ML18038A109
| ML18038A109 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/30/1985 |
| From: | MANGAN C V NIAGARA MOHAWK POWER CORP. |
| To: | ADENSAM E G Office of Nuclear Reactor Regulation |
| References | |
| (NMP2L-0569), (NMP2L-569), NUDOCS 8601060030 | |
| Download: ML18038A109 (1356) | |
Text
YNIAGARAUMOHAWKNIAGARAMOHAWKPOWERCORPORATION/300ERIEBOULEVAROWEST,SYRACUSE.N.Y.13202/TELEPHONE(315)474.'1511December30,1985(NMP2L0569)Ms.ElinorG.Adensam,DirectorBHRPro]ectDirectorateNo.3U.S.NuclearRegulatoryCommission7920NorfolkAvenueHashington,DC20555
DearMs.Adensam:
Re:NineMile.PointUnit2DocketNo.50-410Enclosedisourmarked-upcopyofthe"proofandreview"versionoftheTechnicalSpecifications,whichwereceivedfromyouonNovember22,1985(AttachmentA).Thismarked-upcopyreflectsourcommentsbasedonourreviewagainstthecurrentplantdesign.JustificationforproposedTechnicalSpecificationchangesisprovidedinAttachmentB,whichalsocontainsadditionalcommentsandclarifications,andseveraladditionalpageswhichshouldbeincorporatedintotheTechnicalSpecifications.AttachmentCidentifiesthechangesinAmendment23oftheFinalSafetyanalysisReportwhichaffecttheTechnicalSpecifications.HearealsoincludingatthistimeproposedTechnicalSpecificationsfor"SingleLoopOperation"(AttachmentD),and"EndofCycleRecirculationPumpTripInoperableandTurbineBypassInoperable"(AttachmentE).TheseSpecificationsrepresentenhancementstotheoperationalflexibilityofUnit2andhavealreadybeenapprovedforseveralotherBoilingHaterReactors.AttachmentsFandGcontaintheanalysesnecessarytosupporttheserequestedchanges.HearecontinuingourprogramofSafetyAnalysisReportandTechnicalSpecificationverificationandwillincorporateanyidentifiedchangesasweresolvecommentsdevelopedduringtheBranchTechnicalReviewprocess.Verytrulyyours,C.V.ManganSeniorVicePresidentKHK:)aAttachmentsxc:R.A.Gramm,NRCResidentInspectorPro]ectFile(2)
ATTACHMENTDSINGLELOOPOPERATIONPROPOSEDTECHNICALSPECIFICATIONCHANGES
2.0SAFETYLIMITSANOLIMITINGSAFETYSYSTEMSETTINGS2.1SAFETYLIMITSTHERMALPOWER'LowPressureorLowFlow2.1.1THERMALPOWERshallnotexceed25KofRATEDTHERMALPOWERwiththereactorvesselsteamdomepressurelessthan785psigorcoreflowlessthan10Xofratedflow.APPLICABILITY:OPERATIONALCONDITIONS1and2.~ACTIO:WithTHERMALPOWERexceeding25KofRATEDTHERMALPOWERandthereactorvesselsteamdomepressurelessthan785psigorcoreflowlessthan10Kofratedflow,beinatleastHOTSHUTDOWNwithin2hoursandcomplywiththeruie-.mentsofSpecification6.7.1.i.ov~'AkTHERMALPOWERHihPressureandHihFlow~'~p~~~~'~4~~'~4p.of+<+~<4~2.1.2TheMINIMUMCRITICALPOWERRATIO(MCPR)shallnotbelessthan1.06withthereactorvesselsteamdomepressuregreaterthan785psigandcoreflowgreaterthan10Kofratedflow.APPLICABILITY:OPERATIONALCODITIONS1and2.wI+4+worec)Q.ouLdwLodeof8h04~4~0+1+~+h~~4OtVA4>>N~l.pepopCt4'54MWithMCPRlessthan1.06andthereactorvesselsteamdomepressuregreaterthan785psigandcoreflowgreaterthan10Kofratedflow,beinatleastHOTSHUTDOWNwithin2hoursandcomplywiththerequirementsofSpecification6.71.REACTORCOOLANTSYSTEMPRESSURE2.1;3Thereactorcoolantsystempressure,asmeasuredinthereactorvesselsteamdome,shallnotexceed1325psig.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and4.ACTION:Withthereactor'coolantsystempressure,asmeasuredinthereactorvesselsteamdome,above1325psig,beinatleastHOTSHUTDOWNwithreactorcoolantsystempressurelessthanorequalto1325psigwithin2hoursandcomplywiththerequirementsofSpecification6.7.1.NINEMILEPOINT-UNIT22-1HOVSO1~
ITABLE2.2.1-1I"REACTORPROTECTIONSYSTEHINSTRUMENTATIONSETPOINTS-FUNCTIONALUNITm1.IntermediateRangeMonitor,NeutronFlux-High2.AveragePowerRangeHonitor:a.NeutronFlux-Upscale,SetdownIb.FlowBiasedSimulatedThermalPower-Upscale1)FlowBiased2)HighFlowClampedc.Fixed.NeutronFlux-Upscaled.Inoperative3.ReactorVesselSteamDomePressure-High4.ReactorVesselMaterLevel-Low,Level3TRIPSETPOINT<l20/125divisionsoffullscale<15KofRATEDTHERHALPOMER0,4,~(~-<~>+~I<oWi/iamaximumof<113.5XofRATEDTHERNLPOWER<118KofRATEDTHERMALPOMER<1037psi'g>159.3linchesaboveinstrumentzero"ALLOMABLEVALUES<122/125divisionsoffullscale<20KofRATEDTHERHALPOWERda4C(,W-Qve)+Sf'~/-.//Nil/-iii.amaximumof<115.5XofRATEDTHERHALPOMER<120KofRATEDTHERMALPOWERNA<1057psig>157.8inchesaboveinstrumentzero5.HainSteamLineIsolationValve-Closure6.HainSteamLineRadiation"High7.Dr@wellPressure-HighS.ScramDischargeVolumeMaterLevel-Higha.LevelTransmitter/TripUnits-b.FloatSwitch9.TurbineStopValve-Closure10.TurbineControlValveFastClosure,TripOilPIessure-Low11.ReactorModeSwitch'ShutdownPosition12.HanualScram0~SB/gB3/4i-i.<6Xclosed<3.0xfullpowerbackground<1.68psig<46.5inches<46.5inches<5Xclosed>530psigNANA<7Xclosed<36xfullbackground<1.88psig<79.5inches<79.5inches<7Xclosed.>465psigNApowerCMgee fp 0('%'l~~p~~~~~~V~~~~~a.d~~CD).g@c~'J+dLu~~~~)J;~~~~~~~&&~~~~ca+A~~+b~=Sio+~(.fC4I('<pena,<Poove-t4u<f>'t/2.-4-<
2.1SAFETYLIMITSBASESCoy.-bvotectec~+Co~L-oapopet'wio~bu
2.0INTRODUCTION
~,oqP4>~~~>gpgqgp.cu.Q+gy<popopcto+hoThefuelcladding,reactorpressurevessel"andprimarysystempipingaretheprincipalbarrierstothereleaseofradioactivematerialstotheenvirons.SafetyLimitsareestablished.toprotecttheintegrityofthesebarriersduringnormalplantoperationsandanticipatedtransients.ThefuelcladdingintegritySafetyLimitissetsuchthatnofueldamageiscalculatedtooccurifthelimitisnotviolated.Becausefueldamageisnotdirectlyobservable,astep-backapproachsusedtoestablishaSafetyLimitsuchthattheMCPRisnot.lessan.6MCPRgreaterthan1.06representsaconservativemarginrelativetotheconditionsrequiredtomaintainfuelcladdingintegrity.Thefuelcladdingisoneofthephysicalbarrierswhichseparatetheradioactivemate-rialsfromtheenvirons.Theintegrityofthiscladdingbarrierisrelatedto.itsrelative.freedomfrom.peqforationsorcracking.Althoughsomecorrosionoruse-relatedcrackingmayoccurduringthelifeofthecladding,fissionproductmigrationfromthissourceisincrementallycumulativeandcontinuouslymeasurable.Fuelcladdingperforations,however,canresultfromthermalstresseswhichoccurfromreactoroperationsignificantlyabovedesigncondi-tionsandtheLimitingSafetySystemSettings.Whilefissionproductmigrationfromcladdingperforationisjustasmeasurableasthatfromuse-relatedcracking,thethermallycausedcladdingperforationssignalathresholdbeyondwhichstillgreaterthermalstressesmaycausegrossratherthanincrementalcladdingdeterioration.Therefore,thefuelcladdingSafetyLimitisdefinedwithamargintotheconditionswhichwouldproduceonsetoftransitionboiling,MCPRof1.0.Theseconditionsrepresentasignificantdeparturefromtheconditionintendedbydesignforplannedoperation.2.1.1THERMALPOWERLowPressureorLowFlowTheuseoftheGEXLcorrelationisnotvalidforallcriticalpowercalculationsatpressuresbelow785psigorcoreflowslessthan10Kofratedflow.Therefore,thefuelcladdingintegritySafetyLimitisestablishedbyothermeans.ThisisdonebyestablishingalimitingconditiononcoreTHERMAL-POWERwiththefollowingbasis.Sincethepressuredropinthebypassregionisessentiallyallelevationhead,thecorepressuredropatlowpowerandflowswillalwaysbegreaterthan4.5psi.Analysesshowthatwithabundleflowof28x10'bs/hr,bundlepressuredropisnearlyindependentofbundlepowerandhasavalueof3.5psi.Thus,the,bundleflowwitha4.5psidrivingheadwillbegreaterthan28x10'bs/hr.FullscaleATLAStestdatatakenatpressuresfrom14.7psiato800psiaindicatethatthefuelassemblycriticalpoweratthisflowisapproximately3.35MWt.Withthedesignpeakingfactors,thiscorrespondstoaTHERMALPOWERofmorethan50KofRATEDTHERMALPOWER.Thus,aTHERMALPOWERlimitof25KofRATEDTHERMALPOWERforreactorpressurebelow785psigisconservative.NINEMILEPOINT-UNIT2B2"1gGVRO585
~'
BasesTableB2.1.2-1UNCERTAINTIESUSEDINTHEDETERMINATIONOFTHEFUELCLADDINGSAFETYLIMIT"~uantitFeedwaterFlowFeedwaterTemperature..ReactorPressureCoreInletTemperatureI,CoreotalFlowwoQoclacu,l.O<tagLoaqOqety4toe+++IQclLLotVIQL~opQp'yy4l'oKFrictionFactorMultiplierChannelFrictionFactorMultiplierTIP4eadiagsTwo'Kdcl~~404)oa~yp4peew4ihaRFs)MAL@g0'clA,cuLa47oaHogOqc~aktayCriticalPowerStandardDeviationXofPoint1.760.760.50.210.&5.0l.'r3.6fR*ytyddtblihthIdSafetyLimitMCPRisbasedontheassumptionofquadrantpowersymmetryforthereactorcr.,7~~~J~~~De-Ww~NINEMILEPOINT-UNIT2B2-3NOY2u
3/4.2POWERDISTRIBUTIONLIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATEFM~$a~3""j'P'fgj'/LIMITINGCONDITIONFOROPERATION3.2.1AllAVERAGEPLANARLINEARHEATGENERATIONRATES(APLHGRs)foreachtypeoffuelasafunctionofAVERAGEPLANAREXPOSUREshallnotexceedthelimitsshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3.APPLICABILITY:OPERATIONALCONDITIONl,when'THERMALPOWERisgreaterthanOPEREILOTTOTRRRIOLTOOER.ACTION:WithanAPLHGRexceedingthelimitsofFigure3.2.1-1,3.2.1-2,or3.2.1-3,'ihit'iatecorrectiveactionwjthin15minutesandrestoreAPLHGRtowithintherequiredlimitswithin2hoursorreduceTHERMALPOWERtolessthan25XofRATEDTHERMALPOWERwithinthenext4hours.Qhf.'J~EELEROR'POg+ttagg((,+O+P~2WS.Rl8aJLaJILW~M~Ml+o.siW~~SURVEILLANCEREUIREMENTS4.2.1AllAPLHGRsshallbeverifiedtobeequaltoorlessthanthelimitsdeterminedfromFigures3.2.1-1,3.2.1-2,and3.2.1-3:'a0b.cAtleastonceper24hours,Within12hoursaftercompletionofaTHERMALPOWERincrease.ofatleast15KofRATEDTHERMALPOWER,andWInitiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLRODPATTERNforAPLHGR.d.TheprovisionsofSpecification4.0.4arenotapplicable.rI~NINEMILEPOINT"UNIT23/42-1NQV208
(.-POWERDISTRIBUTIONLIMITS3/4.2.2APRMSETPOINTSLIMITINGCONDITIONFOROPERATION3.2.2TheAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpoint(S)andflowbiasedneutronflux-upscalecontrolrodblocktripsetpoint(SRB)shallbeestablishedaccordingtothefollowingrelationships:TRIPSETPOINTALLOWABLEVALUEd,su)ete6<(0.6>>6)T6<(0.6>>64Ã)T~~)~~SRB<(0.66+42K)TSRB<(0.66/V+45K)Twhere:SandSRBarenpercentof.RATEDTHERMALPOWER,W=Looprecirculationflowasapercentageofthelooprecirculationflowwhichproducesaratedcoreflowof108.5millionlbs/hr.T=Theratio.FRACTIONOFRATEDTHERMALPOWERdivided~bytheCOREMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY.Tisappliedonlyifless-thanorequalto1.0.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanor~tlAEIIIATEETHERMALPIIIIER.ACTION:WiththeAPRNflawbiasedsieu1atedthermaIpowerup'sca1escreetripsetpnint,and/ortheflowbiasedneutronflux-upscalecontrolrodblocktripsetpointlessconservativethanthevalueshown'$ntheAllowableValuecolumnforSorSRB,asabovedetermined,initiatecorrectiveactionwithin15minutesandadjustSand/orSRBtobeconsistentwiththeTripSetpointvalue.within6hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.2.2TheFRTPandtheCMFLPDshallbedetermined,thevalueofTcalculated;.andthemostrecentactualAPRMflowbiasedsimulatedthermalpower-upscalescramandflowbiasedneutronflux-upscalecontrolrodblocktripsetpointsverifiedtobewithintheabovelimitsoradjusted,asrequired:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithCMFLPDgreaterthanorequaltoFRTP.d.TheprovisionsofSpecification4.0.4arenotapplicable.AEAttttPIITPA'PIE-THERMAL-POWER-,ratherthanadjustingtheAPRMsetpoints,theAPRMgainmaybeadjustedsuchthatAPRMreadingsaregreaterthanorequalto100KtimesCMFLPDprovidedthattheadjustedAPRMreadingdoesnotexceed100KofRATEDTHERMALPOWERandanoticeofadjustmentispostedonthereactorcontrolpanel.~~S~~a4)&7~a~.I-lNINEMILEPOINT-UNIT23/42"5HOV8019gS
~~tl'I%'p~tMMICMCObOCa%ICJlCOTRIPFUNCTION1.RODBLOCKMONITORppb.Inoperativec.Downscale2.APRMa.FlowBiasedNeutronFluxUpscaleb.Inoperativec.Downscaled.NeutronFlux-Upscale,Startup3.SOURCERANGEMONITORSa.Detectornotfuinb.Upscale'.Inoperatived..Downscale4.INTERMEDIATERANGEMONITORSa.Detectornotfullnb.Upscalec.Inoperatived.DownscaleTRIPSETPOINT<0.66W+40XHA>5XofRATEDTHERNLPOMER(vo~AN)<0,66~42X~HA>4XofRATEDTHERNLPOMER<12XofRATEDTHERNLPOMERNA<1x10scpsHA3cps*AINA.<108/125divisionsoffullscaleNA>5/125divisionsoffullscalej~TABLE3.3.6-2CONTROLRODBLOCKINSTRUMENTATIOHSETPOINTSALLOMABLEVALUE<0.66W+43XHA>3XofRATEDTHERMALPOMER<(w-Aw)<0.6645X"HA>3XofRATEDTHERNLPOMER<14XofRATEDTHERNLPOMER'A<1.6x10scpsHa>1.8cps**NA<110/125divisionsoffullscaleNA>3/125divisionsoffullscale<39.75in.5.SCRAMDISCHARGEVOLUMEa.MaterLevel-1gh<16.5in.+;-ciaram-Trip-Bypa6.REACTORCOOLANTSYSTEMRECIRCULATIONFLOMa.pscae<10BXratedflow<111Xratedflowb.InoperativeHaHAc.Comparator~<1OXflowdeviation<HXf)owdeviationIthgPIIIIIt.IPtIItttIIIttIIIttIIIt(W).ThetripsettingofthisfunctionmustbemaintainedinaccordancewithSpecification3.2.."*Forinitialloadingandstartupthe."countratemaybelessthan3cpsifthefollowingconditionsaremet;{1)thesignaltonoiseratioisgreaterthan2.0<(2)thesignalisgreaterthan0.7cp~nd-Cr~>t>A~QoICP~r
3/4'4'REACTORCOOLANTSYSTEM3/4.4-1'RECIRCULATIONSYSTEMRECIRCULATION'OOPSLIMTINGCONDITIONFOROPERATION3.4.1.1Tworeactorcoolantsystemrecirculationloopsshallbeinoperationwith:a.Totalcoreflowgreaterthanorequalto45Kofratedcoreflow,orb.THERMALPOWERwithintheunrestrictedzoneofFigure34.1.1-1.APPLICABILITY-OPERATIONALCONDITIONS1*and2*.ACTION:a.Withonereactorcoolantsystemrecirculationloopnotinoperation:1.Withinfourhours:a)PlacetherecirculationflowcontrolsystemintheLocalManual(PositionControl)mode,andb)ReduceTHERMALPOWERtM70XofRATEDTHERMALPOWER,and,c)IncreasetheMINIMUMCRITICALPOWERRATIO(MCPR)Safety-Limitby0.01to1.07perSpecification2.1.2,and,d)ReducetheMaximumAveragePlanarLinearHeatGenerationRate(MAPLHGR)limittoavalueof0.81timesthetworecirculationloopoperationlimitperSpecification3.2.1,and,e)ReducetheAveragePowerRangeMonitor(APRM)ScramandRodBlockandRodBlockMonitorTripSetpointsandAllowableValuestothoseapplicableforsinglerecirculationloopoperationperSpecifications2.2.1,3.2.2and3.3.6.f)Reducethevolumetricflowrateoftheoperatingrecirculationloopto~41,000~gpm.*SeeSpecialTestException3.10.4.Thisvaluerepresentsthedesignvolumetricrecirculationloopflowwhichproduces100Kcoreflowat100ÃTHERMALPOWER.TheactualvaluewillbeestablishedduringtheStartupTestProgram.NineMilePointUnit23/44-1
- \'E:E~'EACTOR'COOLANTSYSTEMLIMITINGCONDITIONFOROPERATIONContinuedEEE')'erformSurveillanceRequirement4A.1.1.2ifTHERNLPOWERis~30K~ofRATEDTHERMALPOWERortherecirculationloopflowintheoperatingloopfs~505~ofratedloopflow.h)DeterminethatthereactorTHERMALPOWERlevelfsnot--withintherestrictedzoneofFigure3.4.1.1-1;otherwise,'reducetheTHERMALPOWERlevelorincreasecoreflow..2.TheprovisionsofSpecification3.0.4arenotapplicable.-3.OtherwisebeinavastHOTSHUTDOWN.withinthenext12hours.b.EMfthnoreactorcoolantsystemrecirculationloopsfnoperation,'amedfatelyinftiateactiontoreduceTHERMAL.POWERsuchthatftisnotwithinthe.restrictedzoneofFigure3.4.1.1-1withintwohours,andinitiatemeasurestoplacetheunitfnatleastSTARTUPwithinsfx.hoursandfnHOTSHUTDOWNwithinthenextsixhours.c."Withtworeactorcoolantsystemrecirculationloopsinoperationandtotalcoreflowlessthan455ofratedcoreflowandTHERNLPOWERgreaterthanthelimitspecifiedinFigure34.1;l-l:1.:DeterminetheAPRMandLPR~noiselevels(Surveillance~~I~~uE\.a)Atleastoncepereighthours,and:b).Mfthfn30minutesafterthecompletionofaTHERNLPOWER'-;increaseof't1east5XofRATEDTHERNLPOWER.'2.-MfththeAPRMorLPRM~neutronfluxnoiselevelsgreaterthan'threetimestheirestablishedbaselinenoiselevels,ftanedfatelyinitiatecorrectiveactiontorestorethenoiselevelswithintherequiredlimitswithintwohoursbyincreasingcoreflowto-greaterthan455ofratedcorefloworbyreducingTHERNLPOWER-sothatitisnotwithintherestrictedzoneofFfgure3A.1.1-1.EE.:.'~.DetectorlevelsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstronginthecenterofthecoreshouldbemonitored..Jnftialvalues.'FinalvaluestobedeterminedduringStartupTesting:;>baseduponthethresholdTHERMALPOWERandrecirculationloopflowwhich~'...4wfll,sweepthecoldwaterfromthevesselbottomheatpreventing-.-,Pwtratfffcation.EEh*.'NineMilePointUnit2'"';;;-..;i<,','-'~'-.~,"3/44-la4
REACTOR'COOLANT'YSTEMSURVEILLANCEREUIREMENTS4.4.1.1.1.Withonereactorcoolantsystemrecirculationloopnotinoperation,atleastonceper12hoursverifythat:a.ReactorTHERMALPOWERis&70%ofRATEDTHERMALPOWER,b.TherecirculationflowcontrolsystemisintheLocalManual{PositionControl)mode,and.c.Thevolumetricflowrateoftheoperatingloopis~41,000gpm.*4A.1.1.2Withonereactorcoolantsystemrecirculationloopnotinoperation,withinnomorethan15minutespriortoeitherTHERMALPOWERincreaseorrecirculationloopflowincrease,verifythatthefollowingdifferentialtemperaturerequirementsaremetifTHERMALPOWERis4-'30K~ofRATEDTHERMALPOWERortherecirculationloopflowintheoperatingrecirculationloopis~50K~ofratedloopflow:a.~145'Fbetweenreactorvesselsteamspacecoolantandbottomheaddrainlinecoolant,b.+50'Fbetweenthereactorcoolantwithintheloopnotinoperationandthecoolantinthereactorpressurevessel,andc.~50'Fbetweenthereactorcoolantwithintheloopnotinoperationandtheoperatingloop.ThedifferentialtemperaturerequirementsofSpecification4A.1.1.2b.andc.donotapplywhentheloopnotinoperationisisolate'dfromthereactorpressurevessel.4.4.1.1.3EachreactorcoolantsystemrecirculationloopflowcontrolvalveshallbedemonstratedOPERABLEatleastonceper18monthsby:a.Verifyingthatthecontrolvalvefails"asis".onlossofhydraulicpressureatthehydrauliccontrolunit,andb.Verifyingthattheaveragerateofcontrolvalvemovementis:1.Lessthanorequaltollewofstrokepersecondopening,and2.Lessthanorequaltoillofstrokepersecondclosing.*Thisvaluerepresentsthedesignvolumetricrecirculationloopflowwhichproduces100Kcoreflowat100$THERMALPOWER.TheactualvaluewillbeestablishedduringtheStartupTestProgram.Initialvalues.FinalvaluestobedeterminedduringStartupTestingbaseduponthethresholdTHERMALPOWERandrecirculationloopflowwhichwillsweepthecoldwaterfromthevesselbottomheadpreventingstratification.NineMilePointUnit23/44-2
REACTOR'OOLANTSYSTEMSURVEILLANCEREUIREMENTSContinued4.4.1.1.4EstablishabaselineAPRMandLPRFVneutronfluxnoisevaluewithintheregionsforwhichmonitoringisrequired{Specification3A.l.l,ACTION-)withintwohoursofenteringtheregionforwhichmonitoringisrequiredunlessbaselininghaspreviouslybeenperformedintheregionsincethelastrefuelingoutage.DetectorlevelsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstringinthecenterofthecoreshouldbemonitored.NineMilePointUnit23/44-2a
,II555~'I'II/IP,r8awialll5~5)gg/1>~)ilI/II/IIsI.~)III'III8~II
REACTOR'COOLANTSYSTEMJET'PUMPSIMITINGCONDITIONFOROPERATION3.4.1.2AllgetpumpsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:Withoneormorejetpumpsinoperable,beinatleastHOTSHUTDOWNwithin12hours.SURVEILLANCEREUIREMENTS44.1.2AlljetpumpsshallbedemonstratedOPERABLEasfollows:EachoftheaboverequiredjetpumpsshallbedemonstratedOPERABLEeriortoTHERMALPOWERexceeding25KofRATEDTHERMALPOWER,andateastonceper24hourswhilegreaterthan25K,ofRATEDTHERMALPOWER,bydeterminingrecirculationloopflow,totalcoreflowanddiffuser-to-lowerplenumdifferentialpressureforeachjetpumpandverifyingthatnotwoofthefollowingconditionsoccurwhenbothrecirculationloopindicatedflowsareincompliancewithSpecification3A.1.3.1.TheindicatedrecirculationloopflowdiffersbymorethanlOXfromtheestablished*flowcontrolvalveposition-loopflowcharacteristics.2.Theindicatedtotalcoreflowdiffersbymorethan105fromtheestablished*totalcoreflowvaluederivedfromrecirculationloopf1owmeasurements.3.Theindicateddiffuser-to-lowerplenumdifferentialpressureofanyindividualjetpumpdiffersfromestablished+patternsbymorethan10K.b.Duringsinglerecirculationloopoperation,eachoftheaboverequiredgetpumpsshallbedemonstratedOPERABLEatleastonceper24hoursbyverifyingthatnotwoofthefollowingconditionsoccur:1.TheindicatedrecirculationloopflowintheoperatingloopdiffersbymorethanlOXfromtheestablishedsinglerecirculationflowcontrolvalveposition-loopflowcharacteristics.+Tobedeterminedduringthestartuptestprogram.NineMilePointUnit23/44-4
REACTOR'COOLANTSYSTEMSURVEILANCEREUIREMENTSContinued2.TheindicatedtotalcoreflowdiffersbymorethanlOXfromtheestablishedtotalcoreflowvaluederivedfromsinglerecirculationloopflowmeasurements.3.Theindicateddifference-to-lowerplenumdifferentialpressureofanyindividualjetpumpdiffersfromestablishedsinglerecirculationlooppatternsbymorethan10K.c.TheprovisionsofSpecification4.0.4arenotapplicableprovidedthatthissurveillanceisperformedwithin24hoursafterexceeding25'0ofRATEDTHERMALPOWER.NineMilePointUnit23/44-4a
."REACTORCOOLANTSYSTEMRECIRCULATIONLOOPFLOWDELIE3""if'RF!LIMITINGCONOITIONFOROPERATION3.4.1.3Recirculationloopflowmismatchshallbemaintainedwithin:.CooC+kd'Ma.SXof'ated'lowwith"coreflowgreaterthanorequalto10Kofratedcoreflow.t.k&d.IV<t.tiltftd~ftIthflIthfdfratedcoreflow..APPLICABILITY:OPERATIONALCONOITIONSI"AndEPAth>iwS<w<LOOP~peEg+;Oa.,ACTION:Miththerecirculationloopflowsdifferentbymorethanthespecifiedlimits,either:a.Restoretherecirculationloopflowstowithinthespecifiedlimitwithin2hours,orb.S~~4Wowea++kgPrC:Zlotyl~8(u.Ice4lkeqOO<iSLLSaSO+'qqQc.nALeSURVEILLANCEREUIREMENTS~~~t-8<itCuria<Woqa~P-k+a-4<s.+++84qeCR<e&'SO~3o-+A~t4~4.4.1.3Recirculationloopflowmismatchshallbeverifiedtobewithinthelimitsatleastonceper24hours.htI(~I4SeeSpecialTestException3.10.4.~~4+;~et.cheVlftwI:4th-LLbcSheeave+LthdhfWw+fec(g~'4oa+op~~5~quip~s~~~eh604lw++4'++4e4WOLOOP~N~NINE.MILEPOINT-UNIT23/44"5
REACTIVITYCONTROLSYSTEHSBASESpPJAF$p>~pl[$qpy3/4.1.3CONTROLRODSThespecificationofthissectionensurethat(1)theminimumSHUTDOMNMARGINismaintained,(2)thecontrolrodinsertiontimesareconsistentwiththoseusedinthesafetyanalyses,and(3)limitthepotentialeffects'oftheroddropaccident.TheACTIONstatementspermitvariationsfromthebasicrequirementsbutatthesametimeimposemorerestrictivecriteriaforcontinuedoperation.Alimitationoninoperablerodsissetsuchthattheresultanteffectontotalrodworthand.scramshapewillbekepttoaminimum.Therequirementsforthevariousscramtimemeasurementsensurethatanyindicationofsystematicproblemswithroddriveswillbe.investigatedonatimelybasis.Damagewithinthecontrolroddrivemechanismcouldbeagenericproblem,thereforewithacontrolrodimmovablebecauseofexcessivefrictionormechanicalinterference,operationofthereactorislimitedtoatimeperiodwhichisreasonabletodeterminethecauseoftheinoperabilityandat,thesametimepreventoperationwithalargenumberofinoperablecontrolrods.Controlrodsthatareinoperableforotherreasonsarepermittedtobetakenoutofserviceprovidedthatthoseinthenonfully-insertedpositionareconsistentwiththeSHUTDOWMARGINrequirements.Thenumberofcqntrolrodspermittedtobeinoperablecouldbemorethantheeightallowedbythespecification,buttheoccurrenceofeightinoperablerodscouldbeindicativeofagenericproblemandthrownforinvestigationandreso1utionof'heproblem.~g~~<lcL+l~ys&&yL~iThecontrolrodsystemisdesignedtobringtheactorsubcriticalataratefastenoughtopreventtheHCPRfrombecominglessthan~96"duringthelimitingpowertransientanalyzedinSection15.4ftheFSAR.Thisanalysisshowsthatthenegativereactivityratesresultingfromthescramwiththeaverageresponseofallthedrivesasgiveninthspecifications,providetherequiredprotectionandMCPRremainsgreaterthan...Theoccurrenceofscramtimeslongerthenthosespecifiedshouldbeviewedasanindicationofasystemicproblemwiththeroddrivesandthereforethesurveillanceintervalisreducedinordertopreventoperationofthereactorforlongperiodsoftimewithapotentiallyseriousproblem.ThescramdischargevolumeisrequiredtobeOPERABLEsothatitwfllbeavailablewhenneededtoacceptdischargewaterfromthecontrolrodsduringareactorscramandwillisolatethereactorcoolantsystemfromthecontainmentwhenrequired.ControlrodswithinoperableaccumulatorsaredeclaredinoperableandSpecification3.1.3.1thenapplies.Thispreventsapatternofinoperableaccumulatorsthatwouldresultinlessreactivityinsertiononascramthanhasbeenanalyzedeventhoughcontrolrodswithinoperableaccumulatorsmaystillbeinsertedwithnormaldrivewaterpressure.Ope.abilityoftheaccumulator.ensuresthatthereisameansavailabletoinsertthecontrolrodsevenunderthemostunfavorabledepressurizationofthereactor.NINEMILEPOINT-UNIT2B3/41-2
4POWERDISTRIBUTIONLIMITSBASESH~86Fggpss(ypg,~()AVERAGEPLANARLINEARHEATGENERATIONRATE(Continued)h.~MCICl1.CoreCCFLpressuredifferential-Ipsi-Incorporatetheassumptionthatflowfromthebypasstolowerplenummustovercomea1psipressuredropincore.2.IncoporateNRCpressuretransferassumption-TheassumptionusedintheSAFE-REFLOODpressuretransferwhenthepressureisincreasingwaschanged.AfewofthechangesaffecttheaccidentcalculationirrespectiveofCCFL.Thesechangesarelistedbelow.~ltCh1.BreakAreas-TheDBAbreakareawascalculatedmoreaccurately.h.~Md1Chl.ImprovedRadiationandConductionCalculation-IncorporationofCHASTE05forheatupcalculation.Alistofthesignificantplantinputparameterstotheloss-of-coolantaccidentanalysisispresentedinBasesTableB3.2.1-1.3/4.2.2APRMSETPOINTSThefuelcladdingintegritySafetyLimitsofSpecification2.2,werebasedonapowerdistributionwhichwouldyieldthedesignLHGRatRATEDTHERMALPOSER.TheflowbiasedsimulatedthermalpowerupscalescramsettingandfloHbiasedneutronfluxupscalecontrolrodblockfunctionsoftheAPRMinstrumentsmustbeadjustedtoensurethattheMCPRdoesnotbecomelessthanl.06orthat>2%plasticstraindoesnotoccurinthedegradedsituation.Thescramsetpointandrodblocksettingsareadjustedinaccordancewiththeformulainthisspecificationwhenthe.combinationofTHERMALPOMERandCMFLPDindicatesahigherpeakedpowerdistributiontoensurethatanLHGRtransientwouldnotbeincreasedinthederadedcondition.r~~F+u3.a.,l-~wl':..TV'a~NINEMILEPOINT-UNIT2-8~~~HAl'Lt%R.3,cLCI-Q.~3,+hl3JLocA-3/42-2HOV301Ž
BasesTab1eB3.2.1"1SIGNIFICANTINPUTPARAMETERSTOTHELOSS"QF"COOLANTACCIDENTANALYSISP1antParameters;CoreTHERMALPOWER.....................Vesse1SteamOutput..........;.........346LMWt"whichcorrespondsto105Xofratedsteamf1ow15.0x101bm/hrwhichcor-respondsto105Kofratedsteamf1owVesselSteamDomePressure..............1055psiaDesignBasisRecircu1ationLineBreakAreafor:a.LargeBreaks3.1ft4b.Sma11Breaks0.09ftFue1Parameters:FUELTYPEInit1alCorePEAKTECHNICALINITIALSPECIFICATIONDESIGN.MINIMUMLINEARHEATAXIALCRITICALFUELBUNDLEGENERATIONRATEPEAKINGPOWERGEOMETRY(kw/ft)FACTORRATIO,8x813.41.41.20&mAmoredetai1edlistingofinputofeachmodeIanditssourceispresentedinSectionIIofReference1andsubsection6.3.3oftheFSAR.~"Thispower1evelmeetstheAppendixKrequirementof102.Thecoreheatupca1cu1ationassumesabund1epowerconsistentwithoperationof-.thehighestpoweredrodat102KofitsTechnicalSpecificationLINEAR.,HEATGENERATIONRATElimit..a+d.l~~LocPHc78-.NINEMILEPOINT-UNIT2B3/42"3
POSERDISTRIBUTIONLIMITSBASESpgJfg<Pf,pr.:f}pyIsgr}y3/4.2.3MINIMUMCRITICALPOMERRATIOTherequiredoperatinglimitMCPRsatsteadystateoperatingconditionsasspecifiedinSpecification3.2.3arederivedfromtheestablishedfuelcladdingintegritySafetyLimitMCPR~F;ORandananalysisofabnormaloperationaltransients.Foranyabnormaloperatingtransientanalysisevalua-tionwiththeinitialconditionofthereactorbeingatthesteadystateoperatinglimit,itisrequiredthattheresultingMCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytime.duringthetransientassuminginstrumenttripsettinggiveninSpecification2.2.ToassurethatthefuelcladdingintegritySafetyLimitisnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtran-sientshavebeenanalyzedtodeterminewhichresultinthelargestreductioninCRITICALPOMERRATIO(CPR).Thetypeoftransientsevaluatedwerelossofflow,increaseinpressureandpo~er,positivereactivityinsertion,andcoolanttemperaturedecrease.~~TheevaluationofagiventransientbeginswiththesysteminitialparametersshowninFSARTable15.O.3thatareinputtoaGE-coredynamicbehaviortransientcomputerprogram.ThecodeusedtoevaluatepressurizationeventsisdescribedinNEDO-24154andtheprogiamusedinnon-pressurizationeventsisdescribedinNEDO-10802.TheoutputsofthisprogramalongwiththeinitialMCPRformtheinputforfurtheranalysesofthethermallylimitingbundlewiththesinglechanneltransientthermalhydraulicTASCcodedescribed"inNEDE-25149~.TheprincipalresultofthisevaluatonisthereductioninMCPRcausedbythetransient.ThepurposeoftheKffactorofFigure3.2.3+istodefineoperatinglimitsatotherthanratedcoreflowconditions.AtlessthanlOOXofratedflowtharequiredMCPRistheproductoftheMCPRandtheKfactorTh.eKffactorsassurethattheSafetyLimitMCPRwi11notbevio}afed.TheKrfactorswerederivedusingTHERMALPOHERandcoref1owcorrespondingtd1,S.Xofratedsteamflow.TheKffactorswerecalculatedsuchthatforthemaximumcoreflowrateandthecorrespondingTHERMALPOMERalongthe105%ofratedsteamflowcontrolline,thelimitingbundle'srelativepowerwasadjusteduntiltheMCPRwasslightlyabovetheSafetyLimit.Usingthisrelativebundlepower,theMCPRswerecalculatedatdifferentpoints-alongthe105Kofratedsteamflowcontrol'inecorrespondingtodifferentcoreflows.TheratiooftheMCPRcalculatedatagivenpointofcoreflow,dividedbytheoperatinglimitMCPR,determinestheKf.NINEMILEPOINT-UNIT283/42-4
13/4.4REACTORCOOLANTSYSTEM><<~F8~'tPPPV@FitBASES3/4.4.1RECIRCULATIONSYSTEM@gal~~~c+k+viset'+pTheobjectiveofGEBMRplantandfueldesignistoprovidestableoperationwithmarginoverthenormaloperatingdomain.However,atthehighpower/lowflowcorneroftheoperatingdomain,asmallprobabilityoflimitcycleneutronfluxoscillationsexistsdependingoncombinationsof'operatingconditions(e.g.,rodpattern,powershape).Toprovideassurancethatneutron,flux1imitcycleoscillationsaredetectedandsuppressed,APRHandLPRMneutronfluxnoiselevelsshouldbemonitoredwhileoperatinginthisregion.StabilitytestsatoperatingBMRswerereviewedtodetermineagenericregionofthepower/flowmapinwhichsurveillanceofneutronfluxnoiselevelsshouldbeperformed.Aconservativedecayratioof0.6was.chosenasthe'basesfordeterminingthegenericregionforsurveillancetoaccountfortheplanttoplantvariabilityofdecayratiowithcoreandfueldesigns.Thisgenericregionhasbeendeterminedtocorrespondtoacore-flowofless--thanorequalto45KofratedcoreflowandaTHERMALPOMERgreaterthanthatspecifiedinFigure3.4.1.1-1.Plantspecificcalculationscanbeperformedtodetermineanapplicableregionformonitoringneutronfluxnoiselevels.Inthiscasethedegreeofconservatismcanbereducesinceplanttoplantvariabilitywouldbeeliminated.Inthiscase,adequatemarginwillbeassuredbymonitoringtheregionwhichhasadecayratiogreaterthanorequalto0.8.e.Neutronfluxnoiselimitsarealsoestablishedtoensureearlydetectionoflimitcycleneutronfluxoscillations.BMRcorestypicallyoperatewithneutronfluxnoisecausedbyrandomboilingandflownoise.Typicalneutron.fluxnoiselevelsof1-X2ofratedpower(peak-to-peak)havebeenreportedfortherangeoflowtohighrecirculationloopflowduringbothsingleanddualrecirculationloopoperation.Neutronfluxnoiselevelswhichsignifi-cantlyboundthesevaluesareconsideredinthethermal/mechanicaldesignofGEBMRfuelandarefoundtobeofnegligibleconsequence.Inaddition,sta-bilitytestsatoperatingBMRshavedemonstratedthatwhenstabilityrelatedneutron'fluxlimitcycleoscillationsoccurtheyresultinpeak-to-peakneutronfluxlimitcyclesof5-10timesthetypicalvalues.Therefore,actionstakentoreduceneutronfluxnoiselevelsexceedingthree(3)timesthetypicalvaluearesufficienttoensureearlydetectionoflimitcycleneutronfluxoscillations.Typically,neutronfluxnoiselevelsshowagradualincreaseinabsolutemagnitudeascoreflowisincreased(constantcontrolrodpattern)withtworeactorrecirculationloopsinoperation.Therefore,thebaselineneutronNINEMILEPOINT-UNIT2B3/44-1
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEMRfÃF~>up~)g);yBASES3/4.4.1RECIRCULATIONSYSTEM(Continued)fluxnoiselevelobtainedataspecifiedcoreflowcanbeappliedover'arangeofcoreflows.Tomaintainareasonab1evariationbetweenthelowflowandhighflowendoftheflowrange,therangeoverwhichaspecificbaselineisappliedshouldnotexceed20Kofratedcoreflowwithtworecirculationloopsinoperation.Oatafromtestsandoperatingplantsindicatethatarangeof20Kofratedcoreflowwillresultinapproximatelya50Kincreaseinneutronfluxnoiselevelduringoperationwithtworecirculationloops.Baselinedatashou1dbetakennearthemaximumrod1ineatwhichthemajorityofoperationwilloccur.However,baselinedatatakenatlowerrodlines(i.e.,lowerpowerwillresultinaconservativevaluesincetheneutronf1uxnoiselevelisproportionaltothepowerlevelatagivencoref1ow.Aninoperablejetpumpisnot,initself,asufficientreasontodeclarearecirculationloopinoperable,butitdyes,incaseofadesign-basis-accident,increasetheblowdownareaandreducethecapabilityofrefloodingthecore;thus,therequirementforshutdownofthe'facilitywithajet-pumpinoperable.Jet'pumpfailurecanbedetectedbymonitoringjetpumpperformanceonaprescribedschedulefor'ficantderadation.WoVactScu.toaoa0C0Recirculationoopfowmiasmacimitsaresncompl>ancewiththeECCSLOCAanalysisdesigncriteria~ThelimitswillensureanadequatecoreflowcoastdownfromeitherrecirculationloopfollowingaLOCA.AG'pl~QwA4~bt5Pp"tInordertopreventunduestressonthevesselnozzlesandbottomheadregion,therecirculationlooptemperaturesshallbewithin504Fofeachotherpriortostartupofanidleloop.Thelooptemperaturemustalsobewithin50Fofthereactorpressurevesselcoolanttemperaturetoprevermalshocktotherecirculationpumpandrecirculationnozzles.~0Il3/4.4.2SAFETY/RELIEFVALVESK8p).aceui~useThesafety/reliefvalvesoperateduringapostulatedATWSeventto'preventthereactorcoolantsystembeingpressurizedaboveadesignallowablevalueof=1375psiginaccordancewiththeASMECode.Atotalof17OPERABLEsafety/reliefvalvesisrequiredtolimitlocalpressureatactivecomponentstowithinASMEIIIallowabledesignvalues(ServiceLevelA).AllotherappropriateASMEIIIlimitsarealsoboundedbythisrequirement.Oemonstrationofthesafety-reliefvalveliftsettingswilloccuronlyduringshutdownandwillbeperformedinaccordancewiththeprovisionsofSpecification4.0.5.NINEMILEPOINT-UNIT2B3/44-2NGVRO
Theimpactofsinglerecirculationloopoperationuponplantsafetyisassessedandsh'owsthatsingle-loopoperationispermittediftheMCPRfuelcladdingsafetylimitisincreasedasnotedbySpecification2.1.2,APRMscram'ndcontrolrodblocksetpointsareadjustedasnotedinTables2.2.1-1and3.3.6.2,respectively,MAPLHGRlimitsaredecreasedbythefactorgiveninSpecification3.2.1,andMCPRoperatinglimitsareadjustedperSection3/4.2.3.Additionally,surveillanceonthevolumetricflowrateoftheoperatingrecirculationloopisimposedtoexcludethepossibilityofexcessivecoreinternalsvibration.Thesurveillanceondifferentialtemperaturesbelow30%>>.THERMALPOWERor50K+ratedrecirculationloopflowistomitigatetheunduethermalstressonvesselnozzles,recirculationpumpandvesselbottomheadduringtheextendedoperationofthesinglerecirculationloopmode.INSERT"F"Inthecasewherethemismatchlimitscannotbemaintainedduringtwoloopoperation,continuedoperationispermittedinasinglerecirculationloopmode.INSERT"G4Sudden-equalization'ofatemperaturedifference145'Fbetweenthereactorvesselbottomheadcoolantandthecoolantintheupperregionofthereactorvesselbyincreasingcoreflowratewouldcauseunduestressinthereactorvesselbottomhead.Initialvalues.ThefinalvaluesaredetermineddutingstartuptestingbaseduponthethresholdTHERMALPOWERandrecirculationloopflowwhichwillsweepthecoldwaterfromthevesselbottomhead,preventingsaturation.
ATTACHMENTEENDOFCYCLE-RECIRCULATIONPUHPTRIPINOPERABLEANDTURBINEBYPASSINOPERABLEPROPOSEDTECHNICALSPECIFICATIONCHANGES
POWER'ISTRIBUTION'LIMITS3/4.'2'3'MINIMUMCRITICALPOWERRATIOt.IMITINGCONDITIONFOROPERATION3.2.3TheMINIMUMCRITICALPOWERRATIO(MCPR)shallbeequaltoorgreaterthantheMCPRlimitshowninFigure3.2.3-1timestheKfshowninFigure3.2.3-2with:~ave-~BA-Bwhere:A=0.86seconds,controlrodaveragescraminsertiontimelimittonotch39perSpecification3.1.3.3,B-0.688+1.65[~]t[0.052j~nave~i1Nii~1n~numberofsurveillancetestsperformedtodateincycle,Ni=numberofactivecontrolrodsmeasuredintheithsurveillancetest,averagescramtimetonotch39ofallrodsmeasuredintheithsurveillancetest,and'Nl=totalnumberofactiverodsmeasuredinSpecification4.1.3.2.a.APPLICABILITY:OPERATIONCONDITION1,whenTHERMALPOWERisgreaterthanorequalto25KofRATEDTHERMALPOWER.NINEMILEPOINTUNIT2
POWERDISTRIBUTIONLIMITSLIMITINGCONDITIONFOROPERATIONContinuedACTIONa.Withtheend-of-cyclerecirculationpumptripsysteminoperableperSpecification3.3A.2,operationmaycontinueandtheprovisionsofSpecification3.0.4arenotapplicableprovidedthat,withinonehour,MCPRisdeterminedtobeequaltoorgreaterthantheMCPRlimitshowninFigure3.2.3-1EOC-RPTinoperablecurve,timestheKfshowninFigure3e2e3~2~b.WiththemainturbinebypasssysteminoperableperSpecification3.7.8,'operationmaycontinue.andtheprovisionsofSpecification3.0e4arenotapplicableprovidedthat,withinonehour,MCPRisdeterminedtobeequaltoorgreaterthantheMCPRlimitshowninFigure3.2.3-1,main'urbinebypassinoperablecurvetimestheKfshowninFigure3.2.3-2.c.WithMCPRlessthantheapplicableMCPRlimitdeterminedfromFigures3.2.3-1and3.2.3-2,asapplicable,initiatecorrectiveactionwithin15minutestorestoreMCPRwithintherequiredlimit.RestoreMCPRtowithintherequiredlimitwithin4hours,ifnecessary,byreducingTHERMALPOWERtothelevelrequired.SURVEILLANCEREUIREMENTS'.2.3MCPR,with:a.~=1.0priortoperformanceoftheInitiaIscramtImemeasurementsforthecycleinaccordancewithSpecification4.1.3.2,orb.asdefinedinSpecification3.2.3usedtodeterminethelimitwithin72hoursoftheconclusionofeachscramtimesurveillancetestrequiredbySpecification4.1.3.2,c.TheprovisionsofSpecification4.0.4arenotapplicableshallbedeterminedtobeequaltoorgreaterthantheappTichbleMCPRlimitdeterminedfromFigures3.2.3-1and3.2.3-2:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLROOPATTERNforMCPR.d,TheprovisionsofSpecification4.0.4arenotapplicable.NINEMILEPOINTUNIT2 0 RBYPASSINOPERBLEEOC-RPTINOPELEEOC-RPTHAINTVRBINEBYPS1.00.800.4TAU,wFIGVRE3.2.3-1MINIMUMCRITICALPOWERRATIO,MCPR,vsTAUATRATEDFLOW0.2
M*trl81~41Z1.3~WWIoIII7%MJ~1.21.00.95020304060'OREFMM,PerceptIi~si~renavt.ac1tlNpTTAHAFPFAfFNTCOREFLOE70='090100
INSTRUMENTATIONPiPvPF5gpss~,/gopgEND-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.4.2Theend-of-cyclerecirculationpumptrip(EOC-RPT)systeminstrumentationchannelsshowninTable3.3.4.2-1shallbeOPERABLEwiththeir.tripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.4.2-2andwiththeEND-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSETIMEasshowninTable3.3.4.2-3.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorIIIIIPIIIIIIIPPIPIIPIII.ACTION:Withanend-of>>cyclerecirculationpumptripsysteminstrumentationchanneltripsetpointlessconservativethanthevalueshownintheAllowableValuescolumnofTable3.3.4.2-2,declarethechannelinoperableuntilthechannelisrestoredtoOPERABLEstatuswiththechannelsetpointadjustedconsistentwiththeTripSetpointvalue.b.cWiththenumberofOPERABLEchannelsonelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforoneorbothtripsystems,placetheinoperablechannel(s)inthetrippedconditionwithinonehour.WiththenumberofOPERABLEchannelstwoormorelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforonetripsystemand:1.Iftheinoperablechannelsconsistofoneturbinecontrolvalvechannelandoneturbinestopvalvechannel,:placebothinoperablechannelsinthetrippedconditionwithinonehour.2.Iftheinoperablechannelsincludetwoturbinecontrolvalvechannelsortwoturbinestopvalvechannels,declarethetripsysteminoperable.Withonetripsysteminoperable,restoretheinoperabletripsystemtoOPERABLEstatuswithin72hoursor+Cg[ogDl/laWithbothtnpsystemsnoperable,resto'reatleastonetripsystemtoOPERABLEstatuswithinonehourorPcziaa.~QQ,3NINEMILEPOINT-UNIT23/43-44HOV20pg
PLANTSYSTEMS3/4.7.9MAINTURBINEBYPASSSYSTEMPciggp$(fpfPcj+gQ~'l/LIMITIHQCONDITIONFOROPERATION3.7.9ThemainturbinebypasssystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITION1whenTHERMALPOWERisgreaterthanorqqqfI%TEDlllBIMLPIIIIER.ACTION:Withthemainturbinebypass%El/AifLEstatuswithin1houror~t2<3>SURVEILLANCEREUIREMENTSsysteminoperable,restorethesystemtoPerformingasystemfunctionaltestwhichincludessimulatedautomaticactuationandverifyingthateachautomaticvalveactuatestoitscorrectposition.2.DemonstratingTURBINEBYPASSSYSTEMRESPONSETIMEmeetsthefollowingrequirementswhenmeasuredfrominitialmovementofthemainturbinestoporcontrolvalve:4.7.9Themainturbinebypasssystem'sha11bedemonstratedOPERABLE:a.Atleastonceper18monthsby:1.a~80Koftheturbinebypasssystemcapacityshallbeestab-lishedwithin0.3seconds,andb.Bypassvalveopeningshallstartinlessthanorequalto.0.1seconds.NINEMILEPOINT-UNIT23/47-35
POWERDISTRIBUTIONLIMITSBASES3/4.2.3MINIMUMCRITICALPOWERRATIOTherequiredoperatinglimitMCPRsatsteadystateoperatingconditionsasspecifiedinSpecification3.2.3arederivedfromtheestablishedfuelcladdingintegritySafetyLimitMCPRof1.06,andananalysisofabnormaloperationaltransients.Foranyabnormaloperatingtransientanalysisevalua-tionwiththeinitialconditionofthereactorbeingatthesteadystateoperatinglimit,itisrequ'iredthattheresultingMCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytimeduringthetransientassuminginstrumenttripsettinggiveninSpecification2.2.ToassurethatthefuelcladdingintegritySafetyLimitisnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtran-sientshavebeenanalyzedtodeterminewhichresultinthelargestreductioninCRITICALPOWERRATIO(CPR).Thetypeoftransientsevaluatedwerelossofflow,increaseinpressureandpower,positivereactivityinsertion,andcoolanttemperaturedecrease.ThelimitingtransientyieldsthelargestdeltaMCPR.WhenaddedtotheSafetyLimitMCPRof1.06,therequiredminimumoperatinglimitMCPRofSpecification3.2.3isobtainedandpresentedinFigure3.2.3-1.TheevaluationofagiventransientbeginswiththesysteminitialparametersshowninFSARTable15.0.3thatareinputtoaGE"coredynamicbehaviortransientcomputerprogram.ThecodeusedtoevaluatepressurizationeventsisdescribedinNEDO-24154andtheprogramusedinnon-pressurizationeventsisdescribedinNEDO-10802.TheoutputsofthisprogramalongwiththeinitialMCPRformtheinputforfurtheranalysesofthethermallylimitingbundlewiththesinglechanneltransientthermalhydraulicTASCcodedescribedinNEDE-25149~i.TheprincipalresultofthisevaluationisthereductioninMCPRcausedbythetransient.'IThepurposeoftheKffacto~ofFigure3.2.3+istodefineoperatinglimitsatotherthanratedcoreflowconditions.Atlessthan100KofratedflowtherequiredMCPRistheproductoftheMCPRandtheK~factor.TheKffactorsassurethattheSafetyLimitMCPRwillnotbeviolated.TheK~factorswerederivedusingTHERMALPOWERandcoreflowcorrespondingtd105Kofratedsteamflow.TheKffactorswerecalculatedsuchthatforthemaximumcoreflowrateandthecorrespondingTHERMALPOWERalongthe105Kofratedsteamflowcontrollinethelimitingbundle'srelativepowerwasadjusteduntiltheMCPRwasslightlyabovetheSafetyLimit.Usingthisrelativebundlepower,theMCPRswerecalculatedatdifferentpointsalongthe105Kofratedsteamflowcontrol'inecorrespondingtodifferentcoreflows.TheratiooftheMCPRcalculatedatagivenpointofcoreflow,dividedbytheoperatinglimitMCPR,determinestheKf.NINEMILEPOINT-UNIT283/42-4i ~' ATTACHMENTFSINGLELOOPOPERATIONANALYSIS
NMPZAPPENDIX15.BTABLEOFCONTENTS15.BRECIRCULATIONSYSTEMSINGLE-LOOPOPERATION~Pae15.B.1-115.B.1INTRODUCTIONANDSUMMARY.15.B.1-1.15.B.2MCPRFUELCLADDINGINTEGRITYSAFETYLIMIT15.B.2.1CoreFlowUncertainty15.B.2.1.1CoreFlowMeasurementDuringSingle-LoopOperation15.B.2.1.2CoreFlowUncertaintyAnalysisI15.B.2.2TIPReadingUncertainty15.B.2-115.B.2>>115.B.2-115.B.2-215.B.2-415.B.3MCPROPERATINGLIMIT15.B.3.1AbnormalOperationalTransients15.B.3.1.1FeedwaterControllerFailure-MaximumDemand15.B.3.1.2GeneratorLoadRejectionWithBypassFailure.15.B.3.1.3Su@naryandConclusions.15.B.3.2RodWithdrawalError.15.B.3.3OperatingMCPRLimit15.B.3-115.B.3-115.B.3-215.B.3-415.B.3-515.B.3-515.B.3-715.B.4STABILITYANALYSIS15.B.4.1Phenomena15.B.4.2CompliancetoStabilityCriteria15.B.4-115.B.4-115.B.4-215.B.5LOSS-OF-COOLANTACCIDENTANALYSIS15.B.5.1BreakSpectrumAnalysis15.B.5.2Single-LoopMAPLHGRDetermination15.B.5.3SmallBreakPeakCladdingTemperature15.B.5-115.8.5-215.B.5-215.B.5-315.8-i
NMP2TABLEOFCONTENTS(Continued)~Pae15.B.6CONTAINMENTANALYSIS15.B.6-115.B.7MISCELLANEOUSIMPACTEVALUATION15.B.7.1.AnticipatedTransientMithoutScramImpact15.B.7.2FuelMechanicalPerformance15.B.7.3VesselInternalVibration15.B.7-115.B.7-115.B.7-115.B.7-115.B.8REFERENCES15.B.S-l15.B-'ii
NMP2LISTOFTABLESNUNBERTIT1EPAGE15.B.3-1InputParametersandInitialConditions15.B.3-8,9,1015.B.3-2SequenceofEventsforFeedwaterController15.B.3-11Failure,MaximumDemand(Figure15.B.3-2)'5.B.3-3Sequence.ofEventsforGeneratorLoadRejectionMithBypassFailure(Figure15.B.3-3)15.B.3-1215.B.3'-4Summary.ofTransientPeakYalueandCPRResults15.B.3-1315.8.6-1ComparisonofContainmentPeakPressures15.B.6-3~~15.B-iii
LISTOFFIGURESNUMBERTITLEPAGE15.B.2-1IllustrationofSingleRecirculationLoopOperationFlows15.B.2-615.8,3-1PeakDomePressurevs.InitialPowerLevel,15.B.3-14LRBPFatEOC15.B.3-2FeedwaterControllerFailure-MaximumDemand15.B.3-15,75%Power,60%Flow16,17,1815.B.3-3GeneratorLoadRejectionwithBypassFailure15.B.3-19,75KPower,60%Flow20,21,2215.B.5-1UncoveredTimevs.BreakArea-SuctionBreak,LPCSDieselGeneratorFailure15.B.5-415.B.6<<1DrywellandWetwellPressureResponses,-15.B-6.4RecirculationBreak,5MPower,35%CoreFlow15.B.6-2DrywellandWetwellTemperatureResponses-15.B-6.5RecirculationLineBreak,55%Power,35KCoreFlow15.B-iv
NHP215.BRECIRCULATIONSYSTEMSSINGLE-LOOPOPERATION15.B.1INTRODUCTIONANDSUMMARYSingle-loopoperation(SLO)atreducedpowerishighlydesirableintheeventrecirculationpumporothercomponentmaintenancerendersoneloopinoperative.To.justifysingle-loopoperation,accidentsandabnormaloperationaltransientsassociatedwithpoweroperations,aspresentedinSections6.2and6."3andthemaintextofChapter15.0,werereviewedforthesingle-loopcasewithonlyonepumpinoperation.ThisappendixpresentstheresultsofthissafetyevaluationfortheoperationoftheNineMilePointUnit2(NMP2)withsinglerecirculationloopinoperable.ThisevaluationisperformedforGE-6fueledNHP2onaninitialcyclebasisandisapplicabletoGE-6fuelednormalinitialcycleoperation.TheconditionsarethoseofcontinuedoperationintheoperatingdomaincurrentlydefinedinFigure4.4:5ofChapter4uptomaximumpowerofapproximately70%ofrated.IncreaseduncertaintiesinthecoretotalflowandTraversingIn-CoreProbe(TIP)readingsresultedina0.01incrementalincreaseintheMinimumCriticalPowerRatio(MCPR)fuelcladdingintegrity'afetylimitduringsingle-loopoperation.NoincreaseinratedHCPRoperatinglimitandnochangeintheflowdependentMCPRlimit(MCPRf)isrequiredbecauseallabnormaloperationaltransientsanalyzedforsingle-loopoperationindicatedthatthereismorethanenoughMCPRmargintocompensateforthisincreaseinHCPRsafetylimit.Therecirculationflowratedependentrodblockandscramsetpointequationgivenin.Chapter16(TechnicalSpecifications)areadjustedforone-pumpoperation.hThermal-hydraulicstability.wasevaluatedforitsadequacywithrespecttoGeneralDesignCriteria12(10CFR50,AppendixA).ItisshownthatSLOsatisfiesthisstabilitycriterion.ItisfurthershownthattheincreaseinneutronnoiseobservedduringSLOisindependentofsystemstabilitymargin.HTK:jsL11151415.8.1-1 I,<<l'I NMP24Topreventpotentialcontroloscillationsfromoccurringintherecircu-lationflowcontrolsystem,thef1owcontrollershouldbeinmastermanual.forsingle-1oopoperation.ThelimitingMaximumAveragePlanarLinearHeatGenerationRate(MAPLHGR)reductionfactorforsingle-loopoperationiscalculatedtobeO.Sl.ThecontainmentresponseforaDesignBasisAccident(DBA)recirculationlinebreakwithsingle-loopoperationisboundedbytheratedpower.two-loopoperationanalysispresentedinSection6.2.Thisconclusioncoversa11single-loopoperationpower/flowconditions.TheimpactofsingleloopoperationontheAnticipatedTransientWithoutScram(ATMS)analysiswasevaluated.ItisfoundthatallATWSacceptancecriteriaaremetduringSLO.~rThefuelthermalandmechanicaldutyfortransienteventso'ccurringduringSLOisfoundtobeboundedbythefueldesignbases.TheAveragePowerRangeMonitor(APRM)fluctuationshouldnotexceedafluxamplitudeof15%ofratedandthecoreplatedifferentialpressurefluctuationshouldnotexceed3.2psipeaktopeaktobeconsistentwit5thefuelrodandassemblydesignbases.Arecirculationpumpdriveflow.limitisimposedforSLO.Thehighest,driveflowthatmeetsacceptablevesselinternalvibrationcriteriaisthedriveflowlimitforSLO.TheexpectedallowabledriveflowinSLOisapproximately41,000gpm.ActualdriveflowflimitinSLOwillbe.determinedduringthestartuptestprogramatNMPZ.HTK:9sL11151415.B.1-2
NMP215.B.2MCPRFUELCLADDINGINTEGRITYSAFETYLIMIT~<<ExceptforcoretotalflowandTIPreading,theuncertaintiesusedinthe,statisticalanalysistodeterminetheMCPRfuelcladdingintegritysafetylimitarenotdependentonwhethercoolantflowisprovidedbyoneortworecirculationpumps.Uncertaintiesusedinthetwo-loopoperationanalysisaredocumentedintheFSAR.A6Xcoreflogmeasurementuncer-taintyhasbeenestablishedforsingle-loopoperation(comparedto2.5'Lfortwo-loopoperation).Asshownbelow,thisvalueconservativelyreflectstheonestandarddeviation(onesigma)accuracyofthecoreflowmeasurementsystemdocumentedinReference15.B.8-1.TherandomnoisecomponentoftheTIPreadinguncertaintywasrevisedforsinglerecircu-lationloopoperationtoreflecttheoperatingplanttestresultsgiveninSubsection15.B.2.2.Thisrevisionresultedinasingle-loopoperationprocesscomputereffectiveTIPuncertaintyof6.8%ofinitialcoresand9.1%forreloadcores.Comparabletwo-loopprocesscomputeruncertaintyvaluesare6.3Cforinitialcoresand8.7%forreloadcores.TheneteffectofthesetworeviseduncertaintiesisaD.OlincreaseintherequiredMCPRfuelcladdingintegritysafetylimit.15.B.2.1CoreFlowUncertaint15.B.2.1.1CoreFlowMeasurementDurinSinle-Loo0erationThejetpumpcoreflowmeasurementsystemiscalibratedtomeasurecoreflowwhenbothsetsofjetpumpsareinforwardflow;totalcoreflowis.thesumoftheindicatedloopflows.Forsingle-loopoperation,however,someinactivejetpumpswillbebackflowing(atactivepumpflowaboveapproximately38%).Therefore,themeasuredflowinthebackflowingjetpumpsmustbesubtractedfromthemeasuredflowintheactivelooptoobtainthetotalcoreflow.Inaddition,thejetpumpcoefficientisdifferentforreverseflowthanforforwardflow,andthemeasurementofreverseflowmustbemodifiedtoaccountforthisdifference.Insingle-loopoperation,thetotalcoreflowisderivedbythefollowingformula:15.B.2-1
NMP2TotalCoreFlowActiveLoopIndicatedFlowInactiveLoopIndicatedFlowMhereC(=0.95)isdefinedastheratioof"InactiveLoopTrueFlow"to"InactiveLoopIndicated.Flow"."LoopIndicatedFlow"istheflowmeasuredbythejetpump"single-tap"loopflowsummersandindicators,whicharesettoreadforwardflowcorrectly.The0.95factorwastheresultofaconservativeanalysistoappropriatelymodifythesingle-tapflowcoefficientforreverseflow.+Ifamoreexact,lessconservativecoreflowisrequired,specialin-reactorcalibrationtestswouldhavetobemade.Suchcalibrationtestswouldinvolve:calibratingcoresupportplatehPversuscoreflowduringone-pumpandtwo-pumpoperationalongwith100%flowcontrollineandcalculatingthecorrectvalueofCbasedonthecoresupportplate4Pandtheloopflowindicatorreadings.15.B.2.1.2CoreFlowUncertafntAnalsisTheuncertaintyanalysisprocedureusedtoestablishthecoreflowuncertaintyforone-pumpoperationisessentiallythesameasfortwo-pumpoperation,withsomeexceptions.ThecoreflowuncertaintyanalysisisdescribedinReference15.B.8-1.Theanalysisofone-pumpcoreflowuncertaintyis.summarizedbelow.Forsingle-loopoperation,thetotalcoreflowcanbeexpressedasfollows(refertoFigure15.B.2-1):f+Theanalyticalexpectedvalueofthe"C"coefficientforNMP2is0.88.~15.B.2-2
where:MC=totalcoreflow,WA=activeloopflow,andinactiveloop(true)flow.Byapplyingthe"propagationoferrors"methodtotheaboveequation,thevarianceofthetotalflowuncertaintycanbeapproximatedby:Q2Q2CsysQ+a22VAT-arandQ2Q2randwhere:uncertaintyoftotalcoreflow;sysuncertaintysystematictobothloops;"Arandrandomuncertaintyof'activelooponly;WrandSrandomuncertaintyofinactivelooponly;Qcuncertaintyof"C"coefficient;andratioofinactiveloopflow(W>)toactiveloopflow(WA).15.B.2-3 0 NNP2Fromanuncertaintyanalysis,theconservative,boundingvaluesofa>,a<,eMandaCare1.6%,2.6%,3;5X,and2.8%,ArandIrandrespectively.Basedontheaboveuncertaintiesandaboundingvalueof0.36*for"a",thevarianceofthetotalflowuncertaintyisapproximately:Mhentheeffectof4.1%corebypassflowsplituncertaintyat12%(bo'undingca'se)bypassflowfraction-isaddedtothetotalcoreflowuncertainty,theactivecoolantflowuncertaintyis:2activecoolant0.12TZ.W(4.1%)'51Ã)~-whichislessthanthe6%flowuncertaintyassumedinthestatisticalanalysis.Insummary,coreflowduringone-pumpoperationismeasuredinaconser-vativewayanditsuncertaintyhasbeenconservativelyevaluated.15.B.2.2TIPREADINGUNCERTAINTYToascertaintheTIPnoiseuncertaintyforsinglerecirculationloopoperation,atestwasperformedatanoperatingBMR.Thetestw~sperformedatapowerlevel59.3'Xofratedwithasinglerecirculationpumpinoperation(coreflow46.3Nofrated).Arotationallysymmetriccontrolrodpatternexistedduringthetest.*Thisflowsplitratiovariesfromabout0.13to0.36.The0.36valueisaconservativeboundingvalue.TheanalyticalexpectedvalueoftheflowsplitratioforNMP2is~0.23.15.B.2-4
NMPZFiveconsecutivetraversesweremadewitheachoffiveTIPmachiness*'ivingatotalof25traverses.Analysisofthisdataresultedinanodal.TIPnoiseof2.85%.UseofthisTIPnoisevalueasacomponentoftheprocesscomputertotaluncertaintyresultsinaone-sigmaprocess...;computertotaleffectiveTIPuncertaintyvalueforsingle-loopoperationof6.SXforinitialcoresand9.1%forreloadcores.~~~15.B.2-5
I<~TotalCoreFlowQi~ActiveLoopFlowMg~inactiveLoopFlowNiaaaraNohawkPowerCoro.IllustrationofSingleRecirculationLoopOperationFlowsFigure.15.8.2-11S.B.2-6
NMP215.S.3MCPROPERATINGLIMIT15.B.3lABNORMALOPERATINGTRANSIENTSOperatingwithonerecirculationloopresultsinamaximumpoweroutputwhichisabout30'4belowthatwhichisattainablefortwo-pumpoperation.Therefore,theconsequencesofabnormaloperationtransientsfromone-loopoperationwillbeconsiderablylessseverethanthoseanalyzedfromatwo-loopoperationalmode.Forpressurization,flowincrease,flowdecrease,andcoldwaterinjectiontransients,theresultspresentedinChapter15boundboththethermalandoverpressureconsequencesofone-loopoperation.Figure15.B.3-1showstheconsequencesofatypicalpressurizationtransient(generatorloadrejection)asafunctionofpowerlevel.Ascanbeseen,theconsequences'fone-loopoperationareconsiderablylessbecauseoftheassociatedreductioninoperatingpowerlevel.Theconsequencesofflowdecreasetransientsarealsoboundedbythefullpoweranalysis.Asinglepumptripfromone-loopoperationislessseverethanatwo-pumptripfromfullpowerbecauseof'hereducedinitialpowerlevel.Theworstflowincreasetransientresultsfromrecirculationflowcon-trollerfailure,andtheworstcoldwaterinjectiontransientresultsfromthelossoffeedwaterheater.Fortheformer,theMCPRf(Kf)curveisderivedassumingbothrecirculationloopcontrollersfail.This,conditionproducesthemaximumpossiblepowerincreaseandhencemaximumhCPRfortransientsinitiatedfromlessthanratedpowerandflow.Whenoperatingwithonlyonerecirculationloop,theflowandpowerincreaseassociatedwiththisfailurewithonlyoneloopwillbelessthanthatassociatedwithbothloops;therefore,theKfcurvederivedwiththetwo-pumpassumptionisconservativeforsingle-loopoperation.Thelatterevent,lossoffeedwaterheating,isgenerallythemostseverecoldwaterincreaseeventwithrespecttoincreaseincorepower.Thiseventiscausedbypositivereactivityinsertionfromcoreinlet15.B.3-1 I ~.0:NHP.2\subcoolinganditisrelatively,insensitivetoinitialpower'evel.Agenericstatisticallossoffeedwaterheateranalysisusingdifferentinitialpowerlevelsandothercoredesignparametersconcludedone-pumpoperation.withlowerinitialpowerlevelisconservativelyboundedbythefullpowertwo-pumpanalysis.Inadvertentrestartoftheidlerecirculationpumphasbeenana1yzedintheFSAR(Chapter15.4.4)andisstillapplicableforsingle-loopoperation.'l,Fromtheabovediscussions,itisconcludedthatthetransientconsequencefromone-loopoperationisboundedbypreviouslysubmittedfullpoweranalyses.Themaximumpowerlevelthatcanbeattainedwithone-loop.operationisonlyrestricted'bytheHCPRandoverpressurelimitsestab-lishedfromafull-poweranalysis.Inthefollowingsections,theresultsoftwoofthemostlimiting/transientsanalyzedforsingle-loopoperationarepresented.Theyare,respectively:a.feedwaterflowcontrollerfailure(maximumdemand),(RlCF)b.generator.loadrejectionwithbypassfailure,(LRBPF).TheplantinitialconditionsaregiveninTable15.8.3-1~15.B.3.1.1FeedwaterControllerFailure-MaximumDemandThiseventispostulatedonthebasisofasinglefailureofacontrol.device,specificallyonewhichcandirectlycauseanincreaseincoolant'nventorybyincreasingthefeedwaterflow.Themostsevereapplicableeventisafeedwater,controllerfailuretomoximumflowdemand.Thefeedwatercontrollerisforcedtoitsupperlimitatthebeginningoftheevent.Withexcessfeedwaterflow,thewaterlevelrisestothehigh-levelreferencepointatwhichtimethefeedwaterpumpsandthemainturbinearetrippedandascramisinitiated..Table15.8.3-2liststhesequence15.8.3-2 0 NMP2ofevents.Figure.15.B.3-2showsthechangesinimportantvariablesduringthistransient.ThecomputermodeldescribedinReference15.B.8-2wasusedtosimulatethisevent.TheanalysishasbeenperformedwiththeplantconditionstabulatedfnTable15.B.3-1,excepttheinitialvesselwaterlevelatlevelsetpointL4forconservatism.Byloweringtheinitialwaterlevel,morecoldfeedwaterwillbeinjectedbeforeLevel8isreachedresultinginhigherheatfluxes.Thesamevoidreactivitycoefficientusedforthepressurizationtransientisappliedsinceamorenegativevalueconservativelyincreasestheseverityofthepowerincrease.Endofcycle(all,rodsout)scramcharacteristicsareassumed.Thesafety/reliefvalveactionisconservativelyassumedtooccurwithhigherthannominalsetpoints.'hetransientissimulatedbyprogramminganupperlimitfailureinthefeedwatersystemsuchthat145%ofratedfeedwaterflowoccursatthedesignpressureof1060psig.Sincethereactorisinitiallyoperatingatalowerpowerlevel,thefeedwaterspargerexperiencesapressurewhichismuchlowerthanthedesignpressure,hencethefeedwaterrunoutcapacityreaches167%ofinitialflow.ResultsThesimulatedfeedwatercontrollertransientisshowninFigure15.B.3-2.forthecaseof75Kpowerand60%coreflow.The'igh-waterlevelturbinetripandfeedwaterpumptripareinitiatedatapproximately6.4seconds.Scramoccurssimultaneouslyfromstopvalveclosure,andlimitstheneutronfluxpeakandfuelthermaltransientsothatnofueldamageoccurs.Table15.B.3-4givesasummaryofthetransientanalysisresults.ThecalculatedNCPRis1.20,whichiswellabovethesafetylimitNCPRof1.07sonofuelfailureduetoboilingtransitionispredicted.Thepeakvesselpressurepredictedis1134psigandiswellbelowtheASMElimitof1375psig."15.B.3-3
NMP215.8.3.1.2GeneratorLoadReectionMith8assFailureFastclosureoftheturbinecontro1valves(TCV)isinitiatedwheneverelectricalgriddisturbancesoccurwhichresultinsignificantlossofelectricalloadonthegenerator.Theturbinecontrolvalvesarerequiredtocloseasrapidlyaspossibletopreventoverspeedoftheturbine-generatorrotor.Closureofthemainturbinecontrolvalveswillincreasesystempressure.MitigationofpressureincreaseduringthistransientisaccomplishedbythescramandRPT.Alossofgeneratorelectricalloadat75%powerand60%flowunder.singlerecirculationloopoperationproducesthesequenceofeventslistedinTable15.8.3-3.Figure15.8.3-3showsthechangesinimportantvariablesduringthistransient.ThecomputermodeldescribedinReference15.8.8-2wasusedtosimulatethisevent.TheanalysishasbeenperformedwiththeplantconditionstabulatedinTable15.8.3-1,exceptthattheturbinebypassfunctionisassumedtofail.ThesimulatedgeneratorloadrejectionwithbypassfailureisshowninFigure15.B.3-3.Table15.8.3-4summarizesthetransientanalysisresults.Thepeakneutronfluxreachesabout166%ofratedandaveragesurfaceheatflux~peaksat106.5Kof,itsinitialvalue.Thepeakvesselpressurepredictedis1175psigandiswellbelowtheASMElimitof1375psig.ThecalculatedMCPRis1.27whichisconsiderablyabovethesafetylimitMCPRof1.07.15.8.3-4
NMP215.B.3.1.3SumnarandConclusionsThetransientpeakvalueresultsandtheCriticalPowerRatioresultsaresummarizedinTable15.B.3-4.Thistableindicatesthatforthetransienteventsanalyzedhere,theMCPRsforalltransientsareabovethesingle-loopoperationsafetylimitvalueof1.07.Itis:concludedtheoperatinglimitMCPRsestablishedfortwo-pumpoperationarealsoapplicabletosingle-loopoperationconditions.Forpressurization,Table15.B.3-4indicatesthepeakpressuresarebelowtheASHEcodevalueof1375psig.Hence,itisconcludedthepressurebarrierintegrityismaintainedundersingle-loopoperationconditions.15.B.3.2RODWITHDRAWALERRORTherodwithdrawalerroratratedpowerisgivenintheFSAR.Theseanalysesareperformedtodemonstrate,eveniftheoperatorignoresallinstrumentindicationsandthealarmwhichcouldoccurduringthecourseofthetransient,therodblocksystemwillstoprodwithdrawalataminimumcriticalpowerratio(MCPR)whichishigherthanthefuelcladdingintegritysafetylimit.Modificationoftherodblockequation(below)assurestheMCPRsafetylimitisnotviolated.TheAveragePowerRangeMonitor(APRM)rodblocksystemprovidesadditionalalarmsandrodblockswhenpowerlevelsaregrosslyexceeded.ModificationoftheAPRMrodblockequation(below)isrequiredtomaintainthetwolooprodblockversuspowerrelationshipwheninone.Lopoperation.One-pumpoperationresultsinbackflowthrough10ofthe20jetpumpswhiletheflowisbeingsuppliedintothelowerplenumfromthe10activejetpumps.Becauseofthebackflowthroughtheinactivejetpumps,thepresentrodblockequationwasconservativelymodifiedforuseduringone-pumpoperationbecausethedirectactive-loopflowmeasurementmaynotindicateactualflowaboveabout38%coreflowwithoutcorrection.15.B.3-5
Aprocedurehasbeenestablishedforcorrectingthe:APRMrodblockequationtoaccountforthediscrepancybetweenactualflowandindicatedflowintheactiveloop.ThispreservestheoriginalrelationshipbetweenAPRMrodblockandactualeffectivedriveflowwhenoperatingwithasingleloop.Thetwo-pumprodblockequationis:RB-mM+RB100-m(100)Theone-pumpequationbecomes:RB=mW+RB100-m(100)-mNwheredifferencebetween.two-loopandsingle-loopeffectivedriveflowatthesamecoreflow.Thisvalueisexpectedtobe5%ofrated(tobedeterminedbytheNiagaraMohawkPowerCorporation)RB=poweratrodblockin5.flowreferenceslopedriveflowinXofrated.toplevelrodblockat100%flow...RB10Iftherodblocksetpoint(RB100)ischanged,theequationmustberecalculatedusingthenewvalue.TheAPRMscramtripsettingsareflowbiasedinthesamemannerastheAPRHrodblocksetting.Therefore,theAPRMscramtripsettingsaresubjecttothesameproceduralchangesastherodblocksettingsdiscussedabove.15.B.3-6 0 NMPZ15.8.3.3OPERATINGMCPRLIMITForsingle-loopoperation,theoperatingMCPRlimitremainsunchangedfromthenormaltwo-loopoperationlimit.Althoughtheincreaseduncer-taintiesincoretotalflowandTIPreadingsresultedina0.01increaseinMCPRfuelcladdingintegritysafetylimitduringsingle-loopoperation(Section15.B.2),thelimitingtransientshavebeenanalyzedtoindicatethatthereismorethanenoughNCPRmarginduringsingle-loopoperationtocompensateforthisincreaseinsafetylimit.Forsingleloopoperationatoff-ratedconditions,thesteady-stateoperatingMCPRlimitisestablishedbytheKcurve.Thisensuresthe99.9Astatisticallimitrequirementisalwayssatisfiedforanypostulatedabnormaloperationaloccurrence.Sincethemaximumcoreflowrunoutduringsingle.loopoperationisonlyabout60'lofrated,thecurrentflowdependentKfcurvewhichisgeneratedbasedontheflowrunoutuptoratedcoreflowarealsoadequatetoprotecttheflowrunouteventsduringsingleloopoperation.'I15.B.3-7
TABLE15.B.3-1INPUTPARAMETERSANDINITIALCONDITIONS1.ThermalPowerLevel,MMtAnalysisValue2.SteamFlow,lbperhrAnalysisValue3.CoreFlow,lbperhr4..FeedwaterFlowRate,lbperhrAnalysisValue5.FeedwaterTemperature,'F6.VesselDomePressure,psig7.CorePressure,psig8.TurbineBypassCapacity,CNBR9.CoreCoolantInletEnthalpy,Btuperlb10.TurbineInletPressure,psigll.FuelLattice12.CoreAverageGapConductance,Btu/sec-ft'-'F13.CoreBypassFlow,514.RequiredMCPROperatingLimitOptionAOptionB15..MCPRSafetyLimit16.'opplerCoefficient4/'F17.VoidCoefficientC/lRatedVoids18.CoreAverageRatedVoidFraction,C19.ScramReactivity,$hK249210.28x10i65.10x1010.28x1039498198725.515.1'52PBxBR0.174411.841.441.401.0743.51tdtttttttmtdttdtt.t.d-ttforendofCycle1conditionbasedontheinputfromCRUNCHtape.15.B.3-8
NMP2TABLE15.B.3-1{Continued)INPUTPARAMETERSANDINITIALCONDITIONS20.ControlRodDriveSpeedPositionVersusTime21.JetPumpRatio,M22.Safety/ReliefValveCapacity,5NBR9103%of1177psigManufacturerguantityInstalled23.ReliefFunctionDelay,seconds24.ReliefFunctionResponseTimeConstant,sec.25.SetPointsforSafety/ReliefValvesSafetyFunction,psigReliefFunction,psig26.NumberofValveGroupingsSimulatedSafetyFunction,No.ReliefFunction,No.27.HighFluxTrip,lNBRAnalysisSetPoint(121x1.043)Figure15.0-33.16>113.85IKKERS180.40.11177,1187,1197,1207,12171106,11.16,1126,1136,114655126.228.HighPressureScramSetPoint,psig29.VesselLevelTrips,FeetAboveSeparatorSkirtBottomLevel8-(LB),FeetLevel4-(L4),FeetLevel3-(L3),FeetLevel2-(L2),Feet10716.1753.751.75-4.70815.B.3-9
NMPZ,TABLE15.B.3-1(Continued)INPUTPARAMETERSANDINITIALCONDITIONS30.APRMThermalTripSetPoint,CNBR8100%CoreFlow(117x1.043)31.RPTDelay,seconds32.TimeConstantofRecirculationPump'--Hotor,seconds~AnalysisValue33.SetPressureofATMSRecirculationPumpTrip,psig34.Tota1SteamLineVolume,ft'220.196.010804012Ihhittttf1fl1bythpwhere:2nJont=0t=inertiatimeconstant(sec)J=pumpmotorinertia(lb-ft)n~ratedpumpspeed(rps)g=gravitationalconstant(ft/sec)T~pumpshafttorque(ft-lb)015.B.3-10
NMP2TABLE15.B.3-2SEUENCEOFEVENTSFORFEEDWATERCONTROLLERFAILURE,XIUNiureTime-eecEvent0.6.46.46.46.56.69.510.015.2Initiatesimulatedfailuretotheupperlimitonfeedwaterflow.L8vesselIeveIsetpointtripsmainturbineandfeedwaterpumps.Reactorscramtripactuatedfrommainturbinestopvalvepositionswitches.Recirculationpumptrip(RPT)actuatedbystopvalvepositionswitches.Hainturbinestopvalvesclosedandturbinebypassvalvesstarttoopen.Recirculationpumpmotorcircuitbreakersopencausingdecreaseincoreflowtonaturalcirculation.Group1reliefvalvesactuated.Group2reliefvalvesactuated.Allreliefvalvesareclosed.15.B.3-11
TABLE15.B.3-3SEUENCEOFEVENTSFORGENERATORLOADREJECTIONWPUsureTime-sec(-)0.015(approx.)EventTurbine-generatordetectslossofelectricalload.Turbine-generatorloadrejectionsensingdevicestriptoinitiateturbinecontrolvalvefastclosure.0.070.100.19e2.12.22.42.52.8'.45.58.2Turbinebypassvalvesfailtooperate.Fastcontrolvalveclosure(FCY)initiatesscramtripandrecirculationpumptrip(RPT).Turbinecontrolvalvesclosed.Turbinebypassvalvesshouldstarttoopen-assumedtofail.Recirculationpumpmotorcircuitbreakersopenc'ausingdecreaseincoreflowtonaturalcirculation.Group1reliefvalvesactuated.Group2reliefvalvesactuated.Group3reliefvalvesactuated.Group4reliefvalvesactuated.Group5reliefvalvesactuated.FeedwaterpumpmotorstrippedonL8highwaterlevel.Group5reliefvalvesstarttoclose.Allreliefvalvesareclosed.15.B.3-12 1 NMP2TABLE15.B.3-4SUMMARYOFTRANSIENTPEAKVALUEANDCPRRESULTSInitialPower/Flow(5Rated)PeakNeutronFlux(5NBR)PeakHeatFlux(XInitial).'Peak'DomePressure{psig)PeakVesselBottomPressure{psig)RequiredInitialMCPROperatingLimitatSLOConditionaCPRTransientMCPRSLMCPRatSLOMargintoSLMCPRiRBPF75/60165.7106.5116011751.440.17*1.271.070.20FMCF75/60157.3113;8112011341.440.24+1.201.070.13dttddd15.B.3-13 0 )230)220)210K1200)190(.Ij180MithBvpassFa$1ure1170MithNormalBypass116070SO10011D~~lnlthil,PowerLevelj%NR)NiagaraMohawkPowerCorporatfoPeakDomePressurevs.Enftfa1Powerlevel,LRBPFat.EOC15.8.3-14Figure15.8.3-1
150;1NEUTRCjN2PERKFUE3AVESURF'1FEEDNRTE5VESSELSlLUXCENTERTEMPCEHERTFLUXFLGHEWNFLGHc)100.UJ50.LJUJCL0.10.15.TINEtSEC)20.-aNtAGARAHOHhl)KPOWERCORPORAT10NFeedwaterControllerFailure-HaximumDemand75KPower,60%FlowFigure15.B.3-2
~~1LEVEL(IN2NRSENS-.3NRSENSl~lCGHEINLI5DRtVEFLH-REF-SEP-SNIRT0LEVEL(INCHES)0LEVEL(INCHES)TFLGH(PCT)'2(PCT)100.50.3I.l0.0.10.15.TINE(SECl20.-10NIAGARANOHAMKPOHERCORPORATIONFeedwatetControllerFa)lure-Hax)mumDemand75KPower,60KFlowFigureisaB.3-2Corit'd. I 200.1VESSELP25TMLINE3TURBINEi)BYPASSSl5BELIEFVF6TURBSTEESRISE(PSI.)PRESBISE(PSI)RESBISE(PS[)ERHFLGH(PCT1LVEFLGN(PCT)MFLGN(PCT)j.00.~)0.-i00.0.Io.-TIME15.SEC)20.-10iHIhriARAHOHAWPOHERCORPORATIONFeedwaterControllerFai1ure-HaximimOemand75KPower,60%FlowFigure15i8)3-2Coated
lYGIOBEA2DGPPLEnl3SCHAHBFf4TGTAL0.5.'10.TINE(SEC)15.20.-LONIAGARANHAHKPOMERCORPORATIONFeedwaterControllerFa)lure-Max)mumOemand75'XPower,60%FlowF)gurel5.8.3-2hnt'd. I 150.iNEUTBGN2PERKFUEL3AVESURFf-~lFEEDNRTE5VESSElSLVXCENTERTEHPCEHEATFlUXFLClHERNFLUE100.'LJCLCCC)UJ50.CCMlL0.0.2.Q.6.TINE(SEC)NIAGARAMOHAHKPOWERCORPORATIONLoadRejectionMithBypassFailure75KPower,60KFlowFigurel5",P.3-3 4 200.LEVEL(IN2NRSENS1'.3NRSENSf;LICUREINL5DRIVEFLH-REF-SEP-SKIRT0LEVEL(INCHES)0LEVEI(.INCHES)TFLGH(PCT)H1(PCT).100.0.-100.2.6.TINE(SEC)>>loNIAtiARAHOHAMKPOMERCORPORATIONLoadRejectionMIthBypassFailure75KPower,60KFlowF)gure15,B.3-3Cont'd. '00 200.VESSELP2STMLINE3TURBINE4BELIEFVI-50IFFUSER6TURBSTEFSRISE(PSI)PRESRISE(PSI)RESRISE(PSI)LVEFLClH(PCT)FLGH2(PCT)MFLGNfPCT)3.00.0.-100.0.2.6.TINE..(SEC)8.-I0NlAGARAMOHAHKPOtlERCORPORATlONLoadRejectionw)thBypassFailure75KPower,6OXFlowF)gure15,8.3-3C8nVd.
1VGtDALATIVITY2DGPPIEBft.:BCTtVI'TY'.SCnnNnl-;rCTIVrTY.4(tGTHLBLf-CTIVITY0.-l.I-L3(ZUJCC2.TINE(SEC.)-iaNIAGARAMOHAMKPOMRRCORPORATIONLoadRejectlonwithBypassFailUre75KPower,60KFlowF)gure15,.8.3-3Coht'd.
NMP215.B.4STABILITYANALYSIS15.B.4.1PhenomenaTheprimarycontributingfactorstothestabilityperformancewithonerecirculationloopnotinservicearethepower/flowratioandtherecirculationloopcharacteristics.Atforcedcirculationwithonlyonerecirculationloopinoperation,thereactorcorestabilityisinfluencedbytheinactivdrecirculationloop.AscoreflowincreasesinSLO,theinactivejetpumpforwardflowdecreasesbecausethedrivingheadacrosstheinactivejetpumpsdecreaseswithincreasingcoreflow.Thereducedflowintheinactiveloopreducestheresistancethattherecirculationloopsimposeonreactorcoreflowperturbationstherebyaddingadestabilizingeffect.Atthesametimetheincreasedcoreflowresultsinalowerpower/flowratiowhichisastabilizingeffect.Thesetwocounteringeffectsresultinslightlydecreasedstabilitymargin{higherdecayratio)in'itiallyascoreflowisincreased(fromminimum)inSLO,andthenanincreaseinstabilitymargin(lowerdecayratio)ascoreflow.isincreasedfurtherandreverseflowintheinactiveloopisestablish'ed.AscoreflowisincreasedfurtherduringSLOandsubstantialreverseflowisestablishedintheinactiveloopanincreaseinjetpumpflow,coreflowandneutronnoiseisobserved.Acrossflowis;establishedintheannulardowncomerregionnearthejetpumpsuction.entrancecausedbythereverseflowoftheinactiverecirculationloop.Thiscrossflowinteractswiththejetpumpsuctionflowoftheactiverecirculationloopandincreasesthejetpumpflownoise.Thiseffectincreasesthetotalcoreflownoisewhichtendstodrivetheneutronfluxnoise.15.B.4-1
NHP2Todetermine'if+heincreasednoiseisbeingcausedbyreducedstabilitymarginasSLOcoreflowwasincreased,anevaluationwasperformedwhichphenomenologicallyaccountsforsingleloopoperationeffectsonstability,assummarized.inReference15.B.8-4.Themodelpredictionswereinitiallycomparedwithtestdataandshowedverygoodagreementforbothtwoloopandsinglelooptestconditions.AnevaluationwasperformedtodeterminetheeffectofreverseflowonstabilityduringSLO.Withincreasingreverseflow,SLOexhibitedslightlylowerdecayratiosthantwoloopoperation.,However,atcoreflowconditionswithnoreverseflow,SLOwasslightlylessstable.ThisisconsistentwithobservedbehaviorinstabilitytestsatoperatingBWRs(Reference15.8.8-5).Inadditiontotheaboveanalyses,thecrossflowestablishedduringreverseflowconditionswassimulatedanalyticallyandshown'tocauseanincreaseintheindividualandtotaljetpumpflownoise,whichisconsistentwithtestdata(Reference15.8.8-4).Theresults'ftheseanalysesandtestsindicatethatthestabilitycharacteristicsarenotsignificantlydifferentfromtwoloopoperation.Atlowcoreflow;SLOmaybeslightlylessstablethantwoloopoperationbutascoreflowisincreasedandreverseflowisestablishedthestabilityperformanceis.similar.Atevenhighercoreflowwithsubstantialreverseflowintheinactiverecirculationloop,theeffectofcrossflowontheflownoiseresultsinanincreaseinsystemnoise(jetpump,coreflowandneutronfluxnoise).15.8.4.2ComliancetoStabilitCriteriaConsistentwiththephilosophyappliedtotwoloopoperation,thestabilitycomplianceduringsingleloopoperationisdemonstratedonagenericba'sis.-Stabilityacceptancecriteriahavebeenestablishedtodemonstratecompliancewiththerequirementsset'orthin10CFR50,AppendixA,GeneralDesignCriterion(GDC)12(Reference15.B.8-6).GenericanalyseswhichcoverthosefuelscontainedintheGeneralElectricStandardApplicationforReloadFuel(Reference15.B.8-7throughAmendment10)havebeenperformed.Theanalysesdemonstratethatintheeventlimit15.B.4-2 E NMP2cycleneutronfluxoscillationsoccurwithintheboundsofsafetysystemintervention,specifiedacceptablefueldesignlimitsarenotexceeded.Sincethereactorcoreisassumedtobeinanoscillatorymode,thequestionofstabilitymarginduringSLOisnotrelevantfromasafetystandpoint(i.e.,theanalysisalreadyassumesnostabilitymargin)..Thefuelperformanceduringlimitcycleoscillationsischaracteristicallydependentonfueldesignandcertainfixedsystemfeatures(highneutronfluxscramsetpoint,channelinletorificediameter,etc.).ThereforetheacceptabilityofGEfueldesignsindependent'ofplantandcycleparametershasbeenestablished.OnlythoseparametersuniquetoSLOwhichaffectfuelperformanceneedtobeevaluated.Themajorconsidera-tionofSLOistheincreasedMinimumCriticalPowerRatio(MCPR)safetylimitcausedbyincreaseduncertaintiesinsystemparametersduringSLO.However,theincreaseinMCPRsafetylimit(0.01)iswellwithinthemarginofthelimitcycleanalyses(Reference15.B.8-6)andthereforeitisdemonstratedthatstabilitycompliancecriteriaaresatisfiedduringsingleloopoperation.Operationally,theeffectsofhigherflownoiseandneutronfluxnoiseobservedathighSLOcoreflow.arqevaluatedtodetermineifacceptablevesselinternalvibrationlevelsaremetandtodeterminetheeffectsonfuelandchannelfatigue,andarenotconsideredinthecompliancetostabilitycriteria.IServiceInformationLetter-380,Revision1{Reference15.B.8-8)hasbeendevelopedtoinformplantoperatorshowtorecognizeandsuppressunanticipatedoscillationswhenencounteredduringplantoperation.~~Asaresultoftheaboveanalysisandoperatorrecoamendations,theNRCstaffhasapprovedthegenericstabilityanalysisforapplicationtosingleloopoperation(Reference15.B.8-9)providedthattherecommenda-tionsofSIL-380havebeenincorporatedintothePlantTechnicalSpecifica-tions.15.B.4-3
NMP215.B.5LOSS-OF-COOLANTACCIDENTANALYSISIftworecirculationloopsareoperatingandapipebreakoccursinoneofthetworecirlationloops,thepumpintheunbrokenloopisassumedtoimmediatelytripandbegintocoastdown.Thedecayingcoreflowduetothepumpcoastdownresultsinveryeffectiveheattransfer(nucleateboiling)duringtheinitialphaseoftheblowdown.Typically,nucleateboilingwillbesustainedduringthefirst5to9secondsaftertheaccident,forthedesignbasisaccident(DBA).Ifonlyonerecirculationloopisoperating,andthebreakoccursintheoperatingloop,continuedcoreflowisprovidedonlybynaturalcirculationbecausethevesselisblowingdowntothereactorcontainmentthroughbothsectionsofthebrokenloop.Thecoreflowdecreasesmorerapidlythaninthetwo-loopoperatingcase,andthedeparturefromnucleateboilingforthehighpowernodemightoccur1or2secondsafterthepostulatedaccident,resultinginmoreseverecladdingheatupfortheone-loopoperatingcase.Inadditiontochangingtheblowndownheattransfercharacteristics,losingrecirculationpumpcoastdownflowcanalsoaffectthesystem'nventoryandrefloodingphenomena.Ofparticularihterestarethechangesinthehigh-powernodeuncoveryandrefloodingtimes,thesystempressureandthetime'ofratedcoresprayfordifferentbreaksizes.One-loopoperationresultsinsmallchangesinthehigh-powernodeuncoverytimesandtimesofratedspray.Theeffectoftherefloodingtimesforvariousbreaksizesisalsogenerallysmall.~~AnanalysisofsinglerecirculationloopoperationusingthemodelsandassumptionsdocumentedinReference15.B.S-10wasperformedforNMP2.Usingthismethod,SAFE/REFLOODcomputercoderunsweremadeforafullspectrumoflargebreaksizesforonlytherecirculationsuctionlinebreaks(mostlimitingforNMP2).Becausetherefloodminusuncoverytimeforthesingle-loopanalysisissimilartothetwo-loopanalysis,themaximumplanarlinearheatgenerationrate(MAPLHGR)curvesweremodified15.B.5-1
'NMP2byderivedreductionfactorsforuseduringonerecirculationpumpoperation.15.B.5.1BREAKSPECTRUMANALYSISSAFE/REFLOODcalculationswereperformedusingassumptionsgiveninSectionII.A.7.3.1ofReference15.B.8-10.Hotnodeuncoveredtime(timebetweenuncoveryandreflood)forsingle-loopoperationiscomparedtothatfortwo-loopoperationinFigure15.B.5-1.Thetotaluncoveredtimefortwoloopoperationis127secondsforthe100%DBAsuctionbreak.Thisisthemostlimitingbreakfortwo-loopoperation.Forsingle-loopoperation,thetotaluncoveredtimeis127secondsandforthe100%DBAsuctionbreak.Thisisthemostlimitingbreakforsingle-loopoperation.15.B.5.2SI'NGLE-LOOPMAPLHGRDETERMINATIONThesmalldifferencesinuncoveredtimeandrefloodtimeforthelimitingbreaksizewouldresultinasmallchangeinthecalculatedpeakcladdingtemperature.Therefore,asnotedasReference15.B.8-10,theoneandtwo-loopSAFE/REFLOODresultscanbeconsideredsimilarandthegenericalternateproceduredescribedinSectionII.A.7.4.of:thisreferencewasusedtocalculatetheMAPLHGRreductionfactorsforsingle-loopoperation.Themostlimitingsingle-loopoperationMAPLHGRreductionfactor(i.e.,yieldingthelowestMAPLHGR)forGEGBx8retrofit-fuelis0.81.One-loopoperationMAPLHGRvaluesarederivedbymultiplyingthecurrenttwo-loopMAPLHGRvaluesbythereductionfactor(0.81).AsdiscussedinReference15.B.8-10,singlerecirculationloopMAPLHGRvaluesareconservativewhencalculatedinthismanner.15.B.5-2
15.B.5.3SMALLBREAKPEAKCLADDINGTEMPERATURESectionII.A.7.4.4.2ofReference15.B.8-10discussesthelowsensitivityofthecalculatedpeakcladdingtemperature(PCT)totheassumptionsusedintheone-pumpoperationanalysisand.thedurationof'ucleateboiling.As,thisslightincrease(~50'F)inPCT~isoverwhelminglyoffsetbythedecreasedMAPLHGR(equivalentto300'Fto500'FPCT)forone-pumpoperation,thecalculatedPCTvaluesforsmallbreakswillbewellbelowthe1522'FsmallbreakPCTvaluepreviouslyreportedforNMP2,andsignificantlybelowthe2200'FlOCFR50.46claddingtemperaturelimit.I15.B.5-3
'I~III~I~III~EEERERREEEHRREHEEEEMEEEEERMEEEEHEESEEEEEEEHaaaararrarrraaarararaMaxaxaraxxarxxMNraaxxraaaaaaaaaaaaaxrrrrraxyaaxaaxxxxxxxxxaarxxaxrxxxxxrNaaaaQiriHQRxrxsrrrrrxaMNNNNNNNRXNRNNXQRNNNNRQXQ55xaRNRxarraasxaraaraMNNRNNNNNNAaxxaxxaxxxaraxaax~RRRQRxxrraa5aaxaarxMNMNNNNNRNRMQMRMNXQXQ~EERBRHEHBMMHEMEEHMEMEEESEMMEEEEEEEMIararrraaraararrrranaxrxaxxaxxxxraxrNxaxxaxrrrxaxI'NRXNRQaaarxaaaaarrxraxrxaxrrrxrxarxxrxaarxQRNNaarxxxaaarvmaxrrraxaaxmarMxaaxarxxaxnaQXNNaaggghrxxrrxrxrrraaxrxRRNRMNNNRMxxaxxraxraaQRNNggrrraaararxmrrrrrraxaxaxxaxMNrxraxxrarxarrNXNNgggaxxsaaxxx%%aarraxaxxrxaxxaxxrNRNMNNNNNRNRRNNRNsrrrxxaraararaxrrxraxarxxxxMxaxxxxaxxxaxrrxriaaxsaraaxxxxaxxrxarrMxaaxaxx~axNNMraxxaxrrxraaaaxxraNarraIII'axaaaxaaxaaraMrrxxax%%%raxaarxrRaarxxaxaxaaxraxNMRRrraaxaxuaaaaxxrruaxr<<sxarII'XNMNMNRRMxxxrxrax%%%XXaaraxRxNRRMMNNRRNXNN~nnnnsRsannausmnunumnmnunsmNxararxaaxrrrxaaaxaxraxrxrarMN'NarNRRNRNRXNMRRXNNmaaaxxaaxaaaxaraararxxxxxxaMRNRRNMMaaxMarxrxa~ERRREREssssssmRREEMREEMamsEEEEMEMEREEEEEE~rxxa&aaaaxaxaaxrrrMMNMNXNRRRNNNXNRNMMrrxxax~aaraaaaaarxaaararrxaxxaaaxaaxaxxxxxaaxaxxxMaxxarxrxxxRRrxaaxrxrrarrxrxxxxaMRNRMRNNXNMNNNMrxxax~rxaxrarrxxraxxrrraNNNMNRNNMNMMxraaxxaxarrNNRRRa%hRgRXRRMRXRXxrrrxxxxrxaxRMMRxxaaaaxxxxMRRhpRRHRMRHMERERHEMMHHEEBHRROKVht>saannanaaaassansnnasusnssnusernsnsmnEEEERERRREEEEHHREssmsnWMHRR~RMEKRERRXNRMtECEKcdHNH~NNraarrxaaaaxEnsnunssn~ssnssnss~ERRREREREssass~eHISREBHRHH~nnnnansnsuusnssswatuuanuRunsun~BERRRMERRRRRREEnnnah&~EEBEEHMEERHEBBsnsssananssssuuunamnHEEHMEEBEEREEH~RRREEREEERRRERREERRHICEEEMBEEEMMEERMRERH~RRRRHBRBRHRERMRi~~RKRRREEERERERRREEERER~ERMRREERRRREEREHIFSE~annEH%REREM~rarraarxmxraarrearNXMMRMaaNMxaaaaMraaEBRRHRRRREEREEHKIEEEERMMRBmssnsnEREEME~RRRREERHREEEHWJCIHEEEEMEEEHEEEBRMMRBM~nnEBRRRRREEEFassnEEBEERunSEEMsMMRRExaarraaraaaaaarxaara~MRRRRMRHRERREEREsnsssuusnnsssssussssnss~MRRHHREREERMERHHEBMBRMHEMMHEEREEnsnnnssasamERmsuMRRRHMEEEMMEHMRM~Mnsssnssnnissnnnsunusnssnss~Ensaauansssamssssnsusuuusssaassssssn~nnssnansssassssunnunsuussssaBananas~MBEMERMRERMRMMRRMMRREMHEEEEEREHERHEE~RERERRHRHRSRBMEEEEEEMsansmssSEERESS~nsansnnsENMMMEMEMRERRRMEMEEESEMEME~'ERNSQRNaaaxaaxaMxrxaaxaarxaraaaraaaaaarraraareas~~MRBEEERHEERHEEMHBREHHBHEEMBEHMHMNsxssasarQaaxNrrNMNNNNNaaaraxarxNNNNNNNNNss~rxrlQNNRSRxaarxrx'BrxxxxxxarxaxxxxxrrxraxxaxwNNIII~IIk'I'II~~~~III'~I~~
0'MP215.B.6.CONTAINMENTANALYSISAsingle-loopoperationcontainmentanalysiswasperformedforNMP2.Thepeakwetwellpressure,peakdrywellpressure,chuggingloads,condensa-tionoscillationandpoolswellcontainmentre'sponsewereevaluatedovertheentiresingle-loopoperationpower/flowregion.rTheanalysisshowsthatthepeakdrywellandwetwe11p'ressureduringsingleloopoperationis33.1psigand27.2psigrespectivelyandoccurunderrecirculatiohlinebreakatthemaximumvesselsubcoolingconditioninthepower/flowmap.Thecorrespondingdifferentialpeakdrywell-to-wetwellpressureis17.2psid.Abasecase,correspondingtotheFSARconditionof102%power/100%coreflow,wasalsoanalyzedforcomparison.TheresultsarepresentedinTable15.B.6-1.Asnotedfromthetable,thepeakdrywellandwetwellpressureandthepeakdrywell-to-wetwellpressurefortheSLOareallboundedbythoseofthebasecaseandaresdgsatanTallybelowthedes'ignlimits.ThepressureandtemperatureresponsesfortheSLOareshowninFigure15.B.6-1and15.B.6-2.ThecontainmentdynamicloadsevaluationwasperformedattheworstconditionfortheSLOandcomparedwiththoseforthebasecase.Poolswell,condensationoscillation,andchuggingloadswereassessedfortheinitialphaseofapostulatedrecirculationlinebreak.Additionally,SafetyReliefValveactuationloadswereconsidered.ItisconcludedfromtheevaluationresultsthatthecurrentFSARcontainmentPoadingsboundtheworstSLOloadings.Theboundingeventforthedrywelltemperatureresponseisa'ainsteamlinebreak.UnderSLO,theincreasedvesselsubcoolinghasnoimpactonthesteambreakflow.However,thelowervesselpressureresultingfromSLOreducesthesteambreakflow.ItisconcludedthatthepeakdrywelltemperatureforSLOisboundedbythatoftheFSAR.15.8.6-1 P NMP2Finally,thepeaksuppressionpoolandwetwellairspacetemperaturesaregovernedbythelong-termreleaseofdecayheatandenergyremovalbytheRHRservicewater.SincethepowerlevelsfortheSLOareboundedbythat.oftheFSAR,itisthereforeconcludedthatthepeaksuppression,pool.temperatureisboundedbythepeaksuppressionpooltemperaturegivenintheFSAR.15.B.6-2
NP2Table15.B.6-1,ComparisonofContainmentPeakPressuresBaseCase(102%Power/100'XCoreFlow)SLO(54%Power/35%CoreFlow)DesignLimitsPeakDry@el1Pressure,PSIG34.6233.07PeakDrywell-To-WetwellDeltaPPSID17.8117.1725PeakWetwell.Pressure.PSIG28.6327.1845~~15.B.6-3
60.i'RYWEILPAESSi'EIWELLPAESSREPSIAAEPSIR>JO.20.LrJ0:V)(AUJCL0.050.IOO.I50.200.TIMESECGNDSNIAGARAHOHAMKPOMERCORPORATIONDRYHELLANDMETHELLPRESSURERESPONSES~RECIRCULATIONLINEBREAK,55KPOWER,35%COREFLOlrJ
350.QBYNELLTEHPERTUBEHLTNELLTEHPERTUBE250.VlUJUJUJC350.0.100.50.TIMESECGNDS150.200.8th"ARAN3HAHKPntER-COPPWe~tOO0~VI!ELLAND'.lETHELLTE!tPERATURERESPONSES-RECIRCULATIONLINEBREhk,55K>OWER,351IREFLOMFIGURE15.B.6-2
0NMP215.B.7MISCELLANEOUSIMPACTEVALUATION15.B.7.1AnticiatedTransientMithoutScram(ASS)IactEvaluationTheprincipaldifferencebetweensingleloopoperation(SLO)andnormaltwoloopoperation(TLO)affectingAnticipatedTransientNthoutScram{ATMS)performanceisthatofinitialreactorconditions.SincetheSLOinitialpowerflowconditionis.lessthantheratedconditionusedforTLOATWSanalysis,thetransientresponsefslesssevereandthereforeboundedbytheTLOanalyses.ItisconcludedthatifanATMSeventwereinitiatedatNMP2fromtheSLOconditions,theresultswouldbelessseverethanifitwereinitiatedfromratedconditions.15.8.7.2.FuelMechanicalPerformanceThethermalandmechanicaldutyforthetransientsanalyzedhavebeenevaluatedandfoundtobeboundedbythefueldesignbases..ItisobservedthatduetothesubstantialreverseflowestablishedduringSLOboththeAveragePowerRangeMonitor(APRM)noiseandcoreplatedifferentialpressurenoiseareslightlyinci'.eased.AnanalysishasbeencarriedouttodeterminethattheAPRMfluctuationshouldnotexceedafluxamplitudeof+15%ofratedandthecoreplatedifferentialpressurefluctuationshouldnotexceed3.2psipeaktopeaktobeconsis-tentwiththefuelrodandassemblydesignbases..15.B.7.3VesselInterna1VibrationArecirculationpumpdriveflowlimitisimposedforSLO.ThehighestdriveflowthatmeetsacceptablevesselinternalvibrationcriteriaisthedriveflowlimitforSLO.15.B.7-1 I An'ssessmenthasbeenmadefortheexpectedreactorvibrationlevelduringSLOforNMPZ.Beforeprovidingtheresultsoftheassessment,itisprudenttodefinetheterm"maximumflow"duringbalanced2-loopoperationandsingleloopoperation.Maximumflowfortwo-pumpbalancedoperationisequaltoratedvolumetriccoreflowatnormalreactoroperatingconditions.Maximumflowforsingle-pumpoperationisthatflowobtainedwiththerecirculationpumpdriveflowequaltothatrequiredformaximumflowduringtwo-pumpbalancedoperation.Forratedreactorwatertemperatureandpressure,themaximumallowablerecirculationpumpdriveflowforNMP2isabout41,000gpm.StartuptestsattheTokai2plantshowedallcomponents,includingthein-coreguidetubeduringsingle-loopoperation,tohavevibrationlevelswithinacceptancelimits.TheTokai2istheBMR5/251prototypeplant.SinceNHP2isnotaprototypeplant,thereisnoreactorinternalvibra-tionmonitoringprogram.Instead,thedatafromtheTokai2plantisusedforNMP2SLOassessment.BasedontheTokai2plantdata,itcanbeinferredthatthevibrationlevelsofthereactorinternalcomponentsforNMPZwouldbeexpectedtobewithinacceptancelimitsduringsingle-loopoperationwithmaximumflowasdefinedabove.Forthejetpumps,theNMPZstartuptestingwi.llyieldtherequiredconfirmationasNMPZjetpumpsareinstrumented.15.8.7-2
NMP215.B.8REFERENCES15.B.8-1"GeneralElectricBWRThermalAnalysisBasis(GETAB);Data,Correlation,andDesignApplication",NEDO-10958-A>January1977.15.B.8-2"gualificationoftheOne-DimensionalCoreTransientModelforBoilingWaterReactors",NED0-24154,October1978.15.B.8-3R.B.Linford,"AnalyticalMethodsofPlantTransientsEvalua-tionfortheGeneralElectricBoilingMaterReactor",NED0-10802,April1973.15.8.8-4Letter,H.C.Pfefferlen(GE)toC.0.Thomas(NRC),"SubmittalofResponsetoStabilityActionItemfromNRCConcerningSingle-LoopOperation,"September1983.15.B.8-5S.F.ChenandR.0.Niemi,"VermontYankeeCycle8StabilityandRecirculationPumpTripTestReport",GeneralElectricCompany,August1982{NEDE-25445,ProprietaryInformation).15.B.8-6G.A.Matford,"ComplianceoftheGeneralElectricBoilingMaterReactorFuelDesignstoStabilityL'icensingCriteria",GeneralElectricCompany,October1984(NEDE-22277-P-1;Propri-etaryInformation).15.B.8-7"GeneralElectricStandardApplicationforReloadFuel",GeneralElectricCompany,April1983(NEDE-24011-P-A-6).15.B.8-8"BWRCoreThermalHydraulicStability",GeneralElectricCompany,February10,1984(ServiceInformationLetter-380,Revision1).'I15.B.8-1
15.B.8REFERENCES(Cont'd)15.B.8-9Letter,C.0.Thomas(NRC)toH.C.Pfefferlen(GE),"Accep-tanceforReferencingofLicensingTopicalReportNEDE-240111Rev.6,Amendment8,ThermalHydraulicStabilityAmendmenttoGESTARII,"April24,1985.15.B.8-10"GeneralElectricCompanyAnalyticalModelforLoss-of-CoolantAnalysisinAccordancewith10CFR50AppendixKAmendmentNo.2-OneRecirculationLoopOut-of-Service",NEDO-20566-2Revision1,July1978.~~15.B.8-2 4v ATTACHMENTG-ENDOFCYCLE-RECIRCULATIONPUMPTRIPINOPERABLEANDTURBINEBYPASSINOPERABLEANALYSIS 0 Sub]ect:JustificationforEOC-RPTInoperableandTurbineBypassInoperableTechnicalSpecificationChangesInordertoimproveoperatingflexibilityandplantavailability,twotransientscenarioshavebeenanalyzedtosupportTech.Spec.changesforminimizingpowerlevelreduction.l.EOC-RPTInoerableThecurrentLimitingConditionforOperationrequiresthatthethermalbducedtolessthan30Kincasetheend-of-cyclerecirculationpumptripbecomesinoperable.Inthesupportinganalysisto)uysitflesspowerreduction,twolimitingcaseswereexaminedwiththetransientcodeODYNtodefinetheboundingoperatinglimitcriticalpowerratio(OLCPR).a.FeedwatercontrollerfailurewithEOC-RPTinoperableb.Generatorloadre)ectionwithoutbypasswhenEOC-RPTisinoperable2.TurbineBassInoerableThecurrentLimitingConditionforOperationrequiresthatthethermalpowerbereducedtoless'than25%incasetheturbinebypassbecomesinoperable.Inthesupportinganalysisto)ustifylesspowerreduction,twolimitingcaseswereexaminedwithODYNtodefinetheboundingOLCPR.a.Feedwatercontrollerfailurewithturbinebypassinoperableb.LossoffeedwaterheaterwithturbinebypassinoperableUsinginputdeterminedfromEOC-lnuclearcharacteristics(seeFSARTable15.0-3),theboundingOLCPRvs.scramspeedisgeneratedforeachtransientscenario.ThisOLCPRplotandrelatedTech.Spec.textrevisionareincludedintheattachment.PleasenotethatthesepostulatedscenariosaretransienteventsbeyondthedesignbasisdocumentedintheFSAR.Therefore,FSAR'revisionisnotrequired.TheattachedLCO3.2.3andtwoassociatedfiguresreplace,initsentirety,theproofandreviewrevisionofLCO3.2.3anditsassociatedfigureonpages3/42-6and2-7.ChangesarealsoprovidedforLCO's3.3.4.2and3.7.9forproofandreviewversionofTechnicalSpecifications.Achangeis'providedforBasespagesB3/42-4. >i~ hn~IFhlI.IIr".~ATTACHMENTAth~NAKEDUPPROOFAND'EVIEWfgRSIONOFTECHNICALSPECIFICATIONS8601060030 HO<VAaO9SOOeMO9>~VVONAaAOArHSTHUTHi0933iN3HH>HQITA'3iRI'3392JAQIHHD3Tfp)~t)gt,'g"A"XEQH399Atlggggg(lOT",.QHiNiDIl NIAGARAMOHAWKPOWERCORPORATIONNINEMILEPOINTUNIT2TECHNICALSPECIFICATIONSAPPENDIX"A"TOLICENSENO. aBAR~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~..................3RU20tlX3RANAJ.................3TARNOITARt3N3BTA3HRA3HIJRANE..HOITARc.Jio~~~,t~~.-~~ot~~~O~~tacoo~~~~~~o~~~~~~i>'araotits~~~~~~~~~~~,~~~o~p~~~~~,,~oT2+TJAHOIiOttfi2-i~~~~~~~~oo~a~stp~.~~ot~ea,~~'o~~~o~o~~o~~~~~~oHOITIt[il,tltS"I.....,....p-:)tI2H30R3MO'l,BNITIHIJ".0NOITDAF.~>nr-ia~~~~~~~~~~~~o~~~~~~~~~~~attotAllRa3~~~~~~~~~~~~~~~~~~oy~~~~~qt~~~~~oylvkIafa3S"I..................,.........YBR3Vi3HOITARB3TNI2........,;3MIT32VQ'l23R(2~3"=)M32Y2BNIJ0003RO:S,"X..3M'2N062:RMgT2Y2AIRTti'lMU'lHOITAJUORI33R=."....Y,L2l30R3HOqBHITIMIJ30..........$3ttttDSJAMR3HT0:"TAR~a.....HOI(ATF3T2Y~TH3&ARTt"">,2"*~~~~~~~o3BAXA3J..3MIT32HOR23RM3T2Y28"I.....HR3gtAt'.OCRJORTHG."E"l.3TARHOITAR3H3BTh3y-r..23'ANOITOHURM3Tt2'TINU-~i' DEFINITIONSP(MF58VPÃiltlP7SECTION1.0DEFINITIONSPAGE1.~1ACTIONo~~~~~~~~~~~~~~~~~~~~~~~~~~e~~~~~~~~~~~~~~~~~~~~~~~~o111.2AVERAGEPLANAREXPOSURE....................................I"11.3AVERAGEPLANARLINEARHEATGENERATIONRATE.................1-11.4OHANNELCALIBRATION........................................1-11.5CHANNELCHECK..............................................1-11.6CHANNELFUNCTIONALTEST........."......................;....1-1-1.7COREALTERATION.................;................,.........1.8COREMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY............1-21-21'.9CRITICALPOWERRATIO..............".........................1-21.10DOSEE(UIVALENTI-131.;....................................1"21.11Z-AVERAGEDISINTEGRATIONENERGY........................;...1-21.12EMERGENCYCORECOOLINGSYSTEM(ECCS)RESPONSETIME...."'....1.13END-OF"CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSETIME.1-21".21.14FRACTIONOFLIMITINGPOWERDENSITY........................1-31.15FRACTIONOFRATEDTHERMALPOWER............,....,.......,.....1"31.16FRE(UENCYNOTATION...................;.....................1'-31.17GASEOUSRADWASTETREATMENTSYSTEM....;...,..................1-31.18IDENTIFIEDLEAKAGE....................1.19ISOLATIONSYSTEMRESPONSETIME.......,.~~~~~~~~~~~~~~13~~~~~~~~~131.20LIMITINGCONTROLRODPATTERN.......,..........................1=31.21LINEARHEATGENERATIONRATE...................................1-31.22LOGICSYSTEMFUNCTIONALTEST...............................1-4NINEMILEPOINT-UNIT2NOY20Mgg X3GHI(bsunr~no.3IJG~J~3HT~G........OITARR3ÃQ'tJAG'.7'.~~~~~......HOITADOJBl'........................-..JAUHAMHOITAJUDJA3c$>>~~~~t~~~~~~~~~~~~e~~~~~~~~~~~~~~~~~~oYTIJISARr~~~~~~~~~.............HOITIGHC3-HOITIGH.".3~~~~~~~~~~~~t~~~~~~~~0~~~~~>~~~~~~~~l4~~0~~~~~~~~1V'.~i~~0~0I~~~13BQA33YRI'~~~....YTIRG"=THITH3hlH'P-8"Z~A,~~~~~~~~~5~~~~~~~~~~'t~~~~~~~.BHiGR'.~~~~~~~~~~~.*.............434'HJAP'~II~~~.~~%~~~~~V~~~K~~~~I~~I~0'~O'~~1NAkllJOIJVl3YiIT3llQ't23RH3T2Y2HQIT.".'"'~o~~~~~~~~~n~~~~-~~~~~~~~~'~~~~~~~~~~......H3V3"~~~~~8~~~~0%~~0~~~~~~~~~~~"~~~~~t~.~~~~~I~'I~~,.YT:Rr".3THITH3NHIT~tO."~~~~~~~~~~,~~~~~~~~~~~~~~.HlDf~~~I'~~~~~~~0~~~0~~~t~~~~..'.;...HOIl.".'~~~~eo~~~~~~~~e~~~~da~~~~~o~'~~:.2I2AGT23T"~~~~~~~~~N~~I~~0~~~~~~~~'~~~~~~~~~~~~~~~0'~'0I~~'5~'~.R39~~~~~~~~~~...3H'rT32HO'i3RH3T2Y222A~'.3DMA3JG3g9),08YON~TIHU"TNi DEFINITIONSINDEXNaÃ5(P/lP/lNP7SECTIONDEFINITIONS(Continued)1.23MEMBER(S)OFTHEPUBLIC.....................................1.24MINIMUMCRITICALPOWERRATIO...............................1.25MILKSAMPLINGLOCATION.....................................PAGE1-41.26OFFSITEDOSECALCULATIONMANUAL............................1-41.27OPERABLE"OPERABILITY............1-41.28OPERATIONALCONDITION-CONDITION..........................1-41.29PHYSICSTESTS.1.30PRESSUREBOUNDARYLEAKAGE...........1"51-51.31PRIMARYCONTAINMENTINTEGRITY................'..............1-51.32PROCESSCONTROLPROGRAM....................................1.33PURGE"PURGING.1.34RATEDTHERMALPOWER..1-51-51-61.35REACTORPROTECTIONSYSTEMRESPONSETIME....................1-61.36REPORTABLEEVENT.................1.37RODDENSITY.1-61-61.38SECONDARYCONTAINMENTINTEGRITY...........................1-61.39SHUTDOWNMARGIN.1.40SITEBOUNDARY..............................................1.41SOLIDIFICATION.........:...................................1.42SOURCECHECK...........................-..........-........1.43STAGGEREDTESTBASIS............-...-......................le44THERMALPOWERo~~~~~~o~~osa~~~~~~~~~o~~~~~~~~~~~~~~~~o~o~~~1"61"71-71"71-71-71.45TURBINEBYPASSSYSTEMRESPONSETIME........................1-71.46UNIDENTIFIEDLEAKAGE...........~..-.-..-..NINEMILEPOINT-UNIT21"7HOY80)SS$ ~~~~~~~i~~~~~~~~~~~~~~~~~~~~o~~~~o~~~~~e,A'HRAva~~~~~~~~~~~~~~~~~......H372Y2TH3NTAjfiT,JAHY""~~~~'~~~~~~~~~~~~~~~~~~~~0~~~~~~~~~~~~~~~~~...,..................HOTTATQHYQH3UP3R~BDHA~.0~~~~~0~~1~~~~~~~~HQTTIQHQDJAH3D DEFINITIONSINDEXPROF8I(PJ,Pg)(P(ISECTIONDEFINITIONS(Continued)1.47UNRESTRICTEDAREA..........................................PAGE1"71.48VENTILATIONEXHAUSTTREATMENTSYSTEM.......................1-8~49VENTINGo~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~e~~~~~~~~~~~~~~~11-8TABLE1.1,SURVEILLANCEFREQUENCYNOTATION......................1-9TABLE1.2,OPERATIONALCONDITIONS...............................1-10NINEMILEPOINT-UNIT2aov&0~dies WVIf}flgg~Q>'g'fqf'P"jQ~Q~<<rgesse~~%il.2BHITT32VBT2Y2YTB-->BHIT>HIJ0h','I"Sc,...................woldwoJaoeauaaszlwo'i;...wol'3rig'rHbnssauaasvRriprH."."....sauaaeaqms~aN2znr;S"S~~~~~~~~~~~~~~~~~~~~a'obrevefsfzk~2BI~IT722N372Y2Yn~...~~~an'roqds2noUstnsmuwanEnszav2nor:::X"S8S"S82"S8............,......woughwoJaoeauaareRwoJ,f.:>>................wof~iprHbnse".uaae;0AglH.fi~.~.s'fuaae'T'9Ale~a/2znp!""--S8.feve'efsHfsa2BY<<it32H272Y2YT"..e-Sa........unroqie2noÃs~nsnuafan'.ms+ay2norv.;: INDEXSAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSP)00F5gppj[(pyISECTIONPAGE2.1SAFETYLIMITSTHERMALPOWER,LowPressureorLowFlow....'...............2-1THERMALPOWER,HighPressureandHighFlow................2-1ReactorCoolantSystemPressure.........................2-1ReactorVesselWaterLevel................................2-22.2LIMITINGSAFETYSYSTEMSETTINGSReactorProtectionSystemInstrumentationSetpoints.......2-3BASES2.1SAFETYLIMITSTHERMALPOWER,LowPressureorLowFlow...................82-1THERMALPOWER,HighPressureandHighFlow................82"2ReactorCoolantSystemPressure...........................82-5lReactorVesselWaterLevel................................B2-52.2LIMITINGSAFETYSYSTEMSElTINGSReactorProtectionSystemInstrumentationSetpoints........B2-6NINEMILEPOINT-UNIT2peRO1%5 X3MI2TV3M3RIUC3R33HSJ.,'I3VRU2QNAHOITAR3q0ROB2HC30ARX"0lid~~~~~~II2M372Y2JORTHO.HIBRAM...23"'AMOHAY;8-l>>,"-rl-IA4"=8al'AC'-rWXC2C".'qadi1'iflsweqOb=-:..............2emrinf.r~92nIms~f2memrxsMb...............2emrinoifae2hImszv2epsom.VAb::~r~ar~~~29>rInord'T92PiImsa'32rqUOfBbORfo~~~~~~r~~~~r~~~~~~~~~~~~2~OarsfUmaf'arDAmS32bc"~-ruac2cZ-'C2Z"rhc,~aa~~~~~r~~rr~~~r~~~~~~~~~~~~~~rQfl~a'qUODevr~Qbr.noiis"FbnInorfi2cqboRr.......................~oqqUcpni2uoH9~r";~:f;o,".2JORTHCDt'ARBQRR005...aezrrifniM:"~~~~~~~~~~~~~~~~~~~~~~~~~~~~meat'2gf0~alanOOOnaga~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~IVIIInOMM3T2Y2JORTHODGIUP',2TIMI3HOITUH."~TA~~~~~~~~~~~~aDTARHOITAR3H3BTA3HRA3HI'AHAJcI."..~~~~~~~~~~~~~~~~~~~~~~~~a~~~~~~~~~~~~~~2IHJO~I....OITARF3MGqJADITIRDt'.......3TARHCITAR3H3BTA3H9o;08Vb,.l2TIHV-INDEXLIMITINGCONDITIONSfOROPERATIONANDSURVEILLANCEREUIREMENTSSECTION3/4.0APPLICABILITY.............................................PAGE3/4O-l3/4.1REACTIVITYCONTROLSYSTEMS3/4.1.1SHUTDOWNMARGIN........................................3/4.1.2REACTIVITYANOMALIES...................................3/4.1.3CONTROLRODSControlRodOperability.'...............................3/41-13/41-2ControlRodMaximumScramInsertionTimes..............3/41-6'IControlRodAverageScramInsertionTimes..............FourControlRodGroupScramInsertionTimes...........3/41-.73/41-8ControlRodScramAccumulators.........................3/41-9ControlRodDriveCoupling.................,............ControlRodPositionIndication........................ControlRodDriveHousingSupport......................3/4.1.4CONTROLRODPROGRAMCONTROLS~~~RodWorthMinimizer....................................RodSequenceControlSystem............................RodBlockMonitor......................................3/41-133/41"153/41-163/41-173/41-183/4.1.5STANDBYLIQUIDCONTROLSYSTEM.......................3/41-193/4.2POWERDISTRIBUTIONLIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATE.............3/42-13/42.2APRMSETPOINTS....".....................................3/42-53/4.2.3MINIMUMCRITICALPOWERRATIO...........................3/42-63/4.2.4LINEARHEATGENERATIONRATE.....-......................3/42"8NINEMILEPOINT-UNIT2NQV801985 Y30HE2:N3N3RIU03R33NAJJI3VrJ2QHANOITA'F380HOa2HC"'OIt:"i5>RE,.~..........HOITATH3NUPT2NIH372Y2HGIT0370,";wOl-EAE..................ViOi7ATVi3PiUS72HINO'AUTDANOITAUTDAVi372Y2BHEJ0033RCi5B~"6she................HOI7>,HOITATV".Surt2N:NOITAUTaA-".Ia7ovuleVC:;00-.1K'.ncrdstnemuafanEmeay2qr".."muRnor.sru::.me>av2giw7amuqi'or'sruaroeRe44"E.'ac.~~~~~I~~~~~~~~~4~~~4~i~~~~~~~~~norvOc"E,44K,NOITAU;Dfl672YP.BHIJOG'.NOET<<'02I3f':~~~~~~~~~~~~~~~~~~~~~~~~~~WHOiTh<7'2lE+l4~~~~~~~~,.HOETATH3NUR72M.)IDOJoQCH0<ATH3HUR72ViEBi'a'-'iC.................nor's:nemua-anign;aoiinoHne3-SO4i.....norris'nemu".'anig~'ao~inoHRx"E>RE............noisJnemu"angr,'-.~c"rr',oNt'sor"c'-i-KAC..alo"i~nc0bnsncizsSnemuvani'eday2fr~'ooDun.e-.-cA~KS-C4SOB"c.01Kaa"aahabre-saxese-sahab...norfsfnemu",~anIpnr.o.rnoR:~~~~~~~~~~~~~~~~o~~aYLnolI~en~.......mefay2edoaR~cG-nign!....norPsmemua~anInorf"e=~..me?'gnor~oedeQ~'fs".pnr",oPrnoMPneuf+T3brugiJev'rf:-~~~~~.nor~sfnem.evSTIHU" INDEXLIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREUIREHENTSSECTIONPAGE3/4.3INSTRUMENTATION3/4.3.1REACTORPROTECTIONSYSTEMINSTRUMENTATION............3/43-13/4.3.2ISOLATIONACTUATIONINSTRUMENTATION..................3/43-103/4.3.3EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATION......................................3/43-283/4.3.4RECIRCULATIONPUMPTRIPACTUATIONINSTRUMENTATIONAPTSRecirculationPumpTripSystemInstrumentation..3/43"403/4.3.53/4.3.6End-of-CycleRecirculationPumpTripSystemInstrumentation............;.........................REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATION.............-.....-.......--.CONTROLRODBLOCKINSTRUMENTATION....................3/43-443/43"503/43-55"3/4.3.7MONITORINGINSTRUMENTATIONRadiationMonitoringInstrumentation.................SeismicMonitoringInstrumentation...................MeteorologicalMonitoringInstrumentation............3/43-633/43-693/43"72RemoteShutdownSystemInstrumentationandControls..3/43-75AccidentMonitoringInstrumentation..................SourceRangeMonitors................................TraversingIn-CoreProbeSystem......................3/43-793/43-833/43-84FireDetectionInstrumentation....................3/43-85Loose-PartDetectionSystem..........................RadioactiveLiquidEffluentMonitoringInstrumentation.................3/43-913/43"92NINEMILEPOINT"UNIT2viNOV20NSS PPgfg',<<'i8"":)xaber2H"=~"=7.I4'C.:."HA'JI3VctJZQHAHOiTAT3%GPO>ZH("(beJnCnoa'Ve-ChiecOE-E,0XChOE-fbXc'~~.bi3".ZYZHG"733TORRG:":-%25:=...............HOITATH3N'JRT2HIHOI;~UTOA.!'nrao.'rnoNSneuf>%3auoeee~"-~~~~~~~~~~~~~~~~~~~~~~~4~~~~~~~~~~~~nioi4vN3".ZYc,¹TZYZHOCc-4OX'-0~%K~~~~~~~4~~0~~~~~~~~~~~~~~~~~~~~~4~~~~~~............~ofhqoodn-~~~~....qvffs>ZCOG'of~5c'-23V.W'i',"z..~~~~~~~~~~~~~~~~*~~~~~~~~~~~~,~liarO>>7<<hh%g~~~~~~~~~~~~~~~~"evfrl;sr:.3DQiAiJM3TZY2TViJV"8"0>REP,C,~400~~~~~~~~0~~~a~~~~~~~,~~0l.eaiC,VZ~aOl~va:4pa~~~0~~~~~~~~~~~~~4~~~~~~~~~~~~~~~>>SQSno~~~~~~~~4~4~~0~~~4~~~~0~~~~~~~~~~~4~~1BE-04K~~~~~~~~4~~~~~~~~~~~0~~~~~~~0YTIjtOE"0A4c.BS"0PE,BS-0A,C2TINI33RUTA5l3%t:="i'.m-"ay2znsfo'.'.4J~~~~~~~4~~~~~.~SilloQlilac>>2.23VJAVHOITA'GZ3HIJYA:-'~~~0~~~~~~~~~~~~~~~.."...7:llG3THIJA5BR-4h'iCeZ-04~c.~~~~~~~~~~~~JAVON3RTA3HJr~~~~~~~~~..nwob~L~~~~~~~~~0nWObarual2I'Vc"HQBeef02VOW INDEXLIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREUIREHENTSSECTIONPAGEINSTRUMENTATION(Continued)RadioactiveGaseousEffluentMonitoringInstrumentation......................................3/43-973/4.3.8TURBINEOVERSPEEDPROTECTIONSYSTEM...................3/43-1033/4.3.9PLANTSYSTEMSACTUATIONINSTRUMENTATION...............3/43"1043/4.4REACTORCOOLANTSYSTEM3/4.4.1RECIRCULATIONSYSTEM3/4.4.4LeakageDetectionSystems............................OperationalLeakage..................................HEMISTRY.................C3/4.4.5SPECIFICACTIVITY....................................3/4.4.6PRESSURE/TEMPERATURELIMITSRecirculationLoops..................................JetPumps............................RecirculationLoopFlow..............................IdleRecirculationLoopStartup......................3/4.4.2SAFETY/RELIEFVALVESSafety/ReliefValves.................3/44.3REACTORCOOLANTSYSTEMLEAKAGE3/44"13/44-43/44-53/44-63/44-73/44-83/44-93/44-133/44"16ReactorCoolantSystem.....................ReactorSteamDome.........................~~~~~~~~~~3/44"193/44-253/4.4.7MAINSTEAMLINEISOLATIONVALVES.....................3/44-263/4.4.8STRUCTURALINTEGRITY.................................3/4.4.9RESIDUALHEATREMOVALotShutdown..........................................HoldShutdown.........................................C3/44-273/44-283/44"29NINEMILEPOINT-UNIT2Vi1HQV201985 iii~,PiIi)(8'Qg(A2t".i72Y2r~V1J003>'iiC'4~~~~~~~~~~~~~~~w~~~~~~~~~~~~~~~~~~~~~II~i'~~~arrTV""'"Ri~~~~~ss~~~~e~~~~~vefTQ9nIvp)iini"-6~C~~~~9pEAG3~flkiln<io"3AXEDaoaJ".tA;n.nnr;.....yreps>nLfs",dvU<'n~.",.-'.;-'alu~~fsmsznT".sdms~."noraa9vq..~?:Oi"8v'iCafU~Gtsc,p97rI~8'Da-"4&V~'lC~~4~~~~~~~~i'~a/~~'D~fll35inI::'i372Y2HO.',.4.,VA8%K\~~~~~~~\~I~~~~\~~)\~..i(i0'(-80'~"................,...yssq2.'ie~iaGbnzrn,.-n:01%~:r~+(~g.fac.~c8'Žc>X:"...................2""VJAVdiO"7/302~'i.'~."-.I'iV're;;. INDEXLIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREUIREHENTSSECTION3/4.5EMERGENCYCORECOOLINGSYSTEMS3/4.5.1ECCS"OPERATING......................................3/41So2ECCSSHUTDOOe~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~PAGE3/45-13/45-63/4.5.3SUPPRESSIONPOOL......................................3/45-83/4.6CONTAINHENTSYSTEMS3/4.6.1PRIMARYCONTAINMENTPrimaryContainmentIntegrity.PrimaryContainmentLeakage;.......................PrimaryContainmentAirLocks...............3/46-13/46"2...3/46"6PrimaryContainmentStructuralIntegrity..............3/46-8OrywejlandSuppressio~Chambe~ataenalPressure.....3/46-9DrywellAverageAirTemperature.......................3/46-10PrimaryContainmentPurgeSystem......................3/46-113/4.6.2DEPRESSURIZATIONSYSTEMSSuppresslonPool......................................3/46-13SuppressionPooland'rywellSpray....................3/46-16SuppressionPoolCooling.....................3/46-173/4.6.3PRIMARYCONTAINMENTISOLATIONVALVES..................3/46"183/4.6.4SUPPRESSIONCHAMBER"DRYWELLVACUUHBREAKERS.........3/46-33NINEMILEPOINT-UNIT2vliiNOV201985 ppr(bsUnr"n~~~1\r~vnOXK.....z.sqmsCnosloa'r~amozuA8"."o>Xc.J>>+4~~~~~ms'<canJORTPiGDHR"H%20NTAnrJmos+08~go~~~~~~~~~~~~PsQC.OQH'f90ms<<0nG~~~~~~~R0-0~XE...ncaavs"'csonoDnsgy~x0~sl'.esner=';..-.;.Qnid=<pQO,s83'i2-i>',E.....".:.:.one2-7AE~~ViJ(Ii~"-ra'EH~T2Y2ViI",7R=TJ,~0"Zrc;"P-,g---<r-rO'iZ.............,...Yi"-i".'?DH'OG'iG.T~.JG:;.f4c,~~~~~~\~~~~~~I~~~~~~~~ec-7AXE~~~~~~~~~~~~~~~~~~aHG')W~,'!3:-T2Y"=;..~~~~~~~~~~~~~~~~~~~~msv~~~~~~t~~~~~~~~~~~~~~2ms4pg2ast'Anr",q~~~~~C.s>.'S-70'4~~~~~~2msdB INDEXLIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREUIREMENTSSECTIONCONTAINMENTSYSTEMS(Continued)3/4.6.5SECONDARYCONTAINMENTPAGESecondaryContainmentIntegrity.......................3/46-35SecondaryContainmentAutomaticIsolationDampers.....3/46-36StandbyGasTreatmentSystem..........................3/46-383/4.6.6PRIMARYCONTAINMENTATMOSPHERECONTROLDrywellandSuppressionChamberHydrogenRecombinerystems.............................................'3/46-41DrywellandSuppressionChamberOxygenConcentration..3/46-423/4.7PLANTSYSTEMS3/4.7.1PLANTSERVICEWATERSYSTEMPlantServiceWater-Operating.......................3/47"1PlantServiceWater-Shutdown................'........3/47"33/4.7.2REVETMENT"DITCHSTRUCTURE..........................3/47-53/4.7.3CONTROLROOMOUTDOORAIRSPECIALFILTERTRAINSYSTEM..3/47-83/4.7.4REACTORCOREISOLATIONCOOLINGSYSTEM.................3/47-113/4.7.5SNUBBERS.~0~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~~~~~~~3/47-133/4.7.6SEALEDSOURCECONTAMINATION...........................3/47-193/4.7.7FIRESUPPRESSIONSYSTEMSFireSuppressionWaterSystem.........................3/47-21Sprayand/orSprinklerSystems........................3/47-2402Systems...........................................CalonSystems.........................................H3/47-263/47"27NINEMILEPOINT"UNIT2ixNOV201985 ~~~~~~OC,NIIA~~~~~~~~~~~~Iorl~$AC>>'W+%v~~~~~~~~~~~I~~8~~'~~~~~~~~~~~~~~~~~~~~*<<"80'g.t~~~~~~.~~~AI~I~~~~0~EE-8)'xC~~~+~l'r-0pC..~~~~~~<<1~BE-6AFi~~~~~~~~~~~~~~~~~~~.~~~i'.~ST"%C~~~~~~~<>r;.~,>s~51('I~e~~~q0I'L>j~r~+,l~gP'lf054,'lv~~~~~~~~~~~~~4IIVll~Il~>Mlive4X('~r~0~~~~pnr.o.rnoH~swo";"r.:oei:-OC8+AC~~~~~~~~~~~~WC4Ijw~~>>~ger",craoNassoconosisass.ayB,",=':s;'-ac.-BP,E,..........(:;wro,=<o(.'i. INDEXLIMITINGCONDITIONSFOROPERATIONANOSURVEILLANCEREUIREMENTSSECTIONPLANTSYSTEMS(Continued)PAGEFireHoseStations.............................'.......3/47-28YardFireHydrantsandHydrantHoseHouses............3/47-313/4.7.8FIRERATEDASSEMBLIES.................:................3/47"333.4.7.9MAINTURBINEBYPASSSYSTEM.............................3/47-353/4.8ELECTRICALPOWERSYSTEMS3/4.8.1A.C.SOURCESA.C.Sources-Operating.;............................A.C.Sources-Shutdown...............................3/4;8.2D.C.SOURCES3/48-13/48-11D.C.Sources-Operat>ng..............................D.C.Sources-Shutdown.......................,........3/4.8.3ONSITEPOWERDISTRIBUTIONSYSTEMSDistribution"Operating..............................Distribution-Shutdown...............................3/48-123/48-163/48-173/48-193/4.8.4ELECTRICALE(UIPMENTPROTECTIVEDEVICESA.C.CircuitsInsidePrimaryContainment..............3/48-21PrimaryContainmentPenetrationConductorOvercurrentProtectiveDevices3/48-25EmergencyLightingSystem-OvercurrentProtectiveDevsces..........3/48-27ReactorProtectionSystemElectricPowerMonitoring(RPSlogic)......................................3/48"29ReactorProtectionSystemElectricPowerMonitoring(SCRAMSolenoids)...................................3/48-30NINEMILEPOINT-UNIT2N0V2OlSBS ~~~~~~~~~~~~~~~~W~\10*~~~Ls~~en~~~~~~~~~~~~~W.~~~~~~~~~~~~~~~~~a4a>gNJ%4~~~~~~~W~~t~0~~~~~<<If'\~~~~~~~~IQ'AlUJ)i!.i~I~~~~~*(W~hI'Ke~~~~~~(/Pl'Wf~vvXKa~o~~~~~~~~~~~~~~~~~~~~ovled~5IIC~aaxrQ.~LM~~~w~~~~~~~~~g~~~2-OI4Xr~~LF)'IIW)~IrITit'jI4aX~llPHD)gCIrn INDEXLIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREUIREMENTSSECTION3/4.9REFUELINGOPERATIONSPAGE3/4.9.1REACTORMODESWITCH...................................3/49-13/4.9.2INSTRUMENTATION.......................................3/49-33/4.9.3CONTROLRODPOSITION..................................3/49-53/4.9.4DECAYTIME............................................3/49-63/4.9.5COMMUNICATIONS......................................3/49-73/4.9.6REFUELINGPLATFORM................................3/49-8'/4.9.73/4.9.83/4.9.9CRANETRAVEL-SPENTFUELSTORAGEPOOL.......,...WATERLEVEL-REACTORVESSEL....................WATERLEVEL-SPENTFUELSTORAGEPOOL.................3/49-93/49-103/49-113/4.9.10CONTROLRODREMOVALSingleControlRodRemoval............................3/49-12MultipleControlRodRemoval..........................3/49-143/4.9.11RESIDUALHEATREMOVALANDCOOLANTCIRCULATIONHh1ghWaterLevel......................................owWaterLevel.....................................L3/4.10SPECIALTESTEXCEPTIONS3/49-163/49"173/4.10.1PRIMARYCONTAINMENTINTEGRITY.........................3/410-13/4.10.2RODSE(UENCECONTROLSYSTEM..........~~~~~~~~~~3/41023/4.10.3SHUTDOWNMARGINDEMONSTRATIONS........................3/410-33/4.10.4RECIRCULATIONLOOPS.................................3/410-43/4.10.5OXYGENCONCENTRATION........................3/410-53/4.10.6TRAININGSTARTUPS................-~...--...........-..3/410-6NINEMILEPOINT-UNIT2X1gOy201985 ~~'~~~~~~~0~~~4~~~~0~J~~~~~~~~~~~~~~~~~~t~~~~0~4IPiI4~~~0P~~0~~~~+~~~\)~~f~~~~~~~~~~~~~~~~~~~~04~~~~~4~~~~~~~~4~~~~~~~I~ INDEXPi100F5KItIMMP1'IMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREUIREHENTSSECTIONPAGE3/4.11RADIOACTIVEEFFLUENTS3/4.11.1LIQUIDEFFLUENTSConcentratson............................................oseo~~~~~~~~~~~~~~~~~~~~~~~~~~~i~~~o~~~~~~~~~~~~~~~~~~~~DLiguidRadwasteTreatmentSystem.........................LiquidHo1dupTanks......................................3/4.11.2GASEOUSEFFLUENTSoseRate................................................0DeoseNob1eGases.......................................3/411-13/411"53/411-63/411-73/411"83/411-120/4.11.3/4.11.'Dose-Iodine-131,Iodine-133,Tritium,and,Radionuc1idesinParticulateForm.................GaseousRadwasteTreatmentSystem.....Venti1ationExhaustTreatmentSystem..ExplosiveGasMixture....................................HainCondenser-Offgas....................;.............VENTINGorPURGING.......................................3SOLIDRADIOACTIVEWASTE...........................--...-.TOTALDOSEo~~~~~~o~~~~~~o~~~~~o~~~~~~~~~~~~.~~~~~~~~~~~3/411"133/411-143/411-153/411"163/411-173/411-183/411-193/411-203/4.12RADIOLOGICALENVIRONMENTALMONITORING3/4.12.3/4.12.3/4.12.2LANDUSECENSUS..........................................3INTERLASORATORYCOMPARISONPROGRAM.-..--.............1MONITORINGPROGRAH.........................-..-...---.--.3/412"1'/412"133/412-14NINEMILEPOINT-UNIT2xi1NOVP.ulS85
