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{{#Wiki_filter:ATTACHMENT2TOAEP'NRC'1213AEXISTINGTECHNICALSPECIFICATIONPAGESMARKEDTOREFLECTPROPOSEDCHANGES9510310312951020PDRADOCK05000315PPDR 0
{{#Wiki_filter:ATTACHMENT 2TOAEP'NRC'1213A EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES9510310312 951020PDRADOCK05000315PPDR 0
34.7SYSTEMS347.TGRBTNECYCLESAFETYVALVESNGCONDXTONFOROPERAON3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.ancC.v~lu~is>a~a.4With4reactorcoolantloopsandassociatesteamgeneratorsin'perationpandwithoneormoremainsteam1necodesafetyvalvesinop'arable,operation,naproceedprovidethatwithin4hours,eithertheinoperablerestoredtoOPlZstatus'rthePowerRangeNeutronFluxHighSetpointtripisreduced.perTable3.7-1;otherwise,beinae:-4e~HOTSTANDBYwithinthenext6hoursand.comply~~a@So%56cAAthAb.b.(Wi3reactorcoolantloopsandassociatedsteamgeneratorsinperation~andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operation4MGMMnayproceedprovidedgthatnirhin4honte,eitherthein'operable<~"+i~C~~s.restoredtoOPERABLEstatus~orthereactortripbreakersareopened;otherwise,bein~SHUTDOWNwithintheNext30hours.Hol-TheprovisionsofSpecification3.0.4arenotapp1.$cable.SURVEXLLANCEREUIREMENTS4.7.1.1.EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLE'naccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue~1Xwheneverfoundoutsidethe+1Ktolerance.qg~po,s-,~SogSq~Q~Otee~i~Wk>M.3~COOKNUCLEARPLANT-UNlT13/47-1~HENTNO.k@0,464  
34.7SYSTEMS347.TGRBTNECYCLESAFETYVALVESNGCONDXTONFOROPERAON3.7.1.1Allmainsteamlinecodesafetyvalvesassociated witheachsteamgenerator shallbeOPERABLE.
'TABLE3.7-lHAXlHUHALLOWABLEPOllERRAHGENEUTRONFLUXlllGIISETPOIHTMITllIHOPERAOLESTEAHEPIE~I'IKTEEEEPEPEIEWIE~HaxinemtiumberofInoperableSafetyValvesonAnOeratinSteamGeneratorHaximumAllowablePowerRangetleutronFluxilighSetpointPercentofRATEDTHERHALPOWER4I~~  
ancC.v~lu~is>a~a.4With4reactorcoolantloopsandassociate steamgenerators in'perationpand withoneormoremainsteam1necodesafetyvalvesinop'arable, operation
/41VV<TheOPERABILITYofthemainsteamlinecodesafetyvalvesensureschatthesecondarysystempressurewillbelimitedcowt.thini.csdesignpressureof1085psigduringthemostsevereanticipatedsystemopera-tionalcransient.Themaximumrelievt.ngcapacityisassociatedwichacurbinetripfrom100%RATEDTHER.fALPOMERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosceambypasscothecondenser).Thespecifiedvalveli.ftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIofcheASMEBoi.lerandPressureCode,1971Edition.Thetotalrelievingcapacicyforallvalvesona11ofthe'steamli.nesis17,153,800lbs/hrwhichisapproximately121percentofthetocalsecondarysteamflowof14,120,000lbs/hrac100%RATEDTHERMALPOMER.Aminimumof2OPERABLEsafecyvalvesperoperabLesteamgeneratorensuresthatsufficientrelievt.ngcapacityi.savailableforcheallo~ableTHER.'iALPOWERrestri.ctioninTable3.7-1.STARTUPand/orPOMEROPERATIONinoperablewithinthelimitationsofofchereductioninsecondarysystembythereducedreactortripseccingschannels.Thereactortripsetpoincfollowingbases:isallowablewithsafetyaalvestheACTIONrequiremencsonthebasissteamflowandTHLq.KLPOt:ERrequiredofthePowerRangeNeutronFluxreductionsarederivedonthe.SPx(109)'XFor4loopoperaci.onQplam..a.Harkr8%here:SPreducedreacctripsetpoinj.npercencofRATEDTHERMALPOPERVmaximumnumberofinablesafecyval.vespersceamline<<1,2or3.X-Totalreli.ev'ngcapacityofalsafecyvalvespersteamline48,450lbs/hour.YNaxumrelievingcapacityofanyonesecyvalve57,690lbs/hour.(10PowerRangeNeutronFlux-HighTripSecpoincforloopoperaci.on.D.C.COOK-UNIT1B3/47-1AHENDHENTNO.120 Relacementtextfor3/4.7.1.1BasesHi<5=(100/Q)(4wpgZwhere:HiC=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Conversionfactor,947.82Q3tu/~SecMwtw,=MinimumtotalstcamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.h,,=HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.
,naproceedprovidethatwithin4hours,eithertheinoperable restoredtoOPlZstatus'rthePowerRangeNeutronFluxHighSetpointtripisreduced.perTable3.7-1;otherwise, beinae:-4e~HOTSTANDBYwithinthenext6hoursand.comply~~a@So%56cAAthA b.b.(Wi3reactorcoolantloopsandassociated steamgenerators inperation~
34.7PLANTSYSTEMS34.7.1XNECYCLESFVALVESNGCONDONFOOPERAON3.7.1.1AllnsdnsteanlinecodesafetyvalvesssscclatedvdeheachsteangeneratorshallbeOPERABLE.APPLXCABXLXY:Modes1,2and3.~OTXON:moog'.CZ:Valve@o~a.Wi.th4reactorcoolantloopsandassociatesteamgeneratorsinoperationandwithoneormoremainsteam1necodesafetyvalvesinoperablL,operationmaproceedprovidedgthatwithin4hours,eithertheinoperablerestoredtoOPLEstatus>orthePowerRangeNeutronFluxHigh'ipetpoint'sreducedperTable3.7-1;otherwise,beinae-~~HOTSTANDBYwithinthenext6hoursand.Complot,40~clog~~4~ta4S.b.4Wi3reactorcoolantloopsandassociatedsteamgeneratorsin'perationyandwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operation~BOYImayproceedprovidedgthatwithin4hours,eitherthe'noperableV<QclS)oVC~o-kerestoredtoOPERABLEstatus/orthereactortripbreakersareopened;otherwise,beinCGASHUTDOWNwithinthe'ext30hours.HoT'-Theprovisions'fSpecification3.0.4arenotapplicable.SURVEXLLANCEREEMENTS4.7.1..1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvaluepl%wheneverfoundoutsidethe+1Ktolerance.~P~g,sy~gQQ~>Q,~~9.0.9o~VO+aPP4cab4~f~iceieiODE3.COOKNUCLEARPLANT-UNIT.23/47-1AMENDMENTNO.Sa,167 TABLE3-1LLOWABLEOWNGEEURONGHSETPOINTWITINOPERABLESESAFVALVESDURING4LOOPOPERA0MaximumNumberofInoperableSafetyValveso0eatnSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpointPercentoRATEDERMALPOWECOOKNUCLEARPLANT-UNIT23/CI.7-2 34.7PIANTSYSTEMSBASES34.7.1TURBINECYCLE34.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteamlinecodasafetyvalvesensureschacthesecondarysystempressurevillbelimitedtovithin110iofi,tsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationalczansient.Th>>maximumreueving'capacityisassociatedvithacuzbinetzipfrom100%RATEDTHERMALPOMERcoincidentvithanassumedlossofcondensezheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveltfcsettingsandrelievingcapacitiesareinaccordancevithcherequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.Thetotalrelievtngcapacityofallsafetyvalvesonallofthesteamlinesis17,153,800lbs/hrvhichisatleast105percentofthemaximumsecondarysteamflovrateat100%RATEDTHERMALPOVER.hminimumof2OPERABLEsafetyvalvespersteamgeneratorensuresthatsufficientrelievingcapacityisavailableforcheallovableTHERMALPOVERrestrictioninTable3.7-1.STARTUPand/orPOVKROPERATIONisallovablevichsafetyvalvesinoperablevithinthelimitacionsoftheACTIONrequirementsonthebasisofthereductioninsecondarysyscemsteamflovandTHERMALPOMrequt.redbythereducedreactortripsettingsofthePoverRangeNeutronFluxchannels.Thereactortripsetpotntreductionsarederivedonthefollovingbases:For4loopoperationWhere:SPreducedreactzipsecpointinperntofRATEDTHECALPOVER@pe~a.~hahVmaximumnumberofinope~safetyvalvespersteamlineXtotalrelievtncapacityofallstyvalvespezsteamlineinlbours4,2&8,450Ymaxrelievingcapacityofanyonesafealvelbs./hour857,6909PoverRangeNeutronFlux-HighTripSecpointfor4loopoperationCOOKNUCLEARPLANT-UNIT2B3/47-1AMENDMENTNO.Sl.134 Relacementtextfor3/4.7.1.1BasesHil=(100/Q)~(4)vh)Kwhere:Hi4=Safe@AnalysispowerrangehighneutronfluxsetpointinpercentQ=NomaalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Contortionfactor,947.82~Bto/SecMwtw,=MimmxmtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSI'openingpressureincludingtoleranceandaccumulation,asappropriate,inIb/sec.Forexample,iftheaazimumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasumnarionofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,exclaKagthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhm-thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMS'peratingprcssure,excludingthethreehighestcapacityMSSVs.h<<=HeateiivaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappepriateinBtu/IbmI4=Numb'floopsinplantThevaluesahalatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforjumentandchanneluncertaintiesby9%.Thisrcduccsthcmaximumplantoperatingpowerlevelsothatitisloserthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.
andwithoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation 4MGMMnayproceedprovidedg thatnirhin4honte,eitherthein'operable
ATTACHMENT3TOAEP:NRC:1213APROPOSEDREVISEDTECHNICALSPECIFICATIONPAGES 3/4LIMITINGCONDlTIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITIONFOROPERATION3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.APPLICABILITY:MODES1,2and3.ACTION:aoMODES1&2:With4reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise,beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatementb.b.MODE3:Withaminimumof3reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s}atbrestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise,beinHOTSHUTDOWNwithinthenext30hours.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.1.1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.4.7.1.2TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3.COOKNUCLEARPLANT-UNIT1Page3/47-1AMENDMENT420,444,4' 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLEPOWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLESTEAMLINESAFETYVALVESDURING4LOOPOPERATIONMaximumNumberofInoperableSafetyValvesonAn0eratinSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)65.146.528.0COOKNUCLEARPLANT-UNIT1Page3/47-2 3/4.nBASES3/4.7PLANTSYSTE<MS3/4.7.1TURBINECYCLE3/4.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteamlinecodesafetyvalvesensuresthatthesecondarysystempressurewillbelimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationaltransient.Themaximumrelievingcapacityisassociatedwithaturbinetripfrom100%RATEDTHERMALPOWERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveliftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingofJ3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidetheJ1%tolerance.Thetotalrelievingcapacityforallvalvesonallofthesteamlinesis17,153,800lbs/hrwhichisapproximately121percentofthetotalsecondarysteamflowof14,120,000Ibs/hrat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvesperoperablesteamgeneratorensuresthatsufficientrelievingcapacityisavailablefortheallowableTHERMALPOWERrestrictioninTable3.7-1.STARTUPand/orPOWEROPERATIONisallowablewithsafetyvalvesinoperablewithinthelimitationsoftheACTIONrequirementsonthebasisofthereductioninsecondarysystemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.Thereactortripsetpointreductionsarederivedonthefollowingbases:ffso=iannfffi~r(4w&Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=K=hfNominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtConversionfactor,947.82~Btu/SecMwtMinimumtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.COOKNUCLEARPLANT-UNIT1PageB3/47-1AMENDMENT420
<~"+i~C~~s.restored toOPERABLEstatus~orthereactortripbreakersareopened;otherwise, bein~SHUTDOWNwithintheNext30hours.Hol-Theprovisions ofSpecification 3.0.4arenotapp1.$cable.SURVEXLLANCE REUIREMENTS 4.7.1.1.Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLE'naccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue~1Xwheneverfoundoutsidethe+1Ktolerance.
qg~po,s-,~S ogSq~Q~Otee~i~Wk>M.3~COOKNUCLEARPLANT-UNlT13/47-1~HENTNO.k@0,464  
'TABLE3.7-lHAXlHUHALLOWABLE POllERRAHGENEUTRONFLUXlllGIISETPOIHTMITllIHOPERAOLE STEAHEPIE~I'IKTEEEEPEPEIEWIE
~HaxinemtiumberofInoperable SafetyValvesonAnOeratinSteamGenerator HaximumAllowable PowerRangetleutronFluxilighSetpointPercentofRATEDTHERHALPOWER4I~~  
/41VV<TheOPERABILITY ofthemainsteamlinecodesafetyvalvesensureschatthesecondary systempressurewillbelimitedcowt.thini.csdesignpressureof1085psigduringthemostsevereanticipated systemopera-tionalcransient.
Themaximumrelievt.ng capacityisassociated wichacurbinetripfrom100%RATEDTHER.fALPOMERcoincident withanassumedlossofcondenser heatsink(i.e.,nosceambypasscothecondenser).
Thespecified valveli.ftsettingsandrelieving capacities areinaccordance withtherequirements ofSectionIIIofcheASMEBoi.lerandPressureCode,1971Edition.Thetotalrelieving capacicyforallvalvesona11ofthe'steamli.nesis17,153,800 lbs/hrwhichisapproximately 121percentofthetocalsecondary steamflowof14,120,000 lbs/hrac100%RATEDTHERMALPOMER.Aminimumof2OPERABLEsafecyvalvesperoperabLesteamgenerator ensuresthatsufficient relievt.ng capacityi.savailable forcheallo~able THER.'iAL POWERrestri.ction inTable3.7-1.STARTUPand/orPOMEROPERATION inoperable withinthelimitations ofofchereduction insecondary systembythereducedreactortripseccingschannels.
Thereactortripsetpoincfollowing bases:isallowable withsafetyaalvestheACTIONrequiremencs onthebasissteamflowandTHLq.KLPOt:ERrequiredofthePowerRangeNeutronFluxreductions arederivedonthe.SPx(109)'XFor4loopoperaci.on Qplam..a.Harkr8%here:SPreducedreacctripsetpoinj.npercencofRATEDTHERMALPOPERVmaximumnumberofinablesafecyval.vespersceamline<<1,2or3.X-Totalreli.ev'ng capacityofalsafecyvalvespersteamline48,450lbs/hour.
YNaxumrelieving capacityofanyonesecyvalve57,690lbs/hour.
(10PowerRangeNeutronFlux-High TripSecpoincforloopoperaci.on.
D.C.COOK-UNIT1B3/47-1AHENDHENT NO.120 Relacementtextfor3/4.7.1.1 BasesHi<5=(100/Q)(4wpgZwhere:HiC=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtK=Conversion factor,947.82Q3tu/~Sec Mwtw,=Minimumtotalstcamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inlb/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthree,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, excluding thethreehighestcapacityMSSVs.h,,=Heatofvaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate inBtu/ibm4=NumberofloopsinplantThevaluescalculated fromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties by9%.Thisreducesthemaximumplantoperating powerlevelsothatitislowerthanthereactorprotection systemsetpointbyanappropriate operating margin.
34.7PLANTSYSTEMS34.7.1XNECYCLESFVALVESNGCONDONFOOPERAON3.7.1.1Allnsdnsteanlinecodesafetyvalvesssscclated vdeheachsteangenerator shallbeOPERABLE.
APPLXCABXLX Y:Modes1,2and3.~OTXON:moog'.CZ:
Valve@o~a.Wi.th4reactorcoolantloopsandassociate steamgenerators inoperation andwithoneormoremainsteam1necodesafetyvalvesinoperablL, operation maproceedprovidedg thatwithin4hours,eithertheinoperable restoredtoOPLEstatus>orthePowerRangeNeutronFluxHigh'ipetpoint'sreducedperTable3.7-1;otherwise, beinae-~~HOTSTANDBYwithinthenext6hoursand.Complot,40~clog~~4~ta4S.b.4Wi3reactorcoolantloopsandassociated steamgenerators in'perationyand withoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation
~BOYImayproceedprovidedg thatwithin4hours,eitherthe'noperable V<QclS)oVC
~o-kerestoredtoOPERABLEstatus/or thereactortripbreakersareopened;otherwise, beinCGASHUTDOWNwithinthe'ext30hours.HoT'-Theprovisions'f Specification 3.0.4arenotapplicable.
SURVEXLLANCE REEMENTS4.7.1..1Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLEinaccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvaluepl%whenever foundoutsidethe+1Ktolerance.
~P~g,sy~gQQ~>Q,~~9.0.9o~VO+aPP4cab4~f~iceieiODE3.COOKNUCLEARPLANT-UNIT.23/47-1AMENDMENT NO.Sa,167 TABLE3-1LLOWABLEOWNGEEURONGHSETPOINTWITINOPERABLE SESAFVALVESDURING4LOOPOPERA0MaximumNumberofInoperable SafetyValveso0eatnSteamGenerator MaximumAllowable PowerRangeNeutronFluxHighSetpointPercentoRATEDERMALPOWECOOKNUCLEARPLANT-UNIT23/CI.7-2 34.7PIANTSYSTEMSBASES34.7.1TURBINECYCLE34.7.1.1SAFETYVALVESTheOPERABILITY ofthemainsteamlinecodasafetyvalvesensureschacthesecondary systempressurevillbelimitedtovithin110iofi,tsdesignpressureof1085psigduringthemostsevereanticipated systemoperational czansient.
Th>>maximumreueving'capacity isassociated vithacuzbinetzipfrom100%RATEDTHERMALPOMERcoincident vithanassumedlossofcondensez heatsink(i.e.,nosteambypasstothecondenser).
Thespecified valveltfcsettingsandrelieving capacities areinaccordance vithcherequirements ofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.Thetotalrelievtng capacityofallsafetyvalvesonallofthesteamlinesis17,153,800 lbs/hrvhichisatleast105percentofthemaximumsecondary steamflovrateat100%RATEDTHERMALPOVER.hminimumof2OPERABLEsafetyvalvespersteamgenerator ensuresthatsufficient relieving capacityisavailable forcheallovable THERMALPOVERrestriction inTable3.7-1.STARTUPand/orPOVKROPERATION isallovable vichsafetyvalvesinoperable vithinthelimitacions oftheACTIONrequirements onthebasisofthereduction insecondary syscemsteamflovandTHERMALPOMrequt.red bythereducedreactortripsettingsofthePoverRangeNeutronFluxchannels.
Thereactortripsetpotntreductions arederivedonthefolloving bases:For4loopoperation Where:SPreducedreactzipsecpointinperntofRATEDTHECALPOVER@pe~a.~hahVmaximumnumberofinope~safetyvalvespersteamlineXtotalrelievtncapacityofallstyvalvespezsteamlineinlbours4,2&8,450 Ymaxrelieving capacityofanyonesafealvelbs./hour 857,6909PoverRangeNeutronFlux-High TripSecpointfor4loopoperation COOKNUCLEARPLANT-UNIT2B3/47-1AMENDMENT NO.Sl.134 Relacementtextfor3/4.7.1.1 BasesHil=(100/Q)~(4)vh)Kwhere:Hi4=Safe@Analysis powerrangehighneutronfluxsetpointinpercentQ=NomaalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtK=Contortion factor,947.82~Bto/SecMwtw,=Mimmxmtotalsteamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSI'opening pressureincluding tolerance andaccumulation, asappropriate, inIb/sec.Forexample,iftheaazimumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasumnarion ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, exclaKagthehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthm-thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMS'perating
: prcssure, excluding thethreehighestcapacityMSSVs.h<<=Heateiivaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappepriate inBtu/IbmI4=Numb'floopsinplantThevaluesahalatedfromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforjumentandchanneluncertainties by9%.Thisrcduccsthcmaximumplantoperating powerlevelsothatitisloserthanthereactorprotection systemsetpointbyanappropriate operating margin.
ATTACHMENT 3TOAEP:NRC:1213A PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES 3/4LIMITINGCONDlTIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITION FOROPERATION 3.7.1.1Allmainsteamlinecodesafetyvalvesassociated witheachsteamgenerator shallbeOPERABLE.
APPLICABILITY:
MODES1,2and3.ACTION:aoMODES1&2:With4reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise, beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatement b.b.MODE3:Withaminimumof3reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s}atbrestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise, beinHOTSHUTDOWNwithinthenext30hours.Theprovisions ofSpecification 3.0.4arenotapplicable.
SURVEILLANCE REUIREMENTS 4.7.1.1Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLEinaccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.
4.7.1.2Theprovisions ofSpecification


