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{{#Wiki_filter:4'OWERDTSTRZMTZON LIMITSALLOWABLE PO~LVEL-APLTZNGCONDITION FOROPTATION3.2.6THKQfALP~shallbelesschanorequalcoALLOWABLE POWERLEt'tEL(~),givenbythefollowfng relationship:
{{#Wiki_filter:4'OWER DTSTRZMTZON LIMITS ALLOWABLE PO~L VEL-APL TZNG CONDITION FOR OPTATION 3.2.6 THKQfAL P~shall be less chan or equal co ALLOWABLE POWER LEt'tEL (~), given by the followfng 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.
APL min over 2 o F (Z)~(Z)P o CFQ is che F.limit ac,.RATED THOL~~PO~c specf.f'ed f.n the COLR for Wescf.nghSuse or Exxon fuel.o F (Z)f.s the measured hot channel factor including a 3%manufacturing tolerance uncertainty and a 5%measuremenc uncercaf.nty.
oV(Z)isthefunctionspecified intheCOLR.oF1.00exceptwhensuccessive steady-state powerdiscrfbucion mapsindicateanincreasefnmaxoverZofFZwithexposure.
o V(Z)is the function specified in the COLR.o F 1.00 except when successive steady-state power discrfbucion maps indicate an increase fn max over Z of F Z with exposure.K Z)Then either of the penaltf.es, F , shall be taken: p F 4A'R-ce, bi crap d~pe.~de<J yaw c.by~pcs+>~+~+"+l~P F 1.00 provided that Surveillance Requirement 4.2.6.2 f.s sRcf.sfied once per 7 Effaccfve Full Power Days until two successive maps inrKaaea tham chs max aver Z oi~Z)is nae increasing.
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)o The above limit is noc applicable in the following core regions.1)Lower core region 0%to l0%inclusive.
KgZ)oTheabovelimitisnocapplicable inthefollowing coreregions.1)Lowercoreregion0%tol0%inclusive.
2)Upper core region 90%to 100%inclusive.
2)Uppercoreregion90%to100%inclusive.
APPLICABILITY:
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:
MODE 1 E~COOK NUC~PLANT-UNIT 1 9505310316 950525 PDR ADQCK 05000315 p PDR 3/4 2-LS AM-ID.":-Vr NO82, l'29,;25, D S VE CONTRO ONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatpry Commission (Attn: Document Control Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CO OPERAT G L S E OR 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
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.
a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.Rod Drop Time Limits for Specification 3/4.1.3.3, c.Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.Control Rod Insertion Limits for Specification 3/4.1.3.5, e.Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.Nuclear Enthalpy Rise Hot Channel'Factor for Specification 3/4.2.3, and h.Allowable.
PowerLevel.for-Specification-3/4i2.6:
Power Level.for-Specification-3/4i2.6:
6.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRCin:a.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: a.WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), b.c~WCAP-8385,"Power Distribution Control and Load Following Procedures
July1985(Westinghouse Proprietary),
-Topical Report," September 1974 (Westinghouse Proprietary),~pcV)5<osw lPL WCAP-10216-P-A,~Par~,"Relaxation of Constant Axial Offset Control/F Surveillance Technical Specification," tun~989.(Westingh8use Proprietary), Fc,b u~r y 1'l t4 d.WCAP-10266-P-A Rev.2,"The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
b.c~WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures
COOK NUCLEAR PLANT-UNIT 1 6-17 AMENDMENT NO.40, kP+, 474, 189 POQZR DISTRIBUTION LLfXTS ALLOVhBLE POSE I VEL-APL LIMITINC CONDITION FOR OP~TION 3.2.6'QfHNhL POMER shall be less chan or equal to ALLIABLE PO~LVEL (APL), given by the folloving relacionshios: ,g~F (Z)xU(Z)xF p o CFQ is the F liaic at RATED TBGQQL POWER specified in the COLR for VescinghPuse or Exxon fuel.o F (Z)is the measured hot channel factor, including a 3i mPnufacturing tolerance uncertaincy and a 5%aeasurenenc uncartaintJJ.
-TopicalReport,"September 1974(Westinghouse Proprietary),
o V(Z)is the func ion specified in the COLR.~F~1.00 except vhea successive steady-state poser distribution alps indicate an increase ia max over Z of F Z vich exposure.K Z)Thea either'f che following penalcies, F, shall be oaken: p~~~.4.~~P dqcMenk P~~(q g~ifiQ)~~COLA, o>F~1.00 provided chat Surveillance Requireaeat 4.2.6.2 is Btisfied oace per 7 Effeccive Full Pover Days until 2 successive maps indicaca chat the sax over Z of~FZ is aoc increasing.
~pcV)5<oswlPLWCAP-10216-P-A,~Par~,
K~)~The above limit is noc applicable in che folloving core regions.1)Lover core regioa Ot co 10%inclusive.
"Relaxation ofConstantAxialOffsetControl/F Surveillance Technical Specification,"
2)Upper core regioa 904 co 100%inclusive.
tun~989.(Westingh8use Proprietary),
APPLICABILITY'ODE 1 COOK NUCLEAR PIZZA>>UNIT 2 ,3(4 2-19 umm~NO 82 187,IX2, v
Fc,bu~ry1'lt4d.WCAP-10266-P-A Rev.2,"The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).
IN S V CO OLS 0 Y EAC OR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatory Commission (Attn: Document Contxol Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CORE 0 E TING S REPOR 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT befoxe each reload cycle or any remaining part of a reload cycle for the following:
COOKNUCLEARPLANT-UNIT16-17AMENDMENT NO.40,kP+,474,189 POQZRDISTRIBUTION LLfXTSALLOVhBLE POSEIVEL-APLLIMITINCCONDITION FOROP~TION3.2.6'QfHNhLPOMERshallbelesschanorequaltoALLIABLEPO~LVEL(APL),givenbythefolloving relacionshios:
a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.Rod Drop Time Limits for Specification 3/4.1.3.4, c.Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, d.Control Rod Insertion Limits for Specification 3/4.1.3.6, e.Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4~2.3, and h.Allowable Power Level for Specification.3/4.2.6.