- '4~<~~~~~~1~~~~~~I'~~~\~~'E~~~~~~~~~~I~~~O~1~\~V~~~~~~v~~~~I~~I>'3~~
BASESINDEXI%MF5KP,HgPSECTION3/4.0APPLICABILITY............................................3/4.1REACTIVITYCONTROLSYSTEMS3/4.1.1SHUTDOWNMARGIN..................................PAGEB3/40-1B3/41"13/4.1.2REACTIVITYANOMALIES.............................B3/41-13/4.1.3CONTROLRODS.....................................B3/41-2~~~-3/4.1.4CONTROLRODPROGRAMCONTROLS.....................B3/41"33/4.1.5STANDBYLI(UIDCONTROLSYSTEM.....,....;.........B3/41-43/4.2POWERDISTRIBUTIONLIMITS3/4.2.IAVERAGEPLANARLINEARHEATGENERATIONRATE...................................B3/4213/4.2.2APRHSETPOINTS.....;.............................B3/42-23/4.2.3HINIMUMCRITICALPOWERRATIO.....................B3/42-43/4.2.4LINEARHEATGENERATIONRATE......................B3/42-53/4.3INSTRUMENTATION3/4.3.1REACTORPROTECTIONSYSTEMINSTRUMENTATION........B3/43-13/4.3.2ISOLATIONACTUATIONINSTRUMENTATION..............B3/43"23/4.3.3EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUHENTATION..................................B3/43"23/4.3.4RECIRCULATIONPUMPTRIPACTUATIONINSTRUMENTATION....................B3/43-33/4.3.53/4.3.6REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATION........................B3/43-4CONTROLRODBLOCKINSTRUMENTATION..................................B3/43"4NINEMILEPOINT"UNIT2X111HOY20l9GS ~~~\~~4~~-~A~l~~~~~~~ BASESINDEXIM~F53~PJiPlftlatSECTIONPAGEINSTRUMENTATION(Continued)3/4.3.7MONITORINGINSTRUMENTATIONRadiationMonitoringInstrumentation..........SeismicMonitoringInstrumentation............MeteorologicalMonitoringInstrumentation.....RemoteShutdownMonitoringInstrumentation....AccidentMonitoringInstrumentation...........SourceRangeMonitors.........................TraversingIn-CoreProbeSystem...............FireDetectionInstrumentation................Loose-PartDetectionSystem...................RadioactiveLiquidEffluentMonitoringInstrumentation...............................RadioactiveGaseousEffluentMonitoringInstrumentation.................................B3/43-4B3/43-4B3/43-5B3/43-5B3/43"5B3/43-5B3/43-6B3/43"6B3/43"6B3/43-7B3/43-73/4.3.8TURBINEOVERSPEEDPROTECTIONSYSTEM.............B3/43"73/4.3.9PLANTSYSTEMSACTUATIONINSTRUMENTATION.........B3/43-73/4.4REACTORCOOLANTSYSTEM3/4.4.1RECIRCULATIONSYSTEM............................B3/44-13/4.4.2SAFETY/RELIEFVALVES............................B3/44"13/4.4.3REACTORCOOLANTSYSTEMLEAKAGELeakageDetectionSystems.......................OperationalLeakage....................B3/44-1B3/44-23/4.4.43/4.4.5HEMISTRYo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~CSPECIFICACTIVITY...............................B3/44-2B.3/44-23/4.4.6PRESSURE/TEMPERATURELIMITS.....................B3/44"33/4.4.7MAINSTEAMLINEISOLATIONVALVES................B3/44"4NINEMILEPOINT-UNIT2xiv>oy20l985 E~~~'1 BASESINDEXPMIFOIAi:JB/N7SECTIONREACTORCOOLANTSYSTEM(Continued)3/4.4.8STRUCTURALINTEGRITY............................3/4.4.9RESIDUALHEATREMOVAL...........................3/4.5EMERGENCYCORECOOLINGSYSTEHSPAGE83/44"583/44-53/4.5.1/2ECCS-OPERATINGandSHUTQOMH....................83/45-13/4.5.3SUPPRESSIONPOOL.-.......-..--...................83/45-23/4.6CONTAINMENTSYSTEHS3/4.6.1-PRIMARYCONTAINMENTPrimaryContainment.Integrity....................PrimaryContainmentLeakage......................PrimaryContainmentAirLocks....................PrimaryContainmentStructuralIntegrity....,....DrywellandSuppressionChamberInternalressure.......................................PDrywel1AverageAirTemperature..................PrimaryContainmentPurgeSystem.................83/46-19.3/46"183/46-183/46-283/46"283/46-283/46"23/4.6.2DEPRESSURIZATIONSYSTEHS.........................83/46-33/4-6.3PRIMARYCONTAINMENTISOLATIONVALVES.......;.....83/46-43/4.6.4SUPPRESSIONCHAMBER-DRYMELLVACUUMBREAKERS....83/46-43/4.6.5SECONDARYCONTAINMENT............................83/46-53/4.6.63/4.7PLANTPRIMARYCONTAINMENTATMOSPHERECONTROL...........83/46"5SYSTEMS3/4.7.1PLANTSERVICEMATERSYSTEMS......................83/47"13/4.7.2CONTROLROOMEMERGENCYOUTDOORAIRSPECIALFILTERTRAINSYSTEM............................B3/47-1NINEMILEPOINT-UNIT2xvHDV80t985
BASESINDEXSECTIONPLANTSYSTEMS(Continued)PAGE3/4.7.3REACTORCOREISOLATIONCOOLINGSYSTEM............83/47"13/4.7.4SNUBBERS.........................................83/47-23/4.7.5SEALEDSOURCECONTAMINATION....................83/4?"33/4.7.6FIRESUPPRESSIONSYSTEMS........................83/47-33/4.7.7FIRERATEDASSEMBLIES...........................83/47-403/4.7.&MAINTURBINEBYPASSSYSTEM......................3/4.8ELECTRICALPOWERSYSTEMS3/4.8.1,3/4.8.2and3/4.8.3.A.C.SOURCES,D.C.SOURCESandONSITEPOWERDISTRIBUTIONSYSTEMS............................83/47-483/48"13/4.8.4ELECTRICALEQUIPMENTPROTECTIVEDEVICES.........83/48"33/4.9REFUELINGOPERATIONS3/4.9.1REACTORMODESWITCH.............................B3/49-13/4.9.2INSTRUMENTATION..........................,..'.....3/4.9.3CONTROLRODPOSITION............,................3/4.9.4DECAYTIME......................................3/4.9.5COMMUNICATIONS..................................3/4.9.6REFUELINGPLATFORM..............................83/49"1B3/49"183/49-183/49"183/49"1'3/4.9.7CRANETRAVEL-SPENTFUELSTORAGEPOOL............83/49-23/4.9.8and3/4.9.9WATERLEVEL-REACTORVESSELandWATERLEVEL"SPENTFUELSTORAGEPOOL.......3/4.9.10CONTROLRODREMOVAL.............................B3/49-28'3/49-23/4.9.11RESIDUALHEATREMOVALANDCOOLANTCIRCULATION...83/49"2NINEMILEPOINT-UNIT2XV1HOV3v/Gv. I BASESINDEXRla8FBIBfXP7SECTION3/4.10SPECIALTESTEXCEPTIONSPAGE3/4.10.1PRIMARYCONTAINMENTINTEGRITY...........3/4.10.2RODSE(UENCECONTROLSYSTEM.....................B3/410"1B3/410"13/4.10.3SHUTDOWNMARGINDEMONSTRATIONS..............';...B3/410"13/4.10.4RECIRCULATIONLOOPS.............................3/4.10.5OXYGEHCONCENTRATION............................3/4.10.6TRAININGSTARTUPS...............................3/4.11RADIOACTIVEEFFLUENTS3/4.11.1LIQUIDEFFLUENTSCJoncentrat1on........................................ose.................................................DLiquidRadwasteTreatmentSystem...........';".........LiquidHoldupTanks.............................~..-3/4.11.2"GASEOUSEFFLUENTSoseRate............................................DDose-NobleGases.............Dose-Iodine-131,Iodine-133,Tritium,andRadionuclidesinParticulateForm.............GaseousRadwasteTreatmentSystem....................VentilationExhaustTreatmentSystem.................ExLk'plosiveGasMixture................................MainCondenser-Offgas..............................VENTINGorPURGING...................................3/4.11.3SOLIDRADIOACTIVEWASTE.......3/4.11.4TOTALDOSE.................3/4.12RADIOLOGICALENVIRONMENTALMONITORING3/4,12.1MONITORINGPROGRAM..................-.-..............3/4.12.2LANDUSECENSUS........................3/4.12.3IHTERLABORATORYCOMPARISONPROGRAM..B3/410-183/410"1B3/410-183/411"1B3/411"1B3/411-2B3/411-2B3/411-2B3/411-3B3/411"3B3/411-4B3/411-4B3/411-483/411-5B3/411-5B3/411-5B3/411-5B3/412-1B3/412-1B3/412-2NINEMILEPOINT"UNIT2xviitto'lt201985
INDEXf>~ggFg$QPg$gpgDESIGNFEATURESSECTIONPAGE5.1SITEExclus1onArea................................LowPopulationZone........................................5>>1MapDefiningUnrestrictedAreasandSiteBoundaryRadioactiveGaseousandLiquidEffluents........for~~~~~~~~~5.2CONTAINMENTCf~~onfsguraaon.............................................5-1DesignTemperatureandPressure............................5-1SecondaryContainment..................................5-15.3REACTORCOREFuelAssemblies............................................ControlRodAssemblies.....................................5-55.4REACTORCOOLANTSYSTEMDesignPressureandTemperature............................5-5V4~golume.....................................................5.5METEOROLOGICALTOWERLOCATION............................5"65.6FUELSTORAGECt~~~1Jr1tlcal1tyo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~560rasnage.............................~~\~~~~~~~~~~~~Capacsty...................................................5.7COMPONENTCYCLICORTRANSIENTLIMIT.........................5"6NINEMILEPOINT-UNIT2XV111NOV301M5
INDEXPi",Ã75>PPP])impyADMINISTRATIVECONTROLSSECTIDNPAGE6.1RESPONSIBILITY............................................6-16.2ORGANIZATION..............................................6"16~2o1OFFSITEo~~~~~~~~~~~~~~~~~~~~~oo~o~~~~~~~~~~~~~~~~~~~~6-16.2.2NITSTAFFo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o'~~U6-16.2.3INDEPENDENTSAFETYENGINEERINGGROUP..................6-6UNCTION~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~F6-6COMPOSITIONo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~6-6RESPONSIBILITIES...........;.........................6"6ECORDS.................................R6.2;4SHIFTTECHNICALADVISOR.................6-66-66.3FACILITYSTAFFUALIFICATIONS.............................6-6~4TRAININGo~~~~~o~~~~~~~~~~~~~~~~~o~~~~~o~~~~~~~~o~~~~~~~~~~66-76o5REVIEWANDAUDITo~o~~~~~~o~~~~'~~o~~~~~~~~~~~~o~~~~~~o~~~~6-76.5.1SITEOPERATIONSREVIEWCOMMITTEE(SORC)..............6-7UNCTION~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~o~~~~~~~~~~~F6-7COMPOSITIONo~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~67ALTERNATES................................6-7MEETINGFRE(UENCY....................................6-7gUORUMo~~~~~~~~~~~~~~o~~6-7RESPONSIBILITIES~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~6"8ECORDS..............................................R6"96.5.2TECHNICALREVIEWANDCONTROL.........................6-9ACTIVITIES..............~~~~~696.5.3SAFETYREVIEWANDAUDITBOARD(SRAB)..................UNCTION~~~~~~~o~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~F6"106-10COMPOSITIONo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~6-11NINEMILEPOINT-UNIT2X1XHOV80iggg
INDEXADMINISTRATIVECONTROLSSECTIONPAGEALTERNATES...........................................6-11CONSULTANTS..........................................6-11MEETINGFRE(UENCY....................................6-11UORUM.......,...,...................,..611REVIEMo~~~~~~o~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~612ECORDSoo~~~~~~~~~~~~'o~o~~~o~o~~~~~~~~~~~~~~~~~~~~~~~613R6.6REPORTABLEEVENTACTION.........;.....,....................6"146.7SAFETYLIMITVIOLATION...................................6.8PROCEDURESANDPROGRAMS..................................6.9REPORTINGREUIREHENTS..........,........................6-146-146-166.9.1ROUTINEREPORTS.........................--......--..6"16STARTUPREPORT.......................................6-16ANNUALREPORTS.......................................6"17MONTHLYOPERATINGREPORTS..........................6"17ANNUALRADIOLOGICALENVIRONMENTALOPERATINGREPORT...6"17SEMIANNUALRADIOACTIVEEFFLUENTRELEASEREPORT.......6-186.9.2SPECIALREPORTS..................................6-206.106.11oRECORDRETENTION........................................RADIATIONPROTECTIONPROGRAM............................6-206"216.12HIGHRADIATIONAREA......................................6-216.13PROCESSCONTROLPROGRAM..................................6-236.14OFFSITEDOSECALCULATIONMANUAL..........................6-236.15MAJORCHANGESTOLIUIDGASEOUSANDSOLIDRAOMASTETREATMENTSYSTEMS........................................6-24NINEMILEPOINT-UNIT250V20iS85
ADMINISTRATIVECONTROLSINDEXPii0(lffg<gQ(gpyLISTOFFIGURESFIGURE6.2.1"16.2.2-1PAGEOFFSITEORGANIZATION................-..............-6-3UNITORGANIZATION...................................6-4LISTOFTABLESTABLEPAGE6.2.2"1IMINIMUMSHIFTCREWCOMPOSITION-TWOUNITSWITHTWOCONTROLROOMS..............................6"5NINEMILEPOINT-UNIT2NOV80t98g
SECTION1.0OEFINITIONSHOV20jS85
Pi%IF8KN87KF'/1.0DEFINITIONSThefollowingtermsaredefinedsothatuniforminterpretationofthesespecifi-cationsmaybeachieved.ThedefinedtermsappearincapitalizedtypeandshallbeapplicablethroughouttheseTechnicalSpecifications.ACTION1.1ACTIONshallbethatpartofaSpecificationwhichprescribesremedialmeasuresrequiredunderdesignatedconditions.AVERAGEPLANAREXPOSURE1.2TheAVERAGEPLANAREXPOSUREshallbeapplicabletoaspecificplanarheightandisequaltothesumoftheexposureofallthefuelrodsinthespecifiedbundleatthespecifiedheightdividedbythenumberoffuelrodsinthe.fuelbundle.AVERAGEPLANARLINEARHEATGENERATIONRAP'E1.3TheAVERAGEPLANARLINEARHEATGENERATIONRATE(APLHGR)shallbeapplicabletoaspecificplanarheightandisequaltothesumoftheLINEARHEATGENERA'FIONRATESforallthefuelrodsinthespecifiedbundleatthespecifiedheightdividedbythenumberoffuelrodsinthefuelbundle.CHANNELCALIBRATION1.4ACHANNELCALIBRATIONshallbetheadjustment,asnecessary,ofthechanneloutputsuchthatitrespondswiththenecessaryrangeandaccuracytoknownvaluesoftheparameterwhichthechannelmonitors.TheCHANNELCALIBRATIONshallencompasstheentirechannelincludingthesensorandalarmand/ortripfunctions,andshallincludetheCHANNELFUNCTIONALTEST.TheCHANNELCALIBRATIONmaybeperformedbyanyseriesofsequential,overlappingortotalchannelstepssuchthattheentirechanneliscalibrated.CHANNELCHECK1.5ACHANNELCHECKshallbethequalitativeassessmentofchannelbehaviorduringoperationbyobservation.Thisdeterminationshallinclude,wherepossible,comparisonofthechannelindicationand/orstatuswithotherindicationsand/orstatusderivedfromindependentinstrumentchannelsmeasuringthesameparameter.CHANNELFUNCTIONALTEST1.6ACHANNELFUNCTIONALTESTshallbe:aOb.Analogchannels-theinjectionofasimulatedsignalintothechannelasclosetothesensoraspracticabletoverifyOPERABILITYincludingalarmand/ortripfunctionsandchannelfailuretrips.Bistablechannels-theinjectionofasimulatedsignalintothesensortoverifyOPERABILITYincludingalarmand/ortripfunctions.NINEMILEPOINT-UNIT2
DEFINITIONSP38llF5lpga:r~)@peTheCHANNELFUNCTIONALTESTmaybeperformedbyanyseriesofsequential,overlappingortotalchannelstepssuchthattheentirechannelistested.COREALTERATION1.7COREALTERATIONshallbetheaddition,removal,relocationormovementoffuel,sources,orreactivitycontrolswithinthereactorpressure'vesselwiththevesselheadremovedandfuelinthevessel.NormalmovementoftheSRMs,IRHs,TIPsorspecialmovabledetectorsisnotconsideredaCOREALTERATION.SuspensionofCOREALTERATIONSshallnotprecludecompletionofthemovementofacomponenttoasafeconservativeposition.COREMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY1.8TheCOREMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY(CMFLPD)shallbehighestvalueoftheFLPDwhichexistsinthecore.CRITICALPOWERRATIO1.9TheCRITICALPOWERRATIO(CPR)shallbetheratioofthatpowerintheassemblywhichiscalculatedbyapplicationoftheGEXLcorrelationstocausesomepointintheassemblytoexperienceboilingtransition,dividedbytheactualfuelassemblyoperatingpower.DOSEEUIVALENTI"1311.10DOSEE(UIVALENTI-131shallbethatconcentrationofI-131,microcuriespergram,whichalonewouldproducethesamethyroiddoseasthequantityandisotopicmixtureofI-131,I-132,I-133,I-134,andI-135actuallypresent.ThethyroiddoseconversionfactorsusedforthiscalculationshallbethoselistedinTableIIIofTID-14844,"CalculationofDistanceFactorsforPowerandTestReactorSites."orTableE-7ofRegulatoryGuide1.109,"CalculationofAnnualDosestoManfromRoutineReleaseofReactorEffluentsforthePurpose.ofEvaluatingCompliancewith10CFRPart50,AppendixI,"Revision1,October1977.E"AVERAGEDISINTEGRATIONENERGYl.llEshallbetheaverage,weightedinproportiontotheconcentrationofeachradionuclideinthereactorcoolantatthetimeofsampling,ofthesumoftheaveragebetaandgammaenergiesperdisintegration,inMeV,forisotopes,withhalflivesgreaterthan15minutes,makingupatleast95Xofthetotalnon-iodineactivityinthecoolant.EMERGENCYCORECOOLINGSYSTEMECCSRESPONSETIME1.12TheEMERGENCYCORECOOLINGSYSTEM(ECCS)RESPONSETIMEshallbethattimeintervalfromwhenthemonitoredparameterexceedsitsECCSactuationset-pointatthechannelsensoruntiltheECCSequipmentiscapableofperformingitssafetyfunction,i.e.,thevalvestraveltotheirrequiredpositions,NINEHILEPOINT-UNIT21-2
DEFINITIONSPMIF5i(PA'8'!~0p~pumpdischargepressuresreachthei'rrequiredvalues,etc.Timesshallincludedieselgeneratorstartingandsequenceloadingdelayswhereapplicable.Theresponsetimemaybemeasuredbyanyseriesofsequential,overlappingortotalstepssuchthattheentireresponsetimeismeasured.END-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSETIME1.13TheEND-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSETIMEshallbethattimeintervaltocompletesuppressionoftheelectricarcbetweenthefullyopencontactsofthereci'rculationpumpcircuitbreakerfrominitialmovementoftheassociated:a.Turbinestopvalves,andb.Turbinecontrolvalves.Theresponsetimemaybemeasuredbyanyseriesofsequential,overlappingortotalstepssuchthattheentireresponsetimeismeasured.FRACTIONOFLIMITINGPOWERDENSITY4'1.14TheFRACTIONOFLIMITINGPOWERDENSITY,(FLPD)shallbetheLHGRexistingatagivenlocationdividedbythespecifiedLHGRlimitforthatbundle'ype.FRACTIONOFRATEDTHERMALPOWER1.15TheFRACTIONOFRATEDTHERMALPOWER(FRTP)shallbethemeasuredTHERMALPOWERdividedbytheRATEDTHERMALPOWER.FREUENCYNOTATION1.16TheFREQUENCYNOTATIONspecified.fortheperformanceofSurveillanceRequirementsshallcorrespondtotheintervalsdefinedinTable1.1.GASEOUSRADWASTETREATMENTSYSTEM1.17AGASEOUSRADWASTETREATMENTSYSTEMshallbeanysystemdesignedandin--stalledtoreduceradioactivegaseouseffluentsbycollectingoffgasesfromthemaincondenserevacuationsystemandprovidingfordelayorholdupforthepurposeofreducingthetotalradioactivitypriortoreleasetotheenvironment.IDENTIFIEDLEAKAGE1.18IDENTIFIEDLEAKAGEshallbe:a.Leakageintocollectionsystems,suchaspumpsealorvalvepackingleaks,thatiscapturedandconductedtoasumporcollectingtank,orb.Leakageintothecontainmentatmospherefromsourcesthatarebothspecificallylocatedandknowneithernottointerferewiththeopera-tionoftheleakagedetectionsystemsornottobePRESSUREBOUNDARYLEAKAGE.NINEMILEPOINT-UNIT21-3
DEFINITIONSP~MF5PPJ,'Pg$0pfISOLATIONSYSTEMRESPONSETIME1.19TheISOLATIONSYSTEMRESPONSETIMEshallbethattimeintervalfromwhenthemonitoredparameterexceedsitsisolationactuationsetpointatthechannelsensoruntiltheisolationvalvestraveltotheirrequiredpositions.Timesshallincludedieselgeneratorstartingandsequenceloadingdelayswhereapplicable.Theresponsetimemaybemeasuredbyanyseriesofsequential,overlappingortotalstepssuchthattheentireresponsetimeismeasured.LIMITINGCONTROLRODPATTERN1.20ALIMITINGCONTROLRODPATTERNshallbeapatternwhichresultsinthecorebeingonathermalhydrauliclimit,i.e.,operatingonalimitingvalueforAPLHGR,LHGR,orHCPR.LINEARHEATGENERATIONRATE1.21LINEARHEATGENERATIONRATE(LHGR)shallbetheheatgenerationperunitlengthoffuelrod.Itistheintegraloftheheatfluxovertheheattransferareaassociatedwiththeunitlength.LOGICSYSTEMFUNCTIONALTEST1.22ALOGICSYSTEMFUNCTIONALTESTshallbeatestofalllogiccomponents,i.e.,allrelaysandcontacts,alltripunits,solidstatelogicelements,etc.,ofalogiccircuit,fromsensorthrodghandincludingtheactuateddevice,toverifyOPERABILITY.TheLOGICSYSTEMFUNCTIONALTESTmaybeperformedbyanyseriesofsequential,overlappingortotalsystemstepssuchthattheentitelogicsystemistested.MEMBERSOFTHEPUBLIC1.23MEMBER(S)OFTHEPUBLICshallincludeallpersonswhoarenotoccupationgllyassociatedwiththeNineMilePointNuclearStationandJamesA.FitzPatrickNuclearPowerPlant.ThiscategorydoesnotincludeemployeesofNiagaraMohawkPowerCorporation,theNewYorkStatePowerAuthority,theircontrac-torsorvendors.Alsoexcludedfromthiscategoryarepersonswhoenterthesitetoserviceequipmentortomakedeliveries.Thiscategorydoesincludepersonswhouseportionsofthesiteforrecreational,occupationalorotherpurposesnotassociatedwithNineMilePointNuclearStationandJamesA.FitzPatrickNuclearPowerPlant.MINIMUMCRITICALPOWERRATIO1.24TheMINIMUMCRITICALPOWERRATIO(MCPR)shallbethesmallest.CPRwhichexistsinthecore.MILKSAMPLINGLOCATION1.25AMILKSAMPLINGLOCATIONisalocationwhere10ormoreheadofmilkanimalsareavailableforthecollectionofmilksamples.NINEMILEPOINT-UNIT2NOV801~~4
DEFINITIONS%Ã532/78MP7OFFSITEDOSECALCULATIONMANUAL1.26TheOFFSITEDOSECALCULATIONMANUAL(ODCM)shallcontainthecurrentmethod-ologyandparametersusedinthecalculationofoffsitedosesduetoradio-activegaseousandliquideffluentsandinthecalculationofgaseousandliquideffluentmonitoringalarm/tripsetpoints.OPERABLE-OPERABILITY1.27Asystem,subsystem,train,componentordeviceshallbeOPERABLEorhaveOPERABILITYwhenitiscapableofperformingitsspecifiedfunction(s)andwhenallnecessaryattendantinstrumentation,controls,electricalpower,coolingorsealwater,lubricationorotherauxiliaryequipmentthatarerequiredforthesystem,subsystem,train,componentordevicetoperformitsfunction(s)arealsocapableofperformingtheirrelatedsupportfunction(s).OPERATIONALCONDITION-CONDITION.1.28AnOPERATIONALCONDITION,i.e.,CONDITION,shallbeanyoneinclusivecombinationofmodeswitchpositionandaveragereactorcoolanttemperatureasspecifiedinTable1.2.PHYSICSTESTS1.29PHYSICSTESTSshallbethosetestsperformedtomeasurethefundamentalnuclearcharacteristicsofthereactorcoreandrelatedinstrumentationand1)describedinChapter14oftheFSAR,2)authorizedundertheprovisionsof10CFR50.59,or3)otherwiseapprovedbytheCommission.PRESSUREBOUNDARYLEAKAGE1.30PRESSUREBOUNDARYLEAKAGEshallbeleakagethroughanon-isolablefaultinareactorcoolantsystemcomponentbody,pipewallorvesselwall.PRIMARYCONTAINMENTINTEGRITY1.31PRIMARYCONTAINMENTINTEGRITYshallexistwhen:a~Allprimarycontainmentpenetrationsrequiredtobeclosedduringaccidentconditionsareeither:1.CapableofbeingclosedbyanOPERABLEprimarycontainmentautomaticisolationsystem,or2.Closedbyatleast'onemanualvalve,blindflange,ordeacti-vatedautomaticvalvesecuredinitsclosedposition,exceptasprovidedinTable3.6.3-1ofSpecification3.6.3.b.Allprimarycontainmentequipmenthatchesareclosedandsealed.C.EachprimarycontainmentairlockisincompliancewiththerequirementsofSpecification3.6.1.3.NINEMILEPOINT-UNIT21-5NOV2018Bg
DEFINITIONSd.TheprimarycontainmentleakageratesarewithinthelimitsofSpecification3.6.1.2.e.ThesuppressionpoolisincompliancewiththerequirementsofSpecification3.6.2.1.f.Thesealingmechanismassociatedwitheachprimarycontainmentpenetration;e.g.,welds,bellowsorO-rings,isOPERABLE.PROCESSCONTROLPROGRAM1.32ThePROCESSCONTROLPROGRAM(PCP)shallcontainthesampling,analysis,andformulationdeterminationbywhichSOLIDIFICATIONofradioactivewastesfromliquidsystemsisassured.PURGE"PURGING1.33PURGEandPURGINGshallbethecontrolled'processofdischargingairor.gasfromaconfinementtomaintaintemperature,pressure,concentrationorotheroperatingcondition,insuchamannerthatreplacementairorgasisrequiredtopurifytheconfinemenX.RATEDTHERMALPOWER1.34RATEDTHERMALPOWERshallbeatotalreactorcoreheattransferratetothereactorcoolantof3323MWt.REACTORPROTECTIONSYSTEMRESPONSETIME1.35REACTORPROTECTIONSYSTEMRESPONSETIMEshallbethetimeintervalfromwhenthemonitoredparameterexceedsitstripsetpointatthechannelsensoruntildeenergizationofthescrampilotvalvesolenoids.Theresponsetimemaybemeasuredbyanyseriesofsequential,overlappingortotalstepssuchthattheentireresponsetimeismeasured.REPORTABLEEVENT1.36AREPORTABLEEVENTshallbeanyofthoseconditionsspecifiedinSec-tion50.73to10CFRPart50.RODDENSITY1.37RODDENSITYshallbethenumberofcontrolrodnotchesinsertedasafractionofthetotalnumberofcontrolrodnotches.AllrodsfullyinsertedisequivalenttolOOXRODDENSITY.SECONDARYCONTAINMENTINTEGRITY1.38SECONDARYCONTAINMENTINTEGRITYshallexistwhen:a.AllReactorBuildingandAuxiliaryBayspenetrationsrequiredtobeclosedduringaccidentconditionsareeither:NINEMILEPOINT-UNIT21-6NOV201985
DEFINITIONSPkiJLuk5llZGP<PI1.CapableofbeingclosedbyanOPERABLEReactorBuildingautomaticisolationsystem,or2.Closedbyatleastonemanualvalve,blindflange,ordeactivatedautomaticdampersecuredinitsclosedposition,exceptasprovidedinTable3.6.5.2-1ofSpecification3.6.5.2.b.AllAuxiliaryBayshatchesareclosedandsealed.c.ThestandbygastreatmentsystemisincompliancewiththerequirementsofSpecification3.6.5.3.d.'tleastonedoorineachaccesstotheReactorBuildingandAuxiliaryBaysareclosed.e.ThesealingmechanismassociatedwitheachReactorBuildingandAuxil"iaryBayspenetration,e.g.,welds,bellowsorO-rings,isOPERABLE.f...'hepressurewithintheReactorBuilding,andAuxiliaryBaysislessthanorequaltothevaluerequiredbySpecification4.6.5.1.a.SHUTDOWNMARGIN1.39SHUTDOWNMARGINshallbetheamountofreactivitybywhichthereactorissubcriticalorwouldbesubcriticalassumingallcontrolrodsarefullyinsertedexceptforthesinglecontrolrodofhighestreactivity"worthwhichisassumedtobefullywithdrawnandthereactoris,intheshutdowncondition;cold,i.e.,68F;andxenonfree.SITEBOUNDARY1.40TheSITEBOUNDARYshallbethatlinearoundtheNineMilePointNuclearStationbeyondwhichthelandisnotowned,leased,orotherwisecontrolledbytheNiagaraMohawkPowerCorporationortheNewYorkStatePowerAuthority.SOLIDIFICATION1.41SOLIDIFICATIONshallbetheconversionofwetwastesintoaformthatmeetsshippingandburialgroundrequirements.SOURCECHECK1.42ASOURCECHECKshallbethequalitativeassessmentofchannelresponsewhenthechannelsensorisexposedtoasourceofincreasedactivity.STAGGEREDTESTBASIS1.43ASTAGGEREDTESTBASISshallconsistof:aoAtestschedulefornsystems,subsystems,trainsorotherdesignatedcomponentsobtainedbydividingthespecifiedtestintervalintonequalsubintervals.NINEMILEPOINT-UNIT21"7
DEFINITIONSPRK$5F~l'8/NP'fb.Thetestingofonesystem,subsystem,trainorotherdesignatedcomponentatthebeginningofeachsubinterval.THERMALPOWER1.44THERMALPOWERshallbethetotalreactorcoreheattransferratetothereactorcoolant.TURBINEBYPASSSYSTEMRESPONSETIME1.45TheTURBINEBYPASSSYSTEMRESPONSETIMEconsistsoftwotimeintervals:'a0b.Timefrominitialmovementofthemainturbinestopvalveorcontrolvalveuntil80Kofturbinebypasscapacityisestablished,andIthetimefrominitialmovementofthemainturbinestopvalveorcontrolvalveuntilinitialmovementoftheturbinebypassvalve.Eitherresponsetimesmaybemeasuredbyanyseriesofsequential,overlappingortotalstepssuchthatbothentireresponsetimecomponentsaremeasured.UNIDENTIFIEDLEAKAGEr1.46UNIDENTIFIEDLEAKAGEshallbe'allleakagewhichisnotIDENTIFIEDLEAKAGE.UNRESTRICTEDAREA1.47AnUNRESTRICTEDAREAshallbeanyareaatorbeyondtheSITEBOUNDARYaccesstowhichisnotcontrolledbytheNiagaraMohawkPowerCorporationortheNewYorkStatePowerAuthorityforpurposesofprotectionofindividualsfromexposuretoradiationandradioactivematerials,oranyareawithinthesiteboundaryusedforresidentialquartersorforindustrial,commer-cial,institutional,and/orrecreationalpurposes.VENTILATIONEXHAUSTTREATMENTSYSTEM1.48AVENTILATIONEXHAUSTTREATMENTSYSTEMshallbeanysystemdesignedandinstalledtoreducegaseousradioiodineorradioactivematerialinpartic-ulateformineffluentsbypassingventilationorventexhaustgasesthroughcharcoaladsorbersand/orHEPAfiltersforthepurposeofremovingiodinesorparticulatesfromthegaseousexhauststreampriortothereleasetotheenvironment(suchasystemisnotconsideredtohaveanyeffectonnoblegaseffluents).EngineeredSafetyFeatures(ESF)atmosphericcleanupsystemsarenotconsideredtobeVENTILATIONEXHAUSTTREATMENTSYSTEMcomponents.VENTING1.49VENTINGshallbethecontrolledprocessofdischargingairorgasfromaconfinementtomaintaintemperature,pressure,concentration,orotheroperatingcondition,insuchamannerthatreplacementairorgasisnotprovidedorrequiredduringVENTING.Vent,usedinsystemnames,doesnotimplyaVENTINGprocess.NINEMILEPOINT-UNIT2gQV201985
DEFINITIONSNvF5(PA'PNÃP'/TABLE1.1SURVEILLANCEFREUENCYNOTATIONC~~NOTATIONSAs/u~FREUENCYAtleastonceper12hours.Atleastonceper24hours.Atleastonceper7days.Atleastonceper31days.Atleastonceper92days.At.leastonceper184days.Atleastonceper366days.Atleastonceper18months(550days).Priortoeachreactorstartup.PriortoeachradioactivereleaseNotapplicable..0NINEMILEPOINT-UNIT21-9NOV201S85
DEFINITIONSPM/ggppppgee~TABLE1.2OPERATIONALCONDITIONSCONDITIONl.POWEROPERATION2.STARTUP3.HOTSHUTDOWN4.COLOSHUTDOWN5.REFUELING"MODESWITCHPOSITIONRunStartup/HotStandbyShutdown'"""Shutdown'hutdownorRefuel"*'VERAGEREACTORCOOLANTTEMPERATUREAnytemperatureAnytemperature>200F<200F<140'FhereactormodeswitchmaybeplacedintheRunorStartup/HotStandbypositiontotesttheswitchinterlockfunctionsprovidedthatthecontrolrodsareverifiedtoremainfullyinsertedbyasecondlicensedoperatororothertechnicallyqualifiedmemberoftheunittechnicalstaff.%ThereactormodeswitchmaybeplacedintheRefuelpositionwhileasinglecontrolroddriveisbeingremovedfromthereactorpressurevesselperSpecification3.9.10.1."Fuelinthereactorvesselwiththevesselheadclosureboltslessthanfullytensionedorwiththeheadremoved.""SeeSpecialTestExceptions3.10.1and3.10.3.*""ThereactormodeswitchmaybeplacedintheRefuelpositionwhileasinglecontrolrodisbeingrecoupledprovidedthattheone-rod-outinterlockisOPERABLE.NINEMILEPOINT"UNIT21"10NOVP.ulo8g
SECTION2.0SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSNOVreJS8S
2.0SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSPiiMF5[gal,'P)JgP1'.1SAFETYLIMITSTHERMALPOWERLowPressureorLowFlow2.1.1THERMALPOWERshallnotexceed25XofRATEDTHERMALPOWERwiththereactorvesselsteamdomepressurelessthan785psigorcoreflowlessthanlOXofratedflow.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:WithTHERMALPOWERexceeding25KofRATEDTHERMALPOWERandthereactorvesselsteamdomepressure'lessthan785psigorcoreflowlessthan10Kofratedflow,beinatleastHOTSHUTDOWNwithin2hoursandcomplywiththerequire-.mentsofSpecification6.7.1.THERMALPOWERHihPressureandHihFlow2.1.2TheMINIMUMCRITICALPOWERRATIO(MCPR)shallnotbelessthan1.06withthereactorvesselsteamdomepressuregreaterthan785psigandcoreflowgreaterthanlOXofratedflow.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:WithMCPRlessthan1.06andthereactorvesselsteamdomepressuregreaterthan785psigandcoreflowgreaterthanlOXofratedflow,beinatleastHOTSHUTDOWNwithin2hoursandcomplywiththerequirementsofSpecification6.7.1.REACTORCOOLANTSYSTEMPRESSURE2.1.3Thereactorcoolantsystempressure,asmeasuredinthereactorvesselsteamdome,shallnotexceed1325psig.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and4.ACTION:Withthereactorcoolantsystempressure,asmeasuredinthereactorvesselsteamdome,above1325psig,beinatleastHOTSHUTDOWNwithreactorcoolantsystempressurelessthanorequalto1325psigwithin2hoursandcomplywiththerequirementsofSpecification6.7.1.NINEMILEPOINT-UNIT22-1NOV201985
PROOF5)gpgyr,SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSSAFETYLIMITS(Continued)REACTORVESSELMATERLEVEL2.1.4Thereactorvesselwaterlevelshallbeabovethetopoftheactiveirradiatedfuel.APPLICABILITY:OPERATIONALCONDITIONS3,4and5ACTION:Withthereactorvesselwaterlevelatorbelowthetopoftheactiveirradiatedfuel,manuallyinitiatetheECCStorestorethewaterlevel,afterdepressurizingthereactorvessel,ifrequired.ComplywiththerequirementsofSpecification6.7.1.NINEMILEPOINT-UNIT22"2NOV801985
SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGS2.2LIHITINGSAFETYSYSTEMSETTINGSREACTORPROTECTIONSYSTEMINSTRUMENTATIONSETPOINTS2.2.1ThereactorprotectionsysteminstrumentationsetpointsshallbesetconsistentwiththeTripSetpointvaluesshowninTable2.2.1"1.APPLICABILITY:AsshowninTable3.3.1-1.ACTION:WithareactorprotectionsysteminstrumentationsetpointlessconservativethanthevalueshownintheAllowableValuescolumnofTable2.2.1-1,declarethechannelinoperableandapply.theapplicableACTIONstatementrequirementofSpecificati'on3.3.1untilthechannelisrestoredtoOPERABLEstatuswithitssetpointadjustedconsistentwiththeTripSetpointvalue.NINEMILEPOINT-UNIT22-3gQQ2~A.
TABLE2.2.1-1';IREACTORPROTECTIONSYSTEHINSTRUMENTATIONSETPOINTSIb.FlowBiasedSimulatedThermalPower-Upscale1)FlowBiasedc.Fixed.NeutronFlux-Upscaled.Inoperative3.ReactorVesselSteamDomePressure-High4.ReactorVesselWaterLevel-Low,Level35.HainSteamLineIsolationValve-Closure6.HainSteamLineRadiation-High7.DrywellPressure-High8.ScramDischargeVolumeMaterLevel-Higha.LevelTransmitter/TripUnitsb.FloatSwitch9.TurbineStopValve-Closure10.TurbineControlValveFastClosure,TripOilPressure-Lowll.ReactorHodeSwitchShutdownPosition12.HanualScramSeeBasesFigureB3/43-1.FUNCTIONALUNITm1.IntermediateRangeMonitor,NeutronFlux-High2.AveragePowerRangeHonitor:a.NeutronFlux-Upscale,SetdownIM2)HighFlowClampedTRIPSETPOINT<120/125divisionsoffullscalei<15XofRATEDTHERMALPOMER<0.66W+51X,withamaximumof<113.5XofRATEDTHERHALPOMER<118XofRATEDTHERHALPOWER<1037psi'g>159.3>inchesaboveinstrumentzero*<6Xclosed<3.0xfullpowerbackground<1.68psig<46.5inches<46.5inches<5Xclosed>530psigNANAALLOWABLEVALUES<122/125divisionsoffullscale<20XofRATEDTHERHALPOWER<0.66W+54X,withamaximumof<115.5XofRATEDTHERHALPOMER<120XofRATEDTHERHALPOMERNA<1057psig>157.8inchesaboveinstrumentzero<7Xclosed<36xfullpowerbackground<1.88psig<795inches<79.5inches<7Xclosed.>465psigNA
BASESFOR,SECTION2.0SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSNOV201S85
NOTETheBASEScontainedinsucceedingpagessummarizethereasonsfortheSpecificationsinSection2.0,butinaccordancewith10CFR50.36arenotpartoftheseTechnicalSpecifications.NOV20JgBg 0 2.1SAFETYLIMITSBASES
2.0INTRODUCTION
Thefuelcladding,reactorpressurevesselandprimarysystempipingaretheprincipalbarrierstothereleaseofradioactivematerialstotheenvirons.SafetyLimitsareestablishedtoprotecttheintegrityofthesebarriersduringnormalplantoperationsandanticipatedtransients.ThefuelcladdingintegritySafetyLimitissetsuchthatnofueldamageiscalculatedtooccurifthelimitisnotviolated.Becausefueldamageisnotdirectlyobservable,astep-backapproachisusedtoestablishaSafetyLimitsuchthattheMCPRisnotlessthan1.06.MCPRgreaterthan1.06representsaconservativemarginrelativetotheconditionsrequiredtomaintainfuelcladdingintegrity.Thefuelcladdingisoneofthephysicalbarrierswhichseparatetheradioactivemate-rialsfromtheenvirons.Theintegrityofthiscladdingbarrierisrelatedtoitsrelativefreedomfromperforationsorcracking.Althoughsomecorrosionoruse-relatedcrackingmayoccurduringthe'lifeofthecladding,fissionproductmigrationfromthissourceisincrementallycumulativeandcontinuouslymeasurable.Fuelcladdingperforations,however,canresultfromthermalstresse'swhichoccurfromreactoroperationsignificantlyabovedesigncondi-tionsandtheLimitingSafetySystemSettings.Whilefissionproductmigrationfromc1addingperforationisjustasmeasurableasthatfromuse-relatedcracking,thethermallycausedcladdingperforationssignalathresholdbeyondwhichstillgreaterthermalstressesmaycausegrossratherthanincrementalcladdingdeterioration.Therefore,thefuelcladdingSafetyLimitisdefinedwithamargintotheconditionswhichwouldproduceonsetoftransitionboiling,MCPRof1.0.Theseconditionsrepresentasignificantdeparturefromtheconditionintendedbydesignforplannedoperation.2.1.1THERMALPOWERLowPressureorLowFlowTheuseoftheGEXLcorrelationisnotvalidforallcriticalpowercalculationsatpressuresbelow785psigorcoreflowslessthan10Kofratedflow.Therefore,thefuelcladdingintegritySafetyLimitisestablishedbyothermeans.ThisisdonebyestablishingalimitingconditiononcoreTHERMALPOWERwiththefollowingbasis.Sincethepressuredropinthebypassregionisessentiallyallelevationhead,thecorepressuredropatlowpowerandflowswillalwaysbegreaterthan4.5psi.Analysesshowthatwithabundleflowof28x10'bs/hr,bundlepressuredropisnearlyindependentofbundlepowerandhasavalueof3.5psi.Thus,thebundleflowwitha4.5psidrivingheadwillbegreaterthan28x10'bs/hr.Full-scaleATLAStestdatatakenatpressuresfrom14.7psiato800psiaindicatethatthefuelassemblycriticalpoweratthisflowisapproximately3.35MWt.Withthedesignpeakingfactors,thiscorrespondstoaTHERMALPOWERofmorethan50KofRATEDTHERMALPOWER.Thus,aTHERMALPOWERlimitof25XofRATEDTHERMALPOWERforreactorpressurebelow785psigisconservative.NINEMILEPOINT-UNIT2B2-1ggv201985
SAFETYLIMITSBASES2.1.2THERMALPOWERHihPressureandHihFlowThefuelcladdingintegritySafetyLimitissetsuchthatnofueldamageiscalculatedtooccurifthelimitisnotviolated.Sincetheparameterswhichresultinfueldamagearenotdirectlyobservableduringreactoropera-tion,thethermalandhydraulicconditionsresultinginadeparturefromnucleateboilinghavebeenusedtomarkthebeginningoftheregionwherefueldamagecouldoccur.AlthoughitisrecognizedthatadeparturefromnucleateboilingwouldnotnecessarilyresultindamagetoBWRfuelrods,thecriticalpoweratwhichboilingtransitioniscalculatedtooccurhasbeenadoptedasaconvenientlimit.However,theuncertaintiesinmonitoringthecoreoperatingstateandintheproceduresusedtocalculatethecriticalpowerresultinanuncertaintyinthevalueofthecriticalpower.Therefore,thefuelcladdingintegritySafetyLimitisdefinedastheCPRinthelimitingfuelassemblyforwhichmorethan99.9Xofthefuelrodsinthecoreareexpectedtoavoidboilingtransitionconsideringthepowerdistributionwithinthecoreandall-uncertainties.'heSafetyLimitMCPRisdeterminedusingtheGeneralElectricThermalAna1ysisBasis,GETAB,whichisastatisticalmodelthatcombinesalloftheuncertaintiesinoperatingparametersandtheproceduresusedtocalculatecriticalpower.TheprobabilityoftheoccurrenceofboilingtransitionisdeterminedusingtheGeneralElectricCriticalguality(X)BoilingLength(L),(GEXL),correlation.TheGEXLcorrelationisvalidovertherangeofconditionsusedinthetestsofthedatausedtodevelopthecorrelation.TherequiredinputtothestatisticalmodelaretheuncertaintieslistedinBasesTableB2.1.2-1andthenominalvaluesofthecoreparameterslistedinBasesTableB2.1.2-2.ThebasesfortheuncertaintiesinthecoreparametersaregiveninNEDO"20340andthebasisfortheuncertaintyintheGEXLcorrelationisgiveninNEDO-10958-A.Thepowerdistributionisbasedonatypical764assemblycoreinwhichtherodpatternwasarbitrarilychosentoproduceaskewedpowerdistributionhavingthegreatestnumberofassembliesatthehighestpowerlevels.Theworstdistributionduringanyfuelcyclewouldnotbeassevereasthedistributionusedintheanalysis.a.GeneralElectricBWRThermalAnalysisBases(GETAB)Data,CorrelationandDesignApplication,"NEDO"10958-A.b.GeneralElectric"ProcessComputerPerformanceEvaluationAccuracy"NEDO-20340andAmendment1,NEDO-20340-1datedJune1974andDecember1974,respectively.NINEMILEPOINT-UNIT2B2-2goal/2b1985
BasesTable82.1.2-1PrÃ.'5>WVauP>UNCERTAINTIESUSEDINTHEDETERMINATIONOFTHEFUELCLADDINGSAFETYLIMIT"~uantitFeedwaterFlowFeedwaterTemperature,ReactorPressureCoreInletTemperatureCoreTotalFlowChannelFlowAreaFrictionFactorMultiplierCChannelFrictionFactor-MultiplierTIPReadingsRFactorCriticalPowerStandardDeviationXofPoint1.760.760.50.22.53.010.05.06.31.53.6heuncertaintyanalysisusedtoestablishthecorewideSafetyLimitMCPRisbasedontheassumptionofquadrantpowersymmetryforthereactorcore.NINEMILEPOINT-UNIT282-3NOV2uss+
BasesTableB2.1.2-2NOMINALVALUESOFPARAMETERSUSEDINTHESTATISTICALANALYSISOFFUELCLADDINGINTEGRITYSAFETYLIMITTHERMALPOWERCoreFlowDomePressureChannelFlowAreaR"Factor3323MW108.5Mlb/hr1010.4psig0.1089f'tHighenrichment-1.043Mediumenrichment-1.039Lowenrichment-1.030NINEMILEPOINT-UNIT2B2-4
SAFETYLIMITSBASES2.1.3REACTORCOOLANTSYSTEMPRESSURETheSafetyLimitforthereactorcoolantsystempressurehasbeenselectedsuchthatitisatapressurebelowwhichitcanbeshownthattheintegrityofthesystemisnotendangered.ThereactorpressurevesselisdesignedtoSec-tionIIIoftheASMEBoilerandPressureVesselCode1971Edition,includingAddendathroughWinter1972,whichpermitsamaximumpressuretransientofllOX,1375psig,ofdesignpressure,1250psig.TheSafetyLimitof1325psig,asmeasuredbythereactorvesselsteamdomepressureindicator,isequivalentto1375psigatthelowestelevationofthereactorcoolantsystem.ThereactorcoolantsystemisdesignedtoSectionIIIoftheASMEBoilerandPressureVesselCode,1977Edition,includingAddendathroughSummer1977forthereactorrecir-culationpiping,whichpermitsamaximumpressuretransientof120~ofdesignpressure.Thedesignpressuresare1250psigforsuctionpipingand1650psigfordischargepipingtotheexitofthedischargeblockvalveand1550psigfortheremainderofthedischargepipingtothevesselnozzles.ThepressureSafetyLimitisselectedtobethe.lowesttransientoverpressureallowedbySectionIIIofthe'ASMEBoilerandPressureVesselCode,1971Edition,includingAddendathrough,Winter1972.2.1.4REACTORVESSELWATERLEVELWithfuelinthereactorvesselduringperiodswhenthereactorisshutdown,considerationmustbegiventowaterlevelrequirementsduetotheeffectofdecayheat.Ifthewaterlevelshoulddropbelowthetopoftheactiveirradiatedfuelduringthisperiod,theabilitytoremovedecayheatisreduced.Thisreductionincoolingcapabilitycouldleadtoelevatedcladdingtemperaturesandcladperforationintheeventthatthewaterlevelbecamelessthantwo-thirdsofthecoreheight.TheSafetyLimithasbeenestablishedatthetopoftheactiveirradiatedfueltoprovideapointwhichcanbemonitoredandalsoprovideadequatemarginforeffectiveaction.NINEMILEPOINT-UNIT2B2-5NGV201985
2.2LIMITINGSAFETYSYSTEMSETTINGSNMk5KEPTFuP7BASES2.2.1REACTORPROTECTIONSYSTEMINSTRUMENTATIONSETPOINTSTheReactorProtectionSysteminstrumentationsetpointsspecified'inTable2.2.1"1arethevaluesatwhichthereactortripsaresetforeachparam-eter.TheTripSetpointshavebeenselectedtoensurethatthereactorcoreandreactorcoolantsystemarepreventedfromexceedingtheirSafetyLimitsduringnormaloperationanddesignbasisanticipatedoperationaloccurrencesandtoassistinmitigatingtheconsequencesofaccidents.OperationwithatripsetlessconservativethanitsTripSetpointbutwithinitsspecifiedAllowableValueisacceptableonthebasisthatthedifferencebetweeneachTripSetpointandtheAllowableValueisanallowanceforinstrumentdriftspecificallyallocatedforeachtripinthesafetyanalyses.Thetripset-pointsandallowablevaluesalsocontainadditionalmarginforinstrumentaccuracyandcalibrationcapability.l..IntermediateRaneMonitorNeutronflux-HihTheIRMsystemconsistsof8chambers,4ineachofthereactortripsystems.TheIRMisa5decade10rangeinstrument.Thetripsetpointof120divisionsofscaleisactiveineachofthe10ranges.ThusastheIRMisrangeduptoaccommodatetheincreaseinpowerlevel,thetripsetpointisalso.rangedup.TheIRMinstrumentsprovideforoverlapwithboththeAPRMandSRMsystems.Themostsignificantsourceofreactivitychangesduringthepowerincreaseisduetocontrolrodwithdrawal.InordertoensurethattheIRMprovidestherequiredprotection,arangeofrodwithdrawalaccidentshavebeenanalyzed.TheresultsoftheseanalysesareinSection15.4oftheFSAR.ThemostseverecaseinvolvesaninitialconditioninwhichTHERMALPOWERisatapproximately1XofRATEDTHERMALPOWER.AdditionalconservatismwastakeniathisanalysisbyassumingtheIRMchannelclosesttothecontrolrodbeingwithdrawnisbypassed.Theresultsofthisanalysisshowthatthereactorisshutdownandpeakpowerislimitedto22KofRATEDTHERMALPOWERwiththepeakfuelenthalpywellbelowthefuelfailurethresholdof170cal/gm.Basedonthisanalysis,theIRMprovidesprotectionagainstlocalcontrolroderrorsandcontinuouswithdrawalofcontrolrodsinsequenceandprovidesbackupprotec-tionfortheAPRM.2.AveraePowerRaneMonitorForoperationatlowpressureandlowflowduringSTARTUP,theAPRMscramsettingof15KofRATEDTHERMALPOWERprovidesadequatethermalmarginbetweenthesetpointandtheSafetyLimits.Themarginaccommodatestheanticipatedmaneuversassociatedwithpowerplantstartup.Effectsofincreasingpressureatzeroorlowvoidcontentareminorandcoldwaterfromsourcesavailableduringstartupisnotmuchcolderthanthatalreadyinthesystem.Tempera-turecoefficientsaresmallandcontrolrodpatternsareconstrainedbytheRSCSandRWM.Ofallthepossiblesourcesofreactivityinput,uniformcontrolNINEMILEPOINT-UNIT2B2-6ggyg01985
LIHITINGSAFETYSYSTEHSETTINGSp9(pffQIpggppll(BASESREACTORPROTECTIONSYSTEMINSTRUMENTATIONSETPOINTS(Continued)AveraePowerRaneMonitor(Continued)rodwithdrawalisthemostprobablecauseofsignificantpowerincrease.Becausethefluxdistributionassociatedwithuniformrodwithdrawalsdoesnotinvolvehighlocalpeaksandbecauseseveralrodsmustbemovedtochangepo~erbyasignificantamount,therateofpowerriseisveryslow.'enerallytheheatfluxisinnearequilibriumwiththefissionrate.Inanassumeduniformrodwithdrawalapproachtothetriplevel,therateofpowerriseisnotmorethan5XofRATEQTHERMALPOWERperminuteandtheAPRHsystemwouldbemorethanadequatetoassureshutdownbefo'rethepowercouldexceedtheSafetyLimit.The15%neutronfluxtripremainsactiveuntilthemodeswitchisplacedintheRunposition.TheAPRMtripsystemiscalibratedusingheat=balancedatatakenduringsteadystateconditions.FissionchambersprovidethebasicinputtothesystemandthereforethemonitorsresponddirectlyandquicklytochangesduetotransientoperationforthecaseoftheFixedNeutronFlux-Upscalesetpoint;i.e.,forapowerincrease,theTHERMALPOWERofthefuelwillbelessthanthatindicatedbytheneutronfluxduetothetimeconstantsoftheheattransferassociatedwiththefuel.FortheFlowBiasedSimulatedThermalPower"Upscalesetpoint,atimeconstantof6t0.6secondsisintroducedintotheflowbiased.-APRMinordertosimulatethefuelthermaltransientcharac"teristics.AmoreconservativemaximumvalueisusedfortheflowbiasedsetpointasshowninTable2.2.l"l.TheAPRMsetpointswereselected.toprovideadequatemarginfortheSafetyLimitsandyetallowoperatingmarginthatreducesthepossibilityofunneces-.saryshutdown.TheflowreferencedtripsetpointmustbeadjustedbythespecifiedformulainSpecification3.2.2inordertomaintainthesemarginswhenCHFLPOisgreaterthanorequaltoFRTP.3.ReactorVesselSteamOomePressure-HihHighpressureinthenuclearsystemcouldcausearupturetothenuclearsystemprocessbarrierresultinginthereleaseoffissionproducts.Apressureincreasewhileoperatingwillalsotendtoincreasethepowerofthereactorbycompressingvoidsthusaddingreactivity.Thetripwillquicklyreducetheneutronflux,counteractingthepressureincrease.Thetripsettingisslightlyhigherthantheoperatingpressuretopermitnormaloperationwithoutspurioustrips.Thesettingprovidesforawidemargintothemaximumallowabledesignpressureandtakesintoaccountthelocationofthepressuremeasurementcom-paredtothehighestpressurethatoccursinthesystemduringatransient.Thistripsetpointiseffectiveatlowpower/flowconditionswhentheturbinecontrolvalvefastclosure,andturbinestopvalveclosuretripsarebypassed.Forloadrejectionoraturbinetripundertheseconditions,thetransientanalysisindicatedanadequatemargintothethermalhydrauliclimit.NINEMILEPOINT-UNIT2B2-7ggq,g0$985
LIMITINGSAFETYSYSTEMSETTINGS)Bg~PPggigppikf)palBASESREACTORPROTECTIONSYSTEMINSTRUMENTATIONSETPOINTS(Continued)4.ReactorVesselWaterLevel-LowThereactorvesselwaterleveltripsetpointwaschosenfarenoughbelow'henormaloperatingleveltoavoidspurioustripsbuthighenoughabovethefueltoassurethatthereisadequateprotectionforthefuelandpressurelimits.5.MainSteamLineIsolationValve-ClosureThemainsteamlineisolationvalveclosuretripwasprovidedtolimittheamountoffissionproductreleaseforcertainpostulatedevents.TheMSIV'sareclosedautomaticallyfrommeasuredparameterssuchashighsteamflow,highsteamlineradiation,lowreactorwater'level,highsteamtunnel.temperature,andlowsteamlinepressure.TheMSIV'sclosurescramanticipatesthepressureandfluxtransientswhichcouldfollowMSIVclosureandthereby.protectsreactorvesselpressureandfuelthermal/hydraulicSafetyLimits.6.'ainSteamLineRadiation-Hihr.'~Themainsteamfailureofthefueljnitiatedtoreducethemainsteamlineproducts.Thetriptopreventspuriousthefuelcladding.lineradiationdetectorsareprovidedtodetectagrosscladding.Whenthehighradiationisdetected;atripisthecontinuedfailureoffuelcladding.Atthesametimeisolationvalvesareclosedtolimitthereleaseoffissionsettingishighenoughabovebackgroundradiationlevelstripsyetlowenoughtopromptlydetectgrossfailuresin7.OrellPressure-Hih0Highpressureinthedrywellcouldindicateabreakintheprimarypressureboundarysystems.Thereactoristrippedinordertominimizethepossibilityoffueldamageandreducetheamountofenergybeingaddedtothecoolant.Thetripsettingwasselectedaslowaspossiblewithoutcausingspurioustrips.8.ScramOischareVolumeWaterLevel-HihThescramdischargevolumereceivesthewaterdisp'lacedbythemotionofthecontrolroddrivepistonsduringareactorscram.Shouldthisvolumefilluptoapointwherethereisinsufficientvolumetoacceptthedisplacedwateratpressuresbelow65psig,controlrodinsertionwouldbehindered.Thereactoristhereforetrippedwhenthewaterlevelhasreachedapointhigh.enoughtoindicatethatitisindeedfillingup,butthevolumeisstillgreatenoughtoaccommodatethewaterfromthemovementoftherodsatpressuresbelow65psigwhentheyaretripped.Thetripsetpointforeachscramdischargevolumeisequivalenttoacontainedvolumeofapproximately25gallonsofwater.NINEMILEPOINT-UNIT2B2-8NOVP01985
LIMITINGSAFETYSYSTEMSETTINGBASESREACTORPROTECTIONSYSTEMINSTRUMENTATIONSETPOINTS(Continued)9.TurbineStoValve-Closure</oTheturbinestopvalveclosuretripanticipatesthepressure,neutronflux,andheatfluxincreasesthatouldresultfromclosureofthestopvalves.Withatripsettingofofvalve'closurefromfullopen,theresultantincreaseinheatfluxissuchthatadequatethermalmargins.aremaintainedduringtheworstcasetransient.10.TurbineControlValveFastClosureTriOilPressure-LowTheturbinecontrolvalvefastclosuretripanticipatesthepressure,neutronflux,andheatfluxincreasethatcouldresultfromfastclosureoftheturbinecontrolvalvesduetoloadrejectionwithorwithoutcoincidentfailureoftheturbinebypassvalves.TheReactorProtectionSysteminit-iatesatripwhenfastclosureoftheconf:rolvalvesisinitiatedbythefast'actingsolenoidvalvesandinlessthan30millisecondsafterthestart.ofcon-trolvalvefastclosure.Thisisachievedbytheactionofthefastactingsolenoidvalvesinrapidlyreducinghydraulictripoilpressureatthemainturbinecontrolvalveactuatordiscdumpvalves.Thislossofpressure=issensedbypressureswitcheswhosecontactsformtheone-out-of-two-twicelogicinputtotheReactorProtectionSystem.Thistripsetting,aslowerclosuretime,andadifferentvalvecharacteristicfromthatoftheturbinestopvalve,combinetoproducetransientswhichareverysimilartothatforthestopvalve.RelevanttransientanalysesarediscussedinSection15.2.2oftheFinalSafetyAnalysisReport.ll.ReactorModeSwitchShutdownPositionThereactormodeswitchShutdownpositionisaredundantchanneltotheautomaticprotectiveinstrumentationchannelsandprovidesadditionalmanualreactortripcapability.12.ManualScramTheManualScramisaredundantchanneltotheautomaticprotectiveinstrumentationchannelsandprovidesmanualreactortripcapability.NINEMILEPOINT"UNIT2B2-9NOV201SSS
SECTIONS3.0and4.0LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTSNOV201S95
3/4.0APPLICABILITYLIMITINGCONDITIONFOROPERATION%SF~!PFZD{ZP73.0.1CompliancewiththeLimitingConditionsforOperationcontained.inthesucceedingSpecificationsisrequiredduringtheOPERATIONALCONDITIONSorotherconditionsspecifiedtherein;exceptthatuponfailuretomeettheLimitingConditionsforOperation,theassociatedACTIONrequirementsshallbemet.3.0.2NoncompliancewithaSpecificationshallexistwhentherequirementsoftheLimitingConditionforOperationandassociatedACTIONrequirementsarenotmetwithinthespecifiedtimeintervals.IftheLimitingConditionforOperationisrestoredpriortoexpirationofthespecifiedtimeintervals,completionoftheActionrequirementsisnotrequired..3.0.3WhenaLimitingConditionforOperationisnotmet,exceptasprovidedintheassociatedACTIONrequirements,withinonehouractionshallbeinitiatedtoplacetheunitinanOPERATIONALCONDITIONinwhichtheSpecificationdoesnotapplybyplacingit,asapplicable,in:1.AtleastSTARTUPwithinthenext6hours,2.AtleastHOTSHUTDOWNwithinthefollowing6hours,and3.AtleastCOLDSHUTDOWNwithinthesubsequent24hours.WherecorrectivemeasuresarecompletedthatpermitoperationundertheACTIONrequirements,theACTIONmaybetakeninaccordancewiththespecifiedtimelimitsasmeasuredfromthetimeoffailuretomeettheLimitingConditionforOperation.ExceptionstotheserequirementsarestatedintheindividualSpecifications.ThisSpecificationisnotapplicableinOPERATIONALCONDITIONS4or5.3.0.4EntryintoanOPERATIONALCONDITIONorotherspecifiedconditionshallnotbemadeunlesstheconditionsfortheLimitingConditionforOperationaremetwithoutrelianceonprovisionscontainedintheACTIONrequirements.Thizprovisionshallnotpreventpassagethroughorto.OPERATIONALCONDITIONSasrequiredtocomplywithACTIONrequirements.ExceptionstotheserequirementsarestatedintheindividualSpecifications.NIMEMILEPOINT-UNIT23/40-1HOV201885 a' APPLICABILITYPM3Fg$Pj'Qf{gp~SURVEILLANCEREUIREMENTS4.0.1SurveillanceRequirementsshallbemetduringtheOPERATIONALCONOITIONSorotherconditionsspecifiedforindividualLimitingConditionsforOperationunlessotherwisestatedinanindividualSurveillanceRequirement.4.0.2EachSurveillanceRequirementshallbeperformedwithinthespecifiedtimeintervalwith:a.Amaximumallowableextensionnottoexceed25Kofthesurveillanceinterval,butb.Thecombinedtimeintervalforanythreeconsecutivesurveillanceintervalsshallnotexceed3.25timesthespecifiedsurveillanceinterval.,4.0.3FailuretoperformaSurveillanceRequirementwithinthespecifiedtimeintervalshallconstituteafailuretomeettheOPERABILITYrequirementsforaLimitingConditionforOperation.ExceptionstotheserequirementsarestatedintheindividualSpecifications.Surveillancerequirementsdonothavetabeperformed'oninoperableequipment.4.0.4EntryintoanOPERATIONALCONOITIONorotherspecifiedapplicableconditionshallnotbemadeunlesstheSurveillanceRequirement(s)associatedwiththeLimitingConditionforOperationhavebeenperformedwithintheapplicablesurveillanceintervalorasotherwisespecified.4.0.5SurveillanceRequirementsforinserviceinspectionandtestingofASMECodeClass1,2,and3componentsshallbeapplicableasfollows:a.InserviceinspectionofASMECodeClass1,2,and3componentsandinservicetestingofASMECodeClass1,2,and3pumpsandvalvesshallbeperformedinaccordancewithSectionXIoftheASMEBoilerandPressureVesselCodeandapplicableAddendaasrequiredby10CFR50,Section50.55a(g),exceptwherespecificwrittenreliefhasbeengrantedbytheCommissionpursuantto10CFR50,Section50.55a(g)(6)(i).b.SurveillanceintervalsspecifiedinSectionXIoftheASMEBoilerandPressureVesselCodeandapplicableAddendafortheinserviceinspectionandtestingactivitiesrequiredbytheASMEBoilerandPressureVesselCodeandapplicableAddendashallbeapplicableasfollowsintheseTechnicalSpecifications:ASMEBoilerandPressureVesselCodeandapplicableAddendaterminologyforinserviceinsectionandtestinactivitiesMeeklyMonthlyquarterlyorevery3monthsSemiannuallyorevery6monthsEvery9monthsYearlyorannuallyRequiredfrequenciesforperforminginserviceinspectionandtestingactivitiesAtleastonceper7daysAtleastonceper31daysAtleastonceper92daysAtleastonceper184daysAtleastonceper276daysAtleastonceper366daysNIMEMILEPOINT-UNIT23/40-2gQV201985
APPLICABILITYSURVEILLANCEREUIREMENTSContinuedP20uF~PPPP()gpyC.d.e.TheprovisionsofSpecification4.0.2areapp1icab1etotheaboverequiredfrequenciesforperforminginserviceinspectionandtestingactivities.Performanceoftheaboveinserviceinspectionandtestingactivitiessha11beinadditiontootherspecifiedSurveillanceRequirements.NothingintheASMEBoi1erandPressureVesse1Codesha11beconstruedtosupersedetherequirementsofanyTechnica1Specification.NIMEMILEPOINT"UNIT23/40"3NOV80)ggg
3/4.1REACTIVITYCONTROLSYSTEMS3/4.l.ISHUTDOWNMARGINLIMITINGCONDITIONFOROPERATIONPilU~FgfppJ/)><py3.1.1TheSHUTDOWNMARGINshallbeequaltoorgreaterthan:a.0.38Kdeltak/kwiththehighestworthrodanalyticallydetermined,orb.0.28Kdeltak/kwiththehighestworthroddeterminedbytest.APPLICABILITY:OPERATIONALCONDITIONS1,2,3,4and5.ACTION:Withtheka0b.C.SHUTDOWNMARGINlessthanspecified:InOPERATIONALCONDITION1or2reestablishtherequiredSHUTDOWN'ARGINwithin6hoursorbeinatleastHOTSHUTDOWNwithinthenext12hours.InOPERATIONALCONDITION3or4,immediatelyverifyallinsertablecontrolrodstobeinsertedandsuspendallactivitiesthatcouldreducetheSHUTDOWNMARGIN.InOPERATIONALCONDITION4,.establishSECONDARYCONTAINMENTINTEGRITYwithin8hours.InOPERATIONALCONDITION5,suspendCOREALTERATIONSandotheractivitiesthatcouldreducetheSHUTDOWNMARGINandinsertallinsertablecontrolrodswithinIhour.EstablishSECONDARYCONTAIN-MENTINTEGRITYwithin8hours.SURVEILLANCEREUIREMENTS4.1.1TheSHUTDOWNMARGINshallbedeterminedtobeequaltoorgreaterthanspecifiedatanytimeduringthefuelcycle:a.Bymeasurement,priortoorduringthefirststartupaftereachrefueling.b.Bymeasurement,within500MWD/TpriortothecoieaverageexposureatwhichthepredictedSHUTDOWNMARGIN,includinguncertaintiesandcalculationbiases,isequaltothespecifiedlimit.c.Within12hoursafterdetectionofawithdrawncontrolrodthatisimmovab'le,asaresultofexcessivefrictionormechanicalinter-ference,orisuntrippable,exceptthattheaboverequiredSHUTDOWNMARGINshallbeverifiedacceptablewithanincreasedallowanceforthewithdrawnworthoftheimmovableoruntrippablecontrolrod.NINEMILEPOINT-UNIT23/41-1
REACTIVITYCONTROLSYSTEMS3/4.1.2REACTIVITYANOMALIESLIMITINGCONDITIONFOROPERATION3.1.2ThereactivityequivalenceofthedifferencebetweentheactualRODDENSITYandthepredictedRODDENSITYshallnotexceedIXdeltak/k.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:WiththereactivityequivalencedifferenceexceedingIXdeltak/k:a0b.Within12hoursperformananalysistodetermineandexplainthecauseofthereactivitydifference;operationmaycontinueifthedifferenceisexplainedand.corrected.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.'URVEILLANCEREUIREMENTS4.1.2ThereactivityequivalenceofthedifferencebetweentheactualRODDENSITYandthepredictedRODDENSITYshallbeverifiedtobelessthanorequalto2Xdeltak/k:a.DuringthefirststartupfollowingCOREALTERATIONS,and0b.Atleastonceper31effectivefullpowerdaysduringPOWEROPERATION.NINEMILEPOINT-UNIT23/41-2NOV2019',
REACTIVITYCONTROLSYSTEMS3/4.1.3CONTROLRODSCONTROLRODOPERABILITYLIMITINGCONDITIONFOROPERATION3.1.3.1AllcontrolrodsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:Withonecontrolrodinoperableduetobeingimmovable,asaresultofexcessivefrictionormechanicalinterference,orknowntobeuntrippable:1.Withinonehour:a)Verifythattheinoperablecontrolrod,ifwithdrawn,isseparatedfroma'llotherinoperablecontrolrodsbyatleasttwocontrol.cellsinalldirections.b)Disarmtheassociateddirectionalcontrolvalves""~b.7~h~draulicallybyclosingthedrivewaterandexhaustwaterisolation.valves.c)ComplywithSurveillanceRequirement4.1.1.c.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.2.RestoretheinoperablecontrolrodtoOPERABLEstatuswithin48hoursorbeinatleastHOTSHUTDOWNwithinthenext12hours.WithoneormorecontrolrodstrippablebutinoperableforcausesotherthanaddressedinACTIONa,above:l.Iftheinoperablecontrolrod(s)iswithdrawn,withinonehour:a)Verifythattheinoperablewithdrawncontrolrod(s)isseparatedfromallotherinoperablewithdrawncontrolrodsbyatleasttwocontrolcellsinalldirections,andb)Demonstratetheinsertioncapabilityoftheinoperablewithdrawncontrolrod(s)byinsertingthecontrolrod(s)atleastonenotchbydrivewaterpressurewithinthenormaloperatingrange".Otherwise,inserttheinoperablewithdrawncontrolrod(s)anddisarmtheassociateddirectionalcontrolvalves*"either:a)Electrically,orb)Hydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.Theinoperablecontrolrodmaythenbewithdrawntoapositionnofurtherwithdrawnthanitspositionwhenfoundtobeinoperable.""Mayberearmedintermittently,underadministrativecontrol,topermittestingassociatedwithrestoringthecontrolrodtoOPERABLEstatus.NINEMILEPOINT-UNIT23/41-3NOV2uIggg
REACTIVITYCONTROLSYSTEMSLIMITINGCONDITIONFOROPERATIONContinuedACTION(Continued)2.Iftheinoperablecontrolrod(s)isinserted,withinonehourdisarmtheassociateddirectionalcontrolvalves~"either:a)Electrically,orb)Hydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.C.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.3.TheprovisionsofSpecification3.0.4arenotapplicable.Withmorethan8controlrodsinoperable,beinatleastHOTSHUTDOWNwithin12'ours.SURVEILLANCEREUIREMENTS4.L3.L1ThescramdischargevolumedrainandventvalvesshallbedemonstratedOPERABLEby:~~a.Atleastonceper31daysverifyingeachvaTvetobeopen,"andb.Atleastonceper92dayscyclingeachvalvethroughatleastonecompletecycleoffulltravel.4.1.3.1.2WhenabovethelowpowersetpointoftheRWMandRSCS,allwithdrawncontrolrodsnotrequiredtohavetheirdirectionalcontrolvalvesdisarmedelectricallyorhydraulicallyshall,bedemonstratedOPERABLEbymovingeachcontrolrodatleastonenotch:a.Atleastonceper7days,andb.Atleastonceper24hourswhenanycontrolrodisimmovableasaresultofexcessivefrictionormechanicalinterference.4.1.3.1.3AllcontrolrodsshallbedemonstratedOPERABLEbyperformanceofSurveillanceRequirements4.1.3.2,4.1.3.4,4.1.3.5,4.1.3.6and4.1.3.7.Thesevalvesmaybeclosedintermittentlyfortestingunderadministrativecontrols.""Mayberearmedintermittently,underadministrativecontrol,topermittestingassociatedwithrestoringthecontrolrodtoOPERABLEstatus.NINEMILEPOINT-UNIT23/41"4AIOV30>goy
REACTIVITYCONTROLSYSTEMSSURVEILLANCEREUIREMENTSContinuedPikÃF),~PPPyIqvPy4.1.3.1.4ThescramdischargevolumeshallbedeterminedOPERABLEbydemonstrating:a.ThescramdischargevolumedrainandventvalvesOPERABLEatleastonceper18months,byverifyingthatthedrainandventvalves:1.Closewithin30secondsafterreceiptofasignalforcontrolrodstoscram,and2.Openwhenthescramsignalisreset.b.Properfloatresponsebyverificationofproperfloatswitchactuationwithin.72hours'ftereachscramfromapressurizedconditiongreaterthanorequalto900psig.NINEMILEPOINT-UNIT23/41-5HOV203s85
REACTIVITYCONTROLSYSTEMSCONTROLRODMAXIMUMSCRAMINSERTIONTIMESLIMITINGCONDITIONFOROPERATIONPt(gjjFggPPCIgspy3.1.3.2Themaximumscraminsertiontimeofeachcontrolrodfromthefullywithdrawnpositiontonotchposition5,basedondeenergizationofthescrampilotvalvesolenoidsastimezero,shallnotexceed7.0seconds.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:a.Withthemaximumscraminsertiontimeofoneormorecontrolrodsexceeding7.0seconds:1.Declarethecontrolrod(s)withtheslowinsertiontimeinoperable,and2.PerformtheSurveillanceRequirementsofSpecification4.1.3.2.c;at:leastonceper60dayswhenoperationiscontinuedwiththreeoriaorecontrolrodswithmaximumscraminsertiontimesinexcessof7.0seconds.Otherwise,beinatleastHOTSHUTDOWNwithin12hours.b.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.1.3.2Themaximumscraminsertiontimeofthecontrolrodsshallbedemonstratedthroughmeasurementwithreactorcoolantpressuregreaterthan.orequalto950psigand,duringsinglecontrolrodscramtimetests,thecontrolroddrivepumpsisolatedfromtheaccumulators:aob.C.ForallcontrolrodspriortoTHERMALPOWERexceeding40KofRATEDTHERMALPOWERfollowingCOREALTERATIONSorafterareactorshutdownthatisgreaterthan120days.Forspecificallyaffectedindividualcontrolrodsfollowingmaintenanceonormodificationtothecontrolrodorcontrolroddrivesystemwhichcouldaffectthescraminsertiontimeofthosespecificcontrolrods,andForatleastlOXofthecontrolrods,onarotatingbasis,atleastonceper120daysofPOWEROPERATION.NINEMILEPOINT-UNIT23/41"6SOY201885~~'I
REACTIVITYCONTROLSYSTEMSCONTROLRODAVERAGESCRAMINSERTIONTIMESLIMITINGCONOITIONFOROPERATION3.1.3.3TheaveragescraminsertiontimeofallOPERABLEcontrolrodsfromthefullywithdrawnposition,basedondeenergizationofthescrampilotvalvesolenoidsastimezero,shallnotexceedanyofthefollowing:PositionInsertedFromFullWithdrawnAverageScramInser-tionTimeSeconds450.43390.86251.9353.49APPLICABILITY:OPERATIONALCONOITIONS1Znd2.ACTION:Withtheaveragescraminsertiontimeexceedinganyoftheabovelimits,beinatleastHOTSHUTOOWNwithin12hours.SURVEILLANCEREUIREMENTS4.1.3.3AllcontrolrodsshallbedemonstratedOPERABLEbyscramtimetestingfromthefullywithdrawnpositionasrequiredbySurveillanceRequirement4.1.3.2.NINEMILEPOINT"UNIT23/41"7NOV201985
REACTIVITYCONTROLSYSTEMSFOURCONTROLRODGROUPSCRAMINSERTIONTIMESLIMITINGCONDITIONFOROPERATIONP)JAP9tlplnn>rn~~~qQllew9re)Qjfj'3.1.3.4Theaveragescraminsertiontime,fromthefullywithdrawnposition,forthethreefastestcontrolrodsineachgroupoffourcontrolrodsarrangedinatwo-by-twoarray,basedondeenergizationofthescrampilotvalvesolenoidsastimezero,shallnotexceedanyofthefollowing:PositionInsertedFromFullWithdrawn4539255AverageScramInser-tionTimeSeconds0.450.922.053.70APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:a.Withtheaveragescraminsertiontimesofcontrolrodsexceedingtheabove~limits:1.Declarethecontrolrodswiththeslowerthanaveragescraminsertiontimesinoperableuntilananalysisisperformedtodeterminethatrequiredscramreactivityremainsfortheslowfourcontrolrodgroup,and2.PerformtheSurveillanceRequirementsofSpecification4.1.3.2.catleastonceper60dayswhenoperationiscontinuedwithanaveragescraminsertiontime(s)inexcessoftheaveragescraminsertiontime.limit.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.b.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.1,3.4AllcontrolrodsshallbedemonstratedOPERABLEbyscramtimetestingfromthefullywithdrawnpositionasrequiredbySurveillanceRequirement4.1.3.2.NINEMILEPOINT"UNIT23/41-8NOY201985
REACTIVITYCONTROLSYSTEMSCONTROLRODSCRAMACCUMULATORSPi%"75(Ppp~~j))pyLIMITINGCONDITIONFOROPERATION3.1.3.5AllcontrolrodscramaccumulatorsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1,2and5".ACTION:a4b.C.a)b)Electrically,orHydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.2.Withmorethanonewithdrawncontrolrodwiththeassociatedscramaccumulatorinoperableornocontrolroddrivepumpoperating,immediatelyplacethereactormodeswitchintheShutdownposition.TheprovisionsofSpecification3.0.4arenotapplicable.InOPERATIONALCONDITIONS1or2:1.Withonecontrolrodscramaccumulatorinoperable,within8hours:a)RestoretheinoperableaccumulatortoOPERABLEstatus,orb)Declarethecontrolrodassociatedwiththeinoperable'.accumulatorinoperable.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.2.Withmorethanonecontrolrodscramaccumulatorinoperable,':declaretheassociatedcontrolrodsinoperableand:Pa)Ifthecontrolrodassociatedwithanyinoperablescramaccumulatoriswithdrawn,immediatelyverifythatatleastonecontrolroddrivepumpisoperatingbyinsertingatleastonewithdrawncontrolrodatleastonenotchorplacethereactormodeswitchintheShutdownposition.b)Inserttheinoperablecontrolrodsanddisarmtheassociatedcontrolvalveseither:1)Electrically,or2)Hydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.Otherwise,beinatleastHOTSHUTDOWNwithin12hours.InOPERATIONALCONDITION5":1.Withonewithdrawncontrolrodwithitsassociatedscramaccumulatorinoperable,inserttheaffectedcontrolrodanddisarmtheassociateddirectionalcontrolvalveswithinonehoGr,either:Atleasttheaccumulatorassociatedwitheachwithdrawncontrolrod.NotapplicabletocontrolrodsremovedperSpecification3.9.10.1or3.9.10.2.NINEMILEPOINT-UNIT23'-9ROY201985
REACTIVITYCONTROLSYSTEMSSURVEILLANCEREUIREMENTS4.1.3.5aOEachcontrolrodscramaccumulatorshallbedeterminedOPERABLE:Atleastonceper7daysbyverifyingthattheindicatedpressureisgreaterthanorequalto940psigunlessthecontrolrodisinsertedanddisarmedorscrammed.b.Atleastonceper18monthsby:1.Performanceofa:a)CHANNELFUNCTIONALTESToftheleakdetectors,andb)CHANNELCALIBRATIONofthepressuredetectors,andverifyinganalarmsetpointof+psigondecreasingpressure.lezS~ra-42..Measuringandrecordingforupto10minutesthateachindividualaccumulatorcheckvalvemaintainstheassociatedaccumulatorpressureabovethealarmsetpointwithnocontrolroddrivepumpchargingwatersupplyingthescramaccumulatorsbyclosingchargingwatermanual,isolationvalveV28anddepressurizingchargingwaterheaderbyopeningvalvesV67andV68.NINEMILEPOINT-UNIT23/41-10AOV20lg,
REACTIVITYCONTROLSYSTEMSCONTROLRODDRIVECOUPLINGLIMITINGCONDITIONFOROPERATION3.1.3e6Allcontrolrodsshallbecoupledtotheirdrivemechanisms.APPLICABILITY:OPERATIONALCONDITIONS1,2and5".ACTION:a.InOPERATIONALCONOITION1and2withonecontrolrodnotcoupledtoiteassociateddrivemechanism,within2hours:l.IfpermittedbytheRWMandRSCS,insertthecontrolroddrivemechanismtoaccomplishrecouplingandverifyrecouplingbywithdrawingthecontrolrod,and:a)Observinganyindicatedresponseofthenuclearinstrumentation,andb.b)Demonstratingthatthecontrolrodwillnotgototheovertravelposition.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.2.Ifrecouplingisnotaccomplishedonthefirstattemptor,ifnotpermittedbytheRWMorRSCS,thenuntilpermittedbytheRWMandR$CS,declarethecontrolrodinoperable,insertthecontrolrodanddisarmtheassociateddirectionalcontrolvalves*"either:a)Electrically,orb)Hydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.InOPERATIONALCONDITION5"withawithdrawncontrolrodnotcoupledtoitsassociateddrivemechanism,within2hours,either:l.Insertthecontrolrodtoaccomplishrecouplingandverifyrecouplingbywithdrawingthecontrolrodanddemonstratingthatthecontrolrodwillnotgototheovertravelposition,or2.Ifrecouplingisnotaccomplished,insertthecontrolrodanddisarmtheassociateddirectionalcontrolvalves*"either:a)Electrically,orb)Hydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.C.TheprovisionsofSpecification3.0.4arenotapplicable.Atleasteachwithdrawncontrolrod.NotapplicabletocontrolrodsremovedperSpecification3.9.10.1or3.9.10.2."*Mayberearmedintermittently,underadministrativecontrol,topermittestingassociatedwithrestoringthecontrolrodtoOPERABLEstatus.NINEMILEPOINT-UNIT23/41"11NOV80is.;
REACTIVITYCONTROLSYSTEMSSURVEILLANCEREUIREMENTS4.1.3.6Eachaffectedcontrolrodshallbedemonstratedtobecoupledtoitsdrivemechanismbyobservinganyindicatedresponseofthenuclearinstrumen-tationwhilewithdrawingthecontrolrodtothefullywithdrawnpositionandthenverifyingthatthecontrolroddrivedoesnotgototheovertravelposition:a.PriortoreactorcriticalityaftercompletingCOREALTERATIONSthatcouldhaveaffectedthecontrolroddrivecouplingintegrity,b.Anytimethecontrolrodiswithdrawntothefulloutpositioninsubsequentoperation,andC.Followingmaintenanceonormodificationtothe'ontrolrodorcontrolroddrivesystemwhichcouldhaveaffectedthecontrolrod.drivecouplingintegrity.4aNINEMILEPOINT"UNIT23/41"12NOV8U1S85
REACTIVITYCONTROLSYSTEMSCONTROLROD-POSITIONINDICATIONLIMITINGCONDITIONFOROPERATIONPMkr'(PJ'8MP(3.1.3.7ThecontrolrodpositionindicationsystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1,2and5".ACTION:aOInOPERATIONALCONDITION1or2withoneormorecontrolrodpositionindicatorsinoperable,withinonehour:1.Determinethepositionofthecontrolroda)Byfulloutindicationifrodisfullywithdrawn,orb)'c)Byfullinindicationifrodisfullyinserted,orFortheaffectedinoperablecontrolrodposition,,verifyonenotch"out"andonenotch~in"controlrodindicatorsOPERABLE,andd)Verifyingnocontrolroddriftalarmatleastonceper12hours,or2.MovethecontrolrodtoapositionwithanOPERABLEpositionindicator,or3.WhenTHERMALPOWERis:a)WithinthelowpowersetpointoftheRSCS:1)Declarethecontrolrodinoperable,and2)Verifythepositionandbypassingofcontrolrodswithinoperablefullinand/orfulloutpositionindicatorsbyasecondlicensedoperatororothertechnicallyqualifiedmemberoftheunittechnicalstaff.b)GreaterthanthelowpowersetpointoftheRSCS,declarethecontrolrodinoperable,insertthecontrolrodanddisarmtheassociateddirectionalcontrolvalves""either:1)Electrically,orAtleasteachwithdrawncontrolrod.NotapplicabletocontrolrodsremovedperSpecification3.9.10.1or3.9.10.2.""Mayberearmedintermittently,underadministrativecontrol,topermittesingassociatedwithrestoringthecontrolrodtoOPERABLEstatus.NINEMILEPOINT-UNIT23/41"13ROYP01985
REACTIVITYCONTROLSYSTEMSCONTROLRODPOSITIONINDICATIONLIMITINGCONDITIONFOROPERATIONACTION:(Continued)2)Hydraulicallybyclosingthedrivewaterandexhaustwaterisolationvalves.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.b.InOPERATIONALCONDITION5"withawithdrawncontrolrodpositionindicatorinoperable,movethecontrolrodtoapositionwithanOPERABLEpositionindicatororinsertthecontrolrod.c.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.1.3.7ThecontrolrodpositionindicationsystemshallbedeterminedOPERABLEbyverifying:tieea.b.C.Atleastonceper24hoursthatthepositionofeachcontrolrodisindicated,ThattheindicatedcontrolrodpositionchangesduringthemovementofthecontrolroddrivewhenperformingSurveillanceRequirement4.1.3.1.2,andThatthecontrolrodpositionindicatorcorrespondstothecontrolrodpositionindicatedbythefulloutpositionindicatorwhenperformingSurveillanceRequirement4.1.3.6.b.Atleasteachwithdrawncontrolrod.NotapplicabletocontrolrodsremovedperSpecification3.9.10.1or3.9.10.2.NINEMILEPOINT-UNIT23/41"14NOV201995
REACTIVITYCONTROLSYSTEMSCONTROLRODDRIVEMOUSINGSUPPORTLIMITINGCONDITIONFOROPERATION3.1.3.8Thecontrolroddrivehousingsupportshallbeinplace.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:Withthecontrolroddrivehousingsupportnotinplace,beinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.1.3.8Thecontrolroddrivehousingsupportshallbeverifiedtobeinplacebyavisualinspectionpriortostartupanytimeithasbeendisassembledorwhenmaintenancehasbeenperformedinthecontrolroddrivehousingsupportarea.NINEMILEPOINT-UNIT23/41"15~DVS019>>
REACTIVITYCONTROLSYSTEMS3/4.1.4CONTROLRODPROGRAMCONTROLSRODWORTHMINIMIZERLIMITINGCONDITIONFOROPERATION3.1.4.1Therodworthminimizer(RWM)shallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2",whenTHERMALPOWERislessIEIRETIETIIERIEll,IIIIlRlsetpoint.ACTION:a.b.WiththeRWMinoperable,verifycontrolrodmovementandcompliancewiththeprescribedcontrolrodpatternbyasecondlicensedoperatororothertechnicallyqualifiedmemberoftheunittechnicalstaffwhoispresentatthe.reactorcontrolcorisole.Otherwise,.-.controlrodmovementispermittedonlybyactuatingthemanualscramorbyplacingthereactormodeswitchintheShutdownposition.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.1.4.1TheRWMshallbedemonstratedOPERABLE:aOb.C.d.InOPERATIONALCONDITION2within8hourspriortowithdrawalofcontrolrodsforthepurposeofmakingthereactorcritical,and,inOPERATIONALCONDITION1within8hourspriortoRWMautomaticinitiationwhenreducingTHERMALPOWER,byverifyingproperindi"cationoftheselectionerrorofatleastoneout-of-sequencecontrolrod.InOPERATIONALCONDITION2within8hourspriortowithdrawalofcontrolrodsforthepurposeofmakingthereactorcritical,byverifyingtherodblockfunctionbydemonstratinginabilitytowithdrawanout-of-sequencecontrolrod.InOPERATIONALCONDITION1withinonehourafterRWMautomaticinitiationwhenreducingTHERMALPOWER,byverifyingtherodblockfunctionbydemonstratinginabilitytowithdrawanout-of"sequencecontrolrod.BydemonstratingthatthecontrolrodpatternsandsequenceinputtotheRWMcomputerarecorrectlyloadedfollowinganyloadingoftheprogramintothecomputer.EntryintoOPERATIONALCONDITION2andwithdrawalofselectedcontrolrodsispermittedforthepurposeofdeterminingtheOPERABILITYoftheRWMpriortowithdrawalofcontrolrodsforthepurposeofbringingthereactortocriticality.NINEMILEPOINT-UNIT23/41-16HOVP.glS85
REACTIVITYCONTROLSYSTEMSRODSEOUENCECONTROLSYSTEMLIMITINGCONDITIONFOROPERATION3.1.4.2Therodsequencecontrolsystem(RSCS)shallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2",whenTHERMALPOWERislessthanorequalto20KRATEDTHERMALPOWER,theminimumallowablelowpowerset"point.ACTION:aOb.WiththeRSCSinoperable,controlrodmovementshallnotbepermitted,exceptbyascram.Withaninoperablecontrolrod(s),OPERABLEcontrolrodmovementmaycontinuebybypassingtheinoperablecontrolrod(s)intheRSCSpro-videdthat:1.Thepositionandbypassingofinoperablecontrolrodsisverifiedbya,secondlicensedoperatororothertechnicallyqualifiedmemberoftheunittechnicalstaff,and2.Therearenotmorethan3inoperablecontrolrodsinanyRSCSgroup.SURVEILLANCEREUIREMENTS4.1.4.2TheRSCSshallbedemonstratedOPERABLEby:a~b.Performanceofaself-test:1.Within8hourspriortoeachreactorstartup,and2.PriortomovementofacontrolrodafterrodinhibitmodeautomaticinitiationwhenreducingTHERMALPOWER.Attemptingtoselectandmoveaninhibitedcontrolrod:1.Afterwithdrawalofthefirstinsequencecontrolrodforeachreactorstartup,and2.WithinonehourafterrodinhibitmodeautomaticinitiationwhenreducingTHERMALPOWER.SeeSpecialestException3.10.2¹EntryintoOPERATIONALCONDITION2andwithdrawalofselectedcontrolrodsispermittedfor,thepurposeofdeterminingtheOPERABILITYoftheRSCSpriortowithdrawalofcontrolrodsforthepurposeofbringingthereactortocriticality.NINEMILEPOINT"UNIT23/41-17NQY201985
REACTIVITYCONTROLSYSTEMSRODBLOCKMONITORLIMITINGCONDITIONFOROPERATION3.1.4.3Bothrodblockmonitor(RBM)channelsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorRERRRTERTREMIPRR.ACTION:aob.WithoneRBMchannelinoperable:1.VerifythatthereactorisnotoperatingonaLIMITINGCONTROLRODPATTERN,and2.RestoretheinoperableRBMchanneltoOPERABLEstatuswithin24hours.Otherwise,placetheinoperable-rodblockmonitor.channelinthe.trippedconditionwithinthenexthour.WithbothRBMchannelsinoperable,placeatleastoneinoperablerodblockmonitorchannelinthetrippedconditionwithinonehour.SURVEILLANCEREUIREMENTS4.1.4.3EachoftheaboverequiredRBMchannelsshallbedemonstratedOPERABLEbyperformanceofa:a..CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONatthefrequencies.andfortheOPERATIONALCONDITIONSspecifiedinTable4.3.6-1.b.CHANNELFUNCTIONALTESTpriortocontrolrodwithdrawalwhenthereactorisoperatingonaLIMITINGCONTROLRODPATTERN.NINEMILEPOINT-UNIT23/41-18NOY20j885
REACTIVITYCONTROLSYSTEMS3/4.1.5STANDBYLIUIDCONTROLSYSTEMLIMITINGCONDITIONFOROPERATIONFJgIIjgjP/'P)<j)04I(3.1.5ThestandbyliquidcontrolsystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1,2,and5"ACTION:aO.b.InOPERATIONALCONDITION1or2:1.Withonepumpand/oroneexplosivevalveinoperable,restoretheinoperablepumpand/orexplosivevalvetoOPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hours.2..Withthestandbyliquidcontrolsystemotherwiseinoperable,restorethesystemtoOPERABLEstatuswithin8hoursorbeinatleastHOTSHUTDOWNwith1nthenext12hours.InOPERATIONALCONDITION5":I.Withonepumpand/oroneexplosivevalveinoperable,restoretheinoperablepumpand/orexplosivevalvetoOPERABLEstatuswithin30daysorinsertallinsertablecontrolrodswithinthenexthour.2.Withthestandbyliquidcontrolsystemotherwiseinoperable,insertallinsertablecontrolrodswithinonehour.SURVEILLANCEREUIREMENTS4.1.5ThestandbyliquidcontrolsystemshallbedemonstratedOPERABLE:aoAtleastonceper24hoursbyverifyingthat;1.Thetemperatureofthesodiumpentaboratesolutioninthestoragetankis>704F.2.TheavailablevolumeofsodiumpentaboratesolutioniswithinthelimitsofFigure3.1.5-1.3.Thetemperatureofthepumpsuctionpipingis>704F.Specification3.9.10.1or3.9.10.2.NINEMILEPOINT-UNIT23/4'-19aov301995
REACTIVITYCONTROLSYSTEMSSURVEILLANCEREUIREMENTSContinuedPM3F5p"-pp(goyb.Atleastonceper31daysby:l.Verifyingthecontinuityoftheexplosivecharge.2.3.Determiningthattheavailableweightofsodiumpentaborateisgreaterthanorequalto5493lbsandtheconcentrationofboroninsolutioniswithinthelimitsofFigure3.1.5-1bychemicalanalysis."Verifyingthateachvalve,manual,poweroperatedorautomatic,intheflowpaththatisnotlocked,sealed,orotherwisesecuredinposition,isin'itscorrectposition.C.d.Demonstratingthat,whentestedpursuanttoSpecification4.0.5theminimumflowrequirementof41.2gpmperpumpatapressureofgreaterthanorequalto1220psigismet.Atleastonceper18monthsduringshutdown,by:1..Initiatingoneofthestandbyliquidcontrolsystemloops,includinganexplosivevalve,andverifyingthataflowpathfromthepumpstothereactorpressurevesselisavailablebypumpingdemineralizedwaterintothereactorvessel.Thereplace-mentchargefortheexplosivevalveshallbefromthesamemanufacturedbatchastheonefiredorfromanotherbatchwhichhasbeencertifiedbyhavingoneofthatbatchsuccessfullyfired.Bothinjectionloopsshallbetestedin36months.2.,Demonstratingthatthepumpreliefva1vesetpointislessthanorequalto1387"""psigandverifyingthatthereliefvalvedoesnotactuateduringrecirculationtothetesttank.3.""Demonstratingthatallheattracedpipingbetweenthestoragetankandthereactorvesselisunblockedbypumpingfromthestoragetanktothetesttankandthendrainingandflushingthepipingwithdemineralizedwater.4.DemonstratingthatthestoragetankheatersareOPERABLEbyveri-fyingtheexpectedtemperatureriseofthesodiumpentaboratesolutioninthestoragetankaftertheheatersareenergized.hsstestshallalsobeperformedanytimewaterorboronisaddedtothesolutionorwhenthesolutiontemperaturedropsbelow70F.*"Thistestshallalsobeperformedwheneverbothheattracingcircuitshavebeenfoundtobeinoperableandmaybeperformedbyanyseriesofsequential,overlappingortotalflowpathstepssuchthattheentireflowpathisincluded."""Benchtestedsetpointvalue.NINEMILEPOINT-UNIT23/41"20HOV2u]S8G
MmMImM5MWCO514.013;8REGIONOFAPPROVEOCONCENTRATION-VOLUMELOMLEVELALMHHIGHLEVELALA+IOVERFLOMVOLUME5L7W5CICl13.513.413.012.5REGIONOFRECOHHENDEOCONCENTRATIONVOLUHE44744625HINIHUHCONCENTRATIONLINES4863EXPANSIONVOLUME5040~ll~i".D~oagq>4400450046004700:4800y-NETVOLUME(GAL)490050005190IFigure3.1.5-1Sodium-PentaborateTankVolumevsConcentrationRequirements
3/4.2POWERDISTRIBUTIONLIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATEP~~Ã~a~FIB'i~F'/LIMITINGCONDITIONFOROPERATION3.2.1AllAVERAGEPLANARLINEARHEATGENERATIONRATES(APLHGRs)foreachtypeoffuelasafunctionofAVERAGEPLANAREXPOSUREshallnotexceedthelimitsshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthan5XfIMTEDTIIER"LP"ER.ACTION:WithanAPLHGRexceedingthelimitsofFigure3.2.1-1,3.2.1-2,or3.2.1-3,initiatecorrectiveactionwithin15minutesandrestoreAPLHGRtowithintherequiredlimitswithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthe.next4hours.SURVEILLANCEREUIREMENTS4.2.1AllAPLHGRsshallbeverifiedtobeequaltoorlessthanthelimitsdeterminedfromFigures3.2.1-1,3.2.1-2,and3.2.1-3:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLRODPATTERNforAPLHGR.d.TheprovisionsofSpecification4.0.4arenotapplicable.NINEMILEPOINT-UNIT23/42-1NOV201985
12.52.~12.0(o.10,12.215ol2.2)2012.2)250,10.~10.5,10.1)~10.09.5051015.20253035'AVEfNGEPLANAREXPOSURE,GMd/stFIGURE3.2.1-1MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(HAPLHGR)VSAVERAGEPLANAREXPOSURE.FUELTYPEPBCIB21940
13o(l,m12(0I-CYCCLCI.02510WCDCYW350.5152025'0AVERAGEPLANAREXPOSURE,GMd/stFIGURE3.2.1-2MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(MAPLHGR)VSAVERAGEPLANAREXPOSURE;FUELTYPEPSCIB17640
(0.2,11.5)(15,11.5)~OIAllIIICICITNKINLYNCN0CDq(.1112011.1CD25CLWCCJCOw940,8.5).505101520253035AVERAGEPLANAREXPOSURE,GMd/stFIGURE3.2.1-3MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(MAPLHGR)VSAVERAGEPLANAREXPOSURE.FUELTYPEPSCIB071
POWERDISTRIBUTIONLIMITS3/4.2.2APRMSETPOINTSLIMITINGCONDITIONFOROPERATION3.2.2TheAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpoint(S)andflowbiasedneutronflux-upscalecontrolrodblocktripsetpoint(SRB)shallbeestablishedaccordingtothefollowingrelationships:TRIPSETPOINTALLOWABLEVALUES<(0.66W+53%)TS<(0.66W+54K)TSRB<(0.66W+42K)TSRB<(0.66W+45K)Twhere:SandSRBareinpercentofRATEDTHERMALPOWER,W=Looprecirculationflowasapercentageofthelooprecirculationflowwhichproducesaratedcoreflowof108.5mill,ionlbs/hr.T=TheratioFRACTIONOFRATEDTHERMALPOWERdividedbytheCOREMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY.Tisappliedonlyifless.thanorequalto1.0.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanor~REIIIATEETNERNALPNNEII.ACTION:WiththeAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpointand/ortheflowbiasedneutronflux-upscalecontrolrodblocktripsetpointlessconservativethanthevalueshownintheAllowableValuecolumnforSorSRB,asabovedetermined,initiatecorrectiveactionwithin15minutesandadjustSand/orSRBtobeconsistentwiththeTripSetpointvaluewithin6hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWER.withinthenext4hours.SURVEILLANCEREUIREMENTS4.2.2TheFRTPandtheCMFLPDshallbedetermined,thevalueofTcalculated;.andthemostrecentactualAPRMflowbiasedsimulatedthermalpower-upscalescramandflowbiasedneutronflux-upscalecontrolrodblocktripsetpointsverifiedtobewithintheabovelimitsoradjusted,asrequired:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithCMFLPDgreaterthanorequaltoFRTP.d.TheprovisionsofSpecification4.0.4arenotapplicable.WithCMFLPOgreaterthantheFRTPAAfIRAPRNPI,RAPRNIyRadjustedsuchthatAPRMreadingsaregreaterthanorequaltolOOXtimesCMFLPDprovidedthattheadjustedAPRMreadingdoesnotexceed100KofRATEDTHERMALPOWERandanoticeofadjustmentispostedonthereactorcontrolpanel.NINEMILEPOINT-UNIT23/42-5HOV20]9B5
3/4.2.3MINIMUMCRITICALPOWERRATIOLIMITINGCONDITIONFOROPERATIONPltooF5KFZ8KP73.2.3TheMINIMUMCRITICALPOWERRATIO(MCPR),asafunctionofcoreflow,shallbeequaltoorgreaterthan1.24timestheKflimitsshowninFigure3.2.3-1.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorREEIRTERTIIERRALPRER.ACTION:WithMCPRlessthantheMCPRlimittimesKfdeterminedfromFigure3.2.3-1,initiatecorrectiveactionwithin15minutesandrestoreMCPRtowithin.therequiredlimitwithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.2;3MCPRshallbedeterminedtobeequaltoorgreaterthantheMCPRlimitdeterminedfromFigure3.2.3-1:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15'fRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLRODPATTERNforMCPR.d.TheprovisionsofSpecification4.0.4arenotapplicable.NINEMILEPOINT"UNIT23/42"6NOV201SB5
1.00.9203040'060COREFLOW,PercentFIGURE3.2.3-1FfASAFUNCTIONOFPERCENTCOREFLOW708090100
POWERDISTRIBUTIONLIMITS3/4.2.4LINEARHEATGENERATIONRATEPM~F8i(PPP~IOp(LIMITINGCONDITIONFOROPERATION3.2.4TheLINEARHEATGENERATIONRATE(LHGR)shallnotexceed13.4kw/ft.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMAL,POWERisgreaterthanor~qlIIIIRTEOTRERIOLPOIIER.ACTION:WiththeLHGRofanyfuelrodexceedingthelimit,initiatecorrectiveactionwithin15minutesandrestoretheLHGRtowithinthelimitwithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.2.4LHGR'sshallbedeterminedtobeequaltoorlessthanthelimit:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofaleast15KofRATEDTHERMALPOWER,andC.d.Initiallyandatleastonceper12hourswhenthereactorisoperatingonaLIMITINGCONTROLRODPATTERNforLHGR.TheprovisionsofSpecification4.0.4arenotapplicable.NINEMILEPOINT-UNIT23/42-8aov2oLoss
3/4.3INSTRUMENTATION3/4.3.1REACTORPROTECTIONSYSTEMINSTRUMENTATION~~LIMITINGCONDITIONFOROPERATION3.3.1Asaminimum,thereactorprotectionsysteminstrumentationchannelsshowninTable3.3.1-1shallbeOPERABLEwiththeREACTORPROTECTIONSYSTEMRESPONSETIMEasshowninTable3.3.1-2.APPLICABILITY:AsshowninTable3.3.1-1.ACTION:aOb.WiththepumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforonetripsystem,placetheinoperablechannel(s)and/orthattripsysteminthetrippedcondition".withinonehour.TheprovisionsofSpecification3.0.4arenotapplicable.WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforbothtripsystems,placeatleastonetripsystem""inthetrippedconditionwithinonehourandtaketheACTIONrequiredbyTable3..3.1-1.SURVEILLANCEREUIREMENTS4.3.1.1EachreactorprotectionsysteminstrumentationchannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsfortheOPERATIONALCONDITIONSandatthefrequenciesshowninTable4.3.1.1-1.4.3.1.2LOGICSYSTEMFUNCTIONALTESTSandsimulatedautomaticoperationofallchannelsshallbeperformedatleastonceper18months.4.3.1.3TheREACTORPROTECTIONSYSTEMRESPONSETIMEofeachreactortripfunctionalunitshowninTable3.3.1-2shallbedemonstratedtobewithinits.limitatleastonceper18months.Eachtestshallincludeatleastonechannelpertripsystemsuchthatallchannelsaretestedatleastonceevery-Ntimes18monthswhereNisthetotalnumberofredundantchannelsinaspecificreactortripsystem.AninoperablechannelneednotbeplacedinthetrippedconditionwherethiswouldcausetheTripFunctiontooccur.Inthesecases,theinoperablechannelshallberestoredtoOPERABLEstatuswithin2hoursortheACTIONrequiredbyTable3.3.1-1forthatTripFunctionshallbetaken.""Thetripsystemneednotbep'lacedinthetrippedconditionifthiswouldcausetheTripFunctiontooccur.WhenatripsystemcanbeplacedinthetrippedconditionwithoutcausingtheTripFunctiontooccur,placethetripsystemwiththemostinoperablechannelsinthetrippedcondition>ifbothsystemshavethesamenumberofinoperablechannels,p'laceeithertripsysteminthetrippedcondition.NINEMILEPOINT-UNIT23/43-1SOV301S95
MmIITABLE3.3.1-1REACTORPROTECTIONSYSTEMINSTRUMENTATION:C)MICMFUNCTIONALUNITl.IntermediateRangeMonitors:a.NeutronFlux-HighAPPLICABLEOPERATIONALCONDITIONS2(b)5'INIMUMOPERABLECHANNELSPERTRIPSYSTEMaACTIONb.Inoperative2.AveragePowerRangeMonitora.NeutronFlux-Upscale,Setdown23,452'(b)5b.C.d.FlowBiasedSimulatedThermalPower-UpscaleFixedNeutronFlux-UpscaleInoperative111,23,45C)C.CDCOCgl3.ReactorVesselSteamDomePressure-High4.ReactorVesselWaterLevel-Low,Level3'.HainSteamLineIsolationValve-Closure2(e)121(d)
TABLE3.3.1-1(Continued)REACTORPROTECTIONSYSTEMINSTRUMENTATIONFUNCTIONALUNIT6.MainSteamLineRadiation-High7.DrywellPressure-High8.ScramDischargeVolumeWaterLevel-Higha.TransmitterTripUnitsb.FloatSwitches9.TurbineStopValve-Closure10.TurbineControlValveFastClosure,ValveTripSystemOilPressure-Lowll.ReactorModeSwitchShutdownPosition12.ManualScramAPPLICABLEOPERATIONALCONDITIONS(h)51,2(h)51(i)1,23,45123,45MINIMUMOPERABLECHANNELSPERTRIPSYSTEMa22(g)224(i)2(i)222ACTION173 3 TABLE3.3.1-1(Continued)N3."F5)<pp(r~p~'EACTORPROTECTIONSYSTEMINSTRUMENTATIONACTIONACTION1ACTION2ACTION3ACTION4ACTION5ACTION6ACTION7ACTION8ACTION9BeinatleastHOTSHUTDOWwithin12hours.VerifyallinsertablecontrolrodstobeinsertedihthecoreandlockthereactormodeswitchintheShutdownpositionwithinonehour.SuspendalloperationsinvolvingCOREALTERATIONSandinsertallinsertablecontrolrodswithinonehour.BeinatleastSTARTUPwithin6hours.BeinSTARTUPwiththemainsteam'lineisolationvalvesclosedwithin6hoursorinatleastHOTSHUTDOWwithin12hours.r-lÃQInitiateareductioninTHERMALPOWERwithin~5minutesandreduceturbinefirststagepressureto<~psig,equivalenttoTHERMALPOWERlessthan30KofRATEDTHERMALPOWER,within2hours.Verifyallinsertablecontrolrodstobeinsertedwithinonehour.LockthereactormodeswitchintheShutdownpositionwithinonehour.SuspendalloperationsinvolvingCOREALTERATIONS,andinsertallinsertablecontrolrodsandlockthereactormodeswitchintheSHUTDOWpositionwithinonehour.NINEMILEPOINT-UNIT23/43"44IOV2uj985
TABLE3.3.1-1(Continued}REACTORPROTECTIONSYSTEMINSTRUMENTATIONTABLENOTATIONS(a)Achannelmaybeplacedinaninoperab'lestatusforupto2hoursforrequiredsurveillancewithoutplacingthetripsysteminthetrippedconditionprovidedatleastoneOPERABLE.channelinthesametripsystemismonitoringthatparameter.(b)IIII(c)AnAPRMchannelisinoperableiftherearelessthan2LPRMinputsperlevelorlessthan14LPRMinputstoanAPRMchannel.(d)ThisfunctionshallbeautomaticallybypassedwhenthereactormodeswitchisnotintheRunposition.(e)ThisfunctionisnotrequiredtobeOPERABLEwhenthereactorpressurevesselheadisremovedperSpecification3.10.1.(f)ThisfunctionisnotrequiredtobeOPERABLEwhenPRIMARYCONTAINMENTINTEGRITYisnotrequired.(g)Alsoactuatesthestandbygastreatment.system.(h)Withanycontrolrodwithdrawn.NotapplicabletocontrolrodsremovedperSpecification3.9.10.1or3.9.10.2.(i)Thisfunctionshallbeautomaticallybypassedwhenturbinefirststagepressureis<"psig,equivalenttoTHERMALPOWERlessthan30KofRATEOTHERMALPOMER.(j)AlsoactuatestheEOC-PTsstem.J469EP.PQhXes-'NotrequiredforcontrolrodsremovedperSpecification3.9.10.1or3.9.10.2.**gNINEMILEPOINT-UNIT23/43-5
S,1TABLE3.3.1-2MmREACTORPROTECTIONSYSTEHRESPONSETIHESImC)ICMFUNCTIONALUNITl.IntermediateRangeHonitors:a.NeutronFlux-Highb.Inoperative2.AveragePowerRangeHonitor":a.NeutronFlux-Upscale,Setdownb.FlowBiasedSimulatedThermalPower-Upscalec.FixedNeutronFlux-Upscaled.Inoperative3.ReactorVesselSteamDomePressure-High4.ReactorVesselWaterLevel-Low,Level35.HainSteamLineIsolationValve-Closure6.HainSteamLineRadiation-High7.DrywellPressure-High8.ScramDischargeVolumeWaterLevel-High9.TurbineStopValve-Closure10.TurbineControlValveFastClosure,ValveTripSystemOilPressure-Lowll.ReactorHodeSwitchShutdownPosition12.HanualScramRESPONSETIMESecondsNA009k)k<0.09NA<0.55<1.05<0.06HANANA<0.06<0.08'ANANeutrondetectorsareexemptfromresponsetimetesting.Responsetimeshallbemeasuredfromthedetectoroutputorfromtheinputofthefirstelectroniccomponentinthechannel.""Notincludingsimulatedthermalpowertimeconstant,6t0.6seconds.Nleasuredfromstartofturbinecontrolvalvefastclosure.
