ML032040035

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Core Operating Limits Report (Colr), Cycle 26, Revision 2
ML032040035
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 07/14/2003
From: Coutu T
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-03-076
Download: ML032040035 (27)
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Text

Committed to Nuclear Excellene Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC NRC-03-076 July 14, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 KEWAUNEE NUCLEAR POWER PLANT DOCKET 50-305 LICENSE No. DPR-43 KEWAUNEE NUCLEAR POWER PLANT - CORE OPERATING LIMITS REPORT (COLR),

CYCLE 26, REVISION 2 In accordance with the requirements of Technical Specification 6.9.a.4, enclosed is Revision 2 of the Cycle 26, Core Operating Limits Report (COLR).

If you have any questions, please contact Mr. Gerald Riste at (920) 388-8424.

This letter contains no new commitments and no revisions to existing commitments.

Thomas Coutu Site Vice-President, Kewaunee Plant GOR cc US NRC, Region III US NRC, Senior Resident Inspector NRC KNPP Project Manager Enclosure - KNPP Core Operating Limits Report N490 Highway 42

  • Kewaunee, Wisconsin 54216-9510 Telephone: 920.388.2560

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

CYCLE 26 REVISION 2 Approved



FORC;Chainnan Date oq

-- / Y46 Mtg.#

M--

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 (FQN(Z)).........................

3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FmN)........................................

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

4 2.9 Overtemperature AT Setpoint....................................... 5 2.10 Overpower AT Setpoint.......................................

5 2.11 RCS Pressure, Temperature, and Flow Departure From....................................

6 Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration....................................... 6 i

List of Figures Figure Title-Pame

1.

Reactor Core Safety Limits Curve (1673 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 5a.

RAOC Summary of W(Z) at 150 MWD/MTU.........................................

11 5b.

RAOC Summary of W(Z) at 5000 MWDIMTU......................................... 12 5c.

RAOC Summary of W(Z) at 7000 MWD/IMTU.........................................

13 5d.

RAOC Summary of W(Z) at 12000 MWD/MTU.........................................

14 Se.

RAOC Summary of W(Z) at 16000 MWD/MTU.........................................

15

6.

Penalty Factors in Excess of 2% per 31 EFPD......................................... 16

7.

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

17 ii

I List of Tables I

Table Title PaQe

1.

NRC Approved Methodologies for COLR Parameters 18 l

iii

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 lI CORE OPERATING LIMTS REPORT CYCLE 26 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) 6.9.4.

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 2.10 2.11 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5a Figure 5b Figure 5c Figure 5d Figure 5e Figure 6 Figure 7 KNPP TS 2.1 3.10.a 3.1.f.3 3.10.d.1 3.10.d.2 3.10.b.1.A 3.1 0.b.5 3.10.b.6.C.i 3.10.b.1.B 3.10.b.8 2.3.a.3.A 2.3.a.3.B 3.10.k 3.10.1 3.10.m.1 3.8.a.5 Description Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Limit Control Bank Insertion Limits Heat Flux Hot Channel Factor (FQ(Z))

Nuclear Enthalpy Rise Hot Channel Factor (F MN)

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 (1673 MWt)

Required Shutdown Margin K(Z) Normalized Operating Envelope Control Bank Insertion Limits RAOC Summary of W(Z) at 150 MWD/MTU RAOC Summary of W(Z) at 5000 MWD/MTU RAOC Summary of W(Z) at 7000 MWD/MTU RAOC Summary of W(Z) at 12000 MWD/MTU RAOC Summary of W(Z) at 16000 MWD/MTU Penalty Factor in Excess of 2% per 31 EFPD Axial Flux Difference I

Cycle 26 Page 1 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 2.0 Operating 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 (1673 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 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.

