ML17332A768

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Proposed Tech Specs Re Incorporation of Cycle & Burnup Dependent Peaking Factor Penalty
ML17332A768
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 05/25/1995
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17332A767 List:
References
NUDOCS 9505310316
Download: ML17332A768 (12)
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Text

4'OWERDTSTRZMTZON LIMITSALLOWABLE PO~LVEL-APLTZNGCONDITION FOROPTATION3.2.6THKQfALP~shallbelesschanorequalcoALLOWABLE POWERLEt'tEL(~),givenbythefollowfng relationship:

APLminover2oF(Z)~(Z)PoCFQischeF.limitac,.RATED THOL~~PO~cspecf.f'ed f.ntheCOLRforWescf.nghSuse orExxonfuel.oF(Z)f.sthemeasuredhotchannelfactorincluding a3%manufacturing tolerance uncertainty anda5%measuremenc uncercaf.nty.

oV(Z)isthefunctionspecified intheCOLR.oF1.00exceptwhensuccessive steady-state powerdiscrfbucion mapsindicateanincreasefnmaxoverZofFZwithexposure.

KZ)Theneitherofthepenaltf.es, F,shallbetaken:pF4A'R-ce,bicrapd~pe.~de<J yawc.by~pcs+>~+~+"+l~PF1.00providedthatSurveillance Requirement 4.2.6.2f.ssRcf.sfied onceper7Effaccfve FullPowerDaysuntiltwosuccessive mapsinrKaaeathamchsmaxaverZoi~Z)isnaeincreasing.

KgZ)oTheabovelimitisnocapplicable inthefollowing coreregions.1)Lowercoreregion0%tol0%inclusive.

2)Uppercoreregion90%to100%inclusive.

APPLICABILITY:

MODE1E~COOKNUC~PLANT-UNIT19505310316 950525PDRADQCK05000315pPDR3/42-LSAM-ID.":-Vr NO82,l'29,;25, DSVECONTROONTHLYREACTOROPERATING REPORT6.9.1.8Routinereportsofoperating statistics andshutdownexperience, including documentation ofallchallenges tothePORVsorsafetyvalves,shallbesubmitted onamonthlybasistotheU.S.NuclearRegulatpry Commission (Attn:DocumentControlDesk),Washington, D.C.20555,withacopytotheRegionalOfficenolaterthanthe15thofeachmonthfollowing thecalendarmonthcoveredbythereport.COOPERATGLSEOR6.9.1.9.1 Coreoperating limitsshallbeestablished anddocumented intheCOREOPERATING LIMITSREPORTbeforeeachreloadcycleoranyremaining partofareloadcycleforthefollowing:

a.Moderator Temperature Coefficient LimitsforSpecification 3/4.1.1.4, b.RodDropTimeLimitsforSpecification 3/4.1.3.3, c.ShutdownRodInsertion LimitsforSpecification 3/4.1.3.4, d.ControlRodInsertion LimitsforSpecification 3/4.1.3.5, e.AxialFluxDifference forSpecification 3/4.2.1,f.HeatFluxHotChannelFactorforSpecification 3/4.2.2,g.NuclearEnthalpyRiseHotChannel'Factor forSpecification 3/4.2.3,andh.Allowable.

PowerLevel.for-Specification-3/4i2.6:

6.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRCin:a.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"

July1985(Westinghouse Proprietary),

b.c~WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures

-TopicalReport,"September 1974(Westinghouse Proprietary),

~pcV)5<oswlPLWCAP-10216-P-A,~Par~,

"Relaxation ofConstantAxialOffsetControl/F Surveillance Technical Specification,"

tun~989.(Westingh8use Proprietary),

Fc,bu~ry1'lt4d.WCAP-10266-P-A Rev.2,"The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).

COOKNUCLEARPLANT-UNIT16-17AMENDMENT NO.40,kP+,474,189 POQZRDISTRIBUTION LLfXTSALLOVhBLE POSEIVEL-APLLIMITINCCONDITION FOROP~TION3.2.6'QfHNhLPOMERshallbelesschanorequaltoALLIABLEPO~LVEL(APL),givenbythefolloving relacionshios:

,g~F(Z)xU(Z)xF poCFQistheFliaicatRATEDTBGQQLPOWERspecified intheCOLRforVescinghPuse orExxonfuel.oF(Z)isthemeasuredhotchannelfactor,including a3imPnufacturing tolerance uncertaincy anda5%aeasurenenc uncartaintJJ.

oV(Z)isthefuncionspecified intheCOLR.~F~1.00exceptvheasuccessive steady-state poserdistribution alpsindicateanincreaseiamaxoverZofFZvichexposure.

KZ)Theaeither'fchefollowing penalcies, F,shallbeoaken:p~~~.4.~~PdqcMenkP~~(qg~ifiQ)~~COLA,o>F~1.00providedchatSurveillance Requireaeat 4.2.6.2isBtisfiedoaceper7Effeccive FullPoverDaysuntil2successive mapsindicacachatthesaxoverZof~FZisaocincreasing.