Mmllf.I;IITABLE4.3.1.1-1REACTORPROTECTIONSYSTEMINSTRUMENTATIONSURVEILLANCEREUIREMENTS;ClMIMFUNCTIONALUNIT1.IntermediateRangeMonitors:a.NeutronFlux-HighCHANNELCHECKS/U,s,(b)SCHANNELFUNCTIONALTESTs/u(')wR(')RWR23,4,5OPERATIONALCHANNELCONDITIONSFORWHICHCALIBRATIONSURVEILLANCEREUIREDb.InoperativeNA2.AveragePowerRangeMonitora.NeutronFlux-s/u,s,(b)Upscale,SetdownSs/u('),wWSASAWNA2,3,4,523,4,5b.FlowBiasedSimulatedThermalPower-UpscaleS,Dc.FixedNeutronFlux-Upscaled.Inoperative3.ReactorVesselSteamDomePressure-High4.ReactorVesselWaterLevel-Low,Level35.MainSteamLineIsolationValve-Closure6.MainSteamLineRadiation-High7.DrywellPressure-Highs/u('),ws/u('),wW(d),SANAR(k)RR(k)SAR(>>1,2,3,4,51,21,22(i)2(m)
mN"./;IAIITABLE4.3.1..1-1(Continued)REACTORPROTECTIONSYSTEMINSTRUMENTATIONSURVEILLANCEREUIREMENTS,C)MFUNCTIONALUNITCHANNELCHECKCHANNELFUNCTIONALTESTCHANNELCALIBRATIONOPERATIONALCONDITIONSFORWHICHSURVEILLANCEREVIREO8.ScramDischargeVolumeWaterLevel-Higha.TransmitterSb.FloatSwitchesNAR(k)R1y2y5(j)(j)1,2,59.TurbineStopValve-ClosureNAI0010.12.TurbineControlValveFastClosure,ValveTripSystemOilPressure-LowReactorModeSwitchShutdownPositionManualScramNARNAMNA1,2,3,4,51,2,3,4,5a(b)(c)(d)(e)(f)(g)bIddICIIANNNLCIILCNNATIIIN.TheIRMandSRMchannelsshallbedeterminedtooverlapforatleast1/2decadeduringeachstartupafterenteringOPERATIONALCONDITION2andtheIRMandAPRMchannelsshallbedeterminedtooverlapforatleast1/2decadeduringeachcontrolledshutdown,ifnotperformedwithintheprevious7days.Within24hourspriortostartup,ifnotperformedwithintheprevious7days.ThiscalibrationshallconsistoftheadjustmentoftheAPRMchanneltoconformtothepowervaluescalculatedbyaheatbalanceduringOPERATIONALCONDITION1whenTHERMALPOWER>25KofRATEDTHERMALPOWER.AdjusttheAPRMchanneliftheabsolutedifferenceisgreaterthan2XofRATEDTHERMAPOWER.AnyAPRMchannelgainadjustmentmadeincompliancewithSpecification3.2.2shallnotbeincludedindeterminingtheabsolutedifference..ThiscalibrationshallconsistoftheadjustmentoftheAPRMflowbiasedchanneltoconformtoacalibratedflowsignal.TheLPRMsshallbecalibratedatleastonceper1000effectivefullpowerhours(EFPH)usingtheTIPsystem.Verifymeasureddriveflowtobelessthanorequaltoestablisheddriveflowattheexistingcontrolvalveposition.."CNeSr~g
mTABLE4.3.1.1-1(Continued)REACTORPROTECTIONSYSTEHINSTRUHENTATIONSURVEILLANCEREUIREHENTS.C)I(h)Thiscalibrationshallconsistofverifyingthe6k0.6secondsimulatedthermalpowertimeconstant.(i)ThisfunctionisnotrequiredtobeOPERABLEwhenthereactorpressurevesselheadisremovedperSpecification3.10.1.(j)Mithanycontrolrodwithdrawn.Notapplicabletocontro'IrodsremovedperSpecification3.9.10.1or3.9.10.2.(k)Calibratetripunitatleastonceper31days.(1)PerformaCHANNELFUNCTIONALTESTwiththemodeswitchinSTARTUP.(m)ThisfunctionisnotrequiredtobeOPERABLEwhenPRIHARYCONTAINHENTINTEGRITYisnotrequiredtobeOPERABLEperSpecialTestException3.10.1.C>IPj
I'i%IF83PP'97HF(INSTRUMENTATION3/4.3.2ISOLATIONACTUATIONINSTRUMENTATIONLIMITINGCONDITiONFOROPERATION3.3.2TheisolationactuationinstrumentationchannelsshowninTable3.3.2-1shallbeOPERABLEwiththeirtripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.2-2andwithISOLATIONSYSTEMRESPONSETIMEasshowninTable3.3.2-3.APPLICABILITY:AsshowninTable3.3.2-1.ACTION:'a0b.C.WithanisolationactuationinstrumentationchanneltripsetpointlessconservativethanthevalueshownintheAllowableValuescolumnofTable3.3.2-2,declarethechannelinoperableuntilthechannelisrestoredtoOPERABLEstatuswithitstripsetpointadjusted.consistentwiththeTripSetpointvalue.WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannels'erTripSystemrequirementforonetripsystem,placetheinoperablechannel(s)an)/orthattripsysteminthetrippedcondition"withinonehour.TheprovisionsofSpecification3.0.4arenotapplicable.WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforbothtripsystems,placeatleastonetripsystem""inthetrippedconditionwithinonehourandtaketheACTIONrequiredbyTable3.3.2-1.AninoperablechannelneednotbeplacedinthetrippedconditionwherethiswouldcausetheTripFunctiontooccur.Inthesecases,theinoperablechannelshallberestoredtoOPERABLEstatuswithin2hoursortheACTIONrequiredbyTable3.3.2-1forthatTripFunctionshallbetaken.""ThetripsystemneednotbeplacedinthetrippedconditionifthiswouldcausetheTripFunctiontooccur.WhenatripsystemcanbeplacedinthetrippedconditionwithoutcausingtheTripFunctiontooccur,placethetripsystemwiththemostinoperab1echanne1sinthetrippedcondition,ifboth~systemshavethesamenumberofinoperablechannels,placewithertripsysteminthetrippedcondition.NINEMILEPOINT-UNIT23/43"10NOV20l985
INSTRUMENTATIONPMQF5$pf'p)(spygoo.mE.CHecA~.4.3.2.1EachisolationactuationinstrumentatiochannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsfortheOPERATIONALCONDITIONSandatthefrequenciesshowninTable4.3.2.1-1.4.3.2.2LOGICSYSTEMFUNCTIONALTESTSandsimulatedautomaticoperationof"allchannelsshallbeperformedatleastonceper18months.4.3.2.3TheISOLATIONSYSTEMRESPONSETIMEofeachisolationtripfunctionshowninTable3.3.2-3shallbedemonstratedtobewithinitslimitatleastonceper18months.EachtestshallincludeatleastonechannelpertripsystemsuchthatallchannelsaretestedatleastonceeveryNtimes18months,whereNisthetotalnumberofredundantchannelsinaspecificisolationtripsystem.NINEMILEPOINT-UNIT23/43-11NOVP.01S85
TABLE3.3.2-1')el~)I:I-:MmMIl1TRIPFUNCTIONISOLATIONACTUATIONINSTRUMENTATIONVALVEGROUPSMINIMUMOPERATEDBY~OPERABLECHANNELSSIGNALiPERTRIPSYSTEMaAPPLICABLEOPERATIONALCONDITIONACTION~DCllCJlC)MIMIM004l)1.PRIMARYCONTAINMENTISOLATIONa.ReactorVesselMaterLevel1.Low,Low,Low,Level12.Low,Low,Level2(b)(e)3.Low,Level3b.DrywellPressure-High(b)(e)c.HainSteamLine1.Radiation-High(c)2.Pressure-Low3.Flow-Highd.HainSteamLineTunnel1.Temperature-High2.temperature-High3.('e~qe)ance-)ghtissue.CondenserVacuumLowf.RHREquipmentArea1.TemperatureHigh(HN's/AKB~-@Terng.ReactorVesselPressureHighC.QAO-c~4Lhlgdtwkly~4c)k.-N))ow)))12,3,6,7,8,94,54,3,8,91,211LcEocl.osutc'umpRooms)4,5,10eve222/Line1,231)2)1,2,31,2,31,2,311,2,31,2,33)II1231,2,320202020212321212121"nCMenVg
MjjlImTRIPFUNCTIONTABLE3.3.2-1(Cont,)ISOLATIONACTUATIONINSTRUMENTATIONVALVEGROUPSMINIHUHOPERATEDBYOPERABLECHANNELSSIGNALiPERTRIPSYSTEMaAPPLICABLEOPERATIONALCONDITIONACTIONMM1.PRIMARYCONTAINMENTISOLATIONSIGNALS(Cont.)i.SGTSExhaust-HighRadiationj.RMCUEquipment'.BFlow-High2.hFlowHigh,Timer3.StandbyLiquidControl,SLCS,Initiationk.RMCUEquipmentArea1.Temperature-High(HX's/AEBPumpRooms)4-hTetttp1.ManualIsolationPushbutton[NSSS]6,76,76712,4,53,6,7891,2,31j2~31231,2,31,2,3292222222224262625,27292.RCICISOLATIONSIGNALSClCDb.C.d.1010,11101j2j31j2j31,2,3RCICSteamLineFlow-High,Timer1RCICSteamSupplyPressure-Low(g)2RCICSteamLineFlow,High1RCICTurbineExhaustDiaphragmPressure-High(g)1021,2,3*c.lac,'bUg.jIjeches~+g~j,H;jj,+S.C7IO~gLAt.I~R&hrC4dp9thQ.tCAh/,Qy4p5$pd3-/Lac~~lr>)3:C7C~CPW$
MmMImCIMMTRIPFUNCTION2.RCICISOLATIONSIGNALS(Cont.)e.RCICEquipmentArea1.Temperature"Highef.RCICSteamLineTunnel1.Temperature-HighTABLE3.3.2-1(Cont.)ISOLATIONACTUATIONINSTRUMENTATIONVALVEGROUPSMINIMUMOPERATEDBYOPERABLECHANNELSSIGNALiPERTRIPSYSTEMai1010:APPLICABLEOPERATIONALCONDITION1,2,31,2,3ACTION2222GOGJIg.ManualIsolationPushButton[RCIC)(h)h.DrywellPressure"High***i.RHR/RCICSteamFlow-High3.SECONDARYCONTAINMENTISOLATIONSIGNALSa.ReactorBuildingAbovetheRefuelFloorExhaustRadiationHighb.ReactorBuildingBelowtheRefuelFloorExhaustRadiationHigh1011(d)I10(b)(e)(b)(e)1/Division1only1,2,31,2,31,2,31<2>3<5AA1,2,3,5AA'622222727IPlQ.g~iI0
TABLE3.3.2-1(Continued)P~"~~0KJ~Pi/g7/ACTION20ACTION21ACTION22IACTION23ACTION24ACTION25-'ACTION26"'CTION27ACTION28ACTION29ISOLATIONACTUATIONINSTRUMENTATIONACTIONBeinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithinthenext24hours.BeinatleastSTARTUPwiththeassociatedisolationvalvesclosedwithin6hoursorbeinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithinthenext24hours.Closetheaffectedsystemisolationvalveswithinonehouranddeclaretheaffectedsysteminoperable.BeinatleastSTARTUPwithin6hours.RestorethemanualisolationfunctiontoOPERABLEstatuswithin8hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Restorethemanualisolationfunction.toOPERABLEstatuswithin48hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.RestorethemanualisolationfunctiontoOPERABLEstatuswithin8hoursorclosetheaffectedsystemisolationvalveswithinthenexthouranddeclaretheaffectedsysteminoperable.EstablishREACTORBUILDINGINTEGRITYwiththestandbygastreatmentsystemoperatingwithinonehour.Locktheaffectedsystemisolationvalvesclosedwithinonehouranddeclaretheaffectedsysteminoperable.WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelrequirement,closethePrimaryContain-mentpurgevalveswithinonehourorinitiatethepre-plannedalternatemethodofmonitoring.Withthechannelathighsetpoint,clearpersonnelfromvicinityofallpurgelinesandvalves,purgingmaycontinue,andobservemainstackeffluentmonitoralarmstatustoensurethatoffsitedosecriteriaarenotexceeded.NOTESWhenanyturbinestopva'Iveisgreaterthan90Kopenand/orwhenthekeylocked.CondenserLowVacuumBypassswitchisopen.WhenhandlingirradiatedfuelintheReactorBuildingandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.SignaIfromLPCS/RHRinitiationcircuitry.(a)Achannelmaybe.placedinaninoperablestatusforupto2hoursforrequiredsurveillancewithoutplacingthetripsysteminthetrippedcon-ditionprovidedatleastoneotherOPERABLEchannelinthesametripsystemismonitoringthatparameter.(b)Alsoactuatesthestandbygastreatmentsystem.(c)Alsotripsandisolatestheairremovalpumps..(d)OnlyusedinconjunctionwithlowRCICsteamsupplypressureandhighdrywellpressuretoisolate2ICS"MOV148and2ICS"MOV164.O~e+~ip~+Lvc~tNINEMILEPOINT"UNIT23/43-15NOV801985
'ABLE3.3.2-1(Continued)ISOLATIONACTUATIONINSTRUMENTATIONPIQQF5]gjpy[gp((e)AlsoactuatesReactorBuildingventilationisolationdampersperTable3.6.5.2-1.(f)InitiationofSLCSPump2SLS"P1Bcloses2WCS"MOV102andmanualinitiationofSLCSpump2SLS"P1Acloses2WCS"MOV112.(g)Forthissignalonetripsystemhas2channelswhichclosevalves2ICS"MOV128and2ICS"MOV170,whiletheothertripsystemhas2channelswhichclose2ICS"MOV121.(h)Manualinitiationonlyisolates2ICS"MOV121andonlyfollowingmanualorautomaticinitiationoftheRCICsystem.(i)RefertoTable3.6.3-1forapplicablevalvesineachvalvegroup.RefertoTable3.3;2"4forvalvegroupsandassociatedisolatedsignalsandtoTable3.3.2-5forkeytoisolationsignals.DuringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.parable~~~~NINEMILEPOINT-UNIT23/43"16HOV3P1@g
TRIPFUNCTIONTABLE3.3.2-2ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTSTRIPSETPOINTALLOWABLEVALUE1.PRIMARYCONTAINMENTISOLATIONSIGNALSa.ReactorVesselWaterLevel"1.Low,Low,Low,Level12.Low,Low,Level23.Low,Level3b.DrywellPressure-Highc.MainSteamLine1.Radiation-High2.Pressure-Low3.Flow-Highd.MainSteamLineTunnel1.Temperature-High2.temperature-High3.Pcmft~ARute'-9spQQSL~pgnEoc&sat+e.CondenserVacuumLowf.RHREquipmentArea1.TemperatureHigh(HX's/A8BPumpRooms)g.ReactorVesselPressureHig4C.&the-C~-eupea~,Wt~ceiIfi.SGTSExhaust-HighRadiation>17.8inches>108.8inches>159.3inches<1.68psig<'3XFullPowerBackground>~psig><+<103psid<175'FV<50F<140'FV>8.5inHgvacuum<135'F40<128psig<1.6X10-epCi/cc>108inches>101.8inches>157.8inches<1.88psig<3.6XFullPowerBackground8psig7~S'109.5psid<178F<53F<143'F~>7.6inHgvacuum<138j<148psig<2.0X10-~pCi/cc
TRIPFUNCTIONTABLE3.3.2-2ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTSTRIPSETPOINTALLOWABLEVALUEClMCM1.PRIMARYCONTAINMENTISOLATIONSIGNALSj.RWCUEquipment1.b,Flow-High2.hFlowHighTimer3.StandbyLiquidControl,SLCS,Initiationk.RWCUEquipmentArea1.Temperature-High(HX's/A8BPumpRooms)<150.5gpm<45secN/A<135'Ff<165.5gpm<47secN/A138F42.1.ManualIsolationPushbuttonI:NSSS]RCICISOLATIONSIGNALSa.RCICSteamLineFlowHighTimerb.RCICSteamSupplyPressure-Lowc.RCICSteamLineFlowHighd.RCICTurbineExhaustOiaphragmPressure-Highe.RCICEquipmentArea1.Temperature-HighN/A>3sec,<13sec75>~ps'184.5in.H20$<10psig13sec'70>~ps+<193.0in.H20t<20psig~8'9c'hAa~EUy.9,Pg~Qhg~4C'~l,.P~g~g3$FW4*c+~~+/~~~+>+<gX~/35IBF()py+fc
TRIPFUNCTION2.RCICISOLATIONSIGNALSf.RCICSteamLineTunnel1.Temperature-HigheI-TABLE3.3.2-2(Continued)ISOLATIONACTUATIONINSTRUHENTATIONSETPOINTSTRIPSETPOINTlM'PYALLOWABLEVALUE~IS@-'PWg.HanualIsolationPushBottomfRCIC7h.DrywellPressure-High.i.RHR/RCICSteamFlow-High3.SECONDARYCONTAINHENTISOLATIONSIGNALSa.ReactorBuildingAbovetheRefuelFloorExhaustRadiationHighb.ReactorBuildingBelowtheRefuelFloorExhaustRadiationHighMttNESNR~BR~PRAYN/A<1.68psig<96inHz0<1.7x10-3pCi/cc<1.7x10-3pCi/cc<1.88psig<104e5inH20<2.1x10-3pCi/cc<2.1x10-3pCi/ccBQlwsBPl'eaaav~Tgll~geaet~aee~vel~ev~e~eval-2~psl+-NB<an-.~~88-ps~>101.'8ie.SeeBasesFigureB343-1tPreliminarysetpoint-actualsetpointtobedeterminedduringstartuptestprogram.f~C.>g~erCW
TABLE3.3.2"3Pii0Pjrg!II;j!"'"i!JfpQvTRIPFUNCTIONISOLATIONSYSTEMINSTRUMENTATIONRESPONSETIMERESPONSETIMESeconds81.PRIMARYCONTAINMENTISOLATIONaOb.C.d.e.ReactorVesselMaterLevelI)Low,Low,Low,Level12)Low,Low,Level23)Low,Level3OrywellPressure-HighHainSteamLine')Radiation-High()2)Pressure-Low3)Flow-HighMainSteamLineTunnel1)Temperature-High2)6Temperature-High3)~iTPM~~Q.f0>>>+KSLCondenserVacuum-LowRHREquipmentArea1)Temperature-High(HeatExchangers/A8BPumpRms)<1.(*((13!~<13<13(a)13(a)(a)ii!A1.0/<13()AA1.O~/<13()p<O.'5.r<13'ANANApaI<Locwt'e'ANAReactorVesselPressure-HighCRttOcu4~I~lee<'~i~i'>+TSGTSExhaust-HighRadiationRWCUEquipment1)6Flow-High2)6Flow-High,Timer(4)3)SLCSInitiationRWCUEquipmentArea1)Temperature-High(HeatExchanger/PumpRms)13(a)NANAManualIsolationPushbuttonfNSSSjNAQe+ego+Q7$g.Piq4.Chase~~].'ppg~v,ct.~'h~NINEMILEPOINT-UNIT23/43-20NOV2dJ98$
TABLE3.3.2-3(Continued)ppggpgpgyp(p~ISOLATIONSYSTEMINSTRUMENTATIONRESPONSETIMETRIPFUNCTIONRESPONSETIMESeconds2.REACTORCOREISOLATIONCOOLINGSYSTEMISOLATIONa.b.C.d.e.RCICSteamLineFlow-High,TimerC4)RCICSteamSupplyPressure-LowRCICSteamLineFlow-HighRCICTurbineExhaustDiaphragmPressure-HighRCICEquipmentArea1)Temperature-High<~3()$3(a)ji7NANAf.RCICSteamLineTunnel1)Temperature-Highg.ManualIsolationPushButtonj:RCICjh.DrywellPressure-HighRHR/RCICSteamFlow-High3.SECONDARYCONTAINMENTISOLATIONa.ReactorBuildingAbovetheR~j~elFloorExhaustRadiationHighb.ReactorBuildingBelowtheR~(~elFloorExhaustRadiationHighNANA($3(a)NANAtip*ii1idieselgeneratorstartingandsequenceloadingdelays.(b)Radiationdetectorsareexemptfromresponsetimetesting.Responsetimeshallbemeasuredfromdetectoroutputortheinputofthefirstelectroniccomponentinthechannel.(d)SeeTable3.3.2-2fortimerdelay."Iso'1ationsysteminstrumentationresponsetimeforMSIVsonly.Nodieselgeneratordelaysassumed.""IsolationsysteminstrumentationresponsetimeforassociatedvalvesexceptMSIVs.8IsolationsysteminstrumentationresponsetimespecifiedfortheTripFunctionactuatingeachvalvegroupshallbeaddedtoisolationtimeshowninTable3.6.3-1and3.6.5.2-1forvalvesineachvalvegrouptoobtainISOLATIONSYSTEMRESPONSETIMEforeachvalve.NINEMILEPOINT-UNIT23/43-21NOV2Ojgag
TABLE3.3.2-4Pi)il3I'~(+j-<)/ttp~qrVALVEGROUPSANDASSOCIATEDISOLATIONSIGNALSVALVEGROUPS10ASSOCIATEDCONTAINMENTISOL.VLVSBYFUNCTIONMSIV'sandHSLDrainsRecircsystemsamplevalvesTIPIsolationRHRSample8Rad.WasteVa1vesRHRShutdownCoolingValvesRWCUOutboardIso1.ValveRWCUInboardIsol.ValveAllContainmentIsolationValvesnotassignedtoanothergroup-ContainmentPurgeValvesRCICSteamSupplyValvesRCICVacuumBreakerIsolationValvesISOLATIONSIGNALSZ,X,C,D,E,P,T,R,RM,AAB,C,Z,RMB,F,Z,RMA,M,Z,F,RMel'.~0>>A,L,M,Z,RM,ce>C9B,U,J,S,Z,RMqGQB,J,U,S,Z,RMg2DB,F,Z,RMB,F,Y,Z,RMK,M,H,Z,RH>g,S,C<>WZH"4F",RHRemoteManuallyOperatedContainmentValvesBothsignslsmustbecoincidenttocauseisolationNINEMILEPOINT-UNIT23/43-22NOY8v)gag
TABLE3.3.2-5KEYTOISOLATIONSIGNALSPi(Uif'$>~)"p'/~GLMNpRSTUWXYLCLMCzAABBC.CpxoLowreactorvesselwater,level3Lowreactorvesselwater,level2HighmainsteamlineradiationHighmainsteamlineflowHighmainsteamlinetunnelambienttemperatureHighdrywellpressureuAmsw4LowmainsteamlineturbineinletpressureLowmaincondenservacuumStandbyliquidcontrolsystemactuatedHighmainsteamlinetunneldifferentialtemperaturesHighreactorwatercleanupsystemdifferentialflowThisletternotusedLowreactorwaterlevel,level1StandbygastreatmentexhausthighradiationLockedclosedRemotemanualswitchfromcontrolroomLockedclosed-positionindicatorManualisolation~a>~~+ew~faneCtcLosupe~gK~~~i~~-tpeRCIC/RHRSteamlineFlow-Highp.ewc<e<<S<<i&i~gBxg<(+..A-c.~JRSv.i~cki~9]oq~C.KA"-~PLg~.AMOL-<+7~+fLowRCICsteamsupplypressureHighreactorwatercleanupsystemequipmentareaambienttemperatureReactorcoreisolationcoolinghighpiperoutingareatemperatureandequipmentareatemperature,highsteamlineflow,highturbine~exhaustdiaphragmpressure=-HighreactorvesselpressureHighresidualheatremovalsystemequipmentareaambienttemperaturesNINEMILEPOINT-UNIT23/43-23aDVa61Sa
-refI)MfoalImDC)MIITRIPFUNCTION1.PRINRYCONTAINMENTISOLATIONSIGNALSa.ReactorVesselWaterLevelTABLE4.3.2.1-1ISOLATIONACTUATIONINSTRUMENTATIONSURVEILLANCEREUIRBlENTSOPERATIONALCONDITIONSFORWHICHCHANNEL'HANNELCHANNELSURVEILLANCECHECKFUNCTIONTESTCALIBRATIONREUIREDb.C.1.Low,Low,Low,Level12.'ow,Low,Level23.Low,Level3DrywellPressureHighHainSteamLineSSSS:1,2,31,2,3and81,2,3~1,2,31.Radiation-High2.Pressure-Low3.Flow-Highd.HainSteamLineTunnel1,2,311,2,3e.1.Temperature-High2.BTemperature-High7e>.<~e~b-+ut8Big%ggLLS+~CondenservacuumLowGt4CLosuwcSR(d)R(d)R(d)1231,2,33A'.RHREquipmentArea1.Temperature-High(HX's/A8BPumpNA'ooms)g.ReactorVesselPressureHighQN0c.W-ibadpetelssi~e)R(d)R(d)1,2,3.1>>23g~M~AQ<<'D~!leCMV~.
m,<'.il<ITABLE4.3.2.1-1(Continued)ISOLATIONACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREMENTS,ImC)MIC:CHANNELTRIPFUNCTIONCHECK1.PRIMARYCONTAINMENTISOLATIONSIGNALS(Continued)i.SGTSExhaust-HighRadiationSj.RWCUEquipmentCHANNELFUNCTIONTESTSA(e)CHANNELCALIBRATIONOPERATIONAL.CONDITIONSFORWHICHSURVEILLANCE~RE<ERE<12>>31.BFlow-Ngh2.hFlowHighTimer3.StandbyLiquidControl,SLCS,Initiationk.RWCUEquipmentAreaSNA1.2>>31,2,31,2,31.Temperature-High(HX's/A8BPumpSRooms)~RR(d)123C5Cb.RCICSteamSupplyPressure-Lowc.RCICSteamLineFlow,Highd.RCICTurbineExhaustDiaphragmPressure-Highe.RCICEquipmentAreaI1.Temerature-Hih'graurRx.GLhg%'Latec.hvrsc4e~gHg)Ay.>LQ~<~~.1.ManualIsolationPushbuttont.'NSSSg2.RCICISOLATIONSIGNALSa.RCICSteamLineFlowHigh,TimerNASMMR(d)~~~))qE.k)1i2131,2,31,2,31,2,31;2,31.23I~)~(>(g2.3:nC'~~I'Qrg
mC)MITRIPFUNCTION-TABLE4.3.2.1-1(Continued)ISOLATIONACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREMENTSCHANNELCHANNELCHANNELCHECKFUNCTIONTESTCALIBRATIONOPERATIONALCONDITIONSFORWHICHSURVEILLANCEREUIREDM2.RCICISOLATIONSIGNALSf.RCICSteamLineTunnel1.Temperature-HighR(d)123bJIg.ManualIsolationPushButton[RCIC)h.DrywellPressure-High*i.RHR/RCICSteamFlow-High3.SECONDARYCONTAINMENTISOLATIONSIGNALSa.ReactorBuildingAbovetheRefuelFloorExhaustRadiation-Highb.ReactorBuildingBelowtheRefuelFloorExhaustRadiation-HighSA(~SA<<~NA1,2,3le%.($1231,2,3and""1,2,3and""~-Reae~aC.NlriAopg
MmMImC)MICMCslI-TABLE4.3.2.1-1(Continued)IISOLATIONACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREHENTSyjher~~Mhenanyturbinestovglveisgreaterthan90KoIenand/orthekeylockedCondenserLowVacuumBypassSwitchis4a-8eWhenhandlingirradiated'fuelinthesecondarycotainmentandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel."*"SignalsfromLPCSandRHRinitiationsignals;seeTable4.3.3.1-1¹OuringCOREALTERATIONSandoperationwithapoteptialfordrainingthereactorvessel.(a)ManualIsolationpushbuttonsaretestedatleastpnceperoperatingcycleduringshutdown.AllothercircuitryassociatedwithManualIsolationshallI'eceiveaChannelFunctionalTestatleastonceper31daysaspartofthecircuitryrequiredtobetstedfortheAutomaticSystemIsolatiqn.(b)s.7hi>p+gr~~ashe(c)Footnotenotused.(d)Calibrationexcludessensors;sensorresponseandcomparisonshallbedoneinlieuof.o>~qid3dScarc.ecynic,~cAeBDCACyt
PMPF5PPPaPMPFINSTRUMENTATION~~3/4.3.3EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.3Theemergencycorecoolingsystem(ECCS)actuationinstrumentationchannelsshowninTable3.3.3-1shallbeOPERABLEwiththeirtripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.3-2andwithEMERGENCYCORECOOLINGSYSTEMRESPONSETIMEasshowninTable3.3.3-3.APPLICABILITY:AsshowninTable3.3.3-1.ACTION:'a0b.C.WithanECCSactuationinstrumentationchanneltripsetpointlessconservativethanthevalueshownintheAllowableValuescolumnofTable3.3.3-2,declarethechannelinoperableuntilthechannelisrestoredtoOPERABLEstatuswithitstripsetpointadjustedconsistentwiththeTripSetpointvalue.WithoneormoreECCSactuationinstrumentationchannelsinoperable,taketheACTIONrequiredbyTable3.3.3-1.WitheitherADStripsystem"A"or"B"inoperable,restoretheinoperable'tripsystemtoOPERABLEstatuswithin:l.7days,providedthattheHPCSandRCICsystemsareOPERABLE,or2.72hours,providedeithertheHPCSorRCICsystemsareinoperable.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandreducereactorsteamdomepressuretolessthanorequalto100psigwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.3.3.1EachECCSactuationinstrumentationchannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsfortheOPERATIONALCONDITIONSandatthefrequenciesshowninTable4.3.3.1-1.4.3.3.2LOGICSYSTEMFUNCTIONALTESTSandsimulatedautomaticoperationofallchannelsshallbeperformedatleastonceper18months.4.3.3.3TheECCSRESPONSETIMEofeachECCStripfunctionshowninTable3.3.3-3shallbedemonstratedtobewithinthelimitatleastonceper18months.EachtestshallincludeatleastonechannelpertripsystemsuchthatallchannelsaretestedatleastonceeveryNtimes18monthswhereNisthetotalnumberofredundantchannelsinaspecificECCStripsystem.NINEMILEPOINT"UNIT23/43"28HOV20198<
-mMItelTRIPFUNCTIONClMA.DIVISIONITRIPSYSTEMTABLE3.3.9-1EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONHINIHUMOPERABLEAPPLICABLECHANNELSPEgOPERATIONALTRIPFUNCTION)CONDITIONSACTION1.RHR-ALPCIMODE4LPCSSYSTEMMI2.a0b.C.d.ReactorVesselWaterLevel-Low,Low,Low,Level1DrywellPressure-HighLPCSPumpDischargeFlow-Low(Bypass)~~LPCSInjectionValvePermissivee.LPCIInjectionValvePermissivef.LPCIPumpAStartTimeDelayRelayNormalPowerg.LPCIPumpAStartTimeDelayRelayEmer.Powerh.LPCSPumpStartTimeDelayNormalPoweri.LPCSPumpStartTimeDelayEmer.Powerj.LPCIPumpADischargeFlow-Low(Bypass)~~k.ManualInitiationAUTOMATICDEPRESSURIZATIONSYSTEMTRIPSYSTEM"A"2(b)2(b)I/W~1'111/pump1/system1,2,3,5III1j2j3j4A5III1j2j3j1j2j3j1231,2,3,4A5III4*5III4III5*4*5*4III5IIC4III5III4III5III4III5IIC30303132333233323232323135EDCOa%b.C.d.e.f.g.ReactorVesselWaterLevel-Low,Low,Low,Level1ADSTimerReactorVesselWaterLevel-Low,Level3(Permissive)LPCSPumpDischargePressure-High(Permissive)LPCIPumpADischargePressure-High(Permissive)ManualInhibit.ManualInitiation2(b)112212/system1,2,31231,2,31,2,31,2,31,2,31~2j330323232323235le~1'CC
TABLE3.3.3-1(Cont'd).TRIPFUNCTIONB.DIVISIONIITRIPSYSTEM1.RHRBLPCIHODEEHERGENCYCORECOOLINGSYSTEHACTUATIONINSTRUMENTATIONHINIHUHOPERABLEAPPLICABLECHANNELSPEgOPERATIONALTRIPFUNCTION~CONDITIONSACTION2.a@b.C.LPCIPumpBStartTimeDelayRelayNormalPowerLPCIPumpCStartTimeDelayRelayNormalPowerLPCIPumpBStartTimeDelayRelayEmer.PowerLPCIPumpCStartTimeDelayRelayEmer.PowerLPCIPumpDischargeFlow-Low(Bypass)~~HanualInitiationd.e.f.g.h.1~AUTOMATICDEPRESSURIZATIONSYSTEHTRIPSYSTEH"B"ReactorVesselWaterLevel-Low,Low,Low,Level1DrywellPressure-HighLPCIInjectionValvePermissive2(b)2(b)1/valve11111/pump1/system1,2,3,1,2,3,4AA1.23lo2A3t1,2,3,1,2,3,4",5"303032334!II5!IC325A325*324A5!II324IIC5A'15A'5aob.C.d.e.f.ReactorVesselMaterLevel-Low,Low,Low,Level12(b)ADSTimer1ReactorVesselMaterLevel-Low,Level3(Permissive)1LPCIPump(BandC)DischargePressure-High.(Permissive)Q.4/pumpHanualInhibit1HanualInitiation2/(system)1$2$31,2,31,2,3303232323235lailCkefg
TABLE3.3.3-1(Cont'd).EHERGENCYCORECOOLINGSYSTEHACTUATIONINSTRUHENTATIONClMIMTRIPFUNCTIONC.DIVISIONIIITRIPSYSTEM1.HPCSSYSTEMa.ReactorVesselWaterLevel-Low,Low,Level2b.DrywellPressure-High(¹¹¹)c.ReactorVesselMaterLevel"High,Level8d.CondensateStorageTankLevel-Lowe.SuppressionPoolMaterLevel-Highf.HPCSSystemFlowRate-Low(Bypass)~~*g.ManualInitiation(¹¹¹)h.PumpDischargePressure-High(Bypass)~ACTION4(b)4(b)4(c).2(d)2(d)11/system11,2,3,1,2,3,1,2,3,1,2,3,1,2,3,4*5III36364",5"324*5IIC374k5III374IIC5IIC354"'O"gS~MINIMUMOPERABLEAPPLICABLECHANNELSPEgOPERATIONALTRIPFUNCTIONS)CONDITIONSD.3/busTOTALNO.CHANNELSOFCHANNELSTOTRIPLOSSOFPOWER(DivisionsI,II,andIII)l.4.16kVEmergencyBusUnder-voltage-LossofVoltage2/bus2.4.16kVEmergencyBusUnder-voltage-DegradedVoltage3/bus2/busMINIMUMCHANNELSOPERABLE2/bus2/busAPPLICABLEOPERATIONALCONDITIONSACTION]234*III5*III3834IICIIC5IIIIII39aAchannemayeplacedinaninoperablestatusforupto2hoursduringperiodsofrequiredsurveillancewithoutplacingthetripsysteminthetrippedconditionprovidedatleastoneotherOPERABLEchannelinthesametripsystemismonitoringthatparameter.(b)Alsoactuatestheassociateddivisiondieselgenerator.(c)ProvidessignaltocloseHPCSpumpinjectionvalveonly.(d)ProvidessignaltoHPCSpumpsuctionvalvesonly.WhenthesystemisrequiredtobeOPERABLEperSpecification3.5.2or3.5.3.RequiredwhenESFequipmentisrequiredtobeOPERABLE.NotrequiredtobeOPERABLEwhenreactorsteamomepressureislessthanorequalto100psig..'7Jaan.~~~'BCCS~uk~~¹¹¹TheinjectionfunctionofDrywe1PressureHighandManual"InitiationisnotrequiredtobeOPERABLEwithindicatedreactorvesselwaterlevelonthewiderangeinstrumentgreaterthanlevel8setpointcoincidentwiththevesselpressurelessthan600psig.O'QIPlQ~eg
TABLE3.3.3"1(Continued)ACTION30-ACTION31"EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONACTIONWiththenumberofOPERABLEchanneisIessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement:a.Withonechannelinoperable,placetheinoperablechannelinthetrippedconditionwithinonehour"ordeclaretheassociatedsysteminoperable.b.Withmorethanonechannelinoperable,declaretheassociatedsysteminoperable.~~r;sACTION32-.ACTION33-ACTION34-WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,~declaretheassociated.AOStripsystemorECCSinoperable.WiththenumberofOPERABLKchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,placetheinoperablechannelinthetrippedconditionwithinonehour.ACTION35"ACTION36-ACTION37"ACTION38-ACTION39-WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,restoretheinoperablechanneltoOPERABLEstatuswithin8hoursordeclaretheassociatedADSvalveorECCSinoperable.WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement:a.Foronetripsystem,placethattripsysteminthetrippedconditionwithinonehour"ordeclaretheHPCSsysteminoperable.b.Forbothtripsystems,declaretheHPCSsysteminoperable.WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,placeatleastoneinoperablechannelinthetrippedconditionwithinonehour"ordeclaretheHPCSsysteminoperable.WiththenumberofOPERABLEchannelslessthantheTotalNumberofChannels,declaretheassociatedemergencydieselgeneratorinoperableandtaketheACTIONrequiredbySpecification3.8.1.1or3.8.1.2,asappropriate.WiththenumberofOPERABLEchannelsonelessthantheTotalNumberofChannels,placetheinoperablechannelinthetrippedconditionwithin1hour";operationmaythencontinueuntilperformanceofthenextrequiredCHANNELFUNCTIONALTEST.TheprovisionsofSpecification3.0.4arenotapplicable.NINEMILEPOINT-UNIT23/43-32fi6VP.088>
z1m~~s@3-3zt~h4.~<'P~~Lv'c~"P~~p~~-2~"~~Op&/.&61C7~~~4Wk'c.m~Wa-t3+'VJL~&PM~M~dAL"P~~'~~-'/m~J4AR(4zk~~~c)Vss.~wm~~c,
Mm-ITABLE3.3.3-2EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONSETPOINTSMmCIMI1.RHR-ALPCIHODEANDLPCSSYSTEHTRIPFUNCTIONA.DIVISIONITRIPSYSTEMTRIPSETPOINTALLOWABLEVALUEMasb.C.d.e.g.h.k.ReactorVesselMaterLevel-Low,Low,Low,Level1DrywellPressure-High.LPCSPumpDischargeFlow-Low(Bypass)WLPCSInjectionValvePermissiveLPCIInjectionValvePermissivelLPCIPumpAStartTimeDelayRelayNormalPowerLPCIPumpAStartTimeDelayRelayEmer.PowerLPCSPumpStartTimeDelayNormalPowerLPCSPumpStartTimeDelayEmer.PowerLPCIPumpADischargeFlow-Low(Bypass)CManualInitiation>17.8in."<1.68psig>1200gpm<88psid,decreasing130paid,decreasing<5sec.'1sec<10sec<6sec>1400gpmNA10.8in.1.88psig1000gpm98psid,decreasing150psid,decreasing<7sec2sec<12sec7sec>1200gpmNA2.AUTOMATICDEPRESSURIZATIONSYSTEMTRIPSYSTEM"A"Casb.C.d.e.f.g.ReactorVesselMaterLevel-Low,Low,Low,Level1ADSTimerReactorVesselWaterLevel-Low,Level3(Permissive)LPCSPumpDischargePressure-High(Permissive)LPCIPumpADischargePressure-High(Permissive)HanualInhibitManualInitiation'17.8in.*<105sec~>159.3in.>145psig,increasing>125psig,increasingNANA>10.8in.<117sec>157.8in.>125psig,increasing>115psig,increasin
MmMIPlTRIPFUNCTIONTRIPSETPOINTALLOWABLEVALUETABLE3.3.3-2(Continued)EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONSETPOINTS,B.DIVISIONIITRIPSYSTEM1.RHRBANDCLPCIMODEa0b.C.ReactorVesselWaterLevel-Low,Low,Low,Level1DrywellPressure-HighLPCIInjectionValvePermissive>17.8in.*<1.68psid<130psid,decreasing>10.8in.<1.88psid<150psid,decreasingd.e.'.h.LPCIPumpBStartTimeDelayNormalPowerLPCIPumpCStartTimeDelayNormalPowerLPCIPumpBStart.TimeDelayEmergencyPowerLPCIPumpCStartTimeDelayEmergencyPowerLPCIPumpDischargeFlow-LowHanualInitiationRelayRelayRelay(Bypass@<5sec<10sec<1secI<6sec>1400gpmNA<7sec<12sec2sec7sec>1200gpmNA2.'UTOMATICDEPRESSURIZATIONSYSTEHTRIPSYSTEHIIB"b.C.d.e.f.ReactorVesselWaterLevel-Low,Low,Low,Level1ADSTimerReactorVesselWaterLevel-Low,Level3(Permissive)LPCIPump(BandC)DischargePressure-High(Permissive)HanualInhibitManualInitiation>17.8in~<105sec>159.3in.*>125psig,increasingNANA>10.8in.<117sec>157.8in.>115psig,increasingNANACD
TABLL,3.3.3-2(Continued)EMERGENCYCORECOOLINGSYSTEHACTUATIONINSTRUMENTATIONSETPOINTS;TRIPFUNCTIONC.DIVISIONIIITRIPSYSTEM1.HPCSSYSTEMTRIPSETPOINTALLOWABLEVALUE>108.8in."<1.68psig<202.3in.">~ft3<201.'0'l.>750gpma.ReactorVesselWaterLevel-Low,Low,Level2b.DrywellPressure-Highc.ReactorVesselWaterLevel-High,Level8d.CondensateStorageTankLevel-Lowe.SuppressionPoolWaterLevel-HighQypAss)f.HPCSSystemFlowRate-LowManualIntitionD.LOSSOF'POWERDIVISIONSIIIIIIumpDscargePressure-High(Bypass~>~psig2~0>101.8in.<1.88psig<209.3in.>~ft$0~.<201.1'l.>700gpmHA>~psig~M4tl.4.16k~VmergencyBusUnder-voltage-LossofVoltage2.4.16kvEmergencyBusUnder-voltage-DegradedVoltagea.4.16kVBasis-5268t161voltsb.<3sec.timedelaya.4.16kVBasis-3843I9Nitsb.8t0'.16sec.timedelayc.30a0.6sec.timedelay3268t315volts<3sec.timedelay3843I7volts8a0.32sec.timedelay3021.2sec.timedelay3333/431.AlarmonlywithoutLOCAsignalpresent;AlarmandtripwithLOCAsignalpresent.+aces
TABLE3.3.3"3PiiMf5i]VP4(gPPEMERGENCYCORECOOLINGSYSTEMRESPONSETIMESECCS1.LOWPRESSURECORESPRAYSYSTEMa.Diese1GeneratorStartTime"b.InjectionVa1veOpeningTimeRESPONSETIMESeconds<10<202.LOWPRESSURECOOLANTINJECTIONMODEOFRHRSYSTEM(DivisionIandDivisionII)a.Diese1GeneratorStartTimeb.InjectionVa1veOpeningTime<10<203.AUTOMATICDEPRESSURIZATIONSYSTEM5.HIGHPRESSURECORESPRAYSYSTEMLOSSOFPOWER<27NA~pd11g"PifigNINEMILEPOINT-UNIT23/43"3680V20gag
ITABLE4.3.3.1-1EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREMENTS,TRIPFUNCTIONCHANNELCHECKCHANNELFUNCTIONALTESTCHANNELCALIBRATIONOPERATIONALCONDITIONSFORWHICHSURVEILLANCEREUIREDA.DIVISIONITRIPSYSTEM1.RHR-APCMODEANDLPCSSYSTEMa.eactorVesseWatereveLow,Low,Low,Level1b.DrywellPressure-Highc.LPCSPumpDischargeFlow-Low(Bypass)d.LPCSInjectionValvePermissivee.LPCIInjectionValvePermissivef.LPCIPumpAStartTimeDelayRelayNormalPowerg.LPCIPumpAStartTimeDelayRelayEmer.'Powerh.LPCSPumpStartTimeDelayNormalPoweri.LPCSPumpStartTimeDelayEmer.Powe~r&>schageLPCIPumpA"Flow-Low(Bypass)k.ManualInitiation2.AUTOMATICDEPRESURIZATIONSYSTEMTRIPSYSTMAa.ReactorVesselWaterLevel-Low,Low,Low,Level1b.ADSTimerc.ReactorVesselWaterLevel-.Low,Level3(Permissive)d.LPCSPumpDischargePressure-High(Permissive)e.LPCIPumpADischargePressure-High(Permissive)f.ManualInhibitg.ManualInitiationNASNASNASNANAMMM(a)MMM(a)RRNA'RQRNANA1,2,3,4",5"1,2,31,2,3,4",5+1234"5"1,2,3,4",5*1,2,3,4",5"1,2,3,4*,5"1,2,3,4",5"1,2,31j2$31,2,31,.2,31,2,31,2,31,2,3~e~eyCXP
TABLE4.3.3.1-1(Continued),MfoalMmTRIPFUNCTIONCMANNELCHECKCHANNELFUNCTIONALTESTCHANNELCALIBRATIONOPERATIONALCONDITIONSFORWHICHSURVEILLANCEREUIREDEHERGENCYCORECOOLINGSYSTEHACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREHENTSIC)MCMB.DIVISIONIITRIPSYSTEH1.RHRBANDCLPCIHODE)a.b.C.d.e.f.g.h.1~ReactorVesse'lMaterLevel-Low,Low,Low,Level1DrywellPressure-HighLPCIInjectionValvePermissiveLPCIPumpBStartTimeDelayRelayNormalPowerLPCIPumpCStartTimeDelayRelayNormalPowerLPCIPumpBStartTimeDelayEmergencyPowerLPCIPumpCStartTimeDelayRelayEmergencyPowerLPCIPumpDischargeFlow-Low(Bypass)HanualInitiation2.AUTOMATICDEPRESURIZATIONSYSTEHNANAHHH'HNA.H(a)RNA1,2,3,4",5"1,2,3,4",5"1,2,3,4",5*1,2,3,4+,5"1234*5"1,2,3,4",5"1,2,3,4*,5+TRIPSYSTEH8a@b.C.d.e.f.ReactorVesselWaterLevel-Low,Low,Low,Level1ADSTimerReactorVesselMaterLevel-Low,Level3(Permissive)LPCIPump(8andC)DischargePressure-High(Permissive)HanualInhibitHanualInitiationSNANANAHHH(a)RNANA1.231,2,312.31,2,31$2$31$2$3:egC:>geCDtel
,~'ll"ITABLE4.3.3.1-1(Continued)EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONSURVEILLANCEREUIRBIENTSiClMITRIPFUNCTIONC.DIVISIONIIITRIPSYSTEM1.HPCSSYSTEMCHANNELCHECKCHANNELFUNCTIONALTESTOPERATIONALCHANNELCONDITIONSFORMHICHCALIBRATIONSURVEILLANCEREUIRED4JIa.ReactorVesselMaterLevel-Low,Low,Leo,l2Sb.DrywellPressure-High(b)Sc.ReactorVesselMaterLevel-High,Level8Sd.CondensateStorageTankLevel-LowSe.SuppressionPoolWaterLevel-HighSf.HPCSSystemFlowRate-Low(Bypass)Sg.PumpDischargePressure-High(Bypass)Sh.ManualInitiation(b)N1,2,3,4",5"1,2,3,4",5"1,2,3,4*,5"1,2,3,4",5"1,2,3,4",5"34'A5A'4A'*RNAD.44.16kVEmergencyBusUndervoltageLossofVoltage4.16kVEmergencyBusUndervoltageDegradedVoltage2.H1$2jcyAV(a)1,2,LOSSOFPOWERA1.SHR1234+*5~*rigSHR34AA5A'A'+aNotrequiredtobeOPERABLEwhenreactorsteamdomepressureislessthanorequalto100psig.*WhenthesystemisrequiredtobeOPERABLEperSpecification3.5.2.RequiredwhenESFequipmentisrequiredtobeOPERABLE.(a)Manualinitiationswitchesshallbetestedatleastonceper18monthsduringshutdown.AllothercircuiassociatedwithmanualinitiationshallreceiveaCHANNELFUNCTIONALTESTatleastonceper31daysaspartofcircuitryrequiredtobetestedforautomatic,systemactuation.(b)TheinjectionfunctionofDrywel'1Pressure-HighandManualInitiationisnotrequiredtobeOPERABLEwithindicatedreactorvesselwaterlevelonthewiderangeinstrumentgreaterthanLevel8setpointcoincidentwiththevesselpressurelessthan600.psig. 4~ INSTRUMENTATIONPMN5gpj,'pgspy3/4.3.4RECIRCULATIONPUMPTRIPACTUATIONINSTRUMENTATIONATWSRECIRCULATIONPUMPTRIPSYSTEMINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.4.1Theanticipatedtransientwithoutscramrecirculationpumptrip(ATWS-RPT)systeminstrumentationchannelsshowninTable3.3.4.1-1shallbeOPERABLEwiththeirtripsetpointssetconsistentwithvaluesshownintheTripSetpointcolumnofTable3.3.4.1"2.APPLICABILITY:OPERATIONALCONDITIONl.ACTION:a.b.C.WithanATWS-RPTsysteminstrumentationchanneltripsetpointlessconservativethenthevalueshownintheAllowableValuecolumnofTable3.3.4.1-2,declarethechannelinoperableuntilthechannelisrestoredtoOPERABLEstatuswiththechanneltripsetpointadjustedconsistentwiththeTripSetpointvalue.WiththenumberofOPERABLEchannelsonelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforoneorbothtripsystems,placetheinoperablechannel(s)inthetrippedconditionwithinonehour.WiththenumberofOPERABLEchannelstwoormorelessthanrequiredbytheMinimumOperableChannelsperTripSystemrequirementforonetripsystemand:1.Iftheinoperablechannelsconsistofonereactorvesselwaterlevelchannelandonereactorvesselpressurechannel,placebothinoperablechannelsinthetrippedconditioMithinonehour.2.Iftheinoperablechannelsincludetworeactorvesselwaterlevelchannelsortworeactorvesselpressurechannels,declarethetripsysteminoperable.4Withonetripsysteminoperable,restoretheinoperabletripsystemtoOPERABLEstatuswithin72hoursorbeinatleastSTARTUPwithinthenext6hours.Withbothtripsystemsinoperable,restoreatleastonetripsystemtoOPERABLEstatuswithinonehourorbeinatleastSTARTUPwithinthenext6hours.SURVEILLANCEREUIREMENTS4.3.4.1.1.EachATWS-RPTsysteminstrumentationchannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.4.1-1.4.3.4.1.2LOGICSYSTEMFUNCTIONALTESTSandsimulatedautomatedoperationofallchannelsshallbeperformedatleastonceper18months.TheinoperablechannelsneednotbeplacedinthetrippedconditionwherethiswouldcausetheTripFunctiontooccur.Inthiscase,theinoperablechannelsshallberestoredtoOPERABLEstatuswithin2hours,orthetripsystemshallbedeclaredinoperable.NINEMILEPOINT"UNIT23/43-40NGV201a 0~: MmMIPlC)MTABLE3.3.4.1"1:'RIPFUNCTION1.ReactorVesselWaterLevel-LowLow,Level22.ReactorVesselPressure-HighATWSRECIRCULATIONPUHPTRIPSYSTEHINSTRUMENTATIONHINIHUHOPERABLECHANNELSPERTRIPSYSTEH2CDtxU'Onechannelanditsassociatedtripsystemmaybeplacedinaninoperablestatusforupto2hoursforrequiredsurveillanceprovidedtheotherchannelanditstripsystemisOPERABLE.C7are~rig~A ~: MmMlmTABLE3.3.4.1-2ATWSRECIRCULATIONPUMPTRIPSYSTEMINSTRUMENTATIONSETPOINTS'aClMICMTRIPFUNCTION1..ReactorVessel,WaterLevel-LowLow,Level22.ReactorVesselPressure-HighTRIPSETPOINT>108.8in"<1050psigALLOWABLEVALUE>101.8in<1065psigeeasesfigures83/'43-1. 0' MmTABLE4.3.4.1"1ATWSRECIRCULATIONPUMPTRIPACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREMENTSC)MCHANNEL:CHECKTRIPFUNCTIONI1.ReactorVesselMaterLevel-SLowLow,Level22.ReactorVesselPressure-HighSCHANNELFUNCTIONALTESTMMCHANNELCALIBRATION
INSTRUMENTATIONEil8PFgPP~~P@AEND"OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.4.2Theend-of-cyclerecirculationpumptrip(EOC-RPT)systeminstrumentationchannelsshowninTable3.3.4.2-1shallbeOPERABLEwiththeirtripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.4.2-2andwiththeEND-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSETIMEasshowninTable3.3.4.2-3.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorRRR'IRETIETIIERRRLTRITER.ACTION:aeb.C.d.e.'.Withanend-of-cyclerecirculationpumptripsysteminstrumentationchanneltripsetpointlessconservativethanthevalueshownintheAllowableYaluescolumnofTable3.3.4.2-2,declarethechannelinoperableuntilthechanne'1isrestoredtoOPERABLEstatuswiththechannelsetpointadjustedconsistentwiththeTripSetpointvalue.WiththenumberofOPERABLEchannelsonelessthanrequiredbytheMinimumOPERABLE.ChannelsperTripSystemrequirementfoioneorbothtripsystems,placetheinoperablechannel(s)inthetrippedconditionwithinonehour.WiththenumberofOPERABLEchannelstwoormorelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforonetripsystemand:I.Iftheinoperablechannelsconsistofoneturbinecontrolvalvechannelandoneturbinestopvalvechannel,placebothinoperablechannelsinthetrippedconditionwithinonehour.2.Iftheinoperablechannelsincludetwoturbinecontrolvalvechannelsortwoturbinestopvalvechannels,declarethetripsysteminoperable.Withonetripsysteminoperable,restoretheinoperabletripsystemtoOPERABLEstatuswithin72hoursorreduceTHERMALPOWERtolessthan30KofRATEDTHERMALPOWERwithinthenext6hours.Withbothtripsystemsinoperable,restoreatleastonetripsystemtoOPERABLEstatuswithinonehourorreduceTHERMALPOWERtolessthan30KofRATEDTHERMALPOWERwithinthenext6hours.NINEMILEPOINT-UNIT23/43-44HOV2019Bg ~' INSTRUMENTATIONSURVEILLANCEREUIREMENTS14.3.4.2.1Eachend-of-cyclerecirculationpumptripsysteminstrumentationchannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.4.2.1-1.4.3.4.2.2LOGICSYSTEMFUNCTIONALTESTSandsimulatedautomaticoperationofallchannelsshallbeperformedatleastonceper18months.4.3.4.2.3TheEND-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSETIMEofeachtripfunctionshowninTable3.3.4.2-3shallbedemonstratedtobewithinitslimitatleastonceper18months.Eachtestshallincludeatleastthelogicofonetypeofchannelinput,turbinecontrolvalvefastclosureorturbinestopvalveclosure,suchthatbothtypesofchannelinputsaretestedatleastonceper36months.(NINEMILEPOINT-UNIT23/43"45
eTABLE3.3.4.2-1(y.MIIIIIIIC)MICMTRIPFUNCTION1.TurbineStopValve-Closure2.TurbineControlValve-FastClosureHINIHUHOPERABLECNANNEH)PERTRIPSYSTEH2(b)2(b)END"OF-CYCLERECIRCULATIONPUHPTRIPSYSTEHINSTRUHENTATION21yypp1df1pP1fp22f21d111pfddthattheothertripsystemisOPERABLE.(b).~~lTLLR-R,4~MA(ry3Olo+47~>TH~qWL-~Q~q++I'powOAVuC+,lP~62PAAOQ~~Xk~dr(~~IAMB~vlQeQ3
"II!I~3TABLE3.3.4.2-2END-OF-CYCLERECIRCULATIONPUMPTRIPSETPOINTSmMItealC:MTRIPFUNCTION1.TurbineStopValve-Closure2.TurbineControlValve-fastClosureTRIPSETPOINT<5Xclosed>530psigALLOWABLEVALUE<7Xclosed>465psig
foalTRIPFUNCTION.TABLE3.3.4.2-3ENO-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEHRESPONSETIMERESPONSETIMEHil1isecondsIfllCII1.TurbineStopValve-Closure2.TurbineControlValve-FastClosure<190<190
m,-ITABLE4.3.4.2.1-1END-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMSURVEILLANCEREUIREHENTS,ImC)ICMTRIPFUNCTION1.TurbineStopValve-Closure2.TurbineControlValve-FastClosureCHANNELFUNCTIONALTESTCHANNELCALIBRATION
INSTRUMENTATIONP~+ff+q.QIfgf!g!fff&tlIJLUBE~~<gj.'g~j'3~)3/4.3.5REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.5Thereactorcoreisolationcooling(RCIC)systemactuationinstrumenta-tionchannelsshowninTable3.3.5-1shallbeOPERABLEwiththeirtripset-pointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.5-2.APPLICABILITY:OPERATIONALCONDITIONS1,2and3withreactorsteamdomepressuregreaterthan150psig.ACTION:a.'ithaRCICsystemactuationinstr'umentationchanneltripsetpointlessconservativethanthevalueshownintheAllowableValuescolumnofTable3.3.5-2,declarethechannelinoperableuntilthechannelisrestoredtoOPERABLEstatuswithitstripsetpointadjustedconsistentwiththeTripSetpointvalue.b.WithoneormoreRCICsystemactuationinstrumentationchannelsinoperable,taketheACTIONrequiredbyTable3.3.5-1.SURVEILLANCEREUIREMENTS4.3.5.1EachRCICsystemactuationinstrumentationchannelshallbedemon-stratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.5.1-1.4.3.5.2LOGICSYSTEMFUNCTIONALTESTSandsimulatedautomaticoperationofallchannelsshallbeperformedatleastonceper18months.NINEMILEPOINT-UNIT23/43-50NOVP.0]995
FUNCTIONALUNITS-TABLE3.3.5-1REACTORCOREISOLATIONCOOLINGSYSTEHACTUATIONINSTRUMENTATIONHINIHUHOPERABLECHANNEL$PERTRIPSYSTEH~ACTIONa.ReactorVesselWaterLevel-Low,Low,Level2b.ReactorVesselMaterLevel-High,Level8c.CondensateStorageink"A"MaterLevel-Lowd.HanualInitiation.2(b)1/system(c)50505152acannemayeplacedinaninoperablestatusforupto2hoursforrequiredsurveillancewithoutplacingthetripsysteminthetrippedconditionprovidedatleastoneotherOPERABLEchannelinthesametripsystemismonitoringthatparameter.(b)Onetripsystemwithone-out-of-twologic.(c)Onetripsystemwithonechannel.(d)HanualinitiationisnotrequiredtobeOPERABLEwithindicatedreactorvesselwaterlevelonthewiderangeinstrumentgreaterthanLevel8setpointcoincidentwiththevesselpressure,lessthan600psig.(e)~Level8tripsmaybebypassedtoperformRCIC150psigoperationalsurveillancetestinaccordancewithSpecification4.7.4.c.2.
TABLE3.3.5-1(Continued)REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATIONFEVER3"7'0ppACTION50-MiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirement:a.Foronetripsystem,placetheinoperablechannel(s)and/orthattripsysteminthetrippedconditionwithinonehourordeclaretheRCICsysteminoperable.b.Forbothtripsystemswithmorethanonechannelinoperable,declaretheRCICsysteminoperable.ACTION51-MiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirement,placeatleastoneinoperablechannelinthetrippedconditionwithinonehourordeclaretheRCICsysteminoperable.~~ACTION52-WiththenumberofOPERABLEchannelsonelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirement,restoretheinoperablechanneltoOPERABLEstatuswithin8hoursordeclaretheRGICsysteminoperable.'INEMILEPOINT-UNIT23/43-52NOV20ass
MITlITIFUNCTIONALUNITSTRIPSETPOINTALLOWABLEVALUE-TABLE3.3.5-2REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATIONSETPOINTS.CIMa.ReactorVesselWaterLevel-Low,Low,Level2b.ReactorVesselWaterLevel-High,Level8c.CondensateStorageTankLevel"A"-Lowd.ManualInitiation>108.8inches"<202.3inches"Cr/5ft>1018inches209.3inches>MMftColOJISeeBasesFigureB3/43-1.
TABLE4.3.5.1-1REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREMENTSFUNCTIONALUNITSa.ReactorVesselWaterLevel-LowLow[Level23b.ReactorVesselWaterLevel-High[Level8]c.CondensateStorageTankLevel-Lowd.ManualInitiationCHANNELCHECKCHANNELFUNCTIONALTESTM(a)CHANNELCALIBRATIONu<<iihh11b<<d1tp1hdighd..A11hcircuitryassociatedwithmanualinitiationshallreceiveaCHANNELFUNCTIONALTESTatleastonceper31daysaspartofcircuitryrequiredtobetestedforadtomaticsystemactuation.(b)ManualinitiationisnotrequiredtobeOPERABLEwithindicatedreactorvesselwaterlevelonthewiderangeinstrumentgreaterthanLevel8setpointcoincidentwiththevesselpressurelessthan600psig.
INSTRUMENTATIONP;,gPFggP/ICW(pqp~~~3/4.3.6CONTROLRODBLOCKINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.6.ThecontrolrodblockinstrumentationchannelsshowninTable3.3.6"1shallbeOPERABLEwiththeirtripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.6-2.APPLICABILITY:AsshowninTable3.3.6-1.ACTION:aob.MithacontrolrodblockinstrumentationchanneltripsetpointlessconservativethanthevalueshownintheAllowableValuescolumnofTable3.3.6-2,declarethechannelinoperableuntilthechannelisrestoredtoOPERABLEstatuswithitstripsetpointadjustedconsistentwiththeTripSetpointvalue.Withthenumberof.OPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,taketheACTIONrequiredbyTable3.3.6-1.SURVEILLANCEREUIREMENTS4.3.6EachoftheaboverequiredcontrolrodblocktripsystemsandinstrumentationchannelsshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsfortheOPERATIONALCONDITIONSandatthefrequenciesshowninTable4.3.6-1.NINEMILEPOINT-UNIT23/43-55~0V28lg8g
MmTRIPFUNCTIONMINIMUMOPERABLECHANNELSPERTRIPFUNCTIONAPPLICABLEOPERATIONALCONDITIONSTABLE3.3.6-1CONTROLRODBLOCKINSTRUMENTATIONACTIONC)I1.2.3.4.5.RODBLOCKMONITORa.Upscaleb.Inoperativec.DownscaleAPRHa.FlowBiasedNeutronFluxUpscaleb.Inoperativec.Downscaled.NeutronFlux-Upscale,StartupSOURCERANGEMONITORS(b)a.Detectornotfullinb.Upscale()c.Inoperatived.DownscaleINTERHEOIATERANGEMONITORSa.Detectornotfull~nb.Upscalec.Inoperatig)d.DownscaleSCRAMDISCHARGEVOLUMEa.WaterLevel-H)gh1A1A'1,12125.25i252522.21212,555%A6060606161616161616161616161616161616162REACTORCOOLANTSYSTEMRECIRCULATIONFLOWC)(7.a.Upscaleb.Inoperativec.ComparatorREACTORHODESWITCHa.ShutdownModeb.RefuelModeI03.56262626262 4 TABLE3.3.6-1(Continued)CONTROLRODBLOCKINSTRUMENTATIONpIIIIIIVOFdpNPlllAAW1tIWV[gjg~~y'pegUP~ACTIONACTION60-DeclaretheRBMinoperableandtaketheACTIONrequiredbySpecification3.1.4.3.ACTION61-WiththenumberofOPERABLEChannels:a.OnelessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,restoretheinoperablechanneltoOPERABLEstatuswithin7daysorplacetheinoperablechannelinthetrippedconditionwithinthenexthour.b.TwoormorelessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,placeatleastoneinoperablechannelinthetrippedconditionwithinonehour.ACTION62-WiththenumberofOPERABLEchannelslessthanrequiredbytheMinimumOPERABLEChannelsperTripFunctionrequirement,placetheinoperablechannelinthetrippedconditionwithinonehour.NOTESWithTHERMALPOWER>30KofRATEDTHERMALPOWER.Withmorethanonecontrolrodwithdrawn.NotapplicabletocontrolrodsremovedperSpecification3.9.10.1or3.9.10.2.a.TheRBMshallbeautomaticallybypassedwhenaperipheralcontrolrodisselected.b.Thisfunctionshallbeautomaticallybypassedifdetectorcountrateis>100cpsortheIRMchannelsareonrange3orhigher.C.d.e.ThisfunctionshallbeautomaticallybypassedwhentheassociatedIRMchannelsareonrange8orhigher.ThisfunctionshallbeautomaticallybypassedwhentheIRMchannelsareonrange3orhigher.ThisfunctionshallbeautomaticallybypassedwhentheIRMchannelsareonrangel.NINEMILEPOINT-UNIT23/43-57NV80SS5
~~.variIIMmTABLE3.3.6-2CONTROLRODBLOCKINSTRUHENTATIONSETPOINTSaCIMICMtQColICOTRIPFUNCTION1.RODBLOCKHONITORa.Upscaleb.Inoperativec.Downscale2.APRHa.FlowBiasedNeutronFluxUpscaleb.Inoperativec.Downscaled.NeutronFlux-Upscale,Startup3.SOURCERANGEHONITORSa.Detectornotfullinb.Upscalec.Inoperatived..Downscale4.INTERMEDIATERANGEMONITORSa.Detectornotfull>nb.Upscalec.Inoperatived.Downscale5.SCRAMDISCHARGEVOLUHEa.WatelLevel-HlghTRIPSETPOINT<0.66M+4OXQ>5XofRATEDTHERHALPOWER<0,66W+42X"HA>4XofRATEDTHERMALPOWER<12XofRATEDTHERHALPOWERNA<1x10scpsHA3cpsAANA.<108/125divisionsoffullscaleNA>5/125divisionsoffullscale<16.5in.ALLOWABLEVALUE<0.66W+43XNA>3XofRATEDTHERHALPOWER.<0.66M+45X"HA>3XofRATEDTHERHALPOWER<14XofRATEDTHERHALPOWERNA<16x10scpsNA>1.8cps""NA<110/125divisionsoffullscaleNA>3/125divisionsoffullscale<39.75in.6.REACTORCOOLANTSYSTEHRECIRCULATIONFLOWa.Upsca1eb.Inoperativec.Comparator<108XratedflowNA<10Xflowdeviation<111XratedflowNA.<11XffowdeviationEDCDCl1TheAveragePowerRangeHonitorrodblockfunctionisvariedasafunctionofrecirculationloopflow(W).ThetripsettingofthisfunctionmustbemaintainedinaccordancewithSpecification3.2.2.*"Forinitialloadingandstartupthe-"countratemaybelegsthan3cpsifthefollowingconditionsaremet;(1)thesignaltonoiseratioisgreaterthan2.0>(2)thesignalisgreaterthan0.7cp~ad-J~~fJi~CP~A
MIlltllaCIMTRIPFUNCTION7.REACTORMODESMITCHa.ShutdownModeb.RefuelModeTABLE3.3.6-2(Continued)CONTROLRODBLOCKINSTRUMENTATIONSETPOINTSTRIPSETPOINTNANAALLOWABLEVALUENANAef
TABLE4.3.6-1CONTROLRODBLOCKINSTRUMENTATIONSURVEILLANCEREUIREHENTSTRIPFUNCTION1.RODBLOCKMONITORCHANNELCHECKCHANNELFUNCTIONALTEST'HANNELCALIBRATIONOPERATIONALCONDITIONSFORWHICHSURVEILLANCEREUIREDa.Upsealeb.Inoperativec.Downscale2.APRHa.FlowBiasedNeutronFluxUpscaleb.Inoperativec.Downscaled.NeutronFlux-Upscale,Startup3.SOURCERANGEHONITORSNANANANAS/U(b)M(b)S/U(b)MS/U(b),MS/U,M(b)(c)(c)NA(b)(c)'c)NANAS/U,H(b)()'c)QNAQNA1*7A1*11,2,512,5a.Detectornotfullinb.Upscalec.Inoperatived.Downscale4.INTERMEDIATERANGEMONITORSa.Detectornotfullinb.Upscalec.Inoperatived.Downscale5.SCRAMDISCHARGEVOLUMENANANANANANANANAS/U(b),W(b)S/U(b),WS/U,WS/U(b)MS/U(b),W(b)S/U(b),MS/U(b)MS/U,WNANANAQNA2,52,52,52,52,52,52,52,5a.Water'evel-Higha.Upsealeb.Inoperativec.ComparatorNANANA6.REACTORCOOLANTSYSTEMRECIRCULATIONFLOMS/U(b),H(b)S/U(b),HS/UQNA5%A'a9
mITABLE4.3.6-1(Continued)CONTROLRODBLOCKINSTRUMENTATIONSURVEILLANCEREUIREMENTSImC)MITRIPFUNCTION7.REACTORMODESMITCHa.ShutdownModeb.RefuelModeCHANNELCHECKNANACHANNELFUNCTIONALTESTCHANNELCALIBRATIONNANAOPERATIONALCONDITIONSFORWHICHSURVEILLANCEREUIRED3,45 ) TABLE4.3.6-1(Continued)%IIi8KPiplfli',P7CONTROLRODBLOCKINSTRUMENTATIONSURVEILLANCEREUIREMENTSNOTES:a.Neutrondetectorsmaybeexc1udedfromCHANNELCALIBRATION.b.Within24hourspriortostartup,ifnotperformedwithintheprevious7days.c.Inc1udesreactormanua1contro1muItip1exingsysteminput.WithTHERMALPOWER>30KofRATEDTHERMALPOWER:Withmorethanonecontro1rodwithdrawn.Notapp1icab1etocontro1rodsremovedperSpecification3.9.10.1or3.9.10.2.NINEMILEPOINT"UNIT23/43-62NOV2u>885
INSTRUMENTATION3/4.3.7MONITORINGINSTRUMENTATIONRADIATIONMONITORINGINSTRUMENTATIONpp~~F8~vvzt.w>LIMITINGCONDITIONFOROPERATION3.3.7.1TheradiationmonitoringinstrumentationchannelsshowninTable3.3.7.1-1shallbeOPERABLEwiththeiralarm/tripsetpointswithinthespecifiedlimits.APPLICABILITY:AsshowninTable3.3.7.1-1.ACTION:a0b.C.Witharadiationmonitoringinstrumentationchannelalarm/tripset-pointexceedingthevalueshowninTable3.3.7.1-1,adjusttheset-pointtowithinthelimitwithin4hoursordeclarethechannelinoperable.Withoneormoreradiationmonitoringchannelsinoperable,taketheACTIONrequiredbyTable3.3.7.1-1.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.3.7.1EachoftheaboverequiredradiationmonitoringinstrumentationchannelsshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsforthecondiionsandatthefrequenciesshowninTable4.3.7.1-1.NINEMILEPOINT-UNIT23/43"63NQV801985
mTABLE3.3.7.1-1RADIATIONMONITORINGINSTRUMENTATIONImINSTRUMENTATIONHINIHUHCMANNELSOPERABLEAPPLICABLECONDITIONSALARH/TRIPSETPOINTACT10N1.HainControlRoomVentilationRadiationMonitors2.AreaMonitorsa.CriticalityHonitor1)NewFuelStorageVaultb.ControlRoomDirectRadiationMonitor1/system"1,2,3,5and""Atalltimes<1.3xlO-spCi/cc<1.0x10~mR/hr~)<2.5x10-~mR/hr747676CDCKCJ'lgcggAe~kQ
TABLE3.3.7.1-1(Continued)RADIATIONMONITORINGINSTRUMENTATIONTABLENOTATIONTwotripsystemsareprovidedwithtwochannelspertripsystem.Aninoperable.ordownscalechannelproducesahighsetpointsignal.Whenhandling,irradiatedfuelinthecontainmentandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.Mithfuelinthenewfuelstoragevault.(a)Initiatescontrolroomemergencyfiltrationwithbothchannelsofonetripsystemathighsetpoint.(b)Alarmonly.(c)Abovemeasuredbackground.NINEMILEPOINT-UNIT23/43-65HOV2,0198S
TABLE3.3.7.1-1(Continued)RADIATIONMONITORINGINSTRUMENTATIONI%00FS>Viet,o~tACTIONACTION72-DeletedACTION73-De1etedACTION74/ACTION75b.MithtwochannelsofonetripsysteminoperablerestoreatleastoneoftheinoperablechannelstoOPERABLEstatuswithin7days,orwithinthenext6hours,ensureoperationofthecontrolroomemergencyfiltrationsysteminthefiltrationmodeofoperation.Mithtwochannelsofbothtripsystemsinoperable,withinonehour,ensureoperationofthecontrolroomemergencyfiltrationsysteminthefiltrationmodeofoperation.DeletedACTION76-Miththerequiredmonitorinoperable,performareasurveysofthemonitoredareawithportablemonitoringinstrumentationatleastonceper24hours.NINEMILEPOINT-UNIT23/43-66NOV2uSaS
foal-TABLE4.3.7.1-1RADIATIONMONITORINGINSTRUMENTATIONSURVEILLANCEREUIREMENTSImClMIINSTRUMENTATION1.MainControlRoomVentilationRadiationMonitors2.AreaMonitorsa.CriticalityMonitors1)NewFuelStorageVaultb.ControlRoomDirectRadiationMonitorCHANNELCHANNELsou~eFUNCTIONALCHECKcoen.TESTssCHANNELCALIBRATIONOPERATIONALCONDITIONSFORMHICHSURVEILLANCEREUIRED1,2,3,5and"1,2,3,4,5epFMCQQat"QtD r' TABLE4.3.7.l-l(Continued)Pi%F5gpppg~gpssRADIATIONMONITORINGINSTRUMENTATIONSURVEILLANCEREUIREMENTSTABLENOTATIONWhenhandlingirradiatedfuelinthecontainmentandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.¹~Pithfuelinthenewfuelstoragevault.NINEMILEPOINT"UNIT23/43-68NOV201905
INSTRUMENTATIONSEISMICMONITORINGINSTRUMENTATIONLIMITINGCONOITIONFOROPERATION~OOAF2MlPr!IPqPII%s4I)ggggjggejgpt3.3.7.2TheseismicmonitoringinstrumentationshowninTable3.3.7.2-1shallbeOPERABLE.APPLICABILITY:Atalltimes.ACTION:aoMithoneormoreoftheaboverequiredseismicmonitoringinstrumentsinoperableformorethan30daysprepareand.submitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2withinthenext10daysoutliningthecauseofthemalfunctionandtheplansforrestoringthei,nstrument(s)toOPERABLEstatus.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS~~~~~~~~~~~~~~4.3.7.2.1EachoftheaboverequiredseismicmonitoringinstrumentsshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNC-TIONALTESTandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.7.2-1.4.3.7.2.2Eachoftheaboverequiredseismicmonitoringinstrumentsactuatedduringaseismiceventgreaterthanorequalto0.01gshallberestoredtoOPERABLEstatuswithin24hoursandaCHANNELCALIBRATIONperformedwithin5daysfollowingtheseismicevent.Oatashallberetrievedfromactuatedinstrumentsandanalyzedtodeterminethemagnitudeofthevibratorygroundmotion.ASpecialReportshallbepreparedandsubmittedtotheCommissionpursuanttoSpecification6.9.2within10daysdescribingthemagnitude,frequencyspectrumandresultanteffectuponunitfeaturesimportanttosafety.NINEMILEPOINT-UNIT23/43-69NOVa0boas
TABLE3.3.7.2-1SEISMICMONITORINGINSTRUMENTATIONBggf$j$P/>pg[n~)gINSTRUMENTSANDSENSORLOCATIONS1.TriaxialTime-HistoryAccelerographsa;,ReactorBldg.Mat.El.175'-0"b.ReactorBldg.RefuelingFloorEI.353'-10"c.ControlBldg.Mat.El.214'-0"12.TriaxialPeakAccelerographsa.DieselGeneratorBldg.ServiceWaterPipingb.Prim.Cont.HighPr.CoreSprayPipingc..Prim.Cont.Recirc.PumpMotor3.TriaxialSeismicSwitchesa.ReactorBldg.Mat.El.175'-0"4.TriaxialResponse-SpectrumRecordersMEASUREMENTRANGE021.0g0t1.0g0f1.0g0-5g~~~0-10gC>)0-10gC.~)0.025-0.25g(adjustable)MINIMUMINSTRUMENTSOPERABLE1(a)a.ReactorBldg.Mat.El.175'-0"b.Prim.Cont.RHRPiping'Pene.El.294'-6"c.ReactorBldg.RefuelingFl.El.353'-10"d.ControlBldg.Mat.El.214'-0"Te(w~(wL5~is,n>c.Macto&-64kg.5~+.pp,('7$'g0~2gQ)0a2gCb022g(b022gCb1(a)111Q.F05-O.o5~1With~~controlroom'nnunciation.Q)5+w4ekageeabLeteruge~e+Libta4<~w~4<~Kgs~~NINEMILEPOINT"UNIT23/43"70~ygOfgg
TABLE4.3.7.2"1nra>~HQ"1'~<<pi~B4$~vggiga)INSTRUMENTSANDSENSORLOCATIONSCHANNELCHANNELFUNCTIONALCHANNELCHECKTESTCALIBRATIONSEISMICMONITORINGINSTRUMENTATIONSURVEILLANCEREUIREMENTS1.TriaxialTime-HistoryAccelerographsa.ReactorBldg.Mat.El.175'-.0"pNA,b.ReactorBldg.RefuelingFl.El.353'-10"c.ControlBldg.Mat.El.214'-0"~ldll2.TriaxialPeakAccelerographsSASASAa.DieselGen.Bldg.ServiceWaterPipingb.Prim.Cont.HighPr.CoreSprayPipingc.Prim.Cont.Recirc.PumpMotor3.TriaxialSeismicSwitches.a.ReactorBldg.Mat.El.175'-0"4.TriaxialResponse-SpectrumRecordersNANANANANANANASARKb)RC>)RCt3+rANANANARCb)RCb)RCW)a.ReactorBldg.Mat.El.175'-0"SAb.Prim.Cont.RHRPipingPene.El.294'-6"c.ReactorBldg.RefuelingFl.El.353'-10"d.ControlBldg.Mat.El.214'-0"Si7f'i4xiA-~Sc%cmic.k4SLkg.let.;15->*SAEg~'on+o~<~<~~0*~~)~~k(ILpgIININEMILEPOINT-UNIT23/43"71HOV201985
INSTRUMENTATIONMETEOROLOGICALMONITORINGINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.7.3ThemeteorologicalmonitoringinstrumentationchannelsshowninTable3.3.7.3-1shallbeOPERABLE.APPLICABILITY:Atal1times.ACTION:aob.]~+syc~l~MithoneormoremeteorologiImonitoringinstrumentationchannelsinoperableformorethan7ays,inlieuofanyotherreportrequiredbySpecification6.9.1,prepareandsubmitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2withinthenext10daysoutliningthecauseofthemalfunctionandtheplansforrestoringtheinstrumentationtoOPERABLEstatus.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.('URVEILLANCEREUIREMENTS4.3.7.3EachoftheaboverequiredmeteorologicalmonitoringinstrumentationchannelsshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECKandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.7.3"1.NINEMILEPOINT-UNIT23/43"72Nay201S85
TABLE3.3.7.3-1Plyj'Fgp'-ppJJgpyMETEOROLOGICALMONITORINGINSTRUMENTATIONINSTRUMENTa.WindSpeedl.Elev.30ft.2.Elev.200ft.b.WindDirectionl.Elev.30ft.2.Elev.200ft.c.AirTemperatureDifference1.Elev.30/200ft.MINIMUMINSTRUMENTSOPERABLENINEMILEPOINT-UNIT23/43-73goy201985
TABLE4.3.7.3"1PP>g~F$Pg<'vl(ng~gMETEOROLOGICALMONITORINGINSTRUMENTATIONSURVEILLANCEREUIREMENTSINSTRUMENTa.WindSpeedl.Elev.30ft.2.Elev.200ft.b.WindOirectionl.Elev.30ft.2.Elev.200ft.c..AirTemperatureOifference1.Elev.30/200ft.CHANNELCHECKCHANNELCALIBRATIONSASASASASANINEMILEPOINT-UNIT23/43-74NOVgg1g8g
INSTRUMENTATIONREMOTESHUTDOWNSYSTEMINSTRUMENTATIONANDCONTROLSLIMITINGCONDITIONFOROPERATION3.3.7.4Theremoteshutdownsysteminstrumentationandcontrols"showninTable3.3.7.4-1shallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONSIand2.ACTION:a.WiththenumberofOPERABLEremoteshutdownsysteminstrumentationchannelslessthanrequiredbyTable3.3.7.4-1,restoretheinope-rablechannel(s)toOPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hours.b.WiththenumberofOPERABLEremoteshutdownsystemcontrolchannelslessthanrequiredbyTable3.3.7.4-1,restoretheinoperablechannel(s)toOPERABLEstatusQlthin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hours.c.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.3.7.4.1Eachoftheaboverequiredremoteshutdownmonitoringinstrumenta-tionchannelsshallbedemonstratedOPERABLEbyperformanceoftheCHANNELCHECKandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.7.4-1.4.3.7.4.2Eachoftheaboveremoteshutdowncontrolswitch(es)andcontrolcircuitsshallbedemonstratedOPERABLEbyverifyingitscapabilitytoperformitsintendedfunction(s)at-1'eastonceper18months.Includestransferswitchesassociatedwithremoteshutdownsystemcontrols.NINEMILEPOINT-UNIT23/43"75NOV30j985
TABLE3.3.7.4-1PggoFgPPtPy~OPREMOTESHUTDOWNMONITORINGINSTRUMENTATIONINSTRUMENT1.ServiceWaterPumpDischFlow(6)2.ReactorVesselPressure(2)3.RXVesselWaterLevelWideRange(2)4.RXVesselWaterLevelNarrowRange(2)5.RXVesselShellFlg.Temp.(1)6.RXVesselBottomHeadTemp.(1).7.RCICTurbineSpeed(1)8.SuppressionPoolWaterLevel(2)9.CST"A"Level(1)10.CST"B"Level(1)~vtt5-w4-'T~11.RHRLoop"A"ow112.RHRHT..EX.'A'low(1)13.RHRHT.EX."A"ServiceWaterOutletTemp.(1)14.RHRHT.EX."A"In/OutTemp.(1).15.SuppressionPoolTemp.(2)16.RHRHT.EX."B"ServiceWaterOutletTemp.(1)17.RHR'HT.EX."B"In/OutTemp.(1)18.RHRLoop"B"Flow(1py~~ic.e'~YE~19.RHRHT.EX."BFlow20.RHRDischargeTemp.toRadwaste(1)21.ADSAcc.TankNo.32Pressure(1)22.ADSAcc.TankNo.33Pressure(1)23.ADSAcc.TankNo.38Pressure(1)24.ADSAcc.TankNo.35Pressure(1)25.Safety/ReliefValvePosition(4Valves)READOUTLOCATION2CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL405ZCES"PNL4052CES"PNL4052CES"PNL4052CES"PNL405ZCES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL405MINIMUMINSTRUMENTSOPERABLE2/Division11111111111*..111111'1111111/valveNINEMILEPOINT-UNIT23/43-76NQV201985
Table3.3.7.4-1(Continued)REMOTESHUTDOWNSYSTEMCONTROLS""'ltF<iYHiPZgt"Q'ystem/Subsystems"1.RCICSystem2.RHRSystemA.ShutdownCoolingModeB.SuppressionPoolCoolingMode3.ServiceWaterSystemMinimumOperableSystems/SubsystemsSystems/SubSys.4.A.PumpsB..SupplyValvestoOivI8DivIIDieselsAOSSystem(PressureRelief)5."NuclearSteamSupplyShutoffSystem(IsolationGroups485Reset)6.NitrogenSupplytoADSAccumulatorTanks61/Div4Valves/Oiv1/Oiv1/Div21/Oiv4Valves1/Div1/Div"IncludesApplicableTransferSwitchesNINEMILEPOINT-UNIT2'3/43-77NOV2O1985
TABLE4.3.7.4"1Pilg3F'$pfjpg@pi~REMOTESHUTDOWNMONITORINGINSTRUMENTATIONSURVEILLANCECHANNELINSTRUMENTCHECKREUIREMENTSCALIBRA-TIONREADOUTLOCATIONl.2.3.5.6.7.8.9.10.11.1Z.13.-"'l4;15.16.-17.18.19.,20.~~2.3.24.25.ServiceWaterPumpDischFlow(6)ReactorVesselPressure(2)RXVesselWaterLevelWideRange(2)RXVesselWaterLevel'NarrowRange(2)RXVesselShellFlg.Temp.(1)RXVesselBottomHeadTemp.(1)RCICTurbineSpeed(1)SuppressionPoolWaterLevel(2)CST"A"Level(1)RHRLoop"A"low1RHRHT.EX."AW~;-Flow(1)RHRHT.EX."A"ServiceWaterOutletTemp.(1)RHRHT.EX;"A"In/OutTemp.(1)SuppressionPoolTemp.(2)RHRHT.EX."B"ServiceWaterOutletTemp.(1)RHRHT.EX."B"In/OutTemp.(1)RHRLoop"B"low1gglEoicsw*MKRHRHT.EX."BtFlowRHRDischargeTemp.toRadwaste(1)ADSAcc.TankNo.32Pressure(1).,ADSAcc.TankNo.33Pressure(1)ADSAcc.TankNo.38Pressure(1)ADSAcc.TankNo.35Pressure(1)Safety/ReliefValvePosition(4Valves)MMMMMMMMMMMMMMMMMMMMMMMMMRRRRRRRRRRRRRRR)tA'RRRRRRRRR"i2CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CESAPNL4052CES"PNL4052CESAPNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL4052CES"PNL405CHANNLcalibrationisdoneperSpec.4.4.2""CHANNELcalibrationexcludessensors;sensorcomparisonshallbedoneinsensorcalibration.lieuofNINEMILEPOINT-UNIT23/43-78NOV201985
INSTRUMENTATIONACCIDENTMONITORINGINSTRUMENTATION4IWA,gqgjjfPgP/LIMITINGCONDITIONFOROPERATION3.3.7.5TheaccidentmonitoringinstrumentationchannelsshowninTable3.3.7.5-1shallbeOPERABLE.APPLICABILITY:AsshowninTable3.3.7.5-1.ACTION:Withoneormoreaccidentmonitoringinstrumentationchannelsinoperable,taketheACTIONrequiredbyTable3.3.7.5-1.SURVEILLANCEREUIREMENTS4.3;7.5EachoftheaboverequiredaccidentmonitoringinstrumentationchannelsshallbedemonstratedOPERABLEbyperformanceoftheCHANNELCHECKandCHANNELCALIBRATIONoperationsatthefrequenciesshowninTable4.3.7.5-1.NINEMILEPOINT"UNIT23/43"79gOV80lSS5
TABLE3.3.7.5-1ACCIDENTMONITORINGINSTRUMENTATIONC)00CÃ)CJlMITTICDCol47ICOEDINSTRUMENT1.ReactorVesselPressure2.ReactorVesselMaterLevel3.SuppressionPoolMaterLevel4.SuppressionPoolWaterTemperature5.SuppressionChamberAirTemperature6.DrywellPressure7.DrywellAirTemperature8.DrywellOxygenConcentration9.DrywellHydrogenConcentrationAnalyzerandMonitor10.Safety/ReliefValvePositionIndicators11.DrywellHighRangeRadiationMonitors12.RHRHeatExchangerServiceMaterRadiationMonitor13.RefuelPlatformAreaRadiationMonitorINREQUIREDNUMBEROFCHANNELS2MINIMUMCHANNELSOPERABLEAPPLICABLEOPERATIONALCONDITIONS1,2,31,2,312.38,2/quadrant4,1/quadrant1,2,32/valve1/valve1,2,31,2,31,2,31,2,31,2,31,2,31,2,31,2,C-3IgC.>L"J1/HeatExchanger1/HeatExchanger11ACTION80808080808080808080818182
Table3.3.7.5-1(Continued)ACCIDENTMONITORINGINSTRUMENTATIONPPggF~>ppPp>]pryACTIONSTATEMENTSp...Qwk."Whenhandlingnewfuel,irradiatedfuel,orirradiatedcomponentsinthefuelpoolorreactorcavity.ACTION80-a.WiththenumberofOPERABLEaccidentmonitoringinstrumentationchannelslessthantheRequiredNumberofChannelsshowninTable3.3.7.5-1,restoretheinoperablechannel(s)toOPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hours.b.Withthenumberof,OPERABLEaccidentmonitoringinstrumentationchannelslessthantheMinimumChannelsOPERABLErequirementsofTable3.3.7.5-1,restoretheinoperablechannel(s)toOPERABLEstatus'ithin48hoursorbeinat.leastHOTSHUTDOWNwithinthenext12hours.ACTION81-WiththenumberofOPERABLE'accidentmonitoringinstrumentationchannelslessthanrequiredbytheMinimumChannelsOPERABLErequirement,eitherrestoretheinoperablechannel(s)toOPERABLEstatus'within72hours,or:a.Initiatethepreplannedalternatemethodofmonitoringtheappropriateparameter(s),andb.InlieuofanotherreportrequiredbySpecification6.9.2,prepareandsubmitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2within14daysfollowingtheeventoutliningtheactiontaken,thecauseoftheinoperabilityandtheplansandscheduleforrestoringthesystemtoOPERABLEstatus.ACTION82-WiththenumberofOPERABLEaccidentmonitoringinstrumentaitonchannelslessthantheMinimumChannelsOPERABLErequirementsofTable3.3.7.5-1,suspendmovementofirradiatedcomponentsinthefuelpoolorreactorcavity,or,initiatethepreplannealternatemethodofmonitoringtheappropriateparameter(s).NINEMILEPOINT-UNIT23/43-81NOV801985
-TABLE4.3.7.5-1ACCIDENTHONITORINGINSTRUMENTATIONSURVEILLANCEREUIREHENTSINSTRUMENTCHANNELCHECKCHANNELCALIBRATIONAPPLICABLEOPERATIONALCONDITIONSCIMIl.ReactorVesselPressure~H2.ReactorVesselMaterLevelH3.SuppressionPoolWaterLevelH4.SuppressionPoolWaterTemperatureH5.SuppressionChamberAirTemperatureH6.DrywellPressureH7.DrywellAirTemperatureH8.DrywellOxygenConcentrationH9.DrywellHydrogenConcentrationAnalyzerandMonitorH10.Safety/ReliefValvePositionIndicatorsH11.DrywellHighRangeRadiationMonitorsH12.RHRHeatExchangerServiceMaterRadiationHonitorH13.RefuelPlatformAreaRadiationHonitorHRRRR8R8RR0RQA'ARR*AARR121,21>>21,21,21,2121,21,2121>>2>>3EA>>00POMhenhandlingnewfuel,irradiatedfuelorirradiatedandunirradiatedcomponentsinthefuelpoolorreactorcavity.AAUsingsamplegascontaining:a.Onevolumepercenthydrogen,balancenitrogen.b.Fourvolumepercenthydrogen,balancenitrogen.*TheCHANNELCALIBRATIONshallconsistofanelectroniccalibrationofthechannel,notincludingthedetector,forrangedecadesabove10R/hrandaonepointcalibrationcheckofthedetectorbelow10R/hrwithaninstalledorportablegammasource.Excludessensors;sensorcomparisonshallbedoneinlieuofsensorcalibration.~leig
INSTRUMENTATIONSOURCERANGEMONITORSLIMITINGCONDITIONFOROPERATIONP~r6Ã5PPJ'P~gPV3.3.7.6AtleastthefollowingsourcerangemonitorchannelsshallbeOPERABLE:a.InOPERATIONALCONDITION2",threeb.InOPERATIONALCONDITION3and4,two.APPLICABILITY:OPERATIONALCONDITIONS2",3and4.ACTION:a.InOPERATIONALCONDITION2"withoneoftheaboverequiredsourcerangemonitorchannelsinoperable,restoreatleast3sourcerangemonitorchannelstoOPERABLEstatuswithin4hoursorbeinatleastHOTSHUTDOWNwithinthenext12hours.b..InOPERATIONALCONDITION3or4withoneormoreoftheaboverequiredsourcerangemonitorchannelsiaoperable,verifyallinsertablecontrolrodstobeinsertedinthecoreandlockthereactormodeswitchintheShutdownpositionwithin.onehour.SURVEILLANCEREUIREMENTS4.3.7.6EachoftheaboverequiredsourcerangemonitorchannelsshallbedemonstratedOPERABLEby:a.Performanceofa:1.CHANNELCHECKatleastonceper:a)12hoursinCONDITION2",andb)24hoursinCONDITION3or4.b.C.2.CHANNELCALIBRATION""atleastonceper18months.PerformanceofaCHANNELFUNCTIONALTEST:1.Within24hourspriortomovingthereactormodeswitchfromtheShutdownposition,ifnotperformedwithintheprevious7days,and2.Atleastonceper31days.Verifying,priortowi$hdrawalofcontrolrods,thattheSRMcountrateisatleast3cpswiththedetectorfullyinserted.WithIRMsonrange2orbelow""NeutrondetectorsmaybeexcludedfromCHANNELCALIBRATION.¹Forinitialloadingandsgygtupthecountratemaybelessthan3cpsifthefollevingconditionsare~;(1)thesignaltonoiseratioisgreaterthan2.~2)thesignalisgreaterthan0.7cps,NINEMILEPOINT-UNIT23/43"83H0VaOle85
INSTRUMENTATIONTRAVERSINGIN-COREPROBESYSTEMLIMITINGCONDITIONFOROPERATION3.3.7.7Thetraversingin"coreprobesystemshallbeOPERABLEwith:a.Fivemovabledetectors,drivesandreadoutequipmenttomapthecore,andb.Indexingequipmenttoallowallfivedetectorstobecalibratedinacommonlocation.APPLICABILITY:Whenthetraversingin-coreprobeisusedfor:a.RecalibrationoftheLPRMdetectors,andb.",MonitoringtheAPLHGR,LHGR,MCPR,orMFLPD.'ACTION:Withthetraversingin-coreprobesysteminoperable,suspenduseofthesystemfortheaboveapplicablemonitoringorcalibrationfunctions.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.3.7.7Thetraversingin-coreprobesystemshallbedemonstratedOPERABLEbynormalizingeachoftheaboverequireddetectoroutputswithin72hourspriortousefortheLPRMcalibrationfunctions.Onlythedetectors)intherequiredmeasurementlocation(s)arerequiredtobeOPERABLE.NINEMILEPOINT"UNIT23/43"84NOV201S85
INSTRUMENTATIONFIREDETECTIONINSTRUMENTATIONLIMITINGCONDITIONFOROPERATIONI>Igl'Pgj>:'.JgiLUPI/thanonehalfthettal>nanyf1rezone,Functionfiredetectioninstrumentsshownin+Qble3.3.7.8-1inoperable,restoretheinoperableFunction+'Vnstrument(s)toOPERABLEstatuswithin14daysorwithin1hourestablishafirewatchpatroltoinspectthezone(s)withtheinoperableinstrument(s)atleastonceperhour.Withmorethanone-halftheFunction~firedetectioninstruments'nanygir~~neshowninTable3;3.7.8-1inoperableorwithanyFunc-tio5~iMrumentsshowninTable3.3.7.8-1inoperable,orwithanytwoormoreadjacentinstrumentsshowninTable3.3.7.8-1inoperable,within1hourestablishafirewatchpatroltoinspectthezone(s)withtheinoperableinstrument(s)atleastonceperhour.b.c.TheprovisionsofSpecifications3.0.3and3.0.4are-not-applicabl.SURVEILLANCEREUIREMENTS3.3.7.8Asaminimum,thefiredetectioninstrumentationforeachfiredetectionzoneshowninTable3.3.7.8-1shallbeOPERABLE.APPLICABILITY:Wheneverequipmentprotectedbythefiredetectioninstrument1srequiredtobeOPERABLE.ACTIONa.Withanutnotmore04.3.7.8.1EachoftheaboverequiredfiredetectioninstrumentswhichareaccessibleduringunitoperationshallbedemonstratedOPERABLEatleastonceper6monthsbyperformanceofaCHANNELFUNCTIONALTEST.FiredetectorswhicharenotaccessibleduringunitoperationshallbedemonstratedOPERABLEbythe.performanceofaCHANNELFUNCTIONALTESTduringeachCOLDSHUTDOWNexceeding,24hoursunlessperformedintheprevious6months.4.3.7.8.2TheNFPAStandard72DsupervisedcircuitssupervisionassociatedwiththedetectoralarmsofeachoftheaboverequiredfiredetectioninstrumentsshallbedemonstratedOPERABLEatleastonceper6months.4.3.7.8.3Thenon-supervisedcircuitsassociatedwithdetectoralarmsbetweentheinstrumentsandthecontrolroomshallbedemonstratedOPERABLEatleastonceper31days.o,gofouuJ'<etk+ouI'LI'~~+pssgwAkiaggt46LG~xpl~><+Qa+~Qq+d~~bLc3.7,3-I.NINEMILEPOINT-UNIT23/43"85gGV20l985 0 TABLE3.3.7.8-1P(<03Fgj'.Ii,'p'fl,',I3yyINSTRUMENTLOCATION2FireZone"RoomorAreaE1evIonizationPhoto-E1ectricHeatReactorBui1din/AuxiliarBasFIREOETECTIONINSTRUMENTATIONTOTALNUMBEROFINSTRUMENTS"*201SMCCPHTXCH4LPCSPumpRoom202SMRHRPumpARoom203SWRHRHTXCHARoom204SMRCICPumpRoom205NZHPCSPumpRoom~c:.":::-206SWRHRHTXCHBRoom2207SMRHRPumpBRoom208SMRHRPumpCRoom21222Jl213SMGenAreaSouth211SWNAuxBayAbovePumpRooms214SWSAuxBayAbovePumpRooms221SWNAuxBayAbovePumpRooms222SWGenArea0"180223SWGenArea180'-360224SWSAuxBayAbovePumpRooms231SWNAuxBayE1ectMCCArea232SMGenAreaOo-180o238SWGenArea180"360'75'-0"NA175'-0"NA175'"0"NA175'-0"6175'-0"NA175'-0"NA175'-0"NA~175'-0"NAIOll13196'-0"175'-0"20196'-0198'-0"NA198'"0"NA215'0"NA215'0"NA215'-0"NA215'"0"NA240'-0"NA240I"0"5240'"1163435222228393925313232NANANANANANA.NANANANANINEMILEPOINT"UNIT23/43"86NOV201985
TABLE3.3.7.8-1ContinuedFIREDETECTIONINSTRUMENTATIONFiMiilF~p~J'pff'fpgINSTRUMENTLOCATIONTOTALNUMBEROFINSTRUMENTS""FireZone*RoomorAreaElevHeatIonizationPhoto-ElectricReactorBuildin/AuxiliaBas(cont)239SWS.AuxBayElect'CCArea243SWGenArea0-180245SWGenArea180o-360o'I252SWGenAreaOo180o253XLE1ectLoadCenterRoom255SW'enArea180-360240'-0"NA261'-0"5261'-0"2289'-0"4289'-0"NA289I-0"429383739NANANA261NZ262HZ271SW272SW273SW274SW281HZPipeChaseGenArea180'-360'enAreaOo90o-GenArea27"360GenArea90-180GenArea180"270GenArea0"360306'"OI'4306'-0"NA328'-10"NA328'-10"NA328'"10"NA328'-10"NA353'-10"NA261915NANANANAControlBuildin305NW306NW307HZ308HZ309NW310HZOivIRizerArea=-~OivICableArea24VBatteryRoom24VBatteryRoomDivIICableChaseRecordsRoom214'0"NA214'0"NA214'-0~'A214'"0"NA214'-0"NA214'-0"NANANANA311NZComputerBatteryRoom214'-0"HANA312NWDivIICableArea214'"0"HANINEMILEPOINT-UNIT23/43-87NOV20)gag
TABLE3.3.7.8-1ContinuedFIREDETECTIONINSTRUMENTATION58gFgp~f'p'fgpyINSTRUMENTLOCATIONTOTALNUMBEROFINSTRUMENTS*"FireZone"RoomorAreaElevHeatIonizationPhoto-Electric322NM323NW324NW325NMOivICableAreaOivIICableArea.5DivIIRiperAreaOivICableArea~C1Bl1di().5'21NMDivIRiperArea237I"0"NA237'-0"NA237'-0"NA237'-0"NA2373-0"NA15NANANA326NW327NM331NW332NW333XL'OivIICableAreaDivIIICableAreaCorridorOivICableChase237'-0"NA237'-0"NA.261I-OI'A.261'O'INADivISwitchgearRoom261'-0"NA207NANANA334NZ335NZ336XL~337NWDivIBatteryRoomDivIIBatteryRoomDivIISwitchgearRoomOivIIandIIICable,Chase261'-0"NA261'-0"NA261'-0"NA261'"0"NANANANA'A338NZRemoteShutdownRoomB261'-0"NA340NZ341NZDivIChillerRoomOivIIChillerRoom339NZHPCSBatteryRoom261'-0"NA261'-0"NA261I-0"NANANA342XL343NZOivIIISwitchgearRoom261'-0"NARemoteShutdownRoomA261'-0"NANANA351NZInstrumentRoomandCorridor288'-6"NA17.NANINEMILEPOINT-UNIT23/43-88NOV20]985
TABLE3.3.7.8-1ContinuedPPlgjjf~tppj:l~$ggpf/INSTRUMENTLOCATIONFIREDETECTIONINSTRUMENTATIONTOTALNUMBEROFINSTRUMENTS~"FireZone"RoomorArea~C)B))di))352QIDivICableChase353SGRelayRoom354SGRelayRoom356NZRelayRoom357XGComputerRoom358XGComputerRoomf359NMDivIIandIIICableChaseElevHeat288'-6I'A288'-6"50288'"6"50288'"6"HA~288'"6"NA288'"6"HA288'-6"NA106120+)+NANANANAIonizationPhoto-Electric362SG371HM3?3NZ374SG375SG376SG37?NW378NZ380NZRelayRoomDivICableChaseControlRoomControlRoomControlRoomControlRoom'ivIIandIIICableChaseHYACEquipmentRoomInstrumentRoomandCorridor381SGControlRoomDieselGeneratorBuildin360HZHYACEquipmentRoom288'"6"HA288'-6"40306'"OI'306'-OIINA'06'-0"43306'-0"44306'"0"NA306'"0"NA306'-0"HA306'-0"NA306'-0"6272751388NANANANANAHANANANA400NZ401HZDivI,II,andIIIDayTankRoomDivI,II,andIIIControlRoom272'-OIINA261'0"HANANANINEMILEPOINT-UNIT23/43-89NOV301985
TABLE3.3.7.8-1ContinuedFIREDETECTIONINSTRUMENTATIONP~MF8RVptpgpyINSTRUMENTLOCATIONFireZone"RoomorAreaDieselGeneratorBuildin(cont)ElevHeatIonizationPhoto-ElectricTOTALNUMBEROFINSTRUMENTS""402SWDivID/GRoom403SWDivIID/GRoom404SWHPCSD/GRoomElectricalTunnels301NW140'unnel302NW35Tunnel303NW.315'unnel'304NW'230Tunnel236NZ.DivIHVACRoom237HZDivIIHVACRoomServiceWaterPumBas806HZDivIPumpBay807NZDivIIPumpBay~Fidd804NWDieselEngineFirePumpRoom805HZElectMotorFirePumpRoomStandbGasTreatmentRooms247HZDivIGTSRoom248NZDivIIGTSRoomSteamTunnel'256NZSteamTunnel261'-0"NA261'-0"NA261'-0"NA215'-0"NA215'0"NA215'-0"NA215'-0"NA237'wNA237'-0"NA244'"0"NA244'-0"NA261'-0"NA261'-0"NA261'"0"NA261'0"NA240'"0"9NA23159NANANANANANAdidd-i*i*iid:d.actuationoffiresuppression;N,noactuationoffiresuppression;andX,actuationoffiresuppression(HalonandC02only)providedonedetectoristrippedineachoftwoloops.Thesecondletterdenotes:W-water;L-lowpressureC02;G-Halon,Z-nothing;andF-Foam.""Inthecaseforafirezonewhichcontainstwofiredetectionloops(denotedbyanXinthefirezonedesignation)thenumberlistedisthetotalnumberofdectectorsinbothloops.NINEMILEPOINT-UNIT23/43"90goy3e>9S5
INSTRUMENTATIONLOOSE"PARTDETECTIONSYSTEMLIMITINGCONDITIONFOROPERATIONPl'a~FQf~~pf[Pp>/3.3.7.9Theloose-partdetectionsystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTIONa.kithoneormoreloose-partdetectionsystemchannelsinoperableformorethan30days,prepareandsubmitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2withinthenext10daysoutliningthecauseofthemalfunctionandtheplansforrestoringt:hechannel(s)toOPERABLEstatus.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.3.7.9Eachchanneloftheloose-partdetectionsystemshallbedemonstratedOPERABLEbyperformanceofa:a.CHANNELCHECKatleastonceper24hours,b.Onceevery7days,listentotheaudiooutput,c.CHANNELFUNCTIONALTESTatleastonceper31days,d.Onceevery92days,verifythebackgroundnoise,ande.CHANNELCALIBRATIONatleastonceper18months.NINEMILEPOINT-UNIT23/43-91NOV001SSS
INSTRUMENTATION~4a~RADIOACTIVELIUIDEFFLUENTMONITORINGINSTRUMENTATION4@pe>)pgpgLIMITINGCONDITIONFOROPERATION3.3.7.10TheradioactiveliquideffluentmonitoringinstrumentationchannelsshowninTable3.3.7.10-1shallbeOPERABLEwiththeiralarm/tripsetpointssettoensurethatthel.imitsofSpecification3.1l.l.larenotexceeded.Thealarm/tripsetpointsofthesechannelsshallbedeterminedandadjustedinaccordancewiththemethodologyandparametersintheOFFSITEDOSECALCULATIONMANUAL(ODCM).APPLICABILITY:AtalltimesACTION':a.Witharadioactiveliquideffluentmonitoringinstrumentationchannelalarm/tripsetpointlessconservativethanrequiredbytheabove.specification,withoutdelaysuspendthereleaseofradioactiveliquideffluentsmonitoredbytheaffectedchannel,ordeclarethechannelinoperable,orchangethesetpointsoitisacceptablyconservative.b.Withthenumberof'channelsOPERABLElessthantheMinimumChannelsOPERABLErequirement,taketheACTIONshowninTable3.3.7.10"1.RestoretheinstrumentstoOPERABLEstatuswithin30daysand,ifunsuccessful,explainin.thenextSemiannualRadioactiveEffluentReleaseReportwhytheinoperabilitywasnotcorrectedinatimelymanner.c.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS:.4.%7.10EachradioactiveliquideffluentmonitoringinstrumentationchannelshallbedemonstratedOPERABLEbyperformanceoftheCHANNELCHECK,SOURCECHECK,CHANNELCALIBRATIONandCHANNELFUNCTIONALTESTatthefrequenciesshown4pTable4.3.7.10-1.NINEMILEPOINT-UNIT23/43-92NOV801985
TABLE3.3.7.10-1RADIOACTIVELIUIDEFFLUENTMONITORINGINSTRUMENTATIONINSTRUMENT1.RadioactivityMonitorsProvidingAlarmandAutomaticTerminationofReleasea.Liquidradwasteeffluentline2.RadioactivityMonitorsProvidingAlarmButNotProvidingAutomaticTerminationofReleasea.ServicewatereffluentlineAb..ServicewatereffluentlineBc.Coolingtowerblowdownline3.FlowRateMeasurementDevicesa.Liquidradwasteeff'luentlineb.Servicewatereffluent'.ineAc.ServicewatereffluentlineBd.Coolingtowerblowdownl.ine4.TankLevelIndicatingDevices"MINIMUMCHANNELSOPERABLEACTIDN130130130131131131131132Tanksincludedinthisspecificationarethoseoutdoortanksthatarenotsurroundedbyliners,dikes,orwallscapableofholdingthetankcontentsanddonothavetankoverflowsandsurroundingareadrainsconnectedtotheliquidradwastetreatmentsystem,suchastemporarytanks.NINEMILEPOINT"UNIT23/43-93goy201985
TABLE3.3.7.10"1ContinuedTABLENOTATIONNQFi5~ZRPNMPY:ACTION128"WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,effluentreleasesmaycontinueprovidedthatpriortoinitiatingarelease:a.AtleasttwoindependentsamplesareanalyzedinaccordancewithSpecification4.11.1.1.1,andb.AtleasttwotechnicallyqualifiedmembersoftheFacilityStaffindependentlyverifythereleaseratecalculationsanddischargelinevalving;Otherwise,suspendreleaseofradioactiveeffluentsviathispcs<>>tz.c-g~"'~pathway.ACTION130-With'thenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedthat,atleastonceper12hours,grabsamplesarecollectedandanalyzedforradioac-tivityatalimitofdetectionofatleast10-~microcuries/ml.ACTION131-WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedtheflowrateisestimatedatleastonceper4hoursduringactualreleases.Pumpperformancecurvesgeneratedinplacemaybeusedtoestimateflow.ACTION132-Withthenumberofchanne'lsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,liquidadditionstothistankmaycontinueprovidedthetankliquidlevelisestimatedduringallliquidadditionstothetank.NINEMILEPOINT-UNIT23/43-94
MmTABLE4.3.7.10-1RADIOACTIVELIUIDEFFLUENTHONITORINGINSTRUHENTATIONSURVEILLANCEREUIREHENTSC)MICMINSTRUHENT1.RADIOACTIVITYHONITORSPROVIDINGALARHANDAUTOMATICTERHINATIONOFRELEASEa.LiquidRadwasteEffluentLine2.RADIOACTIVITYHONITORSPROVIDINGALARHBUTNOTPROVIDINGAUTOMATICTERHINATIONOFRELEASECHANNELCHECKP"R(c)SOURCECHANNELCHECKCALIBRATIBHCHANNELFUNCTIONALTESTSA(')RABUla.ServiceMaterEffluentLineAb.ServiceMaterEffluentLineBc.CoolingTowerBlowdownLine3.FLOWRATEHEASUREHENTDEVICES(4)a.LiquidRadwasteEffluentLineb.ServiceWaterEffluentLineAc.ServiceMaterEffluentLineBd.CoolingTowerBlowdownLine4.TANKLEVELINDICATINGDEVICES"DD(d)D(d)D(d)D(d)NAR(c)R(c)R(c),A(b)SA(b)BdbIIP%A~I~@~IKAM3CICCOPn"Tanksincludedinthisspecificationarethoseoutdoortanksthatarenotsurroundedbyliners,dikesorwallscapableofholdingthetankcontentsanddonothavetankoverflowsandsurroundingareadrainsconnectedtotheliquidradwastetreatmentsystem,suchastemporarytanks."*Duringliquidadditionstothetank.
TABLE4.3.7.10"1(ContinuedlRf3PW0P}~lap<qte~~qyTABLENOTATIONS(a)TheCHANNELFUNCTIONALTESTshallalsodemonstratethatautomaticisolationofthispathwayandcontrolroomalarmannunciationoccursiftheinstrumentindicatesmeasuredlevelsabovetheAlarm/TripSetpoint.(b)TheCHANNELFUNCTIONALTESTshallalsodemonstratethatcontrolroomalarmannunciationoccursifanyofthefollowingconditionsexists:(1)InstrumentindicatesmeasuredlevelsabovetheAlarmSetpoint,or(2)Circuitfailure,or(3)Instrumentindicatesadownscalefailure,or(4)Instrumentcontrolsnotsetinoperatemode.(c)TheCHANNELCALIBRATIONshallbeperformedusingoneormoreoftherefer-encestandardscertifiedbytheNationalBureauofStandards,standardsthataretraceabletotheNationalBureauofStandards,orusingactualsamplesofliquideffluentsthathavebeenanalyzedonasystemthathas.beenca1ibratedwithNationalBureauofStandardstraceablesources.Thesestandardsshallpermitcalibratingthesystemoveritsintendedrangeofenergyandmeasurement.ForsubsequentCHANNELCALIBRATION,sourcesthathavebeenrelatedtotheinitialcalibrationmaybeused.(d)CHANNELCHECKshallconsistofverifyingindicationofflowduringperiodsofrelease.CHANNELCHECKshallbemadeatleastonceper24hoursondaysonwhichcontinuous,periodic,orbatchreleasesaremade.,NINEMILEPOINT-UNIT23/43-96g(}y201985
INSTRUMENTATIONRADIOACTIVEGASEOUSEFFLUENTMONITORINGINSTRUMENTATIONpgf'$pp~gqp<~g~pyLIMITINGCONDITIONFOROPERATION3.3.7.11TheradioactivegaseouseffluentmonitoringinstrumentationchannelsshowninTable3.3.7.ll-1shallbeOPERABLEwiththeiralarm/tripsetpointssettoensurethatthelimitsofSpecification3.11.2.1arenotexceeded.Thea1arm/tripsetpointsofthesechannelsshallbedeterminedandadjustedinaccordancewiththemethodologyandparametersintheODCM.APPLICABILITY:AsshowninTable3.3.7.1l-l.ACTION:aob.C.Witharadioactivegaseouseffluentmonitoringinstrumentationchannelalarm/tripsetpointlessconservativethanrequiredbytheabovespec-ification,withoutdelaysuspendthereleaseofradioactivegaseouseffluentsmonitoredbytheaffectedchannel,ordeclarethechannelinoperable,orchangethesetposntsoitisacceptablyconservative.WiththenumberofchannelsOPERABLElessthantheMinimumChannelsOPERABLErequirement,,taketheACTIONshowninTable3.3.7.11-1.RestoretheinstrumentstoOPERABLEstatuswithin30daysand,ifunsuccessful,explaininthenextSemiannualRadioactiveEffluentReleaseReportwhytheinoperabilitywasnotcorrectedinatimelymanner.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.3.7.11EachradioactivegaseouseffluentmonitoringinstrumentationchannelshallbedemonstratedOPERABLEbyperformanceoftheCHANNELCHECK,SOURCECHECK,CHANNELCALIBRATIONandCHANNELFUNCTIONALTESToperationsatthefrequenciesshowninTable4.3.7.11-1.NINEMILEPOINT"UNIT23/43"97NOV201985
TABLE3.3.7.11"1P~g~~I:gg>pp[gayRADIOACTIVEGASEOUSEFFLUENTMONITORINGINSTRUMENTATIONINSTRUMENT1.OFFGASSYSTEMa.NobleGasActivityMonitor-ProvidingAlarmandAutomaticTerminationofReleaseb.SystemFlowRateMeasuringDevicec.SamplerflowRateMeasuringDevice2.OFFGASSYSTEMEXPLOSIVEGASMONITORINGSYSTEM"""a.HydrogenMonitorTrainA(Instrument20FG-AT-16Aor20FG-AT"115)b.HydrogenMonitorTrainB(Instrument20FG-AT-16Bor20FG-AT-115)3.RADMASTE/REACTORBUILDINGVENTEFFLUENTa.NobleGasActivityMonitor¹b.IodineSamplerc.ParticulateSamplerd.FlowRateMonitore.SamplerFlowRateMonitor4.MAINSTACKEFFLUENTa.NobleGasActivityMonitor¹b.IodineSamplerc.ParticulateSampler~d.FlowRateMonitore.SamplerFlowRateMonitorMINIMUMCHANNELSAPPLICA-OPERABLEBILITYACTION136135135137137139138138135135139138138135135NINEMILEPOINT"UNIT23/43-98NOY201985
TABLE3.3.7.11-1ContinuedTABLENOTATION"Atalltimes.""Duringoffgassystemoperation.""*Onlyonetrainrequiredtobeinoperation.ACTION135-WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedtheflowrateisestimatedatleastonceper4hours.ACTION136-ACTION137-/ACTION138-WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedgrabsamplesaretakenat'eastonceper12hoursandthesesamplesareanalyzedforgrossactivitywithin24hours.WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirementoperationoftheoffgassystemmaycontinueprovidedgrabsamplesarecollectedatleastonceper4hoursandanalyzedwithinthefollowing4hours.WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedsamplesarecontinuouslycollectedwithauxiliarysamplingequipmentasrequiredinTable4.11-2.ACTION139"a.WiththenumberofchannelsOPERABLElessthanrequiredby'theMinimumChannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedgrabsamplesaretakenatleastonceper12hoursandthesesamplesareanalyzedforgrossactivitywithin24hours.b.Restorethe..inoperablechannel(s)toOPERABLEstatuswithin72orinlieuofanotherreportrequiredbySpecifica-1on6.9.1,prepareandsubmitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2within14daysfollowingtheeventoutliningtheactiontaken,thecauseoftheinoperabilityandthescheduleforrestoringthesystemtoOPERABLEstatus.400<~gNINEMILEPOINT-UNIT23/43"99NOV201985
TABLE4.3.7.11-1'ADIOACTIVEGASEOUSEFFLUENTHONITORINGINSTRUMENTATIONSURVEILLANCEREUIREHENTSINSTRUMENTl.OFFGASSYSTEMCHANNELMODESINWHICHCHANNELSOURCECHANNELFUNCTIONALSURVEILLANCECHECKCIIEK'CAIIEETICIITESTEEIEEIEEE'.,C.IodineSamplerParticulateSamplerd.FlowRateMonitore.SamplerFlowRateHonitora.NobleGasActivityHonitor-ProvidingAlarmandAutomaticTerminationofRelease.Db.SystemFlowMeasuringDeviceDc.SamplerFlowRateMeasuringDeviceD2.OFFGASSYSTEHENPLOSIVEGASMONITORINGSYSTEMa.HydrogenMonitorTrainAb.HydrogenMonitorTrainB3.RADWASTE/REACTORBUILDINGVENTEFFLUENTSYSTEHa.NobleGasActivityMonitorR(c)O(d)R(c)SA(a,b)SASAq(b)C.aQeIQeg
MfllTABLE4.3.7.11-1(Continued)RADIOACTIVEGASEOUSEFFLUENTMONITORINGINSTRUMENTATIONSURVEILLANCEREUIREMENTS,MmINSTRUMENTCHANNELSOURCECHANNELCHECKCHECK'ALIBRATIONCHANNELMODESINWHICHFUNCTIONALSURVEILLANCETESTEEIEETEEECMIWC)4.MAINSTACKEFFLUENTa.NobleGasActivityMonitorb.IodineSamplerc.ParticulateSamplerd.FlowRateMonitore.SamplerFlowRateMonitorDR(c)q(b)ClC5CDOOVl
TABLE4.3.7.11-1ContinuedTABLENOTATION"Atalltimes.""Duringoffgassystemoperation.(a)TheCHANNELFUNCTIONALTESTshallalsodemonstratethatautomaticisolationofthispathwayandcontrolroomalarmannunciationoccursiftheinstrumentindicatesmeasuredlevelsabovethealarm/tripsetpoint.(b)TheCHANNELFUNCTIONALTESTshallalsodemonstratethatcontrolroomalarmannunciationoccursifanyofthefollowingconditionsexists:(1)Instrumentindicatesmeasuredlevelsabovethealarmsetpoint.(2)Circuitfailure.(3)Instrumentindicatesadownscalefailure.(4)Instrumentcontrolsnotsetinoperatemode.(c)TheinitialCHANNELCALIBRATIONshallbeperformedusingoneormoreofthereferencestandardscertifiedbytheNationalBureauofStandards(NBS)orusingstandaidsthathavebeenobtainedbysuppliersthatparti-cipateinmeasurementassuranceactivitieswithNBS,orusingactualsamplesofgaseouseffluentsthathavebeenanalyzedonasystemthathasbeencalibratedwithNBStraceablesources.Thesestandardsshallpermitcalibratingthesystemoveritsintendedrangeofenergyandmeasurement.ForsubsequentCHANNELCALIBRATION,sourcesthathavebeenrelatedtotheinitialcalibrationmaybeused.(d)TheCHANNELCALIBRATIONshallincludetheuseofstandardgassamplescontaininganominal:(1)Onevolumepercenthydrogen,balancenitrogen,and(2)Fourvolumepercenthydrogen,balancenitrogen.NINEMILEPOINT-UNIT23/43"102
INSTRUMENTATION~~3/4.3.8TURBINEOVERSPEEOPROTECTIONSYSTEMLIMITINGCONDITIONFOROPERATION3.3.8AtleastoneturbineoverspeedprotectionsystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:a4Withoneturbinecontrolvalve,oneturbinethrottlestopvalveoroneturbinereheatstopvalveperhighpressureturbinesteamleadinoperableand/orwithoneturbineinterceptorvalveperlowpressureturbinesteam1'eadinoperable,restoretheinoperablevalve(s)toOPERABLEstatuswithin72hoursorcloseatleastonevalveintheaffectedsteamlead(s).orisolatetheturbinefromthesteamsupplywithinthenext6hours.b.'Withtheaboverequiredturbineoverspeedprotectionsystemotherwiseinoperable,within6hoursiso7atetheturbinefromthesteamsupply.SURVEILLANCEREUIREMENTS4.3.8.1TheprovisionsofSpecification4.0.4arenotapplicable.4.3.8.2TheaboverequiredturbineoverspeedprotectionsystemshallbedemonstratedOPERABLE:a.Atleastonceper7daysbycyclingeachof.thefollowingvalvesthroughatleastonecompletecyclefromtherunningposition:1.Fourhighpressureturbinestopvalves,2.Fourhighpressureturbinecontrolvalves,and3.Sixlowpressureturbinecombinedstopandinterceptvalves.b.Atleastonceper31daysbymovementofeachoftheabovevalvesthroughatleastonecompletecyclefromtherunningposition.c.Atleastonceper18monthsbyperformanceofaCHANNELCALIBRATIONoftheturbineoverspeedprotectionsystem.d.Atleastonceper40monthsbydisassemblingatleastoneofeachoftheabovevalvesandperformingavisualandsurfaceinspectionofallvalveseats,disksandstemsandverifyingnounacceptableflawsorexcessivecorrosion.Ifunacceptableflawsorexcessivecorrosionarefound,allothervalvesofthattypeshallbeinspected.NINEMILEPOINT"UNIT23/43-103NOV80jg~~
INSTRUMENTATION3/4.3.9PLANTSYSTEMSACTUATIONINSTRUMENTATION~~Ptlif'IBPIIPP[~pyLIMITINGCONDITIONFOROPERATION3.3.9TheplantsystemsactuationinstrumentationchannelsshowninTable3.3.9-1shallbeOPERABLEwiththeirtripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.9-2.APPLICABILITY:AsshowninTable3.3.9-1.ACTION:aob.Mithaplantsystemactuationinstrumentationchanneltripsetpointlessconservativ'ethanthevalueshownintheAllowableValuescolumnofTable3.3.9-2,declarethechannelinoperableandtaketheactionrequiredbyTable3.3.9-1.MithoneormorePlantSystemActuationInstrumentationchannelsinoperabletaketheACTIONrequiredbyTable3.3.9-1.SURVEILLANCEREUIREMENTS4.3.9EachplantsystemactuationinstrumentationchannelshallbedemonstratedOPERABLEbytheperformanceoftheCHANNELCHECK,CHANNELFUNCTIONALTESTandCHANNELCALIBRATIONoperationsfortheOPERATIONALCONDITIONSandatthefrequenciesshowninTable4.3.9.1"l.NINEMILEPOINT-UNIT23/43-104 0 PLANTSYSTEHSIONINSTRUHENTATIONMmC)MIC:MTRIPFUNCTIONFEEDMATERSYSTEH/HAINTURBINETRIPSYSTEHa.ReactorVesselWaterLevel-HighLevel82.SERVICEWATERSYSTEHINSTRUHENTNUMBERHINIHUHAPPLICABLEOPERABLEOPERATIONALCHANNELSaCONDITIONS.ACTION85CQIIDOle.ServiceMaterPumpsDischargeStrainerDifferentialPressure-Train"8"ServiceMaterSupplyHeaderDischargeMaterTemperaturea.DischargeBayLevelb.IntakeTunnel182MaterTemperaturec.ServiceMaterBayd.ServiceWaterPumpsDischargeStrainerDifferentialPressure-Train"A"2SMP"LS-30A,B22SMP"TSL"64A,65A1/Div2SMP"TSL-64B,65B1/Div2SWP*LS"73A,B2I2SWP"PDTA,C,E'/strainerI2SMP"PDTB,F,D1/strainer2SMP"TL-31A,B1,2,3,4,51,2,3,4,51,2,3,4,51,2,3,4,51,2,3,4,51,2,3,4,5878989889109291,9292g.ServiceMaterInletPressureforEDG-2(HPCS,DivIII)h.ControlBuildingWaterFlow2SMP"PSL"95A,B2SWPA-FSL-29A,B1,2,3,4,51,2,3,4,59086aAchannelmaybeplacedinaninoperablestatusforupto2hoursforrequiredsurveillancewithoutplacingthetripsysteminthetrippqdcondition,.exceptfordischargebaylevelandservicewaterbaylevelwhichmaybeplacedinan"operablestatusforupto4hourswithoutplacingthetripsysteminatripedcondition.I@I'R~
MmMImC)MI:TRIPFUNCTION2.SERVICEWATERSYSTEH(Continued)INSTRUMENTNUMBER'INIHUHAPPLICABLEOPERABLEOPERATIONALCHANNELSaCONDITIONSACTION-TABLk;3.9-1(Continued)PLANTSYSTEMSACTUATIONINSTRUMENTATIONJ~ControlBuildingServiceMaterInletTemperatureControlBuildingServiceMaterOutletTemperature2SMP"-TSL-91A,B2SWPATC"35A,B1,2,3,4,51,2,3,4,58686(a)Achannelmaybeplacedsnanoperablestatusforupto2hoursforrequiredsurveillancewithoutplacingthetripsysteminthetrippedcondition.
