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NineMilePointUnit2FSARTABLE5'-8LEAKDETECTIONMETHODS,ACCURACY,ANDSENSITIVITYLeakDetectionMethodDrywellfloordraintanklevelDrywellequipmentdraintanklevel4AirborneparticulatesGaseousradioactivity~Accurac1gpm1gpmSensitivit1gpm/hr1gpm/hr6.6-12uCi/cc''.9-07uCi/cc'~'OTE:6.6-12=6.6x10'''Theairborneparticulateradiationlevelcorrespondingtoa1"gpm/hrleakrateis1.1-07uCi/cc.'~'Thegaseousradioactivitylevelcorrespondingtoa1gpm/hrleakrateis6.3-07uCi/cc.Amendment191of1May1985  
NineMilePointUnit2FSARTABLE5'-8LEAKDETECTIONMETHODS,ACCURACY,ANDSENSITIVITYLeakDetectionMethodDrywellfloordraintanklevelDrywellequipmentdraintanklevel4AirborneparticulatesGaseousradioactivity~Accurac1gpm1gpmSensitivit1gpm/hr1gpm/hr6.6-12uCi/cc''.9-07uCi/cc'~'OTE:6.6-12=6.6x10'''Theairborneparticulateradiationlevelcorrespondingtoa1"gpm/hrleakrateis1.1-07uCi/cc.'~'Thegaseousradioactivitylevelcorrespondingtoa1gpm/hrleakrateis6.3-07uCi/cc.Amendment191of1May1985  


~~ltNineMilePointUnit2FSARrrequirements.The'materialforstuds,nuts,andwashersisSA-540GradeB23orB24atthe130,000psi-specifiedminimumyieldstrengthslevel.Hardness.testsareperformedonallmainclosureboltingtodemonstrate'thatheattreatmenthasbeenproperlyperformed.Aminimumof45ft-lbCharpyV-notch(C)energyand25milsV,lateralexpansionisrequiredat70~F.Themaximumreportedultimatetensilestrengthisbelowthe170,000-psimaximumspecified.inRegulatoryGuide1.65.Also,theCharpyimpacttest,requirementsof10CFR50AppendixGaresatisfied,sincethelowestreportedQenergyis46ft-lbat+10OF,comparedtotherequirementof45ft-lbat70F,andthelowestreportedC>expansionwas26mils,comparedtothe25milsrequired.Studs,nuts,andwashersareultrasonicallyexaminedinaccordancewithASMESectionIII,ParagraphNB-2585,andthefollowingadditionalrequire-ments:1.Examinationwasperformedafterheattreatmentandpriortomachiningthreads.2.3.Straightbeamexaminationwasperformedon100percentofeachstud.Referencestandardfortheradialscanisa1/2-indiameterflat-bottomholehavingadepthequalto10percentofthematerialthickness.FortheendscanthestandardofParagraphNB-2585isused.NutsandwasherswereexaminedbyanglebeamfromtheoutsidecircumferenceinaccordancewithASMESA-388inboththeaxialandcircumferentialdirections.The.surfaceexaminationsrequiredbyParagraphNB-2583areappliedafterheattreatmentandthreading.Therearenometalplatingsappliedtoclosurestuds,nuts,orwashers.A-manganese-phosphatecoatingisappliedtothreadedareasofstudsandnutsandbearingareasofnutsandwasherstoassistinretaininglubricantonthesesurfaces.Subsequenttofabrication,thestudsarelubricatedwithagraphite/alcoholornickelpowderbaselubricant.RegulatoryGuide1.65definesacceptablematerialsandtestingprocedureswithregardtoreactorvesselclosurestudboltingforlight-water-cooledreactors.Amendment115.3-9June1984 NineMilePointUnit:2FSARTheRPVclosurestudsareSA-540GradeB23or24(AISI-4340)andhaveamaximumultimatetensilestrengthof170ksi.Additionally,=,theboltingmaterial.wasspecifiedtohaveCharpyV-notchimpactpropertiesof45ft-lbminimumwith25milslateralexpansion.Nondestructiveexaminationbeforeandafterthreadingisspecifiedtobeinaccordance,,with=ASMESectionIII,SubsubarticleNB-2580whichcomplieswithReglatoryGuide1.65(C.2).InaccordancewithRegulatoryGuide1.65(C.2.b),theboltingmaterialswereultrasonicallyexaminedafterfinalheattreatmentandpriortothreading.Asrequiredforcompliance,theexamination'asdoneinaccordancewithSA-388.,Theproceduresapprovedforuseinpracticewerejudgedtoensurecomparablematerialqualityand,moreover,wereconsideredadequateonthebasisofcompliancewiththeapplicable"requirementsofASMESectionIII,ParagraphNB-2583.Additionally,'straightbeamexaminationwasperformedon100percentofcylindricalsurfaces,andfrombothendsofeachstudusinga3/4-inmaximumdiametertransducer.Inadditiontothecode-requirednotch,thereferencestandardfortheradialscancontaineda1/2-indiameterflat-bottomholewithadepthequalto10percentofthethickness'heendscanstandardcontaineda1/4-indiameterflat-bottomhole1/2-indeep.Anglebeam,ultrasonicexaminationwasperformedontheoutercylindricalsurfaceinbothaflatandcircumferential.direction.Surfaceexaminationswereperformedonthestudsandnutsafterfinalheattreatmentandthreading,asspecifiedbyRegulatoryGuide1.65,inaccordancewithParagraphNB-2583oftheapplicableASMEcode.Radialscan-calibrationisbasedona1/2-in(12.7-mm)diameterflatbottomholeofadepthequalto10percentofthematerialthickness.AnglebeamexaminationisperformedontheoutercylindricalsurfaceofnutsandwashersinaccordancewithASMESA-388inbothaxialandcircumferentialdirections.Noindicationgreaterthan,theindicationfromtheapplicablecalibrationfeaturewasacceptable.Adistance-amplitudecorrectioncurveinaccordancewithParagraphNB-2858isusedforthelongitudinalwaveexamination.InrelationshiptoRegulatoryGuide1.65(C.3),studboltingsurfacesareallowedtobeexposedtohigh-purityfillwater;nutsandwashersaredrystoredduringrefueling.5.3-10 NineMilePointUnit2FSARthistime,theturbinebypasssystemdivertsthesteam.tothemaincondenser,andthefeedwatersystemsuppliesthemakeupwaterrequiredtomaintainreactorvesselinventory.Intheeventthereactorvesselisisolatedandthefeedwatersupplyunavailable,reliefvalvesareprovidedtoautomatically(orremotemanually)maintainvesselpressurewithindesirablelimits.Thewaterlevelinthereactorvesseldropsduetocontinuedsteamgenerationbydecayheat.Uponreachingapredeterminedlowlevel,theRCICsystemisinitiatedautomatically.Theturbine-drivenpumpsuppliesdemineralizedmakeupwaterfromthecondensatestoragetanktothereactorvessel.Analternatesourceofwaterisavailablefromthesuppressionpool.TheRCICsystemallowsautomaticswitchoverofpumpsuctionfromthecondensatestoragetanktothesuppressionpoolifthecondensatestoragetankfallstoapresetlowlevel.Lowlevelinthetankismonitoredbytworedundantlevel.transmitters.Ifeithertransmittersenseslowlevel,pumpsuctionisautomaticallytransferredtothesuppressionpool.Theturbineisdrivenwithaportionofthedecayheatsteamfromthereactorvesselandexhauststothesuppressionpool.Suppressionpoolwaterisnotmaintaineddemineralizedandisusedonlyintheeventallsourcesofdemineralizedwaterhavebeenexhausted.Ifthemainfeedwatersystemisnotoperable,areactorscramisautomaticallyinitiatedwhenreactorwaterlevelfallstoLevel3.TheoperatorcanthenremotelymanuallyinitiatetheRCICsystemfromthemaincontrolroom,orthesystemisautomaticallyinitiatedasfollows.Reactorwaterlevelcontinuestodecreaseduetoboil-offuntilLevel2isreached.Atthispoint,thehigh-pressurecorespray(HPCS)and:thereactorcoreisolationcooling(RCIC)systemsareautomaticallyinitiatedtosupplymakeupwatertotheRPV.Thesesystems'ontinueautomaticinjectionuntilthereactorwaterlevelreachesLevel8,atwhichtimetheHPCSinjectionvalveisclosedandtheRCICsteamsupplyvalveisclosed.Inthenonaccidentcase,the-RCICsystemisnormallytheonlymakeup.systemusedtofurnishsubsequentmakeupwatertotheRPV.TheoperatorremotelymanuallyshutsdowntheHPCSsystem,fromthemaincontrolroom.WhenlevelreachesLevel2againduetolossofinventorythroughthemainsteamreliefvalvesortothemaincondenser,theRCICsystemautomaticallyrestartsasdescribedinSectionII.K.3.13.Thissystemthenmaintainsthecoolantmakeupsupply.RPVpressureisregulatedbytheautomaticorremotemanualoperationofthemainsteamreliefvalveswhichdischargetothesuppressionpool.USARRevision05.4-17April1989 NineMilePointUnit2FSARToremovedecayheatduringaplannedisolationevent,assumingthatthemaincondenserisnotavailable,thesteamcondensingmodeoftheRHRsystemcanbemanuallyinitiated.ResidualsteamisroutedthroughtheRHRheatexchangerswhereitiscondensedandcooled,thenreturnedtotheRPVthroughaninterconnectionwiththeRCICpump.Thus,closedloopcoolingisprovidedbythismode.Ifthesteamcondensingmodeisunavailableforanyreason,thesafetyreliefvalvescanbeusedtodumptheresidualsteamtothesuppressionpool.ThesuppressionpoolwillthenbecooledbyremotemanualalignmentoftheRHRsysteminthesuppressionpoolcoolingmodewhichroutesthepoolwaterthroughtheRHRheatexchangers,coolsit,andreturnsittothesuppressionpoolinaclosedcycle.MakeupwatertotheRPVisstillsuppliedbytheRCICsystem.FortheaccidentcasewiththeRPVathighpressure,theHPCSsystemcanalsobeusedtoautomaticallyprovidetherequiredmakeupflow.Nomanualoperationsarerequired.IftheHPCSsystemispostulatedtofailattheseconditionsandtheRCICcapacityisinsufficient,theautomaticdepressurizationsystem(ADS)willautomaticallyinitiatedepressurizationoftheRPVtopermitthecondensatepumpsorthelowpressureECCS(LPCIandLPCS)toprovidemakeupcoolant.WhenevertheRCICsystemisinitiated,theLSTGturbineistrippedtopreventwaterinductionintotheturbine,andthecontrolroomisalarmedthattheRCICinjectionvalveisopen.Therefore,althoughmanualactionscanbetakentomitigatetheconsequencesofalossoffeedwater,therearenoshorttermmanualactionswhichmustbetaken.Sufficientsystemsexisttoautomaticallymitigatetheseconsequences.DuringRCICoperation,thesuppressionpoolactsastheheatsinkforsteamgeneratedbyreactordecayheat.Thisresultsinariseinpoolwatertemperature.Heatexchangersintheresidualheatremoval(RHR)systemareusedtomaintainthepoolwatertemperaturewithinacceptablelimitsbycoolingthewaterdirectlyorbycondensinggeneratedsteam.ThecondensatedischargefromtheRHRheatexchangersmaybeusedasRCICpumpsuctionsupplyoritmaybedirectedtothesuppressionpool;'TheRCICsystemisequippedwithadischargelinefillpumpthat,operatestomaintainthepumpdischargelineinafilledcondition.KeepingthedischargelinefilledreducesthelagtimebetweenpumpstartupandattainmentoffullflowtotheRPV.Additionally,itsoperationeliminatesthepossibilityofRCICpumpsdischargingintoadrypipeandminimizeswaterhammereffects.ThefillpumpisclassifiedasCategoryIandSafetyClass2.ThepumpmotorisUSARRevision05.4-17aApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER76Athrough6CINSTRUMENTATIONANDCONTROLSYSTEMSTitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3ComponentsVolume1313131313141515151515157.17.27'7'7.57.67~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16161616,1717I179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17181920~2121,2223USARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSIONSYSTEM2310.110.210.310.4Summary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem232324CHAPTER11RADIOACTIVEWASTEMANAGEMENTll.111.211.311.411.5SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendixllACHAPTER12RADIATIONPROTECTION2424252525252512.112.212.312.412~5CHAPTER1313.113.213.313.413.513.6AppendixesEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B252525262626262626.26262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26  
~~ltNineMilePointUnit2FSARrrequirements.The'materialforstuds,nuts,andwashersisSA-540GradeB23orB24atthe130,000psi-specifiedminimumyieldstrengthslevel.Hardness.testsareperformedonallmainclosureboltingtodemonstrate'thatheattreatmenthasbeenproperlyperformed.Aminimumof45ft-lbCharpyV-notch(C)energyand25milsV,lateralexpansionisrequiredat70~F.Themaximumreportedultimatetensilestrengthisbelowthe170,000-psimaximumspecified.inRegulatoryGuide1.65.Also,theCharpyimpacttest,requirementsof10CFR50AppendixGaresatisfied,sincethelowestreportedQenergyis46ft-lbat+10OF,comparedtotherequirementof45ft-lbat70F,andthelowestreportedC>expansionwas26mils,comparedtothe25milsrequired.Studs,nuts,andwashersareultrasonicallyexaminedinaccordancewithASMESectionIII,ParagraphNB-2585,andthefollowingadditionalrequire-ments:1.Examinationwasperformedafterheattreatmentandpriortomachiningthreads.2.3.Straightbeamexaminationwasperformedon100percentofeachstud.Referencestandardfortheradialscanisa1/2-indiameterflat-bottomholehavingadepthequalto10percentofthematerialthickness.FortheendscanthestandardofParagraphNB-2585isused.NutsandwasherswereexaminedbyanglebeamfromtheoutsidecircumferenceinaccordancewithASMESA-388inboththeaxialandcircumferentialdirections.The.surfaceexaminationsrequiredbyParagraphNB-2583areappliedafterheattreatmentandthreading.Therearenometalplatingsappliedtoclosurestuds,nuts,orwashers.A-manganese-phosphatecoatingisappliedtothreadedareasofstudsandnutsandbearingareasofnutsandwasherstoassistinretaininglubricantonthesesurfaces.Subsequenttofabrication,thestudsarelubricatedwithagraphite/alcoholornickelpowderbaselubricant.RegulatoryGuide1.65definesacceptablematerialsandtestingprocedureswithregardtoreactorvesselclosurestudboltingforlight-water-cooledreactors.Amendment115.3-9June1984 NineMilePointUnit:2FSARTheRPVclosurestudsareSA-540GradeB23or24(AISI-4340)andhaveamaximumultimatetensilestrengthof170ksi.Additionally,=,theboltingmaterial.wasspecifiedtohaveCharpyV-notchimpactpropertiesof45ft-lbminimumwith25milslateralexpansion.Nondestructiveexaminationbeforeandafterthreadingisspecifiedtobeinaccordance,,with=ASMESectionIII,SubsubarticleNB-2580whichcomplieswithReglatoryGuide1.65(C.2).InaccordancewithRegulatoryGuide1.65(C.2.b),theboltingmaterialswereultrasonicallyexaminedafterfinalheattreatmentandpriortothreading.Asrequiredforcompliance,theexamination'asdoneinaccordancewithSA-388.,Theproceduresapprovedforuseinpracticewerejudgedtoensurecomparablematerialqualityand,moreover,wereconsideredadequateonthebasisofcompliancewiththeapplicable"requirementsofASMESectionIII,ParagraphNB-2583.Additionally,'straightbeamexaminationwasperformedon100percentofcylindricalsurfaces,andfrombothendsofeachstudusinga3/4-inmaximumdiametertransducer.Inadditiontothecode-requirednotch,thereferencestandardfortheradialscancontaineda1/2-indiameterflat-bottomholewithadepthequalto10percentofthethickness'heendscanstandardcontaineda1/4-indiameterflat-bottomhole1/2-indeep.Anglebeam,ultrasonicexaminationwasperformedontheoutercylindricalsurfaceinbothaflatandcircumferential.direction.Surfaceexaminationswereperformedonthestudsandnutsafterfinalheattreatmentandthreading,asspecifiedbyRegulatoryGuide1.65,inaccordancewithParagraphNB-2583oftheapplicableASMEcode.Radialscan-calibrationisbasedona1/2-in(12.7-mm)diameterflatbottomholeofadepthequalto10percentofthematerialthickness.AnglebeamexaminationisperformedontheoutercylindricalsurfaceofnutsandwashersinaccordancewithASMESA-388inbothaxialandcircumferentialdirections.Noindicationgreaterthan,theindicationfromtheapplicablecalibrationfeaturewasacceptable.Adistance-amplitudecorrectioncurveinaccordancewithParagraphNB-2858isusedforthelongitudinalwaveexamination.InrelationshiptoRegulatoryGuide1.65(C.3),studboltingsurfacesareallowedtobeexposedtohigh-purityfillwater;nutsandwashersaredrystoredduringrefueling.5.3-10 NineMilePointUnit2FSARthistime,theturbinebypasssystemdivertsthesteam.tothemaincondenser,andthefeedwatersystemsuppliesthemakeupwaterrequiredtomaintainreactorvesselinventory.Intheeventthereactorvesselisisolatedandthefeedwatersupplyunavailable,reliefvalvesareprovidedtoautomatically(orremotemanually)maintainvesselpressurewithindesirablelimits.Thewaterlevelinthereactorvesseldropsduetocontinuedsteamgenerationbydecayheat.Uponreachingapredeterminedlowlevel,theRCICsystemisinitiatedautomatically.Theturbine-drivenpumpsuppliesdemineralizedmakeupwaterfromthecondensatestoragetanktothereactorvessel.Analternatesourceofwaterisavailablefromthesuppressionpool.TheRCICsystemallowsautomaticswitchoverofpumpsuctionfromthecondensatestoragetanktothesuppressionpoolifthecondensatestoragetankfallstoapresetlowlevel.Lowlevelinthetankismonitoredbytworedundantlevel.transmitters.Ifeithertransmittersenseslowlevel,pumpsuctionisautomaticallytransferredtothesuppressionpool.Theturbineisdrivenwithaportionofthedecayheatsteamfromthereactorvesselandexhauststothesuppressionpool.Suppressionpoolwaterisnotmaintaineddemineralizedandisusedonlyintheeventallsourcesofdemineralizedwaterhavebeenexhausted.Ifthemainfeedwatersystemisnotoperable,areactorscramisautomaticallyinitiatedwhenreactorwaterlevelfallstoLevel3.TheoperatorcanthenremotelymanuallyinitiatetheRCICsystemfromthemaincontrolroom,orthesystemisautomaticallyinitiatedasfollows.Reactorwaterlevelcontinuestodecreaseduetoboil-offuntilLevel2isreached.Atthispoint,thehigh-pressurecorespray(HPCS)and:thereactorcoreisolationcooling(RCIC)systemsareautomaticallyinitiatedtosupplymakeupwatertotheRPV.Thesesystems'ontinueautomaticinjectionuntilthereactorwaterlevelreachesLevel8,atwhichtimetheHPCSinjectionvalveisclosedandtheRCICsteamsupplyvalveisclosed.Inthenonaccidentcase,the-RCICsystemisnormallytheonlymakeup.systemusedtofurnishsubsequentmakeupwatertotheRPV.TheoperatorremotelymanuallyshutsdowntheHPCSsystem,fromthemaincontrolroom.WhenlevelreachesLevel2againduetolossofinventorythroughthemainsteamreliefvalvesortothemaincondenser,theRCICsystemautomaticallyrestartsasdescribedinSectionII.K.3.13.Thissystemthenmaintainsthecoolantmakeupsupply.RPVpressureisregulatedbytheautomaticorremotemanualoperationofthemainsteamreliefvalveswhichdischargetothesuppressionpool.USARRevision05.4-17April1989 NineMilePointUnit2FSARToremovedecayheatduringaplannedisolationevent,assumingthatthemaincondenserisnotavailable,thesteamcondensingmodeoftheRHRsystemcanbemanuallyinitiated.ResidualsteamisroutedthroughtheRHRheatexchangerswhereitiscondensedandcooled,thenreturnedtotheRPVthroughaninterconnectionwiththeRCICpump.Thus,closedloopcoolingisprovidedbythismode.Ifthesteamcondensingmodeisunavailableforanyreason,thesafetyreliefvalvescanbeusedtodumptheresidualsteamtothesuppressionpool.ThesuppressionpoolwillthenbecooledbyremotemanualalignmentoftheRHRsysteminthesuppressionpoolcoolingmodewhichroutesthepoolwaterthroughtheRHRheatexchangers,coolsit,andreturnsittothesuppressionpoolinaclosedcycle.MakeupwatertotheRPVisstillsuppliedbytheRCICsystem.FortheaccidentcasewiththeRPVathighpressure,theHPCSsystemcanalsobeusedtoautomaticallyprovidetherequiredmakeupflow.Nomanualoperationsarerequired.IftheHPCSsystemispostulatedtofailattheseconditionsandtheRCICcapacityisinsufficient,theautomaticdepressurizationsystem(ADS)willautomaticallyinitiatedepressurizationoftheRPVtopermitthecondensatepumpsorthelowpressureECCS(LPCIandLPCS)toprovidemakeupcoolant.WhenevertheRCICsystemisinitiated,theLSTGturbineistrippedtopreventwaterinductionintotheturbine,andthecontrolroomisalarmedthattheRCICinjectionvalveisopen.Therefore,althoughmanualactionscanbetakentomitigatetheconsequencesofalossoffeedwater,therearenoshorttermmanualactionswhichmustbetaken.Sufficientsystemsexisttoautomaticallymitigatetheseconsequences.DuringRCICoperation,thesuppressionpoolactsastheheatsinkforsteamgeneratedbyreactordecayheat.Thisresultsinariseinpoolwatertemperature.Heatexchangersintheresidualheatremoval(RHR)systemareusedtomaintainthepoolwatertemperaturewithinacceptablelimitsbycoolingthewaterdirectlyorbycondensinggeneratedsteam.ThecondensatedischargefromtheRHRheatexchangersmaybeusedasRCICpumpsuctionsupplyoritmaybedirectedtothesuppressionpool;'TheRCICsystemisequippedwithadischargelinefillpumpthat,operatestomaintainthepumpdischargelineinafilledcondition.KeepingthedischargelinefilledreducesthelagtimebetweenpumpstartupandattainmentoffullflowtotheRPV.Additionally,itsoperationeliminatesthepossibilityofRCICpumpsdischargingintoadrypipeandminimizeswaterhammereffects.ThefillpumpisclassifiedasCategoryIandSafetyClass2.ThepumpmotorisUSARRevision05.4-17aApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER76Athrough6CINSTRUMENTATIONANDCONTROLSYSTEMSTitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3ComponentsVolume1313131313141515151515157.17.27'7'7.57.67~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16161616,1717I179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17181920~2121,2223USARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSIONSYSTEM2310.110.210.310.4Summary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem232324CHAPTER11RADIOACTIVEWASTEMANAGEMENTll.111.211.311.411.5SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendixllACHAPTER12RADIATIONPROTECTION2424252525252512.112.212.312.412~5CHAPTER1313.113.213.313.413.513.6AppendixesEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B252525262626262626.26262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26}}
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Revision as of 23:56, 17 May 2018

Forwards Rev 2 to Updated FSAR for Nine Mile Point Unit 2 & Annual Safety Evaluation Summary Rept
ML18038A334
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/31/1990
From: WILCZEK S W
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18038A335 List:
References
NMP2L-1258, NUDOCS 9011090077
Download: ML18038A334 (597)


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ACCELERATEDDISTRIBUTIONDEMONSTRATIONSYSTEMt<IREGULATORYXNFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9011090077DOC.DATE:90/10/31NOTARIZED:YESFACIL:50-410NineMilePointNuclearStation,Unit2,NiagaraMohaAUTH.NAMEAUTHORAFFILIATIONWILCZEK,S.W.NiagaraMohawkPowerCorp.~~j/+~pggRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)

SUBJECT:

ForwardsRev2toupdatedFSARforNineMilePointUnit2annualsafetyevaluationsummaryrept.DISTRIBUTIONCODE'053DCOPIESRECEIVED'LTRlENCL/SIZEJTITLE:ORSubmittal:UpdatedFSAR(50.71)andAmendmentsNOTES:DOCETg5041R(sXZ+l~5~DSRECIPXENTIDCODE/NAMEPDl-1LAMARTIN,R.INTERNAL:ACRSNRR/DST8E2RGN1EXTERNAL:XHSNSICCOPIESLTTRENCL10112210111111RECXPIENTXDCODE/NAMEPD1-1PDAEOQDJ)OA/XRBGF01NRCPDRSAICLINER,RCOPIESLTTRENCL1011111111DDDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL10DD 0

NIAGARAMOHAWKPOWERCORPORATION/301PLAINFIELDROAD,SYRACUSE,N.Y.13212/TELEPHONE(315)474-1511U.S.NuclearRegulatoryCommissionAttention:DocumentControlDeskWashington,D.C.20555October31,1990NMP2L1258Re:NineMilePointUnit2DocketNo.50-410NPF-6Gentlemen:Pursuanttotherequirementsof10C.F.R.550.71(e)and10C.F.R.550.59(b),NiagaraMohawkPowerCorporationherebysubmitsRevision2totheNineMilePointNuclearStationUnit2UpdatedSafetyAnalysisReport(USAR)andtheannualSafetyEvaluationSummaryReport.Underseparatecover,wearetransmittingupdatestomaterialwhichhaspreviouslybeengivenproprietarystatusbytheNRCpursuanttotheprovisionsof10C.F.R.52.790.One(1)signedoriginalandten(10)qopiesoftheUSARRevision2areenclosed.CopiesarealsobeingsentdirectlytotheRegionalAdministrator,RegionI,and)heNRCResidentInspectoratNineMilePoint.TheUSARrevisioncontainschangesmadesincethesubmittalofRevision1inOctober1989.Includedareanumberofeditorialchanges.Thesechangescorrectspellingandtypographicalerrors;updatereferencestoUSARfigures,sections,documentsortablesofcontents;improvegrammarorclarity;ormoveinformationtomoreappropriatelocations.Thecertificationrequiredby10C.F.R.550.71(e)(2)isattachedtothisletter.ThetextandtablechangesassociatedwithUSARRevision2havebeenpreparedusinganewtextmanagementsystemrecentlyimplementedbyNiagaraMohawk.Consequently,theappearanceoftheRevision2replacementpagesdiffersslightlyfromtheexistingUSARpages;mostnotably,thetextisnotright-margin-justified.InNiagaraMohawk'sletterofOctober25,1989(NMP2L1210),transmittingtheUpdatedSafetyAnalysisReport(USAR)Revision1,weidentifiedcertainitemsforwhichcomplianceandverificationeffortsassociatedwiththeUSARupdatewerenotyetcompleted.AstatusoftheremainingopenverificationitemswasprovidedinNiagaraMohawk'slettersofNovember29,1989(NMP2L1217)andJanuary30,1990(NMP2L1224).AfinaldispositionforeachofthefourcategoriesofopenitemsoriginallyidentifiedintheOctober25,1989,letterisasfollows:~C'Ig901109'0077901031PDRADQCK05000410KPDC I

alI~OPENITEM1DescritionThemajorityofopenverificationitemsinvolveinconsistenciesinthelevelofdetailshownonUSARfigureswhencomparedtothesourcedesigndocuments.Theseitemsdonotinvolvequestionsofaccuracy,butwillrequiredevelopmentofstandardsandrevisionofalargenumberofdesigndrawingstosatisfyNiagaraMohawk'sinternalverificationprocedures.StatusVerificationactivitiesassociatedwiththereviewofdrawings,includinggeneralarrangement,communication,shielding,andradiationzonedrawings,havebeencompleted.AppropriaterevisionstothedrawingsandtheassociatedUSARfigureshavebeenidentifiedandarebeingprocessedinaccordancewithnormalprocedures.OPEITEM2DescritionSeveralverificationitemsrelatingtosetpointsonUSARfiguresarestillbeingcompleted.TheseitemshaveraisedquestionsaboutsetpointscontainedintheUSAR.Proceduresareinplace,including10C.F.R.550.59evaluations,toensureadequatecontrolofsetpointchangesintheplant;however,setpointsonlogicsketches(LSKs)intheUSARarenotroutinelyupdated.SetpointsshownonLSKsareprovidedasguidevaluesandarenotas-built.ThisisidentifiedontheUSARfiguresbynotesthatstate,"Setpointsshownonlogicdrawingsareforlogicclarificationonlyandmaybeonlyapproximationsoftheactualprocesssetpoints.Setpointdatasheetsmustbereferredtoforactualprocesssetpoints."AsmallnumberofthesetpointsintheUSARtextwereoriginallyverifiedusingthedesignLSKs.Thereis,therefore,thepossibilitythatthesesetpointsarealsonotas-built.Aprogramisnowbeingdevelopedtoverifysetpointsinthetextagainsttheas-builtvalues.StatusAllsetpointsreferencedintheUSARtexthavebeenidentified.Eachidentifiedsetpointhasbeenre-verifiedagainsttheas-builtplantconfigurationbyreviewingappropriatesourcedocuments(e.g.,setpointdatasheets).AnynecessaryUSARchangeshavebeeninitiatedandarebeingprocessedinaccordancewithnormalprocedures.

1I

~~DescritionSomeitemsfromthisupdate(Revision1)arestillinthefinalverificationprocess.StatusAllpreviouslyopenverificationitemsfromUSARRevisions0and1havebeencompleted.AppropriateUSARchangeshavebeenincorporatedinRevision2.OPENITEM4DescritionSourcedocumentationforchangesdevelopedbyGEhadnotbeenavailable,preventingfinalverification.SatusAsstatedpreviouslyinNiagaraMohawk'sNovember29,1989,letter(NMP2L1217),allGE-developedchangeshavebeenverified.TheenclosedannualSafetyEvaluationSummaryReportcontainsbriefdescriptionsofchangestothefacilitydesign,USAR,procedures,tests,andexperiments.NoneoftheSafetyEvaluationsinvolvedanunreviewedsafetyquestionasdefinedin10C.F.R.550.59(a)(2).IfyouhaveanyquestionsconcerningthisUSARrevision,pleasecontactJohnJ.Laffreyat(315)428-7334.Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATIONS.W.Wilczek,Jr.VicePresidentNuclearSupportJJL/kmsEnclosurexc:RegionalAdministrator,RegionIMr.R.A.Capra,DirectorMr.R.E.Martin,ProjectDirectorMr.W.A.Cook,SeniorResidentInspectorRecordsManagement v1~l1 UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterof]]NIAGARAMOHAWKPOWERCORPORATION](NineMilePointNuclearStation]UnitNo.2)]DocketNo.50-410CERTIFICATIONS.W.Wilczek,Jr.,beingdulysworn,statesthatheisVicePresident,NuclearSupportofNiagaraMohawkPowerCorporation;thatheisauthorizedonthepartofsaidCompanytosignandfilewiththeNuclearRegulatoryCommissionthiscertification;andthat,inaccordancewith10C.F.R.$50.71(e)(2),theinformationcontainedintheattachedletterandupdatedFi.nalSafetyAnalysisReportaccuratelypresentschangesmadesincetheprevioussubmittalnecessarytoreflectinformationandanalysessubmittedtotheCommissionorpreparedpursuanttoCommissionrequirementandcontainsanidentificationofchangesmadeundertheprovisions-of.-$50.59butnotpreviouslysubmittedtotheCommission.S.W.>1czek,Jr.VicePresidentNuclearSupportSubscribedandsworntobeforemethrsundayof~C,1990.NotaryPulicDlANER.NlMBALLpub"c5rnoSrarsofNrrrrYoredagaCotrmyt3o.493@@QtrardlodInOnondagaMyCommlsslonExplros EnclosuretoNMP2L1258NINENILEPOINT-UNIT2SAFETYEVALUATIONSUNNARYREPORTDocketNo.50-410LicenseNo.NPF-69 0

SafetyEvaluationSummaryReportPage1of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:87-063,Rev.1Mod.PN2Y86MX162Fig.11.4-1aSolidWasteManagementSystem(WSS)TitleofChange:SealWatertoWasteSludgePumpsDescriptionofChange:Anexistingwastesludgetransferpumpwasreplacedwithtwonewcentrifugalslurrypumps(2WSS-P50A6B).Additionalpumpsealwatersupplyandreturnlineswereconnectedfromtheexistinglinesforthesecondpump;onenewmanualisolationvalvewasprovidedoneachoffourlines.ThischangewaspreviouslyreportedinletterNMP2L1177,datedOctober26,1988.Anadditionalchangewasmade,basedonRevision1ofthesafetyevaluation,tominimizewiringchanges.Flowelement2WSS-FE103wasrelocatedtoupstreamofvalve2WSS-V308(fromdownstream)onthesameline.SafetyEvaluationSummary:Thesolidwastemanagementsystemisnotsafety-relatedandisnotrequiredforsafeshutdownoftheplant.Relocationoftheflowelementdoesnotaffectitsoperationasitisstilllocatedonthecommonpumpdischargepiping.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.NOTE:ThissafetyevaluationrevisionisbeingreportedatthistimeinsupportofthechangestoUSARFigure11.4-1a,whichwasrevisedinUSARRevision1.

SafetyEvaluationSummaryReportPage2of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:87-118,Rev.1Mod.PN2Y87MZ132Figures6.2-38(Sh.5),6.2-71a,6.2-71bSystemContainmentAtmosphereMonitoringSystem(CMS)TitleofChange:AddPSIAPressureMonitorforDrywellandSuppressionChamberPressureIndicationDescriptionofChange:0TechnicalSpecification3/4.6.1.5requiresdrywellandsuppressionchamberinternalpressuretobemaintainedbetween14.2and15.45psia.Previouspressuremonitorsonlyreadoutinpsig.Thismodificationaddedtwo(2)transmittersandtwo(2)controlroomindicatorswithpsiascales.ThisnowenablespressuremonitoringintheTechnicalSpecificationsidentifiedscale.Thenewmonitorsareidentifiedas2CMS*PT178and2CMS-PT179.SafetyEvaluationSummary:Theaddedequipmentofthismodificationonlyperformsamonitoringfunctionanddoesnotimpactthesafeoperationofotheroperatingequipment.Nosafety-relatedfunctionsareaffected.Althoughitdoesnotperformasafetyfunction,2CMS*PT178isdesignedandinstalledassafety-relatedsinceitshares"acommonsensinglinewith2CMS*PT1A,whichissafety-related.2CMS-PT179isinstalledasnonsafety-related.Itsharesasensinglinewith2CMS-PT168.Thissensinglineutilizesasafety-relatedexcessflowcheckvalvetoprotecttheintegrityoftheprimarycontainmentinaccordancewithRegulatoryGuide1.11.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

0 I4p4'(!qt.I-l~'~Safvaluation,Sum;;yReport"Page,3of.112j7vafSafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:87-148,Rev.1Mod.PN2Y86MX184Figures9.3-5j,11.2-1f,11.2-1hSystem:TitleofChange:LiquidRadwasteSystem(LWS)WasteandRegeneratorEvaporationReboilerCleanoutDescriptionofChange:Thepipingfromthewasteevaporatorreboilerbottomswas3/4"andconnectedtovalvesV516,V517,V574andV575.Duringstartup,theselinesbecamepluggedduetosodiumsulfate(NA,SO,)crystallization.Inordertocorrectthissituation,thepipingsizewasincreasedto1-1/2"andthecurrentvalveswerereplacedwithpairsofvalves.Flushconnectionswerelocatedbetweenthem.Awarmwaterflushlineandhosewerealsoadded.Existingheattracingwasremovedandnewheattracinginstalled.SafetyEvaluationSummary:Thismodificationhasnoeffectonsafeshutdownorsafeplantoperation.AllmodificationworkwasperformedinaccordancewiththerequirementsofRegulatoryGuide1.143.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.I ce>~>S SafetyEvaluationSummaryReportPage4of112SafetyEvaluationNo.:XmplementationDocumentNo.:87-151Mod.PN2Y87MZ187(Partial)USARAffectedPages:9.4-45,9.4-6,(sh.4)19(Sh.9.4-2c,32,9A.12~3139.4-46,9.4-47;Tables9.5-1(Sh.8),9.5-2Figures1.2-2,1.2-1),8.3-3(Sh.2),9.4-14(Sh.1),9.5-35g1132g12'112.3-34,12.3-46System:TitleofChange:N/ARelocationofZ&CShopDescriptionofChange:ThismodificationisoneofaseriesdesignedforControlRoomenhancements.Thismodificationconvertedtheserviceroom,elev.261'-0"oftheservicebuilding,toanI&Cshop,andproposedadditionalworktotheexistingZ&CShopatelev.288'-6"inthecontrolbuilding.WorkcompletedonthenewZGCShopincludedroomfinishing(dropceiling,tilefloor,drywallandpaint),replacementofexistingheatingandventilationequipmentwithnewHVACsystem,revisiontoexistingfireprotectionwatersprinklersystemandassociatedelectricalwork.ProposedworkontheexistingZaCShopincludesroomfinishingandelectricalwork.Thisworkisstillinprocess;therefore,thisUSARrevisiononlyreflectsworkcompletedonelev.261'-0"asofApril30,1990.SafetyEvaluationSummary:Thismodificationconvertedtheserviceroom,elev.261'-0",toanZaCshopandallowscompletionofworkonanother.Thismodificationdoesnotaffectanysafety-relatedsystemsandhas,noeffectonthesafeshutdownofthe,plant.ComponentsaddedtotheexistingI&Cshopinthecontrolbuilding(elev.288'-6")arenotseismicallysupported(i.e.,dropceilingandlighting).Afailureofsuchcomponentswillhavenoimpactsincenosafety-relatedcomponentsarelocatedinthisarea.

SafetyEvaluationSummaryReportPage5of112SafetyEvaluationNo.87-151(Continued)SafetyEvaluationSummary:(Continued)Fireloadincreaseshavebeencalculated.ThismodificationdoesnotaffecttheAppendixRsafeshutdownanalysis.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage6of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:87-175,Rev.2Mod.PN2Y87MX259(Partial)Figure10.1-6aFeedwaterSystem(FWS)ReplacementofPaulMonroeHydraulicActuatorswithLimitorqueMotor-OperatedActuators,2FWS-LV10A,2FWS-LV10B,and2FWS-LV10CDescriptionofChange:Duetohighfailurerateandmaintenancefrequency,theexistingPaulMonroeelectrohydraulicactuatorsforfeedwatercontrolvalves2FWS-LV10A,B,CareintheprocessofbeingreplacedwithLimitorqueelectrically-operatedactuators.Themodificationofeachvalveincludesthefollowing:1)removalofexistingactuatorandinstallationofnewactuator,controlpanelandtransformers;2)reworkexistingconduitsandcablesandinstallnewconduitsandcablesintolocalcontrolpanel,transformersandvalveactuator;3)revisionstothepositionindicationloopwhichrequireschange-outoftransmittercardforcurrent/voltageconverterinpanelP825(Foxborocabinet);4)minorrewiringinP825;5)theexistingcontrolcircuit,contactor,andoverloadsintheaffectedMCCsaretoberemoved,astheMCCshaveonlyathermal/hydraulicmagneticbreakerfortheseloads.Thefeedwatercontrolsystemgainchangelogicisremovedandissetatafixedvalueforallvalveoperations.Thecavitationinterlockandthefeedwaterrunbacklossofsignalbypassaremaintainedinthecontrolcircuits.USARRevision2reflectstheinstallationofthemotoractuatoron2FWS-LV10B,whichwascompletedpriortoApril30,1990.Thebalanceofthemodificationisongoing.

