ML091190310
| ML091190310 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 04/22/2009 |
| From: | Wilson M Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 09-270 | |
| Download: ML091190310 (24) | |
Text
54*Dominiollll Dominion Energy Kewaunee, Inc.
N490 Highway 42, Kewaunee, W1 54216-9511 APR 2 2 2009 Attn: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Serial No.09-270 LIC/NW/RO Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE. INC.
KEWAUNEE POWER STATION CYCLE 29 REVISION 2 CORE OPERATING LIMITS REPORTS Pursuant to Kewaunee Power Station (KPS) Technical Specification (TS) 6.9.a.4.D, enclosed is a copy of the KPS Technical Requirements Manual (TRM) Section 2.1, Kewaunee Power Station Core Operating Limits Report (COLR), Cycle 29, Revision 2.
KPS TS 6.9.a.4.D states that the COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
If you have any questions or require additional information, Gadzala at (920) 388-8604.
please contact Mr. Jack Very truly yours, fMic ael J. Wilson Director Safety and Licensing Kewaunee Power Station Commitments made by this letter: None
Enclosure:
Serial No.09-270 COLR Cycle 29 Revision 2 Page 2 of 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. P. S. Tam Sr. Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
TRM 2.1 Kewaunee Power Station CORE OPERATING LIMITS REPORT (COLR)
CYCLE 29 REVISION 2 Approved k
'FSR-C Chairma mtgl#
Table of Contents section Title Faa.
1.0 CORE OPERATING LIMITS REPORT...........................................................................
1 2.0 OPERATING LIMITS....................................................................................................
2 2.1 Reactor Core Safety Limits 2
2.2 Shutdown Margin 2
2.3 Moderator Temperature Coefficient (MTC).......................................................
2 2.4 Shutdown Bank Insertion Limits........................................................................
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 Limits (FN)..................................
4 2.8 Axial Flux Difference (AFD) Target Band.........................................................
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 Fiaures figure Title page
- 1.
Reactor Core Safety Limits Curve (1772 MW t).............................................................
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 FON(z).................................................................................
13
- 7.
Axial Flux Difference Envelope......................................................................................
14 Ii
I List of Tables TableTle L
Pate
- 1.
NRC Approved Methodologies for COLR Parameters 15 iii
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 I
CORE OPERATING LIMITS REPORT CYCLE 29 1.0 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.dA1 3.10.d.2 3.10.b.I.A 3.10.b.5 3.10.b,6 3.1 0.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 (MTC)
Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor Limits (FaN(z))
Nuclear Enthalpy Rise Hot Channel Factor Limits (F5 HN)
Axial Flux Difference (AFD) Target Band Overtemperature AT Setpoint Overpower AT Setpolnt 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 FoN(Z)
Axial Flux Difference Envelope Cycle 29 Page 1 of 18 Rev. 2 1
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 2.0 Operating LimiMs 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 Reacor 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 :_ 60% RATED POWER, the moderator temperature coefficient shall be < 5.0 pcm/°F, 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/°F 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 29 Page 2 of 18 Rev. 21
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 2.6 Nuclear Heat Flux Hot Channel Factor (Fg_(Z))
2.6.1 FQN(Z) Limits for Fuel FoN(Z) x 1.03 x 1.05 < (2.50)/P x K(Z) for P > 0.5
[422 V+]
FQN(Z) x 1.03 x 1.05 < (5.00) x K(Z) for P s 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 F0N(Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:
FoN(Z) x 1.03 x 1.05 x W(Z) x Fp _(2.5)1 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 FQN(Z) penalty factor described In 2.6.3.
W(Z)
Is the function given in Figure 5 FoN(Z) is a measured F0 distribution obtained during the target flux determination 2.6.3 The penaltyfactorof 1.0 shall be used forTS 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 3.10.b.6.C.i.
The penalty factorfor all burnups outside the range of Figure 6 shall be 2%.
Cycle 29 Page 3 of 18 Rev, 2 1
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 2.7 Nuclear Enthalpy Rise Hot Channel Factor Limits (F_.IN) 2.7.1 F~AN Limits for Fuel FMN x 1.04*,91.70 [1 + 0.3(1-P)]
[422 V+]
where:
P is the fraction of full power at which the core is OPERATING 2.8 Axial Flux Difference (AFD) Target Band 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 7.
