8.1-4DivisionalorAffiliatedLoadsSuppliedFromClass1EChannelCorD4.16kVBuss8.1-5ContainmentRadiationMonitorsSuppliedfromClass1ESystem 8.2-1SusquehannaUnit#1&#2StabilityCaseList(SummerLightLoadConditions)8.3-1AssignmentofESFandSelectedNon-ESFLoadstoDieselGeneratorsandESSBuses8.3-1aDieselGeneratorLoading(Note1),DieselGeneratorsA,B,CandDInService,Unit-DesignBasisAccident;Unit2-ForcedShutdown8.3-1bSupplementtoTable8.3-1 8.3-1cDieselGeneratorELoading,DieselGeneratorEInServiceforAorBorCorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-2DieselGeneratorLoading,DieselAUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-2aDieselGeneratorELoading,DieselAUnavailable,DieselGeneratorESubstitutedforDieselBorCorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-3DieselGeneratorLoading,DieselBUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-3aDieselGeneratorLoadingE,DieselBUnavailable,DieselGeneratorESubstitutedforDieselAorCorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown SSES-FSARTOCRev.60CHAPTER8TABLESNumberTitleFSARRev.658-vi8.3-4DieselGeneratorLoading,DieselCUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-4aDieselGeneratorELoading,DieselCUnavailable,DieselGeneratorESubstitutedforDieselAorBorD,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-5DieselGeneratorLoading,DieselDUnavailable,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-5aDieselGeneratorELoading,DieselDUnavailable,DieselGeneratorESubstitutedforDieselAorBorC,Unit1-DesignBasisAccident;Unit2-ForcedShutdown8.3-6A125VoltDCLoadCycle through 8.3-6I8.3-6J125VDCBatteryDutyLoadProfiles 8.3-7AUnit1250VDCLoadCycleDiv.I(1D650) 8.3-7BUnit1250VDCLoadCycleDiv.II(1D660) 8.3-7CUnit2250VDCLoadCycleDiv.I(2D650) 8.3-7DUnit2250VDCLoadCycleDiv.II(2D660) 8.3-7E250VDCBatteryDutyLoadProfiles 8.3-824VoltDCLoadCycle8.3-9ACPowerFailureModeEffectsAnalysis8.3-10RoutingTable 8.3-11ThisTableHasBeenDeleted 8.3-12ThisTableHasBeenDeleted SSES-FSARTOCRev.60CHAPTER8TABLESNumberTitleFSARRev.658-vii8.3-13ThisTableHasBeenDeleted8.3-14ThisTableHasBeenDeleted 8.3-15ThisTableHasBeenDeleted 8.3-16DieselGeneratorAutoStartCircuitFailureEffectsAnalysis(1) 8.3-17125VDCControlPowerSourceforNon-Class1E13.8kVand4.16kVSwitchgear8.3-18125VDCControlPowerSourceForNon-Class1E480VL.C.

8.3-19125VDCControlPowerSourceForClass1E4.16kVSwitchgear 8.3-20125VDCControlPowerSourceForClass1E480VLC 8.3-21FailureModeandEffectAnalysis-125VDCSystem(4Channels) 8.3-22FailureModeandEffectAnalysis-250VDCSystem(2Divisions) 8.3-23FailureModeandEffectAnalysis-24VDCSystem(2Divisions) 8.3-24CommonMode-CommonCauseFailureAnalysis-AutoTransferSwitch 8.3-25SeparationMethodsandRequirementsWithinJunctionBoxesandFieldInstalledPullBoxes SSES-FSARTOCRev.60CHAPTER8FIGURESNumberTitleFSARRev.658-viii8.2-1ThisFigureHasBeenReplacedbyDrawingD159760,Sh.18.2-2BulkPowerSupplySysteminVicinityofSusquehannaSteamElectricStation8.2-3TransmissionSystem 8.2-4MontourandMountainSwitchyardsOneLineDiagram 8.3-1-1ThisFigureHasBeenReplacedbyDrawingE-1,Sh.1 8.3-1-2ThisFigureHasBeenReplacedbyDrawingE-1,Sh.1A 8.3-1-2aThisFigureHasBeenReplacedbyDrawingE-1,Sh.2 8.3-2ThisFigureHasBeenReplacedbyDrawingE-4,Sh.2 8.3-2APreferredPowerSuppliestoDieselGeneratorEClass1EPowerSystem 8.3-3ThisFigureHasBeenReplacedbyDrawingE-5,Sh.1 8.3-4ThisFigureHasBeenReplacedbyDrawingE-5,Sh.2 8.3-4AThisFigureHasBeenReplacedbyDrawingE-5,Sh.5 8.3-5ThisFigureHasBeenReplacedbyDrawingE-11,Sh.1 8.3-5AThisFigureHasBeenReplacedbyDrawingE-11,Sh.11 8.3-6ThisFigureHasBeenReplacedbyDrawingE-13,Sh.1 8.3-7ThisFigureHasBeenReplacedbyDrawingE-8,Sh.4 8.3-8ThisFigureHasBeenReplacedbyDrawingE-8,Sh.8 8.3-9480VoltSwingBuses 8.3-10ThisFigureHasBeenReplacedbyDrawingM-260,Sh.1 8.3-10AThisFigureHasBeenReplacedbyDrawingM-261,Sh.1 SSES-FSARTOCRev.60CHAPTER8FIGURESNumberTitleFSARRev.658-ix8.3-10BThisFigureHasBeenReplacedbyDrawingM-5200,Sh.18.3-11ThisFigureHasBeenReplacedbyDrawingE-31,Sh.8 8.3-12ThisFigureHasBeenReplacedbyDrawingE-31,Sh.9 8.3-13SingleLineDiagramfor480VoltSwingBusSystem 8.3-14SwingBusAutoTransforSwitchControlSchematic 8.3-15ThisFigureHasBeenReplacedbyDrawingE-31,Sh.5

SSES-FSARTOCRev.61FSARRev.6510-iCHAPTER10STEAMANDPOWERCONVERSIONSYSTEMTABLEOFCONTENTSTEXTSectionTitle10.1

SUMMARY

DESCRIPTION 10.2TURBINE-GENERATOR 10.2.1DesignBases 10.2.2Description 10.2.2.1Turbine10.2.2.2GeneratorandExciter10.2.2.3ProtectiveValvesFunctions10.2.2.4ExtractionSystemCheckValves10.2.2.5ControlSystem10.2.2.6OverspeedProtection10.2.2.7TurbineShellDiaphragms10.2.2.8Turbine-GeneratorLoadFollowingCapability10.2.3TurbineDiskIntegrity 10.2.3.1MaterialSelection10.2.3.2FractureToughness10.2.3.3High-TemperatureProperties10.2.3.4TurbineDesign10.2.3.5Pre-serviceInspection10.2.3.6InserviceInspection10.2.4Evaluation 10.2.5References 10.3MAINSTEAMSUPPLYSYSTEM 10.3.1DesignBases 10.3.2Description10.3.3Evaluation SSES-FSARTOCRev.61CHAPTER10TEXTSectionTitleFSARRev.6510-ii10.3.4InspectionandTestingRequirements10.3.5WaterChemistry(PWR) 10.3.6SteamandFeedwaterSystemMaterials 10.3.6.1FractureToughness10.3.6.2MaterialSelectionandFabrication10.4OTHERFEATURESOFTHESTEAMANDPOWERCONVERSIONSYSTEM10.4.1MainCondenser 10.4.1.1DesignBases10.4.1.2Description 10.4.1.3SafetyEvaluation10.4.1.3.1RadioactiveGases10.4.1.3.2CondenserLeakage10.4.1.3.3CirculatingWaterSystemRupture10.4.1.4TestsandInspections10.4.1.5ControlsandInstrumentation10.4.1.5.1Condenser10.4.1.5.2CondensateContamination10.4.2MainCondenserEvacuationSystem 10.4.2.1DesignBases10.4.2.2SystemDescription10.4.2.3SafetyEvaluation10.4.2.4TestsandInspections10.4.2.5ControlsandInstrumentation10.4.3SteamSealSystem 10.4.3.1DesignBases10.4.3.2Description10.4.3.3SafetyEvaluation SSES-FSARTOCRev.61CHAPTER10TEXTSectionTitleFSARRev.6510-iii10.4.3.4TestsandInspections10.4.3.5ControlsandInstrumentation10.4.4TurbineBypassSystem 10.4.4.1DesignBases10.4.4.2SystemDescription10.4.4.3SafetyEvaluation10.4.4.4TestsandInspections10.4.4.5ControlsandInstrumentation10.4.5CirculatingWaterSystem 10.4.5.1DesignBases10.4.5.2SystemDescription10.4.5.3SafetyEvaluation10.4.5.4TestsandInspections 10.4.5.5ControlsandInstrumentation10.4.6CondensateCleanupSystem 10.4.6.1DesignBases10.4.6.2SystemDescription10.4.6.2.1CondensateDemineralizers10.4.6.2.2SupportingSystems10.4.6.3SafetyEvaluation10.4.6.4TestsandInspections10.4.6.5ControlsandInstrumentation10.4.7CondensateandFeedwater 10.4.7.1DesignBases10.4.7.2SystemDescription10.4.7.3SafetyEvaluation10.4.7.4TestsandInspections10.4.7.5ControlsandInstrumentation10.4.8SteamGeneratorBlowdownSystem(PWR) 10.4.9AuxiliaryFeedwaterSystem(PWR)

SSES-FSARTOCRev.61CHAPTER10TEXTSectionTitleFSARRev.6510-iv10.4.10ExtractionSteamandFeedwaterHeaterDrainandVentSystem10.4.10.1DesignBasis10.4.10.2SystemDescription10.4.10.3SafetyEvaluation10.4.10.4TestsandInspections10.4.10.5ControlsandInstrumentation10.4.11AuxiliarySteamSystem 10.4.11.1DesignBases10.4.11.2SystemDescription10.4.11.3SafetyEvaluation10.4.11.4TestandInspections10.4.11.5InstrumentationApplication SSES-FSARTOCRev.61CHAPTER10TABLESNumberTitleFSARRev.6510-v10.1-1Unit1-SummaryofTypicalDesignandPerformanceCharacteristicsofPowerConversionSystem10.1-1aUnit2-SummaryofTypicalDesignandPerformanceCharacteristicsofPowerConversionSystem10.2-1TurbineOverspeedProtection 10.4-1CondenserDesignParameters 10.4-2ThisTableHasBeenDeleted 10.4-3CirculatingWaterQualityDesignParametersUsedfortheCondensateCleanup10.4-4ThisTableHasBeenDeleted10.4-5ThisTableHasBeenDeleted10.4-6DesignConditionsforFeedwaterHeaters SSES-FSARTOCRev.61CHAPTER10FIGURESNumberTitleFSARRev.6510-vi10.1-1ThisFigureHasBeenDeleted10.1-1aGuaranteedFlowUnit1 10.1-1bGuaranteedFlowUnit2 10.1-2ThisFigureHasBeenDeleted 10.1-2aValvesWideOpen(VWO)Unit1 10.1-2bValvesWideOpen(VWO)Unit2 10.2-1TurbineStopValveClosureCharacteristic 10.2-2TurbineControlValveFastClosureCharacteristic 10.2-3MechanicalOverspeedTrip 10.2-4ThisFigurehasbeenreplacedbyDwg.M2H-54,Sh.1 10.2-5ThisFigurehasbeenreplacedbyDwg.M2J-101,Sh.5 10.2-6RateSensitivePower/LoadUnbalanceCircuit 10.2-7ThisFigureHasBeenDeleted 10.2-8ThisFigureHasBeenDeleted 10.2-9ThisFigureHasBeenDeleted 10.2-10ThisFigureHasBeenDeleted 10.2-11BulkHydrogenSystem 10.4-1-1ThisFigurehasbeenreplacedbyDwg.M-101,Sh.1 10.4-1-1aThisFigurehasbeenreplacedbyDwg.M-2101,Sh.1 SSES-FSARTOCRev.61CHAPTER10FIGURESNumberTitleFSARRev.6510-vii10.4-1-2ThisFigurehasbeenreplacedbyDwg.M-101,Sh.210.4-1-2aThisFigurehasbeenreplacedbyDwg.M-2101,Sh.2 10.4-1-3ThisFigurehasbeenreplacedbyDwg.M-101,Sh.3 10.4-1-3aThisFigurehasbeenreplacedbyDwg.M-2101,Sh.3 10.4-2ThisFigureHasBeenRenumberedTo10.4-2-1 10.4-2-1ThisFigurehasbeenreplacedbyDwg.M-116,Sh.1 10.4-2-2ThisFigurehasbeenreplacedbyDwg.M-116,Sh.2 10.4-2-3ThisFigurehasbeenreplacedbyDwg.M-116,Sh.3 10.4-3ThisFigureHasBeenRenumberedTo10.4-2-2 10.4-4ThisFigureHasBeenDeleted 10.4-4-1ThisFigurehasbeenreplacedbyDwg.M-105,Sh.1 10.4-4-2ThisFigurehasbeenreplacedbyDwg.M-105,Sh.2 10.4-4-3ThisFigurehasbeenreplacedbyDwg.M-105,Sh.3 10.4-4-4ThisFigurehasbeenreplacedbyDwg.M-105,Sh.4 10.4-5ThisFigureHasBeenRenumberedTo10.4-5-1 10.4-5-1ThisFigurehasbeenreplacedbyDwg.M-106,Sh.1 10.4-5-2ThisFigurehasbeenreplacedbyDwg.M-106,Sh.2 10.4-5-2AThisFigurehasbeenreplacedbyDwg.M-2106,Sh.2 10.4-5-3ThisFigurehasbeenreplacedbyDwg.M-106,Sh.3 10.4-5-3AThisFigurehasbeenreplacedbyDwg.M-2106,Sh.3 SSES-FSARTOCRev.61CHAPTER10FIGURESNumberTitleFSARRev.6510-viii10.4-5-4ThisFigurehasbeenreplacedbyDwg.M-106,Sh.410.4-5-4AThisFigurehasbeenreplacedbyDwg.M-2106,Sh.4 10.4-5-5ThisFigurehasbeenreplacedbyDwg.M-106,Sh.5 10.4-6-1ThisFigurehasbeenreplacedbyDwg.M-102,Sh.1 10.4-6-1aThisFigurehasbeenreplacedbyDwg.M-2102,Sh.1 10.4-6-2ThisFigurehasbeenreplacedbyDwg.M-102,Sh.2 10.4-6-2aThisFigurehasbeenreplacedbyDwg.M-2102,Sh.2 10.4-6-3ThisFigurehasbeenreplacedbyDwg.M-102,Sh.3 10.4-6-3aThisFigurehasbeenreplacedbyDwg.M-2102,Sh.3 10.4-7ThisFigurehasbeenreplacedbyDwg.M-103,Sh.1 10.4-8ThisFigurehasbeenreplacedbyDwg.M-104,Sh.1 10.4-9ThisFigureHasBeenRenumberedTo10.4-9-1 10.4-9-1ThisFigurehasbeenreplacedbyDwg.M-107,Sh.1 10.4-9-2ThisFigurehasbeenreplacedbyDwg.M-107,Sh.2 10.4-9-3ThisFigurehasbeenreplacedbyDwg.M-107,Sh.3 10.4-9-4ThisFigurehasbeenreplacedbyDwg.M-107,Sh.4 SSES-FSARTOCRev.59FSARRev.6511-iCHAPTER11RADIATIONWASTEMANAGEMENTTABLEOFCONTENTSTEXTSectionTitle11.1SOURCETERMS 11.1.1FissionProducts 11.1.1.1NobleRadiogasFissionProducts11.1.1.2RadiohalogenFissionProducts11.1.1.3OtherFissionProducts11.1.1.4Nomenclature11.1.2ActivationProducts 11.1.2.1CoolantActivationProducts11.1.2.2NoncoolantActivationProducts11.1.3Tritium 11.1.4CoreInventory,FuelExperienceandDepressurizationSpiking 11.1.4.1CoreInventory11.1.4.2FuelExperience11.1.4.3DepressurizationSpiking11.1.5ProcessLeakageSources 11.1.6OtherReleases 11.1.7References 11.2LIQUIDWASTEMANAGEMENTSYSTEMS 11.2.1DesignBases 11.2.2SystemDescriptions 11.2.2.1General11.2.2.2LiquidRadwasteProcessingSubsystem SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-ii11.2.2.3LiquidRadwasteChemicalProcessingSubsystem11.2.2.4LiquidRadwasteLaundryDrainProcessingSubsystem11.2.3RadioactiveReleases 11.2.4EstimatedDoses 11.3GASEOUSWASTEMANAGEMENTSYSTEMS 11.3.1DesignBases11.3.2SystemDescriptions11.3.2.1OffgasSystem 11.3.2.1.1ProcessFlowDescription 11.3.2.1.2ActivatedCarbonHoldupTime 11.3.2.1.3DetonationResistance 11.3.2.2ComponentDescription 11.3.2.2.1RecombinerSystem11.3.2.2.2ActivatedCarbonAdsorberSystem11.3.2.2.3InletHEPAFilter11.3.2.2.4WaterRemoval/TemperatureReductionAssembly11.3.2.2.5GuardBeds11.3.2.2.6MainCharcoalAdsorberBed11.3.2.2.7OutletHEPAFilter11.3.2.2.8InstrumentationandControl11.3.2.2.9LeakageofGasesfromOffgasSystem11.3.2.3TypicalOperatingModes 11.3.2.3.1Standby11.3.2.3.2Prestart11.3.2.3.3NormalOperation11.3.2.3.4Startup11.3.2.3.5EquipmentMalfunction11.3.2.4OtherRadioactiveGasSources SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-iii11.3.2.4.1PrimaryandSecondaryContainment11.3.2.4.2RadwasteBuilding11.3.2.4.3TurbineBuilding11.3.3RadioactiveReleases 11.3.4EstimatedDoses 11.3.5References11.4SOLIDWASTEMANAGEMENTSYSTEM11.4.1DesignBases 11.4.2SystemDescription 11.4.2.1General11.4.2.2WetSolidWastes11.4.2.3DrySoildWaste11.4.3References 11.5PROCESSANDEFFLUENTRADIOLOGICALMONITORINGANDSAMPLINGSYSTEMS11.5.1DesignBases 11.5.1.1DesignObjectives11.5.1.2DesignCriteria11.5.2ProcessandEffluentRadiologicalMonitoringSystemDescription 11.5.2.1ContinuousProcessandEffluentMonitorSystems 11.5.2.1.1ReactorBuildingVentStackExhaustMonitorandSampleRMS11.5.2.1.2TurbineBuildingandRadwasteVentStackExhaustMonitorandSampleRMS11.5.2.1.3StandbyGasTreatmentSystemVentStackExhaustMonitorandSampleRMS11.5.2.1.4StandbyGasTreatmentVentExhaustRadiationMonitoringSystem11.5.2.1.5RefuelingFloorWallExhaustDuctRadiationMonitoringSystem SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-iv11.5.2.1.6RefuelingFloorExhaustDuctHighRadiationMonitoringSystemMonitoringSystem(Unit1Only)11.5.2.1.7RailroadAccessExhaustDuctRadiationMonitoringSystem(Unit1only)11.5.2.1.8ControlStructureOutsideAirIntakeRadiationMonitoringSystem11.5.2.1.9LiquidRadwasteEffluentRMSDHRemovalRadiationMonitoringSystem11.5.2.1.10ServiceWaterDischarge/SupplementalDHRemovalRadiationMonitoringSystem11.5.2.1.11OffgasPretreatmentRadiationMonitoringSystem11.5.2.1.12MainSteamlineRadiationMonitoringSystem11.5.2.1.13RHRServiceWaterRadiationMonitoringSystem11.5.2.1.14ReactorBuildingClosedCoolingWaterRadiationMonitoringSystem11.5.2.2RoutineSampling11.5.2.2.1AnalyticalProcedures11.5.3EffluentMonitoringandSampling 11.5.3.1ContainmentAtmosphere11.5.3.2ReactorBuilding11.5.3.3EffluentDischargePaths11.5.3.4PlantEnvironsMeasurement11.5.4ProcessMonitoringandSampling 11.5.4.1ProcessMonitoringandSamplingSystems 11.5.4.1.1PlantRadwasteEffluentRMS11.5.4.1.2ServiceWaterDischarge/SupplementalDHRemovalRMS11.5.4.1.3OffgasPretreatmentRMS11.5.4.1.4MainSteamlineRMS11.5.4.1.5RHRServiceWaterRMSMonitoringSystem11.5.4.1.6ReactorBuildingClosedCoolingWaterRMS11.5.4.2RadioactiveWasteProcessMonitoringandSamplingSystems11.6LOWLEVELRADWASTEHOLDINGFACILITY(LLRWHF) 11.6.1DesignBasis 11.6.2LowLevelRadwasteHoldingFacilityDescription 11.6.3LLRWHFWasteDescriptionandCapacity SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-v11.6.4LLRWHFSourceTerm11.6.5Containers 11.6.6ContainerShieldingforTransportandStorage 11.6.7CraneLoadingandUnloadingSystem11.6.7.1LLRWHF30-TonCraneOperation11.6.7.2LinerStorageinVault11.6.7.3LinerRetrievalinVault11.6.7.4MobileCraneOperation11.6.8HealthandSafetyRequirements 11.6.9FloorDrainSystem 11.6.10LLRWHFHVACSystem11.6.10.1GeneralFunctionsandControls11.6.10.2StorageAreaVentilationSystem11.6.10.3ControlRoomHVACSystem11.6.10.4BatteryChargingStationHeatingandVentilatingSystem11.6.10.5SprinklerValveHouseHeatingSystems11.6.10.6TruckBayVehicleFumeExhaustSystem11.6.10.7InspectionStationVentilation11.6.10.8AirInlets11.6.11EffluentMonitoring 11.6.12ElectricalSystems 11.6.12.1480VoltDistributionSystem11.6.12.2GroundingSystem11.6.12.3LightingSystem11.6.12.4CommunicationSystem11.6.12.5CableandRacewaySystem11.6.13ControlPanels 11.6.14RadiationZoning 11.6.15RadiationMonitoringSystem SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-vi11.6.16Shielding11.6.17Security 11.6.18FireProtectionSystemOperatingDescription 11.6.18.1DryPipeSprinklerSystems11.6.18.2InfraRedSmokeDetectionSystems11.6.18.3PhotoElectricSmokeDetectionSystem11.6.18.4TruckBaySmokeDetectionSystem11.6.18.5FireAlarmSystem11.6.19ExposuretoOperatingPersonnel 11.6.20EnvironmentalConsequencesofOperationoftheLow-LevelRadioactiveWasteHoldingFacility11.6.21LinerInspections 11.6.22SafetyAnalysis 11.6.22.1HandlingandStorageAccidents 11.6.22.1.1ContainerDropfromaTransportVehicle11.6.22.1.2HandlingandStorageAccidentsInsidetheDawStorageVaultandOpenArea11.6.22.1.3DroppingaHeavyComponentOntotheSolidifiedWasteStorageVault11.6.22.1.4DroppingaLLRWContainerIntoSolidifiedWasteStorageCell11.6.22.1.5Collisions-SolidifiedWasteContainerHandling11.6.22.1.6ShieldedLinerStorageModuleAccidents11.6.22.2OtherAccidents 11.6.22.2.1Fires11.6.22.2.2Freezes11.6.22.2.3Tornadoes11.6.22.2.4FloodsandSeismicEvents11.6.22.2.5Sabotage11.6.22.2.6LossofOff-SitePower11.6.22.3Summary SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-vii11.6.23References11.7INDEPENDENTSPENTFUELSTORAGEINSTALLATION(ISFSI) 11.7.1DesignBasis11.7.2NUHOMSHorizontalModularDryStorageSystemDescription(NUHOMSSystem)11.7.3ISFSISourceTerms11.7.3.1RadiationSourceTerm 11.7.3.2AirborneRadioactiveMaterialSourceTerm11.7.4DryShieldedCanister(DSC) 11.7.5HorizontalStorageModule(HSM) 11.7.6TransportEquipment11.7.6.1On-SiteTransferCask11.7.6.2.TransferTrailer11.7.7NUHOMSSystemOperation11.7.7.1On-SiteTransferCask(TC)Preparation11.7.7.2PlacementofDSCinCask11.7.7.3FillTC/DSCAnnuluswithWaterandSeal11.7.7.4TCMovementtotheCaskStoragePit11.7.7.5DSCSpentFuelLoading11.7.7.6DSCTopShieldPlugPlacement11.7.7.7LiftingTCfromPool11.7.7.8InnerDSCTopCoverPlate11.7.7.9DSCDryingandBackfilling11.7.7.10OuterDSCTopCoverPlate11.7.7.11TC/DSCAnnulusDrainingandTooCoverPlatePlacement11.7.7.12PlacementofTConTransferTrailer11.7.7.13TransportofTCtoHSM11.7.7.14TC/HSMPreparation11.7.7.15LoadingDSCintoHSM11.7.7.16SpentFuelStorage11.7.7.17SpentFuelRetrieval SSES-FSARTOCRev.59CHAPTER11TEXTSectionTitleFSARRev.6511-viii11.7.8RadiologicalAssessment11.7.8.1Introduction11.7.8.2Dose11.7.8.3ISFSIControlledArea11.7.8.4FullyLoadedISFSIDoseAssessment11.7.9SiteSpecificEvaluations11.7.9.1AverageAmbientAirTemperatureandTemperatureExtremes11.7.9.2EarthquakeIntensity/SeismicAcceleration11.7.9.3Flooding11.7.9.4TornadoWindPressureandMissiles 11.7.9.5Snow11.7.9.6Lightning11.7.9.7FireandExplosion11.7.10HeavyLoads 11.7.11AuxiliarySystems11.7.11.1ElectricalSystems11.7.11.2Instrumentation SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-ix11.1-1NobleRadiogasSourceTerms11.1-2HalogenRadioisotopesinReactorWaterandSteam 11.1-3OtherFissionProductRadioisotopesinReactorWater 11.1-4CoolantActivationProductsinReactorWaterandSteam 11.1-5NoncoolantActivationProductsinReactorWater 11.1-6DepressurizationSpikingActivity95thPercentileCumulativeProbability 11.2-1ExpectedDailyInputsandActivitiestotheLiquidWasteManagementSystemFromTwoUnits11.2-2ExpectedBatchedInputstotheLiquidRadwasteSystemFromtheSolidRadwasteSystemForNormalOperationofTwoUnits11.2-3LiquidWasteManagementSystemComponentDescription 11.2-4LiquidRadwasteSystemFlows(RefertoFig.11.2-8) 11.2-5ExpectedRadionuclideActivityInventoriesofLiquidRadwasteSystemComponents(CuriesPerComponent)(2)(3)11.2-6DesignBasisRadionuclideActivityInventoriesofLiquidRadwasteSystemComponents(CuriesPerComponent)(2)(3)11.2-7ThisTableHasBeenDeleted11.2-8AssumptionsandParametersUsedForEvaluationofRadioactiveReleases 11.2-9ExpectedRadionuclideActivityConcentrationsInReactorCoolantandMainSteamUsedForEvaluationofRadioactiveReleases(1)11.2-10RadwasteSystemFlowRatesandStreamActivitiesUsedforEvaluationofRadioactiveReleases SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-x11.2-11ExpectedHoldupTimesForCollection,Processing,andDischargeUsedforEvaluationofRadioactiveReleases11.2-12DecontaminationFactorsUsedForEvaluationofRadioactiveReleases 11.2-13ExpectedYearlyActivityReleasedFromLiquidRadwasteManagementSystemsUsedForEvaluationofComplianceWithAppendixIof10CFR50(Ci/yr/site)11.2-14CalculatedExpectedEffluentActivityConcentrationsforEvaluationofRadioactiveReleasestotheSusquehannaRiver11.2-15InputDataforAquaticDoseCalculations 11.2-16TanksOutsidePrimaryContainmentWhichContainPotentiallyRadioactiveLiquids(1)11.3-1AnnualGaseousReleasesPerUnit11.3-2AssumptionsandParametersUsedForEvaluationofGaseousReleases 11.3-3Thistablehasbeendeleted 11.3-4FilterTrainsUsedtoControlGaseousEffluents 11.3-5OffGasSystemMajorEquipmentDescription 11.3-6OffGasSystemEquipmentMalfunctionAnalysis 11.3-7InputDataForAtmosphericDoseCalculations 11.3-8OffGasSystemFlows(RefertoFig.11.3-1)(PPH1SCFM) 11.3-9Thistablehasbeendeleted 11.3-10ComparisonofIndividualDosesfromExpectedGaseousEffluentReleaseswith10CFR50,AppendixIDesignObjectives11.3-11ComparisonofExpectedRadionuclideConcentrationsintheEnvironmentfromRoutineAtmosphericReleasesto10CFR20Limits SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-xi11.4-1InputstotheSolidRadwasteCollectionSystemForBothUnits11.4-2DrySolidWasteAmountFromGas,LaundryDrainFilters,andMaintenanceActivities11.4-3SolidWasteManagementSystemComponentDescription 11.4-4SolidWasteManagementSystemFlows(RefertoFig.11.4-3) 11.4-5ExpectedInventoriesofRadioactiveMaterialsinComponentsoftheSolidRadwasteSystem(2)11.4-6DesignInventoriesofRadioactiveMaterialsinComponentsoftheSolidWasteManagementSystem(Curies)(2)11.4-7ThisTableHasBeenDeleted11.4-8ThisTableHasBeenDeleted 11.4-9ExpectedInventoriesOfRadioactiveMaterialsInWasteShippingCasks 11.4-10DesignInventoriesOfRadioactiveMaterialsInWasteShippingCasks(1,2)11.5-1ProcessandEffluentRadiationMonitoringSystems 11.5-2RadiologicalAnalysisSummaryofRoutineEffluentSampling 11.5-3CompositionandConcentrationofNuclidesinRoutineEffluentSamples 11.6-1DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoaContainerDropfromaTransportVehicle(Reference11.6-7)11.6-2DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoDroppingaHeavyComponentOntotheSolidifiedWasteStorageVault(Reference11.6-11)11.6-3DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoanUnspecifiedIncendiaryEventInvolving100%ofDAW(Reference11.6-4)

