ML071070387

Cycle 27 and 28 Core Operating Limits Reports

ML071070387
Person / Time
Site:	Kewaunee  (DPR-043)
Issue date:	04/16/2007
From:	Gerald Bichof Dominion, Dominion Energy Kewaunee
To:	Document Control Desk, NRC/NRR/ADRO
References
07-0241
Download: ML071070387 (56)

Text

Dominion Energy Kewaunee, Inc.

dl00 I ) o l n ~ n ~ o n Boulevdrd. Glrn Allrn, VA 2 3 0 0 0 A p r i l 16, 2007 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 1

Dominion, Serial No. 07-0241 KPSILICICDS: RO Docket No. 50-305 License No. DPR-43 DOMINION ENERGY KEWAUNEE. INC.

KEWAUNEE POWER STATION CYCLE 27 AND 28 CORE OPERATING LIMITS REPORTS Pursuant to Kewaunee Power Station (KPS) Technical Specification (TS) 6.9.a.4.D, enclosed are copies of the KPS cycle 27, revision 1 and cycle 28, revision 0, Core Operating Limits Reports (COLR).

KPS TS 6.9.a.4.D states that the COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance to the NRC for each reload cycle. It was recently discovered during an internal review of site reporting requirements that the attached COLR's had not been submitted upon issuance, as required. This non-conformance has been documented in the KPS corrective action program and actions have been implemented to ensure that future COLR's are submitted to NRC upon issuance, as required. We apologize for any inconvenience this may have caused.

If you have any questions or require additional information, please contact Mr. Craig Sly at (804) 273-2784.

Very truly yours, Gerald T. Bischof u Vice President - Nuclear Engineering Commitments made by this letter: None.

References:

None Attachments:

1.

TRM 2.1, Kewaunee Nuclear Power Plant Core Operating Limits Report (COLR),

Cycle 27, Revision 1.

2.

TRM 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 28, Revision 0.

Serial No. 07-0241 Core Operating Limits Reports Page 2 of 2 cc: Regional Administrator, Region Ill U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 21 0 Lisle, I L 60532-4352 Ms. M. H. Chernoff U.S. Nuclear Regulatory Commission Mail Stop 8 G9A Washington, D. C. 20555 Mr. S. C. Burton NRC Senior Resident Inspector Kewaunee Power Station

Serial No. 07-0241 ATTACHMENT 1 TRM 2.1 KEWAUNEE NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT (COLR), CYCLE 27, REVISION 1 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

TRM 2.1 Kewaunee Nuclear Power Plant CORE OPERATING LIMITS REPORT (COLR)

CYCLE 27 REVISION 1 cl;rc.w~~

Appro wed d v \\

7 I

Date Mtg.#

I Table of Contents I

Section Title Paqe 1.0 CORE OPERATING LIMITS REPORT........................................................................... 1 2.0 OPERATING LIMITS......................

.............................................................................. 2 2.1 Reactor Core Safety Limits 2

2.2 Shutdown Margin (SDM) 2 2.3 Moderator Temperature Coefficient 2

2.4 Shutdown Bank Insertion Limit 2

2.5 Control Bank Insertion Limits............................................................................. 2 2.6 Nuclear Heat Flux Hot Channel Limits (F~~(z))

................................................... 3 2.7 Nuclear Enthalpy Rise Hot Channel Factor ( F ~ ~ )

............................................. 4 2.8 Axial Flux Difference (AFD)................................................................................. 4 2.9 Overtemperature AT Setpoint.............................................................................. 5 2.1 0 Overpower AT Setpoint........................................................................................ 5 2.1 1 RCS Pressure, Temperature, and Flow Departure From.................................... 6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration............................................................................ 6

List of Fiaures Figure.

Title Paqe Reactor Core Safety Limits Curve (1 772 MWt)................................................................ 7 Required Shutdown Reactivity vs Boron Concentration 8

Hot Channel Factor Normalized Operating Envelope (K(z))

9 Control Bank Insertion Limits 10 RAOC Summary of W(Z) at 1 50 MW DIMTU.................................................................. 11 RAOC Summary of W(Z) at 4000 MWDIMTU................................................................ 12 RAOC Summary of W(Z) at 8000 MWDIMTU................................................................ 13 RAOC Summary of W(Z) at 10000 MWDIMTU................................................................ 14 RAOC Summary of W(Z) at 12000 MWDIMTU................................................................ 15 RAOC Summary of W(Z) at 16000 MW DIMTU............................................................. 16 Penalty Factor, FP(%), for F~~"(z)........................................................................................ 17 Axial Flux Difference.................................................................................................... 18

List of Tables Table -

Title Page

1.