SafetyEvaluationSummaryReportPage7of112SafetyEvaluationNo.SafetyEvaluationSummary:87-175,Rev.2(Continued)Thismodificationisnotsafety-related.Them'odifiedvalvesarelocatedintheturbinebuilding,andnosafety-relatedequipmentwillbeimpacted.Nonewtransientswilloccurasaresultofthismodification.Systemresponsewastestedbothwithandwithoutthegainchangelogicduringpowerascensionandwassatisfactoryinbothconfigurations.ThisfixedgainisstandardGEBWRdesign.ThenewdesigndoesnotchangetheresponseofthevalvestoanATWSevent.Basedontheevaluationsperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage8of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:88-039,Rev.2TemporaryMod.88-138Nj'ABreathingAirSystem(AAS)TemporaryCappingofSafetyValve2AAS-SV126DischargeLineDescriptionofChange:Frequentliftingofsafetyvalve2AAS-SV126wascausingbreathingairsystemcompressor2AAS-Cltorunexcessivelytomaintainacceptablesystempressure.Theoperatingpressureofthecompressorwasoriginallychangedto90psigtoprovidegreatermarginoverthesafetyvalvesetpoint.ThischangewaspreviouslyreportedinletterNMP2L1239,datedJune11,1990.Duetoinsufficientairvolumeavailabilitywiththecompressoroperatingat90psig,theoperatingpressurehasbeenraisedto9Spsig,andsafetyvalve2AAS-SV126hasbeendisabledbycappingitsdischargeline.SafetyEvaluationSummary:Disablingsafetyvalve2AAS-SV126allowssystempressurizationwithoutundulydeterioratingcompressor2AAS-C1.Systemprotectionfromover-pressurizationwithsafetyvalve2AAS-SV126cappedisprovidedbysafetyvalves2AAS-SV127and2AAS-SV128,whichhavethesamesetpointandarelocatedjustdownstream.There,arenovalvesbetween2AAS-SV126and2AAS-SV127topreventprotectionoftheaffectedportionofthesystem.ThistemporarymodificationisexpectedtoremainineffectuntilfinalimplementationofapermanentmodificationwhichiscurrentlyscheduledforOctober1990.

0 SafetyEvaluationSummaryReportPage9of112SafetyEvaluationNo.88-039,Rev.2(Continued)SafetyEvaluationSummary:(Continued)Thebreathingairsystem(AAS)isnotsafety-related.Ztisdesignedtoprovideairsuitableforbreathingatbreathingairstationsforusebyunitpersonnelduringpotentialoractualairbornecontaminationsituations.Thetemporarymodificationwillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarychangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage10of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:88-046DRFL12-00766N//AFuelExtendedLoadLineLimitAnalysis(ELLLA)forCycle1(100%RatedThermalPowerto96%RatedCoreFlow)DescriptionofChange:Theconfigurationofthepowerflowmapwasmodifiedtoallowoperationat100%poweratcoreflowslessthan100%ofrated(108.5millionlb//hr).Specifically,operationdowntoaminimumof96%ratedcoreflowat100%ratedpowerisallowed,aswellasoperationabovethe100%rodline(asdefinedwithinthesafetyevaluation).SafetyEvaluationSummary:ThelimitingUSARChapter15transients(FeedwaterControllerFailureandLoadRejectionwithBypassFailure)attheELLLA100%powerinterceptpoint(100%RatedThermalPower,96%ofRatedCoreFlow)areboundedbythelicensebasispoint(104.3%RatedThermalPower,100%RatedCoreFlow).Forequipmentout-of-servicepreviouslyidentified,theMCPRlimitisnotaffectedbyELLLAoperation.TheanalysesresultsalsoshowthatoperationintheELLLAregioniswithinallowabledesignlimitsforoverpressureprotection,stability,LOCA,containment,reactorinternalsandATWSevents.OperationofNNP2withintheELLLAwindowconcurrentwithsinglerecirculationloopoperationor2SRVsout-of-serviceisanunanalyzedconditionandis,therefore,notallowed.Basedontheevaluationandanalysesperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage11of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:88-059,Rev.1Mod.PN2Y87MX1349.5-6;Tables9A.3-1(Sh.4),9A.3-6(Sh.5);Figures9.5-3c,9.5-3b,9.5-3a,9A.3-7System:TitleofChange:FireProtectionCO~SystemProvideCrossZoneAutoActuationtoCO,Zone757SLDescriptionofChange:Firezone757SL,aspreviouslydesigned,requiredonlyonedetectortoactivatetoinitiateCO~suppressionintheturbinealternatorexciterenclosure.Thismodificationprovidedcrosszoneactuationtofirezone757SL(changedto757XL).ThispreventsunwantedCO,actuationbyrequiringtwodetectors(onesmokeandonethermal)tobeactuated.ThismodificationisconsistentwithothertotalfloodingCO~systems.SafetyEvaluationSummary:ThismodificationpreventsasinglespuriousactuationofadetectionloopfrominitiatingunwantedCO~flooding.TheinstallationofthecrosszoneactuationcomplieswithNFPAStandards12,72D,and72E.Thischangetothefiredetectionsystemdoesnotaffectthesafeoperationorsafeshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage12of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:88-077Mod.PN2Y87MX23311.3-5;Figures11.3-1a,11.3-1bSystem:TitleofChange:OffgasSystem(OFG)AddSamplePumpstoOffgasH,AnalyzerDescriptionofChange:ThismodificationmodifiestheH~analyzerportionoftheoffgassystemtocorrectidentifiedproblemswiththeoperationoftheinstruments.Thefollowingchangesareincluded:1)Installationofasamplegasconditioningsystem,upstreamofthehydrogenanalyzers20FG-AT16A/'Bandupstreamof20FG-AT115,tocontrolmoisturecontentofthesample.2)InstallationofanaireductorinthecommondischargelineofthesubjectH,analyzerstomaintainapositiveflowtotheanalyzers,thusassuringsamplecapability.Threeflowswitchesandannunciationareaddedtoprovideindicationwhenflowandsamplecapabilityislost.Amanualpressurecontrolvalveandalocalpressureindicatorareinstalledontheairsupplylinetotheeductor.Acheckvalveisalsoinstalledontheairsupplylinetopreventcrosscontaminationfromtheoffgastotheinstrumentairsystem.3)RelocatingtheH2sampledischargelineconnection,includinganewrootvalve,furtherdownstreamofthefreeze-outdryerstoalleviateproblemswithfreezingoftherootconnection.Theexistingrootvalve(V25)iscappedin-place.

SafetyEvaluationSummaryReportPage13of112SafetyEvaluationNo.88-077(Continued)SafetyEvaluationSummary:Thismodificationtothenonsafety-relatedoffgassystemenablesittoproperlymonitorhydrogenconcentrationasrequired.Thisdoesnotaffecttheoperationofanysafetysystemsanddoesnotaffectthesafeoperationorshutdownoftheplant.Thereleaseratesoftheoffgassystemarenotaffected.ThenewinstrumentairsupplytotheH,analyzerdischargelinedoesnotimpactthecapabilitiesoftheinstrumentairsystem,andprovisions,havebeenmadetopreventcross-contaminationfromtheoffgastotheinstrumentairsystem.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage14of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:88U-110EE-80SeriesDrawingsFigures9.5-5through9.5-39CommunicationsSystemsPlantCommunicationsPlansDescriptionofChange:ThischangerevisestheUSARcommunicationplanfiguresbasedonthereissuanceoftheassociatedsourceengineeringdrawings.ThereissueddrawingsincorporatechangestoresolvecommentsresultingfromtheindependentverificationreviewconductedbyNiagaraMohawk'sinternalNuclearComplianceandVerificationgroup(partiallysatisfiesthecommitmentmadeinItem1ofNMPCletterNMP2L1217,datedNovember29,1989).Thesechangesaffectonlythebackgrounddetailshownonthedrawings,anddonotinvolveanyactualchangestocommunicationsystemsdevices.SafetyEvaluationSummary:TherevisedUSARcommunicationplanfiguresdepictanincreasedlevelofbackgrounddetail,butdonotinvolveanyactualchangestocommunicationsequipmentsuchashandsets,speakers,amplifiers,strobelights,jacks,ortelephones.Sincetheeffectivenessandreliabilityofthecommunicationssystemsisnotdiminished,thesedrawingchangesdonotinvolveanunreviewedsafetyquestion.NOTE:SafetyEvaluation88U-110isbeingreportedagainatthistimetoaddressthereissuanceofthesourceengineeringdrawings.Alladditions/relocationsofcommunicationssystemsequipmenthavebeenaddressedinSafetyEvaluation88U-110andwerepreviouslyreportedinNMPCletterNMP2L1198,datedApril28,1989.

SafetyEvaluationSummaryReportPage15of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:88U-121,Rev.1LDCNsU-1295,U-1296ListedBelowSuppressionPoolHydrodynamicAnalysis,HighEnergyLineBreakWhip/JetImpingementEvaluations,SpentFuelPoolStorageRacksTitleofChange:MiscellaneousFigures-UpdatingDuetoSourceVerificationDescriptionofChange:ThismodificationdescribeschangestoFSARfiguresresultingfromsourcedocumentverification.Wheresourcedocuments(drawings,calculations,etc.)havebeenrevisedorsuperseded,thefigureshavebeenupdatedtoreflectthechanges.ThissafetyevaluationwaspreviouslyreportedinletterNMP2L1198datedApril28,1989.Additionalcorrections/updateshavebeenmadeforthefollowing:Page6A.2-9Figures3.6A-56,-57,-58,-60Figure6A.1-3Figure6A.2-6,-7Figure6A.4-39Figure9.1-3SafetyEvaluationSummary:TheidentifiedUSARchangesareduetorevisions/supersedingofdrawingsorcalculations.Thesechangesdonotinvolveanyactualplantchanges,donotaffectplantperformanceorreliability,andhavenoimpactonstationprocedures.Basedontheevaluationperformed,itisconcludedthattheseUSARchangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage16of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:88U-323LDCNU-108112'9g12'10'2313'2.3-15;Figures12.3-1through12.3-66System:TitleofChange:N/AEditorialChangestoUSARSection12.3DescriptionofChange:VariouseditorialchangesaremadeinUSARSection12.3.ThesechangesaremadeforclarityandtomaintainconsistencybetweenthetextandfiguresofSection12.3.SafetyEvaluationSummary:TheidentifiedUSARchangesareeditorialinnatureanddonotaltertheplantdesignbasis.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage17of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-004EDC2E00130Figure6.2-38,Sheet10ContainmentMonitoringSystem(CMS)TitleofChange:SetpointChangetoSuppressionPoolHighTemperatureAlarmDescriptionofChange:Thesetpointforthesuppressionpoolhightemperaturealarmhasbeenincreasedfrom82.5'Fto85'F.Thisprovidesadditionalmarginabovecurrentoperationallyexperiencedsummersuppressionpoolwatertemperatures,whichhavecausedconstantalarmingconditions.SafetyEvaluationSummary:Thissetpointchangewillreducethesuppressionpoolwaterhightemperaturealarms,receivedduringnormaloperation,withoutaffectingthesafeoperationorshutdownoftheplant.SufficientmarginisstillmaintainedtoallowinitiationofRHRsuppressionpoolcoolingpriortoexceedingtheTechnicalSpecificationslimitof<904F;thus,theinitialsuppressionpooltemperatureof90'Fusedintheaccidentanalysisismaintained.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage18of112SafetyEvaluationNo.:ImplementationDocumentNo.:89-007CalculationsMS-1722,Rev.1;MS-1126,Rev.2;MS-168S,Rev.1;MS-1424,Rev.4;PZ-002AK,Rev.1USARAffectedPages:System:TitleofChange:36A15'6A16'033ExclusionAreaPipingFSARSection3.6ARevisionDescriptionofChange:Intheprocessofresolvingproblemswithmainsteamlineflooding(LER88-01),adiscrepancybetweentheFSARtextinSection3.6AandQuestionaResponseF210.17Awasfound.TheresponsetotheQ&RstatedthatthedesignofpipeintheexclusionareametBranchTechnicalPosition(BTP)MEB3-1requirements.MEB3-1specifiestherequirementsforallpipinginthe"exclusionarea"betweencontainmentandtheinboardoroutboardisolationvalves.However,Section3.6AdescribedexceptionstakentorequirementsofMEB3-1forcertainevaluationsinthatitdidnotaddressnon-nuclearpiping.Inresponsetothisdiscrepancy,calculationswererevisedtodemonstratecompliancewithMEB3-1forClass3andnon-nuclearpipinginthe"exclusionarea."ThisresultsintherevisedSection3.6AbecomingconsistentwiththeQSRresponse.SafetyEvaluationSummary:TherevisedcalculationsindicatethatthepipinginquestionmeetshigherstandardsthanindicatedintheFSAR.Therefore,thechangestotheFSARindicatethatthedesignismeetingmorestringentrequirements,therebyenhancingsafety,andcontainsadditionalconservatisminthedesign.Thus,thischangedoesnothaveanyaffectonthesafeoperationofanysystemorsafeshutdownoftheplantanddoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage19of112SafetyEvaluationNo.89-007(Continued)SafetyEvaluationSummary:(Continued)NOTE:ThissafetyevaluationisbeingreportedatthistimeinsupportofthechangestoUSARSections3.6Aand10.3,whichwereincorporatedinUSARRevision0.

SafetyEvaluationSummaryReportPage20of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-009TemporaryModificationN/ALiquidRadioactiveWasteSystem(LWS)TitleofChange:TemporaryFilteringSystemat2LWS-PI88BDescriptionofChange:Anacidspilloccurredinthecondenserareaoftheturbinebuilding.Theacidreactingwithconcrete,paint,metal,etc.,introducedawastesolutionofapproximately30%solidsandorganicmaterials,intothefloordrainsystem.Effluentfromthefloordrainsystemisprocessedbytheliquidradioactivewastesystem(LWS).Thefloordrainfilteringsystemintheradwastebuildingisdesignedtoprocessawasteeffluentof2%solidsandorganicmaterials.Collecteddrainageispumpedfromthefloordraincollectorsurgetank(2LWS-TK17),tobeprocessedbytheLWSsystemthroughsurgepump2LWS-P17A/B.Thistemporarymodificationprovidesforthetemporaryremovalofpressureindicator2LWS-PI88Btoallowtheinstallationofa3"flexhosefromthedischargesideofpump2LWS-P17BtoaLondonNuclearFilteringSystem.TheLondonFilteringSystemprovidesanadditionalfilteringprocessintothissystemwhichremovesthemajorityofthesolidsandorganicmaterialspriortoreturningtheeffluentintothedesignedregenerantwastetank/evaporatorsystemandfurtherfilteringif/asrequired.SafetyEvaluationSummary:ThistemporarymodificationprovidesanadditionalfilteringsystemtopreventdamagetoLWSequipmentfollowingtheunexpectedacidspillandallowthenonsafety-relatedLWSsystemtoperformitsdesignfunction.Thisdoesnotaffectthe

SafetyEvaluationSummaryReportPage21of112SafetyEvaluationNo.:89-009(Continued)SafetyEvaluationSummary:(Continued)operationofanysafetysystemsorcomponents.Thepressureindicator(PI88B)thatistemporarilyremovedisforlocalpumpdischargepressureindicationanddoesnotperformanycontrolorprotectivefunctionsfortheLWSsystemorpump2LWS-P17B.Basedontheevaluationperformed,itisconcludedthatthistemporarychangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage22of112SafetyEvaluationNo.:"ImplementationDocumentNo.:USARAffectedPages:89-014,Rev.1Mod.PN2Y88MX093(Partial)Figures9.2-1q,9.2-6a,9.2-17b,9.3-1hSystem:TitleofChange:N/AUnit2ChemistryLab/CountingRoomDescriptionofChange:Thismodificationconvertstheexistingcontaminatedtoolstorageroom(elevation261'econtaminationarea,radwastebuilding,Unit2)intobothachemistrylaboratoryandacountingroom.Thechangesincludeinstallationofcountingroom/chemistrylabequipmentinsupportofroutinewaterchemistrysurveillanceatUnit2,andtheadditionofanairconditioningunittotheroomtomaintaindesiredenvironmentalconditions.USARRevision2reflectsportionsofthemodificationcompletedpriortoApril30,1990.SafetyEvaluationSummary:ThismodificationaddsanewchemistrylabandcountingroomtorelievepersonnelcongestionandimproveavailabilityandconvenienceoffacilitiesforUnit2Chemistrypersonnel.Thisfacilitydoesnotperformasafetyfunction.Postaccidentsamplingandanalysiswillnotbeperformedinthisfacility.Theinstallationofthislaboratorywillnotaffectanysafetysystemsorcomponentsandwillnotaffectthesafeoperationorshutdownoftheplant.Theinstallationofthisfacilitycomplieswithexistingdesignandconstructionspecificationsandcodes.Potentiallycontaminatedandchemicalwastewillbeprocessedthroughtheexistingdrainsystemsandradioactivewasteprocessingfacilities.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage23of112,SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-016,Rev.1N//AN/ADieselGeneratorVentilationSystem(HVP)TitleofChange:RemovePowerfrom2HVP*MOD1Band2HVP*MOD6B;2HVP*MOD1BtobeOpenedand2HVP*MOD6BtobeClosedDescriptionofChange:Thistemporarymodificationde-energizesmotor-operateddampers2HVP*MOD1Band2HVP*MOD6Bbytheremovalofpower.2HVP*MOD1Bdamperwillbeintheopenpositionwhile2HVP*MOD6Bdamperwillbeintheclosedposition,whichwillmaintaincompliancewiththedieselgeneratoremergencycoolingcriteriabyensuringacoolingrateconsistentwiththerequirementsforemergencycoolingwhiletheemergencydieselsareoperating.SafetyEvaluationSummary:Theremovalofpowerfrom2HVP*MOD1B,withthepositioningofthedamperintheopenposition,andtheremovalofpowerfrom2HVP*MOD6Bwithitsdamperpositionedintheclosedposition,willpreventactuationofthesedampers.Uponanautomaticstartsignaltotheemergencydieselgenerator(2EGS*EG3),fans2HVP*FN1Ba2HVP*FN1Dexhaustismodulatedbetweentheexhaustdamper(2HVP*MOD1D)andtherecirculationdamper(2HVP*MOD6D).Themodulationofthedampersassociatedwith2HVP*FN1Dwillmaintainacoolingrateconsistentwiththethermalloadtomaintainthedieselgenerator(EG3)roomtemperaturewithinprescribedlimitsduringoperationofdieselgenerator2EGS*EG3(Div.II).Therearenotripfunctionsassociatedwiththistemporarymodification.

SafetyEvaluationSummaryReportPage24of112SafetyEvaluationNo.:89-016Rev.1(Continued)SafetyEvaluationSummary:(Continued)Thistemporarymodificationwillremovesafety-relatedcomponentsfromservicebutwillnotaffectthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage25of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-017TemporaryMod.89-059N/ACirculatingWaterAcidTreatmentSystemTitleofChange:Manual,DirectAcidInjectiontoCirculatingWaterDescriptionofChange:Duetomaintenanceandrepairs,thecirculatingwateracidsystemisinoperative,thusrequiringanalternatemethodofsupplyingacidtothecirculatingwatersystem.Acidinjectionwillbeperformedatthecoolingtowerthroughtheuseofacommercialtanktruckandatemporaryheaderinstalledacrossthedischargeflumes.Thenormalinjectionportionoftheacidsystemwillremaininoperativeduringthetimethistemporarymodificationisinplace.However,monitoringinstrumentationwillbeavailabletocheckandrecordwaterpH.SafetyEvaluationSummary:Acidtreatmentofthecirculatingwaterisutilizedtomaintaincleanheatexchangersurfacesandtopreventbiologicalgrowthwithinthecirculatingwatersystemscondenser.Thistemporarymodificationprovidesanalternatemethodofperforminganonsafety-relatedfunctionthatwillnotimpactthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage26of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-019,Rev.1TemporaryMods89-061,89-062N/AMiscellaneousEquipmentandFloorDrainsSystemTitleofChange:TemporaryMod.toSteamLineDrainValves2DTM-AOV128and2DTM-AOV144DescriptionofChange:Thistemporarymodificationremovestheelectricalinterlocksbetweenvalves2ASS-STV112and2DTM-AOV144,andbetweenvalves2ASS-STV143and2DTM-AOV128,byliftingorjumperingleadsinthecontrolroom.Removaloftheseinterlocksallowsisolationofdrainpathsthathadallowedextractionsteamtoflowthroughdrainlinestothemaincondenser,resultinginalossofplantefficiency.SafetyEvaluationSummary:Steamsupplylinedrainsremoveanycondensatebuild-upfromthelines.Drainlinevalves2DTM-AOV128and2DTM-AOV144opentoprovideadditionaldrainagecapacityrequiredduringlowpressureoperationsandshutdownconditions.Thenormaldrainlinepathwillstillprovidefortheremovaloflowpointcondensatefromthesteamsupplylinesduringfullpoweroperations.Additionalautomaticvalvecontrolstoopenthevalvesatturbinelowpressurewillbefunctional,andmanualcontrolisavailablethroughcontrolswitchesinthecontrolroom.Thedrainvalvesandtheirassociatedelectricalinterlocksarepartoftheturbinebuildingmiscellaneousdrainssystem.Thisisanonsafety-relatedsystemandisnotrequiredforsafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage27of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-020TemporaryMod.89-063N/AReactorRecirculationSystemReactorRecirculationPumpsVibrationMonitoringPersonalComputerDescriptionofChange:Thistemporarymodificationconsistsoftheinstallationofacomputerworkstation,adjacentandconnectedtovibrationmonitoringpanel2RCS-PNL100,toprovidecontinuous,remote,on-linemonitoringoftheNMP2reactorcoolantrecirculationpumps2RCS*P1Aand2RCS*P1B.Thesystemwillreceivepowerfromalocal120Vconvenienceoutlet.Atemporarytelephonelinehook-upwillbeinstalledtoprovideremoteaccesstothisinformationtositepersonnelandGeneralElectric-SanJose,eliminatingtheneedforfrequentaccesstorestrictedareasoftheplant.SafetyEvaluationSummary:Thereactorcoolantrecirculationpumpvibrationmonitoringprogramisusedfordetectinglossofwearringboltingintegrity,performingshort-andlong-termtrending,andwillserveasabasisforschedulingmaintenanceandrepairinatimelymanner.Thevibrationmonitoringsystemisnotrequiredforthesafeoperationorshutdownoftheplant.Failureofequipmentinstalledunderthistemporarymodificationwouldnotjeopardizeorchallengeplantsafetysystems.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage28of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-021,Rev.1TemporaryMod.89-066N/AServiceWaterSystemControlRoomChillerInletTemperatureControl-TemporarySetpointChangeto2SWP*TSL91A(B)DescriptionofChange:Servicewatertoeachcontrolbuildingchilledwatercondensercontainsarecirculationloopwithapump(2SWP*P2Aand2SWP*P2B).Thesepumpsworkinconjunctionwiththetemperaturecontrolvalveslocatedinthechillerreturnlinestomaintaintheservicewaterinlettemperaturetothechillersabove60'F.Currently,thelogicassociatedwiththeservicewatersystemprovidesforastartsignalfor2SWP*P2A(B)whenservicewatertemperaturedecreasestoanupperlimitof63'Fandalowerlimitof60'F.Thistemporarymodificationwillallowincreasingthesetpointrangeforthecondenserwaterpumps2SWP*P2A(B)toanupperrangeof754Fandlowerrangeof724F.SafetyEvaluationSummary:Thistemporarychangetothesetpointfor2SWP*TSL91A(B)willaddadditionalcoolingcapabilitytohelpmaintainControlRoomenvironment.Aslongastheservicewatertemperatureenteringthechillerislessthan82'F,thereisnoimpactonstationoperation.Inaddition,theservicewateroutlettemperatureofthechillerswillbemonitoredonashiftbasiswhenservicewatertemperatureisgreaterthan70'F.Iftheoutlettemperaturereaches82'F,andthe2SWP*P2A(B)arestillinservice,thentheoperatorshallsecurethepumps.Operatoractionthusensuresthechillerinlettemperaturedoesnotexceed824F.

SafetyEvaluationSummaryReportPage29of112SafetyEvaluationNo.:89-021Rev.1(Continued)SafetyEvaluationSummary:(Continued)Basedontheevaluationperformed,'tisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage30of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:89-022RMUNo.052578N/ASystem:TitleofChange:ControlBuildingHVACSystemTemporaryChangetoAllowOptionalOperationofControlRoomReturnDuctHeaters2HVC*CH11A/Band2HVC*CH12A/BDescription'fChange:Ductheaters2HVC*CH11A/B,CH12A/BheatthereturnairtotheairconditioningunitswhenthetemperatureintheControlRoomdecreasesto40degreesFahrenheit.Thistemporarychangeeliminatestheneedfortheautomaticcontrollingofheaters2HVC*CH11A/B,CH12A/BwhenclimaticconditionsexistsuchthatsupplementalheatingofthereturnairtotheControlRoomHVACsystemisnotrequired.Thisisdesirableto(1)performmaintenanceontheheatersand(2)eliminateunnecessarycyclingoftheairconditioningunits.SafetyEvaluationSummary:AsindicatedintheFSAR,thepurposeoftheControlRoomairreturnductheatersistomaintainairreturningfromtheControlRoomabove40degreesFahrenheit.Therefore,aslongastheControlRoomtemperaturecanbemaintainedabove40degreesFahrenheit,thereisnoimpactonstationoperation.Basedontheevaluationperformed,itisconcludedthat,thistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

45V SafetyEvaluationSummaryReportPage31of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-024,Rev.1N/A9.4-40,9.4-42TurbineBuildingVentilationSystem/EffluentMonitoringOperatingwiththeTurbineBuildingRoofVentsOpenDescriptionofChange:Thischangeallowstheturbinebuildingroofventstobeopenedforintermittentperiodsduringnormalplantoperationtoprovideadditionalcoolingofthemainsteamtunnelandturbinebuilding.ThismodificationisbeingimplementedtopreventinadvertentorspuriousMSIVisolationasaresultofhighoutsideairtemperature.Duringmid-July1989,highoutsideairtemperaturescausedthetemperaturesinthemainsteamtunneltoreachthehighalarmsetpointonseveraloccasions.Thetripsetpoint(TechnicalSpecificationslimit)wasreachedononeoccasion,causingahalfisolation.Becausetheturbinebuildingismaintainedatsubatmosphericpressures,asdiscussedinFSARSection9.4,byopeningtheturbinebuildingroofvents,cooleroutsideairwillbedrawninandthroughthebuilding,eventuallybeingexhaustedthroughthemainstackviathenormalturbinebuildingventilationsystem.Coolingtheturbinebuildingwillresultincoolingthemainsteamtunnel.SafetyEvaluationSummary:TheturbinebuildingHVACsystemhasnosafety-relatedfunction.Failureormalfunctionofthesystemwillnotcompromiseanysafety-relatedsystemorcomponentorpreventsafereactorshutdown.Theturbinebuildingisnotclassifiedasa

SafetyEvaluationSummaryReportPage32of112SafetyEvaluationNo.89-024,Rev.1(Continued)SafetyEvaluationSummary:(Continued)containmentstructure.However,theturbinebuildingventilationsystemisdesignedtoexhaustmoreairfromthebuildingthanisbeingsupplied,therebymaintainingasubatmosphericpressuretoinhibittheexfiltrationofcontaminants.Theopenturbinebuildingroofventsarenotconsideredasadditionalradioactivereleasepoints.Provisionsaremadetoensurethattheopenturbinebuildingroofventsdonotprovideapotentialforunmonitoredeffluentreleasesduringnormaloperation,andtoensurethatthereleasesofactivitytotheenvironmentwillnotdifferfromthoseanalyzedinFSARSection11.3.3andAppendix11A.ThedesignbasismainsteamlinebreakandoffgassystemfailureanalysesinFSARChapter15envelopetheconsequencesofadesignbasisaccidentoccurringwhiletheturbinebuildingroofventsareopen.Loweringthemainsteamtunnelandturbinebuildingtemperatureswillnotadverselyaffecttheabilityofthemainsteamtunneltemperaturemonitorstodetectamainsteamlinebreak.Basedontheevaluationsperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

1 SafetyEvaluationSummaryReportPage33of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-025Mod.PN2Y88MZ093N/AEssentialLightingSystemTemporaryMarkupofTwoEssentialLightingCircuitsinPanel2LAN-PNLU01DescriptionofChange:Thistemporarychangedisabledtwoessentiallightingcircuitsinordertofacilitateinstallationoftwonewessentiallightingcircuitsandtoavoidworkinginahighradiationareawheninstallingthenewcircuits.Theegress/essentiallightingwasdisabledinthefollowingareas:condensatestoragebuilding,radwasteswitchgearroom,dirtyworkshop,sampleroom,largetoolandequipmentdecontaminationarea,andradwastecontrolroom.SafetyEvaluationSummary:Thedisablingoftheessentiallightingcircuits138and540willnotaffectthesafeshutdownoftheplantsincetherearenosafety-relatedcomponentslocatedinthecondensatestoragebuilding,theradwasteswitchgearroom,thedirtyworkshop,thesampleroom,thelargetoolandequipmentdecontaminationareaandtheradwastecontrolroom.Intheeventofalossofnormalpower(LOP)whilethesetwoessentiallightingcircuitsarede-energized,thereferencedareaswouldbecompletelyinthedark;however,sincetheoutagesarebriefinduration,thelikelihoodofexperiencingacoincidentLOPisremote.Basedontheevaluationperformed,itisconcludedthatthistemporarychangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage34of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-026TemporaryMod.88-74N//ACirculatingWaterSystem(CWS)RemoveTemperatureElement2CWS-TE10BDescriptionofChange:Thistemporarymodificationremovesoneoffourtemperatureelements(2CWS-TE10B)locatedonthetube-sidedischargeofthemaincondenser,inthe72inchcirculatingwaterline2CWS-072-405-4.Thischangewasnecessaryduetotemperatureelementfailureandlackofavailabilityofareplacement.SafetyEvaluationSummary:Thecirculatingwatersystemisnonsafety-relatedandisnotrequiredforsafeoperationorshutdownoftheplant.Thethreeremainingtemperatureelementswillstillprovidetheirindividualcomputerpointsignals.Therearenoalarms,controls,orisolationfunctionsassociatedwiththecondensertubesidedischargetemperatureelements.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage35of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-028,Rev.1TemporaryMod.89-71N/AContainmentMonitoringSystem(CMS)TitleofChange:SampleTemperatureforContainmentRadiationMonitorDescriptionofChange:Thistemporarymodificationinstalledthreethermocouplestorecordprocesstemperaturesononeofthecontainmentatmosphereradiationmonitors(2CMS*CAB10B).Thethermocoupleswereinstalledinplaceoftwosamplevalvesandonecalibrationtestvalve.Datacollectedfromthethermocouplesistobeusedtodesignmodificationstoeliminatecondensationofmoistureinthemonitorprocessstream.SafetyEvaluationSummary:Thisinstallationofthermocouplesinplaceofthetwosamplevalvesandtheonecalibrationtestvalvewillnotaffecttheoperationoftheradiationmonitor.Theradiationmonitorremainsoperationalforthefollowingreasons:1)Removalofthevalvesdoesnotaffectthefunctionoftheradiationmonitortomonitortheprimarycontainmentforairborneparticulateradioactivityandairbornegaseousradioactivity.2)ChemistryprocedureN2-CSP-7Vcanbetemporarilyrevisedsothatgrabsamplesoftheprimarycontainmentatmospherecanbetakenattheradiationmonitor,ifrequired.3)Thefunctiontocalibratethegasradiationdetectorisnotchangedwhenoneofthecalibrationtestvalvesisremoved,sincecalibrationisactuallyaccomplishedbyremovingthedetectorfromtheskid.

SafetyEvaluationSummaryReportPage36of112SafetyEvaluationNo.89-028,Rev.1(Continued)SafetyEvaluationSummary:(Continued)4)Theintegrityofthepressureboundarywillbemaintainedbytheuseofseismically-qualifiedcomponents.Theprimarycontainmentatmosphereradiationmonitors2CMS*CAB10AJ'Bprovideonlyindicationandalarmfunctions.Intheeventofanaccident,thesemonitorsareisolatedfromprimarycontainmentandwouldnotaffectthesafeshutdownofthereactor.Thesemonitorsarenotusedforpost-accidentmonitoring.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage37of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-030TemporaryMod.89-050N/AOffgasSystem(OFG)OffgasH,SamplingDischargeLineRevisionDescriptionofChange:ToenableproperoperationoftheOffgasH,Samplingsystem,thistemporarymodificationrevisestheH~samplingcommondischargelineconnectiontotheoffgasprocessstreamsincethepresentlineconnection(20FG-V290)istoorestrictive.Stainlesssteeltubing(1/2")isrunfromathreadedconnectionupstreamofvalve20FG-V290toanexisting3/4"globeventvalve(20FG-V188),whichislocatedapproximatelysixfeetfurtherdownstreamfromthepresentdischargelineconnection.Additionalheattracingandinsulationarealsoprovidedtopreventfreezing.SafetyEvaluationSummary:Thistemporarymodificationwillmodifythenonsafety-relatedoffgassystemtoenableittoproperlymonitorthehydrogenconcentration.TheinstallationofthistemporarymodificationwillnotcompromisetheintegrityoftheoffgassystemandisconsistentwiththedesignintentoftheH~samplingsystem,asdescribedinUSARSections11.3.1,11.3.2andFigures11.3-1aand11.3-16(whichhavebeenmodifiedbyModificationPN2YMX233andSafetyEvaluation88-077).Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage38of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-042TemporaryMod.89-078N/AServiceWaterSystem/ProcessandEffluentRadiologicalMonitoringandSamplingTitleofChange:ServiceWaterSamplingTapDescriptionofChange:Duringrepairstoradiationmonitor2SWP*CAB146A,thischangeinstalledatemporarysampletapfromservicewatereffluentline2-SWP-002-405-4.Anabandonedconductivityelement,2SWP-CE144A,wasremovedandasamplinglinerunfromitslocation.Thelineconsistedofapproximately30feetofTygontubingandashutoffvalve.TheinstallationofaservicewatersamplelineprovidedaconvenientandaccessiblelocationfromwhichtotakegrabsamplesrequiredbytheTechnicalSpecificationsforcontinuedoperationwithachannelofservicewatereffluentradiologicalmonitoringoutofservice.Accessingtheusuallocationfortakinggrabsampleswasconsideredtobeahazardtopersonalsafety.SafetyEvaluationSummary:ThistemporarymodificationwillsupporttheverificationthatservicewaterradioactivelevelsarewithinTechnicalSpecificationslimits.Itwillnotimpactthesafeoperationorshutdownoftheplant.Thesamplelineinstallationisnon-safetyrelated.Effectsofabreakinthesamplelineorfailureoftheshutoffvalvehavebeenconsidered.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage39of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-043TemporaryMod.2087N//ASolidRadioactiveWasteManagementSystem(WSS)TitleofChange:TemporarySamplePointforEvaporatorBottomsDescriptionofChange:Thismodificationprovidesatemporarysamplepointinthesolidradioactivewastemanagementsystem(WSS)atthevalve(2WSS-V714)providedforsystemflushing.Theblindflangedownstreamof2WSS-V714hasbeenremovedandasamplingvalveaddedinitsplace.Thetemporarysamplepointoffvalve2WSS-V714isneededbecauseitisfeltthatnon-representativesamplesarebeingobtainedatthedesignedlocationduetocloggingofthesampleline.SafetyEvaluationSummary:Thistemporarymodificationistoanonsafety-relatedsystem.Thischangewillpermitsamplingofevaporatorbottomsatalocationotherthanthedesignedshieldedlocation(2WSS-SA119).AlthoughALARAlong-termconcernsexistatthetemporarynon-shieldedlocation,itisdeemedacceptableforashortdurationsince,atthisearlystageofplantoperation,theradiationlevelshavenotyetrisentothelevelsexpectedastheplantages.Systemoperatingprocedureshavebeenrevisedtorequireevaluationofradiationlevelspriortoutilizingthetemporarysamplepoint.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage40of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-045TemporaryNod.89-76N/ARadwasteBuildingHVACSystem(HVW)TitleofChange:RecordAirFlowat2HVW-CAB196and2HVW-FI115DescriptionofChange:Thistemporarymodificationrecordstheairflowforcontinuousairborneradiationmonitor2HVW-CAB196.Also,aflowtransmitterhasbeeninstalledinparallelwithflowindicator2HVW-FI115,viatheinstrumentlinedrainvalvesat2HVW-FI115,forthepurposeofrecordingairflowintheequipmentexhaustduct.Thepurposeofthistemporarymodificationistogatherdatatodeterminetherootcauseofthenumerousflowalarmsthathavebeenexperiencedforradiationmonitorswhichhavegasflowcontrols.SafetyEvaluationSummary:Thecontinuousairmonitor2HVW-CAB196andflowindicator2HVW-FI115arenonsafety-related.2HVW-CAB196isacontinuousairbornemonitorwhichmonitorstheairintheradwasteequipmentexhaustsystemduct.ItisusedfortrendingonlyandhasnoTechnicalSpecificationsbasis.Theflowelementfor2HVW-FI115islocateddownstreamofthefiltersandfansfortheequipmentexhaustsystem.2HVW-FI115isalocalindicatoronly.Itprovidesnocontrolnordoesitprovideanyalarms.

