ML073450557

Cycle 28, Rev. 1, Core Operating Limits Report

ML073450557
Person / Time
Site:	Kewaunee
Issue date:	12/10/2007
From:	Gerald Bichof Dominion Energy Kewaunee
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
07-0759
Download: ML073450557 (26)

Text

Dominion Energy Kewaunee, Inc.

';! 1011 Domin;on Boulevard, Glen Allen, VA L\\II()II December 10, 2007 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

07-0759 KPS/UC/CS: RO Docket No.

50-305 License No.

DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION CYCLE 28, REVISION 1, CORE OPERATING LIMITS REPORT Pursuant to Kewaunee Power Station (KPS) Technical Specification 6.9.a.4.D, enclosed is Revision 1 of the Cycle 28, Core Operating Limits Report (COLR).

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

Very truly yours,

fd'l~-I

Gerald T. Bischof U Vice President - Nuclear Engineering

Attachment:

1. Kewaunee Power Station, Cycle 28, Revision 1, Core Operating Limits Report.

Commitments made by this letter: NONE cc:

Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 Mr. P. D. Milano Project Manager U.S. Nuclear Regulatory Commission MaiI Stop 0-8-H-4a Washington, DC 20555-0001 NRC Senior Resident Inspector Kewaunee Power Station

Serial No. 07-0759 ATTACHMENT 1 KEWAUNEE POWER STATION CYCLE 28 REVISION 1 CORE OPERATING LIMITS REPORT DOMINION ENERGY KEWAUNEE, INC.

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

CYCLE 28 REVISION 1 Approved

~~II~A/qV~

POR hairman Date 07-/07 Mtg.#

Table of Contents I

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 (80M) 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 (FoN(Z))

3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FIlHN) 4 2.8 Axial Flux Difference (AFD) 4 2.9 Overtemperature b.T Setpoint 5

2.10 Overpower.D.T Setpoint 5

2.11 ReS Pressure, Temperature, and Flow Departure From 6

Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration 6

List of Figures I

Figure Title Page 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 6.

Penalty Factor, Fp (%), for FoEo(Z) 13 7.

Axial Flux Difference 14 ii

Table 1.

iii

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 1.0 CORE OPERATING LIMITS REPORT TRM 2.1 Revision 1 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.1 3.10.d.2 3.10.b.1.A 3.10.b.5 3.10.b.6 3.10.b.6.C.i 3.10.b.7 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 (Fo(Z))

Nuclear Enthalpy Rise Hot Channel Factor (FAH N)

Axial Flux Difference (AFD)

Overtemperature LlT Setpoint Overpower LlT 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 Insertion Limits W(Z) Values (Top and Bottom 9% excluded)

Penalty Factor, Fp, for FoEo(Z)

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

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 TRM 2.1 Revision 1 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 (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 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 :-s; 60% RATED POWER, the moderator temperature coefficient shall be:-s; 5.0 pcm!OF, 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 (~ 225 steps and ~ 230 steps) when the reactor is critical or approaching criticality.

2.5 Control Bank Insertion 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 of20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 2.6 Nuclear Heat Flux Hot Channel Factor (FgN(Z))

2.6.1 FaN(Z) Limits for Fuel FaN(Z) x 1.03 x 1.05 ~ (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 where:

TRM 2.1 Revision 1

[422 V+]

[422 V+]

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

FaEa(Z) x 1.03 x 1.05 x W(Z) x Fp ~ (2.5)/ 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 FaEa(Z) penalty factor described in 2.6.3.

W(Z)

Is the function given in Figure 5 FoEo(Z) is a measured Fa distribution obtained during the target flux determination 2.6.3 The penalty factor of 1.0 shall be used forTS 3.10.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 burnups outside the range of Figure 6 shall be 2%.

Cycle 28 Page 3 of 20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F~~

2.7.1 FdH N Limits for Fuel FdH N x 1.04 ~ 1.70 [1 + 0.3(1-P)]

where:

TRM2.1 Revision 1

[422 V+]

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. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 TRM 2.1 Revision 1

~To

=

T

=

l'

~

P

=

pI

=

K1

=

K2

=

K3

=

1:1

=

1:2

=

f(~I)

=

2.9 Overtemperature ~T Setpoint Overtemperature ~T setpoint parameter values:

Indicated ~T at RATED POWER, %

Average temperature, of 573.0 of Pressurizer Pressure, psig 2235 psig 1.195 O.015rF O.00072/psig 30 seconds 4 seconds An even function of the indicated difference between top and bottom detectors ofthe 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 -15, +10 %, f(AI) =0 (b)

For each percent that the magnitude of qt - qb exceeds +10 % the

~T 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

~T trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.