2.3 Moderator Temperature Coefficient 2.3.1 When the reactor is critical and

  • 60% RATED POWER, the moderator temperature coefficient shall be *5.0 pcm/0F, 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 pcm/OF 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 (2 224 steps and < 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 26 Page 2 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 2.6 Nuclear Heat Flux Hot Channel Factor (FgN(Z))

2.6.1 FON(Z) Limits for Fuel FQN(Z) x 1.03 x 1.05 * (2.35)/P x K(Z) for P > 0.5 F0N(Z) x 1.03 x 1.05 * (4.70) x K(Z) for P

  • 0.5 FQN(Z) x 1.03 x 1.05 * (2.28)/P x K(Z) for P > 0.5 F0N(Z) x 1.03 x 1.05 *(4.56) x K(Z) for P
  • 0.5 FaN(Z) x 1.03 x 1.05 5 (2.50)/P x K(Z) for P > 0.5 FaN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P < 0.5

[FRA-ANP Hvyj

[FRA-ANP Hvy]

[FRA-ANP Std]

[FRA-ANP Std]

[422 V+]

[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 FQ of interest 2.6.2 The measured F0EQ(Z) hot channel factors underequilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:

FQEQ(Z) x 1.03 x 1.05 x W(Z) < (2.35)/P x K(Z)

[FRA-ANP HvyJ F0EQ(Z) x 1.03 x 1.05 x W(Z) < (2.28)/P x K(Z)

[FRA-ANP Std]

FQEO(Z) x 1.03 x 1.05 x W(Z) * (2.5)/ P x K(Z)

[422 V 4]

where:

P is the fraction of full power at which the core is OPERATING W(Z) is defined in COLR Figure 5 FaEQ(Z) is a measured Fa distribution obtained during the target flux determination 2.6.3 The penalty factor for TS 3.10.b.6.C.i provided in Figure 6 shall be used.

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

Cycle 26 Page 3 of 22 Rev. 2 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 26 2.7 Nuclear Enthalny Rise Hot Channel Factor (FAN")

TRM 2.1 Revision 2 2.7.1 F N Limits for Fuel FmN x 1.04

  • 1.58 [1+ 0.3(1-P)]

[FRA-ANPHvy]

FMN x 1.04*s 1.70 [1 + 0.3(1-P)J FaHN x 1.04 *1.55 [1 + 0.3(1-P)]

[422 V+J

[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 26 Page 4 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:

ATO

=

Indicated AT at RATED POWER, %

T

=

Average temperature, ¶F T'

573.0 OF P

=

Pressurizer Pressure, psig P

=

2235 psig K,

=

1.20 K2

=

0.015/F K3

=

0.00072/psig Tj

=

30 seconds T2

=

4 seconds f(AI)

=

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 qt 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 -22, +12 %, f(AI) = 0 (b)

For each percent that the magnitude of qt - qb exceeds +12 % the AT trip setpoint shall be automaticallyreduced byan equivalentof 0.96 % of RATED POWER.

(c)

For each percent that the magnitude of qt - qb exceed -22 % the AT trip setpoint shall be automatically reduced byan equivalent of 4.00% of RATED POWER.

2.10 Overmower AT SetDoint Overpower AT setpoint parameter values:

ATo

=

Indicated AT at RATED POWER, %

T

=

Average temperature, OF T'

573.0°F K4 1.095 K5 0.0275POF for increasing T; 0 for decreasing T K6 2

0.00103/OF for T > T'; 0 for T<r T3

=

10 seconds f(Al)

=

0for all AI Cycle 26 Page 5 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.71F for control board indication or < 576.50F for computer indication.

2.11.2 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

Ž 186,000 gpm.

2.12 Refueling Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2426 ppm and a shutdown margin of Ž 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 26 Page 6 of 22 Rev. 2 1

KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 Figure 1 665 -

\\24250 sia Unacceptable Operation

@ 2 5

I

\\2000 psia CL Ad 620 5 - --- --- --

t E

0 0

Acceptable Operation 0

565 0

20 40 60 80 100 120 Core Power (percent of 1673 MWt)

Cycle 26 Page 7 of 22 Rev. 2

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUMEMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 26 TRM 2.1 Revision 2 Figure 2 Required Shutdown Reactivity vs. Boron Concentration