SafetyEvaluationSummaryReportPage41of112SafetyEvaluationNo.89-045(Continued)SafetyEvaluationSummary:(Continued)Thetemporaryrecordingofairflowswillnotaffecttheoperationoftheequipmentexhaustsystem.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage42of112SafetyEvaluationNo.:ImplementationDocumentNo.:89-048TechnicalSpecificationTable4.8.1.1.2-1USARAffectedPages:System:Table1.8-1,page122of169DivisionI,II,andIIIDieselGeneratorsTitleofChange:DieselGeneratorTesting,RegulatoryGuide1.108DescriptionofChange:ThischangecorrectsaninconsistencybetweenTechnicalSpecificationsTable4.8.1.1.2-1andUSARTable1.8-1,page122of169,regardingthedieselgeneratortestschedule.TheUSARcommitmenttoRegulatoryGuide1.108Rev.1,regulatorypositionC.2.d,isinconsistentwiththereferencedTechnicalSpecificationstableanddoesnotreflectrecentindustryconcernsoverfaststartsfordieselgenerators.SafetyEvaluationSummary:ThischangetotheUSARmakestheUSARconsistentwiththeTechnicalSpecificationsand'eflectstestingrequirementswhichminimizedieselenginemechanicalstressandwear.ThisUSARchangeisadministrativeinnatureanddoesnotaffectthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage43of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-054EDC2M00287Figures9.3-1c,9.3-1j,9.3-1k,9.5-lc,9.5-1e,9.5-if,9.5-1g,'9.5-1hFireProtectionWaterSystem(FPW),ServiceAirSystem(SAS)TitleofChange:AssignNewEquipmentNumbersforFireProtectionAirRegulatorsDescriptionofChange:Airpressureregulatorunits2FPW-REG1through8werepreviouslyshowninthefireprotectionwater(FPW)systemonP&IDs43C,E,F,andH.Theseregulatorunitswereprovidedbytheinstallingsprinklercontractor.Thesinglecomponent(regulator)shownontheP&IDswasactuallyseveralindividualcomponents(isolationvalves,bypassvalves,checkvalves)inadditiontotheregulator.Theunidentifiedvalveshavebeenassignednewequipmentpartnumbersinordertoprovidepositiveidentificationinprocedures,valvealignmentsandmaintenancerequests.ThisrequiresthatthesecomponentsbeaddedtosystemP&IDs.Theairpressureregulatorshavebeenre-identifiedaspartoftheSASsystemandareremovedfromFPWsystemP&IDsforconsistency.SafetyEvaluationSummary:Thischangedoesnotaddormodifyexistingplantsystemsoroperation,butmerelyaddsadditionaldetail'oexistingdesigndocuments.ItdoesnotaffectthedesignoroperationoftheSASorFPWsystemanddoesnotaffectsafeshutdownoftheplant.

I SafetyEvaluationSummaryReportPage44of112SafetyEvaluationNo.89-054,(Continued)SafetyEvaluationSummary:(Continued)Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage45of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-059EDC2E10072Fig.5.1-2aNuclearBoilerInstrumentationSystemTitleofChange:NuclearBoilerInstrumentationSystemModificationsDescriptionofChange:ThismodificationrevisesUSARFigure5.1-2atocorrectthealarmannunciatorwindownumberforreactorvesselhighpressure,andtoaddthecomponentidentificationnumberforthesteamdomepressureindicator2ISC-PI1108.ThesechangescorrectinconsistenciesbetweentheUSARfigureandas-builtparentdocuments.SafetyEvaluationSummary:ThechangestoUSARFigure5.1-2aareeditorialcorrections/clarifications,anddonotinvolveanyphysicalchangestotheplant.Thesechangesdonotadverselyaffecttheabilityofanysafety-relatedsystemsorcomponentstoperformtheirsafetyfunctions.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage46of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-060,Rev.2N/AN/AMiscellaneousBuildingsFloorDrainsSystem(DFM)OperationofNMP2WaterTreatmentBuildingSumpsasaContaminatedSystemtoSupportSystemDecontaminationDescriptionofChange:Thissafetyevaluationaddressestheuseofthesumpsysteminthewatertreatmentbuilding(northannextothescreenwellbuilding)ascontaminated.Thisevaluationincludesalldecontaminationeffortsrelatedtothepresentcontamination,butdoesnotincludeitslongtermroutineoperationtosatisfyoriginaldesignconsiderations.Theextentofcontaminationincludessumps5,6,and7,sumppumpI7,associatedlinesandtrenches,andpartofthefloorofthewasteneutralizertankcubicle.Noequipmentisbeingadded,deletedormodifiedinconjunctionwiththisevaluation.SafetyEvaluationSummary:ThisevaluationwasperformedinaccordancewithZ.E.BulletinNo.80-10,"ContaminationofNon-RadioactiveSystemandResultingPotentialforUnmonitored,UncontrolledReleaseofRadioactivitytoEnvironment."Thewatertreatmentsumpsandassociatedpipingarepartofanormallynon-contaminatedsystem.However,duetothetiminginthesumppumpstartupsequence,theconnectionofthesumppumpdischargeintothebottomofthefloordraincollectortankinletheader,andleakageofacheckvalve,contaminatedwaterfromthe

,

SafetyEvaluationSummaryReportPage47of112SafetyEvaluationNo.89-060,Rev.2(Continued)SafetyEvaluationSummary:(Continued)floordraincollectortankinletheaderwasabletobackflowintothewasteneutralizertankcubiclesump.Theamountofradioactivecontaminationpresentdoesnotreducetheabilityofthesumpstoperformtheirintendedfunction.Althoughthesumpsystemisnotdesignedtothesamecriteriaasaradioactivesystem,theintegrityofthesystemdoesassuretheshorttermcontainmentofliquidsandprecludesaninadvertentreleasetoanunrestrictedarea.Administrativeandradiationprotectionmeasureshavebeentakentosecurethecontaminatedareaandrestrictitsuse.Thepumpdischargelinehasbeenisolatedandmarkedup.Theareaisproperlypostedandcontrolledasarestrictedareainaccordancewithplantprocedures.Asurveyoftheaccessibleportionofthepumpdischargelinehasconfirmedthatdoseratesfromthelinedonotpresentaradiologicalconcernandthatthereisnoimpactonpersonnelorequipmentintheunrestrictedarea.Operationofsumppump57willbecontrolledtopreventfurthercontaminationofthesystemduringanydecontaminationefforts.DuringoperationofsumppumpN7,thesystemwillbemonitored,including,asaminimum,isotopicanalysisofthesumpcontentsbeforeandaftersystemoperation,andphysicalsurveillanceofthesystempipingintheunrestrictedareaduringsumpsystemoperation.Basedontheevaluationperformed,itisconcludedthatoperationofthesumpsystem,untilsystemdecontaminationeffortsarecompleted,doesnotinvolveanunreviewedsafetyquestion.

0 SafetyEvaluationSummaryReportPage48of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-061ProcedureN2-OP-101DTable13.5-6(Sh.4)ReactorRecirculationSystemProcedureN2-0P-101D,"PowerChanges"DescriptionofChange:Anewoperatingprocedure,N2-OP-101D,"PowerChanges,"hasbeencreated.SafetyEvaluationSummary:Thesubjectprocedureisdevelopedtoconsolidateallconcernsrelatedtopowerchanges,includingrapidpowerreductions.Developmentandapprovalofthisproceduresatisfiesunresolveditemno.89-12-02fromNRCInspectionReport50-410/89-12,anddoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage49of112SafetyEvaluationNo.:ImplementationDocumentNo.:89-066Drawings12187-SK-032483-.25;12177-BY-002AgBgCgE45065-CthruE-45069CUSARAffectedPages:System:TitleofChange:Figure1.2-1VariousMinorConstructionActivitiesattheNineMilePointSiteDescriptionofChange:Thesechangesinvolvevariousminorsiteconstructionactivitiessuchasremovaloradditionoffences;additions,relocation,orremovalofsiteaccessandserviceroads;andregradingandseedingofsiteareasoutsidetheprotectedarea.SafetyEvaluationSummary:Evaluationoftheseminorconstructionactivitiesandsitechangeshasdeterminedthat:1.Siteattributesthatrelatetotheprobablemaximumflood(PMF)analysisarenotadverselyaffected.2.Theabilityoftherevetmentditchsystemtoprotectsafety-relatedfacilitiesfromthemaximumpostulatedlakelevelasaresultoftheprobablemaximumwindstormisnotadverselyaffected.3.Atmosphericdispersionfactorsusedincalculatingtheradiologicalconsequencesofaccidentsarenotaffected.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage50of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:89-068TemporaryMod.88-151N/A1TurbineBuildingHVACSystemTemporaryInstallationofAirConditioningUnitsintheTurbineBuildingEastSwitchgearRoomDescriptionofChange:Temporaryadditionalcoolingforpersonnelcomfortisrequiredintheturbinebuildingeastswitchgearroomtosupplementtheexistingcoolingsuppliedby2HVT-UC225.Twoairconditioningunitsandacondensatepumpunitmovedfromtheradwastecontrolroomwerelocatedintheeastswitchgearroom.Theexistingcondensingunitpositionedatgradeoutsideoftheradwastebuildingwasrelocatedwesttoanoutsideposition,atgrade,adjacenttotheswitchgearroom.TheseunitsarenotconnectedtotheturbinebuildingHVACsystemandprovideairrecirculationwithintheswitchgearroomonly.SafetyEvaluationSummary:AsindicatedinUSARSection9.4.4.3,theturbinebuildingHVACsystemhasnosafety-relatedfunction.Failureormalfunctionofthesystemorsubsystemswillnotcompromiseanysafety-relatedsystemorcomponent,norwillitpreventsafereactorshutdown.Therearenosafety-relatedcomponentsintheturbinebuildingeastswitchgearroom.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage51of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-069,Rev.4TemporaryMod.89-092N/ACirculatingWaterSystem-Units1and2TitleofChange:CirculatingWaterSystemDischargePathDescriptionofChange:ArecentpHimbalanceinthecirculatingwaterchemistryhasresultedinelevatedlevelsofcopperconcentrationfromcondensertubingcorrosion.ThischangeallowsdischargeofUnit2circulatingwaterblowdowntotheUnit1circulatingwatersystemwhereitwillbediluted,thenreturnedtothelakewithUnit1watereffluenthavingsufficientflowtodilutethecopperconcentrationstoacceptablelevels,asdeterminedbytheNew~YorkStateDepartmentofEnvironmentalConservation.ThistemporarymodificationprovidesthemeanstodrawcirculatingwaterdirectlyfromthecoolingtowerbasininitiallyandfromCWSlater,asnecessary.Temporarydischargelinesconsistingofflexiblehose,rigidpipe,andpumpshavebeenrunoverlandtotheUnit1intakecanal.Unit2circulatingwaterwillbedischargedtotheUnit1circulatingwaterinfluentdownstreamoftheservicewaterinfluent.TheUnit1circulatingwatersystemwillbeoperatedcontinuously,providingaminimumflowtobedeterminedbythecalculatedneedfordilutionofUnit2discharge.Theadditionofascaleinhibitor,Betz3450,totheUnit2circulatingwatersystemisrequiredtocontroltheincreasedscalingduetocopperconcentrationandariseinpH.Theadditionofacorrosioninhibitor,BetzCopper-TrolCu-l,willfurtherreducetheleachingofcopperintothecirculatingwateratUnit2.

SafetyEvaluationSummaryReportPage52of112SafetyEvaluationNo.SafetyEvaluationSummary:89-069,Rev.4(Continued)ThecurrentlevelofcopperconcentrationintheUnit2circulatingwaterjeopardizessystemequipmentduetoincreasedcorrosionratesinducedbyacceleratedcorrosionratesbeyondthosealreadyexisting.OperationoftheUnit2circulatingwatersystemdoesnotjeopardizenuclearsafety,asthesystemisnotrequiredforsafeshutdownoftheplantandfailuresassociatedwiththesystemhavealreadybeenanalyzedintheUSAR.TheUnit2circulatingwatercopperconcentrationcontrolsblowdowntoLakeOntario.ThegreatercirculatingwaterinfluentandeffluentflowatUnit1willprovidethemeansbywhichtosufficientlydiluteUnit2circulatingwatersystemdischargepriortoitsreturntothelake.AsthereisadequateUnit1intakeflowtoaccommodatetheUnit2discharge,andthecopperconcentrationwillnotaffectthereliabilityofequipment,thereisnoimpactontheoperationofUnit1.TheremainderoftheUnit2circulatingwatersystemwillcontinuetofunctionasdesigned.TheUnit2CWScopperconcentrationwillnotaffectthereliabilityortheUnit2servicewatersystemrelativetocorrosion.OperationoftheUnit2temperingwatersystemwillhavenonegativeimpactontheservicewatersystemandwillmaintaintheintakewatertemperature.TheadditionofascaleinhibitortotheUnit2circulatingwaterwillhavenonegativeimpactonsystemandequipmentoperationorreliability,andwillhelptoextendservicelifebycontrollingthecorrosiveeffectsofscaling..Theadditionofacorrosioninhibitorwillreducecopperleachingfromthecondensertubesandreducethelevelofsolublecopperinthecirculatingwater.lntheeventofacondensertubeleak,theadditionofthesecompoundswillnothaveanegativeimpactonthechemistryofcondensatewater,feedwater,orreactorwater.AnincreaseinthelevelofchloridesintheUnit2circulatingwateriswithintheabilityofthedemineralizerstomaintainthequalityoffeedwater/reactorwater.

SafetyEvaluationSummaryReportPage53of112SafetyEvaluationNo.SafetyEvaluationSummary:89-069,Rev.4(Continued)(Continued)Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage54of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-070E&DCRC46950C,ECNSFC-612Figure9.1-6(Sheets3,6)SpentFuelPoolCoolingSystem(SFC)TitleofChange:SpentFuelPoolCoolingRelayChangesDescriptionofChange:TheSFCcirculatingpumpflowtimedelayrelayswereresettingassoonasthepumpsweretrippedonlowfloworlowdischargepressure.Thesealarmconditionswerenot"seen"bythePMScomputerduetothealarmcontactresettimebeingmuchfasterthanthecomputerscantime.ThischangereplacedthesubjectAgastatrelayswithAgastatrelayscapableofperformingtwotimedelayfunctions(fourpole,doublethrow).Theoriginaltimedelayfunctionfortrippingthepumpremainsasoriginallydesigned.Thesecondtimedelayfunctionisonlyforholdingthealarmcontactsinlongenoughforthecomputertosensethecondition.SafetyEvaluationSummary:ThesecondtimedelayfunctionofthereplacementrelaysinnowayaffectstheoperationoftheSFCpumps.ThenewAgastatrelaysarethesamesizeastheoldrelaysandareinstalledintheexistingsafety-relatedswitchgear,2ENS*SWG101and2ENS*SWG103.Thenewrelaysaresafety-relatedandmeetthesamedesignandqualificationrequirementsastheoldrelays.Basedontheevaluationperformed,'itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage55of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-071TemporaryMod.89-94N/ACondenserAirRemovalSystem,OffgasSystemTitleofChange:UseofHeliumLeakDetectionSystemDescriptionofChange:Thistemporarymodificationisfortheinstallationanduseofaheliumleakdetectionsysteminanefforttolocatepointsofairinleakagetothecondenser.Thegeneraltestmethodistosprayheliumaroundpotentialpointsofairinleakageatcomponents~~subjecttocondenservacuum(packings,flangedjoints,fittings,etc.)andtoobservethetestmonitorforindicationsofheliumdetection.Theheliumleakdetectorteststationwillbeinstalledat,theairremovalpump2ARC-P1Aduringstartup(steamlinepressure(200psig)andintheoffgascharcoaladsorberroomwhenthesteamjetairejectorsareoperating.Bothlocationswillutilizethesametestequipment:heliumleakteststation(VeecoModelMS-170),3/8"coppertubingwithfittings,shutoffvalves,andavacuumpump.SafetyEvaluationSummary:Thischangehasnoeffectontheoperationorfunctionofthecondenserairremovalsystem,theoffgassystem,orthemaincondenser.Noneofthesesystemsisrequiredforsafeshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage56of112SafetyEvaluationNo.:ImplementationDocumentNo.:89-072LDCNsU-782,U-1405,andU-1401USARAffectedPages:37A20g3~7A25g3~7A26g3.7A-27,3.9A-3a,3.9A-4,39A5g3'A23'A~151g3A152g3A15A1g3A~15A2g6A.3-6,6A.3-11,6A.9-3(Non-Proprietary),and6A.3-11,6A.3-27(Proprietary)System:TitleofChange:N/APermitUseoftheSUPERPIPEComputerProgramforPipingAnalysisDescriptionofChange:ThischangepermitsdesignengineerstousethecomputerprogramSUPERPIPEasanalternativetoNUPIPE-SWforpipinganalysis.SafetyEvaluationSummary:NUPIPE-SWandSUPERPIPEaresimilarprograms.Bothrequirepipingtobeidealizedusingdiscretemasspointswhoseconnectingmembersareassignedrepresentativephysicalproperties.Bothprograms'developstiffnessmatricesandsolveforresultantdeflections,loads,andstresseswhensubjectedtoexternalloads.Theanalyticalmethodsusedtosolvecomplexequationsarealsosimi'lar.AllanalysismethodologiesandcommitmentsdescribedinUSARSections3.7,3.9,andAppendix6Athatareimplementedbyroutinesinacomputerprogramremainunchanged.Eitherprogramcanbeusedwithoutaffectinganypipinganalysisprocedureorcriteria.ThemaindifferencebetweentheprogramsisthatSUPERPIPEprovidesautomaticoptionsformodelling,analyzing,andcombiningloadcasesthatarenotprovidedinNUPIPE-SW.TheSUPERPIPEprogramhasbeenbenchmarkedinaccordancewiththeNRCacceptancecriteriaoutlinedinStandardReviewPlanSection 0

SafetyEvaluationSummaryReportPage57of112SafetyEvaluationNo.89-072(Continued)SafetyEvaluationSummary:(Continued)3.9.TheSUPERPIPEvendorhasaworkingqualityassuranceprogramandsoftwarecontrolprogramwhichhasbeenauditedbyNMPCforcompliancewiththeintentof10CFR50AppendixB.Basedon-theevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion

SafetyEvaluationSummaryReportPage58of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:89-073EDC2M00308IEDC2M10080Figures5.4-16a,5.4-17(Sheet1)System:ReactorWaterCleanupSystem(WCS)TitleofChange:ChangePositionIndicationfor2WCS*MOV101and2WCS*V41toShowNormalPositionDescriptionofChange:ThisdrawingchangerevisesthenormalpositiondesignationonthesystemPaIDandthecorrespondingUSARfiguresforvalves2WCS*MOV101(fromnormallyclosedtonormallyopen)and2WCS*V41(fromnormallyopentonormallyclosed).Thischangereflectsthemannerinwhichthereactorwatercleanupsystemisnormallyoperated.SafetyEvaluationSummary:ThereisoneRPVbottomdrainlinethatisasupplytotheWCSsystem.This4"linehasanormallyclosedmotoroperatedvalve,2WCS*MOV101,thatisusedtocontrolthermalstratificationwhentheRCSpumpsareunavailable.A2"bypasslinearound2WCS*MOV101hasamanuallyoperatedvalve,2WCS*V41,thatisnormallyleftopentoprovideaconstantflowbacktotheWCSsystemtoremovecrudanddebrisfromthebottomheadarea.Bothvalvesarelocatedinthedrywell.Industryoperatingexperienceindicatesthatduringnormaloperation,the2"bypasslinebuildsupcrudblockageovertime.Thisblockagesignificantlyreducesflowthroughthe2"bypasslinenecessitatingtheopeningofthe2WCS*MOV101valvetomaintaintheflow.

SafetyEvaluationSummaryReportPage59of112SafetyEvaluationNo.89-073(Continued)SafetyEvaluationSummary:(Continued)Tosimplifyoperationsofthesetwovalves,theWCSsystemwillbeoperatedwiththe2WCS*MOV101valvenormallyopenandthe2WCS*V41valvenormallyclosed.Thisvalvelineupwillmaintainthedesignfunctionoftheline,whileprovidingthebenefitofremoteoperatingcapabilityforvalve2WCS*MOV101fromtheControlRoomtoisolatetheWCSsystemfromtheRPV,ifrequired.Thischangeinnormaloperationswillnotrequireanyphysicalchangestotheplant,andwillnothaveanyeffectonsysteminteractionorsafeoperation.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage60of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:89-074EDC2S100959A.2-2,9B.2-1;Figures9A.3-5,9A.3-6,9A.3-7System:TitleofChange:FireProtectionFireZoneCorrectionsDescriptionofChange:Variouschangesaremadetothefireprotectionarrangementdrawings(EB-22series)andtheassociatedUSARfiguresinAppendix9A.Thesechangesareneededtocorrectlyrepresentfireprotectionequipmentlocationsandfirezoneboundaries.Theaffectedareasaretheauxiliaryservicebuildingsouthandtheturbinebuilding(FireArea50,Zone762NZandFireArea80,Zones246NW,611NW,and761NZ).Correspondingrevisionsaremadetothecombustibleloadingtabulationsfortheaffectedfirezones,andtoProcedureN2-FDP-11,FireProtectionPreplans.Lastly,thedefinitionofafireareainUSARSections9A.2.4and9B.2isclarifiedtoindicatethatseparationoffireareasby2-hourfirebarriersisacceptableincertaincircumstances.SafetyEvaluationSummary:ThechangestoUSARFigures9A.3.5through9A.3.7,ProcedureN2-FDP-11andtheUSARfireareadefinition,Sections9A.2.4and9B.2,willensuretheplantas-builtorientationiscorrectlyrepresented.Thesearedocumentationchangesonly,andnophysicalplantmodificationsareinvolved.ThesechangeswillnotalteranysafetyfunctiondescribedintheUSARandarenotrequiredforsafeshutdown,asFireAreas50and80donotcontainsafeshutdownequipmentorcabling.Changingthedecontaminationroom,el.306ft.,fromZone761NZto762NZwillseparateFireAreas50and80bya2-hourratedfirewall.Thisarrangementsatisfiesthecircumstancesunderwhichseparationoffireareasbya2-hourfirebarrierisacceptableperBTPCMEB9.5-1.

0 SafetyEvaluationSummaryReportPage61of112SafetyEvaluationNo.89-074(Continued)SafetyEvaluationSummary:(Continued)Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage62of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:89-077,Rev.1WR169489'and169457N//ALiquidRadioactiveWasteSystem(LWS)TitleofChange:RetubingofRegenerantEvaporatorReboiler(2LWS-E7)andRetubingofWasteEvaporatorReboiler(2LWS-E4)DescriptionofChange:Thischangeinvolvestheretubingoftheregenerantevaporationreboilerandthewasteevaporatorreboiler.Thetubesofbothcomponentsweredamagedbycorrosionpitting.Theregenerantevaporatorreboilerhadbeentemporarilyrepairedbyliningthedeterioratedtubeswiththin-walledtubing.Thedamagedtubingandthesleevingusedasatemporaryrepairareremovedandreplacementtubing,equivalenttotheoriginal,installed.SafetyEvaluationSummary:Retubingoftheregenerantevaporatorreboilerandthewasteevaporatorreboilerrestoresthesecomponentstotheiroriginaldesignconditionsandwillhaveapositiveimpactontheeffectiveoperationoftheliquidradwastesystem.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage63of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-001Mod.PN2Y89MX158Figure10.1-5dCondensateSystem(CNM)Reworkof2CNM-RV71A/B/CPipingandReconfigurationofVentLinesDescriptionofChange:ReliefValves2CNM-RV71A/B/Cwerepreviouslylocatedabovecondensateventvalves2CNM-V212A/B/Candtheirassociatedpipinghighpoint,therebynotallowingcompleteairremoval.Themodificationrelocatedtheventlinessuchthattheytapoffthereliefvalveinletlines,riseabovetheelevationofthevalves(2CNM-RV71A/B/C)seats,thenroutedownintotheexistingventlinestotheirassociateddrain.Valves2CNM-V212A/B/Cwereremovedandre-installedwithinreachofthefloorelevationinthecurrentventlinepiping.Newvalves(2CNM-V370A/B/C)havebeenplacedineachofthenewhighpointventpipesections.Thischangealsoreconfiguresinletpipingto2CNM-RV71A/Bslightlytoprecludefailurecausedbycyclicvibration.SafetyEvaluationSummary:Thecondensatesystemisnotsafety-relatedandisnotrequiredforsafeoperationorshutdownoftheplant.Thismodificationensuresproperventingofairthusprecludingtheeffectsofwaterhammer,improvesaccesstotheventvalves,facilitatesrepairstotheventline,andenhancesvibrationhandlingcapability.Basedontheevaluationsperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage64of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-003Calc.A-10.1-AA-26,Rev.12.2-2,2.2-9N//ANMP2HelicopterOperationsDescriptionofChange:NMPChelicopterservicesprovidelocaltransportationbetweenthesiteandsurroundingareasincludingSyracuseHancockAirport.ThissafetyevaluationreviewstheacceptabilityofthistypeofoperationinthecontextofaircrafthazardsasdiscussedinUSARSections2.2.3.1.7and3.5.1.6.NMP2helicopteroperationsinvolveapproximately45to60flightsperyearbetweentheSyracuseAirportandthesite.Theflightpathdoesnotencroachontheairspaceabovethesitesecurityfence.SafetyEvaluationSummary:TherearecurrentlythreehelicopterlandingareasinthevicinityofNMP2,allwithinapproximately0.5milesofthesite:1.Intheparkingarea,approximately1200ftsoutheastoftheNMP2reactorbuilding.2.Intheparkingareaadjacenttothetrainingcenter.3.Inthelawnareaadjacenttothetrainingcenter.BasedontheNRCStandardReviewPlan3.5.1.6methodology,theconservativelycalculatedprobabilityofahelicopteraccidentleadingtoradiologicalconsequencesinexcessof10CFR100limitshasbeenestimatedtobe1x10.Basedontheconservatismsincludedincalculatingthisvalue,itcanbereasonablyconcluded,thattheactualprobabilitywouldbelessthanabout10perreactoryear.InaccordancewithNRCStandardReview

SafetyEvaluationSummaryReportPage65of112SafetyEvaluationNo.90-003(Continued)SafetyEvaluationSummary:(Continued)Plans2.2.3and3.5.1.6,thisensuresthathelicopteroperationsdonotrepresentacrediblehazardtotheplantandneednotbeconsideredintheplantdesignbasis.Basedontheanalysesandevaluationsperformed,itisconcludedthatNMPChelicopteroperationsdonotconstituteanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage66of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-004Mod.PN2Y89MX155Figure10.1-6cFeedwaterPumpSealandLeakoffSystem(FWP)FeedPumpSealCoolingLineIsolationDescriptionofChange:Thismodificationrelocatesisolationvalves2FWP-V12A/B/Candaddsbreakflangesinthesealwatercoolinglinestothefeedwaterpumps(2FWS-P1A/B/C).Thepreviousarrangementdidnotprovidesufficientflexibilityformaintenanceofthefeedwaterpumpsduringplantoperationorshutdownconditions.SafetyEvaluationSummary:Thismodificationfacilitatesthe"performanceofmaintenanceonthefeedwaterpumps.Thefunctionandoriginaldesignrequirementsofthefeedwaterpumpsealandleakoffsystemarenotchanged.Thesystemisnotsafety-related,andthechangeswillnothaveanyadverseeffectonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage67of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-005QATR-1,Rev.517~21N/ARevision5toQualityAssuranceTopicalReport(QATR-1)DescriptionofChange:Revision5totheQualityAssuranceTopicalReport(QATR-1)hasbeenissued.Revision5isageneralupdateandclarification,includingchangesintheNuclearDivisionorganizationsincetheissueofRevision4.~~SafetyEvaluationSummary:QATR-1Revision5wastransmittedtotheNRCinletterNMP1L0475datedFebruary5,1990,tosatisfytherequirementof10CFR50.54foranannualupdatetotheQAProgram.AsnotedinNMP1L0475,thechangesincludedinQATR-1Revision5donotreducetheeffectivenessoftheQAProgram.Thus,thesechangeswillnotadverselyaffectthesafeoperationorshutdownoftheplantanddonotinvolveanunreviewedsafetyquestion.

t SafetyEvaluationSummaryReportPage68'of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:90-007Mod'.PN2Y89MX157Figure10.1-6aTurbineBuildingEquipmentDrainsSystemTitleofChange:RelocationofFeedwaterPumpDrainLineDescriptionofChange:Thefeedwaterpumpdrainsprovidethemeansbywhichtodrainwaterfromthepumpsandnearbypipingwhenmaintenanceand/orrepairisrequired.Previously,thewaterwasdirectedtotheturbinebuildingfloordrainsystemwithdischargetotheLWSdraincollector"subsystem.However,thedraincollectorsystemdidnothavethecapacitytoadequatelyprocessthefeedwater.ThismodificationdirectsthepumpdrainwatertotheequipmentdrainsystemwithdischargetotheLWSwastecollectorsubsystem.SafetyEvaluationSummary:Feedwaterisnon-oily,lowconductivitywatercompatiblewiththeequipmentdrainandLWSwastecollectorsystems,andthesesystemshavethecapacitytohandletheadditionalwater.Theinstallationwillbemadewithmaterialsandspecificationsequaltothoseoftheoriginalinstallation,andtheabilitytodrainthefeedwaterpumpswillnotbeimpacted.FailuresassociatedwiththischangewillnotexceedfloodingconditionsalreadyanalyzedintheUSAR,referenceSection3.4.1.Thesechangeswillnotadverselyaffectthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthismodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage69of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-009Mod.PN2Y90MZ003Figure10.1-5dCondensateSystem(CNM)FeedwaterPumpSuctionValve,BypassValve,2CNM-HV59A,B,CDescriptionofChange:Thismodificationaddedamanualvalveinthebypassloopdownstreamofbypassglobevalves2CNM-HV59A,B,C.Themanualvalveprovidesameansofgraduallyincreasingtheflowofwarmerwaterandalsoprovidesapositiveisolationcapabilityforfeedwaterpumprepairs.SafetyEvaluationSummary:Thechangesimplementedbythismodificationwillnotalterthe.intendeddesignfunctionofthecondensatesystem.Themodificationwill,however,improveoverallperformanceofthesystem.Noneofthesafety-relatedstructures,systems,orcomponentswillbeimpactedbythismodification.Thismodificationwillnotadverselyimpactthecapabilitytoshutdowntheplantsafelyandtomaintaintheplantinasafeshutdowncondition.Therefore,itisconcludedthatthismodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage70of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-010Mod.PN2Y90MZ005Figures9.3-12j,10.1-5dCondensateSystem(CNM)2CNM-HV119DescriptionofChange:Thecondensatesystemwasventedthroughhighpointventfeedwaterpumpsuctionvalve2CNM-HV119.Thisventdrainsintoanequi:pmentdrainlocatedinthevicinityofthevalve.Duetopersonnelsafetyconcernsraisedduetohightemperatureandsplashingofhotfluidsintheareaatthetimeofventing,line2-CNM-750-308-4hasbeenre-routedandtiedintoanexistingdrainline.Anisolationvalvehasalsobeenaddedinline2-CNM-750-308-4downstreamofvalve2CNM-HV119.SafetyEvaluationSummary:Thismodificationalleviatestheconcernsregardinghightemperatureandsplashingofhotfluidsintheareaatthetimeofventing,allowsforthesystemtobeventeddirectlytothemaincondenserduringnormaloperation,andeliminatesthereleaseofcontaminatedsteamtotheatmosphere.Thechangesarenon-safetyrelatedanddonotadverselyaffecttheabilityofanysafety-relatedstructures,systems,orcomponentstoperformtheirsafetyfunction.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage71of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-012EDC2F00030N/ATurbineBuildingFloorDrainSystem(DET/DFT)RerouteEffluentof2SST-TK1FlowPathfromtheFloorDrain(DFT)totheEquipmentDrain(DET)DescriptionofChange:Thistemporarymodificationreroutestheeffluentof2SST-TK1(turbinebuildingsamplepanelrecoverytank)fromthefloor~~drainsystem(DFT)totheequipmentdrain(DET)system.SafetyEvaluationSummary:Thewaterfromtank2SST-TK1isnormallyofpermissibleforinfluxtotheequipmentdrain(DET)system.ShouldconductivitywaterentertheequipmentdrainsystemviaTKl,ahighconductivityalarmwouldbereceivedinthecontrolroom,alertingtheoperatortotakeappropriaterequiredbyexistingprocedures.qualityhigh2SST-radwasteactionasThetemporarychangesarenon-safety-relatedanddonotadverselyaffecttheabilityofanysafety-relatedstructures,systems,orcomponentstoperformtheirsafetyfunctions.ThefloodanalysisasdescribedinUSARAppendix3Cisalsonotaffected.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage72of112SafetyEvaluationNo.:ImplementationDocumentNo.:90-013TemporaryMods90-003thru90-011USARAffectedPages:System:N//AEquipmentandFloorDrainSystems(Various)TitleofChange:TemporaryModificationforDefeatingNine(9)Equipmentand//orFloorDrainNuisanceAlarmsintheMainControlRoomPanel2CEC*PNL851DescriptionofChange:Thistemporarymodificationistodefeatthefollowingequipmentand//orfloordrainnuisancealarmsatControlRoompanel2CEC*PNL851,andallowOperationstomaintainthesesystemtroublealarmsthroughdirectresponsetothespecificradwastecontrolroomannunciatorinalarmatpanel2CES-PNL513.1.2.3.5.6.7.8.9.ReactorBuildingEquipmentDrainSystemTroubleReactorBuildingFloorDrainSystemTroubleTurbineBuildingFloorDrainSystemTroubleTurbineBuildingEquipmentDrainSystemTroubleMainStackFloorDrainSumpTank3SystemTroubleAuxiliaryBoilerBuil'dingFloorDrainSystemTroubleRadwasteBuildingFloor/'EquipmentDrainSystemTroubleCondensateStorageTankFloorDrainSystemTroubleMainStackFloorDrainTank2SystemTroubleSafetyEvaluationSummary:Currently,annunciatorsontheradwastecontrolpanel2CES-PNL513supplyacommonannunciatorsystemtroublealarmtotheMainControlRoompanel2CEC*PNL851.Thistroublealarmisageneralnon-specificindicationthatrequiresoperatorstoaccessradwastecontrolroompanel2CES-PNL513forthespecificproblemindicationtobecorrected.

SafetyEvaluationSummaryReportPage73of112SafetyEvaluationNo.90-013(Continued)SafetyEvaluationSummary:(Continued)Thedefeatingofcontrolroompanel2CEC*PNL851nuisancetroublealarmswilleliminatethedistractionandtime-consumingeffortsoftheMainControlRoomoperatorstocorrectthesealarms.Thespecificradwastecontrolroomannunciatortroubleconditionwillbecorrectedattheradwastecontrolroomwhichismannedonacontinuousbasis.Thesechangesarenon-safety-relatedandwillnotaffectthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage74of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:90-015,Rev.1TemporaryMod.90-012N/ARadwasteBuildingFloorandEquipmentDrainSystem(DFW)TitleofChange:TemporaryReplacementofRadwasteFloorDrainSumpPumpDescriptionofChange:Duetotheunavailabilityofsparepumpsorparts,atemporarysumppumpisinstalledinthesumpservedbypump2DFW-P1A/B.Thisinvolvestheremovalofa2"flangedspoolpieceandassociatedsumpcoverplatefromthesumppumpdischargepiping,allowingthetemporarysumppumptobetiedin.Additionally,an~~~alternatemeansofprocessingdrainwaterthroughtheradwastefloordraincollectorsurgepumps2LWS-P17A/Bisaccomplishedbymeansofatemporaryhoseinstalledbetweenadrainvalveinthe2DFW-P1Adischargepipeandasuctionstrainerdrainvalveofftheinletpipingtothefloordraincollectorsurgepumps.SafetyEvaluationSummary:Thechangeimplementedbythistemporarymodificationwillnotchangethefunctionoftheexistingfloordrainsystemoraffectthesafeoperationorshutdownoftheplant.TheremovedspoolpiecedoesnotperformanyprotectivefunctionfortheDFWsystem.Thistie-inwillallowfortheuseofexistingdischargepipingcheckandisolationvalvestocontroldischargeflow.Thetemporaryhoseinstallationallowsalternateprocessingofdrainwater,ifrequired,andisnotdetrimentaltonormalsystemoperation.Thetemporarysumppumpoperationcanalsobemonitoredbyinstalledsumptanklevelswitches.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage75of112SafetyEvaluationNo.:ImplementationDocument=No.:UFSARAffectedPages:System:90-020TemporaryMod.90-025N/AFireProtectionWaterSystem(FPW)TitleofChange:TemporarySprinklerSystem/TurbineBuildingEl.250'-0"DescriptionofChange:Atemporarysprinklersystemisinstalledtoprovideadditionalfireprotectiontotheareaatel.250'-0"underneaththeturbinetrackbay.Theareaisfrequentlyusedasaworkareaforrepair~~~~~andmaintenanceofequipmentwhich,onsomeoccasions,resultsinstorageofcombustibles.Thetemporarysprinklersystemischargedfromthewatersupplytofirehosereelno.5andisattachedwithamanualvalvebetweenvalveFPW-V203andthehosereel.Theattachmentissuchthatthehoseandsprinklermaybeoperatedindependentlyofoneanother.Thesprinklerpipingisattachedtothebottomoftheel.261'-0"turbinetrackbaysteelandincorporates21sprinklerheadsandprovidesapproximately900sq.ft.ofcoverage.SafetyEvaluationSummary:Thistemporarymodificationislocatedinanon-safety-relatedareaandwillnotaffectanysafety-relatedequipmentorsafeshutdownoftheplant.Thetemporarysprinklersystemisinstalledbeneaththeturbinetrackbayusinghangerstosuspendthepipingfromthestructuralsteel.Theadditionalloadinginducedintothestructuralsteelbythehangersisminimalandwillnotimpactthestructuralintegrityofthetrackbayslab.Ifasprinklerpiperupturewouldoccur,nosafety-relatedequipmentwouldsustaindamagefromflooding.

0 SafetyEvaluationSummaryReportPage76of112SafetyEvaluationNo.90-020(Continued)SafetyEvaluationSummary:(Continued)Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage77of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-022FPEE-2-89-011,EDC2S10168Figure9A.3-5FireProtectionIncorporationofFireProtectionEngineeringEvaluationsIntoFireProtectionArrangementDrawingDescriptionofChange:USARFigure9A.3-5depictsanon-safeshutdown,non-BTP,balanceofplantfirebarrierwhichhasanunsealedacidtrenchrunningbeneaththebarrier.AFireProtectionEngineeringEvaluation~~~~~~~~(FPEE)hasbeenwrittenanalyzingandjustifyingtheopening.ThischangereferencestheFPEEonthefireprotectionarrangementdrawingandassociatedUSARFigure9A.3-5toprovideclarificationandtraceabilityforthefireprotectionprogram.SafetyEvaluationSummary:ThisrevisionhasnoadverseimpactontheFireProtectionProgram,doesnotadverselyaffecttheAppendixRSafeShutdownAnalysis,andisconsistentwiththeguidanceprovidedbyStandardReviewPlanCMEB9.5.1.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage78of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:90-023N/AN/ALiquidWaste/ProcessandEffluentRadiologicalMonitoringandSamplingTitleofChange:TemporaryModificationfor2LWS-CAB206anditsElectricalInterlocktoValve2LWS-AOV142DescriptionofChange:Thistemporarychangeremovestheelectricalinterlockbetweenradiationmonitor2LWS-CAB206andvalve2LWS-AOV142toallowtheoperationofthevalveif,perTechnicalSpecifications,independentsamplesarewithinspecificationlimitstodischargeliquidwasteeffluentsintotheservicewatersystemdischargebay.Radiationmonitor2LWS-CAB206iscurrentlyinoperative,anditsrepairrequiresitsde-energization,whichcausesvalve2LWS-V142tocycleautomaticallyclosedpreventingtheonlydischargepathforliquidwasteeffluentsintotheservicewatersystemdischargebay.SafetyEvaluationSummary:Withradiationmonitor2LWS-CAB206inoperative,TechnicalSpecificationsrequirements(L.C.O.3.3.7.9,ActionStatement"b,"andItem1,Table3.3.7.9-1)alloweffluentreleasestocontinueprovidedthat,beforeinitiatingarelease,atleasttwoindependentsamplesareanalyzedinaccordancewithSpecification4.11.1.1.1(Table4.11.1-1,Item1),andatleasttwotechnicallyqualifiedmembersofthefacilitystaffindependentlyverifythereleaseratecalculationsanddischargelinevalving.TheseTechnicalSpecificationsrequirementsarebeingfulfilled.ThelossofliquidwasteeffluentmonitoringforaperiodinexcessofthirtydayswillbeaddressedintheSemiannualRadioactiveEffluentReleaseReportasrequiredbySection3.3.7.9,ActionBoftheTechnicalSpecifications.

