ML17334B595

From kanterella
Revision as of 07:17, 29 June 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17334B595
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/11/1996
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17333A496 List:
References
NUDOCS 9607150009
Download: ML17334B595 (220)
v • d • e


Text

PROPOSEDCHANGESTOTHECOOKNUCLEARPLANTUNITNO.1TECHNICAL SPECIFICATIONS VSO7i50009 9SO7iaPDRADOCK050003i5PPDR

)f' 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSAFETYVALVES-SHUTDOWNUMITINGCONDITION FOROPERATION 3.4.2Aminimumofonepressurizer codesafetyvalveshallbeOPERABLEwithaliftsettingof2485PSIG+3%.APPLICABILITY:

MODES4and5.ACTION:Withnopressurizer codesafetyvalveOPERABLE:

'8a.Immediately suspendalloperations involving positivereactivity changesandplaceanOPERABLERHRloopintooperation intheshutdowncoolingmode.b.Immediately renderallSafetyInjection pumpsandallbutonechargingpumpinoperable byremovingtheapplicable motorcircuitbreakersfromtheelectricpowercircuitwithinonehour.SURVEILLANCE REUIREMENTS 4.4.2Thepressurizer codesafetyvalveshallbedemonstrated OPERABLEperSurveillance Requirement 4.4.3.Thepressurizer codesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.

Theliftsettingpressureshallcorrespond toambientconditions ofthevalveatnominaloperating temperature andpressure.

Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbySpecification 3.1.2.8.b.2 (MODE4)or3.1.2.7.b.2 (MODE5).COOKNUCLEARPLANT-UNIT 1Page3/444AMENDMENT

&,4A, 3/4LIMI'HNGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSAFETYVALVES-OPERATING LIMITINGCONDITION FOROPERATION 3.4.3Allpressurizer codesafetyvalvesshallbeOPERABLEwithaliftsettingof2485PSIG+3%.>>APPLICABILITY:

MODES1,2and3.ACTION:Withonepressurizer codesafetyvalveinoperable, eitherrestoretheinoperable valvetoOPERABLEstatuswithin15minutesorbeinHOTSHUTDOWNwithin12hours.SURVEILLANCE REUIREMENTS 4.4.3Noadditional surveillance requirements otherthanthoserequiredbySpeciTication 4.0.5.Thepressurizer codesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.

Theliftsettingpressureshallcorrespond toambientconditions ofthevalveatnominaloperating temperature andpressure.

COOKNUCLEARPLANT-UNIT IPage3/44-5AMENDMENT 440,444,

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSCONDENSATE STORAGETANKLIMITINGCONDITION FOROPERATION 3.7.1.3Thecondensate storagetank(CST)shallbeOPERABLEwithaminimumuseablevolumeof175,000gallonsofwater.APPLICABILITY:

MODES1,2and3.ACTION:Withthecondensate storagetankinoperable, within4hourseither:RestoretheCSTtoOPERABLEstatusorbeinHOTSHUTDOWNwithinthenext12hours,orDemonstrate theOPERABILITY oftheEssential ServiceWaterSystemasabackupsupplytotheauxiliary feedwater pumpsandrestorethecondensate storagetanktoOPERABLEstatuswithin7daysorbeinHOTSHUTDOWNwithinthenext12hours.SURVEILLANCE REUIREMENTS 4.7.1.3.1 4.7.1.3.2 Thecondensate storagetankshallbedemonstrated OPERABLEatleastonceper12hoursbyverifying theuseablewatervolumeiswithinitslimitswhenthetankisthesupplysourcefortheauxiliary feedwater pumps.TheEssential ServiceWaterSystemshallbedemonstrated OPERABLEatleastonceper12hoursbyverifying thattheEssential ServiceWaterSystemisinoperation whenevertheEssential ServiceWaterSystemisthesupplysourceiortheauxiliary feedwater pumps.COOKNUCLEARPLANT-UNIT 1Page3/47-7AIKNDMENT 3/4BASES3/4.6CONTAINMENT SYSTEMS3/4.6.1.4 INTERNALPRESSUREThelimitations oncontainment internalpressureensurethat1)thecontainment structure isprevented fromexceeding itsdesignnegativepressuredifferential withrespecttotheoutsideatmosphere of8psigand2)thecontainment peakpressuredoesnotexceedthedesignpressureof12psigduringLOCAconditions.

Themaximumpeakpressureresulting fromaLOCAeventiscalculated tobelessthanthedesignlimitof12psig,whichincludes0.3psigforinitialpositivecontainment pressure.

3/4.6.1.5 AIRTEMPERATURE Thelimitations oncontainment averageairtemperature ensurethat1)thecontainment airmassislimitedtoaninitialmasssufficiently lowtopreventexceeding thedesignpressureduringLOCAconditions and2)theambientairtemperature doesnotexceedthattemperature allowable forthecontinuous dutyratingspecified forequipment andinstrumentation locatedwithincontainment.

Thecontainment pressuretransient issensitive totheinitially contained airmassduringaLOCA.Thecontained airmassincreases withdecreasing temperature.

Thelowertemperature limitof60'Fwilllimitthepeakpressuretolessthanthecontainment designpressureof12psig.Theuppertemperature limitinfluences thepeakaccidenttemperature slightlyduringaLOCA;however,thislimitisbasedprimarily uponequipment protection andanticipated operating conditions.

Boththeupperandlowertemperature limitsareconsistent withtheparameters usedintheaccidentanalyses.

3/4.6.1.6 CONTAINMENT VESSELSTRUCTURAL INTEGRITY Thislimitation ensuresthatthestructural integrity ofthecontainment steelvesselwillbemaintained comparable totheoriginaldesignstandards forthelifeofthefacility.

Structural integrity isrequiredtoensurethat(1)thesteellinerremainsleaktightand(2)theconcretesurrounding thesteellinerremainscapableofproviding externalmissileprotection forthesteellinerandradiation shielding intheeventofaLOCA.Avisualinspection inconjunction withTypeAleakagetestsissufficient todemonstrate thiscapability.

COOKNUCLEARPLANT-UNIT 1PageB3/46-2

3/4BASES3/4.7PLANTSYSTEMS3/4.7.1.3 CONDENSATE STORAGETANKTheOPERABILITY ofthecondensate storagetankwiththeminimumwatervolumeensuresthatsufficient waterisavailable tomaintaintheRCSatHOTSTANDBYconditions for9hourswithsteamdischarge totheatmosphere concurrent withtotallossofoff-sitepower.Theuseablewatervolumelimitreflectsthevolumeofwaterabovethecenterline ofthedischarge pipe.Anallowance forwaternotuseablebecauseoftankdischarge linelocationorotherphysicalcharacteristics isnotrequired.

3/4.7.1.4 ACTIVITYThelimitations onsecondary systemspecificactivityensurethattheresultant off-siteradiation dosewillbelimitedtoasmallfractionof10CFRPart100limitsintheeventofasteamlinerupture.Thisdosealsoincludestheeffectsofacoincident

1.0 gpmprimarytosecondary

tubeleakinthesteamgenerator oftheaffectedsteamline.Thesevaluesareconsistent withtheassumptions usedintheaccidentanalyses.

3/4.7.1.5 STEAMGENERATOR STOPVALVESTheOPERABILITY ofthesteamgenerator stopvalvesensuresthatnomorethanonesteamgenerator willblowdownintheeventofasteamlinerupture.Thisrestriction isrequiredto1)minimizethepositivereactivity effectsoftheReactorCoolantSystemcooldownassociated withtheblowdown, and2)limitthepressurerisewithincontainment intheeventthesteamlineruptureoccurswithincontainment.

TheOPERABILITY ofthesteamgenerator stopvalveswithintheclosuretimesofthesurveillance requirements areconsistent withtheassumptions

'sedintheaccidentanalysesWithonesteamgenerator stopvalveinoperable inMODEI,actionmustbetakentorestoreOPERABLEstatuswithin8hours.Somerepairstothevalvescanbemadewiththeunithot.The8hourcompletion timeisreasonable, considering thelowprobability ofanaccidentoccurring duringthistimeperiodthatwouldrequireaclosureofthesteamgenerator stopvalves.Ifthesteamgenerator stopvalvecannotberestoredtoOPERABLEstatuswithin8hours,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,the.unitmustbeplacedinMODE2within6hoursandtheMODES2and3actionstatement entered.Thecompletion timesarereasonable, basedonoperating experience, toreachMODE2andtoclosethesteamgenerator stopvalvesinanorderlymannerandwithoutchallenging unitsystems.Sincethesteamgenerator stopvalvesarerequiredtobeOPERABLEinMODES2and3,theinoperable valvesmayeitherberestoredtoOPERABLEstatusorclosed.Whenclosed,thevalvesarealreadyinthepositionrequiredbytheassumptions inthesafetyanalysis.

The8hourcompletion timeisconsistent withtheMODE1actionstatement requirement.

Forinoperable steamgenerator stopvalvesthatcannotberestoredtoOPERABLEstatuswithinthespecified completion time,butareclosed,theinoperable valvesmustbeverifiedonaperiodicbasistobeclosed.Thisisnecessary toensurethattheassumptions inthesafetyanalysisremainvalid.The7daycompletion timeisreasonable, basedonengineering judgement, inviewofsteamgenerator stopvalvestatusindications available inthecontrolroom,andotheradministrative

controls, toensurethatthesevalvesareintheclosedposition.

IfinMODES2or3thesteamgenerator stopvalvescannotberestoredtoOPERABLEstatusorarenotclosedwithintheassociated completion time,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,theunitmustbeplacedatleastinMODE3within6hours,andinMODE4within12hours.Theallowedcompletion timesarereasonable, basedonoperating experience, toreachtherequiredunitconditions fromMODE2conditions inanorderlymannerandwithoutchallenging unitsystems.COOKNUCLEARPLANT-UNIT 1PageB3/47-3AMENDMENT

$Q,48$

Thispageintentionally leftblankCOOKNUCLEARPLANT-UNIT IPage83/47-3a f

PROPOSEDCHANGESTOTHECOOKNUCLEARPLANTUNITNO.2TECHNICAL SPECIFICATIONS fh

1.0 DEFINITIONS

DEFINEDTERMS1.1TheDEFINEDTERMSofthissectionappearincapitalized typeandareapplicable throughout theseTechnical Specifications.

THERMALPOWER1.2THERMALPOWERshallbethetotalreactorcoreheattransferratetothereactorcoolant.RATEDTHERMALPOWER1.3RATEDTHERMALPOWERshallbeatotalreactorcoreheattransferratetothereactorcoolantof3588MWt.OPERATIONAL MODE1.4AnOPERATIONAL MODEshallcorrespond toanyoneinclusive combination ofcorereactivity condition, powerlevelandaveragereactorcoolanttemperature specified inTable1.1.ACTION1.5ACTIONshallbethoseadditional requirements specified ascorollary statements toeachprinciple specification andshallbepartofthespecifications.

OPERABLE-OPERABILITY 1.6Asystem,subsystem, train,component ordeviceshallbeOPERABLEorhaveOPERABILITY whenitiscapableofperforming itsspecified function(s).

Implicitinthisdefinition shallbetheassumption thatallnecessary attendant instrumentation,

controls, normalandemergency elecuical powersources,coolingorsealwater,lubrication orotherauxiliary equipment thatarerequiredforthesystem,subsystem, train,component ordevicetoperformitsfunction(s) arealsocapableofperforming theirrelatedsupportfunction(s).

COOKNUCLEARPLANT-UNIT 2Page1-1 0',

2.0SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETI1NGS660650-~640-8630:-OQ>620-I610-'400PSIA2250PSI2100PSI2000600-1775PSIA"590-580.-570'0,20.40.6FRACTIONOFTHERMAIPOWERt8588MWI1.0)0.81.2Pressure(psia)Power(frac)DescritionofSafeLimitsav~PowerTav~PowerTav~PowerTave('FJ(frac)(FII(frac)('Fj(frac)('Fj17750.00615.11.1020000.00632.21.1221000.00639.21.0822500.00649.41.0224000.00659.00.96FlowRate=91,600gpm/loop580.01.18577.41.2,576.4597.61.14596.01.2589A606.51.10604.81.2593.5619.51.10610.91.2599.7631.91.1616.71.2605.7Figure2.1-1ReactorCoreSafetyLimitsFourLoopsinOperations COOKNUCLEARPLANT-UNIT 2Page2-2AMENDMENT 2,4Ã,434,

2.0 SAggYLIMITSANDLHVIrrING

SAFEIYSYSTEMSETTINGSTABLE2.2-1REACTORTRIPSYSTEMINSTRUMENTATION TRIPSETPOINTS FUNCTIONAL UNITl.ManualReactorTrip2.PowerRange,NeutronFluxTRIPSETPOINTNotApplicable LowSetpoint-Lessthaaorequalto25%ofRATEDTHERMALPOWERALLOWABLE VALUESNotApplicable LowSetpoint-Lessthanorequalto26%ofRATEDTHERMALPOWER3.PowerRange,NeutronFlux,HighPositiveRate4.PowerRaagc,NeutroaFlux,HighNegativeRate5.Intermediate Range,NeutronFlux6.SourceRange,NeutronFlux7.Overtemperature DeltaT8.Overpower DeltaTHighSetpoint-Lessthanorequalto109%ofRATEDTHERMALPOWERLessthanorequalto5%ofRATEDTHERMALPOWERwithatimeconstantgreaterthanorequalto2secondsLessthanorequalto5%of,.RATEDTHERMALPOWERwithatimeconstaatgreaterthaaorequalto2secondsLessthaaorequalto25%ofRATEDTHERMALPOWERLessthaaorequalto10couatspersecondSecNote1SeeNote2HighSetpoint-Lessthanorequalto110%ofRATEDTHERMALPOWERLessthanorequalto5.5%ofRATEDTHERMALPOWERwithatimeconstantgreaterthanorequalto2secondsLessthanorequalto5.5%ofRATEDTHERMALPOWERwithatimeconstantgreaterthanorequalto2secondsLessthanorequalto30%ofRATEDTHERMALPOWERLessthaaorequalto1.3x10countspcrsecondSeeNote3SeeNote4Pressurizer Pressure-Low10.Pressurizer Pressure-HighGreaterthanorequalto1950psigGreaterthanorequalto1940psigLessthanor.equalto2385psigLessthanorequalto2395psig11.Pressurizer WaterLcvel--High12.LossofFlowLessthanorequalto92%ofInstrument spanGreaterthanorequalto90%ofdesignflowperloop~Lessthanorequalto93%ofinstrument spanGreaterthanorequalto89.1%ofdesignflowperloop~DesignflowisI/4ReactorCoolantSystemtotalflowratefromLCO3.2.5.COOKNUCLEARPLANT-UNIT 2Page2-5AMENDMENT A,434,

2.0SAFETYLIMITSANDLIMI'IINGSAFETYSYSTEMSEXI'INGS TABLE2.2-1Continued REACTORTRIPSYSTEMINSTRUMENTATION TRIPSETPOINTS NOTATIONI+%'sNote1:Overtemperature hT6hT[K-Ka[-](T-T')+Ks(P-P')-f(~01o'+~st2where:EToIndtcated 6TatRATEDTHERMALPOWERT=Averagetemperature,

'FT=Indicated T>>gatRATEDTHERMALPOWERlessthanorequalto581.3'F.P=Pressurizer

Pressure, psigP=Indicated RCSnominaloperating pressure(2235psigor2085psig).I+tsI+~asThefunctiongenerated bythelead-lagcontroller forTavgdynamiccompensation s~a~Timeconstants utilizedinthelead-Iagcontroller forTavg,'t22secs,T>4secsS=Laplacetransform operatorCOOKNUCLEARPLANT-UNIT 2Page2-7AMENDMENT A,434,

2.0SAFEIYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGSkTABLE2.2-1Continued REACTORTRIPSYSTEMINSTRUMENTATION TRIPSETPOINTS NOTATIONS Continued KI=1.17K2=0.0268K3=0.00111andfi(dI)isafunctionoftheindicated difference betweentopandbottomdetectors ofthepower-range nuclearionchambers; withgainstobeselectedbasedonmeasuredinstrument responseduringplantstartuptestssuchthat:(i)Forqt-qbbetween-16percentand+6percent,fl(hl)=0(whereq,andqbarepercentRATEDTHERMALPOWERinthetopandbottomhalvesofthecorerespectively, andq,+qbistotalTHERMALPOWERinpercentofRATEDTHERMALPOWER).(ii)Foreachpercentthatthemagnitude of(q,-qb)exceeds-16percent,theITtripsetpointshallbeautomatically reducedby2.05percentofitsvalueatRATEDTHERMALPOWER.(iii)Foreachpercentthatthemagnitude of(qt-qb)exceeds+6percent,thehTtripsetpointshallbeautomatically reducedby2.7percentofitsvalueatRATEDTHERMALPOWER.COOKNUCLEARPLANT-UNIT 2Page24AMENDMENT 82,434, 2.0SAFETYLIKGTSANDLIMI'IONG SAFETYSYSTEMSEIfPIGSTABLE2.2-1Continued REACTORTRIPSYSTEMINSTRUMENTATION TRIPSETPOINTS NOTATIONS Continued c>SNote2:Overpower 4T64ToPC,-Ks[-]T-Ks(T-T")-f(41)]'"3where:4ToIndicated 4TatratedpowerAveragetemperature,

'FhdicatedT>>gatRATEDTHERMALPOWERlessthanorequalto576'F.1.08K50.02/'Fforincreasing averagetemperature and0fordecreasing averagetemperature 0.00197forTgreaterthanT;K6=0forTlessthanorequaltoTv>S(I+s>S)Thehactiongeneratebytheratelagconuoller forTavgdy'ccompnsanon+3Timeconstantutilizedintheratelagcontroller forTa<<,T3-"10secs,S=Laplacetransform operatorf2(4I)=0.0Note3:Thechannel's maximumtrippointshallnotexceeditscomputedtrippointbymorethan3.75percent4Tspan.Note4:Thechannel's maximumtrippointshallnotexceeditscomputedtrippointbymorethan2.59percent4Tspan.COOKNUCLEARPLANT-UNIT 2Page2-9AMENDMENT Sl,434, tfd 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.2POWERDISTRIBUTION LIMITSDNBANDTavOPERATING PARAMETERS LIMITINGCONDITION FOROPERATION 3.2.5Thefollowing DNBrelatedparameters shallbemaintained withinthefollowing operational indicated limits:1.ReactorCoolantSystemT>>gLessthanorequalto583.3'F2.Pressurizer Pressure3.ReactorCoolantSystemTotalFlowRateGreaterthanorequalto2200psig(fornominalpressureof2235psig)/Greaterthanorequalto2050psig(fornominalpressureof2085psig)/Greaterthanorequalto366,400gpmAPPLICABILITY:

MODE1ACTION:Withanyoftheaboveparameters exceeding itslimit,restoretheparameter towithinitslimitwithin2hoursorreduceTHERMALPOWERtolessthan5%ofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCE REUIREMENTS 4.2.5.14.2.5.24.2.5.34.2.5AEachoftheaboveparameters shallbeverifiedtobewithintheirlimitsatleastonceper12hours.Theindicators usedtodetermine RCStotalflowshallbesubjected toaCHANNELCALIBRATION atleastonceper18months.TheRCStotalflowrateshallbedetermined byapowerbalancearoundthesteamgenerators atleastonceper18months.Theprovisions ofSpecification 4.0.4shallnotapplytoprimaryflowsurveillances.

Indicated averageofatleastthreeOPERABLEinstrument loops.Limitnotapplicable duringeitheraTHERMALPOWERrampinexcessof5%ofRATEDTHERMALPOWERperminuteoraTHERMALPOWERstepinexcessof10%ofRTPIndicated valueCOOKNUCLEARPLANT-UNIT 2Page3/42-15AMENDMENT A,434, 3/4LIMlTINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE3.34ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION TRIPSETPOINTS FUNCTIONAL UNITl.SAFETYINJECTION, TURBINETRIP,FEEDWATER ISOLATION, ANDMOTORDRIVENAUXILIARY FEEDWATER PUMPSTRIPSETPOINTS ALLOWABLE VALUESa.ManualInitiation b.Automatic Actuation LogicNotApplicable SecFunctional Unit9NotApplicable c.Containment Pressure-HighLessthanorequalto1.1psigLessthanorequalto1.2psigd.Pressurizer Pressure-LowGreaterthanorequalto1815psigGreaterthanorequalto1805psige.Differential PressureBetweenSteamLines-Highf.StcamLinePressure-LowLessthanorequalto100psiGreaterthanorequalto500psigsteamlincpressureLessthanorequaltoto112psiGreaterthanorequalto480psigsteamlineprcssureCOOKNUCLEARPLANT-UNIT 2Page3/43-23AMENDMENT 4;44,&,434,~,

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.3INSTRUMENTATION TABLE3.3CContinued ENGINEERED SAFETYFEATUREACTUATION SYSTEMINSTRUMENTATION TRIPSETPOINTS FUNCTIONAL UNIT4.STEAMLINEISOLATION TRIPSETPOINTS ALLOWABLE VALUESa.Manualb.Automatic Actuation Logicc.Containment Pressure-High-High NotApplicable Lessthanorequalto2.9psigNotApplicable Lessthanorequalto3.0psig-----SeeFunctional Unit9------d.SteamFlowinTwoSteamLines-HighCoincident withTavg-Low-LowLessthanorequaltoafunctiondefinedasfollows:ADelta-pcorresponding to1.6x106lbs/hrsteamflowbetween0%and20%loadandthenaDelta-pincreasing linearlytoaDelta-pcorresponding to4.5x10lbs/hratfullload.Lessthanorequaltoafunctiondefinedasfollows:ADelta-pcorresponding to1.75x10lbs/hrsteamflowbetween0%and20%loadandthenaDelta-pincreasing linearlytoaDelta-pcorresponding to4.55x10Ibs/hratfullload.T>>greaterthanorequalto541FTaygreaterthanorequalto539Fe.SteamLinePressure-LowGreaterthanorequalto500psigGreaterthanorequalto480steamlinepressurepsigsteamlinepressure5.TURBINETRIPANDFEEDWATER ISOLATION a.SteamGenerator WaterLevelLessthanorequalto67%of-High-High narrowrangemtrumentspaneachsteamgenerator Lessthanorequalto68%ofnarrowrangeinstrument spaneachsteamgenerator COOKNUCLEARPLANT-UNIT 2Page3/43-25AMENDMENT A,408,434,~,

,t 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEMSAFETYVALVES-SHUTDOWNLIMITINGCONDITION FOROPERATION 3.4.2Aminimumofonepressurizer codesafetyvalveshallbeOPERABLEwithaliftsettingof2485PSIG23%.APPLICABILITY:

ACTION:MODES4and5.Withnopressurizer codesafetyvalveOPERABLE:

a.,Immediately suspendalloperations involving positivereactivity changes*~

andplaceanOPERABLERHRloopintooperation intheshutdowncoolingmode.b.Immediately renderallSafetyInjection pumpsandallbutonechargingpumpinoperable byremovingtheapplicable motorcircuitbreakersfromtheelectrical powercircuitwithinonehour.SURVEILLANCE REUIREMENTS 4.4.2Noadditional Surveillance Requirements otherthanthoserequiredbySpecification 4.0.5.'IThepressurizer codesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.

Theliftsettingpressureshallcorrespond toambientconditions ofthevalveatnominaloperating temperature andpressure.

Forpurposesofthisspecification, additionofwaterfromtheRWSTdoesnotconstitute adilutionactivityprovidedtheboronconcentration intheRWSTisgreaterthanorequaltotheminimumrequiredbyspecification 3.1.2.8.b.2 (MODE4)or3.1.2.7.b.2 (MODE5).COOKNUCLEARPLANT-UNIT 2Page3/444AMENDMENT

&,4P,

3/4LIMINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUDKMENTS 3/4,4REACTORCOOLANTSYSTEMSAFETYVALVES-OPERATING LIMITINGCONDITION FOROPERATION 3.4.3Allpressurizer codesafetyvalvesshallbeOPERABLEwithaliftsettingof2485PSIG+3%.~>>APPLICABILITY:

MODESI,2and3.ACTION:Withonepressurizer codesafetyvalveinoperable, eitherrestoretheinoperable valvetoOPERABLEstatuswithin15minutesorbeinHOTSHUTDOWNwithin12hours.SURVEILLANCE REUIREMENTS 4.4.3Noadditional Surveillance Requirements otherthanthoserequiredbySpecification 4.0.5.Thepressurizer codesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidetheJ1%tolerance.

Theliftsettingpressureshallcorrespond toambientconditions ofthevalveatnominaloperating temperature andpressure.