3/4'IMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITIONFOROPERATION3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.APPLICABILITY:MODES1,2and3.ACTION:MODES1&2:With4reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise,beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatementb.b.MODE3:Withaminimumof3reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise,beinHOTSHUTDOWNwithinthenext30hours.c.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.1.1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.4.7.1,2TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3.COOKNUCLEARPLANT-UNIT2Page3/47-1 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLEPOWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLESTEAMLINESAFETYVALVESDURING4LOOPOPERATIONMaximumNumberofInoperableSafetyValvesonAnyOperatingSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)61.643.926.2COOKNUCLEARPLANT-UNIT2Page3/47-2AMENDMENT 3/4'ASES3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLE3/4.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteainlinecodesafetyvalvesensuresthatthesecondarysystempressurewill'belimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationaltransient.Themaximumrelievingcapacityisassociatedwithaturbinetripfrom100%RATEDTHERMALPOWERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveliftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingof+3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.Thetotalrelievingcapacityofallsafetyvalvesonallofthesteamlinesis17,153,800lbs/hrwhichisatleast105percentofthemaximumsecondarysteamflowrateat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvespersteamgeneratorensuresthatsufficientrelievingcapacityisavailablefortheallowableTHERMALPOWERrestrictioninTable3.7-1.STARTUPand/orPOWEROPERATIONisallowablewithsafetyvalvesinoperablewithinthelimitationsoftheACTIONrequirementsonthebasisofthereductioninsecondarysystemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.Thereactortripsetpointreductionsarederivedonthefollowingbases:ffsto=taooft2t~r(4w&z)Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Conversionfactor,947.82~Bto/SecMwtw,=MinimumtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.h<<=HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.COOKNUCLEARPLANT-UNIT2PageB3/47-1AMENDMENT82,434 0I ATTACHMENT4TOAEP:NRC:1213AWESTINGHOUSENSAL94-001"OPERATIONATREDUCEDPOWERLEVELSWITHINOPERABLEMSSV'S" I
==4.0. 4arenotapplicable==
WestinghouseEnergySystemsBusinessUnitNUCLEARSAF1TYADVISORYLETTER'HISISANOTIHCATIONOFARECENTLYIDENTIFIEDPOTENTIALSAFETYISSUEPERTAININGTOBASICCOMPONENTS'UPPLIEDBYWESTINGHOUSE.THISINFORMATIONISBEINGPROVIDEDTOYOUSOTHATAREVIEWOFTHISISSUECANBECONDUCEDBYYOUTODETERMINEIFANYACTIONISREQUIRED.P.O.Box355,Pittsburgh,PA152304355
forentryintoMODE3.COOKNUCLEARPLANT-UNIT 1Page3/47-1AMENDMENT 420,444,4' 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLE POWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURING4LOOPOPERATION MaximumNumberofInoperable SafetyValvesonAn0eratinSteamGenerator MaximumAllowable PowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)65.146.528.0COOKNUCLEARPLANT-UNIT 1Page3/47-2 3/4.nBASES3/4.7PLANTSYSTE<MS3/4.7.1TURBINECYCLE3/4.7.1.1 SAFETYVALVESTheOPERABILITY ofthemainsteamlinecodesafetyvalvesensuresthatthesecondary systempressurewillbelimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipated systemoperational transient.
Themaximumrelieving capacityisassociated withaturbinetripfrom100%RATEDTHERMALPOWERcoincident withanassumedlossofcondenser heatsink(i.e.,nosteambypasstothecondenser).
Thespecified valveliftsettingsandrelieving capacities areinaccordance withtherequirements ofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingofJ3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidetheJ1%tolerance.
Thetotalrelieving capacityforallvalvesonallofthesteamlinesis17,153,800 lbs/hrwhichisapproximately 121percentofthetotalsecondary steamflowof14,120,000 Ibs/hrat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvesperoperablesteamgenerator ensuresthatsufficient relieving capacityisavailable fortheallowable THERMALPOWERrestriction inTable3.7-1.STARTUPand/orPOWEROPERATION isallowable withsafetyvalvesinoperable withinthelimitations oftheACTIONrequirements onthebasisofthereduction insecondary systemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.
Thereactortripsetpointreductions arederivedonthefollowing bases:ffso=iannfffi~r(4w&Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=K=hfNominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtConversion factor,947.82~Btu/SecMwtMinimumtotalsteamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inlb/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthree,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, excluding thethreehighestcapacityMSSVs.Heatofvaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate inBtu/ibm4=NumberofloopsinplantThevaluescalculated fromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties by9%.Thisreducesthemaximumplantoperating powerlevelsothatitislowerthanthereactorprotection systemsetpointbyanappropriate operating margin.COOKNUCLEARPLANT-UNIT 1PageB3/47-1AMENDMENT 420
 