SSES-FSARTOCRev.59CHAPTER11TABLESNumberTitleFSARRev.6511-xii11.6-4DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoLossofOff-SitePowertotheLLRWHF(Reference11.6-5)11.6-5DesignBasisSourcesandAssumptionsUsedtoCalculatetheOff-SiteRadiologicalConsequencesDuetoMobileShieldedStorageModuleWithoutLid(Reference11.6-6)

SSES-FSARTOCRev.59CHAPTER11FIGURESNumberTitleFSARRev.6511-xiii11.1-1NobleRadiogasDecayConstantExponentFrequencyHistogram11.1-2RadiohalogenDecayConstantExponentFrequencyHistogram 11.1-3NobelRadiogasVersusI-131Leakage 11.2-1ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-39 11.2-2ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-40 11.2-3ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-41 11.2-4ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-42 11.2-5ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-43 11.2-6ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-1 11.2-7ThisFigureHasBeenDeletedBecauseOfDuplicationSeeFigure1.2-9 11.2-8LiquidRadwasteManagementSystemFlowDiagram 11.2-9ThisFigureHasBeenRenumberedto11.2-9-1 11.2-9-1ThisFigurehasbeenreplacedbyDwg.M-162,Sh.1 11.2-9-2ThisFigurehasbeenreplacedbyDwg.M-162,Sh.2 11.2-9-3ThisFigurehasbeenreplacedbyDwg.M-162,Sh.3 11.2-10ThisFigureHasBeenRenumberedto11.2-9-2 11.2-11ThisFigureHasBeenRenumberedto11.2-11-1 11.2-11-1ThisFigurehasbeenreplacedbyDwg.M-163,Sh.1 11.2-11-2ThisFigurehasbeenreplacedbyDwg.M-163,Sh.2 11.2-11-3ThisFigurehasbeenreplacedbyDwg.M-163,Sh.3 SSES-FSARTOCRev.59CHAPTER11FIGURESNumberTitleFSARRev.6511-xiv11.2-12ThisFigurehasbeenreplacedbyDwg.M-164,Sh.111.2-13LiquidWasteManagementScheme 11.2-14TypicalMobileProcessingSystemFlowDiagram 11.3-1OffgasSystemProcessFlowDiagram 11.3-2AThisFigureHasBeenRenumberedto11.3-2A-1 11.3-2A-1ThisFigurehasbeenreplacedbyDwg.M-169,Sh.1 11.3-2A-2ThisFigurehasbeenreplacedbyDwg.M-169,Sh.2 11.3-2A-3ThisFigurehasbeenreplacedbyDwg.M-169,Sh.3 11.3-2A-4ThisFigurehasbeenreplacedbyDwg.M-169,Sh.4 11.3-2BThisFigureHasBeenRenumberedto11.3-2A-2 11.3-2CThisFigureHasBeenRenumberedto11.3-2C-1 11.3-2C-1ThisFigurehasbeenreplacedbyDwg.M-2169,Sh.1 11.3-2C-2ThisFigurehasbeenreplacedbyDwg.M-2169,Sh.2 11.3-2DThisFigureHasBeenRenumberedto11.3-2D-1 11.3-2D-1ThisFigurehasbeenreplacedbyDwg.M-2171,Sh.1 11.3-2D-2ThisFigurehasbeenreplacedbyDwg.M-2171,Sh.2 11.3-3ThisFigureHasBeenRenumberedto11.3-3-1 11.3-3-1P&IDAmbientTemperatureCharcoalOffgasTreatmentSystem 11.3-3-2P&IDAmbientTemperatureCharcoalOffgasTreatmentSystem 11.3-4ReleasePointsLocationsandDetails 11.4-1ThisFigureHasBeenRenumberedto11.4-1-1 SSES-FSARTOCRev.59CHAPTER11FIGURESNumberTitleFSARRev.6511-xv11.4-1-1ThisFigurehasbeenreplacedbyDwg.M-166,Sh.111.4-1-2ThisFigurehasbeenreplacedbyDwg.M-166,Sh.2 11.4-2ThisFigureHasBeenRenumberedto11.4-2-1 11.4-2-1ThisFigurehasbeenreplacedbyDwg.M-167,Sh.1 11.4-2-2ThisFigurehasbeenreplacedbyDwg.M-167,Sh.2 11.4-3SolidWasteManagementSystemFlowDiagram 11.6-1ThisFigurehasbeenreplacedbyDwg.B1P-005,Sh.1 11.6-2ThisFigurehasbeenreplacedbyDwg.B1N-100,Sh.1 11.6-3ShieldBellAssembly 11.6-4ThisFigureHasBeenDeleted SSES-FSARTextRev.59FSARRev.6512-iCHAPTER12RADIATIONPROTECTIONTABLEOFCONTENTSTEXTSectionTitle12.1ENSURINGTHATOCCUPATIONALRADIATIONEXPOSURESAREASLOWASREASONABLYACHIEVABLE(ALARA)12.1.1PolicyConsiderations 12.1.1.1ManagementPolicy12.1.1.2ManagementResponsibilities12.1.1.3PolicyImplementation12.1.2DesignConsiderations 12.1.2.2EquipmentGeneralDesignConsiderationsforALARA12.1.2.3FacilityLayoutGeneralDesignConsiderationsforALARA12.1.2.4ALARADesignReview12.1.3OperationalConsiderations 12.1.3.1ProcedureDevelopment12.1.3.1.1ALARAProcedures12.1.3.1.2StationProcedures12.1.3.2StationOrganization12.1.3.3OperatingExperience12.1.3.4ExposureReduction12.1.4References 12.2RADIATIONSOURCES 12.2.1ContainedSources 12.2.1.1Drywell12.2.1.1.1ReactorCore12.2.1.1.2ReactorCoolantSystem 12.2.1.1.3PrimarySteamSystem12.2.1.2ReactorBuilding12.2.1.2.1ReactorWaterCleanupSystem SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-ii12.2.1.2.2SpentFuelHandlingandTransfer12.2.1.2.3ResidualHeatRemovalSystem12.2.1.2.4ReactorCoreIsolationCoolingSystem12.2.1.2.5HighPressureCoolantInjectionSystem12.2.1.2.6CoreSpraySystems12.2.1.3RefuelingFacilities12.2.1.3.1SpentFuelStorageandTransfer12.2.1.3.2SpentFuelPoolCoolingAndCleanupSystem12.2.1.4TurbineBuilding12.2.1.4.1PrimarySteamandPowerConversionSystems12.2.1.4.2CondensateSystem12.2.1.4.3OffgasSystemRecombiner12.2.1.5RadwasteBuilding12.2.1.5.1LiquidRadwasteSystems12.2.1.5.2SolidRadwasteSystem12.2.1.5.3AmbientCharcoalOffgasTreatmentSystem12.2.1.6SourcesResultingfromDesignBasisAccidents12.2.1.7SiteBoundaryN-16ShineDose12.2.1.8StoredRadioactivity12.2.1.9SpecialSources12.2.2AirborneRadioactiveMaterialSources 12.2.2.1SourcesofAirborneRadioactivity12.2.2.2ProductionofAirborneMaterials12.2.2.3LocationsofSourcesofAirborneRadioactivity12.2.2.4ControlofAirborneRadioactivity12.2.2.5MethodologyforEstimatingtheConcentrationofAirborneRadioactiveMaterialWithinthePlant12.2.2.6EstimationofTotalAirborneReleases12.2.2.7DistributionofAirborneReleases12.2.2.8EstimatedAirborneRadioactiveMaterial12.2.2.9ChangestoSourceDataSincePSAR12.3RADIATIONPROTECTIONDESIGNFEATURES 12.3.1FacilityDesignFeatures 12.3.1.1CommonEquipmentandComponentDesignsforALARA12.3.1.2CommonFacilityandLayoutDesignsforALARA SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-iii12.3.1.3RadiationZoningandAccessControl12.3.1.4ControlofActivatedCorrosionProducts12.3.2Shielding 12.3.2.1DesignObjectives12.3.2.2GeneralShieldingDesign12.3.2.2.1ReactorBuildingShieldingDesign12.3.2.2.2ReactorBuildingInteriorShieldingDesign12.3.2.2.3RadwasteBuildingShieldingDesign12.3.2.2.4TurbineBuildingShieldingDesign12.3.2.2.5ControlRoomShieldingDesign12.3.2.2.6DieselGeneratorBuildingShieldingDesign12.3.2.2.7MiscellaneousPlantAreasandPlantYardAreas12.3.2.2.8CountingRoomShielding12.3.2.3ShieldingCalculationalMethods12.3.3Ventilation 12.3.3.1DesignObjectives12.3.3.2DesignCriteria12.3.3.3DesignGuidelines12.3.3.3.1GuidelinestoMinimizeAirborneRadioactivity12.3.3.3.2GuidelinestoControlAirborneRadioactivity12.3.3.3.3GuidelinestoMinimizePersonnelExposurefromHVACEquipment12.3.3.4DesignDescription12.3.4AreaRadiationandAirborneRadioactivityMonitoringInstrumentation 12.3.4.1AreaRadiationMonitoring12.3.4.1.1CriteriaforAreaMonitorSelection12.3.4.1.2CriteriaforLocationofAreaMonitors12.3.4.1.3SystemDescription(AreaRadiationMonitoring)General12.3.4.1.4AreaRadiationMonitoringInstrumentation12.3.4.1.5SafetyEvaluation12.3.4.1.6CalibrationMethodandTestability12.3.4.2AirborneRadioactivityMonitoring12.3.5References SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-iv12.4DOSEASSESSMENT12.4.1DirectRadiationDoseEstimatesforExposuresWithinthePlant 12.4.1.1DefinitionofCategoriesUsedinExposureEstimates12.4.1.2ExposureEstimateMethodology12.4.1.3ResultsofAnnualDirectRadiationDoseEstimates12.4.1.3.1RoutineOperationsDoseEstimate12.4.1.3.2RoutineMaintenanceDoseEstimate12.4.1.3.3In-ServiceInspectionDoseEstimate12.4.1.3.4SpecialMaintenanceDoseEstimate12.4.1.3.5WasteProcessingDoseEstimate12.4.1.3.6RefuelingDoseEstimate12.4.1.3.7HealthPhysicsDoseEstimate12.4.1.3.8SummaryofDirectRadiationDoseEstimates12.4.1.3.9MethodsforEstimatingDoses12.4.2AirborneRadioactivityDoseEstimatesforExposuresWithinthePlant 12.4.3ExposuresatLocationsOutsidePlantStructures 12.4.3.1DirectRadiationDoseEstimatesOutsideStructures12.4.3.2AirborneRadioactivityDoseEstimatesOutsideStructures12.4.4References 12.5HEALTHPHYSICSPROGRAM 12.5.1Organization 12.5.1.1Introduction12.5.1.2HealthPhysicsOrganizationandResponsibilities12.5.1.3Authority12.5.1.4ExperienceandQualification12.5.2Facilities,Equipment,&Instrumentation 12.5.2.1HealthPhysicsFacilities12.5.2.1.1HealthPhysicsOfficeFacilities12.5.2.1.2ControlledZoneAccess/EgressFacilities12.5.2.1.3LocalChangeFacilities SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-v12.5.2.1.4DecontaminationFacilities12.5.2.1.4.1PersonnelDecontaminationFacilities12.5.2.1.4.2EquipmentDecontaminationFacilities12.5.2.1.5RespiratoryProtectionFacilities12.5.2.1.6LaundryFacilities12.5.2.1.7InstrumentationFacilities12.5.2.1.8CountRoomFacilities12.5.2.1.9Chemistry/RadiochemistryFacilities12.5.2.1.10RestrictedAreaAccess/EgressFacilities12.5.2.2HealthPhysicsEquipment12.5.2.2.1ProtectiveClothing12.5.2.2.2RespiratoryProtectiveEquipment12.5.2.2.3AirSamplingEquipment12.5.2.2.3.1ContinuousAirMonitors12.5.2.2.3.2PortableAirSamplers12.5.2.2.3.3BreathingZoneSamplers12.5.2.2.3.4SamplingMedia12.5.2.2.3.5SpecialAirSampling12.5.2.2.4PersonnelDosimetry12.5.2.2.5MiscellaneousEquipment12.5.2.3HealthPhysicsInstrumentation12.5.2.3.1CountingRoomInstrumentation12.5.2.3.2PortableRadiationSurvey/Monitoring12.5.2.3.3ContaminationInstrumentation12.5.2.3.4SpecialInstrumentation12.5.3Procedures 12.5.3.1ControlofAccessandStayTimein12.5.3.1.1PhysicalControls12.5.3.1.1.1SecurityCheckPoints12.5.3.1.1.2SecurityDoors12.5.3.1.1.3PostingandLocking12.5.3.1.1.4Surveillance12.5.3.1.2AdministrativeControls12.5.3.1.2.1Training12.5.3.1.2.2RadiationWorkPermit12.5.3.1.2.3ReportingRequirement12.5.3.1.2.4IndependentReview12.5.3.1.2.5ProcedureReview SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-vi12.5.3.2AssuringthatOccupationalRadiationExposure(ORE)willbeasLowasReasonablyAchievable(ALARA)12.5.3.2.1ALARAProceduresCommontoExternalandInternalExposure12.5.3.2.1.1Training12.5.3.2.1.2RadiationWorkPermit12.5.3.2.1.3WorkScheduling12.5.3.2.1.4ReportingRequirements12.5.3.2.1.5InternalProgramReviews12.5.3.2.1.6ExposureGoals12.5.3.2.1.7JobPre-Planning12.5.3.2.1.8Worker'sRecommendations12.5.3.2.1.9AdministrativeLimits12.5.3.2.2ExternalALARA12.5.3.2.2.1DoseRecording12.5.3.2.2.2CategorizationofExposures12.5.3.2.2.3WorkTimeEvaluation12.5.3.2.2.4SpecialAlarmsandInstruments12.5.3.2.2.5TemporaryShielding12.5.3.2.2.6SpecialToolsandApparatus12.5.3.2.3InternalALARA12.5.3.2.3.1EngineeringControls12.5.3.2.3.2RespiratoryProtection12.5.3.2.3.3PreWorkAirSurveys12.5.3.2.3.4SpecialAirSampling12.5.3.2.3.5RoutineAirSampling12.5.3.2.3.6ControlofAreaandEquipmentContaminationLevels12.5.3.2.3.7AirborneExposureEvaluation12.5.3.3RadiationSurveys12.5.3.3.1RadiationSurveyProgramControls12.5.3.3.1.1RecordReview12.5.3.3.1.2IndependentReviews12.5.3.3.1.3SurveyorWorkRotation12.5.3.3.1.4Training12.5.3.3.2RadiationSurveyProgram12.5.3.3.2.1InstrumentSelection12.5.3.3.2.2RoutineRadiationAreaSurveys12.5.3.3.2.3HighRadiationAreaSurveys12.5.3.3.2.4VeryHighRadiationAreaSurveys12.5.3.3.2.5Non-RadiationAreaSurveys12.5.3.3.2.6RadiationWorkPermitSurveys12.5.3.3.2.7SpecialRadiationSurveys SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-vii12.5.3.3.2.8RadiationSurveyRecords12.5.3.4ContaminationSurveyProcedures12.5.3.4.1PersonnelContaminationSurveys12.5.3.4.1.1FriskerSurvey12.5.3.4.1.2NasalSwab12.5.3.4.1.3IntakeProcedures12.5.3.4.1.4Wound,Cut,AbrasionSurveys12.5.3.4.2EquipmentContaminationSurveys12.5.3.4.2.1ContaminatedAreaEquipmentSurveys12.5.3.4.2.2PersonalItemSurveys12.5.3.4.2.3ProtectiveClothingSurveys12.5.3.4.2.4RespiratoryProtectionDeviceSurveys12.5.3.4.2.5SurveysInvolvingReceipt/ShipmentofRadioactiveMaterial12.5.3.4.3SurfaceContaminationSurveys12.5.3.4.3.1ControlledAccessAreas12.5.3.4.3.2Non-ControlledZoneAreas12.5.3.4.3.3Implementation,Review,andReportingPractices12.5.3.5AirborneRadioactiveMaterial12.5.3.5.1PhysicalControls12.5.3.5.1.1AirFlowPatterns12.5.3.5.1.2ContaminationConfinement12.5.3.5.1.3AirExhaust12.5.3.5.1.4PostingandLocking12.5.3.5.2AdministrativeControls12.5.3.5.2.1HealthPhysicsReview12.5.3.5.2.2HealthPhysicsInvestigation12.5.3.5.2.3RWPProcedures12.5.3.5.3AirSamplingEquipment12.5.3.5.4AirborneConcentrationSampling12.5.3.5.4.1RoutineSampling12.5.3.5.4.2SpecialAirSampling12.5.3.5.5AirSampleEvaluation12.5.3.5.5.1ParticulateInitialEvaluation12.5.3.5.5.2SubsequentParticulateEvaluations12.5.3.5.5.3GaseousEvaluations12.5.3.5.6RespiratoryProtection12.5.3.5.6.1TrainingandFitting12.5.3.5.6.2WrittenProcedures12.5.3.5.6.3SelectionofEquipment12.5.3.5.6.4IssueandUse