Latest revision as of 13:36, 22 October 2019

Text

Proposed Tech Specs Re Incorporation of Cycle & Burnup Dependent Peaking Factor Penalty
	ML17332A768
Person / Time
Site:	Cook
Issue date:	05/25/1995
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17332A767	List: ML17332A766; ML17332A768;
References
	NUDOCS 9505310316
	Download: ML17332A768 (12)
	v • d • e

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 4A'R-ce, bi crap d~pe.~de<J yaw c.by >~+~ +"+l ~

F P ~pcs+

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 3/4 2-LS AM-ID.":-Vr NO82, l'29,;25, 9505310316 950525 PDR ADQCK 05000315 p PDR

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. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),

~ pcV) 5<osw lPL c ~ 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, p

shall be oaken:

~~~. 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. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),

@v'i'.io ~ l A c ~ WCAP-10216-P-A, Par~, "Relaxation of Constant Axial Offset Control/F Surveillance" Technical Specification," Jun %Gi (Westingh8use Proprietary), @brea~

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 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLEPOWER LEVEL - APL LIMITINGCONDITION FOR OPERATION 3.2.6 THERMALPOWER shall be less than or equal to ALLOWABLEPOWER LEVEL (APL), given by the following relationships:

APL = min over Z of CFQ x K(Z) x 100%, or 100%, whichever is less.

F Z < Z F 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 Fg(Z) with exposure.

~KZ Then either of the penalties, F>, shall be taken:

Fp = burnup dependent penalty specified in the COLR, or Ft, = 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 Fo(z) is not increasing.

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'ODE1 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 2-15 AMENDMENTSR) ~) 4%) 446

6.0 ADMINISTRATIVECONTROLS 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 AMENDMENT69, 484, kV4, 480

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLEPOWER LEVEL - APL LIMITINGCONDITION FOR OPERATION 3.2.6 THERMALPOWER shall be less than or equal to ALLOWABLEPOWER LEVEL (APL), given by the following relationships:

APL = min over Z of CFQ x K(Z) x 100%, or 100%, whichever is less.

F < < > F 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 no i xi with exposure.

K x Then either of the penalties, Fp, shall be taken:

Fp = burnup dependent penalty specified in the COLR, or Fp = 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 FQ (2) is not increasing.

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-UNIT2 Page 3/4 2-19 AMENDMENTg2, 447, ~, 434

6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR 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-UNIT2 Page 6-17 AMENDMENTZ4, 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 P Q

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

@@ Line 17: / Line 17: @@
 =Text=
-{{#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
-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.
+(~),     given by   the followfng relationship:
-oV(Z)isthefunctionspecified intheCOLR.oF1.00exceptwhensuccessive steady-state powerdiscrfbucion mapsindicateanincreasefnmaxoverZofFZwithexposure.
+APL      min over 2    o F (Z) ~(Z)
-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.
+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.
-KgZ)oTheabovelimitisnocapplicable inthefollowing coreregions.1)Lowercoreregion0%tol0%inclusive.
+o   F  (Z) f.s the measured hot channel factor including a          3%
-)Uppercoreregion90%to100%inclusive.
+manufacturing tolerance uncertainty and a          5%  measuremenc uncercaf.nty.
-APPLICABILITY:
+o  V(Z) is the function specified        in the   COLR.
-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:
+o  F        1.00 except when successive steady-state power discrfbucion maps     indicate an increase fn max over Z of F Z with exposure.
-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.
+K Z)
-PowerLevel.for-Specification-3/4i2.6:
+Then     either of the penaltf.es,   F , shall   be taken:
-.9.1.9.2 Theanalytical methodsusedtodetermine thecoreoperating limitsshallbethosepreviously reviewedandapprovedbytheNRCin:a.WCAP-9272-P-A, "Westinghouse ReloadSafetyEvaluation Methodology,"
+p 4A'R-ce, bi crap d~pe.~de<J       yaw c.by              >~+~ +"+l ~
-July1985(Westinghouse Proprietary),
+F P                                                  ~pcs+
-b.c~WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures
+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.
--TopicalReport,"September 1974(Westinghouse Proprietary),
+: 1)      Lower core region  0%   to l0% inclusive.
-~pcV)5<oswlPLWCAP-10216-P-A,~Par~,
+: 2)      Upper core region  90% to 100% inclusive.
-"Relaxation ofConstantAxialOffsetControl/F Surveillance Technical Specification,"
+APPLICABILITY:       MODE 1 E ~
-tun~989.(Westingh8use Proprietary),
+COOK   NUC~     PLANT - UNIT 1                3/4 2-LS               AM-ID.":-Vr NO82,  l'29,;25, 9505310316 950525 PDR     ADQCK 05000315 p                     PDR
-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.
-)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.
-.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.
-)Uppercoreregion90%to100%inclusive.
-APPLICABILITY'ODE 1COOKNUCLEARPLANT-UNIT 1Page3/42-15AMENDMENT SR)~)4%)446
-==6.0 ADMINISTRATIVE==
+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.
-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:
+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.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,
-July1985(Westinghouse Proprietary),
+: b. Rod Drop Time     Limits for Specification 3/4.1.3.3,
-WCAP-8385, PowerDistribution ControlandLoadFollowing Procedures
+: c. Shutdown Rod     Insertion Limits for Specification 3/4.1.3.4,
--TopicalReport,"September 1974(Westinghouse Proprietary),
+: d. Control   Rod   Insertion Limits for Specification 3/4.1.3.5,
-WCAP-10216-P-A, RevisionIA,"Relaxation ofConstantAxialOffsetControl/F<Surveillance Technical Specification,"
+: e. Axial Flux Difference for Specification 3/4.2.1,
-February1994(Westinghouse Proprietary),
+: f. Heat Flux Hot Channel Factor           for Specification 3/4.2.2,
-WCAP-10266-P-A Rev.2,The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).
+: g. Nuclear Enthalpy Rise Hot Channel'Factor for Specification 3/4.2.3,   and
-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:
+: h. Allowable. Power Level. for- Specification-3/4i2.6:
-APL=minoverZofF<<>Fx100%,or100%,whichever isless.CFQxK(Z)CFQistheF~limitatRATEDTHERMALPOWERspecified intheCOLRforWestinghouse orExxonfuel.F<(Z)isthemeasuredhotchannelfactorincluding a3%manufacturing tolerance uncertainty anda5%measurement uncertainty.
+.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:
-V(Z)isthefunctionspecified intheCOLR.Fp=1.00exceptwhensuccessive steady-state powerdistribution mapsindicateanincreaseinntaxoverZoiwithexposure.
+: a. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary),
-noixiKxTheneitherofthepenalties, Fp,shallbetaken:Fp=Fp=burnupdependent penaltyspecified intheCOLR,or1.00providedthatSurveillance Requirement 4.2.6.2issatisfied onceper7Effective FullPowerDaysuntiltwosuccessive mapsindicatethatthemaxoverZofisnotincreasing.
+: b. WCAP-8385, "Power      Distribution Control and Load Following Procedures     - Topical Report," September 1974 (Westinghouse Proprietary),
-FQ(2)oTheabovelimitisnotapplicable inthefollowing coreregions.1)Lowercoreregion0%to10%inclusive.
+                               ~ pcV) 5<osw  lPL c ~  WCAP-10216-P-A,~Par~,            "Relaxation of Constant Axial Offset Control/F      Surveillance Technical Specification," tun~989.
-)Uppercoreregion90%to100%inclusive.
+(Westingh8use Proprietary),                                  Fc,b u~r y 1
-APPLICABILITY:
+                                                                                      'l t4
-MODE1COOKNUCLEARPLANT-UNIT 2Page3/42-19AMENDMENT g2,447,~,434
+: 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
-==6.0 ADMINISTRATIVE==
+POQZR DISTRIBUTION     LLfXTS ALLOVhBLE POSE    I VEL -    APL
-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,"
+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:
-July1985(Westinghouse Proprietary),
+                    ,g   F (Z)xU(Z)xF p
-WCAP-8385, "PowerDistribution ControlandLoadFollowing Procedures
+o  CFQ   is  the F    liaic   at RATED TBGQQL      POWER  specified in the  COLR for  VescinghPuse      or Exxon fuel.
--TopicalReport,"September 1974(Westinghouse Proprietary),
+o  F (Z)    is the measured hot channel factor, including a 3i mPnufacturing tolerance uncertaincy and a 5% aeasurenenc uncartaintJJ.
-C.WCAP-10216-P-A, Revision1A,"Relaxation ofConstantAxialOffsetControl/F~Surveillance Technical Specification,"
+o  V(Z)    is the func ion specified in         the  COLR.
-February1994(Westinghouse Proprietary),
+           ~  F   ~ 1.00 except vhea successive         steady-state poser distribution alps indicate an increase ia         max  over   Z of F Z vich exposure.
-WCAP-10266-P-A Rev.2,"The1981VersionofWestinghouse Evaluation ModeUsingBASHCode,"March1987(Westinghouse Proprietary).
+K Z)
-COOKNUCLEARPLANT-UNIT 2Page6-17AMENDMENT Z4,438,XSAM,kV$
+Thea   either'f     che  following penalcies,      F, p
-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}}
+shall be oaken:
+                         ~~~. 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.
+.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. WCAP-8385, "Power     Distribution Control         and Load Following Procedures   -  Topical     Report,"   September    1974 (Westinghouse Proprietary),
+                                @v'i'.io ~ l A c ~    WCAP-10216-P-A,    Par~, "Relaxation of Constant Axial Offset Control/F Surveillance" Technical Specification," Jun %Gi (Westingh8use Proprietary),                                   @brea~
+: 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
+/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLEPOWER LEVEL - APL LIMITINGCONDITION FOR OPERATION 3.2.6  THERMALPOWER shall          be less than or equal to ALLOWABLEPOWER       LEVEL (APL), given by the following relationships:
+APL = min over Z of             CFQ x    K(Z)       x 100%, or 100%, whichever is less.
+F Z         < Z       F 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 Fg(Z) with exposure.
+                                                      ~KZ Then either of the penalties, F>, shall be taken:
+Fp  =    burnup dependent penalty specified in the COLR, or Ft, =    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 Fo(z) is not increasing.
+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'ODE1 COOK NUCLEAR PLANT-UNIT 1                     Page 3/4 2-15         AMENDMENTSR)         ~) 4%) 446
+.0      ADMINISTRATIVECONTROLS 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.
+.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            AMENDMENT69, 484, kV4, 480
+/4   LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.2 POWER DISTRIBUTION LIMITS ALLOWABLEPOWER LEVEL - APL LIMITINGCONDITION FOR OPERATION 3.2.6 THERMALPOWER shall be          less than or equal to ALLOWABLEPOWER LEVEL (APL), given by the following relationships:
+APL = min over Z of             CFQ x    K(Z)       x 100%, or 100%, whichever is less.
+F <         < >       F 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 no i xi with exposure.
+K x Then either of the penalties, Fp, shall be taken:
+Fp =     burnup dependent penalty specified in the COLR, or Fp =     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   FQ (2) is not increasing.
+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-UNIT2                     Page 3/4 2-19          AMENDMENTg2, 447,         ~, 434
+.0      ADMINISTRATIVECONTROLS MONTHLYREACTOR 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.
+.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-UNIT2                         Page 6-17            AMENDMENTZ4, 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 P Q
+.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}}

ML17332A768: Difference between revisions

Latest revision as of 13:36, 22 October 2019

Text

Navigation menu

ML17332A768: Difference between revisions

Latest revision as of 13:36, 22 October 2019

Text

Navigation menu

Search