3/4'IMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITION FOROPERATION 3.7.1.1Allmainsteamlinecodesafetyvalvesassociated witheachsteamgenerator shallbeOPERABLE.
APPLICABILITY:
MODES1,2and3.ACTION:MODES1&2:With4reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise, beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatement b.b.MODE3:Withaminimumof3reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s)arerestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise, beinHOTSHUTDOWNwithinthenext30hours.c.Theprovisions ofSpecification 3.0.4arenotapplicable.
SURVEILLANCE REUIREMENTS 4.7.1.1Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLEinaccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.
4.7.1,2Theprovisions ofSpecification
 
==4.0. 4arenotapplicable==
forentryintoMODE3.COOKNUCLEARPLANT-UNIT 2Page3/47-1 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLE POWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURING4LOOPOPERATION MaximumNumberofInoperable SafetyValvesonAnyOperating SteamGenerator MaximumAllowable PowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)61.643.926.2COOKNUCLEARPLANT-UNIT 2Page3/47-2AMENDMENT 3/4'ASES3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLE3/4.7.1.1 SAFETYVALVESTheOPERABILITY ofthemainsteainlinecodesafetyvalvesensuresthatthesecondary systempressurewill'belimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipated systemoperational transient.
Themaximumrelieving capacityisassociated withaturbinetripfrom100%RATEDTHERMALPOWERcoincident withanassumedlossofcondenser heatsink(i.e.,nosteambypasstothecondenser).
Thespecified valveliftsettingsandrelieving capacities areinaccordance withtherequirements ofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingof+3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.
Thetotalrelieving capacityofallsafetyvalvesonallofthesteamlinesis17,153,800 lbs/hrwhichisatleast105percentofthemaximumsecondary steamflowrateat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvespersteamgenerator ensuresthatsufficient relieving capacityisavailable fortheallowable THERMALPOWERrestriction inTable3.7-1.STARTUPand/orPOWEROPERATION isallowable withsafetyvalvesinoperable withinthelimitations oftheACTIONrequirements onthebasisofthereduction insecondary systemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.
Thereactortripsetpointreductions arederivedonthefollowing bases:ffsto=taooft2t
~r(4w&z)Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtK=Conversion factor,947.82~Bto/SecMwtw,=Minimumtotalsteamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inlb/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthree,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: pressure, excluding thethreehighestcapacityMSSVs.h<<=Heatofvaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate inBtu/ibm4=NumberofloopsinplantThevaluescalculated fromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties by9%.Thisreducesthemaximumplantoperating powerlevelsothatitislowerthanthereactorprotection systemsetpointbyanappropriate operating margin.COOKNUCLEARPLANT-UNIT 2PageB3/47-1AMENDMENT 82,434 0I ATTACHMENT 4TOAEP:NRC:1213A WESTINGHOUSE NSAL94-001"OPERATION ATREDUCEDPOWERLEVELSWITHINOPERABLE MSSV'S" I
Westinghouse EnergySystemsBusinessUnitNUCLEARSAF1TYADVISORYLETTER'HISISANOTIHCATION OFARECENTLYIDENTIFIED POTENTIAL SAFETYISSUEPERTAINING TOBASICCOMPONENTS'UPPLIED BYWESTINGHOUSE.
THISINFORMATION ISBEINGPROVIDEDTOYOUSOTHATAREVIEWOFTHISISSUECANBECONDUCEDBYYOUTODETERMINE IFANYACTIONISREQUIRED.
P.O.Box355,Pittsburgh, PA152304355


==Subject:==
==Subject:==
OperationatReducedPowerLevelswithInoperableMSSVsNumbet:NSAL-944)01BasicComponent:LossofLoadfi'urbincTripAnalysisforPlantLicensingBasisDatesOII20$4Plants:SecEnclosedListSubstantialSafetyHazardorFailuretoComplyPursuantto10CFR21.21(a)TransferofInformationPursuantto10CFR21.21(b)AdvisoryInformationPursuantto10CFR21.21(c)(2)SUMMARYYesCiNotlYcs0Ycs0WestinghousehasidentifiedapotentialsafetyissueregardingplantoperationwithinTechnicalSpecificationTable3.7-1.Thisissuedoesnotrepresentasubstantialsafetyhazardforyourplantpursuantto10CFR21.However,thisissuedoesrepresentaconditionwhichmayimpactyourplant'slicensingbasis.ITable3.7-1allowsplantstooperatewithareducednumberofoperableMSSVsatareducedpowerlevel,asdeterminedbythehighneutronQuxtripsetpoint.ThcFSARlossofload/turbinetrip(LOIJIT)analysisfromfullpowerboundsthecasewhereailMSSVsareoperable.TheFSAR(LOLfIT)eventmaynotbeboundingfortheallowableoperatingconfigurationsofTable3.7-1sincethehighneutronfiuxtripsetpojnt,whichisidentifiedinTable3.7-1foracorrespondingnumberofinoperableMSSVs,maynotbelowenoughtoprecludeasecondarysideoverpressurizationcondition.Asaresult,thebasisforTable3.7-1maynotbesuQicienttoprecludeoveipressurizationofthesecondatysideofthesteamgenerator.'Therefore,itisrecommendedthatyoureviewtheenclosedinformationtodeterininethcapplicabilityofthisissuetoyourplant.Theenclosedinfortnationcontainsamoredetaileddescriptionoftheissueandidentifiessolutionsthatyoumaywishtopursuetoaddressthisissue.Thesesolutionsinclude,butarenotlimitedto,areevaluationoftheLOIJITanalysisand/orachangeto~TechnicalSpecificationTable3.7-1.Additionalinformation,ifrequired,maybeobtainedfromthcoriginator.Tclephonc412-3746460.Originator..W.FasnachtStrategicLicensingIssuesH.A.Scpp,Manager,StrategicLicensingIssuesa%418.wpf:1b412094  
Operation atReducedPowerLevelswithInoperable MSSVsNumbet:NSAL-944)01 BasicComponent:
LossofLoadfi'urbinc TripAnalysisforPlantLicensing BasisDatesOII20$4Plants:SecEnclosedListSubstantial SafetyHazardorFailuretoComplyPursuantto10CFR21.21(a)TransferofInformation Pursuantto10CFR21.21(b)AdvisoryInformation Pursuantto10CFR21.21(c)(2)
SUMMARYYesCiNotlYcs0Ycs0Westinghouse hasidentified apotential safetyissueregarding plantoperation withinTechnical Specification Table3.7-1.Thisissuedoesnotrepresent asubstantial safetyhazardforyourplantpursuantto10CFR21.However,thisissuedoesrepresent acondition whichmayimpactyourplant'slicensing basis.ITable3.7-1allowsplantstooperatewithareducednumberofoperableMSSVsatareducedpowerlevel,asdetermined bythehighneutronQuxtripsetpoint.
ThcFSARlossofload/turbine trip(LOIJIT)analysisfromfullpowerboundsthecasewhereailMSSVsareoperable.
TheFSAR(LOLfIT)eventmaynotbeboundingfortheallowable operating configurations ofTable3.7-1sincethehighneutronfiuxtripsetpojnt, whichisidentified inTable3.7-1foracorresponding numberofinoperable MSSVs,maynotbelowenoughtoprecludeasecondary sideoverpressurization condition.
Asaresult,thebasisforTable3.7-1maynotbesuQicient toprecludeoveipressurization ofthesecondaty sideofthesteamgenerator.
'Therefore, itisrecommended thatyoureviewtheenclosedinformation todeterinine thcapplicability ofthisissuetoyourplant.Theenclosedinfortnation containsamoredetaileddescription oftheissueandidentifies solutions thatyoumaywishtopursuetoaddressthisissue.Thesesolutions include,butarenotlimitedto,areevaluation oftheLOIJITanalysisand/orachangeto~Technical Specification Table3.7-1.Additional information, ifrequired, maybeobtainedfromthcoriginator.
Tclephonc 412-3746460.
Originator.
.W.FasnachtStrategic Licensing IssuesH.A.Scpp,Manager,Strategic Licensing Issuesa%418.wpf:
1b412094  