SSES-FSARTextRev.59CHAPTER12TEXTSectionTitleFSARRev.6512-viii12.5.3.5.6.5Cleaning,Decontamination,Inspection,Maintenance,SanitizingandStorage12.5.3.5.6.6QualityControls12.5.3.5.6.7SurveillanceofWorkAreaConditions12.5.3.5.6.8EvaluationofProgramEffectiveness12.5.3.5.6.9MedicalSurveillance12.5.3.5.7HandlingofRadioactiveMaterial12.5.3.5.7.1UnsealedMaterial12.5.3.5.7.2SealedMaterials12.5.3.6PersonnelMonitoring12.5.3.6.1ExternalPersonnelMonitoring12.5.3.6.1.1PersonnelDosimetryEvaluation12.5.3.6.1.2AdministrativeExposureControl12.5.3.6.1.3MethodsofRecordingandReporting12.5.3.6.2InternalRadiationExposureAssessment12.5.3.6.2.1BioassayMethods12.5.3.6.2.2AdministrativeControls12.5.3.6.2.3CriteriaforParticipationorSelection12.5.3.6.2.4EvaluationandReporting12.5.3.7HealthPhysicsTrainingPrograms12.5.3.7.1ProgramControls12.5.3.7.1.1HealthPhysicsTrainingProgramReview12.5.3.7.1.2AccessControl12.5.3.7.1.3Retraining/ReplacementTraining12.5.3.7.2TrainingPrograms12.5.3.7.2.1LevelITraining12.5.3.7.2.2LevelIITraining12.5.3.7.2.3RespiratoryProtectionTraining12.5.3.7.2.4HealthPhysicsTechnicianInitialTrainingProgram12.5.3.7.2.5HealthPhysicsTechnicianRetrainingProgram SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-ix12.2-1BasicReactorData12.2-2CoreRegionDescriptionUsedinCalculationstoDetermineRadialFluxDistributionatReactorCoreMidplane12.2-3MaterialCompositiontoDetermineRadialFluxDistributionsatReactorCoreMidplane12.2-4CalculatedGammaRayandNeutronFluxesatOutsideSurfaceofRPV 12.2-5CalculatedGammaRayandNeutronFluxesatOutsideSurfaceofPrimaryShield12.2-6ReactorWaterCleanupSystemN-16ShieldingSourceTerms 12.2-7ReactorWaterCleanupFilterDemineralizerShieldingSourceTerms 12.2-8ReactorWaterCleanupBackwashReceivingTankShieldingSourceTerms12.2-9ThisTableHasBeenDeleted 12.2-9A1Activity(Curies)perFullCoreofATRIUM-10Fuel 12.2-9A2Activity(Curies)perSingleAssemblyofATRIUM-10Fuel 12.2-10ResidualHeatRemovalSystemShieldingSourceTerms 12.2-11SteamN-16ShieldingSourceTermsforTurbineandReactorBuildingEquipment12.2-12FuelPoolSystemShieldingSourceTerms 12.2-13FuelPoolFilterDemineralizerShieldingSourceTerms 12.2-14FuelPoolWaterCleanupBackwashReceivingTankShieldingSourceTerms12.2-15CondensateShieldingSourceTerms 12.2-16CondensateDemineralizerShieldingSourceTerms SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-x12.2-17Off-gasLinefromSJAEtoRecombinerShieldingSourceTerms12.2-18Off-gasPrimaryRecombinerShieldingSourceTerms 12.2-19Off-gasLinefromRecombinertoCharcoalSystemShieldingSourceTerms12.2-20CharcoalOff-gasSystemInlet-HEPAFilterShieldingSourceTerms 12.2-21Off-gasAmbientCharcoalFreonChillerShieldingSourceTerms12.2-22Off-gasCharcoalGuardBedShieldingSourceTerms 12.2-23Off-gasCharcoalBedsShieldingSourceTerms 12.2-24Off-gasPost-HEPAFilterShieldingSourceTerms 12.2-25Post-LOCAPrimaryContainmentActivity 12.2-26Post-LOCASecondaryContainmentActivity 12.2-27Post-LOCAStandbyGasTreatmentCharcoalFilterActivity 12.2-28IsotopicInventoryofN-16forTurbineOperatingFloorComponents 12.2-29CondensateStorageTankSourceTerms 12.2-30EstimatedAirborneRadioactiveReleasesPriortoTreatment(Curies/Year)12.2-31EstimatedDistributionofAirborneRadioactiveReleases 12.2-32TurbineBuildingAirborneSourceDescriptions 12.2-33ReactorBuildingAirborneSourceDescriptions 12.2-34RadwasteBuildingAirborneSourceDescriptions 12.2-35EstimatedAirborneConcentrationsintheTurbineBuildingandFractionofDACs SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-xi12.2-36EstimatedAirborneConcentrationsintheReactorBuildingandFractionofDACs12.2-37EstimatedAirborneConcentrationsintheRadwasteBuildingandFractionofDACs12.2-38TurbineBuildingShieldingDesignRadiationSourceDescription 12.2-39ReactorBuildingShieldingDesignRadiationSourceDescription 12.2-40RadwasteBuildingShieldingDesignRadiationSourceTerms 12.2-41MaterialCompositionoftheTIPSystemComponentsAsUsedinActivationCalculations12.2-42TraversingIncoreProbeDetectorDecayGammaActivitiesinMEV/Secof0.001gofU-23512.2-43TraversingIncoreProbeDetectorDecayGammaActivitiesofMaterialsintheDetector(ExcludingU-235)inMicrocuriesintheIrradiatedDetector12.2-44DecayGammaActivitiesofMaterialsintheCableinMicrocuriesperInchofIrradiatedCable.12.2-45UltrasonicResinCleanerShieldingSourceTerms 12.2-46CondensateFilterVesselShieldingSourceTerms 12.2-47CondensateFilterVesselBackwashShieldingSourceTerms 12.2-48CondensateFilterVesselBackwashReceivingTankShieldingSourceTerms12.3-1PlantRadiationZoneDescription 12.3-2ListofComputerCodesUsedinShieldingDesignCalculations 12.3-3Thistablehasbeendeleted SSES-FSARTextRev.59CHAPTER12TABLESNumberTitleFSARRev.6512-xii12.3-4Thistablehasbeendeleted12.3-5Thistablehasbeendeleted 12.3-6Thistablehasbeendeleted 12.3-7AreaRadiationMonitoringSystem 12.4-1SummaryofHistoricalDataUsedinCompilationofExposuresReceivedatOperatingBoilingWaterReactors12.4-2OccupationalExposuresByJobFunctionforOperatingBoilingWaterReactors12.4-3ExposureEstimatesfortheTurbineBuildingandControlStructure 12.4-4ExposureEstimatesfortheReactorBuilding 12.4-5ExposureEstimatesfortheRadwasteBuilding 12.4-6EstimatedExposureforOperatorsinResidenceinControlRooms 12.4-7SummaryofRoutineOperationsExposureEstimate 12.4-8EstimateofExpectedMaintenanceMan-hoursforVariousTypesofEquipment12.4-9SummaryofIn-PlantDirectRadiationExposureEstimates 12.4-10EstimatedTurbineBuildingInhalationExposuresDuetoAirborneRadioactivity12.4-11EstimatedReactorBuildingInhalationExposuresDuetoAirborneRadioactivity12.4-12EstimatedRadwasteBuildingInhalationExposuresDuetoAirborneRadioactivity12.4-13ThisTableHasBeenDeleted SSES-FSARTextRev.59CHAPTER12FIGURESNumberTitleFSARRev.6512-xiii12.3-1TypicalShieldingArrangementforLiquidRadwasteFiltersandValveGallery12.3-2TypicalShieldingArrangementforRadwasteDemineralizer 12.3-3TypicalShieldingArrangementforCharcoalandParticulateFilter 12.3-4TypicalShieldingArrangementforOff-gasRecombiners 12.3-5TypicalShieldingArrangementforRadwasteTanksandPumps 12.3-6TypicalShieldingArrangementforRadwasteEvaporator 12.3-7TypicalShieldingArrangementforSampleStation 12.3-8ShieldingandRadiationZoningDrawingControlBuildingEL.656'-0"to714'-0"12.3-9ShieldingandRadiationZoningDrawingControlBuildingEL.729'-1"to783'-0"12.3-10ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.656'-0"12.3-11ShieldingandRadiationZoningDrawingTurbineBuildingEL.676'-0" 12.3-12ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.699'-0"12.3-13ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.714'-0"12.3-14ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.729'-0"12.3-15ShieldingandRadiationZoningDrawingTurbineBuilding-Unit1EL.762'-0"12.3-16ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.645-'0" SSES-FSARTextRev.59CHAPTER12FIGURESNumberTitleFSARRev.6512-xiv12.3-17ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.670'-0"12.3-18ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.683'-0"12.3-19ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.719'-0"12.3-20ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.749'-1"12.3-21ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.779'-1"12.3-22ShieldingandRadiationZoningDrawingReactorBuildingEL.799'-1" 12.3-23ShieldingandRadiationZoningDrawingReactorBuilding-Unit1EL.818'-1"12.3-24ShieldingandRadiationZoningDrawingRadwasteBuildingEL.646'-0" 12.3-25ShieldingandRadiationZoningDrawingRadwasteBuildingEL.660'-0" 12.3-26ShieldingandRadiationZoningDrawingRadwasteBuilding-Unit1EL.676'-0"12.3-27ShieldingandRadiationDrawingRadwasteBuildingEL.691'-6" 12.3-28LLRWHoldingFacilityInterimRadiationZoningandAreaRadiationMonitorLocations12.3-29ScaledIsometricofControlBuildingwithRelationshiptoContainment 12.3-30-1P&IDAreaRadiationMonitoringandMeteorologicalInstruments 12.3-30-2P&IDAreaRadiationMonitoringandMeteorologicalInstruments 12.4-1EstimatedTurbineShineDoseRates 12.5-1HealthPhysicsOrganization SSES-FSAR TOC Rev. 61 FSAR Rev. 68 13-i CHAPTER 13 CONDUCT OF OPERATIONS TABLE OF CONTENTS TEXT Section Title

13.1 ORGANIZATIONAL STRUCTURE

13.1.1 Management and Technical Support Organization

13.1.1.1 Design and Operating Responsibilities 13.1.1.1.1 Design and Construction Activities (Project Phase) (HISTORICAL) 13.1.1.1.2 Preoperational Activities (HISTORICAL) 13.1.1.1.3 Technical Support for Operations: General Office Personnel Responsibilities and Authorities 13.1.1.2 Organizational Arrangement: General Office 13.1.1.3 Qualification Requirements for Personnel in the Off-Site Organization

13.1.2 Operating Organization

13.1.2.1 Plant Organization 13.1.2.2 Plant Personnel Responsibilities and Authorities 13.1.2.3 Operating Shift Crews

13.1.3 Qualification Requirements for Nuclear Plant (On-Site) Personnel

13.1.3.1 Minimum Required Qualifications 13.1.3.1.1 Qualifications of Personnel Who Cannot Be Directly Cross-Referenced to ANSI/ANS 3.1-1978 13.1.3.2 Qualifications of Incumbent Plant Personnel

13.2 TRAINING PROGRAM

13.2.1 Plant Personnel Training Program 13.2.1.1 Pre Licensing Program Description 13.2.1.1.1 Initial Plant Staff Training 13.2.1.1.2 Operations Section Training Program 13.2.1.1.2.1 Initial Cold License Training 13.2.1.1.2.2 Non-Licensed Operator Training Program 13.2.1.1.3 Maintenance Section Training Program 13.2.1.1.4 Technical Section Training Program

SSES-FSAR TOC Rev. 61 CHAPTER 13 TEXT Section Title FSAR Rev. 68 13-ii 13.2.1.1.4.1 Chemistry Personnel 13.2.1.1.4.2 Instrumentation & Control Personnel 13.2.1.1.4.3 Reactor Engineering Personnel 13.2.1.1.5 Health Physics Training Program 13.2.1.1.6 General Employee Training 13.2.1.1.7 Fire Safety Training

13.2.2 Requalification and Replacement Training

13.2.2.1 Licensed Operator Requalification Program 13.2.2.1.1 Curriculum

13.2.2.1.2 Evaluations 13.2.2.1.3 Accelerated Retraining 13.2.2.1.4 Absence From Licensed Duties 13.2.2.1.5 Disability of Licensed Individuals 13.2.2.2 Continuing Training for Non-licensed Personnel 13.2.2.2.1 Continuing Training for Non-licensed Operators 13.2.2.2.2 Continuing Training for Maintenance Personnel 13.2.2.2.3 Continuing Training for Technical Section Personnel 13.2.2.3 Replacement Training 13.2.2.3.1 NRC Licensed Operator Replacement 13.2.2.3.2 Non-Licensed Operator Replacement Training 13.2.2.3.3 Technical Personnel Replacement Training 13.2.2.3.4 Engineering Support Personnel Replacement Training 13.2.2.4 Records 13.2.2.5 Responsible Individual

13.3 EMERGENCY PLAN

13.4 REVIEW AND AUDIT

13.4.1 Plant Operations Review Committee

13.4.1.1 Organization

13.4.1.2 Meetings 13.4.1.3 Responsibility 13.4.1.4 Authority

13.4.2 Nuclear Safety Review Board

13.4.2.1 Charter SSES-FSAR TOC Rev. 61 CHAPTER 13 TEXT Section Title FSAR Rev. 68 13-iii 13.4.2.2 Membership 13.4.2.3 Sub-Committees

13.4.2.4 Consultants 13.4.2.5 Meeting Frequency 13.4.2.6 Quorum 13.4.2.7 Records 13.4.2.8 Responsibility 13.4.2.9 NSRB Audit Program 13.4.2.10 Authority