.a, 0

M-CD 0~

la E0.QL 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

1 ~~~~(1430) -I 1 l

-1

_ 1

_ I 0

200 Full 400 600 800 1000 1200 1400 1600 1800 2000 Power Equilibrium Boron Concentration (ppm)

Cycle 26 Page 8 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMSTS REPORT CYCLE 26 TRM 2.1 Revision 2 I

Figure 3 Hot Channel Factor Normalized Operating Envelope 1.2 1.1 I

0.9 0.8 0.7 X- 0.6 0.5 0.4 0.3 0.2 0.1 0

I I

_I I

I I I

I I

I I

I I

i (0,1.0)

I I

I (6,1.0)

I I

I I

I I

I I

I I.

I I

T I

T T

(12,1.0)

I i

____ I

____ I

____ F

[1 11-I.

__ I ii

__ I

__ I I

T I

__ I i __

____ I

____ I

-

I 1---

I I_

_ Li

,

qwi YIW ¶...



  • IYI*

I...

0 1

2 3

4 5

6 7

8 9

10 11 12 Core height (ft)

Cycle 26 Page 9 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 26 Figure 4 Control Bank Insertion Limits TRM 2.1 Revision 2 la-C, 4-S co L.

0 0

240 220 200 180 160 140 120 100 80 60 40 20 0

0 10 20 30 40 50 60 70 Percent of Rated Thermal Power 80 90 100 Fully withdrawn shall be the condition where control rods are at a position within the interval

> 224 and < 231 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 128 steps.

Note: If operating with a Rod Bank tip-to-tip distance of 126 steps, an additional penalty factor of 2% must be applied during transient FQ surveillance.

Cycle 26 Page 10 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 26 TRM 2.1 Revision 2 lI Figure 5a RAOC Summary of W(Z) at 150 MWD/IMTU 1.51 1.4C 1.30 N

1.20 1.10 1.00 I

I

~

~

~

Hl l

14

~

~

~

~

~

~ ~~I A

I

~~~~~~~~~~~~~~~~~~I la

  • 1 I~~~~~~~

~~~~

~~~~~

'I ~~~~~~1

~

1 i

tL t

l 0

1 2

3 4

5 6

7 8

9 10 11 12 Core Height (Feet)

Bottom Top Cycle 26 Page 11 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 Figure 5b RAOC Summary of W(Z) at 5000 MWD/MTU 1.5 IN 1.41 1.3C 1.20 1.10 1.00 1 1AI f

1f L

I I

L I A

AA ii I

[IiI~~~~~~~~~~~~~~~ittztII III FIII!1IIi]

I

]t~~~~~~~

LI IjltII 1

I

  • f~~

~

~~~~~IA A Ii V I I I II 0

1 2

3 4

5 6

7 8

9 10 11 12 Bottom Core Height (Feet)

Top Cycle 26 Page 12 of 22 Rev. 2 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 Figure 5c RAOC Summary of W(Z) at 7000 MWD/IMTU 1.5C 1.40 1.30 1.20 1.10

'I I

ii~~~~~~~~~~I f

ll il 1

1 L-L

!H i

ll~~~~I Il 1

i~~~~~~~~~I j

I I

t~~~~~~~~~~~I AI I I A I'~~~~~~~~~A Iii A~i I AAI 1.00 0

Bottom 1

2 3

4 5

6 7

8 9

10 11 12 Core Height (Feet)

Top Cycle 26 Page 13 of 22 Rev. 2 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 Figure 5d RAOC Summary of W(Z) at 12000 MWD/MTU 1.50 Ij!

I I I Al 1.40 A

I I~~~~~~A I

I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

I.

III!

I~~A II Al&i I

1.