COOKNUCLEARPLANT-UNIT 2Page3/44-5

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIIKMENTS 3/4.4REACTORCOOLANTSYSTEMLIMITINGCONDITIONS FOROPERATION Continued SURVEILLANCE REUIREMENTS 4.4.6.2.1 ReactorCoolantSystemleakagesshallbedemonstrated tobewithineachoftheabovelimitsby:Monitoring thecontainment atmosphere particulate radioactivity monitoratleastonceper12hours.b.Monitoring thecontainment sumpinventory anddischarge atleastonceper12hours.C.Determining theseallineresistance atleastonceper31dayswhentheaveragepressurizer pressureiswithin20psiofitsnominalfullpressurevalue.Theseallineresistance measuredduringthesurveillance mustbegreaterthanorequalto2.27E-1ft/gpm'.Theseallineresistance, R<<,isdetermined fromthefollowing expression:

2.31(P,p

-P<<)stqswhere:Pcia,=chargingpumpheaderpressure, psigP<<=2112psig(Iowpressureoperation)

=2262psig(highpressureoperation) 2.31=conversion factor(12in/ft)t/(62.3 Ib/fthm)Q=thetotalsealinjection flow,gpmTheprovisions ofSpecification

4.0. 4arenotapplicable

forentryintoMODES3and4.d.Performance ofaReactorCoolantSystemwaterinventory balanceatleastonceper72hoursduringsteadystateoperation, ande.Monitoring thereactorheadflangeleakoffsystematleastonceper24hours.4.4.6.2.2 Eachreactorcoolantsystempressureisolation valvespecified inTable3.4-0shallbedemonstrated OPERABLEpursuanttoSpecification 4.0.5.COOKNUCLEARPLANT-UNIT 2Page3/44-16AMENDMENT 446,474, tIli 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIRElVQMIS 3/4.4REACTORCOOLANTSYSTEM2600240022002000(918001600g1400120001000o0o~800REACTORCOOLANTSYSTEMHEATUPLIMITATIONS APPLICABLE FORFIRST14.5EFFECTIVE FULLPOWERYEARS(MARGINSOF60PSIGAND10'FAREINCLUDEDFORPOSSIBLEINSTRUMENT ERROR)LEAKlESTuMrrMATERIALPROPERTYBASISINTERMEDIATE PLATE,2C&.15%i&.57%INITNLRTIIor'F14.5EFPYRTII0T(1/4T) 178'F(3/47)150'FUNACCEPTABLE IOPERATION PRESSURE-TEMPERATURE UMITFORHEATUPRATESUPTO60'/HRACCEPTABLE OPERATION 50100150200250300350400450AVERAGEREACTORCOOLANTSYSTEMTEMPERATURE (deg.F)Figure3.4-2ReactorCoolantSystemPressure-Temperature Limitsfor60'F/hrRate,Criticality LimitandHydrostatic TestLimitCOOKNUCLEARPLANT-UNIT 2Page3/44-25AMENDMENT 4Q,42$,XV',

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEM240022002000REACTORCOOLANTSYSTEMCOOLDOWNUMITATIONS APPLICABLE FORFIRST14,5EFFECTIVE FULLPOWYEARS(MARGINSOF60PSIGAND10'FAREINCLUDEDFORPOSSIBLEINSTRUMENTATION ERROR.)UNACCEPTABLE OPERATION C9180001600ttj1400g12001000O800oo~600400200COOLDOWNRATE'F/HRIACCEPTABLE OPERATION IPRESSURE-TEMPERATURE LIMITSIIMATERIALPROPERTYBASISINTERMEDIATE PLATE,C5556-2Cu-.15%,Ni.57%INITIALRTNDT58F14.5EFPYRTNDT(1/4I) 178'F(3/4T)-150.F II50100150200250300350400450AVERAGEREACTORCOOLANTSYSTEMTEMPERATURE (deg.F)Figurc3.4-3ReactorCoolantSystem,Pressure-Temperature, LimitsforVariousCooldownRatesCOOKNUCLEARPLANT-UNIT 2Page3/44-26AMENDMENT 6Q,~,474,

3/4LIMI'IONG CONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.5EMERGENCY CORECOOLINGSYSTEMS(ECCS)ECCSSUBSYSTEMS

-T3B330'FLIMITINGCONDITION FOROPERATION 3.5.2Twoindependent ECCSsubsystems shallbeOPERABLEwitheachsubsystem comprised of:a.OneOPERABLEcentrifugal chargingpump,b.OneOPERABLEsafetyinjection pump,OneOPERABLEresidualheatremovalheatexchanger, OneOPERABLEresidualheatremovalpump,AnOPERABLEflowpathcapableoftakingsuctionfromtherefueling waterstoragetankonasafetyinjection signalandtransferring suctiontothecontainment sumpduringtherecirculation phaseofoperation.

APPLICABILITY:

MODES1,2,and3.ACTION:WithoneECCSsubsystem inoperable, restoretheinoperable subsystem toOPERABLEstatuswithin72hoursorbeinHOTSHUTDOWNwithinthenext12hours.IntheeventtheECCSisactuatedandinjectswaterintotheReactorCoolantSystem,aSpecialReportshallbepreparedandsubmitted totheCommission pursuanttoSpecification 6.9.2within90daysdescribing thecircumstances oftheactuation andthetotalaccumulated actuation.

cyclestodate.COOKNUCLEARPLANT-UNIT 2Page3/45-3AMENDMENT

447,

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSKI'EBLIS TABLE3.7-1MAXIMUMALLOWABLE POWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURING4LOOPOPERATION MaximumNumberofInoperable SafetyValvesonAnyOperating SteamGenerator MaximumAllowable PowerRangeNeuttcnFluxHighSetpoint(PercentofRATEDTHERMALPOWER)58.141.224.5COOKNUCLEARPLANT-UNIT 2Page3/47-2

3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.7PLANTSYSTEMSCONDENSATE STORAGETANKLIMITINGCONDITION FOROPERATION 3.7.1.3Thecondensate storagetank(CST)shallbeOPERABLEwithaminimumuseablevolumeof175,000gallonsofwater.APPLICABILITY:

MODES1,2and3.ACTION:Withthecondensate storagetankinoperable, within4hourseither:a.RestoretheCSTtoOPERABLEstatusorbeinHOTSHUTDOWNwithinthenext12hours,orb.Demonstrate theOPERABILITY oftheEssential ServiceWaterSystemasabackupsupplytotheauxiliary feedwater pumpsandrestorethecondensate storagetanktoOPERABLEstatuswithin7daysorbeinHOTSHUTDOWNwithinthenext12hours.SURVEILLANCE REUIREMENTS 4.7.1.3.1 4.7.1.3.2 Thecondensate storagetankshallbedemonstrated OPERABLEatleastonceper12hoursbyverifying theuseablewatervolumeiswithinitslimitswhenthetankisthesupplysourcefortheauxiliary feedwater pumps.TheEssential ServiceWaterSystemshallbedemonstrated OPERABLEatleastonceper12hoursbyverifying thattheEssential ServiceWaterSystemisinoperation whenevertheEssential ServiceWaterSystemisthesupplysourcefortheauxiliary feedwater pumps.COOKNUCLEARPLANT-UNIT 2Page3/47-7

',III BASES2.0SAFEIYLIMITSANDLIMITINGSAH'YSYSTEMSKI'INGS2.1SAFETYLIMITS2:1.1REACTORCORETherestrictions ofthissafetylimitpreventoverheating ofthefuelandpossiblecladdingperforation whichwouldresultinthereleaseoffissionproductstothereactorcoolant.Overheating ofthefuelcladdingisprevented byrestricting fueloperation towithinthenucleateboilingregimewheretheheattransfercoefficient islargeandthe,claddingsurfacetemperature isslightlyabovethecoolantsaturation temperature.

Operation abovetheupperboundaryofthenucleateboilingregimecouldresultinexcessive claddingtemperatures becauseoftheonsetofdeparture fromnucleateboiling(DNB)andtheresultant sharpreduction inheattransfercoefficient.

DNBisnotadirectlymeasurable parameter duringoperation andtherefore THERMALPOWERandreactorcoolanttemperature andpressurehavebeenrelatedtoDNBthroughtheWRB-2correlation andW-3correlation forconditions outsidetherangeofWRB-2.TheDNBcorrelations havebeendeveloped topredicttheDNBfluxandthelocationofDNBforaxiallyuniformandnonuniform heatfluxdistributions.

ThelocalDNBheatfluxratio(DNBR)isdefinedastheratiooftheheatfluxthatwouldcauseDNBataparticular corelocationtothelocalheatflux,andisindicative ofthemargintoDNB.TheDNBdesignbasisisasfollows:theremustbeatleasta95percentprobability thattheminimumDNBRofthelimitingtodduringCondition IandIIeventsisgreaterthanorequaltotheDNBRlimitoftheDNBcorrelation beingused(theWRB-2correlation forVantage-5 fuel,andtheW-3conelation forconditions whichfalloutsidetherangeofapplicability oftheWRB-2).Thecorrelation DNBRlimitsareestablished basedontheentireapplicable experimental datasetsuchthatthereisa95percentprobability with95percentconfidence thatDNBwillnotoccurwhentheminimumDNBRisattheDNBRlimit(1.17forWRB-2and1.3fortheW-3).InmeetingtheDNBdesignbasis,uncertainties inplantoperating parameters, nuclearandthermalparameters, andfuelfabrication parameters arestatistically combinedwiththeDNBRcorrelation statistics suchthatthereisatleasta95percentprobability witha95percentconfidence levelthattheminimumDNBRforthelimitingrodisgreaterthanorequaltoacalculated designlimitDNBR.Theuncertainties intheaboveplantparameters areusedtodetermine theplantDNBRuncertainty.

ThisDNBRuncertainty, combinedwiththeDNBRcorrelation statistics, establishes adesignDNBRvaluewhichmustbemetinplantsafetyanalysesusingvaluesofinputparameters withoutuncertainties.

ForCookNuclearPlantUnit2,thedesignDNBRvaluesare1.23and1.22forVantage-5 fueltypicalandthimblecells,respectively.

Inaddition, marginhasbeenmaintained byperforming safetyanalysestoasafetyanalysislimitDNBR.ThemarginbetweenthedesignandsafetyanalysislimitDNBRisusedtooffsetknownDNBRpenalties (i.e.,transition corepenalties, rodbow,etc,)andprovideDNBRmarginforoperating anddesignflexibility.

ThecurvesofFigure2.1-1showthelociofpointsofTHERMALPOWER,ReactorCoolantSystempressure, andaveragetemperature belowwhichthecalculated DNBRisnolessthanthedesignDNBRlimitvalueortheaverageenthalpyatthevesselexitislessthantheenthalpyofsaturated liquid.COOKNUCLEARPLANT-UNIT 2PageB2-1AMENDMENT 84,434, BASES2.0SAFEIYLIMITSANDLIIUKI1NG SAIK'IYSYSTEMSETHNGS2.2.1REACTORTRIPSYSTEMINSTRUMENTATION SETPOINTS (Continued)

OvewerDeltaTTheOverpower DeltaTreactortripprovidesassurance offuelintegrity, e.g.,nomelting,underallpossibleoverpower conditions, limitstherequiredrangeforOvertemperature DeltaTprotection, andprovidesabackuptotheHighNeutronFluxtrip.Thesetpointincludescorrections forchangesindensityandheatcapacityofwaterwithtemperature, anddynamiccompensation forpipingdelaysfromthecoretothelooptemperature detectors.

Theoverpower deltaTreactortripprovidesprotection orback-upprotection forat-powersteamlinebreakevents.Creditwastakenforoperation ofthistripinthesteamlinebreakmass/energy releasesoutsidecontainment analysis.

Inaddition, itsfunctional capability atthespecified tripsettingisrequiredbythisspecification toenhancetheoverallreliability oftheReactorProtection System.Pressurizer PressureThePressurizer HighandLowPressuretripsareprovidedtolimitthepressurerangeinwhichreactoroperation ispermitted.

TheHighPressuretripisbackedupbythepressurizer codesafetyvalvesforRCSoverpressure protection, andistherefore setlowerthanthesetpressureforthesevalves(2485psig).TheHighPressuretripprovidesprotection foraLossofExternalLoadevent.TheLowPressuretripprovidesprotection bytrippingthereactorintheeventofalossofreactorcoolantpressure.

Pressurizer WaterLevelThePressurizer HighWaterLeveltripensuresprotection againstReactorCoolantSystemoverpressurization bylimitingthewaterleveltoavolumesufficient toretainasteambubbleandpreventwaterreliefthroughthepressurizer safetyvalves.Thepressurizer highwaterleveltripprecludes waterrelieffortheuncontrolled controlrodassemblybankwithdrawal at-powerevent.COOKNUCLEARPLANT-UNIT 2PageB2-5AMENDMENT 82,434,442, 3/4BASES3/4.2POKERDIS'GUBUTION LIMITS3/4.2.2and3/4.2.3HEATFLUXHOTCHANNELFACTORANDNUCLEARENTHALPYRISEHOTCHANNELFACTORContinued WhenRCSflowrateandPAHaremeasured, noadditional allowances arenecessary priortocomparison withthelimitsofSpecification 3.2.3.Measurement errorsof2.1%forRCSflowtotalflowrateand4%forF>Hhavebeenallowedforindetermination ofthedesignDNBRvalueandinthedetermination oftheLOCA/ECCS limit.MarginbetweenthesafetyanalysisDNBRsandthedesignlimitDNBRsismaintained.

(SafetyanalysesDNBRs:1.69and1.61fortheVantage5typicalandthimblecells,respectively.

DesignlimitDNBRs:1.23and1.22fortheVantage5typicalandthimblecells,respectively.)

Afractionofthismarginisutilizedtoaccommodate applicable transition corepenalties andtheappropriate fuelrodbowDNBRpenaltyfortheVantage5fuel(equalto1.3%per%CAP-8691, Rev.1).Theremainder ofthemarginbetweendesignandsafetyanalysisDNBRlimitscanbeusedforplantdesignflexibility.

COOKNUCLEARPLANT-UNIT 2PageB3/424aAMENDMENT

434,

3/4BASES3/4.2POWERDISTRIBUTION LIMITS3/4.2.4UADRANTPOWERTILTRATIOThequadrantpowertiltratiolimitassuresthattheradialpowerdistribution satisfies thedesignvaluesusedinthepowercapability analysis.

Radialpowerdistribution measurements aremadeduringstartuptestingandperiodically duringpoweroperation.

Thelimitof1.02atwhichcorrective actionisrequiredprovidesDNBandlinearheatgeneration rateprotection withx-yplanepowertilts.Thetwohourtimeallowance foroperation withatiltcondition greaterthan1.02butlessthan1.09isprovidedtoallowidentification andcorrection ofadroppedormisaligned rod.Intheeventsuchactiondoesnotcorrectthetilt,themarginforuncertainty onF~isreinstated byreducingthepowerby3percentfromRATEDTHERMALPOWERforeachpercentoftiltinexcessof1.0.3/4.2.5DNBPARAMETERS ThelimitsontheDNB-related parameters ensurethateachoftheparameters aremaintained withinthenormalsteady-state envelopeofoperation assumedinthetransient andaccidentanalyses.

TheTav<lessthanorequalto583.3'Fandpressurizer pressuregreaterthanorequalto2200psig(fornominalpressurizer operating pressureof2235psig)orgreaterthanorequalto2050psig(fornominalpressurizer operating pressureof2085psig)areconsistent withtheUFSARassumptions andhavebeenanalytically demonstrated adequatetomaintainthecoreatorabovethedesignDNBRthoughout eachanalyzedtransient withallowance formeasurement uncertainty.

Pressurizer pressureislimitedtoeitheroftwonominaloperating pressures of2235psigor2085psig,withthecorresponding indicated limitssetforthinthespecifications.

Thelimitsareconsistent withtheUFSARassumptions andhavebeenanalytically demonstrated tobeadequatetomaintainthecoreatorabovetheapplicable designlimitDNBRvalueforthecurrentfueltypethroughout eachanalyzedtransient.

The12hourperiodicsurveillance oftheseparameters throughinstrument readoutissufficient toensurethattheparameters arerestoredwithintheirlimitsfollowing loadchangesandotherexpectedtransient operation.

The12-hoursurveillance oftheRCSflowmeasurement isadequatetodetectflowdegradation.

TheCHANNELCALIBRATION performed afterrefueling ensurestheaccuracyoftheshiftlyflowmeasurement.

Thetotalflowismeasuredaftereachrefueling basedonasecondary sidecalorimetric andmeasurements ofprimarylooptemperatures.

COOKNUCLEARPLANT-UNIT 2PageB3/42-5AMENDMENT S2,434, 0f0 3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.4.9PRESSURE/TEMPERATURE LIMITSAllcomponents intheReactorCoolantSystemaredesignedtowithstand theeffectsofcyclicloadsduetosystemtemperature andpressurechanges.Thesecyclicloadsareintroduced bynormalloadtransients, reactortrips,andstartupandshutdownoperations.

Thevariouscategories ofloadcyclesusedfordesignpurposesareprovidedinSection4.1.4oftheFSAR.Duringstartupandshutdown, theratesoftemperature andpressurechangesarelimitedsothatthemaximumspecified heatupandcooldownratesareconsistent withthedesignassumptions andsatisfythestresslimitsforcyclicoperation.

AnIDorODone-quarter thickness surfaceflawispostulated atthelocationinthevesselwhichisfoundtobethelimitingcase.Thereareseveralfactorswhichinfluence thepostulated location.

Thethermalinducedbendingstressduringheatupiscompressive ontheinnersurfacewhiletensileontheoutersurfaceofthevesselwall.Duringcooldownthebendingstressprofileisreversed.

Inaddition, thematerialtoughness isdependent uponirradiation andtemperature andtherefore, thefluenceprofilethroughthereactorvesselwall,therateofheatupandalsotherateofcooldowninfluence thepostulated flawlocation.

Theheatuplimitcurve,Figure3.4.2,isacomposite curvewhichwaspreparedbydetermining themostconservative case,witheithertheinsideoroutsidewallcontrolling, foranyheatuprateupto60'Fperhour.ThecooldownlimitcurvesofFigure3.4-3arecomposite curveswhichwerepreparedbaseduponthesametypeanalysiswiththeexception thatthecontrolling locationisalwaystheinsidewallwherethecooldownthermalgradients tendtoproducetensilestresseswhileproducing compressive stressesattheoutsidewall.Theheatupandcooldowncurveswerepreparedbasedonthemostlimitingvalueofthepredicted adjustedreference temperature attheendof14.5EFPY.Thereactorvesselmaterials havebeentestedtodetermine theirinitialRTNDT.TheresultsofthesetestsareshowninTableB3/4.4-1.Reactoroperation andresultant fastneutron(E)1MeV)irradiation willcauseanincreaseintheRTNDT.Therefore, anadjustedreference temperature mustbepredicted inaccordance withRegulatory Guide1.99,Revision2.Thisprediction isbasedonthefluenceandachemistry factordetermined fromoneoftwoPositions presented intheRegulatory Guide.Position(1)determines thechemistry factorfromthecopperandnickelcontentofthematerial.

Position(2)utilizessurveillance datasetswhichrelatetheshiftinreference temperature ofsurveillance specimens tothefluence.Theselection ofPosition(1)or(2)ismadebasedontheavailability ofcrediblesurveillance data,andtheresultsachievedinapplyingthetwoPositions.

COOKNUCLEARPLANT-UNIT 2Page83/446AMENDMENT 6Q,4',474,

3/4BASES3/4.4REACTORCOOLANTSYSTEM3/4.49PRESSURE/TEMPERATURE LIMITSContinued Theactualshiftinthereference temperature ofsurveillance specimens andneutronfluenceisestablished periodically byremovingandevaluating reactorvesselmaterialirradiation surveillance specimens anddosimetry installed neartheinsidewallofthereactorvesselinthecorearea.TheheatupandcooldownlimitcurvesofFigures3.4-2and3.4-3includepredicted adjustments forthisshiftinRT>>rattheendof14.5EFPY,aswellasadjustments forpossibleerrorsinthepressureandtemperature sensinginstruments.

The14.5EFPYheatupandcooldowncurvesweredeveloped basedonthefollowing:

1.Theintermediate shellplate, C5556-2,isthelimitingmaterialasdetermined bypositionIofRegulatory Guide1.99,Revision2,withaCuandNicontentof0.15%and0.57%,respectively.

2.Thefluencevaluescontained inTable6-14ofWestinghouse WCAP-13515 report,"Analysis ofCapsuleUFromtheIndianaMichiganPowerCompanyD.C.CookUnit2ReactorVesselRadiation Surveillance Program",

datedFebruary1993.TheRT>>rshiftofthereactorvesselmaterialhasbeenestablished byremovingandevaluating thereactormaterialsurveillance capsulesinaccordance withtheremovalscheduleinTable4.4-5.Perthisschedule, CapsuleUisthelastcapsuletoberemoveduntilCapsuleSistoberemovedafter32EFPY(EOL).CapsulesV,W,andZwillremaininthereactorvesselandwillberemovedtoaddressindustryreactorvesselembrittlement

concerns, ifrequired.

Thepressure-temperature limitlinesshownonFigure3.4-2forreactorcriticality andforinservice leakandhydrostatic testinghavebeenprovidedtoassurecompliance withtheminimumtemperature requirements ofAppendixGto10CFR50.Thenumberofreactorvesselirradiation surveillance specimens andthefrequencies forremovingandtestingthesespecimens areprovidedinTable4.4-5toassurecompliance withtherequirements ofAppendixHto10CFRPart50.Thelimitations imposedonpressurizer heatupandcooldownandspraywatertemperature differential areprovidedtoassuretliatthepressurizer isoperatedwithinthedesigncriteriaassumedforthefatigueanalysisperformed inaccordance withtheASMECoderequirements.

TheOPERABILITY oftwoPORVs,orofonePORVandtheRHRsafetyvalveensuresthattheRCSwillbeprotected frompressuretransients whichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsarelessthanorequalto152'F.EitherPORVorRHRsafetyvalvehasadequaterelieving capability toprotecttheRCSfromoverpressurization whenthetransient islimitedtoeither(1)thestartofanidleRCPwiththesecondary watertemperature ofthestemgenerator lessthanorequalto50'FabovetheRCScoldlegtemperatures of(2)thestartofachargingpumpanditsinjection intoawatersolidRCS.Therefore, anyoneofthethreeblockedopenPORVsconstitutes anacceptable RCSventtoprecludeAPPLICABILITY ofSpecification 3.4.9.3.3/4.4.10STRUTURALINTEGRITY Theinspection andtestingprogramsforASMECodeClass1,2and3components ensurethatthestructural integrity ofthesecomponents willbemaintained atanacceptable levelthroughout thelifeoftheplant.Totheextentapplicable, theinspection programforthesecomponents isincompliance withSectionXIoftheASMEBoilerandPressureVesselCode.COOKNUCLEARPLANT-UNIT 2PageB3/44-10AMENDMENT BQ,423,4A,474 iJ,,L 3/4BASES3/4,5EMERGENCY CORECOOLINGSYSTEMS-3/4.5.1ACCUMULATORS Continued allowedcompletion timesarereasonable, basedonoperating experience, toreachtherequiredplantconditions fromfullpowerconditions inanorderlymannerandwithoutchallenging plantsystems.Ifmorethanoneaccumulator isinoperable, theplantisinacondition outsidetheaccidentanalyses; therefore, LCO3.0.3mustbeenteredimmediately.

3/4.5.2311d3/4.5.3ECCSSUBSYSTEMS TheOPERABILITY oftwoindependent ECCSsubsystems ensuresthatsufficient emergency corecoolingcapability willbeavailable intheeventofaLOCAassumingthelossofonesubsystem throughanysinglefailureconsideration.

Eithersubsystem operating inconjunction withtheaccumulators iscapableofsupplying sufficient corecoolingtolimitthepeakcladdingtemperatures withinacceptable limitsforallpostulated breaksizesrangingfromthedoubleendedbreakofthelargestRCScoldlegpipedownward.

Inaddition, eachECCSsubsystem provideslongtermcorecoolingcapability intherecirculation modeduringtheaccidentrecoveryperiod.COOKNUCLEARPLANT-UNIT 2PageB3/45-laAMENDMENT BQ,447,440, 1II 3/4BASES3/4.6CONTAINMENT SYSTEMS3/4.6.1.4 INTERNALPRESSUREThelimitations oncontainment internalpressureensurethat1)thecontainment structure isprevented fromexceeding itsdesignnegativepressuredifferential withrespecttotheoutsideatmosphere of8psigand2)thecontainment peakpressuredoesnotexceedthedesignpressureof12psigduringLOCAconditions.