PlantsAffectedD.C.Cook1&2J.M.FarleyI&2Byron1&2BraidwoodI&2V.C.SummerIZion1&2ShearonHarrisIW.B.McGuireI&2CatawbaI&2BeaverValleyI&2TurkeyPoint3&4VogtleI&2IndianPoint2&3SeabrookIMillstone3DiabloCanyonI&2WolfCreekCallawayIComanchePeakI&2SouthTexasI&2SequoyahI&2NorthAnnaI&2WattsBarI&2Size,wellBKori1,2,3&4YonggwangI&2SalemI&2@%418.wpf:1b411994II 04 IssueDescritionWestinghousehasidentifiedadeficiencyinthebasisforTechnicalSpecification3.7.1.1.ThisTechnicalSpecificationallowstheplanttooperateatareducedpowerlevelwithareducednumberofoperableMainSteamSafetyValves(MSSVs).ThedeficiencyisintheassumptionthatthemaximumallowableinitialpowerlevelisalinearfunctionoftheavailableMSSVreliefcapacity.ThelinearfunctionisidentifiedintheBasesSectionforTechnicalSpecification3/4.7.1.1andisprovidedasfollows:Sp=(X)aO(V)x(i(e)XSP=Reducedreactortripsetpointin%ofRATEDTHERMALPOWERV=MaximumnumberofinoperablesafetyvalvespersteamlineX=Totalrelievingcapacityofallsafetyvalvespersteamlineinibm/hour(109)=MaximumrelievingcapacityofanyonesafetyvalveinIbm/hourPowerrangeneutronflux-hightripsetpointforallloopsinoperationUndercerfainconditionsandwithtypicalsafetyanalysisassumptions,aLossofLoad/DrrbineTriptransientfrompart-powerconditionsmayresultinoverpressurizationofthemainsteamsystemwhenoperWnginaccordancewiththisTechnicalSpecification.'Ihefollowingdiscussiondescribestheissueinmoredetailandprovidesrecommendedalternativesforaddressingtheissue.TechnicalEvaluation'IheLossofLoad/TurbineTrip(LOLGT)eventisanalyzedintheFSARtoshowthatcorepro~onmarginsaremaintained(DNBR),theRCSwillnotoverpressurize,andthemainsteamsystemwillnotoveipressurize.Theanalysisassumesanimmediatelossofsteamrelievingcapabilitythroughtheturbineandcoincidentlossofallmainfeedwater.Nocreditistakenforthedirectreactortriponturbinetrip,sincethistripwouldnotbeactuatedforthecaseofalossofsteamload.Rather,thetransientisterminatedbyareactortriponhighpressurizerpressure,overtemperatureAT,orlowsteamgeneratorwaterlevel.Secondarysideov'erpressureprotectionisprovidedbyactuationoftheMainSteamSafetyValves(MSSVs),whicharedesignedtorelieveatleastfullpowernominalsteamflow.'IlieanalysisverifiesthattheMSSVcapacityissufficienttopreventsecondarysidepressurefimm.exceeding110percentofthedesignpressure.0%418.vq>f:tb411994  
PlantsAffectedD.C.Cook1&2J.M.FarleyI&2Byron1&2Braidwood I&2V.C.SummerIZion1&2ShearonHarrisIW.B.McGuireI&2CatawbaI&2BeaverValleyI&2TurkeyPoint3&4VogtleI&2IndianPoint2&3SeabrookIMillstone 3DiabloCanyonI&2WolfCreekCallawayIComanchePeakI&2SouthTexasI&2SequoyahI&2NorthAnnaI&2WattsBarI&2Size,well BKori1,2,3
&4Yonggwang I&2SalemI&2@%418.wpf:1b411994 II 04 IssueDescritionWestinghouse hasidentified adeficiency inthebasisforTechnical Specification 3.7.1.1.ThisTechnical Specification allowstheplanttooperateatareducedpowerlevelwithareducednumberofoperableMainSteamSafetyValves(MSSVs).Thedeficiency isintheassumption thatthemaximumallowable initialpowerlevelisalinearfunctionoftheavailable MSSVreliefcapacity.
Thelinearfunctionisidentified intheBasesSectionforTechnical Specification 3/4.7.1.1 andisprovidedasfollows:Sp=(X)aO(V)x(i(e)XSP=Reducedreactortripsetpointin%ofRATEDTHERMALPOWERV=Maximumnumberofinoperable safetyvalvespersteamlineX=Totalrelieving capacityofallsafetyvalvespersteamlineinibm/hour(109)=Maximumrelieving capacityofanyonesafetyvalveinIbm/hourPowerrangeneutronflux-high tripsetpointforallloopsinoperation Undercerfainconditions andwithtypicalsafetyanalysisassumptions, aLossofLoad/Drrbine Triptransient frompart-power conditions mayresultinoverpressurization ofthemainsteamsystemwhenoperWnginaccordance withthisTechnical Specification.
'Ihefollowing discussion describes theissueinmoredetailandprovidesrecommended alternatives foraddressing theissue.Technical Evaluation
'IheLossofLoad/Turbine Trip(LOLGT)eventisanalyzedintheFSARtoshowthatcorepro~onmarginsaremaintained (DNBR),theRCSwillnotoverpressurize, andthemainsteamsystemwillnotoveipressurize.
Theanalysisassumesanimmediate lossofsteamrelieving capability throughtheturbineandcoincident lossofallmainfeedwater.
Nocreditistakenforthedirectreactortriponturbinetrip,sincethistripwouldnotbeactuatedforthecaseofalossofsteamload.Rather,thetransient isterminated byareactortriponhighpressurizer
: pressure, overtemperature AT,orlowsteamgenerator waterlevel.Secondary sideov'erpressure protection isprovidedbyactuation oftheMainSteamSafetyValves(MSSVs),whicharedesignedtorelieveatleastfullpowernominalsteamflow.'IlieanalysisverifiesthattheMSSVcapacityissufficient topreventsecondary sidepressurefimm.exceeding 110percentofthedesignpressure.
0%418.vq>f:tb411994  


TheFSARonlyanalyzestheLOIJITtransientGomtheMpowerinitialcondition,withcasesexaminingtheeffectsofassumingprimarysidepressurecontrolanddifferentreactivityfeedbackconditions.WithfullyoperationalMSSVs,itcanbedemonstratedthatoverpressureprotectionisprovidedforallinitialpowerlevels.However,formostplants,TechnicalSpecification3.7.1.1allowsoperationwithareducednumberofoperableMSSVsatareducedpowerlevelasdeterminedbyresettingthepowerrangehighneutronfiuxsetpoint.ThisTechnicalSpecificationisnotbasedonadetailedanalysis,butratherontheassumptionthatthemaximumallowableinitialpowerlevelisalinearfunctionoftheavailableMSSVreliefcapacity.Recently,ithasbeendeterminedthatthisassumptionisnotvalid.'Iheproblemisthatifmainfeedwaterislost,areactortripisnecessarytopreventsecondarysideoverpressurizationforallpostulatedcoreconditions.Athighinitialpowerlevelsareactortripisactuatedearlyinthetransientas.aresultofeitherhighpressurizerpressureorovertemperaturehT.ThereactortripterminatesthetransientandtheMSSVsmaintainsteampressurebelow110%ofthedesignvalue.Atlowerinitialpowerlevelsareactortripmaynotbeactuatedearlyinthetransient.AnovertempeiaturehTtripisn'tgeneratedsincethecorethermalmarginsareincreasedatlowerpowerlevels.Ahighpressurizerpressuretripisn'tgeneratediftheprimarypressurecontrolsystemsfunctionnormally.Thisresultsinalongertimeduringwhichprimaryheatistransferredtothesecondaryside.'Ihereactoreventually,tripsonlowsteamgeneratorwaterlevel,butthismaynotoccurbeforesteampressureexceeds110%ofthedesignvalueifoneormoreMSSVsareinoperableinaccordancewiththeTechnicalSpecification.DuetothewidevarietyofplantdesignfeaturesthatareimportanttotheLOIJITanalysis,itisdifficulttoperformagenericevaluationtoshowthattheissuedoesnotapplytocertainplants.ThefollowingkeyparametershaveasignificanteffectonthesecondarysidepressuretransientMSSVreliefcapacityModeratorTemperatureCoefficient(MTC)MarginbetweentheMSSVsetpressures(includingtolerance)andtheoverpressurelimitLow-lowsteamgeneratorwaterlevelreactortripsetpointSafetSinificanceTheTechnicalSpecificationsformostplantsallowoperationatareducedpowerlevelwithinoperableMSSVs.Fromalicensingbasisperspective,thisconditionmayresultinsecondarysideoverpressurizationintheeventofaLOIJITtransient.Thelicensingbasisforanticipatedoperationaloccurrences(ANSConditionIIevents)typicallyrequiresthatthesecondarysideprcssureremainbelow110%ofthedesignvalue.a%418.wpf:Ib411994 Westinghousehasdeterminedthatthisissuedoesnotrepresentasubstantialsafetyhazard.Thereareseveralmitigatingfactorswhichprovideassurancethatthereisnolossofsafetyfunctiontotheexteatthatthereisamajorreductioninthedegreeofprotectionprovidedtothepublichealthandsafety.Theseinclude,butarenotlimitedto,thefollowing:1.AdequateoverpressureprotectionisprovidedatallpowerlevelsifalloftheMSSVsareoperable.2.Ifareactortripdoesnotoccurbutmainfeedwaterfiowismaintained,operationinaccordancewiththeTechnicalSpecificationTable3.7-1willnotresultinanoverpressurecondition.3.InanyLOIJITtransient,theatmosphericsteamdumpvalvesand/orcondensersteamdumpvalvesactuatetorelieveenergyiromthesteamgeneratorspriortotheopeningoftheMSSVs,andcontinuetorelievesteamiftheMSSVsdoopen.Sinceitisnotasafety-gradefunction,steamdumpisnotassumedtooperateinthesafetyanalysis;however,inrealityitisthefirstlineofdefenseinprotectingthesecondarysystemagainstoverpressurizatioa.ItisveryimprobablethatallthesecompoaentswouldbeinoperablecoincidentwithinoperableMSSVs.4.EvennearthebeginningofcorelifewithapositiveorzeroMTC,theprimaryvolantheatupresultingfromthetransientwouldtendtodrivethehGCnegative,whichwould.reducethecorepoweraadheatinputtothecoolaat.Thiswouldresultin'alowerrequiredMSSVcapacitytopreventsecondaryovegressurization.ThesafetyanalysisdoesnotcreditthereductionofMTCduringthetransient.NRCAwarenessIReortabilitWestinghousehasnotnotifiedtheNRCofthisissue,baseduponthedeterminationthatitdoesaotrepresentasubstantialsafetyhazardpursuantto10CFR21.However,WestinghousewillsendacopyofthislettertotheNRCsincethisissueimpactsinformationcontainedinNUREG-1431,"StandardTechnicalSpecifications,WestinghousePlants".RecommendationsToaddressthisissue,thefollowingactionsmaybeconsidered:(1)ModifyTechaicalSpecificatioa3.7.1.1(orequivalent)andtheassociatedbasissuchthatthemaximumpowerlevelallowedforoperationwithinoperableMSSVsisbelowtheheatremovingcapabilityoftheoperableMSSVs.Aconservativewaytodothisistosetthepowerrangehighaeutmnfiuxsetpointtothispowerlevel,thusensuringthattheactualpowerlevelcannotexceed@%418.wpf:1b411994  
TheFSARonlyanalyzestheLOIJITtransient GomtheMpowerinitialcondition, withcasesexamining theeffectsofassumingprimarysidepressurecontrolanddifferent reactivity feedbackconditions.
Withfullyoperational MSSVs,itcanbedemonstrated thatoverpressure protection isprovidedforallinitialpowerlevels.However,formostplants,Technical Specification 3.7.1.1allowsoperation withareducednumberofoperableMSSVsatareducedpowerlevelasdetermined byresetting thepowerrangehighneutronfiuxsetpoint.
ThisTechnical Specification isnotbasedonadetailedanalysis, butratherontheassumption thatthemaximumallowable initialpowerlevelisalinearfunctionoftheavailable MSSVreliefcapacity.
: Recently, ithasbeendetermined thatthisassumption isnotvalid.'Iheproblemisthatifmainfeedwater islost,areactortripisnecessary topreventsecondary sideoverpressurization forallpostulated coreconditions.
Athighinitialpowerlevelsareactortripisactuatedearlyinthetransient as.aresultofeitherhighpressurizer pressureorovertemperature hT.Thereactortripterminates thetransient andtheMSSVsmaintainsteampressurebelow110%ofthedesignvalue.Atlowerinitialpowerlevelsareactortripmaynotbeactuatedearlyinthetransient.
Anovertempeiature hTtripisn'tgenerated sincethecorethermalmarginsareincreased atlowerpowerlevels.Ahighpressurizer pressuretripisn'tgenerated iftheprimarypressurecontrolsystemsfunctionnormally.
Thisresultsinalongertimeduringwhichprimaryheatistransferred tothesecondary side.'Ihereactoreventually, tripsonlowsteamgenerator waterlevel,butthismaynotoccurbeforesteampressureexceeds110%ofthedesignvalueifoneormoreMSSVsareinoperable inaccordance withtheTechnical Specification.
Duetothewidevarietyofplantdesignfeaturesthatareimportant totheLOIJITanalysis, itisdifficult toperformagenericevaluation toshowthattheissuedoesnotapplytocertainplants.Thefollowing keyparameters haveasignificant effectonthesecondary sidepressuretransient MSSVreliefcapacityModerator Temperature Coefficient (MTC)MarginbetweentheMSSVsetpressures (including tolerance) andtheoverpressure limitLow-lowsteamgenerator waterlevelreactortripsetpointSafetSinificance TheTechnical Specifications formostplantsallowoperation atareducedpowerlevelwithinoperable MSSVs.Fromalicensing basisperspective, thiscondition mayresultinsecondary sideoverpressurization intheeventofaLOIJITtransient.
Thelicensing basisforanticipated operational occurrences (ANSCondition IIevents)typically requiresthatthesecondary sideprcssureremainbelow110%ofthedesignvalue.a%418.wpf:
Ib411994 Westinghouse hasdetermined thatthisissuedoesnotrepresent asubstantial safetyhazard.Thereareseveralmitigating factorswhichprovideassurance thatthereisnolossofsafetyfunctiontotheexteatthatthereisamajorreduction inthedegreeofprotection providedtothepublichealthandsafety.Theseinclude,butarenotlimitedto,thefollowing:
1.Adequateoverpressure protection isprovidedatallpowerlevelsifalloftheMSSVsareoperable.
2.Ifareactortripdoesnotoccurbutmainfeedwater fiowismaintained, operation inaccordance withtheTechnical Specification Table3.7-1willnotresultinanoverpressure condition.
3.InanyLOIJITtransient, theatmospheric steamdumpvalvesand/orcondenser steamdumpvalvesactuatetorelieveenergyiromthesteamgenerators priortotheopeningoftheMSSVs,andcontinuetorelievesteamiftheMSSVsdoopen.Sinceitisnotasafety-grade
: function, steamdumpisnotassumedtooperateinthesafetyanalysis; however,inrealityitisthefirstlineofdefenseinprotecting thesecondary systemagainstoverpressurizatioa.
Itisveryimprobable thatallthesecompoaents wouldbeinoperable coincident withinoperable MSSVs.4.Evennearthebeginning ofcorelifewithapositiveorzeroMTC,theprimaryvolantheatupresulting fromthetransient wouldtendtodrivethehGCnegative, whichwould.reducethecorepoweraadheatinputtothecoolaat.Thiswouldresultin'alowerrequiredMSSVcapacitytopreventsecondary ovegressurization.
Thesafetyanalysisdoesnotcreditthereduction ofMTCduringthetransient.
NRCAwareness IReortabilit Westinghouse hasnotnotifiedtheNRCofthisissue,baseduponthedetermination thatitdoesaotrepresent asubstantial safetyhazardpursuantto10CFR21.However,Westinghouse willsendacopyofthislettertotheNRCsincethisissueimpactsinformation contained inNUREG-1431, "Standard Technical Specifications, Westinghouse Plants".Recommendations Toaddressthisissue,thefollowing actionsmaybeconsidered:
(1)ModifyTechaical Specificatioa 3.7.1.1(orequivalent) andtheassociated basissuchthatthemaximumpowerlevelallowedforoperation withinoperable MSSVsisbelowtheheatremovingcapability oftheoperableMSSVs.Aconservative waytodothisistosetthepowerrangehighaeutmnfiuxsetpointtothispowerlevel,thusensuringthattheactualpowerlevelcannotexceed@%418.wpf:1b411994  