,g~F(Z)xU(Z)xF poCFQistheFliaicatRATEDTBGQQLPOWERspecified intheCOLRforVescinghPuse orExxonfuel.oF(Z)isthemeasuredhotchannelfactor,including a3imPnufacturing tolerance uncertaincy anda5%aeasurenenc uncartaintJJ.
6.9.1.9.2 The analytical methods used to determine the core operating limi shall be those previously reviewed and approved by the NRC in: 'I a.WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), b.c~WCAP-8385,"Power Distribution Control and Load Following Procedures
oV(Z)isthefuncionspecified intheCOLR.~F~1.00exceptvheasuccessive steady-state poserdistribution alpsindicateanincreaseiamaxoverZofFZvichexposure.
-Topical Report," September 1974 (Westinghouse Proprietary),@v'i'.io~l A WCAP-10216-P-A, Par~,"Relaxation of Constant Axial Offset Control/F Surveillance" Technical Specification," Jun%G (Westingh8use Proprietary),@brea~i d.WCAP-10266-P-A Rev.2,"The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
KZ)Theaeither'fchefollowing penalcies, F,shallbeoaken:p~~~.4.~~PdqcMenkP~~(qg~ifiQ)~~COLA,o>F~1.00providedchatSurveillance Requireaeat 4.2.6.2isBtisfiedoaceper7Effeccive FullPoverDaysuntil2successive mapsindicacachatthesaxoverZof~FZisaocincreasing.
COOK NUCLEAR PLANT-UNIT 2 6-17 AMENDMENT NO.44, ATTACHMENT 3 TO AEP:NRC:1071T PROPOSED REVISED TECHNiCAL SPECIFICATION PAGES 3/4.0 LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLE POWER LEVEL-APL LIMITING CONDITION FOR OPERATION 3.2.6 THERMAL POWER shall be less than or equal to ALLOWABLE POWER LEVEL (APL), given by the following relationships:
K~)~Theabovelimitisnocapplicable inchefolloving coreregions.1)LovercoreregioaOtco10%inclusive.
APL=min over Z of F Z<Z F x 100%, or 100%, whichever is less.CFQ x K(Z)CFQ is the F<limit at RATED THERMAL POWER specified in the COLR for Westinghouse or Exxon-fuel.-
2)Uppercoreregioa904co100%inclusive.
F<(Z)is the measured hot channel factor including a 3%manufacturing tolerance uncertainty and a 5%measurement uncertainty.
APPLICABILITY'ODE 1COOKNUCLEARPIZZA>>UNIT2,3(42-19umm~NO82187,IX2, v
V(Z)is the function specified in the COLR.F>--1.00 except when successive steady-state power distribution maps indicate an increase in max over Z of with exposure.Fg(Z)~KZ Then either of the penalties, F>, shall be taken: Fp=Ft,=burnup dependent penalty specified in the COLR, or 1.00 provided that Surveillance Requirement 4.2.6.2 is satisfied once per 7 Effective Full Power Days until two successive maps indicate that the max over Z of is not increasing.
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:
Fo(z)o The above limit is not applicable in the following core regions.I)Lower core region 0%to 10%inclusive.
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.
2)Upper core region 90%to 100%inclusive.
6.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limishallbethosepreviously reviewedandapprovedbytheNRCin:'Ia.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"
APPLICABILITY'ODE 1 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 2-15 AMENDMENT SR)~)4%)446  
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==
==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:
CONTROLS 0 MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
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,"
a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.Rod Drop Time Limits for Specification 3/4.1.3.3, c.Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.Control Rod Insertion Limits for Specification 3/4.1.3.5, e.Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.Allowable Power Level for Specification 3/4.2.6.6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), WCAP-8385, Power Distribution Control and Load Following Procedures
July1985(Westinghouse Proprietary),
-Topical Report," September 1974 (Westinghouse Proprietary), WCAP-10216-P-A, Revision IA,"Relaxation of Constant Axial Offset Control/F<Surveillance Technical Specification," February 1994 (Westinghouse Proprietary), WCAP-10266-P-A Rev.2, The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
WCAP-8385, PowerDistribution ControlandLoadFollowing Procedures
COOK NUCLEA'R PLANT-UNIT 1 Page 6-17 AMENDMENT 69, 484, kV4, 480 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLE POWER LEVEL-APL LIMITING CONDITION FOR OPERATION 3.2.6 THERMAL POWER shall be less than or equal to ALLOWABLE POWER LEVEL (APL), given by the following relationships:
-TopicalReport,"September 1974(Westinghouse Proprietary),
APL=min over Z of F<<>F x 100%, or 100%, whichever is less.CFQ x K(Z)CFQ is the F~limit at RATED THERMAL POWER specified in the COLR for Westinghouse or Exxon fuel.F<(Z)is the measured hot channel factor including a 3%manufacturing tolerance uncertainty and a 5%measurement uncertainty.
WCAP-10216-P-A, RevisionIA,"Relaxation ofConstantAxialOffsetControl/F<Surveillance Technical Specification,"
V(Z)is the function specified in the COLR.Fp=1.00 except when successive steady-state power distribution maps indicate an increase in ntax over Z oi with exposure.no i xi K x Then either of the penalties, Fp, shall be taken: Fp=Fp=burnup dependent penalty specified in the COLR, or 1.00 provided that Surveillance Requirement 4.2.6.2 is satisfied once per 7 Effective Full Power Days until two successive maps indicate that the max over Z of is not increasing.
February1994(Westinghouse Proprietary),
FQ (2)o The above limit is not applicable in the following core regions.1)Lower core region 0%to 10%inclusive.
WCAP-10266-P-A Rev.2,The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).
2)Upper core region 90%to 100%inclusive.
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:
APPLICABILITY:
MODE1COOKNUCLEARPLANT-UNIT 2Page3/42-19AMENDMENT g2,447,~,434  
MODE 1 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 2-19 AMENDMENT g2, 447,~, 434  