Themaximumpeakpressureresulting fromaLOCAeventiscalculated tobelessthanthedesignlimitof12psig,whichincludes0.3psigforinitialpositivecontainment pressure.

3/4.6.1.5 AIRTEMPERATURE Thelimitations oncontainment averageairtemperature ensurethatI)thecontainment airmassislimitedtoaninitialmasssufficiently lowtopreventexceeding thedesignpressureduringLOCAconditions and2)theambientairtemperature doesnotexceedthattemperature allowable forthecontinuous dutyratingspecified forequipment andinstrumentation locatedwithincontainment.

Thecontainment pressuretransient issensitive totheinitially contained airmassduringaLOCA.Thecontained airmassincreases withdecreasing temperature.

Thelowertemperature limitof60'Fwilllimitthepeakpressuretolessthanthecontainment designpressureof12psig.Theuppertemperature limitinfluences thepeakaccidenttemperature slightlyduringaLOCA;however,thislimitisbasedprimarily uponequipment protection andanticipated operating conditions.

Boththeupperandlowertemperature limitsareconsistent withtheparameters usedintheaccidentanalyses.

3/4.6.1.6 CONTAINMENT VESSELSTRUCTURAL INTEGRITY Thislimitation ensuresthatthestructural integrity ofthecontainment willbemaintained comparable totheoriginaldesignstandards forthelifeofthefacility.

Structural integrity isrequiredtoensurethat(1)thesteellinerremainsleaktightand(2)theconcretesurrounding thesteellinerremainscapableofproviding externalmissileprotection forthesteellinerandradiation shielding intheeventofaLOCA.Avisualinspection inconjunction withTypeAleakagetestsissufficient todemonstrate thiscapability.

COOKNUCLEARPLANT-UNIT 2PageB3/46-2 iI0 3/4BASES3/4.7PLANTSYSTEMS3/4.7.1.3 CONDENSATE STORAGETANKITheOPERABILITY ofthecondensate storagetankwiththeminimumwatervolumeensuresthatsufficient waterisavailable tomaintaintheRCSatHOTSTANDBYconditions for9hourswithsteamdischarge totheatmosphere concurrent withtotallossofoff-sitepower.Theuseablewatervolumelimitreflectsthevolumeofwaterabovethecenterline ofthedischarge pipe.Anallowance forwaternotuseablebecauseoftankdischarge linelocationorotherphysicalcharacteristics isnotrequired.

3/4.7.1.4 ACTIVITYThelimitations onsecondary systemspecificactivityensurethattheresultant off-siteradiation dosewillbelimitedtoasmallfractionof10CFRPart100limitsintheeventofasteamlinerupture.Thisdosealsoincludestheeffectsofacoincident

1.0 gpmprimarytosecondary

tubeleakinthesteamgenerator oftheaffectedsteamline.Thesevaluesareconsistent withtheassumptions usedintheaccidentanalyses.

3/4.7.1.5 STEAMGENERATOR STOPVALVESTheOPERABILITY ofthesteamgenerator stopvalvesensuresthatnomorethanonesteamgenerator willblowdownintheeventofasteamlinerupture.Thisrestriction isrequiredtoI)minimizethepositivereactivity effectsoftheReactorCoolantSystemcooldownassociated withtheblowdown, and2)limitthepressurerisewithincontainment intheeventthesteamlineruptureoccurswithincontainment.

TheOPERABILITY ofthesteamgenerator stopvalveswithintheclosuretimesofthesurveillance requirements areconsistent withtheassumptions usedinthe.accidentanalyses.

Withonesteamgenerator stopvalveinoperable inMODEI,actionmustbetakentorestoreOPERABLEstatuswithm8hours.Somerepairstothevalvescanbemadewiththeunithot.The8hourcompletion timeisreasonable, considering thelowprobability ofanaccidentoccurring duringthistimeperiodthatwouldrequireaclosureofthesteamgenerator stopvalves.Ifthesteamgenerator stopvalvecannotberestoredtoOPERABLEstatuswithin8hours,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,theunitmustbeplacedinMODE2within6hoursandtheMODES2and3actionstatement entered.Thecompletion timesarereasonable, basedonoperating experience, toreachMODE2andtoclosethesteamgenerator stopvalvesinanorderlymannerandwithoutchallenging unitsystems.COOKNUCLEARPLANT-UNIT 2PageB3/47-3AMENDMENT W,470, I

ATTACHMENT 3TOAEP:NRC:1223 EXISTI'NG TECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES

CURRENTPAGESMARKED-UP TOREFLECTPROPOSEDCHANGESTOTHECOOKNUCLEARPLANTUNITNO.1TECHNICAL SPECIFICATIONS I',II'jt RACTORCOOLANTSYSTEMSAFETYVALVES-SHUDOWNLIMITINGCO'.:DITION OROPETON3.4.2Aminimumofonepressurizer codesafetyvalveshallbeOPERABLEwithaliftsettingof2485PSIG+*4~CTION:Withnopressurizer codesafetyvalveOPERABLE:

a.'Immediately'uspend alloperations involving positivereactivity changes++

andplaceanOPERABLERHRloopintooperation intheshutdowncoolingmode.b.Immediately renderallSafetyInjection pumpsandallbutonechargingpumpinoperable byremovingtheapplicable motorcircuitbreakersfromtheelectricpowercircuitwithinonehour.SURVEILLANCE REUIREMENTS 4.4.2Thepressurizer codesafetyvalveshallbedemonstrated OPERABLEperSurveillance Requirement 4.4.3.*Theliftsettingpressureshallcorrespo'nd toambientconditions ofthevalveatnominaloperating temperature andpressure.

~Forpurposesofthisspecification, additionof~aterfromtheRWSTdoesnotconstitute apositivereactivity additionprovidedtheboronconcentration intheRWSTisgreaterthantheminimumrequiredbycification 3.1.2.8.b.2 (MODE4)or3.1.2.7.b.2 (MODE5).sKS+PtD.C.COOK-3JNIT13/44-4AMENDMENT N0.53.lan 0'II C0TEMSAFTYVhLVES-0ERATINGGCOIONFOROPERATON3.4.3hllpressurizer codesafetyvalvesshallbeOPERhBLEvithaliftsettingof2485PSZGg.4goyJRhRVJZt:

Pithonepressuri.zer codesafetyvalveinoperable, eitherrestoretheinoperable valvetoOPERABLEstatusvt.thin15minutesorbeinHOTSHUTDOWNvithin12hours.SURVEILLANCE REUI~NTS4.4.3Noadditional surveillance requirements otherthanthoserequiredby(Specification 4.0.5.Theliftsettingpressureshallcorrespond toambientconditions ofthevalveatnominaloperating temperature andpressure.

~Sce.'wsvtCOOKNUCLEARPLQFZ-UNIT13/laalVOllh%P.WI 4th~

jII Insert4-4for0footnoteontechspecpage3/44-4and3/44-5Thepressurizer codesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethekl%tolerance.

PLANTSYSTB1SCONDENSATE STORAGETANKLIMITINGCONDITION FOROPERATION 3.7.1.3Thecondensate storagetank(CST)shallbeOPERABLEwithaminimumsea%~volumeof175,000gallonsofwater.U5eabWAPPLICABILITY:

MODES1,2and3.ACTION:Miththecondensate storagetankinoperable, within4hourseither:a.RestoretheCSTtoOPERABLEstatusorbeinHOTSHUTDOMNwithinthenext12hours,orb.Demonstrate theOPERABILITY oftheEssential ServiceMaterSystemasabackupsupplytotheauxiliary feedwater pumpsandrestorethecondensate storagetanktoOPERABLEstatuswithin7daysorbeinHOTSHUTDOMNwithinthenext12hours.SURVEILLANCE REUIREMENTS uQ49c4.7.1.3.1 Thecondensate storagetanksallbedonstrated OPERABLEatleastonceper12hoursbyverifying thewateriswithinitslimitswhenthetankisthesupplysourcefortheauxiliary feedwater pumps.4.7.1.3.2 TheEssential ServiceMaterSyst'mshallbedemonstrated OPERABLEatleastonceper12hoursbyverifying thattheEssential ServiceMaterSystemisinoperation whenevertheEssential ServiceMaterSystemis.thesupplysourcefortheauxiliary feedwater pumps.3/47-7 0

CONTAIN~BASLC34.6.1.4..

~RÃaLPRESSUREThe]Mtatiaas oacontainmaat internalpressureensurethat1)th+containmant structure isprevented fromexceeding itsdesignnegativepressuredifferential vithrespectcotheoutsideatmosphere of8psigand2)thecontainmant peakpressuredoesnotexceed*the designpressureof12psigduringLOCAconditions.

Themaximumpeakpressureresulting fromaLOCAeventiscalculated tobaI~So~,vhichincludes0.3psigiorinicialpositiveconcainment pressure.

)a,ps(g,34.6.1.5AIRT~~PERATLRE

.helimicat:.".soncontainment averageaircemperaru.e ensurethat1)thecontairen":r"assis'.'..ite"oaninitialmasssufficiently lovcop"eventexceeding

='.".eCs'"n".ress"eCur'n"LOCAcrdi.c'ons and2)che~=biencar"e""er=re==as"..:=x=eed":".atte.:perarure allovable orchecontnuousCtyrac.".g s"eci"'ed iore,uipment andinstrumentation locacedvithincon"a."..enc.Thecontainmenc pressure=rans'enc

'sse..sitive to-'e'ni.tially contained air=ass'uringaL"CA.:.".e con"a'.".ed airgpssi.".c"eases vi=hecreasi.nr.

rem~eratre.;.e"ver=e=peracreI'sitog60r4illlimit":".epeakpressure=o..esschan5g.concainmenc desi.gnpressureoi12".sip.7:".eu"percemperacure limitinQcaences thepeakacc'Cenecemoera"'e sl'>htlyCr'ngaLOCA:hovever=hislimitisbasedpr'.=a'uponequipment procec"onandantici.paced c"crating conditions.

Borhtheupperandlovertemperacure limitsareconsistent vithcheparamecers

.sedincheacci.dent analvses.

34.6.1.6COVTAIN~EVT VESSELSTRUCTURAL INTEGRITY Thisli-itacion ensuresthatchestructural integrity ofrhecontainmenc stealvesselvillbemaintained comparable totheori-;naldesignstandards forrhali.faofthefacility.

Structural integrity isrequ'"edcoensurethat(1}thesteellinerremainsleakeights..d(2)theconcretesurrounding thesteelli.nerremainscapablec=providing excernalmissileprotection forthesceellinerandradiation shield;.-.g intheevencofaLOCA.Avisualinspection incandu-..scion vt.thTypeAleakagetestsissufficient rodemonstrate chiscapabiicy.COOKNUCLEARPLANTPitIT1B3/46-2AHENDMENT NO.

SSEHS]USES3CONDENSAESTORAGETANKTheOPERABILITY ofthecondensate storagetankwiththeminimumwatervolumeensuresthatsufficient

~aterisavailable tomaintaintheRCSatHOTSTANDBYconditions for9hourswithsteamdischarge totheatmosphere concurrent withCotallossofoff-sitepower.'4.osc~Q~~~wctu~4mbmA~~Voh~+~d4bQc~~~'b~Kkt1ucL'~~pipe~Mo.Lhcl~4cA~v4+QsccLS&~~cf~Qsc4~cfi~locchcoAN't4crppg<icaJclAa~~>~pcs ts4CTUIn~tegoi~~Thelimitations onsecondary systemspecificactfivity ensurethattheresultant off-siteradiation dosevillbelimitedcoasmallfractionof10CFRPart100limitsintheeventofasteamlinerupture.Thisdosealsoincludestheeffectsofacoincident

1.0 gpmprimarytosecondary

tubeleakinthesteamgenerator oftheaffectedsteamline.Thesevaluesareconsistent withtheassumptions usedintheaccidentanalyses.

34STEANGENERATOR STOPUALUESeTheOPERABILITY ofthesteamgenerator stopvalvesensuresthatnomorethanonesteamgenerator villblowdownintheeventofasteamlinerupture.Thisrestriction isrequiredto1)minimizethepositivereactivity effectsoftheReactorCoolantSystemcooldownassociated withtheblowdown,.

and2)limitthepressurerisewithincontainment intheeventChesteamlineruptureoccurswithincontainment.

TheOPERABILITY ofthesteamgenerator stopvaliseswithintheclosuretimesofthesurveillance requirements azeconsistent w5.ththeassumptions usedintheaccidentanalyses.

Withonesteamgenerator stopvalveinoperable inMODEI.,actionmustbeCakentorestoreOPERABLEstatuswithin8hours.Somerepairstothevalvescanbemadewiththeunithot.The8houxcompletion.time isreasonable, considering thelowprobability ofanaccidentoccurring duringthistime.periodthatwouldrequireaclosureof'hesteamgenerator stopvalves.Ifthesteamgenerator scopvalvecannotberestoxedtoOPERABLEstatuswithin8hours,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,theunitmustbeplacedinMODE2within6hoursandtheMODES2and3acCionstatement entered.Thecompletion timesarereasonable, basedonoperaCing experience, CoreachMODE2andtoclosethesteamgenerator stopvalvesinanorderlymannerandwithoutchallenging unitsystems.Sincethesteamgenerator stopvalvesarerequiredtobeOPERABLEinMODES2and3,theinoperable valvesmayeitherberestoredtoOPERABLEstatusorclosed.Whenclosed,thevalvesarealreadyintheposiCionrequiredbytheassumptions inchesafetyanalysis.

The8hourcompletion timeisconsiscenC COOKNUCLEARPLANT-UNIT1B3/47-3AMENDMENT NO.W,185, IANTSYSTEMS~AS~K4STGENERATOR STOPVALVEScotinued.withtheMODE1actionstatement requirement.

Forinoperable steamgenerator stopvalvesthatcannotberestoredtoOPERABLEstatuswithinthespecified completion time,butareclosed,theinoperable valvesmustbeverifiedonaperiodicbasistobeclosed.Thisisnecessary toensurethattheassumptions inthesafetyanalysisremainvalid.The7daycompletion timeisreasonable, basedonengineering Judgement, inviewofsteamgenerator stopvalvestatusindications available inthecontrolzoom,'andotheradlai.stzative

controls, toensurethatthesevalvesareintheclosedposition.

XfinNODES2or3thesteamgenerator stopvalvescannotberestoredtoOPERABLEstatusorazenotclosedwithintheassociated completion time,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,theunit-must beplacedatleastinMODE3within6hours,andinNODE4within12hours.Theallowedcompletion timesazereasonable, basedonoperating experience, toreachtherequired'nit conditions fromMODE2conditions inanorderlymannerandwithoutchallenging unitsystems.COOKNUCLEARPLANT-UNXT1B3/47-3aAMENDMENT NO.185,

CURRENTPAGESMARKED-UP TOREFLECTPROPOSEDCHANGESTOTHECOOKNUCLEARPLANTUNITNO.2TECHNICAL SPECIFICATIONS C~lvlTTCMS OEFlhHTERS1.iTheOEFTHEQTERSofthissect<onayaear<ncayftall~

typeanclareayylfc-aolethrougnoict theseTechnical Soedflcat<ons.

>a~ALHi~cRZ.ZTB60tN.tSCRshallbethetotalrsac~corebeattransferratatomreac-torcoolant.Ui-9%Exalt.NsB33.RlicCTHSNAL~Shal1beatotalreaC~COreheattran!farratatOthereactorcoolantofSzrS'PQATTGM~L, HMK4MQPHHŽQL~KshallcorresyonC tocnyone(nc4s<vt~fnatfonof~reac:lvlty concitjon,

~rle>elaniSereragereactorcoolanttacyerature syicif$ectfnTaoleD~AC.0HL.5~QNsnal1beCeaaacyltfonerecpsfreausss syeclflailaacorol1ary stata-oentxmearnyrfnc!yl~syecffccatfonancshallbepartofthesoedNcaclons.

CPHXZteCP~~iimrs~.Nc~sm,train.~onenterCenceshallbe0$694LEorbert096Nll'TT~ltlscayaoleofyerfornlag laasoedfleis

~ce{s).balldtfncledsoefln<t{on shallOetwass~tenthatal1necessary

~n4ant<~eentat1on,

controls, noroalaniS~rllencyelecMcalonersourcas,coollyersealstar,luurtcac<on or'therecatlfcty eydyaencthatarencpdresforthe~tan,suusystae.

train,~onencocCerlcatoperformitsfunc=$oo(s)arealsocayaul>>ofyerfo~ogtheirrelateiseeyortfunccloaEs).

tagta4CÃ9L40ES?T80fAVlt(JeVg4C(F?etTgFlttpsO.615.9.S.a.024.9.2cQOOO.O.SS6.t0659.55.5QO.QO6.K0261<006'20.72$..9450.660.637340:S6f~00.039..622.0.26540C<0FSS54lA0-14444Stk10A50-,57e-.so.0ffguiI2.11 Fferl4ta91,600gpafloop(FurlVaa'Aia,5~)P~tTave~Q~oCfraclL2'fadL.44k QmrlD750.00613.11.105ea.aI.leSn.a1.220000.00632.21.12597.5I.14596.01.2Tavg~dSZSA589.421000.00639.21.08605.51.106N.81.2593.5225024000.00639.00.96631.9I.l,616.7605;F0.00Q9.41.02&19.51.10610.91.2599.7~~cgLalCSCI4SI5am~i+V75tQA~~M,"toFRACfJNOfllIEWQLNIKR(95OOWt;=La)

Figure2.1-1ReactorConSafetyt.fataFenLoops3aOperatfoa

~TUL2.T.TRI?fYSTDfTN~iQfQfTATI0N WI?S~~0NAJ-UNITWITSETPOIÃZAIICOASI?

VAL~l~NanuelReaocorTrSyNecApplicable 2.feverRange,NeutronLovSecyoknc~LaaathanFlux~requalto25'fRATEDQ)ER)aU.NaXRtghSecpotnt~Loaathanerequalco10%%oCRATEDCREEDALBRED5~loverRange~NeutronLkaathanerequalco51efFlux,Mt'oatctvo RATED%QRNAL?CNXk vtchaRacetiveeonacantgreaterthan~requalto2aeeoaCa4.?overRange,NeutronLaaathanerequaLto5lefflux.&ShNegativeRATEDTHER)fALNE'ERvtthakatetioeconacantggeatarthan~requaLto2aeeoeutaNec~Lteabl<<LovSeeyetnt~L<<<<athanorequaLto2Ct<<CRAIiDTERNAL?mEXQgh5<<gotnc~L<<aa~4orequaLtoLL0IefRATED'DER))AL20QEXLaaathaner<<quaLco5.$iofRATEDQKlXAL8ÃEXviAacthecenacantg.<<at<<rchaner<<qualta2a<<coatsLaaathaner<<quaLto5.5i~CRAtEDTHECAL?CQXL vtW4testcoclacaot

+eaterthaner<<quaLca2aecoack5oEncawedtate Range~Naut=onfluxC.SourceRange,Neucr~flux~~7~Overten)eeracuro DeLcaTLeaathanerequaLto25%~fRATED5)mQLNQXXLaaachanerequaLtoLOoountap4ra4cooLSeeNotalLaaathaner<<qualto20ioCRATEDT))ERALROE'a)athaner<<quaLtoL.lx10ceoncaper<<<<codSeeNota3C.OvegoverDelta7SeeNota2SeeNoca4%.Preaau=Qar

&eaaureLovL0.freaaurtrer tzeaaucaeeQQLL.?teaaurtaar VoterLovel>>QghL2.LoaaofflovCrutarthanerequaLtoL$50yatgLaoachanerequaLto2545yatgLeaachanerequaltoN%~ftna~ncapaaCreatorthaner<<qualtoNtef4aatgnflovperCreacerthanerequaLtoU40patgLoaathaner<<qoaLco25S5yakgLeaathanor'qualcoSls~Ctna~nctp<<nCreacerthan<<requaLto4%.llefCeatpL.'L<<vy<<c'~Deathflovta~)'(~~c.~-.+

<,~-""'

TABLE2.2-1Contfnued REA.CTORTRIPSV~atSmmeeaTIOS TRIPSETPOmrSNOTATIONHote1:Overtemperature

@here:hT0P'+~STloT2hT<hT'K-Kf(1+mls)/(1+g2S)](T-T')+(P-P')-fl(hI)

JIndLcated hTatRhTED5KQQLPSKR~hveragetemperature, F0~Inttcatid TatRhTEDTHHQQLLtSKRlessthanorequalt,o~l.3'FsurferPressure.

psfg~p$$$gfxldicRcId RCSDoEf041opozs'cog pL'55llzEf+95~gorQoP$'@sicThefunctionpnerate4bythelead-lagcontroller forTdynaniccoctpensa&on 4Vj~Tiveconstants utilizedhthelead-laicontroller, forT;rl~secs,v24secs.LaplacetransforaterCOOKHUCLZhRTLhBTQHIT227mxmazrso.82~34 IIf!,

c2.2-lContinued REhCTORTRIP5YSTBfINSTRUMBKlTICN TRIP~c,;TNT'ORTATION Cantiaaad) 4LoopsfnOped'scion Xl~ke09I.l7a~amo.oQ.47+~+41@540.04t1tandf>(4I)iaafunctionoftheindicated difference becveentoysndbottoadetectors oftheyavet-range nucleationchsnbez's; Kthgainstobeselectedbasedonaeaeuedinst@ment responsedutiagy4ncscattytestsescacham:(i)foz'-qbbecveen~yezcentand+6pezcant,f>(hI)W(vhezeqandqatepercentRhTZDQKQQLNVKRinthetopandbottoahalvesofthecozerespectively, andq+qistotalOKRAB%ERinyet'centofRhTEDBANALPOUER).(ii)fox'achpercentthatthemagnitude of{q-q)exceedsyetcanc,che4TeelysetyointshaQbeautocatically t'echoedpeccantofitsvatueatRAZEDTH&LALESKER.ok(iii)Foreachpercentthattheaxed.ateof(gg)exceeds+5percent,thehtcrLysetyointsha11beaxcoeatically itdncedQLrOpattensoiitsvalQ4atRhTZD5KRQLPSKRc4?COOKHUCLEhRP?hHTVHZTg2-4AKHDt62fT 80.82~<'3~

TABLE2.2-1Continued REACTORTRIPSYSTBtINSTRUMENTATION TRIPSETPOINTS NOTATIONS Continued Overpo<<rAT<hT(K4-K5(t3S/(1+r3S)]T-K6(T-T"]-j

(<I)]%here:K4K5K6Indicated hTatratedpoverAveragetemperature, F0CIndicated TatRATEDTHERMALPOVERlessthanoravgequalto576.0F1.0800.02/Fforincreasing averagetemperature and0fordecreasing averagetemperature

-0.0019?forTgreaterthanT',K60forTlessthanorequaltoT"AS/(1+zS)Thefunctiongenerated bythe3Tdynamiccompensation avgT3TimeconstantutilizedintheTyr3~10sees'vg.S=Laplacetransform operatorf2(g)-00ratelagcontroller forratelagcontroller forNote3:Note4:Thechannel's maximumtrippointshallnotpointbymorethan(QtpercentQ'pan.3.'lSThechannel's maximumtrippointshallnotpointbymorethanQPpercentQspan.BS'].exceeditscomputedtripIexceeditscomputedtripCOOKNUCLEARPLANT-UNIT22-9AMamMENTNO.82,134 i

POSEOI5aRI5UTION LINITSDN5hNDTavOPERATINC PARAMZEERS LL9ITINCCONDITION FOROPERATION 3.2.5Thefolloving D?8relatedparameters shallbemaintain<<vichin chefollovtng operational indicaced limits'.a.DNZosz~k1.ReactorCoolancSystemT2.Pressurizer Pressure3.ReaccorCoolantSyscemTotalFlovRateLesschanorequalco57$.7W0Creacerthanorequalco2200paid+/~Creaceroraquato,gp~b.Tavg1.ReactorCoolantSystemTgg/~APPLICA5ILITY:

MODE1Createrchanorequalto543,9F>>hCTION:><chanyoftheaboveparameters exceeding icslimit,rescoretheparameter tovithinicslimitvithin2hoursorreduceTHZ@gZ,pyrZR.colessthan5gofRATEDTHERMALPCQERvichinthenext4hours.SURVEILvVNCE RERBfQiTS4.2.5.1Eachoftheaboveparameters shall'beverifiedtobevithintheir.limitsacleaseonceper12hours.4.2.5.2Th>>indicators usedcodetermine RCStocalflovshallbesubjected coaCHANNELCALXBRATIOH ac,leastonceper1$months.4.2.5.3TheRCStocal'lov ratashallbedetermined byapoverbalancearoundthesteamgeneracors acleaseonceper1$months.4.2.5.4Theprovisions ofSpec&cation 4.0.4shallnotapplytoprimaryflovsurveillancas.