PiMilF8FPIPi'fMP7TABLE3.3.9-1(Continued)PLANTSYSTEMSACTUATIONINSTRUMENTATIONACTION85-a.WiththenumberofOPERABLEchannelsonelessthanrequiredbytheMinimumOPERABLEChannelsrequirement,restoretheinoperablechanneltoOPERABLEstatuswithin7daysorbeinatleastSTARTUPwithinthenext6hours.b.WiththenumberofOPERABLEchannelstwolessthanrequiredbytheMinimumOPERABLEChannelsrequirement,restoreatleastoneoftheinoperablechannelstoOPERABLEstatuswithin72hoursorbeinatleastSTARTUPwithinthenext6hours.ACTION86-ACTION87-,ACTION88-ACTION89-ACTION90-ACTION91-ACTION92-Start2HVK"CHLXAorBasapplicableorestablishflowmanually.Monitordischargebaylevelcontinuouslyiflevelreachestripsetpoint,provideanalternateflowdischargepathbylockingclosed2SWP"MOV-30Aor2SWP*MOV-30B.Monitorservicewaterbaylevelcontinuouslyiflevelreachestripsetpointprovideanalternateintaketotheservicebaybylockingopen2SWP"MOV-?7Aor2SWP"MOV-77B.Placeintakeheatersinserviceiflake<39'F.Lockclose2SWP"MOV-95Aor2SWP"MOV-95Bariddeclar'eEDG-2(HPCS,DivIII)inoperableandtaketheactionrequiredbySpecification3.8.1.Monitortheeffectedpumpdischargepressureandtheapplicableservicewaterloopheaderpressuretodeterminethedifferentialpressureacrossthestrainer;ifthedifferentialpressureexceedsthesetpointmanuallystartthestrainer.Monitorservicewaterlocaldischargetemperatureindicatorsasapplicableperspecifications4.7.1.l.a.2or4.7.1.2.a.2.NINEMILEPOINT-UNIT23/43-107flgV8019gg
TABLE3.3.9-2PKFf5IPjfPg$gPgRTRIPFUNCTIONPLANTSYSTEMSACTUATIONINSTRUMENTATIONSETPOINTSTRIPSETPOINTALLOWABLEVALUE1.FEEOWATERSYSTEM/MAINTURBINETRIPSYSTEMa.ReactorVesselWaterLevel-High<202.3inches"<203.8inchesLevel82.SERVICEMATERSYSTEMa.DischargeBayLevelb.IntakeTunnel142WaterTemperatureC.d.ServiceMaterBayServiceWaterPumpsDischargeStrainerDifferentialPressure-Train"A"g.ServiceWaterInletPressureforEDG-2(HPCS,DivIII)h.ControlBuildingMaterFLowControlBuildingServiceMaterInletTemperatureControlBuildingServiceMaterOutletTemperature""e.ServiceMaterPumpsDischargeStrainerDifferentialPressure-Train"B"ServiceMaterSupplyHeaderDischargeMaterTemperature<275'lev.>39F>234'lev.<10psid<10psid>25psig>225gpm>60F72oF<275'/4"Elev.>38F>233'l3/4"Elev.<10.5psid<10.5psidNA>21.5psig>209gpm)58oF755oFSeeBasesFigureB3/43-1.""Thisisanoperatingcontrolvalve,notatripsetpoint.NINEMILEPOINT-UNIT23/43"108
MmMIIllC)MI~~TABLE4.3.9.11-1.PLANTSYSTEMSACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREHENTSCHANNELCHANNELFUNCTIONALCHECKTESTCHANNELCALIBRATIONTRIPFUNCTION1.FEEDMATERSYSTEM/MAINTURBINETRIPSYSTEMOPERATIONALCONDITIONSFORMHICHSURVEILLANCEREUIREDChSa.ReactorVesselWaterLevel-High)Level8]2.SERVICEWATERSYSTEHa.DischargeBayLevelb.IntakeTunnel182MaterTemperaturec.ServiceWaterBayd.ServiceWaterPumpsDischargeStrainerDifferentialPressure-Train"A"e.ServiceMaterPumpsDischargeStrainerDifferentialPressure-Train"8"f.ServiceMaterSupplyHeaderDischargeMaterTemperatureg.ServiceMaterInletPressureforEDG-2(HPCS,DivIII)h.ControlBuildingMaterFlowNANANA1,2,3,4,51,2,3,4,51,2,3,4,51$2I3$4$51,2,3,4,51,2,3,4,51,2,3,4,51,2,3,4,5~tttp;ptttfttpttttttt~CDCD
MITIMImCDMI-ITABLE4.3.9.11-1(Continued)PLANTSYSTBISACTUATIONINSTRUMENTATIONSURVEILLANCEREUIREHENTSCHANNELCHANELFUNCTIONAL'HECKTESTCHANNELCALIBRATIONTRIPFUNCTION2.SERVICEMATERSYSTEM(Continued)OPERATIONALCONDITIONSFORMHICHSURVEILLANCEREUIREDMi.ControlBuildingServiceMaterInletTemperaturej.ControlBuildingServiceMaterOutTemperature1,2,3,4,51,2,3,4,5tAIWCD
3/4.4REACTORCOOLANTSYSTEM3/4.4.1RECIRCULATIONSYSTEMRECIRCULATIONLOOPSI'IIKF5KVZNIl9FfLIMITINGCONDITIONFOROPERATION3.4.1.1Tworeactorcoolantsystemrecirculationloopsshallbeinoperationwith:a.Totalcoreflowgreaterthanorequalto45Kofratedcoreflow,orb.THERMALPOWERlessthanorequaltothelimitspecifiedinFigure3.4.1.1-1APPLICABILITY:OPERATIONALCONDITIONS1"and2".ACTION:a0b.C.Withonereactorcoolantsystettrrecirculationloopnotinoperation,immediatelyinitiateactiontoreduceTHERMALPOWERtolessthanorequaltothelimit=-specifiedinFigure3.4.1.1-1within2hoursandinitiatemeasurestoplacetheunitinatleastHOTSHUTDOWNwithin12hours.WithnoreactorcoolantsystemrecirculationloopsinoperationimmediatelyinitiateactiontoreduceTHERMALPOWERtolessthanorequaltothelimitspecifiedinFigure3.4.1.1-1within2hoursandinitiatemeasurestoplacetheunitinatleastSTARTUPwithin6hoursandinHOTSHUTDOWNwithinthenext6hours.Withtworeactorcoolantsystemrecirculationloopsinoperationandtotalcoreflowlessthan45KofratedcoreflowandTHERMALPOWERgreaterthanthelimitspecifiedinFigure3.4.1.1"1:1.DeterminetheAPRMandLPRM""noiselevels(Surveillance4.4.1.1.2)2.a)Atleastonceper8hours,andb)Within30minutesafterthecompletionofaTHERMALPOWERincreaseofatleast5XofRATEDTHERMALPOWER.WiththeAPRMorLPRM""neutronfluxnoiselevelsgreaterthanthreetimestheirestablishedbaselinenoiselevels,immediatelyinitiatecorrectiveactiontorestorethenoiselevelstowithintherequiredlimitswithin2hoursbyincreasingcoreflowtogreaterthan45KofratedcorefloworbyreducingTHERMALPOWERtolessthanorequaltothelimitspecifiedinFigure3.4.1.1-1."SeeSpecialTestException3.10.4.""DetectorlevelsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstringinthecenterofthecoreshouldbemonitored.NINEMILEPOINT-UNIT23/44-1
REACTORCOOLANTSYSTEMSURVEILLANCEREUIREMENTS4.4.1.1.1Eachreacto~coolantsystemrecirculationloopflowcontrolvalveshallbedemonstratedOPERABLEatleastonceper18monthsby:a.Verifyingthatthecontrolvalvefails"asis"onlossofhydraulicpressureatthehydrauliccontrolunit,andb.Verifyingthattheaveragerateofcontrolvalvemovementis:1.LessthanorequaltollXofstrokepersecondopening,and2.Lessthanorequalto12Kofstrokepersecondclosing.4.4.1.1.2EstablishabaselineAPRMandLPRM""neutronfluxnoisevaluewithintheregionforwhichmonitoringisrequired(Specification3.4.1.1,~ACTIONc)within2hoursofenteringtheregionforwhichmonitoringisrequiredunlessbaselininghaspreviously.beenperformedintheregionsincethelastREFUELINGOUTAGE.SeeSpecialTestException3.10.4.""DetectorlevelsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstringinthecenterofthecoreshouldbemonitored.NINEMILEPOINT-UNIT23/44-2ainuu'aiaW
mIm706050~40Ixl4I8302010e3t~gagA~t"20304050COREFLOM,CRATED6070P1GURE3.4.1.1-1PERCENTOFRATEDCORETHERNLPOMERVSPERCENTOFRATEDCOREFLOMil,u
REACTORCOOLANTSYSTEMPMÃ8~~PP"f30~7JETPUMPSLIMITINGCONDITIONFOROPERATION3.4.1.2AlljetpumpsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:Withoneormorejetpumpsinoperable,beinatleastHOTSHUTDOWNwithin12hours.SURVEILLANCEREUIREMENTS4.4.1.2EachoftheaboverequiredjetpumpsshallbedemonstratedOPERABLEpriortoTHERMALPOWERexceeding25XofRATEDTHERMALPOWERandatleastonceper24hoursbydeterminingrecirculationloopflow,totalcoreflowanddiffuser-.+o-"lowerplenumdifferentialpressureforeachjetpumpandverifyingthatnotwoofthefollowingconditionsoccurwhentherecirculationloopsareoperatingatthesameflowcontrolvalveposition.a.b.C.Theindicatedrdcirculationloopfiowdiffersbymorethan10Kfromtheestablishedflowcontrolvalveposition-loopflowcharacteristics.TheindicatedtotalcoreflowdiffersbymorethanlOXfromtheestablishedtotalcoreflowvaluederivedfromrecirculationloopflowmeasurements.Theindicateddiffuser-to-lowerplenumdifferentialpressureofany.individualjetpumpdiffersfromestablishedpatternsbymorethan10X.NINEMILEPOINT-UNIT23/44-4 f REACTORCOOLANTSYSTEMRECIRCULATIONLOOPFLOWLIMITINGCONDITIONFOROPERATION3.4.1.3Recirculationloopflowmismatchshallbemaintainedwithin:a.5Xofratedrecirculationflowwithcoreflowgreaterthanorequalto70Kofratedcoreflow.b.10Kofratedrecirculationflowwithcoreflowlessthan70Kofratedcoreflow.APPLICABILITY:OPERATIONALCONDITIONS1~and2*.ACTION:Withtherecirculationloopflowsdifferentbymorethanthespecifiedlimits,either:'.Restoretherecirculationloopflowstowithinthespecifiedlimitwithin2hours,orb.Declaretherecirculation'loopwiththelowerflownotinoperationandtaketheACTIONrequiredbySpecification3.4.1.1.SURVEILLANCEREUIREMENTS4.4.1.3Recirculationloopflowmismatchshallbeverifiedtobewithinthelimitsatleastonceper24hours.SeeSpec>a]TestException3.10.4.NINEMILEPOINT"UNIT23/44-5
REACTORCOOLANTSYSTEMPFKFO3~Vi!BiXP71IDLERECIRCULATIONLOOPSTARTUPLIMITINGCONDITIONFOROPERATION3.4.1.4Anidlerecirculationloopshallnotbestartedunlessthetemperaturedifferentialbetweenthereactorpressurevesselsteamspacecoolantandthebottomheaddrainlinecoolantislessthanorequalto145F,and:Ia.Whenbothloopshavebeenidle,unlessthetemperaturedifferentialbetweenthereactorcoolantwithintheidlelooptobestartedupandthecoolantinthereactorpressurevesselislessthanorequalto50'F,orb.Whenonlyoneloophasbeenidle,unlessthetemperaturedifferential'betweenthereactorcoolant'withintheidleandoperatingrecircula-tionloopsislessthanorequalto50'Fandtheoperatingloopflowrateislessthanorequalto50Kofratedloopflow.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and4.ACTION:Withtemperaturedifferencesand/orflowratesexceedingtheabovelimits,suspendstartupofanyidlerecirculation'1oop.SURVEILLANCEREUIREMENTS4.4.1.4Thetemperaturedifferentialsandflowrateshallbedeterminedtobewithinthelimitswithin15minutespriortostartupofanidlerecirculationloop.NINEMILEPOINT-UNIT23/44"6
REACTORCOOLANTSYSTEM3)>>A.">g)9lp&i3/4.4.2SAFETY/RELIEFVALVES~~SAFETY/RELIEFVALVESLIMITINGCONDITIONFOROPERATION3.4.2Thesafetyvalvefunctionofatleast17ofthefollowingreactorcoolantsystemsafety/reliefvalvesshallbeOPERABLEwiththespecifiedcodesafetyvalvefunctionliftsettings";theacousticmonitorforeachOPERABLEvalveshallbeOPERABLE.2safety-reliefvalves81148psigIiX4safety-reliefvalves91175psigill4safety-reliefvalves91185psig+1X4safety-relief'valvesta1195ps'igIIX4safety-reliefvalvesta1205psig12%APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:a.Withthesafetyh~~valvefunctionofoneormoreoftheaboverequired.safety/reliefvalvesinoperable,beinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithin.thenext24hours.b.Withoneormoresafety/reliefvalvesstuckopen,providedthatsuppres-sionpoolaveragewatertemperatureislessthan110F,closethestuckopensafety/reliefvalve(s);ifunabletoclosetheopenvalve(s)within5minutesorifsuppressionpoolaveragewatertemperatureis110'Forgreater,placethereactormodeswitchintheShutdownposition.c.Withoneormoresafety/reliefvalveacousticmonitorsinoperable,restoretheinoperablemonitor(s)toOPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.4.2Theacousticmonitorforeachsafety/reliefvalveshallbedemon-stratedOPERABLEwiththesetpointverifiedtobe0.25ofthefullopennoiselevelbyperformanceofa:a.CHANNELFUNCTIONALTESTatleastonceper31days,andab.CHANNELCALIBRATIONatleastonceper18months."""Theliftsettingpressureshallcorrespondtoambientconditionsofthevalvesatnominaloperatingtemperaturesandpressures.""TheprovisionsofSpecification4.0.4arenotapplicableprovidedthesurveillanceisperformedwithin12hoursafterreactorsteampressureisadequatetoperformthetest.PInitialsettingshallbeinaccordance'iththemanufacturersrecommendation.Adjustmenttothevalvefullopennoiselevelshallbeaccomplishedduringthestartuptestprogram.NINEMILEPOINT"UNIT23/44-7
REACTORCOOLANTSYSTEM3/4.4.3REACTORCOOLANTSYSTEMLEAKAGE~~LEAKAGEDETECTIONSYSTEMSLIMITINGCONDITIONFOROPERATIONP~yFOIIqng]t[DPP3.4.3.1ThefollowingreactorcoolantsystemleakagedetectionsystemsshallbeOPERABLE:a.Theprimarycontainmentairborneparticulateradioactivitymonitoringsystem,b.Theprimarycontainmentdrywellfloordraintankandequipmentdraintankfillratemonitoringsystems,andc.Theprimarycontainmentairbornegaseousradioactivitymonitoringsystem.-APPLICABILITY:OPERATIONALCONDITIONS1,-2and3.ACTION:Mithonlytwoofthe'boverequiredleakagedetectionsystemsOPERABLE,operationmaycontinueforupto30daysprovidedgrabsamplesofthecon-tainmentatmosphereareobtainedandanalyzedatleastonceper24hourswhentherequiredgaseousand/orparticulateradioactivemonitoringsystemisinoperable;otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.4.3.1ThereactorcoolantsystemleakagedetectionsystemsshallbedemonstratedOPERABLEby:a0b.Primarycontainmentatmosphereparticulateandgaseousmonitoringsystems-performanceofaCHANNELCHECKatleastonceper12hours,aCHANNELFUNCTIONALTESTatleastonceper~daysandaCHANNELCALIBRATIONatleastonceper18months.Primarycontainmentsumpflowmonitoringsystem-performanceofaCHANNELFUNCTIONALTESTatleastonceper31daysandaCHANNELCALIBRATIONTESTatleastonceper18months.mSou.s.cCC+<<<@~~NINEMILEPOINT"UNIT23/44"8
REACTORCOOLANTSYSTEMOPERATIONALLEAKAGELIMITINGCONDITIONFOROPERATIONfl(<<flCgqgpp~~nape3.4.3.2Reactorcoolantsystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE.b.5gpmUNIDENTIFIEDLEAKAGE.c.25gpmtotalleakageaveragedoverany24-hourperiod.d.0.5gpmleakagepernominalinchofvalvesizeuptoamaximum5gpmatareactorcoolantsystempressureof1020220psigfromanyreactorcoolantsystempressureisolationvalvespecifiedinTable3.4.3.2-1.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithinthenext24hours.b.C.d.e.Withanyreactorcoolantsystemleakagegreaterthanthelimitsinband/orc,above,reducetheleakageratetowithinthelimitswithin4hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Withanyreactorcoolantsystempressureisolationvalveleakagegreaterthantheabovelimit,isolatethehighpressureportionoftheaffected'systemfromthelowpressureportionwithin4hoursbyuseofatleasttwootherc'tosed(manualordeactivatedautomaticorcheck")valves,orbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Withoneormoreofthehigh/lowpressureinterfacevalveleakagepressuremonitorsshowninTable3.4.3.2-2inoperable,restoretheinoperablemonitor(s)toOPERABLEstatuswithin7daysorverifythepressuretobelessthanthealarmsetpointatleastonceper12hours;restoretheinoperablemonitor(s}toOPERABLEstatuswithin30daysorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.WithoneormoreoftherequiredinterlocksshowninTable3.4.3.2-3inoperablerestoretheinoperableinterlocktoOPERABLEstatuswithin7daysorisolatetheaffectedheatexchanger(s)fromtheRCICsteamsupplybyclosinganddeenergizingheatexchangervalves2RHS"MOV-22Aand2RHS"MOV-SOAor2RHS"MOV22Band2RHS"MOV80B,asappropriate.Whichhavebeenverifiednottoexceedtheallowableleakagelimitatthelastrefuelingoutageorafterthelasttimethevalvewasdisturbed,whicheverismorerecent.NINEMILEPOINT-UNIT23/44-9HOV301985
REACTORCOOLANTSYSTEM~~MF53ZPJIKP7SURVEILLANCEREUIREMENTS4.4.3.2.1Thereactorcoolantsystemleakageshallbedemonstratedtobewithineachoftheabovelimitsby:a.Monitoringtheprimarycontainmentairborneparticulateradioactivityatleastonceper12hours,b.Monitoringtheprimarycontainmentdrywellfloordraintankandequipmentdraintankfillrateatleastonceper12hours,c.Monitoringtheprimarycontainmentairbornegaseousradioactivityatleastonceper12hours,andd.Monitoringthereactorvesselheadflangeleakdetectionsystematleastonceper24hours.4.4.3.2.2EachreactorcoolantsystempressureisolationvalvespecifiedinTable3.4.3.2-1shallbedemonstratedOPERABLEbyleaktestingpursuanttoSpecification4.0.5andverifyingtheleakageofeachvalvetobewithinthespecifiedlimit:a.Atleastonceper18months,andb.Priortoreturningthevalvetoservicefollowingmaintenance,repairorreplacementworkonthevalvewhichcouldaffectitsleakagerate.TheprovisionsofSpecification4.0.4arenotapplicableforentryintoOPERATIONALCONOITION3.4.4.3.2.3Thehigh/lowpressureinterfacevalveleakagepressuremonitorsshallbedemonstratedOPERABLEwithsetpointsperTable3.4.3.2-2byperformanceofa:a.CHANNELFUNCTIONALTESTatleastonceper31days,andb.CHANNELCALIBRATIONatleastonceper18months.4.4.3.2.4Thehigh/lowpressureinterfaceinterlockforthesteamcondensingmodebypassvalveshallbedemonstratedOPERABLEwithtripssetpointsperTable3.4.3.2-3byperformanceof:a.CHANNELFUNCTIONALTESTatleastonceper92days,andb.CHANNELCALIBRATIONatleastonceper18months.NINEMILEPOINT-UNIT23/44"10NQV205SS
TABLE3.4.3.2-1PMuF5)~ViFN35P'/REACTORCOOLANTSYSTEMPRESSUREISOLATIONVALVESVALVENUMBERSYSTEM2CSH"MOV1072CSHAMOV1082CSL"MOV1042CSL"AOV1012ICS"AOV1562ICS"AOV1572RHS"MOV1122RHS"MOV1132RHS*MOV1042RHS"MOV40A882RHS"MOV67NhB2RHS"MOV24A,BAC2RHS"AOV16A,88(C2RHS"AOV39ABB2RHS"MOV22MB2RHS"MOV23A88-2RHS"MOV80A88HPCSHPCSLPCSLPCSRCICRCICRHRRHRRHRRHRRHRRRR"(LPCI)RHR-(LPCI)RHRRHRRHR-RHRNINEMILEPOINT-UNIT23/44-11NDV201Aac
PiM>V5$ppg~gpssINSTRUMENTNUMBER2RHS*PIS7A2RHS"PIS7BTABLE.3.4.3.2-2REACTORCOOLANTSYSTEMINTERFACEVALVESLKAGPRESSUMONIORSVALVENUMBER2RHS"MOV24A2RHS"MOV40A2RHS"MOV22A2RHS"MOV23A2RHS*MOV80A2RHS"MOV24B2RHS"MOV40B2RHS"MOV22B2RHS"MOV23B2RHS*MOV80B2RHS"MOV104SETPOINTPSIG480a6480R6480a6480a6480R6480a6480f6480a6480f6480k6480k6~2RHS"PIS7C2CSL*PS1082RHS"PISlll2RHS"MOV24C2CSL"MOV1042RHS"MOV112RHS"-MOV113480a6~46200k620026INSTRUMENTNUMBER2RHS*PIS75A/76A2RHS"PIS75B/76BTABLE3.4.3.2-3HIGH/LOMPRESSUREINTERFACEINTERLOCKSVALVENUMBER2RHS*MOV23A2RHS"MOV23BSETPOINTPSIG465+12465~120NINEMILEPOINT-UNIT23/4'-12Mhlf9ll1COC 0 REACTORCOOLANTSYSTEM3/4.4.4CHEMISTRYLIMITINGCONDITIONFOROPERATION~llKFQpppQ/po(3.4.4ThechemistryofthereactorcoolantsystemshallbemaintainedwithinthelimitsspecifiedinTable3.4.4-1.APPLICABILITY:Atalltimes.ACTION:a.In2.3.OPERATIONALCONDITION1:Withtheconductivity,chlorideconcentrationorpHexceedingthelimitspecifiedinTable3.4.4-1forlessthan72hoursduringonecontinuoustimeintervaland,forconductivityandchloride'concen-tration,forlessthan336hoursperyear,butwiththeconductivitylessthan10pmho/cmat25'Candwiththechlorideconcentration.lessthan0.5ppm,thisneednotbereportedtotheCommiss'ionandtheprovisionsofSpecification3.0.4arenotapplicable.Withtheconductivity,chlorideconcentrationorpHexceedingthe=limitspecifiedinTable3.4.4-1formorethan72hoursduringonecontinuoustimeintervalorwiththeconductivityandchlorideconcentrationexceedingthelimitspecifiedinTable3.4.4-1formorethan336hoursperyear,beinatleastSTARTUPwithinthenext6hours.Withtheconductivityexceeding10pmho/cmat25'Corchlorideconcentrationexceeding0.5ppm,beinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithinthenext24hours.b.C.InOPERATIONALCONDITION2and3withtheconductivity,chlorideconcentrationorpHexceedingthelimitspecifiedinTable3.4.4-1formorethan48hoursduringonecontinuoustimeinterval,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Atallothertimes:1.Withthe:a)ConductivityorpHexceedingthelimitspecifiedinTable3.4.4-1,restoretheconductivityandpHtowithinthelimitwithin72hours,orb)ChlorideconcentrationexceedingthelimitspecifiedinTable3.4.4-1,restorethechlorideconcentrationtowithinthelimitwithin24hours,orperformanengineeringevaluationtodeterminetheeffectsoftheout-of-limitconditiononthestructuralintegrityofthereactorcoolantsystem.DeterminethatthestructuralintegrityofthereactorcoolantsystemremainsacceptableforcontinuedoperationpriortoproceedingtoOPERATIONALCONDITION3.2.TheprovisionsofSpecification3.0.3arenotapplicable.NINEMILEPOINT-UNIT23/44-13NOV2019BS
REACTORCOOLANTSYSTEM4.4.4Thereactorcoolantshallbedeterminedto.bewithinthespecifiedchemistrylimitby:aob.Measurementpriortopressurizingthereactorduringeachstartup,ifnotperformedwithintheprevious72hours.iAnalyzingasampleofthereactorcoolantfor:1.Chloridesatleastonceper:a)72hours,andIb)8hourswheneverconductivity.isgreaterthanthelimitinTable3.4.4-1.2.Conductivityatleastonce-per72hours.3.pHatleastonceper:a)72hours,andb)8hourswheneverconductivityisgreaterthanthelimitinTable3.4.4-1.C.Continuouslyrecordingtheconductivityofthereactorcoolant,or,whenthecontinuousrecordingconductivitymonitorisinoperable,forupto31days,obtaininganin-lineconductivitymeasurementatleastonceper:1.4hoursinOPERATIONALCONDITIONS1,2and3,and2.24hoursatallothertimes.d.PerformanceofaCHANNELCHECKofthecontinuousconductivitymonitorwithanin-lineflowcellatleastonceper:1.7days,and2.24hourswheneverconductivityisgreaterthanthelimitinTable3.4.4-1.0NINEMILEPOINT-UNIT23/44-14
TABLE3.4.4-1REACTORCOOLANTSYSTEMCHEMSTIHITSOPERATIONALCONDITIONCHLORIDESiCONDUCTIVITYmhos/cm925'CPH2and3Atallothertimes<0.2ppm<0.1ppm<0.5ppm<1.0<2.0<10.05.6<pH<8.65.6<pH<8.65.3<pH<8.6IW
REACTORCOOLANTSYSTEM3/4.4.5SPECIFICACTIVITY~~Pi'i~vF815'I~8IX'IMITINGCONDITIONFOROPERATION3.4.5Thespecificactivityofthereactorcoolantshallbelimitedto:a.Lessthanorequalto0.2microcuriespergramDOSEEQUIVALENTI-131,andb.Lessthanorequalto100/Emicrocuriespergram.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and4.'dACTION:a.,InOPERATIONALCONDITIONS1,2or3withthespecificactivityof."theprimarycoolant;.1.Greaterthan0.2microcuriespergramDOSEE(UIVALENTI-131butlessthanorequalto4.0eicrocuriespergramDOSEE(UIVALENTI-131formorethan48hoursduringonecontinuoustimeintervalorgreaterthan4.0microcuriespergramDOSEEQUIVALENTI-131,beinatleastHOTSHUTDOWNwiththemainsteamlineisolationvalvesclosedwithin12hours.2.Greaterthan100/Emicrocuriespergram,beinatleastHOTSHUTDOWNwiththemainsteamlineisolationvalvesclosedwithin12hours.b.InOPERATIONALCONDITIONS1,2,3or4,withthespecificactivityoftheprimarycoolantgreaterthan0.2microcuriespergramDOSEE(UIVALENT1-131orgreaterthan100/Emicrocurieapergram,perfor)thesamplingandanalysisrequirementsofItem4aofTable4.4.5-1untilthespecificactivityoftheprimarycoolantisrestoredtowithinitslimit.c.InOPERATIONALCONDITIONIor2,with:1.THERMALPOWERchangedbymorethan15KofRATEDTHERMALPOWERinonehour",or2.Theoff-gaslevel,downstreamoftherecombiner,increasedbymorethan10,000microcuriespersecondinonehourduringsteadystateoperationatreleaserateslessthan75,000microcuriespersecond,or3.Theoff-gaslevel,attheSJAE,increasedbymorethan15Kinonehourduringsteadystateoperationatreleaseratesgreaterthan75,000microcuriespersecond,performthesamplingandanalysisrequirementsofItem4bofTable4.4.5-1untilthespecificactivityoftheprimarycoolantisrestoredwithinits1imit.pplippdppppppppNINEMILEPOINT-UNIT23/44-16NOV201985
REACTORCOOLANTSYSTEMPK3F5KVP~'1PvFfSURVEILLANCEREUIREMENTS4.4.5ThespecificactivityofthereactorcoolantshallbedemonstratedtobewithinthelimitsbyperformanceofthesamplingandanalysisprogramofTable4.4.5"1.NINEMILEPOINT-UNIT23/44"17~nu901985 A ,TABLE4.4.5"1PRIMARYCOOLANTSPECIFICACTIVITYSAMPLEANDANALYSISPROGRAMTYPEOFMEASUREMENTANDANALYSISI.GDeterminationActivity2.IsotopicAnalysisforDOSEEQUIVALENTI-131Concentration3.RadiochemicalforZDetermination4.IsotopicAnalysisforIodineSAMPLEANDANALYSISFREUENCYAt'leastonceper72hoursAtleastonceper31daysAtleastonceper6months"a)Atleastonceper4hours,wheneverthespecificactivityexceedsalimit,asrequiredbyACTIONb.b)Atleastonesample,between2and6hoursfollowingthechangeinTHERMALPOWERoroff-gaslevel,asrequiredbyACTIONc.OPERATIONALCONDITIONSINWHICHSAMPLEANDANALYSISREUIRED1,2,33P,28,38,481,25.IsotopicAnalysisofan.Off-Atleastonceper31days1gasSampleIncludingguantitativeMeasurementsforatleastXe-133,Xe-135andKr-88'VSampletoetakenafteraminimumof2EFPDand20daysofPOWEROPERATIONhaveelapsedsincereactorwaslastsubcriticalfor48hoursorlonger.OUntilthespecificactivityoftheprimarycoolantsystemisrestoredtowithinitslimits..nCMIPIAt'QIrQ
REACTORCOOLANTSYSTEM3/4.4.6PRESSURE/TEMPERATURELIMITS~~REACTORCOOLANTSYSTEMFIMFu'Bf7~7f3"7LIMITINGCONDITIDNFOROPERATION3.4.6.1ThereactorvesselpressureandmetaltemperatureshallbelimitedinaccordancewiththelimitlinesshownonFigures3.4.6.1-1,3.4.6.1-2,and3.4.6.1-3(1)curveAforhydrostaticorleaktesting;(2)curveBforheatupbynon-nuclearmeans,cooldownfollowinganuclearshutdownandlowpowetPHYSICSTESTS;and(3)curveCforoperationswithacriticalcoreotherthanlowpowerPHYSICSTESTS,with:a.Amaximumwaterheatupof100'Finanyonehourperiod,b.Amaximumwatercooldownof.100Finanyonehourperiod,c.Amaximumwatertemperaturechangeoflessthanorequalto20'Finanyonehourperiodduringinservicehydrostaticandleaktestin'goperationsabovetheheatupand'cooldownlimitcurves,andd.Thereactorvesselflangeandheadflangetemperaturegreaterthanorequalto70'Fwhenreactorvesselheadboltingstuds.areunderfulltension.APPLICABILITY:Atal'1times.ACTION:Withanyoftheabovelimitsexceeded,restorethetemperatureand/orpressuretowithinthelimitswithin30minutes;performanengineeringevaluationto.determinetheeffectsoftheout-of-limitconditiononthestructuralintegrityofthereactorcoolantsystem;determinethatthereactorcoolantsystemremainsacceptableforcontinuedoperationsorbeinatleastHOTSHUTDOWNwithin?2hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.4.6.1.1Duringsystemheatup,cooldownandinserviceleakandhydrostatictestingoperations,thereactorvesselpressureandmetaltemperatureofthereactorvesselflangesurfaces,bottomoutsidesurfaceandbottomheadinsidesurfaceasmeasuredbythebottomheaddraintemperatureshallbedeterminedtobewithintheaboveoperatinglimitsdefinedbyFigures3.4.6.1-1asapplicable,atleastonceper30minutes.OTfigupCSi4s'4sl3guCV<6Cu~uCNINEMILEPOINT"UNIT23/44-19NQV50'SM
REACTORCOOLANTSYSTEMPBJF53PPP~J"P'/SURVEILLANCEREUIREMENTSContinued14.4.6.1.2Thereactorcoolantsystemtemperatureandpressureshallbedeterminedto.betotherightofthecriticalitylimitlineofFigure3.4.6.1-3curveCwithin15minutespriortothewithdrawalofcontrolrodstobringthereactortocriticalityandatleastonceper30minutesduringsystemheatup.4.4.6.1.3Thereactorvesselmaterialsurveillancespecimensshallberemovedandexamined,todeterminechangesinreactorpressurevesselmaterialpropertiesasrequiredby10CFR50,AppendixHinaccordancewiththescheduleinTable4.4.6.1.3-1.TheresultsoftheseexaminationsshallbeusedtoupdatethecurvesofFigures3.4.6.1-1,3.4.6.1-2and3.4.6.1-3.4.4.6.1.4Thereactorvesselflangeandheadflangetemperatureshallbeverifiedtobegreaterthanorequalto70'Fwhenreactorvesselheadboltingstudsareunderfulltension:a.InOPERATIONALCONDITION4whenreactorcoolantsystemtemperaturels:1.<90F,atleastonceper12hours.2.<80F,atleastonceper30minutes.b.%thin30minutespriortoandatleastonceper30minutesduringtensioningofthereactorvesselheadboltingstuds.ewe~p+Nolo~++pebaL+~mg~u84m~y4g0uL4Y+~~~~'7o',NINEMILEPOINT-UNIT23/44"20NCY301985
-14001300120011001000900800C)cem700CLQC)K~~600<~50073VALIDFORl6YEARS(12.8'EFPY)OF'PERATION4003002001000100150200SININNRECTORVESSELHETALTENPERATURE{F)FIGURE3.4.6.1-1MINIMUMREACTORVESSELTEMPERATUREFORPRESSURIZATIONDURINGIN-SERVICEHYDROSTATICTESTINGANDLEAKTESTING(CURVEA)NINEMILEPOINT-UNIT23/44-21NOV20ii~~
1400130012001000900800700~600500560VALIDFOR16YEARS(12.8EFPY)'OFOPERATION30020010018050100150200MINIMUNREACTORVESSELf'!ETALTBlPERATURE{'F)FIGURE3.4.6.1-2NININNREACTORVESSELTEMPERATUREFORPRESSURIZATIONDURINGNON-NUCLEARHEATUP/'OOLOOWNANDLOWPOWERPHYSICSTESTS(CURVEjf)8NINEMILEPOINT-UNIT23/44-22Nov$01935
14001300120011001000900~g800R700CLQ600CrO500.ioo60960ALIDFOR16YEARS{12.8EFPY)OFOPERATICCkQLi300200005090100150200HININUMREACTORVESSELNETALTEMPERATURE('F)250FIGURE3.4.6.1-3MINIMUMREACTORVESSELTEMPERATUREFORPRESSURIZATIONDURINGCORECRITICALOPERATIONOPERATION(CURVEC)NINEMILEPOINT-UNIT23/44-23g0y20.3985
MmMImTABLE4.4.6.1.3"1REACTORVESSELMATERIALSURVEILLANCEPROGRAM-MITHDRAMALSCHEDULECDMICAPSULENURSERVESSELLOCATION30177183LEADFACTOR91/4T0.410.410.41MITHDRAWALTIMEEFPY1020spare
REACTORCOOLANTSYSTEMREACTORSTEAMDOMELIMITINGCONDITIONFOROPERATION3.4.6.2Thepressureinthereactorsteamdomeshallbelessthan1020psig.APPLICABILITY:OPERATIONALCONDITION1"and2".ACTTON:Withthereactorsteamdomepressureexceeding1020psig,reducethepressuretolessthan1020psigwithin15minutesorbeinatleastHOTSHUTDOWNwithin12hours.SURYEILLANCEREUIREMENTS4.4.6.2Thereactorsteamdomepressuresha11beverifiedtobelessthanl020psigatleastonceper12hours.Notapplicableduringanticipatedtransients.NINEMILEPOINT"UNIT23/44-25N0y2,O19Ã
REACTORCOOLANTSYSTEM0jjiIllnessQIII.'y>operation,atleastoneshutdowncoolingmodeloopshallbeinoperation"'itheachloopconsistingofatleast:a.OneOPERABLERHRpump,andb.OneOPERABLERHRheatexchanger.APPLICABILITY:OPERATIONALCONDITION3,withreactorvesselpressurelessthantheRHRcut-inpermissivesetpoint.ACTION:.a0b.WithlessthantheaboverequiredRHRshutdowncoolingmodeloopsOPERABLE,immediately8nitiatecorrectiveactiontoreturntherequiredloopstoOPERABLEstatusassoonaspossible.Withinonehourandatleastonceper24hoursthereafter,demonstratetheoerabilityof-atleastonealternatemethodcapableofdecayheatremovalforeachinoperableRHRshutdowncoolingmodeloop.BeinatleastCOLDSHUTDOWNwithin24hours.""WithnoRHRshutdowncoolingmodeloopinoperation,immediatelyinitiatecorrectiveactiontoreturnatleastonelooptooperationassoonaspossible.Withinonehour.establishreactorcoolantcirculationbyanalternatemethodandmonitorreactorcoolanttemperatureandpressureatleastonceperhour.SURVEILLANCEREUIREMENTS4.4.9.1At'leastoneshutdowncoolingmodeloopoftheresidualheatremovalsystemoralternativemethodshallbedeterminedtobeinoperation-handcirculatingreactorcoolantatleastonceper12hours.OneRHRshutdowncoolingmodeloopmaybeinoperableforupto2hoursforsurveillancetestingprovidedtheotherloopisOPERABLEandinoperation.~shutdowncoolingpumpmayberemovedfromoperationforupto2hoursper8hourperiodprovidedtheotherloopisOPERABLE.OOTheRHRshutdowncoolingmodeloopmayberemovedfromoperationduringhydrostatictesting.*"WhenevertwoormoreRHRsubsystemsareinoperable,ifunabletoattainCOLDSHUTDOWNasrequiredbythisACTION,maintainreactorcoolanttemperatureaslowaspracticalbyuseofalternaeheatremovalmethods.NINEMILEPOINT"UNIT23/44-28goy201985
REACTORCOOLANTSYSTEMCOLDSHUTDOWNLIMITINGCONDITIONFOROPERATIONKQi~F8lPPF~IUFf3.4.9.2Twoshutdowncoolingmodeloopsoftheresidualheatremoval(RHR)systemshallbeOPERABLEand,unlessatleastonerecirculationpumpisin>>operation,atleastoneshutdowncoolingmodeloopshallbeinoperation~'itheachloopconsistingofatleast:a.OneOPERABLERHRpump,andb.OneOPERABLERHRheatexchanger.APPLICABILITY:OPERATIONALCONDITION4.ACTION:a0b.WithlessthantheaboverequiredRHRshutdowncoolingmodeloopsOPERABLE,withinonehourandatleastonceper24hoursthereafter,demonstratetheoperabilityofatleastonealternatemethodcapableofdecayheatremovalforeachinoperableRHRshutdowncoolingmode1oop.WithnoRHRshutdowncoolingmodeloopinoperation,withinonehourestablishreactorcoolantcirculationbyanalternatemethodandmonitorreactorcoolanttemperatureandpressureatleastonceperhour.SURVEILLANCEREUIREMENTS4.4.9.2Atleastoneshutdowncoolingmodeloopoftheresidualheatremovalsystemoralternativemethodshallbedeterminedtobeinoperationandcirculatingreactorcoolantatleastonceper12hours.OneRHRshutdowncoolingmodeloopmaybeinoperableforupto2hoursforsurveillancetestingprovidedtheotherloopisOPERABLEandinoperation.Theshutdowncoolingpumpmayberemovedfromoperationforupto2hoursper8hourperiodprovidedtheotherloopisOPERABLE.¹¹Theshutdowncoolingmodeloopmayberemovedfromoperationduringhydrostatictesting.NINEMILEPOINT-UNIT23/44-29NQV$01~a 0 3/4.5EMERGENCYCORECOOLINGSYSTEMS3/4.5.1ECCS-OPERATINGpre8lZ>',P8(QPtLIMITINGCONDITIONFOROPERATION3.5.1ECCSdivisionsI,IIandIIIshallbeOPERABLEwith:a.ECCSdivisionIconsistingof:1.TheOPERABLElowpressurecorespray(LPCS)systemwithaflowpathcapableoftakingsuctionfromthesuppressionpoolandtransferringthewaterthroughthesprayspargertothereactorvessel.2.TheOPERABLElowpressurecoolantinjection(LPCI)subsystem"A"oftheRHRsystemwithaflowpathcapableoftakingsuctionfromthesuppressionpoolandtransferringthewatertothereactorvessel.3.Seven.OPERABLEAOSvalves.b.ECCSdivisionIIconsistingof:1.TheOPERABLElowpressurecoolantinjection(LPCI)subsystems"B"and"C"oftheRHRsystem,eachwithaflowpathcapableoftakingsuctio'nfromthesuppressionpoolandtransferringthewatertothereactor'vessel.2.SevenOPERABLEADSvalves.C.ECCSdivisionIIIconsistingoftheOPERABLEhighpressurecorespray(HPCS)systemwithaflowpathcapableoftakingsuctionfromthesuppressionpoolandtransferringthewaterthroughthesprayspargertothereactorvessel.APPLICABILITY:OPERATIONALCONDITION1,2"'nd3"¹¹.TheAOS1snotrequiredtobeOPERABLEwhenreactorsteamdomepressureislessthanorequalto100psig.SeeSpecialTestException3.10.6.¹¹LPCIsubsystemsoftheRHRsystemmaybeinoperableinthattheyarealignedintheshutdowncoolingmodewhenreactorvesselpressureislessthantheRHRshutdowncoolingpermissivesetpoint.NINEMILEPOINT"UNIT23/45-Z~nvR01985
EMERGENCYCORECOOLINGSYSTEMSLIMITINGCONDITIONFOROPERATIONContinuedACTION:a.ForECCSdivisionI,providedthatECCSdivisionsIIandIIIareOPERABLE:1.WiththeLPCSsysteminoperable,restoretheinoperableLPCSsystemtoOPERABLEstatuswithin7days.2.3.WithLPCIsubsystem"A"inoperable,restoretheinoperableLPCIsubsystem"A"toOPERABLEstatuswithin7days.llWiththeLPCSsysteminoperableandLPCIsubsystem"A"inoperable,restoreatleasttheinoperab'leLPCIsubsystem"A"ortheinoperableLPCSsystemtoOPERABLEstatuswithin72hours.4.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.b.ForECCSdivisionII,providedthatECCSdivisionsIandIIIareOPERABLE:I.WitheitherLPCIsubsystem"B"or"C"inoperable,restoretheinoperableLPCIsubsystem"B"or"C"toOPERABLEstatuswithin7days.2.WithbothLPCIsubsystems"B"and"C"inoperable,restoreatleasttheinoperableLPCIsubsystem"B"or"C"toOPERABLEstatuswithin72hours.C.3.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours".ForECCSdivisionIII,providedthatECCSdivisionsIandIIandtheRCICsystemareOPERABLE:1)WithECCSdivisionIIIinoperable,restoretheinoperabledivisiontoOPERABLEstatuswithin14days.2)Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.d.ForECCSdivisionsIandII,providedthatECCSdivisionIIIisOPERABLE:1)WithLPCIsubsystem"A"andeitherLPCIsubsystem"B"or"C"inoperable,restoreatleasttheinoperableLPCIsubsystem"A"ortheinoperableLPCIsubsystem"B"or"C"toOPERABLEstatuswithin72hours.WhenevertwoormoreRHRsubsystemsareinoperable,ifunableto'attainCOLDSHUTDOWNasrequiredbythisACTION,maintainreactorcoolanttemperatureaslowaspracticalbyuseofalternateheatremovalmethods.NINEMILEPOINT-UNIT23/45-2
EMERGENCYCORECOOLINGSYSTEMSLIMTINGCONDITIONFOROPERATIONContinued)ACTION:(Continued)2)WiththeLPCSsysteminoperableandeitherLPCIsubsystems"B"or"C"inoperable,restoreatleasttheinoperableLPCSsystemortheinoperableLPCIsubsystem"B"or"C"toOPERABLEstatuswithin72hours.3)Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours".e.ForECCSdivisionsIandII,providedthatECCSdivisionIIIisOPERABLEandDivisionsIandIIareotherwiseOPERABLE:MithoneoftheaboverequiredADSvalvesinoperable,restoretheinoperableADSvalvetoOPERABLEstatuswithin14daysorbeinatleastHOTSHUTDOMNwithinthenext12hoursandreducereactorsteamdomepressureto<100psigwithinthenext24hours.-2.WithtwoormoreoftheaboverequiredADSvalvesinoperable,beinatleastHOTSHUTDOWNwithin'2hoursandreducereactorsteamdomepressureto<100psigwithinthenext24hours.IntheeventanECCSsystemisactuatedandinjectswaterintotheReactorCoolantSystem,aSpecialReportshallbepreparedandsub-mittedtotheCommissionpursuanttoSpecification6.9.2within90daysdescribingthecircumstancesoftheactuationandthetotalaccumulatedactuationcyclestodate.ThecurrentvalueoftheuseagefactorforeachaffectedsafetyinjectionnozzleshallbeprovidedinthisSpecialReportwheneveritsvalueexceeds.0.70.WhenevertwoormoreRHRsubsystemsareinoperable,ifunabletoattainCOLDSHUTDOWNasrequiredbythisACTION,maintainreactorcoolanttemperatureas-lowaspracticalbyuseofalternateheatremovalmethods.NINEMILEPOINT-UNIT23/45-31lALI0h1COC
EMERGENCYCORECOOLINGSYSTEMSSURVEILLANCEREUIREMENTS~~~4.5.3.ECCSdsvls1onI,IIandIIIshallbedemonstratedOPERABLEby:a.Atleastonceper31daysfortheLPCS,LPCIandHPCSsystems:l.Verifyingbyventingatthehighpointventsthatthesystempipingfromthepumpdischargevalvetothesystemisolationvalveisfilledwithwater.2.Verifyingthateachvalve(manual,poweroperatedorautomatic)intheflowpaththatisnotlocked,sealed,orotherwisesecuredinposition,isinitscorrect"position.b.Verifying1.LPCSline2.LPCI1ine'.HPCSlinethat,whentestedpursuanttoSpecification4.0.5,each:pumpdevelopsaflowofatleast6350gpmagainstatestpressuregreaterthanorequalto278)psig.pumpdevelopsaflowofatleast7450gpmagainstatestpressuregreaterthanorequalto154'sig.pumpdevelopsaflowofatleast6350gpmagainstatestpressuregreaterthanorequalto385'sig.C.FortheLPCS,LPCIandHPCS""systems,atleastonceper18months,performingasystemfunctionaltestwhichincludessimulatedauto-maticactuationofthesystemthroughoutitsemergencyoperatingsequenceandverifyingthateachautomaticvalveintheflowpathactuatestoitscorrectposition.Actualinjectionofcoolantintothereactorvesselmaybeexcludedromthistest.d.FortheHPCSsystem,atleastonceper18months,verifyingthatthesuctionisautomaticallytransferredfromthecondensatestoragetanktothesuppressionpoolonacondensatestoragetanklowwaterlevelsignalandonasuppressionpoolhighwaterlevelsignal."ExceptthatanautomaticvalvecapableofautomaticreturntoitsECCSpositionwhenanECCSsignalispresentmaybeinpositionforanothermodeofoperation.""VerifyHPCSpumpwillauto-restartonIowreactorvesselwaterlevel,level2,ifthepumphasbeenmanuallystopped.gTheseECCStestlinepressuresarepreliminarynumberstobeverifiedduringpreoperationaltesting.AnychangestothesenumberswillbesubmittedinwritingtotheCommissionwithin90daysoftheirdetermination.NINEMILEPOINT-UNIT23/45-4PQQ2,ulbU5
EMERGENCYCORECOOLINGSYSTEMSQgg.')gp,QQpg')fp'gQfisammym)iaÃi349CiV4SURVEILLANCEREUIREMENTSContinuede.FortheADSby:1.Atleastonceper31days,performingaCHANNELFUNCTIONALTESToftheaccumulatorbackupcompressedgassystemlowpressurealarmsystem.2.Atleastonceper18months:a)Performingasystemfunctionaltestwhichincludessimulatedautomaticactuationofthesystemthroughoutitsemergencyoperatingsequence,butexcludingactualvalveactuation.b)ManuallyopeningeachADSvalvewhenthereactorsteamdomepressureisgreaterthanorequalto100psig"andobservingthateither:1)TheSRVDischargeAcousticMonitoringSystem~~respondsaccordingly,orc)2)~or+heSRVDischargeLineTemperatureMonitoringSystemrespondsaccordingly>otPerformingaCHANNELCALIBRATIONoftheaccumulatorbackupcompressedgassystemlowpressurealarmsystemandverifyinganalarmsetpointof163.5+2.5,-2.5psigondecreasingpressure.TheprovsssonsofSpecification4.0.4.arenotapplicableprovidedthesurveillanceisperformedwithin12hoursafterreactorsteampressureisadequatetoperformthetest.+)zX~~NINEMILEPOINT-UNIT23/45"5NQVQPlo@
EMERGENCYCORECOOLINGSYSTEMS3/45.2ECCS-SHUTDOWNLIMITINGCONDITIONFOROPERATION3.5.2Atleasttwoof'hefollowingshallbeOPERABLE:aoThelowpressurecorespray(LPCS)systemwithaflowpathcapableoftakingsuctionfromthesuppressionchamberandtransferringthewaterthroughthesprayspargertothereactorvessel.b.Lowpressurecoolantinjection(LPCI)subsystem"A"oftheRHRsystemwithaflowpathcapableoftakingsuctionfromthesuppressionchamberandtransferringthewatertothereactorvessel.C.d.e.Lowpressurecoolantinjection(LPCI)subsystem"B"oftheRHRsystemwithaflowpathcapableoftakingsuctionfromthesuppressionchamberandtransferringthewatertothereactorvessel.Lowpressurecoolantinjection(LPCI)subsystem"C"oftheRHRsystemwithaflowpathcapableoftakingsuctionfromthesuppressionchamberandtransferringthewatertothereactorvessel.Thehighpressurecorespray(HPCS)systemwithaf'Jowpathcapableoftakingsuctionfromoneofthefollowingwatersourcesandtransferringthewaterthroughthesprayspargertothereactorvessel:1,.Fromthesuppressionchamber,or2.Whenthesuppressionpoollevelislessthanthelimitorisdrained,fromthe"B"condensatestoragetankcontainingatleast283,000availablegallonsofwater,equivalenttoalevelof30.1'.APPLICABILITY:OPERATIONALCONDITION4and5".ACTION:a.Withoneoftheaboverequiredsubsystems/systemsinoperable,restoreatleasttwosubsystems/systemstoOPERABLEstatuswithin4hoursorsuspendalloperationsthathaveapotentialfordrainingthereactorvessel.b.Withbothoftheaboverequiredsubsystems/systemsinoperable,suspendCOREALTERATIONSandalloperationsthathaveapotentialfordrainingthereactorvessel.Restoreatleastonesubsystem/systemtoOPERABLEstatuswithin4hoursorestablishSECONDARYCONTAINMENTINTEGRITYwithinthenext8hours."TheECCSisnotrequiredtobeOPERABLEprovidedthatthereactorvesselheadisremoved,thecavityisflooded,thespentfuelpoolgatesareremoved,andwaterlevelismaintainedwithinthelimitsofSpecification3.9.8and3.9-9.NINEMILEPOINT-UNIT23/45-6
EMERGENCYCORECOOLINGSYSTEMSSURVEILLANCEREUIREMENTSt4.5.2.1AtleasttheaboverequiredECCSdivisionsshallbedemonstratedOPERABLEperSurveil'lanceRequirement4.5.I.4.5.2.2TheHPCSsystemshallbedetermineOPERABLEatleastonceper12hoursbyverifyingthecondensatestoragetankrequiredvolumewhenthecondensatestoragetankisrequiredtobeOPERABLEperSpecification3.5.2.e.NINEMILEPOINT-UNIT23/45-7NOV801985
EMERGENCYCORECOOLINGSYSTEMS3/4.5.3SUPPRESSIQNPOOLLIMITINGCQNDITIONFOROPERATIONPK3F5I)K(NKFi3.5.3ThesuppressionpoolshallbeOPERABLE:a.InOPERATIONALCONDITION1,2and3withacontainedwatervolumeofatleast145,495fthm,equivalenttoanelevationof199'-6"b.InOPERATIONALCONDITION4and5"withacontainedwatervolumeofatleast145,495ft3,equivalenttoalevelof199'-6",exceptthatthesuppressionpoollevelmaybelessthanthelimitormaybedrainedprovidedthat:1.Nooperationsareperformedthathaveapotentialfordrainingthereactorvessel,2.ThereactormodeswitchislockedintheShutdownorRefuelposition,3;The"B"condensatestoragetankcontainsatleast283,000availablegallonsofwater,equivalenttoalevelof30.1',and4.TheHPCSsystem.jsOPERABLEperSpecification3.5.2withanOPERABLEflowpathcapableoftakingsuctionfrom.the"B"con-densatestoragetankandtransferringthewaterthroughthesprayspargertothereactor'vessel.APPLICABIIITY:OPERATIONALCONDITIONS1,2,3,4and5".ACTION:a0b.InOPERATIONALCONDITIQN1,2or3withthesuppressionpoolwater'levellessthantheabovelimit,restorethewaterleveltowithinthelimitwithin1hourorbeinat1eastHQTSHUTDOWNwithinthenext12hoursandinCQLDSHUTDOWwithinthefollowing24hours.InOPERATIONALCONDITION4or5"withthesuppressionpoolwaterlevellessthantheabovelimitordrainedandtheaboverequiredconditionsnotsatisfied,suspendCOREALTERATIONSandalloperationsthathaveapotentialfordrainingthereactorvesselandlockthereactormodeswitchintheShutdownposition.EstablishSECONDARYCONTAINMENTINTEGRITYwithin8hours.ThesuppressionpoolisnotrequiredtobeOPERABLEinOPERATIONALCONDITION5providedthatthereactorvesselheadisremoved,thecavityisfloodedorbeingflooded,thespentfuelpoolgatesareremoved(whenthecavityisflooded),andthewaterlevelismaintainedwithinthelimitsofSpecification3.9.8and3.9.9.NINEMILEPOINT"UNIT23/45-8QQV2ll1%A'6
EMERGENCYCORECOOLINGSYSTEMSSURVEILLANCEREUIREHENTS4.5.3.1ThesuppressionpoolshallbedeterminedOPERABLEbyverifyingthewaterleveltobegreaterthanorequalto199'-6"atleastonceper24hours.4.5.3.2'iththesuppressionpoollevellessthantheabovelimitordrainedinOPERATIONALCONDITION4or.5",atleastonceper12hours:a.VerifytherequiredconditionsofSpecification3.5.3.btobesatisfied,orb.Verifyfootnoteconditions~tobesatisfied.ThesuppressionpoolisnotrequiredtobeOPERABLEinOPERATIONALCONDITION5providedthatthereactorvesselheadisremoved,thecavityisfloodedorbeingflooded~thespentfuelpoolgatesareremoved(whenthecavityisflooded),andthewaterlevelismaintainedwithinthelimitsofSpecification3.9.8and3.9.9.~~~~~~NINEMILEPOINT-UNIT23/45-9
3/4.6CONTAINMENTSYSTEMS3/4.6.1PRIMARYCONTAINMENTPRIMARYCONTAINMENTINTEGRITYLIMITINGCONDITIONFOROPERATION~n~OI'I)VPI!IJ)II~'f3.6.1.1PRIMARYCONTAINMENTINTEGRITYshallbemaintained.APPLICABILITY:OPERATIONALCONDITIONS1,2"and3.ACTION:WithoutPRIMARYCONTAINMENTINTEGRITY,restorePRIMARYCONTAINMENTINTEGRITYwithin1hourorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURYEILLANCEREUIREMENTS4.6;1.1aob.C.d.PRIMARYCONTAINMENTINTEGRITYshallbedemonstrated:IAftereachclosingofeachpenetrationsubjecttoType8testing,excepttheprimarycontainmentairlocks,ifopenedfollowingTypeAor8test,byleakratetestingthe-sealswithgasatPa,39.75psig,andverifying.thatwhenthemeasuredleakagerateforthesesealsisaddedtotheleakageratesdeterminedpursuanttoSurveillanceRequirement4.6.1.2.dforallotherType8andCpenetrations,thecombinedleakagerateis.'lessthanorequalto0.60La.Atleastonceper31daysbyverifyingthatallprimarycontainmentpenetrations""notcapableofbeingclosedbyOPERABLEcontainmentautomaticisolationvalvesandrequiredtobeclosedduringaccident.conditionsareclosedbyvalves,blindflanges,ordeactivatedautomaticvalvessecuredinposition,exceptasprovidedinTable3.6.3-1ofSpecification3.6.3.ByverifyingeachprimarycontainmentairlockisincompliancewiththerequirementsofSpecification3.6.1.3.ByverifyingthesuppressionchamberisincompliancewiththerequirementsofSpecification3.6.2.l.SeeSpecialTestException3.10.1""Exceptvalves,b'Jindflanges,anddeactivatedautomaticvalveswhicharelocatedinsidethecontainment,andarelocked,sealedorotherwisesecuredintheclosedposition.ThesepenetrationsshallbeverifiedclosedduringeachCOLDSHUTDOWNexceptsuchverificationneednotbeperformedwhentheprimarycontainmenthasnotbeende-inertedsincethelastverificationormoreoftenthanonceper92days.NINEMILEPOINT"UNIT23/46"1
CONTAINMENTSYSTEMSPRIMARYCONTAINMENTLEAKAGELIMITINGCONDITIONFOROPERATION3.6.1.2Primarycontainmentleakageratesshallbelimitedto:a.Anoverallintegratedleakagerateoflessthanorequalto:1.La,1.Ipercentbyweightofthecontainmentairper24hoursatPa,39.75psig,or2.Lt,0.55~percentbyweightofthecontainmentairper24hoursatareducedpressureofPt,20.0psig.b.Acombinedleakagerateoflessthanorequalto0.60Lforallpene-trationsandallvalveslistedinTable3.6.3-1,exceptformainsteamlineisolationvalves""(andvalveswhicharehydrostaticallyleaktestedperTable3.6.3-1),subjecttoTypeBandCtestswhenpressur-izedtoPa,39.75psig.c.4"Lessthanorequalto6.0scfperhourforanyonemainsteamlineisolationvalvewhentestedat40.0psig.d..Acombinedleakagerateoflessthanorequalto1gpmtimesthetotalnumberofcontainmentisolationvalvesinhydrostaticallytestedlineswhichpenetratetheprimarycontainment,whentestedat.1.10Pa,43.73psig.re.Less.thanorequaltothatspecifiedinTable3.6.1.2"1throughvalvesinlinesthatarepotentialbypassleakagepathwayswhentestedat40.0psig.aAPPLICABILITY:@henPRIMARYCONTAINMENTINTEGRITYisrequiredperSpecification3.6.1.1.ACTION:Mith:aoC.d.e.Themeasuredoverallintegratedprimarycontainmentleakagerateexceeding0.75Laor0.75Lt,asapplicable,orThemeasuredcombinedleakagerateforallpenetrationsandallvalveslistedinTable3.6.3-1,exceptformainsteamlineisolationvalves"+andvalveswhicharehydrostaticallyleaktestedperTable&:6.3-1,subjecttoTypeBandCtestsexceeding0.60La,orThemeasuredleakagerateexceeding6.0scfperhourforanyonemainsteamlineisolationvalve,orThemeasuredcombinedleakagerateforallcontainmentisolationvalvesinhydrostaticallytestedlineswhichpenetratetheprimarycontainmentexceeding1gpmtimesthetotalnumberofsuchvalvesThemeasuredleakageratethroughanyvalvethatispart'fapotentialbypassleakagepathwayexceedingthelimitspecifiedinTable3.6.1.2-1FinalnumbertobedeterminedafterinitialType"A"testdoneinaccordancewithAppendix"J"of10CFRPart50andreportedtotheCommissionwithin90daysoftestcompletion.""ExemptiontoAppendix"J"of10CFR50.hNINEMILEPOINT-UiVIT23/46"2HOVP.01985
CONTAINMENTSYSTEMSLIMITINGCONDITIONFOROPERATION(ContinuedpiifIT)'9et+iiFIJACTION(Continued),restore:a.Theoverallintegratedleakagerate(s)tolessthanorequalto0.75Laor0.75Lt,asapplicable,andb.ThecombinedleakagerateforallpenetrationsandallvalveslistedinTable3.6.3-l,exceptformainsteamlineisolationvalves""%ndvalveswhicharehydrostaticallyleaktestedperTable3.6.3-1,subjecttoType8andCteststolessthanorequalto0.60La,andc.Theleakageratetolessthanorequalto6.0scfperhourforanyonemainsteamlineisolationvalve,andd.Thecombinedleakagerateforallcontainmentisolationvalvesinhydrostaticallytestedlineswhichpentratetheprimarycontainmenttolessthanorequalto1gpmtimesthetotalnumberofsuchvalves,ande.TheleakageratetolessthanorequaltothatspecifiedinTable3.6.1.2-1foranyvalvethatispartofapotentialbypassleakagepath.priortoincreasingreactorcoolantsystemtemperatureabove200'F.SURVEILLANCEREVIREMENTS~~~~~4.6.1.2TheprimarycontainmentleakageratesshallbedemonstratedatthefollowingtestscheduleandshallbedeterminedinconformancewiththecriteriaspecifiedinAppendixJof10CFR50usingthemethodsandprovisions'ofANSIN45.4-1972:aec,ThreeTypeAOverallIntegratedContainmentLeakageRatetestsshallbeconductedat40+10monthintervalsduringshutdownatPa,39.75psigoratPt,20.0psig,duringeach10-yearserviceperiod.Thethirdtestofeachsetshallbeconductedduringtheshutdownforthe10-yearplantinserviceinspection.IfanyperiodicTypeAtestfailstomeet0.75Laor0.75Lt,asapplicable,thetestscheduleforsubsequentTypeAtestsshallbereviewedandapprovedbytheCommission.IftwoconsecutiveTypeAtestsfailtomeet0.75Laor0.75Lt,asapplicable,aTypeAtestshallbeperformedatleastevery18monthsuntiltwoconsecutiveTypeAtestsmeet0.75Laor0.75Lt,asapplicable,atwhichtimetheabovetestschedulemayberesumed.TheaccuracyofeachTypeAtestshallbeverifiedbyasupplementaltestwhich:I.ConfirmstheaccuracyofthetestbyverifyingthatthedifferencebetweenthesupplementaldataandtheTypeAtestdataiswithin0.25Laor0.25Lt,asapplicable.NINEMILEPOINT-UNIT23/46-3NOV201985
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTSContinuedd.e.g.h.2.HasdurationsufficienttoestablishaccuratelythechangeinleakageratebetweentheTypeAtestandthesupplementaltest.3.Requiresthequantityofgasinjected,intothecontainmentorbledfromthecontainmentduringthesupplementa'1testtobeequivalenttoatleast25percentofthetotalmeasuredleakageatPa,39.75psig,orPt,20.0psig,asapplicable.TypeBandCtestsshallbeconductedwithgasatPa,39.75psig,"atintervalsnogreaterthan24monthsexceptfortestsinvolving:l.Airlocks,2.Mainsteamlineisolationvalves,3.Containmentisolationvalvesinhydrostaticallytestedlineswhichpenetratetheprimarycontainment,andAirlocksshallbetestedanddemonstratedOPERABLEperSurveillanceRequirement4.6.1.3.Mainsteamlineisolationvalvesshallbeleaktestedatleastonceper18months.TypeBtestsforpenetrationsemployingacontinuousleakagemonitoringsystemshallbeconductedatPa,39.75psig,atintervalsnogreaterthanonceper3years.Leakagefromisolationvalvesthataresealedwithfluidfromasealsystemmaybeexcluded,subjecttotheprovisionsofAppendixJ,SectionIII.C.3,whendeterminingthe.'combinedleakagerateprovidedthesealsystemandvalvesarepressurizedtoatleastl.10Pa,43.73psig,andthesealsystemcapacityisadequatetomaintainsystempressureforatleast30days.Containmentisolationvalvesinhydrostaticallytestedlineswhichpentratetheprimarycontainmentshallbeleaktestedatleastonceper18months.PurgesupplyandexhaustisolationvalveswithresilientmaterialsealsshallbetestedanddemonstratedOPERABLEperSurveillanceRequirements4.6.1.8.2.k.TheprovisionsofSpecification4.0.2arenotapplicable.UnlessahydrostatictestisrequiredperTable3.6.3-1.NINEMILEPOINT-UNIT23/46-4llflll0Ilinnr
TABLE3.6.1.2"1f)g$$ii/gal,'iisg~o~w~ALLOWABLELEAKRATESTHROUGHYALVESINPOTENTIALBYPASSLEAKAGEPATHSLineDescrition4MainsteamlinesMainsteamdrainline(inboard)Mainsteamdrainline(outboard}4PostaccidentsamplinelinesDrywe11equipmentdrainlineDrywellequipmentventlineDrywellfloordrainlineDrywel1floorventline.RWCUlineFeedwaterlineCPSsupplylinetodrywel1CPSsupplylinetodrywel1CPSsupplylinetosupp.chamberCPSsupplylinetosupp.chamberYalveMarkNo2MSS"HYY6A,B,C,D2MSS"HYV7A,B,C,D2MSS"MOY111,1122MSS"MOV2082CMS"SOV77A,B2CMS"SOY74A,B2CMS"SOV?5A,B2CMS"SOV76A,B2DER"MOY1192DER"MOV1202DER"MOY1302DER"MOY1312DFR*MOY1202DFR"MOY1232DFR"MOV1392DFR"MOY1402WCS"MOV1022WCS"MOY1122FWS"AOV23A2FWS"V12A2FWS"AOV23B2FWS"V12B2CPS"AOV1042CPS"AOY1062CPS"SOY1202CPS"SOV1222CP5"AOV1052CPS+AOY1072CPS~AOY1192CPS"AOY121Termi-nation~ReionTurbineBldg.TurbineBldg.TurbineBldg.RadwasteTunnelRadwasteTunnelRadwasteTunnelRadwasteTunnelRadwasteTunnelTurbineBldg.TurbineBldg.StandbyGasTrtmtAreaStandbyGasTrtmtAreaStandbyGasTrtmtAreaStandbyGasTrtmtAreaBypassLeakageBarrier2-21"valvesineachline1-5"valve1"2"valve1-3/4"valveineachline1-4"valve1-2"valve1-6"valve1-3"valve1-8"valve2-24"checkvalves2-14"valves2-2"valves2"12"valves2"2"valves.TechSpecLeakRate(2)SCFH6.01.8750.6250.23441.250.6251.8750.93752.51244.380.6253.750.625(1)StdConditions:(2}TestConditions:14.7psiaand68'FAirmedium;40psigand80'F;LeakratepervalveNINEMILEPOINT-UNIT23/46"5aaVaO>SS5
CONTAINMENTSYSTEMSPRIMARYCONTAINMENTAIRLOCKSLIMITINGCONDITIONFOROPERATiONFCg!},gOPTl!I<}II[f!PI/3.6.1.3EachprimarycontainmentairlockshallbeOPERABLEwith:a.Bothdoorsclosedexceptwhentheairlockisbeingusedfornormaltransitentryandexitthroughthecontainment,thenatleastoneairlockdoorshallbeclosed,andb.Anoverallairlockleakagerateoflessthanorequalto0.05LaatPa,39.75psig.APPLICABILITY:OPERATIONALCONDITIONS1,2"and3.ACTION:Withoneprimarycontainmentairlockdoorinoperable:1.MaintainatleasttheOPERABLEairlockdoorclosedandeitherrestoretheinoperableairlockdoortoOPERABLEstatuswithin24hoursorlocktheOPERABLEairlockdoorclosed.2.OperationmaythencontinueuntilperformanceofthenextrequiredoverallairlockleakagetestprovidedthattheOPERABLEairlockdoorisverifiedtobelockedclosedatleastonceper31days.3.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.4.TheprovisionsofSpecification3.0.4arenotapplicable.b.Withtheprimarycontainmentairlockinoperable,exceptasaresultof~aninoperableairlockdoor,maintainatleastoneairlockdoorclosed;restoretheinoperableairlocktoOPERABLEstatuswithin24hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours."SeeSpecialTestException3.10.1.NINEMILEPOINT-UNIT23/46-6Llhll}lh1MC
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTS4.6.1.3EachprimarycontainmentairlockshallbedemonstratedOPERABLE:Within72hoursfollowingeachclosing,exceptwhentheairlockisbeingusedformultipleentries,thenat'leastonceper72hours,byverifyingsealleakageratelessthanorequalto5scfperhourwhenthegapbetweenthedoorsealsispressurizedtogreaterthanorequalto10psig.b.ByconductinganoverallairlockleakagetestatPa,39.75psigandbyverifyingthattheoverallairlockleakagerateiswithinitslimit:C.l.Atleastonceper6months,and2.PriortoestablishingPRIMARYCONTAINMENTINTEGRITYwhenmaintenancehadbeenperfor'medontheairlockthatcouldaffecttheairlocksealingcapability".Atleastonceper6monthsbyverifyingthatonlyonedoorineachairlockcanbeopenedatatime."~TheprovisionsofSpecification4.0.2arenotapplicable.ExceptiontoAppendixJof10CFR50.ExceptthattheinnerdoorneednotbeopenedtoverifyinterlockOPERABILITYwhentheprimarycontainmentisinerted,providedthattheinnerdoorinterlockistestedwithin8hoursaftertheprimarycontainmenthasbeende-inerted.NINEMILEPOINT-UNIT23/46-7
CONTAINMENTSYSTEMSCONTAINMENTSYSTEMSPRIMARYCONTAINMENTSTRUCTURALINTEGRITYLIMITINGCONDITIONFOROPERATION3.6.1.5ThestructuralintegrityoftheprimarycontainmentshallbemaintainedatalevelconsistentwiththeacceptancecriteriainSpecification4.6.1.5.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:Withthestructuralintegrityoftheprimarycontainmentnotconformingtotheaboverequirements,restorethestructuralintegritytowithinthelimitswithin24hoursorbeinatleastHOT.SHUTDOMNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.6.1;5.1-Thestructuralintegrityoftheexposedaccessibleinteriorandexteriorsurfacesoftheprimarycontainment,includingthelinerplateanddrywelltowetwellbypasspaths,shallbedeterminedduringtheshutdownforeachTypeAcontainmentleakageratetestbyavisualinspectionofthosesurfaces.ThisinspectionshallbeperformedpriortotheTypeAcontainmentleakageratetesttoverifynoapparentchangesinappearanceorotherabnormaldegradation.4.6.1.5.2~geortsAnyabnormaldegradationofthecontainmentstructuredetectedduringtheaboverequiredinspectionsshallbereportedtotheCommis-sionpursuanttoSpecification6.9.2within30days.Thisreportshallincludeadescriptionoftheconditionofthevesselandtheannulusfillconcrete,theinspectionprocedure,thetolerancesonconcretecracking,andthecorrectiveactionstaken.NINEMILEPOINT-UNIT23/46"8HOV8O]ggg l'I CONTAINMENTSYSTEMSDRYWELLANDSUPPRESSIONCHAMBERINTERNALPRESSUREPII'>gPi)).j'gIlt$67!(LIMITINGCONDITIONFOROPERATION3.6.1.6Drywellandsuppressionchamberinternalpressureshallbemaintainedbetween14.2and15.45psia.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:Withthedrywellandsuppressionchamberinternalpressureoutsideofthespecifiedlimits,restoretheinternalpressuretowithinthelimitwithin1hourorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.6.1.6Thedrywellandsuppressionchamberinternalpressureshallbedeterminedtobewithinthelimitsatleastonceper12hours.NINEMILEPOINT-UNIT23/46-9NOV2Plasg
CONTAINMENTSYSTEMSORYWELLAVERAGEAIRTEMPERATURELIMITINGCONDITIONFOROPERATION3.6.1.7Drywellaverageairtemperatureshallnotexceed150'F.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:Withthedrywellaverageairtemperaturegreaterthan150'F,reducetheaverageairtemperaturetowithinthelimitwithin8hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.jrrrSURVEILLANCEREUIREMENTS4.6.1.7Thedrywellaverageairtemperatureshallbethe(arithmetical)averageofthetemperaturesatthefollowinglocationsandshallbedeterminedtobewithinthelimitatleastonceper24hours:a@b.C.d.e.f.g.h.1.J.k.1.Elevation306'-9"294'-5"283'-0"268'-0"255'"6"244'-0"306'-9"296'-4"282'-6"262'-3II253'-l1"244'-0"Azimuth354117'8203326295189323243284169110NINEMILEPOINT-UNIT23/46-10NOy20t985
CONTAINMENTSYSTEMSPRIMARYCONTAINMENTPURGESYSTEMLIMITINGCONDITIONFOROPERATION3.6.1.8Thedrywellandsuppressionchamber12inchand14inchpurgesupplyandexhaustisolationvalvesshallbeOPERABLEand:a.Thepurgesystemmaybeinoperationforupto90hoursper365daysforinerting,deinerting,-eon)~QcPsar4~vJ456~zI"~~3arwklcd<<'0vI(0clQiwk)Purgesystemshallbeblockedtolimitthenidt7('.V~nnB~+epeeAn'vlt'I~LLEW~6d~,APPLICABILITY:OPERATIONALCONDITIOS1,2and3.ACTION:b.C.rourWiththedrywellandsuppressionchamberpurgesupplyand/orexhaustisolationvalve(s)inoperableoropenformorethan90hoursper365daysforotherthanpressurecontrol,closetheopenvalve(s);otherwiseisolatethepenetration(s)withinfourhoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Withadrywellandsuppressionchamberpurgesupplyand/orexhaustisolationvalve(s)withresilientmaterialsealshavingameasuredleakagerateexceedingthelimitofSurveillanceRequirements4.6.1.8.2restoretheinoperablevalve(s)toOPERABLEstatuswithin24hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.6.1.8.1Atleastonceper31dayseachdrywellandsuppressionchamberpurgesupplyandexhausisolationvalveofSpecification3.6.1.8.bshallbeverifieblockedtolimittheopeningto70~+CoNINEMILEPOINT-UNIT23/46-11NOV201985
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTSContinued4.6.1.8.2Atleastonceper92dayseach12and14inchdrywellandsuppressionchamberpurgesupplyandexhaustisolationvalvewithresilientmaterialsealsshallbedemonstratedOPERABLEbyverifyingthatthemeasuredleakagerateislessthanorequalto4.38scfperhourper14inchvalveand3.75scfperhourper12inchvalvewhenpressurizedto40psig.NINEMILEPOINT"UNIT23/46-12NDV201gg-
CONTAINMENTSYSTEMS3/4.6.2DEPRESSURIZATIONSYSTEMS~~SUPPRESSIONPOOLLIMITINGCONDITIONFOROPERATIONp)A<(p,(pe~i~~n~~~3.6.2.1ThesuppressionpoolshallbeOPERABLEwith:a.Thepoolwater:l.Volumebetween154,794ftand145,495ft,equivalenttoan33elevationbetween201'nd199'-6"anda2.'Maximumaveragetemperatureof90~FduringOPERATIONALCONDITION1or2,exceptthatthemaximumaveragetemperaturemaybepermittedtoincreaseto:a)105~Fduringtestingwhichaddsheattothesuppressionpool.b)110'FwithTHERMALPOWERlessthanorequalto1XofRATEDTHERMALPOWER.c)120Fwiththemainsteamlineisolationvalvesclosedfollowingascram.b.Drywell-to-suppressionpoolbypassleakagelessthanorequalto10KoftheacceptableA/~Kdesignvalueof0.054ft~.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:a.b.Withthesuppressionpoolwaterleveloutsidetheabovelimits,restorethewaterleveltowithinthelimitswithin1hourorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.InOPERATIONALCONDITION1or2withthesuppressionpoolaveragewatertemperaturegreaterthan90Frestoretheaveragetemperature'olessthanorequalto90Fwithin24hoursorbeinatleastHOTSHUTDOWNwithinthenext12hours'andinCOLDSHUTDOWNwithinthefollowing24hours,except,aspermittedabove:1.Withthesuppressionpoolaveragewatertemperaturegreaterthan105'Fduringtestingwhichaddsheattothesuppressionpool,stopalltestingwhichaddsheattothesuppressionpoolandrestoretheaveragetemperaturetolessthan90Fwithin24hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.2.Withthesuppressionpoolaveragewatertemperature.greaterthan:a)90Fformorethan24hoursandTHERMALPOWERgreaterthan2XofRATEDTHERMALPOWER,beinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWNwithinthenext24hours.b)110F,placethereactormodeswitchintheShutdownpositionandoperateatleastoneresidualheatremovalloopinthesuppressionpoolcoolingmode.NINEMILEPOINT"UNIT23/46-13NQV201985
-CONTAINMENTSYSTEMSLIMITINGCONDITIONFOROPERATIONContinuedACTION:(Continued)PI)O(IQ,'t))giT'CIIIte(pat3.Withthesuppressionpoolaveragewatertemperaturegreaterthan120'F,depressurizethereactorpressurevesseltolessthan200psigwithin12hours.c.Withonesuppressionpoolwatertemperatureinstrumentationchannelinanypair(s)oftemperatureinstrumentationchannelsinthesamesectorinoperable,restoretheinoperablechannel(s)toOPERABLEstatuswithin7daysorverifysuppressionpoolwatertemperaturetobewithinthelimitsatleastonceper12hours.d.Withbothsuppressionpoolwatertemperatureinstrumentationchannelsinanypair(s)oftemperatureinstrumentationchannelsinthesamesectorinoperable,restoreatleastoneinoperablewatertemperatureinstrumentationchannelineachpairoftemperatureinstrumentationchannelsinthesamesector.toOPERABLEstatuswithin8hoursorbeinatleastHOTSHUTDOWNwithin-thenext12hoursandinCOLDSHUTDOWNwithinthefollowing24h'ours.e.Withthedrywell-to-suppressionpoolbypassleakageinexcessof~thelimit,restorethebypassleakagetowithinthelimitpriortoincreasingreactorcoolanttemperatureabove200'F.SURVEILLANCEREUIREMENTS4.6.2.1aeb.Thesuppressionpoolshall.bedemonstratedOPERABLE:Byverifyingthesuppressionpoolwatervolumetobewithinthelimitsatleastonceper24hours.Atleastonceper24hoursinOPERATIONALCONDITION1or2byverifyingthesuppressionpoolaveragewatertemperaturetobelessthanorequalto90F,except:l.Atleastonceper5minutesduringtestingwhichaddsheattothesuppressionpoolbyverifyingthesuppressionchamber.averagewatertemperaturelessthanorequalto105F.2.Atleastonceperhourwhensuppressionpoolaveragewatertemperatureisgreaterthanorequalto90F,byveri-fying:a)Suppressionpoolaveragewatertemperaturetobelessthanorequa'lto110'F,andb)THERMALPOWERtobelessthanorequaltoIofRATEDTHERMALPOWERaftersuppressionpoolaveragewatertemperaturehasexceeded90Fformorethan24hours.3.Atleastonceper30minutesfollowingascramwithsuppressionpoolaveragewatertemperaturegreaterthanorequalto90F,byverifyingsuppressionpoolaveragewatertemperaturelessthanorequalto120F.NINEMILEPOINT"UNIT23/46"14go/4'eeKrvJ
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTSContinuedgQgQQggp~qpygmyliaUVICt~'cj.~J~LID~c.Byverifyingatleasttwentysuppressionpoolwatertemperatureinstrumentationchannels,atleastonepairineachof10suppressionpoolsectors,OPERABLEbyperformanceofa:1.CHANNELCHECKatleastonceper24hours,2.CHANNELFUNCTIONALTESTatleastonceper31days,and3.CHANNELCALIBRATION~atleastonceper18months,withthewaterhightemperaturealarmsetpointfor<90'F.d.Atleastonceper18monthsbyconductingadrywell-to-suppressionpoolbypassleaktestataninitialdifferentialpressureof3psiandverifyingthattheA/~Kcalculatedfromthemeasured~leakageiswithinthespecifiedlimit.Ifanydrywell-to-suppressionpoolbypassleaktestfails.tomeetthespecifiedlimit,thetestscheduleforsubsequenttestsshallbereviewedandapprovedbytheCommission.Iftwoconsecutivetestsfailtomeetthespecifiedlimit,atestshallbeperformedatleastevery9monthsuntiltwoconsecutivetestsmeetthespecifiedlimit,atwhichtimethe18monthtestschedulemayberesumed.1"Calibrationexcludessensors;.sensorscomparisonsshallbemadeinlieuofcalibration.NINEMILEPOINT-UNIT23/46"15BGY201985
CONTAINMENTSYSTEMSSUPPRESSIONPOOLANDDRYWELLSPRAYLIMITINGCONDITIONFOROPERATION3.6.2.2Thesuppressionpoolanddrywellspraymodeoftheresidualheatremoval(RHR)systemshallbeOPERABLEwithtwoindependentloops,eachloopconsistingof:a.OneOPERABLERHRpump,andb.AnOPERABLEflowpathcapableofrecirculatingwaterfromthesuppressionpoolthr'oughanRHRheatexchangerandthesuppressionchamberanddrywellspraysparger(s).APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:'a0b.Withonesuppressionchamberand/ordrywellsprayloopinoperable,restoretheinoperablelooptoPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Withbothsuppressionchamberand/ordrywellsprayloopsinoperable,restoreatleastonelooptoOPERABLEstatuswithin8hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWN"withinthefollowing24hours.SURYEILLANCEREUIREMENTS4.6.2.2ThesuppressionchamberanddrywellspraymodeoftheRHRsystemshallbedemonstratedOPERABLE:a.'tleastonceper31daysbyverifyingthateachvalve,(manual,pova.roperatedorautomatic)intheflowpaththatisnotlocked,sealedorotherwisesecuredinposition,isinitscorrectposition.b.C.ByverifyingthateachoftherequiredRHRpumpsdevelopsaflowofatleast450gpmonrecirculationflowthroughtheRHRheatexchangerandsuppressionpoolsprayspargerwhentestedpursuanttoSpecification4.0.5.Byperformanceofanairflowtestofthedrywellspraynozzlesatleastonceper5yearsandverifyingthateachspraynozzleisunobstructed.WheneverbothRHRsubsystemsareinoperable,ifunabletoattainCOLDSHUTDOWNasrequiredbythisACTION,maintainreactorcoolanttemperatureaslowaspracticalbyuseofalternateheatremovalmethods.NINEMILEPOINT"UNIT23/46"16gQV201MS
CONTAINMENTSYSTEMSSUPPRESSIONPOOLCOOLINGtLIMITINGCONDITIONFOROPERATIONPIPJ/A$0glgil&ilf$+7$f3.6.2.3Thesuppressionpoolcoolingmodeoftheresidualheatremoval(RHR)systemshallbeOPERABLEwithtwoindependentloops,eachloopconsistingof:a.OneOPERABLERHRpump;andb.AnOPERABLEflowpathcapableofrecirculatingwaterfromthesuppressionchamberthroughanRHRheatexchanger.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:aoWithonesuppressionpoolcoolingloopinoperable,restoretheinoperablelooptoOPERABLEstatuswithin72hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Withbothsuppressionpoolcoolingloopsinoperable,beinatleastHOTSHUTDOWNwithin12hoursandinCOLDSHUTDOWN~withinthenext24hours.SURVEILLANCEREUIREMENTS4.6.2.3ThesuppressionpoolcoolingmodeoftheRHRsystemshallbedemonstratedOPERABLE:a0b.Atleastonceper31daysbyverifyingthateachvalve,manual,poweroperatedorautomatic,intheflowpaththatisnotlocked,sealedorotherwisesecuredinposition,isinitscorrectposition.ByverifyingthateachoftherequiredRHRpumpsdevelopsaflowofatleast7450gpmonrecirculationflowthroughtheRHRheatexchangerandthesuppressionpoolwhentestedpursuanttoSpecification4.0.5.WheneverbothRHRsubsystemsareinoperable,ifunabletoattainCOLDSHUTDOWNasrequiredbythisACTION,maintainreactorcoolanttemperatureaslowaspracticalbyuseofalternateheatremovalmethods.NINEMILEPOINT-UNIT23/46-17NOV"01985
CONTAINMENTSYSTEMS3/4.6.3PRIMARYCONTAINMENTISOLATIONVALVESLIMITINGCONDITIONFOROPERATION3.6.3TheprimarycontainmentisolationvalvesandthereactorinstrumentationlineexcessflowcheckvalvesshowninTable3.6.3-1shallbeOPERABLEwithisolationtimeslessthanorequaltothoseshowninTable3.6.3-1.APPLICABILITY:OPERATIONALCONDITIONS1,2and3ACTION:a.WithoneormoreoftheprimarycontainmentisolationvalvesshowninTable3.6.3-1inoperable,maintainatleastoneisolationvalveOPERABLEineachaffectedpenetrationthatisopenandwithin4hourseither:1.Restortheinoperablevalve(s)toOPERABLEstatus,or2.Isolateeachaffectedpenetrationbyuseofatleastonedeactivatedautomaticvalvesecuredinthe.isolatedposition,"or3.Isolateeachaffectedpenetrationbyuseofatleastoneclosedmanualvalveorblindflange."Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandin~~~~~~COLDSHUTDOWNwithinthefollowing24hours.b.With,oneormoreofthereactorinstrumentationlineexcessflowcheckvalvesshowninTable3.6.3-1inoperable,operationmaycontinueandtheprovisionsofSpecifications3.0.3and3.0.4arenotapplicableprovidedthatwithin4hourseither;1.TheinoperablevalveisreturnedtoOPERABLEstatus,or2.Theinstrumentlineisisolatedandtheassociatedinstrumentisdeclaredinoperable.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Isolationvalvesclosedtosatisfytheserequirementsmaybereopenedonanintermittentbasisunderadministrativecontrol.NINEMILEPOINT"UNIT23/46-18NOV201985
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTS$jg'g~$~$1p~pRlf>Pip)i4.6.3.1EachprimarycontainmentisolationvalveshowninTable3.6.3-1shallbedemonstratedOPERABLEpriortoreturningthevalvetoserviceaftermainte"nance,repairorreplacementworkisperformedonthevalveoritsassociatedactuator,controlorpowercircuitbycyclingthevalvethroughatleastonecompletecycleoffulltravelandverifyingthespecifiedisolationtime.4.6.3.2EachprimarycontainmentautomaticisolationvalveshowninTable3.6.3-1shallbedemonstratedOPERABLEduringCOLDSHUTDOWNorREFUELINGatleastonceper18monthsbyverifyingthatonacontainmentisolationtestsignaleachautomaticisolationvalveactuatestoitsisolationposition.4.6.3.3TheisolationtimeofeachprimarycontainmentpoweroperatedorautomaticvalveshowninTable3.6.3-1shallbedeterminedtobewithinitslimitwhentestedpursuanttoSpecification4.0.5.4.6.3.4EachreactorinstrumentationlineexcessflowcheckvalveshowninTable3.6.3-1shallbedemonstratedOPERABLEatleastonceper18monthsbyverifyingthatthevalvechecksflow.4.6.3.5Eachtraversingin-coreprobesystemexplosiveisolationvalveshallbedemonstratedOPERABLE:aob.Atleastonceper31daysbyverifyingthecontinuityoftheexplosivecharge.Atleastonceper18monthsbyremovingatleastoneexplosivesquibfromatleastoneexplosivevalve,suchthateachexplosivesquibineachexplosivevalvewillbetestedatleastonceper36months,andinitiatingtheexplosivesquib.Thereplacementchargefortheexplodedsquibshallbefromthesamemanufacturedbatchastheone.firedorfromanotherbatchwhichhasbeencertifiedbyhavingatleastoneofthatbatchsuccessfullyfired.Nosquibshallremaininusebeyondtheexpirationofitsshelf-lifeandoperatinglife,asapplicable.NINEMILEPOINT"UNIT23/46-19NQV2G1985
Table3.6.3-1PRIMARYCONTAINMENTISOLATIONVALVESA.AUTOMATICIISOLA108IIA~LVSVALVENUMBERANDFUNCTIONVALVEGROUPSISOLATIONSIGNALSHAXIMUHCLOSINGTIME(SECONDS)2HSS"HYV6A,B,C,D2HSS*HYV7A,B,C,D2HSS*MOV2082MSS"HOVlll2HSS"HOV1122RMS*HOV33A,B2RHSAMOV1042RMS"HOV40A,B2RHS"HOV67A,B2RHS'"HOV1122RHS*HOV1132CSH*HOVlll2ICS*MOV164InsideMSIVOutsideMSIVDSLDrainLineOutsideIVHainSteamDrainLineInsideIVHainSteamDrainLineOutsideIVRNSCont.SprayOutsideIV'sRHSReactorHeadSprayOutsideIVShutdownCoolingReturnOutsideIV'sSDCInboardIVBypassValvesSDCSupplyInsideIVSDCSupplyOutsideIVCSHTestReturntoSuppressionPoolOutsideIVRCICVacuumBreakerOutsideIV11155555Z,X,C,D,E,P,T,R,RH,AAZ,X,C,D,E,P,T,R,RH,AAZ,X,C,D,E,P,T,R,RH,AAZ,X,C,D,E,P,T,R,RH,AAZ,X,C,D,E,P,T,R,RH,AA~RH~cuwSmA,L,H,Z,RH>cc.~~gRHcwJmsV~HF,RH3to53to515151535504015454560152CCP"HOV94A,B2CCP"HOV17A,B2CCP"HOV16A,B2CCP"MOV15A,B2DFR"HOV1202DFR*HOV121CCPSupplytoRCSInsideIV's8CCPSupplytoRCSOutsideIV's8CCPReturnfromRCSPumpsInsideIV's8CCPReturnfromRCSPumpsOutsideIV's8DFRDrainTank-.Veal-LineOutsideIVDFRDrainTangPen-LineInsideIVB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,FRZ,RH303030304545
Table3.6.3-1(Cont.)PRIMARYCONTAINHENTISOLATIONVALVESCIM2DER"MOV1192DER*MOV1202RCSASOV1042RCS"SOV105IVALVENUMBERANDFUNCTIONDERLinefromDrywellInsideIVDERLinefromDrywellOutsideIVRCSSampleInsideIVRCSSampleOutsideIVVALVEGROUPSISOLATIONSIGNALSB,F,Z,RHB,F,Z,RMB,C,Z,RHB,C,Z,RMMAXIMUMCLOSINGTIME(SECONDS)3535NANA~eever~2DFR"MOV1392DFR*HOV1402DER*MOV1302DER"MOV1312CCP*MOV2652CCP"MOV2732CCP*MOV1222CCPAMOV124DFRVentLineOutsideIV8DFRVentLineInsideIV8DERVentLineInsideIVDERVentLineOutsideIVSplytoDrywellSpaceCoolerOutsideIVSplytoDrywellSpaceCoolerInsideIVReturnfromDrywellSpaceCoolerInsideIVReturnfromDrywellSpaceCoolerOutsideIVB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RH2525151560606060CS(DO3CJI2CPSAAOV1042CPS*AOV1052CPS"AOV106(n)2CPS~"AOV107(n)2CPS"AOV108(n)2CPS"AOV109(n)2CPSAAOV1102CPS"AOV111PurgePurgePurgePurgePurgePurgePurgePurgeInlettoDrywellOutsideIV9InlettoSup.ChamberOutsideIV9InlettoDrywellInsideIV9InlettoSup.ChamberInsideIV9ExhaustfromDrywellInsideIV9ExhaustfromSup.ChamberInsideIV9.ExhaustfromDrywellOutsideIV9ExhaustfromSup.ChamberOutsideIV9B,F,Y,Z,RHB,F,Y,Z,RMB,F,Y,Z,RHB,F,Y,Z,RHB,F,Y,Z,RHB,F,Y,Z,RHB,F,Y,Z,RMB,F,Y,Z,RH
Tabl3-1(Cont.)PRIHARYCONTAItISOLATIONVALVES.MmVALVENUMBERANDFUNCTIONVALVEGROUPSISOLATIONSIGNALSHAXIMUMCLOSINGTIME(SECONDS)C)ZOCOtDCAmC)MM2IASASOV1642IASASOV1652IASASOV1662IASASOV1842IAS"SOV1682IAS*SOV1802IAS*SOV1672IAS"SOV1852HCS*MOVlA,B2HCS"MOV2A,B2HCS"MOV3A,B2HCS"HOV4A,B(n)2HCS"thOV5A,B(n)2HCS*MOVGA,B(n)2CPS*SOV119oa~42CPSASOV1202CPS"SOV121(n)2CPS*SOV122(n)2CHS"SOV24A,B,C,D2CHS"SOV26A,B,C,D2CHS"SOV32A,B2CMS"SOV33A,B(n)2CMS"SOV34A,B(n)2CHS"SOV35A,B2CHS"SOVGOA,B2Ct1S"SOV61A,B(n)2CMS"SOV62A,B2CHS"SOV63A,B(n)ADSHdrAN2supplyADSHdrBN2supplyIASDrywellReliefValveIASDrywellReliefValveInst.AirtoTestableCheckOutsideIVInst.AirtoTestableCheckInsideIVIAStoTestCk.8Vac.Bkrs.OutsideIVIAStoTestCk.8Vac.Bkrs.InsideIVH2RecombinersSplytoSupp.ChamberOutsideIV'sH2Recomb.Ret.fromSupp.Chamber'utsideIV'sH2Recomb.ReturnfromDrywellOutsideH2Recomb.Suply.toSupp.ChamberInsideIV'sH2Recomb.Ret.fromSupp.ChamberInsideIV'sH2Recomb.Ret.fromDrywell~InsideIV'sContainmentPurgetoSupp.Chamber-h~e-IVContainmentPurgetoDrywellOutsideIVContainmentPurgetoSupp.ChamberInsideIVContainmentPurgetoDrywellInsideIVCMSfromDrywellInside8OutsideIV'sCt1SfromSPInsidetmOutsideIV'sCHStoDrywellOutsideIV'sCHStoDrywellInsideIV'sCHStoSPInsideIV'sCHStoSPOutsideIV'sCHStoDrywellOutsideIV'sCt1StoDrywellInsideIV'sCHStoDrywellOutsideIV'sCHStoDrywellInsideIV'sB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RMB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RMB,F,Y,Z,RHB,F,Y,Z,RHB,F,Y,Z,RHB,F,Y,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RMB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHNANANANANANANANA303030303030NANANANANANANANANANANANAC>AeC.'N~~~1~~cr
Table3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESCIMI2LHS*SOV152(i)2LMS"SOV153(i)2LHS"SOV156(1)2LHS"SOV157(i)2RCS*SOV65A,B(L)2RCS*SOV66A,'B(L)2RCS"SOV67A,B(L)2RCSASOV68A,B(L)2RCS"SOV79A,B(L)2RCSASOV80A,B(L)2RCS"SOV81A,B(L)2RCSASOV82A,B(L)VALVENUMBERANDFUNCTIONLMSfromDrywellInsideIVLHSfromDrywellOutsideIVLHSfromSPInsideIVLHSfromSPOutsideIVHyd.UnittoRCSFCV'sOutsideIV'sHyd.UnittoRCSFCV'sOutsideIV'sNyd.UnittoRCSFCV'sOutsideIV'sHyd.UnitfromRCSFCV'sOutsideIV'hHyd.UnittoRCSFCV'sInsideIV'sHyd.UnittoRCSFCV'sInsideIV'sHyd.UnittoRCSFCV'sInsideIV'sHyd.UnitfromRCSFCV'sInsideIV'sVALVEGROUPS888888I88ISOLATIONSIGNALSB,F,Z,RMB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHB,F,Z,RHMAXIMUMCLOSINGTIME(SECONDS)NANANANANANANANANANANANA2ICS"MOV1212ICS"HOV128(n)2ICSAMOV170RCICSteamsupplyOutsideIVRCICSteamsupplyInsideIVRCICMarmupValveInsideIV101010K,H,H,Z,RH,BB~+PO14K,H~H~Z~RH~BBc,qPo14K,H,H,Z,RH,BB>cc~>920~KC)2MCS*HOV1022WCS*MOV1122ICS"MOV148TIPBALLVALVES(SOVs)(A,B,C,D,E)2GSN*SOV166MCSSupplyfromRCS&RPVInsideIVMCSSupplyfromRCS&RPVOutsideIVRCICVacuumBreakerOutsideIVNitrogenPurgetoTIPIndexingMechanismOutsideIVB,J,U,S,Z,RH>c~B,J,US,Z,R+PD,RHB,F,Z,RHB,F,Z,RH1414$~$:~W~S~ac3g~IS
,Table3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVES2RHS*HOV142(j)(m)2RHS*HOV149(j)(m)2RHS*SOV35A/B(j)(m)2RHS"SOV36A/B(j)(m)2RDS*AOV124(k)C~~2RDS"AOV132(k)C~')2RDS'"AOV123(k)b)2RDS'"AOV130(k)~~)B.REHOTEMANUAL~5lONAYES2RHS"HOV15A,BVALVENUMBERANDFUNCTIONRHRDraintoRadwasteOutsideIVRHRDraintoRadwasteInsideIVRHRSampleInsideIVsHexRHRSampleOutsideIVsHexSCRAi]DischargevolumeventSCRAMDischargevolumeventSCRAMDischargevolumedrainSCRAMDischargevolumedrainContainmentSpraytoDrywellOutsideIV'sVALVEISOLATIONGROUPSSIGNALSA,H,Z,F,RHp~cpPQA,H,Z,F,RHpec>zgA,H,Z,F,RH>ccrc~~N/AN/AN/AN/AgzRHMAXIMUMCLOSINGTIME(SECONDS)1816NANA303030301302RHS"MOV1A,B,C,2RHS"HOV30A,B2RHS"MOV25A,B(n)2RHS"HOV24A,B,C2CSH"MOV118(n)2CSH*MOV1052CSH*HOV1072CSL"MOV1122CSL"HOV1042ICS"HOV136(n)2ICS*MOV143(n)RHSPumpSuctionOutsideIVsRHSTestLinetoSPOutsideIvsContainmentSpraytoDrywellOutsideIVsRHS/LPCItoRPVOutsideIVsCSHSuctionfromSPOutsideIVHPCSHinFlowBypassOutsideIVCSHtoRPVOutsideIVCSLSuctionfromSPOutsideIVCSLtoRPVOutsideIVICSSuctionfromSPOutsideIVICSHinflowtoSPOutsideIV13'2RHlgzRH1$ZRH13'2'MljfZRHL3z.RM18~RH182RH13zRHlPZRH18'~RH6013013030301045130605010
MImTable3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESMCDCDCDCD2ICS"MOV122(n)2ICS"HOV126TIPSNEAR(EXPLOSIVE)VALVESA,B,C,D,E2FWS*MOV21A,B2WCS"MOV2002RHS*HOV26A,B(C)2RNS+HOVjf7A,B(C)2HSS*SOV97A,B,C,DC.MANUALISOLATIONVALVES2SAS*HCV160(b)2SASAHCV161(b)2SAS"HCV162(b)2SAS*HCV163(b)2AASAHCV134(b)2AASAHCV135(b)2AAS"HCV136(b)2AASAHCV137(b)2FWS"AOV23A,B(h)2FWS"V12A,BVALVENUMBERANDFUNCTIONICSturbineexhausttoSPICStoRPVOutsideIVFeedwatertoRPVOutsideIVsWCStoRPVOutsideIVRHSHxventInboardIVsRHSHxventOutboardIVsHainSteamLineDrains=SAStoDrywellOutsideIVSAStoDrywellOutsideIVSAStoDrywellInsideIVSAStoDrywellInsideIVAAStoDrywellOutsideIVAAStoDrywellOutsideIVAAStoDrywellInsideIVAAStoDrywellInsideIVFeedwatertoRPVOutsideIVsFeedwatertoRPVInsideIVsVALVEISOLATIONGROUPSSIGNALSlE7RH18ZRMleapRHRH13'~RHg'~RH13'2RMRMMAXIMUMCLOSINGTIHE(SECONDS)9020NA80651515
MmMImTable3.6.3-1(Cont.)lPRIMARYCONTAINMENTISOLATIONVALVESC)Ma2RHS"AOY16,A,B,C(h)2RHS"AOV39,A,B,C(h)2CSH"AOV108(h)2CSLAAOV101(h)2ICS"AOV156(h)2ICSAAOV157(h)2SLSAV102SLS"HOV5A,B(g)2FPW-V629(i)2GSN"V1702IAS"V4482IASAV4492SFCAV2032SFC*V204YALYENUHBERANDFUNCTIONRHS/LPCItoRPVInsideIVsSDCtoRCSInsideIVsCSHtoRPVInsideIVCSLtoRPVInsideIVICStoRPVOutsideIVICStoRPVInsideIVSLStoRPVInsideIVSLStoRPVOutsideIVFireWatertoDrywellStandpipesInsideIVNqPurgetoTipIndexMech.InsideIVIAStoADSAccumulatorsInsideIVIAStoAOSAccumulatorsInsideIVInnerRefuelSealLeakoffOutboardIVInnerRefuelSealLeakoffInboardIVVALVEISOLATIONGROUPSSIGNALSHAXIHUHCLOSINGTINE(SECONDS)CD2RCS~V59A,B2RCSAV60A,B2RCSAV90A,B2RHS"V19(d)(f)2RHS"V20(d)(f)2RHSAV117(d)(f)2RHSAV118(d)(f)RDStoRCSPumpASealOutsideIYsRDStoRCSPumpASealInsideIVsRDStoRCSPumpASealOutsideIVsDisckargeCheckfromRCICtoSupp.PoolDischargeCheckfromRCICtoSupp.PoolCheckVa]vefromRCICDraintoSupp.PoolCheckValvefromRCICDraintoSupp.Pool
MmTable3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESC)MiVALVENUMBERANDFUNCTIOND.OTHERISOLATIONVALVESSAFETYRELIEFVALVES(d)VALVEISOLATIONGROUPSSIGNALSMAXIMUMCLOSINGTINE(SECONDS)2RHS*RV20A,B,C2RHSARV61A,B,C2RHS*RV1082RHSARV1102RHS"RV139~2RHS"RV1522RHS"RV56A,B2RHSARV34A,B2RHS"RV62A,B2RHSARVV35A,B2CSLARV1052CSL"RV1232RHS"RVV36A,B2CSHARV1132CSH"RV114RHSRvdisch.toSPOutsideIVsRHSRvdisch.toSPOutsideIVsRHSRvdisch.toSPOutsideIVsSDCtoRHRPumpsuctionRvRHRHdr.FlushtoRadwasteRVSDCSupplyfromRCSRVInsideIVRHSHxshellsideRVsRHSHxsteamsupplySafetyvalvesRHSHxsteamsupplySafetyvalvesRHSVacuumBreakersCSLRVDisch.toSPOutsideIVCSLRVDisch.toSPOutsideIVRHSVacuumBreakersCSHRVDisch.toSPOutsideIVCSHRVDisch.toSPOutsideIVCOCSCACJl2ISC*EFV12ISC"EFV22ISC"EFV32ISCAEFV4Inst.Inst.Inst.Inst.LinefromHSSLinefromN14200oLinefromN14,160LinefromN13,1902ISC"EFV52ISC"EFV6Inst.Linefrq,mN14,20~Inst.LinefromN14,3404EXCESSFLOWCHECKVALVES(e)REACTORINSTRUMENTATIONLINESCMCl5~S~Q~ZJgQAICJ~CiMemQl~~A
7Table3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESVALVENUMBERANDFUNCTIONVALVEISOLATIONGROUPSSIGNALSMAXIMUMCLOSINGTIME(SECONDS)2ISC*EFV72ISCAEFV82ISC"EFV102ISC*EFVll21SCAEFV132ISCAEFV142ISC"EFV1521SCAEFV172ISC"EFV182ISC*EFV202ISC"EFV212ISC"EFV222ISC*EFV232ISCAEFV242ISC"EFV252ISCAEFV262ISC"EFV272ISC"EFV282ISCAEFV292ISC"EFV302ISCAEFV3121SCAEFV322ISC"EFV33Inst.LinefromN13,10'nst.LinefromN12,160Inst.LinefromN12,200'o2ISC"FT47K,FT48BTo2ISC"FT47HVesselBottomtap,loopAJetPumpInst.LinefromN12,340'nst.LinefromN12,20~To2ISC"FT47J,FT48ATo2ISC"FT47EVesselBottomtapforCSH,RDSVesselBottomTapforMCSandLoopBJ.P.lTo2ICS*FT48CandPostAccidentSamplingTo2ISC"FT480andPostAccidentSamplingTo2ISC"FT47LTo2ISC"FT47CTo2ISC"FT47ATo2ISC"FT47RTo2ISC"FT47GTo2ISC"FT47NTo2ISC"FT48ATo2ISC"FT47TTo2ISC"FT47V,FT48CnCWCi
,MmMmTab1e3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESC)MIVALVENUHBERANDFUNCTIONVALVEISOLATIONGROUPSSIGNALSMAXIMUMCLOSINGTIME(SECONDS)2ISCAEFV342ISCAEFV352ISC"EFV362ISC*EFV372ISCAEFV3821SCAEFV392ISCAEFV402ISC"EFV412ISC*EFV422ISC"EFV92ISC*EFV122ISC"EFV162ISCAEFV192CHS*EFV1A2CHS*EFV1B2CMS"EFV3A2CMS"EFV3B2CHS*EFV5A2CHS"EFV5B2CHS"EFV62CMS"EFVBA2CHS"EFVBB2CHS"EFV9A2CHS"EFV9B2CHS"EFV102ICS*EFV12ICS"EFV2ToCHS"PT1AToCMS"PT1BToCHS"PT2AToCMS"PT28ToCHS"PT7AToCHS*PT7BToCHS*TRPkToCHS"LT9A,ToCHS"LT9B,ToCHS"LT9A,ToCHS"LT9B,ToCHS-P1173PT<c.Y11Aqtt411B)t~SllApltwllB>ioSTo2ICS*PDT167To2ICS"PDT167oMEQ*pg43~To2ISC"FT47BTo2ISC*FT47DTO2ISCAFT47FTo2ISC"FT47STo2ISC"FT47HTo2ISC"FT47PTo2ISC*FT48BTo2ISC"FT47UTo2ISC"FT47W,FT48DContainmentPressure2ISC*PT15C,16B,16DContainmentPressure2ISC"PT15B,17B,170ContainmentPressure2ISC"PT15A,16A,16C>ContainmentPressure2ISC"PT15D,17A,17Cel~3
.MmMImTable3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESEDIM2ICS"EFV32ICS"EFV4VALVENUMBERANDFUNCTIONTo2ICS*PDT168To2ICS"PDT168VALVEISOLATIONGROUPSSIGNALSMAXIMUMCLOSINGTIHE(SECONDS)CAIColID2IAS*EFV2002IAS"EFV2012IAS"EFV2022IAS"EFV2032IAS"EFV2042IAS"EFV2052IAS*EFV2062RHS"EFV5,62RHS"EFV7To2IAS"PT230offTo2IAS"PT231offTo21AS"PT232offTo2IAS"PT233offTo2IAS"PT234offTo2IAS"PT235offTo2IAS*PT236offTo2RHS"PDT18BTo2RHS"PDT18AADSAccum.ADSAccum.ADSAccum.ADSAccum.ADSAccum.ADSAccum.ADSAccum.EDR4'HSS"EFV1A,B,C,D2HSS"EFV2A,B,C,D2HSS"EFV3A,B,C,D2HSS"EFV4A,B,C,D2RCS"EFV44A,B2RCS"EFV45A,B2RCS*EFV46A,B2RCS*EFV47A,B2RCS"EFV48A,B2RCS"EFV52A,B2RCS"EFV53A,B2RCS"EFV62A,B2RCS"EFV63A,BToFlowelementsA,B,C,DToFlowelementsA,B,C,DToFlowelementsA,B,C,DToFlowelementsA,B,C,DTo2RCS*PT84A/BT2RCS~Fi2RCS~+TTo2RCS"FT6A/B,FT8A/8To2RCS"FT6A/B,FT8A/BTo2RCS"PDT~(s4/9To2RCS"PDT~lSAJSTo2RCS"PT~5H~WSTo2RCS"PT+H}A4steamlinessteamlinessteamlinessteamlines"la/S,Fz'tA/5q&SWTqQg%3E."3l-sgC
.Table3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESVALVEFUNCTIONANDNUMBERVALVEISOLATIONGROUPSSIGNALSMAXIMUMCLOSINGTIME(SECONDS)2WCSAEFV2212WCS*EFV2222WCSAEFV2232WCS"EFV2242WCS*EFVMOs~oTo2WCS-FT134To2WCS"FT67X,To2WCS"FT67YTo2WCS"FT67YTo2WCS*FT67X,PDS115PDS1152CSH"EFV12CSH"EFV22CSHAEFV32CSL"EFV1To2CSIPLT123,LT124To2CSH"LT123,LT124To2CSH"PDT109To2CSL*PDT132and2RHS"PDT18AITABLENOTATION(a)SeeSpecification3.3.2,Table3.3.2-1,Table3.3.2-4andTable3.3.2-5forisolationsignal(s)thatoperateeachvalvegroup.(b)Maybeopenedonanintermittentbasisunderadministrativecontrol.(c)ThesevalvesaretheRHRheatexchangersventlinesisolationvalves.TheventlineconnectstotheRHRsafetyreliefvalves(SRVs)DischargeHeaderbeforeitpenetratestheprimarycontainment.ThepositionindicatorsforthesevalvesareprovidedintheControlRoomforremotemanualisolation.NotsubjecttTypeCtest.(d)NotsubjecttoTypeCleakagetests.(e)SubjecttoTypeAtest.TypeCtestnotrequired.(f)Thesevalvesarecheckvalves,locatedonthevacuumbreakerlinesforRHRSRVsdischargeheaders.TheSRVdischargeheaderterminatesunderpoolwaterandthereforehasnocontainmentisolationvalves.othethanthoseonlinesfeedingintoit.9
MmMIITIMITable3.6.3-1(Cont.)PRIMARYCONTAINMENTISOLATIONVALVESTABLENOTATION(g)2SLSHOV5A8Bareglobestopcheckvalves.Thesevalvescloseuponreverseflow.Themotoroperatorisprovidedtoremotemanuallyclosethevalvefromthecontrolroom.(h)Thesevalvesaretestablecheckvalves.Theycloseuponreverseflow.Theairoperatoroneachvalveisprovidedonlyforperiodictestingofthevalve.Thesevalvescanonlybetestedagainstazerod/p.(i)Valvesclosedandtheassociatedsystemisisolatedduringnormaloperation.(j)Hotprimarycontainmentpenetrationisolationvalves.Thesevalvescloseonanisolationsignaltoprovideintegrityof"A"and"B"LPCIloops.(k)ValvescloseonaSCRAMsignal;notpartofPrimaryContainmentIsolationSystem.(1)NotsubjecttoTypeAorTypeCleaktestduetoconstantmonitoringunderconstant1800psigpressureandthepossibledetrimentaleffectsofshutdown.(m)NotsubjecttoTypeCtestper10CFRPart50,AppendixJ.4hydrostatictestisperformedinaccordancewithSpecification4.6.1.2.d.3.-(n)ThesevalvesareTypeCtestedinthereversedirection.pscKtal+cL41~>if>oLyH4&p+~<+qp+~~~eycal44~>~~zQL\,dLO+RvmCy+N~.ClCO
CONTAINMENTSYSTEMS3/4.6.4SUPPRESSIONCHAMBER-DRYWELLVACUUMBREAKERSLIMITINGCONDITIONFOROPERATIONh~g'F837PyMp~3.6.4Allsuppressionchamber-drywellvacuumbreakersshallbeOPERABLEandclosed.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:a.Withoneormorevacuumbreakersinonepairofsuppressionchamber-drywellvacuumbreakersinoperableforopeningbutknowntobeclosed,restoretheinoperablepairofvacuumbreakerstoOPERABLEstatuswithin72hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.b.Withonesuppressionchamber-drywellvacuumbreakeropen,verifytheothervacuumbreakerinthe-pairtobeclosedwithin2hours;restoretheopenvacuumbreakertotheclosedpositionwithin72hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.c.Withthepositionindicatorofanysuppressionchamber-drywellvacuumbreakerinoperableverifytheothervacuumbreakerinthepairtobeclosedwithin2hoursandatleastonceper15daysthereafter.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.NINEMILEPOINT-UNIT23/46"33Nay201985
CONTAINMENT.SYSTEMSpffft~,ggpq~gg~qp..a~SURVEILLANCEREUIREMENTS4.6.4Eachsuppressionchamber-drywellvacuumbreakershallbe:a0Verifiedclosedatleastonceper7days.b.OemonstratedOPERABLE:2.Atleastonceper31daysandwithin2hoursafteranydischargeofsteamtothesuppressionchamberfromthesafety-reliefvalves,bycyclingeachvacuumbreakerthroughatleastonecompletecycleoffulltravel.Atleastonceper31daysbyverifyingthepositionindicator(s)OPERABLEbyobservingexpectedvalvemovementduringthecyclingtest."3.Atleastonceper18monthsby;a)Verifyingtheopeningsetpoint,fromtheclosedposition,tobelessthanorequalto0.2Spsid,'andb)VerifyingthepositionindicatorsOPERABLEbyperformanceofaCHANNELCALIBRATION.Observationofexpectedvalvemovementduringcyclingtestwillbeaccom-~~plishedforthepurposesofthissurveillancebyobservingvalvepositionindicatorsinthecontrolroom.NINEMILiŽPOINT-UNIT23/46-34Nova01995
CONTAINMENTSYSTEMS3/4.6.5SECONDARYCONTAINMENTSECONDARYCONTAINMENTINTEGRITYLIMITINGCONDITIONFOROPERATIONPKbF83'gP/gpj3.6.5.1SECONDARYCONTAINMENTINTEGRITYshallbemaintained.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and".ACTION:WithoutSECONDARYCONTAINMENTINTEGRITY:a.InOPERATIONALCONDITION1,2or3,restoreSECONDARYCONTAINMENTINTEGRITYwithin4hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefo'llowing24hours.b.InOperationalCondition~,suspendhandlingofirradiatedfuelinthesecondarycontainment,COREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.TheprovisionsofSpecification3.0.3arenotappkicable.SURVEILLANCE'EUIREMENTS4.6.5.1SECONDARYCONTAINMENTINTEGRITYshallbedemonstratedby:a.Verifyingatleastonceper24hoursthatthepressurewithinthesecondarycontainmentisgreaterthanorequalto0.25inchesofvacuumwatergauge.b.Verifyingatleastonceper31daysthat:I.Allsecondarycontainmentequipmenthatcheareclosedandsealed.2.Atleastonedoorineachaccesstothesecondarycontainmentisclosed,3.AllsecondarycontainmentpenetrationsnotcapableofbeingclosedbyOPERABLEsecondarycontainmentautomaticisolationdampersandrequiredtobeclosedduringaccidentconditionsareclosedbyvalves,blindflanges,ordeactivatedautomaticdamperssecuredinposition.c.Atleast'nceper18months:l.Verifyingthateachstandbygastreatmentsubsystemwilldrawdownthesecondarycontainmenttogreaterthanorequalto"0.25inchesofvacuumwatergaugeinlessthanorequalto90secondswhenstartingatapressurenolessthanzeropsig,and2.Operatingonestandbygastreatmentsubsystemforonehourandmaintaininggreaterthanorequalto-0.25inchesofvacuumwater.gaugeinthesecondarycontainmentataflowratenotexceeding9680cfm.5QoWhenirradiatedfuelisbeinghandledinthesecondarycontainmentandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.NINEMILEPOINT"UNIT23/46-35
CONTAINMENTSYSTEMSSECONDARYCONTAINMENTAUTOMATICISOLATIONDAMPERSLIMITINGCONDITIONFOROPERATION3.6.5.2ThesecondarycontainmentventilationsystemautomaticisolationdampersshowninTable3.6.5.2"1shallbeOPERABLEwithisolationtimeslessthanorequaltothetimesshowninTable3.6.5.2-1.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and".ACTION:WithoneormoreofthesecondarycontainmentventilationsystemautomaticisolationdampersshowninTable3.6.5.2-1inoperable,maintainatleastoneisolationdamperOPERABLEineachaffectedpenetrationthatisopenandwithin8hours'ither:a.Restoretheinoperabledamper(s)toOPERABLEstatus,orb.Isolateeachaffectedpenetrationbyuseofatleastonedeactivateddampersecuredintheisolationposition,orc.Isolateeachaffectedpenetrationbyuseofatleastoneclosedmanualorblindflange.Otherwise,inOPERATIONALCONDITION1,2or3,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Otherwise,inOperationalCondition",suspendhandlingofirradiatedfuelinthesecondarycontainment,COREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.TheprovisionsofSpecification3.0.3arenotapplicable.SURVEILLANCEREUIREMENTS4.6.5.2EachsecondarycontainmentventilationsystemautomaticisolationdampershowninTable3.6.5.2-1shallbedemonstratedOPERABLE:a0Priortoreturningthedampertoserviceaftermaintenance,repairorreplacementworkisperformedonthedamperoritsassociatedactuator,controlorpowercircuitbycyclingthedamperthroughatleastonecompletecycleoffulltravelandverifyingthespecifiedisolationtime.b.DuringCOLDSHUTDOWNorREFUELINGatleastonceper18monthsbyverifyingthatonacontainmentisolationtestsignaleachisolationdamperactuatestoitsisolationposition.c.Byverifyingtheisolationtimetobewithinitslimitwhentestedpursuant.toSpecification4.0.5.WhenirradiatedfuelisbeinghandledinthesecondarycontainmentandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.NINEMILEPOINT"UNIT23/46-36NOV801985
TABLE3.6.5.2"1SECONDARYCONTAINMENTVENTILATIONSYSTEMAUTOMATICISOLATIONDAMPERSDAMPERFUNCTIONMAXIMUMISOLATIONTIMESeconds1.ReactorBui1dingVenti1ationSupp1yDamper2HVR"AOD1Aor2HVR"AODlB2.ReactorBui1dingVenti1ationExhaustDamper2HVR"A009Aor2HVR"AOD983.ReactorBui1dingVenti1ationExhaustDamper2HVR"AODlOAor2HVR"A0010BNINEMILEPOINT-UNIT2.3/46-37g0)2vi~~-
CONTAINMENTSYSTEMSSTANDBYGASTREATMENTSYSTEMPMÃ8KflFI7KP'lLIMITINGCONDITIONFOROPERATION3.6.5.3TwoindependentstandbygastreatmentsubsystemsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and".ACTION:a.Withonestandbygastreatmentsubsysteminoperable,restoretheinoperablesubsystemtoOPERABLEstatuswithin7days,or:1.InOPERATIONALCONDITION1,2or3,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.2.InOperationalCondition~,suspendhandlingofirradiatedfuelinthesecondarycontainment,COREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.TheprovisionsofSpecification3.0.3arenotapplicable.b'ith-both-standbygastreatmentsubsystemsinoperableinOperationalCondition",suspendhandlingofirradiatedfuelinthesecondarycontainment,COREALTERATIONSoroperationswithapotentialfordrainingthereactorvessel.Theprovisionsof'pecification3.0.3.arenotapplicable.SURVEILLANCEREUIREMENTS4.6.5.3EachstandbygastreatmentsubsystemshallbedemonstratedOPERABLE:aoAtleastonceper31daysbyinitiating,fromthecontrolroom,flowthroughtheHEPAfiltersandcharcoaladsorbersandverifyingthat..thesubsystemoperatesforatleast10hourswiththeheatersOPERABLE.WhensrradsatedfuelisbeinghandledinthesecondarycontainmentandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvessel.NINEMILEPOINT"UNIT23/46"38NOY4.i.'