NRC Approved Methodologies for COLR Parameters 19 iii

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMlTS REPORT CYCLE 27 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Nuclear Power Plant (KNPP) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.a.4.

A cross-reference between the COLR sections and the KNPP Technical Specifications affected by this report is given below:

COLR Section 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.1 0 2.1 1 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5a Figure 5b Figure 5c Figure 5d Figure 5e Figure 5f Figure 6 Figure 7 KNPP TS 2.1 3.1 O.a 3.1.f.3 3.10.d.l 3.1 0.d.2 3.10.b.l.A 3.1 O.b.5 3.1 0.b.6.C.i 3.10.b.l.B 3.1 0.b.8 2.3.a.3.A 2.3.a.3.B 3.10.k 3.1 0.1 3.10.m.l 3.8.a.5 Description Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Limit Control Bank lnsertion Limits Heat Flux Hot Channel Factor (FQ(Z))

Nuclear Enthalpy Rise Hot Channel Factor (F,"~)

Axial Flux Difference (AFD)

Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration Reactor Core Safety Limits (1 772 MWt)

Required Shutdown Margin K(Z) Normalized Operating Envelope Control Bank Insertion Limits RAOC Summary of W(Z) at 150 MWDIMTU RAOC Summary of W(Z) at 4000 MWDJMTU RAOC Summary of W(Z) at 8000 MWDIMTU RAOC Summary of W (Z) at 10000 MW DJMTU RAOC Summary of W(Z) at 12000 MWDtMTU RAOC Summary of W (Z) at 16000 MW DIMTU Penalty Factor, Fp(%), for F ~ ~ ( Z )

Axial Flux Difference Cycle 27 Page 1 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 2.0 Operatins Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.

2.1 Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.

2.2 Shutdown Marain 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.

2.3 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and 1 60% RATED POWER, the moderator temperature coefficient shall be 5 5.0 pcmPF, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.

2.3.2 The reactor will have a moderator temperature coefficient no less negative than -8 pcmIoF for 95% of the cycle time at full power.

2.4 Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn (2 226 steps and 5 231 steps) when the reactor is critical or approaching criticality.

2.5 Control Bank Insertion Limit 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4.

Cycle 27 Page 2 of 24 Rev. 1 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 2.6 Nuclear Heat Flux Hot Channel Factor (FQ~(z))

2.6.1 F ~ ~ ( z )

Limits for Fuel fQN(z) x 1.03 x 1.05 I (2.35)lP x K(Z) for P > 0.5

[FRA-ANP Hvy]

F ~ ~ ( z )

x 1.03 x 1.05 I (4.70) x K(Z) for P 10.5

[FRA-ANP Hvy]

F ~ ~ ( z )

x 1.03 x 1.05 r (2.28)lP x K(Z) for P > 0.5

[FRA-ANP Std]

fQN(z) x 1.03 x 1.05 ~(4.56) x K(Z) for P 1 0.5

[FRA-ANP Std]

faN(z) x 1.03 x 1.05 I (2.50)lP x K(Z) for P > 0.5

[422 V+]

F ~ ~ ( z )

x 1.03 x 1.05 I (5.00) x K(Z) for P 5 0.5

[422 V+]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z

is the core height location for the Fa of interest 2.6.2 The measured ~

~

~

~

(

2

)

hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:

FQ"(Z) x 1.03 x 1.05 x W(Z)x F, 5 (2.35)lP x K(Z)

[FRA-ANP Hvy]

FoEQ(z) x 1.03 x 1.05 x W(Z)x Fp 5 (2.28)lP x K(Z)

[FRA-ANP Std]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z

is the core height location for the FQ of interest FP is the F ~ ~ ~ ( z )

penalty factor described in 2.6.3.