==6.0 ADMINISTRATIVE==
==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:
CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
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,"
a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, Rod Drop Time Limits for Specification 3/4.1.3.4, Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, Control Rod Insertion Limits for Specification 3/4.1.3.6, Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g..Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.Allowable Power Level for Specification 3/4.2.6.6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), WCAP-8385,"Power Distribution Control and Load Following Procedures
July1985(Westinghouse Proprietary),
-Topical Report," September 1974 (Westinghouse Proprietary), C.WCAP-10216-P-A, Revision 1A,"Relaxation of Constant Axial Offset Control/F~Surveillance Technical Specification," February 1994 (Westinghouse Proprietary), WCAP-10266-P-A Rev.2,"The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures
COOK NUCLEAR PLANT-UNIT 2 Page 6-17 AMENDMENT Z4, 438, XSAM, kV$
-TopicalReport,"September 1974(Westinghouse Proprietary),
ATTACHMENT 4 TO AEP:NRC:1071T EXAMPLE OF PROPOSED CHANGE TO THE CORE OPERATING LIMITS REPORT IY COLE for Donald C.Cook Nuclear Plant Unit+Cycle PL 2.8 Allowable Po~er Leve-APL (Specification 3.2.6)C*K Z APL-min over Z for F (Z)*V(Z)*F Q P 2.8.1 V(Z)is provided in Table 1 for+5%AFD target band 2.8.2 CPQ and K(Z)are provided in COLR Sections 2.6.1 and 2.6.2, respectively 2.8.3 p Fp>b bvrn~g deP~~cleng e~pc 1'4A":~he~gu.reap'is)css~~<r eying.I+o@go g~w4.z 4&nup 44 g(cab~.g-6o.<lg5o>>+Page 6 of 11}}
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}}