K~)~Theabovelimitisnocapplicable inchefolloving coreregions.1)LovercoreregioaOtco10%inclusive.

2)Uppercoreregioa904co100%inclusive.

APPLICABILITY'ODE 1COOKNUCLEARPIZZA>>UNIT2,3(42-19umm~NO82187,IX2, v

INSVCOOLS0YEACOROPERATING REPORT6.9.1.8Routinereportsofoperating statistics andshutdownexperience, including documentation ofallchallenges tothePORVsorsafetyvalves,shallbesubmitted onamonthlybasistotheU.S.NuclearRegulatory Commission (Attn:DocumentContxolDesk),Washington, D.C.20555,withacopytotheRegionalOfficenolaterthanthe15thofeachmonthfollowing thecalendarmonthcoveredbythereport.CORE0ETINGSREPOR6.9.1.9.1 Coreoperating limitsshallbeestablished anddocumented intheCOREOPERATING LIMITSREPORTbefoxeeachreloadcycleoranyremaining partofareloadcycleforthefollowing:

a.Moderator Temperature Coefficient LimitsforSpecification 3/4.1.1.4, b.RodDropTimeLimitsforSpecification 3/4.1.3.4, c.ShutdownRodInsertion LimitsforSpecification 3/4.1.3.5, d.ControlRodInsertion LimitsforSpecification 3/4.1.3.6, e.AxialFluxDifference forSpecification 3/4.2.1,f.HeatFluxHotChannelFactorforSpecification 3/4.2.2,g.NuclearEnthalpyRiseHotChannelFactorforSpecification 3/4~2.3,andh.Allowable PowerLevelforSpecification.3/4.2.6.

6.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limishallbethosepreviously reviewedandapprovedbytheNRCin:'Ia.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"

July1985(Westinghouse Proprietary),

b.c~WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures

-TopicalReport,"September 1974(Westinghouse Proprietary),

@v'i'.io~lAWCAP-10216-P-A, Par~,"Relaxation ofConstantAxialOffsetControl/F Surveillance" Technical Specification,"

Jun%G(Westingh8use Proprietary),

@brea~id.WCAP-10266-P-A Rev.2,"The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).

COOKNUCLEARPLANT-UNIT26-17AMENDMENT NO.44, ATTACHMENT 3TOAEP:NRC:1071T PROPOSEDREVISEDTECHNiCAL SPECIFICATION PAGES 3/4.0LIMITINGCONDITION FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.2POWERDISTRIBUTION LIMITSALLOWABLE POWERLEVEL-APLLIMITINGCONDITION FOROPERATION 3.2.6THERMALPOWERshallbelessthanorequaltoALLOWABLE POWERLEVEL(APL),givenbythefollowing relationships:

APL=minoverZofFZ<ZFx100%,or100%,whichever isless.CFQxK(Z)CFQistheF<limitatRATEDTHERMALPOWERspecified intheCOLRforWestinghouse orExxon-fuel.-

F<(Z)isthemeasuredhotchannelfactorincluding a3%manufacturing tolerance uncertainty anda5%measurement uncertainty.

V(Z)isthefunctionspecified intheCOLR.F>--1.00exceptwhensuccessive steady-state powerdistribution mapsindicateanincreaseinmaxoverZofwithexposure.

Fg(Z)~KZTheneitherofthepenalties, F>,shallbetaken:Fp=Ft,=burnupdependent penaltyspecified intheCOLR,or1.00providedthatSurveillance Requirement 4.2.6.2issatisfied onceper7Effective FullPowerDaysuntiltwosuccessive mapsindicatethatthemaxoverZofisnotincreasing.

Fo(z)oTheabovelimitisnotapplicable inthefollowing coreregions.I)Lowercoreregion0%to10%inclusive.

2)Uppercoreregion90%to100%inclusive.

APPLICABILITY'ODE 1COOKNUCLEARPLANT-UNIT 1Page3/42-15AMENDMENT SR)~)4%)446

6.0 ADMINISTRATIVE

CONTROLS0MONTHLYREACTOROPERATING REPORT6.9.1.8Routinereportsofoperating statistics andshutdownexperience, including documentation ofallchallenges tothePORVsorsafetyvalves,shallbesubmitted onamonthlybasistotheU.S.NuclearRegulatory Commission (Attn:DocumentControlDesk),Washington, D.C.20555,withacopytotheRegionalOfficenolaterthanthe15thofeachmonthfollowing thecalendarmonthcoveredbythereport.COREOPERATING LIMITSREPORT6.9.1.9.1 Coreoperating limitsshallbeestablished anddocumented intheCOREOPERATING LIMITSREPORTbeforeeachreloadcycleoranyremaining partofareloadcycleforthefollowing:

a.Moderator Temperature Coefficient LimitsforSpecification 3/4.1.1.4, b.RodDropTimeLimitsforSpecification 3/4.1.3.3, c.ShutdownRodInsertion LimitsforSpecification 3/4.1.3.4, d.ControlRodInsertion LimitsforSpecification 3/4.1.3.5, e.AxialFluxDifference forSpecification 3/4.2.1,f.HeatFluxHotChannelFactorforSpecification 3/4.2.2,g.NuclearEnthalpyRiseHotChannelFactorforSpecification 3/4.2.3,andh.Allowable PowerLevelforSpecification 3/4.2.6.6.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRCin:WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"

July1985(Westinghouse Proprietary),

WCAP-8385, PowerDistribution ControlandLoadFollowing Procedures

-TopicalReport,"September 1974(Westinghouse Proprietary),

WCAP-10216-P-A, RevisionIA,"Relaxation ofConstantAxialOffsetControl/F<Surveillance Technical Specification,"

February1994(Westinghouse Proprietary),

WCAP-10266-P-A Rev.2,The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).