Indicacad averageofatleastthreeOPERA$LEinstrument loops.Limitnocapplicable during.eitheraQKBHhLPQMERtampinexcessof5%ofRATEDTKDtMALPCKkpet'inute oraTHEWhLPOMEiLseepinexcessof10'fRTP~Indicated valueCOOKNUCLEARPLANTUNIT23/42-UmuamEHTHO.S7..f34 I

INSERT3I42-<51.ReactorCoolantSystemT2.Pressurizer PressureLessthanorequalto583.3'FGreaterthanorequalto2200psig(fornominalpressureof2235psig)tGreaterthanorequalto2050psig(fornominalpressureof2085psig)I

TABLE3.3-4ENGViEKLED SAFETYFEATUREhCTUATXOH STUD(XHSTRUHEHThTIOH TRXP~OXHTShLLOVhBLE VALUESl.SAFETTXHJECTXOH, TURBXHETRIP,FEEDVhTER ISOLATION, hHDHOTORDRIVEHhGZXLZART FEEDVhTER PUMPSa.EanualInitiation aaammaeaumma See'Functional Unit9amaaw~a~~~~

b.hucoaacic Actuation Logicc.Containmenc Pressure--

Highd.Pressuriser Pressure-Love.Differential PressureBecveenSteantLinesHf.ghHotApplicable Lessthanoc'qualtol.lpsigCreaterthanorequalto~psigIEi8Lessthanorequalto100psiHochpplicable Lessthanorequaltol.2psigCreaterthanorequalto~psiggrasLesschanore~toll2paif.SteanLinePrassure-LovCrearthanorequalCrearchanorequal-topsigsteamlinetopsigsteanlineressure~assureCOOKNUCLEAR~>>IXT23/4323f34,is7 TABLE3.3-4Continued EHCZHZZEED SAFErrFEATmzhCTUATZOH STD(EHSTRmmTATZOH TRIPSETPOiHTS STIr~iLZHEZSOLATZOH a.manual-----------

SeePuaccianal Quit9----b.Automatic Actuation LogicHocApplicable HocAppli,cab].e c.Containment Pressure--

High-High d.SteamFlovtnTvoSteamLines--High Coincident vithTang--Lov-Lov e.SteamLinePressure--Lov 5.TQREIBETRIPAHDPKKDVATEL ISOLATXOS Lassthan,orequalco2.9psigLessthanoraqua!.toafunctiondefinedasfollovs:ADelta-pcorresponding to1.6x10,lbs/hr steamflovbecveen0%and20%loadandchenaDeltapincreasing

'inearlytoaDelta-pcorresponding to4.5x10I.bs/hracfuLLload.TgreatertheaoreQI.to5417Creaerthanozequaltopsigsteamlinepressure.

Lesschanorequa].to3.0psigLessthanorequaltoafunctiondefinedasfollovs:ADelta-pcorresponding co1.75x10lbs/hrsceamflovbecveea0%aad20%I.oadandtheaaDelta-pincreasing linearlycoaDelca-pcorresponding coto4.55x10lbs/hecfullload.Tgreata>>chanbrequalto539PCrearchanozequaltsigsceamlinepressurea.SteamCeaeracor VacerLevel--Egh-Egh Lessthanorequalco67%ofaarrovrangeinstrument spaneachsteamgenerator Lessthanorequalco68\ofnarrovrangeinstrument spaneachsteamgenerator COOKHUCLFJLRPLEX'HZX23/43-25AHRHDHEHT Ho-82,f88,f3{1,I37

3.4.2Aalaiauaofonepreaaurizer codaaafetyvalveahallbeOPERhlLZvf.thaliftsettingof2415PS's/rKGKULthaoaopreaaurirer codeaafecyvalveOPG4ULLE:

Zanediataly suspendalloperation!

invokingpoaitivereactivity changes~aadplaceanOPERhSLERHRloopintooperation Mtheahutdovacoolingaode.b.Tauaediataly readerallSafetyInfection puapaaadallbatonechary~poapiaoperabLe byreaoviagtheappLicable aotorcircuitbreakarxfcoo,theeleccricaL povercircuitvithinoaeboar.4.4.2Noadditional Surveillance Reqnkreaeata othertheaphoaerequiredbySpec'cacion 4;0.5.~%heU.fcaecciagpreset'halL correapond toambientcoaditiona oftbavaLveacnoaixaLoperachgteaperacure aadpreaanre.

~Forpnrpoieaoftheaapecification, additionofeaterfreethe~doeaaocconscience adilutionactivitypcmridadcheboroacoooeacracion LatheMSTia~eaterthanorequalcothaaiaiamarequiredbyspecificacioa 3.L.2.8.b.2 (WOE4)or3.12.l.b.2(~K5).~5am~s~+V~~meSO.SZ,3/44+4 Insert4-4for0footnoteontechspecpage3/44-4and3/44-5Thepressurizer codesafetyvalveshallberesettothenominaLvalue41%vheneverfoundoutsidethei1%tolerance.

REACT"RCMlANTmarVALVeS-OmmT1~LINlTLMCON)ETTAN FOROPGQTION3.4.3Allpressurfzer codesatvalvesshallbeOPUS@fifthalff'tIai:In't'485 PSNAPPLKABtLITY:

NOCHES1.iandi%ON:Mfaonepresmrfzer codesaf'e.yvalvefnoperable, eftherrestorethefnooerable valvetoOP64LMsuNsrfthfn15Nfnucosorbefn%TQQTQSN~i&fn1Zhours.SUR"KILU' RNENCfTS<.<.3Ncaddftfonal Survefilance RCqufteeel&

otherthanMse~ufrtdby8".ccff'fcatfon 4.0.5.'BT'valveac,analogerafhgC4$gcrareandpressuree 9.C.COOX-LifftTZ~Inc5

14.4.6.2.L ReactorCoolantSystemLeakagesshaLLbedemonstrated tobewithineachaftheabaveLimitsby;Monitoring theconadaaeac.atmosphere parciculate xadioaccivicy monicoracleastonceper12hours.Eonicoxing theconcainmenc sumpimrencoxy anddischarge acLeaseonceper12hours.DetezminQ~

thesealLineresistance acLeastonceper31days~hentheaveragepxesstrizer pressureis@%thin20psiofitsnominalfuLLpressurevalue.ThesealLinexesWcmcemeasuredduringthesurveiLLance muse.begx'eaterthanoxeyzalto2.27E-lfc/gpm.TheseaLlineresistance, RSl,isdetermined framthefoLLocring expression:

R2.31(P-P)%81exeiPCHP>>chargingpumpheaderpxessure, psig~+giig,p~~

(t~PvesSam~&~/PSZ2262psig(highpressureoperation) 2.31-cexversioa factor(12in/fc)2/(62.3 Lb/Gc)--thetotalsealinfection floe,cpm.Theprovisions afSpecificacioa

4.0. 4arenocappUrsble

foren~intoKODES3ancL4.d-Performance afcReaccorCoolancSystemvacarQxveatoxy balinceacleaseanceper72hcsduringsteadyscacaaperacioa, aud.e.Eoaicoring theraaccorhead.flangebreakoffsystemacLeaseonceper24~xzs.4.4.62.2.Eachreactorcoolantsystempressureisolation valv>>specified.

inTable34-0shaLLbedemoascxaced OPHUUKKpursuanttoSpecQKcacioa 4.0.5.COOKHUCZZaRPLgrZ-aaron23/44-16 0

'nPQ0024003200g42000~~~ti!ill.lIi']iy,SflEACTOACOOLAHTSYSTEHIIELIHITATIOHS APPLICAQLE FOAFIRSTEFFECTIVE FLLLPOIIEAYEAAsIttAAoltts oFaoPaloAteIooFAAElttcLUAEA FOAPOSSISLEIttSTAUHEllfhf rdtlEAAOA.)!tij:tti!0IiItf000t~LEAKMSTLIHll-"lt1600i40018001000800JidIklACCEPfABLEOPEAAlIOHttt~~IPAE4SNIE-TEHV AATLNELIHllFOAILATN'ATES UPladaof/IN---CA1lICAL11YLIHITACCEPTASLE OPEAATlott 600400200ijlti}.)i'i)t

}
'jII'TEAIALPAOPEAlYSA414IHTEAttEOIATE PLATE,Cdddd-ttcu-.rax.Ht-.av4IHIrrALAl-aaofEfPYAT~<(I/ATIl74of3/1TItdoof060400460100160200260300600AVEAAOEAEACTOACOOLAHTSYSTEHMHPEAAlUAE FIOUAE$.4"SAEACTOACOOLAttlSYSTEH,PAESSUAE TEHPEAATINE,LIHITS FOAdOP/ttAAATE,CAlllCAL11Y LIHll'INIIYOAOSTATIC MSTLIHll

C3'n960024002200IO2000/0lfEACTOACOOLANtSYSTEHCtfNLlHTTATlONS APPLlCASLE FOAFlASTEFFECTIVE FN.LPOMEATEAASQ4AAGTHSOFffdPSlQAIQ10FAAEINCLINEDFOAPOSSISLEINST~NTAT IOflEAAOA.l~~j~~~f~I~joo$I~f';!))'sff')'i)i'000iaaoi4001200I~~~~PAESStNE-TEHPEAATLNE LIHlTS$~~jg~l,)~IWACCEPTAOLE

!OPEAA'TIOH lIoIi.:iif!.:g0ACCEPTABLE OPEAAT10ff i000SOO~~60040020060COOL%50IAATEf/fn100HATKATALPAOPEATYOASISTHTHaaDTATK PLATE,Caadd-aCu~.IdX,NI.d7XINITIALAT-an4rRPPYAT~TIl/4TIl744FIS/ST)IaO4rf~~400460lI'160200;260300360AYEAAOEAEACTOACOOLANTSTSTEHTEHPEAATfÃlE IF)fTON%3.4"3AEAGTOACOOLAIITSTSTEH.PAESSfNE-TEIL'EAATN!E, LlHl18FOAYAAINISCOOLOOMfl llATES I

5.5,2Tvoindependent ECCScubcyctcac challbeOHXQlLK<<itheachcuhcyceaa coapriced of:a.OnaOPKRASLKccntribzgal chargingpuap,b.OnaOPERASLKsafetyinfectionpuapc.OaaOPEMLKresidualheatrclotalheatexchanger, d.OnaOPKMLKracidualbeatrcaovalpuap,~.haOPZRASLKflovpathcapableoC'atcLng cue@Lanfroathcra5aaliag vaearstoragectckonac4fatyinjection cigoa1cadtransferring auctioneotheconeaiaacnt cuspdaringtherecirculation phaseofIoperation+

+6IME5l.2.cad3.hSZZQK:a.lithoaeECCLcubcyscca iaopercb4, raceoeatheiaopeesb4 cubcyseea toOPERhSLKaeacusvithin72hoursorbeinMZSTEROLÃ<<ithinthenextL2hours.'<itisaatelyta]~aau-cueaaaea,naPa.cartSss-

~.cLaval<<eeoopenpociorsochaoetha-corapo<<erlavelaca~E~eo<<iehinoem'hoar.5~4~4,doe+.nacapply.b.ZnehaeventthaKCCSiaaceuatadcndin)acta<<aecrintothaReactorCoo4neSyseaa,aSpecialIaporechalI.bapreparedcadcubccLeaid eotheCoeaisaion pursuanteogpecificatioa 4.9.2.<<ithfn.Kdaysdaacribing ehecircmaecncaa otthaactuation cadthetotalacuaaalaead acacacion cyc4acodataCOOKNUCLEARPLANTUNITI5/455ZmramtTNO.t67 3/4LIMZ71NGCONDITIONS FOROPERATION ANDSURVIHLLANCE REQUGEKENTS 3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLE POWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLE STEAMLINESAFETYVALVESDURING4LOOPOPERATION MaximumNumberofInoperable SafetyValvesonAnygSteamGenerator MaxinuunAllowable PowerRangeNeutronFluxHighSetpoint(PetcentofRATEDTHERMALPOWER)COOKNUCLEARPLANT-UNlT 2Page3/47-2 PLANTSYSTEMSCONOKNSATK STORAGETANKLIMITINGCONOITION FOR'PKRATION gcen4lu3.7.1.3Thecondensate storagetank(CST)shallbeOPKRASLE-withaminimumconta>nevolumeof175,000gallonsofwater.APPLICASILITY:

MOOES1,2and3.ACTION:Miththecondensate storagetankinoperable, within4hourseither:a.Restore>eCSTtoOPKRASLEstatusorbefnHOTSHUTOOMNwithinthenext12hours,orb.Oemonstrate theOPERASILITY oftheEssentfal ServiceMaterSystemasabackupsupplytotheauxiliary feedwater nutnpsandrestorethecondensate storagetanktoOPERASLEstatuswithin7daysorbefnHOTSHUTOOMNwithinthenext12hours.SURVEILLANCE RKUIRKMKNTS usesbit4.7.1.3.1 Thecondensate storagetanksha11beemonstrated OPERASLEat1eastonceper12hoursbyverffyfng thecontainwatervolumefswithinitslfmitswnenthetank.fsthesuppIysourceortheauxiliary feedwater pumps~4.7.1.3.2 TheEssential ServiceMaterSystemshallbedemonstrated OPKRASLEat,leastonceper12hoursbyverifyfng thattheEssentfal ServfceMaterSystemfsfnoperatfan whenevertheEssential ServiceMaterSysteafsthesupplysourcefortheauxiliary feedwater pumps.O.C.COOK-UNIT23/47-7 2.She:rojericeiona ofchiclafteLimeyt~nc~theat'fchar~Lyoai~4yororation&tchvoul4reauleinehoroZIasoogfiaibyream'cew4 fueloyoraeion eovSthpnehaescleataboU,Qrii+neboatc=anafarco~arcoefficient taLac'goaa4@hoclaLCtngaurfacoeNxporaeurl alightlychereehacoolantsaturation eaayoraeura.

yoraeionabmthouyyorbeauhryofthenucleate.boSUng re!~coulgreauleincxcoaaSve claddingeaeyoraeuraa bocauaaofehaoaaatofday~~froanuclaaeabotany(RQ)an4ehoraauleant charyreduction Snboate-anagoge coefficient.

Mianota4tracelyaeaaurabla yaraaeear 4u'Sagoyoration a~therefore QHXM2%SRanlreactorcoolanteaayoraeuro an4yreaauzo~b<<<rolataltoQOthroughthe4'2corrolaeion anl13corralation forcon4itioc outaidatherangeotM-2.IhoNScorre4tioea

~boonMoloyoltopredicttheQQfluxan4eholocationofCAferaxiaLLyuniforaaaclaonuniforheatfluxMeribueiona.

TheLocalNOheatfluxratio(MR)iadafina4agehoratioofchohoatfluxchatvoQL4cauaoOtOaeayareicular coraLocationeoehoLocalheatflux,an4iaindicative oftheaargineoDI3.TheDQdoaigabaaiaiaaafollows:ehaeemtbeatLaaaeaS5yorconcyrobabiliey chiteheakaSauaDHN,ofeheLixiciagro4@ac~Coactionan@IIevontaiagcaaearthanorequaleetheDIIRL~tofehaCAcorrelaoaNX2correlation forVaneago5fse1,catehe1-3cor:aeioneAichfaLLoueaikoeheragaofayylicabofthe-.correlation ONtQuiteareoatabliahe4 baaolontheayylicabla ixyorisoncaL datalesHachehacchemii$4$5yercaccyrobahilfty arith$5yorcantconfidence thatQQ%11tetoccurvheatheaSniemECQkiaattheQStLiait(L.UfotQR$-2anlL.5fmehoV-3).InaeoCageh>>0%daaignbaal,uneareaintiae inylantoyoraeing yaralatars, escloaran4ther,laLyaraaoeare, anlfuelfabrication yaraaoeara a-eatatiaticaLIy coehinalviththe%ORcorrelation, aeatiatics eachthatthoroiaatLaaataNyorcancyrohabiliey WebaS5yoraantconfi4aaco L~Lthateha~~~foreheLidiCQ1$rolikgz04eatchasos~tSacalculatal 4eaiyaLiaieCAR.Theuacereatneiae iotheabeleylantyaraaeeaca arouao4e-4ata~La4ehejlan!MRRuncareainey.

shiaRRuncertaiaey, coabine4vith~~cerrelaC4lc acaCL4CLcs, catahliahee alaa~OAR~Sov5$chQJstbeIocinplantaafacyanalysesmeggy~ueaofigyggyarg~geerg

~theetuncortaineiaa

<or~ktueLaaefiaeeCaid2,ehe4aaiyaNSRmbseaorVanea5-fhaeL~thhshloaoeiffelIIaktf,eioo, earyooSafer.anal~aceeaaafacf1Xatt~Theaaeginboeraaeeh>>4aaigaanlaafaey<<nalyaiaLiiie~++M"+~'Cae4~~e~pa'QQRyonaLeiaa (S.e.,ezanaitioe coroyonaltioa.

ro4box,otalm4~de051Raaronforoyorath~anlCaaiyiflaxiMLf.<.

Thec~offiysto2.1LahevehoLociofyoineeof5RRttaL8$ZR,coactorCoolant5ystaayraaeae,anlcveraiasaeycraeuza meleeMchehecalculatat DIIRQneleaethanehe4aiiyaNRLUsit~aluNettheareraSeanthaljyateheveaae1ad,tiaLaaathantheonehalyyofaaeuratal Liqs44-coecmmucnrut-asia2j20Lgmma2CHo.$2,>>

LIMIT:NOS~SermonSETTINCShASESOverlayer DeltaTTheOverpover DeltaTreactortripprovidesassurance offuelLnteg:Lg, e.g..noaelcing,underallpossibleoverpover conditions.

linitsthezequLredrangeforOvertaarpetasuze DeltaIproceccion, andprovidesabackuptothaHighNeutronFluxcriy.Thesecpointincludaacorrections fotchangesLndensityandheatcapac'Lty afvatezvithtemperature an447tL1liccaepensatLan farpipingdelaysfteathecoretothelooteerasuredetectors.,

reace~Qpe(I'~4-uf~.durcandisifo~fuloverecures~safeyais.avezpaver deltaTreactort-pprovidesprocacconoaceuyprateoforat-paversteanL&ebreakevents.Czedicvastakenforoyetation ofchisttipLnthestaaaLLnebreakness/energy releasesoutsidecantaimaent analysis.

Inaddition.

Ltsfunctional capability acthespecified trapsassingLssquiredbythisspecif'cacion taenhancesheoverallreliability oftheReactorPrataosian Systen.PressurierPressureThePressurizer HighandLovPressurestiyaateytavi4e4coLinistheyressuzerangeinvhichreactoroperation Lspermitted.

TheHighPressuret=ipLsbackedupbychepressurizer codesafetyvalvesfotLC5avezytessuze procection.

andLstherefore sacloverchanchesecptessuzefotthesevalves(24~5psig).TheHLghPzaasut~ttiyprovidesprotection fotaLossofExternalLoadevent.TheLevPteaauzeczipprovidesprotsc'anbyc:Lppingchereactor'n theevensofalossofreactotcoolantpressure.

Pressur'=er PeterLevelThePressurizer HighQatarLeveltripensuresprotection against~actorCoolantSyateeovetyreasuzizasion bylimitingthevatatlaveLcoavolunesufLcienscoretainaac44$bubblean4preventvasarreliefthtoughchepressurizer safetyvalves.Thepteasuzizar highvaserlevelcr'ypteclu4es vatesrelieffottheuncontrolled controlrodassumably bankvithdzaval at~paverevensCaeCNUCme,tOet-UNIT2a2-5~g)gyreHO.jZ.LJS

&~XXGTaCÃSASK/:(Canthus)

~~fl~racaM42areSeaigget, nogtQg+aaaL aLLovagceg aaaeceaa~priorcocoeyartaoc+~

~limitalofgpectftcacSyc 3.2.3Neaaureaet erroraof2.1%forRCXCIectocaLfleegaeaancL44forg~ebeeaallow@forLadaeazakaactoa efthedeatgalMRralua404tathiswca~ctoaofahaLOC~CCfLtmtc..becveeo~Safest454%7etmQgggkCREEtheSkatesLtitcMS'aIaQlcaL044 (Safe'cg48417$eaCAR@:L-Ctm4L.CLfottheVaacage5typicalandLecalla,reapeccSmL DeathLimit411cajoehreapecttveL 4iTacKoc~sar$$0coaocooodkca appltcabIC.IWlt~~~1>>LTfVantage5fueL(equaicoL.3%per~ICAL,Ear.1).Thereaatader ogtheaarginbeateen4eaiyleelaafa~aaaL7itaNRL~tacanbeuaa4forper.death'sflexibtlt ty.

34.2POWERDISTIBUTION LIMITSBASES34.2.4UADRANTPOWERTILTRATIOThequadx'anc pavercflcratiolimitassuresthattheradialpoverdistribution sacfsfies chedesignvaluesusedinchepovarcapability analysis.

Radialpovexdistribution measurements aremadeduringstartuptestingandperiodically duringpoveroperatfon.

Thelimitof1.02atvhfchcorrective actionisrequiredprovidesDNBandlinearheatgeneration rateprotection vithx-yplanepavertilts.Thetvohourtimeallovance foroperation vithatiltcondition greaterthan1.02butlessthan1.09fsprovfdedtoallovidentfffcatfan andcorrectfon ofadroppedormfsalfgned x'od.Intheeventsuchactiondoesnotcozrectthetilt,themarginforuncertainty onFfsreinstated byzeducfngthepoverby3percentfzomRATEDTHERMALPOWERfeareachpercencoftiltfnexcessof1.0.34.2.5DNBPARAMETERS elimitsantheDNB-xelated parametezs ensurethateachoftheparametearemaintained vichfnthenormalsteady-state envelopeopex'ation aedinchetransient andaccidentanalyses.

Th.lessthanorequalto57.Fandpressurizer pxessuregreaterthanequaY.to22000avgpsfgareconsfstenc ththeUFSARassumptions andhaeenanalytically demonstrated adequatemaintainthecoreatorvethedesignDNBRthraughout eachanalyzedtiencvfthallovefoz'easurement uncertainty.

TheTgreateranoreqco543.9Fisconservative toa0safetyanalysispezfoRned todemonthattheplantmayoperateonalineazcontz'olprogramvheretheaycallimitofTat1008RATEDTHERMALPOWERmayxangefxom5.4Fto51F.The1Y5itof543.9F'contains amarginof1.1FThecoremaybeoratedvithindicated vesselaveragetcmperacuze atyvaluebetveentheuppendloverlimits.Pressurizer pressuislimitedcoasinglenominalsoint,viththeloverlimitofchefcacedvaluesetpofntsetforthinthespficacfons.

TheT/Svalueselectedforconsistency vithUnit1andcontaamarginof6psi.elimitsareconsistent vfththeUFSARassumptions andvebeenanticallydemonstxaced tobeadequatetomaintainthecoxeatorvethepplfcable designlimitDNBRvaluesforeachfueltype,(which arelfstechebasesforSectfan2.1.1)throughout eachanalyzedtransient.

1AMENDMENT NO.82.134COOKNUCLEARPLANT-UNIT2B3/42-5The12hourperiodicsurveillance oftheseparameters throughinstrumenc

'eadoutissufficient toensurechacthepazameters arerestoredvithintheirlfmitIfolloving loadchangesandocherexpectedtransient operation.

The12-hoursurveillance oftheRCSflowmeasuremenc fsadequatetodecectflovdegradation.

TheCHANNELCALIBRATION perfarmed afterrefueling ensurestheaccuracyaftheshfftlyflowmeasurement.

Thetotalflovfsmeasuredaftereachrefueling basedonasecondary sidecalorimetric andmeasurements ofprimarylooptemperacures.

INSERTAThelimitsontheDNB-related parameters ensurtheparameters aremaintained withinthenormalenvelopeofoperation assumedinthetransient analyses.

TheT,lessthanorequalto583.3Fpressuregreaterthanorequalto2200psigthateachofsteady-state andaccidentdpressurizer fornominal(pressurizer operating pressureof2235psig)or2050psig(fornominalpressurizer operating pressureof2085psig)areconsistent withtheUSFARassumptions andhavebeenanalytically demonstrated adequatetomaintainthecoreatorabovethe'esign DNBRthroughout eachanalyzedtransient withallowance formeasurement uncertainty.