13.4.3 Audit Program

13.4.4 Process Control Program (PCP)

13.4.5 Technical Review and Control

13.5 PLANT PROCEDURES

13.5.1 Administrative Procedures 13.5.1.1 Procedure Conformance 13.5.1.2 Preparation of Procedures 13.5.1.3 Procedures

13.5.2 Operating and Maintenance Procedures

13.5.2.1 Control Room Operating Procedures 13.5.2.1.1 Operating Procedures 13.5.2.1.2 General Plant Procedures 13.5.2.1.3 Off-Normal Procedures 13.5.2.1.4 Emergency Procedures 13.5.2.1.5 Alarm Response Procedures 13.5.2.1.6 Temporary Procedures 13.5.2.2 Additional Operating and Maintenance Procedures 13.5.2.2.1 Chemistry Procedures 13.5.2.2.2 Emergency Plan Procedures 13.5.2.2.3 Environmental Surveillance Procedures 13.5.2.2.4 Health Physics Procedures 13.5.2.2.5 Instrument and Control Procedures 13.5.2.2.6 Maintenance Procedures 13.5.2.2.7 Procurement and Material Control Procedures 13.5.2.2.8 Radwaste Management Procedures SSES-FSAR TOC Rev. 61 CHAPTER 13 TEXT Section Title FSAR Rev. 68 13-iv 13.5.2.2.9 Reactor Engineering Procedures 13.5.2.2.10 Records Procedures 13.5.2.2.11 Security Procedures 13.5.2.2.12 Surveillance Procedures 13.5.2.2.13 Fire Protection Procedures

13.6 INDUSTRIAL SECURITY

SSES-FSAR TOC Rev. 61 CHAPTER 13 TABLES Number Title FSAR Rev. 68 13-v 13.1-1 Resumes of Key General Office Personnel

13.1-2 Resumes of Key Plant Personnel

13.1-3 (Deleted)

SSES-FSAR TOC Rev. 61 CHAPTER 13 FIGURES Number Title FSAR Rev. 68 13-vi 13.1-1 Talen Energy Corporation Management Organization Applicable to Susquehanna SES

13.1-1a Deleted

13.1-1b Deleted

13.1-2 Susquehanna Nuclear, LLC, Off-Site Organization

13.1-2a Deleted

13.1-2b Deleted

13.1-2c Deleted

13.1-2d Deleted

13.1-2e Deleted

13.1-2f Deleted

13.1-2g Deleted

13.1-3 Susquehanna Nuclear, LLC, On-Site Organization

13.1-3a Deleted

13.1-3b Deleted

13.1-3c Deleted

13.1-3d Deleted

13.1-4 Deleted

13.1-4a Deleted 13.1-4b Deleted

13.1-4c Deleted SSES-FSAR TOC Rev. 61 CHAPTER 13 FIGURES Number Title FSAR Rev. 68 13-vii 13.1-4d Deleted

13.1-5 Deleted

13.5-1 Deleted

13.5-2 Main Control Room

SSES-FSARTextRev.51CHAPTER14FSARRev.6514-iINITIALTESTSPROGRAMTABLEOFCONTENTSTEXTSectionTitle14.1SPECIFICINFORMATIONTOBEINCLUDEDINPRELIMINARYSAFETYANALYSISREPORTS14.2SPECIFICINFORMATIONTOBEINCLUDEDINFINALSAFETYANALYSISREPORT14.2.1SummaryOfTestProgramandObjectives14.2.1.1PreoperationalTestProgram14.2.1.2StartupTestProgram14.2.2OrganizationandStaffing14.2.2.1PlantStaff14.2.2.2IntegratedStartupGroupOrganizationandResponsibilities14.2.2.2.1ISGSupervisor 14.2.2.2.2AssistantISGSupervisor 14.2.2.2.3GroupLeaders14.2.2.2.4ISGCoordinator14.2.2.2.5ISGSpecialistsSupervisor 14.2.2.2.6ISGScheduledSupervisor14.2.2.2.7RecordControlGroupSupervisor14.2.2.2.8GEISGSiteRepresentative 14.2.2.2.9Responsibilities14.2.2.3PlantOperationsReviewCommittee14.2.2.4TestReviewBoard14.2.3TestProcedures14.2.3.1ProcedurePreparation14.2.3.2ProcedureReviewandApproval14.2.4ConductofTestProgram14.2.4.1TestPerformance14.2.4.2TestPrerequisites14.2.4.3ProcedureModifications 14.2.4.4DesignProblems14.2.4.5ControlofRework,Modifications,andRepairs SSES-FSARTextRev.51CHAPTER14FSARRev.6514-iiSectionTitle14.2.4.6TestPhasePrerequisites14.2.5Review,Evaluation,andApprovalofTestResults14.2.5.1IndividualTestResults14.2.5.2MajorTestPhase-TestResults14.2.5.3PowerAscensionTesting-TestResults14.2.6TestRecords14.2.7ConformanceofTestProgramsWithRegulatoryGuides14.2.8UtilizationofReactorOperatingandTestingExperienceIntheDevelopmentofTheTestProgram14.2.9TrialUseofPlantOperatingandEmergencyProcedures14.2.10InitialFuelLoadingandInitialCriticality14.2.11TestProgramSchedule 14.2.12IndividualTestDescriptions14.2.12.1Unit1PreoperationalTestProcedureAbstracts14.2.12.2Unit1StartupTestProgramProcedureAbstracts14.2.12.3RequestedUnit1AcceptanceTestProcedureAbstracts14.2.12.4Unit2PreoperationalTestProcedureAbstracts 14.2.12.5Unit2AcceptanceTestProcedureAbstracts14.2.12.6Unit2StartupTestProgramProcedureAbstracts14.3POWERUPRATETESTPROGRAM14.3.1SummaryofPowerUprateTestProgramandObjectives14.3.2OrganizationandStaffing14.3.2.1TestReviewCommittee14.3.2.2PowerUprateProjectTestGroup14.3.3TestProcedures SSES-FSARTextRev.51CHAPTER14FSARRev.6514-iiiSectionTitle14.3.4ConductofTestProgram14.3.4.1TestPerformance14.3.4.2TestPrerequisites 14.3.4.3ProcedureModifications14.3.4.4DesignProblems14.3.4.5ControlorRework,Modifications,andRepairs 14.3.4.6TestPhasePrerequisites14.3.5Review,Evaluation,andApprovalofTestResults 14.3.5.1IndividualTestResults14.3.5.2MajorTestPhases-TestResults 14.3.5.3PowerAscensionTesting-TestResults14.3.6TestRecords14.3.7IndividualTestDescriptions14.3.7.1ChemistryTests14.3.7.2Test2-Radiological14.3.7.3Test3-FuelLoading14.3.7.4Test4-FullCoreShutdownMargin 14.3.7.5Test5-ControlRodDrive(CRD) 14.3.7.6Test11-LPRMCalibration14.3.7.7Test12-APRMCalibration14.3.7.8Test14-RCICSystem 14.3.7.9Test15-HPCISystem14.3.7.10Test18-TIPUncertainty14.3.7.11Test19-ThermalLimitsEvaluation 14.3.7.12Test22-PressureRegulator 14.3.7.13Test23-FeedwaterSystem14.3.7.14Test24-TurbineValveSurveillance14.3.7.15Test25-MainSteamIsolationValves 14.3.7.16Test29-RecirculationFlowControlSystem14.3.7.17Test32-ContainmentAtmosphereCooling14.3.7.18Test35-RecirculationSystemFlowCalibration 14.3.7.19Test37-GaseousRadwasteSystem14.3.7.20Test42-I&CSurveillance14.3.7.21Test43-SteadyStateDataCollection 14.3.7.22Test45-MainSteamHighFlow 14.3.7.23Test46-MainSteamLineHighTunnelTemperature14.3.7.24Test47-RecirculationSingleLoopOperation14.3.7.25Test48-LoosePartsMonitor 14.3.7.26Test49-MainSteamLineRadiationMonitor14.3.7.27Test50-CoreSprayLeakDetection14.3.7.28Test61-Unit1ReactorRecirculationHydraulicResponseTest SSES-FSARTextRev.51CHAPTER14FSARRev.6514-ivTABLESNumberTitle14.2-1PreoperationalTestProcedures14.2-2AcceptanceTestProcedures14.2-3StartupTestProcedures 14.2-4MajorTestPhaseandTestPlateauSchedule-TestConditionSequence14.2-5ControlRodDriveSystemStartupTests14.2-6Unit2PreoperationalTestProcedures14.2-7Unit2AcceptanceTest14.3-1PowerUprateTestProcedures 14.3-2TestPlateauandTestConditionDefinition SSES-FSARTextRev.51CHAPTER14FSARRev.6514-vFIGURESNumberTitle14.2-1IntegratedStartupGroupOrganization14.2-2APreoperationalTestProcedureStandardFormat14.2-2BStartupTestProcedureStandardFormat-Unit1 14.2-2CStartupTestProcedureStandardFormat-Unit214.2-3InitialTestProgramSchedule14.2-4aUnit1PreoperationalTestSequence14.2-4bUnit2PreoperationalTestSequence14.2-5-1IndividualStartupTestSequence-Unit1 14.2-5-2IndividualStartupTestSequence-Unit114.2-5-3IndividualStartupTestSequence-Unit214.2-5-4IndividualStartupTestSequence-Unit214.2-6-1PowerFlowMapandStartupTestConditions14.2-6-2PowerFlowMapandPowerTestConditions 14.2-7RCICAcceptanceCriteriaCurvesForCapacityandActuationTime SSES-FSAR Text Rev. 62 FSAR Rev. 68 15-i CHAPTER 15 ACCIDENT ANALYSIS TABLE OF CONTENTS TEXT Section Title 15.0 ACCIDENT ANALYSES

15.0.1 Analytical Objective

15.0.2 Analytical Categories

15.0.3 Event Evaluation

15.0.3.1 Identification of Causes and Frequency Classification 15.0.3.1.1 Unacceptable Results for Incidents of Moderate Frequency (Anticipated (Expected) Operational Transients) 15.0.3.1.2 Unacceptable Results for Infrequent Incidents (Abnormal (Unexpected) Operational Transients) 15.0.3.1.3 Unacceptable Results for Limiting Faults (Design Basis (Postulated) Accidents) 15.0.3.2 Sequence of Events and Systems Operations 15.0.3.2.1 Single Failures or Operator Errors

15.0.3.2.1.1 General 15.0.3.2.1.2 Initiating Event Analysis 15.0.3.2.1.3 Single Active Component Failure or Single Operator Failure Analysis 15.0.3.3 Core and System Performance 15.0.3.3.1 Introduction 15.0.3.3.2 Input Parameters and Initial Conditions for Analyzed Events 15.0.3.3.3 Initial Power/Flow Operating Constraints 15.0.3.3.4 Results 15.0.3.5 Barrier Performance 15.0.3.6 Radiological Consequences

15.0.4 Nuclear Safety Operational Analysis (NSQA) Relationship

15.0.5 References

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-ii 15.1 DECREASE IN REACTOR COOLANT TEMPERATURE

15.1.1 Loss of Feedwater Heating 15.1.1.1 Identification of Causes and Frequency Classification 15.1.1.1.1 Identification of Causes 15.1.1.1.2 Frequency Classification 15.1.1.2 Sequence of Events and Systems Operation 15.1.1.2.1 Sequence of Events 15.1.1.2.1.1 Identification of Operator Actions 15.1.1.2.2 Systems Operation 15.1.1.2.3 The Effect of Single Failures and Operator Errors 15.1.1.3 Core and System Performance 15.1.1.3.1 Mathematical Model 15.1.1.3.2 Input Parameters and Initial Conditions 15.1.1.3.3 Results 15.1.1.3.4 Considerations of Uncertainties 15.1.1.4 Barrier Performance 15.1.1.5 Radiological Consequences

15.1.2 Feedwater Controller Failure-Maximum Demand

15.1.2.1 Identification of Causes and Frequency Classification 15.1.2.1.1 Identification of Causes 15.1.2.1.2 Frequency Classification 15.1.2.2 Sequence of Events and Systems Operation 15.1.2.2.1 Sequence of Events 15.1.2.2.1.1 Identification of Operator Actions 15.1.2.2.2 Systems Operation 15.1.2.2.3 The Effect of Single Failures and Operator Errors 15.1.2.3 Core and System Performance 15.1.2.3.1 Mathematical Model 15.1.2.3.2 Input Parameters and Initial Conditions 15.1.2.3.3 Results 15.1.2.3.4 Consideration of Uncertainties 15.1.2.4 Barrier Performance 15.1.2.5 Radiological Consequences 15.1.3 Pressure Regulator Failure - Open

15.1.3.1 Identification of Causes and Frequency Classification 15.1.3.1.1 Identification of Causes SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-iii 15.1.3.1.2 Frequency Classification 15.1.3.2 Sequence of Events and Systems Operation 15.1.3.2.1 Sequence of Events 15.1.3.2.1.1 Identification of Operator Actions 15.1.3.2.2 Systems Operation 15.1.3.2.3 The Effect of Single Failures and Operator Errors 15.1.3.3 Core and System Performance 15.1.3.3.1 Mathematical Model 15.1.3.3.2 Input Parameters and Initial Conditions 15.1.3.3.3 Results 15.1.3.3.4 Consideration of Uncertainties 15.1.3.4 Barrier Performance 15.1.3.5 Radiological Consequences

15.1.4 Inadvertent Safety/Relief Valve Opening

15.1.4.1 Identification of Causes and Frequency Classification 15.1.4.1.1 Identification of Causes 15.1.4.1.2 Frequency Classification 15.1.4.2 Sequence of Events and Systems Operation 15.1.4.2.1 Sequence of Events 15.1.4.2.1.1 Identification of Operator Actions 15.1.4.2.2 Systems Operation 15.1.4.2.3 The Effect of Single Failures and Operator Errors 15.1.4.3 Core and System Performance 15.1.4.3.1 Mathematical Model 15.1.4.3.2 Input Parameters and Initial Conditions 15.1.4.3.3 Qualitative Results 15.1.4.4 Barrier Performance 15.1.4.5 Radiological Consequences

15.1.5 Spectrum of Steam System Piping Failures Inside and Outside of Containment In A PWR

15.1.6 Inadvertent RHR Shutdown Cooling Operation

15.1.6.1 Identification of Causes and Frequency Classification 15.1.6.1.1 Identification of Causes 15.1.6.1.2 Frequency Classification 15.1.6.2 Sequence of Events and Systems Operation 15.1.6.2.1 Sequence of Events SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-iv 15.1.6.2.2 System Operation 15.1.6.2.3 Effect of Single Failures and Operator Action 15.1.6.3 Core and System Performance 15.1.6.4 Barrier Performance 15.1.6.5 Radiological Consequences

15.1.7 References

15.2 INCREASE IN REACTOR PRESSURE

15.2.1 Pressure Regulator Failure - Closed

15.2.1.1 Identification of Causes and Frequency Classification 15.2.1.1.1 Identification of Causes 15.2.1.1.2 Frequency Classification 1.5.2.1.2 Sequence of Events and System Operation 15.2.1.2.1 Sequence of Events 15.2.1.2.1.1 Identification of Operator Actions 15.2.1.2.2 Systems Operation 15.2.1.2.3 The Effect of Single Failures and Operator Errors 15.2.1.3 Core and System Performance 15.2.1.3.1 Mathematical Model 15.2.1.3.2 Input Parameters and Initial Conditions 15.2.1.3.3 Results 15.2.1.3.4 Consideration of Uncertainties 15.2.1.4 Barrier Performance 15.2.1.5 Radiological Consequences

15.2.2 Generator Load Rejection

15.2.2.1 Identification of Causes and Frequency Classification 15.2.2.1.1 Identification of Causes 15.2.2.1.2 Frequency Classification 15.2.2.1.2.1 Generator Load Rejection Without Without Bypass 15.2.2.2 Sequence of Events and System Operation 15.2.2.2.1 Sequence of Events 15.2.2.2.1.1 Generator Load Rejection-Turbine Control Valve Fast Closure with Bypass Operable 15.2.2.2.1.2 Generator Load Rejection with Failure of Bypass 15.2.2.2.1.3 Identification of Operator Actions 15.2.2.2.2 System Operation SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-v 15.2.2.2.2.1 Generator Load Rejection with Bypass Operable 15.2.2.2.2.2 Generator Load Rejection with Failure of Bypass 15.2.2.2.3 The Effect of Single Failures and Operator Errors 15.2.2.3 Core and System Performance 15.2.2.3.1 Mathematical Model 15.2.2.3.2 Input Parameters and Initial Conditions 15.2.2.3.3 Results 15.2.2.3.3.1 Generator Load Rejection with Bypass 15.2.2.3.3.2 Generator Load Rejection with Failure of Bypass 15.2.2.3.4 Consideration of Uncertainties 15.2.2.4 Barrier Performance 15.2.2.4.1 Generator Load Rejection with Bypass Operable 15.2.2.4.2 Generator Load Rejection with Failure of Bypass 15.2.2.5 Radiological Consequences

15.2.3 Turbine Trip

15.2.3.1 Identification of Causes and Frequency Classification 15.2.3.1.1 Identification of Causes 15.2.3.1.2 Frequency Classification 15.2.3.1.2.1 Turbine Trip 15.2.3.2 Sequence of Events and Systems Operation 15.2.3.2.1 Sequence of Events 15.2.3.2.1.1 Turbine Trip with Bypass Operable 15.2.3.2.1.2 Turbine Trip with Failure of the Bypass 15.2.3.2.1.3 Identification of Operator Actions 15.2.3.2.2 Systems Operation 15.2.3.2.2.1 Turbine Trip with Bypass Operable 15.2.3.2.2.2 Turbine Trip with Failure of the Bypass 15.2.3.2.2.3 Turbine Trip at Low Power with Failure of the Bypass 15.2.3.2.3 The Effect of Single Failures and Operators Errors 15.2.3.2.3.1 Turbine Trips at Power Levels Greater Than 30%

15.2.3.2.3.2 Turbine Trips at Power Levels Less Than 30%

15.2.3.3 Core and System Performance 15.2.3.3.1 Mathematical Model 15.2.3.3.2 Input Parameters and Initial Conditions 15.2.3.3.3 Results 15.2.3.3.3.1 Turbine Trip with Bypass Operable 15.2.3.3.3.2 Turbine Trip with Failure of Bypass 15.2.3.3.3.3 Turbine Trip with Bypass Valve Failure, Low Power 15.2.3.3.4 Considerations of Uncertainties SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-vi 15.2.3.4 Barrier Performance 15.2.3.4.1 Turbine Trip with Bypass Operable 15.2.3.4.2 Turbine Trip with Failure of the Bypass 15.2.3.4.2.1 Turbine Trip with Failure of Bypass at Low Power 15.2.3.5 Radiological Consequences

15.2.4 MSIV Closures

15.2.4.1 Identification of Causes and Frequency Classification 15.2.4.1.1 Identification of Causes 15.2.4.1.2 Frequency Classification 15.2.4.1.2.1 Closure of All Main Steam Isolation Valves 15.2.4.1.2.2 Closure of One Main Steam Isolation Valve 15.2.4.2 Sequence of Events and Systems Operation 15.2.4.2.1 Sequence of Events 15.2.4.2.1.1 Identification of Operator Actions 15.2.4.2.2 Systems Operation 15.2.4.2.2.1 Closure of All Main Steam Isolation Valves 15.2.4.2.2.2 Closure of One Main Steam Isolation Valve 15.2.4.2.3 The Effect of Single Failures and Operator Errors 15.2.4.3 Core and System Performance 15.2.4.3.1 Mathematical Model 15.2.4.3.2 Input Parameters and Initial Conditions 15.2.4.3.3 Results 15.2.4.3.3.1 Closure of All Main Steam Isolation Valves 15.2.4.3.3.2 Closure of One Main Steam Isolation Valve 15.2.4.3.4 Considerations of Uncertainties 15.2.4.4 Barrier Performance 15.2.4.4.1 Closure of All Main Steam Isolation Valves 15.2.4.4.2 Closure of One Main Steam Isolation Valve 15.2.4.5 Radiological Consequences