~~thisvalue.Tocalculatethissetpoint,thegoverningequationistherelationshipq=mhh,whereqistheheatinputfmmtheprimaryside,misthesteamflowrateandhhistheheatofvaporizationatthesteamreliefpressure(assumingnosubcooledfecdwater).Thus,analgorithmforuscindefiningtherevisedTechnicalSpecificationtablesetpointvalueswouldbe:Hig=(100/Q)~(wPN)Kwhere:'ig=SafetyAnalysispowerrangehighneutronfluxsetpoint,percentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat),MwtK=Conversionfactor,947.82MwtwsMinimumtotalsteamlowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inib/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingprcssure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVsperstcamgeneratoristhreethenw,shouldbeasummationofthecapacityofthcoperableMSSVsatthehighestoperableMSSVoperatingprcssure,excludingthethreehighestcapacityMSSVs.h+=heatofvaporizationforstcamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,Btu/1bmN=NumberofloopsinplantThevaluescalculatedfromthisalgorithmmustthenbeadjustedlowerforuscinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertainties(typically9%power).Themaximumplantoperatingpowerlevelwouldthenbelowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.0%418.wpf:1b411994 kk  
~~thisvalue.Tocalculate thissetpoint, thegoverning equationistherelationship q=mhh,whereqistheheatinputfmmtheprimaryside,misthesteamflowrateandhhistheheatofvaporization atthesteamreliefpressure(assuming nosubcooled fecdwater).
~y~0C~c.Itshouldbenotedthattheuscofthisequatioawillresolvetheissueideatifiedinthisletterbyeaablingyoutore~culateyourTechnicalSpecification3.7.1.1setpointswithoutfurthermodificationstothestructureoftheTcchnicalSpecification.There-calculatedsetpointsarelikelytobelowerthanthosecurrentlyallowedbytheTechaicalSpecification.However,youshouldbeawareofatleasttwoconscrvatismswiththeequationYoumaywishtoreviewtheseconservatismstoevaluatetheuseoftheequationrelativetoyourplantspecificoperatingobjectives.ItispossibletorelaxsomeoftheseconservatismsforuseintheTechnicalSpecificatioaHowever,relaxationoftheconservatismsarelikelytoresultinmoresignificantchangestothestructureoftheTechnicalSpccificatioaFirst,theaboveequatioa(andtheexistingTechaicalSpecification3.7.1.1)isconservativesinceitisbasedonthemaximumnumberofinoperableMSSVsperloop.Forexample,arepresentativefourloopplant,inaccordancewiththecurrentTechnicalSpecification,shouldreduce'heneutronfluxsetpointto87%ifithasuptooneinoperableMSSVoneachloop.Thismeansthattheplantshouldusethissetpointwhetherthereareone,two,threeorfourinoperableMSSVs,aslongasthereisonlyoneinoperableMSSVpcrloop.Thus,theexistingTechnicalSpecificationandtheaboveequationareconservativeandbounding.However,anyrelaxationofthisconservatismmustbeinterpretedwithcare.Thereasonisthatthesteamgeneratorsmustbeprotcctcd6'omanovcrpressurizationconditionduringalossofloadtransient.'I%ereareseveraleventsthatcouldleadtoalossofload,includingtheinadvertentclosureofoneorallMSIVs.TheaffectedsteamgeneratormusthaveasufficientnumberofoperableMSSVstoprotectitfromanoverpressurizatioacondition,iftheMSIV(orMSIVs)wasiaadvertentlyclosed.Anotherconservatismintheaboveequation(andtheexistingTechnicalSpecification3.7.1.1)isinwwhichistheminimumtotalsteamQowratecapabilityoftheoperableMSSVsonanyonesteamgenerator.ThisvalueisconservativesinceitassumesthatifoneormoreMSSVsareinoperableperloop,theinoperableMSSVsarethelargestcapacityMSSVs,regardlessofwhetherthelargestcapacityMSSVsorthesmallercapacityMSSVsareinoperable.TheassumptionhasbeenmadesothattheaboveequationisconsistentwiththecurrentstructureofTechnicalSpecification3.7.1.1.(2)Asanalternative,plant-specificLOIJITanalysescouldbeperformedtomaximizetheallowablepower.levelforagivennumberofinoperableMSSVs.Dependingonkeyspecificplantparameters,theseanalysesmaybeabletojustifythecoatinuedvalidityofthecurrentTechnicalSpecificatioa(3)Considermodifying,asrequired,theBasesSectionforTechaicalSpecification3/4.7.1.1sothat.itisconsistentwiththeplantsafetyanalysis.Thesafetyanalysiscriterionforpreventiagovciprcssurizationofthesecondarysideisthattheprcssuredoesnotexceed110%ofthedesignpessureforanticipatedtransients.However,inreviewingseveralplanttechaicalspecifications,a%418.wpf:tbsp11994 itwasnotedthatthebasesforsomeplantsstatethatthesafetyvalvesinsurethatthesecondarysystempressurewillbelimitedtowithin10Soreven100%%uoofdesignprcssure.Thisisnotconsistentwiththesafetyanalysisbasisandshouldberevisedtoindicate110%.@%418.vg)f:1b411994}}
Thus,analgorithm foruscindefiningtherevisedTechnical Specification tablesetpointvalueswouldbe:Hig=(100/Q)~(wPN)Kwhere:'ig=SafetyAnalysispowerrangehighneutronfluxsetpoint, percentQ=NominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat),MwtK=Conversion factor,947.82MwtwsMinimumtotalsteamlowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inib/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
: prcssure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVsperstcamgenerator isthreethenw,shouldbeasummation ofthecapacityofthcoperableMSSVsatthehighestoperableMSSVoperating
: prcssure, excluding thethreehighestcapacityMSSVs.h+=heatofvaporization forstcamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, Btu/1bmN=Numberofloopsin plantThevaluescalculated fromthisalgorithm mustthenbeadjustedlowerforuscinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties (typically 9%power).Themaximumplantoperating powerlevelwouldthenbelowerthanthereactorprotection systemsetpointbyanappropriate operating margin.0%418.wpf:
1b411994 kk  
~y~0C~c.Itshouldbenotedthattheuscofthisequatioawillresolvetheissueideatified inthisletterbyeaablingyoutore~culate yourTechnical Specification 3.7.1.1setpoints withoutfurthermodifications tothestructure oftheTcchnical Specification.
There-calculated setpoints arelikelytobelowerthanthosecurrently allowedbytheTechaical Specification.
However,youshouldbeawareofatleasttwoconscrvatisms withtheequationYoumaywishtoreviewtheseconservatisms toevaluatetheuseoftheequationrelativetoyourplantspecificoperating objectives.
Itispossibletorelaxsomeoftheseconservatisms foruseintheTechnical Specificatioa However,relaxation oftheconservatisms arelikelytoresultinmoresignificant changestothestructure oftheTechnical Spccificatioa First,theaboveequatioa(andtheexistingTechaical Specification 3.7.1.1)isconservative sinceitisbasedonthemaximumnumberofinoperable MSSVsperloop.Forexample,arepresentative fourloopplant,inaccordance withthecurrentTechnical Specification, shouldreduce'he neutronfluxsetpointto87%ifithasuptooneinoperable MSSVoneachloop.Thismeansthattheplantshouldusethissetpointwhetherthereareone,two,threeorfourinoperable MSSVs,aslongasthereisonlyoneinoperable MSSVpcrloop.Thus,theexistingTechnical Specification andtheaboveequationareconservative andbounding.
However,anyrelaxation ofthisconservatism mustbeinterpreted withcare.Thereasonisthatthesteamgenerators mustbeprotcctcd 6'omanovcrpressurization condition duringalossofloadtransient.
'I%ereareseveraleventsthatcouldleadtoalossofload,including theinadvertent closureofoneorallMSIVs.Theaffectedsteamgenerator musthaveasufficient numberofoperableMSSVstoprotectitfromanoverpressurizatioa condition, iftheMSIV(orMSIVs)wasiaadvertently closed.Anotherconservatism intheaboveequation(andtheexistingTechnical Specification 3.7.1.1)isinwwhichistheminimumtotalsteamQowratecapability oftheoperableMSSVsonanyonesteamgenerator.
Thisvalueisconservative sinceitassumesthatifoneormoreMSSVsareinoperable perloop,theinoperable MSSVsarethelargestcapacityMSSVs,regardless ofwhetherthelargestcapacityMSSVsorthesmallercapacityMSSVsareinoperable.
Theassumption hasbeenmadesothattheaboveequationisconsistent withthecurrentstructure ofTechnical Specification 3.7.1.1.(2)Asanalternative, plant-specific LOIJITanalysescouldbeperformed tomaximizetheallowable power.level foragivennumberofinoperable MSSVs.Depending onkeyspecificplantparameters, theseanalysesmaybeabletojustifythecoatinued validityofthecurrentTechnical Specificatioa (3)Considermodifying, asrequired, theBasesSectionforTechaical Specification 3/4.7.1.1 sothat.itisconsistent withtheplantsafetyanalysis.
Thesafetyanalysiscriterion forpreventiag ovciprcssurization ofthesecondary sideisthattheprcssuredoesnotexceed110%ofthedesignpessureforanticipated transients.
However,inreviewing severalplanttechaical specifications, a%418.wpf:
tbsp11994 itwasnotedthatthebasesforsomeplantsstatethatthesafetyvalvesinsurethatthesecondary systempressurewillbelimitedtowithin10Soreven100%%uoofdesignprcssure.
Thisisnotconsistent withthesafetyanalysisbasisandshouldberevisedtoindicate110%.@%418.vg)f:1b411994}}