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTSContinuedb.Atleastonceper18monthsor(1)afteranystructuralmaintenanceontheHEPAfilterorcharcoaladsorberhousings,or(2)followingpainting,fireorchemicalreleaseinanyventilationzonecommunicatingwiththesubsystemby:2.3.Verifyingthatthesubsystem,satisfiesthein-placepenetrationandbypassleakagetestingacceptancecriteriaoflessthan0.05KandusesthetestprocedureguidanceinRegulatoryPositionsC.5.a,C.5.candC.5.dofRegulatoryGuide1.52",Revision2,March1978,andthesubsystemflowrateis3500cfm210K.Verifyingwithin31daysafterremovalthatalaboratoryanalysisofarepresentativecarbonsampleobtainedinaccordancewithRegulatoryPositionC.6.bofRegulatoryGuide1.52",Revision2,March1978,meetsthelaboratorytestingcriteriaofRegulatoryPositionC.6.aofRegulatoryGuide1.52",Revision2,March1978,foramethyliodidepenetrationoflessthan0.175K;andVerifyingasubsystemflow-rateof3500cfma10KduringsystemoperationwhentestedinaccordancewithANSIN510-1980.C.Afterevery720hoursofcharcoaladsorberoperationbyverifyingwithin31daysafterremovalthatalaboratoryanalysisofarepre-sentativecarbonsampleobtainedinaccordancewithRegulatoryPositionC.6.bofRegulatoryGuide1.52,Revision2,March1978,meetsthelaboratorytestingcriteriaofRegulatoryPositionC.6.aofRegulatoryGuide1.52,Revision2,March1978,foramethyl.iodidepenetrationoflessthan0.175K.d.Atleastonceper18monthsby:2'3.4.VerifyingthatthepressuredropacrossthecombinedHEPAfiltersandcharcoaladsorberbanksislessthan5.5inchesMaterGaugewhileoperatingthefiltertrainataflowrateof'~cfm+10K.SOderifyingthatthefiltertrainstartsandisolationvalvesopenoneachofthefo'llowingtestsignals:a.Manualinitiationfromthecontrolroom,andb.Simulatedautomaticinitiationsignal.Verifyingthatthedecayheatremovalisolationvalvesareopenandthefancanbemanuallystarted.Verifyingthattheheatersdissipate20.022.0kwwhentestedin-accordancewithANSIN510-1980.IS"ANSIN510-1980~applicableinplaceofANSIN510-1975andANSIN509-1980isapplicableinplaceofANSIN509-1976.NINEMILEPOINT-UNIT23/46-39Mniren~an@
CONTAINMENTSYSTEMSSURVEILLANCEREUIREMENTSContinuede.AftereachcompleteorpartialreplacementofaHEPAfilterbankbyverifyingthattheHEPAfilterbanksatisfiestheinplacepenetrationandbypassleakagetestingacceptancecriteriaoflessthan0.05KinaccordancewithANSIN510-1980whileoperatingthesystemataflowrateof3500cfm210K.f.Aftereachcompleteorpartialreplacementofacharcoaladsorberbankbyverifyingthatthecharcoaladsorberbanksatisfiestheinplacepenetrationandbypassleakagetestingacceptancecriteriaoflessthan0.05KinaccordancewithANSIN510-1980forahalogenatedhydrocarbonrefrigeranttestgaswhileoperatingthesystemataflowrateof3500cfma10K.NINEMILEPOINT-UNIT23/46-40
CONTAINMENTSYSTEMSP(j1AF~PiTPjlg!IIsP)113/4.6.6PRIMARYCOiVTAINMENTATMOSPHERECONTROL~~DRYWELLANDSUPPRESSIONCHAMBERHYDROGENRECOMBINERSYSTEMSLIMITINGCONDITIONFOROPERATION3.6.6.1TwoindependentdrywellandsuppressionchamberhydrogenrecombinersystemsshallbeOPERABLE.APPLICABILITY;OPERATIONALCONDITIONS1and2.ACTION:Nithonedrywe11and/orsuppressionchamberhydrogenrecombinersysteminoperable,restoretheinoperablesystemtoOPERABLEstatuswithin30daysorbeinatleastHOTSHUTDOWNwithinthenext12hours.SURVEILLANCEREUIREMENTS4.6.6.1EachdrywellandsuppressionchamberhydrogenrecombinersystemshallbedemonstratedOPERABLE:~a.Atleastonceper6monthsbyverifyingduringarecombinersystemfunctionaltestthattheminimumoutletgastemperatureincreasestogreaterthanorequalto700'Fwithin90minutes.Maintain>ll50'Fforatleast4hours.b.C.Atleastonceper18monthsby:1.PerformingaCHANNELCALIBRATIONofallrecombinerinstrumen-tationandcontrolcircuits.2.Verifyingtheintegrityofallheaterelectricalcircuitsbyperformingaresistancetogroundtestwithin30minutesfollow-ingtheaboverequiredfunctionaltest.Theresistancetogroundforanyheaterphaseshallbegreaterthanorequalto1,000,000ohms.3.Verifyingthroughavisualexaminationthatthereisnoevi-denceofabnormalconditionswithintherecombinerenclosure;i.e,loosewiringorstructuralconnections,depositsofforeignmaterials,etc.Bymeasuringthesystemleakagerate:1.AsapartoftheoverallintegratedleakageratetestrequiredbySpecification3.6.1.2,or2.BymeasuringtheleakagerateofthesystemoutsideofthecontainmentisolationvalvesatPa,39.75psig,ontheschedulerequiredbySpecification4.6.1.2,andincludingthemeasuredleakageasapartoftheleakagedeterminedinaccordancewithSpecification4.6.1.2.NINEMILEPOINT-UNIT23/46-41Nov201985
CONTAINMENTSYSTEMSPRIMARYCONTAINMENTATMOSPHERECONTROLDRYWELLANDSUPPRESSIONCHAMBEROXYGENCONCENTRATIONLIMITINGCONDITIONFOROPERATION3.6.6.2Thedrywellandsuppressionchamberatmosphereoxygenconcentrationshallbelessthan4Xbyvolume.APPLICABILITY:OPERATIONALCONDITION1",duringthetimeperiod:a.Within24hoursafterTHERMALPOWERisgreaterthan15KofRATEDTHERMALPOWER,followingstartup,tob.Within24hourspriortoreducingTHERMALPOWERtolessthan15KofRATEDTHERMALPOWER,preliminarytoascheduledreactorshutdown.ACTION:Withtheoxygenconcentrationinthedrywelland/orsuppressionchamberexceedingthelimit,restoretheoxygenconcentrationtowithinthelimitwithin24hoursorbeinatleastSTARTUPwithinthenext8hours.SURVEILLANCEREUIREMENTS4.6.6.2Theoxygenconcentrationinthedrywellandsuppressionchambershalj.beverifiedtobewitkinthelimitwithin24hoursafterTHERMALPOWERisgreaterthan15XofRATEDTHERMALPOWERandatleastoncepei7daysthereafter.SeeSpecialTestException3.10.5.NINEMILEPOINT-UNIT23/46-42
3/4.7PLANTSYSTEMS3/4.7.1PLANTSERVICEWATERSYSTEMPLANTSERVICEWATER-OPERATINGLIMITINGCONDITIONFOROPERATION3.7.1.1TwoindependentplantservicewatersystemloopsshallbeOPERABLEwithoneloopinoperation.Eachloopshallbecomprisedof:a.TwoplantservicewaterpumpscapableoftakingsuctionfromLakeOntarioandtransferringthewatertotheassociatedsafetyrelatedequipment.b.Servicewatersupplyheaderdischargewatertemperatureof<76F.ggeAfIntakeDeicingHeaterSystemshallbeinoperationwhenintaketunnelwatertemperatureis<3S0FwithDivisionIhaving7heatersinoperationineachintakestructureandDivisionIIhaying7heatersinoperationineachintakestructure.APPLICABILITY:OPERATIONALCONDITIONS1,2,3.ACTI0N:a.With1inoperableservicewaterpumpinoneloop,restoretheinoperablepumptoOPERABLEstatuswithin30daysorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.b.C.With1inoperableplantservicewaterpumpineachloop,restoreatleastoneinoperablepumptoOPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLOSHUTDOWNwithinthefollowing24hours.With1plantservicewatersystemloopinoperable,restorethein-operablelooptoOPERABLEstatuswithatleastoneOPERABLEpumpwithin72hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursand.inCOLDSHUTDOWNwithinthefollowing24hours.AlsotaketheACTIONrequiredbySpecification3.5.2and3.8.1.2.d.Withtheservicewatersupplyheaderdischargewatertemperatureoverany24hourperiodexceeding76'F,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.e.WithlessthantherequiredDivisionIandDivisionIIheatersoper-able,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.NINEMILEPOINT-UNIT23/47-1NOY20>985
PLANTSYSTEMSSURVEILLANCEREUIREMENTS-OPERATINGprsyqg(P/!PjijgfJPf4.7.1.1aeb.C.ThePlantServiceMaterSystemshallbedemonstratedOPERABLE:Atleastonceper12hoursby:l.Verifyingthewaterlevelattheservicewaterpumpintakeisgreaterthanorequalto233.1feetElevation.2.Verifyingtheservicewatersupplyheaderdischargewatertem-peratureis<76'F.Atleastonceper7daysbyverifyingthatthecurentoftheheaterfeedercablesatthemotorcontrolcentersis>amps~(total)at~518volta'erdivisionalheaterineachintakestructure.Atleastonceper31daysbyverifyingthateachvalve:manual,poweroperatedorautomatic,servicingsafetyrelatedequipmentthatisnot.locked,.sealedorotherwise-.securedinposition,isinitscorrectposition.d.Atleastonceper18monthsduringshutdown,byverifyingthat:l.AfterasimulatedtestsignaIeachautomaticvalveservicingnon-safetyrelatedequipmentactuatestoitsisolationpositiononanisolationtestsignal.2.3.Eachassociatedservicewatersystemcrossconnectandpumpdis-chargevalveactuateautomaticallytotheirisolationposition,andthatasingleservicewaterpumpstartsautomaticallyineachdivisionandthattheassociatedpumpdischargevalvereopensautomatically;inordertosupplyflowtothesystemsafetyre-latedcomponents.Eachpumprunsandmaintainsservicewaterpumpdischargepressureequaltoorgreaterthan90psigwitheachpumpflowequaltoorgreaterthan2500gpm.29'heresistancetogroundis>+ohmsforeachfeedercab1ethatpowerstheIntakeOeicingHeaterSystems."For7heaterelementsinoperation.NINEMILEPOINT-UNIT23/47-2NOV
PLANTSYSTEMSPLANTSERVICEWATER'-SHUTDOWNLIMITINGCONDITIONFOROPERATIONCGAAZ9aors~~op~~~illvUlQill.8esd)VUf13.7.1.2TwoindependentplantservicewatersystemloopsshallbeOPERABLEwithoneloopinoperation.Eachloopshallbecomprisedof:a.OneOPERABLEplantservicewaterpumpcapableoftakingsuctionfromLakeOntarioandtransferringthewatertotheassociatedsafetyrelatedequipment.b.Servicewatersupplyheaderdischargewatertemperatureof<76F.fhAfIntakeDeicingHeaterSysteayshallbeinoperationwhenintaketunnelwatertemperatureis<38FwithDivisionIhaving7heatersinoperationineachintakestructureandDivisionIIhaving7heatersinoperationineachintakestructure.APPLICABILITY:OPERATIONALCONDITIONS4,5.ACTION:aoWithlessthanoneOPERABLEservicewaterpumpineachloop,declaretheassociatedsafetyrelatedequipmentinoperableandtakeACTIONrequiredbySpecifications3.5.2and3.8.1.2.b.Withtheservicewatersupplyheaderdischargetemperatureoverany24hourperiodexceeding76F,suspendCOREALTERATIONSandalloperationsthathaveapotentialfordrainingthereactorvessel.c.WithlessthantherequiredDivisionIandDivisionIIheatersoper-able,suspendCOREALTERATIONSandalloperationsthathaveapoten-tialfordrainingthereactorvessel.NINEMILEPOINT"UNIT23/47-3gey50l%5
PLANTSYSTEMSSURVEILLANCEREUIREMENTSP,'Kgba(ppp~~py4.7.1.2aOb.C.d.ThePlantServiceWaterSystemshallbedemonstratedOPERABLE:Atleastonceper12hoursby:1.VerifyingthewaterlevelattheServiceWaterPumpintakeisgreaterthanorequalto233.1feetElevation.2.Verifyingtheservicewatersupplyheaderdischargetemperatureonanoperationloopis<76F.IOAtleastonceper7daysbyverifyingthatthecrntoftheheaterfeedercablesatthemotorcontrolcentersis>amps~(total)at518voltsperdivisionalheaterineachintakestructure.Atleastonceper31daysbyverifyingthateachvalve:manual,poweroperatedorautomatic,servicingsafetyrelatedequipmentthatisnotlocked,sealedorotherwise.securedinposition,isinitscorrectposition.Atleastonceper18monthsduringshutdown,byverifyingthat:l.Afterasimulatedtestsignaleachautomaticvalveservicingnon-safetyrelatedequipmentactuatestoitsisolationpositiononanisolationtestsignal.2.Eachassociatedservicewatersystemcrossconnectandpumpdis-chargevalveactuateautomaticallytotheirisolationposition,andthatasingleservicewaterpumpstartsautomaticallyineachdivisionandthattheassociatedpumpdischargevalvereopensautomatically;inorder,tosupplyflowtothesystemsafetyre-latedcomponents.3.0Eachpumprunsandmaintainsservicewaterpumpdischargepressureequaltoorgreaterthan90psigwitheachpumpflowequaltoorgreaterthan2500gpm.wF'heresistancetogroundis>/ohmsforeachfeedercablethatpowerstheIntakeDeicingHeaterSystems."For7heaterelementsinoperation.NINEMILEPOINT"UNIT23/47"4g0yRO198S
PLANTSYSTEMS3/4.7.2REVETMENT-DITCHSTRUCTUREPPlUllF5(PppgfgppLIMITINGCONDITIONFOROPERATION3.7.2Therevetment-ditchstructureshallbestructurallysoundandcapableoflimitingwaveactionasintended.Therevetment-ditchstructureshallbemain-tainedsuchthattheelevationofeachsurveypointlistedinTable3.7.2-1isnotmorethan1.0footbelowthelistedelevation.APPLICABILITY:Atalltimes.ACTION:Withtheelevationofoneormoresurveypointsmorethan1footbelowtheelevationgiveninTable3.7.2-1,prepareandsubmittotheCommissionwithin90days,pursuanttoSpecification6.9.2,aSpecialReportwhichincludesthefollowinginformation:a.Explanationofhowtheelevationchangeoccurredandiftherevetment-ditchstructureiscontinuingtochange;b.Aplannedcourseofrepair(ifrequired)andascheduleforaccom-~plishingtherepai~;c.Evaluationofandjustificationforcontinuedplantoperation;andd.ThecurrentelevationofeachsurveypointshowninTable3.7.2-1.e.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREOUIREMENTS4.7.2Therevetment-ditchstructureshallbecapableoflimitingwaveactionandshallbedeterminedtobestructurallysoundbyperforming:a.Avisualandalimitedsurvey"inspectiononceayear.b.Afullsurvey"priortofuelloadandonceeverytwoyearsthereafterprovidedthatthemaximumelevationchangeofoneormorecontrolpointsinthatperiodislessthantwoinches.Iftheelevationchangeofoneormorecontrolpointsexceedstwoinchesinanytwoyearperiod,afullsurveywillbeperformedonceayearthereafter,oruntiltwoconsecutivesurveysshowsanyadditionalelevationchangetobelessthantwoinchesineachtwoyearperiod;c.Avisualinspectionandafullsurvey"within7daysafteraseverestorminwhichthewaverunupgoesoverthetopoftherevetment.d.Avisualinspectionandafullsurvey"within7daysafteranyearth"quakeeventwithanintensitygreaterthantheoperatingbasisearth-quake(OBE)."Limitedandfullsurveysshallbeperformedwithsurveyequipmenttoatleastthird-orderaccuracy.NINEMILEPOINT-UNIT23/47-5pe20198'
TABLE3.7.2"1SURVEYPOINTSFORREVETMENT"DITCHSTRUCTURE.SURVEYPOINT"lc1BlA2C2B2A3C3B3A4C4B4A5C5B5A6C6B6Ajc7B7A8C8B8A9C9B9A10C10B10ANORTH"SOUTHN1283798.13N1283821.89N1283828.48N1283770.08N1283793.42N1283800.75N1283741.94N1283766.13N1283771.53N1283660.46N1283681.23N1283684.30N1283688.87N1283705.21N1283714.96N1283672.49N1283689.60N1283694.74N1283675.92N1283696.02N1283705.09N1283684.19N1283705.28N1283712.00N1283691.57N1283710.39N1283720.79N1283673.00N1283693.66N1283701.25EAST-WESTE546895.34E546888.75E546887.88E546799.33E546793.66E546802.21E546703.71E546696.05E546695.04E-546608.29E546606.66E546597.26E546510.60E546496.47E546498.16E546405.17E546407.84E546404.07E546305.02E546299.75E546309.27E546205.09E546205.14E546206.38E546110.39E546108.25'546102.81E546016.51E546004.95E546006.68OCTOBER1985CONTROLELEVATION252.165263.075264.290253.765263.725264.585252.920263.130263.215254.450263.560263.950255.665263.820263.440255.870264.180264.756256.575263.680265.235256.300263.125263.155257.715263.660263.090257.135265.540264.035"SeeFiguresB3/47.1-1andB3/47.1-2forlocationsketches.NINEMILEPOINT"UNIT23/47-6
TABLE3.7.2"1SURVEYPOINTSFORREVETMENT-DITCHSTRUCTURESURVEYPOINT"11C11B11A12C12B12ANORTH-SOUTHN1283646.76N1283666.83N1283675.17N1283626.37N1283650.74N1283656.67EAST-WESTE545918.23E545918.76E545912.02E545839.53E545835.16E545831.43OCTOBER1985CONTROLELEVATION256.155263.720263.385256.395264.085264.105SurveyPointsAreAnchoredIntoBackArmorUsingStainlessSteelHILTIguickBolts.NINEMILEPOINT-UNIT23/47"7NOV30jS85 h PLANTSYSTEMSPII)l1IIK'ganP~In<g,,<MVtQ-.""p<<~3/4.7.3CONTROLROOMOUTDOORAIRSPECIALFILTERTRAINSYSTEMLIMITINGCONDITIONFOROPERATION3.7.3TwoindependentcontrolroomemergencyoutdoorairspecialfiltertrainshallbeOPERABLE.APPLICABILITY:AllOPERATIONALCONDITIONSand".ACTION:a.InOPERATIONALCONDITION1,2,or3withonecontrolroomfilter'traininoperable,restoretheinoperablefiltertraintoOPERABLEstatuswithin7daysorbeinatleastHOTSHUTDOMNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.b.InOPERATIONALCONDITION4,5or":=Mithonecontrolroomfiltertraininoperable,restoretheinoperablefiltertraintoOPERABLEstatuswithin7daysorinitiateandmaintainoperationortheOPERABLEfiltertraininthepressurizationmodeofoperation.2.Mithbothcontrolroomfiltertrainsinoperable,suspendCOREALTERATIONS,handlingofirradiatedfuelinthereactorbui3dingandoperations.withapotentialfordrainingthereactorvessel.c.TheprovisionsofSpecification3.0.3arenotapplicableinOperationalCondition".SURVEILLANCEREUIREMENTS4.7.3EachcontrolroomoutdoorairspecialfiltertrainshallbedemonstratedOPERABLE:a.Atleastonceper12hoursbyverifyingthatthecontrolroomairtemperatureislessthanorequalto120'F.b.Atleastonceper)1daysonaSTAGGEREDTESTBASISbyinitiating,fromthecontrolroom,flowthroughtheHEPAfiltersandcharcoaladsorbersandverifyingthatthefiltertrainoperatesforatleast10hourswiththeheatersOPERABLE."MhenirradiatedfuelisbeinghandledinthereactorbuildingandduringCOREALTERATIONSandoperationswithapotentialfordrainingthereactorvesselanduncoveringirradiatedfuel.NINEMILEPOINT-UNIT23/47-8HOV20~oat
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinuedPIlitglg0gPIPP~Isq~>~c.Atleastonceper18monthsor(1)afteranystructuralmaintenanceontheHEPAfilterorcharcoaladsorberhousings,or(2)foll.owingpainting,fireorchemicalreleaseinanyventilationzonecommunicatingwiththefiltertrainsby:1.Verifyingthatthefiltertrainsatisfiesthein-placepenetrationandbypasstestingacceptancecriteriaoflessthan0.05KandusesthetestprocedureguidanceinRegulatoryPositionsC.5.a,C.5.candC.5.dofRegulatoryGuide1.52*,Revision2,March1978,andthesytemflowrateis2250cfm210K.2.Verifyingwithin31daysafterremovalthatalaboratoryanalysisofarepresentativecarbonsampleobtainedinaccordancewithRegulatoryPositionC.6.bofRegulatoryGuide1.52",Revision2,March1978,meetsthelaboratorytestingcriteriaofRegulatoryPositionC.6.aofRegulatoryGuide1.52",Revision2,March1978,foramethyliodidepenetrationoflessthan0.175K;and3..Verifyingasubsystemflowrateof2250cfm210KduringsubsystemoperationwhentestedinaccordancewithANSIN510"1980.'d.Afterevery720hoursofcharcoaladsorberoperationbyverifyingwithin31daysafterremovalthatalaboratoryanalysisofarepresentativecarbonsampleobtainedinaccordancewithRegulatoryPositionC.6.bofRegulatoryGuidel.52",Revision2,March1978,.meetsthelaboratorytestingcriteriaofRegulatoryPositionC.6.aofRegulatoryGuide1.52",Revision2,March1978,foramethyliodidepenetrationoflessthan0.175K.e.Atleastonceper18monthsby:1.VerifyingthatthepressuredropacrossthecombinedHEPAfiltersandcharcoaladsorberbanksislessthan5.5inchesMaterGaugewhileoperatingthesubsystemataflowrateof2250cfm2lOX.2.Verifyingthatoneachofthebelowpressurizationmodeactuationtestsignals,thefiltertrainautomaticallyswitchestothepressurizationmodeofoperationandthecontrolroomismaintainedatapositivepressureof318inchM.G.relative"ANSI-N510-1950isapplicableinp'laceofANSI-5510-1975.~igloo~Issue<-/fsp~$jlnsZffSOS'-I97$NINEMILEPOINT-UNIT23/47-9Oypnto
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinuedtotheoutsideatmosphereduringsubsystemoperationatanoutsideairintakeflowrate1eeethanorequa1to/1500/cfm:a)Airintakeradiationmonitors,and3.Verifyingthattheheatersdissipate>7.95kMwhentestedinaccordancewithANSIN510-1980.f.AftereachcompleteorpartialreplacementofaHEPAfilterbankbyverifyingthattheHEPAfilterbanksatisfiestheinplacepenetrationandbypassleakagetestingacceptancecriteriaoflessthan0.05XinaccordancewithANSIN510-1980whileoperatingthesystemataflowrateof2250cfm+10K.g.Aftereachcompleteorpartialreplacementofacharcoaladsorberbankbyverifyingthatthecharcoaladsorberbanksatisfiestheinplacepenetrationandbypassleakagetestingacceptancecriteriaoflessthan0.05XinaccordancewithANSIN510-1980forahalogenatedhydiocarbonrefrigeranttestgaswhileoperatingthesystemataflowrateof2250cfm+10K.NINEMILEPOINT"UNIT23/47-10NOV20i98o
-PLANTSYSTEMS3/4.7.4REACTORCOREISOLATIONCOOLINGSYSTEMLIMITINGCONDITIONFOROPERATIONPV(g)g$PP~q![+I'~~3.7.4Thereactorcoreisolationcooling(RCIC)systemshallbeOPERABLEwithanOPERABLEflowpathcapableofautomaticallytakingsuctionfromthe.suppressionpoolandtransferringthewatertothereactorpressurevessel.APPLICABILITY:OPERATIONALCONDITIONS1,2,and3Pithreactorsteamdomepressuregreaterthan150psig.ACTION:WiththeRCICsysteminoperable,operationmaycontinueprovidedtheHPCSsystemisOPERABLE;restoretheRCICsystemtoOPERABLEstatuswithin14daysorbe'natleastHOTSHUTDOWNwithinthenext12hoursandreducereactorsteamdomepressuretolessthanorequalto150psigwithinthefollowing24hours.SURVEILLANCEREUIREMENTS4.7.4TheRCICsystemshallbedemonstratedOPERABLE:a.Atleastonceper31daysby:1.Verifyingbyventingatthehighpointventsthatthesystempipingfromthepumpdischargevalvetothesystemisolationvalveisfilledwithwater.2.Verifyingthateachvalve(manual,poweroperatedorautomatic)intheflowpaththatisnotlocked,sealedorotherwisesecuredinposition,isinitscorrectposition.3.Verifyingthatthepumpflowcontrollerisinthecorrectposition.b.WhentestedpursuanttoSpecification4.0.5byverifyingthattheRCICpumpdevelopsaflowofgreaterthanorequalto600gpminthe.testflowpathwithasystemheadcorrespondingtoreactorvesseloperatingpressurewhensteamisbeingsuppliedtotheturbineat1000+20,-80psig."TheprovisionsofSpecification4.0.4arenotapplicableprovidedthesurveillanceisperformedwithin12hoursafterreactorsteampressureisadequatetoperformthetest.4CiC~I~l~~~kqC.lfl!llPALj}NINEMILEPOINT-UNIT23/47"11NOV2e>9S5
PLANTSYSTEMSFKiF8~'~FPP'fMP7SURVEILLANCEREUIREHENTSContinuedC.Atleastonceper18monthsby:1.Performingasystemfunctionaltestwhichincludessimulatedautomaticactuation'andrestartandverifyingthateach'utomaticvalveintheflowpathactuatestoitscorrectposition.Actualinjectionofcoolantintothereactorvesselmaybeexcluded.2.Verifyingthatthesystemwilldevelopaflowofgreaterthanorequalto600gpminthetestflowpathwhensteamissuppliedtotheturbineatapressureof150+15,"0psig."3.Verifyingthatthesuction.fortheRCICsystemisautomaticallytransferredfromthecondensatestoragetanktothesuppressionpoolonacondensatestoragetankwaterlevel-lowsignal."TheprovisionsofSpecification4.0.4arenotapplicableprovidedthesurveillanceisperformedwithin12hoursafterreactorsteampiessureisadequatetoperformthetests.NINEMILEPOINT-UNIT23/47-i28V3
PLANTSYSTEMS~~3/4.7.5SNUBBERSLIMITINGCONDITIONFOROPERATIONgqgpp)f)OQ'f3.7.5AllsnubbersshallbeOPERABLE.Theonlysnubbersexcludedfromtherequirementsarethoseinstalledonnonsafety-relatedsystemsandthenonlyiftheirfailureorfailureofthesystemonwhichtheyareinstalledwouldhavenoadverseeffectonanysafety-relatedsystem.APPLICABILITY:OPERATIONALCONDITIONS1,2and3andOPERATIONALCONDITIONS4and5forsnubberslocatedonsystemsrequiredOPERABLEinthoseOPERATIONALCONDITIONS.ACTION:Withoneormoresnubbersinoperable,within72hoursreplaceorrestoretheinoperablesnubber(s)toOPERABLEstatusandperformanengineeringevaluationperSpecification4.7.5onthesupportedcomponentordeclarethesupportedcsysteminoperableandfollowtheappropriateACTIONstatementforthatsystem.'URVEILLANCEREUIREMENTS4.7.5EachsnubbershallbedemonstratedOPERABLEbyperformanceofthefollowingaugmentedinserviceinspectionprogramandtherequirementsofSpecification4.0.5.~ITAsusedinthisspecification,typeofsnubbershallmeansnubbersofthesamedesignandmanufacturer,irrespectiveofcapacity.b.VisualInsectionsSnubbersarecategorizedasinaccessibleoraccessibleduringreactoroperation.EachcategorymaybeinspectedindependentlyaccordingCotheschedulebelow.Thefirstinservicevisualinspectionofsnubbersshallbeperformedafter2monthsbutwithin12monthsofcommencing.POWEROPERATIONandshallincludeallsnubbers.IfallsnubbersarefoundOPERABLEduringthefirstinservicevisualinspection,thesecondinservicevisualinspectionshallbeperformedatthefirstrefuelingoutage.Otherwise,subsequentvisualinspectionsshallbeperformedinaccordancewiththefollowingschedule:No.InoperableSnubberserInsoectionPeriod0123,45,6,78ormoreSubsequentVisualInsectionPeriod"¹18monthse12monthsk'5K6months225K124dayst25K62days125K31daysk25KTheinspectionintervalshallnotbelengthenedmorethanonestepatatime.OTheprovisionsofSpecification4.0.2arenotapplicable.NINEMILEPOINT-UNIT23/47"1350V201S85
PLANTSYSTEMSSURVEILLANCEREUIREMENTSKÃFR~(PA'PitMFlc.VisualInsectionAccetanceCriteriaVisualinspectionsshallverify(1)thattherearenovisibleindicationsofdamageorimpairedOPERABILITY,(2)thatattachmentstothefoundationorsupportingstructureareOPERABLE,and(3)fastenersforattachmentofthesnubbertothecomponentandtothesnubberanchorageareOPERABLE.SnubberswhichappearinoperableasaresultofthesevisualinspectionsmaybedeterminedOPERABLEforthepurposeofestablishingthenextvisualinspectioninterval,providedthat:(1)thecauseoftherejectionisclearlyestablishedandremediedforthatparticularsnubberandforothersnubbersirrespec-tiveofthetypeonthatsystemthatmaybegenericallysusceptible;oe~(2)theaffectedsnubberisfunctionallytestedintheas-foundconditionanddeterminedOPERABLEperSurveillanceRequirement(s)4.7.5.f.d.TransientEventInsectionAninspectionshallbeperformedofallsnubbersattachedtosectionsofsystemsthathaveexperiencedunexpected,potentiallydamagingtransients,asdeterminedfromareviewofoperationa'ldataoravisualinspectionofthesystems,within72hoursforaccessibleareasandwithin6monthsforinaccessibleareasfollowingthisdetermina-tion.In-additiontosatisfyingthevisualinspectionacceptancecriteria,freedom-of-motionofmechanicalsnubbersshallbeverifiedusingatleastoneofthefollowing:(1)manuallyinducedsnubbermovement;or(2)evaluationofin-placesnubberpistonsetting;or(3)strokingthemechanicalsnubberthroughitsfullrangeoftravel.\NINEMILEPOINT-UNIT23/47"14NOV20)g8g
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinuede.FunctionalTestsDuringthefirstrefuelingshutdownandatleastonceper18monthsthereafterduringshutdown,arepresentativesampleofsnubbersshallbetestedusingoneofthefollowingsampleplansforeachtypeofsnubber.Thesampleplanshallbeselectedpriortothetestperiodandcannotbechangedduringthetestperiod.TheNRCRegionalAdministratorshallbenotifiedinwritingofthesampleplanselectedpriortothetestperiodorthesampleplanusedinthepriortestperiodshallbeimplemented:1)Atleast10Kofthetotalofeachtypeofsnubbershallbefunctionallytestedeitherin-placeorinabenchtest.ForeachsnubberofatypethatdoesnotmeetthefunctionaltestacceptancecriteriaofSpecification4.7.5.f,anadditional10Kofthattypeofsnubbershallbefunctionallytesteduntilnomorefailuresarefoundoruntilallsnubbersofthattypehavebeenfunctionallytested;or2)Arepresentativesampleofeachtypeofsnubbershallbefunc-tionallytestedinaccordancewithFigure4.7.5-1."C"isthetotalnumberofsnubbersofatypefoundnotmeetingtheacceptancerequirementsofSpecification4.7.5.f.Thecumula-tivenumberofsnubbersofatypetestedisdenotedby"N".Attheendofeachday'stesting,thenewvaluesof"N"and"C"(previousday'stotalpluscurrentday'sincrements)shallbeplottedonFigure4.7.5-1.Ifatanytimethepointplottedfallsinthe"Reject"regionallsnubbersofthattypeshallbefunctionallytested.Ifatanytimethepointplottedfallsinthe"Accept"region,testingofsnubbersofthattypemaybeterminated.Whenthepointplottedliesinthe"ContinueTesting"region,additionalsnubbersofthattypeshallbetesteduntiltheponitfallsinthe"Accept"regionorthe"Reject"region,orallthesnubbersofthattypehavebeentested;or3)Aninitialrepresentativesampleof55snubbersofeachtypeshallbefunctionallytested.Foreachsnubbertypewhichdoesnotmeetthefunctionaltestacceptancecriteria,anothersampleofatleastone-halfthesizeoftheinitialsampleshallbetesteduntilthetotalnumbertestedisequaltotheinitialsamplesizemultipliedbythefactor,1+C/2,where"C"isthenumberofsnubbersfoundwhichdonotmeetthefunctionaltestacceptancecriteria.Theresultsfromthissampleplanshallbeplottedusingan"Accept"linewhichfollowstheequationN=55(1+C/2).Eachsnubberpointshouldbeplottedassoonasthesnubberistested.Ifthepointplottedfallsonorbelowthe"Accept"line,testingofthattypeofsnubbermaybeterminated.Ifthepointplottedfallsabovethe"Accept"line,testingmustcontinueuntilthepointfallsinthe"Accept"regionorallthesnubbersofthattypehavebeentested.NINEMILEPOINT"UNIT23/47-15HOV801S85
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinuedg.-Testingequipmentfailureduringfunctionaltestingmayinvalidatethatday'stestingandallowthatday'stestingtoresumeanewatalatertime,providingallsnubberstestedwiththefailedequipmentduringthedayofequipmentfailureareretested.Therepresentativesampleselectedforthefunctionaltestsampleplansshallberandomlyselectedfromthesnubbersof'achtypeandreviewedbeforebeginningthetesting.Thereviewshallensureasfaraspracticalthattheyarerepresentativeofthevariousconfigurations,operatingenviron-ments,rangeofsize,andcapacityofsnubbersofeachtype.Snubbersplacedinthesamelocationsassnubberswhichfailedthepreviousfunctionaltestshallberetestedatthetimeofthenextfunctionaltestbutshallnotbeincludedinthesampleplan.'fduringthefunctionaltesting,additionalsamplingisrequiredduetofailureofonlyonetypeofsnubber,thefunctionaltestingresultsshallbe'eviewedatthetimetodetermineifadditionalsamplesshouldbelimitedtothetypeofsnubberwhichhasfailedthefunctionaltesting.FunctionalTestAccetanceCriteriahesnubberfunctionaltestsha1verifythat:1)Activation(restrainingaction)isachievedwi%hinthespecifiedrangeinbothtensionandcompression;2)Formechanicalsnubbers,the.forcerequiredtoinitiateormain-tainmotionofthesnubberiswithinthespecifiedrangeinbothdirectionsoftravel;andTestingmethodsmaybeusedtomeasureparametersindirectlyorparam-etersotherthanthosespecifiedifthoseresultscanbecorrelatedtothespecifiedparametersthroughestablishedmethods.FunctionalTestFailureAnalsisAneng>neeringevaluationshallbemadeofeachfailuretomeetthe.functionaltestacceptancecriteriatodeterminethecauseofthefailure.Theresultsofthisevaluationshallbeused,ifapplicab'le,inselectingsnubberstobetestedinanefforttodeterminetheOPER-ABILITYofothersnubbersirrespectiveoftypewhichmaybesubjecttothesamefailuremode.Forthesnubbersfoundinoperable,anengineeringevaluationshallbeperformedonthecomponentstowhichtheinoperablesnubbersareattached.Thepurposeofthisengineeringevaluationshallbetodetermineifthecomponentstowhichtheinoperablesnubbersareat-tachedwereadverselyaffectedbytheinoperabilityofthesnubbersinordertoensurethatthecomponentremainscapableofmeetingthedesignedservice.NINEMILEPOINT-UNIT23/47-16QQVRulGUS
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinued)Ifanysnubberselectedforfunctionaltestingeitherfailstolockuporfailstomove,i.e.,frozen-in-place,thecausewillbeevaluatedandifcausedbymanufacturerordesigndeficiencyall'snubbersofthesametypesubjecttothesamedefectshallbefunctionallytested.ThistestingrequirementshallbeindependentoftherequirementsstatedinSpecification4.7.5.eforsnubbersnotmeetingthefunctionaltestacceptancecriteria.h.FunctionalTestinofReairedandRelacedSnubbersSnubbersthatfailthevisualinspectionorthefunctionaltestaccep-tancecriteriashallberepairedorreplaced.Replacementsnubbersandsnubbersthathaverepairsthatmightaffectthefunctionaltestresultshallbetestedtomeetthefunctionaltestcriteriabeforeinstallationintheunit.Mechanicalsnubberssha'llhavemettheacceptancecriteriasubsequenttotheirmostrecentservice,andthefreedom-of-motiontestmusthavebeenperformedwithin12monthsbeforebeinginstalledintheunit.SnubberServiceLifeProramheservice>feofasnubbersshallbemonitoredtoensurethattheservicelifeisnotexceededbetweensurveillanceinspections.Themaximumexpectedservice'ifeforvariousseals,springs,andothercriticalpartsshallbedeterminedandestablishedbasedonengineeringinformationandshallbeextendedorshortenedbasedonmonitoredtestresultsandfailurehistory.CriticalpartsshallbereplacedsothatthemaximumservicelifewillnotbeexceededduringaperiodwhenthesnubberisrequiredtobeOPERABLE.Thepartsre-placementsshallbedocumentedandthedocumentationshallberetainedinaccordancewithSpecification6.10.1.2.NINEMILEPOINT"UNIT23/47-17NDV80}985
10REJECTgoalQ.CCONTINUETESTINGgpss$0ACCEPT00102030405060708090100FIGURE4-7.5-1SAMPlEPLAN2FDRSNUBBERFUNCTIDHALTESTNINEMIlEPOINT-UNIT23/47-1B
PLANTSYSTEMS3/4.7.6SEALEDSOURCECONTAMINATIONFMUI5$POIPOJP~PPLIMITINGCONDITIONFOROPERATION3.7.6Eachsealedsourcecontainingradioactivematerialeitherinexcessof100microcuriesofbetaand/orgammaemittingmaterialor5microcuriesofalphaemittingmaterialshallbefreeofgreaterthanorequalto0.005microcuriesofremovablecontamination.APPLICABILITY:Atalltimes.ACTION:aob.Withasealedsourcehavingremovablecontaminationinexcessoftheabovelimit,withdrawthesealedsourcefromuseandeither:1..Decontaminateandrepairthesealedsource,or2.DisposeofthesealedsourceinaccordancewithCommissionRegulations.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.,SURVEILLANCEREUIREMENTS6.7.6.1~TR1-661d6116Rdf1kdand/orcontam1natlonby:a.Thelicensee,orb.OtherpersonsspecificallyauthorizedbytheCommissionoranAgreementState.Thetestmethodshallhaveadetectionsensitivityofatleast0.005microcuriespertestsample..76.2~TT1-.f62fId,161"6sourcesandfission,detectorspreviouslysubjectedtocoreflux,shallbetestedatthefrequencydescribedbelow.aOSourcesinuse-Atleastoncepersixmonthsforallsealedsourcescontasningradioactivematerial:1.Mithahalf-lifegreaterthan30days,excludingHydrogen3,and2.Inanyformotherthangas.NINEMILEPOINT-UNIT23/47-19ggy201S85
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinuedF"-i3uFeKJlP'IllIlP7b.Storedsourcesnotinuse-Eachsea1edsourceandfissiondetectorshallbetestedpriortouseortransfertoanotherlicenseeunlesstestedwithintheprevioussixmonths.Sea1edsourcesandfissiondetectorstransferredwithoutacertificateindicatingthelasttestdatesha11betestedpriortobeingplacedintouse.C.Startusourcesandfissiondetectors-Eachsealedstartupsourceandfisssondetectorshallbetestedwithin31dayspriortobeingsubjectedtocoref1uxorinsta11edinthecoreandfo11owingrepairormaintenancetothesource.4.7.6.3~Reorts-Areportsha11bepreparedandsubmittedtotheCommissiononanannualbasisifsea1edsourceorfissiondetectorleakagetestsrevealthepresenceofgreaterthanorequalto0.005microcuriesofremovab1econtamination.NINEMILEPOINT'-UNIT23/47-20gOg2016'ab
PLANTSYSTEMS3/4.7.7FIRESUPPRESSIONSYSTEMSFIRESUPPRESSIONWATERSYSTEMLIMITINGCONDITIONFOROPERATIONjjPg+ggflI.flpi)pa~~.fhPmp,gy'.7.7.1ThefiresuppressionwatersystemshallbeOPERABLEwith:a.TwoOPERABLEfiresuppressionpumps,eachwithacapacityof2500gpm,withtheirdischargealignedtothefiresuppressionheader,andAnOPERABLEflowpathcapableoftakingsuctionfromtheServiceWaterBayandtransferringthewaterthroughdistributionpipingwithOPERABLEsectionalizingcontrolorisolationvalvestotheyardhydrantcurbvalves,thelastvalveaheadofthewaterflowalarmdeviceoneachsprinklerorhosestandpipeandthelastvalveaheadofthedelugevalveoneach.delugeorspraysystemrequiredtobeications3.7.7.2,3.7.7.5,and3.7.7.6.OPERABLEperSpecsfAPPLICABILITY:Atalltimes.ACTION:b.Withthefiresuppressionwatersystemotherwiseinoperable,establishabackupfiresuppressionwatersystemwithin24hours.SURVEILLANCEREUIREMENTSa.Withonepumpinoperable,restoretheinoperableequipmenttoOPERABLEstatuswithin7daysorprovideanalternatebackuppumporsupply.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.4.7.7.1.1ThefiresuppressionwatersystemshallbedemonstratedOPERABLE:a.Atleastonceper31daysbystartingtheelectricmotordrivenfirepumpandoperatingitforatleast15minutesonrecirculationflow.b.Atleastonceper31daysbyverifyingthateachvalve(manual,poweroperatedorautomatic)intheflowpathisinitscorrectposition.NINEMILEPOINT-UNIT23/47-21NOY?01985
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinuedwPgPPyPEQggp~Q:qP~p(p~~~UfC.d.e.Atleastonceper6monthsbyperformanceofasystemflush.Atleastonceper12monthsbycyclingeachtestablevalveintheflowpaththroughatleastonecompletecycleoffulltravel.Atleastonceper18monthsbyperformingasystemfunctionaltestwhichincludessimulatedautomaticactuationofthesystemthroughoutitsoperatingsequence,and:1.Verifyingthateachautomaticvalveintheflowpathactuatestoitscorrectposition,2.Verifyingthateachfiresuppressionpumpdevelopsatleast2500gpmatanetdischargeheadof113psig,3.Cyclingeachvalveintheflowpaththatisnottestableduringplantoperationthroughat-leastonecompletecycleoffulltravel,and4.Verifyingthateachfiresuppressionpumpstartsandmaintains~thefiresuppressionwatersystempressuregreaterthanorequalto125psig.Atleastonceper3yearsbyperformingaflowtestofthesysteminaccordancewithChapter6,Section16oftheFireProtectionHandbook,15thEdition,publishedbytheNationalFireProtectionAssociation.4.7.7.1.2ThedieseldrivenfiresuppressionpumpshallbedemonstratedOPERABLE:aoAtleastonceper31daysby:1.Verifyingthefueldaytankcontainsatleast350gallonsoffuel.b.C.2.Startingthedieseldrivenpumpfromambientconditionsandoperatingforgreaterthanorequalto30minutesonrecirculationflow.Atleastonceper92daysbyverifyingthatasampleofdieselfuelfromthefuelstoragetank,obtainedinaccordancewithASTM~0276~iswithintheacceptablelimitsspecifiedinTable1ofASTMwhencheckedforviscosity,waterandsediment.Dd-os'-r(oF7smJAtleastonceper18months,duringshutdown,bysubjectingthecleseitoaninspectioninaccordancewithprocedurespreparedinconjunctionwithitsmanufacturer'srecommendationsfortheclassofservice.NINEMILEPOINT-UNIT23/47-22NOV201985
PLANTSYSTEMSSURVEILLANCEREUIREMENTSContinued4.7.7.1.3Thedieseldrivenfirepumpstarting24-voltbatterybankandchargershallbedemonstratedOPERABLE:a.Atleastonceper7daysbyverifyingthat:1.Theelectrolytelevelofeachcellisabovetheplates,2.Thepilotcellspecificgravity,correctedto77'Fandfullelectrolytelevel,isgreaterthanorequalto1.235,3.Theoverallbatteryvoltage.isgreaterthanorequalto25.5vo1ts"withthebatteryonfloatcharge.b.C.Atleastonceper92daysbyverifyingthatallcellparametersforallbatteryce'llsaredemonstratedOPERABLEperSpecifica-tion4.7.7.1.3.aandthedifferencebetweenthepilotcellwiththehighestspecificgravitywhencomparedtothepHotcellwiththelowestspecificgravityis<0.015.Atleastonceper18monthsbyverifyingthat:1.Thebatteries,(ceI1plates)andbatteryracksshownovisualindicationofphysicaldamageorabnormaldeterioration,and2.Batteryandterminalconnectionsareclean,tightandfreeofcorrosion."Anoverallbatteryvoltageof>25.5voltsrepresentstwelvepilotcellseach.earringatleasta2.13voltcharge.NINEMILEPOINT-UNIT23/47-23$0YP.vhd5 4l PLANTSYSTEMSN0tIFg~)Pj!Pg)g~yLIMITINGCONDITIONFOROPERATION3.7.7.2ThefollowingsprayandsprinklersystemsshallbeOPERABLE:a.SPRAYANDSPRINKLERSYSTEMS,SYSTEMNO.BUILDING/ELEVATION1.2.3.4.5.6.7.8.9.10.11;12.13.W-33W-34W-35W-36W-42W-43W-44W-45W-46W-47W"55W-57W-60ElectricalTunnel-ElectricalTunnel-ElectricalTunnel-ElectricalTunnel-ControlBldg.-El.ControlBldg.-El.ControlBldg.-El.ControlBldg.-El.ControlBldg.-El.ControlBldg.-El.ReactorBldg.-El.ReactorBldg.-El.DieselFirePumpRm.35140230315288'"6"306'-0"214'-0"to306'-0"214'-0"to237'-0"214'-0"to306'"0"214'"0"to237'-0"175'-0"261'-OI'El.261'-OIIb.PRE"ACTIONSYSTEMSSYSTEMNO.1.W-482.W-493.W-504.W"545.W"56BUILDING/ELEVATIONDieselGeneratorBldg.-El.DieselGeneratorBldg.-.El.DieselGeneratorBldg.-El.ReactorBldg.-SouthEl.175'-0"ReactorBldg.-NorthEl.175'-0"261'"0"261I0261IOIIto328'-10"to328'"XO"APPLICABILITY:Wheneverequipmentprotectedbythesprayand/orsprinklersystemsisrequiredtobeOPERABLE.ACTION:aOb.Withoneormoreoftheaboverequiredsprayand/orsprinklersystemsinoperable,withinonehourconverttheapplicabledrysystem(s)toawetpipesystemorestablishacontinuousfirewatchwithbackupfiresuppressionequipmentforthoseareasinwhichredundantsystemsorcomponentscouldbedamaged;forotherareas,establishanhourlyfirewatchpatrol.TheprovisionsofSpecification3.0.3and3.0.4arenotapplicable.NINEMILEPOINT"UNIT23/47"24NQV80l985
PLANTSYSTEMSSURVEILLANCEREUIREMENTS4.7.7.2EachoftheaboverequiredsprayandsprinklersystemsshallbedemonstratedOPERABLE:a.Atleastonceper31daysbyverifyingthateachvalve(manual,poweroperatedorautomatic)intheflowpathisinitscorrectposition.b.Atleastonceper12monthsbycyclingeachtestablevalveintheflowpaththroughatleastonecompletecycleoffulltravel.c.Atleastonceper18months:1.Byperformingasystemfunctionaltestwhichincludessimulatedautomaticactuationofthesystem,and:a)Verifyingthattheautomaticvalvesintheflowpathactuatetotheircorrectpositionsonatestsignal,and2.b)Cyclingeachvalveintheflowpaththatisnottestableduringplantoperationthroughatleastonecompletecycleoffulltravel.Byavisualinspectionofthesprayandsprinklerheaderstoverifytheirintegrity,and3.Byavisualinspectionofeachdelugenozzle'ssprayareatoverifythatthespraypatternisnotobstructed.d.Atleastonceper3yearsbyperforminganairorwaterflowtestthrougheachopenheadsprayandsprinklerheaderandverifyingeachopenheadsprayandsprinklernozzleisunobstructed.NINEMILEPOINT"UNIT23/47"25NnVRO1985 I PLANTSYSTEMSC02SYSTEMSLIMITINGCONDITIONFOROPERATIONI'IRO~FfgClIR<]1(Pp~q(3.7.7.3ThefollowinglowpressureC02systemsshallbeOPERABLE:ZONENUMBERBUILDING/ELEVATIONa~b.C.d.336XL333XL342XL253XLControlBuilding/El.261'-0"ControlBuilding/EI.261'-0"ControlBuilding/El.261'-0"ReactorBuilding/El.289'-0"APPLICABILITY:WheneverequipmentprotectedbytheC02systemsisrequiredto~PRRACTION:a.WithoneormoreoftheaboverequiredCOsystemsinoperable,withinonehourestablishacontinuousfirewatchwithbackupfiresuppres-sionequipmentforthoseareasinwhichredundantsystemsorcomponentscouldbedamaged;forotherareas,establishanhourlyfirewatchpatrol.b.'heprovisionsofSpecification3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.7.3.1EachoftheaboverequiredCOsystemsshallbedemonstratedOPERABLEatleastonceper31daysbyve/ifyingthateachvalve(manual,poweroperatedorautomatic)intheflowpathisinitscorrectposition.4.7.7.3.2EachoftheaboverequiredlowpressureC02systemsshallbedemonstratedOPERABLE:a..Atleastonceper7daysbyverifyingtheCOstoragetank2FPL-TKlcontains3tonsofC02atapressuretobeg/eaterthan275psig,andb.,Atleastonceper18monthsbyverifying:1.Thesystem,includingassociatedventilationsystemfiredampersactuatemanuallyandautomatically,uponreceiptofasimulatedactuationsignal,and2.Flowfromeachnozzleduringa"PuffTest."NINEMILEPOINT-UNIT23/47-26HOV20]9@
PLANTSYSTEMSHALONSYSTEMSLIMITINGCONDITIONFOROPERATIONP:.Q.gQ!r!!!~)]~p!3.7.7.4ThefollowingHalonsystemsshallbeOPERABLEwiththestoragetankshavingatleast95Koffullchargeweightorleveland90Ãoffullchargepressure:'arb.C.d.e.f.g.h.'~ZONENO.353SG354SG362SG357XG358XG374SG375SG381SG376XGBUILDING/ELEVATIONControlBldg.-El.288'-6"ControlBldg.-El.288'-6"ControlBldg.-El.288'-6"ControlBldg.-El.288'-6"ControlBldg.-El.288'-6"ControlBldg.-El.306'-0"ControlBldg.-El.306'-0"ControlBldg.-El.306'-0"ControlBldg.-El.306'"0"APPLICABILITY:wheneverequipmentprotectedbytheHalonsystemsisrequiredtobeOPERABLE.ACTION:a.Withone-ormoreoftheaboverequiredHalonsystemsinoperable,withinonehourestablishacontinuousfirewatchwithbackupfiresuppressionequipmentforthoseareasinwhichredundantsystemsorcomponentsrcouldbedamaged;forotherareas,establishanhourlyfirewatchpatrol.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.7.4EachoftheaboverequiredHalonsystemsshallbedemonstratedOPERABLE:a.Atleastonceper31daysbyverifyingthateachvalve(manual,poweroperatedorautomatic)intheflowpathisinitscorrectposition.b.Atleastonceper6monthsbyverifyingHalonstoragetankweightor.5~%andpressure.C.Atleastonceper18monthsby:l.Verifyingthesystem,includingassociatedventilationsystemfiredampersandfiredoorreleasemechanisms,actuates,manuallyandautomatically,uponreceiptofasimulatedactuationsignal,and2.Performanceofanairflowtestthroughheadersandnozzlestoassurenoblockage.NINEMILEPOINT-UNIT23/47-27
PLANTSYSTEMSFIREHOSESTATIONSLIMITINGCONOITIONFOROPERATIONFIICK'"Fg'~J'j$<<~/3.7.7.5ThefirehosestationsshowninTable3.7.7.5-1shallbeOPERABLE.APPLICABILITY:Wheneverequipmentintheareasprotectedbythefirehosestations1srequiredtobeOPERABLE.ACTION:'a0b.WithoneormoreofthefirehosestationsshowninTable3.7.6.5-1inoperable,providegatedwye(s)onthenearestOPERABLEhosestation(s).Oneoutletofthewyeshallbeconnectedtothestandardlengthofhoseprovidedforthehosestation.Thesecondoutletofthewyeshallbeconnectedtoalengthofhosesufficienttoprovidecoverageforthearealeftunprotectedbytheinoperablehosestation.Whereitcanbedemonstratedthatthephysicalroutingofthefirehosewouldresultinarecognizablehazardtooperatingtechnicians,plantequipment,orthehoseitself,thefirehoseshallbestoredinarollattheoutletoftheOPERABLEhosestation.Signsshallbemountedabovethegatedwye(s)toidentifytheproperhosetouse.TheaboveACTIONshallbeaccomplishedwithin1houriftheinoperablefirehoseistheprimarymeansoffiresuppression;otherwiseroutetheadditionalhosewithin24hours.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.7.5EachofthefirehosestationsshowninTable3.7.7.5-1shallbedemonstratedOPERABLE:a.Atleastonceper31daysbyavisualinspectionofthefirehosestationsaccessibleduring.plantoperationtoassureallrequiredequipmentisatthestation.b.Atleastonceper18monthsby:1.Visualinspectionofthefirehosestationsnotaccessibleduringplantoperationtoassureallrequiredequipmentisatthestation.2.Removingthehoseforinspectionandre-racking,and3.Inspectingallgasketsandreplacinganydegradedgasketsinthecouplings.c.Atleastonceper3yearsby:1.PartiallyopeningeachhosestationvalvetoverifyvalveOPERABILITYandnoflowblockage.2.Conductingahosehydrostatictestatapressureof150psigoratleast50psig.abovethemaximumfiremainoperatingpressure,whicheverisgreater.NINEMILEPOINT-UNIT23/47"28ROV201985
TABLE3.7.7.5"1FIREHOSESTATIONS~~~Ut'PQf>'!"~.VPppgLOCATIONControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.ControlBldg.DieselGDieselGReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReacto'rReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorReactorBldg.Bldg.Bldg.Bldg..Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.Bldg.eneratorBldg.eneratorBldg.ELEVATION214'-0"214'-0"237'"0"237'-0"250'-0"261'-0"261'-0"288'-6"288'-6"306'-0"306'-0"261[-0"261'-0"175'-0"175'-0"175'-0"198'-0"198'"0"198'-0"215'-0"215I0ll215I-O'I240'-0"240'-0"240'-0"261'-0"261IOll261'-0"261'-0",,289'-0"289'-0"289'-0"289'-0"306'306'-3P328'-10"328'-10"328'-10"328'-10"353'-10"353'-10"353'"10"353'-0"FHRFHR2233FHR74FHR90FHR100FHR102FHR101FHR103FHR73FHR89FHR99FHR72FHR88FHR98FHR71FHR79FHR87FHR94FHR70FHR78FHR86FHR93FHR69FHR77FHR68FHR76FHR85FHR92FHR67FHR75FHR~~FHR91HOSERACKINDENTIFICATIONFHR118FHR119FHR113FHR117FHR30FHR116FHR112FHR111FHR115FHR114FHR110NINEMILEPOINT-UNIT23/47"29NOV201985
TABLE3.7.7.5-1(Continued)FIREHOSESTATIONSI')PP~>g~gpssLOCATIONAux.BayNorthAux.BayNorthAux.BayNorthAux.BayNorthAux.BaySouthAux.BaySouthAux.BaySouthAux.BaySouthScreenwe11B1dg.ELEVATION175'-0"198'-0"215'-0"240'"0"175'"0"198'"0215'"0"240'"OII261'-0"HOSERACKINDENTIFICATIONFHR97FHR104FHR96FHR95FHR83FHR82FHR81FHR80FHR56ELect>>coL,Tu.~pcQ,pe@.)~1pggl~'tpeat3~FeQ.)3GpBP>'38NINEMILEPOINT"UNIT23/47-30HGVaoS
PLANTSYSTEMSYAROFIREHYORANTSANOHYORANTHOSEHOUSESLIMITINGCONDITIONFOROPERATION3.7.7.6TheyardfirehydrantsandassociatedhydranthosehousesshowninTable3.7.7.6-1shallbeOPERABLE.APPLICABILITY:Wheneverequipmentintheareasprotectedbytheyardfirehydrants1srequiredtobeOPERABLE.ACTION:a.b.WithoneormoreoftheyardfirehydrantsorassociatedhydranthosehousesshowninTable3.7.7.6-1inoperable,within1hourhavesufficientadditionallengthsof21/2inchdiameterhoselocatedinanadjacentOPERABLEhydranthosehousetoprovideservicetotheunprotectedarea(s)iftheinoperablefirehydrantorassociatedhydranthosehouseistheprimarymeansoffiresuppression;otherwiseprovidetheadditionalhosewithin24hours.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.7.6Eachofthe115kVswitchyardfirehydrantsandassociatedhydranthosehousesshowninTable3.7.7.6-1shallbedemonstratedOPERABLE:a0b.C.Atleastonceper31daysbyvisualinspectionofthehydranthosehousetoassureallrequiredequipmentisatthehosehouse.Atleastonceper6months,duringMarch,AprilorMayandduringSeptember,OctoberorNovember,byvisuallyinspectingeachyardfirehydrantandverifyingthatthehydrantbarrelisdryandthatthehydrantisnotdamaged.Atleastonceper12monthsby:Conductingahosehydrostatictestatapressureof150psigoratleast50psigabovethemaximumfiremainoperatingpressure,whicheverisgreater.2.Replacementofalldegradedgasketsincouplings.3.Performingaflowcheckofeachhydrant.NINEMILEPOINT-UNIT23/47"31NOV20lg,'
TABLE3.7.7.6-1$){$j$$+gpi<1J+$jlip;%41~J~Z:igyp'fYARDFIREHYDRANTSANDASSOCIATEDHYDRANTHOSEHOUSESLOCATION115kVYard115kVYardHYDRANTNUMBERFH14FH10NINEMILEPOINT-UNIT23/47-32ttOV20t985
PLANTSYSTEMS3/4.7.8FIRERATEDASSEMBLIESLIMITINGCONDITIONFOROPERATION3.7.8Allfirebarrierassemblies,includingwalls,floor/ceilings,cabletrayenclosuresandotherfirebarriers,separatingsafetyrelatedfireareasorseparatingportionsofredundantsystemsimportanttosafeshutdownwithinafirearea,andallsealingdevicesinfireratedassemblypenetrations,includingfiredoors,firedampers,cableandpipingpenetrationsealsshallbeOPERABLE.APPLICABILITY:Atalltimes.ACTION:Mithoneormore'oftheaboverequiredfireratedassembliesand/orsealingdevicesinoperable,withinonehourestablishacontinuousfirewatchonatleastonesideoftheaffectedassembly(s)and/orsealingdevice(s)orverifytheOPERABILITYoffiredetectorsonatleastonesideoftheinoperableassembly(s)and/orsealingdevice(s)andestablishanh'ourlyfirewatchpatrol.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.8.IEachoftheaboverequiredfireratedassembliesandpenetrationsealingdevicesshallbeverifiedOPERABLEatleastonceper18monthsbyperformingavisualinspectionof:a.Theexposedsurfacesofeachfireratedassembly.b.Atleast10percentoftheaboverequiredfiredampersshallbeverifiedOPERABLEbyremovalofthefusablelinkandobservingclosureoftheassociateddamper.Ifadamperfails-:-toclose,anadditional10percentshallbetesteduntila10percentsamplewithnofailuresisfound.Samplesshallbeselectedsuchthateachwillbeinspectedatleastonceper15years.C,Atleast10percentofeachtypeofsealedpenetration.Ifapparentchangesinappearanceorabnormaldegradationsarefound,avisualinspectionofanadditional10percentofeachtypeofsealedpenetrationshallbemade.Thisinspectionprocessshallcontinueuntila10percentsamplewithnoapparentchangesinappearanceorabnormaldegradationisfound.Samplesshallbeselectedsuchthateachpenetrationsealwillbeinspectedatleastonceper15years.NINEMILEPOINT-UNIT23/47-33NQV201985
PLANTSYSTEMSSURVEILLANCEREVIREMENTSContinued~-,-aq~)f~P]fgP'f4.7.8.2EachoftheaboverequiredfiredoorsshallbeverifiedOPERABLEbyinspectingreleaseandclosingmechanismandlatchesatleastonceper6months,andbyverifying:a.Thateachlocked-closedfiredoorisclosedatleastonceper7days.b.Thatdoorswithreleasemechanismsarefreeofobstructionsatleastonceper24hoursandperformingafunctionaltestofthesemechanismsatleastonceper18months.c.Thateachunlockedfiredoorisclosedatleastonceper24hours.NINEMILEPOINT"UNIT23/47-34NOV20>985
PLANTSYSTEMS3l4.7-9MAINTURBINEBYPASSSYSTEMPjgiMF$TILids'RjIsIIPl/LIMITINGCONDITIONFOROPERATION3.7.9ThemainturbinebypasssystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITION1whenTHERMALPQMERisgreaterthanorAAerfRATERTRERMAIPOIIER.ACTION:Withthemainturbinebypasssysteminoperable,restorethesystemto~OPRABLEstatuswithin1hourorreduceTHERMALPOHERtoiessthan25KofRATERTHERMALPOMERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.7.9Themainturbinebypass'system'shallbedemonstratedOPERABLE:a.Atleastonceper18monthsby:Performingasystemfunctionaltestwhichincludessimulatedautomaticactuationandverifyingthateachautomaticvalveactuatestoitscorrectposition.2.DemonstratingTURBINEBYPASSSYSTEMRESPONSETIMEmeetsthe'ollowingrequirementswhenmeasuredfrominitialmovementofthemainturbinestoporcontrolvalve:a.b.BOXoftheturbinebypasssystemcapacityshallbeestab-lishedwithin0.3seconds,andBypassvalveopeningshallstartinlessthanorequalto.0.1seconds.NINEMILEPOINT-UNIT23/47-35Nnv201985
3/4.8ELECTRICALPOWERSYSTEMS3/4.8.1A.C.SOURCESPZF5KFP'fMP7A.C.SOURCES-OPERATINGLIMITINGCONDITIONFOROPERATION3.8.1.1Asaminimum,thefollowingA.C.electricalpowersourcesshallbeOPERABLE:aOb.TwophysicallyindependentcircuitsbetweentheoffsitetransmissionnetworkandtheonsiteClassIEdistributionsystem,andThreeseparateandindependentdieselgenerators,eachwith:1.Separatedayfueltankscontainingaminimumof250gallonsoffuel,2.Aseparatefuelstoragesystemcontainingaminimumof52,664gallonsoffuelforEDG-1(Div.I)andEDG-3(Div.II),and36,173gallonsforEDG-2(HPCS-Div.III)~8a~<3.fueltransferpum~~APPLICABILITY:OPERATIONALCONDITIONS1,2,and3.ACTION:a.WithoneoffsitecircuitoftheaboverequiredA.C.electricalpowersourcesinoperable,demonstratetheOPERABILITYoftheremainingA.C.sourcesbyperformingSurveillanceRequirements4.8.1.1.1.awithinonehourandatleastonceper8hoursthereafter.IfeitherdieselgeneratorEDG-1orEDG-3hasnotbeensuccessfullytestedwithinthepast24hours,demonstrateitsOPERABILITYbyperformingSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5foreachsuchdieselgenerator,separately,within24hoursunlessthedieselgeneratorsarealreadyoperatingandloaded.Restoretheoffsitecir-cuittoOPERABLEstatuswithin72hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours'.b.WitheitherdieselgeneratorEDG-1orEDG-3inoperable,demonstratetheOPERABILITYoftheaboverequiredA.C.offsitesourcesbyperformingSurveillanceRequirement4.8.1.1.l.awith'rkhourandatleastonceper8hoursthereafter.Ifthedieselgeneratorbecameinoperableduetoanycauseotherthanpreplannedpreventivemain-tenanceortesting,demonstratetheOPERABILITYoftheremainingOPERABLEdieselgenerators,separately,byperformingSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5separatelyforeachdieselgeneratorwith24hours.".Restoretheinoperable'dieselThistestisrequiredtobecompletedregardlessofwhentheinoperabledieselgeneratorisrestoredtoOPERABLEstatus.NINEMILEPOINT"UNIT23/48-1NOV301985
ELECTRICALPOMERSYSTEMSLIMITINGCONDITIONFOROPERATIONContinuedFlgAF$P).NnikjniimyACTION(Continued)d.generatortoOPERABLEstatuswithin72hoursorbeinatleastHOTSHUTDOMNwithinthenext12hoursandinCOLDSHUTDOMNwithinthefollowing24hours.Withoneoffsitecircuitoftheabove-requiredA.C.sourcesanddieselgeneratorEDG-1orEDG-3oftheaboverequiredA.C.electricalpowersourcesinoperable,demonstratetheOPERABILITYoftheremainingA.C.sourcesbyperformingSurveillanceRequirement4.8.1.1.awithin1hourandatleastonceper8hoursthereafterIfadieselgenera-torbecameinoperableduetoanycauseothet'<'ffeplannedpreventivemaintenanceortesting,demonstratetheOPERABILITYoftheremainingOPERABLEdieselgenerators,separatelyforeachdieselgenerator,byperformingSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5within8hoursforeachdieselgeneratorwhichhasnotbeensuccess-fullytestedinthepast24hoursunlessthedieselgeneratorsarealreadyoperatingandloaded."-RestoreatleastoneoftheinoperableA.C.sourcestoOPERABLEstatuswithin12hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOMNwithinthefollowing24hours.RestoreatleasttwooffsitecircuitsanddieselgeneratorsEDG-1andEDG-3toOPERABLEstatuswithin72hoursfromtimeofinitiallossorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.MithdieselgeneratorEDG-2oftheaboverequiredA.C.electricalpowersourcesinoperableforreasonsotherthandieselgeneratorroomairtemperature,demonstratetheOPERABILITYoftheoffsiteA.C.sourcesbyperformingSurveillanceRequirement4.8.1.1.3..awithin1hourandatleastonceper8hoursthereafter.Ifthedieselgen-eratorbecomeinoperableasaresultofanycauseotherthandieselgeneratorroomairtemperatureorpreplannedpreventivemaintenanceortesting,demonstratetheOPERABILITYoftheremainingOPERABLEdieselgenerators,separatelybyperformingSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5within24hours."RestoredieselgeneratorEDG-2toOPERABLEstatuswithin72hoursordeclaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecifications3.5.1and3.7.l.l.e.sysemi~~~MithdieselgeneratorEG-1orEDG-3oftheaboverequiredA.C.electricalpowersourcesinoperable,inadditiontotakingACTIONborc,asapplicable,verifywithin2hoursthatallrequiredsystems,subsystems,trains,componentsanddevicesthatdependontheremain-ingOPERABLEdieselgeneratorasasourceofemergencypowerarealsoOPERABLEotherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.ThistestisrequiredtobecompletedregardlessofwhentheinoperabledieselgeneratorisrestoredtoOPERABLEstatus.NINEMILEPOINT-UNIT23/48-2NOV20]985
ELECTRICALPOWERSYSTEMSL(HAt46CoH4tTioMF08-OPERE=a>>~c.m~~e4""P<>~)<fPAQ~/h.Withbothoftheaboverequiredoffsitecircuitsinoperable,demon-stratetheOPERABILITYofthreedieselgenerators,separately,byperformingSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5separatelyforeachdieselgeneratorwithin8hoursunlessthedieselgeneratorsarealreadyoperatingandloaded;restoreatleastoneoftheabove-requiredoffsitecircuitstoOPERABLEstatuswithin24hours0withinthenext12hours.WithonlyneoffsitecircuitrestoredtoOPERABLEstatus,restoreatleasttwooffsitecircuitstoOPERABLEstatuswithin72hoursfromtimeofini-tiallossorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.Asuccessfultest(s)ofdieselgeneratorOPERABILITYperSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5,performedunderthisACTIONstatementfortheOPERABLEdieselgenerators,satisfiesthedieselgeneratortestre"quirementsofACTIONstatementa.WithdieselgeneratorsEDG-1andEDG-3oftheabove-requiredA.C..electricalpowersourcesinoperable,demonstratethe-OPERABILITYoftheremainingA.C.sourcesbyperformingSurveillanceRequirement4.8.1.1.1.awithin1hourandatleastonceper8hoursthereafterandSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.32.a.5fordieselgeneratorEOG-2within8hours."Restoreatleas+@eoftheinoper"abledieselgeneratorsEDG"1andEDG-3toOPERABLEstatuswithin2hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursand'inCOLDSHUTDOWNwithinthefollowing24hours.RestorebothdieselgeneratorsEDG-1andEDG"3toOPERABLEstatuswithin72hoursfromtimeofinitiallossorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.1Withoneoffsitecircuitoftheabove-requiredA.C.electricalpowersourcesinoperableanddieselgeneratorEDG-2inoperable,applytherequirementsofACTIONaanddspecifiedabove.WitheitherdieselgeneratorEDG-1orEDG-3inoperableanddieselgeneratorEDG-2inoperable,applytherequirementsofACTIONb,dandespecified,above.u.<egg~ev.+o~ling"ThistestisrequiredtobecompletedregardlessofwhentheinoperabledieselgeneratorisrestoredtoOPERABLEstatus.NINEMILEPOINT"UNIT23/48-3HQYR0)985
ELECTRICALPOWERSYSTEMSSURVEILLANCEREUIREMENTSppi~1'>>.Fgp,;siirsifIsrip'It4.8.1.1.1EachoftheaboverequiredindependentcircuitsbetweentheoffsitetransmissionnetworkandtheonsiteClassic%distributionsystemsha11be:a.DeterminedOPERABLEatleastonceper7daysbyverifyingcorrectbreakeralignmentsandindicatedpoweravailability.4.8.1.1.2EachoftheaboverequireddieselgeneratorsshallbedemonstratedOPERABLE:a.InaccordancewiththefrequencyspecifiedinTable4.8.1.1.2"1onaSTAGGEREDTESTBASISby:1.Verifyingthefuellevelinthedayfueltank.2.Verifyingthyfuellevelinthefuelstoragetank.Ctssc.~3.Verifying"4he-fueltransferpumpstartsandtransfersfuelfromthestoragesystemtothedayfueltank.4.VerifyingdieselsEDG-1andEDG-3startfromambientconditionsandacceleratetoatleast600rpminlessthanorequalto10secondsanddieselEDG-2startsfromambientconditionsandacceleratestoatleast870rpminlessthanorequalto10seconds."Thegeneratorvoltageandfrequencyshallbe4160t416voltsand6041.2Hzwithin10secondsafterthestartsignaI.Thedieselgeneratorshallbestartedforthistestbyusingoneofthefollowingsignals:5.6.7.a)Manua1.b)Simulatedlossofoffsitepowerbyitself.c)SimulatedlossofoffsitepowerinconjunctionwithanESFactuationtestsignal.d)AnESFactuationtestsignalbyitself.Verifyingthedieselgeneratorissynchronized,loafedto>4300kWfordieselgeneratorsEDG-1andEDG-3an&%500kWfordieselgeneratorEDG-2inaccordancewiththedieselgenerator-manufacturersrecommendationsandoperateswiththeseloadsforatleast60minutes.Verifyingthedieselgeneratorisalignedtoprovidestandbypowertotheassociatedemergencybusses.VerifyingthepressureindieselgeneratorairstartreceiversforEDG-1andEDG-3tobegreaterthanorequalto225""psigandgreaterthanorequalto225""psigforEDG-2.Thedieselgeneratorstartsfromambientconditionsshallbeperformedatleastonceper184daysforEDG-1andEDG-3andatleastonceper366daysforEDG-2inthesurveillancetests.Allotherenginestartsforthepurposeofthissurveillancetestingmaybepreceededbyanengineprelubeperiodand/orotherwarmupproceduresrecommendedbythemanufacturersothatmechanicalstressandwearonthedieselenginesisminimized.~"Tobeverifiedpsass~+vg~e'Les+~sNINEMILEPOINT-UNIT2NOY201085
-ELECTRICALPOMERSYSTEMSSURVEILLANCEREUIREMENTSContinuedF'3MFlPJ73NP7iese~~C+Atleastonceper14days,separately,rotateEDG-1andEDG-3ontheirjackinggeariftheyhavenotbeenstartedinthepast14days.Byremovingaccumulatedwater:1.Fromthedaytankatleastonceper31daysandaftereachocca-sionwhenthedieselisoperatedfromgreaterthan1hour,and2.Fromthestoragetankatleastonceper31days.BysamplingnewfueloilinaccordancewithASTMD4057-81priortoadditiontothestoragetanksand:1.ByverifyinginaccordancewiththetestsspecifiedinASTM0975-81priortoadditiontothestoragetanksthatthesamplehas:a)AnAPIGravityofwithin0.3degreesat604Foraspecificgravityofwithin0.0016at60/60'F,whencomparedtothesupplier'scertificateoranabsolutespecificgravityat60/60'Fofgreaterthanorequalto0.83butlessthanorequalto0.89oranAPIgravity60Fofgreaterthanorequalto27degreesbutlessthanorequalto39degrees.b)Akinematicviscosityat40Cofgreaterthanorequalto1.9centistokes,butlessthanorequalto4.1centistokes,ifgravitywasnotdeterminedbycomparisonwiththesupplierscertification.c)Aflashpointequaltoorgreaterthan125F,andd)AclearandbrightappearancewithpropercolorwhentestedinaccordancewithASTM04176-82.2.Byverifyingwithin31daysofobtainingthesamplethattheotherp'ropertiesspecifiedinTable1ofASTM0975-81aremetwhentestedinaccordancewithASTMD975-81exceptthattheanalysisforsulfurmaybeperformedinaccordancewithASTMD1552-79orASTMD2622-82.Atleastonceevery31daysbyobtainingasampleoffueloilfromthestoragetanksinaccordancewithASTM02276-78,andverifyingthattotalparticulatecontaminationislessthan10mg/literwhencheckedinaccordancewithASTMD2276-78,MethodA.NINEMILEPOINT"UNIT23/48-5
ELECTRICALPOWERSYSTEMSSURVEILLANCEREUIREMENTSContinued)~~~~7P.'3'.;'.1g~ga~rnzAtleastonceper18months,duringshutdown,by:1.1Subjectingthedieseltoaninspectioninaccordancewithproce-durespreparedinconjunctionwithitsmanufacturer'srecom-mendationsforthisclassofstandbyservice.2.<Verifyingthedieselgeneratorcapabilitytorejectaloadofgreaterthanorequalto1125kWfordieselgeneratorEDG"1,greaterthanorequalto750kWfordieselgeneratorEDG-3,andgreaterthanorequalto2433kWfordieselgeneratorEDG-2whilemaintainingenginespeed<75KofthedifferencebetweennominalspeedandtheoverspeedtripsetpointorIS%abovenominal,whicheverisless.3.Verifyingthedieselgeneratorcapabilitytorejectaloadof4300kWfordieselgeneratorsEDG-1andEDG-3and2500kWfordieselgeneratorEDG-2.withouttripping."Thegeneratorvoltageshallnotexceed4576volta'orEDG-1andEDG-3and5824voltsforEDG-2duringandfollowingtheloadrejection.4.Simulatingalossof.offsitepowerbyitself,and:a)Fordivis'ionsIandII:1}Verifyingdeenergizationoftheemergencybussesandloadsheddingfromtheemergencybusses.2)Verifyingthedieselgeneratorstarts"ontheauto-startsignal,energizestheemergencybusseswithpermanentlyconnectedloadswithin13seconds,energizestheauto-connected(shutdown)loadsthroughtheloadtimersandoperatesforgreaterthanorequalto5minuteswhileitsgeneratorisloadedwiththeshutdownloads.Afterenergization,thesteadystatevoltageandfrequencyoftheemergencybussesshallbemaintainedat4160+416voltsand60i1.2Hzduringthistest.b)FordivisionIII:1)2)Verifyingde-energizationoftheemergencybus.Verifyingthedieselgeneratorstarts"+ontheauto-startsignal,energizestheemergencybuswiththepermanentlyconnectedloadswithin13secondsandoperatesfor~y111,111p1111d-ancewiththemanufacturer'srecommendations."Momentarytransientsduetochangingbusloadsshallnotinvalidatethetest.NINEMILEPOINT-UNIT23/48"6Hoy201985
ELECTRICALPOWERSYSTEMSSURVEILLANCEREUIREMENTSContinuedPgfJRK$gpppf$g'pJgreaterthanorequalto5minuteswhileitsgeneratorisloadedwiththeshutdownloads.Afterenergization,thesteadystatevoltageandfrequencyoftheemergency'usshallbemaintainedat4160a416voltsand6021.2Hzduringthistest.5.VerifyingthatonanECCSactuationtestsign@,withoutlossofoffsitepower,thedieselgeneratorstartPontheauto-startsignalandoperatesonstandbyforgreaterthanorequalto5minutes.Thegeneratorvoltageandfrequencyshallbe4160t416voltsand60+1.2Hzwithin10secondsaftertheauto-startsignaI;thesteadystategeneratorvoltageandfrequencyshallbemaintainedwithintheselimitsduringthistest.nasimulatedlossofthediesel,withoffsitepowernotavaefromtheemergencybussesandthatoasngofthe1etorislncewithdesignrequirements.7.SimulatingalossofoffsigepowerinconjunctionwithanECCSactuationtest'signal,and:a)FordivisionsIandII:1)Verifyingdeenergizationoftheemergencybussesandloadssheddingfromtheemergencybusses.2)Verifyingthedieselgeneratorstarts"ontheauto-startsignal,energizestheemergencybusseswithpermanentlyconnect'edloadswithin10seconds,energizestheauto-connected(shutdown)loadsthroughtheloadtimersandoperatesforgreaterthanorequalto5minuteswhileitsgeneratorisloadedwiththeemergencyloads.Afterenergization,thesteadystatevoltageandfre-quencyoftheemergencybussesshallbemaintainedat41602416voltsand6021.2Hzduringthistest.b)FordivisionIII:1)Verifyingde-energizationoftheemergencybus.2)Verifyingthedieselgeneratorstarts~ontheauto-startsignal,energizestheemergencybuswiththepermanentlyconnectedloadsandtheauto-connectedemergencyloadswithin10secondsandoperatesforgreaterthanorequalto5minuteswhileitsgeneratorisloadedwiththeemergencyloads.Afterenergization,thesteadystatevoltageandfrequencyoftheemergencybusshallbemaintainedat4160+416voltsand60+1.2Hzduringthistest.NINEMILEPOINT-UNIT23/48-7NOV20lBU>
ELECTRICALPOWERSYSTEMSSURVEILLANCEREUIREMENTSContinuedFK3F53PJ"P7MP78.9.10.Verifyingthatallautomaticdieselgeneratortripsareauto-matica11ybypasseduponlossofvoltageontheemergencybusconcurrentwithanECCSactuationsignalexceptengineover-speedandgeneratordifferential~~i~Verifyingthedieselgeneratoroperatesforatleast24hours.Duringthefirst2hoursofthistest,,thedieselgeneratorshallbeloadedto>4840kWfordieselgeneratorsEOG-1andEOG-3and2850kWfordieselgeneratorEDG-2.¹Duringtheremaining22hoursofthistest,thedieselgeneratorshallbeloadedto>4300kWfordieselgeneratorsEOG-1andEOG-3and>2500kWfordieselgeneratorEDG-2.¹Thegeneratorvoltageandfrequencyshallbe4160R416voltsand60t1.2Hzwithin10secondsafterthestartsignal;thesteadystategeneratorvoltageandfrequencyshallbemaintainedwithintheselimits,duringthistest.Within5minutesaftercompletingthis24-hourtest<performSurveillanceRequirement4.8.1.1.2.e.4.a~and~.""e.+.b.Verifyingthattheauto-connectedloadstoeachdieselgeneratordonotexceedthe2000-hourratingof4750kWfordieselgenera-torsEDG-1andEDG-3and2850kWfordieselgeneratorEDG-2.Verifyingthedieselgenerator'scapabilityto:a)Manuallysynchronizewiththeoffsitepowersourcewhilethegeneratorisloadedwithitsemergencyloadsuponasimulatedrestorationofoffsitepower,b)Transferitsloadstotheoffsitepowersource,andc)Berestoredtoitsstandbystatus.'""IfSurveillanceRequirement4.8.1.1.2.P.'4.a)2)and/orb)2)arenotsatisfac-torilycompleted,itisnotnecessarytorepeatthepreceding24hourtest.Instead,thedieselgeneratormaybeoperatedat>4300kWforEDG-1andEDG-3and>2500kWforEDG-2foronehouroruntiloperatigtemperaturehasstabilizedy~y,g..f.l,g.-p,4,a.¹Momentarytransientsduetochangingbusloadsshallnotinvalidatethetest.NINEMILEPOINT-UNIT23148-8NOV80]gal'
ELECTRICALPOMERSYSTEMSSURVEILLANCEREUIREMENTSContinuedltlfIfv)PI~rjflg!)IsitF~tf12.Verifyingthatwiththedieselgeneratoroperatingina.testmodeandconnectedtoitsbus,asimulatedECCSactuationsignaloverridesthetestmodeby(1)returningthedieselgeneratortostandbyoperation,and(2)automaticallyenergizestheemergencyloadswithoffsitepower.13.VerifyingthattheautomaticloadtimerrelaysareOPERABLEwiththeintervalbetweeneachloadblockwithin+10KofitsdesignintervalfordieselgeneratorsEDG-1andEDG-3.14.Verifyingthatthefollowing'dieselgeneratorlockoutfeaturespreventdieselgeneratorstartingonlywhenrequired:a)b)ForDivisionsIandII,turninggearengagedandemergencystop.ForDivisionIII,.engineinthemaintenancemodeanddieselgeneratorlockout.Atleastonceper10yearsorafteranymodificationswhichcouldaffectdieselgeneratorinterdependencebystartingallthreedieselgeneratorssimultaneously,during-shutdown,andverifyingthatalldieselgeneratorsEDG-1andEDG-3acceleratetoatleast600rpmand808-2acceleratestoatleast870rpainlessthanorequaltoAtleastonceper10yearsby:1.Drainingeachfueloil,storagetank,removingtheaccumulatedsedimentandcleaningthetankusingasodiumhypochloritesolu-tion,and2.Performingapressuretestofthoseportionsofthedieselfuel'ilsystemdesignedtoSectionIII,subsectionNDoftheASMECodeinaccordancewithASMECodeSectionIIArticleIMD-5000.-4.8.1.1.3~Reorts-A11dieselgeneratorfailures,validornon-valid,shallbereportedtotheCommissionpursuanttoSpecification6.9.l.ReportsofdieselgeneratorfailuresshallincludetheinformationrecommendedinRegulatoryPositionC.3.bofRegulatoryGuide1.108,Revision1,August1977.Ifthenumberoffailuresinthelast100validtests,onapernuclearunitbasis,isgreaterthanorequalto7,thereportsha11besupplementedtoincludetheadditionalinformationrecommendedinRegulatoryPositionC.3.bofRegulatoryGuide1.108,Revision1,August1977.NINEMILEPOINT-UNIT23/48-9N{)Y8vivv~
TABLE4.8.1.1.2-1I">>ALIIQgQ/>p:"J(ATE>fDIESELGENERATORTESTSCHEDULENumberofFailuresinNumberofFailuresinLTOOVTTdTLOOOVTTdT"~TFAtleastonceper31daysAtleastonceper14daysCriteriafordeterminingnumberoffailuresandnumberofvalidtestsshallbeinaccordancew'ithRegulatoryPositionC.2.eofRegulatoryGuide1.108,butdeterminedonaperdieselgeneratorbasis~Forthepurposesofdeterminingtherequiredtestfrequency,theprevioustestfailurecountmaybereducedtozeroifacompletedieseloverhaultolike-newconditioniscompleted,providedthattheoverhaul,includingappropriatepost-maintenanceoperationandtesting,isspecificallyap-provedbythemanufacturerandifacceptablereliabilityhasbeendemon-strated.Thereliabilitycriterionshallbethesuccessfulcompletionof14consecutivetestsinasingleseries.TenofthesetestshallbeinaccordancewiththeroutineSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5andfourtestsinaccordancewiththe184-dayandthe366-daytestingrequirement,asapplicable,ofSurveillanceRequirements4.8.1.1.2.a.4and4.8.1.1.2.a.5.Ifthiscriterionisnotsatisfieddur"ingthefirstseriesoftests,anyalternatecriteriontobeusedtotransvaluethefailurecounttozerorequiresNRCapproval.""Theassociatedtestfrequencyshallbemaintaineduntilsevenconsecutivefailurefreedemandshavebeenperformedandthenumberoffailuresinthelast20validdemandshasbeenreducedtoone.NINEMILEPOINT-UNIT23/48-10NQV201!
ELECTRICALPOWERSYSTEMSA.C.SOURCES-SHUTDOWNPi>fvl5Ps~Yig1'ggjLIMITINGCONDITIONFOROPERATION3.8.1.2Asaminimum,thefollowingA.C.electricalpowersourcesshallbeOPERABLE:a.OnecircuitbetweentheoffsitetransmissionnetworkandtheonsiteClass1Edistributionsystem,andb.DieselgeneratorEDG-1orEDG-3,anddieselgeneratorEDG-2whentheHPCSsystemisrequiredtobeOPERABLE,witheachdieselgeneratorhaving:1.Dayandenginemountedfueltankscontainingaminimumof250gallonsoffuel.2.Afuelstoragesystemcontainingaminimumof52,664gallonsoffuelforEDG"1andEDG-3and36,1?3gallonsoffuelforEDG-2.-t~odlI-3.A-fueltransferpumps:.APPLICABILITY:OPERATIONALCONDITIONS4,5and".ACTION:aOC.WithlessthanthetheaboverequiredA.C.electricalpowersourcesOPERABLE,suspendCOREALTERATIONS,handlingofirradiatedfuelinthesecondarycontainment,operationswithapotentialfordrainingthereactorvesselandcraneoperationsoverthespentfuelstoragepoolwhenfuelassembliesarestoredtherein.Inaddition,inOPERATIONALCONDITION5,withthewaterlevellessthan22'-3"abovethereactorpressurevesselflange,immediatelyinitiatecorrectiveactiontorestoretherequiredpowersourcestoOPERABLEstatusassoonaspractical.WithdieselgeneratorEDG-2oftheaboverequiredA.C.electricalpowersourcesinoperable,restoretheinoperabledieselgeneratortoOPERABLEstatuswithin72hoursordeclaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.2and3.5.3TheprovisionsofSpecification3.0.3arenotapplicable.SURVEILLANCEREUIREMENTS4.8.1.2AtleasttheaboverequiredA.C.electrical.powersourcesshallbedemonstratedOPERABLEperSurveillanceRequirements4.8.1.1.1,4.8.l.1.2,and4.8.1.1.3,exceptfortherequirementof4.8.1.1.2.a.5.Whenhandlingirradiatedfuelinthesecondarycontainment.NINEMILEPOINT-UNIT23/48-11go>20198S
ELECTRICALPOWERSYSTEMS3/4.8.2D.C.SOURCESD.C.SOURCES-OPERATINGLIMITINGCONDITIONFOROPERATIONpW5~Pht%PL11%%leAAatPciVUi'5")~filiUUi'i3.8.2.1Asaminimum,thefollowingD.C.electricalpowersourcesshallbeOPERABLE:a.DivisionI,consistingof:1.125voltbattery2BYS"BAT2Aand2.one125voltfullcapacitycharger.b.DivisionII,consistingof:l.125voltbattery2BYS"BAT2Band2.one125voltfullcapacitycharger.c.DivisionIII,consistingof:l.125voltbattery2BYS~BAT2Cand~2.one125voltfullcapacity-charger.APPLICABILITY:OPERATIONALCONDITIONS.1,2and3.ACTION:'a0b.WitheitherDivisionIorDivisionIIbatteryand/orchargeroftheabove.requiredD.C.electricalpowersourcesinoperable,restoretheinoperabledivisionD.C.electricalpowersource(s)toOPERABLEstatuswithin2hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.WithDivisionIIIbatteryand/orchargeroftheaboverequiredD.C.electricalpowersourcesinoperable,declaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.1.SURVEILLANCEREUIREMENTS4.8.2.1Eachoftheaboverequired125-voltbatteriesandchargersshallbedemonstratedOPERABLE:a.Atleastonceper7daysbyverifyingthat:1.TheparametersinTable4.8.2.1-1meettheCategoryAlimits,and2.Totalbatteryterminalvoltageisgreaterthanorequalto130-voltsonfloatcharge;NINEMILEPOINT-UNIT23/48"12NOV20>ggg
ELECTRICALPOWERSYSTEMSSURVEILLANCEREUIREMENTSContinuedb.C.d.Atleastonceper92daysandwithin7daysafterabatterydischargewithbatteryterminalvoltagebelow107-volts,orbatteryoverchargewithbatteryterminalvoltageabove142-volts,byverifyingthat:1.TheparametersinTable4.8.2.1-1meettheCategoryBlimits,2.Thereisnovisiblecorrosionateitherterminalsorconnectors.3.Theaverageelectrolytetemperatureofoneoutoffiveconnectedcellsisabove60F.Atleastonceper18monthsbyverifyingthat:1.Thecells,cellplatesandbatteryracksshownovisualindica-tionofphysicaldamageorabnormaldeterioration,2.Thecell-to-cellandterminalconnectionsareclean,tight,freeofcorrosion,3.Theresistanceofeachcell-to-cellandterminalconnectionis<120KoftheresistancereadingstakenduringinitialTnstallation,"ander4.Thebatterychargerwillsupply:1.ForDivisionsIandII,atleast300amperesataminimumof130voltsforatleast4hours.2.FurDivisionIII,atleast50amperesataminimumof130voltsforatleast4hours.Atleastonceper18months,duringshutdown,byverifyingthateither:1.ThebatterycapacityisadequatetosupplyandmaintaininOPERABLEstatusalloftheactualemergencyloadsfor2hoursforDivisionsIandII,and2hoursforDivisionIIIwhenthebatteryissubjectedtoabatteryservicetest,or2.Thebatterycapacityisadequatetosupplyadummyloadofthefollowingprofilewhilemaintainingthebatteryterminalvoltagegreaterthanorequalto105volts.a)Oivision1.Greaterthanorequalto818amperesduringthe>mtsai60seconds;greaterthanorequalto445amperesduringthenext118minutes;'andgreaterthanorequalto701amperesduringtheremainderofthe2hourtest.so~b)DivisionII.Greaterthanorequaltoamperesduringthe1nst1al60seconds;greaterthanorequalto449amperesduringthenext118minutes;andgreaterthanorequalto505amperesduringtheremainderofthe2hourtest.c)DivisionIII.Greaterthanorequalto54.6amperesduringtheinstial60seconds;greaterthanorequalto15.4amperesduringtheremainderofthe2hourtest.InaccordancewithIEEE450-1980.NINEMILEPOINT-UNIT23/48-13HOV30iggg i ELECTRICALPOWERSYSTEMSSURVEILLANCEREUIREMENTSContinued)<~<~~~IPPiB6&7e.Atleastonceper60monthsduringshutdownbyverifyingthatthebatterycapacityisatleast80Kofthemanufacturer'sratingwhensubjectedtoaperformancedischargetest.Duringthisonceper60monthinterval,thisperformancedischargetestmaybeperformedinlieuofthebatteryservicetest.f.Atleastonceper18months,duringshutdown,performdischargetestsofbatterycapacityshallbe,giventoanybatterythatshowssignsofdegradationorhasreached85Koftheservicelifeexpectedfortheapplication.Degradationisindicatedwhenthebatterycapacitydropsmorethan10Kofratedcapacityfromitsaverageonpreviousperformancetests,orisbelow90Kofthemanufacturer'srating.NINEMILEPOINT-UNIT23/48"14hfOV20]985
TABLE4.8.2.1-1BATTERYSURVEILLANCEREUIREMENTSPtigg$)gPPyI~envyCATEGORYA()CATEGORYB()PARAMETERLIMITSFOREACHDESIGNATEDPILOTCELLLIMITSFOREACHALLOWABLECONNECTEDCELLVALUEFOREACHCONNECTEDCELLElectrolyteLevel>Minimumlevelindicationmark,and<V'bovemaximumleve'lindicationmark>Minimumlevelindicationmark,and<4"abovemaximumlevelindicationmarkAbovetopofplates,andnotoverflowingFloatVoltage>2.13volts>2.13volts()>2.07voltsSpecifipGravity'P>1.200(")>1.195Averageofallconnectedcells>1.205Notmorethan0.020belowtheaverageofallconnectedcel1sAverageofallconnect~))ce1le>1.195Correctedforelectrolytetemperatureandlevel.(a)Orbatterychargingcurrentislessthan2ampereswhenonfloatcharge.Maybecorrectedforaverageelectrolytetemperature.(c)ForanyCategoryAparameter(s)outsidethelimit(s)shown,thebatterymaybeconsideredOPERABLEprovidedthatwithin24hoursalltheCategoryBmeasurementsaretakenandfoundtobewithintheirallowablevalues,andprovidedallCategoryAandBparameter(s)arerestoredtowithinlimitswithinthenext6days.ForanyCategoryBparameter(s)outsidethelimit(s)shown,thebatterymaybeconsideredOPERABLEprovidedthattheCategoryBparametersarewithintheirallowablevaluesandprovidedtheCategoryBparameter(s)arerestoredtowithin'limitswithin7days.AnyCategoryBparameternotwithinitsallowablevalueindicatesaninoperablebattery.NINEMILEPOINT-UNIT23/48-15NOY20j985
ELECTRICALPOMERSYSTEMSD.C.SOURCES-SHUTDOMN'IMITINGCONDITIONFOROPERATIONpnAaep~pyzy~~qp~3.8.2.2Asaminimum,DivisionIorDivisionII,and,whentheHPCSsystemisrequiredtobeOPERABLE,DivisionIII,oftheD.C.electricalpowersourcesshallbeOPERABLEwith:a.DivisionIconsistingof:1.125voltbattery2BYS~BAT2Aand2.one125voltfullcapacitycharger.b.DivisionIIconsistingof:1.125voltbattery2BYS*BAT2Band2.one125voltfullcapacitycharger.c.DivisionIIIconsistingof:1.125voltbattery2BYS*BAT2Cand2.one125voltfullcapacitycharger.APPLICABILITY:OPERATIONALCONDITIONS4,5and".ACTION:a4b.C.WithlessthantheDivisionIand/orDivisionIIbatteryand/orchargeroftheaboverequiredD.C.electricalpowersourcesOPERABLE,suspendCOREALTERATIONS,handlingofirradiatedfuelinthesecondarycontainmentandoperationswithapotentialfordrainingthereactorvessel.MithDivisionIIIbatteryand/orchargeroftheaboverequiredD.C.electricalpowersourcesinoperable,declaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.2and3.5.3.TheprovisionsofSpecification3.Q.3arenotapplicable.SURVEILLANCEREUIREMENTS4.8.2.2-At1easttheaboverequiredbatteryandchargershallbedemonstratedOPERABLEperSurveillanceRequirement4.8.2.1.Whenhand>ngsrradiatedfuelinthesecondarycontainment.NINEMILEPOINT-UNIT23/48"16NOY201S85
ELECTRICALPOWERSYSTEMS3/4.8.3QNSITEPOWERDISTRIBUTIONSYSTEMSDISTRIBUTION-OPERATINGLIMITINGCONDITIONFOROPERATIONFftois(CgiAD/PIP(P~f(gpPf3.8.3.1ThefollowingpowerdistributionsystemdivisionsshallbeenergizedwithtiebreakersopenbetweenDivisionIandDivisionIIbuses:a.A.C.PowerDistribution1.DivisionI,consistingof:2.3.a}b}c)4160voltA.C.bus.600voltA.C.LoadCenter/MCC's/distributionpanels.2AQ/120vo1tA.C.and120vo1tA.Cdistributionpanelsenergizedfrominverter2VBg"UPS2A."ADivisionII,consistingof:a)4160voltA.C.bus.b)600voltA.C.LoadCenter/MCC's/distributionpanels.c)240/120voltA.C.and120A.C.vo)tdistributionpanelsenergizedfrominverter2VB$"UPSf2B"DivisionIII,consistingof:a)4160voltA.C.bus.b)600voltA.C.LoadCarper/MCC's/distributionpanels.c)240/120voltA.C.a~20voltA.C.distributionpanelsd)HPCginverterenergizedfromDivisionIIIbatteries.9b.D.C.PowerDistribution1.DivisionI,consistingof125voltO.C.switchgear,MCCandassociateddistributionpanels:2BYS"PNL203A;2BYS"PNL202A;2BYS"PNL204A.2.DivisionII,consistingof125voltD.C.switchgear,MCCandassociateddistributionpanels:2BYS"PNL201B;2BYS"PNL202B;2BYS~PNL204B.3.DivisionIII,consistingof125voltO.C.switchgear,MCCandassociateddistributionpanels:2BYS"PNL201C;2BYS"PNL202C,2BYS"PNL204C.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:a.ForA.C.powerdistribution:1.MitheitherDivisionIorDivisionIIoftheaboverequiredA.C.distributionsystemnotenergized,re-energizethedivisionwithin8hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLOSHUTDOMNwithinthefollowing24hours.2.MithDivisionIIIoftheaboverequiredA.C.distributionsystemnotenergized,declaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.1.TheUPSshallbeenergizedfromtheirnormalA.C.supplyortheirbackupD.C.supply.NINEMILEPOINT-UNIT23/48-17NOV80j98$ I ELECTRICALPOWERSYSTEMSLIMITINGCONDITIONFOROPERATIONContinuedACTION:(Continued)b.ForQ.C.powerdistribution:1.WitheitherDivisionIorDivisionIIoftheaboverequiredD.C.distributionsystemnotenergized,re-energizethedivisionwithin2hoursorbeinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.2.WithDivisionIIIoftheaboverequiredD.C.distributionsystemnotenergized,declaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.1.SURVEILLANCEREUIREMENTS4.8.3.1.1Eachoftheaboverequiredpowerdistributionsystemdivisions,shallbedeterminedenergizedatleastonceper7daysbyverifyingcorrectsupplybreakeralignmentandbyverifyingnobypassinoperabilitystatusindicatorlightsinthecontrolroomarelit."4.8.3.1.2Eachoftheaboverequiredpowerdistributionswitchgearshallbedeterminedenergizedatleastonceper7daysbyverifyingthevoltageonthepanels.Whichwould1ndicatealossofpowertooneormoreoftherequiredMCCs,loadcenterorpanels.NINEMILEPOINT-UNIT23/48"18NOY20185.
ELECTRICALPOWERSYSTEMSDISTRIBUTION-SHUTDOWNLIMITINGCONDITIONFOROPERATIONPP8gFc(ppp)(gpp3.8.3.2Asaminimum,thefollowingpowerdistributionsystemdivisionsshallbeenergized:a.ForA.C.powerdistribution,DivisionIorDivisionII,andwhentheHPCSsystemisrequiredtobeOPERABLE,DivisionIII,with:b.1.DivisionIconsistingof:a)4160voltA.C.bus.b)600voltA.C.LoadCenter/MCC's/distributionpanels.c)240/120voltA.C.and4QSF120vol/A.C.distributionpanels;energizedfrominverter2VBPUPSP2Aoralternatesupply.*2.DivsionIIconssstsngof.a)4160voltA.C.bus.b)600voltA.C.LoadCenter/MCC's/distributionpanels.c)240/120voltA.C.and~120vol/A.C.distributionpanels;energizedfrominverter2VB)f"UPS/'2Boralternatesupply.A3.DivisionIIIconsistingof:a)4160voltA.C.bus.b)600voltA.C.LoadCenter/MCC's/distributionpanels.c)240/120voltA.C.and120voltA.C.distributionpanels;d)HPCginverterenergizedfmDivisionIIIbatteries.5rForD.C.powerdistribution,Divis)IorDivisionII,andwhentheHPCSsystemisrequiredtobeOPERABLE,DivisionIII,with:l.DivisionIconsistingof125voltD.C.Switchgear,MCCanddistribu-.tionpanels.3.DivisionIIIconsistingof125voltD.C.Switchgear,MCCanddistributionpanels.2.DivisionIIconsistingof125voltD.C.Switchgear,MCCanddistribu-tionpanels.APPLICABILITY:OPERATIONALCONDITIONS4,5and".Whenhandlingirradiatedfuelinthesecondarycontainment.NINEMILEPOINT-UNIT23/48-19NOV20]985
ELECTRICALPOWERSYSTEMSPi~ÃF53BilMKHfLIMITINGCONDITIONFOROPERATION(ContinuedACTION:a.ForA.C.powerdistribution:1.WithlessthanDivisionIandDivisionIIoftheaboverequiredA.C.distributionsystemenergized,suspendCOREALTERATIONS,handlingofirradiatedfuelinthereactorbuildingandoperationswithapoten-tialfordrainingthereactorvessel.2.WithDivisionIIIoftheaboverequiredA.C.distributionsystemnotenergized,declaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.2and3.5.3.b.ForD.C.powerdistribution:~M1.WithlessthanDivisionIandDivisionIIoftheaboverequiredD..C.distributionsystemenergized,suspendCOREALTERATIONS,handlingofirradiatedfuelintheReactorBuilding,andoperationswithapotentialfordrainingthereactorvessel.2.WithDivisionIIIoftheaboverequiredD.C.distributionsystemnotenergized,denlaretheHPCSsysteminoperableandtaketheACTIONrequiredbySpecification3.5.2and3.5.3.C.TheprovisionsofSpecification3.0.3arenotapplicable.SURVEILLANCEREUIREMENTS4.8.3.2.1Atleasttheaboverequiredpowerdistributionsystemdivisionsshallbedeterminedenergizedatleastonceper7daysbyverifyingcorrectsupplybreakeralignmentandbyverifyingnobypassinoperabilitystatusindicatorlightsinthecontrolroomarelit."4.8.3.2.2Eachoftheaboverequiredpowerdistributionswitchgearshallbedeterminedenergizedatleastonceper7daysbyverifyingthevoltageonthepanels.WhichwouldindicatelossofpowertooneormoreoftherequiredMCCs,loadcentersorpanels.NINEMILEPOINT-UNIT23/48-20JiQV20$85
ELECTRICALPOSERSYSTEMS3/4.8.4ELECTRICALEUIPMENTPROTECTIVEDEVICESA.C.CIRCUITSINSIDEPRIMARYCONTAINMENTP~MF5KIIlMN'IF/LIMITINGCONDITIONFOROPERATION3.8.4.1TheA.C.circuitsinsideprimarycontainmentshowninTable3.8.4.1-1shallbede"energized:"APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:Withanyoftheaboverequiredcircuitsenergized,triptheassociatedcircuitbreaker(s)inthespecifiedpanel(s)within1hour.SURVEILLANCEREUIREHENTS4.8.4.1EachoftheaboverequiredA.C;circuitsshallbedeterminedtobede-energizedatleastonceper24hours""byverifyingthattheassociatedcircuitbreakers-are-in-the-trTpped-condition;Requiredpriortopowerascensionandfollowingfinaldrywellinspection.""Exceptatleastonceper31daysiflocked+~Aashandsecuredin.thetrippedconditionbytaggingouttheequipment.NINEMILEPOINT-UNIT'23/48"21NOV201985
l1lIfOTABLE3.8.4.1"1PRIMARYCONTAINMENTACCIRCUITSERM%9.coiZ~>C)MICIRCUITNOPOWERSOURCECIRCUITBKRNOEUIPHENTPOMEREON12-11N12-12N12-132LARPNLN122LAR-PNLN122LAR-PNLN12111213NormalLightingCKTS-Elev.261'ormalLightingCKTS-Elev.261'ormalLightingCKTS-Elev.261'12-14N12-15N12-16N12-17N12-18H12-192LAR-PNLN122LAR-PHLN122LAR-PNLN122LAR-PNLN122LAR-PNLN122LAR-PNLN12141516171819NormalNormalNormalNormalNormalNormalLightingCKTS-Elev.289'ightingCKTS-Elev.289'ightingCKTS-Elev.289'ightingCKTS-Elev.240'ightingCKTS-Elev.240'ightingCKTS-Elev.240'LC4NCOCllCOIN12-1N12-2N12-3N05-14U02"14U02-15U02-16U02-12H03-7NAHANANANAHA2LAR-PNLN122LAR-PNLN122LAR-PNLN122LAR-PNLN052LAR-PNLU022LAR-PNLU022LAR-PNLU022LAR-PNLU022LAR-PNLH032WPS-PNL2002WPS-PNL2002WPS-PNL2002WPS-PHL2002WPS-PNL2002WPS-PNL2001414151612202224262830NormalRechptacleCKTS-Elev.240'ormalReceptacleCKTS-Elev.261'ormalReceptacleCKTS-Elev.289'MForNormalLTGContractorCoilCKTEssentialLightingCKTS-Elev.240'ssentialLightingCKTS-Elev.261'ssentialLightingCKTS-Elev.289'MForEssentialLTGContractorCoilCKTNormalReceptacleCKTS-SuppPool2WPS-RCPT51A&B-MeldingReceptEley261'2WPS-RCPT51A&B-MeldingReceptElev261'WPS-RCPT51A&B-MeldingReceptElev261'WPS-RCPT52A&B-WeldingReceptElev261'WPS-RCPT52A&B-WeldingReceptElev261'WPS-RCPT52A8B-MeldingReceptElev261'
TABLE3.8.4.1-1(cont)PRIMARYCONTAINMENTACCIRCUITSC)I2DERA032NNS-MCC012CIRCUITNOPOMERSOURCESECT7BEUIPMENTPOWERED2DER"MOV128-REACTORDRAINISOL.VALVE2RHSA252RHSB25NANANA2EHS"HCC1032EHS"MCC3032NHS-MCC0052NHS-MCC0052NHS-MCC0052NHS-MCC0052NHS-MCC00522A21C7B7C7D7E7F2RHS~MOV67A-RHRASHTONCLGCVBYPASS2RHS"MOV67B"RHRBSHTONCLGCVBYPASS2HHR-CRN3-RECIRCMTRHNDLGCRANE-AMHR-PNL1012MHR-CRN4-RECIRCMTRHNDLG'RANE-AMHR"PNL1022HHR-CRN65-MONRAIL2TONFOR2MSS"PSVZMHR-CRN66"MONORAIL2TONFORRDSCARTZMHR-CRN67-MONORAIL2TONFORZMSS"HVYVALVES(OCOCfl
mMITABLE3.8.4.1-1(cont)PRIMARYCONTAINMENTACCIRCUITSDESkl&RG1M')aC)MIU01-15U03-122LAR-PNLUOl2LAR-PNLU03CIRCUITNOPOWERSOURCECIRCUITBKRRO1512EUIPMENTPOWEREDComm-PartyPagingSuppressionPoolComm-PartyPagingAboveSuppressionPoolCIRCUITNONAMAINTENANCE/CALIBR.SELECTORSWITCHPANELRSC-88RSC-88RSC-88RSC-88SWITCHNO128134137EUIPHENTPOWEREDMaintenance/CalibrationJack-JK124Maintenance/CalibrationJack-JK128Maintenance/CalibrationJack-JK134Maintenance/CalibrationJack-JK137C)CPnp>I1 a1 ELECTRICALPOWERSYSTEMSPRIMARYCONTAINMENTPENETRATIONCONDUCTOROVERCURRENTPROTECTIVEDEVICESLIMITINGCONDITIONFOROPERATION3.8.4.2A'llPrimarycontainmentpenetrationconductorovercurrentprotectivedevices"shallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1,2and3.ACTION:a.Mithoneormoreoftheprimarycontainmentpenetrationconductorovercurrentprotectivedevices"inoperable,declaretheaffectedsystemorcomponentinoperableandapplytheappropriateACTIONstatementfortheaffectedsystemand:1333k~ittt88-318338~3circuitsbytrippingtheassociatedredundantcircuitbreaker(s)within72hoursandverifytheredundantcircuitbreakertobetrippedatleastonceper7daysthereafter.2.For600voltMCCcircuitbreakers,removetheinoperablecircuitbreaker(s)fromservicebyrackingoutthe-breakerwithin72hoursandverifytheinoperablebreaker(s)tobeinthedisconnectpositionatleastonceper7daysthereafter.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hoursandinCOLDSHUTDOWNwithinthefollowing24hours.b.TheprovisionsofSpecification3.0.4arenotapplicabletoovercurrentdevicesin13.8.circuitswhichhavetheirredundantcircuitbreakerstrippedorto600voltcircuitswhichhavetheinoperablecircuitbreakerdisconnected.SURVEILLANCEREUIREMENTS4.8.4.2Eachoftheprimarycontainmentpenetrationconductorovercurrentpro-tectivedevices"shallbedemonstratedOPERABLE:a.Atleastonceper18months:1.Byverifyingthatthemediumvoltage13.8~d-3;.~kVcircuitbreakersareOPERABLEbyselecting,onarotatingbasis,atleast10Kofthecircuitbreakersofeachvoltagelevelandperforming:a)ACHANNELCALIBRATIONoftheassociatedprotectiverelays,andb)Anintegratedsystemfunctionaltestwhichincludessimulatedautomaticactuationofthesystemandverifyingthateachrelayandassociatedcircuitbreakersandover-currentcontrolcircuitsfunctionasdesigned.Excludedfromthisspecificationarethosepenetrationassembliesthatarecapableofwithstandingthemaximumcurrentavailableduetoanelectricalfaultinsidecontainment.NINEMILEPOINT-UNIT23/48-25NOYRO1885
ELECTRICALPOMERSYSTEMSSURVEILLANCEREUIREMENTSContinued)2.c)Foreachcircuitbreakerfoundinoperableduringthese.functionaltests,anadditionalrepresentativesampleofatleastIOXofallthecircuitbreakersoftheinoperabletypeshallalsobefunctionallytesteduntilnomorefailuresarefoundorallcircuitbreakersofthattypehavebeenfunctionallytested.Byselectingandfunctionallytestingarepresentativesampleofatleast10Kofeachtypeoflowervoltagecircuitbreakers.CircuitbreakersselectedforfunctionaltestingshallbeseIectedonarotatingbasis.Testingofthesecircuitbreakersshallconsistofinjectingacurrentwithavalueequalto300Kofthepickupofthelongtimedelaytripelementand150Kofthepickupoftheshorttimedelaytripelement,andverifyingthatthecircuitbreakeroperateswithinthetimedelaybandwidthforthatcurrentspecifiedbythemanufacturer.Theinstantaneouselementshallbetestedbyinjectingacurrentequalto+20Kofthepickupvalueoftheelementandverifyingthatthecircuitbreakertripsinstantaneouslywithnointen-tionaltimedelay.Moldedcasecircuitbreakertestingshallalsofollowthisprocedureexceptthat,generallynomorethantwotripelements,timedelayandinstantaneous,willbeinvolved.)CircuitbreakersfoundinoperableduringfunctionaltestingshallberestoredtoOPERABLEstatuspriortoresumingoperation.Foreachcircuitbreakerfoundinoperableduringthesefunctionaltests,anadditionalrepresentativesampleofatleast,10KofaIIthecircuitbreakersoftheinoperabletypeshallalsobefunctionallytesteduntilnomorefailuresarefoundorallcircuitbreakersofthattypehavebeenfunctionallytested.b.Atleastonceper60monthsbysubjectingeachcircuitbreakertoaninspectionandpreventivemaintenanceinaccordancewithprocedurespreparedinconjunctionwithitsmanufacturer'srecommendations.NINEMILEPOINT-UNIT23/48-2650V20Loqc
ELECTRICALPOWERSYSTEMSEMERGENCY'IGHTINGSYSTEM-OVERCURRENTPROTECTIVEDEVICESLIMITINGCONOITIONFOROPERATION3.8.4.3TheemergencylightingsystemovercurrentprotectiondevicesshowninTable3.3.4.3~she'llbeOPERABLEAPPLICABILITY:Atalltimes.ACTTON:liithoneormoreoftheovercurrentprotectivedevice&showninTable3.8.4.3-1inoperable,within72hoursremovetheinoperablecircuitbreaker(s)fromservicebyopening.'thebreaker.Returnthebreaker(s)toOPERABLEstatuswithin7days,otherwisebeinatleastHOTSHUTOOWNwithinthenext12hoursandinCOLOSHUTOOWNwithinthefollowing24hours.ISURVEILLANCEREUIREMENTS4.8.4.3TheovercurrentprotectivedevicesshallbedemonstratedOPERABLEatleastonceper18moqthsbyselectingandtestingone-halfofeachtypeofcircuitbreakeronarotatingbasis.Testingofthesecircuitbreakersshallconsistofinjectingcurrentsinexcessofthebreaker'snormalsetpointandmeasuringdthesetpointoftheinstantaneouselement,asappropriate.Themeasureddatashallbecomparedtothemanufacturer'sdatatoensurethatitislessthanorequaltoavaluespecifiedbythemanufacturer.NINEMILEPOINT-UNIT23/48-27HOV20>SSS
MmMImTable3.8.4.3-1OVERCURRENTPROTECTIVEDEVICESFORNONCLASS1ELIGHTINGFIXTURESONCLASS1EEMERGENCYSYSTEM4DIPRIMARYCIRCUITBREAKERBACKUPCIRCUITBREAKERC:HFR/TYPECURRENTRATINGE(UIPHENTPOWEREDLOCATION-120/208VHFR/TYPECURRENTCIRPOWERSUPPLYRATINGNO.LOCATION-600VMI00GOULD-EH100AGOULD-EH100AGOULD-EH100AGOULD-EH100A2LAC"PgEOlDivISMGRDIESELGEN.RH.8REM(RESHUTDOWNRM.2LAC*PNLE04RELAYROON2LAC"PNLE06CONTROLROOM2LAC"P2DivIISWGRDIESELGEN.RH.8REHOSHUTDOMNRH.GOULD"HE45AGOULD-HE45AGOULD,-HE45AGOULD-HE45AQLAcwP+Li4W2LAC"PNL100AQL+cwp~L,<oem'Q.LAC~f'HL-Zoo+CiGOULD-EH100AGOULD-EH100AGOULD-EH100A2LAC*PNLE05RELAYROOM2LAC"PNLE07CONTROLROOM2LAC"PNLE3Div.IIISMGRDIESELGENRH.GOULD-HE45AGOULD-HE45AGOULD"HE45A2LAC"PNL300B2~ac~V~Compt10B2EHS"MCC201r~gf/'"0
P;lgtlFggqqI",,~~~~REACTORPROTECTIONSYSTEMELECTRICPOWERMONITORING(RPSLOGIC)LIMITINGCONDITIONFOROPERATION3.8.4.4.1TwoRPSUPSelectricpowermonitoringchannels(EPA's)foreachinserviceUPSsetoralternatesourceshallbeOPERABLE.APPLICABILITY:Atal1times.ACTION:a0b.WithoneRPSelectricpowermonitoringchannelforaninserviceRPSUPSinoperable,restoretheinoperablepowermonitoringchanneltoOPERABLEstatuswithin72hoursorremovetheassociatedRPSUPSfromservice.WithbothRPSelectricpowermonitoringchannelsforaninserviceRPSUPSinoperable,restoreatleastoneelectricpowermonitoringchanneltoOPERABLEstatuswithin30minutesorremovetheassociatedRPSUPSfromservice.SURVEILLANCEREUIREMENTS4.8.4.4.1Theabovespecified'RPSpowermonitoringchannelsinstrumentationshallbedeterminedOPERABLE:a.ByperformanceofaCHANNELFUNCTIONALTESTeachtimetheplantisinCOLDSHUTDOWNforaperiodofmorethan24hoursunlessperformedintheprevioussixmonths.b.Atleastonceper18monthsbydemonstratingtheOPERABILITYofover-voltage,under-voltageandunder-frequencyprotectiveinstru-mentationbyperformanceofaCHANNELCALIBRATIONincludingsimulatddautomaticactuationoftheprotectiverelays,trippinglogicandoutputcircuitbreakersandverifyingihefollowingsetpoints.1.Over"voltage<132"VAC2.Under-voltage>108*VAC3.Underfrequency>57Hz,-0+2.InstsalSetpoints,finalvaluestobedeterminedduringpreoperat'ionaltesting.NINEMILEPOINT-UNIT23/48-29aOVaOlSSS
l'iiMF5PPAYS/KP7REACTORPROTECTIONSYSTEMELECTRICPOWERMONITORING(SCRAMSOLENOIDS)LIMITINGCONOITIONFOROPERATION3.8.4.4.2TwoRPSUPSelectricpowermonitoringchannels(EPA's)foreachinserviceRPS(MGsetoralternatesource)shallbeOPERABLE.APPLICABILITY:Atalltimes.ACTION:WithoneRPSelectricpowermonitoringchannelforaninserviceRPSMGsetoralternatepowersupply)inoperable,restoretheinoperablepowermonitoringchanneltoOPERABLEstatuswithin72hoursorremovetheassociatedRPSMGsetoralternatepowersupplyfromservice.b.WithbothRPSelectricpowermonitoringchannelsforaninserviceRPSMGsetoralternatepowersupply)inoperable,restoreatleastoneelectricpowermonitoringchanneltoOPERABLEstatuswithin30minutesorremovetheassociatedRPSMGsetoralternatepowersupplyfromservice.SURVEILLANCEREUIREMENTS4.8.4.4.2TheabovespecifiedRPSpowermonitoringchannelsinstrumentationshallbedeterminedOPERABLE:a.ByperformanceofaCHANNELFUNCTIONALTESTeachtimetheplantisinCOLOSHUTOOWNforaperiodofmorethan24hoursunlessperformedintheprevioussixmonths.b.Atleastonceper18monthsbydemonstratingtheOPERABILITYofovervoltage,undervoltageandunder-frequencyprotectiveinstru-mentationbyperformanceofaCHANNELCALIBRATIONincludingsimulatedautomaticactuationoftheprotectiverelays,trippinglogicandoutputcircuitbreakersandverifyingthefollowingsetpoints.1.Over"voltage<125"VAC2.Under-voltage>105"VAC3.Under-frequency>57Hz,-0+2K.InitialSetpoints,finalvaluestobedeterminedduringpreoperationaltesting.NINEMILEPOINT-UNIT23/48"30NQV30jÃ]
F(MF53PZhf3P/3/4.9REFUELINGOPERATIONS3/4.9.1REACTORMODESWITCHLIMITING.CONDITIONFOROPERATION3.9.1ThereactormodeswitchshallbeOPERABLEandlockedintheShutdownorRefuelposition.WhenthereactormodeswitchislockedintheRefuelposition:a.AcontrolrodshallnotbewithdrawnunlesstheRefuelpositionone-rod-outinterlockisOPERABLE.b.COREALTERATIONSshallnotbeperformedusingequipmentassociatedwithaRefuelpositioninterlockunlessatleastthefollowingassoci"atedRefuelpositioninterlocksareOPERABLEforsuchequipment.1..2.3.4.5.APPLICABILITY:ACTION:Allrodsin.Refuelplatformposition.Refuelplatformhoistsfue1-'loaded.Fuelgrappleposition.Serviceplatformhoistfuel-loaded.OPERATIONALCONDITION5"b.C.WiththereactormodeswitchnotlockedintheShutdownorRefuelpositionasspecified,suspendCOREALTERATIONSandlockthereactormodeswitchintheShutdownorRefuelposition.Withtheone-rod-outinterlockinoperable,lockthereactormodeswitchintheShutdownposition.WithanyoftheaboverequiredRefuelpositionequipmentinterlocksinoperable,suspendCOREALTERATIONSwithequipmentassociatedwith-theinoperableRefuelpositionequipmentinterlock.SeeSpecialTestExceptions3:10.1and3.10.3.0ThereactorshallbemaintainedinOPERATIONALCONDITION5wheneverfuelisinthereactorvesselwiththevesselheadclosureboltslessthanfullytensionedorwiththeheadremoved.NINEMILEPOINT"UNIT23/49-1~OVW>S8S
REFUELINGOPERATIONSSURVEILLANCEREUIREMENTS4.9.1.1ThereactormodeswitchshallbeverifiedtobelockedintheShutdownorRefuelpositionasspecified:a.Within2hourspriorto:1.BeginningCOREALTERATIONS,and2.ResumingCOREALTERATIONSwhenthereactormodeswitchhasbeenun1oeked.b.Atleastonceper12hours.4.9.1.2EachoftheaboverequiredreactormodeswitchRefuelpositioninterlocks"shallbedemonstratedOPERABLEbyperformanceofaCHANNELFUNCTIONALTESTwithin24hourspriortothestartofandatleastonceper7daysduringcontrolrodwithdrawalorCOREALTERATIONS,asapplicable.4.9.1.3EachoftheaboverequiredreactormodeswitchRefuelpositioninterlocks"thatisaffectedshallbedemonstratedOPERABLEbyperformanceofaCHANNELFUNCTIONALTESTpriortoresumingcontrolrodwithdrawalorCOREALTERATIONS,asapplicable,followingrepair,maintenanceorreplacementofanycomponentthatcouldaffecttheRefuelpositioninterloc."ThereactormodeswitchmaybeplacedintheRunorStartup/HotStandbypositiontotesttheswitchinterlockfunctionsprovidedthatal1controlrodsareverifiedtoremainfullyinsertedbyasecondlicensedoperatororothertechnicallyqualifiedmemberoftheunittechnicalstaff.NINEMILEPOINT-UNIT23/49-2NOV20>egg
REFUELINGOPERATIONS3/4.9.2INSTRUMENTATIONLIMITINGCONDITIONFOROPERATIONQ'3Qggg.QQitip,gpAwv'ii~v<4L)SLY'k.~dlvlQK33.9.2Atleast2sourcerangemonitor"(SRM)channelsshallbeOPERABLEandinsertedtothenormaloperatinglevelwith:a.Continuousvisualindicationinthecontrolroom,b.Audibleindicationinthecontrolroom,c.OneoftherequiredSRMdetectorslocatedinthequadrantwhereCOREALTERATIONSarebeingperformedandtheotherrequiredSRMdetectorlocatedinanadjacentquadrant,andd.APPLICABILITY:OPERATIONALCOACTION:S.l'I.34.Miththeeabosuspendalloperationsinvolvingcontrol-rods-.mOQRAEL+3.7'r~Sc>cationnotsatisfied,immedsaeyCOREALTERATIONS""andinsertallinsertableSURVEILLANCEREUIREMENTS4.9.2EachoftheaboverequiredSRMchannelsshallbedemonstratedOPERABLEby:a.Atleastonceper12hours:1.PerformanceofaCHANNELCHECK,2.Verifyingthedetectorsareinsertedtothenormaloperatinglevel,and3.DuringCOREALTERATIONS,verifyingthatthedetectorofanOPERABLESRMchannelislocatedinthecorequadrantwhereCOREALTERATIONSarebeingperformed'andanotherislocatedinanadjacentquadrant."TheuseofspecialmovabledetectorsduringCOREALTERATIONSinplaceofthenormalSRMnucleardetectorsispermissibleaslongasthesespecialdetectorsareconnectedtothenormalSRMcircuits.""ExceptmovementofIRM,SRMorspecialmovabledetectors.NotrequiredforcontrolrodsremovedperSpecification3.9.10.1and3.9.10.2.NINEMILEPOINT"UNIT23/49-3NOV30ieger
REFUELINGOPERATIONSSURVEILLANCEREUIREHENTSContinuedb.PerformanceofaCHANNELFUNCTIONALTEST:1.Within24hourspriortothestartof.COREALTERATIONS,andC.d.2.Atleastonceper7days.Verifyingthatthechannelcountrateisatleast3cps"1.Priortocontrolrodwithdrawal,2.Priortoandatleastonceper12hoursduringCOREALTERATIONS,and3.Atleastonceper24hours.aeclrculrysort&ff+Ag.orPC3)~~~&4.0gpss~'A~Forinitialloadingandstartupthecountratemaybelessthan3cpsifthefollayingconditionsaremet;(1)thesignaltonoiseratioisgreaterthan2.0~2)thesignalisgreaterthan0.7cps,NINEMILEPOINT"UNIT23l49-4NOY20lg8g
REFUELINGOPERATIONS3/4.9.3CONTROLRODPOSITIONPi)gI]FgPI~"QJ>IIII.fLIMITINGCONDITIONFOROPERATION3.9.3Allcontrolrodsshallbeinserted."APPLICABILITY:OPERATIONALCONDITION5,duringCOREALTERATIONS.""ACTION:Withallcontrolrodsnotinserted,suspendallotherCOREALTERATIONS.SURVEILLANCEREUIREMENTS4.9.3Allcontrolrodsshallbeverifiedtobeinserted,exceptasabovespecified:a.Mithin2hourspriorto:1.ThestartofCOREALTERATIONS.2.ThewithdrawalofonecontrolrodunderthecontrolofthereactormodeswitchRefuelpositionone-rod-outinterlock.b.Atleastonceper12hours.ExceptcontrolrodsremovedperSpecification3.9.10.1or3.9.10.2,orwithonecontrolrodwithdrawnundercontrolofthereactormodeswitchRefuelpositionone-rod-outinterlock.""SeeSpecialTestException3.10.3.NINEMILEPOINT-UNIT23/49-5HOP8gp@
REFUELINGOPERATIONS3/4.9.4DECAYTIMEPj)ggjg(PJIPggpgn(LIMITINGCONDITIONFOROPERATION3.9.4Thereactorshallbesubcriticalforatleast24hours.APPLICABILITY:OPERATIONALCONDITION5,duringmovementofirradiatedfuelinthereactorpressurevessel.ACTION:Withthereactorsubcriticalforlessthan24hours,suspendalloperationsinvolvingmovementofirradiatedfuelinthereactorpressurevessel.SURVEILLANCEREUIREMENTS4.9.4Thereactorshallbedeterminedtohavebeensubcriticalforatleast24hoursbyverificationofthedateandtimeofsubcriticalitypriortomovementofirradiatedfuelinthereactorpressurevessel.NINEMILEPOINT-UNIT23/49"6NOV8g~gg~
REFUELINGOPERATIONS3/4.9.5COMMUNICATIONSLIMITINGCONDITIONFOROPERATION3.9.5Directcommunicationshallbemaintainedbetweenthecontrolroomandrefuelingfloorpersonnel.APPLICABILITY:OPERATIONALCONDITION5,duringCOREALTERATIONS.ACTION:Mhendirectcommunicationbetweenthecontrolroomandrefuelingfloorpersonnelcannotbemaintained,immediatelysuspendCOREALTERATIONS.SURVEILLANCEREUIREMENTS4.9.5Directcommunicationbetweenthecontrolroomandrefuelingfloorper-sonnelshallbedemonstratedwithinonehourpriortothestartofandatleastonceper12hoursduringCOREALTERATIONS.NINEMILEPOINT-UNIT23/49-7~ovso~~~>
REFUELINGOPERATIONS3/4.9.6REFUELINGPLATFORMLIMITINGCONDITIONFOROPERATION3.9.6TherefuelingplatformshallbeOPERABLEandusedforhandlingfuelassembliesorcontrolrodswithinthereactorpressurevessel.APPLICABILITY:Duringhandlingoffuelassembliesorcontrolrodswithinthereactorpressurevessel.ACTION:WiththerequirementsforrefuelingplatformOPERABILITYnotsatisfied,suspenduseofanyinoperablerefuelingplatformequipmentfromoperationsinvolvingthehandlingofcontrolrodsandfuelassemblieswithinthereactorpressurevesselafterplacingtheloadinasafecondition.SURVEILLANCEREUIREMENTS4.9.6EachrefuelingplatformcraneorhoistusedforhandlingofcontrolrodsorfuelassemblieswithinthereactorpressurevesselshallbedemonstratedOPERABLEwithin7dayspriortothestartofsuchoperationswiththatcr'aneorhoistby:aeb.C.d.e.g.Demonstratingoperationoftheoverloadcutoffonthemainhoistwhentheloadexceeds1200t50pounds.Demonstratingoperationoftheoverloadcutoffontheframemountedandmonorailmountedauxiliaryhoistswhentheloadexceeds1000k50pounds.Demonstratingoperationofthemainandauxiliaryhoistuptravelstopswhenthegrappleislowerthanorequalto8feetbelowtheplatformtracks.Demonstratingoperation'ofthedowntravelmechanicalcutoffonthemainhoistwhengrapplehookdowntravelreaches4inchesbelowfuelassemblyhandle.Demonstratingoperationoftheslackcablecutoffonthemainhoistwhentheloadislessthan50e10pounds.Demonstratingoperationoftheloadedinterlockonthemainhoistwhentheloadexceeds485250pounds.Demonstratingoperationoftheredundantloadedinterlockonthemainhoistwhentheloadexceeds550+50pounds.NINEMILEPOINT-UNIT23/49-8tfOV20188g
REFUELINGOPERATIONS3/4.9.7CRANETRAVEL-SPENTFUELSTORAGEPOOLLIMITINGCONOITIONFOROPERATION3.9.7Loadsinexcessof1150poundsshallbeprohibitedfromtraveloverfuelassembliesinthespentfuelstoragepoolracks.APPLICABILITY:Withfuelassembliesinthe'spentfuelstoragepoolracks.ACTION:Withtherequirementsoftheabovespecificationnotsatisfied,placethecraneloadinasafecondition.TheprovisionsofSpecification3.0.3arenotapplicable.SURVEILLANCEREUIREHENTS4.9.7Ciik'ihpd~overfuelassembliesinthespentfuelstoragepoolracksshallbedemonstratedOPERABLEwithin7dayspriortoandatleastonceper7daysduringcraneoperation.NINEMILEPOINT-UNIT23/49"9NOV.20l985
REFUELINGOPERATIONS3/4.9.8WATERLEVEL-REACTORVESSELFt<~4t5f~Kfi6if~iVfLIMITINGCONDITIONFOROPERATIONLc3.9.8Atleast22'3"ofwatershallbemaintainedoverthetopofthereactorpressurevesself'lange.APPLICABILITY:DuringhandlingoffuelassembliesorcontrolrodswithinthereactorpressurevesselwhileinOPERATIONALCONDITION5whenthefuelassembliesbeinghandledareirradiatedorthefuelassembliesseatedwithinthereactorvesselareirradiated.ACTEON:Withtherequirementsoftheabovespecificationnotsatisfied,suspendall-operationsinvolvinghandlingoffuelassembliesorcontrolrodswithinthe.reactorpressurevesselafterplacingall-fuelassembliesandcontrolrodsinasafecondition.SURVEILLANCEREUIREMENTS4.9.8Thereactorvesselwaterlevelshallbedeterminedtobeatleastitsminimumrequireddepthwithin2hourspriortothestartofandatleastonceper24hoursduringhandlingoffuelassembliesorcontrolrodswithinthereactorpressurevessel.NINEMILEPOINT-UNIT23/49-1ONQVP019BS
REFUELINGOPERATIONS3/4.9.9MATERLEVEL-SPENTFUELSTORAGEPOOLt'laÃ5RV<>re~LIMITINGCONDITIONFOROPERATION3.9.9Atleast22'3"ofwatershallbemaintainedoverthetopofirradiatedfuelassembliesseatedinthespentfuelstoragepoolracks.APPLICABILITY:Mheneverirradiatedfuelassembliesareinthespentfuelstoragepool.ACTION:Miththerequirementsoftheabovespecificationnotsatisfied,suspendallmovementoffuelassembliesandcraneoperationswithloadsinthespentfuelstoragepoolareaafterplacingthefuelassembliesandcraneloadinasafe=-condition.TheprovisionsofSpecification3.0.3arenotapplicable.SURVEILLANCEREUIREMENTS4.9.9Thewaterlevelinthespentfuelstoragepoolshallbedeterminedtobeatleastatitsminimumrequireddepthatleastonceper7days.NINEMILEPOINT"UNIT23/49-11NOV80lsd
REFUELINGOPERATIONS3/4.9.10CONTROLRODREMOVALSINGLECONTROLRODREMOVALLIMITINGCONDITIONFOROPERATION3.9.10.1Onecontrolrodand/ortheassociatedcontrolroddrivemechanismmayberemovedfromthecoreand/orreactorpressurevesselprovidedthatatleastthefollowingrequirementsaresatisfieduntila.controlrodandassoci-atedcontrolroddrivemechanismarereinstalledandthecontrolrodisfullyinsertedinthecore.a.ThereactormodeswitchisOPERABLEandlockedintheShutdownpositionorintheRefuelpositionperTable1.2andSpecification3.9.1.b..Thesourcerangemonitors(SRM)areOPERABLEperSpecification3.9.2.C.TheSHUTDOWNMARGINrequirementsofSpecification3.1.1aresatisfied,exceptthatthecontrolrodselectedtoberemoved;1.MaybeassumedtobethehighestworthcontrolrodrequiredtobeassumedtobefullywithdrawnbytheSHUTDOWNMARGINtest,andd.2.Neednotbeassumedtobeimmovableoruntrippab'le.Allothercontrolrodsinafive-by-fivearraycenteredonthecontrolrodbeingremovedareinsertedandelectricallyorhydraulicallydisarmedorthefourfuelassembliessurroundingthecontrolrodorcontrolroddrivemechanismtoberemovedfromthecoreand/orreactorvesselareremovedfromthecorecell.Se.Allothercontrolrodsareinserted.APPLICABILITY:OPERATIONAICONDITIONS4and5.ACTION:Withtherequirementsoftheabovespecificationnotsatisfied,suspendremovalofthecontrolrodand/orassociatedcontrolroddrivemechanismfromthecoreand/orreactorpressurevesselandinitiateactiontosatisfytheaboverequirements.NINEMILEPOINT-UNIT23/49-12HOV30leg
REFUELINGOPERATIONSSURVEILLANCEREUIREMENTSFKÃ5IP~ZJMF'!4.9.10.1Within4hourspriortothestartofremovalofacontrolrodand/ortheassociatedcontrolroddrivemechanismfromthecoreand/orreactorpressurevesselandatleastonceper24hoursthereafteruntilacontrolrodandassoci-atedcontrolroddrivemechanismarereinstalledandthecontrolrodisinsertedinthecore,verifythat:a.ThereactormodeswitchisOPERABLEperSurveillanceRequirement4.3.1.1or4.9.1.2,asapplicable,andlockedintheShutdownpositionorintheRefuelpositionwiththe"onerodout"RefuelpositioninterlockOPERABLEperSpecification3.9.1.b.TheSRMchannelsareOPERABLEperSpecification3.9.2.C.d.TheSHUTDOWNMARGINrequirementsofSpecification3.l.1aresatisfiedperSpecification3.9.10.1.c.Allothercontrolrodsinafive-by-fivearraycenteredonthecontrolrodbeingremovedareinsertedandelectricallyorhydraulicallydisarmedorthefourfuelassembliessurroundingthecontrolrodorcontrolroddrivemechanismtoberemovedfromthecoreand/orreactorvesselareremovedfromthecorecell.e.Allothercontrolrodsareinserted.NINEMILEPOINT"UNIT23/49"1384V20)8Bg
REFUELINGOPERATIONSMULTIPLECONTROLRODREMOVALk3KFVFi!Ui'JI3P'fLIMITINGCONDITIONFOR'OPERATION3.9.10.2Anynumberofcontrolrodsand/orcontrolroddrivemechanismsmayberemovedfromthecoreand/orreactorpressurevesselprovidedthatatleastthefollowingrequirementsaresatisfied,untilallcontrolrodsandcontrolroddrivemechanismsarereinstalledandallcontrolrodsareinsertedinthecore.a.ThereactormodeswitchisOPERABLEandlockedintheShutdownpositionorintheRefuelpositionperSpecification3.9.1,exceptthattheRefuelposition"one-rod-out"interlockmaybebypassed,asrequired,forthosecont>olrodsand/orcontrolroddrivemechanismstoberemoved,afterthefuelassemblieshavebeenremovedasspecifiedbelow.b..Thesourcerangemonitors(SRM)-areOPERABLEperSpecification3.9.2.c.TheSHUTDOWNMARGINrequirementsofSpecification3.1.1aresatisfied.d.Allothercontrolrodsareeitherinsertedorhavethesurroundingfourfuelassembliesremovedfromthecorecell.e.Thefourfuelassembliessurroundingeachcontrolrodorcontrolroddrivemechanismtoberemovedfromthecoreand/orreactorvesselareremovedfromthecore.cell.APPLICABILITY:OPERATIONALCONDITION5.ACTION:4Withtherequirementsoftheabovespecificationnotsatisfied,suspendremovalofcontrolrodsand/orcontrolroddrivemechanismsfromthecoreand/orreactorpressurevesselandinitiateactiontosatisfytheaboverequirements.NINEMILEPOINT-UNIT23/49-14NOV20t98~
REFUELINGOPERATIONSSURVEILLANCEREUIREMENTS4.9.10.2.1Within4hourspriortothestartofremovalofcontrolrodsand/orcontrolroddrivemechanismsfromthecoreand/orreactorpressurevesselandatleastonceper24hoursthereafteruntilallcontrolrodsandcontrolroddrivemechanismsarereinstalledandallcontrolrodsareinsertedinthecore,verifythat:a.ThereactormodeswitchisOPERABLEperSurveillanceRequirement4.3.1.1or4.9.1.2,asapplicable,andlockedintheShutdownpositionorintheRefuelpositionperSpecification3.9.1.b.TheSRMchannelsareOPERABLEperSpecification3.9.2.c.TheSHUTOOWNMARGINrequirementsofSpecification3.1.1aresatisfied.d.Allothercontrolrodsareeitherinsertedorhavethesurroundingfourfuelassemblies,removedfrgmthecorecell.e.Thefourfuelassembliessuproundingeachcontrolrodand/orcontrolroddrivemechanismtoberemovedfromthecoreand/orreactorvesselareremovedfromthecorecell.4.9.10.2.2Followingreplacementofallcontrolrodsand/orcontr'olroddrivemechanismsremovedinaccordancewiththisspecification,performafunctionaltestofthe"one-rod-out"Refuelpositioninterlock,ifthisfunctionhadbeenbypassed.NINEMILEPOINT-UNIT23/49"15
REFUELINGOPERATIONS3/4.9.11RESIDUALHEATREMOVALANDCOOLANTCIRCULATIONHIGHMATERLEVELP16Ã8k~iS'III,FILIMITINGCONDITIONFOROPERATION3.9.11.1Atleastoneshutdowncoolingmodeloopoftheresidualheatremoval(RHR)systemshallbeOPERABLEandinoperation"withatleast:a..OneOPERABLERHRpump,andb.OneOPERABLERHRheatexchanger.APPLICABILITY:OPERATIONALCONDITION5,whenirradiatedfuelisinthereactorvesselandthewaterlevelisgreaterthanorequalto22'3"abovethetopofthereactorpressurevesselflange.ACTION:aob.MithnoRHRshutdowncoolingmodeloopOPERABLE,withinonehourandatleastonceper24hoursthereafter,demonstratetheoperabilityofatleastonealternatemethodofdecayheatremoval.Otherwise,suspendalloperationsinvolvinganincreaseinthereactordecayheatloadandestablishSECONDARYCONTAINMENTINTEGRITYwithin4hours;Mith'noRHRshutdowncoolingmodeloopinoperation,withinonehourestablishreactorcoolantcirculationbyanalternatemethodandmonitorreactorcoolanttemperatureatleastonceperhour.SURYEILLANCEREUIREMENTS4.9.11.1Atleastoneshutdowncoolingmodeloopoftheresidualheatremovalsystemoralternatemethodshallbeverifiedtobeinoperationandcirculatirrgreactorcoolantatleastonceper12hours."Theshutdown'coolingpumpmayberemovedfromoperationforupto2hoursper8"hourperiod.NINEMILEPOINT-UNIT23/49-16trOVP.0]9B5
REFUELINGOPERATIONSLOWMATERLEVEL)P(o(FgP~rtJIP)ggTI('IMITINGCONDITIONFOROPERATION3.9.11.2Twoshutdowncoolingmodeloopsoftheresidualheatremoval(RHR}systemshallbeOPERABLEandatleastoneloopshallbeinoperation,"witheachloopconsistingofatleast:a.OneOPERABLERHRpump,andb.OneOPERABLERHRheatexchanger.APPLICABILITY:OPERATIONALCONDITION5,whenirradiatedfuelisinthereactorvesselandthewaterlevelislessthan22'3"abovethetopofthereactorpressurevesselflange.ACTION:aoWithlessthantheaboverequiredshutdowncoolingmodeloopsoftheRHRsystemOPERABLE,withinonehourandatleastonceper24hoursthereafter,demonstratetheopedabilityofatleastonealternativemethodcapableofdecayheatremovalforeachinoperableRHRshutdowncoolingmodeloop.MithnoRHRshutdowncoolingmodeloopinoperation,withinonehourestablishreactorcoolantcirculationbyanalternativemethodandmonitorreactorcoolanttemperatureatleastonceperhour.SURVEILLANCEREUIREMENTS4.9.11.2Atleastoneshutdowncoolingmodeloopoftheresidualheatremovalsystem,oralternatemethodshallbeverifiedtobeinoperationandcirculatmgreactorcoolantatleastonceper12hours."Theshutdowncoolingpumpmayberemovedfromoperationforupto2hoursper8-hourperiod.NINEMILEPOINT"UNIT23/49-17HOV2P)gag
3/4.10SPECIALTESTEXCEPTIONS3/4.10.1PRIMARYCONTAINMENTINTEGRITYFMÃ8IP~Zl~)~yyLIMITINGCONDITIONFOROPERATION3.10.1TheprovisionsofSpecifications3.6.1.1,3.6.1.3and3.9.1andTable1.2maybesuspendedtopermitthereactorpressurevesselclosureheadandthedrywellheadtoberemovedandtheprimarycontainmentairlockdoorstobeopenwhenthereactormodeswitchisintheStartuppositionduringlowpower.PHYSICSTESTSwithTHERMALPOWERlessthanIXofRATEDTHERMALPOWERandreac-torcoolanttemperaturelessthan200F.APPLICABILITY:OPERATIONALCONDITION2,duringlowpowerPHYSICSTESTS.ACTION:~,'.WithTHERMALPOWERgreaterthanorequalto3XofRATEDTHERMALPOWERorwiththereactorcoolanttemperaturegreaterthanorequalto2004F,immediatelyplacethereactormodeswitchintheShutdownposition.SURVEILLANCEREUIREMENTS4.10.1TheTHERMALPOWERandreactorcoolanttemperatureshallbeverifiedtobewithinthelimitsatleastonceperhourduringlowp'owerPHYSICSTESTS.NINEMILEPOINT-UNIT23/410"1NQV20lgB5
SPECIALTESTEXCEPTIONS3/4.10.2RODSEUENCECONTROLSYSTEMLIMITINGCONDITIONFOROPERATIONPPIRFCOIjig),P)3.10.2Thesequenceconstraintsimposedoncontrolrodgroupsbytherodsequencecontrolsystem(RSCS)perSpecification3.1.4.2maybesuspendedbymeansofbypassswitchesforthefollowingtestsprovidedthattherodworthminimizerisOPERABLEperSpecifications3.1.4.I:a.Shutdownmargindemonstrations,Specification4.l.1.b.Controlrodscram,Specification4.1.3.2.c.Controlrodfrictionmeasurements.d.StartupTestProgramwiththeTHERQLPOMERlessthan20"ofRATED.THERMAL,POWER.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:Withtherequirementsoftheabovespecificationnotsatisfied,verifythattheRSCSisOPERABLEperSpecification3.1.4.2.SURVEILLANCEREUIREMENTS4.10.2WhenthesequenceconstraintsimposedoncontrolrodgroupsbytheRSCSarebypassed,verify:a0Mithin8hourspriortobypassinganysequenceconstraintandatleastonceper12hourswhileanysequenceconstraintisbypassed:anal1.ThattherodworthminimizerisOPERABLEperSpecification3;1.4.1,2.Thatmovementofcontrolrodsfrom75KRODDENSITYtotheRSCSlowpowersetpointislimitedtotheapprovedcontrolrodwithdrawalsequenceduringscramandfrictiontests.b.Conformancewiththisspecificationandtestproceduresbyasecondlicensedoperatororothertechnicallyqualifiedmemberoftheunittechnicalstaff.NINEMILEPOINT-UNIT23/410-2NOV20lgsg
SPECIALTESTEXCEPTIONS3/4.10.3SHUTDOWNMARGINDEMONSTRATIONSP(g:$$GRAPE![$.g/LIMITINGCONDITIONFOROPERATION3.10.3TheprovisionsofSpecification3.9.1,Specification3.9.3andTable1.2maybesuspendedtopermitthereactormodeswitchtobeintheStartuppositionandtoallowmorethanonecontrolrodtobewithdrawnforshutdownmargindemonstration,providedthatatleastthefollowingrequire-mentsaresatisfied.a.ThesourcerangemonitorsareOPERABLEwiththeRPScircuitry"shortinglinks"removedperSpecification3.9.2.b.TherodworthminimizerisOPERABLEperSpecification3.1.4.1andisprogrammedfortheshutdownmargindemonstration,orconformancewiththeshutdownmargindemonstrationprocedureisverifiedbyasecondlicensedoperatororothertechnicallyqualifiedmemberoftheunjttechnicalstaff.c.Thecontinuousrodwithdrawalcontrolshallnotbeusedduringout-of-sequencemovementofthecontrolrods.d.NootherCOREALTERATIONSareinprogress.APPLICABILITY:OPERATIONALCONDITION5,duringshutdownmargindemonstrations.ACTION:Nththerequirementsoftheabovespecificationnotsatisfied,immediatelyplacethereactormodeswitchintheShutdownorRefuelposition.SURVEILLANCEREUIREMENTS4.10.3Mithin30minutespriortoandatleastonceper12hoursduringtheperformanceofashutdownmargindemonstration,verifythat;aOb.C.ThesourcerangemonitorsareOPERABLEperSpecification3.9.2,TherodworthminimizerisOPERABLEwiththerequiredprogramperSpecification3.1.4.1orasecondlicensedoperatororothertechni"callyqualifiedmemberoftheunittechnicalstaffispresentandverifiescompliancewiththeshutdowndemonstrationprocedures,andNootherCOREALTERATIONSareinprogress.NINEMILEPOINT"UNIT23/410"3ggy20lo85
SPECIALTESTEXCEPTIONS3/4.10.4RECIRCULATIONLOOPSLIMITINGCONDITIONFOROPERATIONFECAL8IPPgl(<p~3.10.4TherequirementsofSpecifications3.4.1.1and3.4.1.3thatrecircula-tionloopsbeinoperationwithmatchedflowmaybesuspendedforupto24hoursfortheperformanceof:a.PHYSICSTESTS,providedthatTHERMALPOWERdoesnotexceed5XofRATEDTHERMALPOWER,orb.TheStartup.TestProgram.APPLICABILITY:OPERATIONALCONDITIONS1and2,duringPHYSICSTESTSandtheStartupTestProgram.ACTION:a0b.Withtheabovespecifiedtimelimitexceeded,insertallcontrolrods.WiththeabovespecifiedTHERMALPOWERlimitexceededduringPHYSICSTESTS,immediatelyplacethereactormodeswitchintheShutdown,position.SURVEILLANCEREUIREMENTS4.10.4.1Thetimeduringwhichtheabovespecifiedrequirementhasbeensuspendedshallbeverifiedtobelessthan24hoursatleastonceperhourduringPHYSICSTESTSandtheStartupTestProgram.4.10.4.2THERMALPOWERshallbedeterminedtobelessthan5XofRATEDTHERMALPOWERatleastonceperhourduringPHYSICSTESTS.NINEMILEPOINT"UNIT23/410-4gaySo1985
SCIALTESTEXCEPTIONS3/4.16TRAININGSTARTUPSLIMITINGONDITIONFOROPERATION3.10.6TheprisionsofSpecification3.5.1maybesuspendtopermitoneRHRsubsystemtoalignedintheshutdowncoolingmoderingtrainingstartupsprovidedttthereactorvesselisnotpressized,THERMALPOWERislessthanorequalolXofRATEDTHERMALPOWERareactorcoolanttemperatureislesstha200'F.APPLICABILITY:OPERATIONALCDITION2,dngtrainingstartups.ACTION:Miththerequirementsoftheabovspecicationnotsatisfied,immediatelyplacethereactormodeswitchitheShutwn.position.SURVEILLANCEREUIRNTS4.10.6TheeactorvesselshallbeverifiedtobeunpressurdandtheTHERMALPERandreactorcoolanttemperatureshallbeverifiedbewithinthelisatleastonceperhourduringtrainingstartups.NINEMILEPOINT-UNIT23/410-5gQQR01985
SPECIALTESTEXCEPTIONS3l4.10.6TRAININGSTARTUPSLIMITINGCONDITIONFOROPERATIONPiIO3FCIgt~j;Pi~]ggP)3.10.6TheprovisionsofSpecification3.5.1maybesuspendedtopermitoneRHRsubsystemtobealignedintheshutdowncoolingmodeduringtrainingstartupsprovidedthatthereactorvesselisnotpressurized,THERMALPOMERislessthanorequalto1XofRATEDTHERMALPOWERandreactorcoolant,temperatureislessthan200F.APPLICABILITY:OPERATIONALCONDITION2,duringtrainingstartups.ACTION:Withtherequirementsoftheabovespecificationnotsatisfied,immediatelyplacethereactormodeswitchintheShutdownposition.SURVEILLANCEREUIRBlENTS4.10.6ThereactorvesselshallbeverifiedtobeunpressurizedandtheTHERMALPOSERandreactorcoolanttemperatureshallbeverifiedtobewithinthelimitsatleastonceperhourduringtrainingstartups.NINEMILEPOINT"UNIT23/410-6N4V40IBS
3/4.11RADIOACTIVEEFFLUENTS3/4.11.1LIUIDEFFLUENTSCONCENTRATIONLIMITINGCONDITIONFOROPERATION3.11.1.1TheconcentrationofradioactivematerialreleasedinliquideffluentstoUNRESTRICTEDAREAS(seeFigure5.1.3-1)shallbelimitedtotheconcentrations,specifiedin10CFRPart20,AppendixB,TableII,Column2forradionuclidesotherthandissolvedorentrainednoblegases.Fordissolvedorentrainednoblegases,theconcentrationshallbelimitedto2x10-~microCurie/mltotalactivity.APPLICABILITY:Atalltimes.ACTION:WiththeconcentrationofradioactivematerialreleasedinliquideffluentstoUNRESTRICTEDAREASexceedingtheabovelimits,withoutdelayrestorethe'concentrationtowithintheabovelimits.-SURVEILLANCEREUIREMENTS.4.11.1.1..1RadioactiveliquidwastesshallbesampledandanalyzedaccordingtothesamplingandanalysisprogramofTable4.11-1.4.11.1.1.2Theresultsoftheradioactivityanalysesshallbeusedinaccord-ancewiththemethodologyandparametersintheODCMtoassurethatthecon-centrationsatthepointofreleasearemaintainedwithinthelimitsofSpecification3.11.1.1.NINEMILEPOINT-UNIT23/4ll"1HOV20lg8g P TABLE4.11-1PM~XKI'iFHiJ.iRADIOACTIVELIUIDWASTESAMPLINGANDANALYSISPROGRAMLI(UIDRELEASETYPESAMPLINGFRE(UENCYMINIMUMANALYSISFRE(UENCYTYPEOFACTIVITYANALYSISLOWERLIMITOFDETECTION(LLD)(1)(~Ci/mI)1.BatchWasteReIeaseTanksPEachBatchPEachBatchPrincipaIGamma5x10-~EmittersI"1311xl0-sa.2LWS-TK5Ab.2LWS-TK5BPOneBatch/MOneBatch/MDissoIvedand&10-EntrainedGases(GammaEmitters)PM4H-3lxl0-sEach.BatchComposite()GrossAIphalxlO-~PEachBatchCompositeFe-55lx10-sSr-89,Sr-905xlO-s2.ContinuousReIeasesa.ServiceWaterEffIuentAGrabSampIe.GrabSampIeM(5)M(5)Principa1Gamma5x10-7Emitters()I"131lx10-s4DissoIvedandlx10"sEntrainedGases(GammaEmitters)b.ServiceWaterEffIuentBc.CooIingTowerBIowdownGrabSampIeGrabSampIeq(5)q(5)H"3GrossAIphaSr-89,Sr-90Fe-55lx10-slxl0-75xlO-slxl0-sNINEMILEPOINT-UNIT23/411-2NOV201985
TABLENOTATIONSQ~I!]f'efppiotaeslf()TheLLDisdefined,forpurposesofthesespecifications,asthesmallestconcentrationofradioactivematerialinasamplethatwillyieldanetcount,abovesystembackground,thatwillbedetectedwith95Ãprobabilitywithonly5Xprobabilityoffalselyconcludingthatablankobservationrepresentsa"real"signal.Foraparticularmeasurement.system,whichmayincluderadiochemicalseparation:4.66sbWhere:E~V~2.22x106~Y-exp{-Rt)LLO=the"apriori"lowerlimitofdetection(microCurieperunitmassorvolume),s=thestandarddeviationofthebackgroundcountingrateorof"bthecountingrateofablanksampleasappropriate(countsperminute),E=thecountingefficiency(countsperdisintegration),V=thesamplesize(unitsofmassorvolume),2.22x106=thenumberofdisintegrationsperminutepermicroCurie,Y='hefractionalradiochemicalyield,whenapplicable,A,=theradioactivedecayconstantfortheparticularradionuclide(sec-~),andht=theelapsedtimebetweenthemidpointofsamplecollectionandthetimeofcounting{sec).TypicalvaluesofE,V,Y,andhtshouldbeusedinthecalculation.Itshou'ldberecognizedthattheLLDisdefinedasanapriori(berorethefact)limitrepresentingthecapabilityofameasurementsystemand"""""o""'))Abatchreleaseisthedischargeofliquidwastesofadiscretevolume.Priortosamplingforanalyses,eachbatchshallbeisolated,.andthenthoroughlymixedbyamethoddescribedintheOOCMtoassurerepresentativesampling.NINEMILEPOINT"UNIT23/411"3NOV,201985
TABLE4.11-1ContinuedTABLENOTATIONSContinued-'hfAO~lPvvt'wiaZbU~fTheprincipalgammaemmitersforwhichtheLLDspecificationappliesincludethefollowingradionuclides:Mn-54,Fe-59,Co-58,Co-60,Zn-65,Mo-99,Cs-134,Cs-137andCe-141.Ce-144shallalsobemeasured,butwithanLLDof5x10-.Thislistdoesnotmeanthatonlythesenuclidesaretobeconsidered.Othergammapeaksthatareidentifiable,togetherwiththoseoftheabovenuclides,shallalsobeanalyzedandreportedintheSemiannualRadioactiveEffluentReleaseReportpursuanttoSpecification6.9.1.8intheformatoutlinedinRegulatoryGuide1.21,AppendixB,Revision1,June1974.Acompositesampleisoneinwhichthequantityofliquidsampledisproportionaltothequantityofliquidwastedischargedandinwhichthemethodofsamplingemployedresultsinaspecimenthatisrepresentativeoftheliquidsreleased.Ifthealarmsetpointoftheeffluentmonitor,asdeterminedbythemethodpresentedintheODCM,isexceeded,thefrequencyofsamplingshallbeincreasedtodailyuntiltheconditionnolongerexists.Frequencyof.analysisshallbeincreasedtodailyforprincipalgammaemittersandanincidentcompositeforH-3,grossalpha,Sr-89,Sr-90,andFe-55.NINEMILEPOINT-UNIT23/411-4NOY201985
RADIOACTIVEEFFLUENTSDOSELIMITINGCONDITIONFOROPERATION3.11.1.2ThedoseordosecommitmenttoaMEMBEROFTHEPUBLICfromradioactivematerialsinliquideffluentsreleased,fromeachunit,toUNRESTRICTEDAREAS(seeFigure5.1.3-1)shallbelimited:a.Duringanycalendarquartertolessthanorequalto1.5mremstothewholebodyandtolessthanorequalto5mremstoanyorgan,andb.During.anycalendaryeartolessthanorequalto3mremstothewholebodyandtolessthanorequalto10mremstoanyorgan.APPIICABILITY:Atalltimes.ACTION:Withthe-calculateddosefromthereleaseofradioactivematerialsinliquideffluentsexceedinganyoftheabovelimits,prepareandsubmittotheCommissionwithin30days,pursuanttoSpecification6.9.2,aSpecialReportthatidentifiesthecause(s)forexceedingthelimit(s)anddefinesthecorrectiveactionsthathavebeentakentoreducethereleasesandtheproposedcorrectiveactionstobetakento"assurethatsubsequentreleaseswillbeincompliancewiththeabovelimits.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.11.1.2Cumulativedosecontributionsfromliquideffluentsforthecurrent.calendarquarterandthecurrentcalendaryearshallbedeterminedinaccordancewiththemethodologyandparametersintheODCMatleastonceper31days.NINEMILEPOINT-UNIT23/4ll"5spyp0jo
RADIOACTIVEEFFLUENTSLIUIDRADWASTETREATMENTSYSTEM/TIEf'Q7~~]~p~yLIMITINGCONDITIONFOROPERATION3.11.1.3TheLiquidRadwasteTreatmentSystemshallbeOPERABLEandappropriateportionsofthesystemshallbeusedtoreducereleasesofradioactivitywhentheprojecteddosesduetotheliquideffluent,fromtheunit,toUNRESTRICTEDAREAS(seeFigure5.1.3-1)wouldexceed0.06mremtothewholebodyor0.2mremtoanyorganina31-dayperiod.APPLICABILITY:Atall.times.ACTION:aoWithradioactiveliquidwastebeingdischargedwithouttreatmentandinexcessoftheabovelimitsandanyportionoftheLiquidRadwasteTreatmentSystemnotinoperation,prepareandsubmittotheCommis"sionwithin30days,pursuanttoSpecification6.9.2,aSpecialReportthatincludesthefollowinginformation:1.Explanationofwhyliquidradwastewasbeingdischargedwithouttreatment,identificationofanyinoperableequipmentorsubsystems,andthereasonfortheinoperability,2.Action(s)takentorestoretheinoperableequipmenttoOPERABLEstatus,and3.Summarydescriptionofaction(s)takentopreventarecurrence.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURYEILLANCEREUIREMENTS4.11.1.3.1DosesduetoliquidreleasesfromeachunittoUNRESTRICTEDAREAS-shallbeprojectedatleastonceper31daysinaccordancewiththemethodologyandparametersintheODCMwhenLiquidRadwasteTreatmentSystemsarenotbeingfullyutilized.4.11.1.3.2TheinstalledLiquidRadwasteTreatmentSystemshallbeconsideredOPERABLEbymeetingSpecifications3.11.1.1and3.11.1.2.NINEMILEPOINT"UNIT23/411-6NOV20~gsg
RADIOACTIVEEFFLUENTSLIUIDHOLDUPTANKS"IILPvl6jlPJ(pj's$gff'IMITINGCONDITIONFOROPERATION3.11.1.4Thequantityofradioactivematerialcontainedineachunprotectedoutdoortankshallbelimitedtolessthanorequalto10Curies,excludingtritiumanddissolvedorentrainednoblegases:APPLICABILITY:Atal1times.ACTION:aoMiththequantityofradioactivematerialinanytankexceedingtheabovelimit,immediatelysuspendalladditionsofradioactivematerialtothetank,within48hoursreducethetankcontentstowithinthelimit,anddescribetheeventsleadingtothisconditioninthenextSemiannualRadioactiveEffluentReleaseReport,pursuanttoSpecification6.9.1.8.b.'heprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.11.1.4Thequantityofradioactivematerialcontainedineachtankshallbe~determinedtobewithin"the-above-limit-by-analyzing-a-repres'entativesampleofthetank'scontentsatleastonceper7dayswhenradioactivematerialsarebeingaddedtothetank."Tanksincludedinthisspecificationarethoseoutdoortanksthatarenotsurroundedbyliners,dikes,orwallscapableofholdingthetankcontentsandthatdonothavetankoverflowsandsurroundingareadrainsconnectedtotheLiquidRadwasteTreatmentSystem,suchastemporarytanks.NINEMILEPOINT-UNIT23/411-750V8u585
RAOIOACTIVEEFFLUENTS3/4.11.2GASEOUSEFFLUENTSOOSERATELIMITINGCONOITIONFOROPERATION3.11.2.1ThedoserateduetoradioactivematerialsreleasedingaseouseffluentsfromthesitetoareasatorbeyondtheSITEBOUNOARV(seeFigure5.1.1"1)shallbelimitedtothefollowing:a.Fornoblegases:Lessthanorequalto500mrems/yrtothewholebodyandlessthanorequalto3000mrems/yrtotheskin,andb.ForIodine-131,forIodine-133,fortritium,andfora11radio-nuclidesinparticulateformwithhalf"livesgreaterthan8days:Lessthanorequalto1500mrems/yrtoanyorgan.APPLICABILITY:Atalltimes.ACTION:Withthedoserate(s)exceedingtheabovelimits,immediatelyrestorethereleaseratetowithintheabovelimit(s).SURVEILLANCEREUIREMENTS4.11.2.1.1Thedoserateduetonoblegasesingaseouseff'1uentsshallbedeterminedtobewithintheabovelimitsinaccordancewiththemethodologyandparametersintheODCM.4.11.2.1.2ThedoserateduetoIodine-131,Iodine-133,tritium,andallradionuclidesinparticulateformwithhalf-livesgreaterthan8daysingaseouseffluentsshallbedeterminedtobewithintheabovelimitsinaccordancewiththemethodologyandparametersintheODCHbyobtainingrepresentativesampIesandperforminganalysesinaccordancewiththesamplingandanalysisprogramspecifiedinTable4.11-2.NINEMILEPOINT-UNIT23/411-8oov20>995
.I:0MfoalMIPlC)ISAMPLINGGASEOUSRELEASETYPEFREQUENCYMINIMUMANALYSISFRE(UENCYTYPEOF'CTIVITYANALYSIS1.ContainmentTABLE4.11-2RADIOACTIVEGASEOUSWASTESAMPLINGANOANALYSISPROGRAMLOWERLIMITOF1DETECTION(LLD)()(pCi/ml)MEachPURGEPrincipalGammaEmitters1xlO-~EachPURGEH-3(oxide),PiincipalGammaEmitters>>)lx10"e,1x10-42.HainStack.Radwaste/ReactorBuildingVentH(3)GrabSample(4)H(3)PrincipalGammaEmittersH-3(oxide)1xlO-~lxlO-eContinuousWCharcoalSample~I-1311x10-~>ContinuousWParticulateSamplePrincipalGammaEmitters1x10-~~ContinuousHGrossAlphaCompositePar-ticulateSample1x1O->>C)CAContinuousSr-89,Sr-90CompositePar-ticulateSample1x1O-"
TABLE4.11-2ContinuedTABLENOTATIONSPMO8kBfpgf,OP,I(1)TheLLDisdefined,forpurposesofthesespecifications,asthesmallestconcentrationofradioactivematerialinasamplethatwillyield'anetcount,abovesystembackground,thatwillbedetectedwith95Kprobabilitywithonly5Xprobabilityoffalselyconcludingthatablankobservationrepresentsa"real"signal.Foraparticularmeasurementsystem,whichmayincluderadiochemicalseparation:Where:4.66sbE~V~2.22x108~Y~exp(-Qt)LLD=the"apriori"lowerlimitofdetection(microCurieperunitmassorvolume),sb=thestandarddeviationofthebackgroundcountingrateorofthecountingrateofablanksampleasappropriate.(countsperminute),E=thecountingefficiency(countsperdisintegration),V=thesamplesize(unitsofmassorvolume),2.22x10=thenumberofdisintegrationsperminutepermicroCurie,Y=thefractionalradiochemicalyield,whenapplicable,A,=theradioactivedecayconstantfortheparticularradionuclide(sec"~),andht=theelapsedtimebetweenthemidpointofsamplecollectionandthetimeofcounting(sec}.TypicalvaluesofE,V,Y,and4tshouldbeusedinthecalculation.ItshouldberecognizedthattheLI.Gisdefinedasanapriori(beforethefact)limitrepresentingthecapabilityofameasurementsystemand'<<'*)'"NINEMILEPOINT-UNIT23/411-10OV30f985
TABLE4.11-2ContinuedE~~vAC9736/lggpnr<glhl%Jv5QILW)LSD4Uf3TABLENOTATIONS(ContinuedTheprincipalgammaemittersforwhichtheLLDspecificationappliesincludethefollowingradionuclides:Kr-87,Kr88,Xe-133,Xe-133m,Xe-135,andXe-138innoblegasreleasesandMn-54,Fe-59,Co-58,Co-60,Zn-65,Mo-99,I-131,Cs-134,Cs-137,Ce-141andCe-144inIodineandparticulatereleases.Thislistdoesnotmeanthatonlythesenuclidesaretobeconsidered.Othergammapeaksthatareidentifiable,togetherwiththoseoftheabovenuclides,shallalsobeanalyzedandreportedintheSemiannualRadioactiveEffluentReleaseReportpursuanttoSpecification6.9.1.8intheformatoutlinedinRegulatoryGuide1.21,AppendixB,Revision1,June1974.~<<IftheMainStackorReactor/RadwastebuildingisotopicmonitorisnotOPERABLE,samplingandanalysisshallalsobeperformedfollowingshutdown,startup,orwhenthereisanalertalarmontheoffgaspretreatmentmonitor.TritiumgrabsamplesshallbetakenweeklyfromtheReactor/Radwasteventilationsystemwhenfuelisoffloadeduntilstabletritiumreleaselevelscanbedemonstrated.Theratioofthesampleflowratetothesampledstreamflowrateshallbeknownforthetimeperiodcoveredby'achdoseordoseratecalculationmadeinaccordancewithSpecifications3.11.2.1b,and3.11.2.3.WhenthereleaserateoftheHainStackorReactor/Radwastebuildingventexceedsitsalertalarmsetpoint,theiodineandparticulatedeviceshallberemovedandanalyzedtodeterminethechangesiniodineandparticulatereleaserates.Theanalysisshallbedonedailyuntilthereleasenolongerexceedsthealarmsetpoint.Whensamplescollectedfor24hoursareanalyzed,thecorrespondingLLD'smaybeincreasedbyafactorof10.SampleandanalysispriortoPURGEisusedtodeterminepermissablePURGErates.SampleandanalysisduringactualPURGEisusedforoffsitedose-calculations.NINEMILEPOINT"UNIT23/411-11NDV80@gal
RADIOACTIVEEFFLUENTSDOSE-NOBLEGASESLIMITINGCONDITIONFOROPERATIONp]fg~pgfpipVJga(py3.11.2.2Theairdoseduetonoblegasesreleasedingaseouseffluents,fromeachunit,toareasatorbeyondtheSITEBOUNDARY(seeFigure5.1.1"1)shallbelimitedtothefollowing:a.Duringanycalendarquarter:Lessthanorequalto5mradsforgammaradiationandlessthanorequalto10mradsforbetaradiation,andb.Duringanycalendar'year:Lessthanorequalto10mradsforgammaradiationandlessthanorequalto20mradsforbetaradiation.APPLICABILITY:Atalltimes.ACTIONa~Withthecalculatedairdosefromradioactivenoblegasesingaseouseffluentsexceedinganyoftheabovelimits,prepareandsubmittotheCommissionwithin30days,pursuanttoSpecification6.9.2,aSpecialReportthatidentifiesthecause(s)forexceedingthelimit(s)anddefinesthecorrectiveactionsthathavebeentakentoreducethereleasesandtheproposedcorrectiveactions'tobetakentoassurethatsubsequentreleaseswillbeincompliancewiththeabovelimits.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.11.2.2CumulativedosecontributionsforthecurrentcalendarquarterandcurrentcalendaryearfornoblegasesshallbedeterminedinaccordancewiththemethodologyandparametersintheODCMaleastonceper31days.NINEMILEPOINT-UNIT"23/411"12NOVSOlpga
RADIOACTIVEEFFLUENTSQQPtII0Plgpgq>@peDOSE-IODINE-131IODINE-133TRITIUMANDRADIONUCLIDESINPARTICULATEFORMLIMITINGCONDITIONFOROPERATION3.11.2.3ThedosetoaMEMBEROFTHEPUBLICfromIodine-131,Iodine-133,tritium,andall.radionuclidesinparticulateformwithhalf-livesgreaterthan8daysingaseouseffluentsreleased,fromeachunit,toareasatorbeyondtheSITEBOUNDARY(seeFigure5.1.1-1)shallbelimitedtothefollowing:a.Duringanycalendarquarter:Lessthanorequalto7.5mremstoanyorganand,b.Duringanycalendaryear:Lessthanorequalto15mremstoanyorgan.APPLICABILITY:Atalltimes.ACTION:aob.WiththecalculateddosefromthereleaseofIodine-131,Iodine-133,tritium,andradionuclidesinparticulateformwithhalf-livesgreaterthan8days,ingaseouseffluentsexceedin'ganyoftheabovelimits,prepareandsubmittotheCommissionwithin30days,pursuanttoSpecification6.9.2,aSpecialReportthatidentifiesthecause(s)forexceedingthelimit(s)anddefinesthecorrectiveactionsthathavebeentakentoreducethereleasesandtheproposedcorrectiveactionstobetakentoassurethatsubsequentreleaseswillbeincompliancewiththeabovelimits.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURYEILLANCEREUIREMENTS4.11.2.3CumulativedosecontributionsforthecurrentcalendarquarterandcurrentcalendaryearforIodine-131,Iodine-133,tritium'ndradionuclidesinparticulateformwithhalf-livesgreaterthan8daysshallbedeterminedinaccordancewiththemethodologyandparametersintheODCMatleastonceper31days.NINEMILEPOINT"UNIT23/411"13HOV30lggg
RADIOACTIVEEFFLUENTSGASEOUSRADWASTETREATMENTSYSTEMLIMITINGCONDITIONFOROPERATION'I8PF,J$QJ~gg)gPy3.11.2.4TheGASEOUSRADWASTETREATMENTSYSTEMshallbeinoperation.APPLICABILITY:wheneverthemaincondenserairejectorsystemisinoperation.ACTION:'a0Withgaseousradwastefromthemaincondenserairejectorsystembeingdischargedwithouttreatmentformorethan7days,prepareandsubmittotheCommissionwithin30days,pursuanttoSpecifica-tion6.9.2,aSpecialReportthatincludesthefollowinginformation.1.Identificationoftheinoperableequipmentorsubsystemsandthereasonfortheinoperability,2.Action(s)takentorestoretheinoperableequipmenttoOPERABLEstatus,and3.Summarydescriptionofaction(s)takentopreventarecurrence.b.TheprovisionsofSpecifications3.0.3and3.0.4are-notapplicable.SURVEILLANCEREUIREMENTS4.11.2.4Thereadingsoftherelevantinstrumentsshallbecheckedevery12hourswhenthemaincondenserairejectorisinusetoensurethatthegaseousradwastetreatmentsystemisfunctioning.NINEMILEPOINT-UNIT23/411-14NOV80teag
RADIOACTIVEEFFLUENTSVENTILATIOHEXHAUSTTREATMEHTSYSTEMLIMITINGCONDITIONFOROPERATIONPOOPJF$PIF+NQ'I'fCINiP'f3.11.2.5TheVENTILATIONEXHAUSTTREATMENTSYSTEMshallbeOPERABLEandappro-priateportionsofthissystemshallbeusedtoreducereleasesofradioactivitywhentheprojecteddosesin31daysduetoiodineandparticulatereleases,fromeachunit,toareasatorbeyondtheSITEBOUNDARY(seeFigure5.1.1-1)wouldexceed0.3mremtoanyorganofaMEMBEROfTHEPUBLIC.APPLICABILITY:Atalltimes.ACTION:Withradioactivegaseouswastebeingdischargedwithouttreatment'ndinexcessoftheabovelimits,prepareandsubmittotheCommissionwithin30days,pursuanttoSpecification6.9.2,aSpecialReportthatincludesthefollowinginformation:1..Identificationofanyinoperableequipmentorsubsystems,hndthereasonfortheinoperability,2.Action(s)takentorestoretheinoperableequipmenttoOPERABLEstatus,and3.Summarydescriptionofaction(s)takentopreventarecurrence.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMEHTS4.11.2.5.1DosesduetoiodineandparticulatereleasesfromeachunittoareasatorbeyondtheSITEBOUNDARYshallbeprojectedatleastonceper31daysinaccordancewiththemethodologyandparametersintheODCMwhentheVENTILATIONEXHAUSTTREATMENTSYSTEMisnotbeingfullyutilized.4.11.2.5.2TheinstalledVENTILATIONEXHAUSTTREATMENTSYSTEMshallbeconsideredOPERABLEbymeetingSpecifications3.11.2.1or3.11.2.3.NIHEMILEPOINT-UNIT23/411-15NOV20laBc
RADIOACTIVEEFFLUENTSEXPLOSIVEGASMIXTUREPI'3O/Pig&)JPTIm'ggLIMITNGCONDITIONFOROPERATION3.11.2.6Theconcentrationofhydrogeninthemaincondenseroffgastreatmentsystemshallbelimitedtolessthanorequalto4Xbyvolume.APPLICABILITY:Atalltimes.ACTION:'a0b.C.Withtheconcentrationofhydrogeninthemaincondenseroffgastreatmentsystemexceedingthelimit,restoretheconcentrationtowithinthelimitwithin48hours.Withcontinuousmonitorsinoperable,utilizegrabsamplingproce-duresforaperiodnottoexceed30days.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.11.2.6Theconcentrationofhydrogeninthemaincondenseroffgastreatment'ystemshallbedeterminedtobewithintheabovelimitsbycontinuouslymonitoringthewastegasesinthemaincondenseroffgastreatmentsystemwheneverthemaincondenserevacuationsytemisinoperationwiththehydrogenmonitorsrequiredOPERABLEbyTable3.3.7.11-1ofSpecification3.3.7.11.NINEMILEPOINT-UNIT23/411-16$P'gR0)535NOV~...-
RADIOACTIVEEFFLUENTSMAINCONDENSER-OFFGASP59F5Iy>)gp(LIMITINGCONDITIONFOROPERATION3.11.2.7Theradioactivityrateofnoblegasesmeasureddownstreamoftherecombinershallbelimitedtolessthanorequalto350,000microcuries/sec.APPLICABILITY:Atalltimes.ACTION:Withtheradioactiverateofnoblegasesdownstreamoftherecombinerexceed-ing350,000microcuries/sec,restoretheradioactivityratetowithinitslimitwithin72hoursorbeinatleastHOTSTANDBYwithinthenext12hours.ISURVEILLANCEREUIREMENTS4.11.2.7.1.TheradioactiverateofnoblegasesdownstreamoftherecombinershallbecontinuouslymonitoredinaccordancewithSpecification3.3.7.11.4.11.2.7.2Theradioactivityrateofnoblegasesdownstreamoftherecombinershall,bedeterminedtobewithinthelimitsofSpecifications3.11.2.7atthefollowiiigfrequenciesbyperforminganisotopicanalysisofarepresentativesampleofgasestakenpriortoholdupanddischargedownstreamoftherecombiner:a.Atleastonceper31days.b.Within4hoursfollowinganincrease,asindicatedbytheOffgasNobleGasActivityMonitor,ofgreaterthan50K,afterfactoringoutincreasesduetochangesinTHERMALPOWERlevel,inthenominalsteadystatefissiongasreleasefromtheprimarycoolant.NINEMILEPOINT-UNIT23/411-17NOV20<SB5
RADIOACTIVEEFFLUENTSVENTINGORPURGINGLIMITINGCONDITIONFOROPERATIONKXFOIF/Ff39P/3.11.2.8VENTINGorPURGINGbfthedrywelland/orsuppressionchamber'shallbethroughthestandbygastreatmentsystem.APPLICABILITY:lyACTION:Withtherequirementsoftheabovespecificationno'tsatisfied,suspendallVENTINGandPURGINGofthedrywelland/orsuppressionchamber.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.11.2.8.1Thecontainmentdrywelland/orsuppressionchambershallbedeter-s~~~~~~minedtobealignedforVENTINGorPURGINgthroughthestandbygastreatmentsystemwithin4hourspriortostartofandatleastonceper12hoursduringVENTINGorPURGINGofthedrywell.4.11.2.8.2Priortouseofthepurgesystemthroughthestandbygastreatmentsystemassurethat:a.BothstandbygastreatmentsystemtrainsareOPERABLEwheneverthepurgesystemisinuse,andb.Wheneverthepurgesystemisinuse~~onestandbygastreatmentsystemtrainshallbeinoperation.SNotapplicableuntilinitialcriticality.b~LWC,A.FLIC,'WC>AnibCQ'SSV.t'O'.OIJ~+~Lw~~u6+t4A%5u<I~+pe2.>HID.~LctWA+~~)3+SNINEMILEPOINT-UNIT23/411-18<<>s<vW>
RADIOACTIVEEFFLUENTS3/4.11.3SOLIDRADIOACTIVEWASTESLIMITINGCONDITIONFOROPERATIONPK~~F5l)V~"I56Pf3.11.3RadioactivewastesshallbesolidifiedordewateredinaccordancewiththePROCESSCONTROLPROGRAMtomeetshippingandtransportationrequirementsduringtransit,anddisposalsiterequirementswhenreceivedatthedisposalsite.APPLICABILITY:Atal1times.ACTION:a4WithSOLIDIFICATIONordewateringnotmeetingdisposalsiteandshippingandtransportationrequirements,suspendshipmentoftheinadequatelyprocessedwastesandcorrectthePROCESSCONTROLPROGRAM,theprocedures,and/ortheSolidWasteSystemasnecessarytopreventrecurrence.b..WithSOLIDIFICATIONordewateringnotperformedinaccordancewiththePROCESSCONTROLPROGRAM,testtheimproperlyprocessedwasteineachcontainertoensurethatitmeetsburialgroundandshippingrequirementsandtakeappropriateadministrativeactiontopreventrecurrence.c.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.11.3SOLIDIFICATIONofatleastonerepresentativetestspecimenfromatleasteverytenthbatchofeachtypeofwetradioactivewastes(e.g.,filtersludges,spentresins,evaporatorbottoms,andsodiumsulfatesolutions)shallbeverifiedinaccordancewiththePROCESSCONTROLPROGRAM:a.IfanytestspecimenfailstoverifySOLIDIFICATION,theSOLIDIFICATIONofthebatchundertestshallbesuspendeduntilsuchtimeasadditmnaltestspecimenscanbeobtained,alternativeSOLIDIFICATIONparameterscanbedeterminedinaccordancewiththePROCESSCONTROLPROGRAM,andasubsequenttestverifiesSOLIDIFICATION.SOLIDIFICATIONofthebatchmaythenberesumedusingthealternativeSOLIDIFICATIONparametersdeterminedbythePROCESSCONTROLPROGRAM;b.IftheinitialtestspecimenfromabatchofwastefailstoverifySOLIDIFICATION,thePROCESSCONTROLPROGRAMshallprovideforthecollectionandtestingofrepresentativetestspecimensfromeachconsecutivebatchofthesametypeofwetwasteuntilatleastthreeconsecutiveinitialtestspecimensdemonstrateSOLIDIFICATION.ThePROCESSCONTROLPROGRAMshallbemodifiedasrequired,asprovidedinSpecification6.13,toassureSOLIDIFICATIONofsubsequentbatchesofwaste;andc.WiththeinstalledequipmentincapableofmeetingSpecification3.11.3ordeclaredinoperable,restoretheequipmenttoOPERABLEstatusorprovideforcontractcapabilitytoprocesswastesasnecessarytosatisfyallapplicabletransportationanddisposalrequirements.NINEMILEPOINT"UNIT2SOV2019M 0 RADIOACTIYEEFFLUENTS3/4.11.4TOTALDOSELIMITINGCONDITIONFOROPERATIONNMFJj~p'P""fgpf3.11.4Theannual(calendaryear)doseordosecommitmenttoanyMEMBEROFTHEPUBLICduetoreleasesofradioactivityandtoradiationfromuraniumfuelcyclesourcesshallbelimitedtolessthanorequalto25mremstothewholebodyoranyorgan,exceptthethyroid,whichshallbelimitedtolessthanorequalto75mrems.APPLICABILITY:Atalltimes.ACTTON:aOb.Withthecalculateddosesfromthereleaseofradioactivematerialsinliquid'orgaseouseffluentsexceedingtwicethelimitsof'pecifi-cation3.H..l.2a.,3.11.1.2b.,3.11.2.2a.,3.11.2.2b.,3.11.2.3a.,or3.11.2.3b.,calculationsshallbemadeincludingdirectradiationcon-tributionsfromtheunits(includingoutsidestoragetanks,etc.)todeterminewhethertheabovelimitsofSpecification3.11.4havebeenexceeded.IfsuchisthecaseprepareandsubmittotheCommissionwithin30days,pursuant'oSpecification6.9.2,aSpecialReportthatdefinesthecorrectiveactiontobetakentoreducesubsequentreleasestopreventrecurrenceol'xceedingtheabovelimitsandincludesthescheduleforachievingconformancewiththeabovelimits.ThisSpecialReport,asdefinedin10CFR20.405(c),shallincludeananalysisthatestimatestheradiationexposure(dose)toaMEMBEROFTHEPUBLICfromuraniumfuelcyclesources,includingalleffluent=pathwaysanddirectradiation,forthecalendaryearthatincludestherelease(s)coveredbythisreport.Itshallalsodescribelevelsofradiationandconcentrationsofradioactivematerialinvolved,andthecauseoftheexposurelevelsorconcentrations.Iftheestimateddose(s)exceedstheabovelimits,andifthereleaseconditionresult-inginviolationof40CFRPart190hasnotalreadybeencorrected,theSpecialReportshallincludearequestforavarianceinaccor-.dancewiththeprovisionsof40CFRPart190.Submittalofthereportisconsideredatimelyrequest,andavarianceisgranteduntilstaffactionontherequestiscomplete.TheprovisionsofSpecifications3.0.3and3.0.~renotapplicable.SURVEILLANCEREUIREMENTS4.11.4.1CumulativedosecontributionsfromliquidandgaseouseffluentsshallbedeterminedinaccordancewithSpecifications4.11.1.2,4.1L.2.2,and4.11.2.3,andinaccordancewiththemethodologyandparametersintheODCM.4.11.4.2Cumulativedosecontributionsfromdirectradiationfromtheunits(includingoutsidestoragetanks,etc.)shallbedeterminedinaccordancewiththemethodologyandparametersintheODCM.ThisrequirementisapplicableonlyunderconditionssetforthinACTIONa.ofSpecification3.11.4.NINEMILEPOINT"UNIT23/411-20Mnvun~ave
- IIy, 3/4.12RADIOLOGICALENVIRONMENTALMONITORING3/4.12.1MONITORINGPROGRAMPigMFg($tpppffpjp3/LIMITINGCONDITIONFOROPERATION3.12.1TheRadiologicalEnvironmentalMonitoringProgramshallbeconductedasspecifiedinTable3.12-1.APPLICABILITY:.Atalltimes.ACTION:b.WiththeRadiologicalEnvironmentalMonitoringProgramnotbeingconductedasspecifiedinTable3.12-1,prepareandsubmittotheCommission,intheAnnualRadiologicalEnvironmentalOperatingReportrequiredbySpecification6.9.1.7,adescriptionofthereasonsfornotconductingtheprogramasrequiredandtheplansforpreventingarecurrence.WiththelevelofradioactivityastheresultofplanteffluentsfnanenvironmentalsamplingmediumataspecifiedlocationexceedingthereportinglevelsofTable3.12-2whenaveragedoveranycalendarquarter,pryoareandsubmittotheCommissionwithin30days,pursuanttoSpecification6.9.2,aSpecialReportthatidentifiesthecause(s)forexceedingthelimit(s)anddefinesthecorrectiveactionstobetakentoreduceradioactiveeffluentssothatthepotentialannualdose"toaMEMBEROFTHEPUBLICislessthanthecalendaryearlimitsofSpecifications3.11.1.2,3.11.2.2,or3.11.2.3.WhenmorethanoneoftheradionuclidesinTable3.12-2aredetectedinthesamplingmedium,thisreportshallbesubmittedif:concentration(1)+'oncentration2*+)1Oreportinglevel(1=reportinglevel(2WhenradionuclidesotherthanthoseinTable3.12-2aredetectedand'.aretheresultofplanteffluents,thisreportshallbesubmittedifthepotentialannualdose"toaMEMBEROFTHEPUBLICfromallradio-nuclidesisequaltoorgreaterthanthecalendaryearlimitsofSpecification3.11.1.2,3.11.2.2,or3.11.2.3.Thisreportisnotrequiredifthemeasuredlevelofradioactivitywasnottheresultofplanteffluents;however,insuchanevent,theconditionshallbereportedanddescribedintheAnnualRadiologicalEnvironmentalOperatingReportrequiredbySpecification6.9.1.7."ThemethodologyandparametersusedtoestimatethepotentialannualdosetoaMEMBEROFTHEPUBLICshallbeindicatedinthisreport.NINEMILEPOINT-UNIT23/412"1NOV3Qj98'
RADIOLOGICALENVIRONMENTALMONITORINGLIMITINGCONDITIONFOROPERATIONACTIONContinuedC.MithmilkorfreshleafyvegetablesamplesunavailablefromoneormoreofthesamplelocationsrequiredbyTable3.12"1,identify.specificlocationsforobtainingreplacementsamplesandaddthemwithin30daystotheRadiologicalEnvironmentalMonitoringProgram.Thespecificlocationsfromwhichsampleswereunavailablemaythenbedeletedfromthemonitoringprogram.PursuanttoSpecifica"tion6.9.1.8,submitinthenextSemiannualRadioactiveEffluentReleaseReportdocumentationforachangeintheODCMincludingarevisedfigure(s)andtablefortheODCMreflectingthenewloca-tion(s)withsupportinginformationidentifyingthecauseoftheunavailabilityofsamplesandjustifyingtheselectionofthenewlocation(s)forobtainingsamples.d.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.12.1TheradiologicalenvironmentalmonitoringsamplesshallbecollectedpursuanttoTable3.12-1fromthespecificlocationsgiveninthetableandfigure(s)intheODCM,andshallbeanalyzedpursuanttotherequirementsofTable3.12-1andthedetectioncapabilitiesrequiredbyTable4.12-1.NINEMILEPOINT-UNIT23/412-2HOV2d143)
ITABLE3.12"1RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM"mMImEXPOSUREPATHWAYAND/ORSAMPLE1.DirectRadiationNUMBEROFSAMPLESANDSAMPLELOCATIONSThirtytworoutinemonitoringstationseitherwithtwoormoredosimetersorwithoneinstrumentformeasuringandrecordingdoseratecontinuously,placedasfollows:Aninnerringofstations,oneineachmeteorologicalsectorinthegeneralareaoftheSITEBOUNDARY;Anouterringofstations,oneineachlandbasemeteorologicalsectorinthe4to5mile"rangefromthesite;andSAMPLINGANDCOLLECTIONFREUENCYOnceperthreemonths.TYPEANDFREQUENCYOFANALYSISGammadoseonceperthreemonths.Thebalanceofthestationsshouldbeplacedinspecialinterestareassuchaspopulationcenters,nearbyresidences,schoo'ls,andinoneortwoaretL~>toserveascontrolstations."Atthisdistance,8windrosesectorsareoverLakeOntario.~ILCf~elC:NWP$P+I~a
MmmDPOSUREPATWAYAND/ORSAMPLE2.AirborneTABLE3.12-1ContinuedNUMBEROFSAMPLESANDSAMPLELOCATIONS()SAMPLINGANDCOLLECTIONFREUENCYRADIOLOGICALENVIRONMENTALMONITORINGPROGRAHTYPEANDFREQUENCYOFANALYSISRadioiodineandParticulatesSamplesfromfivelocations:Threesamplesfromoff-sitelocationsindifferentsectorsofthehighestcalculatedannualsiteaverageground-levelD/g(basedonallsitelicensedreactors);Onesamplefromthevicinityofanestablishedyearroundcommunityhavingthehighestcalculatedannualsiteaverageground-level0/g(basedonallsitelicensedreactors);andContinuoussampleroper-ationwithsamplecollec-tionweekly,ormorefrequentlyifrequiredbydustloading.RadioiodineCannister:I-131analysisweekly.ParticulateSamler:Grossbetaradioactivityanalysisfollowingfilterchange;and(3)gammaisotopicanalysisofcomposite(bylocation)quarterly(asaminimum).Onesamplefromacontrolloca-tion,atleasttenmilesdistantandinal~~~tprevalentwinddirection.3.Waterbornea.Surface(Onesampleupstream.(7)Onesamplefromthesite'sdownstreamcoolingwaterintake.Compositesampleover1-monthperiod.C63Gammaisotopicanalysis(4)oncepermonth.Compositefortritiumanalysisonceperthreemonths.