15.2.5 Loss of Condenser Vacuum

15.2.5.1 Identification of Causes and Frequency Classification 15.2.5.1.1 Identification of Causes 15.2.5.1.2 Frequency Classification 15.2.5.2 Sequence of Events and Systems Operation 15.2.5.2.1 Sequence of Events 15.2.5.2.1.1 Identification of Operator Actions 15.2.5.2.2 Systems Operation SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-vii 15.2.5.2.3 The Effect of Single Failures and Operator Errors 15.2.5.3 Core and System Performance 15.2.5.3.1 Mathematical Model 15.2.5.3.2 Input Parameters and Initial Conditions 15.2.5.3.3 Results 15.2.5.3.4 Considerations of Uncertainties 15.2.5.4 Barrier Performance 15.2.5.5 Radiological Consequences

15.2.6 Loss of AC Power

15.2.6.1 Identification of Causes and Frequency Classification 15.2.6.1.1 Identification of Causes 15.2.6.1.1.1 Loss of Auxiliary Power Transformer 15.2.6.1.1.2 Loss of All Grid Connections 15.2.6.1.2 Frequency Classification 15.2.6.1.2.1 Loss of Auxiliary Power Transformer 15.2.6.1.2.2 Loss of All Grid Connections 15.2.6.2 Sequence of Events and Systems Operation 15.2.6.2.1 Sequence of Events 15.2.6.2.1.1 Loss of Auxiliary Power Transformer 15.2.6.2.1.2 Loss of All Grid Connections 15.2.6.2.1.3 Identification of Operator Actions 15.2.6.2.2 Systems Operation 15.2.6.2.2.1 Loss of Auxiliary Power Transformer 15.2.6.2.2.2 Loss of All Grid Connections 15.2.6.2.3 The Effect of Single Failures and Operator Errors 15.2.6.3 Core and System Performance 15.2.6.3.1 Mathematical Model 15.2.6.3.2 Input Parameters and Initial Conditions 15.2.6.3.2.1 Loss of Auxiliary Power Transformer 15.2.6.3.2.2 Loss of All Grid Connections 15.2.6.3.3 Results 15.2.6.3.3.1 Loss of Auxiliary Power Transformer 15.2.6.3.3.2 Loss of All Grid Connections 15.2.6.3.4 Consideration of Uncertainties 15.2.6.4 Barrier Performance 15.2.6.4.1 Loss of Auxiliary Power Transformer 15.2.6.4.2 Loss of All Grid Connections 15.2.6.5 Radiological Consequences

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-viii 15.2.7 Loss of Feedwater Flow

15.2.7.1 Identification of Causes and Frequency Classification 15.2.7.1.1 Identification of Causes 15.2.7.1.2 Frequency Classification 15.2.7.2 Sequence of Events and Systems Operation 15.2.7.2.1 Sequence of Events 15.2.7.2.1.1 Identification of Operator Actions 15.2.7.2.2 Systems Operation 15.2.7.2.3 The Effect of Single Failures and Operator Errors 15.2.7.3 Core and System Performance 15.2.7.3.1 Mathematical Model 15.2.7.3.2 Input Parameters and Initial Conditions 15.2.7.3.3 Results 15.2.7.3.4 Considerations of Uncertainties 15.2.7.4 Barrier Performance 15.2.7.5 Radiological Consequences

15.2.8 Feedwater Line Break

15.2.9 Failure of RHR Shutdown Cooling

15.2.9.1 Identification of Causes and Frequency Classification 15.2.9.1.1 Identification of Causes 15.2.9.1.2 Frequency Classification 15.2.9.2 Sequence of Events and System Operation 15.2.9.2.1 Sequence of Events 15.2.9.2.1.1 Identification of Operator Actions 15.2.9.2.2 System Operation 15.2.9.2.3 The Effect of Single Failures and Operator Errors 15.2.9.3 Core and System Performance 15.2.9.3.1 Methods, Assumptions, and Conditions 15.2.9.3.2 Results 15.2.9.3.2.1 Full Power to Approximately 100 psig 15.2.9.3.2.2 Approximately 100 psig to Cold Shutdown 15.2.9.4 Barrier Performance 15.2.9.5 Radiological Consequences

15.2.10 References

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-ix 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE

15.3.1 Recirculation Pump Trip

15.3.1.1 Identification of Causes and Frequency Classification 15.3.1.1.1 Identification of Causes 15.3.1.1.2 Frequency Classification 15.3.1.1.2.1 Trip of One Recirculation Pump 15.3.1.1.2.2 Trip of Two Recirculation Pumps 15.3.1.2 Sequence of Events and Systems Operation 15.3.1.2.1 Sequence of Events 15.3.1.2.1.1 Trip of One Recirculation Pump 15.3.1.2.1.2 Trip of Two Recirculation Pumps 15.3.1.2.1.3 Identification of Operator Actions 15.3.1.2.1.3.1 Trip of One Recirculation Pump 15.3.1.2.1.3.2 Trip of Two Recirculation Pumps 15.3.1.2.2 Systems Operation 15.3.1.2.2.1 Trip of One Recirculation Pump 15.3.1.2.2.2 Trip of Two Recirculation Pumps 15.3.1.2.3 The Effect of Single Failures and Operator Errors 15.3.1.2.3.1 Trip of One Recirculation Pump 15.3.1.2.3.2 Trip of Two Recirculation Pumps 15.3.1.3 Core and System Performance 15.3.1.3.1 Mathematical Model 15.3.1.3.2 Input Parameters and Initial Conditions 15.3.1.3.3 Results 15.3.1.3.3.1 Trip of One Recirculation Pump 15.3.1.3.3.2 Trip of Two Recirculation Pumps 15.3.1.3.4 Consideration of Uncertainties 15.3.1.4 Barrier Performance 15.3.1.4.1 Trip of One Recirculation Pump 15.3.1.4.2 Trip of Two Recirculation Pumps 15.3.1.5 Radiological Consequences

15.3.2 Recirculation Flow Control Failure - Decreasing Flow

15.3.2.1 Identification of Causes and Frequency Classification 15.3.2.1.1 Identification of Causes 15.3.2.1.2 Frequency Classification 15.3.2.2 Sequence of Events and Systems Operation 15.3.2.2.1 Sequence of Events SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-x 15.3.2.2.1.1 Failure of One Speed Control Loop Including Failure of the Redundant Control Processor (CP) Pair 15.3.2.2.1.2 Identification of Operator Actions 15.3.2.2.2 Systems Operation 15.3.2.2.3 The Effect of Single Failures and Operator Errors 15.3.2.3 Core and System Performance 15.3.2.3.1 Mathematical Model 15.3.2.3.2 Input Parameters and Initial Conditions 15.3.2.3.3 Results 15.3.2.3.4 Consideration of Uncertainties 15.3.2.4 Barrier Performance 15.3.2.5 Radiological Consequences

15.3.3 Recirculation Pump Seizure

15.3.3.1 Identification of Causes and Frequency Classification 15.3.3.1.1 Identification of Causes 15.3.3.1.2 Frequency Classification 15.3.3.2 Sequence of Events and Systems Operations 15.3.3.2.1 Sequence of Events 15.3.3.2.1.1 Identification of Operator Actions 15.3.3.2.2 Systems Operation 15.3.3.2.3 The Effect of Single Failures and Operator Errors 15.3.3.3 Core and System Performance 15.3.3.3.1 Mathematical Model 15.3.3.3.2 Input Parameters and Initial Conditions 15.3.3.3.3 Results 15.3.3.3.4 Considerations of Uncertainties 15.3.3.4 Barrier Performance 15.3.3.5 Radiological Consequences 15.3.3.5.1 Design Basis Analysis 15.3.3.5.2 Realistic Analysis

15.3.4 Recirculation Pump Shaft Break

15.3.4.1 Identification of Causes and Frequency Classification 15.3.4.1.1 Identification of Causes 15.3.4.1.2 Frequency Classification 15.3.4.2 Sequence of Events and Systems Operations 15.3.4.2.1 Sequence of Events 15.3.4.2.1.1 Identification of Operator Actions SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xi 15.3.4.2.2 Systems Operation 15.3.4.2.3 The Effect of Single Failures and Operator Errors 15.3.4.3 Core and System Performance 15.3.4.3.1 Qualitative Results 15.3.4.4 Barrier Performance 15.3.4.5 Radiological Consequences

15.3.5 References

15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES

15.4.1 Rod Withdrawal Error - Low Power

15.4.1.1 Control Rod Removal Error During Refueling 15.4.1.1.1 Identification of Causes and Frequency Classification 15.4.1.1.2 Sequence of Events and Systems Operation 15.4.1.1.2.1 Initial Control Rod Removal 15.4.1.1.2.2 Fuel Movement With Control Rod Removed 15.4.1.1.2.3 Control Rod Removal Without Fuel Removal 15.4.1.1.2.4 Identification of Operator Actions 15.4.1.1.2.5 Effect of Single Failure and Operator Errors 15.4.1.1.3 Core and System Performances 15.4.1.1.4 Barrier Performance 15.4.1.1.5 Radiological Consequences 15.4.1.2 Continuous Rod Withdrawal During Reactor Startup 15.4.1.2.1 Identification of Causes and Frequency Classification 15.4.1.2.2 Sequence of Events and Systems Operation 15.4.1.2.2.1 Sequence of Events 15.4.1.2.2.2 Identification of Operator Actions 15.4.1.2.2.3 Effects of Single Failure and Operator Errors 15.4.1.2.3 Core and System Performance 15.4.1.2.4 Barrier Performance 15.4.1.2.5 Radiological Consequences

15.4.2 Rod Withdrawal Error-at Power

15.4.2.1 Identification of Causes and Frequency Classifications 15.4.2.1.1 Identification of Causes 15.4.2.1.2 Frequency Classification 15.4.2.2 Sequence of Events and Systems Operation 15.4.2.2.1 Sequence of Events SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xii 15.4.2.2.2 System Operations 15.4.2.2.3 Effect of Single Failure and Operator Errors 15.4.2.3 Core and System Performance 15.4.2.3.1 Mathematical Model 15.4.2.3.2 Input Parameters and Initial Conditions 15.4.2.3.2.1 REM System Operation 15.4.2.3.3 Results 15.4.2.3.4 Considerations of Uncertainties 15.4.2.4 Barrier Performance 15.4.2.5 Radiological Consequences

15.4.3 Control Rod Maloperation (System Malfunction or Operator Error)

15.4.4 Abnormal Startup of Idle Recirculation Pump

15.4.4.1 Identification of Causes and Frequency Classification 15.4.4.1.1 Identification of Causes 15.4.4.1.1.1 Normal Restart of Recirculation Pump at Power 15.4.4.1.1.2 Abnormal Startup of Idle Recirculation Pump 15.4.4.2 Sequence of Events and Systems Operation 15.4.4.2.1 Sequence of Events 15.4.4.2.1.1 Operator Actions 15.4.4.2.2 Systems Operation 15.4.4.2.3 The Effect of Single Failures and Operator Errors 15.4.4.3 Core and System Performance 15.4.4.3.1 Mathematical Model 15.4.4.3.2 Input Parameters and Initial Conditions 15.4.4.3.3 Results 15.4.4.3.4 Consideration of Uncertainties 15.4.4.4 Barrier Performance 15.4.4.5 Radiological Consequences

15.4.5 Recirculation Flow Control Failure with Increasing Flow

15.4.5.1 Identification of Causes and Frequency Classification 15.4.5.1.1 Identification of Causes 15.4.5.1.2 Frequency Classification 15.4.5.2 Sequence of Events and Systems Operation 15.4.5.2.1 Sequence of Events 15.4.5.2.1.1 Identification of Operator Actions 15.4.5.2.2 Systems Operation SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xiii 15.4.5.2.3 The Effect of Single Failures and Operator Errors 15.4.5.3 Core and System Performance 15.4.5.3.1 Mathematical Model 15.4.5.3.2 Input Parameters and Initial Conditions 15.4.5.3.3 Results 15.4.5.3.4 Considerations of Uncertainties 15.4.5.4 Barrier Performance 15.4.5.5 Radiological Consequences

15.4.6 Chemical and Volume Control System Malfunctions

15.4.7 Misplaced Bundle Accident

15.4.7.1 Identification of Causes and Frequency Classification 15.4.7.1.1 Identification of Causes 15.4.7.1.2 Frequency of Occurrence 15.4.7.2 Sequence of Events and Systems Operation 15.4.7.2.1 Effect of Single Failure and Operator Errors 15.4.7.3 Core and System Performance 15.4.7.3.1 Mathematical Model 15.4.7.3.2 Input Parameters and Initial Conditions 15.4.7.3.3 Results 15.4.7.3.4 Considerations of Uncertainties 15.4.7.4 Barrier Performance 15.4.7.5 Radiological Consequences

15.4.8 Spectrum of Rod Ejection Assemblies

15.4.9 Control Rod Drop Accident (CRDA)

15.4.9.1 Identification of Causes and Frequency Classification 15.4.9.1.1 Identification of Causes 15.4.9.1.2 Frequency of Classification 15.4.9.2 Sequence of Events and System Operation 15.4.9.2.1 Sequence of Events 15.4.9.2.2 Systems Operation 15.4.9.2.3 Effect of Single Failures and Operator Errors 15.4.9.3 Core and System Performance 15.4.9.3.1 Mathematical Model 15.4.9.3.2 Input Parameters and Initial Conditions 15.4.9.3.3 Results SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xiv 15.4.9.4 Barrier Performance 15.4.9.5 Radiological Consequences 15.4.9.5.1 Design Basis Analysis 15.4.9.5.2 Realistic Analysis

15.4.10 References

15.5 INCREASE IN REACTOR COOLANT INVENTORY

15.5.1 Inadvertent HPCI Startup

15.5.1.1 Identification of Causes and Frequency Classification 15.5.1.1.1 Identification of Causes 15.5.1.1.2 Frequency Classification 15.5.1.2 Sequence of Events and Systems Operation 15.5.1.2.1 Sequence of Events 15.5.1.2.1.1 Identification of Operator Actions 15.5.1.2.2 System Operation 15.5.1.2.3 The Effect of Single Failures and Operator Errors 15.5.1.3 Core and System Performance 15.5.1.3.1 Mathematical Model 15.5.1.3.2 Input Parameter and Initial Conditions 15.5.1.3.3 Results 15.5.1.3.4 Consideration of Uncertainties 15.5.1.4 Barrier Performance 15.5.1.5 Radiological Consequences

15.5.2 Chemical Volume Control System Malfunction (or Operator Error)

15.5.3 BWR Transients Which Increase Reactor Coolant Inventory

15.5.4 References

15.6 DECREASE IN REACTOR COOLANT INVENTORY

15.6.1 Inadvertent Safety Relief Valve Opening 15.6.2 Instrument Line Break

15.6.2.1 Identification of Causes and Frequency Classification 15.6.2.1.1 Identification of Causes SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xv 15.6.2.1.1.1 Event Description 15.6.2.1.2 Frequency Classification 15.6.2.2 Sequence of Events and Systems Operation 15.6.2.2.1 Sequence of Events 15.6.2.2.1.1 Identification of Operator Actions 15.6.2.2.2 System Operation 15.6.2.2.3 The Effect of Single Failures and Operator Errors 15.6.2.3 Core and System Performance 15.6.2.3.1 Qualitative Summary - Results 15.6.2.3.2 Quantitative Results 15.6.2.3.3 Considerations of Uncertainties 15.6.2.4 Barrier Performance 15.6.2.5 Radiological Consequences 15.6.2.5.1 Design Basis Analysis 15.6.2.5.2 Realistic Analysis 15.6.2.5.3 Results

15.6.3 Steam Generator Tube Failure

15.6.4 Steam System Piping Break Outside Containment

15.6.4.1 Identification of Causes and Frequency Classification 15.6.4.1.1 Identification of Causes 15.6.4.1.2 Frequency Classification 15.6.4.2 Sequence of Events and Systems Operation 15.6.4.2.1 Sequence of Events 15.6.4.2.1.1 Identification of Operator Actions 15.6.4.2.2 Systems Operation 15.6.4.2.3 The Effect of Single Failures and Operator Errors 15.6.4.3 Core and System Performance 15.6.4.3.1 Input Parameters and Initial Conditions 15.6.4.3.2 Results 15.6.4.3.3 Considerations of Uncertainties 15.6.4.4 Barrier Performance 15.6.4.5 Radiological Consequences 15.6.4.5.1 Design Basis Analysis 15.6.4.5.2 Realistic Analysis 15.6.4.5.3 Results

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xvi 15.6.5 Loss-Of-Coolant Accidents (Resulting From Spectrum of Postulated Piping Breaks Within The Reactor Coolant Pressure Boundary) -

Inside Containment

15.6.5.1 Identification of Causes and Frequency Classification 15.6.5.1.1 Identification of Causes 15.6.5.1.2 Frequency Classification 15.6.5.2 Sequence of Events and Systems Operation 15.6.5.2.1 Sequence of Events 15.6.5.2.1.1 Identification of Operator Actions 15.6.5.2.2 Systems Operations 15.6.5.2.3 The Effect of Single Failures and Operator Errors 15.6.5.3 Core and System Performance 15.6.5.3.1 Mathematical Model 15.6.5.3.2 Input Parameters and Initial Conditions 15.6.5.3.3 Results 15.6.5.3.4 Consideration of Uncertainties 15.6.5.4 Barrier Performance 15.6.5.5 Radiological Consequences 15.6.5.5.1 Design Basis Analysis 15.6.5.5.1.1 Fission Product Release from Fuel 15.6.5.5.1.2 Fission Product Transport to the Environment 15.6.5.5.2 Realistic Analysis 15.6.5.5.2.1 Fission Product Release from Fuel 15.6.5.5.2.2 Fission Product Transport to the Environment 15.6.5.5.3 Results 15.6.5.5.3.1 Offsite Exposure 15.6.5.5.3.2 Control Room Doses

15.6.6 Feedwater Line Break-Outside Containment

15.6.6.1 Identification of Causes and Frequency Classification 15.6.6.1.1 Identification of Causes 15.6.6.1.2 Frequency Classification 15.6.6.2 Sequence of Events and Systems Operation 15.6.6.2.1 Sequence of Events 15.6.6.2.1.1 Identification of Operator Actions 15.6.6.2.2 Systems Operations 15.6.6.2.3 The Effect of Single Failures and Operator Errors 15.6.6.3 Core and System Performance 15.6.6.3.1 Qualitative Summary SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xvii 15.6.6.3.2 Qualitative Results 15.6.6.3.3 Consideration of Uncertainties 15.6.6.4 Barrier Performance 15.6.6.5 Radiological Consequences 15.6.6.5.1 Design Basis Analysis 15.6.6.5.2 Realistic Analysis 15.6.6.5.3 Fission Product Release 15.6.6.5.4 Fission Product Transport to the Environment 15.6.6.5.5 Results

15.6.7 References

15.7 RADIOACTIVE RELEASE FROM SUBSYSTEMS AND COMPONENTS

15.7.1 Gaseous Radwaste System Leak or Failure

15.7.1.1 Ambient Charcoal Offgas Treatment System Failure 15.7.1.1.1 Identification of Causes and Frequency Classification 15.7.1.1.1.1 Identification of Causes 15.7.1.1.1.2 Frequency Classification 15.7.1.1.2 Sequence of Events and System Operation 15.7.1.1.2.1 Sequence of Events 15.7.1.1.2.2 Identification of Operator Actions 15.7.1.1.2.3 Systems Operation 15.7.1.1.2.4 The Effects of Single Failures and Operator Errors 15.7.1.1.3 Core and System Performance 15.7.1.1.4 Barrier Performance 15.7.1.1.5 Radiological Consequences 15.7.1.1.5.1 Design Basis Analysis 15.7.1.1.5.2 Realistic Analysis 15.7.1.1.5.3 Results 15.7.1.2 Malfunction of Main Turbine Gland Sealing System 15.7.1.2.1 Identification of Causes and Frequency Classification 15.7.1.2.1.1 Identification of Causes 15.7.1.2.1.2 Frequency Classification 15.7.1.2.2 Sequence of Events and System Operation 15.7.1.2.2.1 Sequence of Events 15.7.1.2.2.2 Identification of Operator Actions 15.7.1.2.2.3 System Operation 15.7.1.2.3 Core and System Performance SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xviii 15.7.1.2.4 Barrier Analysis 15.7.1.2.5 Radiological Consequences 15.7.1.3 Failure of Air Ejector Lines 15.7.1.3.1 Identification of Causes and Frequency Classification 15.7.1.3.2 Sequence of Events and Systems Operation 15.7.1.3.3 Core and System Performance 15.7.1.3.4 Barrier Analysis 15.7.1.3.5 Radiological Consequences 15.7.1.3.5.1 Design Basis Analysis 15.7.1.3.5.2 Realistic Analysis 15.7.1.3.5.3 Fission Product Release 15.7.1.3.5.4 Fission Product Transport to the Environment 15.7.1.3.5.5 Results