Revision as of 07:58, 29 June 2018

Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV
ML17332A999
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Issue date: 10/20/1995
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ATTACHMENT 2TOAEP'NRC'1213A EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES9510310312 951020PDRADOCK05000315PPDR 0

34.7SYSTEMS347.TGRBTNECYCLESAFETYVALVESNGCONDXTONFOROPERAON3.7.1.1Allmainsteamlinecodesafetyvalvesassociated witheachsteamgenerator shallbeOPERABLE.

ancC.v~lu~is>a~a.4With4reactorcoolantloopsandassociate steamgenerators in'perationpand withoneormoremainsteam1necodesafetyvalvesinop'arable, operation

,naproceedprovidethatwithin4hours,eithertheinoperable restoredtoOPlZstatus'rthePowerRangeNeutronFluxHighSetpointtripisreduced.perTable3.7-1;otherwise, beinae:-4e~HOTSTANDBYwithinthenext6hoursand.comply~~a@So%56cAAthA b.b.(Wi3reactorcoolantloopsandassociated steamgenerators inperation~

andwithoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation 4MGMMnayproceedprovidedg thatnirhin4honte,eitherthein'operable

<~"+i~C~~s.restored toOPERABLEstatus~orthereactortripbreakersareopened;otherwise, bein~SHUTDOWNwithintheNext30hours.Hol-Theprovisions ofSpecification 3.0.4arenotapp1.$cable.SURVEXLLANCE REUIREMENTS 4.7.1.1.Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLE'naccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue~1Xwheneverfoundoutsidethe+1Ktolerance.

qg~po,s-,~S ogSq~Q~Otee~i~Wk>M.3~COOKNUCLEARPLANT-UNlT13/47-1~HENTNO.k@0,464

'TABLE3.7-lHAXlHUHALLOWABLE POllERRAHGENEUTRONFLUXlllGIISETPOIHTMITllIHOPERAOLE STEAHEPIE~I'IKTEEEEPEPEIEWIE

~HaxinemtiumberofInoperable SafetyValvesonAnOeratinSteamGenerator HaximumAllowable PowerRangetleutronFluxilighSetpointPercentofRATEDTHERHALPOWER4I~~

/41VV<TheOPERABILITY ofthemainsteamlinecodesafetyvalvesensureschatthesecondary systempressurewillbelimitedcowt.thini.csdesignpressureof1085psigduringthemostsevereanticipated systemopera-tionalcransient.

Themaximumrelievt.ng capacityisassociated wichacurbinetripfrom100%RATEDTHER.fALPOMERcoincident withanassumedlossofcondenser heatsink(i.e.,nosceambypasscothecondenser).

Thespecified valveli.ftsettingsandrelieving capacities areinaccordance withtherequirements ofSectionIIIofcheASMEBoi.lerandPressureCode,1971Edition.Thetotalrelieving capacicyforallvalvesona11ofthe'steamli.nesis17,153,800 lbs/hrwhichisapproximately 121percentofthetocalsecondary steamflowof14,120,000 lbs/hrac100%RATEDTHERMALPOMER.Aminimumof2OPERABLEsafecyvalvesperoperabLesteamgenerator ensuresthatsufficient relievt.ng capacityi.savailable forcheallo~able THER.'iAL POWERrestri.ction inTable3.7-1.STARTUPand/orPOMEROPERATION inoperable withinthelimitations ofofchereduction insecondary systembythereducedreactortripseccingschannels.

Thereactortripsetpoincfollowing bases:isallowable withsafetyaalvestheACTIONrequiremencs onthebasissteamflowandTHLq.KLPOt:ERrequiredofthePowerRangeNeutronFluxreductions arederivedonthe.SPx(109)'XFor4loopoperaci.on Qplam..a.Harkr8%here:SPreducedreacctripsetpoinj.npercencofRATEDTHERMALPOPERVmaximumnumberofinablesafecyval.vespersceamline<<1,2or3.X-Totalreli.ev'ng capacityofalsafecyvalvespersteamline48,450lbs/hour.

YNaxumrelieving capacityofanyonesecyvalve57,690lbs/hour.

(10PowerRangeNeutronFlux-High TripSecpoincforloopoperaci.on.

D.C.COOK-UNIT1B3/47-1AHENDHENT NO.120 Relacementtextfor3/4.7.1.1 BasesHi<5=(100/Q)(4wpgZwhere:HiC=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtK=Conversion factor,947.82Q3tu/~Sec Mwtw,=Minimumtotalstcamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inlb/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating

pressure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthree,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
pressure, excluding thethreehighestcapacityMSSVs.h,,=Heatofvaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate inBtu/ibm4=NumberofloopsinplantThevaluescalculated fromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties by9%.Thisreducesthemaximumplantoperating powerlevelsothatitislowerthanthereactorprotection systemsetpointbyanappropriate operating margin.

34.7PLANTSYSTEMS34.7.1XNECYCLESFVALVESNGCONDONFOOPERAON3.7.1.1Allnsdnsteanlinecodesafetyvalvesssscclated vdeheachsteangenerator shallbeOPERABLE.

APPLXCABXLX Y:Modes1,2and3.~OTXON:moog'.CZ:

Valve@o~a.Wi.th4reactorcoolantloopsandassociate steamgenerators inoperation andwithoneormoremainsteam1necodesafetyvalvesinoperablL, operation maproceedprovidedg thatwithin4hours,eithertheinoperable restoredtoOPLEstatus>orthePowerRangeNeutronFluxHigh'ipetpoint'sreducedperTable3.7-1;otherwise, beinae-~~HOTSTANDBYwithinthenext6hoursand.Complot,40~clog~~4~ta4S.b.4Wi3reactorcoolantloopsandassociated steamgenerators in'perationyand withoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation

~BOYImayproceedprovidedg thatwithin4hours,eitherthe'noperable V<QclS)oVC

~o-kerestoredtoOPERABLEstatus/or thereactortripbreakersareopened;otherwise, beinCGASHUTDOWNwithinthe'ext30hours.HoT'-Theprovisions'f Specification 3.0.4arenotapplicable.

SURVEXLLANCE REEMENTS4.7.1..1Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLEinaccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvaluepl%whenever foundoutsidethe+1Ktolerance.

~P~g,sy~gQQ~>Q,~~9.0.9o~VO+aPP4cab4~f~iceieiODE3.COOKNUCLEARPLANT-UNIT.23/47-1AMENDMENT NO.Sa,167 TABLE3-1LLOWABLEOWNGEEURONGHSETPOINTWITINOPERABLE SESAFVALVESDURING4LOOPOPERA0MaximumNumberofInoperable SafetyValveso0eatnSteamGenerator MaximumAllowable PowerRangeNeutronFluxHighSetpointPercentoRATEDERMALPOWECOOKNUCLEARPLANT-UNIT23/CI.7-2 34.7PIANTSYSTEMSBASES34.7.1TURBINECYCLE34.7.1.1SAFETYVALVESTheOPERABILITY ofthemainsteamlinecodasafetyvalvesensureschacthesecondary systempressurevillbelimitedtovithin110iofi,tsdesignpressureof1085psigduringthemostsevereanticipated systemoperational czansient.

Th>>maximumreueving'capacity isassociated vithacuzbinetzipfrom100%RATEDTHERMALPOMERcoincident vithanassumedlossofcondensez heatsink(i.e.,nosteambypasstothecondenser).

Thespecified valveltfcsettingsandrelieving capacities areinaccordance vithcherequirements ofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.Thetotalrelievtng capacityofallsafetyvalvesonallofthesteamlinesis17,153,800 lbs/hrvhichisatleast105percentofthemaximumsecondary steamflovrateat100%RATEDTHERMALPOVER.hminimumof2OPERABLEsafetyvalvespersteamgenerator ensuresthatsufficient relieving capacityisavailable forcheallovable THERMALPOVERrestriction inTable3.7-1.STARTUPand/orPOVKROPERATION isallovable vichsafetyvalvesinoperable vithinthelimitacions oftheACTIONrequirements onthebasisofthereduction insecondary syscemsteamflovandTHERMALPOMrequt.red bythereducedreactortripsettingsofthePoverRangeNeutronFluxchannels.

Thereactortripsetpotntreductions arederivedonthefolloving bases:For4loopoperation Where:SPreducedreactzipsecpointinperntofRATEDTHECALPOVER@pe~a.~hahVmaximumnumberofinope~safetyvalvespersteamlineXtotalrelievtncapacityofallstyvalvespezsteamlineinlbours4,2&8,450 Ymaxrelieving capacityofanyonesafealvelbs./hour 857,6909PoverRangeNeutronFlux-High TripSecpointfor4loopoperation COOKNUCLEARPLANT-UNIT2B3/47-1AMENDMENT NO.Sl.134 Relacementtextfor3/4.7.1.1 BasesHil=(100/Q)~(4)vh)Kwhere:Hi4=Safe@Analysis powerrangehighneutronfluxsetpointinpercentQ=NomaalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtK=Contortion factor,947.82~Bto/SecMwtw,=Mimmxmtotalsteamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSI'opening pressureincluding tolerance andaccumulation, asappropriate, inIb/sec.Forexample,iftheaazimumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasumnarion ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating

pressure, exclaKagthehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthm-thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMS'perating
prcssure, excluding thethreehighestcapacityMSSVs.h<<=Heateiivaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappepriate inBtu/IbmI4=Numb'floopsinplantThevaluesahalatedfromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforjumentandchanneluncertainties by9%.Thisrcduccsthcmaximumplantoperating powerlevelsothatitisloserthanthereactorprotection systemsetpointbyanappropriate operating margin.