Revision as of 08:10, 6 July 2018

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)
v • d • e


Text

4'OWER DTSTRZMTZON LIMITS ALLOWABLE PO~L VEL-APL TZNG CONDITION FOR OPTATION 3.2.6 THKQfAL P~shall be less chan or equal co ALLOWABLE POWER LEt'tEL (~), given by the followfng relationship:

APL min over 2 o F (Z)~(Z)P o CFQ is che F.limit ac,.RATED THOL~~PO~c specf.f'ed f.n the COLR for Wescf.nghSuse or Exxon fuel.o F (Z)f.s the measured hot channel factor including a 3%manufacturing tolerance uncertainty and a 5%measuremenc uncercaf.nty.

o V(Z)is the function specified in the COLR.o F 1.00 except when successive steady-state power discrfbucion maps indicate an increase fn max over Z of F Z with exposure.K Z)Then either of the penaltf.es, F , shall be taken: p F 4A'R-ce, bi crap d~pe.~de<J yaw c.by~pcs+>~+~+"+l~P F 1.00 provided that Surveillance Requirement 4.2.6.2 f.s sRcf.sfied once per 7 Effaccfve Full Power Days until two successive maps inrKaaea tham chs max aver Z oi~Z)is nae increasing.

KgZ)o The above limit is noc applicable in the following core regions.1)Lower core region 0%to l0%inclusive.

2)Upper core region 90%to 100%inclusive.

APPLICABILITY:

MODE 1 E~COOK NUC~PLANT-UNIT 1 9505310316 950525 PDR ADQCK 05000315 p PDR 3/4 2-LS AM-ID.":-Vr NO82, l'29,;25, D S VE CONTRO ONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatpry Commission (Attn: Document Control Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CO OPERAT G L S E OR 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.Rod Drop Time Limits for Specification 3/4.1.3.3, c.Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.Control Rod Insertion Limits for Specification 3/4.1.3.5, e.Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.Nuclear Enthalpy Rise Hot Channel'Factor for Specification 3/4.2.3, and h.Allowable.