SafetyEvaluationSummaryReportPage79of112SafetyEvaluationNo.90-023(Continued)SafetyEvaluationSummary:(Continued)Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationwillnotimpactthesafeoperationorshutdownoftheplantanddoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage80of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:90-024EDC2E00437Figures6.2-71a,9.3-1d,9.3-1fSystem:InstrumentAirSystem,ContainmentAtmosphereMonitoringSystemTitleofChange:PID-19D,19F,and82ATypographicalErrorsDescriptionofChange:TypographicalerrorswerefoundandcorrectedonPID-19D,19F,and82ArelatingtoERFcomputeridentificationnumbers~~~~~~~~~~(duplicationandomissions).TheassociatedUSARfiguresarerevisedaccordingly.SafetyEvaluationSummary:Thisisadocumentationchangeonlyanddoesnotinvolveanyphysicalchanges.USARfigurechanges(ERFcomputeridentificationnumbers)aremadetobringthefigurestoanas-builtconfiguration,andnologicfunctionsareaffected.Thesedocumentcorrectionsdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage81of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:90-029EDC2M00340Figures9.4-8a,9.4-10a,9.4-12bSystem:Reactor,Turbine,andRadwasteBuildingsHVACSystemsTitleofChange:RemovalofPre-filtersfromtheReactor,Turbine,andRadwasteBuildingsSupplyAirVentilationUnitsDescriptionofChange:Thismodificationprovidesfortheannualremovalofintakepre-~~~~~~~~filtersfromthereactorbuildingnormalventilationsystem,theturbinebuildingHVACsystem,andtheradwastebuildingHVACsystemforthedurationofthewintersnow'season.Theequipmentidentificationnumbersforthesepre-filtersare2HVR-FLT4throughFLT9(reactorbuilding),2HVW-FLT1(radwastebuilding),and2HVT-FLT3andFLT4(turbinebuilding).Duringsevereweatherconditions,(highwindswithlake-effectsnow),operationofthesesystemshasresultedintheaccumulationofsnowandiceonthepre-filterscausingahighpressuredifferentialacrossthefilters.SafetyEvaluationSummary:OperationoftheaffectedHVACsystemswithoutthepre-filtersinplaceisacceptablesincedownstreamfiltersareinplaceandprovidetherequireddegreeoffiltration.Theoutsideairisgenerallycleanerduringthewintermonthsbecausethegroundissnow-covered,frozen,orwet,andtheairisfreeofflyinginsects,incontrasttoconditionsinsummermonths.Also,theexistingsystemsprovidealowtemperaturealarmintheeventthattheheatingcoilweretobecomeinefficient,andatroublealarmwillbepresentifahighdifferentialpressureexistsacrossthedownstreamfilters.Inaddition,theoutsidesurfacesandfinsoftheheatingcoilsareinspectedforcleanlinessat

SafetyEvaluationSummaryReportPage82of112SafetyEvaluationNo.90-029(Continued)SafetyEvaluationSummary:(Continued)leastonceayearandcleanedifnecessary.Thismodificationaffectsthenon-safetyrelatedportionsofthereactorbuildingventilationsystemandthenon-safetyrelatedradwasteandturbinebuildingventilationsystems.Thesechangesdonotadverselyaffecttheabilityofanysafety-relatedsystemsorcomponentstoperformtheirsafetyfunction.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage83of112SafetyEvaluationNo.:ImplementationDocumentNo.:90-035DrawingsEV-4M-1,EM-021M;GEN-930,EV4K3gEV4L3EV198AQOgEM002GgProceduresN2-MMP-931USARAffectedPages:9.1-32;Table3.2-1(Sh.16,26h);Figures1.2-10(Sh.2),9.1-25,12.3-12,12.3-45;Appendix9C,Figure5-2System:TitleofChange:RefuelingEquipmentReactorInternalsStoragePoolGateDescriptionofChange:~~~~~Thischangeinvolvesthepurchaseandinstallationofthereactorinternalsstoragepoolgatetosupportrefuelingoutageactivities.Thoughthisactivitywasdeferreduntilaftercommercialoperation,thegatedetailsarealreadyshownonplantdesigndrawings,andthegatestoragelocationiscurrentlyshownintheFSAR.Inordertofacilitaterefuelingoutageoperationsandmaintenanceactivities,thelaydownlocationforthereactorinternalsstoragepoolgate,andalsoforthereactorvesselinsulation,reactorvesselserviceplatform,andthestudtensionerandstandhavebeenrevised.Operatingandmaintenanceprocedureshavealsobeenrevisedtoaddressrestrictionsontheuseofthereactorinternalsstoragepoolgate.SafetyEvaluationSummary:Thereactorinternalsstoragepoolisdesignedtofacilitatestorageofthereactordryerandseparatorduringrefueling.Thesealingmechanismassociatedwiththegateiscomprisedofredundantinflatableseals.Thegate'ssealshavebeendesignedwithapressuregaugethatcanbereadilycheckedbyoperatorsatanytimeduringtheuseofthereactorinternalsstoragepoolgatetoconfirmsealintegrity.Additionally,eachgatesealhasadedicatedcheckvalvewhichisdesignedtominimizetherateat

SafetyEvaluationSummaryReportPage84of112SafetyEvaluationNo.90-035(Continued)SafetyEvaluationSummary:(Continued)whichsealairpressuredecreasesintheeventofalossofthenon-safety-relatedinstrumentairsystem.Theinternalsstoragepoolisrequiredtobefloodedwhileremovingtheseparatorandremainsfloodedduringtheentirerefuelingprocessuntilthesteamdryerandseparatorarere-installed.Therefore,anytimethatthereactorcavityisfloodedandthespentfuelpoolgatesareremoved,thereactorinternalsstoragepoolwillbeflooded.Consequently,atnotimecouldafailureofthereactorinternalsstoragepoolgateorsealresultinloweringwaterleveltounacceptablelevelsinthespentfuelpool.TheinternalsstoragepoolgateisfabricatedsothatafailureofthestructuralaspectsofthegatewillnotoccurduringaSSE.Thisdesign/fabricationpreventsportionsofthegatefromfallingintotheRPVorontotherefuelingsealbetweentheRPVanddrywellwallduringaSSEwhenthegateisineithertheinstalledorstoredposition.Thegatehasalsobeendesignedtowithstandconcurrenthydrostaticandseismicloadswhenintheinstalledpositionbetweenthestoragepoolandthereactorcavity.Thechangetothelaydownareasfortheinternalsstoragepoolgate,reactorvesselinsulation,thereactorserviceplatform,andthestudtensionerdonotincreasethepossibilityorconsequenceofanaccidentormalfunctionsincetheentirerefuelfloorelevationissafety-relatedandhasbeendesignedtosupportheavyloadsregardlessoflocation.Heavyloadhandlingconsiderations,asdefinedinNUREG-0612,havebeenevaluated.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

0 SafetyEvaluationSummaryReportPage85of112SafetyEvaluationNo.:ImplementationDocumentNo.:90-036TemporaryMods.90-028,90-029,90-030USARAffectedPages:System:N/ATurbineBuildingEquipmentDrains(DET),CondensateSystem(CNM)TitleofChange:DivertPumps2CNM-P2A,B,CPedestalDrainLineFlowDescriptionofChange:Thecondensateboosterpumps(2CNM-P2A,B,C)areseepingoilontothepumppedestalwhicheventuallyflowstotheattacheddrainlinesandtheDETdrainsystem.Thistemporarychangeinvolvesthediversionofflowofthecondensateboosterpumps(2CNM-P2A,B,C)pedestal'rainlinesfromtheturbinebuildingequipmentdrainsystem(DET)toacollectionapparatus.SafetyEvaluationSummary:Theturbinebuildingequipmentdrainsystem(DET)isforthecollectionandprocessingoflowconductivity,non-oilyradioactive,potentiallyradioactive,ornon-radioactivewater.ThetemporarymodificationwillpreventtheoilfromenteringtheDETsystemandallowOperationstomonitortherateofleakagefromthecondensateboosterpumps.Shouldawaterleakdeveloparoundthecondensatepumps(2CNM-P2A,B,C)thatproducesflownormallydirectedtotheequipmentdrainsystem(DET)throughtheaffecteddrainlines,andsaidflowweresufficienttooverflowthecollectorapparatus,thefloordrainsystem(DFT)iscapableofhandlingtheaddedvolume.ThefloodanalysispreviouslyevaluatedinSection3.4.1oftheUSARisnotaffected.

0 SafetyEvaluationSummaryReportPage86of112SafetyEvaluationNo.90-036(Continued)SafetyEvaluationSummary:(Continued)Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage87of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:90-040TemporaryMod.90-032N/AReactorPlantSamplingSystem(SSR)TitleofChange:2SSR-IPNL145HydrolasingDescriptionofChange:Hydrolasingwasperformedonthedrainheaderforthereactorwatersamplepanel,2SSR-IPNL145,toreducecontaminationandtheresultingexposurestoChemistrypersonnelusingthesamplepanel.Seventubinglinesareservicedbytheheader.Toaccomplishthehydrolasing,theheaderwasisolatedbyclosingisolationvalvesinfiveofthetubinglines(whichplacestheminaninoperablestate),andbymodifyingtwolinesbyaddingTygontubingofsufficientlength(lessthan10'-0")tobypasstheheaderandaccessequipmentdrain2DER-ED4404directly.SafetyEvaluationSummary:Althoughfivetub'inglineswhichutilizethedrainheadertoroutewatertotheequipmentdrain(2DER-ED4404)willbemarked-upandinoperable,thetwolineswhicharerequiredtomeetTechnicalSpecificationsrequirementsinSection3/4.4.4regardingcontinuousmonitoringofreactorwaterconductivity(influenttoRWCUfilter-demineralizersandRCSsystemloopApumpdischarge),willremaininservice.Hydrolasingoftheheaderwillonlyrequiretheheadertobeisolatedtemporarily.Thesamplepaneldesignstillprovidesameansforobtaininggrabsamplesfromthefivesamplelineswhichareinoperable,ifneeded.Thistemporarymodificationisexpectedtobeinplacelessthanoneweekandwillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthistemporarymodificationdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage88of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-041EDC2F0069Figure9.2-2(Sheet19)ServiceWaterSystemUSARFigure9.2-2,DrawingErrorDescriptionofChange:Thischangecorrectsanerrorthatwasfoundontheservicewatersystemlogicdiagram,USARFigure9.2-2,Sheet19.Theannunciatorwindowidentifiedas851225shouldactuallybe851255(RHRheatexchangerservicewaterdischargeradiationhigh).SafetyEvaluationSummary:Thisisadocumentationchangeonlyanddoesnotinvolveanychangestotheactualsystemlogic.Thisdocumentcorrectionreflectstheas-builtplantconditionanddoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage89of112SafetyEvaluationNo.:XmplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-042FPQAP-l,Rev.29A.3-32FireProtectionQualityAssuranceProgramRevision2toFireProtectionQualityAssuranceProgram(FPQAP-1)DescriptionofChange:Revision2totheFireProtectionQualityAssuranceProgram(FPQAP-1)hasbeenissued.Revision2isageneralupdateandclarification,includingchangesintheNuclearDivisionOrganizationsincetheissueofRevision1.SafetyEvaluationSummary:4FPQAP-1Revision2wastransmittedtotheNRCinletterJP90-228,datedMay25,1990,tosatisfytherequirementof10CFR50.54foranannualupdatetotheQAprogram.AsnotedintheMay25,1990letter,thechangesincludedinFPQAP-1Revision2donotreducetheeffectivenessoftheFireProtectionQAprogram.Thus,thesechangeswillnotadverselyaffectthesafeoperationorshutdownoftheplantanddonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage90of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:90-044TemporaryModificationN/AMoistureSeparators6ReheatersTitleofChange:TemperatureMonitoringofReheate'rDrainReceiverTanks(2DSR-TK6A/6B)LevelInstrumentationDescriptionofChange:Thistemporarymodificationinvolvesexternallyattachingtemperaturesensorstothestandpipes,instrumentlines,level~~~~~~~switches,andassociatedreferencelegsofthereheaterdrainreceivertanks.Temperaturedatawillbecollectedtodetermineifthecalibrationofthetanklevelinstrumentationcontainserrorsresultingfromincorrectdensityvalues.Thetemperaturesensorsarepoweredfromnon-safety-relatedsources.SafetyEvaluationSummary:Thistemporarymodificationaddstemperaturesensorstonon-safety-relatedpiping,standpipes,andinstrumentlinestocollecttemperaturedata,andwillnotaffectthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage91of112SafetyEvaluationNo.:90-050ImplementationDocumentNo.:N/AUSARAffectedPages:System.TitleofChange:N/AControlBuildingChilledWaterSystem(HVK)Operationof2HVK*CHL1AwithWornOilSealDescriptionofChange:Controlbuildingchiller2HVK*CHL1Acompressorsealhasbecomewornallowingtheoilintheuppersumptoseepdowntothelowersumpwhentheunitisnotoperating.Thisleakagewiththechillershutdownoveralongdurationwouldmakeautomaticstartsuncertain.Thxsevaluate.onanalyzestheoperationofthechiller(2HVK*CHL1A)withthewornsealutilizingatrendingprogramtodeterminetherateofdegradation.Thiswillassurereliableoperationofthechilleruntilrepairscanbefacilitated.Acceptancecriteriaaredevelopedwhichareusedtodeterminechilleroperability.SafetyEvaluationSummary:Toassurethatchiller2HVK*CHL1Awillbecapableofanautostart,itwillbeoperatedfulltime,therebynotallowingtheoiltoseepoutofitsupperoilsump,asispossiblewhilethechillerunitisshutdown.Theweeklysurveillanceprocedurewillchecktodetermineiftheidleleakageratefortheequipment(2HVK*CHL1A)isacceptabletoassureautomaticrestartforaDBAwithinterruptionofpowertothechiller.Aspecialsurveillanceprogramwilltrendthecompressorseal'sconditionusingtwomethods;onemethodtrendsbearingpressureonceeachshiftandtheothermethodtrendssealleakageonaweeklybasis.

SafetyEvaluationSummaryReportPage92of112SafetyEvaluationNo.90-050(Continued)SafetyEvaluationSummary:(Continued)Thetrendingprogramprovidessufficientconfidencethatunacceptablesealdeteriorationwillbedetectedinatimelymanner.Therefore,thisspecialsurveillanceprogramallowsoperationofNMP2withoutdeclaringchiller2HVK*CHL1AinoperablesincereasonableassuranceisprovidedthatthechillerwillstartandperformitsintendedfunctionforatleastthirtydaysconsistentwiththerequirementsofcontrolroomhabitabilityafteraLOCA.IfaLOCAeventoccurswithatotallossofoffsitepowertobothchillertrainsandasingleactivefailureoftheDivisionIIchiller(2HVK*CHL1B)torestart,adequateassuranceexiststhatchiller2HVK*CHL1Awillperformitssafetyfunction.ThedurationofthedowntimeassociatedwiththeweeklysurveillancetestissufficientlylongtodemonstratethatthechillerunitwouldautomaticallyrestartduringDBA.Basedontheevaluationperformed,itisconcludedthatoperationofthechiller(2HVK*CHL1A)isacceptableanddoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage93of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:90-066,Rev.1EAS-34-0688B,NEDC-31538P15.0-9,15.0-12,15.1-8;Table15.0-3(Sheets1,2,3)SystemTitleofChange:VariousNMP2IncreasedCoreFlowAnalysis(ICFA)DescriptionofChange:Thepurposeofthissafetyevaluationistoallowoperationsupto105%ofratedcoreflow(113.9MLB/HR)andrevisethecycle1CoreOperatingLimitReport(COLR).Thissafetyevaluationappliestothecycle1COLRonly.SafetyEvaluationSummary:TheresultsofthissafetyevaluationshowthattheMCPRoperatinglimitsforthelimitingtransients(Feedwatercontrollerfailureandloadrejectionwithbypassfailure)operatingintheICFAregionareboundedbythelicense(100%ratedcoreflow),exceptwhenEOC-RPTisoutofservice.AcorrectionismadetotheMCPRlimitintheCoreOperatingLimitReport(COLR)forEOC-RPToutofservice.ForotherequipmentoutofservicepreviouslyidentifiedintheTechnicalSpecifications,theoperatingMCPRlimitisnotaffectedbyincreasedcoreflowoperation.TheanalysisresultsalsoshowthatoperationintheICFAregioniswithinallowabledesignlimitsforoverpressureprotection,LOCA,containment,reactorinternalsandflowinducedvibration.IncreasedcoreflowisallowedundertheconstraintsofNMP2TechnicalSpecificationsandCoreOperatingLimitReport.Toensurethecurrentrodwithdrawalerroranalysisremainsvalid,theRMBsetpointwillbeclippedto106%.Basedontheevaluationandanalysesperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage94of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:90-085EDC2M10159Figures1.2-7(Sheet1),12.3-28,12.3-61System:TitleofChange:RadwasteBuildingRadwasteBuildingTruckBayRadiationZoneDescriptionofChange:USARFigures12.3-28and12.3-61arerevisedtoaddamissingradiationzonesymbol(/I)tothetruckbayarea.Figure1.2-7isrevisedtoincorporateamissingequipmentidentifier.Thesearedrawingchangesonly.SafetyEvaluationSummary:Dependingontheoperationsoccurring,thedoseratesinthetruckbayareawillvaryfrom(1MR/HRwhentheradwastetruckbayareaisemptyto>100MR/HRwhenacaskisbeingfilledforshipment.Thesedoserateswereassumedintheoriginalanalysisorcalculationsbutwereinadvertentlyleftoffthedrawings.Nochangesarerequiredtoanyotherdocuments.Basedontheevaluationperformed,itisconcludedthatthesedrawingchangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage95of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:90-107NMPCLettersNMP2L0653,NMP2L06657~17aInstrumentationandControls(General)TitleofChange:FSARSection7.1.2.3RevisionDescriptionofChange:Section7.1.2.3oftheFSARisrevisedasfollows:Thecommitmenttoperformananalysiswithrespecttotheuseofliftedleadsorjumpersisdeleted,asthecommitmentwassatisfiedbyNMPC'ssubmittalofletterNMP2L0653,datedMarch6,1986.2.Supplementalinformationisaddedwithrespecttoproceduralrequirementsgoverningtheuseofliftedleadsandjumpers.ThisinformationwaspreviouslysubmittedbyNMPCinletterNMP2L0665,datedMarch21,1986.SafetyEvaluationSummary:TheNRCSafetyEvaluationReport,Supplement3,Section7.3.2.5,concludesthat,basedonNMPC'scommitments,thenecessarystepsandprecautionsaretakentopermittestingofsafety-relatedsystemswithoutdegradingsystemfunctions.TheseFSARrevisionsreflecttheNRC-approvedpositionregardingtheuseofliftedleadsandjumpersduringtestingand,therefore,donotconstituteanyunreviewedsafetyquestions.

SafetyEvaluationSummaryReportPage96of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-108ProceduresNTP-11,NTP-161.10-16N/AFSARTable1.10-1RevisiontoAdministrationofTrainingProgramsDescriptionofChange:ThischangetotheNMPCpositionregardingNUREG-0737ItemI.A.2.3deletesreferencetoNMPUnit1SROlicenseholderssinceNMPUnit2nowhasitsowninstructorqualificationprogram.ThisrevisedFSARpositionclarifiesthequalificationrequirementforNMPinstructorsandmeetstherequirementsofNUREG-0737,andisconsistentwithFSARSection13.2.1.2inthatallinstructorsteachingthelicensedtrainingandretrainingprogramsshalldemonstrateSROqualificationsandparticipateinappropriaterequalificationprograms.SafetyEvaluationSummary:ThechangetotheNMPCpositionregardingNUREG-0737ItemI.A.2.3enhancestheclarityofthecurrentFSARpositionwithregardtoadministrationoftrainingprogramsconsistentwithNRCrequirementsandFSARChapter13.2commitmentsand,therefore,doesnotconstituteanunreviewedsafetyquestion.

SafetyEvaluationSummaryReport'QPage97of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-109N/ATable1.8-1,Sht.149of169N/ANMP2FSARTable1.8-1RevisiontoLicensedPersonnelMedicalEvaluationRequirementsDescriptionofChange:ThischangetoFSARTable1.8-1RegulatoryGuide1.134,Rev.1,1976,endorsedbythisrevisionRegulatoryGuide1.134,Rev.2,revisestheNMPCcommitmentfromandtheassociatedANSIN546-tothecurrentrequirementsofandANSI/ANS-3.4-1983.Additionally,referencetoFSARChapter13isdeletedsinceChapter13doesnotdiscussmedicalexaminationorcertificationrequirementsforlicensedoperators.SafetyEvaluationSummary:ThischangeupgradestheFSARcommitmentformedicalevaluationoflicensedoperatorsandsenioroperatorstothelatestNRCapprovedstandards.ThisrevisedcommitmentwascontainedinNMPC'sletterNMP62510,datedFebruary21,1990.Thus,thisFSARchangeisadministrativeinnatureanddoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage98of112SafetyEvaluationNo.:ImplementationDocumentNo.:90-113ProcedureN2-RTP-129,Spec.P281FUSARAffectedPages:System:Table5.2-8DrywellAtmosphereMonitoringSystemTitleofChange:ClarificationofLeakDetectionDetailsDescriptionofChange:setpoints:~~1.Footnotes1and2toTable5.2-8arerevisedandcombinedintoasinglefootnotetoclarifythattheleakdetectionsensitivitypresentedinthetableisaMinimumDetectableConcentrationbasedona10minuteMinimumDetectableLevel(MDL)forI-131(particulate)andXe-133(gaseous)radioactivity.ThefollowingFSARchangesaremadetoprovideclarificationoftheleakdetectionequipmentsensitivityandadditionalexplanationofthemethodfordeterminingleakdetection2.AsecondfootnoteisaddedtoTable5.2-8,clarifyingthemethodusedtodetectreactorcoolantpressureboundaryleakageusingairborneparticulateandgaseousradioactivityreadings.SafetyEvaluationSummary:ThechangestoFSARTable5.2-8maketheFSARdiscussionofRCPBleakagedetectionsensitivitiesandmethodsconsistentwiththeplantas-builtconditionandworkingprocedures,andwithTechnicalSpecificationInterpretation539,whichaddressesthelimitationsofparticulateandgaseousradioactivitymonitorstodetectRCPBleakage.

SafetyEvaluationSummaryReportPage99of112SafetyEvaluationNo.90-113(Continued)SafetyEvaluationSummary:(Continued)ThesechangesdonotreflectadeteriorationintheRCPBleakagedetectioncapabilitiesofNMP2',nordotheyaffectanysystemoreffluentreleasesinsuchawaythattheradiologicalconsequencesofpostulatedaccidentscouldbeincreased.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage100of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:90-114Calc.WH(C)-001Table2.4-15N/'ACorrectInconsistenciesBetweenSourceDocumentandtheUSARDescriptionofChange:USARTable2.4-15isrevisedtocorrectinconsistenciesbetweenthetableanditssourcedocument,calculationWH(C)-001andDispositionNo.OA.Thechangesincluderevisionstoassumedbuildingdepths,flowthroughdoors,andadditionofanewdoorforconsiderationinthefloodinganalysis.Severaleditorialcorrectionsarealsoincorporated.SafetyEvaluationSummary:ThesechangesrevisethefloodingcalculationandtheUSARtable(whichsummarizesthefloodinganalysisresults)toproperlyreflecttheplantas-builtcondition.Therevisedcalculationsdemonstratethattheconclusionsoftheprobablemaximumprecipitation(PMP)floodstudyarenotaffected;i.e.,theplantcanbesafelyshutdown.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage101of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:90-115Drawings945E400,945E493Figure9.5-41(Sheets1thru12)System:TitleofChange:High-PressureCoreSpraySystemDivisionIIIDieselGeneratorUSARFigure9.5-41UpdateDescriptionofChange:USARFigure9.5-41isupdatedtocorrecteditorialmistakesandaddmissinginformationtoagreewiththesourcedocumentsasfollows:~~~~1.Sheet8:"LowCoolingWaterExp.TankLevel"alarmisindicatedasinputtocommonalarm.2.Sheet10:MissingelementsareaddedandcorrectionsaremadetothelogicoftheD.C.circulatingoilpump.3.Sheet11:Fueloilsystemflowdiagram,legendtableandnotesarecorrectedforclarificationpurposesandtoreflect"as-built"condition.4.Sheet12:Thissheetisaddedformissingfueloilprimepumplogicandfueloilsystemalarms.5.6.Sheets6through11:Legendfor'!local"indicationisrevisedforconsistency.Sheets1through11:Thetotalnumberofsheetsis,correctedfrom11to12.

SafetyEvaluationSummaryReportPage102of112SafetyEvaluationNo.SafetyEvaluationSummary:90-115(Continued)ThischangeupdatesUSARFigure9.5-41toagreewiththesourcedocuments.ThedesignfunctionandmethodofperformanceoftheHPCSsystemanditscomponentsisnotaltered,andnofieldworkisrequired.Assuch,thischangehasnoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage103of112SafetyEvaluationNo.:ImplementationDocumentNo.:90-116AppendixRSafeShutdownAnalysisUSARAffectedPages:System:TitleofChange:9B~21g9B22I9B~23g9B~4-3,9B.6-1,9B.6-2,9B.6-3,9B.8-7,9B.9-1;Tables9B.8-1,9B.8-2;Figure9B.4-2VariousUpdateofAppendixRSafeShutdownAnalysis-Appendix9BofUSARDescriptionofChange:IThischangerevisesUSARAppendix9B,AppendixRSafeShutdownAnalysis,toincorporateresolutionstocommentsresultingfromtheindependentverificationreviewconductedbyNiagaraMohawk'sinternalNuclearComplianceandVerificationgroup.Thechangesincludethefollowing:2.CorrectionofinconsistenciesbetweenSection9B.4andTable9B.8-1regardingtheRCICsystem.Section9B.4correctlydesignatestheRCICsystemaspartofsafeshutdowntrains3and4,whereasTable9B.8-1erroneouslylistedtheRCICsystemaspartofsafeshutdowntrains1and3.InSection9B.2,thedefinitionsfortheterms"generalfirearea"and"divisionalfirearea"aredeleted,asthesetermsarenotusedinthesafeshutdownanalysis.Thedefinitionsoffireareaandfiresubareaareclarified.TheseUSARchangesdonotinvolveanyphysicalmodificationstotheplant.SafetyEvaluationSummary:TherearenodesignorhardwarechangesasaresultoftheserevisionstoUSARAppendix9B.Thesafeshutdownanalysis

SafetyEvaluationSummaryReportPage104of112SafetyEvaluationNo.90-116(Continued)SafetyEvaluationSummary:(Continued)continuestoshowthatatleastonetrainofsafeshutdownsystemsisavailabletosafelyshuttheplantdownincaseoffireinanyfirearea.Therefore,safeshutdowncapabilityexistsasrequiredbyAppendixRintheeventofafire.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage105of112SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:90-117Calc.12177-WM(B)-27,Rev.21.10-133,2.2-6;Tables2'3g2'5(Sh1)I2272.2-8System:TitleofChange:EnvironmentalProgramUpdateUSARTextandTablesDescriptionofChange:effectofacchabitability.ThischangeidentifiesrevisionstoUSARtextandtablestocorrectinconsistenciesbetweentheUSARandsourcedocumentation.TheUSARrevisionsrelatetocalculationsoftheidentalreleaseoftoxicchemicalsoncontrolroomSafetyEvaluationSummary:TheidentifiedUSARchangescorrectinconsistenciesbetweentheUSARandsourcedocumentation.Thesecorrectionsdonotinvolveanyactualplantchanges,donotaltertheplantdesignbasis,andinnowayalterthehabitabilityconditionsinthecontrolroom.Basedontheevaluationperformed,itisconcludedthattheseUSARchangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage106of112SafetyEvaluationNo.:ImplementationDocumentNo.:90-122FireHazardsAnalysisUSARAffectedPages:9.5-5,9.5-6,9.5-6a,9A.2-2,9A.2-3,9A.3-7,9A.3-7a,9A.3-12,9A.3-49,9A.3-56;Tables9A.3-1(Sh.3),9A.3-6(Sh.2,4)I9A~3-8(Sh.2)System:TitleofChange:FireProtectionFireProtection1990USARUpdateDescriptionofChange:ThAnischangedocumentsandevaluatesrevisionstotheFireHazardsalysis.ThefollowingsummarizestheUSARchangesmade:Sections9.5.1.2.8and9A.3-Clarifiedtoindicatethatcharcoalfilters2HVC-FLT1A,Band2HVR-FLT3arenotprotectedwithsprinklers.2.Section9.5.1.2.10-ThecommitmenttoNFPA12A(halonsystems)isclarifiedtoindicateuseofthe1980edition.3.Sections9.5.1.2.13and9A.3.6.1.2-ThetextisclarifiedtoindicatethatUnit2doesnotentirelycomplywithNFPA72Dand72E.ThesedeviationsarealreadyidentifiedinUSARTable9.5-3.4~Section9A.2-Thedefinitionsfortheterms"generalfirearea"and"divisionalfirearea"aredeleted,asthesetermsarenotusedintheFireHazardsAnalysis.Thedefinitionsoffireareaandfiresubareaareclarified.5.Section9A.3andTables9A.3-1,9A.3-6,and9A.3-8-,Theseareupdatedtoreflectchangesinfireloadingthathaveoccurred.6.Section9A.3-Updatedtoaccountforthedesignatedstoragearea(turbinebuildingtrackbay)forcombustibleliquidsandClassAcombustibles.

SafetyEvaluationSummaryReportPage107of112SafetyEvaluationNo.DescriptionofChange:90-122(Continued)(Continued)7.Section9A.3.7.4-Correctedtoproperlystatethatthewallsoftheplantcomputerroomarepartiallyrated.SafetyEvaluationSummary:TherevisionsdescribedhereinaprovidedinNRCStandardReviewPositionCMEB9.5-1fortheimplProtectionProgram,andprovidesafetytothatalreadyprovidedchangeshaveanyadverseimpactshutdownintheeventofafireperformed,itisconcludedthatunreviewedsafetyquestion.reconsistentwiththeguidancePlan9.5.1andBranchTechnicalementationandcontrolofaFireanequivalentorgreaterlevelofintheplant.Noneoftheontheplant'sabilitytosafelyBasedontheevaluationthesechangesdonotinvolvean

SafetyEvaluationSummaryReportPage108of112USARTEXTtTABLEANDFIGURECHANGES(BASEDONPREVIOUSLYREPORTEDSAFETYEVALUATIONS)AnumberoftextandfigurerevisionsweremadetotheUSARtoincludeadditionalchangesthatarebasedonpreviouslyreportedsafetyevaluations.Thesechangesareidentifiedbelow.SafetyEvaluationNo.:87-059,Revision2PreviouslyReported:10/25/89USARTable3B-5Sheets1,3,4,5,Table3B-6Sheets1,3,4,5,6andFigure3B-2Sheet3,havebeenrevisedtoincludeadditionalfootnotesregardingplantoperationwiththeremovalofsecondarycontainmenthatches.SafetyEvaluationNo.:87-155PreviouslyReported:10/25/89~~~USARFigure10.1-6chasbeenupdatedtodeleteinstruments2FWP-PDK5A/B/C,perECNFWP-604andSafetyEvaluation87-155.SafetyEvaluationNo.:88-032PreviouslyReported:10/26/88USARFigure10.4-11Sheets1,2,3and9havebeenfurtherupdatedtoincludechangesperECNFWS-612andEDC2E10099,asdescribedinSafetyEvaluation88-032.SafetyEvaluationNo.:88-061PreviouslyReported:06/11/90USARPage6.2-86ahasbeenupdated,perEDC2M00085,tobeconsistentwithchangesmadetoFigure6.2-73a(USARRevision0),asdescribedinSafetyEvaluation88-061.

0 SafetyEvaluationSummaryReportPage109of112SafetyEvaluationNo.:88-064Revision2PreviouslyReported:10/25/89USARFigure9.3-1bhasbeenrevisedtocorrectaneditorialerroronLDCNU-549,Revision3.SafetyEvaluationNo.:88-085PreviouslyReported:06/11/90USARFigure9.3-6Sheet1hasbeenupdatedtoreflecttherevisedsetpointfor2SSR-CSL106perEDC2E00078,asdescribedinSafetyEvaluation88-085.SafetyEvaluationNo.:88U-014PreviouslyReported:04/28/89USARFigure9.2-2Sheet19hasbeenupdatedtoreflectadditional~~~changesperECNSWP-649,asdescribedinSafetyEvaluation88U-014.SafetyEvaluationNo.:88U-019PreviouslyReported:04/28/89USARFigure9.5-40ahasbeenrevisedtoreflecttheas-builtconditionof*PI322A/Band*AOV323A/BperECNEGA-607,asdescribedinSafetyEvaluation88U-019.SafetyEvaluat'ionNo.:88U-029PreviouslyReported:04-28/89USARFigure10.4-10Sheet11hasbeenrevisedtocorrectadraftingerror.Page10.4-32hasbeenupdatedtoincludetheadditionofalarmstothecondensatepumpsandcondensateboosterpumpsasdescribedinSafetyEvaluation88U-029.

0 SafetyEvaluationSummaryReportPage110of112SafetyEvaluationNo.:88U-068PreviouslyReported:04/28/89USARFigures12.3-5,12.3-8,12.3-38,1.2-19Sheet2and12.3-47havebeenupdatedtoreflect'heas-builtconfiguration.ThesechangesinvolveequipmentlocationsandradiationzonesdescribedinSafetyEvaluation88U-068.SafetyEvaluationNo.:88U-069PreviouslyReported:04/28/89USARFigures1.2-19Sheet1,12.3-13,12.3-46,1.2-19Sheet2,12.3-14and12.3-47havebeenupdatedtoreflecttheas-builtconfigurationperEDC2M10129and2M10161,asdescribedinSafetyEvaluation88U-069.SafetyEvaluationNo.:88U-071~~~~~~~~~~~PreviouslyReported:04/28/89USARFigures1.2-26,1.2-27,1.2-28,12.3-22,12.3-23,12.3-55,12.3-56,and10.4-7dhavebeenupdatedtoreflecttheas-builtconfigurationperEDC2M10151,asdescribedinSafetyEvaluation88U-071.SafetyEvaluationNo.:88U-072PreviouslyReported:04/28/89USARFigures12.3-24,12.3-27,12.3-57,12.3-58,and12.3-60havebeenupdatedtoreflecttheas-builtconfigurationperEDC2M10151,asdescribedinSafetyEvaluation88U-072.

SafetyEvaluationSummaryReportPage111of112SafetyEvaluationNo.:88U-120PreviouslyReported:04/28/89USARFigures6A.2-13and6A.2-25havebeenupdatedtoincludepreviouslyapprovedchanges,identifiedinLDCNU-447,thatwereinadvertentlyomittedfromtheupdate.ThisomissionwasidentifiedduringtheverificationofLDCNU-447.SafetyEvaluationNo.:88U-129PreviouslyReported:04/28/89USARFigure9.4-4(Sheet9)hasbeenupdatedperEDC2E10125,asdescribedinSafetyEvaluation88U-129.SafetyEvaluationNo.:88U-238PreviouslyReported:04/28/89USARFigure9.3-11ehasbeenupdatedperEDC2M10043A,as~~~describedinSafetyEvaluation88U-238.SafetyEvaluationNo.:88U-255PreviouslyReported:04/28/89USARTable1.8-1Sheets65,66,and67havebeenrevisedtodeleteinformationwhichwaspreviouslyrelocatedtoUSARSection14.2,perLDCNU-1145,asdescribedinSafetyEvaluation88U-255.SafetyEvaluationNo.:88U-262PreviouslyReported:04/28/89USARPage1.12-32hasbeenrevisedtocorrectaneditorialerrorregardingthedateofaNRCletter.