ATTACHMENT 3TOAEP:NRC:1213A PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES 3/4LIMITINGCONDlTIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITION FOROPERATION 3.7.1.1Allmainsteamlinecodesafetyvalvesassociated witheachsteamgenerator shallbeOPERABLE.

APPLICABILITY:

MODES1,2and3.ACTION:aoMODES1&2:With4reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise, beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatement b.b.MODE3:Withaminimumof3reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s}atbrestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise, beinHOTSHUTDOWNwithinthenext30hours.Theprovisions ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.1.1Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLEinaccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.

4.7.1.2Theprovisions ofSpecification

4.0. 4arenotapplicable

forentryintoMODE3.COOKNUCLEARPLANT-UNIT 1Page3/47-1AMENDMENT 420,444,4' 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLE POWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURING4LOOPOPERATION MaximumNumberofInoperable SafetyValvesonAn0eratinSteamGenerator MaximumAllowable PowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)65.146.528.0COOKNUCLEARPLANT-UNIT 1Page3/47-2 3/4.nBASES3/4.7PLANTSYSTE<MS3/4.7.1TURBINECYCLE3/4.7.1.1 SAFETYVALVESTheOPERABILITY ofthemainsteamlinecodesafetyvalvesensuresthatthesecondary systempressurewillbelimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipated systemoperational transient.

Themaximumrelieving capacityisassociated withaturbinetripfrom100%RATEDTHERMALPOWERcoincident withanassumedlossofcondenser heatsink(i.e.,nosteambypasstothecondenser).

Thespecified valveliftsettingsandrelieving capacities areinaccordance withtherequirements ofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingofJ3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidetheJ1%tolerance.

Thetotalrelieving capacityforallvalvesonallofthesteamlinesis17,153,800 lbs/hrwhichisapproximately 121percentofthetotalsecondary steamflowof14,120,000 Ibs/hrat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvesperoperablesteamgenerator ensuresthatsufficient relieving capacityisavailable fortheallowable THERMALPOWERrestriction inTable3.7-1.STARTUPand/orPOWEROPERATION isallowable withsafetyvalvesinoperable withinthelimitations oftheACTIONrequirements onthebasisofthereduction insecondary systemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.

Thereactortripsetpointreductions arederivedonthefollowing bases:ffso=iannfffi~r(4w&Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=K=hfNominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtConversion factor,947.82~Btu/SecMwtMinimumtotalsteamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inlb/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating

pressure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthree,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
pressure, excluding thethreehighestcapacityMSSVs.Heatofvaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate inBtu/ibm4=NumberofloopsinplantThevaluescalculated fromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties by9%.Thisreducesthemaximumplantoperating powerlevelsothatitislowerthanthereactorprotection systemsetpointbyanappropriate operating margin.COOKNUCLEARPLANT-UNIT 1PageB3/47-1AMENDMENT 420

3/4'IMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITION FOROPERATION 3.7.1.1Allmainsteamlinecodesafetyvalvesassociated witheachsteamgenerator shallbeOPERABLE.

APPLICABILITY:

MODES1,2and3.ACTION:MODES1&2:With4reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise, beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatement b.b.MODE3:Withaminimumof3reactorcoolantloopsandassociated steamgenerators inoperation, andwithoneormoremainsteamlinecodesafetyvalvesassociated withanoperating loopinoperable, operation mayproceedprovidedthatwithin4hours,eithertheinoperable valve(s)arerestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise, beinHOTSHUTDOWNwithinthenext30hours.c.Theprovisions ofSpecification 3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.1.1Eachmainsteamlinecodesafetyvalveshallbedemonstrated OPERABLEinaccordance withSpecification 4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.

4.7.1,2Theprovisions ofSpecification

4.0. 4arenotapplicable

forentryintoMODE3.COOKNUCLEARPLANT-UNIT 2Page3/47-1 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLE POWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURING4LOOPOPERATION MaximumNumberofInoperable SafetyValvesonAnyOperating SteamGenerator MaximumAllowable PowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)61.643.926.2COOKNUCLEARPLANT-UNIT 2Page3/47-2AMENDMENT 3/4'ASES3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLE3/4.7.1.1 SAFETYVALVESTheOPERABILITY ofthemainsteainlinecodesafetyvalvesensuresthatthesecondary systempressurewill'belimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipated systemoperational transient.

Themaximumrelieving capacityisassociated withaturbinetripfrom100%RATEDTHERMALPOWERcoincident withanassumedlossofcondenser heatsink(i.e.,nosteambypasstothecondenser).

Thespecified valveliftsettingsandrelieving capacities areinaccordance withtherequirements ofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingof+3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.

Thetotalrelieving capacityofallsafetyvalvesonallofthesteamlinesis17,153,800 lbs/hrwhichisatleast105percentofthemaximumsecondary steamflowrateat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvespersteamgenerator ensuresthatsufficient relieving capacityisavailable fortheallowable THERMALPOWERrestriction inTable3.7-1.STARTUPand/orPOWEROPERATION isallowable withsafetyvalvesinoperable withinthelimitations oftheACTIONrequirements onthebasisofthereduction insecondary systemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.

Thereactortripsetpointreductions arederivedonthefollowing bases:ffsto=taooft2t

~r(4w&z)Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat)inMwtK=Conversion factor,947.82~Bto/SecMwtw,=Minimumtotalsteamflowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inlb/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating

pressure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVspersteamgenerator isthree,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating
pressure, excluding thethreehighestcapacityMSSVs.h<<=Heatofvaporization forsteamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate inBtu/ibm4=NumberofloopsinplantThevaluescalculated fromthisalgorithm arethenadjustedlowerforuseinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties by9%.Thisreducesthemaximumplantoperating powerlevelsothatitislowerthanthereactorprotection systemsetpointbyanappropriate operating margin.COOKNUCLEARPLANT-UNIT 2PageB3/47-1AMENDMENT 82,434 0I ATTACHMENT 4TOAEP:NRC:1213A WESTINGHOUSE NSAL94-001"OPERATION ATREDUCEDPOWERLEVELSWITHINOPERABLE MSSV'S" I

Westinghouse EnergySystemsBusinessUnitNUCLEARSAF1TYADVISORYLETTER'HISISANOTIHCATION OFARECENTLYIDENTIFIED POTENTIAL SAFETYISSUEPERTAINING TOBASICCOMPONENTS'UPPLIED BYWESTINGHOUSE.

THISINFORMATION ISBEINGPROVIDEDTOYOUSOTHATAREVIEWOFTHISISSUECANBECONDUCEDBYYOUTODETERMINE IFANYACTIONISREQUIRED.

P.O.Box355,Pittsburgh, PA152304355

Subject:

Operation atReducedPowerLevelswithInoperable MSSVsNumbet:NSAL-944)01 BasicComponent:

LossofLoadfi'urbinc TripAnalysisforPlantLicensing BasisDatesOII20$4Plants:SecEnclosedListSubstantial SafetyHazardorFailuretoComplyPursuantto10CFR21.21(a)TransferofInformation Pursuantto10CFR21.21(b)AdvisoryInformation Pursuantto10CFR21.21(c)(2)

SUMMARYYesCiNotlYcs0Ycs0Westinghouse hasidentified apotential safetyissueregarding plantoperation withinTechnical Specification Table3.7-1.Thisissuedoesnotrepresent asubstantial safetyhazardforyourplantpursuantto10CFR21.However,thisissuedoesrepresent acondition whichmayimpactyourplant'slicensing basis.ITable3.7-1allowsplantstooperatewithareducednumberofoperableMSSVsatareducedpowerlevel,asdetermined bythehighneutronQuxtripsetpoint.

ThcFSARlossofload/turbine trip(LOIJIT)analysisfromfullpowerboundsthecasewhereailMSSVsareoperable.

TheFSAR(LOLfIT)eventmaynotbeboundingfortheallowable operating configurations ofTable3.7-1sincethehighneutronfiuxtripsetpojnt, whichisidentified inTable3.7-1foracorresponding numberofinoperable MSSVs,maynotbelowenoughtoprecludeasecondary sideoverpressurization condition.

Asaresult,thebasisforTable3.7-1maynotbesuQicient toprecludeoveipressurization ofthesecondaty sideofthesteamgenerator.

'Therefore, itisrecommended thatyoureviewtheenclosedinformation todeterinine thcapplicability ofthisissuetoyourplant.Theenclosedinfortnation containsamoredetaileddescription oftheissueandidentifies solutions thatyoumaywishtopursuetoaddressthisissue.Thesesolutions include,butarenotlimitedto,areevaluation oftheLOIJITanalysisand/orachangeto~Technical Specification Table3.7-1.Additional information, ifrequired, maybeobtainedfromthcoriginator.

Tclephonc 412-3746460.

Originator.

.W.FasnachtStrategic Licensing IssuesH.A.Scpp,Manager,Strategic Licensing Issuesa%418.wpf:

1b412094

PlantsAffectedD.C.Cook1&2J.M.FarleyI&2Byron1&2Braidwood I&2V.C.SummerIZion1&2ShearonHarrisIW.B.McGuireI&2CatawbaI&2BeaverValleyI&2TurkeyPoint3&4VogtleI&2IndianPoint2&3SeabrookIMillstone 3DiabloCanyonI&2WolfCreekCallawayIComanchePeakI&2SouthTexasI&2SequoyahI&2NorthAnnaI&2WattsBarI&2Size,well BKori1,2,3

&4Yonggwang I&2SalemI&2@%418.wpf:1b411994 II 04 IssueDescritionWestinghouse hasidentified adeficiency inthebasisforTechnical Specification 3.7.1.1.ThisTechnical Specification allowstheplanttooperateatareducedpowerlevelwithareducednumberofoperableMainSteamSafetyValves(MSSVs).Thedeficiency isintheassumption thatthemaximumallowable initialpowerlevelisalinearfunctionoftheavailable MSSVreliefcapacity.

Thelinearfunctionisidentified intheBasesSectionforTechnical Specification 3/4.7.1.1 andisprovidedasfollows:Sp=(X)aO(V)x(i(e)XSP=Reducedreactortripsetpointin%ofRATEDTHERMALPOWERV=Maximumnumberofinoperable safetyvalvespersteamlineX=Totalrelieving capacityofallsafetyvalvespersteamlineinibm/hour(109)=Maximumrelieving capacityofanyonesafetyvalveinIbm/hourPowerrangeneutronflux-high tripsetpointforallloopsinoperation Undercerfainconditions andwithtypicalsafetyanalysisassumptions, aLossofLoad/Drrbine Triptransient frompart-power conditions mayresultinoverpressurization ofthemainsteamsystemwhenoperWnginaccordance withthisTechnical Specification.

'Ihefollowing discussion describes theissueinmoredetailandprovidesrecommended alternatives foraddressing theissue.Technical Evaluation

'IheLossofLoad/Turbine Trip(LOLGT)eventisanalyzedintheFSARtoshowthatcorepro~onmarginsaremaintained (DNBR),theRCSwillnotoverpressurize, andthemainsteamsystemwillnotoveipressurize.