2.10 Overpower ~T Setpoint Overpower ~T setpoint parameter values:

~To

=

Indicated ~T at RATED POWER, %

T

=

Average temperature, of l'

~

573.0 of K4

~

1.095 Ks

~

0.0275/oF for increasing T; 0 for decreasing T K6

~

O.00103/oF for T > l' ; 0 for T < T'

<3

=

10 seconds f(~I)

=

0 for all AI Cycle 28 Page 5of 20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 TRM 2.1 Revision 1 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.7°F for control board indication or < 576.5°F 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

~ 189,720 gpm.

2.12 Refueling Boron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of ~ 5% Ii klk 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. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM2.1 Revision 1 CORE OPERATING LIMITS REPORT CYCLE 28 Figure 1 Reactor Core Safety Limits Curve (1772 Mwt)

(Cores Containing 422V+ fuel) 665 -r------r-----,----------.,..----.....,....----.

120 100 80 I

Unac~eptable Operation I

~ -

-I -

I 60 40 Accepta~le Operati~m 20 I

L J

I I

I, I

I I

I, I

I 565 +------i-----+-----__-

+'

-+

~

o

....o.-

(,)m585 0:::

.-c:

605 C1:l ooo LLL. 645 e

2.-E Q)

Q.

E Q) 625 f-Q)

C)

E Q)><<

Core Power (percent of 1772 MWt)

Cycle 28 Page 7 of20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Figure 2 Required Shutdown Reactivity V5. Boron Concentration TRM 2.1 Revision 1 I

I I

T

_.~'----

I I

I I

I

~---L -r=~+.. +t-+-I--

~=+=+=l= 1*-=

-I H JJ-r~

~

'----.-i-I

' I I

I

--t- -~t-

_Lt-1 1

I I

I 1=ll-t.=

-- -t---

~_.

.-1--

I i +

-+l~L+/-~

~'-l-I-i -',

---.-._~'..~-_.~-+

I I

I 1-.--.1 -+.-..

---

~--,~-+~I-I--

I i

iii i

1700 1600 1542 1500 1400 1300 1200 1100 b

'S;

~

1000 Ol..

II::

c 900

~~

o E

't:l 0

"'Co

I_

.e 800 U)

't:l CII

I 700 C'

CII II::

600 500 400 300 200 100 o

a Cycle 28 200 400 600 800 1000 1200 1400 Full Power Equilibrium Boron Concentration (ppm)

Page 8 of 20 1600 1800 2000 Rev. 1

KEWAUNEE POWER STAnON TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 TRM 2.1 Revision 1 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(z>>

1.2 1.1 0.9 0.8 0.7 N

0.6

ld 0.5 0.4 0.3 0.2 0.1 0

T T

I (0,1.0)

(6,1.0)

I (12,1.0)

Cycle 28 o

2 3

4 5

6 7

8 9

10 11 12 Core height (ft)

Page 9 of 20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Figure 4 Control Bank Insertion Limits TRM2.1 Revision 1

\\

I 1

1 I

1/ (12.7%,225)

/

(64.6%, 225)

~ANK~

7 T

/

I 1/

I V

1 (0.0%, 194)

/

(100.0%, 185)

/

V V

/

I I

I/BANKC

/

I I

I 1/

i

/

I i

i/i I

I l7 I /

1/

i7BANK D

/

I

/

1

[7:

I I

VI

\\

(0.0%,68)

I 1

/

I I

Ir T

/

I 1 I'

v I

. (23.8%, 0)/

I I

1 240 220 200 180 C

~

160 cu...