SafetyEvaluationSummaryReportPage112of112SafetyEvaluationNo.:88U-276PreviouslyReported:04/28/89USARTable7.1-3Sheet4hasbeenrevisedtoreflectRevision3ofRegulatoryGuide1.97tobeconsistentwithLDCNU-361Revision1,andSafetyEvaluation88U-276.SafetyEvaluationNo.:88U-282PreviouslyReported:04/28/89USARFigure6.2-70Sheet21hasbeenupdatedtobeconsistentwithPaIDs13A-10,13D-9andSafetyEvaluation88U-282.USARFigure6.2-70Sheet30hasbeenupdatedtobeconsistentwithPGIDs19D-10,19F-7andSafetyEvaluation88U-282.SafetyEvaluationNo.:89-056PreviouslyReported:10/25/89~~~~~~~~USARTables9A.3-2Sheet2,9A.3-9Sheet2,9A.3-1Sheet2,and9A.3-6Sheet5havebeenrevisedtoreflectcalculationFPW-28Revision8,asdescribedinSafetyEvaluation89-056.ThesechangesresolveverificationcommentsregardingLDCNsU-883,U-1117andU-1200,whichwereincorporatedintoUSARRevision1.ENDOFSAFETYEVALUATIONSUMMARYREPORT

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NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESAPPENDIXRREVIEWSAFESHUTDOWNANALYSISAPPENDIX98PageT=Table~F=Fiure98-i98-ia98-ib98-ii98-iii98-iv98.1-198.2-198'-298.2-398.3-198'-198.4-298.4-398.4-498.4-598.4-698.4-798.4-8F98.4-1F98.4-298.5"198.5-298.5-398.5-498'-5T98.5-198.6-198.6-298.6-398.6-4T98.6-1Sh1Sh2Sh3Sh4Sh5Sh6T98.6-2AmendmentNumber242423RO24423RO442342244224442222RO442123RO221125112828RORORORO11Page"T=Table~F=FiureT98'-3Sh1Sh2Sh3Sh4Sh5sh6Sh7Sh7aS}18Sh9F98.6-1F98'-2F98.6-3F98.6-4F98.6-5F98'-698.7-198.8-198.8-298.8-398.8-498.8-598.8-5a98.8-5b98.8-698.8-7T98'-1Sh1ShlaSh2S}13sh4Sh5Sh5aSh6S}17Sh8Sh9Sh10Sh11Sh12Sh13AmendmentNumber23llRO11RO1123RO28114llllllllll23RO23Rl23RlRlRO25RORO2811RO28282811282828RO11RO11PageT=Table~F=FiureSh14Sh15Sh16Sh17Sh18Sh19Sh20Sh21Sh22Sh23Sh24Sh25Sh26Sh27Sh28Sh29Sh30Sh30aSh31Sh32Sh33Sh34S}135Sh36Sh37Sh38Sh39Sh40Sh41Sh42Sh43Sh44Sh45Sh46Sh47Sh48Sh49Sh50Sh51Sh52Sh53Sh54Sh55Sh56Sh57AmendmentNumberllRO1111RO11282828282828ROROROROROROllRORO2828232323232323232323232323232323llRORO23RO1919USARRevisionSSA-1October.1989

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NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolume5.3ReactorVessel5.4ComponentandSubsystemDesignAppendixes5A,5B131313CHAPTER6ENGINEEREDSAFETYFEATURES136.16.26,36.46.56.6Appendixes6Athrough6CEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER7INSTRUMENTATIONANDCONTROLSYSTEMS157.17.27'7.47.57.67~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControls.EngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16161616i1717179.19.29.39'9.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17181920,2121,2223USARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSIONSYSTEM2310.110.210.310.4Summary,DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem23'232411.111.211.311.411.5SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendix11ACHAPTER12RADIATIONPROTECTIONCHAPTER11RADIOACTIVEWASTEMANAGEMENT2424252525252512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B262626,26262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARCHAPTER1LISTOFFIGURESFigureNumber1.1-11.2-11.2-21.2-31.2-41.2-5TitleHEATBALANCEATRATEDPOWERPLOTPLANSTATIONARRANGEMENTDELETEDDELETEDDELETED261.2-6Sjl.1l.2-6S}1.21.2-71.2-7SI1.21.2-8S11.11.2-8Sjl.2GENERALARRANGEMENT,REACTORBUILDINGPLANEK175'-0"AND188.'-6"GENERALARRANGEMENT,REACTORBUILDINGPLANEK196'-0"GENERALARRANGEMENT,REACTORBUILDINGPLANEL215'-0~~GENERALARRANGEMENT,REACTORBUILDINGPLANEK240'-0"GENERALARRANGEMENT,REACTORBUILDINGPLAN-EL261'-0"ANDMISCELLANEOUSGENERALARRANGEMENT,REACTORBUILDINGPLANEL215'-0"ANDMISCELLANEOUS1.2-9S11.1GENERALARRANGEMENT,REACTORBUIKDINGPLANEL289'-0"1.2-9Sh.21.2-10Sh.1GENERALARRANGEMENT,REACTORBUILDINGPLANEL306'-0"GENERALARRANGEMENT,REACTORBUILDINGPLANEL328'-10"1.2-10Sh.2GENERALARRANGEMENT,REACTORBUILDINGPEANEL353'-10"Amendment261-viiMay1986 NineMilePointUnit2FSARCHAPTER1LISTOFFIGURES(Cont)FigureNumberTitle1.2-111.2-121.2-131.2-141.2-151.2-161.2-171.2-18GENERALARRANGEMENT,REACTORBUILDINGSECTIONS(SHEETS1THROUGH4)GENERALARRANGEMENT,REACTORBUILDINGSECTION2-21GENERALARRANGEMENT,RADWASTEBUILDINGPLANEL261'0",270'9I'ND309'0"(SHEETS1THROUGH3)GENERALARRANGEMENT,RADWASTEBUILDINGSECTIONSGENERALARRANGEMENT,CONTROLROOMPLANEL360'-0"I288'-6"I261'-0"(SHEETS1THROUGH3)GENERALARRANGEMENT,CONTROLBUILDINGGENERALARRANGEMENT,EMERNGECYDIESEIGENERATORBUILDINGPLAN(SHEETS1THROUGH6)GENERALARRANGEMENT,EMERGENCYDIESELGENERATORBUILDINGSECTIONS1.2-191.2-201.2-22'"I1.2-231.2-24GENERALARRANGEMENT,TURBINEBUILDINGPLANEL250'-0"(SHEETS1AND2)GENERALARRANGEMENT,TURBINEBUILDINGPLANEL277'-6"(SHEETS1AND2)GENERALARRANGEMENT,TURBINEBUILDINGPLANEL306'-6"(SHEETS1AND2)GENERALARRANGEMENT,TURBINEBUILDINGSECTION1-1(SHEETS1AND2)GENERALARRANGEMENT,TURBINEBUILDINGPLANSECTION2-2AND4-4.(SHEETS1AND2)GENERALARRANGEMENT,TURBINEBUiLDINGPLANSECTION3-3Amendment241ViiiFebruary1986 .NineMilePointUnit2FSARCHAPTER1LISTOFFIGURES(Cont)FigureNumberTitle1.2-25GENERALARRANGEMENT,TURBINEBUILDINGPLANSECTION5-51.2-261.2-271.2-281.2-291.2-301~2-311.2-321~2331.2-341.2-351.2>>361~2371.2-38GENERALARRANGEMENT,SCREENWELLBUILDINGWATERTREATMENTANDSERVICEWATERPUMPSPLAN(SHEETS1AND2)GENERALARRANGEMENT,SCREENWELLBUILDINGWATERTREATMENTANDSERVICEWATERPUMPSPLANSECTION(SHEETS1AND2)GENERALARRANGEMENT,SCREENWELLBUILDINGWATERTREATMENTAND,SERVICEWATERPUMPSPLANSECTIONGENERALARRANGEMENTANDDETAILS,INTAKEANDDISCHARGETUNNELS(SHEETS1THROUGH3)GENERALARRANGEMENTANDDETAILS,INTAKESTRUCTUREGENERALARRANGEMENTANDDETAILS,MAINSTACKGENERALARRANGEMENT,NORMALSWITCHGEARBUILDINGPLANS(SHEETS1THROUGH3)GENERALARRANGEMENT,NORMALSWITCHGEARBUILDINGGENERALARRANGEMENT,AUXILIARYBOILERHOUSEGENERALARRANGEMENT,STANDBYGASTREATMENTBUILDINGEL261'-0"GENERALARRANGEMENT,STANDBYGASTREATMENTBUILDINGANDRAILROADACCESSIOCKSECTIONGENERALARRANGEMENT,CONDENSATESTORAGETANKBUILDING(SHEETS1AND2)COOLINGTOWERFILLLEVELPLANANDSECTIONAmendment241-ixFebruary1986 NineMilePointUnit.2FSARCHAPTER1LISTOFFIGURES(Cont)FigureNumber1.2-391.2-401.7-11.7-21.7-31.7-41.8-1~TitleCOOLINGTOWERSECTIONBELOWTHEFILLLEVELGENERALARRANGEMENTiHYDROGENSTORAGEAREAPIPINGANDINSTRUMENTATIONDIAGRAM(SWEC)(SHEETS1THROUGH5)PIPINGANDINSTRUMENTSYMBOLS(GE)LOGICDIAGRAMSSYMBOLS(SWEC)(SHEETS1AND2)ELECTRICAL'NE-LINEDIAGRAMSSYMBOLS(SWEC)ENGINEEREDSAFETY-FEATUREFILTERDRAINARRANGEMENT1.10-11.10-21.10,-31.10-4DELETEDDELETEDDELETEDDELETEDUSARRevision01-xApril1989 NineMilePointUnit2FSARTABLE1.8-1(Cont)ReulatorGuide1.23Revision0Februar1972OnsiteMeteorologicalProgramFSARSection2.3.3PositionNiagaraMohawkPowerCorporationcomplieswithRegulatoryGuide1.23(SafetyGuide23)(February,1972).However,thewindspeedsensorinuseatthe200-ftleveluntilJuly1982didnotmeettherequirementsoftheguide.ThenewsensorinstalledafterJuly1982hasthestartingspeedandac-curacyspecifiedbytheRegulatoryGuide.ThesevereweatherconditionsencounteredatNineMilePointleadtothechoiceoftheveryruggedwindspeedsensorin-stalledinNovember1972.Ithadastartingspeedofabout2.6mphandwouldcontinuetooperatewithspeedsof1to1.5mph.Thewindspeedaccuracyis+1.0mphabove10mphasopposedto,theRegulatoryGuide1.23CriterionI0.5mphforall)windspeeds.Moresensitivewindspeedsensorsavailableatthattimewerepronetoicingandphysicaldamagefromhighwindspeeds.24of169

NineNilePointUnit2FSARTABLE1.8-1(Cont)RelatorGuide1.58Revision1Setember1980Cont3.5.2LevelIIOneyearofsatisfactoryperformanceasLevelIor5yearsrelatedexperienceinthecorrespondinginspection,examination,ortestcategoryorclass,or2.Highschoolgraduation/GEDequivalentplus3yearsofrelatedexperienceinequivalentinspection,examination,ortestingactivities,or3.Completionofcollege-levelworkleadingtoanas-sociatedegreeinarelateddisciplineplus1yearrelatedexperienceinequivalentinspection,examination,ortestingactivities,or4.-Four-yearcollegegraduateplus6monthsofrelatedexperienceinequivalentinspection,examination,ortestingactivities.3.5.3LevelIIISixyearsofsatisfactoryperformanceasaLevelIIor15yearsofrelatedexperienceinthecor-respondinginspection,examination,ortestcategoryorclass,or2.Highschoolgraduate/GEDequivalentplus10yearsofrelatedexperienceinequivalentinspection,examination,ortestingactivities;orhighschoolgraduationplus8yearsexperienceinequivalentinspection,examination,ortestingactivities,withatleast2yearsasLevelII,andwithat'least2yearsassociatedwithnuclearfacilitiesorifnot,atleastsufficienttrainingtobeac-quaintedwiththerelevantqualityassuranceaspectsofanuclearfacility,or3.Completionofcollegelevelworkleadingtoanas-sociatedegreeand7yearsofrelatedexperienceinequivalentinspection,examination,ortestingactivities,withatleast2yearsofthisex-perienceassociatedwithnuclearfacilities,orifnot,atleastsufficienttrainingtobeacquainted65of169 0-NineMilePointUnit2FSARTABLE1.8-1(Cont)ReulatorGuide1.58Revision1Setember1980Contwiththerelevantqualityassuranceaspectsofanuclearfacility,orFour-yearcollegegraduateplus5yearsofrelatedexperienceinequivalentinspection,examination,ortestingactivities,withatleast2yearsofthisexperienceassociatedwithnuclearfacilities-orifnot,atleastsufficient,trainingtobeacquaintedwiththerelevantqualityassuranceaspectsofanuclearfacility.5.Graduatedegreeplus3yearsofrelatedexperienceinequivalentinspection,examination,ortestingactivities,withatleast2yearsofexperienceas-sociatedwithnuclearfacilitiesor,ifnot,atleastsufficienttrainingtobeacquaintedwiththerelevantqualityassuranceaspectsofanuclearfacility.NMPCTheNMPCqualityassuranceprogramforUnit2iscurrentlyincompliancewithRegulatoryPositionsC.5,6,7,8,and10ofRegulatoryGuide1.58,Revision1.NSSSGeneralElectricstartupoperationspersonnelqualificationsmeettherequirementsofthisguideasdescribedbelow:1.PersonnelareselectedandtrainedaccordingtothecriteriaofANSIN18.1-1971(NRC.RegulatoryGuide1.8),withtheexceptionofNRCLicensing.2.TheOperationsManagermeetstheequivalentofANSIN18.1,Paragraph4.2.2,OperationsManager.TheOperationsManagerisnormallypresentforpreoperationaltesting,andwillthereforebequalifiedatthetimethatpreoperationaltestingisbegun.3.TheOperationsSuperintendentmeetstheequivalentofANSIN18.1,Paragraph4.3.1,SupervisorsRequiringNRCLicenses.TheOperatingSuperinten-66of169

NineMilePointUnit2FSARTABLE1.8-1(Cont)RelatorGuide1.58Revision1Setember1980Contdentwillnormallybepresentforpreoperationaltestingandthereforewillbequalifiedatthetimepreoperationaltestingisbegun.TheShiftSuperintendentsmeetthequalificationofANSIN18.1,Paragraph4'.1,SupervisorsRequiringNRCLicenses.5.TheLeadStartupTestDesignandAnalysisEngineermeetsthequalificationsofANSI.N18.1,Paragraph4.4.1,ReactorEngineeringandPhysics.Hewillbequalifiedatthetimeofinitialcoreloadingorappointment,totheposition.Hisonsiteresponsibilitiesbeginjustpriortofuelloading.6.TheStartupTestDesignandAnalysisEngineersmeetthequalificationsofANSIN18.1,Paragraph3.3,ReactorTechnicalsupportpersonnel.Theironsiteresponsibilitiesbeginjustpriortofuelloading.7.TheStartupControlandInstrumentationEngineermeetsthequalificationsofANSIN18.1,Paragraph4.4.2,InstrumentationandControl.Hewillbequalifiedatthetimepreoperationaltest-ingisbegun.8.TheStartupChemistmeetsthequalificationsofANSIN18.1,Paragraph4.4.3,.Radiochemistry,utilizingcumulativeexperiencefromseveralreac-torstartupprograms.Hewillbequalifiedatthetimeoftheinitialcoreloading.67of169

NineMilePointUnit2FSARTABLE1.8-1(Cont)RelatorGuide1.108Revision1Auust1977PeriodicTestingofDieselGeneratorUnitsUsedasOnsiteElectricPowerSystemsat,NuclearPowerPlantsFSARSections8.3.1.2,14.2PositionTheUnit2projectcomplieswith'theRegulatoxyPosition(ParagraphC)ofthisguide.TheIEEE387-1977(Section3.7)definitionsofContinuousRatingandShort-TimeRatingareappliedtothedieselgeneratorcontinuousratingand2-hourratingreferredtoinSectionC.2.a.3oftheRegulatoryGuide.Section3/4.8oftheTechnicalSpecificationsdetailstheperiodictestingrequirementsofthedieselgeneratorunits.26Amendment26122of169May1986

NineMilePointUnit2CESARTABLE1.8-1(Cont)RelatorGuide1.134Revision1March1979MedicalEvaluationofNuclearPowerPlantPersonnelRequiringOperatingLicensesFSARSectionChapter13PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.Themedicalrequirementsforpersonnelrequiringoperatorlicenses,asdetailedinANSIN546-1976andendorsedbythisguidewillbeimplementedbySiteAdministrativeProcedures.149of169

NineMilePointUnit,2FSARThestaffrealizesthatthenecessaryknowledgeandexperiencecanbegainedinavarietyofways.Consequently,creditforequivalentexperienceshouldbegiventoapplicantsforSROlicenses.ApplicantsforSROlicensesatafacilitymayobtaintheir1yroperatingexperienceinalicensedcapacity(OperatororSeniorOperator)atanothernuclearpowerplant.Inaddition,actualoperatingexperienceinapositionthatisequivalenttoaLicensedOperatororSeniorOperatoratmilitarypropulsionreactorswillbeacceptableonaone-for-onebasis.Individualapplicantsmustdocumentthisexperienceintheirindividualapplicationsinsufficientdetailsothatthestaffcanmakeafindingregardingequivalency.ApplicantsforSROlicenseswhopossessadegreeinengineeringorapplicablesciencesaredeemedtomeettheaboverequirement,providedtheymeettherequirementssetforthinSectionsA.l.aandA.2inenclosure1intheletterfromH.R.Dentonandallpowerreactorapplicantsandlicensees,datedMarch28,1980,andhaveparticipatedinatrainingprogramequivalenttothatofacoldSeniorOperatorApplicant.TheNRChasnotimposedthe1-yrcoldapplicantsforSROlicenses.workonafacilitynotyetinprogramsaredesignedtosupplyexperiencenotavailabletothem.experiencerequirementonColdapplicantsaretooperation;theirtrainingtheequivalentoftheNineMilePointUnit2PositionTheUpgradingofOperatorTrainingandSeniorOperatorTrainingforUnit2isbeingperformedasdescribed-inSection13.2oftheFSAR.ThisisalsoinaccordancewiththeSiteAdministrativeProcedures.1.10-15 NineMilePointUnit2FSARI.A.2.3ADMINISTRATIONOFTRAININGPROGRAMSFSARCrossReferenceSection13.2.1NUREG-0737PositionPendingaccreditationoftraininginstitutions,licenseesandapplicantsforoperatinglicenseswillassurethattrainingcenterandfacilityinstructorswhoteach-systems,integratedresponses,transient,andsimulatorcoursesdemonstrateSROqualificationsandareenrolledinappropriaterequalificationprograms.Theabovepositionisashort-termposition.Inthefuture,accreditationoftraininginstitutionswillincludereviewof,theprocedureforcertificationofinstructors.ThecertificationofinstructorsmayormaynotincludesuccessfulcompletionofaSeniorOperatorexamination.ThepurposeoftheexaminationistoprovidetheNRCwithreasonableassuranceduringtheinterimperiodthatinstructorsaretechnicallycompetent.Therequirementisdirectedtopermanentmembersofthetrainingstaffwhoteachthe.subjectsenumeratedabove,includingmembersofotherorganizationswhoroutinelyconducttrainingatthefacility.Thereisnointentiontorequireguestlecturerswhoareexpertsinparticularsubjects(reactortheory,instrumentation,thermodynamics,healthphysics,chemistry,etc)tosuccessfullycompleteaSeniorOperatorexamination.Nordoweintendtorequireasystemexpert,suchastheSupervisor-InstrumentandControlMaintenanceteachingtherodcontrol"drivesystemtositforaSeniorOperatorexamin-ation.Theuseofguestlecturersshouldbelimited.NineMilePointUnit2PositionTrainingcenterandfacilityinstructorswhoteachsystems,integratedresponses,transient,andsimulatorcoursespresentlyholdSROlicensesonUnit1and,assuch,areenrolledinoperatorrequalificationprograms,asoutlinedinsiteadministrativeprocedures.Thequalificationofthetraininginstructorsmeetstherequirementsofthistask,asdescribedinSection13.2oftheFSAR.USARRevision01.10-16April1989 NineMilePointUnit2'FSARII.K.3.22RCICSUCTIONSOURCEFSARCrossReferenceSections5.4.6,7.4NUREG-0737PositionThereactorcoreisolationcooling(RCIC)systemtakessuc-tionfromthecondensatestoragetankwithmanualswitchovertothesuppressionpoolwhenthecondensatestoragetanklevelislow.Thisswitchovershouldbemadeautomatically.Untiltheautomaticswitchoverisimplemented,licenseesshouldverifythatclearandcogentproceduresexistforthemanualswitchoveroftheRCICsystemsuctionfromthecon-densatestoragetanktothesuppressionpool.NineMilePointUnit2PositionTheUnit2projecthasimplementedtheNRCpositiontoautomaticallytransferRCICsuctionsource.CondensatestoragetanklowwaterinventoryautomaticallyinitiatestransferofthesuctionoftheRCICpumptothesuppressionpool.ThemodificationoftheRCICsystemallowsautomaticswitchoverofpumpsuctionfromthecondensatestoragetanktothesuppressionpoolifthecondensatestoragetankfallstoapresetlowlevel.Lowlevelinthetankismonitoredbytworedundantleveltransmitters.Ifeithertransmittersenseslowlevel,pumpsuctionisautomaticallytransferredtothesuppressionpool.Thesearedifferenttransmitters/tripunitsfromthosethatactivateswitchoverfortheHPCSsystem.Thecondensatestoragetanksuctionvalvewillbesignaledtocloseuponopeningofthesuppressionpoolsuctionvalve.TheP&ID,Figure5.4-9,andelementarydiagramhavebeenrevisedtoreflectarelocationofthetransmittertothepumpsuctionline.USARRevision01.10-93April1989 NineMilePointUnit2FSARII.K.3.24RCICANDHPCISUPPORTPOWER'SARCrossReferenceSection9.4NUREG-0737PositionLong-termoperationofthereactorcoreisolationcooling(RCIC)andhighpressurecoolantinjection(HPCI)systemsmayrequirespacecoolingtomaintainthepumproomtem-peratureswithinallowablelimits.Licenseesshouldverifytheacceptabilityoftheconsequencesofacompletelossofacpower.TheRCICandHPCIsystemsshouldbedesignedtowithstandacompletelossofoffsiteacpowertotheirsup-port,systems,includingcoolers,foratleast2hr.NineMilePointUnit2PositionTheUnit2ECCSdesignemploysacubiclearrangementtoen-surephysical,electrical,andenvironmentalseparationofeachportionoftheECCS.TheRCICsystemisalsolocatedwithinaseparatecubicle.TheHPCS,pumproomiscooledbyeitheroftwofullyredundantCategoryIunitspacecoolers.TheremainingECCSpumproomsandtheRCICpumproomareeachcooledbyoneCategoryIunitspacecoolerwithanad-ditionalcoolerprovidedasaspare.Thesecoolersarepartofthereactorbuildingheating,ventilation,andaircon-ditioning(HVAC)systemwhichutilizecoolingwaterfromtheservicewater(SWP)system.Thesafety-relatedportionsoftheSWPsystemarepoweredfromthestandbydieselgenerators.followingalossofoffsitepower;thereforeareliablesupplyofcoolingwaterisprovided.,Likewise,thecontrolsystemsinvolvedintheoperationoftheunitcoolersalsoreceivetheirpowerfromthedieselgeneratorsfollowingalossofoffsitepower.Thisdesignassuresthat.thepumproomtemperaturesaremaintainedwithinnormallimitsforanindefiniteperiodfollowingacompletelossofoffsitepower.1.10-94 NineMilePointUnit2FSAR'ABLEIII.D.3.4-1RESULTSOFTOXICCHEMICALANALYSISFORTHECONTROLROOMHABITABILITYSTUDYChemicalLocationJ.A.FitzPatrickPlantAlcanRoute104NineMilePointUnit1NineMil'ePointUnit2OswegoWireIncorporatedUSARRevision0ChemicalN~HqSOCO~PropaneHalonCl~PropaneNqHclCO~HclN~CO~NqCOqHqSOHclHalonHqSOCO~Halon1301N~IsopropylAlcoholNqPropaneH~SOMaximumControlRoomConcentration(m'1.26.6x106.21.291.730.0381.10.090.0032.5x100.0090.540.022.214.71.3x0.0090.576.6x10446.83.8832.12.2x1041.2x102.1x101.0x101.10-133ToxicLimit(m'74-0.00254.843.10.04543.12740.0554.80.05027454.827454.80.0020.054320.00254.84322741.227443.10.002AllowableTimePeriod(min1521515215151521515215152151521515151515152April1989 h NineMilePointUnit2FSARInadditiontotheloadcombinationrequirementforthecon-tainmentdesign,thereisa.fatigueanalysisrequirementforthelinerofaconcretecontainment.Forsteelcontainment,theconsiderationoffatigueisspecifiedinASMEBoilerandPressureVesselCodeSectionIII,Division1,SubsectionNE.However,thelinerontheconcretefoundationmat.ofthesteelcontainmentshouldbetreatedasthelinerofacon-cretecontainment.Sincethestaff'spositionrequiresthepoollinertobedesignedinaccordancewiththeASMEBEcPVCodeSectionIII,Division1,SubsectionNE,itissuggestedthatagenericmethodtoconsiderfatigueofboththesteelcontainmentandthesteellinerintheconcretecontainmentshouldbeadopted.PositionTheabsolutesummethodofcombiningdynamicloadsisusedforthedesignofstructures.Thedetailsofloadcom-binationsusedindesigningthestructuresarecoveredinFSARSection3.8.TheUnit2primarycontainmentlinerisevaluatedforfatiguetotherequirementsofASMEBoilerandPressureVes-selCodeSectionIII,Division1,SubsectionNE.LICENSINGISSUE:43-FLUID/STRUCTUREINTERACTIONIssueThedynamicforcingfunctionsforvariousloadshavebeenestablishedthroughtestingonmodelsthataregenerallymorestiffthantheactualstructurestowhichtheloadswillbeapplied.Bydirectlyapplyingsuchforcingfunc-tionstoactualstructuresintheanalysis,theinteractiveeffectbetweenthefluidmassandthestructureisneglected.Undercertainconditions,thiseffectmaybesignificant.Itisproposedthatagenericapproachtostudysucheffectsshouldbeestablished.PositionThisissueisnotdirectlyapplicabletotheUnit2MarkIIcontainment.SincetheUnit2containmentisstiffinthesuppressionpool,regionandthedynamicforcingfunctionsareconservativelydefined,anyinteractiveeffectbetweenthefluidmassandthestructureisinherentlyincluded.Amendment31.12-31June1983 NineMilePointUnit2FSARLICENSINGISSUE44-LONG-TERMPOST-LOCAOPERABILITYOFDEEP-DRAFTECCSPUMPSIssueIEBulletin79-15,datedJuly1979,identifiedproblemswithdeep-draftECCSpumpsthatcouldthreatentheirlong-termpost-LOCAoperability.Structureflexibility;shaft/columnmisalignment;vibrationalfrequenciesnearrotationspeeds;inletflowinducedvortices;anddimensionaldeficienciessuch*asthosediscoveredwithcertainLaSalleECCSpumps,couldcauseexcessivevibrationandbearingwear.TheNRCstaffhasaskedapplicantstodefineprogramsandprovidedatathatcomparetheexpectedservicelifewiththeac-cumulatedoperatingtimeandconfirmthelong-termoperability.PositionTherearefivesafety-relateddeepdraftpumpsutilizedintheUnit2design.Thesearethreeresidualheatremovalpumps,onelowpressurecorespraypump,andonehighpres-surecorespraypump.TheinherentdesignfeaturesoftheByronJacksonECCSpumpsinUnit2precludeexcessivevibrationandbearingwear.Eachpumpissuppliedwithacasingorsuctionbarrelandisnotinstalledinawetsump.Theydonothavelong,limbercolumns;thelongestpumpisonly24ft,comparedtothe30-to160-ftpumpsdescribedinIEBulletin79-15.Alsothepumpassemblyrigidityisenhancedbyseismicringsbetweentheassemblyandthebarrel.Thepumpsuseadouble-suctionfirststagetoprovidestabilityoverawiderangeofflows.Columnfrequenciesarewellremovedfrompumpspeed.Largerdiameterbarrelsprovidelowflowvelocitiesaroundpumpinlets,andringseismicrestraints'ctasflowstraightenerstosuppressvortexformation.Thepumpshavehigh-precision,keyed,sleeve-typecouplings.AnNRCletterdatedDecember8,1983,requestedadditionalinformationonmethodsusedtoqualifylong-termoperabilityofdeepdraftpumps.Thefollowingisadescriptionofthemethodused.Long-termoperabilityhasbeenconsideredintheemergencycorecoolingsystem(ECCS)pump-design.TheECCSpumps'ffectivenessisevaluatedbyacceptance,qualification,andin-planttesting.Long-termoperabilityisassuredbypreventivemaintenance,functionaltestingandsurveil-lance,"andvibrationmonitoring.Scheduledpreventivemaintenanceconsistsofresistancereadingsofmotorwindings;lubricationofcriticalrotatingcomponents;generalcleaningandinspectionofrotatingelectricalequipment;andinspection,overhaul,alignment,andadjust-USARRevision01.12-32April1989 Ni.'neMilePo'intUnit2FSARmentofimpellerlift.Functional-testingmeasurementsofeachpump'sinletpressure,differentialpressure,flowrate,andvibrationasprescribedbySectionXIoftheASMEB&PVCodeandapplicableaddenda,asrequiredby10CFR50.55a,providedataforengineeringanalysistoidentifyper-formance.changesortrends.Inaddition,vibrati'ondatabases,establishedduringthe,preoperational/startuptesting,arecomparedwithfunctional-testingvibrationdatatomonitorjournalbearingwearandshaftwhip.Functionaltestingandsurveillancerequirementsarespeci-fiedinUnit2TechnicalSpecifications,surveillanceprocedures,andinserviceinspection(ISI)programs.Preventivemaintenanceandsurveillancetestingaresche-duledatperiodicintervalsastheISIprogramtestresultsindicate.AspartoftheUnit2plantISIprograms,vibrationmeasurementswillbetakeninaccordancewithSectionXIoftheASMEBoilerandPressureVesselCodeandapplicableAddendaasrequiredby10CFR50.55a.Thedatawillbeevaluatedonascheduledbasistopredictpotentialbearingandjournalfailuresandestablishreplacementschedules.Datawillbeavailableonsiteforinspection.Vibrationshouldbelimitedto0.3in/secvelocitypeak-to-peakoverallmeasuredfrequencies,asmeasuredbyanIRD360orequivalentequipment,whenthemotorandpumpareoperatedasaunitoverthenormaldesignrangeofpressureandflow.Thislimitisbasedonnormaloperation.Highermomentaryincreasesmaybeacceptableduringstartingoratshutoff.Thislimitisnotbasedonwhattheequipmentcanwithstand.Theequipmentdamagethresholdishigher:closeto0.020inch,momentaryandnotsustained.Anysustainedvibrationover0.3in/secmaycauseextensivebearingwear.Thesedeepdraftpumps,duetotheirrelativeshortness,demonstratefeweroftheproblemsassociatedwithlongerpumps.Thehydraulicdesignhasbeendevelopedoverthelast40yearsofexperienceinmanyapplications.TheECCSpumpscontaindesignfeaturestoprecludefailureoftheimpellers,impellerstaking,shafts,bearings,wearrings,couplings,andstuffingboxes.Thedesignincludes,safetyfactors(loadingcriteria)basedontheexpectedpressures,temperatures,andloadingsdefinedinthedesignspeci'fication.Lateralrestraintsareincludedinthepumptocontroldeflections.Tolerancesassuringalignmentoftheshaftandpumpingelementsareverifiedbydesigncalculations.Motorshaftdeflectionswithintolerancearepredictedinastaticseismicanalysisandareverifiedbyaqualificationtestofasimilarmotor.AdynamicanalysisofthepumpandmotorisperformedtodetermineUSAR-Revision01.12-32aApril1989 NineMilePointUnit"2FSAR.resonancesandpredictloadingsthroughoutthepumpandmotor.Testsareperformedoneachpumpdelivered.Thetestsincludeheadversusflow,NPSH,andvibrationmonitoring.Theassembledpumpsarecheckedforproperassemblyandlowfrictionbyhandturning(rotating)theshaft.Eachpumpisrunforatotalof100hrduringtesting.Aqualifica-tiontestofasimilarpumpmotorwasperformed.ThisdataprovidesqualificationoftheUnit2pumpsmotorsbyasimilarityanalysis.USARRevision01.12-32bApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolume5.3ReactorVessel5.4ComponentandSubsystemDesignAppendixes5A,5B131313CHAPTER6ENGINEEREDSAFETYFEATURES136.16.26.36.46.56.6Appendixes6Athrough6CEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER7INSTRUMENTATIONANDCONTROLSYSTEMS157.17'7'7.47.57.67~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafety'ontrolSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8AELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystem1616.16'16,17ICHAPTER9AUXILIARYSYSTEMS179.19.29.39.49.5AppendixesFuelStorageandHandlingWater'SystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17,181920,2121,2223USARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont:)SectionCHAPTER1010.110.210.310.4CHAPTER11TitleSTEAMANDPOWERCONVERSIONSYSTEMSummary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume2323232411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525-CHAPTER12RADIATIONPROTECTION2512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)iv26 NineMilePointUnit2FSARCHAPTER2LISTOFTABLES'ableNumberTitle2~11MINIMUMDISTANCEBYSECTORBETWEENRESTRICTEDAREABOUNDARYANDROUTINERELEASEPOINTS2.1-22~132.1-42.1-52.1-62~172.1-82.1-92.1-102.1-112.1-122~1132.1-142.1-152.1-162'-172.1-181980POPULATIONANDPOPULATIONDENSITIESFORTOWNSANDCITIESWITHIN16KM(10MI)OFUNIT21970-1980POPULATIONGROWTHFORTOWNSANDCITIESWITHIN16KM(10MI)OFUNIT2DELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDPOPULATIONCENTERSWITHOVER25,000PEOPLEIN1980Amendment72-izDecember1983 NineMilePointUnit2FSARCHAPTER2LISTOF,TABLES(Cont)TableNumberTitle2.1-192.1-202.1-212.1-222.2-12.2-22~232.2-4DELETEDDELETEDDELETEDDELETEDDAILYTRAFFIC,VOLUMEOF.COUNTYHIGHWAYSINTHEVICINITYOFUNIT21978FREIGHTTRAFFICFORLAKEONTARIOAROUNDOSWEGOHARBORINDUSTRIALFIRMSWITHIN8KM(5MI)OFUNIT2ARMYCORPSOFENGINEERSHAZARDOUSMATERIALCOMMODITYDESIGNATIONFORRATERBORNECOMMERCE2.2-52.2-62~272.2-82.2-92.3-12.3-2HAZARDOUSMATERIALSSTORED/USEDBYINDUSTRIESWITHIN8KM(5MI)1978LAKEONTARIOCARGOTRANSPORTFOROSWEGOHARBORSOURCESOFTOXICCHEMICALSWITHIN8KM(5MI)OFUNIT2SITEPREDICTEDVAPORCONCENTRATIONSINTHEUNIT2CONTROLROOMINPUTDATAFORVAPORRUNDESIGNBASISTORNADOPARAMETERSVERTICALPROFILEOFTHE100-YEARRECURRENCEINTERVALFASTESTMILEOFWINDAmendment,242-xFebruary1985 NineMilePointUnit2FSAR2.2NEARBYINDUSTRIAL,TRANSPORTATION,ANDMIIITARYFACILITIES2.2.1LocationsandRoutesOnlyonemanufacturingorindustrialplant,AlcanAluminumCorporation'sAlcanSheetandPlateDivision,islocatedwithin8km(5mi)ofUnit2.Therearealsotwoelectricalpowergenerationfacilities,theJ.A.FitzPatrickNuclearPowerPlantoperatedbyNYPAandNineMilePointUnit1operatedbyNiagaraMohawkPowerCorporation,locatedwithin8km(5mi)ofUnit2.Figure2.1-2showsthelocationofthesetwofacilitiesrelativetoUnit2.TheprincipalproductsoftheAlcanAluminumCorporationplantarealuminumsheetandplate.Therearenochemicalplants,refineries,militarybases,orundergroundgasstoragefacilitieswithin8kmoftheplant.Inaddition,nopipelineorfuelstoragefacilitiesliewithinthe8-kmradiusexceptthosestoragefacilitiesassociatedwiththeAlcanplant,theFitzPatrickplant,andNineMilePointUnits1and2.Finally,therearenohazardouswastestorageordisposalsitespermittedbythestateinthe8-kmradiusfromtheplant.MajortransportationfacilitiesareshownonFigure2.2-1.Theprincipalroadwaywithin8kmofUnit2isU.S.Route104whichpasses6.2km(3.9mi)southoftheplantandconnectsthecityofOswegoandMexicoVillage.DailytrafficvolumeforU.S.Route104was5,841vehiclesin1979.Highwayaccesstothesiteisviatwocountyroutes,RoutelAtothesouthwestandRoute29totheeast.Aprivateeast-westroadcrossesthesiteandconnectsthesetwocountyroutes.Otherlocalroadsinthe,vicinitygenerallyhadaveragedailytrafficcountsoffewer.than2,000vehiclesin1978-1979,themostcurrentsurveydates.Table2.2-1presentsdailytrafficvolumecountsforcountyhighwayswithin8kmoftheplant.Onerailroadcompany,ConsolidatedRailCorporation(Conrail),transportsfreightinthevicinity,oftheplant.TheraillinesandspursservingUnit2,aswellastheJ.A.FitzPatrickplantandNineMilePointUnit1,areshownonFigure2.1-2.TheclosestraillinetoUnit2istheOswego-MexicobranchofConraillocatedapproximately2.5km(1.5mi)fromtheNineMilePointsite.Thisbranchlinehasdailyserviceondemandandaveragesonetraindaily,5daysaweek.ArailspurwasconstructedtoserveUnit2duringconstructionandoperationoftheplant.PossibleAmendment192.2-1May1985 NineMilePointUnit2FSARrsourcesoftrafficorhazardousmaterialsutilizinggroundtransportationrouteswithin8kmoftheplantareiden-tifiedanddetailedinSection2.2.3.TheOswegoRiverpasseswithinllto12km(6.6to7.2mi)ofUnit2atitsnearestpointandservesasamajorrouteforwaterbornecommerceonLakeOntario.FreighttrafficstatisticsaremaintainedbytheU.S.ArmyCorpsofEngineers.TotalsfortheriversectionfromNewYorkStateBargeCanal'LockNo.8totheportoftheCityofOswegoaretheonlystatisticsapplicableforthenearestreachofrivertothestation.Table2.2-2detailsthe1978freighttrafficforthisreachofriver.ThePortofOswego,theeasternmostportonLakeOntario,islocatedapproximatelyllkm(6.6mi)southwestofUnit2andprovidesalinkwithallportsontheGreatLakesandSt.LawrenceRiver.ShipsinnormalcommerciallanesboundtoandfromthePortofOswegopassnocloserthan11.3km(7mi)totheintakestructuresofUnit2.RegularcommercialairserviceisprovidedattheClarenceE.HancockAirport,located49.8km(31mi)southeastofUnit2nearSyracuse,NY.Thenearestflightcorridorassociatedwiththisairportis22.2km(13.8mi)fromtheNineMilePointStation.LightplanetrafficishandledattheOswegoCountyAirportinthetownofVolney,approximately19.3km(12mi)southoftheNineMilePointsite.LakesideAirstrip,aprivatefacilitywhichoperatesprimarilyasamaintenancefacility,withverylittleairtraffic,islocatedalongRoute176approximately10km(6.2mi)southoftheNineMilePointsite.Itisnotanticipatedthattherewillbeanysignificantin-creaseinthenumberofindustrial,transportation,andmilitaryfacilitieslocatedwithinan8-kmradiusofUnit2overtheplantlifetime.TherearealsonosignificantchangesexpectedinthenatureofexistingfacilitiesortheextentoftheiractivitieswithinthedesignatedareaovertheprojectedlifetimeofUnit2.2.2.2Description2.2.2.1DescriptionofFacilitiesMajorindustrialfacilitieswithin8kmofUnit2arelistedinTable2.2-3.AlcanRolledProducts,locatedap-proximately4.5km(2.7mi)southwestofNineMilePointStation,isthelargestemployerwithapproximately1,000workersmanufacturingaluminumsheetandplating.Nohazar-dousmaterialsaremanufacturedwithinthe8-kmradius.HazardousmaterialsstoredorusedarediscussedinSection2.2.2.2.TheNewYorkStateDepartmentofUSARRevision0202-2April1989 NineMilePointUnit2FSAR.EnvironmentalConservationrecordsthetype,amount,androuteofhazardousmaterialscarriedinthestate.Oneraillinepassesthroughthe8-kmradius.ConrailhasabranchlineservingAlcanAluminum,NineMilePointUnits1and2,andtheJames'.FitzPatrickNuclearPowerPlant.Themainlineislocatedapproximately3.5km(2.1mi)atitsnearestpointfromUnit2.WaterbornecommercestatisticspreparedbytheU.S.ArmyCorpsofEngineersonlypartiallyidentifyspecifichazardousmaterialsonLakeOntario.Commerceisrecordedbygeneralcommodity<'~.Alistingofhazardousmaterialsidentified,andtheircommoditydesignationsisprovidedinTable2.2-4.HazardousmaterialstransportedbyairhavenotbeenidentifiedbecauseofthedistanceofairwaysandfacilitiesfromUnit2.2.2.2.2DescriptionofProductsandMaterialsToidentifyhazardousmaterialsregularlystoredorusedwithin8kmofUnit2,surveyswereconductedofindustrialfirms,pipelinecompanies,anddistributorsthatmightbeexpectedtohandletoxicchemicalsorexplosives.Appendix2Adescribesthemethodusedtocollectdataregardinghazardousmaterialsusedbyvariousindustriesnear.the-site.HazardousmaterialsconsideredareincludedinTable2.2-4.ToxicchemicalsandexplosivesstoredorusedbyindustriesordistributorsinthevicinityofthestationaresummarizedinTable2.2-5.Nopipelinesorlocaldistributionandstoragelocationsarefoundwithin8kmofUnit2.Waterborne.commercefor1978LakeOntariotrafficisdescribedinTables2.2-2and2.2-6.Approximately1.2milliontonsofcargoweretransportedonLakeOntario.Sincemorespecificcommoditycategoriesarenotusedindatacollection,therearenomeansofidentifyingtypes,frequency,andamountsofhazardousmaterialshipmentspastthesite.ThenearestpassageofcommercialvesselstoUnit2occurswhennavigatingtoandfromtheCityofOswegoharbor,locatedapproximately10km(6.2mi)fromNineMile.PointSt'ation.ThePortofOswegoAuthorityindicatesthatnoneofthehazardousmaterialslistedinTable2.2-5havebeenUSARRevision02~23April1989 NineMilePoint'nit2FSARtransportedonLakeOntario,eitheroriginatingatordestinedtothePortofOswego.AllindustriesreportedreceivinghazardousmaterialshipmentsviaU.STHighway104andCountyRoute1bytruck.2.2.2.3ProjectionsofIndustrialGrowthTherearenoplansformajorexpansionintransportation,storage,orindustrialfacilitiesinthevicinityofUnit2.2.2.3EvaluationofPotentialAccidentsTheconsiderationofa'arietyofpotentialaccidents,andtheireffectsontheplantorplantoperation,isincluded.inthissection.Typesofaccidentsconsideredincludeexplosions,flammablevaporclouds,toxicchemicals,fires,collisionswithintakestructures,andliquidspills.2.2~3~1DeterminationofDesignBasisEvents2.2.3'.1ExplosionsBasedonacomprehensivesurveyofindustrieswithina10-km(6.2-mi)radiusofUnit2,thenearest.highwayonwhichexplosivematerialscanbetransportedisRoute104,,whichisadistanceofabout6.2km(3.9mi)fromsafety-relatedstructures.Thisseparationdistancefarex-ceedsthesafedistancefortrucktraffic(approximatelyS48.6m,1,800.ft)givenonFigure1ofRegulatoryGuide1.91.IndiscussionswithConrail,it,wasdeterminedthatnoex-plosiveorflammablematerialsaretransportedto,theOswegoterminaloftheraillinebetweenOswegoandMexico,NY.Inanyevent,thedistancefromthisraillinetoUnit2ismuchgreater,thanthesafedistanceforrailtrafficgiveninRegulatoryGuide1.91.SincethenearestcommercialshippinglanesonLakeOntarioaremorethan10km(6'mi)fromUnit2(accordingtotheU.S.CoastGuard),potentialexplosionsonashiporbargearenotconsideredadesignbasisevent'.Thisdistanceiswellbeyondtheradiusofthepeakincidentpressureof1psiasgiveninRegulatoryGuide1.91.Therefore,accord-ingtoguidancecontainedinRegulatoryGuide1.91,ex-'losionsonnearbytransportationroutesarenotconsidereddesignbasiseventsduetotheseparationdistancesofpotentialsourcesofexplosionsfromUnit2.Amendment262.2-4May1986 NineMilePointUnit2FSARThisresultsinaneffectivereleaserateof6,802g/sec(1.17xl0'g/172sec),therebyyieldingacenterlinepuffconcentrationof0.04whichislessthanthecriticalvalueof0.07.Therefore,thedelayedignitionofthepufforplumereleasefromthepropanetankattheFitzPatrickstationwillnotcausea1-psioverpressuretoreachtheUnit2containmentbuilding.2.2.3.1.3ToxicChemicalsPotentialSourcesofToxicChemicalsAccordingtoRegulatoryGuide1.78,bothonsiteandoffsitepotentialtoxicgashazardsmustbeconsidered.Anytoxicsubstancestoredonsiteinaquantitygreaterthan45kg(100lb)mustbeevaluated.Offsitesourcestobeevaluatedincludestationary,facilitiesandfrequenttransportationoftoxicsubstances(truck,rail,andbarge)within8km(5mi)ofthesite.Frequentshipmentsaredefinedasexceeding10/yrfortruckshipments,30/yrforrailshipments,and50/yrforbargeshipments.FortheNineMilePointsite,sourcesofpotentialtoxicchemicalhazardsincludechemicalsstoredonsite,aswellasfourstationaryandtwotransportationsourceswithin8kmofthesite.Table2.2-7liststhechemicalsassociatedwitheachsourcealongwiththeirquantitiesanddistancesfromtheUnit2controlroomairintake.ThethreestationarysourcesincludetheJamesA.FitzPatrickplant,theALCANRolledProductsDivision,OswegoWireInc.,andUnitl.OnetransportationsourceofpossiblehazardousmaterialsistrucktrafficalongRoute104,whichpasseswithin6.2"km(3.9mi)ofthesite.Thesecondtranspor-tationsourceistherailroadlinebetweenOswegoandMexico,NY.DiscussionswithConrailindicatethatonanaverage,onlyonehazardouschemicalshipmentduringan18-monthperiodpassesthroughtheOswegoterminal.Trafficonaspurtothesiteisnotfrequentenough(<30/yr)towarrantcon-sideration.'Onlythosechemicalsthathavethepotentialtoformatoxicvaporcloudorplumeafterreleaseto=theenvironmentneedtobeevaluated.ThiscriterionismetbyallchemicalslistedinTable2.2-7.8USARRevision02.2-5bApril1989 NineMilePointUnit2FSARControlRoomHabitabilitDeterminationTheeffectofanaccidentalreleaseofeachofthechemicalsdescribedintheprevioussectiononcontrolroomhabitabilityisevaluatedbycalculatingvaporconcentrationsinsidethecontrolroomasafunctionoftimefollowingtheaccident.ThiscalculationisperformedusingtheconservativemethodologyoutlinedinNUREG-0570andutilizingtheassumptionsdescribedinRegulatoryGuide1.78.Inapostulatedaccident,theentirecontentofthelargestsinglestoragecontainerisreleased,resultinginatoxicvaporcloudand/orplumethatisconservativelyassumedtobetransportedbythewinddirectlytowardthecontrolroomintake.Theformationofthetoxiccloudand/orplumeisdependentonthecharacteristicsofthechemicalandtheenvironment.Theentireamountofachemicalstoredasagasistreatedasapufforcloudthathasafinitevolumedeterminedfromthequantityanddensityof'thestoredchemical.Asubstancestoredasa.liquidwithaboilingpointbelowtheambienttemperatureformsaninstantaneouspuffduetoflashing(rapidgasformation)ofsomefractionofthestoredquantity.Theremainingliquidformsapuddlethatquicklyspreadsintoathinlayerontheground,subsequentlyvaporizingandformingaground-levelvaporplume.Ahighboilingpointliquid(aboveambienttemperature)formsapuddlethatevaporatesbyforcedconvectionwithnoflashinginvolved.Thecalculationsaredonebyacomputerprogram(VAPOR)basedonNUREG-0570methodologythatrequiresthefollowinginputinformation:chemicalphysicalproperties,controlroomparameters,meteorology,distancefromthespilltothecontrolroomintake,quantityofchemicalreleased,andtoxicitylimits.ThefollowingUnit2control-roomparametersareused:ventilationrateof0.551cum/sec(1,167cuft/min),andnetfreevolumeof5,935cum(209,600cuft).Themostconservativemeteorologicalconditionisassumedforthecalculation,consistingofPasquillClassGstability,awindspeedof0.5m/sec(1.6ft/sec),andanambienttemperatureof32.8'C(91F).Thecriteriafordeterminingchemicaltoxicityandsettinglimitsforhabitabilitydeterminationsaretakenfromregulatoryguidancedocuments.AccordingtoRegulatoryGuide1.78,thetoxicitylimitofachemicalisthemaximumconcentrationthatcanbetoleratedbyanaveragehumanfor2minwithoutphysicalincapacitation(severecoughing,eyeburn,severeskinirritation).StandardReviewPlanSectionUSARRevision02.2-6April1989 NineMilePointUnit2FSAR(1,000ft)toreachtheintakestructuresandwouldbesub-jecttodilutionduringtransport.Anyliquidspillsoriginatingduringcommoncommercialshiptransportwouldhavetotravelappromimately10km(6.2mi)toreachthein-I~6takelocation.Duetothecombinedeffectsofthesubmergedintakestructures'esignandthedistancebetweenintakestructurelocationandoriginofthepotentialliquidspill,theriskofentrainmentofanysignificantquantitiesofoil,orcorrosive,cryogenic,orcoagulableliquidsbytheintakestructuresisnegligible.2.2.3.1.7AirplaneCrashesThenearestaircorridorisapproximately22.5km(14mi)east,ofthesite(Section3.5'.6).Thereareonlytwoair-fieldsbetweenthe8-km(5-mi)and24-km(15-mi)radiiofthesite;theLakesideAirparkandOswegoCountyAirportareabout12km(7.5mi)and19km(12mi)southofthesite,respectively.Theaircraftapproachestotheseairportsarenotneartheplantsite.Thegeneralaviationmovementsattheseairportstotalapproximately1,460/yrand19,900/yr,respectively.Theannualmovementsarebelowthecriticalnumberatwhichaprobabilityanalysisforaircraftac-cidentswouldberequiredaccordingtoRegulatoryGuide1.70.Therefore,theprobabilityofaircraftcrashingintothesiteisconsideredtoberemote,andairplanecrashesneednotbeconsidereddesignbasisevents.2.2.3.2EffectsofDesignBasisEventsPotentialdesignbasiseventsareidentifiedinSection2.2.3.1.Theeffectsoftheseeventsonthesafety-relatedcomponentsoftheplantareinsignificant.Thepotentialfortoxicchemicalaccidentsaffectingmaincon-trolroompersonnelhasbeenevaluated.Thisshowsnopotentialimpact,onmaincontrolroomhabitability.Self-containedbreathingapparatus,however,willbeprovidedformaincontrolroomoperators'mendment262.2-9May1986 NineMilePointUnit2FSAR2.2.4ReferencesTransmittalfromMr.MartinWeiss,OswegoCountyPlanningBoard,November7,1979.Updatedandverified,April4,1981.2.WaterborneCommerceoftheUnitedStates,Part3,1978.DepartmentoftheArmy,CorpsofEngineers,Virginia.3.TelephoneconversationbetweenP.A.Hughes(SWEC)andJ.Robinson(U.S.CoastGuard,9thDistrict).June23,1981'ransmittalfromB.Gorman,PowerAuthorityoftheStateofNewYork,December7,1979,toP.Johnson,Stone6WebsterEngineeringCorporation.5.Patty,F.A.(ed.).IndustrialHygieneandToxicology,Vol.IandII.IntersciencePublishers,NewYork,NY,1958,1963,and1978.6.Sax,N.E.DangerousPropertiesofIndustrialMaterials,3rdEdition,VanNostrandReinhold,NewYork,NY,1968.7.CriteriaforaRecommendedStandard:OccupationalExposuretoCarbonDioxide,PublicationNo.NIOSH76-194,August1976.8.Tilton,B.E.andBruce,R.M.ReviewofCriteriaforVapor-PhaseHydrocarbons,EnvironmentCriteriaandAssessmentOffice,USEPA,EPA-600/8-80-045,p6-150.9.FireProtectionHandbook,13thEdition,NationalFireProtectionAssociation,1969,Boston,MA,p15.14-45.10.TransmittalfromR.J.Mangold,AlcanAluminumCorporation,July8,1981,toP.D.Patel,StoneEcWebsterEngineeringCorporation.TransmittalfromT.J.Perkins,NiagaraMohawkPowerCorporation,August3,1981,toK.A.Baraniak,Stone&WebsterEngineeringCorporation.12.Burgess,D.S.andZabetakes,M.-G.DetonationofaFlammableCloudFollowingaPropanePipelineBreak.U.S.BureauofMinesReportofInvestigations(RI7752),1973.Amendment32.2-10June1983 NineMilePointUnit2FSARTABLE2.2-3INDUSTRIALFIRMSWITHIN8KM(5MI)OFUNIT2FirmAlcanAluminumCorporationDistance/DirectionfromSite(km4.5/SWAluminumsheetandplate1,000JamesA.FitzPatrick<1/ENuclearPowerPlantElectrical515generationNineMile'PointUnit1AdjacenttoUnit2Electrical450generationSOURCE:References4,10,llUSARRevision01of1April1989