W(Z) is the function given in Figure 5 FQEQ(z) is a measured Fa distribution obtained during the target flux determination Cycle 27 Page 3 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 TRM 2.1 Revision 6 I

2.6.3 The penalty factor of 1.O shall be used for TS 3.1 0.b.6.A and TS 3.10.b.6.B.

The penalty factor provided in Figure 6 shall be used for TS 3.lO.b.6.C.i.

The penalty factor for all burnups outside the range of Figure 6 shall be 2%.

2.7 Nuclear Enthalpv Rise Hot Channel Factor FA^ )

N 2.7.1 F~~~ Limits for Fuel F

~

H

~

x 1.04 5 1.38 [ I + 0.3(1 -P)]

[FRA-ANP Hvy]

F ~ H ~

x 1.04 1 1.70 [1 + 0.3(1 -P)]

[422 V+]

F,H~ x 1.04 11.38 [ I + 0.3(1-P)]

[FRA-ANP Std]

where:

P is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.

Cycle 27 Page 4 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:

Indicated AT at RATED POWER, %

Average temperature, OF 573.0 OF Pressurizer Pressure, psig 2235 psig 1.195 0.01 5PF 0.000721psig 30 seconds 4 seconds An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qr and q b are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a)

For qt - qb within -1 5, +10 %, f(A1) = 0 (b)

For each percent that the magnitude of qt - qb exceeds +lo % the AT trip setpoint shall be automatically reduced by an equivalent of 1.51 % of RATED POWER.

(c)

For each percent that the magnitude of qt - qb exceed -15 % the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.

2.1 0 Overpower AT Setpoint Overpower AT setpoint parameter values:

lndicated AT at RATED POWER, %

Average temperature, OF 573.0 O F 1.095 0.0275I0F for increasing T; 0 for decreasing T 0.001031°F for T > T' ; 0 for T < T' 10 seconds 0 for all A1 Cycle 27 Page 5 of 24 Rev. 1 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 2.1 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.1 1.1 During steady state power operation, Tavg shall be < 576.7"F for control board indication or < 576.S°F for computer indication.

2.1 1.2 During steady state power operation, Pressurizer Pressure shall be

> 2217 psig for control board indication or > 2219 psig for computer indication 2.11.3 During steady state power operation, reactor coolant total flow rate shall be 2 186,000 gpm.

2.1 2 Refuelina Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of 2 5% A k/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.

Cycle 27 Page 6 of 24 Rev. 1 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 TRM 2.1 Revision 6 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel)

Cycle 27 Page 7 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 TRM 2.1 Revision 6 I

Figure 2 Required Shutdown Reactivity vs. Boron Concentration 0

200 400 600 800 lo00 1200 1400 1600 1800 2000 Full Power Equilibrium Boron Concentration

( P P ~ )

Cycle 27 Page 8 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Cycle 27 Figure 3 Hot Channel Factor Normalized Operating Envelope 0

1 2

3 4

5 6

7 8

9 1

0 1

1 1

2 Core height (ft)

Page 9 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 4 Control Bank Insertion Limits BANK D 0

10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Fully withdrawn shall be the condition where control rods are at a position within the interval 2 226 and 1231 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.

Cycle 27 Page 10 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUlREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5a RAOC Summary of W(Z) at 150 MWDIMTU 1.50 1.40 1.30 25 3

1.20 1.10 1.oo 0

1 2

3 4

5 6

7 8

9 10 11 12 Core Height (Feet)

Bottom Cycle 27 Page 11 of 24 Rev. 1 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LRvlITS REPORT CYCLE 27 Figure 5b RAOC Summary of W(Z) at 4000 MWDIMTU 1.50 1.40 1.30 fi r'

1.20 1.10 1.oo 0

1 2

3 4

5 6

7 8

9 10 11 12 B O N O ~

Core Height (Feet)

TOP Cycle 27 Page 12 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5c RAOC Summary of W(Z) at 8000 MWDIMTU 0

1 2

3 4

5 6

7 8

9 1

0 1

1 1

2 Bottom Core Height (Feet)

TOP Cycle 27 Page 13 of 24 Rev. 1 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5d RAOC Summary of W(Z) at 10000 MWDIMTU 1.50 1.40 1.SO 6-5 1.20 1.10 1.oo 0

1 2

3 4

5 6

7 8

9 10 11 12 Bottom Core Height (Feet)