15.7.2 Liquid Radwaste System Failure

15.7.2.1 Miscellaneous Small Releases Outside Containment

15.7.3 Postulated Radioactive Releases Due To Liquid Radwaste Tank Failure 15.7.3.1 Identification of Causes and Frequency Classification 15.7.3.1.1 Identification of Causes 15.7.3.1.2 Frequency Classification 15.7.3.2 Sequence of Events and Systems Operation 15.7.3.3 Core and System Performance 15.7.3.4 Barrier Performance 15.7.3.5 Radiological Consequences 15.7.3.5.1 Design Basis Analysis 15.7.3.5.2 Realistic Analysis

15.7.4 Fuel and Equipment Handling Accidents

15.7.4.1 Identification of Causes and Frequency Classification 15.7.4.1.1 Identification of Causes 15.7.4.1.2 Frequency Classification 15.7.4.2 Sequence of Events and Systems Operation 15.7.4.2.1 Sequence of Events 15.7.4.2.2 Identification of Operator Actions 15.7.4.2.3 System Operation 15.7.4.2.4 The Effects of Single Failures and Operator Errors SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xix 15.7.4.3 Core and System Performance 15.7.4.3.1 Mathematical Model 15.7.4.3.2 Input Parameters and Initial Conditions 15.4.7.3.3 Results 15.7.4.3.3.1 Energy Available 15.7.4.3.3.2 Energy Loss Per Impact 15.7.4.3.3.3 Fuel Rod Failures 15.7.4.3.3.3.1 First Impact Failures 15.7.4.3.3.3.2 Second Impact Failures 15.7.4.3.3.3.3 Total Failures 15.7.4.4 Barrier Performance 15.7.4.5 Radiological Consequences 15.7.4.5.1 Design Basis Analysis 15.7.4.5.1.1 Fission Product Release from Fuel 15.7.4.5.1.2 Fission Product Transport to the Environment 15.7.4.5.1.3 Results 15.7.4.5.2 Realistic Analysis 15.7.4.5.2.1 Fission Product Release from Fuel 15.7.4.5.2.2 Fission Product Transport to the Environment 15.7.4.5.2.3 Results

15.7.5 Spent Fuel Cask Drop Accident

15.7.6 References

15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS)

15.8.1 Causes, Frequency Classification, Initiating Events, Acceptance Criteria, Mathematical Models, Input Parameters, and Initial Conditions 15.8.1.1 Identification of Causes 15.8.1.2 Frequency Classification 15.8.1.3 Initiating Events 15.8.1.4 Acceptance Criteria 15.8.1.4.1 Peak Clad Temperature and Vessel Pressure Associated with Initial Pressurization Transient 15.8.1.4.2 Peak Suppression Pool Temperature and Containment Pressure 15.8.1.4.3 Fuel Integrity Under Unstable Operation 15.8.1.4.4 Radiological Consequences and Long-Term Shutdown and Cooling Capability 15.8.1.5 Mathematical Models SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xx 15.8.1.6 Input Parameters and Initial Conditions

15.8.2 Inadvertent Control Rod Withdrawal

15.8.3 Loss of Feedwater (LOFW)

15.8.4 Loss of Offsite Power (LOOP)

15.8.5 Loss of Electrical Load

15.8.6 Loss of Condenser Vacuum

15.8.7 Turbine Trip

15.8.8 Closure of Main Steam Line Isolation Valves 15.8.8.1 Sequence of Events, Systems Operation, and Operator Actions 15.8.8.2 Results

15.8.9 Pressure Regulator Failure-Open 15.8.9.1 Sequence of Events, Systems Operation, and Operator Actions 15.8.9.2 Results

15.8.10 Feedwater Controller Failure-Open (FWCFO)

15.8.11 Inadvertent Opening of a S/R Valve

15.8.12 References

15.9 STATION BLACKOUT (SBO)

15.9.0 Coping Assessment for the Susquehanna Steam Electric Station During a Station Blackout

15.9.1 References

15A Nuclear Safety Operational Analysis (NOSA) (A System Level/Qualitative Type Plant FMEA)

15A.1 OBJECTIVES

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxi 15A.1.1 General Objectives

15A.1.2 Specific Objectives

15A.2 APPROACH TO OPERATIONAL NUCLEAR SAFETY

15A.2.1 General Philosophy

15A.2.2 Specific Philosophy

15A.2.2.1 Consistency of the Analysis

15A.2.3 Comprehensiveness of the Analysis

15A.2.4 Systematic Approach of the Analysis

15A.2.5 Relationship of Nuclear Safety Operational Analysis to Safety Analyses of Chapter 15

15A.2.6 Relationship Between NSOA and Operational Requirements, Technical Specifications, Design Basis, and SACF Aspects

15A.2.7 Unacceptable Results Criteria

15A.2.8 General Nuclear Safety Operational Criteria

15A.3 METHOD OF ANALYSIS

15A.3.1 General Approach

15A.3.2 BWR Operating States

15A.3.3 Selection of Events for Analysis

15A.3.3.1 Planned Operations 15A.3.3.2 Anticipated (Expected) Operational Transients 15A.3.3.3 Abnormal (Unexpected) Operational Transients 15A.3.3.4 Accidents 15A.3.3.5 Additional Special Plant Capability Events

15A.3.4 Applicability of Events to Operating States SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxii 15A.3.5 Rules for Event Analysis

15A.3.6 Steps in an Operational Analysis

15A.4 DISPLAY OF OPERATIONAL ANALYSIS RESULTS

15A.4.1 General

15A.4.2 Protection Sequence and Safety System Auxiliary Diagrams

15A.5 BASES FOR SELECTING SURVEILLANCE TEST FREQUENCIES

15A.5.1 Normal Surveillance Test Frequencies

15A.5.2 Allowable Repair Times

15A.5.3 Repair Time Rule

15A.6 OPERATIONAL ANALYSES

15A.6.1 Safety System Auxiliaries

15A.6.2 Planned (Normal) Operations

15A.6.2.1 General 15A.6.2.2 Event Definitions 15A.6.2.3 Required Safety Actions/Related Unacceptable Results 15A.6.2.3.1 Radioactive Material Release Control 15A.6.2.3.2 Core Coolant Flow Rate Control 15A.6.2.3.3 Core Power Level Control 15A.6.2.3.4 Core Neutron Flux Distribution Control 15A.6.2.3.5 Reactor Vessel Water Level Control 15A.6.2.3.6 Reactor Vessel Pressure Control 15A.6.2.3.7 Nuclear System Temperature Control 15A.6.2.3.8 Nuclear System Water Quality Control 15A.6.2.3.9 Nuclear System Leakage Control 15A.6.2.3.10 Core Reactivity Control 15A.6.2.3.11 Control Rod Worth Control 15A.6.2.3.12 Refueling Restriction 15A.6.2.3.13 Containment & Reactor Building Pressure and Temperature Control SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxiii 15A.6.2.3.14 Stored Fuel Shielding, Cooling, and Reactivity Control 15A.6.2.4 Operational Safety Evaluations

15A.6.3 Anticipated (Expected) Operational Transients

15A.6.3.1 General 15A.6.3.2 Required Safety Actions/Related Unacceptable Result 15A.6.3.3 Event Definitions & Operational Safety Evaluations

15A.6.4 Abnormal (Unexpected) Operational Transients

15A.6.4.1 General 15A.6.4.2 Required Safety Actions/Related Unacceptable Results 15A.6.4.3 Event Definition & Operational Safety Evaluation

15A.6.5 Design Basis (Postulated) Accidents

15A.6.5.1 General 15A.6.5.2 Required Safety Actions/Unacceptable Results 15A.6.5.3 Event Definition and Operational Safety Evaluations

15A.6.6 Special (Plant Capability) Events

15A.6.6.1 General 15A.6.6.2 Required Safety Action/Unacceptable Results 15A.6.6.3 Event Definitions and Operational Safety Evaluation

15A.7 REMAINDER OF NSQA

15A.8 CONCLUSIONS

15A.9 LIST OF REFERENCES

15B ACCIDENT DOSE MODEL DESCRIPTIONS

15B.1 OFFSITE DOSE MODEL 15B.1.1 Total Body Gamma Dose

15B.1.2 Thyroid Inhalation Dose

SSES-FSAR Text Rev. 62 CHAPTER 15 TEXT Section Title FSAR Rev. 68 15-xxiv 15B.1.3 Beta Skin Dose

15B.2 CONTROL ROOM DOSE MODEL

15B.3 REFERENCES

APPENDIX 15C SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 FINAL SAFETY ANALYSIS REPORT - CYCLE SPECIFIC DATA

APPENDIX 15D SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 FINAL SAFETY ANALYSIS REPORT - CYCLE SPECIFIC DATA

APPENDIX 15E INITIAL CORE FOR SSES UNITS 1 AND 2 NON-LIMITING EVENTS SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxv 15.0-1 15.0-1A 15.0-2 15.0-3 15.0-4 15.0-5 SECTION15.0 - All Tables have been moved to Appendix 15C and D 15.1-1 15.1-2 15.1-3 15.1-4 15.1-5 15.1-6 15-1-7 Sequence or Events for Inadvertent Safety Relief Valve Opening Safety Relief Valve Opening Event Activity Above Suppression Pool (Curies)

Safety Relief Valve Opening Event Activity Release to Environs (Curies) Safety Relief Valve Opening Event Radiological Doses (REM-TEDE) These Tables Are not Used These Tables Are not Used These Tables Are not Used 15.2-1 15.2-2 15.2-3 15.2-4 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 15.2-15 15.2-16 SECTION 15.2 - All Tables have been moved to Appendix 15C and D 15.3-1 15.3-2 15.3-3 SECTION 15 All Tables have been moved to Appendix 15C and D 15.4-1 15.4-2 15.4-3 15.4-4 15.4-5 15.4-6 15.4-7 15.4-8 15.4-9 15.4-10 15.4-11 15.4-12 15.4-13 15.4-14 15.4-15 15.4-16 Sequence of Events for Control Rod Drop Accident Control Rod Drop Accident - Design Basis Analysis-Airborne Activity in Condense (2000 Failed Rods) Control Rod Drop Accident - Design Basis Analysis-Airborne Activity in Condenser (30 Failed Rods) Control Rod Drop Accident - Design Basis Analysis- Activity Released to Environs (2000 Failed Rods) Control Rod Drop Accident - Design Basis Analysis- Activity Released to Environs (30 Failed Rods) Control Rod Drop Accident - Activity Airborne in Condenser (Realistic Analysis) (2000 Rods) Control Rod Drop Accident - Activity Airborne in Condenser (Realistic Analysis) (30 Rods) Control Rod Drop Accident - Activity Released to Environs (Realistic Analysis) (2000 Rods) Control Rod Drop Accident - Activity Released to Environs (Realistic Analysis) (30 Rods) Control Rod Accident Radiological Effects Design Basis Case and Realistic Case Control Rod Drop Accident - Parameters to be Tabulated for Postulated Accident Analysis Sequence of Events for Misloaded Bundle/Accident/Sequence of Events for Rotated Bundle Accident These Tables are not Used These Tables are not Used These Tables are not Used These Tables are not Used

SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxvi 15.5-1 This Table Has Been Deleted

15.6-1 Sequence of Events for Instrument Line Break 15.6-2 Mass Releases-Instrument Line Break 15.6-3 Instrument Line Break Activity Released to the Environment (Curies) 15.6-4 Instrument Line Break Inside Secondary Containment Radiological Consequences 15.6-5 Instrument Line Break Accident - Parameters for Postulated Accident Analysis 15.6-6 Sequence of Events for Steam Line Break Outside Containment 15.6-7 Steam Line Break Accident Activity Released to the Environment (Curies) (Design Basis Analysis) 15.6-8 Steam Line Break Accident Activity Released to the Environment (Curies) (Realistic Analysis) 15.6-9 Steam Line Break Outside Containment Radiological Doses (rem) 15.6-10 Steam Line Break Accident - Parameters to be Tabulated for Postulated Accident Analyses 15.6-11 Loss of Coolant Accident - Activity Airborne in Primary Containment (Curies) (Design Basis Analysis) 15.6-12 This Table Has Been Intentionally Left Blank 15.6-13 Loss of Coolant Accident - Activity Airborne in Reactor Building (Curies) (Design Basis Analysis) 15.6-14 Loss of Coolant Accident - Activity Released to Environment (Curies) (Design Basis Analysis) 15.6-15 Loss of Coolant Accident - Activity Airborne in Primary Containment (Curies) (Realistic Analysis) 15.6-16 Loss of Coolant Accident - Activity Airborne in Reactor Building (Curies) (Realistic Analysis) 15.6-17 Loss of Coolant Accident - Activity Released to Environment (Curies) (Realistic Analysis) 15.6-18 Loss-of-Coolant Accident - Summary of Offsite Doses 15.6-19 This Table Has Been Intentionally Left Blank 15.6-20 This Table Has Been Intentionally Left Blank 15.6-21 Loss-of-Coolant Accident - Summary of Control Room Operator Doses (Design Basis Analysis) 15.6-22 Loss-of-Coolant Accident - Parameters for Postulated Accident Analysis 15.6-23 Sequence of Events for Feedwater Line Break Outside Containment 15.6-24 Feedwater Line Break Accident - Parameters for Postulated Accident Analyses 15.6-25 Feedwater Line Break Activity Released to Environment (Curies)

SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxvii 15.6-26 Feedwater Line Break Outside Containment Radiological Doses (rem) 15.7-1 Sequence of Events for Main Condenser Offgas Treatment System Failure 15.7-2 Activity Inventory Stored in Offgas Treatment System Activity Released to the Environs (curies) (Design Basis Analysis) 15.7-3 Activity Inventory Stored in Offgas Treatment System Activity Released to the Environs (curies) (Realistic Analysis) 15.7-4 Main Condenser Offgas Treatment System Failure Radiological Effects 15.7-5 Offgas Treatment System Failure Parameters for Postulated Accident Analysis 15.7-6 Failure of Air Ejector Lines Activity Released to the Environment (curies/sec) 15.7-7 Failure of Steam Jet Air Ejector Lines Radiological Consequences 15.7-8 Failure of Air Ejector Lines Parameters for Postulated Accident Analysis 15.7-9 RWCU Phase Separator Tank Failure Activity Release to Environment 15.7-10 RWCU Phase Separator Tank Failure Radiological Effects 15.7-11 RWCU Phase Separator Tank Failure 15.7-12 Refueling Accidents Activity Airborne in Reactor Building (Curies) (Design Basis Analysis) 15.7-13 Refueling Accidents Activity Released to Environment (Curies) (Design Basis Analysis) 15.7-14 Refueling Accidents - Activity Airborne in Reactor Building (Realistic Analysis) 15.7-15 Refueling Accidents - Activity Released to Environs (Realistic Analysis) 15.7-16 Refueling Accidents - Radiological Effects 15.7-16A Refueling Accidents with Additional Assembly (LUA) - Radiological Effects 15.7-17 Refueling Accidents - Parameters to be Tabulated for Postulated Accident Analyses 15.7-18 Sequence of Events for SJAE Failure

15.8-1 Input Parameters for ATWS Analysis 15.8-2 This Table Has Been Deleted 15.8-3 Input Operating Conditions for ATWS Analysis 15.8-4 This Table Has Been Deleted 15.8-5 Sequence of Events for MSIV Closure ATWS 15.8-6 This Table Has Been Deleted 15.8-7 Results for MSIV Closure ATWS Event 15.8-8 This Table Has Been Deleted 15.8-9 Sequence of Events for Prego ATWS 15.8-10 This Table Has Been Deleted 15.8-11 Results for Prego ATWS Event SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxviii 15.8-12 This Table Has Been Deleted 15.9-1 Unit 1 Station Blackout Instrumentation List 15.9-2 Unit 2 Station Blackout Instrumentation List 15A.2-1 Planned (Normal) Operation Cross-Correlation References 15A.2-2 Anticipated (Expected) Operational Transients Cross-Correlation References 15A.2-3 Abnormal (Unexpected) Operational Transients Cross-Correlation References 15A.2-4 Design Basis (Postulated) Accidents Cross-Correlation References 15A.2-5 Special (Plant Capability) Events Cross-Correlation References 15A.2-6 Plant Event Category: Planned (Normal) Operation Unacceptable Results Criteria 15A.2-7 Plant Event Category: Anticipated (Expected) Operational Transients Unacceptable Results Criteria 15A.2-8 Plant Event Category: Abnormal (Unexpected) Operational Transients Unacceptable Results Criteria 15A.2-9 Plant Event Category: Design Basis (Postulated) Accidents Unacceptable Result Criteria 15A.2-10 Plant Event Category: Special (Plant Capability) Events Unacceptable Results Considerations 15A.3-1 BWR Operating States 15A.6-1 Plant Events Applicable in Each BWR Operating State Planned (Normal)

Operation 15A.6-2 Plant Events Applicable in Each BWR Operating State Anticipated (Expected) Operational Transients 15A.6-3 Plant Events Applicable in Each BWR Operating State Abnormal (Unexpected) Operational Transients 15A.6-4 Plant Events Applicable in Each BWR Operating State Design Basis (Postulated) Accidents 15A.6-5 Plant Events Applicable in Each BWR Operating State Special (Plant Capability) Events 15.B-1 Control Room Atmospheric Dispersion Factors For Design Basis Accidents - X/Q 15B-2 Physical Data for Isotopes 15B-3 Breathing Rates 15B-4 This Table Has Been Deleted 15C.0-1 Results Summary of Transient Events Unit 1 15C.0-1A This Table Has Been Deleted 15C.0-2 Input Parameters and Initial Conditions for Transients Unit 1 15C.0-3 MCPR Fuel Cladding Integrity Safety Limit (All Fuel) Unit 1 SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxix 15C.0-4 Unit 1 Minimum MCPR Requirement For Single Loop Operation & 2 Loop Operation 15C.0-5 Average Scram Insertion Times Unit 1

15C.1.1-1 Sequence of Events for Loss of Feedwater Heating Unit 1 15C.1.2-1 Sequence of Events for Feedwater Controller Failure, Maximum Demand Unit 1 15C.1.3-1 Sequence of Events for Pressure Regulator Failure - Open Unit 1

15C.2.2-1 Sequence of Events for Generator Load Rejection Without Bypass and Turbine Trip Without Bypass Unit 1

15C.3.3-1 Pump Seizure Accident from Two Loop Operation Sequence of Events Unit 1 15C.3.3-2 Pump Seizure Accident from Single Loop Operation Sequence of Events Unit 1 15C.3.3-3 This Table Has Been Deleted 15C.3.3-4 This Table Has Been Deleted 15C.3.3-5 This Table Has Been Deleted 15C.3.3-6 This Table Has Been Deleted 15C.3.3-7 This Table Has Been Deleted 15C.3.3-8 This Table Has Been Deleted

15C.4.2-1 Sequence of Events - RWE Drift in Power Range Unit 1 15C.4.5-1 Sequence of Events for Recirculation Flow Controller Failure Unit 1 15C.4.7-1 Unit 1 Sequence of Events for Misloaded Bundle Accident 15C.4.9-1 Sequence of Events for Control Rod Drop Accident Unit 1 15C.4.9-2 Control Rod Drop Accident Unit 1 15C.4.9-3 This Table Has Been Deleted 15C.4.9-4 This Table Has Been Deleted 15C.4.9-5 This Table Has Been Deleted 15C.4.9-6 This Table Has Been Deleted 15C.4.9-7 This Table Has Been Deleted 15C.4.9-8 This Table Has Been Deleted 15D.0-1 Results Summary of Transient Events Unit 2 15D.0-1A This Table Has Been Deleted 15D.0-2 Input Parameters and Initial Conditions for Transients Unit 2 15D.0-3 MCPR Fuel Cladding Integrity Safety Limit (All Fuel) Unit 2 15D.0-4 Unit 2 Minimum MCPR Requirement for Single Loop Operation &