TABLE3.12-1ContinuedMmtmC)IC:MRADIOLOGICALENVIRONMENTALMONITORINGPROGRAMNUMBEROFEXPOSUREPATHWAYSAMPLESANDAND/ORSAMPLESAMPLELOCATIONS3.Waterborne(Continued)SAMPLINGANDCOLLECTIONFREUENCYb.SedimentfromShoreline4.IngestionOnesamplefromadownstreamTwiceperyear.areawithexistingorpotentialrecreationalvalue.TYPE.ANDFRE(UENCYOFANALYSISeGammaisotopicanalysisa.MilkSamplesfromMILKSAMPLINGLOCA-TIONSinthreelocationswithin3.5milesdistancehavingthehighestcalculatedsiteaverageD/g(basedonalllicensedsitereactors).Iftherearenone,thenonesamplefromMILKSAHPL-INGLOCATIONSineachofthreeareas3.5-5.0milesdistanthav-ingthehighestcalculatedsiteaverage0/g(basedonallli-censedsitereactors).OnesamplefromaMILKSAMPLINGLOCA-TIONatacontrollocation(9-20milesdistantandinaleastpre-velantwinddirection.(Twicepermonth,April-December,(sampleswillbecollectedJanuary-MarchifI-131isdetectedinNovemberandDecemberoftheprecedingyear).IGammaisotopicandI-131analysistwicepermonthwhenanimalsareonpasture(April-December)oncepermonthatothertimes(January-Marchifrequired.)b.FishTwosamplesofacommerciallyorrecreationallyimportantspeciesinthevicinityofaplantdis-chargearea.(g)Onesampleofthesamespeciesorofaspecieswithsimilarfeedinghabitsfrom.snareaatleast5milesdistantfromthesite.Twiceperyear.Gammaisotopicanalysisonedibleportionstwiceperyear.@0III't~Ir'gVf)5tl F MrnITABLE3.12-1ContinuedRADIOLOGICALENVIRONMENTALMONITORINGPROGRAHC)MIEXPOSUREPATHWAYAND/ORSAHPLE4.Ingestion(Continued)NUMBEROFSAHPLESANDSAMPLE-LOCATIONS(SAMPLINGANDCOLLECTIONFREUENCYTYPEANDFREQUENCYOFANALYSISMColIc.FoodProductsSixsamplestotal(utilizingatleasttwosectors)offruitsand/orvegetableswillbecollectedfromavailableoff"sitelocationsofhighestcal-culatedsiteaverage0/g(basedonalllicensedsitereactors).Onesampleofeachofsimilarvegetationgrowninalea~))prevalentwinddirection.Onceperyearduringtheharvestseason.Onceperyearduringtheharvestseason.Gammaisotopic(4)analysisofediblepor"tions(isotopictoincludeI"131)onceduringtheharvestseason.Gammaisotopic(4)analysisofedibleporrtions(isotopictoincludeI-131)onceduringtheharvestseason.4A%f1 0~P TABLE3.12-1(ContinuedTABLENOTATIONSfgvjJ)f0)'lpgagAP/(2)(3)Specificparametersofdistanceanddirectionsectorfromthecenterlineofonereactor,andadditionaldescriptionwherepertinent,shall'bepro-videdforeachandeverysamplelocationinTable3.12-1inatableandfigure(s)intheODCM.RefertoNUREG-0133,"PreparationofRadiologicalEffluentTechnicalSpecificationsforNuclearPowerPlants,"October1978,andtoRadiologicalAssessmentBranchTechnicalPosition,Revision1,Novem"ber1979.Oeviationsarepermittedfromtherequiredsamplingscheduleifspecimensareunobtainableduetocircumstancessuchashazardouscondi-tions,seasonalunavailability,theft,uncooperativeresidentsormalfunc"tionofautomaticsamplingequipment.Ifspecimensareunobtainableduetosamplingequipmentmalfunction,effortshallbemadetocompletecorrec-tiveactionpriortotheendofthenextsamplingperiod.Alldeviationsfromthesamplingscheduleshall-bedocumentedintheAnnualRadiologicalEnvironmentalOperatingReportpursuanttoSpecification6.9.1.7.Itisrecognizedthat,attimes,itmaynotbepossibleorpracticabletocon-tinuetoobtainsamplesofthemediaofchoiceatthemostdesiredlocationortime.Intheseinstancessuitablealternativemediaandlocationsmaybechosenfortheparticularpathwayinquestionandappro-priatesubsitutionsmade.PursuanttoSpecification6.9.1.8,submitinnextSemiannualRadioactiveEffluentReleaseReportarevisedfigure(s)andtablefortheOOCMreflectingthenewlocation(s).Oneormoreinstruments,suchasapressurizedionchamber,formeasuringandrecordingdoseratecontinuouslymaybeusedinplaceof.,orinaddi-tionto,integratingdosimeters'.Forthepurposesofthistab'le,athermoluminescentdosimeter(TLD)isconsideredtobeonephosphor;twoormorephosphorsinapacketareconsideredastwoormoredosimeters.Filmbadgesshallnotbeusedasdosimetersformeasuringdirectradiation.Airborneparticulatesamplefiltersshallbeanalyzedforgrossbetaradioactivity24hoursormoreaftersamplingtoallowforradonandthorondaughterdecay.Ifgrossbetaactivityinairparticulatesamplers.isgreaterthan10timestheyearlymeanofcontrolsamples,gammaisotopicanalysisshallbperformedontheindividualsamples.pCPVC69$NINEMILEPOINT-UNIT23/412-7NOVP,0@
TABLE3.12-1ContinuedTABLENOTATIONSContinued(4)Gammaisotopicanalysismeanstheidentificationandquantificationofgamma-emittingradionuclidesthatmaybeattributabletotheeffluentsfromthefacility.(5)The"upstreamsample"shallbetakenatadistancebeyondsignificantinfluenceofthedischarge.The"downstream"sampleshallbetakeninanareabeyondbutnearthemixingzone.(6)Inthisprogramcompositesamplealiquotsshallbecollectedattimeintervalsthatareveryshort(e.g.,hourly)relativetothecompositingperiod(e.g.,monthly)inordertoassureobtainingarepresentativesamp1e.(7)Thepurposeofthesesamplesistoobtainbackgroundinformation.Ifitisnotpracticaltoestablishcontrollocationsinaccordancewiththedistanceandwinddirectioncriteria,othersites,suchashistorical.controllocationswhichprovidevalidbackgrounddatamaybesubstituted.(8)Inthe.eventcommercialorrecreationalimportantspeciesarenotavail-ableasaresultofthreeattempts,thenotherspeciesmaybeutilizedasavailable.NINEMILEPOINT-UNIT23/412"8NOv20]gg
TABLE3.12"2REPORTINGLEVELSFORRADIOACTIVITYCONCENTRATIONSINENVIRONHENTALSAHPLESREPORTINGLEVELSANALYSISMATER(pCi/1)AIRBORNEPARTICULATEORGASES(pCi/m~)FISH(pCi/kg,wet)HILK(pCi/1)FOODPRODUCTS(pCi/kg,wet)H-3Hn-54Fe-59Co-58Co-60Zn-65Zr-95)Nb-95I"131Cs-134Cs"137Ba/La-14030,000+li0004001,0003003004002030502000.9102030,00010,00030,00010,00020,000I1,0002,0006070300100110002,000 I~ MMIfoalTABLE4.12"1DETECTIONCAPABILITIESFORENVIRONMENTALSAMPLEANALYSIS()LOWERLIMITOFDETECTIONLLDC)MMATERANALYSIS(pCi/1)GrossBeta4H-33000AIRBORNEPARTICULATEORGASES(pCi/ms)0.01=FISHMILK(pCi/kg,wet)(pCi/1)FOODPRODUCTSSEDIMENT(pCi/kg,wet)(pCi/kg,dry)Mn-54Fe-591530130260Co"58,6015130En-65302602r-95,Nb-9515I-1310.0760Cs-134Cs-137Ba/La-14015180.050.061301501518156080150180
TABLE4.12-1ContinuedTABLENOTATIONS(1)Thislistdoesnotmeanthatonlythesenuclidesaretobeconsidered.Otherpeaksthatareidentifiable,togetherwiththoseoftheabovenuclides,shallalsobeanalyzedandreportedintheAnnualRadiologicalEnvironmentalOperatingReportpursuanttoSpecification6.9.1.,7.(2)TheLLDisdefined,forpurposesofthesespecifications,asthesmallestconcentrationofradioactivematerialinasamplethatwillyieldanetcount,abovesystembackground,thatwillbedetectedwith95Kprobabilitywithonly5Xprobabilityoffalselyconcludingthatablankobservationrepresentsa"real"signal.Foraparticularmeasurementsystem,whichmayincluderadiochemicalseparation:4.66sbLLO=E~V~2.22~Y-exp("Abt)Where:LLObthe"apriori"lowerlimitofdetection(picoCuriesperunitmass'orvolume),thestandarddeviationofthebackgroundcountingrateorofthecountingrateofablanksampleasappropriate(countsperminute),thecountingefficiency(countsperdisintegration),thesamplesize(unitsofmassorvolume),2.22=thenumberofdisintegrationsperminuteperpicoCurie,Y=thefractionalradiochemicalyield,whenapplicable,=theradioactivedecayconstantfortheparticularradionuclide(sec-~),andht=theelapsedtimebetweenenvironmentalcollection,orendofthesamplecollectionperiod,andtimeofcounting(sec).Typical'aluesofE,V,Y,and4tshouldbeusedinthecalculation.NINEMILEPOINT-UNIT23/412"11NOV801985
TABLE4.12-1Continued)TABLENOTATIONSContinuedPklggjidiIPV)g~hf'tshoo'IdberecognisedthattheLLDisdefinedasana~riori(beforethefact)limitrepresentingthecapabilityofameasurementsystemandnotas(fhfj1iifpi1t.AnalysesshallbeperformedinsuchamannerthatthestatedLLOswillbeachievedunderroutineconditions.Occasionallybackgroundfluctuations,unavoidablesmallsamplesizes,thepresenceofinterferingnuclides,orotheruncontro11ablecircumstancesmayrendertheseLLOsunachievable.Insuchcases,thecontributingfactorsshallbeidentifiedanddescribedintheAnnualRadiologicalEnvironmentalOperatingReportpursuanttoSpecification6.9.1.7.'INEMILEPOINT-UNIT23/412-12NOV20!egg
RADIOLOGICALENVIRONMENTALMONITORING3/4.12.2LANDUSE'CENSUSLIMITINGCONDITIONFOROPERATION~+PlQt)~yIi!PJ~fitPJJ~lPgP>>IPII$$Pijfj)3.12.2ALandUseCensusshallbeconductedandshallidentifywithinadistanceof5milesthelocationineachofthe16meteorologicalsectorsofthenearestmilkanimal,-andthenearestresidence.Inlieuofagardencensus,specificationsforvegetationsamplinginTable3.12-1shallbefollowed,includinganalysisofappropriatecontrols.APPLICABILITY:Atalltimes.ACTION:f>>a>>b.C.WithaLandUseCensusidentifyingalocation(s)thatyieldsaD/gvaluegreaterthanthevaluescurrentlybeingcalculatedinSpecification'.4.11.2.3,pursuanttoSpecification6.9.1.8,identify.thenewlocation(s)inthenextSemiannualRadioactiveEffluentReleaseReport.WithaLandUseCensusidentifyingamilkanimallocation(s)thatyieldsaD/q(viathesameexposurepathway)50Kgreaterthanatalocationfromwhichsamplesarecurrentlybeingobtainedinaccord-ancewithSpecification3.12.1,addthenewlocation(s)within30daystotheRadiologicalEnvironmentalMonitoringProgram.Thesamplinglocation(s),excludingthecontrolstationlocation,havingthelowestD/gvalue,viathesameexposurepathway,maybedeletedfromthismonitoringprogramafterOctober31oftheyearinwhichthisLandUseCensuswasconducted.PursuanttoSpecification6.9.1.8,submitinthenextSemiannualRadioactiveEffluentReleaseReportdocumentationforachangeintheODCMincludingarevisedfigure(s)andtable(s)fortheODCMreflectingthenewlocation(s).TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.12.2TheLandUseCensusshallbeconductedduringthegrowingseasonatleastonceper12monthsusingthatinformationthatwillprovidethebestresults,suchasbyadoor-to-doorsurvey,aerialsurvey,orbyconsultinglocalagricultureauthorities.TheresultsoftheLandUseCensusshallbeincludedintheAnnualRadiologicalEnvironmentalOperatingReportpursuanttoSpecification6.9.1.7.NINEMILEPOINT-UNIT23/412-13HOV20l98S
RADIOLOGICALENVIRONMENTALMONITORING3/4.12.3INTERLABORATORYCOMPARISONPROGRAM@All(09lreee~LIMITINGCONDITIONFOROPERATION3.12.3Analysesshallbeperformedonallradioactivematerials,suppliedaspartofanInterlaboratoryComparisonProgramthathasbeenapprovedbytheCommission,thatcorrespondtosamplesrequiredbyTable3.12-1.Participa-tioninthisprogramshallincludemediaforwhichenvironmentalsamplesareroutinelycollectedandforwhichinter-comparisonsamplesareavailable.APPLICABILITY:Atalltimes.ACTION:aoMithanalysesnotbeingperformedasrequiredabove,reportthecorrectiveactionstakentopreventarecurrencetotheCommission.intheAnnualRadiologicalEnvironmentalOperatingReportpursuanttoSpecification6.9.l.7.b.TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.12.3TheInterlaboratoryComparisonProgramshallbedescribedintheODCM.AsummaryoftheresultsobtainedaspartoftheaboverequiredInterlaboratoryComparisonProgramshallbeincludedintheAnnualRadiologicalEnvironmentalOperatingReportpursuanttoSpecification6.9.1.7.ParticipantsintheEPACrossCheckProgrammayprovidetheEPAprogramcodedesignationinlieuofprovidingresults.NINEMILEPOINT-UNIT23/412-14NOV201985
BASESFORCSECTIONS3.0AND4.0LIMITINGCONDITIONSFOROPERATION'WANDSURVEILLANCERE(UIREMENTSNINE-MILEPOINT"UNIT2g0Y201985 i NOTETheBASEScontainedinsucceedingpagessummarizethereasonsfortheSpecificationsinSection3.0and4.0,butinaccordancewith10CFR50.36arenotpartoftheseTechnicaISpecifications.NINEMILEPOINT"UNIT2goy201985 i 3/4.0APPLICABILITYBASESThespecificationsofthissectionprovidethegeneralrequirementsapplicabletoeachoftheLimitingConditionsforOperationandSurveillanceRequirementswithinSection3/4.3.0.1ThisspecificationstatestheapplicabilityofeachspecificationintermsofdefinedOPERATIONALCONDITIONorotherspecifiedapplicabilitycon-ditionandisprovidedtodelineatespecificallywheneachspecificationisapplicable.3'.2ThisspecificationdefinesthoseconditionsnecessarytoconstitutecompliancewiththetermsofanindividualLimitingConditionforOperationandassociatedACTIONrequirement.'I3.0.3ThisspecificationdelineatesthemeasurestobetakenforthosecircumstancesnotdirectlyprovidedforintheACTIONstatementsandwhoseoccurrenc'ewouldviolatetheintentofthespecification.Forexample,Specifi-cation3.7.2requirestwocontrolroomemergencyfiltrationsubsystemstobeOPERABLEandprovidesexplicitACTIONrequirementsifonesubsystem'isinoperable.UndertherequirementsofSpecification3.0.3,ifbothoftherequiredsubsystemsareinoperable,withinonehourmeasuresmustbeinitiatedtoplacetheunitinatleastSTARTUPwithinthenext6hours,inatleastHOTSHUTDOWNwithinthefollowing6hoursandinCOLDSHUTDOWNwithinthesubsequent24hours.Asafurtherexample,Specification3.6.6.1requirestwoprimarycontainmenthydrogenrecombinersystemstobeOPERABLEandprovidesexplicitACTIONrequirementsifonerecombinersystemisinoperable.Undertherequire-mentsofSpecification3.0.3,ifbothoftherequiredsystemsareinoperable,withinonehourmeasuresmustbeinitiatedtoplacetheunitinatleastSTARTDPwithinthenext6hours.andinatleastHOTSHUTDOWNwithinthefollowing6hours.3.0.4ThisspecificationprovidesthatentryintoanOPERATIONALCONDITIONmustbemadewith(a)thefullcomplementofrequiredsystems,equipmentorcomponentsOPERABLEand(b)allotherparametersasspecifiedintheLimitingConditionsforOperationbeingmetwithoutregardforallowabledeviationsandoutofserviceprovisionscontainedintheACTIONstatements.Theintentofthisprovisionistoensurethatunitoperationisnotinitiatedwitheitherrequiredequipmentorsystemsinoperableorotherlimitsbeingexceeded.Exceptionstothisprovisionhavebeenprovidedforalimitednumberofspecificationswhenstartupwithinoperableequipmentwouldnotaffectplantsafety.TheseexceptionsarestatedintheACTIONstatementsoftheappropriatespecifications.NINEMILEPOINT-UNIT2B3/40-1
APPLICABILITYBASESpQQ"..WS~0iiegjQ~giggyf4.0.1Thisspecificationprov'idesthatsurveillanceactivitiesnecessarytoensuretheLimitingConditionsforOperationaremetandwillbeperformedduringtheOPERATIONALCONDITIONSorotherconditionsforwhichtheLimitingConditionsforOperationareapplicable.ProvisionsforadditionalsurveillanceactivitiestobeperformedwithoutregardtotheapplicableOPERATIONALCONDI-TIONSorotherconditionsareprovidedintheindividualSurveillanceRequire-ments.SurveillanceRequirementsforSpecialTestExceptionsneedonlybeperformedwhentheSpecialTestExceptionisbeingutilizedasanexceptiontoanindividualspecification.4.0.2Theprovisionsofthisspecificationprovideallowabletolerancesforperformingsurveillanceactivitiesbeyondthosespecifiedinthenominalsurveillanceinterval.Thesetolerancesarenecessarytoprovideoperationalflexibilitybecauseofschedulingandperformanceconsiderat'ions.Thephrase"atleast"associatedwithasurveillancefrequencydoesnotnegatethis'allowabletolerance;instead,itpermits4hemorefrequentperformanceofsurveillanceactivities.Thetolerancevalues,takeneitherindividuallyorconsecutivelyover3testintervals,aresufficientlyrestrictivetoensurethatthereliabilityassociatedwiththesurveillanceactivityisnotsignificantlydegradedbeyondthatobtainedfromthenominalspecifiedinterval.4.0.3Theprovisions.ofthisspecificationsetforththecriteriafordeterminationofcompliancewiththeOPERABILITYrequirementsoftheLimitingConditionsforOperation.Underthiscriteria,equipment,systemsorcomponentsareassumedtobeOPERABLEiftheassociatedsurveillanceactivitieshavebeensatisfactorilyperformedwithinthespecifiedtimeinterval.Nothinginthisprovisionistobeconstruedasdefiningequipment,systemsorcomponents~.OPERABLE,whensuchitemsarefoundorknowntobeinoperablealthoughstillmeetingtheSurveillanceRequirements.4.0.4ThisspecificationensuresthatsurveillanceactivitiesassociatedwithaLimitingConditionsforOperationhavebeenperformedwithinthespecifiedtimeintervalpriortoentryintoanapplicableOPERATIONALCONDITIONorotherspecifiedapplicabilitycondition.TheintentofthisprovisionistoensurethatsurveillanceactivitieshavebeensatisfactorilydemonstratedonacurrentbasisasrequiredtomeettheOPERABILITYrequirementsoftheLimitingConditionforOperation.Underthetermsofthisspecification,forexample,duringinitialplantstartuporfollowingextendedplantoutage,theapplicablesurveillanceactiv-itiesmustbeperformedwithinthestatedsurveillanceintervalpriortoplacingorreturningthesystemorequipmentintoOPERABLEstatus.NINEMILEPOINT-UNIT2B3/40-2gov20585
APPLICABILITYBASESPi~iggpp(p~!pJ[~py4.0.5ThisspecificationensuresthatinserviceinspectionofASMECodeClass1,2and3componentsandinservicetestingofASMECodeClass1,2and3pumpsandvalveswillbeperformedinaccordancewithaperiodicallyupdatedversionofSectionXIoftheASMEBoilerandPressureVesselCodeandAddendaasrequiredby10CFR50,Section50.55a.Relieffromanyoftheaboverequire-mentshasbeenprovidedinwritingbytheCommissionandisnotapartoftheseTechnicalSpecifications.Thisspecificationincludesaclarificationofthefrequenciesofperform-ingtheinserviceinspectionandtestingactivitiesrequiredbySectionXIoftheASMEBoilerandPressureVesselCodeandapplicableAddenda.Thisclarifi-cationisprovidedtoensureconsistencyinsurveillanceintervalsthroughouttheseTechnicalSpecificationsandtoremoveanyambiguitiesrelativetothefrequenciesforperformingtherequiredinserviceinspectionandtestingactiv-ities..UnderthetermsofthisspecificationthemorerestrictiverequirementsoftheTechnicalSpecificationstakeprecedenceovertheASMEBoilerandPressureVesselCodeandapplicableAddenda.Forexample,therequirementsofSpecifi-cation4.0.4toperformsurveillanceactivitiespriortoentryintoanOPERATIONALCONOITIONorotherspecifiedapplicabilityconditiontakesprecedenceovertheASMEBoilerandPressureVesselCodeprovisionwhichallowspumpstobetested-uptoone.weekafterreturn-tonormaloperation.Andfor.'xample,theTechnicalSpecificationdefinitionofOPERABLEdoesnotgrantagraceperiodbeforeadevicethatisnotcapableofperformingitsspecifiedfunctionisdeclaredinoperableandtakesprecedenceovertheASMEBoilerandPressureVesselprovi"sionwhichallowsavalvetobeincapableofperformingitsspecifiedfunctionforupto24hoursbeforebeingdeclaredinoperable.NINEMILEPOINT-UNIT2B3/40-3
3/4.1REACTIVITYCONTROLSYSTEMSBASES3/4.1.1SHUTDOWNMARGINAsufficientSHUTDOWNMARGINensuresthat1)thereactorcanbemadesubcriticalfromalloperatingconditions,2)thereactivitytransientsasso-ciatedwithpostulatedaccidentconditionsarecontrollablewithinacceptablelimits,and3)thereactorwillbemaintainedsufficientlysubcriticaltoprecludeinadvertentcritical-ityintheshutdowncondition.Sincecorereactivityvalueswillvarythroughcorelifeasafunctionoffueldepletionandpoisonburnup,thedemonstrationofSHUTDOWNMARGINwillbeperformedinthecold,xenon-freeconditionandshallshowthecoretobesubcriticalbyatleastR+0.38Kdeltak/korR+0.28Kdeltak/k,asappro-priate..ThevalueofRinunitsofIdeltak/kisthedifferencebetweenthecalculatedvalueofmaximumcorereactivUyduringtheoperatingcycleandthecalculatedbeginning-of-lifecorereactivity.ThevalueofRmustbepositiveor-zeroandmustbedeterminedforeachfuelloadingcycle.TwodifferentvaluesaresuppliedintheLimitingConditionforOperationtoprovideforthedifferentmethodsofdemonstrationoftheSHUTDOWNMARGIN.Thehighestworthrodmaybedeterminedanalyticallyorbytest.TheSHUTDOWNMARGINisdemonstratedbyaninsequencecontrolrodwithdrawalatthebegin-ningoflifefuelcycleconditions,and,ifnecessary,atanyfuturetimeinthecycleifthefirstdemonstrationindicatestiiattherequiredmargincouldbereducedasafunctionofexposure.Observationofsubcritica'lityinthisconditionassuressubcriticalitywiththemostreactivecontrolrodfullywithdrawn.Thisreactivitycharacteristichasbeenabasicassumptionintheanalysisofplantperformanceandcanbebestdemonstratedatthetimeoffuelloading,butthemarginmustalsobedeterminedanytimeacontrolrodisincapableofinsertion.3/4.1.2REACTIVITYANOMALIESSincetheSHUTDOWNMARGINrequirementforthereactorissmall,acarefulcheckonactualconditionstothepredictedconditionsisnecessary,andthechangesinreactivitycanbeinferredfromthesecomparisonsofrodpatterns.Sincethecomparisonsareeasilydone,frequentchecksarenotanimpositiononnormaloperations.A2Xdeltak/kchangeislargerthanisexpectedfornormaloperationsoachangeofthismagnitudeshouldbethoroughlyevaluated.Achangeaslargeas2Xdeltak/kwouldnotexceedthedesignconditionsofthereactorandisonthesafesideofthepostulatedtransients.NINEMILEPOINT-UNIT2B3/4l-lHOV30}9B5 1'l REACTIVITYCONTROLSYSTEMSBASESpgAFg)/~pl]pgp3/4.1.3CONTROLRODSThespecificationofthissectionensurethat(1)theminimumSHUTDOWNMARGINismaintained,(2)thecontrolrodinsertiontimesareconsistentwiththoseusedinthesafetyanalyses,and(3)limitthepotentialeffectsoftheroddropaccident.TheACTIONstatementspermitvariationsfromthebasicrequirementsbutatthesametimeimposemorerestrictivecriteriaforcontinuedoperation.Alimitationoninoperablerodsissetsuchthattheresultanteffectontotalrodworthandscramshapewillbekepttoaminimum.Therequirementsforthevariousscramtimemeasurementsensurethatanyindicationofsystematicproblemswithroddriveswillbeinvestigatedonatimelybasis.Damagewithinthecontrolroddrivemechanismcouldbeagenericproblem;thereforewithacontrolrodimmovablebecauseofexcessivefrictionormechanicalinterference,operationofthereactorislimitedtoatimeperiodwhichisreasonabletodeterminethecauseoftheinoperabilityandatthesametimepreventoperationwithalargenumberofinoperab'lecontrolrods.Controlrodsthatareinoperableforotherreasonsarepermittedtobetakenoutofserviceprovidedthatthoseinthenonfully-insertedpositionareconsistentwiththeSHUTDOWNMARGINrequirements.Thenumberofcontrolrodspermittedtobeinoperablecouldbemorethantheeightallowedbyth'especification,buttheoccurrenceofeightinoperablerodscouldbeindicativeofagenericproblemandthereactormustbeshutdownforinvestigationandresolutionoftheproblem.ThecontrolrodsystemisdesignedtobringthereactorsubcriticalataratefastenoughtopreventtheHCPRfrombecominglessthan1.06duringthelimitingpowertransientanalyzedinSection15.4oftheFSAR.Thisanalysisshowsthatthenegativereactivityratesresultingfromthescramwiththeaverageresponseofallthedrivesasgiveninthespecifications,providetherequiredprotectionandHCPRremainsgreaterthan1.06.Theoccurrenceofscramtimeslongerthenthosespecifiedshouldbeviewedasanindicationofasystemicproblemwiththeroddrivesandthereforethesurveillanceintervalisreducedinordertopreventoperationofthereactorforlongperiodsoftimewithapotentiallyseriousproblem.ThescramdischargevolumeisrequiredtobeOPERABLEsothatitwillbeavailablewhenneededtoacceptdischargewaterfromthecontrolrodsduringareactorscramandwillisolatethereactorcoolantsystemfromthecontainmentwhenrequired.ControlrodswithinoperableaccumulatorsaredeclaredinoperableandSpecification3.1.3.1thenapplies.Thispreventsapatternofinoperableaccumulatorsthatwouldresultinlessreactivityinsertiononascramthanhasbeenanalyzedeventhoughcontrolrodswithinoperableaccumulatorsmaystillbeinsertedwithnormaldrivewaterpressure.Operabilityoftheaccumulatorensuresthatthereisameansavailabletoinsertthecontrolrodsevenunderthemostunfavorabledepressurizationofthereactor.NINEMILEPOINT"UNIT2B3/41-2tlOV20N5
REACTIVITYCONTROLSYSTEMSBASESCONTROLRODS(Continued)ControlrodcouplingintegrityisrequiredtoensurecompliancewiththeanalysisoftheroddropaccidentintheFSAR.Theovertravelpositionfeatureprovidestheonlypositivemeansofdeterminingthatarodisproperly'coupledandthereforethischeckmustbeperformedpriortoachievingcriticalityaftercompletingCOREALTERATIONSthatcouldhaveaffectedthecontrolrodcouplingintegrity.Thesubsequentcheckisperformedasabackuptotheinitialdemonstration.Inordertoensurethatthecontrolrodpatternscanbefollowedandthereforethatotherparametersarewithintheirlimits,thecontrolrodpositionindicationsystemmustbeOPERABLE.Thecontrolrodhousingsupportrestrictstheoutwardmovementofacontrolrodtolessthan6inchesintheeventofahousingfailure.Theamountofrodreactivitywhichcouldbeaddedbythissmallamountofrodwithdrawalislessthananormalwithdrawalincrementagdwillnotcontributetoanydamagetotheprimarycoolantsystem.Thesupportisnotrequiredwhenthereisnopressuretoactasadrivingforcetorapidlyejectadrivehousing.TherequiredsurveillanceintervalsareadequatetodeterminethattherodsareOPERABLEandnotsofrequentastocauseexcessivewearonthesystemcomponents.3/4.1.4CONTROLRODPROGRAMCONTROLSControlrodwithdrawalandinsertionsequencesareestablishedtoassurethatthemaximuminsequenceindividualcontrolrodorcontrolrodsegmentswhicharewithdrawnatanytimeduringthefuelcyclecouldnotbeworthenoughtoresultinapeakfuelenthalpygreaterthan280cal/gmintheeventofacontrolroddropaccident.Thespecifiedsequencesarecharacterizedbyhomogeneous,.scatteredpatternsof,controlrodwithdrawal.WhenTHERMALPOWERisgreaterthan20KofRATEDTHERMALPOWER,thereisnopossiblerodworthwhich,ifdroppedatthedesignrateofthevelocitylimiter,couldresultinapeakenthalpyof280cal/gm.ThusrequiringtheRSCSandRWMtobeOPERABLEwhenTHERMALPOWERislessthanorequalto20ofRATEDTHERMALPOWERprovidesadequatecontrol.TheRSCSandRWMprovideautomaticsupervisiontoassurethatout-of-sequencerodswillnotbewithdrawnorinserted.TheanalysisoftheroddropaccidentispresentedinSection15.4oftheFSARandthetechniquesoftheanalysisarepresentedinatopicalreport,Reference1,andtwosupplements,References2and3.TheRBMisdesignedtoautomaticallypreventfueldamageintheeventoferroneousrodwithdrawalfromlocationsofhighpowerdensityduringhighpoweroperation.Twochannelsareprovided.Trippingoneofthechannelswillblockerroneousrodwithdrawalsoonenoughtopreventfueldamage.Thissystembacksupthewrittensequenceusedbytheoperatorforwithdrawalofcontrolrods.NINEMILEPOINT-UNIT2B3/41-3gpss80198~
REACTIVITYCONTROLSYSTEMSBASESFIKF8gppbtJpip/3/4.1.5STANDBYLIUIDCONTROLSYSTEMThestandbyliquidcontrolsystemprovidesabackupcapabilityforbringingthereactorfromfullpowertoacold,Xenon-freeshutdown,assumingthatthewithdrawncontrolrodsremainfixedintheratedpowerpattern.Tomeetthisobjectiveitisnecessarytoinjectaquantityofboronwhichproducesaconcen"trationof660ppminthereactorcoreandotherpipingsystemsconnectedtothereactorvessel.Toallowforpotentialleakageandimperfectmixing,thiscon-centrationisincreasedby20K.Therequiredconcentrationisachievedbyhavinga.minimumavailablequantityof4625gallonsofsodium-pentaboratesolutioncon-tainingaminimumof5493lbsofsodium-pentaborate.Thisquantityofsolutionisanetamountwhichisabovethepumpsuction,thusaIlowingfortheportionwhichcannotbeinjected.Theminimumpumpingrateof41.2gpmperpumpprovidesainegativereactivityinsertionrateoverthepermissiblepenetaboratesolutionvolumerange,whichadequatelycompensatesforthepositivereactivityeffectsduetotemperatureandXenonduringshutdown.Thetemperaturerequirementisnecessarytoensurethatthesodiumpentaborateremainsinsolution.Withredundantpumpsandexplosiveinjectionvalvesandwithahighlyreliablecontrolrodscramsystem,operationofthereactorispermittedtocontinueforshortperiodsoftimemitt-rthesystemssuper'sbIeorforTongerperiodsoftimewithoneoftheredundantcomponentsinoperable.Surveillancerequirementsareestablishedonafrequencythatassuresa'ighreliabilityofthesystem.Oncethesolutionisestablished,boroncon-centrationwillnotvaryunlessmoreboronorwaterisadded,thusacheckonthetemperatureandvolumeonceeach24hoursassuresthatthesolutionisavailableforuse.Replacementoftheexplosivechargesinthevalvesatregularintervalswillassurethatthesevalveswillnotfailbecauseofdeteriorationofthecharges.2.3.C.J.Paone,R.C.StirnandJ.A.Woolley,"RodDropAccidentAnalysisforLargeBWR's,"G.E.TopicalReportNED0-10527,March1972C.J.Paone,R.C.StirnandR.M.Young,SupplementltoNED0.-10527,July1972J.M.Haun,C.J.PaoneandR.C.Stirn,Addendum2,"ExposedCores,"Supplement2toNED0-10527,January1973NINEMILEPOINT-UNIT283/4l"4NQVSO885
3/4.2POMERDISTRIBUTIONLIMITSBASESPR!5$gpI)/pegypThespecificationsofthissectionassurethatthepeakcladdingtemper-aturefollowingthepostulateddesignbasis'loss-of-coolantaccidentwillnotexceedthe2200Flimitspecifiedin10CFR50.46.Wns'3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATEThepeakcladdingtemperature(PCT)followingapostulatedloss-of-coolantaccidentisprimarilyafunctionoftheaverageheatgenerationrateofalltherodsofafuelassemblyatanyaxiallocationandisdependentonlysecondarilyontherodtorodpowerdistributionwithinanassembly.ThepeakcladtemperatureiscalculatedassumingaLHGRforthehighestpoweredrodwhichisequaltoor~lessthanthedesignLHGRcorrectedfordensification.ThisLHGRtimes@1.0isusedintheheatupcodealongwith.theexposuredependentsteadyst&egapconductanceandrod-to-rodlocalpeakingfactor.TheTechnicalSpecificationAVERAGEPLANARLINEARHEATGENERATIONRATE(APLHGR)istheLHGRofthehighestpoweredroddividedbyitslocalpeakingfactor.ThelimitingvalueforAPLHGRs4sshowninFigure~3.2.1-.1feartworecirculationloopoperation.J,a<-z~>.z,l.>,ThecalculationalprocedureusedtoestablishtheAPLHGRshownonFigures-3-.2-.1-1-,3.2.1-2and3.2:1-3isbasedonalossof-coo-lantaccidentanaiysis.TheanalysiswasperformedusingGeneralElectric(GE)calculationalmodelswhichareconsistentwiththerequirementsofAppendixKto10CFR50.Acompletediscussionof'achcodeemployedintheanalysisispresentedinReference1.Differencesinthisanalysiscomparedtopreviousanalysescanbebrokendownasfollows.InutChanes1.CorrectedVaporizationCalculation-CoefficientsinthevaporizationcorrelationusedintheREFLOODcodewerecorrected.2.3.Incorporatedmoreaccuratebypassareas-ThebypassareasinthetopguidewererecalculatedusingamoreaccuratetFcCinique.tCorrectedguidetubethermalresistance.4.Correctheatcapacityofreactorinternalsheatnodes.NINEMILEPOINT-UNIT2B3/42-1NOVYMi"ov I POWERDISTRIBUTIONLIMITSBASESAVERAGEPLANARLINEARHEATGENERATIONRATE(Continued)h.~dd1dh1.Core.CCFLpressuredifferential-1psi-Incorporatetheassumptionthatflowfromthebypasstolowerplenummustovercomea1psipressuredropincote.2.IncoporateNRCpressuretransferassumption-TheassumptionusedintheSAFE-REFLOODpressuretransferwhenthepressureisincreasingwaschanged.AfewofthechangesaffecttheaccidentcalculationirrespectiveofCCFL.Thesechangesarelistedbelow.~ldh1.BreakAreas-TheDBAbreakaieawascalculatedmoreaccurately.-h.~dd1dhl.ImprovedRadiationandConductionCalculation-IncorporationofCHASTE05for.heatupcalculation.Alistofthesignificantplantinputparameterstotheloss-of-coolantaccidentanalysisispresentedinBasesTableB3.2.1-1.3/4.2.2APRMSETPOINTSThefuelcladdingintegritySafetyLimitsofSpecification2.1werebasedonapower,distributionwhichwouldyieldthedesignLHGRatRATEDTHERMALPOWER.Theflowbiasedsimulatedthermalpower-upscalescramsettingandfloHbiasedneutronfluxupscalecontrolrodblockfunctionsoftheAPRMinstrumentsmustbeadjustedtoensurethattheMCPRdoesnotbecomelessthanl.06orthat>2Xplasticstraindoesnotoccurinthedegradedsituation.ThescramsetpointandrodblocksettingsareadjustedinaccordancewiththeformulainthisspecificationwhenthecombinationofTHERMALPOWERandCMFLPDindicatesahigherpeakedpowerdistributiontoensurethatanLHGRtransientwouldnotbeincreasedinthedegradedcondition.NINEMILEPOINT"UNIT2B3/42-2NOV3P~oB5
BasesTableB3.2."PÃ9F8PPZA'6P'/SIGNIFICANTINPUTPARAMETERSTOTHELOSS-OF-COOLANTACCIDENTANALYSIS*1'~~PlantParameters;CoreTHERMALPOWER.....................3461MWt"whichcorrespondsto105XofratedsteamflowVesselSteam'Output....................15.0x10ibm/hrwhichcor-6respondsto105KofratedsteamflowVesselSteamDomePressure..............1055psiaDesignBasisRecirculationLineBreakAreafor:a.LargeBreaks3.1ftb.SmallBreaks0.09ftFuelParameters:FUELTYPEInitialCorePEAKTECHNICALINITIALSPECIFICATIONDESIGNMINIMUMLINEARHEATAXIALCRITICALGENERATIONRATEPEAKINGPOWER(kw/ft)FACTORRATIOFUELBUNDLEGEOMETRY8x813.41.41.20AmoredetailedlistingofinputofeachmodelanditssourceispresentedinSectionIIofReference1andsubsection6.3.3oftheFSAR.."ThispowerlevelmeetstheAppendixKrequirementof102.Thecoreheatupcalculationassumesabundlepowerconsistentwithoperationofthehighestpoweredrodat102KofitsTechnicalSpecificationLINEARHEATGENERATIONRATElimit.NINEMILEPOINT-UNIT2B3/42-3
POWERDISTRIBUTIONLIMITSBASESR)PIPIT~fg"pfpffft3/4.2.3MINIMUMCRITICALPOWERRATIOTherequiredoperatinglimitMCPRsatsteadystateoperatingcondftionsasspecifiedinSpecification3.2.3arederivedfromtheestablishedfuelcladdingintegritySafetyLimitMCPRof1.06,andananalysisofabnormaloperationaltransients.Foranyabnormaloperatingtransientanalysisevalua-tionwiththeinitialconditionofthereactorbeingatthesteadystateoperatinglimit,itisrequiredthattheresultingMCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytimeduringthetransientassuminginstrumenttriosettinggiveninSpecification2.2.1ToassurethatthefuelcladdingintegritySafetyLimitisnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtran-sientshavebeenanalyzedtodeterminewhichresultinthelargestreductioninCRITICALPOWERRATIO(CPR).Thetypeoftransientsevaluatedwerelossofflow,increaseinpressureandpower,positivereactivityinsertion,andcoolanttemperaturedecrease.ThelimitingtransientyieldsthelargestdeltaMCPR.WhenaddedtotheSafetyLimitMCPRof1.06,therequiredminimumoperatinglimitMCPRofSpecification3.2.3isobtainedandpresentedinFigure3.2.3-1.TheevaluationofagiventransientbeginswiththesysteminitialparametersshowninFSARTable15.0.3thatareinputtoaGE-coredynamicbehaviortransientcomputerprogram.ThecodeusedtoevaluatepressurizationeventsisdescribedinNEDO-24154andtheprogramusedinnon-pressurizationeventsisdescribedinNEDO-10802.TheoutputsofthisprogramalongwiththeinitialMCPRformtheinputforfurtheranalysesofthethermallylimitingbundlewiththesinglechanneltransientthermalhydraulicTASCcodedescribedinNEDE-25149~~.TheprincipalresultofthisevaluatinisthereductioninMCPRcausedbythetransient.ThepurposeoftheKffactorofFigure3.2.3-istodefineoperatinglimitsatotherthanratedcoreflowconditions.Atlessthan100KofratedflowtherequiredMCPRistheproductoftheMCPRandtheKfactor.TheKffactorsassurethattheSafetyLimitMCPRwillnotbeviolated.TheKfactorswerederivedusingTHERMALPOWERandcoreflowcorrespondingtb105Kofratedsteamflow.TheKfactorswerecalculatedsuchthatforthemaximumcoreflowrateandthecorrespondingTHERMALPOWERalongthe105Kofratedsteamflowcontrolfline,thelimitingbundle'srelative'owerwasadjusteduntiltheMCPRwasslightlyabovetheSafetyLimit.Usingthisrelativebundlepower,theMCPRswerecalculatedatdifferentpointsalongthe105Kofratedsteamflowcontrol'inecorrespondingtodifferentcoreflows.TheratiooftheMCPRcalculatedatagivenpointofcoref'low,dividedbytheoperatinglimitMCPR,determinestheKf.NINEMILEPOINT"UNIT2B3/42-4N8V20139)
POWERDISTRIBUTIONLIMITS,BASESpjg~~p$Vzi/'P<<'$$flQfMINIMUMCRITICALPOWERRATIO(Continued)fAtTHERMALPOWERlevelslessthanorequalto25KofRATEDTHERMALPOWER,thereactorwillbeoperatingatminimumrecirculationpumpspeedandthemoderatorvoidcontentwillbeverysmall.Foralldesignatedcontrolrodpatternswhichmaybeemployedatthispoint,operatingplantexperienceindi-catesthattheresultingMCPRvalueisinexcessofrequirementsbyaconsiderablemargin.Duringinitialstart-uptestingoftheplant,aMCPRevaluationwillbemadeat25KofRATEDTHERMALPOWERlevelwithminimumrecirculationpumpspeed.TheMCPRmarginwillthusbedemonstratedsuchthatfutureMCPRevaluationbelowthispowerlevelwillbeshowntobeunnecessary.ThedailyrequirementforcalculatingMCPRwhenTHERMALPOWERisgreaterthanorequalto25KofRATEDTHERMALPOWERissufficientsincepowerdistributionshiftsareveryslowwhentherehavenotbeensignificantpowerorcontrolrodchanges.TherequirementforcalculatingMCPRwithin12hoursafterthecompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWERensuresthermal'imitsaremetafterpowerdistributionshiftswhilestillallottingtimeforthepowerdistri-butiontostabilize.TherequirementforcalculatingMCPRafterinitiallydeterminingaLIMITINGCONTROLRODPATTERNexistsensuresMCPRwillbeknownfollowingachangeinTHERMALPOWERorpowershape,thatcouldplaceoperationexceedingathermalunit.3/4.2.4LINEARHEATGENERATIONRATEThisspecificationassuresthattheLinearHeatGenerationRate(LHGR)inanyrodislessthanthedesignlinearheatgenerationeveniffuelpelletdensificationispostulated.ThedailyrequirementforcalculatingLHGRwhenTHERMALPOWERisgreaterthanorequalto25KofRATEDTHERMALPOWERissuffi-.cientsincepowerdistributionshiftsareveryslowwhentherehavenotbeensignificantpowerorcontrolrodchanges.TherequirementtocalculateLHGRwithin12hoursafterthecompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWERensuresthermallimitsaremetafterpowerdistri-butionshiftswhilestillallottingtimeforthepowerdistributiontostabilize.TherequirementforcalculatingLHGRafterinitiallydeterminingaLIMITINGCONTROLRODPATTERNexistsensuresthatLHGRwillbeknownfollowingachangeinTHERMALPOWERorpowershapethatcouldplaceoperationexceedingathermallimit.
References:
1.GeneralElectricCompanyAnalyticalModelforLoss-of-CoolantAnalysisinAccordancewith10CFR50,AppendixK,NEDE-20566,November,3.975.2.R.B.Linford,AnalyticalMethodsofPlantTransientEvaluationsfortheGEBWR,NED0-10802,February1973.3.gualificationoftheOneDimensionalCoreTransientModelForBoilingWaterReactors,NED0-24154,October1978.4.TASCOl-AComputerProgramForTheTransientAnalysisofaSingleChannel,TechnicalDescription,NEDE"25149,January1980.NINEMILEPOINT-UNIT2B3/42-5BOY20jf4'5
3/4.3INSTRUMENTATIONBASESF~MF5ikPl!PBK'73/4.3.1REACTORPROTECTIONSYSTEMINSTRUMENTATIONThereactorprotectionsystemautomaticallyinitiatesareactorscramto:a.Preservetheintegrityofthefuelcladding.b.Preservetheintegrityofthereactorcoolantsystem.c.Minimizetheenergywhichmustbeadsorbedfollowingaloss-of-coolantaccident,andd.Preventinadvertentcriticality.-Thisspecificationprovidesthelimiiingconditionsforoperationnecessarytopreservetheabilityofthesystemtoperformitsintendedfunctionevenduringperiodswheninstrumentchannelsmaybeoutofservicebecauseofmain-tenance.Whennecessary,onechannelmaybemadeinoperableforbriefintervalstoconductrequiredsurveillance.Thereactorprotectionsystemismadeupoftwoindependenttripsystems.Thereareusuallyfourchannelstomonitoreachparameterwithtwochannelsineachtripsystem.Theoutputsofthechannelsinatripsystemarecombinedinalogicsothateitherchannelwilltripthattripsystem.Thetrippingofbothtripsystemswillproduceareactorscram.ThesystemmeetstheintentofIEEE-279fornuclearpowerplantprotectionsystems.ThebasesforthetripsettingsoftheRPSarediscussedinthebasesforSpecification2.2.1.Themeasurementofresponsetimeatthespecifiedfrequenciesprovidesassurancethattheprotectivefunctionsassociatedwitheachchannelarecom-pletedwithinthetimelimitassumedinthesafetyanalyses.Nocreditwastakenforthosechannelswithresponsetimesindicatedasnotapplicable.Responsetimemaybedemonstratedbyanyseriesofsequential,overlappingortotalchanneltestmeasurement,providedsuchtestsdemonstratethetotalchannelresponsetimeasdefined.Sensorresponsetimeverificationmaybedemonstratedby'either(1)inplace,onsiteoroffsitetestmeasurements,or(2)utilizingreplacementsensorswithcertifiedresponsetimes.NINEMILEPOINT-UNIT2B3/43-1Hov20)99'
INSTRUMENTATIONBASESpfggfgppjp'ij$'/pe/3/4.3.2ISOLATIONACTUATIONINSTRUMENTATIONThisspecificationensurestheeffectivenessoftheinstrumentationusedtomitigatetheconsequences-ofaccidentsbyprescribingtheOPERABILITYtripsetpointsandresponsetimesforisolationofthereactorsystems.Mhennecessary,onechannelmaybeinoperableforbriefintervalstoconductrequiredsurveillance.'omeofthetripsettingsmayhavetolerancesexplicitlystatedwhereboththehigh:,andlowvaluesarecriticalandmayhaveasubstantialeffectonsafety.Theset-pointsofotherinstrumentation,whereonlythehighorlowendofthesettinghaveadirectbearingonsafety,areestablishedatalevelawayfromthenormaloperatingrangetopreventinadvertentactuationofthesystemsinvolved.ExceptfortheMSIVs,thesafetyanalysisdoesnotaddressindividualsensorresponsetimesortheresponsetimesofthelogicsystemstowhichthesensorsareconnected.ForA.C.operatedvalves,itisassumedthattheA.C.powersupplyislostandisrestoredbystartupoftheemergencydieselgenerators.Inthisevent,atimeof13secondsisassumedbeforethevalvestartstomove.Inadditiontothepipebreak,thefailureoftheD.C.operatedvalveisassumed;thusthesignaldelay(sensorresponse)isconcurrentwiththe13seconddieselstartup.Thesafetyanalysisconsidersanallowableinventorylossineachcasewhichinturndeterminesthevalvespeedinconjunctionwiththe13seconddelay.Itfollowsthatcheckingthevalvespeedsandthe13secondtimeforemergencypowerestablishmentwillestablishtheresponsetimefortheisolationfunctions.However,toenhanceoverallsyst'mreliabil-ityandtomonitorinstrumentchannelresponsetimetrends,theisolationactuationinstrumentationresponsetimeshallbemeasuredandrecordedaspartoftheISOLATIONSYSTEMRESPONSETIME.OperationwithatripsetlessconservativethanitsTripSetpointbutwithinitsspecifiedAllowableValueisacceptableonthebasisthatthedifferencebetweeneachTripSetpointandtheAllowableValueisanallowanceforinstrumentdriftspecificallyallocatedforeachtripinthesafetyanalysis.TheTripSetpointandAllowableValuealsocontainadditionalmarginforinstrumentaccuracyandcalibrationcapability.3/4.3.3EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATIONTheemergencycorecoolingsystemactuationinstrumentationisprovidedtoinitiateactionstomitigatetheconsequencesofaccidentsthatarebeyondtheabilityoftheoperatortocontrol.ThisspecificationprovidestheOPERABILITYrequirements,tripsetpointsandresponsetimesthatwillensureeffectivenessofthesystemstoprovidethedesignprotection.Althoughtheinstrumentsarelistedbysystem,insomecasesthesameinstrumentmaybeusedtosendtheactuationsignaltomorethanonesystematthesametime.OperationwithatripsetlessconservativethanitsTripSetpointbutwithinitsspecifiedAllowableValueisacceptableonthebasisthatthedifferencebetweeneachTripSetpointandtheAllowableValueisanallowanceforinstrumentdriftspecificallyallocatedforeachtripinthesafetyanalysis.TheTripSetpointandAllowableValuealsocontainadditionalmarginforinstru-mentaccuracyandcalibrationcapability.NINEMILEPOINT-UNIT2B3/43"2ROY201985
INSTRUMENTATIONBASESpjjggjg)pJ'v~fpgy3/4.3.4RECIRCULATIONPUMPTRIPACTUATIONINSTRUMENTATIONTheanticipatedtransientwithoutscram(ATWS)recirculationpumptripsystemprovidesameansoflimitingtheconsequencesoftheunlikelyoccurrenceofafailuretoscramduringananticipatedtransient.TheresponseoftheplanttothispostulatedeventfallswithintheenvelopeofstudyeventsinGeneralElectricCompanyTopicalReportNED0-10349,datedMarch1971,NED0-24222,datedDecember1979,andSection15.8oftheFSAR.Theend-of"cyclerecirculationpumptrip(EOC-RPT)systemisapartoftheReactorProtectionSystemandisanessentialsafetysupplementtothereactortrip.ThepurposeoftheEOC-RPTistorecover.thelossofthermalmarginwhichoccursattheend-of-cycle.Thephysicalphenomenoninvolvedisthatthevoidreactivityfeedbackduetoapressurizationtransientcanaddpositivereactivitytothereactorsystematafasterratethanthecontrolrodsaddnegativescramreactivity.EachEOC-RPTsystemtripsbothrecirculationpumps,reducingcoolantflowinordertoreducethevoidcollapse-inthecoreduringtwoofthemostlimitingpressurizationevents.ThetwoeventsforwhichtheEOC-RPTprotectivefeaturewillfunctionareclosureoftheturbinestopvalvesandfastclosureoftheturbinecontro'lvalves.AfastclosuresensorfromeachoftwoturbinecontrolvalvesprovidesinputtotheEOC-RPTsystem;a'fastclosuresensorfromeachoftheothertwoturbinecontrolvalvesprovidesinputtothesecondEOC-RPTsystem.Similarly,apositionswitchforeachoftwoturbinestopvalvesprovidesinputtooneEOC-RPTsystem;apositionswitchfromeachoftheothertwostopvalvesprovidesinputtotheotherEOC-RPTsystem.foreachEOC-RPTsystem,thesensorrelaycontactsarearrangedtoforma2-out-of-2logicforthefastclosureofturbinecontrolvalvesanda2-out-of-2logicfortheturbinestopvalves.Theoperationofeitherlogicwill.actuatetheEOC-RPTsystemandtripbothrecirculationpumps.EachEOC-RPTsystemmaybemanuallybypassedbyuseofakeyswitchwhichisadministrativelycontrolled.ThemanualbypassesandtheautomaticOperatingBypassatlessthan30KofRATEDTHERMALPOWERareannunciatedinthecontrolroom.TheEOC-RPTsystemresponsetimeisthetimeassumedintheanalysisbetweeninitiationofvalvemotionandcompletesuppressionoftheelectricarc,i.e.,190ms.Includedinthistimeare:thetimefrominitialvalvemovementtoreachingthetripsetpoint,theresponsetimeofthesensor>theresponsetimeofthesystemlogicandthetimeallotedforbreakerarcsupression.OperationwithatripsetlessconservativethanitsTripSetpointbutwithinitsspecifiedAllowableValueisacceptableonthebasisthatthedifferencebetweeneachTripSetpointandtheAllowableValueisanallowanceforinstrumentdriftspecificallyallocatedforeachtripinthesafetyanalyses.TheTripSetpointandAllowableValuealsocontainadditionalmarginforinstrumentaccuracyandcalibrationcapability.NINEMILEPOINT-UNIT2B3/43-3NGV201985
INSTRUMENTATIONBASES3/4.3.5REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMENTATIONThereactorcoreisolationcoolingsystemactuationinstrumentationisprovidedtoinitiateactionstoassureadequatecorecoolingintheeventofreactorisolationfromitsprimaryheatsinkandthelossoffeedwaterflowtothereactorvessel.OperationwithatripsetlessconservativethanitsTripSetpointbutwithinitsspecifiedAllowableValueisacceptableonthebasisthatthedifferencebetweeneachTripSetpointandtheAllowableValueisanallowanceforinstrumentdriftspecificallyallocatedforeach'tripinthesafetyanalyses.TheTripSetpointandAllowableValuealsocontainadditionalmarginforinstrumentaccuracyandcalibrationcapability.I3/4.3.6';.CONTROLRODBLOCKINSTRUMENTATION'hecontrolrodblockfunctionsareprovidedconsistentwiththerequirementsofthespecificationsinSection3/4.1.4,ControlRodProgramControlsandSection3/4.2PowerDistributionLimits.Thetriplogicisarrangedsothatatripinanyoneoftheinputswillresultinacontrolrodblock.,OperationwithatripsetlessconservativethanitsTripSetpointbut'ithinitsspecifiedAllowableValueisacceptableonthebasisthatthedifferencebetweeneachTrip'SetpointandtheAllowableValueisanallowanceforinstrumentdriftspecificallyallocatedforeachtripinthesafetyanalyses.TheTripSetpointandAllowableValuealsocontainadditionalmarginforinstrumentaccuracyandcalibrationcapability.3/4.3.7MONITORINGINSTRUMEHTATION3/4.3.7.1RADIATIONMONITORINGINSTRUMENTATIOHTheOPERABILITYoftheradiationmonitoringinstrumentationensuresthat;(1)theradiationlevelsarecontinuallymeasuredintheareasservedbytheindividualchannels;(2)thealarmorautomaticactionisinitiatedwhentheradiationleveltripsetpointisexceeded;and(3)sufficientinformationisavailableonselectedplantparameterstomonitorandassessthesevariablesfollowinganaccident.Thiscapabilityisconsistentwith10CFRPart50,AppendixA,GeneralDesignCriteria19,41,60,61,63and64.,3.4.3.7.2SEISMICMONITORINGIHSTRUMEHTATION'heOPERABILITYoftheseismicmonitoringinstrumentationensuresthatsufficientcapabilityisavailabletopromptlydeterminethemagnitudeofaseismiceventandevaluatetheresponseofthosefeaturesimportanttosafety.Thiscapabilityisrequiredtopermitcomparisonofthemeasuredresponsetothatusedinthedesignbasisfortheunit.ThisinstrumentationisconsistentwiththerecommendationsofRegulatoryGuidel.12,"InstrumentationforEarthquakes,"April1974.NINEMILEPOIHT-UNIT2B3/43-4gOV201995
INSTRUMENTATIONBASESPfl'.lZ9QVBPiJ$gP!fMONITORINGINSTRUMENTATION(Continued)3/4.3.7.3METEOROLOGICALMONITORINGINSTRUMENTATIONTheOPERABILITYofthemeteorologicalmonitoringinstrumentationensuresthatsufficientmeteorologicaldataisavailableforestimatingpotentialradiationdosestothepublicasaresultofroutineoraccidentalreleaseofradioactivematerialstotheatmosphere.Thiscapabilityisrequiredtoevaluatetheneedforinitiatingprotectivemeasurestoprotectthehealthandsafetyofthepublic.ThisinstrumentationisconsistentwiththerecommendationsofRegulatoryGuide1.23"OnsiteMeteorologicalPrograms,"February1972.3/4.3.7.4REMOTESHUTDOWNMONITORINGINSTRUMENTATIONTheOPERABILITYoftheremoteshutdownmonitoringinstrumentationensuresthatsufficientcapabilityisavailabletopermitshutdownandmaintenanceofHOTSHUTDOWNof.theunitfromlocationsoutsideofthecontrolroom.Thiscapabil-.,ityisrequiredintheeventcontrolroomhabitabilityislostandisconsistentwithGeneralDesignCriteria19of10CFR50.'heOPERABILITY,oftheremoteshutdownsystemcontrolsensuresthatafirewillnotprecludeachievingsafeshutdown.Theremoteshutdownsysteminstru-mentation,controlsandpowercircuitsandtransferswitchesnecessarytoeliminateeffectsofafireandallowoperationofinstrumentation,controlandpowercircuitsrequiredtoachieveandmaintainasafeshutdownconditionareindependentofareaswhereafirecoulddamagesystemsnormallyusedtoshutdownthereactor.ThiscapabilityisconsistentwithGeneralDesignCriterion3ofAppendixRto10CFRPart50.3/4.3.7.5ACCIDENTMONITORINGINSTRUMENTATIONTheOPERABILITYoftheaccidentmonitoringinstrumentationensuresthatsufficientinformationisavailableonselectedplantparameterstomonitorandassessimportantvariablesfollowinganaccident.ThiscapabilityisconsistentwiththerecommendationsofRegulatoryGuide1.97,"InstrumentationforLightWaterCooledNuclearPowerPlantstoAssessPlantConditionsDuringandFollowinganAccident,"December1980andNUREG-0737,"ClarificationofTMIActionPlanRequirements,"November1980.3/4.3.7.6SOURCERANGEMONITORSThesourcerangemonitorsprovidetheoperatorwithinformationofthestatusoftheneutronlevelinthecoreatverylowpowerlevelsduringstartupandshutdown.Atthesepowerlevels,reactivityadditionsshallnotbemadewithoutthisfluxlevelinformationavailabletotheoperator.Whentheinter-mediaterangemonitorsareonscale,adequateinformationisavailablewithouttheSRMsandtheycanberetracted.NINEMILEPOINT-UNIT2B3/43-5ggV8~i~
INSTRUMENTATIONBASESi@Pidi"5jig~~)p8)fop/MONITORINGINSTRUMENTATION(Continued)3/4.3.7.7TRAVERSINGIN"COREPROBESYSTEMTheOPERABILITYofthetraversingin"coreprobesystemwiththespecifiedminimumcomplementofequipmentensuresthatthemeasurementsobtainedfromuseofthisequipmentaccuratelyrepresentthespatialneutronfluxdistributionofthereactorcore.TheTIPsystemOPERABILITYisdemonstratedbynormalizingallprobes(i.e.,detectors)priortoperforminganLPRMfunctioncalibration.MonitoringcorethermallimitsmayinvolveutilizingindividualdetectorstomonitorselectedareasofthereactorcorethusalldetectorsmaynotberequiredtobeOPERABLE.Theoperabilityofindividualdetectorstobeusedformonitoringisdemonstratedbycomparingthedetector(s)outputwithdataobtainedduringthepreviousLPRMcalibrations.3/4.3.7.8FIREDETECTIONINSTRUMENTATION'PERABILITYofthedetectioninstrumentationensuresthatbothadequatewarningcapabilityisavailable.forpromptdetectionoffiresandthatfiresuppressionsystems,thatareactuatedbyfiredetectors,willdischargeextin-guishingagentinatimelymanner.Promptdetectionandsuppressionoffireswillreducethepotentialfor.damagetosafety-relatedequipmentandisanintegralelementintheoverallfacilityfireprotectionprogram.Firedetectorsthatareusedtoactuatefiresuppressionsystemsrepresentamorecriticallyimportantcomponentofaplant'sfireprotectionprogramthandetectorsthatareinstalledsolelyforearlyfirewarningandnotification.Consequently,theminimumnumberofOPERABLEfiredetectorsmustbegreater.Thelossofdetectioncapabilityforfiresuppressionsystems,actuatedbyfiredetectors,representsasignificantdegradationoffireprotectionforanyarea.Asaresult,theestablishmentofafirewatchpatrolmustbeiniti"atedatanearlierstagethanwouldbewarrantedforthelossofdetectorsthatprovideonlyearlyfirewarning.TheestablishmentoffrequentfirepatrolsintheaffectedareasisrequiredtoprovidedetectioncapabilityuntiltheinoperableinstrumentationisrestoredtoOPERABILITY.3/4.3.7.9LOOSE-PARTDETECTIONSYSTEMTheOPERABILITYoftheloose-partdetectionsystemensuresthatsufficientcapabilityisavailabletodetectloosemetallicpartsintheprimarysystemand.avoidormitigatedamagetoprimarysystemcomponents.Theallowableout-of-servicetimesandsurveillancerequirementsareconsistentwiththerecommen-dationsofRegulatoryGuide1.133,"Loose-PartDetectionProgramforthePrimarySystemofLight-Mater-CooledReactors,"May1981.NINEMILEPOINT-UNIT2B3/43-6NOV4viw>>
INSTRUMENTATIONBASES+~Of'Vovgs)z~~<<vlct<"y~F:jMONITORINGINSTRUMENTATION(Continued)3/4.3.7.10RADIOACTIVELIUIDEFFLUENTMONITORINGINSTRUMENTATIONTheradioactiveliquideffluentinstrumentationisprovidedtomonitorandcontrol,asapplicable,thereleasesofradioactivematerialsinliquideffluentsduringactualorpotentialreleasesofliquideffluents.Thealarm/tripsetpointsfortheseinstrumentsshallbecalculatedandadjustedinaccordancewiththemethodologyandparametersintheODCMtoensurethatthealarm/tripwilloccurpriortoexceedingthelimitsof10CFRPart20.TheOPERABILITYanduseofthisinstrumentationisconsistentwiththerequirementsofGeneralDesignCriteria60,63and64ofAppendixAto10CFRPart50.ThepurposeoftanklevelindicatingdevicesistoassurethedetectionandcontrolofleaksthatifnotcontrolledcouldpotentiallyresultinthetransportofradioactivematerialstoUNRESTRICTEDAREAS.3/4.3.7..11RADIOACTIVEGASEOUSEFFLUENTMONITORINGINSTRUMENTATIONTheradioactivegaseouseffluentinstrumentationisprovidedtomonitorandcontrol,asapplicaule,thereleasesofradioactivematerialsingaseouseffluentsduringactualorpotentialreleasesofgaseouseffluents.Thealarm/tripsetpointsfortheseinstrumentsshallbecalculatedandadjustedinaccordancewiththemethodologyandparametersintheODCMtoensurethatthealarm/tripwilloccurpriortoexceedingthelimitsof10CFRPart20.Thisinstrumentationalsoincludesprovisionsformonitoringandcontrollingtheconcentrationsofpotentiallyexplosivegasmixturesintheoffgassystem.TheOPERABILITYanduseofthisinstrumentationisconsistentwiththerequire-mentsofGeneralDesignCriteria60,63and64ofAppendixAto10CFRPart50.3/4.3.8TURBINEOVERSPEEDPROTECTIONSYSTEMThisspecificationisprovidedtoensurethattheturbineoverspeedprotectionsysteminstrumentationandtheturbinespeedcontrolvalvesareOPERABLEandwillprotecttheturbinefromexcessiveoverspeed.Protectionfromturbineexcessiveoverspeedisrequiredsinceexcessiveoverspeedoftheturbinecouldgeneratepotentiallydamagingmissileswhichcouldimpactanddamagesafetyrelatedcomponents,equipmentorstructures.3/4.3.9PLANTSYSTEMSACTUATIONINSTRUMENTATIONTheplantsystemsactuationinstrumentationisprovided:1)toinitiateactionofthefeedwatersystem/mainturbinetripsystemintheeventoffeed-watercontrollerfailure,and2)toensuretheproperoperationoftheservicewatersystemduringnormalandaccidentconditions.NINEMILEPOINT-UNIT2B3/43"7
NINEMILEPT2900TWATERLEVELNOMENCLATURE800750700850745-VESSE~FLANGE648.0MAINSTEAMLINESCALERANGENO.IB)l7)I4)l3)I2)t1158356855954048995398.520293187,3178.315993108.817.8HEIGHTABOVEVESSELZERORR.IRRAOING.BOTTOMOFSEPARATORSKIRT51425500FEED493.WATER450585,7IB)583I7)568I4)559I3)540I2)4894CORE479~5SPRAY205+14IB)202;3RCIC89HPCSTRIPSI2l108.8INITIATERCICfaHPCS,TRIPRECIRCPUMPS.I7)18793HIALARMI4)17893LOALARMI3I159.3REACTORSCRAM400350I1)3989538097INSTZERO366930e5I1)17,8INITIATERHR.CS.STARTDIESEL.CONTRIBUTETOA.D.S.,ANDCLOSEMSIV'S300250200RECIRCOUTLET'72,5NOZZLE150ACTIVEFUEL2164RECIRC181INLETNOZZLEHIDERANGELEVELThisindicationiscoolanttemperaturesensitive.Thecalibrationisladeat'ratedconditions.Thelevelerrorat1'owpressures(temperaturesfisboundedbythesafetyanalysiswhichreflectstheweight-of-coolantabovethelowertapandnotindicatedlevel.50NOTE:DIMENSIONSININCHES'RELATIVETOVESSELBaserFigureB3/4.31.ReactorVesselN'ateri.evelNINENILEPOINT2B3/43.8NOV4VIGLOO i 3/4.4REACTORCOOLANTSYSTEMpgpl)g(jpppq~@pi~BASES3/4.4.1RECIRCULATIONSYSTEMOperationwithonereactorcorecoolantrecirculationloopinoperableisprohibiteduntilanevaluationoftheperformanceoftheECCSduringoneloopoperationhasbeenperformed,evaluatedanddeterminedtobeacceptable.TheobjectiveofGEBWRplantandfueldesignistoprovidestableoperationwithmarginoverthenormaloperatingdomain.However,atthehighpower/lowflowcorneroftheoperatingdomain,asmallprobabilityoflimitcycleneutronfluxoscillationsexistsdependingoncombinationsofoperatingconditions(e.g.,rodpattern,powershape).Toprovideassurancethatneutronfluxlimitcycleoscillationsaredetectedandsuppressed,APRMandLPRMneutronfluxnoiselevelsshouldbemonitoredwhileoperatinginthisregion.StabilitytestsatoperatingBWRswerereviewedtodetermineagenericregionofthepower/flowmapinwhichsurveillanceofneutronfluxnoiselevelsshouldbeperformed.Aconservativedecayratioof0.6waschosenasthebasesfordeterminingthegenericregionforsurveillancetoaccountfortheplanttoplantvariabilityofdecayratiowithcoreandfueldesigns.Thisgenericregionhasbeendeterminedtocorrespondtoacoreflowoflessthanorequalto45KofratedcoreflowandaTHERMALPOWERgreaterthanthatspecifiedinFigure3.4.1.1"l.Plantspecificcalculationscanbeperformedtodetermineanapplicableregionformonitoringneutronfluxnoiselevels.Inthiscasethedegreeofconservatismcanbereducesinceplanttoplantvariabilitywouldbeeliminated.Inthiscase,adequatemarginwillbeassuredbymonitoringtheregionwhichhasadecayratiogreaterthanorequalto0.8..Neutronfluxnoiselimitsarealsoestablishedtoensureearlydetectionoflimitcycleneutronfluxoscillations.BWRcorestypicallyoperatewithneutronfluxnoisecausedbyrandomboilingandflownoise.Typicalneutronfluxnoiselevelsof1-12ofratedpower(peak-to-peak)havebeenreportedfortherangeoflowtohighrecirculationloopflowduringbothsingleanddualrecirculationloopoperation.Neutronfluxnoiselevelswhichsignifi-cantlyboundthesevaluesareconsideredinthethermal/mechanicaldesignofGEBWRfuelandarefoundtobeofnegligibleconsequence.Inaddition,sta"bilitytestsatoperatingBWRshavedemonstratedthatwhenstabi'1ityrelatedneutronfluxlimitcycleosci'Ilationsoccurtheyresultinpeak-to-peakneutronfluxlimitcyclesof5-10timesthetypicalvalues.Therefore,actionstakentoreduceneutronfluxnoiselevelsexceedingthree(3)timesthetypicalvaluearesufficienttoensureearlydetectionoflimitcycleneutronfluxoscillations.Typically,neutronfluxnoiselevelsshowagradualincreaseinabsolutemagnitudeascoreflowisincreased(constantcontrolrodpattern)withtworeactorrecirculationloopsinoperation.Therefore,thebaselineneutronNINEMILEPOINT-UNIT2B3/44-1NQy201985
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEMFpigJFg.)(+p~p$JywyBASES3/4.4.1RECIRCULATIONSYSTEM(Continued)fluxnoiselevelobtainedataspecifiedcoreflowcanbeappliedover'arangeofcoreflows.Tomaintainareasonablevariationbetweenthelowflowandhighflowendoftheflowrange,therangeoverwhichaspecificbaselineisappliedshouldnotexceed20Kofratedcoreflowwithtworecirculationloopsinoperation.Datafromtestsandoperatingplantsindicatethatarangeof20Kofratedcoreflowwillresultinapproximatelya50Kincreaseinneutronfluxnoiselevelduringoperationwithtworecirculationloops.Baselinedatashouldbetakennearthemaximumrodlineatwhichthemajorityofoperationwilloccur;However,baselinedatatakenatlowerrodlines(i.e.,lowerpowerwillresultinaconservativevaluesincetheneutronfluxnoiselevelisproportionaltothepowerlevelatagivencoreflow.Aninoperablejetpumpisnot,initself,asufficientreasontodeclare.,arecirculationloopinoperable,butitdges,incaseofadesign-basis-accident,.increasetheblowdownareaandreducethecapabilityofrefloodingthecore;thus,therequirementforshutdownofthefacilitywithajetpump,inoperable.Jet'pumpfailurecanbedetectedbymonitoringjetpumpperformanceonaprescribedscheduleforsignificantdegradation.Recirculationloopflowmismatchlimitsareincompliancewithth'eECCSLOCAanalysisdesigncriteria.Thelimitswillensureanadequatecore'flow.coastdownfromeitherrecirculationloopfollowingaLOCA.Inordertopreventunduestressonthevesselnozzlesandbottomheadregion,therecirculationlooptemperaturesshallbewithin50'Fofeachotherpriortostartupofanidleloop.Thelooptemperaturemustalsobewithin504Fofthereactorpressurevesselcoolanttemperaturetopreventthermalshocktotherecirculationpumpandrecirculationnozzles.Sincethecoolant.inthebottomofthevesselisatalowertemperaturethanthecoolantintheupperregionsofthecore,unduestressonthevesselwouldresultifthetemperaturedifferencewasgreaterthan145F.3/4.4.2SAFETY/RELIEFVALVESThesafety/reliefvalvesoperateduringapostulatedATWSeventtopreventthereactorcoolantsystembeingpressurizedaboveadesignallowablevalueof1375psiginaccordancewiththeASMECode.Atotalof17OPERABLEsafety/reliefvalvesisrequiredtolimitlocalpressureatactivecomponentstowithinASMEIIIallowabledesignvalues(ServiceLevelA).AllotherappropriateASMEIIIlimitsarealsoboundedbythisrequirement.Demonstrationofthesafety-reliefvalveliftsettingswilloccuronlyduringshutdownandwillbeperformedinaccordancewiththeprovisionsofSpecification4.0.5.NINEMILEPOINT"UNIT2B3/44-2NQV201985
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEMBASES~%~~pgfRHig<<SpF",gpeggyt4'g+ygQi'gg3/4.4.3.1.LEAKAGEDETECTIONSYSTEMSTheRCSleakagedetectionsystemsrequiredbythisspecificationareprovidedtomonitoranddetectleakagefromthereactorcoolantpressureboundary.ThesedetectionsystemsareconsistentwiththerecommendationsofRegulatoryGuide1.45,"ReactorCoolantPressureBoundaryLeakageDetectionSystems",May1973.3/4.4.3.2OPERATIONALLEAKAGETheallowableleakageratesfromthereactorcoolantsystemhavebeenbasedonthepredictedandexperimental'lyobservedbehaviorofcracksinpipes.Thenormallyexpectedbackgroundleakageduetoequipmentdesignandthedetectioncapabilityoftheinstrumentationfordeterminingsystemleakagewasalsoeon-'.sidered.Theevidenceobtainedfromexperimentssuggeststhatforleakage'omewhatgreaterthanthatspecifiedforQNIDENTIFIEDLEAKAGEthe.probabilityissma'11thattheimperfectionor,crackassociatedwithsuchleakagewouldgrowrapidly.However,inallcases,iftheleakageratesexceedthevaluesspecifiedortheleakageislocatedandknowntobePRESSUREBOUNDARYLEAKAGE,thereactorwillbeshutdowntoallowfurtherinvestigationandcorrectiveaction.TheSurveillanceRequirementsforRCSpressureisolationvalvesprovideaddedassuranceofvalveintegritytherebyreducingtheprobabilityofgrossvalvefailureandconsequentintersystemLOCA.3/4.4.4CHEMISTRYThewaterchemistrylimitsofthereactorcoolantsystemareestablishedtopreventdamagetothereactormaterialsincontactwiththecoolant.Chloridelimitsarespecifiedtopreventstresscorrosioncrackingofthestainlesssteel.Theeffectofchlorideisnotasgreatwhentheoxygenconcentrationinthecoolantislow,thusthe0.2ppmlimitonchloridesispermittedduringPOWEROPERATION.Duringshutdownandrefuelingoperations,thetemperaturenecessaryforstresscorrosiontooccurisnotpresentsoa0.5ppmconcentrationofchloridesisnotconsideredharmfulduringtheseperiods.Conductivitymeasurementsarerequiredonacontinuousbasissincechangesinthisparameterareanindicationofabnormalconditions.Whentheconductivityiswithinlimits,thepH,chloridesandotherimpuritiesaffectingconductivitymustalsobewithintheiracceptablelimits.Withtheconductivitymeterinoperable,additionalsamplesmustbeanalyzedtoensurethatthechloridesarenotexceedingthelimits.Thesurveillancerequirementsprovideadequateassurancethatconcentrationsinexcessofthelimitswillbedetectedinsufficienttimetotakecorrectiveaction.NINEMILEPOINT-UNIT283/44-3/gal4uia60
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEMBASESP<85$gpjJp!/gs.;,~!J3/4.4.5SPECIFICACTIVITYThelimitationsonthespecificactivityoftheprimarycoolantensurethatthe2hourthyroidandwholebodydosesresultingfromamainsteamlinefailureoutsidethecontainmentduringsteadystateoperationwillnotexceedsmallfractionsofthedoseguidelinesof10CFR100.ThevaluesforthelimitsonspecificactivityrepresentinterimlimitsbaseduponaparametricevaluationbytheNRCoftypicalsitelocations.Thesevaluesareconservativeinthatspecificsiteparameters,suchassiteboundarylocationandmeteorologicalconditions,werenotconsideredinthisevaluation.TheACTIONstatementpermittingPOWEROPERATIONtocontinueforlimitedtimeperiodswiththeprimarycoolantsspecificactivitygreaterthan0.2microcuriespergramDOSEEQUIVALENTI-131,butlessthanorequalto4.0micro-curiespergramDOSEE(UIVALENTI-131,.accommodatespossibleiodinespiking.RhhfhyIIIIEhIIITHERRELPER.I-1bulestnorequato.0crocriespergrDOSEQUIALEI-1muberesicdtonomretan80horspr-yar,pprimalypecenoftheunisyarlyopertingim,sinethsectivtyevelinceasethehouthoiddoseattesiebndarbyfatorftofolowigostlatstam1ner'tur.Terortgoculaveerangmeove50hosianymoncseciveerdwhreattn0mio-cieserramOSEgUIVLENI-1wiaowffcietifoCoissionaluioofec'umsncsprrrechint80holit.Informationobtainedoniodinespikingwillbeusedtoassesstheparametersassociatedwithspikingphenomena.Areductioninfrequencyofisotopicanal-ysisfollowingpowerchangesmaybepermissibleifjustifiedbythedataobtained.Closingthemainsteamlineisolationvalveslimitsthereleaseofactivitytotheenvironsshouldasteamlineruptureoccuroutsidecontainment.Thesurveillancerequirementsprovideadequateassurancethatexcessivespecificactivitylevelsinthereactorcoolantwillbedetectedinsufficienttimetotakecorrectiveaction.3/4.4.6PRESSURE/TEMPERATURELIMITSAllcomponentsinthereactorcoolantsystemaredesignedtowithstandtheeffectsofcyclicloadsduetosystemtemperatureandpressurechanges.Thesecyclicloadsareintroducedbynormalloadtransients,reactortrips,and.startupandshutdownoperations.ThevariouscategoriesofloadcyclesusedfordesignpurposesareprovidedinSection3.9ottheFSAR.Duringstartupandshutdown,theratesoftemperatureandpressurechangesarelimitedsothatthemaximumspecifiedheatupandcooldownratesareconsistentwiththedesignassumptionsandsatisfythestresslimitsforcyclicoperation.NINEMILEPOINT-UNIT2B3/44"4NOV201%5
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEMBASESPRESSURE/TEMPERATURELIMITS(Continued)r"('.g'-(I64Vrig.fh~g(~spAAQm4h4at)4yTheoperatinglimitcurvesofFigures3.4.6.1-1,3.4.6.1-2and3.4.6.1-3arederivedfromthefracturetoughnessrequirementsof10CFR50AppendixGandASMECodeSectionIII,AppendixG.ThecurvesarebasedontheRTNDandstressintensityfactorinformationforthereactorvesse1components.FracturetoughnesslimitsandthebasisforcompliancearemorefullydiscussedinFSARChapter5,Paragraph5.3.1.5,"FractureToughness."7mb~ThereactorvesselmaterialshavebeentestedtodeterminetheirinitialRTNZTheresultsofthesetestsareshownin~ere.B3/4.4.6-1.Reactoroplutionandresu1tantfastneutron,Egreaterthan1Mey,irradiationwi11causeanincreaseintheRT~>>.Therefore,anadjustedreferencetemperature,baseduponthe,fluence,phosphoruscontentandcoppercontentofthematerialinquestion,canbepredictedusingBasesFigureB3/4.4.6-1andtherecommenda-tionsofRegulatoryGuide1.99,Revision$,"EffectsofResidualElementsonPredictedRadiationDamag'etoReactorVesselMaterials.""TheactualshiftinRTofthevesselmaterialwillbeestablished.NATSP(mCffetasggpIddIlydIgpIbyIg1IIg,dddd~installedneartheinsidew,ofthereactorvesselinthecoreareasincetheneutronspectraatthe.andvesselinsideradiusareessentiallyidentical.TheirradiatedŽcanbeusedwithconfidenceinpredict-ingreactorvesselmaterialtransitiontemperatureshift.TheoperatinglimitcurvesofFigure3.4.6.1-1,3.4.6.1-2and3.4.6.1-3shallbeadjusted,asrequired,onthebasisoft;heecimendptaandrecommendationsofRpgujatoryGuidey.99,Revisiopl.Qa+A,ebys~iyod~e~+l~t,wowsŽ~lA'ttM<Y~wLT.~%58+0O~Ort.~4m~t.ueaCE'mPWiPufegg+9,4-f.Thepressure-temperaturelimitlinesshowninFigures3.4.6.1-3and3.4.6.3.-1,curvesCandAforreactorcriticalityandforinserviceleakandhydrostatictestinghavebeenprovidedtoassurecompliancewiththeminimumtemperaturerequirementsofAppendixGto10CFRPart50forreactorcriticalityandforinserviceleakandhydrostatictesting.ThenumberofrectorvesselirradiationsurveillancecapsulesandthefrequenciesforremovingandtestingthespecimensinthesecapsulesareprovidedinTable4.4.6.1.3-1toassurecompliancewiththerequirementsofAppendixHto10CFRPart50.3/4.4.7MAINSTEAMLINEISOLATIONVALVESDoubleisolationvalvesareprovidedoneachofthemainsteamlinestominimizethepotentialleakagepathsfromthecontainmentincaseofalinebreak.Onlyonevalveineachlineisrequiredtomaintaintheintegrityofthecontainment,however,singlefailureconsiderationsrequirethattwovalvesbeOPERABLE.Thesurveillancerequirementsarebasedontheoperatinghistoryofthistypevalve.ThemaximumclosuretimehasbeenselectedtoNINEMILEPOINT"UNIT2B3/44-5NOV201985
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEM~licJajjggulp/pgpiBASES3/4.4.7MAINSTEAMLINEISOLATIONVALVES(Continued)containfissionproductsandtoensurethecoreisnotuncoveredfollowinglinebreaks.Theminimumclosuretimeisconsistentwiththeassumptionsinthesafetyanalysestopreventpressuresurges.3/4.4.8STRUCTURALINTEGRITYTheinspectionprogramsforASMECodeClass1,2and3componentsensurethatthestructuralintegrityofthesecomponentswillbemaintainedatanacceptablelevelthroughoutthelifeoftheplant.Componentsof'hereactorcoolantsystemweredesignedtoprovideaccesstopermitinserviceinspectionsinaccordancewithSectionXIoftheASMEBoilerandPressureVesselCode1980Edition.andAddendathroughM80.TheinserviceinspectionprogramforASMECodeClass1,2and3componentswillbeperformedinaccordancewithSectionXIoftheASMEBoilerandPressureVesselCodeandapplicableaddendaasrequiredby10CFRPart50.55a(g)exceptwherespecificwrittenreliefhasbeengrantedbytheNRCpursuantto10CFRPart50.55a(g)(6)(i).3/4.4.9RESIDUALHEATREMOVALAsingleshutdowncoolingmodeloopprovidessufficientheatremovalcapabilityforremovingcoredecayheatandmixingtoassureaccuratetempera-tureindication,however,singlefailureconsiderationsrequirethattwoloopsbeOPERABLEorthatalternatemethodscapableofdecayheatremovalbedemonstratedandthatanalternatemethodofcoolantmixingbeinoperation.NINEMILEPOINT"UNIT2B3/44"6NOY801S85
l.iCI.~1.241.00.8a0(QJ<g0.4g0.2a0.0010ZOSD40SERYICELIFE~TEARS~FIGURE83/44.6-1FASTNEQTRONFLQENCE(E>lNev)AT1/4TASAFUNCTIONOFSERVICELIFE*At9XofRATEDTHERMALPOSERandSO%avaflab)lkty.NINEMILE'OINT-UNIT2B3/44-7HOVSo1985
3/4.5EMERGENCYCORECOOLINGSYSTEMBASES3/4.5.1and3/4.5.2ECCS-OPERATINGandSHUTDOWNECCSDivisionIconsistsofthelowpressurecorespraysystemandlowpressurecoolantinjectionsubsystem"A"oftheRHRsystemandtheautomaticdepressurizationsystem(ADS)asactuatedbyADStripsystem"A".ECCSdivision2consistsoflowpressurecoolantinjectionsubsystems"B"and"C"oftheRHRsystemandtheautomaticdepressurizationsystemasactuatedbyADStripsystem"B".Thelowpressurecorespray(LPCS)systemisprovidedtoassurethatthecoreis.adequatelycooledfollowingaloss-of"coolantaccidentandprovidesadequatecorecoolingcapacityforallbreaksizesuptoandincludingthedouble-endedreactorrecirculationlinebreak,andforsmallerbreaksfollowingdepressurizationbytheADS.TheLPCSisaprimarysourceofemergencycorecoo1ingafterthereactorvesselisdepressurizedandasourcefor'floodingofthecoreincaseofaccidentaldraining.ThesurveillancerequirementsprovideadequateassurancethattheLPCSsystemwil.lbeOPERABLEwhenrequired.Althoughallactivecomponentsaretestableand-fullflowcanbedemonstratedbyrecirculationthroughatestloopduringreactoroperation,acompletefunctionaltestrequiresreactorshutdown.Thepumpdischargepipingismaintainedfulltopreventwaterhammerdamagetopiping.Thelowpressurecoolantinjection(LPCI)modeoftheRHRsystemisprovidedtoassurethatthecoreisadequatelycooledfollowingaloss-of-coolantaccident.Threesubsystems,eachwithonepump,provideadequatecorefloodingforallbreaksizesuptoandincludingthedouble-endedreactor.recirculationlinebreak,andforsmallbreaksfollowingdepressurizationbytheADS.ThesurveillancerequirementsprovideadequateassurancethattheLPCIsystemwil&beOPERABLEwhenrequired.Althoughallactivecomponentsaretestableandfullflowcanbedemonstratedbyrecirculationthroughatestloopduringreactoroperation,acompletefunctionaltestrequiresreactorshutdown.Thepumpdischargepipingismaintainedfulltopreventwaterhammerdamagetopiping.ECCSDivisionIIIconsistsofthehighpressurecorespraysystem.Thehighpressurecorespray(HPCS)systemisprovidedtoassurethatthereactorcoreisadequatelycooledtolimitfuelcladtemperatureintheeventofasmallbreakinthereactorcoolantsystemandlossofcoolantwhichdoesnotresultinrapiddepressurizationofthereactorvessel.TheHPCSsystempermitsthereactortobeshutdowhwhilemaintainingsufficientreactorvesselwaterlevelinventoryuntilthevesselisdepressurized.TheHPCSsystemoperatesoverarangeof1160psid,differentialpressurebetweenreactorvesselandHPCSsuctionsource,to0psid.NINEMILEPOINT-UNIT2B3/45"1gQV8~l935
EMERGENCYCORECOOLINGSYSTEMBASESECCS-OPERATINGandSHUTDOMN(Continued)Thecapacityofthesystemisselectedtoprovidetherequiredcorecooling.TheHPCSpumpisdesignedtodelivergreaterthanorequalto516/1550/6350gpmatdifferentialpressuresof1160/1130/200psi.Initially,waterfrom'thecondensatestoragetankisusedinsteadofinjectingwaterfromthesuppressionpoolintothereactor,butnocreditistakeninthesafetyanalysesforthecondensatestoragetankwater.MiththeHPCSsysteminoperable,adequatecorecoolingisassuredbytheOPERABILITYoftheredundantanddiversifiedautomaticdepressurizationsystemandboththeLPCSandLPCIsystems.Inaddition,thereactorcoreisolationcooling(RCIC)system,asystemforwhichnocreditistakeninthesafetyanalysis,willautomaticallyprovidemakeupatreactoroperatingpressuresonareactorlowwaterlevelcondition.TheHPCSout-of-serviceperiodofL4daysisbasedonthedemonstratedOPERABILITYofredundantanddiversifiedlowpressurecorecoolingsystems.Thesurveillancerequirements.provideadequateassurancethattheHPCSsystemwillbeOPERABLEwhenrequired.Althoughallactivecomponentsaretestableandfullflowcanbedemonstratedbyrecirculationthroughatestloopduringreactoroperation,acompletefunctionaltestwithreactorvesselinjectionrequiresreactorshutdown.Thepumpdischargepipingismaintainedfu11topreventwaterhammerdamage.UponfailureoftheHPCSsystemtofunctionproperlyafterasmallbreakloss-of-coolantaccident,theautomaticdepressurizationsystem(ADS)automa-ticallycausesselectedsafety-reliefvalvestoopen,depressurizingthereactorsothatflowfromthelowpressurecorecoolingsystemscanenterthecoreintimetolimitfuelcladdingtemperaturetolessthan2200F.ADSisconserva-tivelyrequiredtobeOPERABLEwheneverreactorvesselpressureexceeds100psig.ThispressureissubstantiallybelowthatforwhichthelowpressurecorecoolingsystemscanprovideadequatecorecoolingforeventsrequiringADS.ADSautomaticallycontrolssevenselectedsafety-reliefvalvesalthoughthesafetyanalysisonlytakescreditforsixvalves.Itisthereforeappro-priatetopermitonevalvetobeout-of-serviceforupto14dayswithoutmateriallyreducingsystemreliability.3/4.5.3SUPPRESSIONPOOLThesuppressionpoolisrequiredtobeOPERABLEaspartoftheECCStoensurethatasufficientsupplyofwaterisavailabletotheHPCS,LPCSandLPCIsystemsintheeventofaLOCA.Thislimitonsuppressionpoolminimumwatervolumeensuresthatsufficientwaterisavailabletopermitrecirculationcoolingflowtothecore.TheOPERABILITYofthesuppressionpoolinOPERA-TIONALCONDITIONS1,2or3isrequiredbySpecification3.6.2.1.NINEMILEPOINT-UNIT2B3/45-2iVOV201'98S
EMERGENCYCORECOOLINGSYSTEMBASESFjiggig,fpp>l.l[g~ySUPPRESSIONPOOI(Continued)'epairworkmightrequiremakingthesuppressionpoolinoperab1e.Thisspecificationwillpermitthoserepairstobemadeandatthesametimegiveassurancethattheirradiatedfuelhasanadequatecoolingwatersupplywhenthesuppressionpoolmustbemadeinoperable,includingdraining,inOPERATIONALCONDITION4or5.'nOPERATIONALCONDITION4and5thesuppressionpoolminimumrequiredwatervolumeisequaltothatrequiredforOPERATIONALCONDITIONS1,2and3becauseinallcasestheminimumwatervolumeisbasedonNPSH,recirculationvolumeandvortexpreventioninaccordancewithNUREG0869(April1983,issuedForComment).NINEMILEPOINT-UNIT2B3/45-3gOy<01985
3/4.6CONTAINMENTSYSTEMSi%".pj's,9lj~>p'pi]/pe'l(BASES3/4.6.1PRIMARYCONTAINMENT3/4.6.1.1PRIMARYCONTAINMENTINTEGRITYPRIMARYCONTAINMENTINTEGRITYensuresthatthereleaseofradioactivemate-rialsfromthecontainmentatmospherewillberestrictedtothoseleakagepathsandassociatedleakratesassumedintheaccidentanalyses.Thisrestriction,inconjunctionwiththeleakageratelimitation,willlimitthesiteboundaryradiationdosestowithinthelimitsofGeneralDesignCriteria19and10CFRPart100duringaccidentconditions.3/4.6.1.2PRIMARYCONTAINMENTLEAKAGE,~IThelimitationsonprimarycontainmentleakageratesensurethatthetotalcontainmentleakagevolumewillnotexceedthevalueassumedintheaccidentanalysesatthepeakaccidentpressureof39.75psig,Pa.Asanaddedconserva"tism,themeasuredoverallintegratedleakagerateisfurtherlimitedtoless.thanorequalto0.75Laduringperformanceoftheperiodicteststoaccountf'rpossibledegradationofthe-containmentleakagebarriersbetweenleakagetests.Operatingexperiencewiththemainsteamlineisolationvalveshasindicatedthatdegradationhasoccasionallyoccurredintheleaktightnessofthevalves;thereforethespecialrequirementfortestingthesevalves./Thesurveillancetestingformeasuring'leakageratesisconsistentwiththerequirementsofAppendix"J"of10CFRPart50withtheexceptionofexemp-tionsgrantedformainsteamisolationvalveleaktestingandtestingtheair1ocksaftereachopening.Theleakageratesspecifiedforthemainsteamlineisolationvalves,the'ainsteamdrainlineisolationvalves,andthepost-accidentsamplingsystemgassampleandreturnlineblockvalvesareusedtoquantifythemaximumamountofprimarycontainmentatmospherethatcouldbypasssecondarycontainmentandleakdirectlytotheenvironmentafteradesignbasisloss-of"coolantaccident.Thisdataisusedtodeterminetheradiologicalconsequencesofthisaccidentandensurethattheresu)tantdosesarewithinthelimitsoftheGeneralDesignCriteria19and10CFR100.3/4.6.1.3PRIMARYCONTAINMENTAIRLOCKSThelimitationsonclosureandleakratefortheprimarycontainmentairlocksarerequiredtomeettherestrictionsonPRIMARYCONTAINMENTINTEGRITYandtheprimarycontainmentleakagerategiveninSpecifications3.6.1.1and3.6.1.2.Thespecificationmakesallowancesforthefactthattheremaybelongperiodsoftimewhentheairlockswillbeinaclosedandsecuredposi-tionduringreactoroperation.Onlyonecloseddoorineachairlockisrequired'tomaintaintheintegrityofthecontainment.NINEMILEPOINT-UNIT2B3/46"1
CONTAINMENTSYSTEMSBASESpgpFp)gyve>ppv~s~3/4.6.1.5PRIMARYCONTAINMENTSTRUCTURALINTEGRITYThislimitationensuresthatthestructuralintegrityofthecontainmentwillbemaintainedcomparabletotheoriginaldesignstandardsforthelifeoftheunit.Structuralintegrityisrequiredtoensurethatthecontainmentwillwithstandthedesignpressureof45psigintheeventofaLOCA.AvisualinspectioninconjunctionwithTypeAleakagetestsissufficienttodemon-stratethiscapability.3/4.6.1.6ORYWELLANDSUPPRESSIONCHAMBERINTERNALPRESSUREThelimitationsondrywellandsuppressionchamberinternalpressureensurethatthecontainmentpeakpressureof39.75psigdoesnotexceedthedesignpressureof45.0psigduringLOCAconditionsorthattheexternalpres-suredifferentialdoesnotexceedthedesignmaximumexternalpressuredifferentialof4.7psi.Thelimitof14.2to15.4psiaforinitialpositivecontainmentpressurewilllimitthetotalpressureto39.75psigwhichislessthanthedesignpressureandisconsistentwiththesafetyanalysis.3/4.6.1.7ORYMELLAVERAGEAIRTEMPERATUREThelimitationondrywellaverageairtemperatureensuresthatthecontainmentpeakairtemperaturedoesnotexceedthedesigntemperatureof340'Fduringsteamlinebreakconditionsandisconsistentwiththesafetyanalysis.Inaddition,themaximumdrywellaverageairtemperatureisalsothelimitinginitialconditionusedtodeterminethemaximumnegativedifferentialpressureactingonthedrywel1andsuppressionchamberfo'llowinginadvertentactuationofthecontainmentsprays..3/4.6.1.8PRIMARYCONTAINMENTPURGESYSTEM)~sSO-<e14inchand12inchdrywellandsuppressionchamberpurgesupndexhaustsonvalves2CPS"AOV-105,2CPS"AOV"107,2CPS"AOV"12CPS"AOV-111arerdtobesealedclosedduringplerationsincethesevalveshavenotbeendemonscapableofcduringaLOCA.Maintainingthesevalvessealedclosedduringplaationsensuresthatexcessivequan-titiesofradioactivematerials~notberedviathepurgesystem.Toprovideassurancethattvalvescannotbeinadveropened,theyaresealedclosedinrdancewithStandardReviewPlan6.2.4,includesmechanicacestosealorlockthevalveclosedorpreventpowereingsedtothevalveoperator.Theuseofthedrywellandsuppressionchamberpurgelinesisrestric~totheinchpurgesupplyandexhaustisolationvalves2GBS"N$-106,2CPS"AOV-108,2CPS"nd2CPS"AOV-104since,un'likee-cherva'Ives,thesevalveswillcloseduringrsteameakaccidentandthereforethesiteboundarydoseguidelinesof~1G00wouldnotbeexceededintheeventofanaccidentdugoingoperations.signofthepurgesupplyandexhaussonvalvesmeetstherequirementsoaa.hTechnica1Positi-4,"ContainmentPurgingOuringNormalPlantOperations.NINEMILEPOINT-UNIT2B3/46"2NOVS01S85
INSERT"A"(placeonB3/46-2)The14inchdrywelland12inchsuppressionchambersupplyandexhaustvalvesopenlimitof90hoursper365daysduringpurgeorventoperationinconditions1,2and3meettherequirementofBranchTechnicalPositionCSB6-4forvalvesgreaterthan8inchesindiameter.Therequirementtolimittheopeningof2CPS+AOV105and2CPS+AOV110to70degrees,and2CPS+AOVlllto60degreesensurethesevalveswillcloseduringaLOCAorsteamlinebreakaccident,andtherefore,thesiteboundarydoseguidelinesof10CFR100wouldnotbeexceededintheeventofanaccidentduringpurgingorventingoperations.