Pressurizer pressureislimitedtoeitheroftwonominaloperating pressures of2235psigor2085psig,withthecorresponding indicated limitssetforthinthespecifications.

Thelimitsareconsistent withtheUFSARassumptions andhavebeenanalytically demonstrated tobeadequatetomaintainthecoreatorabovetheapplicable designlimitDNBRvalueforthecurrentfueltypethroughout eachanalyzedtransient.

J ACTORCOOLANTSYSTEMBASES34.4.9PRESSURETEMPERATURE LIMITSIAllcomponents intheReactorCoolantSystemaredesignedtowithstand theeffectsofcyclicloadsduetosystemtemperature andpressurechanges.Thesecyclicloadsareintroduced bynormalloadtransients, reactortrips,andstartupandshutdownoperations.

Thevariouscategories ofloadcyclesusedfordesignpurposesareprovidedinSection4.1.4oftheFSAR.Duringstartupandshutdown, theratesoftemperature andpressurechangesarelimitedsothatthemaximumspecified heatupandcooldownratesareconsistent withthedesignassumptions andsatisfythestresslimitsforcyclicoperation.

AnZDorODone~arter thickness surfaceflawispostulated atthelocationinthevesselwhichisfoundtobethelimitingcase.Thereareseveralfactorswhichinfluence thepostulated location.

Thethermalinducedbendingstressduringheatupiscompressive ontheinnersurfacewhiletensileontheoutersurfaceofthevesselwall.Duringcooldown, thebendingstressprofileisreversed.

Znaddition, thematerialtoughness isdependent uponirradiation andtemperature andtherefore, thefluenceprofilethroughthereactorvesselwall,therateofheatupandalsotherateofcooldowninfluence thepostulated flawlocation.

Theheatuplimitcurve,Figure3.4.2,isacomposite curvewhich=waspreparedbydetermining themostconservative case,witheithertheinsideoroutsidewallcontrolling, foranyheatuprateupto60'Fperhour.ThecooldownlimitcurvesofFigure3.4-3arecomposite curveswhichwerepreparedbaseduponthesametypeanalysiswiththeexception thatthecontrolling locationisalwaystheinsidewallwherethecooldownthermalgradients tendtoproducetensilestresseswhileproducing compressive stressesattheoutsidewall.Theheatupandcooldowncurveswerepreparedbasedonthemostimitingvalueofthepredicted adjustedreference temperature attheendofEFPY.t9.8'hereactorvesselmaterials havebeentestedtodetermine theirinitialRTmn.'heresultsofthesetestsareshowninTableB3/4.4-1.Reactoroperation andresultant fastneutron(E>1MeV)irradiation willcauseanincreaseintheRT~.Therefore, anadjustedreference temperature mustbepredicted inaccordance withRegulatory Guide1.99,Revision2.Thisprediction isbasedonthefluenceandachemistry

-factordetermined fromoneoftwoPositions presented intheRegulatory Guide.position(1)determines thechemistry factorfromthecopperandnickelcontentofthematerial.

Position(2)utilizessurveillance datasetswhichrelatetheshiftinreference temperature ofsurveillance specimens tothefluence.Theselection ofPosition(1)or(2)ismadebasedontheavailability ofcrediblesurveillance data,andtheresultsachievedinapplyingthetwoPositions.

COORNUCLEARPLANT-UNIT203/44-6AMENDMENT NO.69i,~,17),

REACTORCOOLANTSYSTEMBASESTheactualshiftinthereference temperature ofsurveillance specimens andneutronfluenceisestablished periodically byremovingandevaluating reactorvesselmaterialirradiation surveillance specimens anddosimetry installed neartheinsidewallofthereactorvesselinthecorearea.TheheatupandcooldownlimitcurvesofFigures3.4-d3.4-3predicted adjustments forthisshiftinRT~attheendofFPY,asadjustments f'rpossibleerrorsinthepressureandemperature instruments.

TheEFPYheatupandcooldowncurvesweredeveloped basedfollowing:

includewellassensingonthe1.Theintermediate shellplate, C5556-2,isthelimitingmaterialasdetermined byposition1ofRegulatory Guide1.99,Revision2,withaCuandNicontentof0.15%and0.57%,respectively.

2~Thefluencevaluescontained inTable6-14ofWestinghouse WCAP-13515 report,"Analysis ofCapsuleUFromtheIndianaMichi,gan Po~erCompanyD.C.CookUnit2ReactorVesselRadiation Surveillance Program",

datedFebruary1993.TheRT~shiftofthereactorvesselmaterialhasbeenestablished byremovingandevaluating thereactormaterialsurveillance capsulesinaccordance withtheremovalscheduleinTable4.4-5.Perthisschedule, CapsuleUisthelastcapsuletoberemoveduntilCapsuleSistoberemovedafter32EFPY(EOL).CapsulesV,W,and2willremaininthereactorvesselandwillberemovedtoaddressindustryreactorvesselembrittlement

concerns, ifrequired.

Thepressure-temperature limitlinesshownonFigure3.4-2forreactorcriticality andforinservice leakandhydrostatic testinghavebeenprovidedtoassurecompliance withtheminimumtemperature requirements ofAppendixGto10CFR50.Thenumberofreactorvesselirradiation surveillance specimens andthefrequencies forremovingandtestingthesespecimens areprovidedinTable4.4-5toassurecompliance withtherequirements ofAppendixHto10CFRPart50.Thelimitations imposedonpressurizer heatupandcooldownandspraywatertemperature differential areprovidedtoassurethatthepressurizer isoperatedwithinthedesigncriteriaassumedforthefatigueanalysisperformed accordance withtheASMECoderequirements.

TheOPERABILITY oftwoPORVs,orofonePORVandtheRHRsafetyvalveensuresthattheRcswillbeprotected frompressuretransients whichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsarelessthanorequalto1524F.EitherPORVorRHRsafetyvalvehasadequaterelieving capability toprotecttheRCSfromoverpressurization whenthetransient islimitedtoeither(1)thestartofanidleRCPwiththesecondary watertemperature ofthestemgenerator lessthanorequalto50'FabovetheRCScoldlegtemperatures of(2)thestartofachargingpumpandinjection intoawatersolidRCS~Therefore, anyoneofthethreeblockedopenPORVsconstitutes anacceptable RCSventtoprecludeAPPLICABILITY ofSpecification 3.4.9.3.34.4.10STRUCTURAL INTEGRITY Theinspection andtestingprogramsforASMECodeClass1,2and3components ensurethatthestructural integrity ofthesecomponents willbemaintained atanacceptable levelthroughout thelifeoftheplant.Totheextentapplicable, theinspection programforthesecomponents isincompliance withSectionXZoftheASMEBoilerandPressureVesselCode.COOKNUCLEARPLANT-UNIT2B3/44-10AMENDMENT NO~89,~i15ki171

(Conabu~d) allovectccnnpla&on tineaarecaasonabla, buedonoperactng experience, toreachcherequiredplantconditions

&mfuLLpowercoaditioaa inanorderlyearnerandvichoucchaLLcagiag planeaystaaa.Ifnor~thanoneaocuasulator Sainoperable, theplantisfnacondition outside.thaaccidentanalyau;therefore, LCO3.0.3axscbeenteredSaaediataly.

~~adbsuesadecreaseacceptable LhxjtsinTheOPD4QZLITY ofacoindependent ECCSaubaystaas ensuruthatsufhcient

~nergencycot'acoolLagcapability vtLLbearailabla inthacraneofaQKAassumingtheLoaaofoneaubsyctaa tbr~hanyaislefailureconsideration.

Eitheraubayssea operaetng inconjunction viththeatamxlacncs iadapablaofsupplying audientcoracoolingtoLimitthepeakcladdhrg~ieracuras

&chinacceptable XfsicaforaLLpoatulatad breakaixaaragtagfroathedoubleendedbreakoftheLargestPCScoldLegpipedoenaar4.

Inaddi~,eachECCSII!doaCagtheaccLdeacrecoveryperiod.45EEis~ooc?M$clE01$,tvolinestheLosscfonesafa@lefailureco'tion.TheresnlTHERMhLQuoitthetaspezstnra theerencapostulated aaallbreakQÃlCOOKNQC~~PLhHTUHlT255/45-4CTHO.~I69,

CONTAIHMEHTSYSTEMSBASES3/4.6.1.4 INTERNALPRESSUREThelimitations oncontainment internalpressureensurethat1)thecontainment structure isprevented fromexceeding itsdesignnegativepressuredifferential withrespecttotheoutsideatmosphere of8psigand2)thecontainment peakpressuredoesnotexceedthedesignpressureof12psigduringLOCAconditions.

Themaximumpeakpressureisresvl6nfromaLOCAevent~lcolaWd+++asf4~MdcS\qm4vQK+Ipsgq0+i'-lv~itic'Ivies 0.$pstggeelacuna(.3/4.6.1.5 C.IRTEMPERATURE The'limitations oncontainment averageairtemperature ensurethat1)(thecontainment airmassislimitedtoaninitialmasssufficiently lowtopreventexceeding thedesignpressureduringLOCA'conditions and2)theambientairtemperature doesnotexceedthattemperature allowable forthecontinuous dutyrating.specified forequipment andinstrumentation locatedwithincontainment.

Thecontainment pressuretransient issensitive totheinitially contained airmassduringaLOCA.Thecontained

.airmassincreases withdecreasing temperature.

Thelowertemperature limitof60'FwilllimitkPPP~tItktdtgpressureof12psig.The'upper temperature limitinfluences thepeakaccidenttemperature slightlyduringaLOCA;however,thislimitisbasedprimarily uponequipment protection andanticipated operating conditions.

Boththeupperandlowertemperature limitsareconsistent withthepara-metersusedintheaccidentanalyses.

3/4.6.1.6 CONTAIHMEHT STRUCTURAL INTEGRITY Thislimitation ensuresthatthestructural integrity ofthecon-tainmentw'illbemaintained comparable totheoriginaldesignstandards forthelifeofthefacility.

Structural integrity isrequiredtoensurethat(1)thesteellinerremainsleaktightand(2)theconcretesurround-ingthesteellinerremainscapableofproviding externalmissileprotec-tionforthesteellinerandradiation shielding intheeventofaLOCA.Avisualinspection inconjunction withTypeAleakagetestsissufficient todemonstrate thiscapability.

(yqO43CONDENSATE STOGETANK~allowance forwaternotusablebecauseoftankdischarge linelocationorotherphysicalcharacteristicsis m+cello'i~.

u5~.TheOPERABILITY ofthecondensate stagetankwiththemnimumwatervolumeensuresthatsufficient waterisavilabletomaintaintheRCSatHOTSTANDBYconditions for9hourswithsteamdichargetotheatmosphex concurrent withtotallossofoff-sitepower.TheA4CTVITYThelimitations onsecondary systemspecificactivityensurethattheresultant off-siteradiation dosewillbelimitedtoasmallfractionof10CFRPart100limitsintheeventofasteamlinerupture.Thisdosealsoincludestheeffectsofacoincident

1.0 gpmprimarytosecondary

tubeleakinthesteamgenerator oftheaffectedsteamline.Thesevaluesaxeconsistent withtheassumptions usedintheaccidentanalyses.

45SGENERATOR STOPVALVESTheOPERABILITY ofthesteamgenerator stopvalvesensuresthatnomorethanonesteamgenerator willblowdownintheeventofasteamlinerupture.Thisrestriction isrequiredto1)minimizethepositivereactivity effectsoftheReactorCoolantSystemcooldownassociated withtheblowdown, and2)limitthepressurerisewithincontainment intheeventthesteamlineruptureoccurswithincontainment.

TheOPERABILITY ofthesteamgenerator stopvalveswithintheclosuretimesofthesurveillance requirements

.areconsistent withtheassumptions usedintheaccidentanalyses.

Withonesteam'enerator stopvalveinoperable inMODE1,actionmustbetakentorestoreOPERABLEstatuswithin8hours.'ome repaizstothevalvescanbemadewiththeunit.hot.The8hourcompletion timeisreasonable, considering thelowpxobability ofanaccidentoccuzring duringthistimeperiodthatwouldrequireaclosureofthesteamgenerator stopvalves.Ifthesteamgenerator stopvalve.cannotberestoredtoOPERABLEstatuswithin&hours,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,theunitmustbeplacedinMODE2within6hoursandtheMODES2and3actionstatement entered.Thecompletion timesarereasonable, basedonoperating experience, toreachMODE2andtoclosethesteamgenerator stopvalvesinanorderlymannerandwithoutchallenging unitsystems.COOKNUCLEARPLANT-UNIT2B3/47-3AMENDMENT NO.m,170

ATTACHMENT 4TOAEP:NRC:1223 SUMMARYDESCRIPTION OFPROPOSEDUNIT2POWERUPRATETECHNICAL SPECIFICATIONS IIl Attachment 4toAEP:NRC:1223 Page1KeyforSummaryTablePageSectionTechnical Specification PageTechnical Specification GroupRelatedGroupsDiscussed inAttachment 1,Description ofProposedChangesand10CFR50.92Significant HazardsConsideration AnalysisUprateGroup1,ChangesDirectlyRelatedtoIncreased ratedthermalpowerHHSIGroup2,ChangetoRemovePowerRestriction forHighHeadSafetyInjection CrossTiesClosedOperation MarginGroup3,ChangesProposedtoIncreaseUnit2Operating MarginTransition Group4,ChangesRelatedtoTransition CoreorTransition toTemperature Window/Dual PressureTechnical Specifications Both'roup 5,ChangesProposedforbothunits.AdminGroup6,Administrative ChangeDescription RemarksABriefDescription ofEachProposedChangeBriefCommentswithaCrossReference totheAnalysesNotethatallchangesare~onlforunit2unlesstheyareincludedinthe"both"group.Thechangesinthisgroupareproposedforbothunit1andunit2ofCookNuclearPlant.

(i Attachment 4toAEP:NRC:1223 Page2Page2-2Section1.3Figure2.1-1Group.UprateMarginDescription Increaseratedthermalpowerto3588MNt.ReviseReactorCoreSafetyLimitsRemarksThesupportforthisproposedchangeconsistsofanalysesthathavebeenperformed overaperiodofyears.Including thenewanalyses, whicharedescribed inAttachment 6,NCAP14489,andtheevaluations described inAttachment 7,BalanceofPlantEvaluations andMiscellaneous SafetyEvaluations, allthenecessary analysesandevaluations havebeencompleted tosupportanuprateofUnit2toacorepowerof3588MNt.Thenewanalysesandsummaries ofearlieranalysesandevaluations performed byWestinghouse ElectricCorporation forthenuclearsteamsupplysystem(NSSS)aredescribed inNCAP14489.Theimpactofrecentmodelchangeson.thenewanalysesisdiscussed inAttachment 1underGroup1changesaswellasinAttachment 6.Attachment 7describes balanceofplantevaluations andmiscellaneous safetyevaluations.

Sincetheanalyseswhichsupporttheupratedpowerhavebeenperformed overaperiodofyears,Attachment 5isprovidedtodescribethehistoryofearlieranalysesandtoidentifythesubmittal ofearlierworkandtheassociated SER's.Thereviewstatusoftheanalysessupporting theupratedcorepowerisdiscussed inAttachment 1underGroup1changesandinAttachment 5.TheSafetyLimitFigurecurrently intheUnit2Technical Specifications wasdesignedforamixedcoreofWestinghouse andAdvancedNuclearFuel.TheUnit2corenowconsiststotallyofWestinghouse Vantage5fuel.Thenewthermaldesignisdiscussed inSection3.3.2.1ofAttachment 6WCAP14489'heproposedSafetyLimitFigureisconsistent witharatedthermalpowerof3588MWtandanallVantage5core.

Attachment 4toAEP:NRC:1223 Page3Page2-5SectionTable2.2-1FootnoteGroupAdminDescription RedefinedesignflowinfootnoteofTable2.2-1tobe1/4MMF.RemarksMinimumMeasuredFlow(MMF)isReactorCoolantSystemTotalFlowRateofT.S.3.2.5.MMFisuseddirectlyintheDNBanalysesasdiscussed inSection3.3.2.1ofAttachment 6,WCAP14489.MMFis1'35timesthermaldesignflow(TDF).Therefore, theMMFemployedintheDNBanalysisis1.035timesTDF.TDFisspecified inSection3.3.3.1ofWCAP14489.TDFisgenerally usedinno-DNBanalyses.

See,forexample,WCAP14489tables3.1-7and3.1-13.Alower(loop)TDFisindicated inTable3.5-1becausethecontainment analysisboundsbothunitsandUnit1isanalyzedforaStflowasymmetry.

Designflowincurrenttechnical specification Table2.2-1isloopMMFortotalMMF/4.2-72-72-7Table2.2-1MarginTable2.2-1MarginTable2.2-1MarginTheupperlimitonT'ncreased to581.34Ftoreflectanalyses.

Bothanalyzed, nominalRCSpressures, 2235psigand2085psig,areindicated.

Tau1reducedfrom28secsto22secs.NewOTDTandOPDTsetpoints havebeencalculated tosupportoperation ataratedthermalpowerof3588MWtwithallWestinghouse Vantage5coreswhicharecurrently beingusedinUnit2.K1wasincreased fromitscurrentvalueof1.09to1.17therebysigni,ficantly increasing loadrejection margin.Thevalue1.17wasselectedtoallocatesomemargintoinstrumentation, increased allowance forcoreburnupeffectssuchaschangesinhotlegstreaming, andanincreaseinthepositive~Ibreakpointforthef(~I)penalty.Increased loadrejection marginwasalsoobtainedbyreducingtau1from28secondsto22seconds.TheanalysisvalueofK4wasalsoevaluated toobtainincreased marginforburnupeffects.TheOTDTandOPDTtripsarediscussed inSection3.3.2.1ofWCAP14489.Details,including T',T',andtimeconstants oftheanalyzedsetpoint, areinTable3.3-4ofWCAP14489.Duetotheanalysisperformed fortransition coresofbothWestinghouse andAdvancedNuclearFuel,lowpressureoperation wasnotpermitted foroperation withmixedcoresofWestinghouse andAdvancedNuclearFuel.Thebasisforthislimitation isdiscussed inSection"Group4"ofAttachment 1.Unit2iscurrently operatedwithcoresofallWestinghouse Vantage5fuel.Therefore, lowpressureoperation isacceptable.

SeeremarkonincreaseofT'pperlimitonpage2-7.

Attachment 4toAEP:NRC:1223 Page4PageSectionGroupDescription Remarks2-82-82-82-82-9Table2.2-1MarginTable2.2-1MarginTable2.2-1MarginTable2.2-1MarginTable2.2-1MarginIncreaseKlfrom1.09to1.17.IncreaseK2from0.01331to0.0268IncreaseK3from0.00058to0.00111Changef(al)penalty.Maintaintheupperlimit.onTat576oFtoreflectanalyses.

SeeremarkonincreaseofT'pperlimitonpage2-7.SeeremarkonincreaseofT'pperlimitonpage2-7.SeeremarkonincreaseofT'pperlimitonpage2-7.SeeremarkonincreaseofT'pperlimitonpage2-7.Thisitemisnotachange.However,duetothefactthat5764Fisnotthemaximumanalyzedtemperature ofthetemperature window,itisappropriate toidentifythefactthattheupperlimitonTisbeingdeliberately maintained atitscurrentvalue.2-9Table2.2-1MarginChangetheallowable valuesinnotes3and4.CookNuclearPlantUnit2isoperatedatemperature significantly lowerthanthemaximumanalyzedtemperature.

Therefore, theOPDTsetpointwasanalyzedwithalowupperlimitonTtoconvertunusedmargintooperating margin.TheOPDTtripisdiscussed inSection3.3.2.1ofWCAP14489.Details,including T,oftheanalyzedsetpointareinTable3.3-4ofWCAP14489.Thevaluesindicated inthemarkupsof'Attachment 3andintheproposedtechnical specifications ofAttachment 2werecalculated byourorganization usingtheWestinghouse "stepit"methodology described inWCAP-12741.

Thisisthesamemethodology usedforthecalculation ofallexistingReactorTripandEngineered SafetyFeatureActuation Setpoints.

Thismethodology isconsistant withtherequirements ofISAStandardS67.04.

Attachment 4toAEP:NRC:1223 Page5Page3/42-15SectionSection3.2.5GroupTransitionDescription IncreaseDNBtemperature limitfrom578.74Fto583.30F.RemarksDuetotheanalysisperformed fortransition coresconsisting ofbothWestinghouse fuelandAdvancedNuclearFuel,themaximumnominalTavgwaslimitedto576Fforoperation withmixedcoresofWestinghouse andAdvancedNuclearFuel.Unit2iscurrently operatedwithcoresofallWestinghouse Vantage5fuel.Therefore, thefullanalyzedtemperature windowanalyzedforanallVantage5coreisacceptable.

TheDNBtemperature limitisobtainedbyaddingthecontroller allowance tothehighnominalTavgusedintheanalysisandthensubtracting thereadability allowance.

ThehighnominalTavgforafullVantage5coreis581.34Fandthecontroller allowance is4.1oF.ThesevaluesarefoundinTable3.3-1andSection3.3.3.1ofWCAP14489,respectively.

Thereadability allowance, calculated byAEPSC,is2.1F.Theresulting DNBtemperature limitis583.3OF.ThehighnominalTavgforafullVantage5coreisidentified intheVantage5ReloadTransition SafetyReportforCookNuclearPlantUnit2(RTSR),reference 11ofAttachment 5.RTSRwassubmitted viareference 13ofAttachment 13ofAttachment 5.Operation ofUnit2withWestinghouse fuelwasapprovedinreference 17ofAttachment

5.

Attachment 4toAEP:NRC:1223 Page6Page3/42-153/42-153/43-23SectionSection3.2.5Section3.2.5Table3.3-4GroupTransitionTransitionTransitionDescription DNBpressurelimitsforbothanalyzednominalRCSpressures, 2200psigand2050psig,areindicated.

Removereference tolowtemperature limitinordertoreturnthespecification toapurelyDNBspecification.

Reducesafetyinjection actuation setpointonlowpressurizer pressureto1815psig.RemarksDuetotheanalysisperformed fortransition coresconsisting ofbothWestinghouse fuelandAdvancedNuclearFuel,lowpressureoperation wasnotpermitted foroperation withmixedcoresofWestinghouse andAdvancedNuclearFuel.Thebasisforthislimitation isdiscussed inSection"Group4"ofAttachment 1.Unit2iscurrently operatedwithcoresofallWestinghouse Vantage5fuel.Therefore, lowpressureoperation isacceptable.

TheDNBpressurelimitisobtainedbysubtracting thetotalpressureallowance usedintheanalysisfromthenominaloperating pressureusedintheanalysisandthenaddingthereadability allowance.

Thenominalpressures andthetotalallowance arefoundinSection3.3.1and3.3.3.1ofWCAP14489,respectively.

Thereadability allowance, calculated byAEPSC,is18.9psi.Thepressurelimitcurrently intheT/Ssforhighpressureoperation isconservatively higherthanthecalculated valueof2191psig.Theproposedlimitof2050psigforlowpressureoperation isanaddition.

Ztisconservatively higherthanthecalculated valueof2041psig.Theproposedvalueforthelowpressurelimitisthesameastheunit1limit.TheproposedchangeconvertstheDNBspeci.fication backtoapurelyDNBspecification.

Thisproposalisdiscussed furtherinAttachment 1.Additional margintotripforsafetyinjection onlowpressurizer pressurewasneededasdiscussed inthedescription ofchangesforGroup4ofAttachment 1.Therequiredevaluations tolowerthesafetyanalysisvalueforthesetpointhavebeenperformed asdiscussed inSections3.3.4.5and3.3.4.6ofWCAP14489.ThenominalTechnical Specification setpointproposedisthesameasthecorresponding setpointforUnit1.Th'einstrument allowances calculated byourorganization supportthisnominalsetpoint.

Attachment 4toAEP:NRC:1223 Page7Page3/43-233/43-23SectionTable3.3-4Table3.3-4GroupTransitionTransitionDescription Changeallowable valueforsafetyinjection actuation setpointonlowpressurizer pressureto1805psig.Reducesafetyinjection actuation setpointonlowsteamlinepressureto500peig.RemarksThevalue1805psig,indicated inthemarkupsofAttachment 3andintheproposedtechnical specifications ofAttachment 2,isconservative tothevaluethatwascalculated byourorganization.