Minimum MCPR Requirement for 2 Loop Operation 15D.0-5 Average Scram Insertion Times Unit 2 SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxx 15D.1.1-1 Sequence of Events for Loss of Feedwater Heating Unit 2 15D.1.2-1 Sequence of Events for Feedwater Controller Failure, Maximum Demand Unit 2 15D.1.3-1 Sequence of Events for Pressure Regulator Failure - Open Unit 2

15D.2.2-1 Sequence of Events for Generator Load Rejection Without Bypass and Turbine Trip Without Bypass Unit 2

15D.3.3-1 Pump Seizure Accident from Two Loop Operation Sequence of Events Unit 2 15D.3.3-2 Pump Seizure Accident from Single Loop Operation Sequence of Events Unit 2 15D.3.3-3 This table has been deleted 15D.3.3-4 This table has been deleted 15D.3.3-5 This table has been deleted 15D.3.3-6 This table has been deleted 15D.3.3-7 This table has been deleted 15D.3.3-8 This table has been deleted

15D.4.2-1 Sequence of Events - RWE Drift in Power Range Unit 2 15D.4.5-1 Sequence of Events for Recirculation Flow Controller Failure Unit 2 15D.4.7-1 Sequence of Events for Misloaded Bundle Accident Unit 2 15D.4.9-1 Sequence of Events for Control Rod Drop Accident Unit 2 15D.4.9-2 Control Rod Drop Accident Unit 2 15D.4.9-3 This Table Has Been Deleted 15D.4.9-4 This Table Has Been Deleted 15D.4.9-5 This Table Has Been Deleted 15D.4.9-6 This Table Has Been Deleted 15D.4.9-7 This Table Has Been Deleted 15D.4.9-8 This Table Has Been Deleted

15E.0-1 Results Summary of Transient Events Units 1 and 2 Non-Limiting Events (Values are for the Initial Cores Only) 15E.0-2 Input Parameters and Initial Conditions for Transients Units 1 and 2 Initial Cycles 15E.1.1-1 Operator Actions When Reactor Scram is Incurred 15E.1.4-1 Sequence of Events for Inadvertent Safety Relief Valve Opening 15E-1-4-2 Safety Relief Valve Opening Event Activity Above Suppression Pool (curies)

SSES-FSAR Text Rev. 62 CHAPTER 15 TABLES Number Title FSAR Rev. 68 15-xxxi 15E-1-4-3 Safety Relief Valve Opening Event Activity Released to the Environs (curies) 15E-1-4-4 Safety Relief Valve Opening Event Offsite Radiological Doses (rems) 15E.1.6-1 Sequence of Events for Inadvertent RHR Shutdown Cooling Operation

15E.2.2-1 Sequence of Events for Figure 15E2.2-1 Generator Load Rejection, Bypass On 15E.2.3-1 Sequence of Events for Turbine Trip With Bypass Operable Figure 15E.2.3-1 15E.2.4-1 Sequence of Events for MSIV Closure, Figure 15E.2.4-1 15E.2.4-2 This table has been deleted 15E.2.4-3 This table has been deleted 15E.2.4-4 This table has been deleted 15E.2.5-1 Typical Rates of Decay for Condenser Vacuum 15E.2.5-2 Loss of Condenser Vacuum Sequence of Events for Figure 15E.2.5-1 15E.2.5-3 Trips Signals Associated With Loss of Condenser Vacuum 15E.2.6-1 Loss of Auxiliary Power Sequence of Events for Figure 15E.2.6-1 15E.2.6-2 Loss of All Grid Connections Sequence of Events for Figure 15E.2.6-2 15E.2.7-1 Loss of Feedwater Flow Sequence of Events for Figure 15E.2.7-1 15E.2.9-1 Sequence of Events for Failure of RHR Shutdown Cooling 15E.2.9-2 Input Parameters for Evaluation of Failure of RHR Shutdown Cooling

15E.3.1-1 Sequence of Events for Trip of One Recirculation Pump 15E.3.1-2 Sequence of Events for Trip of Two Recirculation Pumps

15E.4.4-1 Sequence of Events Abnormal Startup of Idle Recirculation Pump for Figure 15E.4.4-1 15E.5.1-1 Sequence of Events for Inadvertent Startup of HPCI

SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxii 15.0-1 15.0-2 15.0-3a 15.0-3b SECTION 15.0 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.1-1 15.1-2 15.1-3 15.1-4 SECTION 15.1 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.2-1 15.2-2 15.2-3 15.2-4 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 15.2-15 SECTION 15.2 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.3-1 15.3-2 15.3-3 SECTION 15.3 - All Figures have been moved to Appendix 15C and 15D and/or 15E 15.4-1 15.4-2 15.4-3 15.4-4 15.4-5 15.4-6 15.4-7 15.4-8 15.4-9 Leakage Path for Control Rod Drop Accident SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E SECTION 15.4 - This Figure has been moved to Appendix 15C and 15D and/or 15E 15.5-1 This Figure Has Been Renumbered to 15E.5.1-1

15.6-1 Leakage Path for Instrument Line Break 15.6-2 Steam Flow Schematic for Steam Break Outside Containment SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxiii 15.6-3 Leakage Flow for LOCA 15.6-4 Leakage Path for Feedwater Line Break Outside Containment

15.7-1 Leakage Path for Refueling Accidents

15A.2-1 Possible Inconsistencies in the Selection of Nuclear Safety Operational Requirements 15A.2-2 Methods Used to Derive NSO Requirements System and Sub-System Level Qualitative FMEA and Design Basis Confirmation Audits and Tech.

Specs. 15A.4-1 Format for Protection Sequence Diagrams 15A.4-2 Format for Safety System Auxiliary Diagrams 15A.4-3 Format for Commonality of Auxiliary Diagrams 15A.6-1 Safety System Auxiliaries 15A.6-2 Safety System Auxiliaries 15A.6-3 Safety Action Sequences for Planned Operations in State A 15A.6-4 Safety Action Sequences for Planned Operations in State B 15A.6-5 Safety Action Sequences for Planned Operations in State C 15A.6-6 Safety Action Sequences for Planned Operations in State D 15A.6-7 Protection Sequence for Manual or Inadvertent Scram 15A.6-8 Protection Sequence for Loss of Plant Instrument Air System 15A.6-9 Protection Sequence for Inadvertent Start-Up of HPCI's Pump 15A.6-10 Protection Sequences for Inadvertent Start-Up of Idle Recirculation Loop Pump 15A.6-11 Protection Sequence for Recirculation Loop Flow Control Failure - Maximum Demand 15A.6-12 Protection Sequence for Recirculation Loop Flow Control Failure -

Decreasing 15A.6-13 Recirculation Loop Pump Trip - One or Both 15A.6-14a Protection Sequences for Isolation of All Main Steamlines 15A.6-14b Protection Sequences for Isolation of the One Main Steamline 15A.6-15 Protection Sequences for Inadvertent Opening of a Safety/Relief Valve 15A.6-16 Protection Sequence for Control Rod Withdrawal Error - Startup and Refueling Operation 15A.6-17 Protection Sequence for Control Rod Withdrawal Error - Power Operation 15A.6-18 Protection Sequences for RHR'S - Loss of Shutdown Cooling Failure 15A.6-19 RHR'S - Shutdown Cooling Failure - Increased Cooling 15A.6-20 Protection Sequences for Loss of Feedwater Flow 15A.6-21 Protection Sequence for Loss of a Feedwater Heater 15A.6-22 Protection Sequences for Feedwater Controller Failure - Maximum Demand SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxiv 15A.6-23 Protection Sequences for Pressure Regulator Failure - Open 15A.6-24 Protection Sequence for Pressure Regulator Failure - Closed 15A.6-25 Protection Sequences for Main Turbine Trip with Bypass 15A.6-26 Protection Sequences for Loss of Main Condenser Vacuum 15A.6-27 Protection Sequences for Main Generator Trip with Bypass 15A.6-28 Protection Sequence for Loss of Normal AC Power - Aux Transformer Failure 15A.6-29 Protection Sequences for Loss of Normal AC Power - Grid Connection Loss 15A.6-30 Protection Sequences Main Generator Trip - Without Bypass 15A.6-31 Protection Sequences Main Turbine Trip - With Bypass Failure 15A.6-32 Protection Sequence for Inadvertent Loading and Operations of Fuel Assembly in Improper Position 15A.6-33 This Figure Has Been Intentionally Left Blank 15A.6-34 This Figure Has Been Intentionally Left Blank 15A.6-35 This Figure Has Been Intentionally Left Blank 15A.6-36 This Figure Has Been Intentionally Left Blank 15A.6-37 This Figure Has Been Intentionally Left Blank 15A.6-38 Protection Sequences for Recirculation Loop Pump Seizure 15A.6-39 Protection Sequence for Recirculation Loop Pump Shaft Break 15A.6-40 Protection Sequences for Control Rod Drop Accident 15A.6-41 Protection Sequences for Fuel Handling Accident 15A.6-42 Protection Sequences for Loss-of-Coolant Piping Breaks in RCPB - Inside Containment 15A.6-43 Protection Sequences for Liquid, Steam, Large, Small Piping Breaks Outside Containment 15A.6-44 This Figure Has Been Intentionally Left Blank 15A.6-45 This Figure Has Been Intentionally Left Blank 15A.6-46 Protection Sequences for Gaseous Radwaste System Leak or Failure 15A.6-47 Protection Sequence for Off-Gas Treatment System Failure 15A.6-48 Protection Sequence for Liquid Radwaste System Leak or Failure 15A.6-49 Protection Sequence for Liquid Radwaste System Storage Tank Failure 15A.6-50 Protection Sequence for Spend Fuel Cask Drop 15A.6-51 Protection Sequence for Reactor Shutdown - From Anticipated Transient Without Scram 15A.6-52 Protection Sequences for Reactor Shutdown - From Outside Main Control Room 15A.6-53 Protection Sequence for Reactor Shutdown - Without Control Rods 15A.6-54 Figure Deleted 15A.6-54-1 Commonality of Auxiliary Systems - DC Power Systems (125/250 Volts) 15A.6-54-2 Event Identification For Figure 15A.6-54, Page 1 of 2 SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxv 15A.6-54-3 Event Identification For Figure 15A.6-54, Page 2 of 2 15A.6-55 Figure Deleted 15A.6-55-1 Commonality of Auxiliary Systems - AC Power Systems (120/480/4160 Volts) 15A.6-55-2 Event Identification For Figure 15A.6-55, Page 1 of 2 15A.6-55-3 Event Identification For Figure 15A.6-55, Page 2 of 2 15A.6-56 Figure Deleted 15A.6-56-1 Commonality of Auxiliary Systems - Equipment Area Coding System 15A.6-56-2 Event Identification For Figure 15A.6-56 15A.6-57 Figure Deleted 15A.6-57-1 Commonality of Auxiliary Systems - Plant Service Water System 15A.6-57-2 Event Identification For Figure 15A.6-57 15A.6-58 Commonality of Auxiliary Systems - RHR Service Water System 15A.6-59 Figure Deleted 15A.6-59-1 Commonality of Auxiliary Systems - Suppression Pool Storage 15A.6-59-2 Event Identification For Figure 15A.6-59 15A.6-60 Figure Deleted 15A.6-61 Figure Deleted 15A.6-62 Figure Deleted 15A.6-63 Figure Deleted 15A.6-64 Figure Deleted 15A.6.65 Figure Deleted

15C.0-1 This Figure Has Been Deleted 15C.1.2-1-1 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-2 Susquehanna Feedwater controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-3 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-4 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.2-1-5 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip 15C.1.3-1-1 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15C.1.3-1-2 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.1.3-1-3 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.1.3-1-4 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.1.3-1-5 Pressure Regulator Failure - Steam Flow 130% of Rated 15C.2.2-1-1 Susquehanna Generator Load Reject Without Bypass and Turbine Trip SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxvi Without Bypass 15C.2.2-1-2 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.2.2-1-3 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.2.2-1-4 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.2.2-1-5 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15C.3.3-1 Pump Seizure Accident Two Loop Operation (101/108) 15C.3.3-2 Pump Seizure Accident Single Loop Operation (76/52) 15C.4.5-1-1 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-2 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-3 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-4 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.5-1-5 Susquehanna Recirculation Flow Controller Failure Init. Cond. 69% Power 60 Mlbs/hr Flow 15C.4.9-1 This Figure Has Been Deleted

15D.0-1 This Figure Has Been Deleted 15D.1.2-1-1 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-2 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-3 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-4 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.2-1-5 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip 15D.1.3-1-1 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15D.1.3-1-2 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15D.1.3-1-3 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 MWt 15D.1.3-1-4 Pressure Regulator Failure - Steam Flow at 130% of Steam Flow at 3441 SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxvii MWt 15D.1.3-1-5 Pressure Regulator Failure - Steam Flow at 130% of Rated 15D.2.2-1-1 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-2 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-3 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-4 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.2.2-1-5 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass 15D.3.3-1 Pump Seizure Accident Two Loop Operation (101/108) 15D.3.3-2 Pump Seizure Accident Single Loop Operation (76/52) 15D.4.5-1-1 This Figure Has Been Deleted 15D.4.5-1-2 This Figure Has Been Deleted 15D.4.5-1-3 This Figure Has Been Deleted 15D.4.5-1-4 This Figure Has Been Deleted 15D.4.5-1-5 This Figure Has Been Deleted 15D.4.9-1 This Figure Has Been Deleted

15E.0-1 Typical Power/Flow Map 15E.0-2 Scram Position and Reactivity Characteristics 15E.2.2-1 Susquehanna Generator Load Rejection, With Bypass On 15E.2.3-1 Turbine Trip, Trip Scram, Bypass and RPT On 15E.2.4-1 Three-Second Closure of All MSIV's With Position Switch Scram Trip 15E.2.5-1 Loss of Condenser Vacuum at 2 Inches Per Second 15E.2.6-1 Loss of Auxiliary Power Transformer 15E.2.6-2 Loss of All Grid Connections 15E.2.7-1 Loss of All Feedwater Flow 15E.2.7-2 Loss of Feedwater Core Power, Heat Flux and Core Flow 15E.2.7-3 Loss of Feedwater, Feedwater Flow Steam Flow and RCIC Flow 15E.2.9-1-1 ADS/RHR Cooling Loops 15E.2.9-1-2 Notes for Figure 15E.2.9-1-1 15E.2.9-1-3 Notes for Figure 15E.2.9-1-1 15E.2.9-2 Summary of Paths Available to Achieve Cold Shutdown 15E.2.9-3 Vessel Temperature and Pressure Versus Time (Activity C1 or C2) 15E.2.9-4 Suppression Pool Temperature Versus Time (90 Service Water Temperature) Capacity C1 or C2 15E.2.9-5 Activity C1 Alternate Shutdown Cooling Path Utilizing RHR Loop B 15E.2.9-6 Activity C2 Alternate Shutdown Cooling Path Utilizing RHR Loop A SSES-FSAR Text Rev. 62 CHAPTER 15 FIGURES Number Title FSAR Rev. 68 15-xxxviii 15E.3.1-1 Trip of One Recirculation Pump Motor 15E.3.1-2 Trip of Both Recirculation Pump Motors 15E.4.4-1 Startup of Idle Recirculation Loop Pump

15E.5.1-1 Inadvertent Startup of HPCI SSES-FSARTOCRev.58FSARRev.6516-iCHAPTER16TECHNICALSPECIFICATIONSTABLEOFCONTENTSTEXTSectionTitle16.1PRELIMINARYTECHNICALSPECIFICATIONS 16.2PROPOSEDFINALTECHNICALSPECIFICATIONS 16.3TECHNICALREQUIREMENTSMANUALS SSES-FSAR TOC Rev. 65 FSAR Rev. 68 17-i CHAPTER 17 QUALITY ASSURANCE TABLE OF CONTENTS TEXT Section Title 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION

17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE

17.2.0 Introduction

17.2.1 Organization

17.2.1.1 Chief Nuclear Officer 17.2.1.2 Site Vice President 17.2.1.3 Plant Manager 17.2.1.4 General Manager-Nuclear Engineering 17.2.1.5 General Manager-Operations 17.2.1.6 Manager-Special Projects 17.2.1.7 Manager-Nuclear Oversight 17.2.1.8 Manager-Performance Improvement 17.2.1.9 Manager-Nuclear Design Engineering 17.2.1.10 Manager-Nuclear Fuels and Analysis 17.2.1.11 Manager-Nuclear Maintenance 17.2.1.12 Manager-Nuclear Operations 17.2.1.13 Manager-Nuclear Regulatory Affairs 17.2.1.14 Manager-Nuclear Security 17.2.1.15 Manager-Nuclear Training 17.2.1.16 Manager-Radiation Protection 17.2.1.17 Manager-Station Engineering 17.2.1.18 General Manager-Work Management 17.2.1.19 Manager-Plant Chemistry/Environment 17.2.1.20 PPL Electric Utilities 17.2.1.21 Talen Energy Corporation 17.2.1.22 General Manager-Programs 17.2.1.23 Manager-Engineering Programs 17.2.1.24 General Manager-Maintenance

SSES-FSAR TOC Rev. 65 CHAPTER 17 TEXT Section Title FSAR Rev. 68 17-ii 17.2.2 Quality Assurance Program

17.2.3 Design Control

17.2.4 Procurement Document Control

17.2.5 Instructions, Procedures, and Drawings

17.2.6 Document Control

17.2.7 Control of Purchased Material, Equipment, and Services

17.2.8 Identification and Control of Materials, Parts, and Components

17.2.9 Control of Special Processes

17.2.10 Inspection

17.2.11 Test Control

17.2.12 Control of Measuring and Test Equipment

17.2.13 Handling, Storage, and Shipping

17.2.14 Inspection, Test, and Operating Status

17.2.15 Nonconforming Materials, Parts, or Components

17.2.16 Corrective Action

17.2.17 Quality Assurance Records

17.2.18 Audits

SSES-FSAR TOC Rev. 65 CHAPTER 17 TABLES Number Title FSAR Rev. 68 17-iii 17.2-1 Quality Assurance Program Description Compliance Matrix

17.2-2 Operational Policy Statement Cross Reference Matrix with 10CFR50 Appendix B Criteria

SSES-FSAR TOC Rev. 65 CHAPTER 17 FIGURES Number Title FSAR Rev. 68 17-iv 17.2-1 Hierarchy of Operational Quality Assurance Documents

17.2-2 Talen Energy Corporation Management Organization Applicable to Susquehanna SES