CONTAINMENTSYSTEMSBASESPRIMARYCONTAINMENTPURGESYSTEM(Continued)Leakageintegritytestswithamaximumallowableleakagerateforpurgesupplyandexhaustisolationvalveswillprovideearlyindicationofresilientmaterialsealdegradationandwillallowtheopportunityforrepairbeforegrossleakagefailuredevelops.Theleakagelimitshallnotbeexceededwhentheleakageratesaredeterminedtobe<4.38scf/hper14inchvalveand3.75scf/hper12inchvalvewherepressurizedto40.0psig.3/4.6.2.OEPRESSURIZATIONSYSTEMSThespecificationsofthissectionensurethattheprimarycontainmentpressurewillnotexceedthedesignpressureof45psigduringprimarysystemblowdownfromfulloperatingpressure.Thesuppressionpoolwaterprovidestheheatsinkforthereactorcoolantsystemenergyreleasefollowingapostulatedruptureofthesystem.Thesuppres"sionpoolwatervolumemustabsorbtheassociateddecayandstructuralsensibleheatreleasedduringreactorcoolantsystemblowdownfrom1040psig.Sinceallofthegasesinthedrywellarepurgedintothesuppressionpoolairspaceduringalossofcoolantaccident,thepressureoftheliquidmustnotexceed45psig,thesuppressionchambermaximumpressure.Thedesignvolumeofthesuppressionchamber,waterandair,wasobtainedbyconsideringthat.thetotalvolumeofreactorcoolantisdischargedtothesuppressionchamberandthatthedrywellvolumeispurgedtothesuppressionchamber.Usingtheminimumormaximumwatervolumesgiveninthisspecification,containmentpressureduringthedesignbasisaccidentisapproximately40psigwhichisbelowthedesignpressureof45psig.Maximumwatervolumeof154,794ft~resultsinadowncomersubmergenceofll'-0"andtheminimumvolumeof145,495ft~resultsinasubmergenceapproximately18inchesless.ThemajorityoftheBodegatestswererunwithasubmergedlengthoffourfeetandwithcompletecondensation.Thus,withrespecttothedowncomersubmergence,thisspecificationisadequate.Themaximumtemperatureattheendoftheblow-downtestedduringtheHumboldtBayandBodegaBaytestswas170'Fandthisis.conservativelytakentobethelimitforcompletecondensationofthereactorcoolant,althoughcondensationwouldoccurfortemperaturesabove1704F.Shoulditbenecessarytomakethesuppressionchamberinoperable,thisshallonly'bedoneasspecifiedinSpecification3.5.3.Underfullpoweroperatingconditions,blowdowntothesuppressionpoolattheinitialwatertemperatureof90'Fresultsinawatertemperatureofapproximately140'Fimmediatelyfollowingblowdownwhichisbelowthe200'FusedforcompletecondensationviaT-quencherdevices.Atthistemperatureandatmosphericpressure,theavailableNPSHexceedsthatrequiredbyboththeRHRandcorespraypumps,thusthereisnodependencyoncontainmentoverpressureduringtheaccidentinjectionphase.IfbothRHRloopsareusedforcontainmentcooling,thereisnodependencyoncontainmentoverpressureforpost-LOCAoperations.NINEMILEPOINT"UNIT2B3/46"3
CONTAINMENTSYSTEMSBASESfivdf"'].'viK,'J$4Ui'fQEPRESSURIZATIONSYSTEMS(Continued)Experimentaldataindicatesthatexcessivesteamcondensingloadscanbeavoidedifthepeakbulktemperatureofthesuppressionpoolismaintainedbelow2004FduringanyperiodofreliefvalveoperationwithsonicconditionsatthedischargeexitforT-quencherdevices.Specificationshavebeenplacedontheenvelopeofreactoroperatingconditionssothatthereactorcanbedepres-surizedinatimelymannertoavoidtheregimeofpotentiallyhighsuppressionchamberloadings.Becauseofthelargevolumeandthermalcapacityofthesuppressionpool,the'volumeandtemperaturenormallychangesveryslowlyandmonitoringtheseparametersdailyissufficienttoestablishanytemperaturetrends.Byrequiringthesuppressionpooltemperaturetobefrequentlyrecordedduringperiodsofsignificantheataddition,thetemperaturetrendswillbecloselyfollowedsothatappropriateactioncanbetaken.Inadditiontothelimitsontemperureofthesuppressionchamberpoolwater,operatingproceduresdefinetheactiontobetakenintheeventasafety"reliefvalve.inadvertentlyopensorsticksopen.Asaminimumthisactionshallinclude:(I)useofallavailablemeanstoclosethevalve,(2)initiatesuppres-sionpoolwatercooling,(3)initiatereactorshutdown,and(4)ifothersafety-reliefvalvesareusedtodepressurizethereactor,theirdischargeshallbeseparatedfromthatofthestuck-opensafetyreliefvalvetoassuremixinganduniformityofenergyinsertiontothepool.3/4.6.3PRIMARYCONTAINMENTISOLATIONVALVESTheOPERABILITYoftheprimarycontainmentisolationvalvesensuresthatthecontainmentatmospherewillbeisolatedfromtheoutsideenvironmentintheeventofareleaseofradioactivematerialtothecontainmentatmosphereorpressurizationofthecontainmentandisconsistentwiththerequirementsofGQC54through57ofAppendixAto10CFR50.ContainmentisolationwithinthetimelimitsspecifiedensuresforthoseisolationvalvesdesignedtocloseautomaticallythatthereleaseofradioactivematerialtotheenvironmentwillbeconsistentwiththeassumptionsusedintheanalysesforaLOCA.3/4.6.4SUPPRESSIONCHAMBER"DRYMELLVACUUMBREAKERSVacuumreliefbreakersareprovidedtoequalizethepressurebetweenthesuppressionchamberanddrywell.Thissystemwillmaintainthestructuralintegrityoftheprimarycontainmentunderconditionsoflargedifferentialpressures..Thevacuumbreakersbetweenthesuppressionchamberandthedrywellmustnotbeinoperableintheopenpositionsincethiswouldallowbypassingofthesuppressionpoolincaseofanaccident.Therearefourpairsofvalvestoprovideredundancysothatoperationmaycontinueforupto72hourswithnomorethanonepairofvacuumbreakersinoperableintheclosedposition.NINEMILEPOINT"UNIT2B3/46"4>>nu%0885
CONTAINMENTSYSTEMSPg~f~>~"~>~BASES3/4.6.5SECONDARYCONTAINMENTSecondarycontainmentisdesignedtominimizeanygroundleve'ireleaseofradioactivematerialwhichmayresultfromanaccident.TheReactorBuildingandassociatedstructuresprovidesecondarycontainmentduringnormaloperationwhenthedrywellissealedandinservice.Atothertimesthedrywellmaybeopenand,whenrequired,secondarycontainmentintegrityisspecified.Establishingandmaintainingasub-atmosphericconditioninthereactorbuildingwiththestandbygastreatmentsystemonceper18months,alongwiththesurveillanceofthedoors,hatches,dampersandvalves,isadequatetoensurethattherearenoviolationsoftheintegrityofthesecondarycontainment.TheOPERABILITYofthestandbygastreatmentsystemsensuresthatsuffi-cientiodineremovalcapabilitywillbeavailableintheeventofaLOCA.Thereductionincontainmentiodineinventory-reducestheresultingsiteboundaryradiationdosesassociatedwithcontainmentleakage.TheoperationofthissystemandresultantiodineremovalcapacityareconsistentwiththeassumptionsusedintheLOCAanalyses.Continuousoperationofthesystemwiththeheatersoperatingfor10hoursduringeach31dayperiodissufficienttoreducethebuildupofmoistureontheadsorbersandHEPAfilters.3/4.6.6PRIMARYCONTAINMENTATMOSPHERECONTROLTheOPERABILITYofthesystemsrequiredforthedetectionandcontrolofhydrogengasensuresthatthesesystemswillbeavailabletomaintainthehydrogenconcentrationwithintheprimarycontainmentbelowitsflammab1elimitduringpost-LOCAconditions.Thedrywellandsuppressionchamberhydrogenrecombinersystemiscapableofcontrollingtheexpectedhydrogenandoxygengenerationassociatedwith(1)zirconium-waterreactions,(2)radiolyticdecom-.positionofwaterand(3)corrosionofmetalswithincontainment.ThehydrogencontrolsystemisconsistentwiththerecommendationsofRegulatoryGuide1.7,"ControlofCombustibleGasConcentrationsinContainmentFollowingaLOCA,"March1971.NINEMILEPOINT-UNIT2B3/46-5g0g20l985
3/4.7PLANTSYSTEMSBASES3/4.7.1PLANTSERVICEMATERSYSTEMSTheOPERABILITYoftheservicewatersystemsensuresthatsufficientcoolingcapacityisavailableforcontinuedoperationofsafety-relatedequipmentduringnormalandaccidentconditions.Theredundantcoolingcapacityofthesesystems,assumingasinglefailure,isconsistentwiththeassumptionsusedintheaccidentconditionswithinacceptablelimits.TheIntakeDeicingheaterspecificationistoensureadequatewaterisavailabletotheservicewatersystem.Inordertoprovethatthesystemissupplyingadequateheattothebarracks,aportableammetershallbeusedtocheckthefullloadcurrentoftheheaters.Thecurrentshouldbecheckedonaweeklybasis.Currentshallbemeasuredforeachphaseateachofthefourmotorcontrolcenterlocations.Ifamajordeviationfromratedcurrentisdetected,furtherinvestigationisrequiredtodetermineifanopencircuitexistsintheindividualheatercircuits.The10monthcheckofcircuitmeggarreadingswillcheckagainstlongtermdegradationofcircuitinsulations,3/4:7.2REVETMENTDITCHSTRUCTUREPROTECTIONThepurposeoftherevetmentditchstructureistoprotecttheplantfillandfoundationfromwaveerosion,expectedduringtheprobablemaximumwindstormfora'maximumstillwaterelevationof254feet.Category1structuresarethedesignedtowithstandtheimpactofwaves.Solongasthefillisinplace,wavescannotimpactCategory1structuresbecauseofthelackofsufficientdepthofwatertosustainsuchwaves.Therevetmentditchstructurecansustainahighdegreeofdamageandstillperformitsfunction,protectingthesitefillfromerosion.Thus-the.operabilityconditionforoperationoftherevetmentditchstructurehasbeen'rittentoensurethatseveredamagetothestructurewillnotgoundetectedforasubstantialperiodoftimeandtoprovideforpromptcorrectiveactionandNRCnotification.3/4.7.3CONTROLROOMEMERGENCYOUTDOORAIRSPECIALFILTERTRAINSYSTEMTheOPERABILITYofthecontrolroomemergencyoutdoorairspecialfiltertrainsystemensuresthat1)theambientairtemperaturedoesnotexceedtheallowabletemperatureforcontinuousdutyratingfortheequipmentandinstru-mentationcooledbythissystemand2)thecontrolroomwillremainhabitableforoperationspersonnelduringandfollowingalldesignbasisaccidentcondi-tions.ContinuousoperationofthesystemwiththeheatersOPERABLEfor10hoursduringeach31-dayperiodissufficienttoreducethebuildupofmoistureontheadsorbersandHEPAfilters.TheOPERABILITYofthissysteminconjunctionwithcontrolroomdesignprovisionsisbasedonlimitingtheradiationexposuretopersonneloccupyingthecontrolroomto5remor1'esswholebody,oritsequivalent.Thislimitationisconsistentwiththerequire-mentsofGeneralDesignCriteria19ofAppendix"A",10CFRPart50.NINEMILEPOINT"UNIT2B3/47-1vnuontoad
588k08AOM~-Lv/E'2J.IN~INIpd31IH3NINrtCXlE545,000E545,500C2l44C7IDr~rCr05%5%gp00E546,000STA8+00T7+00C/lPlt/latTlDDDD<<<<XHK2~CVDVlQlrtettQfllgllIVlO~~CUQlDlVrtrtC/lrl'L<<O~$OKODCDtQO~OO~9CJQltQthtQ~thDl<<cV.VlCLO%CKCQvrtatbH'l<<tbtQO5&%tQgBCCVDtthtQDJVletO'OththDVl~C'NWtu'OOOOXIE546,500E547,000+0C7rtO.g~<stCC<~t<iC~LEa'v.Qr~~iQ0UlD
PlC:ELEVATIONVARIESCLDITCHlO'-O"5'-0"gACLEVETMENT4'-6"O14'57'07"GROUNDSUDESIGNTOPOFREVETMENT-263'-0"TOPOFROCKUL31ULlMEANLAKELEVELEL246D-0'ELEGENDFAFrontArmor,DoubleLayerof4900lbDolidsUnitsULIFirstUnderlayer,2000to5000lbStoneUnitsUL2SecondUnderlayer.75to250lbStoneUnitsUL3ThirdUnderlayer,2.3to15lbStoneUnitsIBABackArmor,SingleLayerof10,000to16,000lbStoneArmorUnitsA,B,CSurveyPointsFIGUREB3/47.8;2TYPICALSECTION-REVETMENTDITCHSTRUCTURE,INSERVICEINSPECTIONSTATIONLOCATION~~~Ip~l~lySlglgi"EjL~Jstag(IM04aQ
PLANTSYSTEMSBASES3/4.7.4REACTORCOREISOLATIONCOOLINGSYSTEMThereactorcoreisolationcooling(RCIC)systemisprovidedtoassureadequatecorecoolingintheeventofreactorisolationfromitsprimaryheatsinkandthelossoffeedwaterflowtothereactorvesselwithoutrequiringactuationofanyoftheEmergencyCoreCoolingSystemequipment.TheRCICsystemisconservativelyrequiredtobeOPERABLEwheneverreactorpressureexceeds150psig.ThispressureissubstantiallybelowthatforwhichtheRCICsystemcanprovideadequatecorecoolingforeventsrequiringtheRCICsystem.TheRCICsystemspecificationsareapplicableduringOPERATIONALCONDITIONS1,2and3whenreactorvesselpressureexceeds150psigbecauseRCICistheprimarynon-ECCSsourceofemergencycorecoolingwhenthereactorispressurized.WiththeRCICsysteminoperable,adequatecorecoolingisassuredbytheOPERABILITYoftheHPCSsystemandjustifiesthespecified14-dayout-of-serviceperiod.ThesurveillancerequirementsprovideadequateassurancethatRCICwillbeOPERABLEwhenrequired.Althoughallactivecomponentsaretestableandfullflowcanbedemonstratedbyrecirculationduringreactoroperation,acompletefunctionaltestrequiresreactorshutdown.Thepumpdischargepipingismaintainedfulltopreventwaterhammer,damage.3/4.7.5SNUBBERSAllsnubbersarerequiredOPERABLEtoensurethatthestructuralintegrityofthereactorcoolantsystemandallothersafetyrelatedsystemsismaintainedduringandfollowingaseismicorothereventinitiatingdynamicloads.Snubbersexcludedfromthisinspectionprogramarethoseinstalledonnonsafetyrelatedsystemsandthenonlyiftheirfailureorfailureofthesystemonwhichtheyareinstalledwouldhavenoadverseeffectonanysafetyrelatedsystem.Thevisualinspectionfrequencyisbaseduponmaintainingaconstantlevelofsnubberprotectiontosystems.Therefore,therequiredinspectionintervalvariesinverselywiththeobservedsnubberfailuresandisdeterminedbythenumberofinoperablesnubbersfoundduringaninspection.Inspectionsperformedbeforethatintervalhaselapsedmaybeusedasanewreferencepointtodeterminethenextinspection.However,theresultsofsuchearlyinspectionsperformedbeforetheoriginalrequiredtimeintervalhaselapsed,nominaltimeless25K,maynotbeusedtolengthentherequiredinspectioninterval.Anyinspectionwhoseresultsrequireashorterinspectionintervalwilloverridethepreviousschedule.Whenthecauseoftherejectionofasnubberisclearlyestablishedandremediedforthatsnubberandforanyothersnubbersthatmaybegenericallysusceptible,andverifiedbyinservicefunctionaltesting,thatsnubbermaybeNINEMILEPOINT-UNIT2B3/47"4NOV30]9B5
PLANTSYSTEMSBASESC~MIfi,g<Ilil~g<~DppPL!~p~~~~ISNUBBERS(Continued)exemptedfrombeingcountedasinoperable.Genericallysusceptiblesnubbersarethosesnubberswhichareofaspecificmakeormodelandhavethesamedesignfeaturesdirectlyrelatedtorejectionofthesnubberbyvisualinspectionoraresimilarlylocatedorexposedtothesameenvironmentalconditions,suchastemperature,radiation,andvibration.Whenasnubberisfoundinoperable,anengineeringevaluationisperformed,inadditiontothedeterminationofthesnubbermodeoffailure,inordertodetermineifanysafety-relatedcomponentorsystemhasbeenadverslyaffectedbytheinoperabilityofthesnubber.Theengineeringevaluationshalldeterminewhetherornotthesnubbermodeoffailurehasimpartedasignificanteffectordegradationonthesupportedcomponentorsystem.Toprovidefurtherassuranceofsnubberreliability,arepresentativesampleoftheinstalledsnubberswillbefunctiona'llytestedduringplantshutdownsat18-monthintepvals.Selectionofarepresentativesampleaccordingtotheexpres-sion35(1+-)providesaconfidencelevelofapproximately95Kthat90Kto100Ãofthesnubb'ebsintheplantwillbeOPERABLEwithinacceptancelimits.Observedfailuresofthesesamplesnubberswillrequirefunctionaltestingof'dditionalunits.Theservicelifeofasnubberisevaluatedviamanufacturerinputandinformationthroughconsiderationofthesnubberserviceconditionsandasso-ciatedinstallationandmaintenancerecords,i.e.,newlyinstalledsnubber,sealreplaced,springreplaced,inhighradiationarea,inhightemperaturearea,etc.Therequirementtomonitorthesnubberservicelifeisincludedtoensurethatthesnubbersperiodicallyundergoaperformanceevaluationinviewoftheirageandoperatingconditions.Theserecordswillprovidestatisticalbasesforfutureconsiderationofsnubberservicelife.Therequirementsforhemaintenanceofrecordsandthesnubberservicelifereviewarenotintendedtoaffectplantoperation.3/4.7.6SEALEDSOURCECONTAMINATIONThelimitationsonremovablecontaminationforsourcesrequiringleaktesting,includingalphaemitters,isbasedon10CFR70.39(c)limitsforplutonium.Thislimitationwillensurethatleakagefrombyproduct,source,andspecialnuclearmaterialsourceswillnotexceedallowableintakevalues.Sealedsourcesareclassifiedintothreegroupsaccordingtotheiruse,withsurveillancerequirementscommensuratewiththeprobabilityofdamagetoasourceinthatgroup.Thosesourceswhicharefrequentlyhandledarerequiredtobetestedmoreoftenthanthosewhicharenot.Sealedsourceswhicharecontinuouslyenclosedwithinashieldedmechanism,i.e.,sealedsourceswithinradiationmonitoringdevices,areconsideredtobestoredandneednotbetestedunlesstheyareremovedfromtheshieldedmechanism.NINEMILEPOINT-UNIT2B3/47-5gay201'85
PLANTSYSTEMSBASESi'N>Xi[g,)j~p<<pAp'/FIRESUPPRESSIONSYSTEMS(Continued)3/47.7FIRESUPPRESSIONSYSTEMSTheOPERABILITYofthefiresuppressionsystemsensuresthatadequatefiresuppressioncapabilityisavailabletoconfineandextinguishfiresoccurringinanyportionofthefacilitywheresafetyrelatedequipmentislocated.Thefiresuppressionsystemconsistsofthewatersystem,sprayand/orsprinklersystems,C02systems,Halonsystemsandfirehosestations.Thecollectivecapabilityofthefiresuppressionsystemsisadequatetominimizepotentialdamagetosafetyrelatedequipmentandisamajorelementinthefacilityfireprotectionprogram.Intheeventthatportionsofthefiresuppressionsystemsareinoperable,alternatebackupfirefighting'quipmentisrequiredtobemadeavailableintheaffectedareasuntiltheinoperableequipmentisrestoredtoservice.Whentheinoperablefirefightingequipmentisintendedforuseasabackupmeansoffiresuppression,alongerperiodoftimeisallowedtoprovideanalternatemeansoffirefightingthaniftheinoperableequipmentistheprimarymeansoffiresuppression.ThesurveillancerequirementsprovideassurancesthattheminimumOPERABILITYrequirementsofthefiresuppressionsystemsaremet.AnallowanceismadeforensuringasufficientvolumeofHaloninthe'Halonstoragetanksbyverifyingtheweightorlevelandpressureofthetanks.LevelmeasurementsaremadebyeitheraU.L.orF.M.approvedmethod.Intheeventthefiresuppressionwatersystembecomesinoperable,immediatecorrectivemeasuresmustbetakensincethissystemprovidesthemajorfiresuppressioncapabilityof'theplant.3/4.7.8FIRERATEOASSEMBLIESTheOPERABILITYofthefirebarriersandbarrierpenetrationsensurethatfiredamagewillbelimited.Thesedesignfeaturesminimizethepossibilityofasinglefireinvolvingmorethanonefireareapriortodetectionandextinguish-ment.Thefirebarriers,firebarrierpenetrationsforconduits,cabletraysandpiping,firedampers,andfiredoorsareperiodicallyinspectedtoverifytheirOPERABILITY.3/4.7.9MAINTURBINEBYPASSSYSTEMThemainturbinebypasssystemisrequiredtobeOPERABLEconsistentwiththeassumptionsofthefeedwatercontrollerfailureanalysisofFSARChapter15.NINEMILEPOINT-UNIT2B3/47-6HOV80198.'
3/4.8ELECTRICALPOWERSYSTEMSPftjf'f~5.R"IprnQh~y~g~~ygypBASES3/4.8.13/4.8.2and3/4.8.3A.C.SOURCESD.C.SOURCESandONSITEPOWER0STRIBUIONSYSTEMSTheOPERABILITYoftheA.C.andO.C.powersourcesandassociateddistributionsystemsduringoperationensuresthatsufficientpowerwillbeavailabletosupplythesafetyrelatedequipmentrequiredfor(1)thesafeshutdownofthefacilityand(2)themitigationandcontrolofaccidentconditionswithinthefacility.TheminimumspecifiedindependentandredundantA.C.andD.C.powersourcesanddistributionsystemssatisfytherequirementsofGeneralDesignCriteria17ofAppendix"A"to10CFR50.TheACTIONrequirementsspecifiedforthelevelsofdegradationofthepowersourcesproviderestrictionuponcontinuedfacilityoperationcommensuratewiththelevelofdegradation.TheOPERABILITYofthepowersourcesconsistentwiththeinitialconditionassumptionsofthesafetyanalysesandarebased'ponmaintainingatleastDivisionIorHoftheonsiteA.C.andD.C.powersourcesandassociateddistributionsystemsOPERABLEduringaccidentconditions'oincidentwithanassumedlossofoffsitepowerandsinglefailureoftheotheronsiteA.C.orD.C.source.DivisionIIIsuppliesthehighpressurecorespray(HPCS)systemonly.TheA.C.andD.C.sourceallowableout-of-servicetimesarebasedonRegulatoryGuide1.93,"AvailabilityofElectricalPowerSources",December1974.WhendieselgeneratorEDG-1(DIVI)orEDG-3(DIVII)isinoperable,thereisanadditionalACTIONrequirementtoverifythatallrequiredsystems,subsystems,trains,componentsanddevices,thatdependontheremainingOPERABLEdieselgeneratorEDG-1(DIVI)orEDG-3(DIVII)asasourceofemergencypower,arealsoOPERABLE.ThisrequirementisintendedtoprovideassurancethatalossofoffsitepowereventwillnotresultinacompletelossofsafetyfunctionofcriticalsystemsduringtheperioddieselgeneratorEDG-1(DIVI)orEDG-3.(DIVII)isinoperable.Thetermverifyasusedinthiscontextmeanstoadministrativelycheckbyexamininglogsorotherinformationtodetermineifcertaincomponentsareout-of-serviceformaintenanceorotherreasons.ItdoesnotmeantoperformthesurveillancerequirementsneededtodemonstratetheOPERABILITYofthecomponent.TheOPERABILITYoftheminimumspecifiedA.C.andD.C.powersourcesandassociateddistributionsystemsduringshutdownandrefuelingensuresthat(1)thefacilitycanbemaintainedintheshutdownorrefuelingconditionforextendedtimeperiodsand(2)sufficientinstrumentationandcontrolcapabilityisavailableformonitoringandmaintainingtheunitstatus.ThesurveillancerequirementsfordemonstratingtheOPERABILITYofthedieselgeneratorsareinaccordancewiththerecommendationsofRegulatoryGuide1.9,"SelectionofDieselGeneratorSetCapacityforStandbyPowerSupp1ies",December1979,RegulatoryGuide1.108,"PeriodicTestingofDieselGenerator'Units.UsedasOnsiteElectricPowerSystemsatNuclearPowerPlants",Revision1,August1977andRegulatoryGuide1.137"Fuel-OilSystemsforStandbyDieselGenerators",Revision1,October1979.NINEMILEPOINT"UNIT2B3/48"1NhV0A1'.
ELECTRICALPOWERSYSTEMSBASESA.C.SOURCESO.C.SOURCESandONSITEPOWEROISTRIBUTIONSYSTEMS(Continued)ThesurveillancerequirementsfordemonstratingtheOPERABILITYoftheunitbatteriesareinaccordancewiththerecommendationsofRegulatoryGuidel.129,"MaintenanceTestingandReplacementofLargeLeadStorageBatteriesforNuclearPowerPlants,"February1978,andIEEEStd450-1980,"IEEERecommendedPracticeforMaintenance,Testing,andReplacementofLargeLeadStorageBatteriesforGeneratingStationsandSubstations."Verifyingaverageelectrolytetemperatureabovetheminimumforwhichthebatterywassized,totalbatteryterminalvoltageonfloatcharge,connectionresistancevaluesandtheperformanceofbatteryserviceanddischargetestsensurestheeffectivenessofthechargingsystem,theabilitytohandlehighdischargeratesandcomparesthebatterycapacityatthattimewiththeratedcapacity.\Table4.8.2.1-1specifiesthenormallimitsforeachdesignatedpilot'ellandeachconnectedcellforelectrolytelevel,floatvoltageandspecificgravity.Thelimitsforthedesignatedpilotcellsfloatvoltageandspecificgravity,greaterthan2.13voltsand.015belowthemanufacturer'sfullchargespecificgravityorabatterychargercurrentthathadstabilizedatalowvalue,ischaracteristicofachargedcellwithadequatecapacity.Thenormallimitsforeachconnectedcellforfloatvoltageandspecificgravity,greaterthan2.13voltsandnotmorethan.020belowthemanufacturer'sfullcharge'pecificgravitywithanaveragespecificgravityofalltheconnectedcellsnotmorethan.010belowthemanufacturer'sfullchargespecificgravity,ensurestheOPERABILITYandcapabilityofthebattery.Operationwithabatterycell'sparameteroutsidethenormallimitbutwithintheallowablevaluespecifiedinTable4.8.2.l-lispermittedforupto7days.Ouringthis7dayperiod:(1)theallowablevaluesforelectrolytelevelensuresnophysicaldamagetotheplateswithanadequateelectrontransfercapability;(2)theallowablevaluefortheaveragespecificgravityofallthecells,notmorethan.020belowthemanufacturer'srecommendedfullchargespecificgravityensuresthatthedecreaseinratingwillbelessthanthesafetymarginprovidedinsizing;(3)theallowablevalueforanindividualcell'sspecificgravity,ensuresthatanindividualcell'sspecificgravitywillnotbemorethan.040belowthemanufacturer'sfullchargespecificgravityandthattheoverallcapabilityofthebatterywillbemaintainedwithinanacceptablelimit;and(4)theallowablevalueforanindividualcell'sfloatvoltage,greaterthan2.07volts,ensuresthebattery'scapabilitytoperformitsdesignfunction.NINEMILEPOINT-UNIT2B3/48-2HOVSOBSE
ELECTRICALPOWERSYSTEMSBASES3/4.8.4ELECTRICALEUIPMENTPROTECTIVEDEVICESPrimarycontainmentelectricalpenetrationsandpenetrationconductorsareprotectedbyeitherde-energizingcircuitsnotrequiredduringreactoroperationordemonstratingtheOPERABILITYofprimaryandbackupovercurrentprotectioncircuitbreakersbyperiodicsurveillance.Thesurveillancerequirementsapplicabletolowervoltagecircuitbreakersandfusesprovidesassuranceofbreakerandfusereliabilitybytestingat.leastonerepresentativesampleofeachmanufacturersbrandofcircuitbreakerand/orfuse.Eachmanufacturer'smoldedcaseandmetalcasecircuitbreakersand/orfusesaregroupedintorepresentativesampleswhicharethantestedonarotatingbasistoensurethatallbreakersand/orfusesaretested.If.awidevarietyexistswithinanymanufacturer'sbrandofcircuitbreakersand/orfuses,itisnecessarytodividethatmanufacturersbreakersand/orfusesintogroupsandtreateachgroupasaseparatetypeofbreakerorfusesforsurveil-lancepurposes..Theemergencylightingsystemovercurrentprotectivedevicesensurethatafailureof.thenon-Class1Eportionofthecircuitwillnoteffecttheoper-ationoftheremainingportionsoftheClasslEcircuitsthatarenecessaryforsafeshutdown.TheEPAsprovideClass1EisolationcapabilitiesfortheRPSpowersuppliesandtheScrampowersupplies.ThisisrequiredbecausethepowersuppliesarenotClass1Epowersupplies.NINEMILEPOINT"UNIT2B3/48-3
3/4.9REFUELINGOPERATIONSBASES3/4.9.1REACTORMODESMITCHLockingtheOPERABLEreactormodeswitchintheShutdownorRefuelposition,asspecified,ensuresthattherestrictionsoncontrolrodwithdrawalandrefuelingplatformmovementduringtherefuelingoperationsareproperlyactivated.Theseconditionsreinforcetherefuelingproceduresandreducetheprobabilityofinadvertentcriticality,damagetoreactorinternalsorfuelassemblies,andexposureofpersonneltoexcessiveradioactivity.3/4.9.2INSTRUMENTATIONTheOPERABILITYofatleasttwosourcerangemonitorsensuresthatredundantmonitoringcapabilityisavailabletodetectchangesinthereactivityconditionofthecore.3/4.9.3CONTROLRODPOSITION)Therequirementthatallcontrol'odsbeinsertedduringotherCOREALTERATIONSensuresthatfuelwillnotbeloadedintoacellwithoutacontrolrod,3/4.9.4DECAYTIMETheminimumrequirementforreactorsubcriticalitypriortofuelmovementensuresthatsufficienttimehaselapsedtoallowtheradioactivedecayofthe.shortlivedfissionproducts.Thisdecaytimeisconsistentwiththeassump-tionsusedintheaccidentanalyses.3/4.9.5COMMUNICATIONSTherequirementforcommunicationscapabilityensuresthatrefuelingstationpersonnelcanbepromptlyinformedofsignificantchangesinthefacilitystatusorcorereactivityconditionduringmovementoffuelwithinthereactorpressurevessel.3/4.9.6REFUELINGPLATFORMTheOPERABILITYrequirementsensurethat(1)therefuelingplatformwillbeusedforhandlingcontrolrodsandfuelassemblieswithinthereactorpressurevessel,(2)eachcraneandhoisthassufficientloadcapacityforhandlingfuelassembliesandcontrolrods,and(3)thecoreinternalsandpressurevesselareprotectedfromexcessiveliftingforceintheeventtheyareinadvertentlyengagedduringliftingoperations.NINEMILEPOINT"UNIT2B3/49-1NOY201985
REFUELINGOPERATIONSBASESVp@(pal)p<)p~p(3/4.9.7CRANETRAVEL-SPENTFUELSTORAGEPOOLTherestrictiononmovementofloadsinexcessofthenominalweightofafuelassemblyoverotherfuelassembliesinthestoragepoolensuresthatintheeventthisloadisdropped1)theactivityreleasewillbelimitedtothatcon-tainedinasinglefuelassembly,and2)anypossibledistortionoffuelinthestoragerackswillnotresultinacriticalarray.Thisassumptionisconsistentwiththeactivityreleaseassumedinthesafetyanalyses.3/4.9.8and3/4.9.9WATERLEVEL-REACTORVESSELandWATERLEVEL-SPENTFUELSTORAGEPOOLTherestrictionsdnminimumwaterlevelensurethatsufficientwaterdepthisavailabletoremove99KoftheassumedlOXiodinegapactivityreleasedfromtheruptureofanirradiatedfuelassembly.Thisminimumwaterdepthisconsistentwiththeassumptionsoftheaccidentanalysis.13/4.9.10CONTROLRODREMOVALThesespecificationsensurethatmaintenanceorrepairofcontrolrodsorcontrolroddriveswillbeperformedundercovditionsthatlimittheprobabilityofinadvertentcriticality.TherequirementsforsimultaneousremovalofmorethanonecontrolrodaremorestringentsincetheSHUTDOWNMARGINspecificationprovidesforthecoretoremainsubcriticalwithonlyonecontrolrodfullywighdrawn.3/4.9.11RESIDUALHEATREMOVALANDCOOLANTCIRCULATIONTherequirementthatatleastoneresidualheatremovalloopbeOPERABLEorthatanalternatemethodcapableofdecayheatremovalbedemonstratedandthatanalternatemethodofcoolantmixingbeinoperationensuresthat(1)sufficientcoolingcapacityisavailabletoremovedecayheatandmaintaiqthewaterinthereactorpressurevesselbelow140'FasrequiredduringREFUELING,and(2)sufficientcoolantcirculationwouldbeavailablethroughthereactorcoretoassureaccuratetemperatureindicationandtodistributeandpreventstratificationofthepoisonintheeventitbecomesnecessarytoactuatethestandbyliquidcontrolsystem.TherequirementtohavetwoshutdowncoolingmodeloopsOPERABLEwhenthereislessthan(22'-3")ofwaterabovethereactorvesselflangeensuresthatasinglefailureoftheoperatingloopwillnotresultinacompletelossofresidualheatremovalcapability.Withthereactorvesselheadremovedand(22'-3")ofwaterabovethereactorvesselflange,alargeheatsinkisavail-ableforcorecooling.Thus,intheeventafailureoftheoperatingRHRloop,adequatetimeisprovidedtoinitiatealternatemethodscapableofdecayheatremovaloremergencyprocedurestocoolthecore.NINEMILEPOINT-UNIT2B3/49-2
34.10SPECIALTESTEXCEPTIONSiljjijf$wr,R4BASES3/4.10.1PRIMARYCONTAINMENTINTEGRITYTherequirementforPRIMARYCONTAINMENTINTEGRITYisnotapplicableduringtheperiodwhenopenvesseltestsarebeingperformedduringthelowpowerPHYSICSTESTS.IKTKMInordertoperformthetestsrequiredinthetechnicalspecificationsitisnecessarytobypassthesequencerestraintsoncontrolrodmovement.Theadditionalsurveillancerequirmentsensurethatthespecificationsonheatgenerationratesandshutdownmarginrequirementsarenotexceededduringtheperiodwhenthesetestsarebeingperformedandthatindividualrodworthsdonotexceedthevaluesassumedinthesafetyanalysis.34.10.3SHUTDOWNMARGINOEMONSTRATIONSPerformanceofshutdownmargindemonstrationswiththevesselheadremovedrequiresadditionalrestrictionsinordertoensurethatcriticalitydoesnotoccur.TheseadditionalrestrictionsarespecifiedinthisLCO.34.10.4RECIRCULATIONLOOPSThisspecialtestexceptionpermitsreactorcriticalityundernoflowconditionsandisrequiredtoperformcertainstartupandPHYSICSTESTSwhileatlowTHERMALPOWERlevels.34.10.5OXYGENCONCENTRATIONRelieffromtheoxygenconcentrationspecificationsisnecessaryinordertoprovideaccesstotheprimarycontainmentduringtheinitialstartupandtestingphaseofoperation.Withoutthisaccessthestartupandtestprogramcouldberestrictedanddelayed.34.10.6TRAININGSTARTUPSThisspecialtestexceptionpermitstrainingstartupstobeperformedwiththereactorvesseldepressurizedatlowTHERMALPOWERandtemperaturewhilecontrollingRCStemperaturewithoneRHRsubsystemalignedintheshutdowncoolingmodeinordertominimizecontaminatedwaterdischargetotheradioactivewastedisposalsystem.NINEMILEPOINT-UNIT2B3/410"1NOV201985
3/4.11RADIOACTIVEEFFLUENTSBASES3/4.11.1LIUIDEFFLUENTS3/4.11.1.1CONCENTRATIONCThisspecificationisprovidedtoensurethattheconcentrationofradio-activematerialsreleasedinliquidwasteeffluentstoUNRESTRICTEDAREASwillbelessthantheconcentrationlevelsspecifiedin10CFRPart20,AppendixB,TableII,Column2.ThislimitationprovidesadditionalassurancethatthelevelsofradioactivematerialsinbodiesofwaterinUNRESTRICTEDAREASwillresultinexposureswithin:(1)theSectionII.AdesignobjectivesofAppendixI,10CFRPart50,toaMEMBEROFTHEPUBLIC,and(2)thelimitsof10CFRPart20.106(e)tothepopulation.TheconcentrationlimitfordissolvedorentrainednoblegasesisbasedupontheassumptionthatXe-135isthecontrollingradioisotopeanditsMPCinair(submersion)wasconvertedtoanequivalentconcentrationinwaterusingthemethodsdescribedinInter-nationalCommissiononRadiologicalProtection(ICRP)Publication2.Therequireddetectioncapabilitiesforradioactivematerialsinliquidwastesamplesaretabulatedintermsofthelowerlimitsofdetection(LLDs).DetaileddiscussionoftheLLD,andotherdetectionlimitscanbefoundinCurrie,L.A.,"LowerLimitofDetection:DefinitionandElaborationofaProposedPositionforRadiologicalEffluentandEnvironmentalMeasurements,"NUREG/CR-4007(September1984),andintheHASLProceduresManual,HASL-300(revisedannually).3/4.11.1.2DOSEThisspecificationisprovidedtoimplementtherequirementsofSectionsII.A,III.AandIV.AofAppendixI,10CFRPart50.TheLimitingConditionforOperationimplementstheguidessetforthinSectionII.AofAppendixI.TheACTIONstatementsprovidetherequiredoperatingflexibilityandatthe~.sametimeimplementtheguidessetforthinSectionIV.AofAppendixItoassurethatthereleasesofradioactivematerialinliquideffluentstoUNRESTRICTEDAREASwillbekept"aslowasisreasonablyachievable."Thedosecalcula-tionmethodologyandparametersintheODCMimplementtherequirementsinSec-tionIII.AofAppendixIthatconformancewiththeguidesofAppendixIbeshownbycalculationalproceduresbasedonmodelsanddata,suchthattheactualexposureofaMEMBEROFTHEPUBLICthroughappropriatepathwaysisunlikelytobesubstantiallyunderestimated.TheequationsspecifiedintheODCMforcalculatingthedosesduetotheactualreleaseratesofradioactivematerialsinliquideffluentsareconsistentwiththemethodologyprovidedinRegulatoryGuide1.109,"CalculationofAnnualDosestoHanfromRoutineReleasesofReactorEffluentsforthePurposeofEvaluatingCompliancewith10CFRPart50,AppendixI"Revision1,October1977andRegulatoryGuidel.113,"EstimatingAquaticDispersionofEffluentsfromAccidentalandRoutineReactorReleasesforthePurposeofImplementingAppendixI,"April1977.NINEMILEPOINT"UNIT2B3/411-1Hov~01~+
RADIOACTIYEEFFLUENTSBASESFI)t3~lk5;.4,i~!!(f!jjj3/4.11.1.3LIUIDRADMASTETREATMENTSYSTEMTheOPERABILITYoftheLiquidRadwasteTreatmentSystemensuresthatthissystemwillbeavailableforusewheneverliquideffluentsrequiretreatmentpriortoreleasetotheenvironment.Therequirementthattheappropriateportionsofthissystembeusedwhenspecifiedprovidesassurancethatthereleasesofradioactivematerialsinliquideffluentswillbekept"aslowasisreasonablyachievable".Thisspecificationimplementstherequirementsof10CFR50.36a,GeneralDesignCriterion60ofAppendixAto10CFRPart50andthedesignobjectivegiveninSectionII.DofAppendixIto10CFRPart50.ThespecifiedlimitsgoverningtheuseofappropriateportionsoftheLiquidRadwasteTreatmentSystemwerespecifiedasasuitablefractionofthedosedesignobjectivessetforthinSectionII.AofAppendixI,10CFRPart50,forliquideffluents.3/4.11.1.4LIUIDHOLDUPTANKSThetankslistedinthisspecificationincludeallthoseoutdoorradwastetanksthatarenotsurroundedbyliners,dikes,orwallscapableofholdingthetankcontentsandthatdonothavetankoverflowsandsurroundingareadrainsconnectedtotheLiquidRadwasteTreatmentSystem.Restrictingthequantityofradioactivematerialcontainedinthespecifiedtanksprovidesassurancethatintheeventofanuncontrolledreleaseofthetanks'ontents,theresultingconcentrationswouldbelessthanthelimitsof10CFRPart20,AppendixB,TableII,Column2,atthenearestpotablewatersupplyandthenearestsurfacewatersupplyinanUNRESTRICTEDAREA.3/4.Il.2GASEOUSEFFLUENTS3/4.11.2.IDOSERATEThisspecificationisprovidedtoensurethatthedoseatanytimeatand'.beyondtheSITEBOUNDARYfromgaseouseffluentsfromallunitsonthesitewillbewithintheannualdoselimitsof10CFRPart20toUNRESTRICTEDAREAS..Theannualdoselimitsarethedosesassociatedwiththeconcentrationsof10CFRPart20,AppendixB,Tab'leII,Columnl.TheselimitsprovidereasonableassurancethatradioactivematerialdischargedingaseouseffluentswillnotresultintheexposureofaMEMBEROFTHEPUBLICinanUNRESTRICTEDAREA,eitherwithinoroutsidetheSITEBOUNDARY,toannualaverageconcentrationsexceedingthelimitsspecifiedinAppendixB,TableIIof10CFRPart20(10CFR20.106(b)).ForMEMBERSOFTHEPUBLICwhomayattimesbewithintheSITEBOUNDARY,theoccupancyofthatMEMBEROFTHEPUBLICwillusuallybesufficientlylowtocompensateforanyincreasefntheatmosphericdiffusionfactorabovethatfortheSITEBOUNDARY.Thespecifiedreleaseratelimitsrestrict,atalltimes,thecorrespondinggammaandbetadoseratesabovebackgroundtoaMEMBEROFTHEPUBLICatorbeyondtheSITEBOUNDARYtolessthanorequalto500mrems/yeartothewho1ebodyortolessthanorequalto3000mrems/yeartotheskin.Thesereleaseratelimitsalsorestrict,atallNINEMILEPOINT-UNIT2B3/411-2NOV201985
RADIOACTIVEEFFLUENTSBASESDOSERATE(Continued)timesthecorrespondingthyroiddoserateabovebackgroundviathecow-milk-childpathwaytolessthanorequalto1500mrems/year.Therequireddetectioncapabilitiesforradioactivematerialsingaseouswastesamplesaretabulatedintermsofthelowerlimitsofdetection(LLDs).DetaileddiscussionoftheLLD,andotherdetectionlimitscanbefoundinCurrie,L.A.,"LowerLimitofDetection:DefinitionandE'laborationofaProposedPositionforRadiologicalEffluentandEnvironmentsMeasurements,"NUREG/CR-4007(September1984),andintheHASLProceduresManual,HASL-300(revisedannually).3/4.ll.2.2DOSE"NOBLEGASESThisspecificationisprovidedtoimplementtherequirementsofSectionsII.B,III.AandIV.AofAppendixI,10CFRPart50.TheLimitingConditionforOperationimplementstheguidessetforthinSectionII.BofAppendixI.TheACTIONstatementsprovidetherequiredoperatingflexibilityandatthesametimeimplementtheguidessetforthinSectionIV.AofAppendixItoassurethatthereleasesofradioactivematerialingaseouseffluentstoUNRESTRICTEDAREASwillbekept"aslowasisreasonablyachievable."TheSurveil'lanceRequirementpimplementtherequirementsinSectionIII.AofAppend>xIthatconformancewiththeguidesofAppendixIbeshownbycalcula-tionalproceduresbasedonmodelsanddatasuchthattheactualexposureofa'EMBEROFTHEPUBLICthroughappropriatepathwaysisunlikelytobesubstantiallyunderestimated.ThedosecalculationmethodologyandparametersestablishedintheODCMforcalculatingthedosesduetotheactualreleaseratesofradioactivematerialsinliquideffluentsareconsistentwiththemethodologyprovidedinRegulatoryGuide1.109,"CalculationofAnnualDosestoManfromRoutineReleasesofReactorEffluentsforthePurposeofEvaluatingCompliancewith10CFRPart50,AppendixI"Revisionl,October,1977andRegulatoryGuidel.ill,"MethodsforEstimatingAtmosphericTransportandDispersionofGaseousEffluentsinRoutineReleasesfromLight-WaterCooledReactors,"Revisionl,"July1977.TheODCMequationsprovided;fordeterminingtheairdosesat-and-beyondtheSITEBOUNDARYarebaseduponthehistoricalaverageatmospheri%"conditions.3/4.11.2.3DOSE-IODINE-131ANDlANDRIONUDPARTICULATEFORMThisspecificationisprovidedtoimplementtherequirementsofSectionsII.C,III.AandIV.AofAppendixI,10CFRPart50.TheLimitingConditionsforOperationaretheguidessetforthinSectionII.CofAppendixI.TheACTIONstatementsprovidetherequiredoperatingflexibilityandatthesametimeimplementtheguidessetforthinSectionIV.AofAppendixItoassurethatthereleasesofradioactivematerialsingaseouseffluentstoUNRESTRICTEDAREASwillbekept"aslowasisreasonablyachievable."TheODCMcalculationalNINEMILEPOINT-UNIT2B3/4ll-3NOY201965
RADIOACTIVEEFFLUENTSBASES)p(p~pgg'(7T!lfP~5IDOSE-IODINE-131AND133TRITIUMANDRADIONUCLIDESINPARTICULATEFORMContinuedmethodsspecifiedintheSurveillanceRequirementsimplementtherequirementsinSectionIII.AofAppendixIthatconformancewiththeguidesofAppendixIbeshownbycalculationalproceduresbasedonmodelsanddata,suchthattheactualexposureofaMEMBEROFTHEPUBLICthroughappropriatepathwaysisunlikelytobesubstantiallyunderestimated.TheODCMcalculationalmethodologyandparametersforcalculatingthedosesduetotheactualreleaseratesofthesubjectmaterialsareconsistentwiththemethodologyprovidedinRegulatoryGuide1.109,"CalculationofAnnualDosestoManfromRoutineReleasesofReactorEfiluentsforthePurposeofEvaluatingCompliancewith10CFRPart50,AppendixI,"Revision1,October1977andRegulatoryGuidel.ill,"MethodsforEstimatingAtmosphericTransportandDispersionofGaseousEffluentsinRoutineReleasesfromLight-Water-CooledReactors,"Revision1,July1977.Theseequa-tionsalsoprovidefordeterminingtheactualdosesbaseduponthehistoricalaverageatmosphericconditions.ThereleaseratespecificationsforIodine-131,Iodine-133,tritium,andradionuclidesin-particulateformwithhalf-livesgreaterthan8daaredependentuponthe.existingradionuclidepathwaystoman,intheareasabeyondtheSITEBOUNDARY.Thepathwaysthatwereexaminedinthedevelopmentofthesecalculationswere:(1)individualinhalationofair-borneradionuclides,(2)depositionofradionuclidesontogreenleafyvegetationwithsubsequentconsumptionbyman,(3)depositionontograssyareas,wheremilkanimalsandmeatproducinganimalsgrazewithconsumptionofthemilkandmeatbyman,and(4)depositiononthegroundwithsubsequentexposuretoman.3/4.11.2.4AND3/4.11.2.5GASEOUSRADWASTETREATMENTSYSTEMANDVENTILATIONEXHAUSTTREATMENTSYSTEMTheOPERABILITYoftheGASEOUSRADWASTETREATMENTSYSTEMandtheVENTILATIONEXHAUSTTREATMENTSYSTEMensuresthatthesystemswillbeavailableforusewhenevergaseouseffluentsrequiretreatmentpriortoreleasetotheenviron-'.ment.Therequirementthattheappropriateportionsofthesesystemsbeused,whenspecifiedprovidesreasonableassurancethatthereleasesofradioactivematerialsingaseouseffluentswillbekept"aslowasisreasonablyachievable".Thisspecificationimplementstherequirementsof10CFR50.36a,GeneralDesignCriterion60ofAppendixAto10CFRPart50andthedesignobje'ctivesgiveninSectionII.DofAppendixIto10CFRPart50.Thespecifiedlimitsgovern-ingtheuseofappropriateportionsofthesystemwerespecifiedasasuitablefractionofthedosedesignobjectivessetforthinSectionII.BandII.CofAppendixI,10CFRPart50,forgaseouseffluents.3/4.11.2.6EXPLOSIVEGASMIXTUREThisspecificationisprovidedtoensurethattheconcentrationofpoten-tiallyexplosivegasmixturescontainedintheGASEOUSRADWASTETREATMENTSYSTEMismaintainedbelowtheflammabilitylimitsofhydrogen.Automaticcontrolfeaturesareincludedinthesystemtopreventthehydrogenconcen-trationsfromreachingtheseflammabilitylimits.TheseautomaticcontrolNINEMILEPOINT-UNIT2B3/411-4NOV2O>9BS
RADIOACTIVEEFFLUENTSBASES3/4.11.2.6EXPLOSIVEGASMIXTUREcontinuedfeaturesincludeinjectionofdilutantstoreduceconcentrationsbelowflamma-bilitylimits.Maintainingtheconcentrationofhydrogenbelowtheirflamma-bilitylimitsprovidesassurancethatthereleasesofradioactivematerialswillbecontrolledinconformancewiththerequirementsofGeneralDesignCri-terion60ofAppendixAto10CFRPart50.3/4.11.2.7MAINCONDENSER-OFFGASRestrictingthegrossradioactivityrateofnoblegasesfromthemaincondenseroffgasprovidesreasonable'.assurancethatthetotalbodyexposuretoanindividualattheexclusionareaboundarywillnotexceedasmallfractionofthelimitsof10CFRPart100intheeventthiseffluentisinadvertentlydischargeddirectlytotheenvironmentwithouttreatment.ThisspecificationimplementstherequirementsofGeneralDesignCriteria60and64ofAppendixAto10CFRPart50.3/4.11.2.8VENTINGORPURGINGThisspecificationprovides'reasonableassurancethatreleasesfromdrywelland/orsuppressionchamberpurgingoperationswillnotexceedtheannualdoselimitsof10CFRPart20forunrestrictedareas.3/4.11.3SOLIDRADIOACTIVEMASTESThisspecificationimplementstherequirementsof10CFR50.36aandGeneralDesignCriterion60ofAppendixAto10CFRPart50.TheprocessparametersincludedinestablishingthePROCESSCONTROLPROGRAMmayinclude,butarenotlimitedto,wastetype,wastepH,waste/liquid/SOLIDIFICATIONagent/catalystratios,wasteoilcontent,wasteprincipalchemicalconstituents,andmixingandcuringtimes.3/4.11.4TOTALDOSEThisspecificationisprovidedtomeetthedoselimitationsof40CFRPart190thathavebeenincorporatedinto10CFRPart20by46FR18525.ThespecificationrequiresthepreparationandsubmittalofaSpecialReportwhen-everthecalculateddosesduetoreleasesofradioactivityandtoradiationfromuraniumfuelcyclesourcesexceed25mremstothewholebodyoranyorgan,exceptthethyroid,whichshallbelimitedtolessthanorequalto75mrems.Forsitescontaininguptofourreactors,itishighlyunlikelythattheresultantdosetoaMEMBEROFTHEPUBLICwillexceedthedoselimitsof40CFRPart190iftheindividualreactorsremainwithintwicethedosedesignobjectivesofAppendixI,andifdirectradiationdosesfromtheunitsincludingoutsidestoragetanks,etc.,arekeptsmall.TheSpecialReportwilldescribeacourseofactionthatshouldresultinthelimitationoftheannualdosetoaMEMBEROFTHEPUBLICtowithinthe40CFRPart190limits.ForthepurposesoftheNINEMILEPOINT-UNIT2B3/4ll"5'OV801S85
RAOIOACTIVEEFFLUENTSBASESP~TJ@flfg]Pl(1plp$p'p(TOTALDOSE(Continued)SpecialReport,itmaybeassumedthatthedosecommitmenttotheMEMBERofthePUBLICfromother=uraniumfuelcyclesourcesisnegligible,withtheexceptionthatdosecontributionsfromothernuclearfuelcyclefacilitiesatthesamesiteorwithinaradiusof5milesmustbeconsidered.IfthedosetoanyMEMBEROFTHEPUBLICisestimatedtoexceedtherequirementsof40CFRPart190,theSpecialReportwitharequestforavariance(providedthereleaseconditionsresultinginviolationof40CFRPart190havenotalreadybeencorrected),inaccordancewiththeprovisionsof40CFR190.11and10CFR20.405c,isconsideredtobeatimelyrequestandfulfillstherequirementsof40CFRPart190untilNRCstaffactioniscompleted.Thevarianceonlyrelatestothelimitsof40CFRPart190,anddoesnotapplyinanywaytotheotherrequirementsfordoselimitation.of10CFRPart20,asaddressedinSpecifi-cations3.11,1.1and3.11.2.1.AnindividualisnotconsideredaMEMBEROFTHE'UBLICduringanyperiodinwhichhe/sheisengagedincarryingoutanyoperationthatispartofthenuclearfuelcycle'.NINEMILEPOINT"UNIT283/411-6HOV201985
D3/4.12RAIOLOGICALENVIRONMENTALMONITORINGBASES3/4.12.1MONITORINGPROGRAMl'TheRadiologicalEnvironmentalMonitoringProgramrequiredbythisspecificationprovidesrepresentativemeasurementsofradiationandofradio-activematerialsinthoseexposurepathwaysandforthoseradionuclidesthatleadtothehighestpotentialradiationexposureofMEMBERSOFTHEPUBLICresultingfromtheplantoperation.ThismonitoringprogramimplementsSectionIV.B.2ofAppendixIto10CFRPart50andtherebysupplementstheRadiologicalEffluentMonitoringProgrambyverifyingthatthemeasurableconcentrationsofradioactivematerialsandlevelsofradiationarenothigherthanexpectedonthebasisoftheeffluentmeasurementsandthemodelingoftheenvironmentalexposurepathways.GuidanceforthismonitoringprogramisprovidedbytheRadiologicalAssessmentBranchTechnicalPositiononEnviron-mentalMonitoring,Revision1,November1979.Theinitiallyspecifiedmonitor-ingprogramwillbeeffectiveforatleastthefirst3yearsofcommercialoperation.Followingthisperiod,programchangesmaybeinitiatedbasedonoperationalexperience..Therequireddetectioncapabilitiesforenvironmentalsampleanalysesaretabulatedin.termsofthelowerlimitsofdetection(LLDs).TheLLDsrequiredbyTable4.12-1areconsideredoptimumforroutineenvironmentalmeasurementsinindustriallaboratories.ItshouldberecognizedthattheLLDisdefinedasanagriori(beforethefact)limitrepresentingthecapabilityofameasure-~(<<*)'measurement.DetaileddiscussionoftheLLD,andotherdetectionlimits,canbefoundinCurrie,L.A.,"LowerLimitofDetection:DefinitionandElaborationofaProposedPositionforRadiologicalEffluentandEnvironmentalMeasurements,"NUREG/CR-4007(September1984),andintheHASLProceduresManual,HASL-300(revisedannually).3/4.12.2LANDUSECENSUSThisspecificationisprovidedtoensurethatchangesintheuseofareas-atandbeyondtheSITEBOUNDARYareidentifiedandthatmodif1cationstotheRadiologicalEnvironmentalMonitoringProgramaremadeifrequiredbytheresultsofthiscensus.Thebestinformation,suchasfromadoor-to-doorsurvey,fromanaerialsurvey,orfromconsultingwithlocalagriculturalauthoritiesshallbeused.ThiscensussatisfiestherequirementsofSec"tionIV.B.3ofAppendixIto10CFRPart50.Inlieuofagradencensus,thesignificanceoftheexposureviathegardenpathwaycanbeevaluatedbythesamplingofvegetationasspecifiedinTable3.12-1..AMILKSAMPLINGLOCATION,asdefinedinSection1,requiresthatatleast10milkingcowsarepresentatadesignatedmilksamplelocation.Ithasbeenfoundfrompastexperience,andasaresultofconferringwithlocalfarmers,thataminimumof10milkingcowsisnecessarytoguaranteeanadequatesupplyofmilktwicepermonthforanalyticalpurposes.Locationswithlessthan10milkingcowsareusuallyutilizedforbreedingpurposeswhicheliminatesastablesupplyofmilkforsamplesasaresultofsucklingcalvesandperiodswhentheadultanimalsaredry.NINEMILEPOINT"UNIT2B3/412-1NOy2OlSSS
RADIOLOGICALENVIRONMENTALMONITORINGBASESp,,fggj~~l~V'p%1fjalap~3/4.12.3INTERLABORATORYCOMPARISONPROGRAMTherequirementforparticipationinanapprovedInterlaboratoryComparisonProgramisprovidedtoensurethatindependentchecksontheprecisionandaccuracyofthemeasurementsofradioactivematerialsinenvironmentalsamplematricesareperformedaspartofthequalityassuranceprogramforenvironmentalmonitoringinordertodemonstratethattheresultsarevalidforthepurposesofSectionIV.B.2ofAppendixIto10CFRPart50.NINEMILEPOINT-UNIT2B3/412-2cov20SB5
SECTION5.0DESIGNFEATURESNOV20'tSI
5.0DESIGNFEATURESpgg@Pp+0/pj's)ll/5.1SITETheNineMilePointNuclearStationandJamesA.FitzPatrickNuclearPowerPlantsitecomprisingapproximately1500acres,islocatedontheshoresofLakeOntario,aboutsevenmilesnortheastofOswego,NewYork.Anexclu-siondistanceofnearly4000feetisprovidedbetweenthestationandthenearestSITEBOUNDARYtothewest,amiletotheboundaryontheeast,andamileandahalftothesouthernSITEBOUNDARY.EXCLUSIONAREA5.1.1Theexclusionareasha'llbeasshowninFigure5.1.1-1.LOWPOPULATIONZONE5.1.2ThelowpopulationzoneshallbeasshowninFigure5.1.2-1.MAPDEFININGUNRESTRICTEDAREASANDSITEBOUNDARYFORRADIOACTIVEGASEOUSANDIIIKFFE75.1.3Informationregardingradioactivegaseousandliquideffluents,whichwillallowidentificationofstructuresandreleasepointsas'ellasdefini-tionofUNRESTRICTEDAREASwithintheSITEBOUNDARYthatareaccessibletoMEMBERSOFTHEPUBLIC,shallbeasshowninFigure5.1.3"1.5.2CONTAINMENT5.2.1Theprimarycontainmentisasteellinedconcretestructureconsistingofadrywellandsuppressionchamber.Thedrywellisasteel-linedprestressedconcretevesselintheshapeofatruncatedconeontopofawaterfilledsup-pressionchamberandisattachedtothesuppressionchamberthroughaseriesofdowncomervents.Thedrywellhasaminimumfreeairvolumeof(303,418)cubicfeet.Thesuppressionchamberhasaminimumairregionof192,028cubicfeetandaminimumwaterregionof145,495cubicfeet.DESIGNTEMPERATUREANOPRESSURE5.2.2Theprimarycontainmentisdesignedandshallbemaintainedfor:a.Maximuminternalpressure45psig.b.'aximuminternaltemperature:drywell340F.suppressionpool212'Fsuppressionchamber270~Fc.Maximumexternalpressure4.7psig.d.Maximumfloordifferentialpressure:25psid,downward.10psid,upward.NINEMILEPOINT"UNIT25-1NOV201985
ITEMNO.FSARLOCATIONTECH.SPEC.LOCATIONSUBJECT28)29)30)g(s'lgi)6.3-14aL$8~Table3.3.3-2~q~L.C.O.3.4.3.2.dandTables3.4.3.2-1,3.4.3.2-2and3.4.3.2-3Table3.3.7.1-1F210.62Table12.3-1Page2of4Tables8.3-8and4.8.2'.d.2.a)8.3-9andb)LPCSInjectionValveDifferentialPressurePerimissiveSetpointLeakRateTestingOfValvesSeparatingReactorCoolantSystemFromLowPressureSystemsMainControlRoomVentilationRadiationMonitorsDivisionsIandIIBatteryLoadProfilesABBREVIATIONLISTHPCS-ADSLPCI-TIPRCIC-RHR-RHCU-LPCS-HighPressureCoreSprayAutomaticDepressurizationSystemLowPressureCoolantInjectionTraversingIncoreProbeReactorCoreIsolationCoolingResidualHeatRemovalReactorHaterCleanupLowPressureCoreSpray
~WTCOCLCNCTTlCCHAITWCWCWQOCIKCCOICICCIC440CCWCCCTff5CCTTCCVCCCCCOEIT(c)40WITIr'og~%~~'II:~JAFI~IIII~asap'C~CJCITTTCT+CaCITC1'XCLUSIONAREABOUNDARY(a)NiagaraMohawkPowerCorp.PropertyLine(b)NewYorkPowerAuthorityPropertyLine(c)RegionControlledByCoastGuardDuringEmergencies.SA4OagCWCsaoeC~0FIGURE3.1.1-1EXCLUSIONAREA,BOUNDARYNINEMILEPOINTUNIT25-2t'jOV20]oag
aC)SCALE,Hiles234BarnonsBeachLaisV4ntoneMsepeagshet4isLPZteeasanlHickorytransGroveOenrsterBeechMestcotranMe@coBeyBeachCJlILPZcswarsnsIOSeIalarIS~ttenHarmBarrrnfeSeelapssYesesII~IIIIaer~IIreeaIoeriIaScrrha4nonongGranSoolhtlewI4een~~~EI(sAVEanmenfosGaleMokoScIpIBssst&CDCDCDCylFIGURE5.1.2-1LOWPOPULATIONZONE,LPZ
(4)E~()(k)~~)~aassiraaiarT~arlttef+cs~c)ieaaoolC~ONCEJQTlCÃCTTSTAT%OfICWTONKSlOQs5jnezC/lILJ~C>>CAs~C9CalC)C/l~'$~$)iCa)~aaseaC~la)aa')Ca)sotasa<<Claaaaeiaan'Ca)~aeasacaaaaaeienal)Ca)~aeeseaaeockeaaaaeaaeesasC)eaeassessor~C)eea~aWsa~C)<<~~ci)JQ%F~esseaea)aesaa~cacao%eases'erase)Caleaseseller@Ol)Qe~Hose)leoCa)QaealaeiaoaSorerQlassesseeoeeaeOlheeitAdemsues4aeeee~aeeaee~~ieleoeaaatat1m'eeaeseeeiless)<<wraasweeaseedaueaae~m~inm~~)assieRlWasaaaaeaSaa)aaaa~ieLllSeaaaeee~aeaa)erae~~arrearsease)osaaea~~m~sara)et)aaaaiaeasaae~aDS~~~ease~aieoo~CtX%ll&JCCaseareas~aeaaeaeareasaeea'M1SCISMKISSaaea)aa1RS$0assess)eeeWMcttS7%0NINEMILEPOINT-UNIT25-4fggyi')335
DESIGNFEATURESNBF5)pgpgglypt>>SECONDARYCONTAINMENT5.2.3Thesecondarycontainmentconsistsofthe(ReactorBuilding,andtheNorthandSouthAuxiliaryBaysandhasaminimumfreevolumeof3,876,630cubicfeet.5.3REACTORCOREFUELASSEMBLIES5.3.1Thereactorcoreshallcontain764fuelassemblieswitheachfuelassemblycontaining62fuelrodsandtwowaterrodscladwithZircaloy-2.Eachfuelrodshallhaveanominalactivefuellengthof150inches.Theinitialcoreloadingshallhaveamaximumaverageenrichmentof1.88weightpercentU-235.CONTROLRODASSEMBLIES5.3.2Thereactorcoreshallcontaining.ofacruciformarrayofstainlessboroncarbide,B4C,powdersurroundedsheath.185controlrodassemblies,eachconsist-steeltubescontaining143inchesofbyacruciformshapedstainlesssteel5.4REACTORCOOLANTSYSTEMDESIGNPRESSUREANDTEMPERATURE5.4.1Thereactorcoolantsystemisdesignedandshallbemaintained:a.InaccordancewiththecoderequirementsspecifiedinSection5.2oftheFSAR,withallowancefornormaldegradationpursuanttothe..applicableSurveillanceRequirements,b.Forapressureof:l.1250psigonthesuctionsideoftherecirculationpump.2.1650psigfromtherecirculationpumpdischargetotheoutletsideofthedischargeshutoffvalve.3.1550psigfromthedischargeshutoffvalvetothejetpumps.c.Foratemperatureof575F..VOLUME5.4.2Thetotalwaterandsteamvolumeofthereactorvesselandrecirculationsystemisapproximately22,000cubicfeetatanominalsteamdomesaturation(average)temperatureof533F.NINEMILEPOINT-UNIT25-5NOV201985
DESIGNFEATURESF>>~>"~~IIPJlP7ÃP75.5METEOROLOGICALTONERLOCATION35.5.1Themeteoroiogica1towersha11beIocatedasshownonFigure5.I/1.5.6FUELSTORAGECRITICALITY5.6e1Thespentfuelstorageracksaredesignedandshallbemaintainedwith:a.Akffequivalenttolessthanorequalto0.95whenfloodedwithunboratedwater,includingallcalculationaluncertaintiesandbiasesasdescribedinSection9-1oftheFSAR.b.Anominal6.18inchcenter-to-centerdistancebetweenfuelassembliesplacedinthestorageracks.5.6.1.2Thekefffornewfuelstoredinthenewfuelstorageracksshallnotexceed0.95inthenormaldryconditionorintheabnormalcompletelywaterfloodedcondition,TheKeffshallnotexceedO-98s.wA.b.6lLio~+owe~+bgwoo,-cev4~~<.bLe~4c~oecunnL+causesinoboesuIcenogirnnMrnJgrnt<eu(+>nncDRAINAGEo>SW5sU~<opl~~iSMsu.5.6.2Thespentfuelstoragepoolisdesignedandshallbemaintainedtopreventinadvertentdrainingofthepoolbelowelevation329'-7".CAPACITY5.6.3Thespentfuelstoragepoolisdesignedandshallbemaintainedwitha'toragecapacitylimitedtonomorethan4D50fuelassemblies.5.7COMPONENTCYCLICORTRANSIENTLIMIT5.7.1ThecomponentsidentifiedinTable5.7.1-1aredesignedandshallbemaintainedwithinthecyclicortransientlimitsofTable5.7.1-1.NINEMILEPOINT"UNIT25-6NOVSD1985
~"MIPlC)MCOHPONENTReactorCYCLICORTRANSIENTLIMIT120heatupandcooldowncycles80stepchangecycles19SreactortripcyclesDESIGNCYCLEORTRANSIENT70Fto565Fto70FLossoffeedwaterheaters100KtoOXofRATEDTHERHALPOMERTAOLE5.7.1-1COHPONENTCYCLICORTRANSIENTLIMITS130hydrostaticpressureandleaktestsPressurizedto>930psigand<1250psigC,goal
DESIGNFEATURESFi~MI83FAG'IKP75.5METEOROLOGICALTOWERLOCATION5.5.1ThemeteorologicaltowershallbelocatedasshownonFigure5.1..1-1.5.6FUELSTORAGECRITICALITY5.6.1Thespentfuelstorageracksaredesignedandshallbemaintainedwith:a.Akffequivalenttolessthanorequalto0.95whenfloodedwithunboratedwater,includingallcalculationaluncertaintiesandbiasesasdescribedinSection4.3oftheFSAR.b.Anominal6.18inchcenter-to-centerdistancebetweenfuelassembliesplacedinthestorageracks.;5.6;1.2Thekefffornewfuelstoredin.thenewfuelstorageracksshallnotexceed0.95.inthenormaldryconditionorintheabnormalcompletelywaterfloodedconditionwiththenon-combustiblestoragevaultcoversinplace.DRAINAGE5.6.2Thespentfuelstoragepoolisdesignedandshallbemaintainedtopreventinadvertentdrainingofthepoolbelowelevation329'-7".CAPACITY5.6.3Thespentfuelstoragepoolisdesignedandshallbemaintainedwithastoragecapacitylimitedtonomorethan4050fuelassemblies.5.7COMPONENTCYCLICORTRANSIENTLIMIT5.7.1ThecomponentsidentifiedinTable5.7.1-1aredesignedandshallbemaintainedwithinthecyclicortransientlimitsofTable5.7.1-1.NINEMILEPOINT"UNIT2
STlMI01CIMICOMPONENTReactorCYCLICORTRANSIENTLIMIT120heatupandcooldowncyclesDESIGNCYCLEORTRANSIENT70oFto565oFto70oFTABLE5.7.1-1COMPONENTCYCLICORTRANSIENTLIMITSM80stepchangecycles198reactortripcycles130hydrostaticpressureandleaktestsLossoffeedwaterheaterslOOXtoOXofRATEDTHERMALPOWERPressurizedto>930psigand<1250psig~jfM
SECTION6.0I,ADMINISTRATIVECONTROLS
6-0ADMINISTRATIVECONTROLS6.1RESPONSIBILITY6.1.1TheGeneralSuperintendent-NuclearGenerationshallberesponsibleforoverall.unitoperationandshalldelegateinwritingthesuccessiontothisresponsibilityduringhisabsence.6.1.2TheStationShiftSupervisor-Nuclear(orduringhisabsencefromthecontrolroom,adesignatedindividual}shallberesponsiblefor.thecontrolroomcommandfunction.Amanagementdirectivetothiseffect,signedbytheYicePresident-NuclearGenerationshallbereissuedtoallstationpersonnelonanannualbasis.6.2ORGANIZATIONOFFSITE6.2.1TheoffsiteorganizationforunitmanagementandtechnicalsupportshallbeasshownonFigure6.2.1-1.UNITSTAFF6.2.2Theunit.organizationshallbeasshownonFigure6.2.2-1and:a.EachondutyshiftshallbecomposedofatleasttheminimumshiftcrewcompositionshowninTable6.2.2-1;b.AtleastonelicensedOperatorshallbeinthecontrolroomwhenfuelisinthereactor.Duringreactoroperation,thislicensedoperatorshallbepresentatthecontrolsofthefacility.c.Anindividualqualifiedinradiationprotection~proceduresshallbeonsitewhenfuelisinthereactor;d.Atleasttwolicensedoperatorsshallbepresentinthecontrolrootsduringreactorstartup,scheduledreactorshutdownandduringrecoveryfromreactortrips.e.AlicensedSeniorReactorOperatorshallberequiredintheControlRoomduringOperationalConditions1,2and3andwhentheemergencyplanisactivated.ThismaybetheStationShiftSupervisor-NuclearortheAssistant.StationShiftSupervisor-Nuclearduringpoweroper-ations.Whentheemergencyplanisactivated,theAssistantStationShiftSupervisor-NuclearbecomestheShiftTechnicalAdvisorandtheStationShiftSupervisor-Nuclearisrestrictedinthecontrolroomuntilanadditional-licensedSeniorReactorOperatorarr'ives."TheRadiationProtectionqualifiedindividualandfirebrigadecompositionmaybelessthantheminimumrequirementsforaperiodoftimenottoexceed2hours,inordertoaccommodateunexpectedabsence,providedimmediateactionistakentofilltherequiredpositions.NINEMILEPOINT-UNIT26"I.gg/g".0198
ADMINISTRATIVECONTROLSUNITSTAFF(continued)g.AlicensedSeniorReactorOperatorshallberesponsibleforallmove-mentofnewandirradiatedfuelwithinthesiteboundary.Allcorealterationsshallbedirectlysupervisedbyalicensedseniorreactoroperatorwhohasnootherconcurrentresponsibilitiesduringthisoperation.ALicensedOperatorwillberequiredtomanipulatethecontrolsofallfuelhandlingequipmentexceptmovementofnewfuelfromreceiptthroughdrystorage.Allfuelmoveswithinthecoreshallbedirectlymonitoredbyamemberofthereactoranalystgroup.AFireBrigadeoffive(5)membersshallbemaintainedonsiteatalltimes.h.Administrativeproceduresshallbedevelopedandimplementedtolimittheworkinghoursoffacilitystaffwhoperformsafety-relatedfunc-tions;e.g.,1icensedSeniorOperators,licensedOperators,healthphysicists,auxiliaryoperatorsandkeymaintenancepersonnel.Adequateshiftcoverageshallbemaintainedwithoutroutineheavyuseofovertime.Theobjectiveshallbetohaveoperatingpersonnelworkanormal8-hourday,4Q-hourweekwhiletheunitisoperating.However,intheeventthatunforeseenproblemsrequiresubstantialamountsofovertimetobeused,orduringextendedperiodsofshut"downforrefueling,majormaintenance,ormajorunitmodifications,onatemporarybasisthe'ollowingguidelinesshallbefollowed:1.Anindividualshouldnotbepermittedtoworkmorethan16hoursstraight,excludingshiftturnovertime.2.Anindividualshouldnotbepermittedtoworkmorethan16hoursinany24-hourperiod,normorethan24hoursinany48-hourperiod,normorethan72hoursinanysevendayperiod,allexcludingshiftturnovertime.3.Abreakofatleasteighthoursshouldbeallowedbetweenworkperiods,includingshiftturnovertime.4.Exceptduringextendedshutdownperiods,theuseofovertimeshouldbeconsideredonanindividualbasisandnotfortheentirestaffonashift.AnydeviationfromtheaboveguidelinesshallbeauthorizedbytheGeneralSuperintendent-NuclearGenerationorhisdeputy,orhigherlevelsofmanagement,inaccordancewithestablishedproceduresandwithdocumentationofthebasisforgrantingthedeviation.ControlsshallbeincludedintheproceduressuchthatindividualovertimeshallbereviewedmonthlybytheGeneralSuperintendent-NuclearGenerationorhisdesigneetoassurethatexcessivehourshavenotbeenassigned.Routinedeviationfromtheaboveguidelinesisnotauthorized.NINEMILEPOINT"UNIT26-2
PRESIDENTVICEPRESIDENT=QUALITYASSURANCESENIORVICEPRESIDENTVICEPRESIDENTNUCI.EARENGINEERINGANOLICENSINGVICEPRESIDENTNUCLEARGENERATIONGENERALSUPERINTENDENTNUCLEARGENERATIONSTATIONSUPERINTENDENTNUCLEARGENERATIONUNIT2figure6,21-1-NineMilePointNuclearStationManagementOrgan.cationChart,.NineMilePointJhxitD,6-3
mFIGURE8.2.2NINEMILEPOINTNUCLEARSITEOPERATIONSORGANIZATIONImNCalILNTCl4Ies4lwtlNH'I1aDIHILlasscsalaalsoa~Dsswsslassvlas'HIILNItoaaossHIIIILIsoaLaotLaew40SsatsoaWPIIWIIaolsstHVCllkACIAINafSoseVMIIHslwtlAusflaolatHassellaaaclMKLILAlutlausflssDIallaawwoMCLlkA'ltIAWIISsolalCeslsallATkaoALDJLIAMHateLCIstIIIIICHSJSCLLIVtlAHIIaosa'IMCltM0ISSIILIWIIAfCHIvtllewllaolslfHUCLIMOINIALSIONILNT1CDasIswCIsolelacuslsaHJtlIWIIssDINIOtIAaIlailMCLILA'4aasllaal10wtIIsee4aoIIIOtII4HokIaWIILIIaIM4IIIOPSNalsoa~UtlaleleaeLIISNLJIIssassaalllopsaalsoaIUpIleveloaWlHICHuawlIvtvstlCH04HIIIVJCILNellaalWttaICHuaeaIItsASKISSwDskasclaaoJLNJIQslalAlovwlDJIuttIllCINasallutvILICVasesIIesLACIAllsllaa1WvlIICI4NeIII4al~a111CIJLKskssl4'IAIDUHIISLNsllase'IIUtlleucIIaol1lesaswaoSPUCLILAWtIAvsloes'IIaussseoAVCISLAcl~ssesaleDNIaosass11allO~tlCSLLellllutlavelOACalsssllAVLHDALDJ41soa~Aollclesw\welIutlssvslCssISeelIAVValilutlavslaausaltHOIICIwtltsveloaHIIwttoselNCMJClaselLasNIDUWI01IVPSAVSIOJS~taltAONCflalNVCILLSILIHIILAfIutIIvIHas~USItaollCIsoaWSIIlutIkvslewIlssltssolsclsoa141ItoesIIPsl~LaeeaueoCOINIDINL1DelWPIAHlles0111TICHaC4LIIJLVJCNMCL141lutlIVNOSLlac'IDAAJI4LTsUNIIWPIAVNOAIILCTOJILALLI~1tICwesCJasNIOUULIDIuesAnsoA'IICweeCLLiuttoafNVCLI41ANSIILNlVPIIVTlcwecaLSuttosslINIAAIlseosallalwlIeaflseosslfWlIslVJCIWNSCINHWellNJIIJSVSClINIPICISaeWPIIVelosl~IsesoAWIIAVSCI~altlCIHH~tlaalssrNSNAVSCIHestlCTSON~psaasssfcoasfssscfloN1ADHSSIAWPIIHIIssolafDttIaflONINVCLSMeeLNSIILSPI10IvtlasaTIaoleefOtlaatsoasINUCLIAAILDHaflfOPSAAIIoa~UtIIVHINSaNJIIAafIALDHLII~CtlAATSONWPIIVJIOIChILNsllaatHJPIsuaNIDIIICtllafsoas~HJCII4I~fassOHIwt~QJPIIVJIOIIHJCLIaa'4NeII44I~4IlossSWPIWPIIVHDANWPIIICwaCLLLDVIICOSIee'OtIILIONSLsIIOUNJIDCIIII4IsoaIacwIIIILseo~PIDLLSSISWes1141eoelIseosstIIasLNDSJIDLLI~I~ao'III~UpsIVDOAILesoLNslIaaflutlavsHWILAILNcal0IoILeseIfatsoaMalasIIOJIAID.VaslwsIVIIIIIIIIIVIJOIHIOJHII~DJAICILT~1avlaowf1otIJH114'TKaswplawllaDlsstMKLIM0INlI4IJDAHas1IDJII~CtlIafoALJCIIII~0llasossDPIALIOALsclsell~~~lselaossuallwt'IClwtllsslaTWALLllLCausoueoIolalll~I11OtIHIIICweeCLLIPICIJICLIssasl4LNsoal010lutlIvssosslLlAlovs110NCVNJIT.OVLLII~LNVNkssCIHallssIAIIlsassaCIIJSNI.LNLIHILJNJNLLILIIIT~IIJVCI~asstttsolNJIIPIMNt~~IMaakNLHussaaaCINVIMLIIIIVI1IJNDLNIILIHW~avwoewlalastNOIICIJOSSCODADue4IOAWIIVSISMSLLWDLOCKLLfuttoAIDDHHSIIVcooaosaafoaseLososoccaLIHCwllAIIIPHLIOJITPSSOIICICHcooasaaaloaIWAClesCT~LkasewoDoesIsa4IDAAL414CouauwallulLNJIIaaf~LLJeaWDCOCMDHPLTDAWSIvHOALDswaslaalttfSIAVCSICLIALIIIIDJAIIDWtlIVSSON~IIIDCILPHCIIJIVCI~4NsltaaIWtlIVSIOALIWseeslIALIIVSNAVCSIwtlsNNIIssoltlfeslcswIIIHLNLDIleII'Ivali~sNlssvIsVHSelCIJSWSssaesaCIuassIWPIIVeloelWITAuusss1AlsOCINPIIOLSPVCLILILwslWSIVSSOA~SeIIwwtItLceoCOalssWassesILNIHJtlAVIIOAwllwwsa'IaaocoaIADLCIIIIkINNIIHOLLIIASalsostlaalursIIaswaaal~IIOVHI0Cf.ns..ra4.ionE;hl9fhect>S40fkSfof'afffLiQWIAVNOACOLPVIlI~IALTSDLSLesHasaIIJJLssclLNJSska1wlavsloagCOHPVIIAOtlSILTsasIaaoHLNPIINLJKIOsalaatsoalaowllASAa0SPIDAIHI~LIHIIANfDJtlAwfIaolssfcpsaalsoasSIJCLILI11alsossswtfWtlAveculMCLT41stLlullaal~AIMPIWPIAVSHSISSNLP1IIDWJCALLDVVDAI~4sotI1410asAIIIDVWIDAICIMDI~PICsalslleCDCCfCACLIIII~IIOSNII0Leaiu~g0f'44PJ~t 0 TABLE6.2.2-1PA$fRetPPV@PlyMINIMUMSHIFTCREMCOMPOSITIONLicenseNormal~0erationShutdownConditionOperation()M/QProcessReactor~C'I<<SeniorOperatorOperatorUnlicensed()~Ca)~(5)Asst.StationShiftSupervisor(ShiftTechnicalAdvisorflection)(SeniorOperatorLicense)TABLENOTATION(1)Atanyonetime,morelicensedorunlicensedoperatingpeoplecouldbepresentformaintenance,repairs;refueloutages,etc.(2)Thoseoperatingpersonnelnotholdingan"Operator"or"SeniorOperator"License.(3)Foroperationlongerthaneighthourswithoutprocesscomputer.(4)Hotshutdownconditiononly.(5)Anadditionalseniorreactoroperatorwhohasno-otherconcurrentrespon-sibilitiesshallsuperviseallcorealterations.(6)TheShiftCrewCompositionmaybeonelessthantheminimumrequirementsofTable6.2.2-1foraperiodoftimenottoexceedtwohoursinorderto.accommodateunexpectedabsenceofon-dutyshiftcrewmembersprovidedimmediateactionistakentorestoretheShiftCrewCompositiontowithintheminimumrequirementsofTable6.2.2-1.Thisprovisiondoesnotpermitanyshiftcrewpositiontobeunmanneduponshiftchangeduetoanoncomingshiftcrewmanbeinglateorabsent.(7)TheAssistantStationShiftSupervisorperformstheShiftTechnicalAdv'sorfunctionandshallholdaseniorreactoroperatorlicense.heshiftcrewcompositionexceptfortheShiftSupervisor,maybeonelessthantheminimumrequirementsofTable6.2.2-1foraperiodoftimenottoexceed2hoursinordertoaccommodateunexpectedabsenceof.on-dutyshiftcrewmembersprovidedimmediateactionistakentorestoretheshiftcrewcompositiontowithintheminimumrequirementsofTable6.2.2-1.Thisprovisiondoesnotpermitanyshiftcrewpositiontobeunmanneduponshiftchangeduetoanoncomingshiftcrewmanbeinglateorabsent.g)GoringanyabsenceoftheShiftSupervisorfromthecontrolroomwhiletheunitisin.OPERATIONALCONDITION1,2or3,anindividual(otherthantheShiftTech-nicalAdvisor)withavalidSeniorOperatorlicenseshallbedesignatedtoassumethecontrolroomcommandfunction.DuringanyabsenceoftheShiftSupervisorNINEMILEPOINT"UNIT26"5
TABLENOTATIONcontinue'dfromthecontrolroomwhiletheunitisinOPERATIONALCONOITION4or5,anindi-vidualwithavalidSeniorOperatorlicenseorOperatorlicenseshallbedesignatedtoassumethecontrolroomcommandfunction.NINEMILEPOINT-UNIT26"6jiOi)50185
AOMINISTRATIVECONTROLS6.2.3INOEPENOENTSAFETYENGINEERINGGROUPISEGFUNCTION6.2.3.1TheISEGshallfunctiontoexamineunitoperatingcharacteristics,NRCissuances,industryadvisories,LicenseeEventReports,andothersourcesofunitdesignandoperatingexperienceinformation,includingunitsofsimi-lardesign,whichmayindicateareasforimprovingunitsafety.TheISEGshallmake'detailedrecommendationsforrevisedprocedures,equipmentmodifications,maintenanceactivities,operationsactivities,orothermeansofimprovingunitsafetytotheSupervisorTechnicalSupportNuclear.COMPOSITION6.2.3.2TheISEGshallbecomposedofatleastfive,dedicated,full-timeengineerslocatedonsite.Eachshallhaveabachelor'sdegreeinengineeringorrelatedscienceandatleast2yearsprofessionallevelexperienceinhisfield,atleast1yearofwhichexperienceshallbeinthenuclearfield.RESPONSIBILITIES6.2.3.3snepenentlar.'XSE<T~CJM~kP6.2.3.4RecordsofactivitiesperformedbytheISEGshallbetained,andforwardedeachcalendarmonthtothe7'.2.4ASSISTANTSTATIONSHIFTSUPERVISORASSS%~4.prepared,main-cA~~~6.2.4.1TheASSSshallprovideadvisorytechnicalsupporttotheShiftSuper-visorintheareasofthermalhydraulics,reactorengineering,andplantanal-ysiswithregardtosafeoperationoftheunit.TheASSSsha11haveabachelor'sdegreein'scientificorengineeringdisciplineandshallhavereceivedspecifictrainingintheresponseandanalysisoftheunitfortran-sientsandaccidents,andinunitdesignandlayout,includingthecapabilitiesofinstrumentationandcontrolsinthecontrolroom.6.3FACILITYSTAFFUALIFICATIONSp,wsi/p,ws-s,)-I'la86.3.1Eachmemberoftheunitstaffshallmeetorexceedminimumqualifica-tionsof.forcomparablepositions,heASSSwhoshallmeetorexceedthequalificationsofRegulatoryGuide1.8,September1975.ThelicensedOperatorsandSeniorOperatorsshallalsomeetorexceedtheminimumqualificationsofthesupplementalrequirementsspecifiedinSectionsAandCofEnclosure1oftheMarch28,1980NRClettertoalllicensees.resle0NINEMILEPOINT-UNIT26-7QQV201985
ADMINISTRATIVECONTROLS6.4TRAININGAPSES./AMS-3,l-h5'lg6.4.1AretrainingandreplacementtrainingprogramfortheunitstaffshallbemaintainedunderthedirectionoftheSuperintendent-TrainingNuclear,shallmeetorexceedtherequirementsandrecommendationsofSection5.5ofdAppdi*APPPPPPPt5555ppitidimentsspecifiedinSectionsAandCofEnclosure1oftheMarch28,1980NRClettertoalllicensees,andshallincludefamiliarizationwithrelevantindustryoperationalexperience.AtrainingprogramfortheFireBrigadeshallbemaintainedunderthedirectionofthe.Superintendent-TrainingNuclearandSupervisor-FireProtectionNuclearandshallmeetorexceedtherequirementsofAppendixRto10CFRPart50.6.5REVIEWANDAUDIT6.5.1SITEOPERATIONSREVIEWCOMMITTEESORCFUNCTEON,6.5.1.1TheSORCshallfunctiontoadvisetheGeneralSuperintendent-NuclearGenerationonallmattersrelatedtonuclearsafety.COMPOSITION6.5.1.2The-SORCshallChairman:.Member:Member:Member:Member:Member:Member:Member:ember:Member:ref~~;ALTERNATESbecomposedofthe:GeneralSuperintendent-NuclearGenerationStationSuperintendent-NuclearGenerationTechnicalSuperintendent-NuclearGenerationSuperintendentTechnicalServices-NuclearSiteSuperintendentMaintenance-NuclearSupervisorInstrumentandControl-NuclearSuperintendentChemistryandRadiationManagementSupervisorReactorAnalysisSupervisorTechnicalSupport(Engineer)+ufsedp+prCedufu4erOqeu&iuueuJIfiulAm'M*Nu+6.5.1.3AllalternatemembersshallbeappointedinwritingbytheSORCChairmantoserveonatemporarybasis;however,nomorethantwoalternatesshallparticipateasvotingmembersinSORCactivitiesatanyonetime.MEETINGFREUENCY6.5.1.4TheSORCshallmeetatleastoncepercalendarmonthandasconvenedbytheSORCChairmanorhisdesignatedalternate.gUORUM6.5.1.5ThequorumoftheSORCnecessaryfortheperformanceoftheSORCresponsibilityandauthorityprovisionsoftheseTechnicalSpecificationsshallconsistoftheChairmanorhisdesignatedalternateand~membersincludingalternates.NINEMILEPOINT-UNIT26-8NOV201985
PM3FC.fLFNP8MP'/AOMINISTRATIVECONTROLSRESPONSIBILITIES6.5.1;6b.C.d.TheSORCshallberesponsiblefor:InvestigationofallviolationsoftheTechnicalSpecifications,includingthepreparationandforwardingofreportscoveringevaluationandrecommendationstopreventrecurrence,totheVicePresident-NuclearGenerationandtotheSafetyReviewandAuditBoard;ReviewallREPORTABLEEVENTS;rReviewofunitoperationstodetectpotentialhazardstonuclearsafety;Performanceofspecialreviews,investigations,oranalysesandreportsthereonasrequestedbytheGeneralSuperintendent-NuclearGenera-tionortheSafetyReviewandAuditBoard;6.5.1.7TheSORCshall:a~b.RECOROSRenderdeterminationsin,writingwithregardtowhetherornoteachitemconsideredunderSpecification6.5.1.6.a.throughd.constitutesanunreviewedsafetyquestion.Providewrittennotificationwithin24hourstotheVicePresident--NuclearGenerationandtheSafetyReviewandAuditBoardofdisagree-mentbetweentheSORCandtheGeneralSuperintendent-NuclearGenera-tion;however,theGeneralSuperintendent-Nuc'1earGenerationshallhaveresponsibilityforresolutionofsuchdisagreementspursuanttoSpecification6.1.1.6.5.1.8:TheSORCshallmaintainwrittenminutesofeachSORCmeeting.CopiesshallbeprovidedtotheVicePresident-NuclearGenerationandtheSafetyReviewandAuditBoard.6.5.2TECHNICALREVIEMANDCONTROLACTIVITIES6.5.2.1EachprocedureandprogramrequiredbySpecification6.8andotherprocedureswhichaffectnuclearsafety,andchangesthereto,shallbepreparedbyaqualifiedindividual/organization.Eachsuchprocedure,and.changesthereto,shallbereviewedbyanindividual/groupotherthantheindividual/groupwhichpreparedtheprocedure,orchangesthereto,butwhomaybefromthesameorganizationastheindividual/groupwhichpreparedtheprocedure,orchangesthereto.Approvalofproceduresandprogramsandchangestheretoandtheirsafetyevaluations,shallbecontrolledbyadministrativeprocedures.6.5.2.2ProposedchangestotheTechnicalSpecificationsshallbepreparedbyaqualifiedindividual/organization.ThepreparationofeachproposedTechnicalSpecificationschangeshallbereviewedbyanindividual/groupotherthantheindividual/groupwhichpreparedtheproposedchange,butwhomaybefromthesameorganizationastheindividual/groupwhichpreparedtheproposedchange.ProposedchangestotheTechnicalSpecificationsshallbeapprovedbytheGeneralSuperintendent-NuclearGeneration.NINEMILEPOINT"UNIT26"9Hav20Sla
AOMINISTRATIVECONTROLSACTIVITIES(Continued)6.5.2.3Proposedmodificationstounitstructures,systemsandcomponentsthataffectnuclearsafetyshallbedesignedbyaqualifiedindividual/organization.Eachsuchmodificationshallbereviewedbyanindividual/groupotherthantheindividual/groupwhichdesignedthemodification,butwhomaybefromthesameorganizationastheindividual/groupwhichdesignedthemodification.Proposedmodificationstostructures,systemsandcomponentsandthesafetyevaluationsshallbeapprovedpriortoimplementationbytheGeneralSuperintendent"NuclearGeneration;ortheStationSuperintendent-NuclearGeneration;ortheTechnicalSuperintendent-NuclearGenerationaspreviously~~sadbytheGeneralSuperintendent-NuclearGeneration.CLCJiNeh.6.5.2.4IndividualsresponsibleforreviewsperformedinaccordancewithSpecifications6.5.2.1,6.5.2.2and6.5.2.3shallbemembersofthestationsupervisorystaff,previouslydesignatedbytheGeneralSuperintendent-NuclearGenerationtoperform-suchreviews.Eachsuchreviewshallinc'ludeadetermina-tionofwhe'therornotadditional,cross-disciplinary,reviewisnecessary.Ifdeemednecessarysuchreviewshallbeperformedbytheappropriatedesignatedstationreviewpersonnel.6.5.2.5ProposedtestsandexperimentswhichaffectstationnuclearsafetyandarenotaddressedintheFSARorTechnicalSpecificationsandtheirsafetyevaluationsshallbereviewedbytheGeneralSuperintendent-NuclearGeneration;ororbytheStationSuperintendent-NuclearGeneration,ortheTechnicalSuperintendent-Nuclear-Generation-as-previousIy-designat'ed"5ytheGeneralSuperintendent-NuclearGeneration.6.5.2.6TheGeneralSuperintendent-NuclearGenerationshallassuretheper-formanceofspecialreviewsandinvestigations,andthepreparationandsub-mittalofreportsthereon,asrequestedbytheVicePresident"NuclearGeneration.6.5.2.7Thefacilitysecurityprogram,andimplementingprocedures,shallbereviewedatleastevery12months.RecommendedchangesshallbeapprovedbytheGeneralSuperintendent-NuclearGenerationandtransmittedtotheVicePresident-NuclearGeneration,andtotheChairmanoftheSafetyReviewandAuditBoard.6.5.2.8Thefacilityemergencyplan,andimplementingproceduresshallbereviewedatleastevery12months.RecommendedchangesshallbeapprovedbytheGeneralSuperintendent-NuclearGenerationandtransmittedtotheVicePresident-NuclearGenerationandtotheChairmanoftheSafetyReviewandAuditBoard.6.5.2.9TheGeneralSuperindendent-NuclearGenerationshallassuretheper-formanceofareviewbyaqualifiedindividual/organizationofchangestotheRadiologicalMasteTreatmentsystems.6.5.2.10Reviewofanyaccidental,unplanned,oruncontrolledradioactivereleaseincludingthepreparationofreportscoveringevaluation,recommenda-tionsanddispositionof.hecorrectiveactiontopreventrecurrenceandtheforwardingofthesereportstotheVicePresident-NuclearGenerationandtotheSafetyReviewandAuditBoard.NINEMILEPOINT-UNIT26"10WOVc 0 ADMINISTRATIVECONTROLSBKF87g7py>@peACTIVITIES(Continued)6.5.2.11RofchangestotheProcessControlProgramandtheOffsiteDoseCalcuaionManual.ApprovalofanychangesshallbemadebytheGeneralSuperintendent-NuclearGenerationorhisdesigneebefore'implementationofsuchchanges.6.5.2.12ReportsdocumentingeachoftheactivitiesperformedunderSpecifica-tions6.5.2.1through6.5.2.9shallbemaintained.CopiesshallbeprovidedtotheVicePresident-NuclearGenerationandtheSafetyReviewandAuditBoard.6.5.3SAFETYREVIEWANDAUDITBOARDSRABFUNCTION6.5.3.1TheSRABshallfunctiontoprovideindependentreviewandauditofdesignatedactivitiesintheareasof:aOb.C.e.g.Nuclearpowerplantoperations,Nuclearengineering,Chemistryandradiochemistry,Metallurgy,Instrumentationandcontrol,Radiologicalsafety,Mechanicalandelectricalengineering,gualityassurancepractices,and(Otherappropriatefieldsassociatedwiththeuniquecharacteristicsofthenuclearpowerplant).TheSRABshallreporttoandadvisetheVicePresident-NuclearGenerationonthoseareasofresponsibilityinSpecifications6.5.2.7and6.5.2.8.COMPOSITION6.5.3.2TheSRABshallbecomposedofthe:Chairman:Member:Member:Member:Member:Member:ALTERNATESVicePresident-NuclearGenerationoeA~Ae~g-,<c-c~wau@e~oc-GeneralSuperintendent-NuclearOperationvie.s--p~~ii4<+StaffEngineer-NuclearStaff,Engineer-MechanicalorNuclearStaffEngineer-EnvironmentalConsultant(Specification6.5.3.4)6.5.3.3AllalternatemembersshallbeappointedinwritingbytheSRABChairmantoserveonatemporarybasis;however,nomorethantwoalternatesshallparticipateasvotingmembersinSRABactivitiesatanyonetime.NINEMILEPOINT-UNIT26-11HQVa0>985 0 ADMINISTRATIVECONTROLSCONSULTANTS6.5.3.4Consultantsshallbeutilizedasdeterminedbythe,SRABDirectortoprovideexpertadvicetotheSRAB.MEETINGFREUENCY6.5.3.5TheSRABshallmeetatleastoncepercalendarquarterduringtheinitialyearofunitoperationfollowingfuelloadingandatleastonceper6monthsthereafter.UORUM6.5.3.6ThequorumoftheSRABnecessaryfortheperformanceoftheSRABreviewandauditfunctionsoftheseTechnicalSpecificationsshallconsistoftheChairmanorhisdesignatedalternateandatleastthreeSRABmembersincludingalternates.Nomorethanaminorityofthequorumshallhavelineresponsibilityforoperationoftheunit.REVIEW6.5.3.7a(b.C.d.e.TheSRABshallberesponsibleforthereviewof:Thesafetyevaluationsfor(1)changestoprocedures,equipment,orsystems;and(2)testsorexperimentscompletedundertheprovisionof10CFR50.59toverifythatsuchactionsdidnotconstitutean.unreviewedsafetyquestion;Proposedchangestoprocedures,equipment,orsystemswhichinvol.veanunreviewedsafetyquestionasdefinedin10CFR50.59;Proposedtestsorexperimentswhichinvolveanunreviewedsafetyquestionasdefinedin10CFR50.59;ProposedchangestoTechnicalSpecificationsorthisOperatingLicense;Violationsofcodes,regulations,orders,TechnicalSpecifications,licenserequirements,orofinternalproceduresorinstructionshavingnuclearsafetysignificance;Significantoperatingabnormalitiesordeviationsfromnormalandexpectedperformanceofunitequipmentthataffectnuclearsafety;g.AllREPORTABLEEVENTS;h.Allrecognizedindicationsofanunanticipateddeficiencyinsomeaspectofdesignoroperationofstructures,systems,orcomponentsthatcouldaffectnuclearsafety;andReportsandmeetingminutesoftheSORC.NINEMILEPOINT"UNIT26-12HQV201985
ADMINISTRATIVECONTROLSAUDITS6.5.3.8AuditsofunitactivitiesshallbeperformedunderthecognizanceoftheSRAB.Theseauditsshallencompass:'a0b.C.d.e.TheconformanceofunitoperationtoprovisionscontainedwithintheTechnicalSpecificationsandapplicablelicenseconditionsatleastonceper12months;Theperformance,trainingandqualificationsoftheentireunitstaffatleastonceperi2months;Theresultsofactionstakentocorrectdeficienciesoccurringinunitequipment,structures,systems,ormethodofoperationthataffectnuclearsafety,atleastonceper6months;TheperformanceofactivitiesrequiredbytheOperationalgualityAssuranceProgramtomeetthecriteriaofAppendixB,10CFRPart50,atleastonceper24months;TheUnitEmergencyPlanandimplementingproceduresatleastonceevery12months.TheUnitSecurityPlanandimplementingproceduresatleastonceeverylgmonths.TheRadiologicalEnvironmentalMonitoringProgramandtheresultsthereofatleastonce-per12months;TheOFFSITEDOSECALCULATIONMANUALandimplementingproceduresatleastonceper24months;ThePROCESSCONTROLPROGRAMandimplementingproceduresforprocessingandpackagingofradioactivewastesatleastonce~4months;P8f'heperformanceofactivitiesrequiredbythegualityssuranceProgramtomeettheCriteriaofAppendixB10CFR50atleastonceperyear.AnyotherareaofunitoperationconsideredappropriatebytheSRABortheVicePresident-NuclearGenerationortheVicePresident"NuclearEngineeringandLicensing.RECORDSIo6.5.3WRecordsofSRABactivitiesshallbeprepared,approved,anddistributedasindicatedbelow:aoMinutesofeachSRABmeetingshallbeprepared,approved,andfor"wardedtotheVicePresident-NuclearGenerationandVicePresident-NuclearEngineeringandLicensingwithin+5daysfollowingeachmeeting.90NINEMILEPOINT"UNIT26-13HQY2c}.'35
ADMINISTRATIVECONTROLSFiick~5kii)P~7KP7RECORDS(Continued)b.ReportsofreviewsencompassedbySpecification6.5.3.7e,,g,hshallbeprepared,approved,andforwardedtotheVicePresident-NuclearGeneration-andVicePresident-NuclearEngineeringandLicensingwithin14daysfollowingcompletionofthereview..c.AuditreportsencompassedbySpecification6.5.2.8shallbeforwardedtotheVicePresident-NuclearGenerationandVicePresident-NuclearEngineeringandLicensingandtothemanagementpositionsresponsiblefortheareasauditedwithin90daysaftercompletionoftheauditbytheauditingorganization.AUTHORITY6.5.3.38TheSRABshallreporttoandadvisetheVicePresident-NuclearGenerationandVicePresident-NuclearEngineeringandLicensingonthoseareasofresponsibilityspecifiedinSection6.5.3.7and6.5.3.8.6.6REPORTABLEEVENTACTION6.6..1ThefollowingactionsshallbetakenforREPORTABLEEVENTS:So,pa~a.TheCommissionshallbenotiiedandareportsubmittedpursuanttotherequirementsofSectio50.73to10CFRPart50,andb.EachREPORTABLEEVENTtotheCommissionshallbereviewedbytheSORC,andtheresultsofthisreviewshallbesubmittedtotheSRABandtheVicePresident-NuclearGeneration.6.7SAFETYLIMITVIOLATION6.7.1Thefollowingactionsshall.betakenintheeventaSafetyLimitisviolated:a.TheNRCOperationsCentershallbenotifiedby.telephoneassoonaspossibleandinallcaseswithin1hour.rs.b.C.ASafetyLimitViolationReportshallbeprepared.ThereportshallbereviewedbytheSORC.Thisreportshalldescribe(1)applicablecircumstancesprecedingtheviolation,(2)effectsoftheviolationuponunitcomponents,systems,orstructures,and(3)correctiveactiontakentopreventrecurrence.TheSafetyLimitViolationReportshallbesubmittedtotheCommissionwithin30daysoftheviolationandtotheSRAB,andtheVicePresident-NuclearGenerationimmediately.NINEMILEPOINT"UNIT26-14NAv9n>aar.
ADMINISTRATIVECONTROLS'.8PROCEDURESANDPROGRAMS6.8.1Writtenproceduresshallbeestablished,implemented,andmaintainedcoveringtheactivitiesreferencedbelow:aob.Cod'.f.,gh.1~J.TheapplicableproceduresrecommendedinAppendixAofRegulatoryGuide1.33,Revision2,February1978.TheapplicableproceduresrequiredtoimplementtherequirementsofNUREG-0737.Refuelingoperations.Surveillanceandtestactivitiesofsafety-relatedequipment.SecurityPlanimplementation.EmergencyPlanimplementation.FireProtectionProgramimplementation.PROCESSCONTROLPROGRAMimplementation.OFFSITEDOSECALCULATIONMANUALimplementation;andgualityAssuranceforeffluentandenvironmentalmonitoring.6.8.2EachprocedurefSpecification6.8.l,andchangesthereto,shallbereviewedapprovedbytheGeneralSuperintendent-NuclearGenerationpriortoimplementationandreviewedperiodicallyassetforthinadministrativeprocedures.6.8.3TemporarychangestoproceduresofSpecification6.8.1maybemadepro-vided:a.Theintentoftheoriginalprocedureisnotaltered;b.Thechangeisapprovedbytwomembersoftheunitmanagementstaff,atleastoneofwhomholdsaSeniorOperatorlicenseontheunitaffected;andThhgTdd,Td~,dddhyhGeneralSuperintendent-NuclearGenerationwithin14daysofimplementation.46.8.4Thefollowingprogramsshallbeestablished,implemented,andmaintained:'\a.PrimarCoolantSourcesOutsideContainmentAprogramtoreduceleakagefromthoseportionsofsysemsoutsidecontainmentthatcouldcontainhighlyradioactivefluidsduringaserioustransientoraccidenttoaslowaspracticallevels.Thesystemsincludethe(HPCS,RHR,RCIC,hydrogenrecombiner,processsampling,containmentandstandbygastreatment)systems.Thepro-gramshallincludethefollowing:1.Preventivemaintenanceandperiodicvisualinspectionrequirements,and2.Integratedleaktestrequirementsforeachsystematrefuelingcycleintervalsorless..NINEMILEPOINT-UNIT26-15NOV201985 ' ADMINISTRATIVECONTROLSPROCEDURESANDPROGRAMS(Continued)b.In"PlantRadiationMonitorinAprogramwhichwillensure-thecapabilitytoaccuratelydeterminetheairborneiodineconcentrationinvitalareasunderaccidentconditions.Thisprogramshallincludethefollowing:1.'rainingof'ersonnel,2.Proceduresformonitoring,and3.Provisionsformaintenanceofsamplingandanalysisequipment.c.Post-accidentSamlinA-programwhichwillensurethecapabilitytoobtainandanalyzereactorcoolant,radioactiveiodinesandparticulatesinplantgaseousefflu-ents,andcontainmentatmospheresamplesunderaccidentconditions.Theprogramshallincludethefollowing:'.Trainingofpersonnel,2.Proceduresforsampling.andanalysis,and3;Provisionsformaintenanceofsamplingandanalysisequipment.6.9REPORTINGREUIREMENTSROUTINEREPORTS6.9.1InadditiontotheapplicablereportingrequirementsofTitle10,CodeofFederalRegulations,thefollowingreportsshallbesubmittedtotheRegionalAdministratoroftheRegionalOfficeoftheNRCunlessotherwisenoted.STARTUPREPORT6.9.1.1Asummaryreportofplantstartupandpowerescalationtestingshallbesubmittedfollowing(1)receiptofanOperatingLicense,(2)amendmenttothelicenseinvolvingaplannedincreaseinpowerlevel,(3)installationoffuelthathasadifferentdesignorhasbeenmanufacturedbyadifferentfuelsupplier,and(4)modificationsthatmayhavesignificantlyalteredthenuclear,thermal,,orhydraulicperformanceoftheunit.6.9.1.2ThestartupreportshalladdresseachofthetestsidentifiedintheFinalSafetyAnalysisReportandshallincludeadescriptionofthemeasuredvaluesoftheoperatingconditionsorcharacteristicsobtaineddunngthetestprogramandacomparisonofthesevalueswithdesignpredictionsandspecifica-tions.Anycorrectiveactionsthatwererequiredtoobtainsatisfactoryoperationshallalsobedescribed.Anyadditionalspecificdetailsrequiredinlicenseconditionsbasedonothercommitmentsshallbeincludedinthisreport.NINEMILEPOINT-UNIT26"16ggyi0ts85
AOMINISTRATIVECONTROLSSTARTUPREPORT(Continued)6.9.1.3Startupreportsshallbesubmittedwithin(1)90daysfollowingcomple-tionofthestartuptestprogram,(2)90-daysfollowingresumptionorcommence-mentofcommercialpoweroperation,or(3)9monthsfollowinginitialcriticality,whicheverisearliest.Ifthestartupreportdoesnotcoverallthreeevents(i.e.,initialcriticality,completionofstartuptestprogram,andresumptionorcommencementofcommercialoperation)supplementaryreportsshallbesubmittedatleastevery3monthsuntilallthreeeventshavebeencompleted.ANNUALREPORTS6.9.1.4AnnualreportscoveringtheactivitiesoftheunitasdescribedbelowforthepreviouscalendaryearshallbesubmittedpriortoMarch1ofeachyear.TheinitialreportshallbesubmittedpriortoMarch1oftheyearfollowinginitialcriticaIity.6.9.1.5Reportsrequiredonanannualbasisshallinclude:a0Atabulationonanannualbasisofthenumberofstation,utility,andotherpersonnel(includingcontractors)receivingexposuresgreaterthan100mremlyrandtheirassociatedman-remexposureaccordingtoworkandjobfunctions"(e.g.,reactoroperationsandsurveillance,inserviceinspection,routinemaintenance,specialmaintenance(describmaintenance),wasteprocessing,andrefueling).Thedoseassignmentstovariousdutyfunctions.maybeestimatedbasedonpocketdosimeter,thermoluminescentdosimeter(TLO),orfilm,badgemeasure-ments.Smallexposurestotallinglessthan20Koftheindividualtotaldoseneednotbeaccountedfor.Intheaggregate,atleast80Kofthetotalwhole-bodydosereceivedfromexternalsourcesshouldbeassignedtospecificmajorworkfunctions;b.TheresultsofspecificactivityanalysisinwhichtheprimarycoolantexceededthelimitsofSpecification3.4.5.Thefollowinginformationshallbeincluded:(1)Reactorpowerhistorystarting48hourspriortothefirstsampleinwhichthelimitwasexceeded;(2)Resultsofthelastisotopicanalysisforradioiodineperformedpriortoexceed=ingthelimit,resultsofanalysiswhilelimitwasexceededandre-sultsofoneanalysisaftertheradioiodineactivitywasreducedtolessthanlimit.Eachresultshouldincludedateandtimeofsamplingandtheradioiodineconcentrations;(3)Clean>>upsystemflowhistorystarting48hourspriortothefirstsampleinwhichthelimitwasexceeded;(4)GraphoftheI-131concentrationandoneotherradioio-dineisotopeconcentrationinmicrocuriespergram-asafunctionoftimeforthedurationofthespecificactivityabovethesteady-statelevel;and(5)Thetimedurationwhenthespecificactivjtyoftheprimarycoolantexceededtheradioiodinelimit.Thistabulationsupplementstherequirementsof520.407of10CFRPart20.NINEMILEPOINT"UNIT26-17N0Y20)N5 Jg0 ADMINISTRATIVECONTROLSANNUALREPORTS(Continued)c.Documentationofallchallengestosafety/reliefvalves;andd.Anyotherunituniquereportsrequired'y7~J~c~L-S~cgEc4'tioOS~MONTHLYOPERATINGREPORTS6.9.1.6Routinereportsofoperatingstatisticsandshutdownexperience,in"eludingdocumentationofallchallengestothemainsteamsystemsafety/reliefvalves,shallbesubmittedonamonthlybasistotheDirector,OfficeofResourceManagement,U.S.Nuclear--RegulatoryCommission,Washington,D.C.20555,withacopytotheRegionalAdministratoroftheRegionalOfficeoftheNRCnolaterthanthe15thofeachmonthfollowingthecalendarmonthcoveredbythereport.ANNUALRADIOLOGICALENVIRONMENTALOPERATINGREPORT"6.9.1.7RoutineAnnualRadiologicalEnvironmentalOperatingReportscoveringtheoperationoftheunitduringthepreviouscalendaryearshallbesubmittedpriortoMay1ofeachyear.TheinitialreportshallbesubmittedpriortoMay1of'heyearfollowinginitialcriticality.TheAnnualRadiologicnvironmenta1OperatingReportsshallincludesum-maries,interpretationsdananalysisoftrendsoftheresultsoftheradio-logicalenvironmentalurveillanceactivitiesforthereportperiod,includingacomparisonasappropriatewith'preoperationalstudies,operationalcontrols,previouse'nvlrnmrveillancereports,andanassessmentoftheobservedimpactsoftheplantoperationontheenvironment.ThereportsshallalsoincludetheresultsoftheLandUseCensusrequiredbySpecification3.12.2.The'AnnualRadiologicalEnvironmentalOperatingReportsshallincludetheresultsofanalysisofallradiologicalenvironmentalsamplesandofallenvironmentalradiationmeasurementstakenduringtheperiodpursuanttothelocationsspecifiedinthetableandfiguresintheOffsiteDoseCalculationManual,aswellassummarizedandtabulatedresultsoftheseanalysesandmeasurementsintheformatofthetableintheRadiologicalAssessmentBranch~TechnicalPosition,Revision1,November1979.Intheeventthatsomeindivi-dualresultsarenotavailableforinclusionwiththereport,thereportshallbesubmittednotingandexplainingthereasonsforthemissingresults.Themissingdatashallbesubmittedassoonaspossibleinasupplementreport.Thereportsshallalsoincludethefollowing:asummarydescriptionoftheRadiologicalEnvironmemtalMonitoringProgram;atleasttwolegiblemaps""cover-ingallsamplinglocationskeyedtoatablegivingdistancesanddirectionsfromthecenterlineofonereactor;theresultsoflicenseeparticipationintheInterlaboratoryComparisonProgram,requiredbySpecification3.12.3;discussionofalldeviationsfromtheSamplingScheduleofTable3.12-1;anddiscussionofallanalysesinwhichtheLLDrequiredbyTable4.12-1wasnotachievable.sA.eAsing'lesubmittalmaybemadeforamultipleunit~~t.Thesubmittalshouldcombinethosesectionsthatarecommontoallunitsatthestation.OnemapshallcoverstationsneartheSITEBOUNDARY;asecondshallincludethemoredistantstations.NINEMILEPOINT-UNIT26"18 'II ADMINISTRATIVECONTROLSSEMIANNUAL'ADIOACTIVEEFFLUENTRELEASEREPORT"6.9.1.8RoutineSemiannualRadioactiveEffluentReleaseReportscoveringtheoperationoftheunitduringtheprevious6monthsofoperationshallbesubmittedwithin60daysafterJanuary1andJuly1ofeachyear.Theperiodofthefirstreportshallbeginwiththedateofinitialcriticality.TheSemiannualRadioactiveEffluentReleaseReportsshallincludeasummaryofthequantitiesofradioactiveliquidandgaseouseffluentsandsolidwastereleasedfromtheunitasoutlinedinRegulatoryGuide1.21,"Measuring,Evaluating,andReportingRadioactivityinSolidMastesandReleasesofRadioactiveMaterialsinLiquidandGaseousEffluentsfromLight-Mater-CooledNuclearPowerPlants,"Revision1,June1974,withdatasummarizedonaquarterlybasisfollowingtheformatofAppendixBthereof.Forsolidwastes,theformatforTable3inAppendixBshallbesupplementedwiththreeadditionalcategories:classofsolidwastes(asdefinedby10CFRPart61),typeofcontainer(e.g.,LSA,TypeA,TypeB,Largeguantity)andSOLIDIFICATIONagentorabsorbent(e.g.,cement,ureaformaldehyde).TheSemiannualRadioactiveEffluentReleaseReporttobesubmittedwithin60daysafterJanuary'ofeachyearshallincludeanannualsummaryofhourlymeteorologicaldatacollectedoverthepreviousyear.Thisannualsummarymaybeeitherintheformofanhourby'-hourlistingonmagnetictapeofwindspeed,winddirection,atmosphericstability,andprecipitation(ifmeasured),orintheformofjointfrequencdistributionofwindspeed,winddirection,andatmosphericstability.*"Thissamereportshall,includeanassessmentof".theradiation.dosesduetotheradioactiveliquidandgaseouseff'Juentsreleasedfromtheunitorstationduringthepreviouscalendaryear.ThissamereportshallalsoincludeanassessmentoftheradiationdosesfromradioactiveliquidandgaseouseffluentstoMEMBERSOFTHEPUBLICduetotheiractivitiesinsidetheSITEBOUNDARY(Figure5.1.3)duringthereportperiod.Allassumptionsusedinmakingtheseassessments,i.e.,specificactivity,exposuretime,andlocation,shallbeincludedinthesereports.Themeteorologicalconditionsconcurrentwiththetimeofreleaseofradioactivematerialsingaseouseffluents,asdeterminedbysamplingfrequencyandmeasurement,shallbeusedfordeterminingthegaseouspathwaydoses.Theassessmentofradiationdosesshallbeperformedinaccordancewiththemethodologyandparametersin-theOFFSITEDOSECALCULATIONMANUAL(ODCM).TheSemiannualRadioactiveEffluentReleaseReporttobesubmittedwithin60daysafterJanuary1ofeachyearshallalsoincludeanassessmentofradiationdosestothelikelymostexposedMEMBEROFTHEPUBLICfromreactorreleasesandothernearbyuraniumfuelcyclesources,includingdosesfromAsinglesubmittalmaybemadeforamultipleunitstation.Thesubmittalshouldcombinethosesectionsthatarecommontoallunitsatthestation;however,forunitswithseparateradwastesystems,thesubmittalshallspecifythereleasesofradioactivematerialfromeachunit.M(InlieuofsubmissionwiththeSemiannualRadoactiveEffluentReleaseReport,thelicenseehastheoptionofretainingthissummaryofrequiredmeteorolog-icaldataonsiteinafilethatshallbeprovidedtotheNRCuponrequest.NINEMILEPOINT-UNIT26"19gaygO1985
ADMINISTRATIVECONTROLSSEMIANNUALRADIOACTIVEEFFLUENTRELEASEREPORT(Continued)primaryeffluentpathwaysanddirectradiation,forthepreviouscalendaryeartoshowconformancewith40CFR.Part190,"EnvironmentalRadiationProtectionStandardsforNuclearPowerOperation.".AcceptablemethodsforcalculatingthedosecontributionfromliquidandgaseouseffluentsaregivenintheODCM.TheSemiannualRadioactiveEffluentReleaseReportsshallincludealistanddescriptionofunplannedreleasesfromthesitetoUNRESTRICTEDAREASofradioactivematerialsingaseousandliquideffluentsmadeduringthereportingperiod.TheSemiannualRadioactiveEffluentReleaseReportsshallincludeanychangesmadeduringthereportingperiodtothePROCESSCONTROLPROGRAM(PCP)andtotheOFFSITEDOSECALCULATIONMANUAL(ODCM),pursuanttoSpecifications6.13and6.14,respectively,aswellasanymajorchangetoLiquid,Gaseous,orSolidRadwasteTreatmentSystemspursuanttoSpecification6.15.Itshallalsoincludealistingofnewlocationsfordosecalculationsand/orenvironmentalmonitoringidentifiedbytheLandUseCensuspursuanttoSpecification3.12.2."TheSemiannualRadioactiveEffluentReleaseReportsshallalsoincludethefollowing:anexplanationastowhytheinoperabilityofliquidorgaseouseffluentmonitoringinstrumentationwasnotcorrectedwithinthetimespecifiedinSpecification3.3.'3.10or3.3.3.11,respectively;anddescriptionofthe"-events"leading-toliquidholduptanksorgasstoragetanksexceedingthelimitsofSpecification3.11.1.4or3.11.2.6,respectively.SPECIALREPORTS6.9.2SpecialreportsshallbesubmittedtotheRegionalAdministratoroftheRegionalOfficeoftheNRCwithinthetimeperiodspecifiedforeachreport.6.10RECORDRETENTION6.10.1InadditiontotheapplicablerecordretentionrequirementsofTitle10,CodeofFederalRegulations,thefollowingrecordsshallberetainedforatleasttheminimumperiodindicated.6.10.1.1Thefollowingrecordsshallberetainedforatleast5years:aOb.C.Recordsandlogsofunitoperationcoveringtimeintervalateachpowerlevel.Recordsandlogsofprincipalmaintenanceactivities,inspections,repair,andreplacementofprincipalitemsofequipmentrelatedtonuclearsafety.AllREPORTABLEEVENTSsubmittedtotheCommission.Recordsofsurveillanceactivities,inspections,andcalibrationsrequiredbytheseTechnicalSpecifications.NINEMILEPOINT"UNIT26-20goy801985
AOMINISTRATIVECONTROLS~j+,~~qfggiFiPgwJRECORORETENTION(Continued)e.RecordsofchangesmadetotheproceduresrequiredbySpecification6.8.1.f.Recordsofradioactiveshipments.g.Recordsofsealedsourceandfissiondetectorleaktestsandresults.h.Recordsofannualphysicalinventoryofallsealedsourcematerialofrecord.Recordsofreactortestsandexperiments.6.10.1.2ThefollowingrecordsshallberetainedforthedurationoftheunitOperatingLicense:RecordsanddrawingchangesreflectingunitdesignmodificationsmadetosystemsandequipmentdescribedintheFinalSafetyAnalysisReport.b.C.Recordsofnewandirradiatedfuelinventory,fueltransfers,andas.semblyburnuphistories.Recordsofradiationexposureforallindividualsenteringradiationcontrolareas.d.e.Recordsofgaseousandliquidradioactivematerialreleasedtotheenvirons.Recordsoftransientot'operationalcyclesforthoseunitcomponentsidentifiedinTable5.7.1-1.goh.Recordsofreactortestsandexperiments.Recordsoftrainingandqualificationforcurrentmembersoftheunitstaff.RecordsofinserviceinspectionsperformedpursuanttotheseTechnicalSpecifications.RecordsofqualityassuranceactivitiesrequiredbytheOperationalgualityAssuranceManual,andnotlistedinSpecification6.10.1.1.Recordsofreviewsperformedforchangesmadetoproceduresorequip-mentorreviewsoftestsandexperimentspursuantto10CFR50.59.k.RecordsofmeetingsoftheSORCandtheSRAB.Recordsoftheservicelivesofallsnubbersincludingthedateatwhichtheservicelifecommencesandassociatedinstallationandmaintenancerecords.NINEMILEPOINT"UNIT26"21ggygo1985 0 .AOMINISTRATIVECONTROLSPi%~3F53Pj'Qfpgp!fRECORDRETENTION(Continued)RecordsofanalysesrequiredbytheRadiologicalEnvironmentalMoni-toringProgramthatwouldpermitevaluationoftheaccuracyoftheanalysisatalaterdate.ThisshouldincludeprocedureseffectiveatspecifiedtimesandgArecordsshowingthattheseprocedureswerefollowed.n.Recordsofunitradiationandcontaminationsurveys.6.llRADIATIONPROTECTIONPROGRAM6.11.1Proceduresforpersonnelradiationprotectionshallbepreparedcon-sistentwiththerequirementsof10CFRPart20andshallbeapproved,main-tained,andadheredtoforalloperationsinvolvingpersonnelradiationexposure.6.12HIGHRADIATIONAREA6.12.1.Inlieuofthe"controldevice"or"alarmsignal"requiredbyparagraph20.203(c)(2)of10CFRPart20,eachhighradiationareainwhichtheintensityofradiationisgreaterthan100mrem/hPSutlessthan1000mrem/hr~sKa11bebarricadedandconspicuouslypostedasahighradiationareaandentrancetheretoshallbecontrolledbyrequiringissuanceofaRadiationWorkPermit(RWP)".Anyindividualorgroupofindividualspermittedtoentersuchareasshallbeprovidedwithoraccompaniedbyoneormoreofthefollowing:a.Aradiationmonitoringdevicewhichcontinuouslyindicatestheradiationdoserateinthearea.b.Aradiationmonitoringdevicewhichcontinuouslyintegratestheradiationdoserateintheareaandalarmswhenapresetintegrateddoseisreceived.Entryintosuchareaswiththismonitoringdevicemaybemadeafterthedoseratelevelsintheareahavebeenestablishedandpersonnelhavebeenmadeknowledgeableofthem.C.Anindividualqualifiedinradiationprotection(i.e.,qualifiedinradiationprotectionprocedures)witharadiationdoseratemonitoriiigdevicewhoisresponsibleforprovidingpositivecontrolovertheactivitieswithintheareaandshallperformperiodicradiationsur-veillanceatthefrequencyspecifiedbytheRadiationProtectionSuper"visororhisdesigneeintheRWP.Healthphysicspersonnelorpersonnelescortedbyhealthphysics'personnelshallbeexemptfromtheRWPissuancerequirementduringtheperformanceoftheirassignedradiationprotectionduties,providedtheyareotherwisefollowingplantradiationprotectionproceduresforentryintohighradiationareas.~3JMW~X9A.~~iliadNINEMILEPOINT"UNIT26-22ggy201S85
ADMINISTRATIVECONTROLS-HIGHRADIATIONAREA(Continued)6.12.2InadditiontotherequirementsofSpecification6.12.1,areasaccessibletopersonnelwithradiationlevelssuchthatamajorportionofthebodycouldreceivein1houradosegreaterthan1000mrem""shallbeprovided,withlackeddoorstopreventunauthorizedentry,andthekeyedaccessshallbemaintainedundertheadministrativecontroloftheStationShiftSupervisororhisdesigneeondutyand/ortheRadiationProtectionSupervisororhisdesignee.DoorsshallremainlockedexceptduringperiodsofaccessbypersonnelunderanapprovedRWPwhichshallspecifythedoseratelevelsintheimmediateworkareaandthemaximumallowablestaytimeforindividualsinthatarea.Forindividualareasaccessibletopersonnelwithradiationlevelssuchthatamajorportionofthebodycou'Idreceivein1houradoseinexcessof1000mrem*~thatarelocatedwithinlargeareas,suchasthedrywell,wherenoenclosureexistsforpurposesoflocking,andnoenclosurecanbereasonablyconstructedaroundtheindividualareas,thenthatareashallberopedoff,conspicuouslyposted,andaflashing'lightshallbeactivatedasawarningdevice.InlieuofthestaytimespecificationoftheRWP,continuoussurveillancedirectorremote(suchasuseofclosedcircuitTVcameras),maybemadebypersonnelqualified'inradiationprotectionprocedurestoprovidepositiveexposurecontrolovertheactivitieswithinthearea.6.13PROCESSCONTROLPROGRAMPCP6.13.1ThePCPshallbeapprovedbytheCommissionpriortoimplementation.6.13.2Licensee-initiatedchangestothePCP:~~~~~~a.ShallbesubmittedtotheCommissionintheSemiannualRadioactiveEffluentReleaseReportfortheperiodinwhichthechange(s)wasmade.Thissubmittalshallcontain:1)Sufficientlydetailedinformationtototallysupporttherationaleforthechangewithoutbenefitofadditionalorsupplementalinformation;2)Adeterminationthatthechangedidnotreducetheoverallconformanceofthesolidifiedwasteproducttoexistingcriteriaforsolidwastes;and3)DocumentationofthefactthatthechangehasbeenreviewedandfoundacceptablebytheSORC.b.ShallbecomeeffectiveuponreviewandacceptancebytheSORC.6.14OFFSITEDOSECALCULATIONMANUALODCM6.14.1TheODCMshallbeapprovedbytheCommissionpriortoimplementation.NINEMILEPOINT-UNIT26-23'NOV20l985
ADMINISTRATIVECONTROLS500$53P~P8M""7OFFSITEDOSECALCULATIONMANUALODCM(Continued)6.14.2Licensee-initiatedchangestotheODCM:a.ShallbesubmittedtotheCommissionintheSemiannualRadioactiveEffluentReleaseReportfortheperiodinwhichthechange(s)wasmadeeffective.Thissubmittalshallcontain:1)Sufficientlydetailedinformationtototallysupporttherationaleforthechangewithoutbenefitofadditionalorsupplementalinformation.InformationsubmittedshouldconsistofapackageofthosepagesoftheODCMtobechangedwitheachpagenumbered,datedandcontainingtherevisionnumber,togetherwithappropriateanalysesorevaluationsjustifyingthechange(s);2)Adeterminationthatthechangewillnotreducetheaccuracyor-=reliabilityof.dosecalculationsorSetpointdeterminations;andb.3)DocumentationofthefacttTiatthechangehasbeenreviewedandfoundacceptablebytheSORC.I'hallbecomeeffectiveuponreviewandacceptancebytheSORC.6.15MAJORCHANGESTOLIUIDGASEOUSAND"SOLIDRADMASTETREATMENTSYSTEMS"6.15.1Licensee-initiatedmajorchangestotheRadwasteTreatmentSystems(liquid,gaseous,andsolid):ShallbereportedtotheCommissionintheSemiannualRadioactiveEffluentReleaseReportfortheperiodinwhichtheevaluationwasreviewedbytheSORC.Thediscussionofeachchangeshallcontain:1)Asummaryoftheevaluationthatledtothedeterminationthat'.thechangecouldbemadeinaccordancewith10CFR50.59;2)Sufficientdetailedinformationtototallysupportthereasonforthechangewithoutbenefitofadditionalorsupplementalinformation;3)Adetaileddescriptionoftheequipment,components,andprocessesinvolvedandtheinterfaceswithotherplantsystems;4)Anevaluationofthechange,whichshowsthepredictedreleasesofradioactivemateria1sinliquidandgaseouseffluentsand/orquantityofsolidwastethatdifferfromthosepreviouslypredictedintheLicenseapplicationandamendmentsthereto;LicenseesmaychoosetosubmittheinformationcalledforinthisSpecifica-tionaspartoftheannualFSARupdate.NINEMILEPOINT-UNIT26"24~:NOV801985 0 ADMINISTRATIVECONTROLSMAJORCHANGESTOLIUIDGASEOUSANDSOLIDRADMASTETREATMENTSYSTEMS(Cont)5)Anevaluationofthechange,whichshowstheexpectedmaximumexposurestoaMEMBEROFTHEPUBLICintheUNRESTRICTEDAREAandtothegeneralpopulationthatdifferfromthosepreviouslyestimatedintheLicenseapplicationandamendmentsthereto;6)Acomparisonofthepredictedreleasesofradioactivematerials,inliquidandgaseouseffluentsandinsolidwaste,totheactualreleasesfortheperiodpriortowhenthechangeistobemade;7)Anestimateoftheexposuretoplantoperatingpersonnelasaresultofthechange;and,8)DocumentationofthefactthatthechangewasreviewedandfoundacceptablebytheSORC.b.Shall:becomeeffectiveuponreviewandacceptancebytheSORC.NINEMILEPOINT"UNIT26"25NQV20'1985
ATTACHMENTB1)COMMENTS2)JUSTIFICATIONFORPROPOSEDTECHNICALSPECIFICATIONCHANGES3)NEWPAGES
COMMENTS2.3.4.6-14,6.6.1.b;Clarifythemeaningofthisstatement.Ourreviewof10CFR50.72and10CFR50.73revealsno24hournotificationrequirements.Does6.6.l.brequire~onlREPORTABLEEVENTSrequiring24-hournotificationbeSORC,SRABandVPreviewed?3/47-5,4.7.2.c;ItisimpracticaltoaskNMP2toperformthissurveillancesince:1)waverunup(splashing)canoccurfrequently;2)duringwinter,duetowhite-outs,theshorebarriercannotbeseen;3)impracticalanddangeroustodigthroughseveralfeetoficetofindmarkersduringastorm;and4)stormsruntogetherandaresometimeslongerthansevendays.NMPCisrequestingrelieffromthissurveillance.Basespage83/44-6isprovidedunderAttachmentBforinclusioninTech.Specs.AnupdatedversionofFigure6.2'-1,6-4,isprovidedunderAttachment"B"forinclusioninTech.Specs.ThenewmylarwillbemaileddirectlytoMr.Schulten.5.6.7.8.9.10.NMPCisrequestingthatpage5-4oftheTech.Specs.besplitintotwopages(SiteBoundariesandNotes).Thisrequestismadebecausethepresentversionofthesetwoitemson5-4isillegible.NMPCisrequestinganinterpretationofthephrase"unexpected,potentiallydamagingtransient"in4.7.5.don3/47-14.Page3/410-5,LCO3.10.5,isprovidedinAttachment"B"sincethisLCOwasomittedintheProofandReviewversionofTech.Specs.Page3/47-11,4.7.4.a.l;NMPCisrequestingthatafootnotebeaddedtothissurveillancethatallowsviolationofprimarycontainmenttoperformitem4.7.4.a.l.AsimilarchangemustbemadetoHighPressureCoreSpray,LowPressureCoreSprayandResidualHeatRemovalSystems.AcomparisonofLCO's3.6.5.3,3/46-38,and3.11.2.8,3/411-18indicatesthatworkononestandbygastreatmentsubsystemcanonlybeperformedinmodeswitchpositions4and5withprimarycontainmentineffect.NMPCviewsthisasanincorrectinterpretationoftheSERstatement(page6-23)requiringbothSGTStrainstobeoperableduringpurging.TheSERconcernisbasedsolelyaroundtheinabilityoftheSGTStoresistthepostulatedimpulseloadingpost-LOCAevent.Theactualpressureriseisessentiallyzeroinmodeswitchcondition4and5foraLOCA.ItisourpositionthatLCO3.11.2.8shouldapplyonlyinOPERATIONALCONDITIONS1,2and3.NMPCisrequestingSERchangesonpage6-23toeliminatetherequirementofbothSGTStrainsbeingOPERABLEandtoeliminatethelimitingof90hoursperyearofoperationofthe12and14inchlines.ThisrequestisbasedupontheabilityoftheSGTStosurviveapost-LOCAimpulseloadingduetotherestrictingorificeeffectofthe2inchpipingbetweentheSGTStrainsandthe12and14lines.TheseSERchangeswouldalsoresultinchangestoproofandreviewversionsofTech.Specs.
ll.WearerequestinganSERchangeonpage3-49tosupportLCO3.4.3.2.donpage3/44-9.12.Wearerequestingthechangesonpages3/46-11andB3/46-2begrantedbaseduponalettersenttoDr.Butler,datedNovember19,1985,fromC.V.Mangan.ThisletteraddressesanSERconcernraisedonpage6-23.AcopyofthisletterisprovidedunderAttachmentB.13.Wearerequestingachangebegrantedtonote(g)onpage3/43-8.ThechangeandjustificationareinAttachmentB.14.Wearerequestingadeletionofitem5.b.,"ScramTripBypass"onpages3/43-56,3/43-58and3/43-60.ThejustificationforthischangeisprovidedinAttachmentB.15.ChangesinSection6.0,AdministrativeControls,arerequestedinordertomakeNineMilePointUnits1and2identicalinthissectionofTechnicalSpecifications.16.Wearerequestingdeletionof4.8.1.1.2.bandcbasedonSERpages9-7,9-4and9-5insupplement2.17.Wearerequestingdeletionofthephrase,"beinatleastHOTSHUTDOWN"inaction"f"onpage3/48-3andreplacingitwith"reducepowerto415K."ThejustificationforthischangeisinAttachmentB. 0 7t4lAGARA~gPQRMATlQNUMOHAWKNIAGARAMOHAWKPOWERCORPORATION/300ERIEBOULEVARDWEST,SYRACUSE,N.Y.13202/TELEPHONE(315)474-1511November19,1985(NMP2L0539)Dr.WalterButler,ChiefLicensingBranchNo.2U.S.NuclearRegulatoryCoranissionWashington,DC20555
DearDr.Butler:
Re:NineMilePointUnit2DocketNo.50-410YourletterofSeptember10,1985toMr.B.G.HootenconcerningtheoperabilityofcontainmentpurgeandventvalvesforNineMilePoint2requestedasubmittalofadditionalinformationbyNovember15,1985.Theinformationbelowissubmittedinresponsetothatletter.l.ValvesAOV-106,AOV-108,andAOV-109TheNRCconcludedthatoperabilityofthesevalveshasbeensatisfactorilydemonstrated.2.Va1veAOV-104ThisvalvewillbeorientedinthepreferreddirectioninaccordancewithPosiSealInternationalrecommendation.OperabilityforthisvalvewillthusbedemonstratedconsistentwiththeNRCletter.NOTE:Preferreddirectionisdefinedrelativetothedirectionofflowfollowingalossofcoolantaccident:i.e.,frominsidetooutsidecontainment.3.ValvesAOV-105,AOV-107,AOV-110,andAOV-illTheNRCconcludedthatoperabilityforthesevalveswasnotdemonstrated.Thefollowingactionshavebeentakenorareinprocess:a.ValvesAOV-105andAOV-110Bothofthesevalveswillbereorientedinthepreferreddirection.PosiSealInternationalhasreanalyzedthesevalvesandconcludedthat,usinganallowableshearstressof21,120
Page2psiforthediscpin,theangleofopeningofValvesAOV-105andAOV-110shouldberestrictedto70degrees.Thismodificationwillbeimplementedbeforefuelload.b.ValveAOV-107Thisvalvewillbeorientedinthepreferreddirection.PosiSealInternationalindicatesthatwiththevalvesooriented,thetorquewillbereducedfrom3,998to3,237in.-lb.Thiswillresultinadiscpinstresslessthanthe21,120psiallowable.NofurthermodificationsarerequiredtodemonstrateoperabilityforValveAOV-107.c.ValveAOV-111Thisvalvewillbereorientedinthepreferreddirection.PosiSealInternationalhasreanalyzedthisvalveandconcludedthat,usinganallowableshearstressof21,120psiforthediscpin,theangleofopeningshouldberestrictedto60degrees.Thismodificationwillbeimplementedbeforefuelload.PosiSealInternationalwillsupplementtheirLossofCoolantAccidentandSeismicAnalysisReporttoincorporatetheresultsandrecommendationsdiscussedabove.LimitstopstolimittheopeningangleforValvesAOV-105,AOV-110,andAOV-illhavebeenorderedandwillbeinstalledpriortofuelload.Webelievethatcompletionoftheitemsdiscussedaboveadequatelyaddressestheidentifiedconcerns.Verytrulyyours,r>aC.V.ManganSeniorVicePresidentxc:R.A.Gramm,NRCResidentInspectorProjectFile(2)
<<r4UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterof))NiagaraMohawkPowerCorporation))(NineMilePointUnit2))DocketNo.50-410AFFIDAVITC.V.Manan,beingdulysworn,statesthatheisVicePresidentoNiagaraoawowerorporation;thatheisauthorizedonthepartofsaidCorporationtosignandfilewiththeNuclearRegulatoryCoaeissionthedocumentsattachedhereto;andthatallsuchdocumentsaretrue'ndcorrecttothebestofhisknowledge,informationandbelief.Subscribedandswotobeforeme,aNotaryPublicandfrtheStateofNewYorkandCountyof,this~dayof,1985-NotyubscsnandorCounty,NewYorkMyCooerssigngxpies:NotaryPubttcIntheStateofNewYorkQuaflftedlnOnenoayeCountyfro,47S'5+SMyCommissionExpireshlatch30r19k]..
Subject:
Deletionofitem5.b.,"ScramTripBypass"onpages3/43-56,3/43-58and3/43-60JustificationfordeletionofItem5b,alltablesofControlRodBlockInstrumentation.Ascramdischargevolumewaterlevel-highsignalcurrentlyprovidesascramsignaltotheReactorProtectionSystem.Amanuallyinitiatedscramdischargevolumewaterlevel-highbypassexists(inOperationalConditions(OC)3,4and5only)forarmingtheReactorProtectionSystemimmediatelyfollowingascram(whenthescramdischargevolumeisexpectedtobehigh).ThebypassisonlyfunctionalwheninOC3,4and5andtheswitchisinthebypassposition.Therodblockfortheseconditionsthenexists.Alternaterodblocks,duetothereactormodeswitch,existwhichpreventrodmovementinOC3and4(designedtosinglefailurecriteria).Therefore,therodblockfromtheSDVtripbypassisredundant.SurveillancetestingofthisredundantSDVtripbypassrodblockfunctionisverydifficultinthepresenceoftheReactorModeSwitchRodBlockandwouldprobablyrequirecircuitdisconnections.Duetotheveryminorsignificance(redundancy)oftheSDVtripbypassrodblock,itisconsideredcounter-productivetosafetytoprescribesurveillancetesting.ThispositionwasestablishedforGrandGulfandisrecommendedforallplants,hencethe,deletionofItem5bfromalltables.
Subject:
Changetonote(g)onpage3/43-8Theoriginalnote(g)wasplacedherebytheNRC,asameansofdeterminingcruddingoftheflowcontrolvalve.Asitwaswritten,itwasnonconservativefortheinstrument;therefore,GrandGulf,inconjunctionwiththeNRC,modifiedittothenotetheynowhave.OriginalSTSnote(h)-1983:Verifymeasuredcoreflowtobegreaterthanorequaltoestablishedcoreflowattheexistingflowcontrolvalveposition.CurrentGrandGulfnote(h):Verifymeasureddriveflowtobelessthanorequaltoestablisheddriveflowattheexistingflowcontrolvalveposition.CurrentStandardTechnicalSpecificationnote(g):Verifymeasuredcoreflow(totalcoreflow)tobegreaterthanorequaltoestablishedcoreflowattheexistingloop(APRMX).Note(g),asshowninTable4.3.1.1-1,providesasurveillancecheck.whichisoutsidethenormalscopeofaCHANNELCHECK.ACHANNELCHECKasdefinednormallyonlyrequiresaqualitativedeterminationthattheparameterofinterestisbeingindicatedintheexpectedrange.Note(g),however,isa"go/nogo"situation;i.e.,indicationmustbetoonesideofanestablishedvalue.Ifitdoesnotmeetthiscriterion,thereisnoclearlydefinedACTION.Therewouldseemtobetwopossiblecoursesofaction:First,removethenote;which,asexplainedpreviously,istherebydefault.Second,rewritethenoteasfollows:"Verifymeasuredcoreflow(totalcoreflow)tobeintherangeofestablishedcoreflowfortheexistingloopflow(APRMX).
Subject:
Deletionofphrase"beinatleastHOTSHUTOOWN"inACTION"F"onpage3/48-3andreplacementwithphrase"reducepowerto15$."NiagaraMohawkPowerCorporationisrequestingarelieffromtherequirementinactionstatement"F"ofL.C.O.3.8.1.1whichrequirestheplanttogotohotshutdownwithin36hoursofthelossofbothoftherequiredoffsitecircuitsforitsNineMilePointUnit2NuclearStation.NMPCspositionisthatthisrequirementwillreducethelevelofplantsafetyratherthanenhanceit.Ouringanormalshutdown,loadistransferredtotheoffsitesourcesat10to12percentreactorpowertoprecludeareversepowertripoftheturbinegenerator.This10to12percentcorrespondstotheloadrequiredforourhouseloads.Thistransferallowsustomaintainallofourturbineauxiliariessuchascirculatingwaterforourreactorheatsink,glandexhausters,lubeoilpumps,closedloopcoolingpumps,aswellasreactorfeedpumps(threeavailable,tworunning),therebypermittingacontrolledreactorshutdownandcooldown.ShutdownwithoutatleastoneofthesesourcesofnormalA.C.powerwouldresultinacompletelossofnormalA.C.powerwhentheturbinewasremovedfromthegrid.Thiswouldcausealossofthetwooperatingfeedpumps,aswell.astheoneinstandby,alossofthecondenserwithin15secondsofthelossofpowerduetothelossofcirculatingwaterpumps,isolationofthereactorfromtheheatsink(MSIVclosureonlowvacuum)andsubsequentscram,achallengetothereliefvalveswiththeaccompanyingheatadditiontothesuppressionpool,anECCSinitiation(HPCS)torestorelevelfollowTngthelossoffeedQate~ndshrinkdGe'toMSIVclosure.Sinceitisboththeindustry'saswellastheNRC'sgoaltoreducethenumberofscramsandreducethechallengestothereliefvalvesandECCSsystems,wefeelthatareductionto15percentpowerisasaferalternativethanareactorshutdownundertheseconditions.WealsofeelthiswouldbeinharmonywithNUReg0737,TMIactionitemII.K.3.16,reducingchallengestothereliefvalves,andinthespiritofNUReg1024,"TechnicalSpecifications-EnhancingtheSafetyImpact,"Section3.6,"ModeChanges."