COOKNUCLEA'RPLANT-UNIT 1Page6-17AMENDMENT 69,484,kV4,480 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.2POWERDISTRIBUTION LIMITSALLOWABLE POWERLEVEL-APLLIMITINGCONDITION FOROPERATION 3.2.6THERMALPOWERshallbelessthanorequaltoALLOWABLE POWERLEVEL(APL),givenbythefollowing relationships:

APL=minoverZofF<<>Fx100%,or100%,whichever isless.CFQxK(Z)CFQistheF~limitatRATEDTHERMALPOWERspecified intheCOLRforWestinghouse orExxonfuel.F<(Z)isthemeasuredhotchannelfactorincluding a3%manufacturing tolerance uncertainty anda5%measurement uncertainty.

V(Z)isthefunctionspecified intheCOLR.Fp=1.00exceptwhensuccessive steady-state powerdistribution mapsindicateanincreaseinntaxoverZoiwithexposure.

noixiKxTheneitherofthepenalties, Fp,shallbetaken:Fp=Fp=burnupdependent penaltyspecified intheCOLR,or1.00providedthatSurveillance Requirement 4.2.6.2issatisfied onceper7Effective FullPowerDaysuntiltwosuccessive mapsindicatethatthemaxoverZofisnotincreasing.

FQ(2)oTheabovelimitisnotapplicable inthefollowing coreregions.1)Lowercoreregion0%to10%inclusive.

2)Uppercoreregion90%to100%inclusive.

APPLICABILITY:

MODE1COOKNUCLEARPLANT-UNIT 2Page3/42-19AMENDMENT g2,447,~,434

6.0 ADMINISTRATIVE

CONTROLSMONTHLYREACTOROPERATING REPORT6.9.1.8Routinereportsofoperating statistics andshutdownexperience, including documentation ofallchallenges tothePORVsorsafetyvalves,shallbesubmitted onamonthlybasistotheU.S.NuclearRegulatory Commission (Attn:DocumentControlDesk),Washington, D.C.20555,withacopytotheRegionalOfficenolaterthanthe15thofeachmonthfollowing thecalendarmonthcoveredbythereport.COREOPERATING LIMITSREPORT6.9.1.9.1 Coreoperating limitsshallbeestablished anddocumented intheCOREOPERATING LIMITSREPORTbeforeeachreloadcycleoranyremaining partofareloadcycleforthefollowing:

a.Moderator Temperature Coefficient LimitsforSpecification 3/4.1.1.4, RodDropTimeLimitsforSpecification 3/4.1.3.4, ShutdownRodInsertion LimitsforSpecification 3/4.1.3.5, ControlRodInsertion LimitsforSpecification 3/4.1.3.6, AxialFluxDifference forSpecification 3/4.2.1,f.HeatFluxHotChannelFactorforSpecification 3/4.2.2,g..Nuclear EnthalpyRiseHotChannelFactorforSpecification 3/4.2.3,andh.Allowable PowerLevelforSpecification 3/4.2.6.6.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRCin:WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"

July1985(Westinghouse Proprietary),

WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures

-TopicalReport,"September 1974(Westinghouse Proprietary),

C.WCAP-10216-P-A, Revision1A,"Relaxation ofConstantAxialOffsetControl/F~Surveillance Technical Specification,"

February1994(Westinghouse Proprietary),

WCAP-10266-P-A Rev.2,"The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).

COOKNUCLEARPLANT-UNIT 2Page6-17AMENDMENT Z4,438,XSAM,kV$

ATTACHMENT 4TOAEP:NRC:1071T EXAMPLEOFPROPOSEDCHANGETOTHECOREOPERATING LIMITSREPORT IYCOLEforDonaldC.CookNuclearPlantUnit+CyclePL2.8Allowable Po~erLeve-APL(Specification 3.2.6)C*KZAPL-minoverZforF(Z)*V(Z)*FQP2.8.1V(Z)isprovidedinTable1for+5%AFDtargetband2.8.2CPQandK(Z)areprovidedinCOLRSections2.6.1and2.6.2,respectively 2.8.3pFp>bbvrn~gdeP~~cleng e~pc1'4A":~he~gu.reap'is)css~~<reying.I+o@gog~w4.z4&nup44g(cab~.g-6o.<lg5o>>+Page6of11

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