Theanalysisassumesanimmediate lossofsteamrelieving capability throughtheturbineandcoincident lossofallmainfeedwater.

Nocreditistakenforthedirectreactortriponturbinetrip,sincethistripwouldnotbeactuatedforthecaseofalossofsteamload.Rather,thetransient isterminated byareactortriponhighpressurizer

pressure, overtemperature AT,orlowsteamgenerator waterlevel.Secondary sideov'erpressure protection isprovidedbyactuation oftheMainSteamSafetyValves(MSSVs),whicharedesignedtorelieveatleastfullpowernominalsteamflow.'IlieanalysisverifiesthattheMSSVcapacityissufficient topreventsecondary sidepressurefimm.exceeding 110percentofthedesignpressure.

0%418.vq>f:tb411994

TheFSARonlyanalyzestheLOIJITtransient GomtheMpowerinitialcondition, withcasesexamining theeffectsofassumingprimarysidepressurecontrolanddifferent reactivity feedbackconditions.

Withfullyoperational MSSVs,itcanbedemonstrated thatoverpressure protection isprovidedforallinitialpowerlevels.However,formostplants,Technical Specification 3.7.1.1allowsoperation withareducednumberofoperableMSSVsatareducedpowerlevelasdetermined byresetting thepowerrangehighneutronfiuxsetpoint.

ThisTechnical Specification isnotbasedonadetailedanalysis, butratherontheassumption thatthemaximumallowable initialpowerlevelisalinearfunctionoftheavailable MSSVreliefcapacity.

Recently, ithasbeendetermined thatthisassumption isnotvalid.'Iheproblemisthatifmainfeedwater islost,areactortripisnecessary topreventsecondary sideoverpressurization forallpostulated coreconditions.

Athighinitialpowerlevelsareactortripisactuatedearlyinthetransient as.aresultofeitherhighpressurizer pressureorovertemperature hT.Thereactortripterminates thetransient andtheMSSVsmaintainsteampressurebelow110%ofthedesignvalue.Atlowerinitialpowerlevelsareactortripmaynotbeactuatedearlyinthetransient.

Anovertempeiature hTtripisn'tgenerated sincethecorethermalmarginsareincreased atlowerpowerlevels.Ahighpressurizer pressuretripisn'tgenerated iftheprimarypressurecontrolsystemsfunctionnormally.

Thisresultsinalongertimeduringwhichprimaryheatistransferred tothesecondary side.'Ihereactoreventually, tripsonlowsteamgenerator waterlevel,butthismaynotoccurbeforesteampressureexceeds110%ofthedesignvalueifoneormoreMSSVsareinoperable inaccordance withtheTechnical Specification.

Duetothewidevarietyofplantdesignfeaturesthatareimportant totheLOIJITanalysis, itisdifficult toperformagenericevaluation toshowthattheissuedoesnotapplytocertainplants.Thefollowing keyparameters haveasignificant effectonthesecondary sidepressuretransient MSSVreliefcapacityModerator Temperature Coefficient (MTC)MarginbetweentheMSSVsetpressures (including tolerance) andtheoverpressure limitLow-lowsteamgenerator waterlevelreactortripsetpointSafetSinificance TheTechnical Specifications formostplantsallowoperation atareducedpowerlevelwithinoperable MSSVs.Fromalicensing basisperspective, thiscondition mayresultinsecondary sideoverpressurization intheeventofaLOIJITtransient.

Thelicensing basisforanticipated operational occurrences (ANSCondition IIevents)typically requiresthatthesecondary sideprcssureremainbelow110%ofthedesignvalue.a%418.wpf:

Ib411994 Westinghouse hasdetermined thatthisissuedoesnotrepresent asubstantial safetyhazard.Thereareseveralmitigating factorswhichprovideassurance thatthereisnolossofsafetyfunctiontotheexteatthatthereisamajorreduction inthedegreeofprotection providedtothepublichealthandsafety.Theseinclude,butarenotlimitedto,thefollowing:

1.Adequateoverpressure protection isprovidedatallpowerlevelsifalloftheMSSVsareoperable.

2.Ifareactortripdoesnotoccurbutmainfeedwater fiowismaintained, operation inaccordance withtheTechnical Specification Table3.7-1willnotresultinanoverpressure condition.

3.InanyLOIJITtransient, theatmospheric steamdumpvalvesand/orcondenser steamdumpvalvesactuatetorelieveenergyiromthesteamgenerators priortotheopeningoftheMSSVs,andcontinuetorelievesteamiftheMSSVsdoopen.Sinceitisnotasafety-grade

function, steamdumpisnotassumedtooperateinthesafetyanalysis; however,inrealityitisthefirstlineofdefenseinprotecting thesecondary systemagainstoverpressurizatioa.

Itisveryimprobable thatallthesecompoaents wouldbeinoperable coincident withinoperable MSSVs.4.Evennearthebeginning ofcorelifewithapositiveorzeroMTC,theprimaryvolantheatupresulting fromthetransient wouldtendtodrivethehGCnegative, whichwould.reducethecorepoweraadheatinputtothecoolaat.Thiswouldresultin'alowerrequiredMSSVcapacitytopreventsecondary ovegressurization.

Thesafetyanalysisdoesnotcreditthereduction ofMTCduringthetransient.

NRCAwareness IReortabilit Westinghouse hasnotnotifiedtheNRCofthisissue,baseduponthedetermination thatitdoesaotrepresent asubstantial safetyhazardpursuantto10CFR21.However,Westinghouse willsendacopyofthislettertotheNRCsincethisissueimpactsinformation contained inNUREG-1431, "Standard Technical Specifications, Westinghouse Plants".Recommendations Toaddressthisissue,thefollowing actionsmaybeconsidered:

(1)ModifyTechaical Specificatioa 3.7.1.1(orequivalent) andtheassociated basissuchthatthemaximumpowerlevelallowedforoperation withinoperable MSSVsisbelowtheheatremovingcapability oftheoperableMSSVs.Aconservative waytodothisistosetthepowerrangehighaeutmnfiuxsetpointtothispowerlevel,thusensuringthattheactualpowerlevelcannotexceed@%418.wpf:1b411994

~~thisvalue.Tocalculate thissetpoint, thegoverning equationistherelationship q=mhh,whereqistheheatinputfmmtheprimaryside,misthesteamflowrateandhhistheheatofvaporization atthesteamreliefpressure(assuming nosubcooled fecdwater).

Thus,analgorithm foruscindefiningtherevisedTechnical Specification tablesetpointvalueswouldbe:Hig=(100/Q)~(wPN)Kwhere:'ig=SafetyAnalysispowerrangehighneutronfluxsetpoint, percentQ=NominalNSSSpowerratingoftheplant(including reactorcoolantpumpheat),MwtK=Conversion factor,947.82MwtwsMinimumtotalsteamlowratecapability oftheoperableMSSVsonanyonesteamgenerator atthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, inib/sec.Forexample,ifthemaximumnumberofinoperable MSSVsonanyonesteamgenerator isone,thenw,shouldbeasummation ofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperating

prcssure, excluding thehighestcapacityMSSV.Ifthemaximumnumberofinoperable MSSVsperstcamgenerator isthreethenw,shouldbeasummation ofthecapacityofthcoperableMSSVsatthehighestoperableMSSVoperating
prcssure, excluding thethreehighestcapacityMSSVs.h+=heatofvaporization forstcamatthehighestMSSVopeningpressureincluding tolerance andaccumulation, asappropriate, Btu/1bmN=Numberofloopsin plantThevaluescalculated fromthisalgorithm mustthenbeadjustedlowerforuscinTechnical Specification 3.7.1.1toaccountforinstrument andchanneluncertainties (typically 9%power).Themaximumplantoperating powerlevelwouldthenbelowerthanthereactorprotection systemsetpointbyanappropriate operating margin.0%418.wpf:

1b411994 kk

~y~0C~c.Itshouldbenotedthattheuscofthisequatioawillresolvetheissueideatified inthisletterbyeaablingyoutore~culate yourTechnical Specification 3.7.1.1setpoints withoutfurthermodifications tothestructure oftheTcchnical Specification.

There-calculated setpoints arelikelytobelowerthanthosecurrently allowedbytheTechaical Specification.

However,youshouldbeawareofatleasttwoconscrvatisms withtheequationYoumaywishtoreviewtheseconservatisms toevaluatetheuseoftheequationrelativetoyourplantspecificoperating objectives.

Itispossibletorelaxsomeoftheseconservatisms foruseintheTechnical Specificatioa However,relaxation oftheconservatisms arelikelytoresultinmoresignificant changestothestructure oftheTechnical Spccificatioa First,theaboveequatioa(andtheexistingTechaical Specification 3.7.1.1)isconservative sinceitisbasedonthemaximumnumberofinoperable MSSVsperloop.Forexample,arepresentative fourloopplant,inaccordance withthecurrentTechnical Specification, shouldreduce'he neutronfluxsetpointto87%ifithasuptooneinoperable MSSVoneachloop.Thismeansthattheplantshouldusethissetpointwhetherthereareone,two,threeorfourinoperable MSSVs,aslongasthereisonlyoneinoperable MSSVpcrloop.Thus,theexistingTechnical Specification andtheaboveequationareconservative andbounding.

However,anyrelaxation ofthisconservatism mustbeinterpreted withcare.Thereasonisthatthesteamgenerators mustbeprotcctcd 6'omanovcrpressurization condition duringalossofloadtransient.

'I%ereareseveraleventsthatcouldleadtoalossofload,including theinadvertent closureofoneorallMSIVs.Theaffectedsteamgenerator musthaveasufficient numberofoperableMSSVstoprotectitfromanoverpressurizatioa condition, iftheMSIV(orMSIVs)wasiaadvertently closed.Anotherconservatism intheaboveequation(andtheexistingTechnical Specification 3.7.1.1)isinwwhichistheminimumtotalsteamQowratecapability oftheoperableMSSVsonanyonesteamgenerator.

Thisvalueisconservative sinceitassumesthatifoneormoreMSSVsareinoperable perloop,theinoperable MSSVsarethelargestcapacityMSSVs,regardless ofwhetherthelargestcapacityMSSVsorthesmallercapacityMSSVsareinoperable.

Theassumption hasbeenmadesothattheaboveequationisconsistent withthecurrentstructure ofTechnical Specification 3.7.1.1.(2)Asanalternative, plant-specific LOIJITanalysescouldbeperformed tomaximizetheallowable power.level foragivennumberofinoperable MSSVs.Depending onkeyspecificplantparameters, theseanalysesmaybeabletojustifythecoatinued validityofthecurrentTechnical Specificatioa (3)Considermodifying, asrequired, theBasesSectionforTechaical Specification 3/4.7.1.1 sothat.itisconsistent withtheplantsafetyanalysis.

Thesafetyanalysiscriterion forpreventiag ovciprcssurization ofthesecondary sideisthattheprcssuredoesnotexceed110%ofthedesignpessureforanticipated transients.

However,inreviewing severalplanttechaical specifications, a%418.wpf:

tbsp11994 itwasnotedthatthebasesforsomeplantsstatethatthesafetyvalvesinsurethatthesecondary systempressurewillbelimitedtowithin10Soreven100%%uoofdesignprcssure.

Thisisnotconsistent withthesafetyanalysisbasisandshouldberevisedtoindicate110%.@%418.vg)f:1b411994

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