Etisconsistent withvalueforunit1andisproposedinordertomaketheTechnical Specifications ofthetwounitsmoresimilar.Atthetimeofthetransition fromAdvancedNuclearFueltoWestinghouse fuel,thereanalysis ofmassandenergyrelease(M&E)outsidecontainment forreratingandreducedtemperature/reduced pressureoperation wasnotcomplete.

Theevaluation ofthethenapplicable analysisassumedanNSSSpowerof3425MWtandanominalsetpointforlowsteamlinepressurenolessthan520psig.TheAEPSCanalysisoftheimpactofthesteamlinemassandenergyrelease(SM&E)outsidecontainment ontheoperabilit ofequipment inthemainsteamenclosures, at3588MWtcorepower,wasdescribed andsubmitted inreference 24ofAttachment 5.Reference 24wasourproposaltooperatebothunitswith0ppmboronconcentration intheboroninjection tank(BZT).TheSHEEwasanalyzedconsistently withtheproposedsafetyinjection setpointonlowsteamlinepressure.

Themassandenergyreleaseportionofthisanalysisisdiscussed inSection3.3.4.7ofWCAP14489.Thecoreresponsesteamline andfeedwater linebreakssubmitted withtheRTSRsupporttheproposedsetpoint.

Thereferences fortheRTSR,itssubmittal, andapprovalare11,13,and17ofAttachment 5.Evaluations oftheseanalysesarediscussed inSections3.3.4.6and3.3.4.7ofWCAP14489.TherevisedSM&Ereleaseanalysistocontainment alsosupportstheproposedsetpoint.

Thisanalysisisdiscussed inWCAP14285,reference 29ofAttachment 5.WCAP14285wassubmitted viareference 30ofAttachment 5.Ztisnotyetapproved.

Thisanalysisissummarized, inSection3.5.4ofWCAP14489.

Attachment 4toAEP:NRC:1223 Page8Page3/43-233/43-253/43-253/44-43/44-43/44-53/44-5SectionTable3.3-4Table3.3-4Table3.3-4Section3.4.2Section3.4.2Section3.4.3Section3.4.3GroupTransitionTransitionTransitionMarginBothMarginBothDescription Changeallowable valueforsafetyinjection actuation setpointonlowsteamlinepressureto480psig.Reducesteamlineisolation actuation setpointonlowsteamlinepressureto500psig.Changeallowable valuefoxsteamlineisolation actuation setpointonlowsteamlinepressureto480psig.IncreasePressuxizer ValveSetpointTolerance to3%..Addfootnoterequiring anaslefttolerance of1%.IncreasePressurizer ValveSetpointTolerance to3%.Addfootnoterequiring anaslefttolerance of1%.RemarksThevalue480psig,indicated inthemarkupsofAttachment 3andintheproposedtechnical specifications ofAttachment 2,isconservative tothevaluethatwascalculated byourorganization.

Itisconsistent withvalueforunit1andisproposedinordertomaketheTechnical Specifications ofthetwounitsmoresimilar.Seeremarkonreduction ofsafetyinjection actuation onlosteamlinepressureonpage3/43-23.Seeremarkonthechangeofallowable valueforsafetyinjection actuation setpointonlowsteamlinepressureonpage3/43-23.TheNon-LOCAaccidents werereanalyzed orreevaluated basedonapressurizer valvesetpointtolerance of3%.Thisisnotedinsection1.1and3.3.2.2ofWCAP14489.Theanalysesaffectedarediscussed inSections3.3.4.3,3.3.4.4,3.3.4.6,3.3.5.1,and3.3.5.2ofWCAP14489.Thisrequirement isconsistent withasimilarrequirement whichwasapprovedforthemainsteamsafetyvalves.Itisbeingsubmitted forbothunitsbecauseitwasinadvertently omittedinoursubmittal AEP:NRC:1207, datedMay26,1995,whichincludedtheanalytical justification foranincreaseinpressurizer safetyvalvesetpointtolerance forUnit1.Seeremarkonsetpointtolerance magnitude onpage3/44-4.Seeremarkonasleftsetpointtolerance onpage3/44-4.

j',

Attachment 4toAEP:NRC:1223 Page9PageSectionGroupDescription Remarks3/44-163/44-253/44-263/45-3Section4.4.6.2.1 Figure3.4-2Figure3.4-3Section3.5.2TransitionUprateUprateHHSZPressurecriteriaforbothanalyzednominalRCSpressux'es areindicated.

Reducetheapplicability oftheheatupcurvefrom15to14.5EFPY's.Reducetheapplicability ofthecooldowncurvefrom15to14.5EFPY's.Removepowerreduction currently requiredforoperation withHHSZcrosstievalvesclosed.Duetotheanalysisperformed fortransition coresofbothWestinghouse andAdvancedNuclearFuel,lowpressureoperation wasnotpermitted foroperation withmixedcoresofWestinghouse andAdvancedNuclearFuel.Thebasisforthislimitation isdiscussed inSection"Group4"ofAttachment l.Unit2iscurrently operatedwithcoresofallWestinghouse Vantage5fuel.Therefore, lowpressureoperation isacceptable.

Theapplicability ofthecurrentheatupandcooldowncurvesisdiscussed inSection3.11.2.1ofAttachment 6,WCAP14489.Seethexemarkontheapplicability oftheheatupandcooldowncurvesonpage3/44-25WhentheSBLOCAanalysisperformed tosupportthemainsteasafetyvalvetolerance relaxation to3%wascarriedout,itwasfoundthatapowerreduction wasrequiredtoobtainsatisfactory resultswiththehighheadsafetyinjection (HHSZ)crosstiesclosed.Sincethen,improvements havebeenmadetotheWestinghouse NOTRUMPSBLOCAmodel.Asindicated inthecoverlettertothissubmittal, theSBLOanalysisperformed forthissubmittal wasperformed usingthenewmodel.Theresultsofthisanalysisshowthatanacceptable PCTresultswiththeHHSZcrosstievalvesclosedatacorepowerof3588MWt.TheSBLOCAanalysesaredescribed inSection3.1.2.4ofWCAP14489.3/47-2Table3.7-1UprateLowerthemaximumAllowable PowerRangeSetpoint.

Thesesetpoints arecalculated inaccordance withtheprescription inWestinghouse NuclearSafetyAdvisoryLetter94-001.Znthisprescription, nominalNSSSpowerappearsinthedenominator oftheequationforthesetpoint.

Therefore, theproposedsetpoints wereloweredaccordingly.

Attachment 4toAEP:NRC:1223 Page10PageUNIT13/47-7UNIT23/47-7B2-1B2-5B3/42-4aB3/42-5B3/44-6B3/44-10SectionUNIT1Sections3.7.1.3and4.7.1.3.1 UNIT2Sections3.7.1.3and4.7.1.3.1 BasesSection2.1.1BasesSection2.2.1Bases.Section3/4.2.2and3/4.2.3Bases;Section3/4.2.5BasesSection3/4.4.9BasesSection3/4.4.9GroupBothTransitionMarginTransitionTransitionUprateUprateDescription Changecontained volumetouseablevolume.Removereferences toAdvancedNuclearFuel.Removedetailfromthediscussion oftheOPDTprotection trip.Removereferences toAdvancedNuclearFuel.Removereference tolowtemperature limitinordertoreturnthespecification toapurelyDNBspecification.

Reducetheapplicability oftheheatupandcooldowncurvesfrom15to14.5EFPY's.Reducetheapplicability oftheheatupandcooldowncurvesfrom15to14.5EFPX's.RemarksTheanalysisof3.10.2.5ofWCAP-14489 showsthat174,500gallonsofwaterarerequiredtomaintaintheRCSathotstandbyfor9hours.TheTechnical Specifications currentlrequireaminimumcontained volumeof175,000gallonsofwater.However,duetothefactthatthezeroofthelevelinstrumentation islocatedatthecenterline ofthedischarge pipe,abovethelevelforrequiredNPSH,alltheindicated volumeisuseable.Therefore, theproposedTechnical Specifications arerevisedtoaddressuseablevolume.TheUnit2corenowconsiststotallyofWestinghouse Vantage5fuel.Thediscussion ofthepropernormalization ofTisbeingremoved.Thisinformation isdocumented inSection3.3.2.1ofWCAP14489andwillbecontrolled administratively.

TheUnit2corenowconsiststotallyofWestinghouse Vantage5fuel.Seeremarkonlowtemperature limitonpage3/42-15.Seeremarkontheapplicability oftheheatupcurveonpage3/44-25.Seeremarkontheapplicability oftheheatupcurveonpage3/44-25.

Attachment 4toAEP:NRC:1223 Page11PageB3/45-1aUNIT1B3/46-2UNIT2B3/46-2SectionBasesSections3/4.5.2and3/4.5.3UNZT1BasesSections3/4.6.1.4 3/4.6.1.5 UNIT2BasesSections3/4.6.1.4 3/4.6.1.5 GroupHHSZBothDescription Removepowerreduction currently requiredforoperation withHHSZcrosstievalvesclosed.Changepeakcontainment pressuretoreflectanalysisresult.RemarksSeeremarkonpowerreduction requiredbySBLOCAonpage3/45-3.Discussion ofmaximumcalculated containment pressureisgiveninSections1.2and3.5.2ofWCAP14489.ZtisnotedthattheanalysisboundsbothUnit1and2inSection3.5.2.1andthepeakcontainment pressureisdocumented inSection3.5.3.6.UNIT1B3/47-3UNIT1BasesSection3/4.7.1.3 AdminChangecontained volumetouseablevolume.Seeremarkonchangingcontained volumetouseablevolumepage3/47-7.UNIT1B3/47-3UNIT2BasesSection3/4.7.1.3 I

ATTACHMENT 5TOAEP:NRC:1223 DISCUSSION OFPREVIOUSRELATEDSUBMISSIONS

Attachment 5toAEP:NRC:1223 Page1Introduction TheanalysesthatsupporttheproposedupratingofDonaldC.CookNuclearPlantunit2havebeenperformed overaperiodofyearsinseveralcontexts.

Theanalysisofthenuclearsteamsupplysystem(NSSS)foranNSSSpowerof3600MWtwasperformed inconjunction withanalysestooperateunit1atreducedtemperature andpressure(the"Rerating Program").Mostofthecoreresponseanalyseswereperformed atanupratedcorethermalpowerof3588MWtasapartofthetransition fromAdvancedNuclearFueltoWestinghouse Vantage5fuel.Therecentlysubmitted

analyses, AEP:NRC:1223, tosupportanincreaseinthepermitted levelofsteamgenerator tubeplugging(SGTP)forunit1includesasteammassandenergyrelease(SM&E)analysistothecontainment whichboundsbothunitsat3600MWt.Forthissubmittal, previousNSSSanalysesandcoreresponseanalyseshavebeenreviewed, newanalyseshavebeenperformed wherenecessary, andthebalanceofplant(BOP)evaluated, asdescribed withinthissubmittal, tosupporttheproposaltoincreasethecoreratedthermalpowerto3588MWt.Attachment 6tothissubmittal isWCAP14489.Xtdescribes theanalyses, evaluations, andreviewsperformed byWestinghouse ElectricCorporation andsummarizes earlierworkperformed byWestinghouse ElectricCorporation tosupportanincreased coreratedthermalpowerforunit2.WCAP14489alsodescribes analysesandevaluations performed simultaneously tosupportcertainincreases inoperating marginsuchasincreased setpointtolerance forthepressurizer safetyvalves.Attachment 7discusses balanceofplantevaluations thathavebeenperformed byAEPSCtoassesstheimpactofincreased corepower.Section2.0ofWCAP14489discusses thepreviousworkperformed byWestinghouse ElectricCorporation tosupporttheupratedcorepowerforunit2.Theevaluations described inWCAP14489arebasedontheseearlieranalyses.

Theearlieranalysesaredescribed inReratingProgramWCAP's11902and11902Supplement 1,references 3and10,andintheVantage5ReloadTransition SafetyReportforDonaldC.CookNuclearPlantUnit2,Revision1,March1990(RTSR),reference 11.TheSGTPSMEEanalysisisdescribed inWCAP14285,reference 29.WCAP11902anditssupplement arereferredtoasthe"Rerating Program"inWCAP14489.Thereloadtransition safetyreportisreferredtoas"RTSR"inWCAP14489.Theincreaseinthepermitted levelofsteamgenerator tubepluggingprogramisreferredtoas"SGTPProgram"inWCAP14489.ThereratingProgram,RTSR,SGTPProgram,WCAP14489(theunit2UpratingProgram),

andtheBOPevaluations providethesupportforthissubmittal.

PuoseofAttachment 5Thepurposesof.thisattachment areto:2.indicatethoseaspectsofearlieranalyseswhichhavebeensubmitted forNRCreviewandapproved, indicatethoseaspectsofearlieranalyseswhichhavebeensubmitted forNRCreviewbutarenotyetapproved(Thiscategoryiscomprised oftheSGTPProgram.),

Attachment 5toAEP:NRC:1223 Page23.4~brieflydescribetheearlieranalyses, andprovidereferences forprevioussubmittals andNRCSER'sfortheconvenience ofthereviewer.

Thediscussion ofthisattachment describes submittals forbothunitsbecausemuchofthesupporting analysisforunit2wasperformed toboundbothunits.Submittals primarily forunit1aresometimes supported byanalysesboundingbothunitsand/orincludeTechnical Specifications modifications forunit2.Thefollowing listsummarizes thestatusofanalysisfeaturesofearlieranalyses:

PrincialFeaturesoftheEarlierAnalsesWhichHaveBeenReviewedandArovedbNRC1~2.3.4.5.6.Reducedtemperature operation forunit2.10%degradation fortheRHRandHHSIpumpsforbothunits.Increased MSIVresponsetimeforbothunits.BIT0ppmboricacidconcentration forbothunits.Reducedtemperature andpressureoperation forunit1.Reducedminimummeasuredflowforunit1.PrincialFeaturesoftheEarlierAnalsesWhichHaveBeenSubmitted forReviewButHaveNotBeenAroved(Thesefeaturesareproposedintheunit1increased steamgenerator tubeplugginglimitsubmittal, reference 30.)2.3.4,5.10%degradation forthecentrifugal chargingpumpsforbothunits.MinimumRWSTtemperature of70~Fforbothunits.ShutdownMarginrequirement of1.3%forbothunits.Proposals toincreaseoperating marginforunit1.Analysistosupportoperation ofthespentfuelpoolwithoneunit.operating at3588MWtPrincialFeaturesofThisunit2UrateSubmittal 1.2.3.4.5.Unit2rerateto3588MWt.Increasethetolerance ofpressurizer safetyvalvesetpointto3%forunit2.IncreaseOTaT/OP~T operating margin.Removemixedcorepenalties.

15%degradation forsafetyinjection andRHRpumps.PuoseoftheEarlierAnalsesReratinProramTheearlieranalyseswereperformed toaccomplish anumberofgoals.Thefirstofthesewastopermitoperation ofunit1atreducedprimarytemperature andpressure.

Thebenefitof.operating inareducedprimarytemperature andpressuremodewastoslowthedegradation oftheunit1steamgenerators.

Inaddition, sinceessentially alloftheanalyticbasisoftheCookNuclearPlantunitshadtobereviewedorrevised,analyseswereperformed topositionunit1forsubsequent upratingto3413MWtcorepowerandunit2to3588MWtcorepower.Themarginformerlyintendedtobeallocated toapotential unit1upratewassubsequently allocated toanincreased steamgenerator tube

Attachment 5toAEP:NRC:1223 Page3plugginglimitintheunit1increased steamgenerator tubeplugginglimitsubmittal, reference 30.Theearlieranalysesalsosupported increased operating marginsinselectedareas.Amongthesewereincreased allowable ECCSpumpdegradation, reduction ofrequiredshutdownmargin(SDM),areduction intheminimumtemperature oftherefueling waterstoragetanks(RWST),reduction tozerooftheboronconcentration intheboroninjection tanks(BIT),andslowerresponsetimesforcertaincomponents andsystemswhichappliedtounit2.DescritionandReviewHistoofPriorSubmittals Thissectiondescribes theprioranalysesfortheCookunitsinessentially chronological orderwithanemphasisonunit2.Thefirstoftheearlieranalysesisdescribed inreference 1,WCAP-11908, "Containment Integrity AnalysisforCookNuclearPlantunits1and2."Itwassubmitted forNRCreviewbyreference 2.Reference 1presented alongtermcontainment analysiswhichboundedbothunitsatacorepowerof3413MWt,operation atareducedtemperature andpressure, andoperation oftheECCSwithresidualheatremoval(RHR)crossties closed.Sincetheanalysisdescribed inreference 1wasperformed, twonewlongtermcontainment integrity analyseshavebeenperformed fortheCookNuclearPlantunits.Onewasperformed inconjunction withtheproposaltoincreasetheunit1steamgenerator tubeplugginglimit.Itwasperformed atanNSSSpowerof3425MWtandisdescribed inreference 29.Therefore, anewanalysiswasperformed atanNSSSpowerof3600MWt.Itisdescribed inWCAP-14489 whichisAttachment 6tothissubmittal andreference 31.NeitherofthesenewanalyseshasbeenreviewedatthistimebytheNRC.Thenextgroupofanalysesisdescribed inreference 3,WCAP-11902, "ReducedTemperature andPressureOperation forCookNuclearPlantUnit1Licensing Report."Reference 3presented theremainder oftheanalysesandevaluations necessary tosupportoperation ofunit1atreducedtemperature andpressure.

TheNSSSsystemsandcomponents analysiswasperformed foranNSSSpowerlevelof3600MWt.Reference 3wassubmitted forNRCreviewbyreference 4.Thelettersofreferences 5,6,7,and8providedsupplementary information tothestaffrelatedtotherequestforapproval(references 2and4)tooperateunit1atreducedtemperature andpressure.

Therequesttooperateunit1inthismannerwasapprovedbyreference 9.Reference 10,WCAP11902,Supplement 1,"ReratedPowerandRevisedTemperature andPressureOperation forCookNuclearPlantUnits1&.2Licensing Report",describes thebalanceoftheanalyseswhichwereperformed byWestinghouse ElectricCorporation tosupporttheoperation ofunit1atupratedpowerandreducedtemperature andpressure.

Thisreportdescribes analysesandevaluations whichwereperformed toboundbothunitsatanupratedNSSSpowerof3600MWt.Inparticular, NSSSsystemsandcomponents wereevaluated foranupratedNSSSpowerof3600MWtforbothunits.Thereportalsodescribes ananalysisofthesteammassandenergyrelease(SM&E)tocontainment, theassociated containment

analysis, andtheSMRE

Attachment 5toAEP:NRC:1223 Page4releaseoutsidecontainment.

Thesetwoanalysesassumedashutdownmarginof1.3%,anincreased timeresponseformainsteamisolation, 0ppmboronconcentration intheboroninjection tank(BIT),andwereperformed toboundbothunitsattheunit2upratedcorepowerof3588MWt.SincetheSMGEtocontainment analysisdescribed inreference 10wasperformed, theSMREtocontainment hasbeenreanalyzed.

ThenewanalysisalsoboundsbothunitsatanNSSSpowerof3600MWt.Ztwasperformed inconjunction withtheproposaltoincreasetheunit1steamgenerator tubeplugginglimit.Itisdescribed inreference 29andwassubmitted withreference 30.Reference 11,"Vantage5ReloadTransition SafetyReportforCookNuclearPlantUnit2(RTSR)",togetherwithreference 1,"Containment Integrity AnalysisforCookNuclearPlantunits1and2",reference 3,WCAP11902,ReducedTemperature andPressureOperation, andreference 10,WCAP11902,Supplement 1,ReratedPowerandRevisedTemperature andPressureOperation, supportreducedtemperature andpressureoperation forunit2atanupratedcorepowerof3588MWt.However,reference 1andtheRHRandHHSZcrosstieclosedLOCAcasesofreference 11onlysupportaunit2corepowerof3413MWt.Theanalysesreportedinreferences 1,10,and11supportoperation withWestinghouse fuel,10%degradation oftheCCP's,HHSZpumps,andRHRpumps,anincreaseof3secondsinMSIVresponsetimeforunit2,0ppmboricacidconcentration intheBITforunit2,aminimumRWSTtemperature of70'Fforunit2,andaSDMof1.3%forunit2.Theletterofreference 13submitted reference 11,RTSR,andtheportionsofreference 10,WCAP11902,Supplement 1,whichaddressed theSMEEtothecontainment.

Thelettersofreferences 14,15,and16providedsupplementary information tothestaffrelatedtoreference 13.Operation ofunit2withWestinghouse fuelatreducedtemperature, with10%degradation oftheRHRandHHSZpumps,wasapprovedbyreference 17.Somechangestoboththeunit1andunit2Technical Specifications whichreturnedcertainactivities toadministrative controlwerealsomade.Thelettersofreferences 18and19forunit1andunit2respectively proposedtechnical specifications thatimplemented anincreaseof3secondsintheMSZVresponsetimes.Theseproposals weresupported byreference 3,WCAP-11902, forbothunits,reference 10,WCAP-11902, Supplement 1,forbothunits,reference 11,RTSR,forunit2,andevaluations performed byus.Thelettersinreferences 18and19submitted theportionsofreference 10,WCAP11902,Supplement 1,whichaddressed theSMEEtothecontainment.

Thepropo'sais toincreasetheMSZVresponsetimesby3secondswereapprovedbyreferences 20and21.Theletterofreference 22proposedtoreducetheprimarysystemminimummeasuredflow(MMF)forunit1.Thisproposalwasapprovedbyreference 23.Theletterofreference 24proposedtoreducetheboronconcentration intheBIT'sofbothunitsto0ppm.Thisproposalwassupported byreference 3,WCAP-11902, reference 10,WCAP-11902,Supplement 1,reference 11,RTSR,andanalysesperformed byus.TheAEPSCanalysisoftheimpactofthesteamlinemassandenergyrelease(SM&E)outsidecontainment ontheoperability 4fl Attachment 5toAEP:NRC:1223 Page5ofequipment inthemainsteamenclosures wasdescribed inreference 24.Reference 10,WCAP11902,Supplement 1,wassubmitted initsentiretyinsupportofthisproposal.

Theproposalwasapprovedbyreference 25.Thelettersofreferences 26and27proposedtorelaxthetolerance ofthemainsteamsafetyvalve(MSSV)setpoints forbothCookNuclearPlantunits.Theproposalwasbasedonnewanalysesandonevaluations performed byWestinghouse ElectricCorporation.

Theevaluations werebasedontheanalysesdescribed inreference 1,WCAP-11908, "Containment Integrity AnalysisforCookNuclearPlantunits1and2",reference 3,WCAP-11902, reference 10,WCAP-11902, Supplement 1,andreference 11,RTSR.Thedescriptions ofthenewanalysesandevaluations wereincludedasattachments totheseletters,references 26and27.Theunit2SBLOCAanalysisdescribed intheMSSVsubmittal wasperformed assumingthatthehighheadsafetyinjection (HHSI)crossties wereclosed.Itwasperformed atacorepowerof3250MWt.Asaresultprovisions wereincludedintheTechnical Specifications whichrequiredapowerreduction whentheHHSIcrossties areclosed.Inthissubmittal, aproposaltoremovethisprovision ismadebasedonanewSBLOCAanalysisusingnewmodels.Thenewanalysisisde'scribed inAttachment 6ofthissubmittal whichisreference 31.TheMSSVsetpointrelaxation proposalwasapprovedbyreference 28.Arecentsubmittal whichimpactstheproposaltouprateunit2istheproposaltoincreasethelimitofunit1steamgenerator tubeplugging.

Thissubmittal isreference 30.IthasnotyetbeenapprovedbytheNRC.Reference 30includesarevisedsteammassandenergyreleasetocontainment analysiswhichboundsbothunitsatanNSSSpowerof3600MWtandproposals toincreaseoperational marginforunit2.Theincreases inoperating margininclude10%headdegradation forthecentrifugal chargingpumps,areduction intheminimumrefueling waterstoragetanktemperature to70oF,andareduction intherequiredshutdownmarginto1.3't.Reference 30alsoproposestoincreasethepressurizer safetyvalvetolerance from1%to3%forunit1only.Twooftheproposedchangesinthissubmittal, AEP:NRC:1223,istheadditionoffootnotes whichrequiresthattheasleftmagnitude ofthepressurizer safetyvalvesbe1%.Thisproposalwasinadvertently omittedfromReference 30.Attachment 6toreference 30isreference 29,WCAP14285,Revision1,"DonaldC.CookNuclearPlantUnit1SteamGenerator TubePluggingProgramLicensing Report".Inaddition, thissubmittal r'equires theapprovalofprevioussubmittals (references 32and33)inordertobeimplemented.