Cycle 29 Page 4 of 18 Rev. 2 1
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:
ATo
=
Indicated AT at RATED POWER, %
T
=
Average temperature, OF T'
573.0 OF P
=
Pressurizer Pressure, psig P
=
2235 psig K1 1.195 K2
=
0.015/°F K3
=
0.00072/psig 1
30 seconds 12 4 seconds f1(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 -15, +6 %, f1(AI) = 0 (b) For each percent that the magnitude of qt - qb exceeds +6% 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 exceeds -15%, the AT trip setpoint shall be automatically reduced by an equivalent of 3.78% of RATED POWER.
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
ATo
=
Indicated AT at RATED POWER, %
T
=
Average temperature, OF T'
573.0 OF K4 1.095 K5 0.0275/OF for increasing T; 0 for decreasing T K6
Ž 0.00103/OF for T > T' ; 0 for T < T' T3 2
10 seconds f2(AI)
=
0 for all Al Cycle 29 Page 5 of 18 Rev. 2 1
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNBj Limits 2.11.1 During steady state power operation, Tavg shall be < 576.70F 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 1 186,000 gpm.
2.12 RefuelingqBoron Concentration 2.12.1 When there is fuel in the reactor, a minimum boron concentration of 2500 ppm and a shutdown margin of,- 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 29 Page 6 of 18 Rev. 2 1
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 I
CORE OPERATING LIMITS REPORT CYCLE 29-Figure 1 Reactor Core Safety Umits Curve (1772 Mwt)
(Cores Containing 422V+ fuel) 665 0
0 I-585 565 0
20 40 60 80 100 Core Power (percent of 1772 MWt) 120 Cycle 29 Page 7 of 18 Rev. 2 1
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 Figure 2 Required Shutdown Reactivity vs. Boron Concentration 1700 27 0
200 400 600 800 100D 1200 1400 Full Power Equilibrium Boron Conceantration (pp-)
1600 1800 2000 Cycle 29 Page 8 of 18 Rev. 2 1
KEWAUNIEE POWER STATION fECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 I
CORE OPERATING LDIiTS REPORT CYCLE 29 Figure 3 Hot Channel Factor Normalized Operating Envelope (K(Z))
1.2 1.-I 1
0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0
(0,1.0)
(6~.1.)
~,
(12,1.0)
I
~ ~YY W...
I...
4...
I d
I h
~
h 0
1 2
3 4
5 6
7 8
9 10 11 12 Core Height (ft)
Cycle 29 Page 9 of 18 Rev. 2 I
KEWAUNEE POWER STATION TECHNICAL REQUREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 2 I
Figure 4 Control Bank Insertion Limits 240 220 200 180 160
- 13 140 U) 120 i100 C-60 60 40 20 0
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 a225 and <230 steps withdrawn.
Note: The Rod Bank Insertion Limits are based on a control bank tip-to-lip distance of 126 steps.
Cycle 29 Page 10 of 18 Rev. 2
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 2 I
Figure 5. - W(Z) Values CTop and Bottom 9% excluded)
- lMal lt ftl" IdMWAThITf mm
~......
150 2000 6000 I12000 1
17000 AO-"2.11% IA0=-4.08%
AO--L.43% IA0--2S9% I AO=-3.07%
[BOTTOM] 1 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 2
0.20 1.0000
.D 1.o000 1.0000 1.0000 3
0.40 1.o0000 10 1.0000 1.0000 1.0000 4
0,00 1.0000 1.0000 1.0000 1,0000 1.0000 5
0.80 1.0000 1.0000 1000 1.0000 1.0000 6
1.00 1.0000 1.00 1.0000 1.0000 1.0000 7
1.20 1.3735 1.2862 1.2244 1.1994 1.1670 8
1.40 1.3580 1.2728 1.2133 1.1902 1.1591 9