Power Level.for-Specification-3/4i2.6:

6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: a.WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), b.c~WCAP-8385,"Power Distribution Control and Load Following Procedures

-Topical Report," September 1974 (Westinghouse Proprietary),~pcV)5<osw lPL WCAP-10216-P-A,~Par~,"Relaxation of Constant Axial Offset Control/F Surveillance Technical Specification," tun~989.(Westingh8use Proprietary), Fc,b u~r y 1'l t4 d.WCAP-10266-P-A Rev.2,"The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT 1 6-17 AMENDMENT NO.40, kP+, 474, 189 POQZR DISTRIBUTION LLfXTS ALLOVhBLE POSE I VEL-APL LIMITINC CONDITION FOR OP~TION 3.2.6'QfHNhL POMER shall be less chan or equal to ALLIABLE PO~LVEL (APL), given by the folloving relacionshios: ,g~F (Z)xU(Z)xF p o CFQ is the F liaic at RATED TBGQQL POWER specified in the COLR for VescinghPuse or Exxon fuel.o F (Z)is the measured hot channel factor, including a 3i mPnufacturing tolerance uncertaincy and a 5%aeasurenenc uncartaintJJ.

o V(Z)is the func ion specified in the COLR.~F~1.00 except vhea successive steady-state poser distribution alps indicate an increase ia max over Z of F Z vich exposure.K Z)Thea either'f che following penalcies, F, shall be oaken: p~~~.4.~~P dqcMenk P~~(q g~ifiQ)~~COLA, o>F~1.00 provided chat Surveillance Requireaeat 4.2.6.2 is Btisfied oace per 7 Effeccive Full Pover Days until 2 successive maps indicaca chat the sax over Z of~FZ is aoc increasing.

K~)~The above limit is noc applicable in che folloving core regions.1)Lover core regioa Ot co 10%inclusive.

2)Upper core regioa 904 co 100%inclusive.

APPLICABILITY'ODE 1 COOK NUCLEAR PIZZA>>UNIT 2 ,3(4 2-19 umm~NO 82 187,IX2, v

IN S V CO OLS 0 Y EAC OR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatory Commission (Attn: Document Contxol Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CORE 0 E TING S REPOR 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT befoxe each reload cycle or any remaining part of a reload cycle for the following:

a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.Rod Drop Time Limits for Specification 3/4.1.3.4, c.Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, d.Control Rod Insertion Limits for Specification 3/4.1.3.6, e.Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4~2.3, and h.Allowable Power Level for Specification.3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limi shall be those previously reviewed and approved by the NRC in: 'I a.WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), b.c~WCAP-8385,"Power Distribution Control and Load Following Procedures

-Topical Report," September 1974 (Westinghouse Proprietary),@v'i'.io~l A WCAP-10216-P-A, Par~,"Relaxation of Constant Axial Offset Control/F Surveillance" Technical Specification," Jun%G (Westingh8use Proprietary),@brea~i d.WCAP-10266-P-A Rev.2,"The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT 2 6-17 AMENDMENT NO.44, ATTACHMENT 3 TO AEP:NRC:1071T PROPOSED REVISED TECHNiCAL SPECIFICATION PAGES 3/4.0 LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLE POWER LEVEL-APL LIMITING CONDITION FOR OPERATION 3.2.6 THERMAL POWER shall be less than or equal to ALLOWABLE POWER LEVEL (APL), given by the following relationships:

APL=min over Z of F Z<Z F x 100%, or 100%, whichever is less.CFQ x K(Z)CFQ is the F<limit at RATED THERMAL POWER specified in the COLR for Westinghouse or Exxon-fuel.-

F<(Z)is the measured hot channel factor including a 3%manufacturing tolerance uncertainty and a 5%measurement uncertainty.

V(Z)is the function specified in the COLR.F>--1.00 except when successive steady-state power distribution maps indicate an increase in max over Z of with exposure.Fg(Z)~KZ Then either of the penalties, F>, shall be taken: Fp=Ft,=burnup dependent penalty specified in the COLR, or 1.00 provided that Surveillance Requirement 4.2.6.2 is satisfied once per 7 Effective Full Power Days until two successive maps indicate that the max over Z of is not increasing.