TOP Cycle 27 Page 14 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 56 RAOC Summary of W(Z) at 12000 MWD/MTU 1.SO 1.40 1.30 1.20 1.10 l. o o - " " " " " " " " " " " " " " " ' " ' " " ' " -

0 1

2 3

4 5

6 7

8 9

10 11 12 Bottom Core Height (Feet)

TOP Cycle 27 Page 15 of 24 Rev. 1 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5f RAOC Summary of W(Z) at 16000 MWDIMTU 0

1 2

3 4

5 6

7 8

9 10 11 12

)ttom Core Height (Feet)

TOP Cycle 27 Page 16 of 24 Rev, 1 I

KEWAUNEE MJCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMlTS REPORT CYCLE 27 Figure 6 Penalty Factor, Fp (%), for F*O(Z)

Note: Linear interpolation is adequate for intermediate cycle burnup.

All cycle burnups outside the range of the table shall use a penalty factor, Fp, of 2.0%.

Refer to TS 3.1 0.b.6.C.

Cycle 27 Page 17 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Figure 7 Axial Flux Difference

-40

-3 0

-2 0

-1 0 0

10 20 3 0 4 0 Axial Flux Difference (% delta-I)

Note: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure RD 11.4.1 of the Reactor Data Manual.

Rev. 1 I Cycle 27 Page 18 of 24

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 NRC Approved Methodoloaies for COLR Parameters COLR Section Parameter 2.1 Reactor Gore Safety Limits Shutdown Margin 2.3 Moderator Temperature Coefficient 2.4 Shutdown Bank Insertion Limit NRC Approved Methodolo~y WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985 Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Off ice of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Cycle 27 Page 19 of 24

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 I

CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 (cont)

NRC Approved Methodoloaies for COLR Parameters COLR Section Parameter NRC Approved Methodology Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

2.5 Control Bank Insertion Limits WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report W PSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

2.6 Heat Flux Hot Channel Factor WCAP-10216-P-A, Revision 1 A, "Relaxation of Constant Axial Offset Control-Fa Surveillance Technical Specification,"

February 1994.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

W CAP-1 2945-P-A (Proprietary),

"Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes II-V, Rev. 1, and WCAP-14747 (Non-Proprietary), March 1998.

Cycle 27 Page 20 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter Cycle 27 Model NOTRUMP Nuclear Enthalpy Rise Hot Channel Factor (F~,H)

NRC Approved Methodolow ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PW R Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, dated December 1991.

WCAP-14449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revision1, and WCAP-14450-NP-A, Rev.1 (Non-Proprietary), October 1999.

WCAP-12610-P-A, 'Vantage+ Fuel Assembly Reference Core Report," April 1995.

WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code," August 1985.

Note: WCAP-10081 -A as referenced in TS which is the non-prop version of WCAP-1 0054-P-A.

WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the Code: Safety Injection into the Broken Loop and COSl Condensation Model," July 1997.

WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21, 1979, report date September 29,1978.

Kewaunee Nuclear Power Plant-Review forKewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

Page 21 of 24 Rev.1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 CORE OPERATING LIMTTS REPORT CYCLE 27 Table 1 (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC A~proved Methodology XN-82-06 (P)(A) Revision 1 and Supplements 2,4, and 5, "Qualifications of Exxon Nuclear Fuel for Extended Burnup, Exxon Nuclear Company, dated October 1986.

ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PW R Design Methodology for Rod Burnups for 62 GWd/MTUIn Advanced Nuclear Fuels Corporation, dated December 1991.

EMF-92-1 16 (P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.

Axial Flux Difference WCAP-10216-P-A, Revision 1 A, "Relaxation of Constant Axial Offset (AFD) Control-Fa Surveillance Technical Specification,"

February 1994.

Safely Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report W PSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

2.9 Reactor Protection System (RPS)

WCAP-8745-P-A, "Design Bases For The Instrumentation-Overtemperature AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Page 22 of 24 Rev. 1 I

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 CORE OPERATING LIMlTS REPORT CYCLE 27 Table 1 (cont)

NRC Approved Methodologies for COLR Parameters COLR Section Parameter 2.10 Reactor Protection System (RPS)

Instrumentation-Overpower AT 2.1 1 RCS Pressure, Temperature, and Flow Departure From Nucleate (DNB) Limits NRC Approved Methodoloay Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report W PSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

WCAP-11397-P-A, "Revised Thermal Design Procedure, "April 1989, for those events analyzed using RTDP WCAP-15591, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology-Kewaunee Nuclear Power Plant (Power Uprate to 1757 MWt-NSSS Power with Feedwater Venturis, or 1780 MWt-NSSS Power with Ultrasonic Flow Measurements, and 54F Replacement Steam Generators), Revision 1, December Cycle 27 Page 23 of 24

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 6 CORE OPERATING LIMITS REPORT CYCLE 27 2002, Proprietary. Safety Evaluation dated July 8, 2003.