17.2-3 Susquehanna Nuclear, LLC Management Organization

17.2-4 Nuclear Oversight Organization

SSES-FSARTOCRev.59FSARRev.6518-iCHAPTER18RESPONSESTOTMIRELATEDREQUIREMENTSTABLEOFCONTENTSTEXTSectionTitle18.0RESPONSESTOTMIRELATEDREQUIREMENTS18.1RESPONSETOREQUIREMENTSINNUREG 073718.1.1ShiftTechnicalAdvisor(I.A.1.1) 18.1.1.1StatementofRequirement18.1.1.2Interpretation18.1.1.3StatementofResponse18.1.2ShiftSupervisorResponsibilities(I.A.1.2)18.1.3ShiftManning(I.A.1.3)18.1.3.1StatementofRequirement18.1.3.2Interpretation18.1.3.3StatementofResponse18.1.4ImmediateUpgradingOfReactorOperatorandSeniorReactorOperatorTrainingandQualifications(I.A.2.1)18.1.4.1StatementofRequirement18.1.4.2Interpretation18.1.4.3StatementofResponse18.1.5AdministrationofTrainingPrograms(I.A.2.3) 18.1.5.1StatementofRequirement18.1.5.2Interpretation18.1.5.3StatementofResponse18.1.6ReviseScopeAndCriteriaforLicensingExaminations(I.A.3.1) 18.1.6.1StatementofRequirement18.1.6.2Interpretation 18.1.6.3StatementofResponse SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-ii18.1.7EvaluationOfOrganizationandManagement(I.B.1.2)18.1.7.1StatementofRequirement18.1.7.2Interpretation18.1.7.3StatementofResponse18.1.8Short-TermAccidentandProcedureReview(I.C.1) 18.1.8.1StatementofRequirement18.1.8.2Interpretation18.1.8.3StatementofResponse18.1.9ShiftReliefandTurnoverProcedures(I.C.2)18.1.10ShiftSupervisorResponsibility(I.C.3)18.1.11ControlRoomAccess(I.C.4)18.1.12FeedbackOfOperatingExperience(I.C.5)18.1.12.1StatementofRequirement18.1.12.2Interpretation18.1.12.3StatementofResponse18.1.13VerifyCorrectPerformanceofOperatingActivities(I.C.6) 18.1.13.1StatementofRequirement18.1.13.2Interpretation18.1.13.3StatementofResponse18.1.14NSSSVendorReviewofProcedures(I.C.7)18.1.15PilotMonitoringofSelectedEmergencyProceduresforNearTermOperatingLicenses(I.C.8)18.1.16ControlRoomDesignReview(I.D.1)18.1.16.1StatementofRequirement18.1.16.2Interpretation18.1.16.3StatementofResponse18.1.17PlantSafetyParameterDisplaySystem(I.D.2) 18.1.17.1StatementofRequirement SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-iii18.1.17.1.1Function18.1.17.1.2Location18.1.17.1.3Size18.1.17.1.4Staffing18.1.17.1.5DisplayConsideration18.1.17.1.6DesignCriteria18.1.17.2Interpretation18.1.17.3StatementofResponse18.1.18TrainingDuringLow-PowerTesting(I.G.1)18.1.19ReactorCoolantSystemVents(II.B.1)18.1.19.1StatementofRequirement18.1.19.2Interpretation18.1.19.3StatementofResponse18.1.20PlantShielding(II.B.2) 18.1.20.1StatementofRequirement 18.1.20.1.1DocumentationRequiredforVitalAreaAccess18.1.20.1.2DocumentationRequiredforEquipmentQualification18.1.20.2Interpretation 18.1.20.2.1SourceTerms18.1.20.2.2Post-AccidentSystems18.1.20.2.3EquipmentQualification18.1.20.3StatementofResponse 18.1.20.3.1Introduction18.1.20.3.2DesignReviewBases18.1.20.3.2.1SystemsSelectedforShieldingReview 18.1.20.3.2.1.1CoreSpray,HPCI,RCICandRHR(LPCIMode)18.1.20.3.2.1.2RHR(ShutdownCoolingMode)18.1.20.3.2.1.3RHR(SuppressionPoolCoolingMode)18.1.20.3.2.1.4RHR(ContainmentSprayMode)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-iv18.1.20.3.2.1.5CRDHydraulicSystem18.1.20.3.2.1.6RWCUSystem18.1.20.3.2.1.7LiquidRadwasteSystem18.1.20.3.2.1.8ThisSubsectionIsNotUsed18.1.20.3.2.1.9SamplingSystems18.1.20.3.2.1.10StandbyGasTreatmentSystem18.1.20.3.2.1.11ContainmentAtmosphere(Drywell)18.1.20.3.2.1.12SuppressionPool(Wetwell)18.1.20.3.2.2RadioactiveSourceReleaseFractions18.1.20.3.2.3SourceTermQuantification18.1.20.3.2.3.1DecayTime18.1.20.3.2.3.2DilutionVolume18.1.20.3.2.4System/SourceSummary18.1.20.3.2.5DoseIntegrationFactorsforPersonnel18.1.20.3.3ShieldingReviewMethodology 18.1.20.3.3.1RadiationDoseCalculationModel18.1.20.3.3.2Post-AccidentRadiationZoneMaps18.1.20.3.3.3PersonnelRadiationExposureGuidelines18.1.20.3.3.4VitalAreaIdentificationandAccess18.1.20.3.3.4.1VitalAreaClarification18.1.20.3.3.4.2VitalAreaAccess18.1.20.3.4Results 18.1.20.3.4.1PostAccidentRadiationLevels18.1.20.3.4.2IntegratedPersonnelExposures18.1.20.3.4.3ReactorBuildingAccessibility18.1.20.3.4.4ControlBuildingAccessibility18.1.21Post-AccidentSampling(II.B.3) 18.1.21.1StatementofCommitment 18.1.21.2.1Introduction18.1.21.2.1SystemDescription SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-v18.1.21.2.2SamplePoints18.1.21.2.3IsolationValvesandSampleLines18.1.21.2.4PipingStation18.1.21.3.2.4SampleStationandControlPanels 18.1.21.2.5.1GasSampler18.1.21.2.5.2LiquidSampler18.1.21.2.5.3SampleStationVentilation18.1.21.2.5.4SampleStationSump18.1.21.2.5.5SampleHandlingToolsandTransportContainers 18.1.21.2.5.6SampleStationPowerSupply18.1.21.2.6DescriptionofSamplePreparation/ChemistryandNuclearCountingFacilities18.1.21.2.7SummaryDescriptionofProcedures18.1.21.2.7.1Chemical/RadiochemicalProcedures 18.1.21.2.7.1.1Introduction18.1.21.27.2.1SamplePreparation18.1.21.2.7.2SystemTestingandOperatingTraining 18.1.22TrainingForMitigatingCoreDamage(II.B.4) 18.1.22.1StatementofRequirement18.1.22.2Interpretation18.1.22.3StatementofResponse18.1.23ReliefandSafetyValveTestRequirements(II.D.1) 18.1.23.1StatementofRequirement18.1.23.2Interpretation18.1.23.3StatementofResponse18.1.24Safety/ReliefValvePositionIndication(II.D.3)18.1.24.1StatementofRequirement18.1.24.2Interpretation18.1.24.3StatementofResponse SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-vi18.1.25AuxiliaryFeedwaterSystemEvaluation(II.E.1.1)18.1.26AuxiliaryFeedwaterSystemInitiationAndFlow(II.E.1.2)18.1.27EmergencyPowerforPressurizerHeaters(II.E.3.1)18.1.28DedicatedHydrogenPenetrations(II.E.4.1)18.1.28.1StatementofRequirement18.1.28.2Interpretation18.1.28.3StatementofResponse18.1.29ContainmentIsolationDependability(II.E.4.2) 18.1.29.1StatementofRequirement18.1.29.2Interpretation18.1.29.3StatementofResponse18.1.30Accident-MonitoringInstrumentation(II.F.1) 18.1.30.1StatementofRequirement 18.1.30.1.1NobleGasEffluentMonitor18.1.30.1.2SamplingandAnalysisofPlantEffluents18.1.30.1.3ContainmentHigh-RangeRadiationMonitor18.1.30.1.4ContainmentPressureMonitor18.1.30.1.5ContainmentWaterLevelMonitor18.1.30.1.6ContainmentHydrogenMonitor18.1.30.2Interpretation18.1.30.3StatementofResponse18.1.30.3.1NobleGasEffluentMonitor18.1.30.3.2SamplingandAnalysisofPlantEffluents18.1.30.3.3ContainmentHigh-RangeRadiationMonitor18.1.30.3.4ContainmentPressureMonitor18.1.30.3.5ContainmentWaterLevelMonitor18.1.30.3.6ContainmentHydrogenMonitor18.1.31InstrumentforDetectionofInadequateCoreCooling(II.F.2) 18.1.31.1StatementofRequirement18.1.31.2Interpretation SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-vii18.1.31.3StatementofResponse18.1.31.3.1Introduction18.1.31.3.2ReactorWaterLevelInstrumentationReport18.1.31.3.3InadequateCoreCoolingReport18.1.31.3.4Conclusion18.1.32EmergencyPowerforPressurizerEquipment(II.G.1)18.1.33ReviewESFValves(II.K.1.5)18.1.34OperabilityStatus(II.K.1.10)18.1.35TripPressurizerLow-LevelCoincidentSignalBistables(II.K.1.17) 18.1.36OperatorTrainingforPromptManualReactorTrip(II.K.1.20)18.1.37AutomaticSafetyGradeAnticipatoryReactorTrip(II.K.1.21)18.1.38AuxiliaryHeatRemovalSystemProcedures(II.K.1.22)18.1.39ReactorVesselLevelProcedures(II.K.1.23)18.1.40CommissionOrdersOnBabcockandWilcoxPlants(II.K.2)18.1.41AutomaticPower-OperatedReliefValveIsolationSystem(II.K.3.1)18.1.42ReportOnPower-OperatedReliefValveFailures(II.K.3.2)18.1.43ReportingSafety/ReliefValveFailuresandChallenges(II.K.3.3)18.1.44AutomaticTripofReactorCoolantPumpsDuringALOCA(II.K.3.5)18.1.45EvaluationofPower-OperatedReliefValveOpeningProbability(II.K.3.7)18.1.46ProportionalIntegralDerivativeControllerModification(II.K.3.9)18.1.47ProposedAnticipatoryTripModification(II.K.3.10)18.1.48Power-OperatedReliefValveFailureRate(II.K.3.11)18.1.49AnticipatoryReactorTriponTurbineTrip(II.K.3.12)18.1.50SeparationOfHighPressureCoolantInjectionandReactorCoreIsolationCoolingSystemInitiationLevels(II.K.3.13)18.1.50.1StatementofRequirement18.1.50.2Interpretation18.1.50.3StatementofResponse18.1.51ModifyBreak-DetectionLogictoPreventSpuriousIsolationofHighPressureCoolantInjectionandReactorCoreIsolationCooling(II.K.3.15)18.1.51.1StatementofRequirement18.1.51.2Interpretation18.1.51.3StatementofResponse18.1.52ReductionofChallengesandFailuresofReliefValves(II.K.3.16)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-viii18.1.52.1StatementofRequirement18.1.52.2Interpretation18.1.52.3StatementofResponse18.1.53ReportOnOutagesOfEmergencyCoreCoolingSystems(II.K.3.17)18.1.53.1StatementofRequirement18.1.53.2Interpretation18.1.53.3StatementofResponse18.1.54ModificationofAutomaticDepressurizationSystemLogic(II.K.3.18) 18.1.54.1StatementofRequirement18.1.54.2Interpretation18.1.54.3StatementofResponse18.1.55RestartofCoreSprayAndLowPressureCoolantInjectionSystems(II.K.3.21)18.1.55.1StatementofRequirement18.1.55.2Interpretation18.1.55.3StatementofResponse18.1.56AutomaticSwitchoverofReactorCoreIsolationCoolingSystemSuction(II.K.3.22)18.1.56.1StatementofRequirement18.1.56.2Interpretation18.1.56.3StatementofResponse18.1.57ConfirmAdequacyofSpaceCoolingForHighPressureCoolantInjectionandReactorCoreIsolationCoolingSystems(II.K.3.24)18.1.57.1StatementofRequirement18.1.57.2Interpretation18.1.57.3StatementofResponse18.1.58EffectofLossofAlternating-CurrentPoweronRecirculationPumpSeals(II.K.3.25)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-ix18.1.58.1StatementofRequirement18.1.58.2Interpretation18.1.58.3StatementofResponse18.1.59ProvideACommonReferenceLevelforVesselLevelInstrumentation(II.K.3.27)18.1.59.1StatementofRequirement18.1.59.2Interpretation18.1.59.3StatementofResponse18.1.60VerifyQualificationofAccumulatorsonAutomaticDepressurizationSystemValves(II.K.3.28)18.1.60.1StatementofRequirement18.1.60.2Interpretation18.1.60.3StatementofResponse18.1.61RevisedSmall-BreakLossofCoolantAccidentMethods(II.K.3.30) 18.1.61.1StatementofRequirement18.1.61.2Interpretation18.1.61.3StatementofResponse18.1.62Plant-SpecificCalculationsToShowCompliancewith10CFRPart50.46(II.K.3.31)18.1.62.1StatementofRequirement18.1.62.2Interpretation18.1.62.3StatementofResponse18.1.63EvaluationofAnticipatedTransientswithSingleFailureToVerifyNoFuelCladdingFailure(II.K.3.44)18.1.63.1StatementofRequirement18.1.63.2Interpretation18.1.63.3StatementofResponse18.1.64EvaluationofDepressurizationWithOtherThanTheAutomaticDepressurizationSystem(II.K.3.45)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-x18.1.64.1StatementofRequirement18.1.64.2Interpretation18.1.64.3StatementofResponse18.1.65MichelsenConcerns(II.K.3.46) 18.1.65.1StatementofRequirement18.1.65.2Interpretation18.1.65.3StatementofResponse18.1.66EmergencyPreparedness-ShortTerm(III.A.1.1)18.1.67UpgradeEmergencySupportFacilities(III.A.1.2)18.1.67.1StatementofRequirement18.1.67.2Interpretation18.1.67.3StatementofResponse18.1.68EmergencyPreparedness-LongTerm(III.A.2) 18.1.68.1StatementofRequirement18.1.68.2Interpretation18.1.68.3StatementofResponse18.1.69IntegrityOfSystemsOutsideContainmentLikelyToContainRadioactiveMaterial(III.D.1.1)18.1.69.1StatementofRequirement18.1.69.2Interpretation18.1.69.3StatementofResponse18.1.70InplantIodineRadiationMonitoring(III.D.3.3)18.1.70.1StatementofRequirement18.1.70.2Interpretation18.1.70.3StatementofResponse18.1.71ControlRoomHabitabilityRequirements(III.D.3.4) 18.1.71.1StatementofRequirement SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xi18.1.71.1.1RequirementsforLicenseesthatMeetCriteria18.1.71.1.2RequirementsforLicenseesthatDoNotMeetCriteria18.1.71.1.3DocumentationandImplementation18.1.71.2Interpretation18.1.71.3StatementofResponse18.1.72References 18.2RESPONSETOREQUIREMENTSINNUREG069418.2.1ShiftTechnicalAdvisor(I.A.1.1)18.2.2ShiftSupervisorAdministrativeDuties(I.A.1.2)18.2.2.1StatementofRequirement18.2.2.2Interpretation18.2.2.3StatementofResponse18.2.3ShiftManning(I.A.1.3)18.2.4ImmediateUpgradingOfOperatorAndSeniorOperatorTrainingAndQualification(I.A.2.1)18.2.5ReviseScopeAndCriteriaForLicensingExaminations(I.A.3.1)18.2.6EvaluationOfOrganizationAndManagementImprovementsOfNear-TermOperatingLicenseApplicants(I.B.1.2)18.2.6.1StatementofRequirement18.2.6.2Interpretation18.2.6.3StatementofResponse18.2.7Short-TermAccidentAnalysisAndProcedureRevision(I.C.1)18.2.8ShiftReliefAndTurnoverProcedures(I.C.2)18.2.8.1StatementofRequirement18.2.8.2Interpretation18.2.8.3StatementofResponse18.2.9ShiftSupervisorResponsibilities(I.C.3) 18.2.9.1StatementofRequirement18.2.9.2Interpretation18.2.9.3StatementofResponse SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xii18.2.10ControlRoomAccess(I.C.4)18.2.10.1StatementofRequirement18.2.10.2Interpretation18.2.10.3StatementofResponse18.2.11ProceduresForFeedbackOfOperatingExperienceToPlantStaff (I.C.5)18.2.12NSSSVendorReviewOfProcedures(I.C.7)18.2.12.1StatementofRequirement18.2.12.2Interpretation18.2.12.3StatementofResponse18.2.13PilotMonitoringOfSelectedEmergencyProceduresNear-TermOperatingLicenseApplicants(I.C.8)18.2.13.1StatementofRequirement18.2.13.2Interpretation18.2.13.3StatementofResponse18.2.14ControlRoomDesign(I.D.1)18.2.15TrainingDuringLowPowerTesting(I.G.1)18.2.15.1StatementofRequirement18.2.15.2Interpretation18.2.15.3StatementofResponse18.2.16ReactorCoolantSystemVents(II.B.1)18.2.17PlantShielding(II.B.2)18.2.18Post-AccidentSampling(II.B.3)18.2.19TrainingForMitigatingCoreDamage(II.B.4)18.2.20ReliefAndSafetyValveTestRequirements(II.D.1)18.2.21ReliefAndSafetyValvePositionIndication(II.D.3)18.2.22ContainmentIsolationDependability(II.E.4.2)18.2.23AdditionalAccidentMonitoringInstrumentation(II.F.1)18.2.24InadequateCoreCoolingInstruments(II.F.2)18.2.25AssuranceOfProperESFFunctioning(II.K.1.5)

SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xiii18.2.25.1StatementofRequirement18.2.25.2Interpretation18.2.25.3StatementofResponse18.2.26SafetyRelatedSystemOperabilityStatus(II.K.1.10) 18.2.26.1StatementofRequirement18.2.26.2Interpretation18.2.26.3StatementofResponse18.2.27TripPressurizerLow-LevelCoincidentSignalBistables(II.K.1.17)18.2.28OperatorTrainingForPromptManualReactorTrip(II.K.1.20)18.2.29AutomaticSafetyGradeAnticipatoryTrip(II.K.1.21)18.2.30AuxiliaryHeatRemovalSystemsOperatingProcedures(II.K.1.22)18.2.30.1StatementofRequirement18.2.30.2Interpretation18.2.30.3StatementofResponse18.2.31ReactorLevelInstrumentation(II.K.1.23) 18.2.31.1StatementofRequirement18.2.31.2Interpretation18.2.31.3StatementofResponse18.2.32CommissionOrdersOnBabcockAndWilcoxPlants(II.K.2)18.2.33ReportingRequirementsForSafety/ReliefValveFailuresOrChallenges(II.K.3.3)18.2.33.1StatementofRequirement18.2.33.2Interpretation18.2.33.3StatementofResponse18.2.34ProportionalIntegralDerivativeController(II.K.3.9)18.2.35AnticipatoryReactorTripModification(II.K.3.10)18.2.36PowerOperatedReliefValveFailureRate(II.K.3.11)18.2.37AnticipatoryReactorTriponTurbineTrip(II.K.3.12)18.2.38EmergencyPreparedness-ShortTerm(II.A.1.1)18.2.38.1StatementofRequirement18.2.38.2Interpretation SSES-FSARTOCRev.59CHAPTER18TEXTSectionTitleFSARRev.6518-xiv18.2.38.3StatementofResponse18.2.39UpgradeEmergencySupportFacilities(III.A.1.2)18.2.40PrimaryCoolantSourcesOutsideContainment(III.D.1.1)18.2.41InplantRadiationMonitoring(III.D.3.3)18.2.42ControlRoomHabitability(III.D.3.4)

SSES-FSARTOCRev.59CHAPTER18TABLESNumberTitleFSARRev.6518-xv18.1-1InterimRequiredShiftStaffing18.1-2InitialCoreIsotopicInventory 18.1-3PostAccidentRadiationZoneClassification 18.1-4VitalAreas 18.1-5PrincipalDoseRateContributorsinPlantArea 18.1-6ThisTableHasBeenDeleted 18.1-7ThisTableHasBeenDeleted 18.1-8TrainingCriteriaforMitigatingCoreDamage 18.1-9MitigatingCoreDamageCourseOutline 18.1-10ContainmentIsolationActuationProvision 18.1-11ThisTableHasBeenDeleted 18.1-12Actuation/IsolationSignalCodesandCorrespondingActuatingSwitches18.1-13MeteorologicalInformation 18.1-14ThisTableHasBeenDeleted 18.1-15ThisTableHasBeenDeleted 18.1-16ThisTableHasBeenDeleted 18.1-17InformationRequiredforControlRoomHabitabilityEvaluation 18.1-18PossibleICCDetectionDevices 18.2-1TestingProgramOutline SSES-FSARTOCRev.59CHAPTER18FIGURESNumberTitleFSARRev.6518-xvi18.1-1RadiationLevelsfortheSitePlan18.1-2RadiationLevelsfortheSitePlanElevations646'-0,"645'0,"and656'-0"18.1-3RadiationLevelsforElevations670'-0"and676'-0" 18.1-4RadiationLevelsforElevations683'-0,"699'-0,"714'-0,"and716'-3"18.1-5RadiationLevelsforElevations719'-1,"729'-0,"and741'-1"18.1-6RadiationLevelsforElevations749'-1,"754'-0,"762'-0,"771'-0,"and783'-0"18.1-7RadiationLevelsforElevations779'-1,"799'-1,"and806'-0" 18.1-8RadiationLevelsforElevations818'-1"and872'-41/2" 18.1-9ThisFigureHasBeenDeleted 18.1-10ThisFigureHasBeenDeleted 18.1-11ThisFigureHasBeenDeleted 18.1-12TypicalHPCIRCICSteamlineBreakDetectionLogic 18.1-13TypicalReactorWaterLevelDisplay 18.1-14DowncomerWaterLevelHistory 18.1-15WaterLevelasanIndicatorofCoreOverheating 18.1-16CladdingTemperatureSensitivitytoCoreRecoveryTime