TheyhavenotyetbeenapprovedbytheNRC.Thesesubmittals containa"Refueling Operations DecayTimeTechnical SpecificationAmendment Request"permitting coreoffload100hoursaftersubcriticality.

Theanalysesforthisproposalsupporttheoperation ofoneunit,DonaldC.CookNuclearPlantunit2,atacorepowerof3588MWtfromaspentfuelpoolthermalhydraulic pointofview.The"finalsubmittal forunit2isthissubmittal.

Itproposestoupratethecoreratedthermalpowerto3588MWt.Italsoproposesincreases inunit2operating marginbyincreasing as Attachment 5toAEP:NRC:1223 Page6foundpressurizer safetyvalvesetpointtolerance to3%,increasing theOT~T/OP~T operating margin,andincreasing theanalyzedsafetyinjection andresidualheatremovalpumpheaddegradation to15%.Attachment 6tothissubmittal isreference 31,WCAP14489,Revision1,"DonaldC.CookNuclearPlantUnit2,3600MWtUpratingProgramLicensing Report".References 2.WCAP-11908, Containment Integrity AnalysisforCookNuclearPlantUnits1and2,M.E.Wills,July1988.LetterAEP:NRC:1024D, Containment LongTermPressureAnalysistoSupportRHRCrosstieClosure,fromM.P.AlexichtoT.E.Murley,August22,1988.WCAP-11902, ReducedTemperature andPressureOperation forCookNuclearPlantUnit1Licensing Report,D.L.Cecchett, andD.B.Augustine, October1988.4,5.6.LetterAEP:NRC:1067, ReducedTemperature andPressureProgramAnalysesandTechnical Specification Changes,fromM.P.AlexichtoT.E.Murley,October14,1988.LetterAEP:NRC:1067A, Supplemental Technical Specification ChangesforReducedTemperature andPressureProgram,fromM.P.AlexichtoT.E.Murley,December30,1988.LetterAEP:NRC:1067B, Additional Information onReducedTemperature andPressureSubmittal:

BoronDilutionAccident, fromM.P.AlexichtoT.E.Murley,February, 6,1989.7.8~LetterAEP:NRC:1067C, Unit1RTPProgram:Additional Information onContainment Structural

Analysis, fromM.P.AlexichtoT.E.Murley,March14,1989.LetterAEP:NRC:1067D, Modification ofReducedTemperature andPressureProgramTechnical Specification Changes,fromM.P.AlexichtoT.EDMurley,June5,1989.9.Amendment No.126toFacilityOperating LicenseNo.DPR-58.10.WCAP11902,Supplement 1,ReratedPowerandRevisedTemperature andPressureOperation forCookNuclearPlantUnits162Licensing Report,September 1989.11.Vantage5ReloadTransition SafetyReportforCookNuclearPlantUnit2,B.W.Gergos,Editor,January1990.12.Noreference 12.13.LetterAEP:NRC:1071E, Unit2Cycle8ReloadLicensing, ProposedTechnical Specifications forUnit2Cycle8,andRelatedUnit.1Proposals, fromM.P.AlexichtoT.E.Murley,February6,1990.14.LetterAEP:NRC:1071H, Modification toOurPreviousSubmittal AEP:NRC:1071E; RevisedFiguresfortheLossofLoadEvent,fromM.P.AlexichtoT.E.Murley,April6,

Attachment 5toAEP:NRC:1223 Page71990.15.16.17.18.19.20.21.22'3.25.2627.28.29.30.LetterAEP:NRC:1071I, Information toSupplement OurPreviousSubmittals AEP:NRC:1071E and1071H,fromM.P.AlexichtoT.E.Murley,May29,1990.LetterAEP:NRC:1071K, OffsiteDoseCalculation fortheReactorCoolantPumpLockedRotorEventforUnit2Cycle8,fromM.P.AlexichtoT.E.Murley,July23,1990.Amendment No.148toFacilityOperating LicenseNo.DPR-58andAmendment No.134toFacilityOperating LicenseNo.DPR-74.LetterAEP:NRC:1120, Expedited Technical Specification ChangeRequestSteamGenerator StopValves,fromM.P,AlexichtoT.E.Murley,January31,1990.LetterAEP:NRC:1123, Technical Specification ChangeRequest,SteamGenerator StopValves,fromM.P.AlexichtoT.E.Murley,May14,1990.Amendment No.147toFacilityOperating LicenseNo.DPR-58.Amendment No.135toFacilityOperating LicenseNo.DPR-74.LetterAEP:NRC:1130, Technical Specification ChangeforUnit1Cycle11,fromM.P.AlexichtoT.E.Murley,July23,1990.Amendment No.152toFacilityOperating LicenseNo.DPR-58.LetterAEP:NRC:1140, Technical Specification ChangeRequest,BITBoronConcentration Reduction, fromM.P.AlexichtoT.E.Murley,March26,1991.Amendment No.158toFacilityOperating LicenseNo.DPR-58andAmendment No.142toFacilityOperating LicenseNo.DPR-74.LetterAEP:NRC:1169, Technical Specifications ChangetoIncreasetheAllowable Tolerance forMainSteamSafetyValves,fromE.E.Fitzpatrick toT.E.Murley,November11,1992.LetterAEP:NRC:1169A, UpdateforTechnical Specification ChangetoIncreasetheAllowable Tolerances forMainSteamSafetyValves,fromE.E.Fitzpatrick toT.E.Murley,December17,1993.Amendment No.182toFacilityOperating LicenseNo.DPR-58andAmendment No.167toFacilityOperating LicenseNo.DPR"74.WCAP14285,Revision1,DonaldC.CookNuclearPlantUnit1,SteamGenerator TubePluggingProgramLicensing Report,May1995.LetterAEP:NRC:1207, Technical Specification ChangesSupported byAnalysestoIncreaseUnit1SteamGenerator TubePluggingLimitandCertainProposedChangesforUnit2Supported byRelatedAnalyses, fromE.E.Fitzpatrick to I,

Attachment 5toAEP:NRC:1223 Page8USNRCDocumentControlDesk,May26,1995.31.WCAP14489,Revision1,DonaldC.CookNuclearPlantUnit2,3600MWt,UpratingProgramLicensing Report,May31,1996.32.LetterAEP:NRC:1202, "Refueling Operations DecayTimeTechnical SpecificationAmendment Request",

from-E.E.Fitzpatrick toW.T.Russell,November16,1994.33.LetterAEP:NRC:1202A, "Refueling Operations DecayTimeTechnical UpdatedAnalysisandResponsetoRequestforAdditional Information",

fromE.E.Fitzpatrick toDocumentControlDesk,February1,1996

Oditgdg~~~5TCPIHEOTE~ogthfssectfonappearfncapftalfaa4 typeancIareapplfc-aol~~rougnout theseTecnnfcal SoecfI'Icatfons.

fŽAL~icRLgTHP?QLKVQshallbathetotalreactorcoreheattransferratatothereactor<<oolant.RA~~.%~ERALDOVER>3.M-,c5THQNAl.KVHtshallbeatotalreactorcoreheattransferratato%ereacarcoolantof'm'PKVT.ORAL 8308AnQp~'KATRINA$~5 shal1correspond toanyonefnclusfvecMfnatfonofcarsreaCtivity Canoitien,

~rleVelancaVeragereaCta~COOlanttaCperature SpeCiffeo fnTableLLAC.."N1.5ACHCNShallbethOSeaelftfcnal reCuf~ntS SpeCfffed aaCOrellary Stata-aentseachprfnCfple specff'fcatfon anCshallbepartofthespeCftfcatfonS.

OycRlSt~-OPKRAEIITr1.dAsystae,sesysta,trafn,aaponentorcevfcashallbeOPQNQorhaveOPKRASLLLTY

~ftfscapableof'erfenfnfl Its<pecfffed tune.fon(s).

belfcftInthis4effnftfon shallbetheass~tfonthatallnecessary at~tInstru-aentatfon,

controls, norealancI~agencyelectNcal

~rsourcas,coolfngorseaIqatar,luhrfcatfon orotheroaflfaryequfpeent thatarerecufee4torthesystem,subsystem, trafn,coeenentoravfcatoperronItsI'unc:fon(s) arealsocapanleofperf'orafng thefrrelatedsupportfunctfon(s).

0.C.CXKUN' f,II yE5ICN~V~91.600CP:I/'OPp.capture~'~O'ESCA-'P

-ONPouar~(.IcOFSAFE%I.~uj-.SPouter~~~~C)1TavgPoua't~F~t.sclTL'lg(00.CO~~615.40.9d553.5020.91.25jI00.8.00631.dd6605.d0597.5156.5';00.'.500.00639.10CO0.7262.609562120626140096016125.3..Sjo.-2CQ0.00659.0.62642.01.1599.01.2Sdd.;50-40~30-24)5IA250~5IA2IOO10")0-2OOOeelA)0-30-1775P5IAIO00.8POISE0.2e.40.11.2FRACTiONOFRADTHERhLFigure2.1-1yaccorCoraSafacy'kakcs FoucLoopsQOparacfon

~INUCLEARP~UNIT22.3ANBQMmNO.Sk,l87>34

D/-'desi~-.FloeRate~91,6009~)oopPressur~PeerTaveCfoulQQPeerTavePaverTavePoserTavoLfraal~Lfml~Qml17750.00C15.11.105.Dl.li577.41.2576.420000,00C32.21,lk597.C1.14594.0l,2589.421000.00639.21,00604.51.10604.81.2593.522500.00649.41.0261%.$1.10610.9l,2599.724000.00659.00.9C631.%1,161C.71.2605.7Figure2.1-1RectorCoreSafetyLte)tcFourLoops)e'perat)oa

(%P

REA~RTRIPSYS~INSTRUKQfTATION TRIPSETPOINTS FCVC.IONAJ.CRITTRIPSETPO!ÃTl.manualReactorTrtpNoeAPPltcable 2.'FeverRange.NeuctonLovSeepotntLesschanFluxorequaleo2SiofRATEDI3uuaLPOVERHtghSetpotne~Leaachanorequalto109iofRATEDTHERMAL?OVERPove'rRange,NeutronLeeschanetequaLtoSiofFlux.HtghtoatttveRATEDTHERQLAVERvtchaRacettaeconstantgreaterthaaorequaLto2aecoeta4.PoverRange,NeutronLesechanetequalcoSiofFlux,HtghNegactv>>RATEDTIEMtOVERvtthaRacectaeconstantgreatetchanorequaLco2aecon4a5.Ineernedtate Range,LeesthanotequaLto25iNeuetoaFluxofRATEDTHESNhL?OVER,ALLOVaSLE VA~"ZSNethppltcabl

~LovSeepotneLeeschanorequaleo2iiofRA~iTHENtALPOVERHtghSetpotnt-Lesschanotequalto110iofRATEDntERHALPentaLeaathanotequaLco5.SiofRATEDTHER'.M'ERvtchattaeconstantgreeterchanotequaLto2secondsLeaathanorequaltoS.SiofRATEDTHERMALtOVKXvtchctheconstantgteecet~chanerequaLeo2second@LeaathanotequaLto30iofRATEDTHERMAL8REXC.SourceRange,NeueroneFLux.7.Overeeapetatute DeltaTLesethanerequaLto10couacspersacer!SeeNote1La~achanerequaleoL.3x10countspersecondSeeNoee3l.Ovetpover DeltaTSeeNote2SeeNote49.Pressuriset

?tessure~~Lov10.tressurtser

?ressure~Htgh11.Presauttser VatatLave1Htgh12.LossotFlovCreatorchanorequalco1950pstgLiaachanorequalto25g5yatgLesethanorequalco92ioftnsetuleae epaaCteatetthanotequalce90iof4eatgnflovpet'oop+CreatetthanorequaLeo1940patgLeaathanotequaLeo2395pstgLeaachanorequaleo93ioftnsetuaeat spanCreatorthanotequalco49.Liofdostgnflovper1ooprDestgnflovtsCOOKNUCLEARl(yg~+wCori~~+(p+Am<~F,2~NO.$2,1 2.1.1REACTORCORETheresertctions ojthissafetylkattpreventoverheating ofthefuelandposstbl~<Laddtngperforation vhtchvouldresultknehereleaseoffissionproducestothereactorcoolant.Overheating ofthefuelcladdingksprevented byrescrtcstng fueloperacLon tovtthknthenucleateboilingregiaevhereeheheactransfercoeffickenc Lslarge'ndthecladdingsurfaceteaperature ksslightlyabovethecoolantsaturation teaperatura.

Op<<ratton aboveeheuyperboundaryofthenucleateboilingregiaecouldresulttnexcessLve clad4ingeeayeraeures becauseoftheonsetofdeparture froanucleateboiling(DNb)andtheresultant sharyreduction tnheattransfercoeffLckenc.

OHbLsnocadLrectlyaeasurable paraaecer duringoperation andtherefore TNERNAL.POVERandreactorcoolantteaperaace andpressurehavebeeneelaeedeoDNbthroughtheVkb2correlation andV3correlation forconditions outsidecherangeofVkb.2.TheDNbcorrelations hawbeendeveloped eopredicttheDHbfluxandthelocaetonofDNbforaxiallyuniforaandnonunkfora heacfluxdiatrtbutkons.

ThelocalDHbheaefluxraeLo(DHbR)tsdefinedastheratioofcheheatfluxthatvouldcauseDNlataparticular corelocationeothelocalheacflux,andkskndkcatiw ofeheaargkntoDNb.TheDNbdesignbasksksasfollovs:thereaustb>>aeleasea95percencyrobabilkty chattheakntamDNbkofehelkaktingrodduringCondition IandIIevencsksgreaserthanorequaltoeheOHbkltaktofeheOHbcorrelacion betn~Vkb-2correlaeion forVantage.5 fuaL,andtheV.Scorrelacion forfess'on4ktkons vhkchfalloutsidetherangeofapylkcabklity of~correlaeion DNbklkaitsareestablished basedontheentireaypltcable axperkaental dacasecsuchthasshareks~95percentprobahklkey vich95percencconfi4ence thatONbvillnotoccurvheneheaknkauwONbkisattheDNbkliatt(1.Ufoe'kb2andl.SfortheV.S).Inseatingehe,DHbdesignbasis,uncertainties inplaneoyeraekng paraaesers, nuclearandcharnelparaaeeers, andfuelfabrication paraaeters arestatksttcally coabknedviehtheDNlkcorralackon staeksekcs suchthatshareLsacleasta9SyercencprobabklLey vkth~95percentconfidence levelthateheaknkauaONbkforthe1kakekngrodksgreatershanorequaltoacalculated designliaicDHbk.Theuncertainties Lntheaboveplantparaaetars areuse4sodeceratne theplaneDHbkuncertakncy.

ThisDHbkuncertakncy, coabknedvtehsheDNbkcorrelackon scaekstics, establishes adesignONbkvaluevhLchaustbeaecinplanesafetyanalysesustngvaluesottnyutparaaecers vtehoucuncereaknttes.

ForCookHuclearPlaneUnLe2,shedesignDHbkvaluesare1.2SandVents~-5fuelthkablecells~resectkvel~natton,aargna~aaneanenoratngsafetyanalyseaeoasafecyanalysisltateOHbk.TheaargknbetvaenshedesignandsafecyanalysisltakeDNbRksusedtooffsetknovnDHbkpenalttes (i.~.,sransttkon corepenalties.

eodbov,etc.)andprovtdeDHbkaargtnforoyeracing an4designflexkbklkcy.

Thecurvesoffigure2.1-1shovth>>lockofpointsofTNERNALPOVER,ReactorCoolantSysseapressure, andaveragetaaperature belovvhichthecalculated DNbkisnolessthanthe4eskgnDHbkltakevalueoreheaverage~nehalpyaeehevesselextetaLessthaneheenthalpyofsaturated liquid.COOKNUCLEARRIANTUNIT2b2~1~MBCNOSZ,~I AbLE.2-1ConttnuedCTORTRItSYSTEMINSTRUMENTATION TRIPSETPOINTS NOTATIONT'ndicated TatRATEDQtHNALPOVERleeathanorequaltoZT!.P'~rTressuriser

Tressure, S~IgP'3455peijgpdtcated RCSnoaknaloperating pressure[

ZZg5PSST)aTgOeSPSTg)efunctionjenerated bythelead-lagcontroller forTdynaakccoapenaatkon ay!Togaeconstance utilizedkntheleadlajcontroller forTaygeTl~carT2<aceca~gzSLaplacetraneforN operator1+tSNote1:Oyerteaperature hT<hTtK1K2((1+rlS)/(1+f25)](TT)+Kg(P'P)f(hI)11@here:4TIndIcated hTatRATEDTHMAL?OVERTAverajetemperature, FCOOKNUCLEARPLANTUNIT2F7A)tBrDKNT NO.S2~

~1ContLnuedRRIP5YSDtSTRUNXNT+

OfTRIPSIT?OISROTA0ÃContLnuedClAsLnorationLl-o-og4'PO.OOIIlandf(41)isafunctionofthe.Ln4icated difference betveentopandbottokdetectors ofthepower.rangenuclearLonchaabors:

vithgainstobeselectedbase4onaeasuredLnsttuaent responseduringplantatartuptestssuchchat:~lb(L)forq-qbbetveen-percentand+Cpercent,fl(4I)W(vhereqan4qtaropercentRATEDTHESNhLPOSERLnthotopan4bectoehalvesofthlcorerespectively.

andqiqLstotalTHIS(AI.?CNKk LapercentofRA~iT)CRQLROVER).(LL)foreach'percentthatthe%aptitude of(q~~)exceeds~g-Apercent.the4TtripsetpointshalllA<<ut5aatically iC~ropercentofitavalueatRATEDQCRHAlPCQZXc.os(LLL)ForpercentthatthoaagnLtuda ef(q-q)exceeds+4percent,the4TtripsetpointshallbeauteKatically reducedby~percentofLtsvalueatRATEDTHERMALPOCk.nSay~2-'sCOOLHVCLXAkNJ8TUNIT224A)mammerHO52134

Insert2-8forNoteafortechspecpage2-&NoteaT'hallbesettoavalueequaltoorlessthantheIndicated T~atRATEDTHEF22LPOWER.Indicated T~'andT'anbesettoanyvaluewithintherangeof547to581.3deg.F.

LX2.IContinued REACTORTRI?SYSTEMINSTRUMENTATION TRI?SET?OINTS NOTATIONS Continued Note2:Overyover hT4hT]X~K(t5/(I+t$)]T-f.(TT']f(hI)]4>ere:hTIndicated hTatratedyover~Averageteayerature, F~Indicated TatkATEDTHECALtNTXleesthanoravgoequalto576.0F~1.0$00.02/Fforincreaaing averageteayerature and0fordecreaaing averageteayerature e0.00197forTgreaterchanT',X<~0forTleaathanorequaltoT'35/(I+t35)

Thefunctiongenerated bytheratelagcontroller torTdpuaiccoarpenaati.on t3~Tineconacantutiliaedintheracelagcontroller forT~t3~10aeca~5=~Laplacetranafonoyeratorf(hl)0.0Note3:Noce4:Thechannel'a aaxieiatrippoincshallnotexceeditsyoincbyaore'than%i@

percenthTapan.Thechannel'a aaxiauacrpointshallnocexceeditapoincbysorethan~prcenchTapan.coayutedtrip'IcoeyutedtripCOOKNUCLGRPlhÃt-UNIT22'A)memeNQ.82,~

(l LIHITINCS~SYSTEM(S~INCSEASESOveroover

'DeltaTTheOvcrpover DeltaTreactortripprovidesassurance offuelintegrity.

e.g..nomelting.underallpossibleoverpover conditions, 1tattstherequiredrangeforOvertemperature DeltaTprocection, andprovidesabackuptotheHighNeutronFluxtrip.Thesecpointincludescorrections forchangestndensttyandheatcapacityofvatervithteayerature, anddynaatccoap<<nsatton forpipingdelaysfromthecoretochelooterecuredecectors.

rence~mp(Tse~uersufeduroconditifoeefuleverecuresasuaenesafelysis.eoverpover deltaTreactortrpprovidesprocecconoac.upprocecconforat.poversteam1!nebreakevents.Creditvastakenforoperation ofthistrtpinthesteamlinebreakmass/energy releasesoutsidecontainment analysis.

Inaddition, its.unctional capability atthispecified tripsettingisrequiredbythisspecification toenhancetheoverallreliability oftheReactorProtection System.Pressurizer PressureThePressurtter HighandLovPressuretripsareprovtdedtolimitthepressurerangeinvhichreactoroperation ispermitted.

TheHighPressuretripisbackedupbythepressurtser codesafecyvalvesforRCSoverpressure protection.

andistherefore secloverthanthesetpressureforthesevalves(2485pstg).TheMtghPressur'e tripprovidesproceccton foraLossofExternalLoadevent.TheLovPressuretripprovidesprotection bytrippingt'ereactorintheeventofalossofreactorcoolancpressure.

Pressurtter abaterLevelThePressurizer HighVaterLeveltrtpensuresprocectton againstReactorCoolantSysceaoverpreasurttatton byltitctngthevacerlevelcoavolumesufficienc toretainastemsbubbleandpreventv'aterreliefthroughchepressurizer safetyvalves.Thepresauriser htghvaterlevelcripprecludes vaterrelieftorcheunconcrolled controltodasaeablybankvithdraval at~poverevent~COOKNUCLEARPLANTUNIT2g2-5AHENDHENT NO.Sl.D4

~DrSmZauZTOX

~nS~ES:(Consinued)

VhenkCSflovrateandFareaeaaured, noadditional allovancea areneseaeary priortosoapariaoAith theliaiseofSpecificacion 3,2.3Heaaureaenc erroraof2.1tforkCStlovtotalflovraceand4eforF'<hav<<beenallovedforindetermination ofthedaaignDNSkvaluehandinthPdetermination ottheLOCA/ECCS linis.marginbecveencheeafecyanalyaiaDNAandshedeathliaitDNAiaaaintained.

(SafecyanalyaeaMka.'.C9and1.SlfortheVantage5sypicalandthbablecellsreapeeckvel DeaigiIMHfHSka:

1;2$an41.22forcdVantagi5icaland~caa,reapeccively,I ISSS856'"-""'tanaision corepenaltiea an4theappropriate fuelrodbowDMpenaltyforsheVantage5fuel(e~lto1.$tperMCA?4691.kev.1).Thereaaindar oftheaarginbecveendeaignandaafesyanalyataDHRliaisecanbeuaedforplansdesignflexibility.

IDc@COOK8UCLXAkASLANTUNIT2I3/42.44 rOVKRISTHMIUrONDMSANDTaOrEU.TINO Bma~lDMITINCCONDITION OtEQUATION~~l.Leaa6piio524.76erchanOQpeigt/mCreator~~a3CC,400gp~3.2.5Thefolloving DHSrelatedparaaecara ahallbemaintained vichinchefolloving operational indicated liaica:f1.keactoaneSyate2.Pauditor.ReactorantSyetoeRate~~av1,'orantSaT.Cerchano1ee~N~iACT10!l:Vithanyofeheabowparaaeeere exceeding italiaic,restoretheparaseeer toviehinttaliaitviehin2hastaorreduceTSKNALNvEktoleaachanSeofkATXDDtXRQLNOELviehinthenext4haxz,a.SURVEILLANCE 4.2.5.1Earthoftheabowparaaetara ahallbewrifiedtobevichintheir.Linicaatleaatonceper12ho%ra.4.2.S.2Theindicatora usedtodetermine kCStotalflovshallb<<cub)ected eoaCHANELCALIBRATION aeleaatonceper18aontha.4.2.5.3ThekCStotalflovraceahallbedetermined byapoverbalancearoundtheaeeaagenerators atleaaeenceper1!acth!.4.2.5.4Theprovtaiona ofSpeciftcaeien 4;0.4ahallnoeapplyeoprimaryflovaurveillancea.

Indicaead averageotaeleaaethreeOPQAlLIinsceuene loope,~enetapplicable haringeieheraTHOLNVRraspinexceaaofSeofRATEDTHDHALtOQXXpersiNkceoraTSXRQLNVKXace'pinexc~eeof10%ofRX?Indicaced YalU4COOKNCLXAkKANTUNIT23/42-15ANE2mnttSO.S2,134 insert1topage3/42-15ReactorCoolantSystemT,,T,,((581.3+5.1-Indication errortn)'F*2.Pressurizer Pressure-fornormalPressureOperation, PrzrPres>(2235-63+

Indication error"')psig/'~atReducedPressureOperation, PtzrPres>(2085-63+

Indication error"')psig*/"3.ReactorCoolantSystem>366,400gpm*"'otal FlowRate(1)Indication errortobeprovidedbyAEPSCfortheselimitsnotethatonceAEPSCdetermines theindication errorsfortheseDNBlimitstheabsolutelimitcanbecalculated andinsertedintotheLCO ff!ffIf TASLK3.34ENCIHZZkXD SAXXT?TKlTUkZACTUATIOH SYSTZHIMSTkUKEKfATION TkII'ZTTO~S FURCTIOÃALUNIT1.S~IHJZCTIOH.