Table 1 (cont)

NRC Approved Methodoloqies for COLR Parameters COLR Section Parameter NRC Approved Methodoloqy Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report W PSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.

Boron Concentration WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Cycle 27 Page 24 of 24 Rev. 1 I

Serial No. 07-0241 ATTACHMENT 2 TRM 2.1 KEWAUNEE POWER STATION CORE OPERATING LIMITS REPORT (COLR),

CYCLE 28, REVISION 0 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)

CYCLE 28 REVISION 0 Approved

Table of Contents Section.

Title Page 1.0 CORE OPERATING LIMITS REPORT....................

............................................... 1 2.0 OPERATING LIMITS 2

2.1 Reactor Core Safety Limits 2

2.2 Shutdown Margin (SDM)................................................................................. 2 2.3 Moderator Temperature Coefficient.................................................................... 2 2.4 Shutdown Bank Insertion Limit.......................................................................... 2 2.5 Control Bank Insertion Limits............................................................................. 2 2.6 Nuclear Heat Flux Hot Channel Limits (F~~(z))

.................................................. 3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F*"~).............................................

4 2.8 Axial Flux Difference (AFD)................................................................................

4 2.9 Overtemperature AT Setpoint............................................................................

5 2.1 0 Overpower AT Setpoint................................................................................... 5 2.1 1 RCS Pressure. Temperature. and Flow Departure From................................... 6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration...................................................................... 6

I List of Fiqures I

1.

Reactor Core Safety Limits Curve (1772 MWt) 7 2

Required Shutdown Reactivity vs Boron Concentration 8

3.

Hot Channel Factor Normalized Operating Envelope (K(z))

9 4.

Control Bank Insertion Limits....................................................................................... 10 5.

W(Z) Values (Top and Bottom 9% excluded)................................................................ 11 EQ 6.

Penalty Factor. Fp (%). for Fa (Z)............................................................................. 13 7.

Axial Flux Difference.....................................................................................................

14

List of Tables 1

I I

Table Title Pape

1.

NRC Approved Methodologies for COLR Parameters 15

KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 I

.O CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Kewaunee Power Station (KPS) has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.a.4.

A cross-reference between the COLR sections and the KPS Technical Specifications affected by this report is given below:

COLR Section 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7 KPS TS 2.1 3.10.a 3.1.f.3 3.10.d.l 3.10.d.2 3.10.b.l.A 3.10.b.5 3.10.b.6 3.10.b.6.C.i 3.1 O.b.7 3.10.b.l.B 3.1 0.b.8 2.3.a.3.A 2.3.a.3.B 3.10.k 3.1 0.1 3.10.rn.l 3.8.a.5 Description Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Limit Control Bank lnsertion Limits Heat Flux Hot Channel Factor (Fo(Z))

Nuclear Enthalpy Rise Hot Channel Factor (F,,.,~)

Axial Flux Difference (AFD)

Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration Reactor Core Safety Limits (1772 MWt)

Required Shutdown Margin K(Z) Normalized Operating Envelope Control Bank lnsertion Limits W(Z) Values (Top and Bottom 9% excluded)

Penalty Factor, F,, for F ~ ~ ~ ( z )

Axial Flux Difference Cycle 28 Page 1 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 2.0 O~eratina Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.a.4.

Reactor Core Safety Limits The combination of rated power level, coolant pressure, and coolant temperature shall not exceed the limits shown in COLR Figure 1 (1772 MWt). The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.

Shutdown Margin 2.2.1 When the reactor is subcritical prior to reactor startup, the SHUTDOWN margin shall be at least that shown in COLR Figure 2.