"C=

§ 140 III Co S

120 (f)

..ll::

Ccum 100 0...-

c 0()

80 60 40 20 0 o 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 2: 225 and :'S 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 of20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Figure 5

• W(Z) Values (Top and Bottom 9% excluded)

TRM2.1 Revision 1 Cycle 28 Heil!ht BU IMWd/MTUl 1ft) 150 6000 12000 16000 AO = 0.90 AO=-3.20 AO=-3.36 AO - -1.32

[BOTTOMl 1

0.00 1.0000 1.0000 1.0000 1.0000 2

0.20 1.0000 1.0000 1.0000 1.0000 3

0.40 1.0000 1.0000 1.0000 1.0000 4

0.60 1.0000 1.0000 1.0000 1.0000 5

0.80 1.0000 1.0000 1.0000 1.0000 6

1.00 1.0000 1.0000 1.0000 1.0000 7

1.20 1.3228 1.2245 1.2002 1.2060 8

1.40 1.3076 1.2135 1.l899 1.l971 9

1.60 1.2899 1.2007 1.l782 1.l870 10 1.80 1.2699 1.l864 1.l652 1.l757 11 2.00 1.2507 1.1709 1.l512 1.l635 12 2.20 1.2316 1.l547 1.1367 1.1508 13 2.40 1.2116 1.1382 1.l217 1.1377 14 2.60 1.l916 1.l218 1.1071 1.1247 15 2.80 1.l724 1.1073 1.0985 1.1127 16 3.00 1.l553 1.0997 1.0953 1.l033 17 3.20 1.1434 1.0972 1.0935 1.1013 18 3.40 1.l372 1.0951 1.0912 1.l033 19 3.60 1.l341 1.0929 1.0888 1.1056 20 3.80 1.1313 1.0934 1.0858 1.1078 21 4.00 1.l281 1.0945 1.0858 l.I098 22 4.20 1.1246 1.0950 1.0891 1.l114 23 4.40 1.l207 1.0954 1.0933 1.l126 24 4.60 1.l164 1.0955 1.0970 1.1132 25 4.80 1.1115 1.0954 1.1001 1.l140 26 5.00 1.1073 1.0946 1.l029 1.l151 27 5.20 1.1034 1.0945 1.1050 1.1158 28 5.40 1.0989 1.0960 1.l066 1.l159 29 5.60 1.0940 1.0979 1.l077 1.l165 30 5.80 1.0895 l.IOl8 1.l084 1.l220 31 6.00 1.0899 1.l057 1.1130 1.l314 32 6.20 1.0954 1.l104 l.II98 l.I421 33 6.40 1.l021 1.l174 1.l267 1.l529 34 6.60 l.I079 1.1244 1.1376 1.l626 35 6.80 1.l127 1.1307 1.l480 1.l711 36 7.00 I.l J67 1.l354 l.I571 l.I783 37 7.20 1.l197 1.1411 1.l663 1.1842 38 7.40 1.l222 1.l501 1.1753 1.1886 39 7.60 1.l246 1.l583 1.l831 1.l915 40 7.80 1.1260 1.l655 1.1896 1.1928 41 8.00 1.l264 1.l718 1.l949 1.l924 42 8.20 1.l256 1.l769 1.l988 1.1903 43 8.40 1.l238 1.l809 1.2013 1.l864 44 8.60 1.l209 1.1838 1.2023 1.1803 45 8.80 1.1180 1.1842 1.2017 1.1757 46 9.00 1.1214 1.1880 1.l993 1.1755 47 9.20 1.1366 1.1975 1.l996 1.l773 48 9.40 1.l498 1.2089 1.2069 1.1769 49 9.60 1.l624 1.2237 1.2161 1.1765 50 9.80 1.l768 1.2413 1.2232 1.l782 Page 11 of 20 Rev. 1

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

TRM 2.1 Revision 1 Cycle 28 Heil!ht BU IMWdlMTUl 150 6000 12000 16000 Iftl AO=0.90 AO =-3.20 AO = -3.36 AO=-1.32 51 10.00 1.1913 1.2555 1.2311 1.1834 52 10.20 1.2053 1.2661 1.2410 1.1893 53 10.40 1.2214 1.2764 1.2504 1.1996 54 10.60 1.2398 1.2816 1.2632 1.2128 55 10.80 1.2526 1.2878 1.2732 1.2258 56 11.00 1.0000 1.0000 1.0000 1.0000 57 11.20 1.0000 1.0000 1.0000 1.0000 58 11.40 1.0000 1.0000 1.0000 1.oo 59 11.60 1.0000 1.0000 1.0000 1.0000 60 11.80 1.0000 1.0000 1.0000 1.0000 nOPl 61 12.00 1.0000 1.0000 1.0000 1.0000 Page 12 of 20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Figure 6 Penalty Factor, Fp (%), for FQEQ(Z)

Cycle Burnup Penalty (MWD/MTU)

Factor Fp (%)

150 2.00 20,743 2.00 TRM 2.1 Revision 1 Note: Linear interpolation is adequate for intermediate cycle bumups.