NineMilePointUni.t2FSARTABLE2.2-5HAZARDOUSMATERIALSSTORED/USEDBYINDUSTRIESWITHIN8KM(5MI)MaterialCarbondioxideIndustrialUserAlcanFitzPatrickStorageonPremises(Max.atO~eTLeMOd*~A*aSla65tonsTruck6tons26,000lbTruck6,900galMaximumQuantity~Shed10tons6,900galShient~FeueeWeeklyInfrequently,asneededsystemAverageQuantity~Shi~edyr250tonsSmallquantitresusedtorechargeChlorineNMPUnit1Alcan20,000lb30tonsTruckTruck5,000lb1(1ton)cylinder6,300gal12tonsMonthlyBiweekly56,000gal350cylindersHeliumAlcan1,917ftTruck213ft9cylinders(213fteach)Asneeded94cylinders(20i022ft)HydrochloricacidHydrogenNitrogenPropaneSodiumhydroxideAlcanFitzPatrickNMPUnit1OswegoWireAlcanFitzPatrickNMPUnit1OswegoWireFitzPatrickAlcanFitzPatrickAlcanNMPUnit1OswegoWire500galTruck28,800ftTruck12,000ftTruck6,450ftTruck970,000ftTruck10,000galTruck15,300galTruck160,000ftTruck55gal128g000ft24,000ft515ft670,000'ft6,900gal6,300gal385gal128,000ft24,000ft5,375ft670,000ft6,900gal6,300gal145,000ft160,000ft80i000lb5,000gal3,000gal165gal385galTruckTruckTruckTruckTruck7,000lb3g000lb55gal55gal55gal22,500lb7,000lb3,000lb1,000gal55gal55gal1,000galTruck22,500lbWeeklyBiweeklyBimonthly10WeeksHonthlyMonthlyMonthlyWeeklyMonthlyBiweeklyMonthlyMonthlyAsneededMonthly16,000gal221,000ft72,000ft27,305ft8,999,200ft129,000gal56,000gal8,000,000ft3,000gal200,000gal246,000lb10,000gal100gal660galUSARRevision01of2April1989

NineMilePointUnit2FSARTABLE2.2-7SOURCESOFTOXICCHEMICALSWITHIN8KM(5MI)OFUNIT2SITEChemicalLocationChemicalAmountDistancetoIntakes(mJamesA.Fitz-PatrickplantAlcanN2H2SOCO2PropaneHalonClqPropaneN2HCLCOR0.3050.3461.180.2210.2600.1810.3630.2600.2260.533x10sx10sx10'10'10'10'10sx10sx107x10s6206206206206204,9904,9904,9904,9904i990Route104HC1N2CO20.542x1070.183x10'.272x10~5,4705,4705,470NineMilePointUnit1N2CO2H2SOHCLHalon0.4430.9070.1140.4540.227x10sx10'10'10'10e290265290290290NineMilePointOswegoWireIncorporatedH22Halon1301N2IsopropylAlcoholN2PropaneH2SOHCL0.118x10'.113x10'.671x10s0.330x10e0.525x10e0.947x10e0.750x10e0.182x10"33451507,0807,0807,0807,0807,080USARRevision01of1April1989

NineMilePointUnit2FSARTABLE2.2-8PREDICTEDVAPORCONCENTRATIONINTHEUNIT2CONTROLROOMChemicalLocationJamesA.FitzPatrickplantAlcanRoute104NineMilePointUnit1NineMilePointUnit2OswegoWireIncorporatedChemicalN~HqSOCOqPropaneHalonClqPropaneN~HCLCO~HclN~CO~NqCOqH~SOHalonHclHqSOCO~Halon1301N~IsopropylAlcoholNqPropaneHqSOMaximumControlRoomConcentration(m~11.26.6x10-~6.21.291.730.0381.10.090.0032.5x10-'.0090.540.022.214.71.3x10-~0.570.0096.6x1046.83.8832.12.2x10-41.2x10-~2.1x101.0x10-'oxicLimit2740.00254.843.14320.04543.12740.0554.80.05027454.827454.80.0024320.050.00254.84322741.227443.10.002AllowableTimePeriod(min152151515215151521515215152151521515151515152USARRevision01of1April1989 ' NineMilePointUnit2FSARSurveillance,includinginkingandroutinepreventivemaintenance,isperformedatleasttwiceweekly.Chartsarechangedat2-weekintervals.Calibrationsoccuratleastevery6monthswithcomponentchecks'ndadjustmentsperformedwhenrequired.'Allmetersandotherequipmentusedincalibrationsare,inturn,-calibratedatscheduledintervals.Inspectionandmaintenanceofallequipmentisaccomplishedinaccordancewithproceduresintheinstrumentmanufacturer'smanuals.Inspectioniscarriedoutbyqualifiedtechnicianscapableofperformingthemaintenance,ifrequired.Theresultsoftheinspectionsandmaintenance'erformedarekeptinalog.F2.3.3.1.6DataAcquisitionandReductionFromJanuary1974toOctober1980,analogstripchartswerechangedevery2weeksandprocessed.Aftereachchartwasscannedforinstrumentmalfunctions,hourlyvalueswereread.Thedatawereroutinelykeypunchedonamonthlybasis.Afterkeypunchverification,acomputerlistingandqualitycontrolsummarywasgeneratedofhourlyreadings.The'atawereagaincheckedforinconsistenciesbyaninstrumentspecialistandaqualifiedmeteorologist.Afterincorporatinganycalibrationsfromsitepersonnel,afinallistingwasgenerated.Thedatawerethentransferredtomagnetictapeandacopywasmade.2.3.3.1.7DataAnalysisProceduresAlldataweresubjecttoqualitycontrolcheckspriortofinalizationintomonthlylistings.Attheendofeachquarter,routinesummariesofwinddirection,speed,andstabilitywerecomputed.MonthlyandannualdataanalyseswereperformedaswarrantedforspecialprojectsinadditiontotheroutinesubmittalofthedataforNineMilePointUnit1totheNRC.2.3.3.2OperationalMeasurementsProgram2.3.3.F1DescriptionThepreoperationalonsitemeteorologicalmeasurementsprogramhasbeenupgradedandexpandedtomeettheintentandrecommendationsofRegulatoryGuide1.23andNUREG-06S4fortheoperationalmeasurementsprogram'.Thepreoperational,steel,openlattice61-m(200-ft)meteorologicaltowerservesastheprimaryinstallation.Newmeteorologicalsensors.wereinstalledatthefacilityAmendment32'31June1983 NineMilePointUnit2FSARstartinginJuly1982andtheentirereplacementwascompletedbyFebruary1983.SupplementalinlandmeasurementsareobtainedfrominstrumentationattheOswegoCountyAirportnearFulton.Back-upinstrumentationislocatedeastof'heJ.A.FitzPatrickPlant.AmapshowingthedetailedrelationshipofUnit2totheprimarymeteorologicaltowerandthebackuptowerisshownonFigure2;3-40.Figure2.3-40Ashowsthelocationoftheinlandtower,theprimarytower,andthebackuptowerwithrespecttoUnit2onalargerscalemap.Theprimarytowerisinstrumented.withwinddirectionandspeedsensorsatthreelevels:9m(30ft),30m(100ft),and61m(200ft).Sigmathetaisderivedforeachofthethreewindlevels.Inaddition,ambienttemperatureismeasuredat8m(27ft)andtemperaturedifferencesaredeterminedbetweenthe61-m(200-ft)and8-m(27-ft)levels.Dewpointtemperatureisobtainedatthe8-m(27-ft)level.Nearthebaseofthetower,precipitationandbarometricpressurearealsomeasured.Theinland10-m(33-ft)meteorologicaltowerislocatedwithgoodexposureinalldirectionsandissituatedawayfromallrunwaysandbuildingsattheOswegoCountyAirport.Theinstrumentationprovideswindspeedanddirectionfromwhichsigmathetavaluesarecalculated.Theback-upwinddirectionandspeedinstrumentationislocatedeastoftheJ.A.FitzPatrickPlant,ona.27-m(90-ft)utilitypole.Onecoincidentannualcycleofwinddatafromthebackupinstrumentationandtheprimarytowerwillnotbeavailableuntilmid-1984.Atthattime,acomparisonofthetwodatasetswillbemadetodeterminetherepresentativenessofthebackupwindmeasurements.Theresults.ofthiscomparisonwillbeprovidedbytheendof1989.2.3.3.2.2MeteorologicalInstrumentationTheoperationalmeteorologicalmeasurementsprogramisdesignedtomeettheNRCrecommendationsatthetimeofinstallationinmid-summer1982andisinaccordancewithRegulatoryGuide1.23.Manufacturers'odelnumbersandspecificationsforthesensorsareshowninTable2.3-4-A.Componenterrors,aswellassensorandsystemaccuracies,arelistedinTable2.3-5A.WindInstrumentsAllmonitoringlocationsemploytheTeledyneGeotechthree-cupanemometerandvane.USARRevision02'-32April1989 NineMilePointUnit2FSAR67.Dewey,K.E.Lake-EffectSnowstormsandtheRecordBreaking1976-1977SnowfalltotheLeeofLakesErieandOntario,Weatherwise,Vol.30,No.6,1976.68.U.S.DepartmentofCommerceLocalClimatologicalData-MonthlySummary-Syracuse,New=York.NOAA,Environmental,DataandInformationService,NationalClimaticCenter,Asheville,NC,1977-October1983.69.Sykes,R.,Pack,A.B.andLoveridge,E.TheClimateandSnowClimatologyofOswego,NewYork.LakeOntarioEnvironmentalLaboratory,ContributionNo.2,Vol.1,June1971,p.59.70.Hershfield,D.M.RainfallFrequencyAtlasoftheUnitedStatesforDurationsFrom30Minutesto24HoursandReturnPeriodsFrom1to100Years.TechnicalPaperNo.40,WeatherBureau,U.S.DepartmentofCommerce,Washington,D.C.,1961.Amendment192.3-62aMay1985 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKAmendment192.3-62bMay1985 NineMilePointUnit2PSARTABLE2.4-15SUMMARYOFRESULTSANALYSISOFBUILDINGFLOODINGDUETOPMPBASEDONHYDROMET51AND52~BiidiDieselgeneratorControlbuildingAuxiliarybaysouthElectricaltunnel-southareaStoplogsC261-29C261-24C261-31SA262-3ET262-4Length~ft15TotalFlow~ftA404.2551.1257.2110.2110.263.663.6Bldg.Depth~inDistributionofPlowFluxEvenlyoverfloor;providedcaulkingmaterialtomakestoplogswatertight.C261-29andC261-31flowswillcombineandspreadthroughEl.261corridorsandintosomerooms.C261-24willflowdownstairwellandspreadthroughcorridorsonlowerfloors.Nofixisrequired.Plowwillbeconfinedtoauxiliarybaystairwellarea.Nofixisrequired.Plowwillbespreadevenlythrougheachtunnel.Electricaltunnel-northareaET261-1102.6AuxiliarybaynorthRBrailroadtrackbayStandbygastreatmentServicewaterpumproom(north)fromauxiliaryboilerroomET261-2NA262-1RR-261-1SG261-2SG261-1SG261-6AB261-317102.663.6NA273.6273.6102.6NANA2.5Plowwillbeconfinedtoauxiliarybaystairwellarea.Nofixisrequired.Doorsareequippedwithinflatableairseals;waterleakagewillbenegligible.Nosafety-relatedequipmentisinthisarea.Plowisspreadevenlythroughoutthebuilding(seeNote5).Plowintoauxiliaryboilerbuildingisdis-tributedintothepumphouseifAB261-3isopen.USARRevision01of2April1989

NineMilePointUnit2FSARTABLE2.4-15(Cont)B~B'd'ervicewaterpumproom(south)fromscreenwellareaDoorSW261-14Length~ftTotalFlow~ftA94.2Bldg.Depth~inDistributionofFlowFluxEvenlythroughoutbuilding.NOTES:l.UsehydrographsfromCalculationNo.12177-WH(B)-062forwatersurfaceelevations.2.Doorsillelevationisinthedooridentificationnumber,e.g.,SH261-14,where"261"isthedoorsillelevation.3.CalculationmethodforinflowthroughdoorwaysfromPHFsubmergedorificedischargeequation:9=CA~gh()-"Flow(cfs)C=Dischargecoefficient=0.6A=Crosssectionalareaofflow=lengthofdoor(L)xcrackwidthofdooropening(1/16induetoflow"necking")g"-Gravityh=Headwatersurfaceelevationonexteriorofdoor4.Nocredithasbeentakenintheanalysisforsump~aterretainageorsumppumpoperation.5.Sinceequipmentstructuralpadheightis6in,resultantbuildingwaterdepthslessthanthisareacceptable.USARRevision02of2April1989

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER7Title6Athrough6CINSTRUMENTATIONANDCONTROLSYSTEMSReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3ComponentsVolume1313131313141515151515157.17'7'7,47.57.67'Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8AELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystem16161616,1717'CHAPTER9AUXILIARYSYSTEMS179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9Ag9C17181920,2121,22IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER1010.110.210.310.4STEAMANDPOWERCONVERSIONSYSTEMSummary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem23232324CHAPTER11RADIOACTIVEWASTEMANAGEMENT11'11.211.311.411'SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendixllACHAPTER12RADIATIONPROTECTION2424252525252512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER76Athrough6CINSTRUMENTATIONANDCONTROLSYSTEMSTitleReactorVesselComponentandSubsystemDesign5Ag5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3ComponentsVolume1313131313141515151515157'7'7'7'7.57.67'Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16161616,17I179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17181920,2121,2223IUSARRevisionApril1989 NineNilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSIONSYSTEM2310.110.210.310.4Summary,DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem232324CHAPTER11RADIOACTIVEWASTEMANAGEMENT11.111.211.311.411.5AppendixllACHAPTER12RADIATIONPROTECTIONSourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems2424252525252512.112.212.312~412.5CHAPTER1313.113.213.313.413.513.6AppendixesEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)-RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B25252526262626262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER7TitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Componentsthrough6CINSTRUMENTATIONANDCONTROLSYSTEMSVolume1313131313141515151515157.17'7'7'7.57.67'Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16161616,1717I179.19.29.39'9.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17181920,2121,22IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER1010.110.210.310.4CHAPTER11TitleSTEAMANDPOWERCONVERSIONSYSTEMSummary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume2323232411.111.211.311.411'AppendixllASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525CHAPTER12RADIATIONPROTECTION2512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B262626.26'62626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER7TitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components6Athrough6CINSTRUMENTATIONANDCONTROLSYSTEMSVolume"1313131313141515151515157'7'7'7'7.57.67~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety15.15151616161616CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5AppendixesELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C1616'16'16,17171717.181920,2121,22IUSARRevision0I~IApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER1010.110.210.310.4CHAPTER11STEAMANDPOWERCONVERSIONSYSTEMSummary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT2323232411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsII242425252525CHAPTER12RADIATIONPROTECTION2512~112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613~113.213,.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B26262626'62626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit.2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER7TitleReactorVesselComponentandSubsystemDesign5Ag5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components~through6CINSTRUMENTATIONANDCONTROLSYSTEMSVolume1313131313141515151515157.17'7'7.47.57'7~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5AppendixesELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9Ag9C1616,16'16,1717I1717.181920,2121,22IUSARRevisionApril1989 .NineMilePointUnit2FSARTABLEOFCONTENTS'(Cont),SectionCHAPTER1010.110.210.310'TitleSTEAMANDPOWERCONVERSIONSYSTEMISummary,DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemVolume23232324CHAPTER11RADIOACTIVEWASTEMANAGEMENT11.111.211.311.411.5AppendixllASourceTerms1LiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525CHAPTER12RADIATIONPROTECTION2512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26iv FigureNumberNineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont)Title3.6A-403.6A-413.6A-423.6A-433.6A-443.6A-453.6A-463.6A-473.6A-483.6A-493.6A-503.6A-513.6A-523.6A-533.6A-54HIGHENERGYPIPEBREAKSREACTORWATERCLEANUPOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSREACTORWATERCLEANUPOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSSTANDBYLIQUIDCONTROLINSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTHIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENTDELETEDDELETEDHIGHENERGYPIPECOMPOSITEPLANEL175'-0"AND215'-0"HIGHENERGYPIPECOMPOSITEPLANEL240'-0"HIGHENERGYPIPECOMPOSITEPLANEL261'-0"27Amendment273-xliJuly1986 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont)FigureNumber3.6A-553.6A-563.6A-573.6A-58TitleHIGHENERGYPIPECOMPOSITEPLANEL289'-0"HIGHENERGYPIPECOMPOSITEPLANEL306'-6"HIGHENERGYPIPECOMPOSITEPLANEL328'-10"HIGHENERGYPIPECOMPOSITESECTION1-13.6A-593.6A-603.6B-13.6B-23.6B-3HIGHENERGYPIPECOMPOSITESECTION2-2HIGHENERGYPIPECOMPOSITESECTIONS3-3AND4-4TYPICALRESTRAINTFORCEDEFLECTIONCURVETYPICALPIPEWHIPRESTRAINT'ONFIGURATIONBREAKLOCATIONSANDRESTRAINTSANALYZED,PDAVERIFICATIONPROGRAM3.7A-l3.7A-23.7A-33.7A-4HORIZONTALSSEDESIGNRESPONSESPECTRANORMALIZEDTO0.15GVERTICALSSEDESIGNRESPONSESPECTRANORMALIZEDTO0.15GHORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTH-QUAKE)BASEDON2.0PERCENTDAMP1NGRATIOHORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTHQUAKE)BASEDON1PERCENTDAMPINGRATIOAmendment213-xlilSeptember1985 NineMilePointUnit2PSARTABLE3.2-1(Cont)125-VDCPowerSstemsScopeof~Su~1LocationElectricalClassifi-cationSeismicC~atoGroupClassifi-cationQuality(31,32,Assurance33,Reirement34TornadoProtectionNotes125-Vdcemergencybatteriesandracks125-Vdcemergencybatterychargers125-Vdcemergencyswitchgear125-Vdcemergencycenters125-VdcemergencydistributionpanelsEmergencycablesCabletrayandfabricatedsupportswithsafetyfunctionsDCcontainmentpenetrationsConduitandnonemergencycabletrayMiscellaneousComnentsReactorbuildingpolarcraneCivilStructuresPrimarycontainmentReactorbuilding,includingfuelstoragefacilitiesandauxiliarybaysRadwastebuildingControlbuildingDieselgeneratorbuildingTurbinebuilding,includingheaterbay,exceptasnotedMainsteamtunnelPortionofturbinebuildingPipetunnelportionoftheturbinebuildingbetweencolumnlinesAKandAMbelowel261ftPipetunnelportionoftheturbinebuildingbetweencolumnlines10and12belowel248ftTurbinebuildingel250ftslaboverthepipetunnelsbetweencolumnlines10and12NAM,C,RBMiCiRBMiCgRBRBMgCgRB1E1E1ENA1ENANon-1ENANANANANANANAIZ(22)NRTT(34)(29)(28g44)(28,29i36)(20)USARRevision116of26October1989 1I Nine'ilePointUnit2FSARTABLE3.2-1(Cont)PenetrationZ-328-32RCS-750-151-2ExtensionofPrimarContainment,ReactorBuildinEuiment(DER)PenetrationZ-452DER-002-034-2(47)TheequipmentanditsclassificationalsoapplytotheairstartsystemassociatedwiththeDivisionIII(HPCS)dieselgenerator.(48)TheGEcompressormotorisSeismicCategoryI.Thecom-pressormotorstarterisSeismicCategoryNA,butitisseismicallymountedandevaluatedtoensurethatiffailureoccursitwillnotcausedegradationofsafety-relatedequipment.USARRevision026hof26April1989