Moderator Tem~erature Coefficient 2.3.1 When the reactor is critical and l 60% RATED POWER, the moderator temperature coefficient shall be 15.0 pcmIoF, except during LOW POWER PHYSICS TESTING. When the reactor is > 60% RATED POWER, the moderator temperature coefficient shall be zero or negative.

2.3.2 The reactor will have a moderator temperature coefficient no less negative than -8 pcrnJ0F for 95% of the cycle time at full power.

Shutdown Bank Insertion Limit 2.4.1 The shutdown rods shall be fully withdrawn (2 225 steps and I230 steps) when the reactor is critical or approaching criticality.

Control Bank lnsertion Limits 2.5.1 The control banks shall be limited in physical insertion; insertion limits are shown in COLR Figure 4.

Cycle 28 Page 2 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 2.6 Nuclear Heat Flux Hot Channel Factor (F~~~z))

2.6.1

~ ~ ~ ( 2 )

Limits for Fuel FaN@) x 1.03 x 1.05 I (2.50)IP x K(Z) for P > 0.5

[422 V+]

FQN(Z) x 1.03 x 1.05 5 (5.00) x K(Z) for P 1 0.5

[422 V+]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z

is the core height location for the Fa of interest 2.6.2 The measured F Q ~ ~ ( z )

hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:

F ~ ~ ( Z )

x 1.03 x 1.05 x W(Z) x Fp 5 (2.5)l P x K(Z)

[422 V +]

where:

P is the fraction of full power at which the core is OPERATING K(Z) is the function given in Figure 3 Z

is the core height location for the Fa of interest Fp is the ~

~

~

~

(

2

)

penalty factor described in 2.6.3.

W(Z)

Is the function given in Figure 5 F ~ ~ ~ ( z )

is a measured FQ distribution obtained during the target flux determination 2.6.3 The penalty factor of 1.O shall be used for TS 3.lO.b.6.A and TS 3.10.b.6.B.

The penalty factor provided in Figure 6 shall be used for TS 3.10.b.6.C.i.

The penalty factor for all bumups outside the range of Figure 6 shall be 2%.

Cycle 28 Page 3 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 2.7 2.7.1 F~~~ Limits for Fuel where:

P is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.

Cycle 28 Page 4 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:

Indicated AT at RATED POWER, %

Average temperature, OF 573.0 OF Pressurizer Pressure, psig 2235 psig 1.195 0.015PF 0.000721psig 30 seconds 4 seconds An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where q, and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a)

For qt - qb within -15, +10 %, f(AI) = 0 (b)

For each percent that the magnitude of qt - q b exceeds +10 % the AT trip setpoint shall be automatically reduced by an equivalent of 1.51 % of RATED POWER.

(c)

For each percent that the magnitude of qt - qb exceed -1 5 % the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.

2.1 0 Ovemower AT Set~oint Overpower AT setpoint parameter values:

lndicated AT at RATED POWER, %

Average temperature, OF 573.0 OF 1.095 0.0275I0F for increasing T; 0 for decreasing T 0.001031°F for T > T' ; 0 for T < T' 10 seconds 0 for all AI Cycle 28 Page 5 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 2.1 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.1 1.1 During steady state power operation. Tavg shall be < 576.7"F for control board indication or < 576.5"F for computer indication.

2.1 1.2 During steady state power operation, Pressurizer Pressure shall be

> 2217 psig for control board indication or > 2219 psig for computer indication 2.1 1.3 During steady state power operation, reactor coolant total flow rate shall be 2 186,000 gprn.

2.12 Refuelinq Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of 2 5% A k/k shall be maintained in the Reactor Coolant System during reactor vessel head removal or while loading and unloading fuel from the reactor.

Cycle 28 Page 6 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Figure I Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel)

Cycle 28 20 40 60 80 100 Core Power (percent of 1772 MWt)

Page 7 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 TRM 2.1 Revision 0 Figure 2 Required Shutdown Reactivity vs. Boron Concentration Cycle 28 Full Power Equilibrium Boron Concentration

( P P ~ )

Page 8 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(z))

Cycle 28 0

1 2

3 4

5 6

7 8

9 1

0 1

1 1

2 Core height (ft)

Page 9 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Figure 4 Control Bank Insertion Limits 0

10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Fully withdrawn shall be the condition where control rods are at a position between the interval 1 225 and 5 230 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.