I 1.00 0

1 2

3 4

5 6

7 8

9 10 11 12 ottom Core Height (Feet)

Tc Bi op Cycle 26 Page 14 of 22 Rev. 2 l

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMNT MANUAL TRM 2.1 Revision 2 CORE OPERATING LIMlTS REPORT CYCLE 26 Figure 5e RAOC Summary of W(Z) at 16000 MWD/MTU i

1.5C 1.4C 1.30 1.20 1.10 1.00 4

1..-Ili f e 1 1i iii I t

i

  • 1~~~~~~~~~~~

ALIiiIL4IL I

I

~~~~~~~~~~~~~~~~~IIIIJI

~~~~~~~~~~~~~~~IL I A AI I

7 A

i

'I ii~~~~~~~~~~~~~~~~~~~~FF111 I III 0

1 2

3 4

5 6

7 8

9 10 11 12 Bottom Core Height (Feet)

Top Cycle 26 Page 15 of 22 Rev. 2 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 CORE OPERATING LIMITS REPORT CYCLE 26 Figure 6 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWDMU)TW F0Q(Z) (%)

4742 2.00 5004 2.44 5135 2.50 5398 2.74 5660 2.89 5922 3.01 6053 3.01 6185 3.03 6316 2.95 6578 2.57 6841 2.06 6972 2.00 Note: Linear interpolation is adequate for intermediate cycle bumup.

All cycle bumups outside the range of the table shall use a 2% decrease in Fq margin for compliance with the Surveillance Requirements.

Cycle 26 Page 16 of 22 Rev. 2 1

KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 CORE OPERATING LiMITS REPORT CYCLE 26 Figure 7 Axial Flux Difference 110 100 90 I-0 11.

0 4-C UP 80 70 60~

V__Ai__

50

(-30.0, 50.0)

(28.0, 50.0) 401...

0 1l

-40

-30

-20

-10 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 26 Page 17 of 22 Rev. 2 1

Table I NRC Approved Methodoloqies for COLR Parameters COLR Section Parameter NRC Approved Methodoloaq 2.1 Reactor Core Safety Limits WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology," July 1985.

Safety Evaluation by the Office of Nuclear Reactor Regulation on uQualifications 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.

2.2 Shutdown Margin 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.

2.3 Moderator Temperature Coefficient 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.

2.4 Shutdown Bank Insertion Limit 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.

Page 18 of 22

CQLR Section Parameter NRC Approved Methodolo2M 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 WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

2.6 Heat Flux Hot Channel Factor WCAP-10216-P-A, Revision 1A, 'Relaxation of Constant Axial Offset Control-F0 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.

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

Page 19 of 22

.-- COLR Section Parameter NRC Approved Methodology (Fa(Z))

WCAP-1 4449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection, Revisionl, and WCAP-14450-NP-A, Rev.1 (Non-Proprietary), October 1999.

WCAP-12610-P-A, OVantage+ Fuel Assembly Reference Core Reports April 1995.

Model WCAP-1 0054-P-A, 'Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,' August 1985.

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

2.7 Nuclear Enthalpy Rise WCAP-9272-P-A, "Westinghouse Reload Hot Channel Factor (FNAH)

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.

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 GWd/MTU,' Advanced Nuclear Fuels Corporation, dated December 1991.

Page 20 of 22



COLR Section Parameter NRC Approved Methodology EMF-92-116 (P)(A) Revision 0, 'Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.

2.8 Axial Flux Difference WCAP-10216-P-A, Revision 1A, 'Relaxation of Constant Axial Offset (AFD) Control-F0 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)

Instrumentation-Overtemperature AT WCAP-8745-P-A, ODesign 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 WPSRSEM-NP, Revision 3 (TAC NO MB0306) dated September 10, 2001.

CENP-397-P-A, 'lmproved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology,'

Rev. 1, May 2000.

2.10 Reactor Protection System (RPS)

Instrumentation-Overpower AT 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 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.

Page 21 of 22

COLR Section Parameter NRC Approved Methodolocw 2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate (DNB) Umits WCAP-1 1397-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 Ventudis, or 1780 MWt-NSSS Power with Ultrasonic Flow Measurements, and 54F Replacement Steam Generators), Revision 1, December 2002, Proprietary. Safety Evaluation dated July 8, 2003.

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.

2.12 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 Kewauneen Report, dated August 21, 1979, report date September 29, 1978.

Page 22 of 22

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