Fo(z)o The above limit is not applicable in the following core regions.I)Lower core region 0%to 10%inclusive.

2)Upper core region 90%to 100%inclusive.

APPLICABILITY'ODE 1 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 2-15 AMENDMENT SR)~)4%)446

6.0 ADMINISTRATIVE

CONTROLS 0 MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.Rod Drop Time Limits for Specification 3/4.1.3.3, c.Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.Control Rod Insertion Limits for Specification 3/4.1.3.5, e.Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.Allowable Power Level for Specification 3/4.2.6.6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), WCAP-8385, Power Distribution Control and Load Following Procedures

-Topical Report," September 1974 (Westinghouse Proprietary), WCAP-10216-P-A, Revision IA,"Relaxation of Constant Axial Offset Control/F<Surveillance Technical Specification," February 1994 (Westinghouse Proprietary), WCAP-10266-P-A Rev.2, The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEA'R PLANT-UNIT 1 Page 6-17 AMENDMENT 69, 484, kV4, 480 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLE POWER LEVEL-APL LIMITING CONDITION FOR OPERATION 3.2.6 THERMAL POWER shall be less than or equal to ALLOWABLE POWER LEVEL (APL), given by the following relationships:

APL=min over Z of F<<>F x 100%, or 100%, whichever is less.CFQ x K(Z)CFQ is the F~limit at RATED THERMAL POWER specified in the COLR for Westinghouse or Exxon fuel.F<(Z)is the measured hot channel factor including a 3%manufacturing tolerance uncertainty and a 5%measurement uncertainty.

V(Z)is the function specified in the COLR.Fp=1.00 except when successive steady-state power distribution maps indicate an increase in ntax over Z oi with exposure.no i xi K x Then either of the penalties, Fp, shall be taken: Fp=Fp=burnup dependent penalty specified in the COLR, or 1.00 provided that Surveillance Requirement 4.2.6.2 is satisfied once per 7 Effective Full Power Days until two successive maps indicate that the max over Z of is not increasing.

FQ (2)o The above limit is not applicable in the following core regions.1)Lower core region 0%to 10%inclusive.

2)Upper core region 90%to 100%inclusive.

APPLICABILITY:

MODE 1 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 2-19 AMENDMENT g2, 447,~, 434

6.0 ADMINISTRATIVE

CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C.20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a.Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, Rod Drop Time Limits for Specification 3/4.1.3.4, Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, Control Rod Insertion Limits for Specification 3/4.1.3.6, Axial Flux Difference for Specification 3/4.2.1, f.Heat Flux Hot Channel Factor for Specification 3/4.2.2, g..Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.Allowable Power Level for Specification 3/4.2.6.6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: WCAP-9272-P-A,"Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary), WCAP-8385,"Power Distribution Control and Load Following Procedures

-Topical Report," September 1974 (Westinghouse Proprietary), C.WCAP-10216-P-A, Revision 1A,"Relaxation of Constant Axial Offset Control/F~Surveillance Technical Specification," February 1994 (Westinghouse Proprietary), WCAP-10266-P-A Rev.2,"The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT 2 Page 6-17 AMENDMENT Z4, 438, XSAM, kV$

ATTACHMENT 4 TO AEP:NRC:1071T EXAMPLE OF PROPOSED CHANGE TO THE CORE OPERATING LIMITS REPORT IY COLE for Donald C.Cook Nuclear Plant Unit+Cycle PL 2.8 Allowable Po~er Leve-APL (Specification 3.2.6)C*K Z APL-min over Z for F (Z)*V(Z)*F Q P 2.8.1 V(Z)is provided in Table 1 for+5%AFD target band 2.8.2 CPQ and K(Z)are provided in COLR Sections 2.6.1 and 2.6.2, respectively 2.8.3 p Fp>b bvrn~g deP~~cleng e~pc 1'4A":~he~gu.reap'is)css~~<r eying.I+o@go g~w4.z 4&nup 44 g(cab~.g-6o.<lg5o>>+Page 6 of 11

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