All cycle bumups outside the range of the table shall use a penalty factor, Fp, of2.0%.

Refer to TS 3.10.b.6.C.

Cycle 28 Page 13 of 20 Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 1 CORE OPERATING LIMITS REPORT CYCLE 28 Figure 7 Axial Flux Difference 110 -r---------,----r----;------,.----r---"""i----,

(-9.0, 100.0)

(8.0,100.0)

_.-- ------;---------1----+---_.

50 +-~---l---~-_+_---_+_-~--+---+~---+-~ l____

_____l

(-27.0,50.0)

(28.0,50.0)

'I 60 80 100 40 30 20 10 o

-10

-20

-30 40 -f--T...,...,I""'"T""+-r-..,...,-,-t-r-"'I"""T...,....,-r-T"-r-..,.....r..,....,r""'T"".,...+""I'"'"'l--r-,....,....,....,...,...,r-+T-r-"'T""'l....

-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. 1

KEWAUNEE POWER STAnON TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Table 1 TRM2.l Revision 1 NRC Approved Methodologies for COLR Parameters COLR Section 2.1 2.2 Parameter Reactor Core Safety Limits Shutdown Margin NRC Approved Methodology 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 2.3 2.4 Cycle 28 Moderator Temperature Coefficient Shutdown Bank Insertion Limit Page 15 of 20 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.

Rev. 1

KEWAUNEE POWER STAnON TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Table 1 (cont)

TRM 2.1 Revision 1 NRC Approved Methodologies 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 2.6 Cycle 28 Control Bank Insertion Limits Heat Flux Hot Channel Factor Page 16 of 20 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-10216-P-A, Revision 1A, "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.

WCAP-12945-P-A (Proprietary),

"Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume I, Rev.2, and Volumes 11-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.

Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Table 1 (cont)

TRM2.1 Revision 1 NRC Approved Methodologies for COLR Parameters COLR Section Parameter (Fo(Z>>

Model NRC Approved Methodology ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR 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-AlWCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,"

August 1985.

2.7 Cycle 28 NOTRUMP Nuclear Enthalpy Rise Hot Channel Factor (FN....H)

Page 17 of 20 WCAP-1 0054-P-AlWCAP-1 0081-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 COSI 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, Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 TRM 2.1 Revision 1 Revision 3 (TAC NO MB0306) dated September 10, 2001.

Table 1 (cont)

NRC Approved Methodologies for COLR Parameters COLR Section 2.8 Parameter Axial Flux Difference NRC Approved 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' PWR Design Methodology for Rod Burnups for 62 GWd/MTU," Advanced Nuclear Fuels Corporation, dated December 1991.

EMF-92-116 (P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.

WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset (AFD) 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.

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 Cycle 28 Reactor Protection System (RPS)

Instrumentation-Overtemperature ~T Page 18 of 20 WeAP-8?45-P-A, "Design Bases For The Thermal Overpower ~T and Thermal Overtemperature ~T Trip Functions,"

September 1986.

Rev. 1

KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Table 1 (cont)

TRM 2.1 Revision 1 NRC Approved Methodologies 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.

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

Rev. 1, May 2000.

2.10 Cycle 28 Reactor Protection System (RPS)

Instrumentation-Overpower.1T Page 19 of 20 WCAP-8745-P-A, "Design Bases For The Thermal Overpower.1T and Thermal Overtemperature.1T 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.

Rev. 1

KEWAUNEE POWER STAnON TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 28 Table 1 (cont)

TRM2.1 Revision I NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 2.11 2.12 Cycle 28 RCS Pressure, Temperature, and Flow Departure From Nucleate (DNB) Limits Boron Concentration Page 20 of 20 WCAP-11397-P-A, "Revised Thermal Design Procedure, "April 1989, for those events 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.

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.

Rev. 1