TUkaIZXTZI?.TZXDUATXk ISOIATIOtf, ANDHOTOkDkIVXNAQXIIZJXT FXXDVATXX ZEROSTkI?SE?20IHTS AILOVAMXVALUESa.ManualInitiation oroosoooooooSeefunctional Unit$oaoooeoaosab.Autoaatic Actuacion Logf.cc.Concahaent heeaure-Highd.?zeeeuriaer

?reeaur~-Loere.Dfdferencial teeaaurele@teenSteaaLinee--HighHotApplicable Lee!thanoc'qualco1.1paigCreaortpefKsWLeaaorequalto100paf.SotApplicable Crtoregalaethanoreqaalto12pei'aaathanoretpklto~i+2peigt.SteanLinePzeaaure--

LcnrCreatarthanor1,.Createrthanorequalto0eigsteaainLtopaigaceaalinepaaura~:pregpPjCgcP~COOKNUCLZAXfLAÃ7-UHIT23/4323AffXHD~SO.ffICta7 l~

TLSLXS.S4CoachmedEHCDtEERED SAFETYtEATURXACTUATION STSTENIliST1~4TIOg

~SET~~FUNCTIONAL UETZ4.STEAMLTSXZSOLLTXOS a.NamaliTRIPStTPOIÃTS

Seetanctional Uaic9-<<--------

b.Aacoaatic ketaacioa Logicc.Coacainaeat

?zessare--

RLghRt$hd.SteantloeiaTwoSteanLines--Nigh Coincident arithTang--Lcm-bar SotAcyl,icable Lesschanore~2.9ps+L444chanor~coabmccioadefinedasfolly:LDelta-pcorre~dSng to1.Ix10lbs/hnsteanfleebetweentAand20%loadandthenaDeltapiacreasiag linearlytoaDeltapcorres~ding to4.5n10Ebs/hr'tfallload.Sotipplicable L4ssthanorequalcp3~opaidLesschanoCe~lcoabmctioadefinedasfoliose:4Delta-pcorrespond~

toL.75a10lbs/hrsteanfloebetween0\aad20%loadaadtheaaDelta-piacrushglinearlyto4Delta-pcorresponding toco4.55x10lbs/hratM.load.poutertheaor~Qlco541PTgreaterchanor~Qlco5391e.SteuLinehessareLet5.TURJDCTXZ?i'ttÃELfZR ZSOLATIQN

~rchanoc'tpLlCteaterchanotegaltopaidsceaalinetopaidsteanline~searssnreEP.C(egga.ScwaCenerator 1facerLevel--1K'-ltd, L444thanor~coI71ofnarrow~einstrnNenc spaneachsteangenerator LessthenoregadtoINofnarrowsteaseinsczuaeac spaneachaceanjeaetacor COOKHUCLXLkHL?CUSXT23/4S25

3.4.2Aminimumofonepzessuzixer codesafetyvalveshallbeOPGLQLEvithaliftsettingof2485PSIG+3/~ithnopressurizer codesafetyvalveOPERhSLE:

Immediately suspendalloperations involving positivereacivitychanges~andplaceanOPERhbLERHRloopintooperation intheshutdovncoolingmode.b.Zmmediately zendezallSafetyZn]ection pumpsandall.butonechargingpumpinoperable byremovingtheapplicable motorcircuitbreakersfromtheelectrical povercircuitvt.thinonehour.'.4.2'Hoadditional Surveillance Requirements ocherthanthoserequiredbySpecification 4.0.5.~Theliftsettingpressur~shallcorrespond coambientconditions ofchevalveac.nominal opezating temperature andpressure.

Forpurposesofthisspecification, additionofvaterfromcheRUSTdoesnotconstitute adilutionactivityprovidedth>>boronconcentration

'intheRJSTisgzeacerthanozequaltotheminimumrequiredbyspecification 3.1.2.8.b.2 (MODE4)or3.1.2.7.b'.2 (MODE5).ssg~M5g~f3/44-4 Insert4-4for4footnoteontechspecpage3/44-4and3/44-5Thepressurizer codesafetyvalveshallberesettothenominalvalue'l%wheneverfoundoutsidethe+1%tolerance.

~Jl~

REACTORCNLAMTSYSTEMSAf5TYYALVKSOPERATING

ITIA%COJOITION'OR OPERATION l.4.3Allpressurfxer codesaf'alves shallbeOPBNHLEitha1fi'tsettingof2485PSIG+APPi.I&8ILITY:USES12andACTION:Nthonepressurfzer codesafetyvalveinoperable, eitherrestoretheinoperable valvetoOPERA8LKstatuswithin15efnutosorbeinifOTS:UTCOX(withfn12hours.SURVKILH.'CK REJIREMBITS 4.4.3Ncaddftional Survef1'ance Roqufre.entsotherthanthoserecufredbySpecfffcatfon 4.0.5.'TKT.valveatemfna!operatfnq tcmperatreandpressure.

~vSCr+Q.C.COOK-UNIT22/44-5 4.4.6.2.1ReactorCoolantSystaaleakagesshallbeoeaonscraced tobevinineachoftheabovelimitsbyeaab.Nonitoring thecontainment aerosphere parcioukate radioaccivicy aonitoratleastonceper12hours.Nonitoring thecontainnent ampinventory snddischarge atleuconceper12bours.L0~CoDetenaining theseallineresistance atleastonceper31daysvhentheaveragepressuriier pressureisvithin20psiofitsnominalfullpressurevalue.ThesealUnaresistance meuuredduringchesurveillance austbegreaterthanorequalto2.27E-1ft/gpa.Theseallineresistance, RSL,isdeteaained fronthefolloving

~xpresaion:

R<<2.31(P-P)vhere:PCHPchargingpaapheaderpressure, psigPSZ~2262psig(highpressureoperation) 2.31~conversion faccor(12in/ft)2/(62.3 lb/fc3)thetotalsealln]ectionflovygpssTheprevtsiona otSpecification

4.0. 4arenocapplicable

for<<ncxyincoNODES3and4.d.Perfonsance ofakeactorCoolantSysceavaterinventory balanceacleastonceper72hoursduringsteadystateoperacion, and~.Monitoring thereactorbeadflangeledcoffsysteaatleastonceper24bours.4.4.6.2.2.

Eachreactorcoolantsysteapressureisolation valvespecified inTable3.40shallbedeaanstcated OPERASLEpursuanttoSpecification 4.0.5.COCKHUCLEQPLAFT-UNIT23/44-16

I~IFAIIF~HH

~IPMUSl'UU~~IIIII[.I

llllllW~~

IIHllI8'5QlQllIIIIIIIIIIII~II

3.5.2Tvoindependent ECCSsubsysteas shallbeOPH4QLEvitheachsubsystacs coacprised of:4.OneOPERAILECenRifugal ChargingpCnCpeb.OneOPMLKsafetyinjection pucapc.OnaOPERAILKresidualheatreaova1heatexchanEer, d.OneOPERABLEresidualheatreaevalpuap,e~AnOPERAILKflovpathcapableoftakingsuctiontroatherefueling vaterstoragetankon4safetyinjection siEnalandtransferring suctiontothecontainsent suscpduringtherecirculation phaseofoperation.

b3r&Waf4ecticr~EZZQEc4>>b.VithoneECCSsubsystea inoperable, restoretheinoperable subsystaa toOPERAELKstatusvithin12hoursorbeinHOTQNTDOQHvithinthenext12hours.arith.asafetyinjecross-tie closed,restoreth~oss-tiavalvetoopenpositorwheetha-corepoverlaveless~wequaltovithineoahour.Specifi.0,4does,nnt.apply.Ztchea>>>>acthaEttatea>>ca>>tedaadcafe>>caeatattacetheReact>>aCoolantSystea,aSpecialReportshallbepreparedandsubcLitted totheCoemisaionpursuanttoSpecification6.9.2vithin90daysdescribing thecircuaatancea oftheactuation andthetotalaccucaulatad actuation cycleatodate.COOKHUCLEARPLAHT-lAGT2,3/45-3AHmmmeHO.167 PLANTSYSTEMCOHOEHSATE STORAGETAHKLIHITINGCOHOITIOHFOROPERATION 3.7.1.3Thecondensate storagetank(CST)shallbeOPERABLKwithaminimumcontained volumeof,allonsofwater.ZddAPPLICABILITY:

HOOKS13.ACT'.5N:Mfththecondensate storagetankinoperable, within4hourseither:a.RestoretheCSTtoOPERABLEstatusorbeinHOTSHUTDOWNwfthfnhenext12hours,otb.Oemonstrate theOPERABILITY oftheEssentfal ServiceWaterSystemasabackupsupplytotheauxiliary feedwater pumpsandrestorethecondensate storagetanktoOPERABLEstatuswithin7daysorbeinHOTSHUTDOMNwithinthenext12hours.SURYKILLAHCE REUIREMENTS 4.7.1.3.1 Thecondensate storagetankshallbedemonstrated OPERABLKatleastonceper12hoursbyverifying thecontained watervolumeiswiafnftslimitswhenthetankfsthesupplysourcefortheauxiliary feedwater

'umpsA4.7.1.3.2 TheEssential ServiceMaterSystemshallbedemonstrated OPERABLEatleastonceper12hoursbyverifyfng thattheEssential ServiceMaterSystemfsinoperation whenevertheKssential ServiceMaterSystemfsthesupplysourcefortheauxiliary feedwatcr pumps.0.C.COOK-UNIT23/47-7 34.2tCVEXDISTIbUTION UMIT34.2.4AMAHTPOVXRTITRA0Th>>quadrantpovertiltratioli<<icassuresthattheradialpoverdistribution satisfies thedesignvaluesusedLnthepowercapability

~nalysis.kadialpoverdistribucion

<<easure<<ence are<<adeduringstartuptestingandperiodically duringpoveroperacion.

ThelL<<itof1.02atvhichcorrective actionLsrequiredprovidesDAandlinearheatgeneration raceprocection vithx.ypianopovertilts.ThetvohourtLaeallovance foreperation vithatiltcondition greaterthan1.02butlessthan1.09Lsprovidedtoallovidentification andcorrection ofadroppeder<<Lsaligaed zo4.Intheeventsuchactiondoesnotcorrectthecilt,cheaarjinforuncertainty'n FLsteinstata4 byreducingchepoverby3percencfro<<1ATXDTHQNLNVELBreachpercentoftiltLnexcessof1.0:The12hourperiodicsurveillance otthesepara<<etezs throughLnstru<<ent readoucLssufficient toensurethattheparameters arerestoredvithintheirltaitafolloving loadchangesandotherexpectedtransient operation.

The12hoursurveillance ofthetCSflov<<assure<<ent Lsadequatetodetectflovdegradation.

TheC24QACLCAUQhTZOt perforaad afterrefueling ensurescheaccuracyoftheshiftlytlov<<assure<<ent.

ThecocalflovLs<<easuredaftereachrefueling basedonasecondary sidecalori<<attic and<<assure<<ants ofpri<<aryloopte<<peratuzes.

Itrumexaaso.SZ.134lS/42~5COOKNJCLXAkPLhXTQGT234.2.5DN3PARAMETERS ThelL<<itson~M.related patersensurethateachofthepara<<scars arentaineichinnor<<alsteady.staW envelopeo&~operation as4intransiandacntananias.Thelessthanorequal57I.7Fpresiserpruraprerthanoquito2200paigarconsisccvithVFSARuaptionshavenanalytica

<<oracedquateLntaincereetabove~designshoutanal4transcvithevancet<<assure<<en ertai.Thegreethanerqualte.9FLacrvativecoa'afecylysisrPolaedde<<onscethatplantaayraceonaLnecontrorograarethelyticaltofTt100%RApDaayrfroa54.aFto,5.1t.Thetot54).9ntainsaazjin1.1t.ecote,beoperacevithLndicadvesselaversece<<pere~atanysluebecvnth>>upperlover1ts.presLterpr~sureisLce4tosingleno<<1setpointviththelover1totth'syndicated alwsetntsecforLntheticacions.

eT/5valu~yasselectfercscencyviLt1an@'tains a<<ano4psi.+eliaL~consLntvithas'ionsan4nanalytically decratedtobea4aquateco<<aintachecoroetheapplicable deslLILtMLvaluesforeachfueltype(vhichLatedLn(chebasesfoedtzansLent.

ssumptions andhavebeenanalytically demonstrated adeqcoreatorabovethedesignOHBRthroughout eachanalyzallowance formeasurement uncertainty.

pressurizer preseitheroftwonominaloperating pressures of2235psigcorresponding indicated limitssetforthinthespecifiareconsistent withtheUFSARassumptions andhavebeendemonstrated tobeadequatetomaintainthecoreitortransient.

designlimitOHBRvalueforthecurrentfueltythyperouteomaintainthetrsientwithureislimitedto25psig,withtheat>s.Thelimitsanaticallybovetheapplicable out'achanalyzedThelimitsontheOHB-related parameters ensurethateachofparameters aremaintained withinthenormalsteady-state eassuinthetransient andaccidentanalyThTto81.0andpressurizer pressuregreaterthanorequalnominapressurizer operating pressureof2235psig)orpsfig(forpressurizer operating pressureof2085psig)apsgareconsistewihtheUFSAR 1

Allcoeponenta LntheReactorCoolant%yetiareCeaLgae4tovLthatand theeffectsotcyclicloadaCuetooysterteaperature an4preaaurechang@a.Thesecyclicloa4aareintroduced bynoraalloadtraneienta, reactortripe,an4etartupandahutdovnoperationa.

Therariouacatagoriea ofloa4cycleauaedforCeaignpurpoaeaareprovidedLntection4.1.4ofthetNR.()uriayetartupandahutdovn, therateaoftemperature andpreaaurechange>>areliaitedaothattheaaxismumapecified heatupandcooldovnrateeareconaiatent viththeCeaigaaaauaptioaa andaatiafytheetreaaligniteforcyclicoperation.

AnZDorCOo~uarterthickneee aurfaceflavLapoetulated atthelocationLntheveaaelvhichLafoundtobethe1Laitiaycaee.Thereareseveralfactoravhichinfluence thepoatulated location.

Thetheraalinducedbend~atreaaduringheatupiacoapreaaive ontheinneraurfacevhiletenaileontheoutereurfaceoftheveeaelvail.Durin((cooldovn, tbebendixetreaaprofileLarefereed.

Inaddition, theaaterialtaeyhneee Ledependent uponirradiation andteeperature andt?~ore,thefluenceprofilethroughthereactorveaaelvali,therat~ofheatupandalaotherateofoooldovninfluence thepoetulated flavlocation.

TheheatupliaLtcurve,PLyue3.62,Laacoepoaite nevervhLchvaapreparedbyCeteahnlsg thecoenconsecrative caae,vitheithertheinaLdeoroutaLdevalicontrollkay, foranyheatuprateuptoCO%perhour.ThecooldovnlinitcurvoeofPLgere3.4-3arecoepoaite carveavhichverepreparedbaaeduponthecanetypeanalyaiavLththeexception thatthecontrolliny locatLoniaalvayatheLnaidevalivherethecooldovntheaaalgradianta tendtoproducetenaileatreeaeavhLleproduciay caepreaeim etreeaesattheouteidevali.TheheatupanCcooldovnnevoaveregeapazedbaaedonthenoet1tinyvalthepredicted adjuatedreference teaperature attheen4ofXT?I.Thereactornaaelaateriala havebeenteatedtodeteraLne thetialRT~cThereeulteoftheeeteetaareahovnLnTableI3(i.4-1.Reactoroperation andreeultant factneutron(Is1)6ev)irradiation villcauaeanLncreaaeLntheRT~.Therefore, anad)uetedreference temperature anatbepredicted Lnaccordance vithNoqalatory Cuide1.0%,Reriaion2.Thiaprediction baaedonthefluencean4acheaiatry factordeterained fnxaon~ofPoaitiona preaented Lnthehagulatory Cuide.Poaition(1)Ceterninea cheaietry factorfroathecopperandnickelcontentoftheaateriai.

poaition(2)utilixeaecrnillance dataactavhichrelatetheahiftLnreference t+8+:ature oCaaznillance apeckaena tothefluence.Theeelectioa ofpoaition(1)or(2)ianadebaae4ontheavail.abilityofcredibleearveillance data,andthereaultaachievedLnapplyingthetvoPoaitiona.

83/466NQM,444,a7~

I (Continued) allovedconplecton tineaarereasonable, basedonoperating experience, toreach~requiredplaneconditions fromfullpoverconditions inanorderlyaannarandvithoucchallenging plantsystems.Kfaozechanoneaccuuulitor iatnoperable, theplantiainacondition outsidethaaccidentanalyaea; therefore, LCO3.0.3austbeenteredtaaadtately.

TheOPEBhSILXTY ofcvoindependent ECCSsubsystems anaur<<athatsufficient emergency cozecoolingcapability villbeavailable tntheeventofaLOCha!waxingthelossofonesubaystei throughanysinglefailureconaideracion.

ithersubsystem operating incon)unction vichtheaccumulators iscapableofsupplying sufficient cozecoolingcoltatcchapeakcladdingtemperatures vithinacceptable 1tntcaforallpoaculated breaksizeszangtngfromthedoubleendedbreakofchelargestRCScoldlegpipedovnvard.

Xnaddition, eachECCSsubsystem provideslongcenacoracoolingcapability tnchezacirculacion sodaduringtheaccidentreccnrery period."~fasafecjecttoncross-tie eisosed,safetyinoavouldbelimitotvolinesassthelossofonesafeecnsubsyrouaglefailurecoaration.Theresuloveredovresadecrease'lKRNALolimitthepeteaperaturc acceptable limitsinItheeventapostulated asallbreakURL

COHTAIHKEHT SYSTBtSSASES3/4.6.1.4 IHTERVALPRESSUREThelimitations onconCainment internalpressureensurethat1)thecontafnmenC structure isprevented fromexceeding ftsdesignnegativepressuredifferential withrespecttocheoutsideaCmosphere of8psfqand2)thecontafreent peakpressuredoesnotexceedthedesignpressureof12sfgduringLOCAconditions.

hemaximumpeakr'xecedtobeobCainedfromaLOCAevent1spsfeit.3fortitivtapreuri1cetpreto.p1cesn~pressisnsiswfthMwL'~~~1w~gQ,g'/Xi'+t)wc4rwlpoSq~~co~a3/4.6.1.5 AIRe><ssu~Thelfmftatfonsoncontainmenc averageafrtemperature ensurethat1)theCOntafrvnent afrmaSS1SlimitedtOaninffalmaSSSufffCfently lOwCOpreventexceeding thedesignpressureduringLOCAconditions and2)theambient,airtemperature doesnotexceedthattemperature allowable forthe~continuous duCyratingspecfffed forequipment and1nstrumentatfon locatedwfChincontaireent.

/IMThecontainment pressurrfssensitive totheinitially contained airmassduringOCA.Thecontained af'rmassincreases withdecreasing temperatur

.helowertemperature limitof60'f'flllimitthepeakpressuretopsfgwhichfslessthanthecontainment desfgnpressureof12psfg,heuppertemperature lfmftfnfluences thepeakaccfdenttemperature slightlydurfngaLOCA;however,thislfmftfsbasedprimer11yuponequfpeent protection andantfcfpatedoperating conditions~

.8oththeupperandlowertanoeratur elimitsareconsistent wfththepara-metersusedfntheaccfdenCanalyses.

3/4.6.1.6 CONTAIHMHT9RAIHTRTYThfslfmftac1on ensuresthatthesCruccural fntegrfty ofthecon-tainmentwillbemafntafned comparable totheorfgfnaldesignstandards forche1ffeofthefac11ity.

Scructural integrity fsrequiredtoensurethat(1)thesteellinerremafnsleaktightand(2)theconcretesurround-ingthesteellinerreefnscapableofprovfdfng externalmfssfleprotec-tionforthesceellf<<erand.radfat1on shielding fntheevencofaLOCA.Av1sualinspection fncon)unction withTypeAleakagetestsfssuff1cfent todenonstrate Chfscapability.

0,Irtlhv<<srtw l

PLANTSYSTEMSCONOENSATE STORAGETANKLIMIT.'NG CONOITION FOR'PERATION 3.7.1.3Thecondensate storagetank(CST)shallbeOPKRABLEwithaminimumvolumeof175,000gallonsofwater.usa.glA.AB:LITY:HOOKS1,2and3.ACT:QM:Miththecondensate storagetankinoperable, within4hourseither:a.b.RestoretheCSTtoOPERABLEstatusorbeinHOTSHUTDOWNwithinthenext12hours,orOemonstrate theOPERABILITY oftheEssential ServiceMaterSystemasabackupsupplytotheauxiliary feecwater oumpsandrestorethecondensate storagetanktoOPERABLEstatuswithin7daysorbeinHOTSHUTGOWNwithinthenext12hours..SURVEILLANCE REUIREMENTS us~/lq4.7.1.3.1 TheCandenSate StOragetankShalledemanStrated OPERABLEatleastonceper12hours'byverifying the'watrvolumeiswithinitslimitswnenthetankisthesupplysourcefortheauxiliary feedwater pumps'.7.1.3.2 TheEssential ServiceMate~Systemshallbedemonstrated OPERABLEatleastonceper12hoursbyverifying

.hattheEssential ServiceMaterSystemisinoperation whe~evertheEssential ServiceMaterSystemisthesupplysourcefortheauxiliary feedwater pumps.0.C.COOK-UNIT23/47-7

o~0ctf5ckn>gePiPc~TheOPERABILITY ofthecondensate storagetankwiththe~numwatervolumeensuresthatsuficientwaterisavailable tomaintainchaiRCSatHOTSTANDBYconditions for9hourswithsteamdischarge totheatmosphere concurrent

'trhtotalloaaofoff-sitepover.Thewatervolumelb'.t~haalteJaa-an inallovm~eor vatartotuaatlibeoaueaoftatf'taoEiirrelit~looitfotorotiier'hysicalcharacteristics i's~+<<elf,wP0~~44'PvuSao2Thelimitations onsecondary systemspecificactivityensurethattheresultant off-siteradiation dosewillbel.imitedtoasmallfractionof10CPRPart100limitsintheeventofasteamlinerupture.Thisdosealsoincludestheeffectsofacoincident

1.0 gpmprimarytosecondary

tubeleakinthesteamgenerator oftheaffectedsteamline.Thesevaluesareconsistent withthcassumptions usedinrheaccidentanalyses.

TheOPERABILITY ofthesteamgenerator stopvalvesensuresthatnomorethanonesteamgenerator willblowdownintheeventofasteamlinerupcure.Thisrestriction isrequiredto1)minimirethepositivereactivity effectsoftheReactorCoolantSystemcooldownassociated withrheblowdown, and2)limitrhepressurerisewithincontainment intheeventthesteamlineruptureoccurswithincontainment.

TheOPEMILITY ofthesteamgenerator stopvalveswithintheclosuretimesofthesurveillance requirements areconsistent withtheassumptions usedintheaccidentanalyses.

Virhonesteamgenerator stopvalveinoperable inMODE1,actionmustbetakentorestoreOPERABLEstatuswithin8hours.Somerepairstothevalvescanbemadewiththeunithot.The8hourcompletion timeisreasonable, considering thelowprobability ofanaccidentoccurring duringthistimeperiodthatwouldrequireaclosureofthesteamgenerator stopvalves.Ifthesteamgenerator stopvalvecannotberestoredtoOPERABLEstatuswithin8hours,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,thepa~adinMODE2within6heu.i....~~u2and3actionstatement entered.Thecompletion timesarereasonable, basedonoperating experience, toreachMODE2andtoclosethesteamgenerator stopvalvesinanorderlymanner<<ndwirhoutchallenging unitsystems.COOKNUCLEARPLANT-UNIT2B3(47-3~IAMENDHBlT NO.~~~>

ATTACHMENT 6TOAEP:NRC:1223 DESCRZPTZON OFANALYSESPERFORMED BYWESTZNGHOUSE ELECTRZCCORPORATZON FORCOOKNUCLEARPLANTUNZT2 i

Attachment 6toAEP:NRC:1207 Page1WCAP14489

-fII6

Retrieved from "https://kanterella.com/w/index.php?title=ML17334B595&oldid=735346"