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35'AppendixesCHAPTER6TitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESVolume131313136.16.26.36.46.56.6Appendixes6Athrough6CEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77.17'7'7'7.57.67~7AppendixesCHAPTER88.18.28.3Appendix8AINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7A,7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystem1515151516161616161616.16'16,1717'CHAPTER9AUXILIARYSYSTEMS179.19.29.39'9.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9Ag9C17.181920,2121,2223IUSARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER10TitleSTEAMANDPOWERCONVERSIONSYSTEMVolume2310.110.210.310.4CHAPTERllSummary,DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT23232411.111.211.311.411'AppendixllASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525CHAPTER12RADIATIONPROTECTION2512.112.212.312.412.5CHAPTER1313.113.213.313.4-13.513.6AppendixesEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B25,2525262626262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER77.17'7'7.47'7'7~7.AppendixesCHAPTER8TitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components6A.through6CINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdown.Safety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7Ag7BELECTRICPOWERVolume13131313131415151515151515151516'16161616168.18.28.3Appendix8ACHAPTER9IntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16,1616,1717I179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17,181920,2121,22IUSARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER1010.110.210.310'CHAPTERllTitleSTEAMANDPOWERCONVERSIONSYSTEMSummary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume2323232411.111.211.311.411.5AppendixllASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525CHAPTER12RADIATIONPROTECTION2512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113~213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B2626262626'626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSAR3.7.3.1.3AOtherDynamicLoadsLoadingcombinationsandstresslimits,includingloadsduetohydrodynamiceffects,aredescribedinSection3.9.3.1A.AfurtherdiscussionofhydrodynamicphenomenaisincludedintheDesignAssessmentReportforHydrodynamicLoads(Appendix6A).3.7.3.2ADeterminationofNumberofEquivalentStressCyclesThefollowingcriteriaareappliedtoallCategoryIsubsystems:l.AtotaloffiveOBEandoneSSEareconsidered.2.Forsubsystems,exceptpiping,20cycles(fullsignreversals)perseismicevent,i.e.,atotalof120cycles,areconsidered.3.Forallpipingsystems,10maximumstresscyclesperOBE(i.e.,atotalof50cycles)arepostulated.4.Wheretimehistoryanalysisisperformed,aminimumdurationof10secisassumed.3.7.3.3AProcedureUsedforModelingTheproceduredescribedinthefollowingsectionsisspecificallywrittenforpipingsystems.OthersubsystemsareseismicallyqualifiedasdescribedinSection3.7.3.1.1A.3.7.3.3.1ASummaryPortionsofpipingsystemsthatareboundedbyanchorsorequipmentarestaticallyanddynamicallyindependentfromtheremainderofthepiping.Generally,apipingsystemconsistsofseveralsuchsubsystems.Theanalyticalmodelanditsgeometricboundariesaredescribedindetailinthefollowingsections.3.7.3.3.2AGeometricBoundariesofAnalyticalModelsForthepurposeofanalysis,pipingsystemsaresubdividedintosmallerunits(referredtoasproblems)thatareboundedbystructuralanchors(6-deg-of-freedomconstraints)orbyothervirtuallyrigidpointssuchasequipment,penetrations,andpipingofmuchlargerdiameter.Amendment233.7A-19December1985 NineMilePointUnit2FSARAbranchlinewithamomentofinertiaof1/10orlessoftherunpipemaybeignoredinthemodel.However,ifthebranchlineneedstobeanalyzed,itsmodelincludestheef-fectoftherunpipe.WhereCategoryIpipingisconnectedtononseismicpiping,theadjoiningportionofthenon-seismicpipinguptothefirstanchorisincludedintheanalyticalmodeloftheCategoryIpiping,andallsupportsuptoandincludingthisanchor,aredesignedseismically(Section3.7.3.13A).3.7.3.3.3AModelThebasicmethodofanalysisusedisNUPIPE,afiniteelementcomputerprogram(Appendix3A)~Inaccordancewiththismethod,thecontinuouspipingismathematicallyidealizedasanassemblyofelasticstructuralmemberscon-nectingdiscretenodalpoints.Nodalpointsareplacedinsuchamannerastoisolateparticulartypesofpipingelementssuchasstraightrunsofpipe,elbows,valves,etc,forwhichforce-.deformationcharacteristicscanbecategorized.Nodalpointsarealsoplacedatalldiscon-tinuitiessuchaspipingsupports,concentratedweights,branchlines,andchangesincrosssection.Systemloadssuchasweights,equivalentthermalforces,fluidtransientdynamicforces,andinertiaforcesareappliedatthenodalpoints.Stiffnesscharacteristicsoftheinterconnectingmembersarerelatedtotheeffectiveshearareaandmomentofinertiaofthepipe.Thestiffnessofpipingelbowsandcertainbranchconnectorsismodifiedtoaccountfor.localdeformationeffectsbytheflexibilityfactorsspecifiedinASMESectionIII,1974,SubarticlesNB-3600(SafetyClass1pipinganalysis)andNC-3600(SafetyClass2and3pipinganalysis).Theincreasedstiffnessofvalvebodiesistakenintoconsideration.3.7.3.3.4ASelectionofMassPointsThelumpedmassesarelocatedtoadequatelyrepresentthedynamicpropertiesofthepipingsystem.Masspointsaregenerallyselectedinaccordancewiththefollowingguidelines:At.-eachnodewhereaconcentratedweightisplaced(valves,flanges,orotherin-line"pipingcomponents).2~Ateachintersectionwherethreeormorepipingelementsareconnected(branchconnections,tees,andy-fittings).Amendment,33.7A-20June1983 NineMilePointUnit2FSARResonseSectrumMethodWhenapipingsystemisanalyzedbymeansoftheresponsespectrummethod,thecomputercodeNUPIPEisusedtocal-culatethemodalresponseateachnodepointinthepipingsystemduetotheARSexcitationappliedtothesystem.GenerationorselectionoftheappropriatesetofARSforasubsystemsupportedatdifferentelevations,andcon-siderationoftheeffectofseismicdifferentialdisplacementsbetweenrestraintsarediscussedinSection3.7.3.9A.ThedampingvaluesforpipingdependonpipesizeandaregiveninTable3.7A-1.Theequationsofmotionandtheirsolutionareaspreviouslydescribedforstructures(Section3.7.2).TimeHistorMethodTheapplicablebasemotiontimehistoryisthestructuralresponseatarepresentativemasspointofthestructuretothegroundmotiontimehistory.TheequationsofmotionandtheirsolutionarethesameasinSection3.7.2.5A,butthescalaraccelerationtermintheexcitationfunctionisnowtheamplitudeoftheaccelerationofthebaseofthesub-system(pointsofattachment),notoftheground.Theef-fectofparametervariationsonthefloorresponsespectraaretakenintoaccount(Section3.7.2.9A).DnamicAnalsisFormulationThebasicequationsofmotionandtheirsolutionsarethesameasforstructures(Section3.7.2).Absoluteac-celerationsatpointsonthepipingsystemaresometimesneededforqualificationofcritical,safety-relatedequipment.Withtheresponsespectrummethod,themaximumabsoluteaccelerationatamasspointinmodeiisobtainedfromNewton'slawbydividingtheeffectiveinertiaforcebythemassatthemasspoint:ta1=tMl'lQl(3.7A-6)Where:[M]=Diagonalmassmatrixofthesystem[Qf=EffectiveinertiaforcesinmodeiWiththetimehistorymethod,theabsoluteaccelerationsareobtainedbyaddingthebaseaccelerationtotherelativeac-celerationsofthemasspoints.I"Amendment,263.7A-25May1986 NineMilePointUnit2FSARSeismicDifferentialDislacementsDescritionofInutTheseismicdifferentialdisplacementsarealsocalledseismicanchormovements.ThiseffectisanalyzedinaseparatestaticloadcaseforOBEanchormovements.Theanchormovementsareobtainedfromtheseismicdifferentialdisplacementsofthestructuralnodes.Thedisplacementsareobtainedinthefollowingform,onesetforeachmasspoint,N,ofthebuildingmodel:EarthuakeDirectionMassNodeX(East-~WestVerticalZ(North-~SouthDgXDpXD3XDgYDpD3DzzDgzD3zNWhere:NXNNzDN(DN,DN)=SRSSofdisplacementsinX(Y,Z)dir-xyzectionduetoearthquakeexcitationinX,Y,andZdirectionsatNodeNThesearethemovementsofpointsonthewallsrelativetothefoundationofthebuilding.Relativedisplacementsbetweenmasspointsareusedtodeterminethemovementsofsupportpoints.Supportdisplacementsareimposedonthesysteminaconservativemanner.CombinationofAnchorMovementLoadsTheindividualX,Y,andZanchormovementcomponentsofOBEareanalyzedasthreeseparatestaticanchormovementloadcasesintheNUPIPEcomputerprogram.TheseloadcasesarethencombinedbytheSRSSmethodinNUPIPE,andtheresultantloadcaseisusedinthecodestressevaluation.CombinedSeismicResonseThesystemresponsetotheresponsespectrumexcitation(i.e.,displacements,internalforcesandmoments,stresses,andsupportreactions)isobtainedbyfirstcombiningthe3.7A-26 NineMilePointUnit2FSARmodalcontributionsforeachearthquakecomponent.Incon-formancewithRegulatoryGuide1.92,theeffectofcloselyspacedmodesistakenintoaccountbytheproceduredescribedinSection3.7.2.7A.ThecontributionsofeachofthethreecomponentsarethencombinedbytheSRSSmethods;Whentheresponsespectrummethodisused,responsetothedifferentialsupportmotionisconsidered..InSafetyClass1pipinganalysis,thismotioniscombinedwiththeinertialresponse;theresultis-thencombinedwithotherloadcases.Intheanalysisofotherpipingclasses,theseismicanchormovementiscombinedwithsecondaryloads.Seismicloadcasesarecombinedwithotherloadcases(thermal,weight,pressure,otheroccasionalloads)inac-cordancewithASMESectionIII,1974.TheloadcombinationsaregiveninSection3.9.3.1A.FatiueConsiderationsForASMESafetyClass1piping,ifEquation(10)ofSubpara-graphNB-3653.1isnotsatisfied,afatigueanalysisisper-formedinaccordancewithSubparagraphNB-3653.2orSubarti-cleNB-3200.ThisanalysisusesthetotalnumberofstresscyclesofallOBEs.ThenumberofearthquakecyclesisdiscussedinSection3.7.3.2A.ComuterProramsUsedforSeismicAnalsisAllanalysesareperformedwithNUPIPE.Thisprogramhan-dlesresponsespectrumandsupportmotiontimehistoryanalyses.PSPECTRAisusedforpeakspreading,aswellasforenvelopegeneration,toobtaintheARSrequiredasNUPIPEinputtoallspectralanalyses.TheseprogramsusedinpipinganalysisaredescribedinAppendix3A.DevelomentofRelativeDislacementsandTheirAlicationtoPiinAnalsisTherelativedisplacementbetweenapointonthereactorbuildingandapointontheprimarycontainmentisobtainedasfollows:1.Thedisplacementtimehistoryateachpointiscalculatedusingasinputthethree-directionalsynthetictimehistoryofgroundmotion.2.Thedisplacementtimehistoryofthefirstpointissubstractedfromthatofthesecondtogetatimehistoryofrelativedisplacement.SomeexamplesofdisplacementsareincludedonFigure3.7A-35.USARRevision03.7A-27April1989 NineMilePointUnit2FSARTheeffectofrelativedisplacementbetweenthesupportsisconsideredinthepipinganalysis.Onesupportisselectedasareferencepoint.Dynamicdisplacementsatthisreferencepointaretakeneitheraszeroorasdisplacementsrelativetoagivenstructuralnode.Atthe'first(adjacent)supportfromthereferencepoint,relativedisplacementsbetweenthissupportandthereferencepointaretakenandaddedtothedynamicdisplacementofthereferencepoint(thedirectionofdisplacementsisdeterminedandappliedtothesupportsinrelationtoitsfunction).Theresultantdisplacementsbecomethedynamicdisplacementsofthefirstsupport.Thefirstsupportthenbecomesthenewreferencepoint.Thisprocessisrepeateduntildynamicdisplacementsatallsupportsareobtained.3.7.3.9AMultiplySupportedEquipmentComponentswithDistinctInputsWhenasubsystemisattachedtodifferentpartsofastructure,suchasseparateelevationsononewallorseveralwalls,theresponsespectraofallstructuralnodesforwhichresponsespectraexistandwhichlienearesttothesupportelevationatthesubsystem,bothbelowandabovethesupportelevation,areenveloped,andthisenvelopespectrumisappliedtothesubsystem.Incaseswhereasub-systemrunsbetweentwodifferentbuildings,asingleARSenvelopingthespectraassociatedwithallsupportpointsisused.USARRevision03'A-27aApril1989 NineMilePointUni't2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.3-6.46.56.6AppendixesCHAPTER77.17'7'7'7.57.67'AppendixesCHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.3,9.49.5AppendixesTitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergency'CoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components6A.through6CINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)-'System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7A,7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9CVolume131313131314,.15151515151515151516161616161616'.16'16,1717I1717:181920,2121,2223USARRevision0April1989 NineMilePointUnit2FSARTABLE'OFCONTENTS(Cont)SectionCHAPTER1010.110.210.310'TitleSTEAMANDPOWERCONVERSIONSYSTEMSummary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemVolume2323232411.111.211.311.411.5SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendixllACHAPTER12RADIATIONPROTECTIONCHAPTERllRADIOACTIVEWASTEMANAGEMENT242424252525252512.112.212.312.412.5CHAPTER1313.113.213.313.413.513.6AppendixesEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProcedures.IndustrialSecurity13A,13B252525262626.26262626'*262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)iv26 NineMilePointUnit2FSARAnalyticalmodelingandseismicanalysisaredescribedinSection3.7.3.8A.Staticanalysisandotherdynamicanalysesthatcontributetheremainingstressesinthecodestresscriteriaaredescribedinthefollowingsections.PipingengineeringanddesignspecificationsforUnit2allowtheuseofvarioustypesofbranchconnections,includingpipe-to-pipe.Unlessaspecificbranchconnectionisindica-tedinthespecificationoronthepipingdrawings,anunre-inforcedpipe-to-pipeconnectionisusedinthepipestressanalysis.Nofurtheractionisrequirediftheallowablestressesaremet.Iftheallowablestressesarenotmet,thenthepipingstresscalculationidentifiesthereinforce-mentof,thebranchconnectionthatisrequired.Forcaseswherethebranchlineisdecoupledfromtherunpiping,theproperstressintensificationfactorisusedintheanalysisofboththebranchlineandthemainrunpiping.Ifreinforcementformechanicalloadsisrequired,itissoidentifiedinthepipingstresscalculationanddrawings.Reinforcementrequirementsformechanicalloads,identifiedbythepipestresscalculations,areincorporatedonthepipingdrawings.PressurereinforcementcalculationsrequiredbyASMEIII,paragraphNB-3643,andANSIB31.1,paragraph104.3,areperformedbythepipingfabricator,andadditionalreinforcement,ifrequired,isidentifiedandaddedtothefabricatedpipe.3.9.1.5.1AStaticAnalysisThestaticequationofequilibriumfortheidealizedsystemmaybewritteninmatrixform,asfollows:KU=P-Q(3.9A-1)Where:K=StiffnessmatrixforassembledsystemU=NodaldisplacementvectorExternalforces,weights,etcEquivalentthermalforcesCross-sectionarea0E=Young'sModulus~<=ThermalexpansioncoefficientT=Averagewalltemperatureless70'FinstallationtemperatureUSARRevision03.9A-3April1989 NineMilePointUnit2FSAR=CoordinatealongpipeaxisL=LengthofpipeTheunknownnodaldisplacementsareobtainedfromtheNUPIPEcomputerprogrambysolvingthisequationusingtheGaussianmethod.Thenodaldisplacementsarethenappliedtotheindividualmembers,andmemberstiffnessesareusedtofindinternalforces.Thenodaldisplacementsatsupportlocationscanbeusedalongwiththesupportstiffnesstodeterminesupportreactions.DeadLoadsWeiht,PressureandLiveLoadsInNUPIPE,theeffectofpressureiscalculatedsimultaneouslywiththedeadweightcase.Theanalysisfordeadweightassumesallflexiblerestraints,suchasspringhangers,toberigid.Ifapipehasdifferentcontents(medium)andthereforedifferentweightsinvariousflowUSARRevision03.9A-3aApril1989 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKUSARRevision03.9A-3bApril1989 NineMilePointUnit2FSARmodes,thisistakenintoconsideration.OtherdetailsarediscussedinSection3.7.3.8.3A.Liveloadsareconsiderediftheyareexpectedtoconstituteasignificantcomponentofthetotalmechanicalload.ThefillingofmainsteamlineswithwaterduringvesselfloodingandalternateshutdowneventsisindicatedonthemainsteamthermaltransientsandconsideredinpipestressanalysisinaccordancewithNB-3600.Springhangersaredesignedtocarrythefullwater-filledpipingloadduringhydrotest.AdditionaldeadweightstressasaresultoffillingthepipingwithwaterisconsideredintheNB-3600analysisofthesystem.Themainsteamsafetyreliefvalve(S/RV)dischargepipinghasbeendesignedandqualifiedforthesteamhammerloadduetosteamblow'down.TheresultsoftheBWROwners'roupSafetyReliefValveTestProgram,inwhichUnit2hasbeenaparticipant,showthatthemeasuredspringandsupportresponsewassignificantlylessforwaterthansteam.Thetestreport,asdocumentedinNEDE-24988-P,statedthat"themaximumpiperesponseduetoliquiddischargewasgenerallylessthan30%ofthatduetosteamdischarge."ThetestprogramwasestablishedtomeasuretheS/RVdischargeline(S/RVDL)responseforalternateshutdowncoolingconditionsandtocomparetheseloadswithsteamloads.Additionaldeadweightstressresultingfromwater-filledmainsteamsafetyreliefisconsideredintheND-3600analysisofthemainsteamreliefvalvelines.InitialDislacementsAnchorMovementsNUPIPEpermitscalculationofthethermalinitialsupportdisplacementscombinedwiththethermalresponseduetotheaveragepipewalltemperaturechange.Earthquakeanchormovementsareconsidered(Section3.7.3.8.3A).InASMESafetyClass1analysistheloadsduetoOBEanchormovementsarecombinedwiththeOBEinertialoadsviaabsolutesummation.InASMESafetyClass2and3analysisthecodepermitstheirexclusionfromoccasionalloadsiftheyareincludedwiththethermalexpansionloads.ThermalLoadsApipingsystemmayexperiencevariousoperatingmodes.Alloperatingmodesaremodeledasfollows:Portionsofpipingwithflowingmediumhavethetemperatureofthemedium,whileinactivebrancheshaveambienttemperature.Nonuniformtemperaturedistributionsalongthepipenearbranchconnectionsofactiveandinactivelegsareconsidered.USARRevision03.9A-4April1989 NineMilePointUnit2FSARInSafetyClass1analysis,stressesduedistributionacrossthethicknessofthegeometricandmaterialdiscontinuitiestransientsmustbeconsidered.TheseareASMESectionIII,SubarticleNB-3600,by:totemperaturepipewallandduringthermalrepresentedinE~hT,andE(~T-cx12'b(aabb((3.9A-2)Basedongeometry,fluidtype,transients,environmentaldata:insulation,thermal~hT,~AT,andE~Ta-~T12ababb(3.9A-3)areobtainedfromtheHTLOADprogram(Appendix3A),orhandcalculations.USARRevision03.9A-4aApril1989 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKUSARRevision03.9A-4bApril1989 NineMilePointUnit2FSAR3.9.1.5.2AOccasionalDynamicLoadsExcludingSeismicandHydrodynamicInertiaLoadsOccasionalloadsarealsomatrixequationofmotion:analyzedwithNUPIPE.IntheMU+CU+KU=F(t)(3.9A-4)Where:M=MassmatrixC=DampingmatrixK=StiffnessmatrixU=DisplacementvectortheforcingfunctionF(t)isappliedasasetofforcetimehistories,oneforeachmassdegree-of-freedomthatexperiencesadynamicload.FluidTransientsFluidtransientsareconsideredinthefollowingsystems:1.Mainsteamandmainsteambypasssystems.2.Mainsteamsafety/reliefvalve(SRV)dischargesystem.3.Moistureseparator/reheatersafetyreliefsystem.4.Feedwatersystem.5.Emergencycorecoolingsystem(ECCS),includingECCSpressurereliefvalvedischargepiping.6.Servicewatersyst:em.7.Residualheatremovalsystem.8.Reactorcoreisolationcoolingsystem.9.Reactorwatercleanupsystem.10.Standbyliquidcontrolsystem.11.Controlroddrivesystem.Amendment233.9A-SDecember1985 NineMilePointUnit2FSARThecomputerprograms(Appendix3A)usedtocalculatetheseforcetimehistoriesduetowaterhammer,steamhammer,andpipewithairtrappedinwaterlines,areWATHAM,STEHAM,andWATAIR,respectively.JetIminementTheeffectsofdirectjetimpingementonpipingareevaluatedafterallotherpipinganalysesarecompletedandtargetsfromallpostulatedbreakshavebeenidentified.Amendment193'A-5aMay1985 NineMilePointUnit2FSAR3.9.3,.3ADesignandInstallationDetailsforMountingofPressure-ReliefDevicesPressure-relievingdevicesforASMESafetyClass1and2systemcomponentsare:1.Mainsteamsafety/reliefvalves(SRV).2.SRVsforprotectingresidualheatremoval(RHR)systemheatexchangers.ThedesignandinstallationofmainsteamSRVsisdescribedinSection3.9.3.3B.4ThedesignandinstallationofSRVsforprotectingtheRHRsystemheatexchangers(Section5.4.7.2.3)isinaccordancewithASMESectionIII,ArticleNC-7000,andRegulatoryGuide1.67.PipingtoandfromSRVsisdesignedinaccordancewithASMESectionIII,ParagraphNC-3677.TheSTEHAMcomputerprogram(Appendix3A)isusedtocalculatefluidtransientforcesineachpipingsegment(straightpipepiecebetweentwoelbows,anelbowandatee,oranelbowandaterminalend)downstreamoftheSRVs.'conservativelylowvalueofvalveopeningtimeisusedinthiscalculation.Waterslugsinpipesegmentsendinginthesuppressionpoolaretakenintoaccount.DynamicstressesinthepipingarecomputedbytimehistoryintegrationortheequivalentstaticmethodsusingtheNUPIPEcomputerprogram(Appendix3A).Thesestressesarecombinedwiththoseduetoothermechanicalloads,inaccordancewithloadcombinationsdescribedinSection3.9.3.1A.BothSRVsprotectingaheatexchangerareassumedtodischargeconcurrently.Theseloadsmeetdesignallowablesprovidedbythevendor.3.9.3.4AComponentSupportsExpansionanchorbolts,usedinsupportingthemechanicalcomponentsfromconcretestructures,aredrilled-inwedge-typeuniformholeanchors.Drilled-inbearing-typeflaredholeanchorsarealsousedinsupportingthemechanicalcomponentsfromconcretestructures.Drilled-inwedge-type,uniformholeexpansionanchorsaredesignedforaminimumsafetyfactoroffour,asdeterminedbytheultimateloadtestsperformedbythemanufacturer.Thesettingtorqueisdeterminedfromin-situtests.USARRevision03.9A-23April1989 NineMilePointUnit2FSARDrilled-inbearing-type,flaredholeanchorsaredesignedforaminimumsafetyfactorofthree,asdeterminedbyfieldtesting.Theloadsaretransferredintoconcretebydirectbearingagainstconcrete.Theboltmaterialiscapableofreachingfullductilitypriortofailure.Duetothesereasons,theanchorsaffordgreaterreliability,andalowersafetyfactori'sjustified.Thedesign,procurement,andinstallationofbuildingsteelcomplywithrequirementsoftheAISCspecificationforthedesign,fabrication,anderectionofstructuralsteelforbuildings,asdescribedinSections3.8.4.2and3.8.4.6.3.TheexaminationandinspectionofbuildingsteelcomplywiththerequirementsofNRCRegulatoryGuide1.94,asdescribedinTable1.8-1.3.9.3.4.1APipeSupportsThepipesupportdesigns,usingbaseplatesandconcrete.expansionanchorbolts,areperformedusingtheflexibilitycriteriaofNRCIEBulletin79-02beforetheyarereleasedforfabrication.Verificationofas-builtconditionsinaccordancewithNRCIEBulletin79-14is.describedinSection3.7.3.8.1A.ThebasesfordesignandconstructionofASMEandnon-ASMEpipingsupportsaregiveninTable3.9A-16.USARRevision03.9A-23aApril1989 NineMilePointUnit2FSARTABLE3.9A-14LOADCONDITIONSFORPIPESUPPORTSLoadConditionNumberPlantConditionNormalLoadsPrimarysustainedDLD~Bct1tSoAllowableStressASMEIZZ(1974,includingSummer1974Addenda),SubsectionNF;andSubsectionNA,AppXVIliArticleXVZI-2000UpsetUpsetPrimarysustainedandoccasionalassociatedwithupsetAllprimaryandsecondaryDL+SRSS(OBEIgOCCU)DL+THER+SRSS(OBEIgOCCU)EmergencyFaultedPrimarysustainedandoccasionalassociatedwithemergencyPrimarysustainedandoccasionalassociatedwithfaultedDL+SRSS(OBEIiOCCE)DL+SRSS(SSEIgOCCF)ASMEIII(1974,includingSummer1974Addenda),SubsectionNA,App.XVZI,-ArticleXVII-2110ASMEIIZ(1974,includingSummer1974Addenda)>App.FiParagraphF-1370KEY:DLOBEIOBETOCC(UiEiF)SSETHER*USARRevision0=Deadload=Operatingbasisearthquakeinertialoadofpiping=Operatingbasisearthquaketotal,i.e.,theabsolutesumoftheamplitudesofOBEinertialoadandloadduetoOBEanchormovements=Primaryoccasionalmechanicaloperatingloadsassociatedwithupset,emergency,andfaultedoperatingconditions,respectively,butexcludingearthquakeloads.Occasionalloadsmaybevibratoryornonvibratoryforloadcombinationpurposes.Theyarecombinedwitheachotherandwithotherloadtypesinthesamewayasintheassociatedpipinganalysis.(Seenotestoloadcombinationsforpiping,Table3.9A-2).Themaximumandtheminimumresponsefromeachtimehistoryisusedwiththeassociatedsigninthecombination.=Safeshutdownearthquakeinertialoadofpiping=Thermalload;asecondaryloadTHER1=Selectingthethreemomentsfromthatthermalloadwhosethreemomentsrepresentthemaximumsquarerootofthesumofthesquaresofthemoments.Theforcesselectedarethe-most(+)ofeachforcecomponentalongwithitspropersign(eachforcecomponentchosenmaycomefromadifferentthermalload).THER2=SameasforTHER1,exceptthatthemost(-)ofeachforcecomponentwithsignsischosen.THER3=Forcesandmomentsarethoseforthenormaloperatingcondition.*Forfeedwaterpiping,includesapplicablethermalstratificationload.1of1April1989

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER77.17'7'7'7.57.67~7AppendixesCHAPTER8TitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components6A.through6CINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7A,7BELECTRICPOWERVolume1313131313141515151515151515151616161616168.18.28.3Appendix8AIntroductionOffsitePowerSystemOnsitePowerSystem16,16'16,1717ICHAPTER9,AUXILIARYSYSTEMS179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17,181920g2121,2223IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER10TitleSTEAMANDPOWERCONVERSIONSYSTEMVolume2310.110.210.310.4CHAPTER11Summary.DescriptionTurbineGeneratorMainSteamSupplySyst:emOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT23232411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525CHAPTER12RADIATIONPROTECTION2512.112.212.312.412.5EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARAPPENDIX3ACOMPUTERPROGRAMSFORDYNAMICANDSTATICANALYSISOFCATEGORYISTRUCTURES,EQUIPMENT,ANDCOMPONENTSTABLEOFCONTENTSSectionINTRODUCTIONTitlePacae3A-13A~13A.l.l3A.1.23A.1.3SHELI1GeneralDescriptionProgramVerificationReferences3A.1-13A.1-13A.l-l3A.1-33A.23A.2.13A.2.23A.2.33A.33A.3.13A.3.23A.2.,3ASAASGeneralDescriptionProgramVerificationReferencesTAC2DGeneralDescriptionProgramVerificationRef'erences3A.2-13A.2-13A.2-13A.2-43A.3-13A.3-13A.3-13A.3-53A.43A.4.'13A.4.23A.4.33A.53A.5.13A.5.23A.5.33A.63A.6.13A.6.23A.6.33A.73A.7.13A.7.23A.83A.8.13A.8.23A.8.3Amendment27MAT6GeneralDescriptionProgramVerificationReferencesSTRUDLIIandSTRUDL-SWGeneralDescriptionProgramVerificationReferencesTime'istory(TIMHIS6)ProgramGeneralDescriptionProgramVerificationReferencesDELETEDDELETEDDELETEDDINASAWGeneralDescriptionProgramVerificationReferences3A-i3A.4-13A.4-13A.4-13A~4-23A.5-13A.5-13A.5-13A.5-23A.6-13A.6-13A.6-13A.6-23A.7-13A.7-13A.7-1.3A.8-13A.8-13A.8-13A.8-3July198627 NineNilePointUnit2FSARSection3A.93AF9.13A.9.23A.9.33A.103A.10.13A.10.23A.10.33A.113A.11.13A.11.23A.123A.12.1,3A.12.23A.12.33A.133A~13.13A.13.23A.13.3APPENDIX3ATABLEOFCONTENTS(Cont)TitleLIMITAIIGeneralDescriptionProgramVerificationReferencesLIMITAIIIGeneralDescriptionProgramVerificationReferencesSTARDYNEGeneralDescriptionProgramVerificationSSLAMGeneralDescriptionProgramVerificationReferencesSSLOADGeneralDescriptionProgramVerificationReferencesPacae3A.9-13A.9-13A.9-43A.9-53A.10-13A.10-13A.10-23A.10-33A.ll-l3A.ll-l3A.ll-l3A.12-13A.12-13A.12-13A.12-23A.13-13A.13-13A~13-13A:13-23A.143A.14.13A.14.23A.14.33A.14.4MISSILEGeneralDescriptionHighTrajectoryVerificationLowTrajectoryVerificationReferences3A.3A.3A.3A.3A~14-114-114-114-214-33A.153A.15.13A.15.23A.15~33A.163A.16.13A;16.2,3A.16'3A.173A.17.13A.17.23A.17.3Amendment19NUPIPEGeneralDescriptionProgramVerificationReferencesDELETEDDELETEDDELETEDDELETEDHTLOADGeneralDescriptionProgramVerificationReferences3A-ii3A.15-13A.15-13A.15-13A.15-23A.16-13A.16-13A.16-1.3A.16-23A.17-13A.17-13A.17-23A.17-3May1985 N.'n~NilePointUnit2FSAP.APPENDIX.3ATABLEOFCONTENTS(Cont)Section3A.183A.18.13A.18.23A.18.33A.19"3A.19.13A.19.23A.203A.20F13A.20.23A.20.3.3A.213A.21.13A21.23A.21.3JA.d23~.22.13.i.22.23A.22.3TitleGHOSH-WILSONGeneralDescriptionProgramVerificationReferencesPSPECTRAGeneralDescriptionProgramVerificationSTEHAMGeneralDescriptionProgramVerificationReferencesWATHAMGeneralDescriptionProgramVerificationReferencesPITRUSTGeneralDescriptionProgramVerificationReferences~Pae3A.'~.8-13h1;3-)3A.18-13A.18-?3A.19-13A.19-13A.19-13A.20"13A.20"13A.20-13A.20.-23A.21-13A.21-13A.21-i3A.21-z3A.22-13A.22-13A.22-13A.22-23A.233A.23.13A~23.23A.23.33A.243A.24.13A.24.23A.24.:93A.253A.25.13A.25.23A.263A.26.13A.26.23A.26.3PILUGGeneralDescriptionProgramVerificationReferencesWATAIRGeneralDescriptionProgramVerificationReferencesANSYSGeneralDescriptionProgramVerificationCWI(ContainmentWallLoading)GeneralDescriptionPr'ogramVerificationReferences3A.23-13A.23-13A.23-13A.23-23A.24-13A.24-13A.24-13A.24-23A.25-13A.25-13A.25-23A.26-13A.26-13A.26-13n,262 NineMilePointUnit2FSARAPPENDIX3A'ABLEOFCONTENTS(Cont)23.Section3A.273A.27.13A.27.23A.27.33A.283A.28.13A.28.23A.28.33A.28.43A.293A.303A.30.13A.30.23A.30.33A.313A.31.13A.31.23A.31.33A~323A.32.13A.32.23A.333A.33.13A.33.23A.33.3TitleLUGSTRGeneralDescriptionProgramVerificationReferencesComputerProgramsforStructuralResponsestoHydrodynamicLoading(TRANFUNANDINVTRAN)IntroductionTRANFUNINVTRANReferencesNASTRANBIJLAARD:VesselPenetrationAnalysisGeneralDescriptionProgramVerificationReferencesSLOSH:SimplifiedTankSloshingAnalysisGeneralDescriptionProgramVerificationReferencesSNUFFE:SupplementtoNUPIPEforFatigueEvaluationGeneralDescriptionProgramVerificationPITRIFEGeneralDescriptionProgramVerificationReferencesPacae3A.27-13A.27-13A.27-13A.27-23A.28-13A.28"13A.28-13A.28-13A.28-33A.29-13A.30-13A.30-13A.30-13A.30-23A~31-13A.31-13A.31-13A.31-23A.32-13A.32-13A.32-13A.33-13A.33-13A.33-13A.33-2Amendment233A-ivDecember1985 NineMilePointUnit2FSAR3A.15NUPIPE3A.15.1GeneralDescriptionNUPIPEwasdevelopedbytheNuclearServicesCorporationandisfullydocumented.'heSWECversionofNUPIPEdiffersslightlyfromthepublicdomainprogramNUPIPEinthepost-processingoftheanalyticalresults.NUPIPEperformsalinearelasticanalysisofthree-dimensionalpipingsystemssubjectedtothermal,static,anddynamicloads.Itutilizesthefiniteelementmethodofanalysiswithspecialfeaturesincorporatedtoaccommodatespecificrequirementsinpipinganalysis.Inaddition,itchecksanalyticalconformancetoASMESectionIIIandANSIB31.1.Thisprogramacceptsthecompletegeometricandphysicaldescriptionofthepipingsystem,providesacompleteerrorandcoordinatecheckfortheinputs,andcomputesinternalforcesandmoments,supportandequipmentreactions,anddisplacementsandstressvaluesforavarietyofloadingcases.3A.15.2ProgramVerificationNUPIPEhasbeenverifiedwithADLPIPEorthermal,weight,andresponsespectrumseismicanalyses.TheresultsfrombothprogramsarepresentedinTables3A.15-1through3A.15-7.ThemodelusedforthiscomparisonispresentedonFigure3A.15-1.ThecomparisonisalsomadewithASMEBenchmarksolutionforforcetimehistorydynamicresponse'.ThemodelusedforthiscomparisonisshownonFigure3A.15-2.TheresultsforcomparisonsarepresentedintheformofplotsonFigure3A.15-2.ThenaturalfrequenciesaregiveninTable3A.15-8.TheSafetyClass1pipingstresscomputationconformswiththehandcalculations.ThemodelusedisshownonFigure3A.15-3.TheresultsaretabulatedinTables3A.15-9and3A.15-10.3A.15-1 NineMilePointUnit2FSAR3A.'15.3References1.ArthurD.Iittle,Inc.ADLPIPE:Static,Dynamic,ThermalPipeStressAnalysis.2.AmericanSocietyofMechanicalEngineers.PressureVesselandPiping;1972ComputerProgramsVerification.ProblemNo.5.3A.15-2 NineMilePointUnit2FSARAPPENDIX3BTABLEOFCONTENTSSection3B.l3B.23B.33B.3.13B.3.23B.3.33B.3.43B.3.53B.3.63B~3'3B.4TitleDESIGNBASESDESIGNFEATURESDESIGNEVALUATIONElevation175ft0in.215ft0in.Elevation215ft0in.240ft0in.Elevation240ft0in.261ft0in.Elevation261ft0in.289ft0in.Elevation289ft0in.306ft6.in.Elevation306ft6in.328ft10in.Elevation328ft10inREFERENCEStoElevationtoElevationtoElevationtoElevationtoElevationtoElevationandAbovePacae3B-13B-33B-53B-53B-6.3B-73B-83B-9.3B-103B-103B-llUSARRevision03B-iApril1989 NineMilePoint'nit2FSARAPPENDIX3BLISTOFTABLESTableNumberTitle3B-13B-23B-33B-43B-53B-63B-7HIGHENERGYLINEBREAKSANALYZEDINTHEREACTORBUIIDINGHIGHENERGYLINEBREAKSANALYZEDINTHEMAINSTEAMTUNNELSUBCOMPARTMENTNODALDESCRIPTION-HIGHENERGYLINEBREAK"ANALYSISINREACTORBUILDINGSUBCOMPARTMENT,NODALDESCRIPTION-MAINSTEAMTUNNELHIGHENERGYLINEBREAK'ANALYSISSUBCOMPARTMENTVENTPATHDESCRIPTIONREACTOR,BUILDINGHIGHENERGYLINEBREAKANALYSIS(4-NODEMODEL)SUBCOMPARTMENTVENTPATHDESCRIPTIONREACTORBUILDINGHIGHENERGYLINEBREAKANALYSIS(33-NODEMODEL)VENTPATHDESCRIPTION-MAINSTEAMTUNNEIHIGHENERGYLINEBREAKANALYSIS-TWO-PHASEBREAKINMST-33B-83B-93B-103B-113B-12VENTPATHDESCRIPTION-MAINSTEAMTUNNELHIGHENERGYLINEBREAKANALYSIS-TWO-PHASEBREAKINMST>>5MASSANDENERGYRELEASEFOR4-INRCICDERINVOLUME175-1-BREAKNO.19MASS,ANDENERGYRELEASEFOR4-INRCICDERINVOLUME175-2-BREAKNO.20MASSANDENERGYRELEASEFOR8-INRWCUDERINVOLUMES215-1AND215-5BREAKNO.16AND17MASSANDENERGYRELEASEFOR4-INRWCUDERINVOLUME215-9-BREAKNO.15 NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHEHTVENTPATHDESCRIPTION:HIGH-ENERGYLIKEBREAKANALYSISINTHEREACTORBUILDING(45NODEHOOEL)VentPathNumberFromVolunaNurberToVoluneNumberHeadLossCoefficientsInertiaVentFactorAreaL/A(1)Turning(ft2)(1/ft)ContractionExpansionObstructionLossFrictionSharpEdgeLossTotal1175-'I175-2(a)2175-1175-9(a)3175-2175-3(a)4175-2175-3(b)5175-2215-1175-2175-1175-9175-1175-3175-2175-3175-2215-1175-225.8825.8810.0010.0010.0010.0010.0010.001.0471.0470.3270.3270.2580.2580.3660.3660.3660.3662.6482.6480.49320.47150.45170.46460.45170'646O.C7730.49820.88910.97290.86350.81610.86350.81610.993D0.91130.2000.2000.33680.34450.15680.15460~15680.15460.02600.02600.03470.03470.03470.03470.09200.09200.6310.6311.4111.4111.7451.8151.50714701F5071.4701.7621.7026'175-3175-4175-4175-321.0021.000.2150.2150'240.2240.8981.1221.5841.8087175.4175-5175-5175-4242.86242.860.0150.0150.2000.2000.9941.1941.8472.0478175-4175-6175-6175-4265.09265.090~0140.0140.2000.2000.9921.1921.8402.0409175-4175-7'175-7175-4241.26241.260.0140.0140.2DO0.2000.9941.1941.8482.04810175-4175-811175-4175-9175-8175-4175-9175-4240.31240.31140.18140.180.0150.0150.0200.0200.2000.2000.2000.2000.99C1.1941.8482.0480.8141.0141.6981.89812175-4215-8215-8175-462.4262.420.0390.0390.49640.49620.98490.98560.2000.2001.15481~15490'0660.00662.8432.843USARRevision01of5April1989

NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHEHTVEHTPATHDESCRIPTION:HIGH-ENERGYLINEBREAKANALYSISIHTHEREACTORBUILDIHG(45NOOENOOEL)VentPathNumberFromVoluneNunberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)ContractionExpansionHeadLossCoefficientsSharp(1)TurningEdgeObstructionLossFrictionLossTotal25215-6215-8215-8215-621.00N/A0.321N/A0.36980.96553.424(c)0.90100.00985.670(c)2627215-8215-9215-8215-10215-9215-8215-10215-8H/A14.33N/A14.33N/A0.313N/A0.313(c)3.424(c)3.4242.0872.185(c)5.511(c)5.60928215-8240-5240-5215-852.0352.030.0450.0450.49690.49700.98780.98760.2000.2001.14191.14180.00720.00722.8342.83429215-9215-10215-10215-915.7515.750.4140.4140.43790.43790.76690.76690.05870.05870.03660.03661.3001.30030240.1240-2240-2240-1101.05101.050.0640.0640.8350.8350.5570.55731240-1261-1261-1240-128.3828.380.3360.3360.2000.2000.6520.8520.3790.57932240-3240-4240-4240-337.8337.830.1100.1100.2000.2000.5040.7041.0931.29333240-3240-5240-5240-316.38N/A0.234N/A3.424(c)1.6885.112(c)34240-3240-3261-3261-339.6839.680.1430.1430.2000.2000.8671.6171.0671.8173536240-5240-7240-5240-8240-7240-5240-8240-52.2992.2992.2992.2990.0910.0910.0930.0930.49930.49620.49930.49580.98470.99710.98340.99711.26721.27111.26631.27070.00330.00330.00330.00332.7552.7682.7522.767USARRevision03of5April1989 0 NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHEHTVENTPATHDESCRIPTION:HIGH-EHERGYLINEBREAKANALYSISIHTHEREACTORBUILDING(45NOOEHOOEL)VentPathNumberFromVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)HeadLossCoefficientsSharp(1)TurningEdgeContractionExpansionObstructionLossFrictionLossTotal373839240-5261-4240.6306-4261-1261-2261-4240-5306-4240.6261-2261-167.4567.4521.1521.1533.2633.260.0290.0291.6741.6740.1690.1699600.49670.98680.98400.1880.1880.2000.2001.16151.16060.7680.1810.00640.00642.8392.8361.1461.9140.6630.8440.9381.1381.2461.44640261-1261-4261-4261-115.93H/A0.213N/A3.424(c)1.7655~189(c)414243261-2289-1261-3261-5261-4289-3289-'I261-2261-5261-3289-3261-426.3026.3049.9549.95503.31503.310.2930.2930.2270.2270.0100.0100.48020.47960.91990.92240.2000.2000.2000.2001'6071.06140.00230.00230.7750.9750.8971.0970.2200.4200.1980.3982.4632.466261-5289-2289-2261-565.7565.750.1740.1740.2000.2000'820.4820.2350.435454647289.1306-1289-2306-4289-3306-5289-3306-5306-1289-1306-4289-2306-5289-3306-5289-340.8240.8236.8636.862079.02079.02590.02590.00.1740.1740.1690.1690.0100.0100.0100.0100.31660.46760.41560.39100.39480.36430.87460.40100.61160.69070.53070.62350.2000.2000.4000.4000.75110.61820.93170.96050.84590.88580.01080.01080.00150~00150.00130.00131.1680.5201.3680.7202.3531.8981.9602.0441.7731.875USARRevision04of5April1989

NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHENTVENTPATHDESCRIPTION:HIGH-ENERGYLINEBREAKANALYSISINTHEREACTORBUILDING(45NODEMODEL)VentPathNumberFromVolcanoHumberToVoluneNunberInertiaVentFactorAreaL/A(ft2)(1/ft)ContractionExpansionHeadLossCoefficientsSharp(1)TurningEdgeObstructionLossFrictionLossTotal49306.1306-2245.990.014306.2306-1245.990.0142.3112.3112.3902.39050306-1328-28.9560.4010.49690.9731328-2306-18.9560.4010.49320.98750~16450.16510.02720.02721.662'I.67351306-2306-3136.800.035306.3"306-2136.800.0351.6451.6451.9591.95952306.3306-492.480.445306-43D6.392.480.4450.3240.3240.3900.39053306-5328-1508.580.0100.47330.7057328-1306-5508.580.0100.42000.89621.05041.11510.00230.002322322.4345C328-1353-1502.880.0100.42090.9554353-1328-1502.M0.010O.C8870.70871.15221.06930.00230.00232.5312.269(1):TheobstructionLossincludeslossesfromagrill,grating,wiremeshdoor,and/orventcurtains.TheselossesaredescribedinSection38.2:DesignFeatures.(a):Thisventpathisablowoutpanel.Thevaluesinthistableareforafterthepanelhasfullyopened(ifitisnotassumedtofoilclosedunderthesingle-failurecriteria).Theblowoutpanelisfullyopen0.3secondsaftera0.5psidforceisappliedacrossit.Thepanelopensinthedirectionshowninthetoplistingfortheventpath.(b):ThisJunctionisusedonlyforBreakNumbers6and9.ThisisexplainedinTable38-1:High-EnergyLineBreaksAnalyzedintheReactorBuildingandSection38.3.2:Elevation215'0<<toElevation240'0<<.(c):ThisJ~tionhasventcurtains.Thecurtainallo~sflowinonLyonedirection.VentcurtainsarediscussedinSection3B.2:DesignFeatures,Section3B.3.2:Elevation215~0<<toElevation240'0",Section3B.3.3:Elevation240'0<<toElevation261'0",andSection38.3.4:Elevation261'0<<toElevation289'0<<.NOTE:thehonogeneousequfLIbrfunmodel(HEN)forchokedflowisusedforallbreeksandnodalizations.Appendix6B:THREEDSubncompartmentAnalyticalNodalgivesadescriptionoftheHEHusedintheSWECcomputercodeTHREED.USARRevision05of5April1989 0 NineHitePointUnit2FSARTABLE3B-6SUBCOHPARTNENTVENTPATHDESCRIPTIOH:HIGH-ENERGYLINEBREAKANALYSISIHTHEREACTORBUILDIHG(46HODENODEL)VentPathNumberFromVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)ContractionExpansionHeadLossCoefficientsSharp(1)TurningEdgeObstructionLossFrictionLossTotal175-1175.2(a)2175-1175-9(a)3175-2175-3175.2175-1175-9'175-1175-3175-225.8825.8810.0010.0010.0010.000.3270.3270.2580.2580.3660.3660.49320.47150.45170.46460.88910.97290.86350.81610.33680.34450.15680.15460.02600.02600.03470.03470.6310.6311.4111.4111.7451.8151.5071.470175-2215-1215-1175-21.0471.0472.6482.6480.47730.49820.99300.91130.2000.2000.09200.09201.7621.702175-3175-4'175-4175-5175-4175-3175-5175-421.0021.00242.86242.860.2150.2150.0150.0150.2240.2240.2000.2000.8981.1221.5841.8080.9941.1941.8472.047175-4175-6175-6175-4265.09265.090.0140~0140.2000.2000.9921.1921.8402.0401012175-4175-7175-4175-8175-4175.,9175-4215-8175-10215-3175.7175.4175-8175-4175-9175-4215.8175-4215-3175-10241.26241.26240.31240.31140.18140.1862.4262.4281.3081.300.0140.0140.0150.0150.0200.0200.0390.0390.1210.1210.49640.49620.98490.98560.2000.2000'000.2000.2000.2000.2000.2000.2000.2001.15481.15490.00660.00660.9941.1941.8482.0480.9941.1941.8482.0480.8141.0141.6981.8982.8432.8431.3371.5370.7630.963USARRevision01of6April1989

NineNilePointUnit2FSARTABLE38-6SUBCOHPARTNENTVENTPATHDESCRIPTION:HIGH-ENERGYLINEBREAKAHALYSISINTHEREACTORBUILOIHG(46NODEMODEL)VentPathNurherFromVoiuneNunberToVoiuneNumberVentArea(ft2)InertiaFactorL/A(1/ft)HeadLossCoefficientsSharp(1)TurningEdgeContractionExpansionObstructionLossFrictionLossTotal252627215-8215-9215-8215-10215;8215-8215-9215-8215-10215-8240-5240-5N/A14.33H/A14.3352.0352.03N/A0.313N/A0.3130.0450.0450.49690.49700.98780.9876(b)3.424(b)3.4240.2000.2001.14191.14180.00720.00722.0872.185(b)5.511(b)5.6092.8342.83428215-9215-10215-10215-915.7515.750.4140.4140.43790.43790.76690.76690.05870.05870.03660.03661.3001.30029240-1240-2240-2101.05240-1101.050.0640.0640.8350.8350.5570.5573031240-1261-1240-3240-4261-1240-1240-4240-328.3828.3837.8337.830.3360.3360.1100.1100.2000.2000.2000.2000.6520.8520.3790.5790.5040.7041'931'9332240-3240-5240-5240.316.38H/A0.234H/A3.424(b)1.6885.112(b)33240-3240-3261-3261-339.6839.680.1430.1430'000.2000.8671.6171.0671.81734240.5240-7240-7240-52.2992.2990.0910.0910.49930.49620.98470.99711.26721.27110.00330.00332.7552.76835240.5240-8240.8240-52.2992.2990.0930.0930.49930.49580.98340.99711.26631.27070.00330.00332.7522.76736240-5261-4261-4240-567.4567.450.0290.0290.49600.49670.98680.98400.1880.1881.16151.16060.00640.00642.8392.836USARRevision03of6April1989

NineNilePointUnit2FSARTABLE38-6SUBCONPARTHENTVENTPATHDESCRIPTION:HIGH-ENERGYLINEBREAKANALYSISINTHEREACTORBUILDING(46NODEHODEL)HeadLossCoefficientsVentPathNumberFramVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1)Turning(1/ft)ContractionExpansionObstructionLossSharpEdgeFrictionLossTotal37240.6306.4306-4240-621.1521.151.6741.6740.7680.1811.1461.9140.6630.84438261.1261-2261-2261-133.2633.260.1690.1690.2000.2000.9381.1381.2461.44639261-1261-4261-4261-115.93N/A0.213N/A3.424(b)1.7655.189(b)40261-2289.1289-1261-226.30.26.300.2930.2930.2000.2000.7750.9750.8971.09741261-3261-5261-4289.3261-5261-3289-3261-449.9549.95503.31503.310.2270.2270.0100.0100.48020.47960.91990.92240.2000.2001.06071.06140.00230.00230.2200.4200.1980.3982.4632.46643261-4289-3289-3261-4197.42197.420.0100.0100.49220.49200.96820.96921.20781.20800.00400.00402.6722.67344261-5289-2289-2261-565.7565.750.1740.1740.2000.2000.2820.4820.2350.43545289-1306-1306-1289-140.8240.820.1740.1740.2000.2001.1680.5201.3680.72046289.2306.4306-4289-236.8636.860.1690.1690.31660.46760.87460.40100.4000.4000.75110.61820.01080.01082.3531.89847289.3306.5306-5289-32079.02079.00.0100.0100.41560.39100.61160.69070.93170.96050.00150.00151.9602.04448289-3306-5306-5289-32590.02590.00.0100.0100.39480.36430.53070.62350.84590.88580.00130.00131.7731.875USARRevision04of6April1989 4 HineNilePointUnit2FSARTABLE38-6SUBCONPARTHENTVENTPATHDESCRIPTIOH:HIGH-ENERGYLINEBREAKANALYSISIHTHEREACTORBUILDING(46NODEHOOEL)VentPathNumberFromVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)HeadLossCoefficientsSharp(1)Turn>ngEdgeContractionExpansionObstructionLossFrictionLossTotal49289-3306-5306.5289.3202'6202.160.0100.0100.49180.48940.95810.96741.20221.20500.00390.00392.6562.6665051306-1306.2306-1328-2306-2306.1328-2306-1245.99245.997.1927.1920.0140.0140.4930.4930.49690.49320.97310.9S750.2000.2000.16450.16510.02720.02722.3112.3112.3902.3901.8621.8735253306-2306.3306-3306-4306-3306-2306-4306-3136.80136.8092.4892.480.0350.0350.4450.4451.6451.6451.9591.9590.3240.3240.3900.390306-5328-1328-1306-5508.58508.580.0100.0100.47330.42000.70570.89621.05041.11510.00230.002322322.43455328-'I353-1353-1328-1502.88502.880.0100.0100.42090.48870.95540.70871.15221.06930.00230.00232.5312.26956SC328190306-1306-1SC3281900.1700.17020.6520.650.50000.50001.00001.00000.26180.26181.7621.76257SC328190306-1306-1SC3281900.0490.04971.5171.510.50000.50001.00001.00000.58620.58622.0862.0865eSC32e190306-1306-1SC32819059SC328190328-2328-2SC32819060SC328190328-2328-2SC3281900.8630.8630.7180.7180.7180.7184.0984.0984.9154.9154.9154.9150.50000.50000.50000.50000.50000.50001.00001.00001.0000F00001F00001.00000.14580.14580.14580~14580~14580.14581.6461.6461.6461.6461.6461.646USARRevision05of6April1989

NineNilePointUnit2FSARTABLE38-6SUBCOHPARTHEHTVEHTPATHDESCRIPTION:HIGH-ENERGYLINEBREAKANALYSISIHTHEREACTORBUILDING(46NODEHODEL)VentPathNumberFromVoiuneNunberToVoluneHwherVentArea(ft2)InertiaFactorL/A(1/ft)ContractionHeadLossCoefficientsSharp(1)TurningEdgeExpansionObstructionLossFrictionLossTotal61SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001.00001.00000.35370.35371.8541.85462SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001F00001.00000.35370.35371.8541.85463SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001.00001.00000.35370.35371.8541.85464SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001.00001.00000.35370.35371.8541.854Thisnodalizationmodelisusedforthe6"RNCUbreaksinVoiunes328-2andSC328190~ThefiredeeperJunctionbetweenVolwes175-2and215-1isassumedtobeopenfortheentiretransient.(1):Theobstructionlossincludeslossesfromagrill,grating,wiremeshdoor,and/orventcurtains.TheselossesaredescribedinSection38.2:DesignFeatures.(a):Thisventpathisablowoutpanel.Thevaluesinthistableareforafterthepanelhasfullyopened.Theblowoutpanelisfullyopen0.3secondsaftera0.5psidforceisappliedacrossit.Thepanelopensinthedirectionshowninthetoplistingfortheventpath.(b):ThisJunctionhasventcurtains.Thecurtainallowsflowinonlyonedirection.VentcurtainsarediscussedinSection3B.2:DesignFeatures,Section38.3.2:Elevation215'OatoElevation240'0",Section38.3.3:Elevation240'0"toElevation261'0",andSection38.3.4:Elevation261'OwtoElevation289'0".NOTE:ThehomogeneousequiIibriunmodel(HEH)forchokedflowisusedforallbreaksandnodalizations.Appendix68:THREEDSubmcompartmentAnalyticalNodalgivesadescriptionoftheHEHusedintheSPECcomputercodeTHREEO.USARRevision06of6April1989

TO261-4FROM215-8TO261-3240-5GENERALAREA240-3TIPGUBlGLETO261-1240-7PENETRATIONAREA240-8PENETRATIONAREA240-1PIPECHASE240-2PENETRATIONAREA240"4PIPECHASEFROM215-1FROM215-2NOTES:sVENTCURTAINJUNCTION~COONWITNLOUVERsDIRECTIONOfVENTFLOWVOLUIIE2404ISSHOWNONSHEET4OFFIOURESSIFIGURE3B-2NODALI2ATIONDIAGRAM-REACTORBUILDINGHIGH-ENERGYLINEBREAKANALYSIS(4SNODEMODEL)SHEET3OF6NIAGARAMOHAWKPOWERCORPORATIONNINEMILEPOINT-UNIT2UPDATEDSAFETYANALYSISREPORTUSARREVISION0APRIL1989 4 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKAmendment183C-11bMarch1985 NineMilePointUnit2FSARreactororthatcouldincreasetheoffsiteradiationbeyondthelimitsof10CFR100.3C.2.9.2RPVSteamVentLine28)ThelocationsofpostulatedpipebreaksareshownonFigure3.6A-15.Themainsteam2-inventlinebranchesoffthemainsteamline(2MSS-026-43-1)at.el314ft10in.Itthenloopsitswayuptoel342ft8ll/16inanddropsverticallyintotheRPVhead.2828ITheMSSpiping,ifallowedtowhip,couldimpact,targetssuchasdrywellhead,vesseldome,insulationsupportstructure,mainsteamline2MSS-026-43-1,andrupturerestraint2RHS*PRR014.Sincethepipingisa2-indiameterline,theimpactingforcesofthepipingsystemarerelativelysmallandwillnotcausedetrimentalresultstothetargetsmentionedabove.Thepipewhipduetoabreakinthislinewillnotcauseanylossofstructuralintegritytothetargetsmentionedabove.ConclusionsUsingveryconservativeassumptionsandcriteria,nopostulatedfailureoftheMSSventlinecancausedamagethatcouldimpairtheabilitytosafelyshutdownthereactororthatcouldincreasetheoffsiteradiationeffectsbeyondthelimitsof10CFR100.3C.2.10MainSteamSafetyReliefValvePiping(SVV)asfsa/ThelocationofpipebreaksareshownonFigures3.6A-16and3.6A-17'hemainsteamsafetyreliefvalvepipingforeachofthe18SRVsconsistsofan8-inconnectionoffthemainsteamlinetotheSRVanda10-indischargelinefromtheSRVtothesuppressionpool.Thehigh-energyportionofthesystemisthe1-ftlengthfortheconnectionfrommainsteampipetothenormallyclosedSRV.TwobreaksarepostulatedforeachSRV;theyareterminalpoint,circumferentialbreaksforthe8-inconnection.Targetsfrompipewhiparethe12-inRHSlines.ImpactanalysisshowsfailureofSVVpipingcannotcauseadditionaldamagethatcouldimpairtheAmendment28I'C-12May1987 NineMilePointUnit2FSARTABLE'OFCONTENTS(Cont).Section5.35.4AppendixesCHAPTER6TitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESVolume131313136.16.26.36.46.56.6Appendixes6A.through6CEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77.17'7~37'7.57.67'AppendixesCHAPTER8INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7Ai7BELECTRICPOWER151515151616161616168.18.28.3Appendix8AIntroductionOffsitePowerSystemOnsitePowerSystem=-16,16'16,1717I~CHAPTER9AUXILIARYSYSTEMS179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17.181920,2121,2223USARRevision0April1989 NineNilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER10TitleSTEAMANDPOWERCONVERSIONSYSTEMVolume2310.110.210.310.4CHAPTERSummaryDescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT23232411.111.211.3~11.411.5SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendix11ACHAPTER12RADIATIONPROTECTION24242525252525,12.1-12.212.312.4.12.5EnsuringThat,OccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213'13.413.5.13.6AppendixesOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1Specific"Information,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARCHAPTER5LISTOFFIGURESFigureNumber5.l-la5.l-lb5.1-2a,b,c5.2-15.2-25.2-35.2-45.2-55.2-5a5.2-65.2-75.2-85.2-95.3-15.3-25.3-35.3-4TitleRATEDOPERATINGCONDITIONSOFTHEBOILINGWATERREACTORCOOLANTVOLUMESOFTHEBOILINGWATERREACTORNUCLEARBOILERSYSTEMSAFETYRELIEFVALVECAPACITYSIZINGTRANSIENT"MSIVCLOSUREWITHHIGHFLUXTRIP"SAFETYRELIEFVALVESCHEMATICELEVATIONSAFETYRELIEFVALVEANDSTEAMLINESCHEMATICNUCLEARBOILERSYSTEMPAIDSCHEMATICOFSAFETYRELIEFVALVEWITHAUXILIARYACTUATINGDEVICEABNORMALAMBIENTCONDITIONSFORACTUATORQUALIFICATIONTESTTYPICALBWRFLOWDIAGRAMCONDUCTIVITY'HgCHLORIDECONCENTRATIONOFAQUEOUSSOLUTIONSAT77F(25C)CALCULATEDLEAKRATEVSCRACKLENGTHASAFUNCTIONOFAPPLIEDHOOPSTRESSAXIALTHROUGHWALLCRACKLENGTHDATACORRELATIONBRACKETFORHOLDINGSURVEILLANCECAPSULEMINIMUMTEMPERATURESREQUIREDVERSUSREACTORPRESSUREPREDICTEDADJUSTMENTOFREFERENCETEMPERATURE"A"ASAFUNCTIONOFFLUENCEANDCOPPERCONTENTREACTORVESSELUSARRevision05-ixApril1989 NineMilePoint'Unit2FSARCHAPTER5LISTOFFIGURES(Cont)FigureNumber5.3-5TitleNOMINALREACTORVESSELWATERLEVELTRIPANDALARMELEVATIONSETTINGS5.4-1RECIRCULATIONSYSTEMELEVATIONANDISOMETRIC5.4-2athroughREACTORRECIRCULATIONSYSTEMP&ID5.4.265.4-35.4-45.4-55.4-65.4-75.4-8RECIRCULATIONPUMPHEAD,NPSH,FLOWANDEFFICIENCYCURVESOPERATINGPRINCIPLEOFJETPUMPCOREFLOODINGCAPABILITYOFRECIRCULATIONSYSTEMMAINSTEAMLINEFLOWRESTRICTORMAINSTEAMISOLATIONVALVECUTAWAYVIEWDELETED5.4-9athroughRCICSYSTEM5.4-915.4-105.4-10a5.4-10b5.4-115.4-12REACTORCOREISOLATIONCOOLANTSYSTEMPROCESSDIAGRAMRCICTURBINECHARACTERISTICCURVESSTEAMFLOWVS.POWERRCICTURBINECHARACTERISTICCURVESSTEAMFLOWVS.PRESSUREVESSELCOOLANTTEMPERATUREVERSUSTIME(TWOHEATEXCHANGERSAVAILABLE)VESSELCOOLANTTEMPERATUREVERSUSTIME(ONEHEATEXCHANGERAVAILABLE)5.4-13athroughRHRSYSTEM5.4-13gUSARRevision05-xApril1989 NineMilePointUnit2FSARCHAPTER5LISTOFFIGURES(Cont)FigureNumber5.4-145.4-15TitleRESIDUALHEATREMOVALSYSTEMPROCESSDIAGRAMANDDATARHRPUMPCHARACTERISTICCURVES5.4-16athroughREACTORWATERCLEANUPANDFILTER5.4-16fDEMINERALIZERSYSTEMPAID5.4-175.4-18REACTORWATERCLEANUPSYSTEMDELETEDUSARRevision05-xaApril1989 ,NineMilePoi.ntUnit2FSARTHISPAGEINTENTIONALlYBLANKAmendment75-xbDecember1983 NineMilePointUnit2FSAR(SeeSection3.9.6Afortheprogramforpumpsandvalves.)Subsequentinserviceinspectionswillbeperformedinaccordancewiththerequirementsof10CFR50.55a(g)asdescribedintheInserviceInspectionProgram.5.2.5ReactorCoolantPressureBoundaryandECCSLeakageDetectionSystem5.2.5.1LeakageDetectionMethodsThenuclearboilerleakdetectionsystem(LDS)consistsoftemperature,pressure,level,flow,airbornegaseousandparticulatefissionproductsensors,andprocessradiationsensorswithassociatedinstrumentationusedtoindicateandalarmleakagefromtheRCPB.TheLDSincertaincasesisusedtoinitiatesignalsusedforautomaticclosureofisolationvalvestoshutoffleakageexternaltothecontainment.ThesystemisassessedtobeinconformancewithRegulatoryGuide1.45.ThoseportionsofthesystemwhichaffectautomaticisolationofleakagearedesignedtoIEEE279-1971(refertoTable3.2-1).Abnormalleakagefromthefollowingsystemswithinthecontainmentandwithintheselectedareasoftheplantoutsidetheprimarycontainmentisdetected,indicated,alarmed,andincertaincases,isolated.1.Mainsteamlines.2.RWCUsystem.3.RHRsystem.45.RCICsystem.Feedwatersystem.6.HPCS.7.Coolantsystemswithinthecontainment.8.LPCS.9.RPV.10.Miscellaneoussystems.LeakdetectionmethodsusedtoobtainconformancewithRegulatoryGuide1.45forplantareasinsidetheprimarycontainmentdifferfromthoseforareaslocatedoutsidetheAmendment265.2-29May1986 NineMilePointUnit2FSARprimarycontainment.Theseareasareconsideredseparatelyinthefollowingsections.5.2.5.1.1DetectionofLeakageWithinthePrimaryContainmentTheprimarydetectionmethodsforsmallunidentifiedleakswithintheprimarycontainmentincludecontinuousmonitoringofdrywellfloordraintankfillrateandairbornegaseousandparticulateradioactivityincreases.(ThesensitivitiesoftheseprimarydetectionmethodsforunidentifiedleakagewithintheprimarycontainmentarelistedinTable5.2-8.)Thesevariablesarecontinuouslyindicatedand/orrecordedinthecontrolroom.Iftheunidentifiedleakageincreasestoatotalof5gpm,thedetectinginstrumentationchannel(s)willtripandactivateanalarminthemaincontrolroom.Thisdoesnotresultinacontainmentisolationsignal.Thesecondarydetectionmethods(i.e.,themonitoringofpressureandtemperatureoftheprimarycontainmentatmosphere)areusedtodetectgrossunidentifiedleakage.Highprimarycontainmentpressurewillalarmandtriptheisolationlogicwhichresultsinclosureofthecontainmentisolationvalves.Thedetectionofsmallidentifiedleakagewithintheprimarycontainmentisaccomplishedbycontinuousdrywellequipmentdraintankfillratemonitoring.Analarmwillbeactivated!inthemaincontrolroomwhentheleakratereaches25gpmaveragedovera24-hrperiod.Thedeterminationofthesourceofidentifiedleakagewithintheprimarycontainmentisaccomplishedbymonitoringthedrainlinestothedrywellequipmentdraintankfromvariouspotentialleakagesources.Theseincludereactorrecirculationpumpsealdrainflowandreactorvesselheadsealdrainlinepressure.Additionally,temperatureismonitoredintheSRVdischargelinestothesuppressionpooltodetectleakagethrougheachoftheSRVs.Allofthesemonitors,exceptthereactorrecirculationpumpsealdrainflowmonitor,continuouslyindicateand/orrecordinthecontrolroom.Allofthesemonitorstripandactivateanalarminthecontrolroomondetectionofleakagefrommonitoredcomponents.Excessiveleakageinsidetheprimarycontainment(e.g.,processlinebreakorLOCAwithinprimarycontainment)isdetectedbyhighprimarycontainmentpressure,lowreactorwaterlevelorhighsteamlineflow(forbreaksdownstreamUSARRevision05.2-30April1989 NineMilePointUnit2FSARoftheflowelements).Theinstrumentationchannelsforthesevariablestripwhenthemonitoredvariableexceedsapredeterminedlimittoactivateanalarmandtriptheisolationlogicwhichclosesappropriateisolationvalves(Table5.2-9).ThealarmsandindicationandisolationtripfunctionsinitiatedbytheLDSsaresummarizedinTables5.2-9and.5.2-10.5.2.5.1.2DetectionofLeakageExternaltothePrimaryContainment(WithinReactorBuilding)Thedetectionofleakagewithinthereactorbuilding(outsidetheprimarycontainment)isaccomplishedbydetectionofincreasesinreactorbuildingfloordrainsumpandreactorbuildingequipmentdraintankfilluptimeandpumpout,time(Section5.2.5.2.2).Thereactorbuildingfloordrainsumpmonitorswilldetectunidentifiedleakageincreasesandactivateanalarminthemaincontrolroom.Thereactorbuildingequipmentdraintankmonitorswilldetectidentifiedleakageincreasesandactivateanalarminthemaincontrolroomwhenleakageincreasesabovenormalbackgroundlevels.SeeSection5.2.5.2.2foradiscussionofthefuelpoollinerleakagedetectionmethod.5'.2.5.1.3DetectionofLeakageExternaltothePrimaryContainmentAreasoutsidetheprimarycontainmentthataremonitoredforprimarycoolantleakageare:equipmentareasintheauxiliarybays,themainsteamtunnel,andtheturbinebuildi'ng.Theprocesspipingforeachsystemtobemonitoredforleakageislocatedincompartmentsorroomsseparatefromothersystemswherefeasiblesothatleakagemaybedetectedbyareatemperatureindications.Theseareasaremonitoredbydualelementthermocouplesforsensinghighambienttemperatureinalltheseareasandhighdifferentialtemperaturebetweentheinletand"outletventilationductsinthemainsteamtunnel.Thetemperatureelementsarelocatedorshieldedsothattheyaresensitivetoairtemperatureonlyandnottoradiatedheatfromhotpipingorequipment.Increasesinambientand/ordifferentialtemperatureindicateleakageofreactorcoolantUSARRevision05.2-31April1989 NineMilePointUnit2FSAR23intothearea.Themonitorslocatedinthemainsteamtunnelandturbinebuildinghavesensitivitiessuitablefordetectionofincreasesinambientairtemperaturewhichareequivalenttoreactorcoolantleakageintothemonitoredareasof2Sgpmorless.Thetemperaturetripsetpointsareafunctionofroomsizeandthetypeofventilationprovided.Thesemonitorsprovidealarm,indication,andrecordinginthemaincontrolroom,and'riptheisolationlogictocloseselectedisolationvalves(e.g.,themainsteamtunnelmonitorsclosetheMSIVandmainsteamlinedrainisolationvalvesandothervalves[Table5.2-9]).23Theturbinebuildingtemperaturemonitorsalarmandindicateinthemaincontrolroomandtriptheisolationlogictoclosethemainsteamisolationandmainsteamlinedrainisolationvalveswhenleakageexceeds2Sgpm.Thesesensorsmonitorambienttemperatureintheenclosedspacebetweenthesteamtunneloutletandtheinlettothehighpressureturbine.2323Excess-leakageexternaltothecontainment(e.g.,processlinebreakoutsidecontainment.)isdetectedby.lowreactorwaterlevel,highprocesslineflow,highambienttemperatureinthepipingorequipmentareas,highdifferentialflow,andlowmaincondenservacuum.Thesemonitorsprovidealarmandindicationinthemaincontrolroomandtriptheisolationlogictocauseclosureofappropriatesystemisolationvalvesonindicationofexcessleakage(Table5.2-9).Setpointsforthehighambienttemperaturemonitorsinthepipingandequipmentareasofthereactorbuildingandauxiliarybaysarebasedonlimitingthemaximumenvironmentalconditionsoftheseareastowithintheenvironmentalqualificationcapabilitiesoftheapplicableequipment.5.2.5.1.4IntersystemLeakageMonitoringLeakagefromtheHPCS,LPCS,RCIC,andRHRsystemsoutsidecontainmentisdetectedbyacombinationofmethods,includinghighareatemperature,higharearadiation,highsumplevel,andreactorpressurevesselcondition(seeSection5.2.5.1~3).RadiationmonitorsareusedtodetectreactorcoolantleakageintocoolingwatersystemssupplyingtheRHRheatexchangersandtheRWCUnonregenerativeheatexchanger.Thesemonitoringchannelsarepartoftheprocessradiationmonitoringsystem.ProcessradiationmonitoringchannelsmonitorforleakageintoeachcommoncoolingwaterheaderdownstreamoftheRHRheatexchangersandtheRWCUAmendment235.2-32December1985 NineNilePointUnit2FSARTABLE5.2-1(Cont)CodeCaseNumber/RevisionApplicableRaJ'-""TitleTherequiredexposuretimesforlowhydrogenelectrodeswereadheredtoexceptfortheexposuretimeswereincreasedslightlyforsomesitewelding.ForelectrodeE70XX,theexposuretimewasincreasedform4to5hr,andforelectrodeE80XX,from2to4hr.'nthesecases,allcoveredelectrodescontinuedtobeissuedinheatedportablerodovens.TheincreasedexposuretimesarebasedonindustryusagedataandtestdatatomeettheintentofRegulatoryGuide1.85andCodeCase1644-9requirements.Amendment243bof8February1986

NineMilePointUnit2FSARTABLE5'-8LEAKDETECTIONMETHODS,ACCURACY,ANDSENSITIVITYLeakDetectionMethodDrywellfloordraintanklevelDrywellequipmentdraintanklevel4AirborneparticulatesGaseousradioactivity~Accurac1gpm1gpmSensitivit1gpm/hr1gpm/hr6.6-12uCi/cc.9-07uCi/cc'~'OTE:6.6-12=6.6x10'Theairborneparticulateradiationlevelcorrespondingtoa1"gpm/hrleakrateis1.1-07uCi/cc.'~'Thegaseousradioactivitylevelcorrespondingtoa1gpm/hrleakrateis6.3-07uCi/cc.Amendment191of1May1985

~~ltNineMilePointUnit2FSARrrequirements.The'materialforstuds,nuts,andwashersisSA-540GradeB23orB24atthe130,000psi-specifiedminimumyieldstrengthslevel.Hardness.testsareperformedonallmainclosureboltingtodemonstrate'thatheattreatmenthasbeenproperlyperformed.Aminimumof45ft-lbCharpyV-notch(C)energyand25milsV,lateralexpansionisrequiredat70~F.Themaximumreportedultimatetensilestrengthisbelowthe170,000-psimaximumspecified.inRegulatoryGuide1.65.Also,theCharpyimpacttest,requirementsof10CFR50AppendixGaresatisfied,sincethelowestreportedQenergyis46ft-lbat+10OF,comparedtotherequirementof45ft-lbat70F,andthelowestreportedC>expansionwas26mils,comparedtothe25milsrequired.Studs,nuts,andwashersareultrasonicallyexaminedinaccordancewithASMESectionIII,ParagraphNB-2585,andthefollowingadditionalrequire-ments:1.Examinationwasperformedafterheattreatmentandpriortomachiningthreads.2.3.Straightbeamexaminationwasperformedon100percentofeachstud.Referencestandardfortheradialscanisa1/2-indiameterflat-bottomholehavingadepthequalto10percentofthematerialthickness.FortheendscanthestandardofParagraphNB-2585isused.NutsandwasherswereexaminedbyanglebeamfromtheoutsidecircumferenceinaccordancewithASMESA-388inboththeaxialandcircumferentialdirections.The.surfaceexaminationsrequiredbyParagraphNB-2583areappliedafterheattreatmentandthreading.Therearenometalplatingsappliedtoclosurestuds,nuts,orwashers.A-manganese-phosphatecoatingisappliedtothreadedareasofstudsandnutsandbearingareasofnutsandwasherstoassistinretaininglubricantonthesesurfaces.Subsequenttofabrication,thestudsarelubricatedwithagraphite/alcoholornickelpowderbaselubricant.RegulatoryGuide1.65definesacceptablematerialsandtestingprocedureswithregardtoreactorvesselclosurestudboltingforlight-water-cooledreactors.Amendment115.3-9June1984 NineMilePointUnit:2FSARTheRPVclosurestudsareSA-540GradeB23or24(AISI-4340)andhaveamaximumultimatetensilestrengthof170ksi.Additionally,=,theboltingmaterial.wasspecifiedtohaveCharpyV-notchimpactpropertiesof45ft-lbminimumwith25milslateralexpansion.Nondestructiveexaminationbeforeandafterthreadingisspecifiedtobeinaccordance,,with=ASMESectionIII,SubsubarticleNB-2580whichcomplieswithReglatoryGuide1.65(C.2).InaccordancewithRegulatoryGuide1.65(C.2.b),theboltingmaterialswereultrasonicallyexaminedafterfinalheattreatmentandpriortothreading.Asrequiredforcompliance,theexamination'asdoneinaccordancewithSA-388.,Theproceduresapprovedforuseinpracticewerejudgedtoensurecomparablematerialqualityand,moreover,wereconsideredadequateonthebasisofcompliancewiththeapplicable"requirementsofASMESectionIII,ParagraphNB-2583.Additionally,'straightbeamexaminationwasperformedon100percentofcylindricalsurfaces,andfrombothendsofeachstudusinga3/4-inmaximumdiametertransducer.Inadditiontothecode-requirednotch,thereferencestandardfortheradialscancontaineda1/2-indiameterflat-bottomholewithadepthequalto10percentofthethickness'heendscanstandardcontaineda1/4-indiameterflat-bottomhole1/2-indeep.Anglebeam,ultrasonicexaminationwasperformedontheoutercylindricalsurfaceinbothaflatandcircumferential.direction.Surfaceexaminationswereperformedonthestudsandnutsafterfinalheattreatmentandthreading,asspecifiedbyRegulatoryGuide1.65,inaccordancewithParagraphNB-2583oftheapplicableASMEcode.Radialscan-calibrationisbasedona1/2-in(12.7-mm)diameterflatbottomholeofadepthequalto10percentofthematerialthickness.AnglebeamexaminationisperformedontheoutercylindricalsurfaceofnutsandwashersinaccordancewithASMESA-388inbothaxialandcircumferentialdirections.Noindicationgreaterthan,theindicationfromtheapplicablecalibrationfeaturewasacceptable.Adistance-amplitudecorrectioncurveinaccordancewithParagraphNB-2858isusedforthelongitudinalwaveexamination.InrelationshiptoRegulatoryGuide1.65(C.3),studboltingsurfacesareallowedtobeexposedtohigh-purityfillwater;nutsandwashersaredrystoredduringrefueling.5.3-10 NineMilePointUnit2FSARthistime,theturbinebypasssystemdivertsthesteam.tothemaincondenser,andthefeedwatersystemsuppliesthemakeupwaterrequiredtomaintainreactorvesselinventory.Intheeventthereactorvesselisisolatedandthefeedwatersupplyunavailable,reliefvalvesareprovidedtoautomatically(orremotemanually)maintainvesselpressurewithindesirablelimits.Thewaterlevelinthereactorvesseldropsduetocontinuedsteamgenerationbydecayheat.Uponreachingapredeterminedlowlevel,theRCICsystemisinitiatedautomatically.Theturbine-drivenpumpsuppliesdemineralizedmakeupwaterfromthecondensatestoragetanktothereactorvessel.Analternatesourceofwaterisavailablefromthesuppressionpool.TheRCICsystemallowsautomaticswitchoverofpumpsuctionfromthecondensatestoragetanktothesuppressionpoolifthecondensatestoragetankfallstoapresetlowlevel.Lowlevelinthetankismonitoredbytworedundantlevel.transmitters.Ifeithertransmittersenseslowlevel,pumpsuctionisautomaticallytransferredtothesuppressionpool.Theturbineisdrivenwithaportionofthedecayheatsteamfromthereactorvesselandexhauststothesuppressionpool.Suppressionpoolwaterisnotmaintaineddemineralizedandisusedonlyintheeventallsourcesofdemineralizedwaterhavebeenexhausted.Ifthemainfeedwatersystemisnotoperable,areactorscramisautomaticallyinitiatedwhenreactorwaterlevelfallstoLevel3.TheoperatorcanthenremotelymanuallyinitiatetheRCICsystemfromthemaincontrolroom,orthesystemisautomaticallyinitiatedasfollows.Reactorwaterlevelcontinuestodecreaseduetoboil-offuntilLevel2isreached.Atthispoint,thehigh-pressurecorespray(HPCS)and:thereactorcoreisolationcooling(RCIC)systemsareautomaticallyinitiatedtosupplymakeupwatertotheRPV.Thesesystems'ontinueautomaticinjectionuntilthereactorwaterlevelreachesLevel8,atwhichtimetheHPCSinjectionvalveisclosedandtheRCICsteamsupplyvalveisclosed.Inthenonaccidentcase,the-RCICsystemisnormallytheonlymakeup.systemusedtofurnishsubsequentmakeupwatertotheRPV.TheoperatorremotelymanuallyshutsdowntheHPCSsystem,fromthemaincontrolroom.WhenlevelreachesLevel2againduetolossofinventorythroughthemainsteamreliefvalvesortothemaincondenser,theRCICsystemautomaticallyrestartsasdescribedinSectionII.K.3.13.Thissystemthenmaintainsthecoolantmakeupsupply.RPVpressureisregulatedbytheautomaticorremotemanualoperationofthemainsteamreliefvalveswhichdischargetothesuppressionpool.USARRevision05.4-17April1989 NineMilePointUnit2FSARToremovedecayheatduringaplannedisolationevent,assumingthatthemaincondenserisnotavailable,thesteamcondensingmodeoftheRHRsystemcanbemanuallyinitiated.ResidualsteamisroutedthroughtheRHRheatexchangerswhereitiscondensedandcooled,thenreturnedtotheRPVthroughaninterconnectionwiththeRCICpump.Thus,closedloopcoolingisprovidedbythismode.Ifthesteamcondensingmodeisunavailableforanyreason,thesafetyreliefvalvescanbeusedtodumptheresidualsteamtothesuppressionpool.ThesuppressionpoolwillthenbecooledbyremotemanualalignmentoftheRHRsysteminthesuppressionpoolcoolingmodewhichroutesthepoolwaterthroughtheRHRheatexchangers,coolsit,andreturnsittothesuppressionpoolinaclosedcycle.MakeupwatertotheRPVisstillsuppliedbytheRCICsystem.FortheaccidentcasewiththeRPVathighpressure,theHPCSsystemcanalsobeusedtoautomaticallyprovidetherequiredmakeupflow.Nomanualoperationsarerequired.IftheHPCSsystemispostulatedtofailattheseconditionsandtheRCICcapacityisinsufficient,theautomaticdepressurizationsystem(ADS)willautomaticallyinitiatedepressurizationoftheRPVtopermitthecondensatepumpsorthelowpressureECCS(LPCIandLPCS)toprovidemakeupcoolant.WhenevertheRCICsystemisinitiated,theLSTGturbineistrippedtopreventwaterinductionintotheturbine,andthecontrolroomisalarmedthattheRCICinjectionvalveisopen.Therefore,althoughmanualactionscanbetakentomitigatetheconsequencesofalossoffeedwater,therearenoshorttermmanualactionswhichmustbetaken.Sufficientsystemsexisttoautomaticallymitigatetheseconsequences.DuringRCICoperation,thesuppressionpoolactsastheheatsinkforsteamgeneratedbyreactordecayheat.Thisresultsinariseinpoolwatertemperature.Heatexchangersintheresidualheatremoval(RHR)systemareusedtomaintainthepoolwatertemperaturewithinacceptablelimitsbycoolingthewaterdirectlyorbycondensinggeneratedsteam.ThecondensatedischargefromtheRHRheatexchangersmaybeusedasRCICpumpsuctionsupplyoritmaybedirectedtothesuppressionpool;'TheRCICsystemisequippedwithadischargelinefillpumpthat,operatestomaintainthepumpdischargelineinafilledcondition.KeepingthedischargelinefilledreducesthelagtimebetweenpumpstartupandattainmentoffullflowtotheRPV.Additionally,itsoperationeliminatesthepossibilityofRCICpumpsdischargingintoadrypipeandminimizeswaterhammereffects.ThefillpumpisclassifiedasCategoryIandSafetyClass2.ThepumpmotorisUSARRevision05.4-17aApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER76Athrough6CINSTRUMENTATIONANDCONTROLSYSTEMSTitleReactorVesselComponentandSubsystemDesign5A,5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3ComponentsVolume1313131313141515151515157.17.27'7'7.57.67~7Appendixes7A,7BIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS16161616,1717I179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9A,9C17181920~2121,2223USARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSIONSYSTEM2310.110.210.310.4Summary.DescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem232324CHAPTER11RADIOACTIVEWASTEMANAGEMENTll.111.211.311.411.5SourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsAppendixllACHAPTER12RADIATIONPROTECTION2424252525252512.112.212.312.412~5CHAPTER1313.113.213.313.413.513.6AppendixesEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentHealthPhysicsProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity13A,13B252525262626262626.26262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,ToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26}}