Cycle 28 Page 10 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Figure 5 - W(Z) Values (Top and Bottom 9% excluded)

Cycle 28 Page 11 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Figure 5 Cont'd (Top and Bottom 9% excluded)

Cycle 28 Page 12 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATTNG LIMITS REPORT CYCLE 28 Figure 6 Penalty Factor, F, (%), for F Q ~ ~ ( z )

I Cycle Burnup I Penalty I

Factor I (MWDMTv I Fp(%)

Note: Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of the table shall use a penalty factor, Fp, of 2.0%.

Refer to TS 3.10.b.6.C.

Cycle 28 Page 13 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATTNG LIMITS REPORT CYCLE 28 Figure 7 Axial Flux Difference 4 0

-3 0

-20

-1 0 0

10 20 30 40 Axial Flux Difference (% delta-I)

Note: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure RD 11.4.1 of the Reactor Data Manual.

Cycle 28 Page 14 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Table 1 NRC Approved Methodologies for COLR Parameters COLR Section Parameter 2.1 Reactor Core Safety Limits Shutdown Margin 2.3 Moderator Temperature Coefficient 2.4 Shutdown Bank Insertion Limit NRC A~proved Methodolouy WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee* Report, dated August 21,1979, report date September 29, 1978.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Cycle 28 Page 15 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Table I (cont)

NRC Approved Methodoloqies for COLR Parameters COLR Section Parameter NRC A ~ ~ r o v e d Methodoloay Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

Control Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on 'Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

2.6 Heat Flux Hot Channel Factor WCAP-10216-P-A, Revision 1 A, 'Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification,"

February 1994.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

WCAP-12945-P-A (Proprietary),

"Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes II-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.

Cycle 28 Page 16 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Table I (cont)

NRC Amroved Methodoloaies for COLR Parameters COLR Section Parameter Model NOTRUMP Nuclear Enthalpy Rise Hot Channel Factor (F~,~)

NRC A~proved Methodology ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Bumups of 62 GWdlMTU," Advanced Nuclear Fuels Corporation, dated December 1991.

WCAP-14449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revision1, and WCAP-14450-NP-A, Rev. 1 (Non-Proprietary), October 1999.

WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995.

WCAP-10054-P-ANVCAP-10081 -NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,"

August 1985.

WCAP-10054-P-AMICAP-1008 1 -NP-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the Code: Safety Injection into the Broken Loop and COSl Condensation Model," July 1997.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review forKewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Cycle 28 Page 17 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Revision 3 (TAC NO MB0306) dated September 10,2001.

Table I (cont)

NRC Approved Methodoloqies for COLR Parameters COLR Section Parameter Axial Flux Difference NRC Amroved Methodoloay XN-82-06 (P)(A) Revision 1 and Supplements 2,4, and 5, "Qualifications of Exxon Nuclear Fuel for Extended Bumup, Exxon Nuclear Company, dated October 1986.

ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Bumups for 62 GWdlMTU," Advanced Nuclear Fuels Corporation, dated December 1991.

EMF-92-1 16 (P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.

WCAP-10216-P-A, Revision 1 A, "Relaxation of Constant Axial Offset (AFD) Control-Fo Surveillance Technical Specification,"

February 1994.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

2.9 Reactor Protection System (RPS)

WCAP-8745-P-A, "Design Bases For The Instrumentation-Overtemperature AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Cycle 28 Page 18 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Table I (cont)

NRC Approved Methodoloaies for COLR Parameters COLR Section Parameter NRC Approved Methodoloqy Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

2.10 Reactor Protection System (RPS)

WCAP-8745-P-A, "Design Bases For The Instrumentation-Overpower AT Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986.

Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,"

Rev. 1, May 2000.

Cycle 28 Page 19 of 20 Rev. 0

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 0 CORE OPERATING LIMITS REPORT CYCLE 28 Table I (cont)

NRC Approved Methodolo~ies for COLR Parameters COLR Section Parameter NRC Approved Methodoloqy 2.1 1 RCS Pressure, Temperature, and WCAP-11397-P-A, "Revised Thermal Design Flow Departure From Nucleate Procedure, "April 1989, for those events (DNB) Limits analyzed using RTDP Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10,2001.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.

Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods for Application to Kewaunee" Report, dated August 21,1979, report date September 29, 1978.

Cycle 28 Page 20 of 20 Rev. 0