ML17332A768

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)

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 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 >>+

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