NINEMILEPOINT2BASESTABLEB3/4.4.6"1LIMITINGREACTORVESSELTOUGHNESSHEAT/SLABBELTLINEWELDSEAMI.D.ORCOMPONENTORMAT'TYPEHEAT/LOT~CUISTARTINGMAX."RThRT~PX~(~FUNIRRADIATEDMAX.UPPERSHELFRTT~FT-LBSPlateSA-533GRBCL.1C3147-20.11yWeldSeamsBA,BB,8BC5P6214B/03310.0140.0120300.011"40188897+30-22"NOTE:Thesevaluesaregivenonlyforthebenefitofcalculatingtheend-of-life(EOL)RTNON-BELTLINECOMPONENTShellRingBottomHeadDomeBottomHeadTorusTopHeadDomeTopHeadTorusTopHeadFlangeVesselFlange*"LPCINozzleFeedwaterNozzleWeld~ClosureStuds,MT'LTYPEORWELDSTEAMI.D.SA-533,Gr..B,CL.1IIIIIIIIIIII~1IIIISk-508,CL..2IIIIIIIIIIIIINMM/LINDE124SA-540,Gr.B24HEAT/SLABORHEAT/LOTAllPlatesC3073/2IIIIA0678/1C2325/249D161,49B16848D1072,48B1121Q2QL3WQ2QL2WAllHeatsAllHeatsHIGHEST+10+10+10-20-1-30-20-20"20"20Meet45ft-lb825milslateralexpansionrequire-mentta+10OF""NOTE:ThedesignlocationoftheLowPressureCoreInjection(LPCI)nozzlesresultsinthesecomponentsand.theirrelatedvesselweldstoexperienceanEnd-of-Life(EOL)fluenceof1.7x10'7n/cm2(E>1MeV).Asaresult,thenozzlesarepredictedtohaveanEOLRTNDTof-13'FandthelimitingweldmaterialwillhaveanEOLRTNDTof12F.NSS:ca1:rm/K051511"5/20/85OMN$1<6
zzlitKIIll'$20zICZCONSTRUCTIOHENGINEERMSTATIONSUtERINTCNDENTNUCLEARGENERATIONUNITISUtfRINTENDENTCtERATIOHSNUCLEAR"ASSISTANTTOQIPCAINTENDENTOffRATIONSNVClEAARAOWASTEOtCRATIONSUtfRVISOAA$51$TANTAADWASTEOPERATION5UPERVISORSECRETAAYGKNfMALSVtERINTfNDENTVCLEARGENERATIONADMINISTRATIVEASSISTANtfORADMINISTRATIONANOSLAMMINGSITESVtERIHTCNDCNTMAINTENANCENVCLCAASUPERINTENDENTTRAIMINCNUCLEAR'iSUPERINTENDENT'HEMISTRYANDRADIATIONMANAGEMfNtTCCHNICALSUttRINKENDfNTNUCLfARGKNtRATIONSUtTMECHMAINT5UPVMCCN0AINTENANCCASQSTANTSVtVMECHMAINTfNANCEhMKCHANICSNOJANITORSASRKOUIREDI5UPTELECTMAIHT05VtVClfCMAINTENANCtA$5ISTANTSWVELECT.MAINTENANCEhCLfCTAICIANSIASREOVIAEDASSISTANTCAINTEROCNTRAINIHGNVCLEAASUtEAVISORTAAININGNVCLEAAGENERATIONKNGINEERSANDStECIALISTSSUPERVISORCHEMISTRYANORADIATIONPROTECTIONUNIT5VttRVCHEM15TRYUNITSVtfAVIRADIATtROTCCT.5WKAVISORIN5TSUttORTTECHNICIANSIASRCOUIRCOISWERVISORfIREtAOTEC'tlOHNVCLEAAASQSTANTSUPERVISORflREPAOTEC'TION5HIFlSUttRV1$0RSIREtAOlfCTIONSIREFIGHTERStLANHINCCOORDINATORSUPERINTENDENTlfCHNICALSERVICESNUCLEARSVPCAVISORtACTOAANALYSUNITSUPERVISOA.REACTORANALYSTCCMfRATIOHtNGIMCCR5ANDStECIALISTSSVPKRVISORTfCHNICALSUftORTNUClEARASSISTANTERVISORTECHNICALSVPtORlfHERATIKNGINKCR$.FIGURE6.2.2-1NINEMILEPOINTNUCLEARSITEOPERATIONSORGANIZATIONSUtfRIHTENDCNTINSCRVICEINStECTIONUNITINSERVICEINStECTIONSVPERVISORSENIORIMSERVICEINSPECTIONStECIALIStINSERVICEINStfClIONStECIALISTCONSTRUCTIONENGINCERSTATIONSWCRINTEMOEHTNUCLEARGENERATIONVNIt2SVPERINTENDKNTOtERATIOMSNUCLEAR'S$15TANtTOSUPERINTENDENTOPERATIONSNUClEARAAOWASTEOPERATIONSVtKRVISORASSISTANTRADWASTEOtERATIONSVPERVISORASSISTANTSUtfRINTCNDCNTOtfRATIONSNUClfAA"GENtRATIONENGINCCR5ANDStECIAU5T5GENERATIONKNGINKEASANOStECIALISTSENVIRONMENTAL~AOTtC'tlIWCOORDINATORASQSTANTtlANNWGCOORDINATORhTECANICIAN5REOVIREDASQSTANTSVPEAINTENDCNTOtKRAtIONSNUCLEARYSTATHWSHIFTSVPERVISORNUCLEAAiA$515TANTSTATIONSHlfTSUtERVISOAISMIFTTECHNICALADVISORIhOtfRATORSASRCOVIREDOSUPEAVICONSANOA$$15TANTSUttAVISORSAREASSIGNf0TOEACHSTATIONUNITASREOVIRCD.UNITSWCRVISORSRCCtlVE$05RCOUCSTSDIRECTLYSYAUTHORITYOfTHESTATIONSUtfAIMTCROCNlNUCLEARGKHERATIONUNITIOR2HOPERATORUCEN5E48StNIOAOtfAATORLICENSE444THENORMALSHIFTCOMPLEMKNTSHALLSEACCORDINGTOTASLE52.2.10$THETECHHICALSPECIfICATIONShASSIGNEDTOSWCRYISOA5ASMCGUIRE05ECVRITY.DUALITYA55URANCC,MATEFIIALSMAHAGtMCNT.ANDWDVSTAIALSAFETYSEAVICtfAREPROVIOf0ONSITESYNIAGARAMOHAWKCORPORATELEVELORGANIZATION5VPCRVISORFIADIOLOGICALSUPPORtDOQMETRYCOOADIHATORAAOICLOGICALENGINEERRfltlRATORY~ROTfCTIONCOORDINATORCMKRCENCYtlANNIN0COOROIMA'TORAlAAACOORDINATORSVtfRVISORADMINIflRATIVESERVICESCLEANS5RfOUIREDSUPERVISOR5TfNOGRAtHICStRVICC5ASSISTANTSUPEAVISORADMINQ'tRATIVESERVICESSUPERINTENDEN'tRECORDSMANAGEMENTUNITAPERVISORRECORDSMANAGKMSNlSUtERVISORINSTAVMENTAHDCONTROLNVCLtARIWllSVtEAVISORINSTRUMENTANDCOHTROlASSISTANTSUPERVISORINSTRUMENTANDCONlROLGENERATIONENGINEERSANDStECIALISTShTECHNICIANS5RCOUIAEOSUPERVISORCOMPVTCAOtfRATIONSANMAINTENANCEASSISTANTSVPERVISORSCOMPVTEROffRATIONSANOMAINTENANCECENCAATIONENGINEKRSANDSPECIALISTSSTATIONSHIflSVtfRVISORNVCLEAAiiASSISlANT5TATIONSHIFtSVPCRVISONIQHSTTECHNICALADVISORI'iiOPEAATORSASRfOVIRfDRECORDSSPECIALISTCLERKSREOUNIED
SPECIALTESTEXCEPTIONS3/4.10.5OXYGENCONCENTRATIONLIMITIHGCONDITIONFOROPERATION3.L0.5TheprovisionsofSpecification3.6.6maybesuspendedduringtheperformanceoftheStartupTest.ProgramAPPLICBILITY:OPERATIONALCONDITIONl.ACTIQM"Withtherequirementsoftheabovespecificationnotsatisfied,beinatleastSTARTUPwithin6hours.SURVEILLANCEREUIREMEHTS~~4.10.5Thenumberofmonthssinceinitialcriticalityshallbeverifiedtobe.lessthanorequalto6monthsatleastonceper31daysduringtheStartupTestProgram.NINEMILEPOINT-UNIT23/410-5gaggV1985
ATTACHMENTCCHANGESINAMENDMENT23OFTHEFINALSAFETYANALYSISREPORTWHICHAFFECTTECHNICALSPECIFICATIONS
ITEMNO.FSARLOCATIONTECH.SPEC.LOCATIONSUBJECT1)a1)b1)c2)3)4)5)6)7)8)9)10)12)13)14)Table7.3-1Table7.3-2Tables7.3-1,2,34,5,6and7.Table7.4-1Table5.2-6Page6.2-86Page9.2-6Page5.4-37Page7.6-7Page7.7-5Table8.3-101of1F430.74Table6.2-567of24PenetrationZ-32Table6.2-56Note19,Page20of2411.5-211.5-211.5-8and11.5-9Table3.3.3-2Table3.3.3-2FigureB3/4.3-1Table3.4.4-1Table3.6.3-13/46-244.7.1.1.d.2Table3.3.3.2Table3.3.4.2-1L.C.O.3.2.23/42-54.8.2.l.d.2.c)3/48-134.8.1.1.2.bTable3.6.3-13/46-23Table3.6.3-13/46-23Table3.3.7.10-1Table3.3,7.11-1Table3.3.7.10-1HPCSSetpointsADSSetpointsInstrumentZeroBWRWaterChemistryScramDischargeVentAndDrainLinesServiceWaterPumpStartingOnLossOfOffsitePowerLPCIInjectionValvePressureInterlockSetpointsEndOfCycleRecirc.PumpTrip.APRMandRodBlockSetpointsDiv.IIIBatteryLoadProfileRoomTemp.,Div.IIIDieselGeneratorNitrogenPurgeToTIPIndexingMechanismOutsideIsolationValvesType"C"TestingOf'IPBallValvesServiceWaterDischargeLiquidEffluentRadiationMonitoringStandbyGasTreatmentRadiationMonitoringCoolingTowerBlowdown,LiquidRadwasteAndServiceWaterEffluentRadiationMonitors
ITEMNO.FSARLOCATIONTECH.SPEC.LOCATIONSUBJECT15)16)17)18)19)20)21)22)23)24)25)26)27)11.5-11Table11.5-1Pages1and29.5-23Tables9B.6-1,9B.8-1,and9B.8-2F440.16Table6.2-3Page1of2Pages5.2-31,32and37Table6.2-567.3-16,17and7.6-9and7.3-257.4-11Table12.3-27.3-5Tables9A.3-19A.3-2,9A.3-49A.3-5,9A.3-7and9A~3-12Tables3.3.7.1-1,3.3.7.10-1and3.3.7.11-1Tables3.3.7.1-1,3.3.7.10-1and3.3.7.11-1;andRETSPortionofT.S.L.C.0.3.8.1.1.bTable3.3.7.8-1Table3.3.2-2Items2.e.2and2.f.25.2.2.bPage5-1Table3.3.2-2Tables3,6.3-13.3.2-4and3'.2-5Table3.3'-2Table3.3.7.4-1NoneTable3.3.3-2Table3.3.7.8-1LiquidAndGaseousRadiationMonitoringInstrumentationProcessAndEffluentRadiationMonitoringInstrumentationTrip/HighSetPointsFuelOilStorageRequirementsForDivisionsI,IIandIIIDieselGeneratorsFireDetectionInstrumentationRCICDeltaTemperatureIsolationSignalsMaximumDesignSuppressionChamberTemperatureDeltaTemperatureLeakDetectionForMainSteamLineTunnel,RHR,RCICandRWCUContainmentIsolationValvesDeltaTemp.LeakDetectionForRWCU,RCICandRHRRHRLoops"A"and"B"FlowOnRemoteShutdownPanelDefinitionOfHighSetpointBasesADSLogicOperationFireDetectionInstrumentation
ITEMNO.FSARLOCATIONTECH.SPEC.LOCATIONSUBJECT28)29)30)31)6.3-14aF210.62Table12.3-1Page2of4Tables8.3-8and8.3-9Table3.3.3-2L.C.O.3.4.3.2.dandTables3.4.3.2-1,3.4.3.2-2and3.4.3.2-3Table3.3.7.1-14.8.2.l.d.2.a)andb)LPCSInjectionValveDifferentialPressurePerimissiveSetpointLeakRateTestingOfValvesSeparatingReactorCoolantSystemFromLowPressureSystemsMainControlRoomVentilationRadiationMonitorsDivisionsIandIIBatteryLoadProfilesABBREVIATIONLISTHPCS-ADSLPCI-TIPRCIC-RHR-RHCU-LPCS-HighPressureCoreSprayAutomaticDepressurizationSystemLowPressureCoolantInjectionTraversingIncoreProbeReactorCoreIsolationCoolingResidualHeatRemovalReactorHaterCleanupLowPressureCoreSpray
ATTACHMENTDSINGLELOOPOPERATIONPROPOSEDTECHNICALSPECIFICATIONCHANGES
2.0SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSPIlM~5I~PIG~!tlaB2.1SAFETYLIMITSTHERMALPOWERLowPressureorLowFlow2.1.1THERMALPOWERshallnotexceed25KofRATEDTHERMALPOWERwiththereactorvesselsteamdomepressurelessthan785psigorcoreflowlessthan10Xofratedflow.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:WithTHERMALPOWERexceeding25KofRATEDTHERMALPOWERandthereactorvesselsteamdomepressurelessthan785psigorcoreflowlessthanlOXofratedflow,beinatleastHOTSHUTDOWNwithin2hoursandcomplywiththereuie-.mentsofSpecification6.7.1.shel.LuRboLed%~<.Oq~'QgTHERMALPOWERHihpressureandHihlow~'~8L~~+<<M~i~ti4*Lo4pop+4~4tomWA+h.2.1.2TheMINIMUMCRITICALPOWERRATIO(MCPR)shallnotbelessthan1.06withthereactorvesselsteamdomepressuregreaterthan785psigandcoreflowgreaterthanlOXofratedflow.APPLICABILITY:OPERATIONALCODITIONS1and2.v4Itk+v4oQcc(Q.oAAhdgLoopopec'+<o+L<~+~W+4O"t~Ath~><~144'PCt&L4MWithMCPRlessthan1.06andthereactorvesselsteamdomepressuregreaterthan785psigandcoreflowgreaterthanlOXofratedflow,beinatleastHOTSHUTDOWNwithin2hoursandcomplywiththerequirementsofSpecification6.7.1.REACTORCOOLANTSYSTEMPRESSURE2.1.3Thereactorcoolantsystempressure,asmeasuredinthereactorvesselsteamdome,shallnotexceed1325psig.APPLICABILITY:OPERATIONALCONDITIONS1,2,3and4.ACTION:~'iththereactorcoolantsystempressure,asmeasuredinthereactorvesselsteamdome,above1325psig,beinatleastHOTSHUTDOWNwithreactorcoolantsystempressurelessthanorequalto1325psigwithin2hoursandcomplywiththerequirementsofSpecification6.7.1.NINEMILEPOINT-UNIT22-1NOV201995
.pit%~(vTABLE2.2.1-1IREACTORPROTECTIONSYSTEHINSTRUHENTATIONSETPOINTSFUNCTIONALUNITml.IntermediateRangeMonitor,NeutronFlux-Highm2.AveragePowerRangeMonitor:C)a.NeutronFlux-Upscale,SetdownIb.FlowBiasedSimulatedThermalPower-Upscale1)FlowBiased2)HighFlowClampedc.Fixed.NeutronFlux-Upscaled.Inoperative3.ReactorVesselSteamDomePressure"High4.ReactorVesselMaterLevel-Low,Level35.HainSteamLineIsolationValve-Closure6.MainSteamLineRadiation-HighjTRIPSETPOINT<120/125divisionsoffullscale<15KofRATEDTHERMALPOMERo,kb(vJ-KM)+BIloHetlelalihamaximumof<113.5XofRATEDTHERMALPOMER<118XofRATEDTHERMALPOMER<1037psi'g>159.3>inchesaboveinstrumentzero"<6Xclosed<3.0xfullpowerbackgroundALLOMABLEVALUES<122/125divisionsoffullscale<20KofRATEDTHERHALPOMERoi4ageJ-gm3~Sgjg~amaximumof<115.5XofRATEDTHERMALPOMER<120XofRATEDTHERMALPOMERNA<1057psig>157.8inchesaboveinstrumentzero<7Xclosed<3.6xfullpowerbackground7.8.9.10.12.HanualScramSeeBasesFigureB3/43-1.DrywellPressure-HighScramDischargeVolumeMaterLevel-Higha.LevelTransmitter/TripUnitsb.FloatSwitchTurbineStopValve-ClosureTurbineControlValveFastClosure,TripOilPressure-LowReactorHodeSwitch'ShutdownPosition'1.68psig<46.5inches<46,5inches<5Xclosed>530psigNA<1.88psig<79.5inches<79.5inches<7Xclosed.>465psigNANAC~CD
El~~p(~~~~~%~84~fllcltldJLJI~Jl-~C.~3J~~(~~+4~~~~)am~~~~4~(8-+4~~co~~.b,w=5'g<>+~tv&8H(LGPo]lvf-lbVl74
2.1SAFETYLIMITSBASES4~q.+wet'ec>tcg3A+fonl-bop0peI'<io~b~
2.0INTRODUCTION
),0qP~~~y~~~(ec.)p.cuLA+toa,Laop4pete+~Thefuelcladding,reactorpressurevesselandprimarysystempipingaretheprincipalbarrierstothereleaseofradioactivematerialstotheenvirons.SafetyLimitsareestablished,toprotecttheintegrityofthesebarriersduringnormalplantoperationsandanticipatedtransients.ThefuelcladdingintegritySafetyLimitissetsuchthatnofueldamageiscalcu'tatedtooccurifthelimitisnotviolated.Becausefueldamageisnotdirectlyobservable,astep-backapproachisusedtoestablishaSafetyLimitsuchthattheMCPRisnot.lessan.6.MCPRgreaterthan1.06representsaconservativemarginrelativetotheconditionsrequiredtomaintainfuelcladdingintegrity.Thefuelcladdingisoneofthephysicalbarrierswhichseparatetheradioactivemate-rialsfromtheenvirons.Theintegrityofthiscladdingbarrierisrelatedtoitsrelativefreedomfromperforationsorcracking.Althoughsomecorrosionoruse-relatedcrackingmayoccurduringthelifeofthecladding,fissionproductmigrationfromthissourceisincrementallycumulativeandcontinuouslymeasurable.Fuelcladdingperforations,however,canresultfromthermalstresseswhichoccurfromreactoroperationsignificantlyabovedesigncondi-tionsandtheLimitingSafetySy'temSettings.Whilefissionproductmigrationfromcladdingperforationisjustasmeasurableasthatfromuse-relatedcracking,thethermallycausedcladdingperforationssignalathresholdbeyondwhichstillgreaterthermalstressesmaycausegrossratherthanincrementalcladdingdeterioration.Therefore-,the-fuel-cladding-Safety-Limit-is-defined-withamargintotheconditionswhichwouldproduceonsetoftransitionboiling,MCPRof1.0.Theseconditionsrepresentasignificantdeparturefromtheconditionintendedbydesignforplannedoperation.2.1.1THERMALPOWERLowPressureorLowFlowTheuseoftheGEXLcorrelationisnotvalidforallcriticalpowercalculationsatpressuresbelow785psigorcoreflowslessthanlOXofratedflow.Therefore,thefuelcladdingintegritySafetyLimitisestablishedbyothermeans.ThisisdonebyestablishingalimitingconditiononcoreTHERMAL-POWERwiththefollowingbasis.Sincethepressuredropinthebypassregionisessentiallyallelevationhead,thecorepressuredropatlowpowerandflowswillalwaysbegreaterthan4.5psi.Analysesshowthatwithabundleflowof28x10'bs/hr,bundlepressuredropisnearlyindependentofbundlepowerandhasavalueof3.5psi.Thus,the,bundleflowwitha4.5psidrivingheadwillbegreaterthan28x10'bs/hr.FullscaleATLAStestdatatakenatpressuresfrom14.7psiato800psiaindicatethatthefuelassemblycriticalpoweratthisflowisapproximately3.35MWt.Withthedesignpeakingfactors,thiscorrespondstoaTHERMALPOWERofmorethan50KofRATEDTHERMALPOWER.Thus,aTHERMALPOWERlimitof25XofRATEDTHERMALPOWERforreactorpressurebelow785psigisconservative.NINEMILEPOINT-UNIT2B2-1QQQ201985
Base'sTable82.1.2-1(%K'PfHlcm"IUNCERTAINTIESUSEDINTHEDETERMINATIONOFTHEFUELCLADDINGSAFETYLIHIT"~uantitFeedwaterFlowFeedwaterTemperatureReactorPressureCoreInletTemperatureICoreotalFlow~oReclae~LA<tog4sepoqttyhta~Channe)9fanAreaFrictionFactorMultiplierChannelFrictionFactorHultiplierTIPpleadings>Weeg,<CtaCtt.LA+)0tt.~opepi.'em+,t>eRFacg~g~<~<clacuLa4.'tiaraLooPOqcia4tooCriticalPowerStandardDeviationXofPoint1.760.760.50.2g)$3.010.&5.03.6dbiihhSafetyLimitMCPRisbasedontheassumptionofquadrantpowersymmetryforthereactorcor.,TJ4~~J4~~NINEMILEPOINT"UNIT282-3QQV2uSb
3/4.2POWERDISTRIBUTIONLIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATEF'I~~~~CIFPP4kiV'tLIMITINGCONDITIONFOROPERATION~~3.2.1AllAVERAGEPLANARLINEARHEATGENERATIONRATES(APLHGRs)foreachtypeoffuelasafunctionofAVERAGEPLANAREXPOSUREshallnotexceedthelimitsshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorequalto25KofRATEDTHERMALPOWER.ACTION:WithanAPLHGRexceedingthelimitsofFigure3.2.1-1,3.2.1-2,or3.2.1-3,initiatecorrectiveactionwjthin15minutesandrestoreAPLHGRtowithintherequiredlimitswithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.2.1AllAPLHGRsshallbeverifiedto.beequaltoorlessthanthelimitsdeterminedfromFigures3.2.1-1,3.2.1-2,and3.2.1-3:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincrease.ofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLRODPATTERNforAPLHGR.d.TheprovisionsofSpecification4.0.4arenotapplicable.VI~NINEMILEPOINT-UNIT23/42"1NOV201985
POWERDISTRIBUTIONLIMITS3/4.2.2APRMSETPOINTSLIMITINGCONDITIONFOROPERATIONPIIII-"5r'~"~t'IIr<\3.2.2TheAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpoint(S)andflowbiasedneutronflux-upscalecontrolrodblocktripsetpoint(SRB)shallbeestablishedaccordingtothefollowingrelationships:TRIPSETPOINTALLOWABLEVALUEuv-g~QetS<(0.6+5)TS<(0.6+54")TSRB<(0.66+42K)TS66<(0.66~+45X)TC-'~)where:SandSRBareinpercentofRATEDTHERMALPOWER,W=Looprecirculationflowasapercentageofthelooprecirculationflowwhichproducesaratedcoreflowof108.5millionlbs/hr.T=TheratioFRACTIONOFRATEDTHERMALPOWERdividedbytheCOREMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY.Tisappliedonlyiflessthanorequalto1.0.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanor~q1RR1RATEDTHERMALTDIIER.ACTION:WiththeAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpointand/ortheflowbiasedneutronflux-upscalecontrolrodblocktripsetpointlessconservativethanthevalueshownintheAllowableValuecolumnforSorSRB,asabovedetermined,initiatecorrectiveactionwithin15minutesandadjustSand/orSRBtobeconsistentwiththeTripSetpointvaluewithin6hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.'URVEILLANCEREUIREMENTS4.2.2TheFRTPandtheCMFLPDshallbedetermined,thevalueofTcalculated;.andthemostrecentactualAPRMflowbiasedsimulatedthermalpower-upscalescramandflowbiasedneutronflux-upscalecontrolrodblocktripsetpointsverifiedtobewithintheabovelimitsoradjusted,asrequired:a.Atleastonce'er24hours,b.-Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithCMFLPDgreaterthanorequaltoFRTP.d.TheprovisionsofSpecification4.0.4arenotapplicable.WithCMLPDgreaterthantheFRTPMur+ng-power-ascension-up-4o-90~~kTED--7HERMAL-POWER-,ratherthanadjustingtheAPRMsetpoints,theAPRMgainmaybeadjustedsuchthatAPRMreadingsaregreaterthanorequalto100KtimesCMFLPDprovidedthattheadjustedAPRMreadingdoesnotexceed100KofRATEDTHERMALPOWERandanoticeofadjustmentispostedonthereactorcontrolpanels~S~~<Ca)&7~a.'.I-ININEMILEPOINT-UNIT23/42"5HOV20]gsg
SITRIPFUNCTIONTABLE3.3.6-2CONTROLRODBLOCKINSTRUMENTATIONSETPOINTSTRIPSETPOINTALLOWABLEVALUEl.2.3.4.RODBLOCKHONITORa.Upscaleb.Inoperativec.DownscaleAPRHa.FlowBiasedNeutronFluxUpscaleb.Inoperativec.Downsealed.NeutronFlux-Upscale,StartupSOURCERANGEHONITORSa.Detectornotfullinb.Upscale'.Inoperatived..DownscaleINTERMEDIATERANGEHONITORSa.Detectornotfull1nb.Upscalec.Inoperatived.Downscale<0.66W+4DXHA>5XofRATEDTHERHALPOMER(w~AN)<0,66~+42X+HA>4XofRATEDTHERMALPOWER<12XofRATEDTHERHALPOWERNA<1x10scpsHA3cps'*INA.<108/125divisionsoffullscaleNA>5/125divisionsoffullscale<0.66M+43XNA>3XofRATEDTHERHALPOWERgw-Aw)<0.66~45X"HA>3XofRATEDTHERHALPOMER<14XofRATEDTHERHALPOMERNA<1.6x10scpsNA8'psAANA<110/125divisionsoffullscaleNA>3/125d>vissonsoffullscale<16.5in.N5.SCRAHDISCHARGEVOLUMEa.MaterLevel-High<39.75in.Scram-Trip-BypaA-6.REACTORCOOLANTSYSTEHRECIRCULATIONFLOMa.Upsca1e<108Xratedflow<111Xratedflowb.InoperativeNAHAc.Comparator<10Xflowdeviation<11XflowdeviationTheAveragePowerRangeHonitorrodblockfunctionisvariedasafunctionofrecirculationloopflow(W).ThetripsettingofthisfunctionmustbemaintainedinaccordancewithSpecification3.2..**Forinitialloadingandstartupthe"countratemaybelessthan3cpsifthefollowingconditionsaremet;(1)thesignaltonoiseratioisgreaterthan2.0~(2)thesignalisgreaterthan0.7cp~nd-m~~a3gw~za.i-l~Qa~~I,.~QimCP'
3/4;4REACTOR'COOLANTSYSTEM3/4'4'1'"RECIRCULATION'YSTEMRECIRCULATION'OOPSLIMITINGCONDITIONFOROPERATION3A.l.lTworeactorcoolantsystemrecirculationloopsshallbeinoperationwith:a.Totalcoreflowgreaterthanorequalto45Kofratedcoreflow,orb.THERMALPOWERwithintheunrestrictedzoneofFigure3.4.1.1-1.APPLICABILITY:OPERATIONALCONDITIONS1*and2*.ACTION:a~Withonereactorcoolantsystemrecirculationloopnotinoperation:1.Withinfourhours:a)PlacetherecirculationflowcontrolsystemintheLocalManual(PositionControl)mode,andb)ReduceTHERMALPOWERtM70AofRATEDTHERMALPOWER,and,c)IncreasetheMINIMUMCRITICALPOWERRATIO(MCPR)SafetyLimitby0.01to1.07perSpecification2.1.2,and,d)ReducetheMaximumAveragePlanarLinearHeatGenerationRate(MAPLHGR)limittoavalueof0.81timesthetworecirculationloopoperationlimitperSpecification3.2.1,and,e)ReducetheAveragePowerRangeMonitor(APRM)ScramandRodBlockandRodBlockMonitorTripSetpointsandAllowableValuestothoseapplicableforsinglerecirculationloopoperationperSpecifications2.2.1,3.2.2and3.3.6.f)Reducethevolumetricflowrateoftheoperatingrecirculationloopto~41,000**gpm.*SeeSpecialTestException3.10.4.**Thisvaluerepresentsthedesignvolumetricrecirculationloopflowwhichproduces1005coreflowat100KTHERMALPOWER.TheactualvaluewillbeestablishedduringtheStartupTestProgram.NineMilePointUnit23/44-1
REACTOR'COOLANT'SYSTEMLIMITINGCONDITIONFOROPERATIONContinuedg)PerformSurveillanceRequirement4.4.1.1.2ifTHERMALPOWERis~30K*~ofRATEDTHERMALPOWERortherecirculationloopflowintheoperatingloopis~505*~ofratedloopflow.h)DeterminethatthereactorTHERMALPOWERlevelisnotwithintherestrictedzoneofFigure3.4.1.1-1;otherwise,reducetheTHERMALPOWERlevelorincreasecoreflow.2.TheprovisionsofSpecification3.0.4arenotapplicable.3.OtherwisebeinatleastHOTSHUTDOWNwithinthenext12hours.b.Withnoreactorcoolantsystemrecirculationloopsinoperation,immediatelyinitiateactiontoreduceTHERMALPOWERsuchthatitisnotwithintherestrictedzoneofFigure3.4.1.1-1withintwohours,andinitiatemeasurestoplacetheunitinatleastSTARTUPwithinsixhoursandinHOTSHUTDOWNwithinthenextsixhours.c~Withtworeactorcoolantsystemrecirculationloopsinoperationandtotalcoreflowlessthan45KofratedcoreflowandTHERMALPOWERgreaterthanthelimitspecifiedinFigure3.4.1.1-1:l.DeterminetheAPRMandLPRM**noiselevels(Surveillance4.4.1.1.4):a)Atleastoncepereighthours,andb)Within30minutesafterthecompletionofaTHERMALPOWERincreaseofatleast5XofRATEDTHERMALPOWER.2.WiththeAPRMorLPRM**neutronfluxnoiselevelsgreaterthanthreetimestheirestablishedbaselinenoiselevels,immediatelyinitiatecorrectiveactiontorestorethenoiselevelswithintherequiredlimitswithintwohoursbyincreasingcoreflowtogreaterthan45KofratedcorefloworbyreducingTHERMALPOWERsothatitisnotwithintherestrictedzoneofFigure3.4.1.1-1.**DetectorlevelsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstronginthecenterofthecoreshouldbemonitored.***Initialvalues.FinalvaluestobedeterminedduringStartupTestingbaseduponthethresholdTHERMALPOWERandrecirculationloopflowwhichwillsweepthecoldwaterfromthevesselbottomheatpreventingstratification.NineMilePointUnit23/44-la
REACTOR'OOLANT'YSTEMSURVEILLANCEREUIREMENTS4A.l.l.l-Withonereactorcoolantsystemrecirculationloopnotinoperation,atleastonceper12hoursverifythat:a.ReactorTHERMALPOWERisL,70KofRATEDTHERMALPOWER,b.TherecirculationflowcontrolsystemisintheLocalManual(PositionControl)mode,andc.Thevolumetricflowrateoftheoperatingloopis~41,000gpm.*4.4.1.1.2Withonereactorcoolantsystemrecirculationloopnotinoperation,withinnomorethan15minutespriortoeitherTHERMALPOWERincreaseorrecirculationloopflowincrease,verifythatthefollowingdifferentialtemperaturerequirementsaremetifTHERMALPOWERis~30K**ofRATEDTHERMALPOWERortherecirculationloopflowintheoperatingrecirculationloopis~505+~ofratedloopflow:a.~145'Fbetweenreactorvesselsteamspacecoolantandbottomheaddrainlinecoolant,b.<50'Fbetweenthereactorcoolantwithintheloopnotinoperationandthecoolantinthereactorpressurevessel,andc.~50'Fbetweenthereactorcoolantwithintheloopnotinoperationandtheoperatingloop.ThedifferentialtemperaturerequirementsofSpecification4.4.1.1.2b.andc.donotapplywhentheloopnotinoperationisisolatedfromthereactorpressurevessel.4.4.1.1.3EachreactorcoolantsystemrecirculationloopflowcontrolvalveshallbedemonstratedOPERABLEatleastonceper18monthsby:a.Verifyingthatthecontrolvalvefails"asis"onlossofhydraulicpressureatthehydrauliccontrolunit,andb.Verifyingthattheaveragerateofcontrolvalvemovementis:1.Lessthanorequaltoillofstrokepersecondopening,and2.Lessthanorequaltoillofstrokepersecondclosing.*Thisvaluerepresentsthedesignvolumetricrecirculationloopflowwhichproduces100Kcoreflowat100KTHERMALPOWER.TheactualvaluewillbeestablishedduringtheStartupTestProgram.**Initialvalues.FinalvaluestobedeterminedduringStartupTestingbaseduponthethresholdTHERMALPOWERandrecirculationloopflowwhichwillsweepthecoldwaterfromthevesselbottomheadpreventingstratification.NineMilePointUnit23/44-2
REACTOR'COOLANTSYSTEMSURVEILLANCEREUIREMENTSContinued4.4.1.1.4EstablishabaselineAPRMandLPRM*neutronfluxnoisevaluewithintheregionsforwhichmonitoringisrequired(Specification3.4.1.1,ACTIONc)withintwohoursofenteringtheregionforwhichmonitoringisrequiredunlessbaselininghaspreviouslybeenperformedintheregionsincethelastrefuelingoutage.*OetectorlevelsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstringinthecenterofthecoreshouldbemonitored.NineMilePointUnit23/44-2a
L'1PI:,l'P1gpgg1.~aslll,II/R~~'C'glIg5$gb>~")ilIIIflII.slIIgkM5hie5!II)Ils8HRl~~'I1,
REACTOR'COOtANTSYSTEMJET'UMPSLIMITINGCONDITIONFOROPERATION3.4.1.2AlljetpumpsshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITIONS1and2.ACTION:Withoneormorejetpumpsinoperable,beinatleastHOTSHUTDOWNwithin12hours.SURVEILLANCEREUIREMENTS4.4.1.2AlljetpumpsshallbedemonstratedOPERABLEasfollows:a~b.EachoftheaboverequiredjetpumpsshallbedemonstratedOPERABLEpriortoTHERMALPOWERexceeding25KofRATEDTHERMALPOWER,andatleastonceper24hourswhilegreaterthan25KofRATEDTHERMALPOWER,bydeterminingrecirculationloopflow,totalcoreflow.anddiffuser-to-lowerplenumdifferentialpressureforeachjetpumpandverifyingthatnotwoofthefollowingconditionsoccurwhenbothrecirculationloopindicatedflowsareincompliancewithSpecification3.4.1.3.1.'heindicatedrecirculationloopflowdiffersbymorethan10Kfromtheestablished*flowcontrolvalveposition-loopflowcharacteristics.2.Theindicatedtotalcoreflowdiffersbymorethan10/fromtheestablished*totalcoreflowvaluederivedfromrecirculationloopflowmeasurements.'.Theindicateddiffuser-to-lowerplenumdifferentialpressureofanyindividualjetpumpdiffersfromestablished*patternsbymorethan10K.Duringsinglerecirculationloopoperation,eachoftheaboverequiredjetpumpsshallbedemonstratedOPERABLEatleastonceper24hoursbyverifyingthatnotwoofthefollowingconditionsoccur:1.TheindicatedrecirculationloopflowintheoperatingloopdiffersbymorethanlOXfromtheestablishedsinglerecirculationflowcontrolvalveposition-loopflowcharacteristics.*Tobedeterminedduringthestartuptestprogram.NineMilePointUnit23/44-4
REACTOR'COOLANTSYSTEMSURVEILLANCEREUIREMENTSContinued2.Theindicatedtotalcoreflowdiffersbymorethan105fromtheestablishedtotalcoreflowvaluederivedfromsinglerecirculationloopflowmeasurements.3.Theindicateddifference-to-lowerplenumdifferentialpressureofanyindividualjetpumpdiffersfromestablishedsinglerecirculationlooppatternsbymorethan10K.c~TheprovisionsofSpecification4.0.4arenotapplicableprovidedthatthissurveillanceisperformedwithin24hoursafterexceeding25%ofRATEDTHERMALPOWER.NineMilePointUnit23/44-4a
REACTORCOOLANTSYSTEMRECIRCULATIONLOOPFLOW)CJ)fjfPIIt"iil&tJIiDJPtLIMITINGCONDITIONFOROPERATION3.4.1.3aob.Recirculationloopflowmismatchshallbemaintainedwithin:.Cooe+ket.i'.5Xofratedflowwith"coreflowgreaterthanorequalto70Kofratedcoreflow.e44d.I<<100ftd~ftfttf11tt700fratedcoreflow.APPLICABILITY:OPERATIONALCONDITIONSI"And2"P4~t'tnJg<~0LooP~pet44,<on.,ACTION:withtherecirculationloopflowsdifferentbymorethanthespecifiedlimits,either:a.Restoretherecirculationloopflowstowithinthespecifiedlimitwithin2hours,orb.~~~~~~Shu.4h.C~~aIAee++ggt.8l..itCuLt+iOn.+peEtc'Tlo<<~8(UI0e+5g++ci+Lc.~+toAS,wilIicincpl'daiscab$o++pic&icgkiQAbio+5w5d~WqqL<c.ALe.SURVEILLANCEREUIREMENTS0.4.4.1.3Recirculationloopflowmismatchshallbeverifiedtobewithinthelimitsatleastonceper24hours.0'eeSpecialTestException3.10.4.~M4~4,;~eettteIlaw0:b~LLbetheegrc'Iertt&Ittdtwa~resJM(444+4t<<~~~~4<Loop~F5mph9~ss,d.MP~4~bc~++~<0+'+We4WOLOOP+LC,~gNINEMILEPOINT-UNIT23/44-5
REACTIVITYCONTROLSYSTEMSBASES)plJAFf$g~jp!fpgpy3/4.1.3CONTROLRODSThespecificationofthissectionensurethat(1)theminimumSHUTDOWNMARGINismaintained,(2)thecontrolrodinsertiontimesareconsistentwiththoseusedinthesafetyanalyses,and(3)limitthepotentialeffects'oftheroddropaccident.TheACTIONstatementspermitvariationsfromthebasicrequirementsbutatthesametimeimposemorerestrictivecriteriaforcontinuedoperation.Alimitationoninoperable.rodsissetsuchthattheresultanteffectontotalrodworthand.scramshapewillbekepttoaminimum.Therequirementsforthevariousscramtime-measurementsensurethatanyindicationofsystematicproblemswithroddriveswillbeinvestigatedonatimelybasis.Damagewithinthecontrolroddrivemechanismcouldbeagenericproblem,thereforewithacontrolrodimmovablebecauseofexcessivefrictionormechanicalinterference,operationofthereactorislimitedtoatimeperiodwhichisreasonabletodeterminethecauseoftheinoperabilityandatthesametimepreventoperationwithalargenumberofinoperablecontrolrods.Controlrodsthatareinoperableforotherreasonsarepermittedtobetakenoutofserviceprovidedthatthoseinthenonfully-inseFtedpositionareconsistentwiththeSHUTDOWNMARGINrequirements.Thenumberofcontrolrodspermittedtobeinoperablecouldbemorethan,theeightallowedbythespecification,buttheoccurrenceofeightinoperablerodscouldbeindicativeofagenericproblemandthreownforinvestigationandresolutionoftheproblem.~~~u~Lcled.hi>ysolelyL<w1Thecontrolrod'systemisdesignedtobringtheactorsubcriticalataratefastenoughtopreventtheMCPRfrombecominglessthan~i-duringthelimitingpowertransientanalyzed=inSection15.4ftheFSAR.Thisanalysis'howsthatthenegativereactivityratesresultingfromthescramwiththeaverageresponseofallthedrivesasgiveninthespecifications,providetherequiredprotectionandMCPRremainsgreaterthan..Theoccurrenceofscramtimeslongerthenthosespecifiedshouldbeviewedasanindicationofasystemicproblemwiththeroddrivesandthereforethesurveillanceintervalisreducedinordertopreventoperationofthereactorfor-longperiodsoftimewithapotentiallyseriousproblem.ThescramdischargevolumeisrequiredtobeOPERABLEsothatitwfllbeavailablewhenneededtoacceptdischargewaterfromthecontrolrodsduringareactorscramandwillisolate.thereactorcoolantsystemfromthecontainmentwhenrequired.ControlrodswithinoperableaccumulatorsaredeclaredinoperableandSpecification3.1.3.1thenapplies.Thispreventsapatternofinoperableaccumulatorsthatwouldresultinlessreactivityinsertiononascramthanhasbeenanalyzedeventhoughcontrolrodswithinoperableaccumulatorsmaystillbeinsertedwithnormaldrivewaterpressure.Operabilityoftheaccumulatorensuresthatthereisameansavailabletoinsertthecontrolrodsevenunderthemostunfavorabledepressurizationofthereactor.NINEMILEPOINT"UNIT2B3/41-2
POWERDISTRIBUTIONLIMITSBASESAVERAGEPLANARLINEARHEATGENERATIONRATE(Continued)h.~dd1Ch1.CoreCCFLpressuredifferential-1psi-Incorporatetheassumptionthatflowfromthebypasstolowerplenummustovercomea1psipressuredropinc'ore.2.IncoporateNRCpressuretransferassumption-TheassumptionusedintheSAFE"REFLOODpressuretransferwhenthepressureisincreasingwaschanged.AfewofthechangesaffecttheaccidentcalculationirrespectiveofCCFL.Thesechangesarelisted.below.~CC11.BreakAreas-TheDBAbreakareawascalculatedmoreaccurately.h.~dd1Ch1.ImprovedRadiationandConductionCaTculation-IncorporationofCHASTE05forheatupcalculation.Alistofthesignificantplantinputparameterstotheloss-of-coolantaccidentanalysisispresentedinBasesTableB3.2.1-1.3/4.2.2APRMSETPOINTSThefuelcladdingintegritySafetyLimitsofSpecification2.1werebasedonapowerdistributionwhichwouldyieldthedesignLHGRatRATEDTHERMALPOWER.Theflowbiasedsimulatedthermalpower-upscalescramsettingandfloQbiasedneutronfluxupscalecontrolrodblockfunctionsoftheAPRMinstrumentsmustbeadjustedtoensurethattheMCPRdoesnotbecomelessthan1.06orthat>2Xplasticstraindoesnotoccurinthedegradedsituation.ThescramsetpointandrodblocksettingsareadjustedinaccordancewiththeformulainthisspecificationwhenthecombinationofTHERMALPOWERandCMFLPDindicatesahigherpeakedpowerdistributiontoensurethatanLHGRtransientwouldnotbeincreasedinthederadedcondition.anpuwdt-~-.~~'~~NAPL.HCR.>.Z,t-IS,W1I-X~a.w.l-3~J0,P,La~+40Lo~NINEMILEPOINT-UNIT2B3/42-2HOVa0>oBS
BasesTableB3.2.1-1RigQF$gpg~VJtropySIGNIFICANTINPUTPARAMETERSTOTHELOSS-OF-COOLANTACCIDENTANALYSISPlantParameters;CoreTHERMALPOWER.....................3461.MWt"whichcorrespondsto105XofratedsteamflowVesselSteamOutput....................15.0x10ibm/hrwhichcor-6respondsto105KofratedsteamflowVesselSteamDomePressure..............1055psiaDesignBasisRecirculationLineBreakAreafor:a.LargeBreaks3.1ftb.SmallBreaks0.09ftFuelParameters:FUELTYPEFUELBUNDLEGEOMETRYPEAKTECHNICALINITIALSPECIFICATIONDESIGNMINIMUMLINEARHEATAXIALCRITICALGENERATIONRATEPEAKINGPOWER(kw/ft)FACTORRATIOInitialCoreSxs13.41.4,1.20W~Amoredetailed1istingofinputofeachmodelanditssourceispresentedinSectionIIofReference1andsubsection6.3.3oftheFSAR."ThispowerlevelmeetstheAppendixKrequirementof102.Thecoreheatupcalculationassumesabundlepowerconsistentwithoperationofthehighestpoweredrodat102KofitsTechnicalSpecificationLINEARHEATGENERATIONRATElimit.NINEMILEPOINT-UNIT2B3/42-3
POWERDISTRIBUTIONLIMITSBASES3/4.2.3MINIMUMCRITICALPOWERRATIOTherequiredoperatinglimitMCPRsatsteadystateoperatingconditionsasspecifiedinSpecification3;2.3arederivedfromtheestablishedfuelcladdingintegritySafetyLimitMCPR-A=RW8,andananalysisofabnormaloperationaltransients.Foranyabnormaloperatingtransientanalysisevalua-tionwiththeinitialconditionofthereactorbeingatthesteadystateoperatinglimit,itisrequiredthattheresultingHCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytimeduringthetransientassuminginstrumenttripsettinggiveninSpecification2.2.ToassurethatthefuelcladdingintegritySafetyLimitisnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtran-sientshavebeenanalyzedtodeterminewhichresultinthelargestreductioninCRITICALPOWERRATIO(CPR).Thetypeoftransientsevaluatedwerelossofflow,increaseinpressureandpower,positivereactivityinsertion,andcoolanttemperaturedecrease.TheevaluationofagiventransientbeginswiththesysteminitialparametersshowninFSARTable15.0.3thatareinputtoaGE-coredynamicbehaviortransientcomputerprogram.Thecodeusedtoevaluatepressurizationeventsis'describedinNEDO-24154andtheprogramusedinnon-pressurizationeventsisdescribedinNEDO-10802.TheoutputsofthisprogramalongwiththeinitialHCPRformtheinputforfurtheranalysesofthethermallylimitingbundlewiththesinglechanneltransientthermalhydraulicTASCcodedescribedinNEDE-25149.TheprincipalresultofthisevaluatonisthereductioninMCPRcausedbythetransient.ThepurposeoftheKffactorofFigure3.2.3+istodefineoperating/limitsatotherthanratedcoreflowconditions.Atlessthan100Kofratedflowthe.requiredHCPRistheproductoftheHCPRandtheKfactor.TheKffactorsassurethattheSafetyLimitMCPRwillnotbeviolated.TheK~'actorswerederivedusingTHERMALPOWERandcoreflowcorrespondingtb,.lOSXofratedsteamflow.TheKffactorswerecalculatedsuchthatforthemaximumcoreflowrateandthecorrespondingTHERMALPOMERalongthe105Kofratedsteamflowcontrolline,thelimitingbundle'srelativepowerwasadjusteduntiltheMCPRwasslightlyabovetheSafetyLimit.Usingthisrelativebundlepower,theHCPRswerecalculatedatdifferentpointsalongthe105Kofratedsteamflowcontrol-'inecorrespondingtodifferentcoreflows.TheratiooftheMCPRcalculatedatagivenpointofcoreflow,dividedbytheoperatinglimitMCPR,determinestheKf.NINEMILEPOINT-UNIT2B3/42"4NbV2d199 l 3/4.4REACTORCOOLANTSYSTEMpg,IFppfi~ppp'p~@qiana~BASES3/4.4.1RECIRCULATIONSYSTEMpg~~e~<+kZestt'+2,TheobjectiveofGEBWRplantandfueldesignistoprovidestableoperationwithmarginoverthenormaloperatingdomain.However,atthehighpower/lowflowcorneroftheoperatingdomain,asmallprobabilityoflimitcycleneutronfluxoscillationsexistsdependingoncombinationsofoperatingconditions(e.g.,rodpattern,powershape).Toprovideassurancethatneutronfluxlimitcycleoscillationsaredetectedandsuppressed,APRMandLPRMneutronfluxnoiselevelsshouldbemonitoredwhileoperatinginthisregion.StabilitytestsatoperatingBWRswerereviewedtodetermineagenericregionofthepower/flowmapinwhichsurveillanceofneutronfluxnoiselevelsshouldbeperformed.Aconservativedecayratioof0.6waschosenasthe'basesfordeterminingthegenericregionforsurveillancetoaccountfortheplanttoplantvariabilityofdecayratiowithcoreandfueldesigns.Thisgenericregionhasbeendeterminedtocorrespondtoacoreflowoflessthanorequalto45KofratedcoreflowandaTHERMALPOWERgreaterthanthatspecifiedinFigure3.4.1.1-'1.Plantspecificcalculationscanbeperformedtodetermineanapplicableregionformonitoringneutronfluxnoiselevels.Inthiscasethedegreeofconservatismcanbereducesinceplanttoplantvariabilitywouldbeeliminated.Inthiscase,adequatemarginwillbeassuredbymonitoring,theregionwhichhasadecayratiogreaterthanorequalto0.8.,Neutronfluxnoiselimitsarealsoestablishedtoensureearlydetectionoflimitcycleneutronfluxoscillations.BWRcorestypicallyoperatewithneutronfluxnoisecausedbyrandomboilingandflownoise.Typicalneutron.fluxnoiselevelsof1-12"ofratedpower(peak-to-peak)havebeenreportedfortherangeofIowtohighrecirculationloopflowduringbothsingleanddualrecirculationloopoperation.Neutronfluxnoiselevelswhichsignifi-cantlyboundthesevaluesareconsideredinthethermal/mechanicaldesignofGEBWRfuelandarefoundtobeofnegligibleconsequence.Inaddition,sta-bilitytestsatoperatingBWRshavedemonstratedthatwhenstabilityrelatedneutronfluxlimitcycleoscillationsoccurtheyresultinpeak-to-peakneutronfluxlimitcyclesof5-10timesthetypicalvalues.Therefore,actionstakent'oreduceneutronfluxnoiselevelsexceedingthree(3)timesthetypicalvaluearesufficienttoensureearlydetectionoflimitcycleneutronfluxoscillations.Typically,neutronfluxnoiselevelsshowagradualincreaseinabsolutemagnitudeascoreflowisincreased(constantcontrolrodpattern)withtworeactorrecirculationloopsinoperation.Therefore,thebaselineneutronNINEMILEPOINT-UNIT2B3/44-1yzvP01985
REACTORCOOLANTSYSTEM3/4.4REACTORCOOLANTSYSTEMP,AAV,BASES3/4.4.1RECIRCULATIONSYSTEM(Continued}fluxnoiselevelobtainedataspecifiedcoreflowcanbeappliedover'arangeofcoreflows.Tomaintainareasonablevariationbetweenthelowflowandhighflowendoftheflowrange,therangeoverwhichaspecificbaselineisappliedshouldnotexceed20Kofratedcoreflowwithtworecirculationloopsinoperation.Datafromtestsandoperatingplantsindicatethatarangeof20Kofratedcoreflowwillresultinapproximatelya50'ncreaseinneutronfluxnoiselevelduringoperationwithtworecirculationloops.Baselinedatashouldbetakennearthemaximumrodlineatwhichthemajorityofoperationwilloccur.However,baselinedatatakenatlowerrodlines(i.e.,lowerpowerwillresultinaconservativevaluesincetheneutronfluxnoiselevelisproportionaltothepowerlevelatagivencoreflow.Aninoperablejetpumpisnot,initself,asufficientreasontodeclarearecirculationloopinoperable,butitdyes,incaseofadesign-basis-accident,increasetheblowdownareaandreducethecapabilityofrefloodingthecore;thus,therequirementforshutdownofthefacilitywithajet-pumpinoperable.Jetpumpfailurecanbedetectedbymonitoringjetpumpperformanceonaprescribedschedulefors'ficantderadation.c.vlofectncu.toa+<ocft4HRecirculationoopfowm>smacimitsaresncompliancewiththeECCSLOCAanalysisdesigncriteria~The'limitswillensureanadequatecoreflowcoastdownfromeitherrecirculationloopfollowingaLOCA.QppltcQwAk~t45pctInordertopreventunduestressonthevesselnozzlesandbottomheadregion,therecirculationlooptemperaturesshallbewithin50'Fofeachotherpriortostartupofanidleloop.Thelooptemperaturemustalsobewithin50Fofthereactorpressurevesselcoolanttemperaturetoprevemalshocktotherecirculationpumpandrecirculationnozzles.~03/4.4.2SAFETY/RELIEFVALVES~8nKe~1~~<+4Mesc>4Thesafety/reliefvalvesoperateduringapostulatedATMSeventtoi"prevent.thereactorcoolantsystembeingpressurizedaboveadesignallowablevalueof1375psiginaccordancewiththeASMECode.Atotalof17OPERABLEsafety/reliefvalvesisrequiredtolimitlocalpressureatactivecomponentstowithinASMEIIIallowabledesignvalues(ServiceLevelA}.AllotherappropriateASMEIIIlimitsarealsoboundedbythisrequirement.Demonstrationofthesafety-reliefvalveliftsettingswilloccuronlyduringshutdownandwillbeperformedinaccordancewiththeprovisionsofSpecification4.0.5.NINEMILEPOINT-UNIT2B3/44-2NOV201985
INSERT'"E"Theimpactofsinglerecirculationloopoperationuponplantsafetyisassessedandshowsthatsingle-loopoperationispermittediftheMCPRfuelcladdingsafetylimitisincreasedasnotedbySpecification2.1.2,APRMscramandcontrolrodblocksetpointsareadjustedasnotedinTables2.2.1-1and3.3.6.2,respectively,MAPLHGRlimitsaredecreasedbythefactorgiveninSpecification3.2.1,andMCPRoperatinglimitsareadjustedperSection3/4.2.3.Additionally,surveillanceonthevolumetricflowrateoftheoperatingrecirculationloopisimposedtoexcludethepossibilityofexcessivecoreinternalsvibration.Thesurveillanceondifferentialtemperaturesbelow30K*THERMALPOWERor50K+ratedrecirculationloopflowistomitigatetheunduethermalstressonvesselnozzles,recirculationpumpandvesselbottomheadduringtheextendedoperationofthesinglerecirculationloopmode.INSERT"F"Inthecasewherethemismatchlimitscannotbemaintainedduringtwoloopoperation,continuedoperationispermittedinasinglerecirculationloopmode.INSERT"G"Suddenequalizationofatemperaturedifference145'Fbetweenthereactorvesselbottomheadcoolantandthecoolantintheupperregionofthereactorvesselbyincreasingcoreflowratewouldcauseunduestressinthereactorvesselbottomhead.*Initialvalues.ThefinalvaluesaredeterminedduringstartuptestingbaseduponthethresholdTHERMALPOWERandrecirculationloopflowwhichwillsweepthecoldwaterfromthevesselbottomhead,preventingsaturation.
ATTACHMENTEENDOFCYCLE-RECIRCULATIONPUMPTRIPINOPERABLEANDTURBINEBYPASSINOPERABLEPROPOSEDTECHNICALSPECIFICATIONCHANGES
POWER'ISTRIBUTION'IMITS3/4;2;3'MINIMUMCRITICAL'POWER'RATIOLIMITING'ONDITION'OR'PERATION.2.3TheMINIMUMCRITICALPOWERRATIO(MCPR)shallbeequaltoorgreaterthantheMCPRlimitshowninFigure3.2.3-1timestheKfshowninFigure3.2.3-2with:~ave--~BA-8where:~A=0.86seconds,controlrodaveragescraminsertiontimelimittonotch39perSpecification3.1.3.3,B=O.6BB+nXave=i=1n1~65[-]6[0.052jiI"3.Ninumberofsurveillancetestsperformedtodateincycle,Nl=numberofactivecontrolrodsmeasuredintheithsurveillancetest,i=averagescramtimetonotch39ofallrodsmeasuredintheithsurveillancetest,andNl=totalnumberofactiverodsmeasuredinSpecification4.1.3.2.a.APPLICABILITY:OPERATIONCONDITION1,whenTHERMALPOWERisgreaterthanorequalto25KofRATEDTHERMALPOWER.NINEMILEPOINTUNIT2
POWER'ISTRIBUTION'IMITSLIMITINGCONDITIONFOR.OPERATIONContinuedACTIONa.Withtheend-of-cyclerecirculationpumptripsysteminoperableperSpecification3.3.4.2,operationmaycontinueandtheprovisionsofSpecification3.0.4arenotapplicableprovidedthat,withinonehour,MCPRisdeterminedtobeequaltoorgreaterthantheMCPRlimitshowninFigure3.2.3-1EOC-RPTinoperablecurve,timestheKfshowninFigure3-2~b.WiththemainturbinebypasssysteminoperableperSpecification3.7.8,operationmaycontinueandtheprovisionsofSpecification3.0.4arenotapplicableprovidedthat,withinonehour,MCPRisdeterminedtobeequaltoorgreaterthantheMCPRlimitshowninFigure3.2.3-1,mainturbinebypassinoperablecurvetimestheKfshowninFigure3.2.3-2.c.WithMCPRlessthantheapplicableMCPRlimitdeterminedfromFigures3.2.3-1and3.2.3-2,asapplicable,initiatecorrectiveactionwithin15minutestorestoreMCPRwithintherequiredlimit.RestoreMCPRtowithintherequiredlimitwithin4hours,ifnecessary,byreducingTHERMALPOWERtothelevelrequired.SURVEILLANCE'EQUIREMENTS'4.2.3MCPR,with:a.T=1.0priortoperformanceoftheinitialscramtimemeasurementsforthecycleinaccordancewithSpecification4.1.3.2,orb.gasdefinedinSpecification3.2.3usedtodeterminethelimitwithin72hoursoftheconclusionofeachscramtimesurveillancetestrequiredbySpecification4.1.3.2,c.TheprovisionsofSpecification4.0.4arenotapplicableshallbedeterminedtobeequaltoorgreaterthantheapplicableMCPRlimitdeterminedfromFigures3.2.3-1and3.2.3-2:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLRODPATTERNforMCPR.d.TheprovisionsofSpecification4.0.4arenotapplicable.NINEMILEPOINTUNIT2
1,391.37MAIURBIAN0RABL1.35.CC~1.33CDCLa1.311.29iMEOC-0RABLE1.271.25MAIEOC-URBINEBYPSSRPTANDe1.230.81.00.600.4TAU,vFIGURE3.2.3-1MINIMUMCRITICALPOWERRATIO,MCPR,vsTAUATRATEDFLOW
1.00.92050304060'kCOREFLOM,PercentFIGURE3.2.3pFfASAFUNCTIONOFPERCENTCOREFLOM708090100
INSTRUMENTATIONsItgPiFQQf/~+~~j)fop/END"OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMINSTRUMENTATIONLIMITINGCONDITIONFOROPERATION3.3.4.2Theend-of-cyclerecirculationpumptrip(EOC-RPT)systeminstrumentationchannelsshowninTable3.3.4.2-1shallbeOPERABLEwiththeirtripsetpointssetconsistentwiththevaluesshownintheTripSetpointcolumnofTable3.3.4.2-2andwiththeEND-OF-CYCLERECIRCULATIONPUMPTRIPSYSTEMRESPONSE-TIMEasshowninTable3.3.4.2-3.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorIIATKBiHKIIMALPWKII.ACTIDN:aOC..d.e.Withanend-of-cyclerecirculationpumptripsysteminstrumentationchanneltripsetpointlessconservativ'ethanthevalueshownintheAllowableValuescolumnofTable3.3.4.2-2,declarethechannelinhperableuntilthechannelisrestoredtoOPERABLEstatuswiththechannelsetpointadjustedconsistentwiththeTripSetpointvalue.WiththenumberofOPERABLEchannelsonelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementfoioneorbothtripsystems,placetheinoperablechannel(s)inthetrippedconditionwithinonehour.WiththenumberofOPERABLEchannelstwoormorelessthanrequiredbytheMinimumOPERABLEChannelsperTripSystemrequirementforonetripsystemand:l.Iftheinoperablechannelsconsistofoneturbinecontrolvalvechannelandoneturbinestopvalvechannel,placebothinoperablechannelsinthetrippedconditionwithinonehour.2.Iftheinoperablechannelsincludetwoturbinecontrolvalvechannelsortwoturbinestopvalvechannels,declarethetripsysteminoperable.Withonetripsysteminoperable,restoretheinoperabletripsystemtoOPERABLEstatuswithin72hoursorAc.Y(ogDlglgWithbothtripsystemsnoperable,restoreatleastonetripsystemtoOPERABLEstatuswithinonehourorPctiOB.~NINEMILEPOINT-UNIT23/43"44HOV20loB5
PLANTSYSTEMS3/4.?.9MAINTURBINEBYPASSSYSTEM),gJtI'i)pf.T.,JLnplfLIMITINGCONDITIONFOROPERATION3.7.9ThemainturbinebypasssystemshallbeOPERABLE.APPLICABILITY:OPERATIONALCONDITION1whenTHERMALPOWERisgreaterthanorRqq22RATERThERMALTOIIER.ACTION:Withthemainturbinebypass~OPRABLEstatuswithin1hourorsysteminoperable,restorethesystemtoJL-eLtuf~AClION~SURVEILLANCEREUIREMENTS4.7.9Themainturbinebypasssystem'shallbedemonstratedOPERABLE:a.Atleastonceper18monthsby:1.Performingasystemfunctionaltestwhichincludessimulatedautomaticactuationandverifyingthateachautomaticvalveactuatestoitscorrect,position.2.DemonstratingTURBINEBYPASSSYSTEMRESPONSETIMEmeetsthefollowingrequirementswhenmeasuredfrominitialmovementofthemainturbinestoporcontrolvalve:a.80Koftheturbinebypasssystemcapacityshallbeestab-lishedwithin0.3seconds,andb.Bypassvalveopeningshallstartinlessthanorequalto.0.1seconds.NINEMILEPOINT-UNIT23/47-35Nnv201985
POMERDISTRIBUTIONLIMITSBASES3/4.2.3MINIMUMCRITICALPOWERRATIOTherequiredoperatinglimitMCPRsatsteadystateoperatingcondftionsasspecifiedinSpecification.3.2.3arederivedfromtheestablishedfuelcladdingintegritySafetyLimitMCPRof1.06,andananalysisofabnormaloperationaltransients.Foranyabnormaloperatingtransientanalysisevalua-tionwiththeinitialconditionofthereactorbeingatthesteadystateoperatinglimit,itisrequiredthattheresultingMCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytimeduringthetransientassuminginstrumenttripsettinggiveninSpecification2.2.ToassurethatthefuelcladdingintegritySafetyLimitisnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtran-sientshavebeenanalyzedtodeterminewhichresultinthelargestreductioninCRITICALPOMERRATIO(CPR).Thetypeoftransientsevaluatedwerelossofflow,increaseinpressureandpower,positivereactivityinsertion,andcoolanttemperaturedecrease.ThelimitingtransientyieldsthelargestdeltaMCPR.WhenaddedtotheSafetyLimitMCPRof1.06,therequiredminimumoperatinglimitMCPRofSpecification3.2.3isobtainedandpresentedinFigure3.2.3-1.TheevaluationofagiventransientbeginswiththesysteminitialparametersshowninFSARTable15.0.3thatareinputtoaGE-coredynamicbehaviortransientcomputerprogram.ThecodeusedtoevaluatepressurizationeventsisdescribedinNEDO-24154andtheprogramusedinnon-pressurizationeventsisdescribedinNEDO-10802.TheoutputsofthisprogramalongwiththeinitialMCPRformtheinputforfurtheranalysesofthethermallylimitingbundlewiththesinglechanneltransientthermalhydraulicTASCcodedescribedinNEDE-25149~~.TheprincipalresultofthisevaluationisthereductioninMCPRcausedbythetransient.ThepurposeoftheKffactorofFigure3.2.3-istodefineoperatinglimitsatotherthanratedcoreflowconditions.Atlessthan100KofratedflowtherequiredMCPRistheproductoftheMCPRandtheKfactor.TheKffactorsassurethattheSafetyLimitMCPRwillnotbeviolated.TheKfactorswerederivedusingTHERMALPOWERandcoreflowcorrespondingt3105Kofratedsteamflow.TheKffactorswerecalculatedsuchthatforthemaximumcoreflowrateandthecorrespondingTHERMALPOMERalongthe105Kofratedsteamflowcontrolline,thelimitingbundle'srelativepowerwasadjusteduntiltheMCPRwasslightlyabovetheSafetyLimit.Usingthisrelativebundlepower,theMCPRswerecalculatedatdifferentpointsalongthe105Kofratedsteamflowcontrollinecorrespondingtodifferentcoreflows.TheratiooftheMCPRcalculatedatagivenpointofcoreflow,dividedbytheoperatinglimitMCPR,determinestheKf.NINEMILEPOINT"UNIT283/42-4NGV20l59."
ATTACHMENTFSINGLELOOPOPERATIONANALYSIS
NMPZAPPENDIX15.BTABLEOFCONTENTS15.BRECIRCULATIONSYSTEMSINGLE-LOOPOPERATION~Pae15.B.1-115.B.1INTRODUCTIONANDSUMMARY15.B.1-115.B.ZMCPRFUELCLADDINGINTEGRITYSAFETYLIMIT'5.B.2.1CoreFlowUncertainty15.B.2.1.1CoreFlowMeasurementDuringSingle-LoopOperation15.B.2.1.2,CoreFlowUncertaintyAnalysis15.B.2.2TIPReadingUncertainty15.B.2-115.B.2-115.B.2-115.B.2-215.B.2-415.B.3MCPROPERATINGLIMIT15.B.3.1AbnormalOperationalTransients15.B.3.l.1FeedwaterControllerFailure-MaximumDemand15.B.3.1.2GeneratorLoadRejectionWithBypassFailure15.B.3.1.3SummaryandConclusions15.B.3.2RodWithdrawalError15.B.3.3OperatingMCPRLimit15.B.3-115.B.3-115.B.3-215.B.3-415.B.3-515.B.3-515.B.3-715.8.4STABILITYANALYSIS'5.B.4.1Phenomena15.B.4.2CompliancetoStabilityCriteria15.B.4-115.B.4-115.B.4-215.B.5LOSS-OF-COOLANTACCIDENTANALYSIS15.B.5.1BreakSpectrumAnalysis15.B.5.2.-Single-LoopMAPLHGRDetermination15.B.S.3SmallBreakPeakCladdingTemperature15.B.5-115.B.5-215.B.5-215.B.5-315.B-i 0 NMPZTABLEOFCONTENTS(Continued)~Pae15.B.6CONTAINMENTANALYSIS15.B.6-115.B.7MISCELLANEOUSIMPACTEVALUATION15.B.7.1AnticipatedTransientWithoutScramImpact15.B.7.2FuelMechanicalPerformance15.B.7.3VesselInternalVibration15.8.7-115.B.7-115.B.7-115.B.7-115.B.8REFERENCES15.B.8-115.B-ii 0 NMP2LISTOFTABLESNUMBERTITLEPAGE15.B.3-1InputParametersandInitialConditions15.B.3-8,9,1015.B.3-2SequenceofEventsforFeedwaterController15.B.3-11Failure,MaximumDemand(Figure15.B.3-2)15.B.3-3Sequence.ofEventsforGeneratorLoadRejectionWithBypassFailure(Figure15.B.3-3)15.B.3-1215.8.3-4Summary.ofTransientPeakValue'ndCPRResults15.B.3-1315.B.6-1ComparisonofContainmentPeakPressures15.B.6-315.B-iii
NMP2LISTOFFIGURESNUMBERTITLEPAGE15.B.2-1IllustrationofSingleRecirculationLoop15.B.2-6OperationFlows15.B.3-1PeakDomePressurevs.InitialPowerLevel,15.B.3-14LRBPFatEOC15.B.3-2FeedwaterControllerFailure-MaximumDemand15.B.3-15,75KPower,60%Flow16,17,1815.B.3-3GeneratorLoadRejection-withBypassFailure15.B.3-19,75KPower,60KFlow20,21.2215.B.5-1UncoveredTimevs.BreakArea-SuctionBreak,LPCSDieselGeneratorFailure15.B.5-415.B.6-1DrywellandWetwellPressureResponses-15.B-6.4RecirculationBreak,55KPower,35KCoreFlow15.B.6-2\DrywellandWetwellTemperatureResponses-15.8-6.5RecirculationLineBreak,55KPower,35%CoreFlow15.B-iv
NMP215.BRECIRCULATIONSYSTEMSSINGLE-LOOPOPERATION15.B.1.INTRODUCTIONANDSUMMARYSingle-loopoperation(SLO)atreducedpowerishighlydesirableintheeventrecirculationpumporothercomponentmaintenancerendersoneloopinoperative.To.justifysingle-loopoperation,accidentsandabnormaloperationaltransientsassociatedwithpoweroperations,aspresentedinSections6.2and6.3andthemaintextofChapter15.0,werereviewedforthesingle-loopcasewithonlyonepumpinoperation.ThisappendixpresentstheresultsofthissafetyevaluationfortheoperationoftheNineMilePointUnit2(NMP2)withsinglerecirculationloopinoperable.ThisevaluationisperformedforGE-6fueledNMP2onaninitialcyclebasisandisapplicabletoGE-6fuelednormalinitialcycleoperation.TheconditionsarethoseofcontinuedoperationintheoperatingdomaincurrentlydefinedinFigure4.4.5ofChapter4uptomaximumpowerofapproximately70%ofrated.IncreaseduncertaintiesinthecoretotalflowandTraversingIn-CoreProbe(TIP)readingsresultedina0.01incrementalincreaseintheMinimumCriticalPowerRatio(MCPR)fuelcladdingintegrity'afetylimitduringsingle-loopoperation.NoincreaseinratedHCPRoperatinglimitandnochangeintheflowdependentMCPRlimit(MCPRf)isrequiredbecauseallabnormaloperationaltransientsanalyzedforsingle-loopoperationindicatedthatthereismorethanenoughHCPRmargintocompensateforthisincreaseinMCPRsafetylimit.Therecirculationflowratedependentrodblock=andscramsetpointequationgivenin.Chapter16(TechnicalSpecifications)areadjustedforone-pumpoperation.Thermal-hydraulicstabilitywasevaluatedforitsadequacywithrespecttoGeneralDesignCriteria12(10CFR50,AppendixA).ItisshownthatSLOsatisfiesthisstabilitycriterion.ItisfurthershownthattheincreaseinneutronnoiseobservedduringSLOisindependentofsystemstabilitymargin.~~rw'HTK:jsL11151415.B.1-1
NMP2Topreventpotentialcontroloscillationsfromoccurringintherecircu-lationflowcontrolsystem,theflowcontrollershouldbeinmastermanual.forsingle-loopoperation.ThelimitingMaximumAveragePlanarLinearHeatGenerationRate(MAPLHGR)reductionfactorforsingle-loopoperationiscalculatedtobe0.81.ThecontainmentresponseforaDesignBasisAccident(DBA)recirculationlinebreakwithsingle-loopoperationisboundedbytheratedpowertwo-loopoperationanalysispresentedinSection6.2.Thisconclusioncoversallsingle-loopoperationpower/flowconditions.TheimpactofsingleloopoperationontheAnticipatedTransientWithoutScram(ATWS)analysiswasevaluated.ItisfoundthatallATWSacceptancecriteriaaremetduringSLO.ThefuelthermalandmechanicaldutyfortransienteventsoccurringduringSLOisfoundtobeboundedbythefueldesignbases.TheAveragePowerRangeMonitor(APRM)fluctuationshouldnotexceedafluxamplitudeof+15'Aofratedandthecoreplatedifferentialpressurefluctuationshouldnotexceed3.2psipeaktopeaktobeconsistentwiththefuelrodandassemblydesignbases.ArecirculationpumpdriveflowlimitisimposedforSLO.Thehighestdriveflowthatmeetsacceptablevesselinternalvibrationcriteriaisthedrive'flowlimitforSLO.TheexpectedallowabledriveflowinSLOisapproximately41,000gpm.Actualdriveflowflimitin.SLOwillbe.determinedduringthestartuptestprogramatNMP2.HTK:jsL111514I15.B.1-2
NMPZ15.8.2MCPRFUELCLADDINGINTEGRITYSAFETYLIMITExceptforcoretotalflowandTIPreading,theuncertaintiesusedinthestatisticalanalysistodeterminetheMCPRfuelcladdingintegritysafetylimitarenotdependentonwhether,coolantflowisprovidedbyoneortworecirculationpumps.Uncertaintiesusedinthetwo-loopoperationanalysisaredocumentedintheFSAR.A6Xcoreflopmeasurementuncer-taintyhasbeenestablishedforsingle-loopoperation(comparedto2.5Xfortwo-loopoperation).Asshownbelow,thisvalueconservativelyreflectstheonestandarddeviation(onesigma)accuracyofthecoreflowmeasurementsystemdocumentedinReference15.B.8-1.TherandomnoisecomponentoftheTIPreadinguncertaintywasrevisedforsinglerecircu-lationloopoperationtoreflecttheoperatingplanttestresultsgiveninSubsection15.B.2.2.Thisrevisionresultedinasingle-loopoperationprocesscomputereffectiveTIPuncertaintyof6.8Xofinitialcoresand9.1%forreloadcores.Comparabletwo-loopprocesscomputeruncertaintyvaluesare6.3lforinitialcoresand8.7%forreloadcores.Theneteffectofthesetworeviseduncertaintiesisa0.01increaseintherequiredMCPRfuelcladdingintegritysafetylimit.15.B.2.1CoreFlowUncertaint15.8.2.l.1CoreFlowMeasurementDurinSinle-Loo0erationThejetpumpcoreflowmeasurementsystemiscalibratedtomeasurecoreflowwhenbothsetsofjetpumpsareinforwardflow;totalcoreflowisthesumoftheindicatedloopflows.Forsingle-loopoperation,however,someinactivejetpumpswi11bebackflowing(atactivepumpflowaboveapproximately38%).Therefore,themeasuredflowinthebackflowingjetpumpsmustbesubtractedfromthemeasuredflowintheactivelooptoobtainthetotalcoreflow.Inaddition,thejetpumpcoefficientisdifferentforreverseflowthanforforwardflow,andthemeasurementofreverseflowmustbemodifiedtoaccountforthisdifference.Insingle-loopoperation,thetotalcoreflowisderivedbythefollowingformula:15.B.2-1
NMP2TotalCoreFlowActiveLoopIndicatedFlowInactiveLoopIndicatedFlowWhereC(=0.95)isdefinedastheratioof"InactiveLoopTrueFlow"to"InactiveLoopIndicatedFlow"."LoopIndicatedFlow"istheflowmeasuredbythejetpump"single-tap"loopflowsummersandindicators,whicharesettoreadforwardflowcorrectly.The0.95factorwastheresultofaconservativeanalysistoappropriatelymodifythesingle-tap.flowcoefficientforreverseflow.*Ifamoreexact,lessconservative'oreflowisrequired,specialin-reactorcalibrationtestswouldhavetobemade.Suchcalibrationtestswouldinvolve:calibratingcoresupportplatehPversuscoreflowduringone-pumpandtwo-pumpoperationalongwith100%flowcontrollineandcalculatingthecorrectvalueofCbasedonthecoresupportplatehPandtheloopflowindicatorreadings.15.B.2.1.2CoreFlowUncertaintAnalsisTheun'certaintyanalysisprocedureusedtoestablishthecoreflowuncertaintyforone-pumpoperationisessentiallythesameasfortwo-pumpoperation,withsomeexceptions.ThecoreflowuncertaintyanalysisisdescribedinReference15.B.8-1.Theanalysisofone-pumpcoreflowuncertaintyissummarizedbelow.forsingle-loopoperation,thetotalcoreflowcanbeexpressedasfollows(refertoFigure15.8.2-1):*Theanalyticalexpectedvalueofthe"C"coefficientforNMP2is0.88.15.8.2-2
NHP2WC=WA-WIwhere:WC=totalcoreflow,WA=activeloopflow,andWI=inactiveloop(true)flow.Byapplyingthe"propagationoferrors"methodtotheaboveequation,thevarianceofthetotalflowuncertaintycanbeapproximatedby:0~U~WCW21-aa~WAranda2+]-aQ2Q2WICrandwhere:WCuncertaintyoftotalcoreflow;Wsysuncertaintysystematictobothloops;WArandrandomuncertaintyofactivelooponly;WIrandrandomuncertaintyofinactivelooponly;uncertaintyof"C"coefficient;andratioofinactiveloopflow(WI)toactiveloop<<ow(WA).15.B.2"3
NMP2Fromanuncertaintyanalysis,theconservative,boundingvaluesofoW,eW,oWanaC~dNrandrandsysArespectively.Basedontheaboveuncertaintiesandaboundingvalueof0.36*for"a",thevarianceofthetotalflowuncertaintyisapproximately:WC(16)z+~ga(2.6)z+~~(35)a+(28)=(5.0X)'hentheeffectof4.1%corebypassflowsplituncertaintyat12%(bo'undingcase)bypassflowfractionisaddedtothetotalcoreflowuncertainty,theactivecoolantflowuncertaintyis:(S.DX,)'ctive.='~>'(4.1'5)'(5.1%)a0.12coolantwhichislessthanthe6Xflowuncertaintyassumedinthestatisticalanalysis.Insummary,coreflowduringone-pumpoperationismeasuredinaconser-vativewayanditsuncertaintyhasbeenconservativelyevaluated.15.B.2.2TIPREADINGUNCERTAINTYToascertaintheTIPnoiseuncertaintyforsinglerecirculationloopoperation,atestwasperformedatanoperatingBWR.Thetestwasperformedatapowerlevel59.3%ofratedwithasinglerecirculationpumpinoperation(coreflow46.3Xofrated).Arotationallysymmetriccontrolrodpatternexistedduringthetest.*Thisflowsplitratiovariesfromabout0.13to0.36.The0.36valueisaconservativeboundingvalue.'TheanalyticalexpectedvalueoftheflowsplitratioforNMP2is~0.23.15.B.2-4
NMP2FiveconsecutivetraversesweremadewitheachoffiveTIPmachines,givingatotalof25traverses.Analysisofthisdataresultedinanodal.TIPnoiseof2.85%.UseofthisTIPnoisevalueasacomponentoftheprocesscomputertotaluncertaintyresultsinaone-sigmaprocesscomputertotaleffectiveTIPuncertaintyvalueforsingle-loopoperationof6.8Xforinitialcoresand9.1%forreloadcores.15.8.2-5
WAwcWzWc~TotalCoreFlowMA~ActiveLoopFlowMg~InactiveLoopFlowgaraNohawkPowerCorp.IllustrationofSingleRecirculationLoopOperationFlowsFigure15.B.2-115.B.2-6
NMP215.8.3MCPROPERATINGLIMIT15.B.3;1ABNORMALOPERATINGTRANSIENTSOperatingwithonerecirculationloopresultsinamaximumpoweroutputwhichisabout30'Abelowthatwhichisattainablefortwo-pumpoperation.Therefore,theconsequencesofabnormaloperationtransientsfromone-loopoperationwillbeconsiderablylessseverethanthoseanalyzedfromatwo-loopoperationalmode.Forpressurization,flowincrease,flowdecrease,andcoldwaterinjectiontransients,theresultspresentedinChapter15boundboththethermalandoverpressureconsequencesofone-loopoperation.Figure15.B.3-1showstheconsequencesofatypicalpressurizationtransient(generatorloadrejection)asafunctionofpowerlevel.Ascanbeseen,theconsequencesofone-loopoperationareconsiderablylessbecauseoftheassociatedreductioninoperatingpowerlevel.Theconsequencesofflowdecreasetransientsarealsoboundedbythefullpoweranalysis.Asinglepumptripfromone-loopoperationis.lessseverethanatwo-pumptripfromfullpowerbecauseof'hereducedinitialpowerlevel.Theworstflowincreasetransientresultsfromrecirculationflowcon-trollerfailure,andtheworstcoldwaterinjectiontransientresultsfromthelossoffeedwaterheater.Fortheformer,theMCPRf(Kf)curveisderivedassumingbothmecirculationloopcontrollersfail.This.conditionproducesthemaximumpossiblepowerincreaseandhencemaximumhCPRfortransientsinitiatedfromlessthanratedpowerandflow.Whenoperatingwithonlyonerecirculationloop,theflowandpowerincreaseassociatedwiththisfailurewithonlyoneloopwillbelessthanthatassociatedwithbothloops;therefore,theKfcurvederivedwiththetwo-pumpassumptionisconservativeforsingle-loopoperation.Thelatterevent,lossoffeedwaterheating,isgenerallythemostseverecoldwaterincreaseeventwithrespecttoincreaseincorepower.Thiseventiscausedbypositivereactivityinsertionfromcoreinlet15.B.3-1
NMP2subcoolinganditisrelativelyinsensitivetoinitialpowerlevel.Agenericstatisticallossoffeedwaterheateranalysisusingdifferentinitialpowerlevelsandothercoredesignparametersconcludedone-pumpoperationwithlowerinitialpowerlevelisconservativelyboundedbythefullpowertwo-pumpanalysis.InadvertentrestartoftheidlerecirculationpumphasbeenanalyzedintheFSAR(Chapter15.4.4)andisstillapplicableforsingle-loopoperation.'IFromtheabovediscussions,itisconcludedthatthetransientconsequencefromone-loopoperationisboundedbypreviouslysubmittedfullpoweranalyses.Themaximumpowerlevelthatcanbeattainedwithone-loop.operationisonlyrestrictedbytheMCPRandoverpressurelimitsestab-lishedfromafull-poweranalysis.Inthefollowingsections,theresultsoftwoofthemostlimitingtransientsanalyzedforsingle-loopoperationarepresented.Theyare,respectively:a.feedwaterflowcontrollerfailure(maximumdemand),(FWCF)b.generatorloadrejectionwithbypassfailure,(LRBPF).TheplantinitialconditionsaregiveninTable15.B.3-115.B.3.1.1FeedwaterControllerFailure-MaximumDemandThiseventis.postulatedonthebasisofasinglefailureofacontrol.device,specificallyonewhichcandirectlycauseanincreaseincoolantinventorybyincreasingthefeedwaterflow.Themostsevereapplicableeventisafeedwatercontrollerfailuretomaximumflowdemand.Thefeedwatercontrollerisforcedtoitsupperlimitatthebeginningoftheevent.Withexcessfeedwaterflow,thewaterlevelrisestothehigh-levelreferencepointatwhichtimethefeedwaterpumpsandthemainturbine.aretrippedandascramisinitiated.Table15.B.3-2liststhesequence15.B.3-2 Ip NMP2ofevents.Figure.15.B.3-2showsthechangesinimportantvariablesduringthistransient.ThecomputermodeldescribedinReference15.B.8-2wasusedtosimulatethisevent.TheanalysishasbeenperformedwiththeplantconditionstabulatedinTable15.B.3-1,excepttheinitialvesselwaterlevelatlevelsetpointL4forconservatism.Byloweringtheinitialwaterlevel,morecoldfeedwaterwillbeinjectedbeforeLevel8isreachedresultinginhigherheatfluxes.Thesamevoidreactivitycoefficientusedforthepressurizationtransientis'appliedsinceamorenegativevalueconservativelyincreasestheseverityofthepowerincrease.Endofcycle(a11rodsout)scramcharacteristicsareassumed.Thesafety/reliefvalveactionisconservativelyassumedtooccurwithhigherthannominalsetpoints.Thetransientissimulatedbyprogramminganupper-limitfailureinthefeedwatersystemsuchthat145%ofratedfeedwaterflowoccursatthedesignpressureof1060psig.Sincethereactorisinitiallyoperatingatalowerpowerlevel,thefeedwaterspargerexperience'sapressurewhichismuchlowerthanthedesignpressure,hencethefeedwaterrunoutcapacityreaches167%ofinitialflow.ResultsThesimulatedfeedwatercontrollertransientisshowninFigure15.B.3-2.forthecaseof75%powerand60%coreflow.The'igh-waterlevelturbinetripandfeedwaterpumptripareinitiatedatapproximately6.4seconds.Scramoccurssimultaneouslyfromstopvalveclosure,andlimitstheneutronfluxpeakandfuelthermaltransientsothatnofueldamageoccurs.Table15.B.3-4givesasummaryofthetransientanalysisresults.ThecalculatedMCPRis1.20,whichiswellabovethesafetylimitMCPRof1.07sonofuelfailureduetoboilingtransitionispredicted.Thepeakvesselpressurepredictedis1134psigandiswellbelowtheASMElimitof1375psig.15.B.3-3
NMP215.8.3.1.2GeneratorLoadReectionWith8assFailureFastclosureoftheturbinecontrolvalves(TCV)isinitiatedwheneverelectricalgriddisturbancesoccurwhichresultinsignificantlossofelectricalloadonthegenerator.Theturbinecontrolvalvesarerequiredtocloseasrapidlyaspossibletopreventoverspeedoftheturbine-generatorrotor.Closureofthemainturbinecontrolvalveswillincreasesystempressure.MitigationofpressureincreaseduringthistransientisaccomplishedbythescramandRPT.Alossofgeneratorelectricalloadat75Kpowerand60'4flowundersinglerecirculationloopoperationproducesthesequenceofeventslistedinTable15.8.3-3.Figure15.8.3-3showsthechangesinimportantvariablesduringthistransient.ThecomputermodeldescribedinReference15.8.8-2wasusedtosimulatethisevent.TheanalysishasbeenperformedwiththeplantconditionstabulatedinTable15.8.3-1,exceptthattheturbinebypassfunctionssassumedtofail.ThesimulatedgeneratorloadrejectionwithbypassfailureisshowninFigure15.8.3-3.Table15.8.3-4summarizesthetransientanalysisresults.Thepeakneutronfluxreachesabout166Ãofratedandaveragesurfaceheatfluxpeaksat106.5/ofitsinitialvalue.Thepeakvesselpressurepredictedis1175psigandiswellbelowtheASMElimitof1375psig.ThecalculatedMCPRis1.27whichisconsiderablyabovethesafetylimitMCPRof1.07.15.8.3-4
NMP215.B.3.1.3SumnarandConclusionsThetransientpeakvalueresultsandtheCriticalPowerRatioresultsaresummarizedinTable15.B.3-4.Thistableindicatesthatforthetransienteventsanalyzedhere,theMCPRsforalltransientsareabovethesingle-loopoperationsafetylimitvalueof1.07.ItisconcludedtheoperatinglimitMCPRsestablishedfortwo-pumpoperationarealsoapplicabletosingle-loopoperationconditions.Forpressurization,Table15.B.3-4indicatesthepeakpressuresarebelowtheASMEcodevalueof1375psig.Hence,itisconcludedthepressurebarrierintegrityismaintainedundersingle-loopoperationconditions.15.B.3.2RODWITHDRAWALERRORTherodwithdrawalerroratratedpowerisgivenintheFSAR.Theseanalysesareperformedtodemonstrate,eveniftheoperatorignoresallinstrumentindicationsandthealarmwhichcouldoccurduringthecourseofthetransient,therodblocksystemwi11stoprodwithdrawalataminimumcriticalpowerratio(HCPR)whichishigherthanthefuelcladdingintegritysafetylimit.Modificationoftherodblockequation(below)assurestheHCPRsafetylimitisnotviolated.TheAveragePowerRangeMonitor(APRH)rodblocksystemprovidesadditionalalarmsandrodblockswhenpowerlevelsaregrosslyexceeded.ModificationoftheAPRHrodblockequation(below)isrequiredtomaintainthetwolooprodblockversuspowerrelationshipwheninoneloopoperation.One-pumpoperationresultsinbackflowthrough10ofthe20jetpumpswhiletheflowisbeingsuppliedintothelowerplenumfromthe10activejetpumps.Becauseofthebackflowthroughtheinactivejetpumps,thepresentrodblockequationwasconservativelymodifiedforuseduringone-pumpoperationbecausethedirectactive-loopflowmeasurementmaynotindicateactualflowaboveabout38%coreflowwithoutcorrection.15.B.3-5
NMP2AprocedurehasbeenestablishedforcorrectingtheAPRMrodblockequationtoaccountforthediscrepancybetweenactualflowandindicatedflowintheactiveloop.ThispreservestheoriginalrelationshipbetweenAPRMrodblockandactualeffectivedriveflowwhenoperatingwithasingleloop.Thetwo-pumprodblockequationis:RBmW+RB100m100Theone-pumpequationbecomes:RB=mW+RB1-m(100)-mN100wheredifferencebetween,two-loopandsingle-loopeffectivedriveflowatthesamecoreflow.Thisvalueisexpectedtobe5Xofrated(tobe"determinedbytheNiagaraMohawkPowerCorporation)RB=poweratrodblockin5flowreferenceslopedriveflowin5ofrated..RB100-toplevelrodblockat100%flow.Iftherodb1ocksetpo1nt(RB100)ischanged,theequationmustberecalculatedusingthenewvalue.TheAPRMscramtripsettingsareflowbiasedinthesamemannerastheAPRMrodblocksetting.Therefore,theAPRMscramtripsettingsaresubjecttothesameproceduralchangesastherodblocksettingsdiscussedabove.15.B.3-6 ]I NMP215.B.3.3OPERATINGMCPRLIMITForsingle-loopoperation,theoperatingMCPRlimitremainsunchangedfromthenormaltwo-loopoperationlimit.Althoughtheincreaseduncer-taintiesincoretotalflowandTIPreadingsresultedina0.01increaseinMCPRfuelcladdingintegritysafetylimitduringsingle-loopoperation(Section15.B.2),thelimitingtransientshavebeenanalyzedtoindicatethatthereismorethanenoughMCPRmarginduringsingle-loopoperationtocompensateforthisincreaseinsafetylimit.Forsingleloopoperationatoff-ratedconditions,thesteady-stateoperatingMCPRlimitisestablishedbytheKfcurve.Thisensuresthe99.9'Astatisticallimitrequirementisalwayssatisfiedforanypostulatedabnormaloperationaloccurrence.Sincethemaximumcoreflowrunoutduringsingle.loopoperationisonlyabout60%ofrated,thecurrentflowdependentKfcurvewhichisgeneratedbasedontheflowrunoutuptoratedcoreflowarealsoadequatetoprotecttheflowrunouteventsduringsingleloopoperation.15.B.3-7 / NMPZTABLE15.B.3-1INPUTPARAMETERSANDINITIALCONDITIONS1.ThermalPowerLevel,MWtAnalysisValue2.SteamFlow,lbperhrAnalysisValue3.CoreFlow,lbperhr4.FeedwaterFlowRate,lbperhrAnalysisValue5.FeedwaterTemperature,'F6.VesselDomePressure,psig7.CorePressure,psig8.TurbineBypassCapacity,5NBR9.CoreCoolantInletEnthalpy,Btuperlb10.TurbineInl'etPressure,psig11.FuelLattice12.CoreAverageGapConductance,Btu/sec-ft'-'F13.CoreBypassFlow,'414.RequiredMCPROperatingLimitOptionAOption815.MCPRSafetyLimit16.DopplerCoefficient4/'F17.VoidCoefficient4/5RatedVoids18.CoreAverageRatedVoidFraction,519.ScramReactivity,$6K249210.28x10i65.10x1010.28x1039498198725.515.1952PBxBR0.174411.84l.441.401.0743.5dihiICd(Rf15.B.8-2)forendofCycle1conditionbasedontheinputfromCRUNCHtape.15.B.3-8
NMP2TABLE15.B.3-1(Continued)INPUTPARAMETERSANDINITIALCONDITIONS20.ControlRodDriveSpeedPositionVersusTime21.JetPumpRatio,M22.Safety/ReliefValveCapacity,'ANBR8103Ãof1177psigManufacturerguantityInstalled23.ReliefFunctionDelay,seconds24.ReliefFunctionResponseTimeConstant,sec.Figure15.0-33.16>113.85IKKERS180.40.125.SetPointsforSafety/ReliefValvesSafetyFunction,psigReliefFunction,psig26.NumberofValveGroupingsSimulatedSafetyFunction,No.ReliefFunction,No.27.HighFluxTrip,5NBRAnalysisSetPoint(121x1.043)1177,1187,1197,1207,12171106,1116,"-1126,1136,114655126.228.HighPressureScramSetPoint,psig29.VesselLevelTrips,FeetAboveSeparatorSkirtBottomLevel8-(LB),FeetLevel4-(L4),FeetLevel3-(L3),FeetLevel2-(L2),Feet10716.1753.751.75-4.70815.B.3-9
NMP2TABLE15.B.3-1(Continued)INPUTPARAMETERSANDINITIALCONDITIONS30.APRMThermalTripSetPoint,%NBR8100%CoreFlow(117x1.043)31.RPTDelay,seconds32.TimeConstantofRecirculationPump'-Motor,seconds~AnalysisValue33.SetPressureofATWSRecirculationPumpTrip,psig34.TotalSteamLineVolume,ft'220.196.010804012~hiiiidfidbtlpwhere:2nJn~gt=inertiatimeconstant(sec)Jopumpmotorinertia(1b-ft)-~n,=ratedpumpspeed(rps)g=gravitationalconstant(ft/sec)T=pumpshafttorque(ft-lb)015.B.3-10 ~I NMP2TABLE15.B.3-2SEQUENCEOFEVENTSFORFEEDMATERCONTROLLERFAILURE,AXIU0NDiure.B.-Time-secEventInitiatesimulatedfailuretotheupperlimitonfeedwaterflow.6.46.46.46.56.6LBvessellevelsetpointtripsmainturbineandfeedwaterpumpsReactorscramtripactuatedfrommainturbinestopvalvepositionswitches.Recirculationpumptrip(RPT)actuatedbystopvalvepositionswitches.Hainturbinestopvalvesclosedandturbinebypassvalves'starttoopen.Recirculationpumpmotorcircuitbreakersopencausingdecreaseincoreflowtonaturalcirculation.9.510.015.2Group1reliefvalvesactuated.Group2reliefvalvesactuated.Allreliefvalves.areclosed.15.B.3-11
NHP2TABLE15.B.3-3SEUENCEOFEVENTSFORGENERATORLOADREJECTIONWPLURsureTime-sec(-)0.015(approx.)EventTurbine-generatordetectslossofelectricalload."Turbine-generatorloadrejectionsensingdevicestriptoinitiateturbinecontrolvalvefastclosure.0.07Turbinebypassvalvesfailtooperate.Fastcontrolvalveclosure(FCV)initiatesscramtripandrecirculationpumptrip(RPT).Turbinecontrolvalvesclosed.0.10Turbinebypassvalvesshouldstarttoopen-assumedtofai-10.19Recirculationpumpmotorcircuitbreakersopencausingdecreaseincoreflowtonaturalcirculation.2.12.22.42e62.8Group1reliefvalvesactuated.Group2reliefvalvesactuated.Group3reliefvalvesactuated.Group4reliefvalvesactuated.Group5reliefvalvesactuated.5.45.5FeedwaterpumpmotorsGroup5reliefvalvestrippedonL8highwaterlevel;starttoclose.8.2Allreliefvalvesareclosed.15.B.3-12
NMP2TABLE15.B.3-4SUMMARYOFTRANSIENTPEAKVALUEANDCPRRESULTSInitialPower/Flow(5Rated)PeakNeutronFlux(5NBR)PeakHeatFlux(XInitial)PeakDomePressure(psig)PeakVesselBottomPressure(psig)RequiredInitial'CPROperatingLimitatSLOConditionaCPRTransientMCPRSLMCPRatSLOMargintoSLMCPRLRBPF75/60165.7106.5116011751.440.17*1.271.070.20FMCF75/60157.3113.8112011341.440.24+1.201.070.1315.B.3-13
)230)220)210E12001190Hith8ypassFailure11801170MithNormalBypass1160115070809010011DinitialPowerLeve1(XNBR)NiaaaraMohawkPowerCoroorationPeakOomePressurevs.InitialPowerLevel,LRBPFatEOC15.B.3-14Figure15.B.3-1
150.1NEUTRGN2PEAKFUE3AVESUBFI-i1FEEDHATL5VESSELStLUXCENTERTEMPCEHEATFLUXFLCIHEWHFLGNc3100.UlCQ40IUlI-SO.CCUJCL0.0.5.10.15.TINEfSEC)20.-10NIAGARAHOHAHKPOlrJERCORPORATIONFeedwaterControllerFailure-HaximumOemand75KPower,60KFlowFigure15.B.3-2
150.1LEVEL(IN2HRSENSk3NRSENSIi<CuREINLr:5DRIVEFLH-REF-SEP-SKIRT0LEVEL(INCHES)0LEVEL(INCHES)TFLGH(PCT)H2(PCT)100.50.3I.I0.0.10.15.TIME(SEC)20.-10NIAGARANOH%KPOt<ERCORPORATIONFeedwaterControllerFailure-MaximumDemand75KPower,60KFlowFigure15'.3-2Corit'd.
200.1VESSLLP2STMLINE3TURBINEi)BYPASSS15RELIEFVf-6TURBSTELSRISE(PSI)PRESRISE(PSI)RESRISE(PSI)EAHFLGH(PCTlLVEFLGH(PCT)MFlCIH(PCT)100.0.-100.0.5.10.15.TIME(SLC)20.-10NIArARAMOHAWKPOHERCORPORATIONFeedwaterControllerFailure-HaximumOemand75K,Power,60KFlowFigure15+B.3-2Con't'd.
1VcjIDBEA2OGPPLEn3~CnnMnrr-4TGTFlLTIVITYEACT[V[TYCT[V[TY(MalY0.VlCDICD)I-CCLLjCC-2.0.10.TIMElSEC)20.<<10NIAGARAHOHANK,PO>fERCORPORATIONFeedwaterControllerFailure-MaximumDemand75KPower,6OXFlowFigure15.B.3-2hnt'd.
150.1NEUTRGNLUX2PERKFUFLCENTERTEMP3RVESUBFr-CEHERT.FLUXiiFEEOWRTLFLCIW5VESSELSERNFLCjHa100.LLJw.50.UJ0230.0.Q.6.TINE'SEC)8.NIAGARAHOHAHKPOMERCORPORATIONLoadRejectionWithBypassfailure75KPower,60KflowFigure15:.P.3-3
200.1LEVEL(IN2HRSENS('.3NRSENSI;4CURLINLSDRIVEFLH-REF-SEP-SKIRT0LEVEL(INCHES)0LEVEI(.INCHES)TFLGN(PCT)N1(PCT)100.UlU7I~C)0.-100.0.4.6.TIME(SEC)8.-10NlAfiARAMOHAWKPOllERCORPORATIONLoadRejectionMithBypassfailure75KPower,60KFlowFigure15,B.3-3Co'nt'd.
200.VESSELP2STMLINE3TURBINE4RELIEFVk5DIFFUSER6TURBSTEFSRISE(PSI)PRESBISE(PSI)RESRISE(PSI)LVEFLGH(PCT)FLCIH2(PCT)MFLC)N(PCT)0.-100.0.LJ.6.TIME(SEC)8.-IoNIAGARAMOHAWKPOWERCORPORATIONLoadRejectionwithBypassFailure75KPower,6OXFlowFigurel5.B.3-3Chant'.
1VCIIDBL.ATIVITY2DCIPPIEBfLBCTIVITYSf:llflHBEf:CTIVITY.4)TGTHLREf-CTIVITY0.-1.I-L3CCLLICC-2.0.2.-TIMF(SEC)-10NIAGARAHOHAMKPOWERCORPORATIONLoadRe)ectionwithBypassFailure75KPower,60KFlowFigure15,B.3-3Coht'd.
NHP215.B.4STABILITYANALYSIS15.B.4.1PhenomenaTheprimarycontributingfactorstothestabilityperformancewithonerecirculationloopnotinservicearethepower/flowratioandtherecirculationloopcharacteristics.Atforcedcirculationwithonlyonerecirculationloopinoperation,thereactorcorestabilityisinfluencedbytheinactivdrecirculationloop.AscoreflowincreasesinSLO,theinactivejetpumpforwardflowdecreasesbecausethedrivingheadacrosstheinactivejetpumpsdecreaseswithincreasingcoreflow.Thereducedflowintheinactiveloopreducestheresistancethattherecirculationloopsimposeonreactorcoreflowperturbationstherebyaddingadestabilizingeffect.Atthesametimetheincreasedcoreflowresultsinalowerpower/flowratiowhichisastabilizingeffect.Thesetwocounteringeffectsresultinslightlydecreasedstabilitymargin(higherdecayratio)in'itiallyascoreflowisincreased(fromminimum)inSLOandthenanincreaseinstabilitymargin(lowerdecayratio)ascore-flow.isincreasedfurtherandreverseflowintheinactiveloopisestablished.AscoreflowisincreasedfurtherduringSLOandsubstantialreverseflowisestablishedintheinactiveloopanincreaseinjetpumpflow,coreflowandneutronnoiseisobserved.Acrossflowisestablishedintheannulardowncomerregionnearthejetpumpsuction.entrancecausedbythereverseflowoftheinactiverecirculationloop.Thiscrossflowinteractswiththejetpumpsuctionflowoftheactiverecirculationloopandincreasesthejetpumpflownoise.Thiseffectincreasesthetotalcoreflownoisewhichtendstodrivetheneutronfluxnoise.15.B.4-1
NHP2rTodetermineiftheincreasednoiseisbeingcausedbyreducedstabilitymarginasSLOcoreflowwasincreased,anevaluationwasperformedwhichphenomenologicallyaccountsforsingleloopoperationeffectsonstability.assummarizedinReference15.B.8-4.Themodelpredictionswereinitiallycomparedwithtestdataandshowedverygoodagreementforbothtwoloopandsinglelooptestconditions.Anevaluationwasperformedtodeterminetheeffectofreverseflowonstabi1,ityduringSLO.Withincreasingreverseflow,SLOexhibitedslightlylowerdecayratiosthantwoloopoperation.However,atcoreflowconditionswithnoreverseflow,SLOwasslightlylessstable.ThisisconsistentwithobservedbehaviorinstabilitytestsatoperatingBWRs(Reference15.B.8-5).Inadditiontotheaboveanalyses,thecrossflowestablishedduringreverseflowconditionswassimulatedanalyticallyandshown'tocauseanincreaseintheindividualandtotaljetpumpflownoise,whichisconsistentwithtestdata(Reference15.B.8-4).Theresultsoftheseanalysesandtestsindicatethatthestabilitycharacteristicsarenotsign'tficantlydiff-erentfrom-two~copoperation.Atlow"coref'low,SLOmaybeslightly'less'tablethantwoloopoperationbutascoreflowisincreased.andreverseflowisestablishedthestabilityperformanceissimilar.Atevenhighercoreflowwithsubstantialreverseflowintheinactiverecirculationloop,theeffectofcrossflowontheflownoiseresultsinanincreaseinsystemnoise(jetpump,coreflowandneutronfluxnoise).15.B.4.2ComliancetoStabilitCriteriaConsistentwiththephilosophyappliedtotwoloopoperation,thestabilitycomplianceduringsingleloopoperationisdemonstratedonagenericbasis.StabilityacceptancecriteriahavebeenestablishedtodemonstratecompliancewiththerequirementssetforthinlOCFR50,AppendixA,GeneralDesignCriterion(GDC)12(Reference15.B.8-6).GenericanalyseswhichcoverthosefuelscontainedintheGeneralElectricStandardApplicationforReloadFuel(Reference15.B.8-7throughAmendment10)havebeenperformed.Theanalysesdemonstratethatintheeventlimit,15sB42
NMP2cycleneutronfluxoscillationsoccurwithintheboundsofsafetysystemintervention,specifiedacceptablefueldesignlimitsarenotexceeded.Sincethereactorcoreisassumedtobeinanoscillatorymode,thequestionofstabilitymarginduringSLOisnotrelevantfromasafetystandpoint(i.e.,theanalysisalreadyassumesnostabilitymargin).Thefuelperformanceduringlimitcycleoscillationsischaracteristicallydependentonfueldesignandcertainfixedsystemfeatures(highneutronfluxscramsetpoint,channelinletorificediameter,etc.).ThereforetheacceptabilityofGEfueldesignsindependent'ofplantandcycleparametershasbeenestablished.OnlythoseparametersuniquetoSLOwhichaffectfuelperformanceneedtobeevaluated.Themajorconsidera-tionofSLOistheincreasedMinimumCriticalPowerRatio(MCPR)safetylimitcausedbyincreaseduncertaintiesinsystemparametersduringSLO.However,theincreaseinMCPRsafetylimit(0.01)iswellwithinthemarginofthelimitcycleanalyses(Reference15.B.8-6)andthereforeitisdemonstratedthatstabilitycompliancecriteriaaresatisfiedduringsingleloopoperation.Operationally,theeffectsofhigherflownoiseandneutronfluxnoiseobservedathighSLOcoreflow,are'evaluated'todetermineifacceptablevesselinternalvibrationlevelsaremetandtodeterminetheeffectsonfuelandchannelfatigue,andarenotconsideredinthecompliancetostabilitycriteria.ServiceInformationLetter-380,Revision1(Reference15.B.8-8)hasbeen'evelopedtoinformplantoperatorshowtorecognizeandsuppressunanticipatedoscillationswhenencounteredduringplantoperation.Asa'esultoftheaboveanalysisandoperatorrecomnendations,theNRCstaffhasapprovedthegenericstabilityanalysisforapplicationtosingleloopoperation(Reference15.B.8-9)providedthattherecommenda-tionsofSIL-380havebeenincorporatedintothePlantTechnicalSpecifica-tions.15.B.4-3
NMP215.B.5LOSS-OF-COOLANTACCIDENTANALYSISIftworecirculationloopsareoperatingandapipebreakoccursinoneofthetworecirlationloops,thepumpintheunbrokenloopisassumedtoimmediatelytripandbegintocoastdown.Thedecayingcoreflowduetothepumpcoastdownresultsinveryeffectiveheattransfer(nucleateboiling)duringtheinitialphaseoftheblowdown.Typically,nucleateboilingwillbesustainedduringthefirst5to9secondsaftertheaccident,forthedesignbasisaccident(DBA).Ifonlyonerecirculationloopisoperating,andthebreakoccursintheoperatingloop,continuedcoreflowisprovidedonlybynaturalcirculationbecausethevesselisblowingdowntothereactorcontainmentthroughbothsectionsofthebrokenloop.Thecoreflowdecreasesmorerapidlythaninthetwo-loopoperatingcase,andthedeparturefromnucleateboilingforthehighpowernodemightoccur1or2secondsafterthepostulatedaccident,resultinginmoreseverecladdingheatupfortheone-loopoperatingcase.Inadditiontochangingtheb1owndownheattransfercharaeteristies,losingrecirculationpumpcoastdownflowcanalsoaffectthesysteminventoryandrefloodingphenomena.Ofparticularinterestarethechangesinthehigh-powernodeuncoveryandrefloodingtimes,thesystempressureandthetimeofratedcoresprayfordifferentbreaksizes.One-loopoperationresultsinsmallchangesinthehigh-powernodeuncoverytimesandtimesofratedspray.Theeffectoftherefloodingtimesforvariousbreaksizesisalsogenerallysmall.AnanalysisofsinglerecirculationloopoperationusingthemodelsandassumptionsdocumentedinReference15.B.8-10wasperformedforNMP2.Usingthismethod,SAFE/REFLOODcomputercoderunsweremadeforafullspectrumoflargebreaksizesforonlytherecirculationsuctionlinebreaks(mostlimitingforNMP2).Becausetherefloodminusuncoverytimeforthesingle-loopanalysisis,similartothetwo-loopanalysis,themaximumplanarlinearheatgenerationrate(MAPLHGR)curvesweremodified15.B.5-1 "Vt~'IPLj)ly NMPZbyderivedreductionfactorsforuseduringonerecirculationpumpoperation.15.B.5.1BREAKSPECTRUMANALYSISSAFE/REFLOODcalculationswereperformedusingassumptionsgiveninSectionII.A.7.3.1ofReference15.8.8-10.Hotnodeuncoveredtime(timebetweenuncoveryandreflood)forsingle-loopoperationiscomparedtothatfortwo-loopoperationinFigure15.B.5-1.Thetotaluncoveredtimefortwo-loopoperationis127secondsforthe100%DBAsuctionbreak.Thisisthemostlimitingbreakfortwo-loopoperation.Forsingle-loopoperation,thetotaluncoveredtimeis127secondsandforthe100%DBAsuctionbreak.Thisisthemostlimitingbreakforsingle-loopoperation.15.8.5.2SINGLE-LOOPMAPLHGRDETERMINATIONThesmalldifferencesinuncoveredtimeandrefloodtimeforthelimitingbreaksizewouldresultinasmallchangeinthecalculatedpeakcladdingtemperature.Therefore,asnotedasReference15.B.8-10,theoneandtwo-loopSAFE/REFLOODresultscanbeconsideredsimilarandthegenericalternateproceduredescribedinSectionII.A.7.4.ofthisreferencewasusedtocalculatetheMAPLHGRreductionfactorsforsingle-loopoperation.Themostlimitingsingle-loopoperationMAPLHGRreductionfactor(i.e.,yieldingthelowestMAPLHGR)forGE68x8retrofit-fuelis0.81.One-loopoperationMAPLHGRvaluesarederivedbymultiplyingthecurrenttwo-loopMAPLHGRvaluesbythereductionfactor(0.81).AsdiscussedinReference15.B.8-10,singlerecirculationloopMAPLHGRvaluesareconservativewhencalculatedinthismanner.15.B.5-2 P NMP215.B.5.3SMALLBREAKPEAKCLADDINGTEMPERATURESectionII.A.7.4.4.2ofReference15.B.8-10discussesthelowsensitivityofthecalculatedpeakcladdingtemperature(PCT)totheassumptionsusedintheone-pumpoperationanalysisand,thedurationofnucleateboiling.Asthisslightincrease(~50'F)inPCT~isoverwhelminglyoffsetbythedecreasedMAPLHGR(equivalentto300'Fto500'FPCT)forone-pumpoperation,thecalculatedPCTvaluesforsmallbreakswillbewellbelowthe1522'Fsma11breakPCTvaluepreviouslyreportedforNMP2,andsignificantlybelowthe2200'FlOCFR50.46claddingtemperaturelimit.15.B.5-3 Lee+~wr'\+~'~~\~'eCcIJ/.IElII1III~~~eq~Mfa.jI\"0(iAqspaI CllnLUCC4J200180160T1ioLOOP-------SINGLELOOP4JnCD140120I~~I~ICDI100GO6040201.0FTBREAKa~IIlI~II~II~I0010203040506070GO90100BREAKAREA(>>OFODA}'anaraMohawkowerCoro.UncoveredTimevs.BreakArea-SuctionBreak,LPCSDieselGeneratorFailure15.B.5-4Figure15.B.5-l 'vC1"4~'p~+4t,w\PWHrptfggI4Illa'34Wl)~PE75)fgY~tVt~8figIOsinfl<I0""!',fc"~9"2BVh~CfhW'CI'<pic,~E'"<siJ'Pi~~~el~ NHP215.B.6.CONTAINMENTANALYSISAsingle-loopoperationcontainmentanalysiswasperformedforNMPZ.Thepeakwetwellpressure,peakdrywellpressure,chuggingloads,condensa-tioqoscillationandpoolswellcontainmentresponsewereevaluatedovertheentiresingle-loopoperationpower/flowregion.Theanalysisshowsthatthepeakdrywellandwetwellpressureduringsingleloopoperationis33.1psigand27.2psigrespectivelyandoccurunderrecirculationlinebreakatthemaximumvesselsubcoolingconditioninthepower/flowmap.Thecorrespondingdifferentialpeakdrywell-to-wetwellpressureis17.2psid.Abasecase,correspondingtotheFSARconditionof102%power/100%coreflow,wasalsoanalyzedforcomparison.TheresultsarepresentedinTable15.B.6-1.Asnotedfromthetable,thepeakdrywellandwetwellpressureandthepeakdrywell-to-wetwellpressurefortheSLOareallboundedbythoseofthebasecaseandaresubstantiallybelowthedesignlimits.ThepressureandtemperatureresponsesfortheSLOareshowninFigure15.B.6-1and15.B.6-2.ThecontainmentdynamicloadsevaluationwasperformedattheworstconditionfortheSLOandcomparedwiththoseforthebasecase.Poolswell,condensationoscillation,andchuggingloadswereassessedfortheinitialphaseofapostulatedrecirculationlinebreak.Additionally,SafetyReliefValveactuationloadswereconsidered.ItisconcludedfromtheevaluationresultsthatthecurrentFSARcontainmentloadingsboundtheworstSLOloadings.Theboundingeventforthedrywelltemperatureresponseisamainsteamlinebreak.UnderSLO,theincreasedvesselsubcoolinghasnoimpactonthesteambreakflow.However,thelowervesselpressureresultingfromSLOreducesthesteambreakflow.ItisconcludedthatthepeakdrywelltemperatureforSLOisboundedbythatoftheFSAR.15.B.6-1 Ves.eav+ez~vmai""~qadi.s[i~'.es'."-to'-'i7Qf'01VR~9'~'(4fBV09~9"f>'"'~".".A9vd:."-':.rur~.=.-i.DABI!ICf.".29f)GLi~~'~'ee-ur";sam>l'o:qr~i;-;=.":",'.~3III)GM' NMP2Finally,the-peaksuppressionpoolandwetwellairspacetemperaturesaregovernedbythelong-termreleaseofdecayheatandenergyremovalbytheRHRservicewater.SincethepowerlevelsfortheSLOareboundedbythatoftheFSAR,itisthereforeconcludedthatthepeaksuppressionpooltemperatureisboundedbythepeaksuppressionpooltemperaturegivenintheFSAR.15.B.6-2 rr~iill1(1'pq<936Pi4"t+W'xaewc",<<SGfg"s'rr;.rJno)'aeGJ/\><elf"is~o.'"Gl>5h5p,1C~~~~~,rpf~g.i4C~ii.B.' NHP2Table15.B.6-1ComparisonofContainmentPeakPressuresBaseCase(102%Power/100%CoreFlow)SLO(54%Power/35KCoreFlow)DesignLimitsPeakDrywell.Pressure,PSIG34.6233.0745PeakDrywel1-To-WetwellDeltaPPSID17.8117.1725PeakWetwell.Pressure,PSIG28.6327.1815.B.6-3 COULOUVLIOBHIVVVHVNOIIVHK40I'IEI$i'c".4bOIIEI"3NI':OUEEI'Oi-;DUAliEIIVHDHElr1EfTbUEP/flUEUEZbO!IZLZ-UEl;LUCfllVlOHIIIIEJUL"K'hC~j2'0e-jLIefIUEI)0I"lgTl~l2Utt~~lag!QlIl'>lgj0~~S~AII 60.ORYWFLLPRESSWEIWELLPRESSREPSlAREPSIA<IO.20.0.0.50.100..150.200.TINE5ECCjNDSNIAGARAMOHAWKPOWERCORPORATIONDRYllELLANDMETHELLPRESSURERESPONSES-.RECIRCULATIONLINEBREAK.55KPOWER,35KCOREFLOWFIGURE15.B.6-1 CUlibVlÃ3.IONHl'adVHV831)VIIKbupEUAWWA)y~~~~WgPg))U)qEIt'i'4COIfEtlUNOtiAiiEITVWDi<Eltlf:I-IlEiIbEI!ttlAUEliEdbOHPE2"UFCJUCAIVll0t1<fHEBUEVK'2'0'e-'jtiVAVEttHLe.iJI2l).')00'))0t,JP 350.'RTNELLTEHPEATURE,NLTHELLTEMPERTUREUlCQCllICJl250.(AQJUJCCUJC3LLj0:t50.I-CT:Ct:LLjCLUJI-50.0.50.TOO.150.200.TIMESECGNDS"II!"iARAHOHyÃKPOwERCORPORA~IOND~Y!!ELLANDHETHELLTE.'1PERATURERESPONSES<<RECIRCULATIONLINEBREAK,55%~WER,35KCOREFLOWFIGURE15.B,6-2 )n('IttATIT>S~32f'Ior'M~IT&anss:b&noifsulsY3rsI~onbns(O>2)no.;.-S~eqoqoorefpnin&weed&ones&;T..msŽ>2fuofliHineians".Tbe.-sq,io.'.fI.onion9s(OJ.);;o.'I2&fl."eon'2.anor..'bnooaoos&a'.-'.inic-sf'."-:so=,b&2'oi+ibnoobe+so&Il."nsr..=2&'rno-'"-ibnoo:.TlO'Toi&"f&nfblls9'T&v&2.2&fI&2!Toq!&PA&r2nsTPeiU.2&zgnsO.OJ&lipIITGf'ggt~+6bettor-'f'n9'Tek~IT&Y&~VTA'lsVr~hlbets('sfnr&Iew.r'tlnsdt9",&v&222&I'.b'uow2f>>9>.8'IG~~9:.'Isr,f~o,zeqfs~ins,"',=-need&vs'eryfsfs'+n~'-2"..s~+&~i;o~,".-'u.",fsz;nsno=..2&asdnp!'&bf&I.T&nog:.I:9:'rue<:&ao~",behzifls29wof?f&'"ItsfsflE.'..'6G;&Ub'3"cacobns&aron(NRRAjaotinol'IepnsR~&wolepsw&YA&l.-aical'~nsnA.bezs&-."niy.f.floi'fz&.~s...i;n".uaa&~qffSonbfuorlanoifsudou"tNRRA96;asl..:&~,ilI;~&debc.'uefs,iver.Diib&is,'qe~o;&nPonsbefs-.To"c.'=Wo=-bu::if-zrznoo&do~As&f,'P.Is&qiZq,Cbe&ox&Sonbfuofi2For.2&zsdnQi29bvfQN&zasbrlsDG'linoi+swd'rVfsc~&..".Paerlpi.fl&ri..QJ2<7ai'.~sdrwonci~ssdivIb&gg>>tyIO'Ir'yoIgve,gf.snT=-,g-f='.2&Y:Ids=q&oos2.rJ'2;G." NMP215.B.7MISCELLANEOUSIMPACTEVALUATION15.B.7.1AnticiatedTransientWithoutScram(ATWS)ImactEvaluationTheprincipaldifferencebetweensingleloopoperation(SLO)"andnormaltwoloopoperation(TLO)affectingAnticipatedTransientWithoutScram(ATWS)performanceisthatofinitialreactorconditions.SincetheSLOinitialpowerflowconditionislessthantheratedconditionusedforTLOATWSanalysis,thetransientresponseislesssevereandthereforeboundedbytheTLOanalyses.Itisconcludedthat,ifanATWSeventwereinitiatedatNMP2.fromtheSLOconditions,theresultswouldbelessseverethanifitwereinitiatedfromratedconditions.15.B.7.2FuelMechanicalPerformanceThethermaland'echanicaldutyforthetransientsanalyzedhavebeenevaluatedandfoundtobeboundedbythefueldesignbases.,ItisobservedthatduetothesubstantialreverseflowestablishedduringSLOboththeAveragePowerRangeMonitor(APRM)noiseandcoreplatedifferentialpressurenoiseareslightlyincreased.AnanalysishasbeencarriedouttodeterminethattheAPRM'luctuationshouldnotexceedafluxamplitudeof+15%ofratedandthecoreplatedifferentialpressurefluctuationshouldnotexceed3.2psipeaktopeaktobeconsis-tentwiththefuelrodandassemblydesignbases.15.B.7.3VesselInternalVibrationArecirculationpumpdriveflowlimitisimposedforSLO.ThehighestdriveflowthatmeetsacceptablevesselinternalvibrationcriteriaisthedriveflowlimitforSLO.15.'B.7-1 .'f:evef.nor+swdrvaofose'Tbefoeqxeerid"fclebsm.needenf.eb<OPfneblllq2rfrsnem2292s96~02+fuael30.qoofefynia,basnordsweqoqoof-.."",beonsf'sd'pnr~ub",woiT;-~;o+"f'supezf.norisweqobeonsfsdlqmuq-ow.~oR.wo'fmum.~ano'sibnco,on-fs1eqo'."ro;use'1.ismion'..'swo:.i91oo1ettNr;..r~'rissdowof>:;;seedaino'Js~e"..oqmuq-efg.".iz,~woi-"-mumrxsm'wo>>..beer.p'ez,.s~aodf.'supwoi,evr'ebqm;ewudsteqme.'e~swac.'osezbeds~'so~,,no;zsseqobeonsfs(zo'-,wol'"'yl~bqmuq:no,'Psfuowroe1efdswoffs.mumrxsm9PF.mqp3i.9d.On-ouf>nr";~~enoqmc;.;sbew;"".pnsfq3isAOT~n:areve'Ord'S'for%VSACfnOrSS19)Qqoef"efpnlrzQnf1uu=.znss~q'gfofoaaf28423489"~.t3:.sA;,el)T'.z~rmri-,sidrvfs;-~+nt~o:escaI.;~2)ewerlv,SnsqeqYPozo~qszr.3nsfg9rsAQT,9:f~moAs~sb.&dz,bse.-anf.ms-fpo-..ed.'so't,.s.sb,~nsfq.S."'sxoTer"ncbez'-8...~nemazez:-s'TOTalive10MOO-fS'1~9'r0DS91en'"',e>efpor+s>c,~Y.qooi-efonrapni~ub2.'",.'ons.g=os"60"wedcbe.evoCshenr.ebzswofRmumr:..,be~'ru-"=~en're,'-Mfirepnr.29.ac.,s:2""RRNen."~Je~nemu'f02n~9ls2qmug7~~I~el NMP2AnassessmenthasbeenmadefortheexpectedreactorvibrationlevelduringSLOforNMP2.Beforeprovidingtheresultsoftheassessment,itis'rudenttodefine.theterm"maximumflow'-'uringbalanced2-loopoperationandsingleloopoperation.Maximumflowfortwo-pumpbalancedoperationisequaltoratedvolumetriccoreflowat'normalreactoroperatingconditions.Maximumflowforsingle-pumpoperationisthatflowobtainedwiththerecirculationpumpdriveflowequaltothatrequiredformaximumflowduringtwo-pumpbalancedoperation.Forratedreactorwatertemperatureandpressure,themaximumallowablerecirculationpumpdriveflowforNMP2isabout41,000gpm.StartuptestsattheTokai2plantshowedallcomponents,includingthein-coreguidetubeduringsingle-loopoperation,tohavevibrationlevelswithinacceptance.limits.TheTokai'istheBMR5/251prototypeplant.Since-NMP~s-not-a~rototyp~lan~trer'e'"isnoreactorinternalvibra-tionmonitoringprogram.Instead,thedatafromtheTokai2plantisusedforNMP2SLOassessment.BasedontheTokai2plantdata,it.canbeinferredthatthevibrationlevelsofthereactorinternalcomponentsforNMPZwouldbeexpectedtobewithin'cceptancelimitsduringsingle-loop'operationwithmaximumflowasdefinedabove.Forthejetpumps,theNMP2startuptestingwi11yieldtherequiredconfirmationasNMP2jetpumpsareinstrumented.15.B..7-2 2331'sG(BA.39)".2';2sezi2yfsnAfhm~enT9'8,oi.~.oef3,i:-,A-,CcHOf-003H,"norlsv'rfqqA',no.r290'ns.norfsf,$0f~os'bon,Pnerans~Te~o".'nor'anemrQ-enOerf::'tonor.;.o'=,.'.8,;ofsado+00;,~@f03-'003H,,,"zw"losel;~e)s'4o.-sUJ5~32;nyt2psgT~ps/'q'-02b~,"zeN'>".pien/'",boo'tnrJ.8080-OQ3H,',,"~ofoaeP,-~ebs~'rrf",09'i:e.:ief3;fs~ezeB,en.-~o'.i."jmdv2"',(GRV)znoilT.~,.30>>'.3")nf~e='tHR.3,>>'nrnaeon03'Rl'.moat;me.'.-',no.'.PvAvierfrasS2,ogear>.CBo",".:dr."qeP',nords~eqQqocVi."'frCS~Z8.efayDeeinSY:nOr"e~'",rrr.e'H.0.0bnSV"Of"zoefH,s..er!98."P0099P29TqJr"":pAURr'Jr'assi)o~.(norswno~ni;v~".z:'~a-.~9,24~2'--9G".l~)8C.":...'nrrro8orwfoef3fsweneBerIPtoevaerfqmoJ",boot."sb's.'"Tetr(3pnrzne.f3~'"~ds;:cdpnoi?5":ed'I'~ass%-'raqoqi,j-"-.-".7SR-333Vi)>BBi'e"'o.'.,(nsqmo0ore:ef'3.(noises"wc't;,'"feUYosofeilso=.nor:soffcaAb~sbn.2or",:oem'".'(8-'A-8-ff04~'2-3G3NiEBeffr".qA,ynsqm03o'r;Ooef3of'rfoef3's"reneB,"v."rfrds.2orfusrbyHfsmfefiT910".OSi-se"+eJnor.Sm'To'neo."Y".92)>F-"i,Of"oscar'.e~ NMP215.B.8REFERENCES15.8.8-1"GeneralElectricBWRThermal.Analysis-Basis-(GETAB)",.Data;Correlation,-and.DesignApplication",,:NEDO-10958-'A.January1977.-15.B.8-2"gualificationoftheOne-DimensionalCoreTransientModelforBoilingWaterReactors",NEDO-24154;October1978.-"115.8.8-3R.B.Linford,"AnalyticalMethodsofPlantTransientsEvalua-tionfortheGeneralElectricBoilingWaterReactor",NED0-10802,April1973.15.B.8-4Letter,H.C.Pfefferlen(GE)toC.0.Thomas(NRC),"SubmittalofResponsetoStabilityActionItemfromNRCConcerningSingle-LoopOperation,"September1983.15.B.8-5S.F.ChenandR.0.Niemi,"VermontYankeeCycle8StabilityandRecirculationPumpTripTestReport",GeneralElectricCompany,August1982(NEDE-25445,ProprietaryInformation).15.B.8-6G.A.Watford,"ComplianceoftheGeneralElectricBoilingWaterReactorFuelDesignstoStabilityLicensingCriteria",GeneralElectricCompany,October1984(NEDE-22277-P-l,Propri-etaryInformation).15.B.8-7"GeneralElectricStandardApplicationforReloadFuel",GeneralElectricCompany,April1983(NEDE-24011-P-A-6).15.B.8-8"BWRCoreThermalHydraulicStabi1ity",GeneralElectricCompany,February10,1984(ServiceInformationLetter-380Revision1).15.B.8-1. qMoA",'(~B)nef'fs~"9i.0eHOJ(3RYI)zsiTioflj~0,3,ffv>S-303H,fzoqeRfsoraoT.pnrzneorJTognrone~e;eHaoTod3nembnemAgi'rfrdsf2o'rfuswbyHfsmaer(7,8PnembnemA."Ser,OSrt~qA",".<nsfooD-vo-z"oJcol-:.eboNfsv.'P.,snA~nsqmo3v,'ieoef3i;.9.oHfnembnemA)tx.bneqqA0273."Qf~Pi~ernsbaovoAn.'r,inoir"-veR8-BBPOS-093Vi,'~rv~e2-~)-suC.ao"Jnor'+sfUvaro3F0~$.i~h7 NMP215.B.8REFERENCES(Cont'd)15.B.8-9Letter,C.0.Thomas(NRC)toH.C.Pfefferlen(GE),"Accep-tanceforReferencingofLicensingTopicalReportNEDE-24011,Rev.6,Amendment8,ThermalHydraulicStabilityAmendmenttoGESTARII,"April24,1985.15.B.8-10"GeneralElectricCompanyAnalyticalModelforLoss-of-CoolantAnalysisinAccordancewith10CFR50AppendixK'mendmentNo.2-OneRecirculationLoopOut-of-Service",NEDO-20566-2Revision1,July1978.15.B.8-2 hErtrCw-lttl'.Jpgp@g."e.')9:~w"'g()~-",<<ajar@.~gpssQ)3-:;","'pig('~-":,>8AAp<"yN459-.-63NBRtU7'.Ci F.ve444',p'I44I'Irp4II'P4IIFFF4Fvn4FFI4ATTACHHEN7G:F=I,FIIIIEND>OF'GYCL'E".RECIRCULATION"PUfH'RIPINOPERABLEAND4'URBINE'YPASS.INOPERABL'EANALYSISrI4'I8NI',FII'.I4>4F4 efds~eqonIzzsqy8entc'su:bnsefds~eqonITRR-DO."-~oinotpot.zepnsri3notfsvtltveqc-,.f.ow".,y~tlidsftsvsn-icbnsyfif'dixel3antis".eqovc-,~oizensriv.~eq2.rivef~oqq.lzof.beyfsnsneedevsdzci"..Aot:rube'eve,efdsne.-lsm"lerlfer.'i".Sr.'f29".tUpe'lnotfs~eaOloTnot0tbno3pnt:tmtJinotisfuv~taevel~sr-fo-bneer.".ezsvnt4'Ornsrldzzefo."beaut.zzelyflzu,'".zizv.lsnspnt.-aoqquzertinl.efasseqontzemoj~r'bo."fneizns~"erlfd..rwoentrr.sxee.~ewzezF.gnl-.'mitow,no..'.lR"JO)otssswewoqrr.i."t;:=i@ifprittysweaopntbnuoderl";enr:elds-reqontTgj.-393rfew9ru[is-,le:olgnog'.:efds~~qont2'.RH-'303ne.."zzsqg~dsuorstwnotice)eabsofsc.~'i'~Y<A.Id6'YB~QP.:i:"FiAtericertfPsfll"9"'Upe'.riot'sr'10ro,nordibro3onffte',zero~edzzsaydenrd~uf9;.'zs.'.'2Sn~dfzzel'fbe..,noifrube".'"ylioq>'zef'p~~~<',itll6'z!<'"!'~;Ont.O"qyz,98.9l:JQpn;cl"oi.erl:Ien'2ppgc~)I)g(i~l;>wef!llAS'x)9<,9~)~)Hi)292S<ieiuseaor:<2::q;:;en,'V'lI.;.~,)9'lglts3zefiowgrlriaaefdsseqon'zsqvd9>>'dwu'at>>wefserlvefswbe-",'insTRialeez~z~tf2."lst~""sr!3>we'DU'>r-.+3%0'iTben'":.ivarlet?Asr$A7&~~~.09S'T',<<I',!"Cl,';-":.":DZ.2V19330P':'~rtibebuDf.'.'lsAol'2f~9I.xeJ.3q2.do~iDes&f9lbnh;:(~fggRlwJO~sr'ied'i'~y'dZZWV:i',".<,"'.'.""A~r-"b"uf~e>zen",59'rtuper~on2tIo~2i.."-h'.6.Ct.=-.<r";.en:n"':.efnefilL'~.,g"9I.'."Ao2~lr.t,&.'6)qe~.29gugr+be~s3izzsc'rfbfls.S.Czeqsqnce~urt~,t'e-.stoozzs.z.t'bnsF.":E,G.".J'o-.norzrv"wetv~weive~bns>o~".q,.so=6.7;:bns5:':C2'0"Jioibebrvowc.zrloifspftoeq2fs.h-,S-lkK"-,zeosq,zezsB~o,bebi
Subject:
JustificationforEOC-RPTInoperableandTurbineBypassInoperableTechnicalSpecificationChangesInordertoimprove-'peratingflexibilityandplantavailability,twotransientscenario'shavebeenanalyzedtosupportTech.Spec.changesforminimizingpowerlevelreduction.l.EOC-RPTInoerableThecurrentLimitingConditionforOperationrequiresthatthethermalpowerbereducedtolessthan30Kincasetheend-of-cyclerecirculationpumptripbecomesinoperable.Inthesupportinganalysistojusitfylesspowerreduction,twolimitingcaseswereexaminedwiththetransientcodeODYNtodefinetheboundingoperatinglimitcriticalpowerratio(OLCPR).a.Feedwater'ontrollerfailurewith'EOC-RPTinoperableb.GeneratorloadrejectionwithoutbypasswhenEOC-RPTisinoperable2.TurbineBassInoerableThecurrentLimitingConditionforOperationrequiresthatthethermalpowerbereducedtolessthan25%incasetheturbinebypassbecomesinoperable.Inthesupportinganalysistojustifylesspowerreduction,twolimitingcaseswereexaminedwithODYNtodefinetheboundingOLCPR.a.Feedwatercontrollerfailurewithturbinebypassinoperableb.LossoffeedwaterheaterwithturbinebypassinoperableUsinginputdeterminedfromEOC-1nuclearcharacteristics(seeFSARTable15.0-3),theboundingOLCPRvs.scramspeedisgeneratedforeachtransientscenario.ThisOLCPRplotandrelatedTech.Spec;textrevisionareincludedintheattachment.PleasenotethatthesepostulatedscenariosaretransienteventsbeyondthedesignbasisdocumentedintheFSAR.Therefore,FSARrevisionisnotrequired.TheattachedLCO3.2.3andtwoassociatedfiguresreplace,initsentirety,theproofandreviewrevisionofLCO3.2.3anditsassociatedfigureonpages3/42-6and2-7.ChangesarealsoprovidedforLCO's-3.3.4.2and3.7.9forproofandreviewversionofTechnicalSpecifications.AchangeisprovidedforBases'agesB3/42-4: N<<If"ii<<$Vg'~I/O,<,illI)lf>>I3Vy~<<1+I<<1Nlg~<<JnI',Ivg,V)II(3!IIIlirtg(li~llI'I.II)33l'g)=~I('ll,g1<"f~,")pt'I"NfQ<<'i')"<<<<'ii'CI)'i(>>ilitNi.,1VA&Q<<>>'I)I'll(~P"'i'ININ,I,<<,/IIF>>,IQQ'(;NV',I+NVN4"V'I<<,Ii>>,IK.,I>>$93//gfi,Vni,I'}}