1.60 1.3398 1.2573 1.2003 1.1797 1.1 05 10 1.80 1.3194 1.2404 1.1860 1.1681 1.1414 11 2.00 1.2974 1.2248 1.1702 1.1556 1.1319 12 2.20 1.2742 1.2098 1.1545 1.1424 1.1222 13 2.40 12505 1.1938 1.1400 1.1291 1.1126 14 2.60 1.2267 1.1779 1.1264 1.1158 1.1032 15 2.80 11030 1.1617 1.1127 1.1020 1.0941 16 3.00 1.1816 1.1478 1.1019 1.0925 1.0858 17 3.20 1.1652 1.1394 1.0972 1.0892 1.0842 18 3.40 1.1561 1.1355 1.0970 1.0887 1.0908 19 3.60 1.1534 1.1313 1.0963 1.0880 1.0973 20 3.80 1.1506 1.1263 1.0955 1.0899 1.1036 21 4.00 1.1468 1.1226 1.0947 1.0928 1.1098 22 4.20 1.1428 1.1199 1.0936 1.0950 1.1154 23 4.40 1.1381 1.1166 1.0926 1.0970 1.1205 24 4.60 1.1330 1.1130 1.0921 1.0989 1.1249 25 4.80 1.1274 1.1087 1.0922 1.1018 1.1286 26 5.00 1.1212f 1.1050 1.0922 1.1046 1.1314 27 5.20 1.1144 1.1018 1.0920 1.1067 1,1336 28 5.40 1.1072 1.0981 1.0923 1.1090 1.1346 29 5.60 1.W95 1,0940 1.0963 1.1132 1.1348 30 5.80 1.0912 1.0878 1.1012 1.1209 1.1392 31 6.00 1.0892 1.0899 1.1058 1.1312 1.1508 32 6.20 1.0942 1.0990 1.1124 1.1419 1.1649 33 6.40 1.1007 1.1065 1.1217 1.1512 1.1769 34 6.60 1.1061 1,1134 1.1304 1.1596 1.1879 35 6.80 1.1107 1.1195 1.1383 1.1668 1.1975 36 7.00 1.1146 1.1246 1.1449 1.1729 1.2056 37 7.20 1.1174 1.1289 1.1511 1.1787 1.2122 38 7.40 1.1194 1.1325 1.1573 1.1840 1.2170 39 7.60 1.1219 1.1363 1.1626 1.1877 1.2200 40 7.80 1.1235 1.1391 1.1667 1.1899 1.2210 41 8.00 1.1241 1.1408 1.1695 1.1906 1.2200 42 8.20 1.1237 1.1413 1.1710 1.1898 1.2169 43 8.40 1.1224 1.1408 1.1713 1.1873 1.2118 44 8.60 1.1202 1.1392 1.1702 1.1830 1.2063 45 8.80 1.1172 1.1378 1.1661 1.1792 1.2071 46 9.00 1.1216 1.1448 1.1679 1.1800 1.2075 47 9.20 1.1359 1.1638 1.1778 1.1845 1.2076 48 9.40 1.1485 1.1802 1.1899 1.1921 1.2129 49 9.60 1.1677 1.1966 1.2015 1.2098 1.2341 50 9.80 1.1854 1.2105 1.2114 12315 12562 51 10.00 1.2019 1.2299 1.2271 1.2525 1.2755 52 10.20 1,2142 1.2519 1.2446 1.2707 1.2939 53 10.40 1.2210 1.2690 1.2576 1.2896 1,3110 Cycle 29 Page 11 of 18 Rev. 2 1
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 2 I
Figure 5 Cont'd (Top and Bottom 9% excluded)
H t
Ifn]
UT !
/MWM*/U7T I
1,i
,,, 2000 6000 1
12000 1
17000:
I AO-2.11% I A0-8.09% I AO--2.43% I AO-2.2S9% 1 A0~-3.010/ I 54 10.60 1.2336 1.2877 1.2715 1.3049 1.3283 55 10.80 1.2480 1.3015 1.2779 1.3142 1.3430 7
56 11.00 1.0000 1.0000 1.0000 1.0000
,.'oO0 57 112.0 1.0000 0000
.0000 1.0000 1,0000 58 11.40
.oooo 1.0000 1.0000 1.0000 1.0000 59 11.60 1.0000 1.0000w L00 1.0000 1.0000 60 11.80 1.0000 1.0000 1
.0000O 1.0000 L
I TOP 61 12.00 1 ].0000 1.0000 1
1.0000 1.0000 1.0000 Note:
These W(Zys are based upon the previous cycle's RAOC Band of 1.0%, -90/0, +8%, 0.5%.
-27%, 28%. The current RAOC Band of 1.0%, -9%, +6%, 0.5%, -27%, 28% is less inclusive, thus, these W(Z)'s are conservative.
Cycle 29 Page 12 of 18 Rev. 2 1
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 2 I
Figure 6 Penalty Factor, F. (%), for FQN(Z)
Cycle Burnup Penalty Factor (MWD/MTU)
Fp (%)
150 2.00 18,185 2.00 Note: Linear interpolation is adequate for Intermediate cycle bumups.
All cycle bumups outside the range of the table shall use a penalty factor, Fp,. of 2.0%.
Refer to TS 3.10.b.6.C.
Cycle 29 Page 13 of 18 Rev. 2 1
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 2 I
Figure 7 Axial Flux Difference Envelope 0
0 (L
I-a,I 110 100 90 80 70 60
(-9.0, 100.0)
(6.0, 100.0)
(-27.0, 50.0)
(28.0,50.0) i I
I I
I I
I
' I I
"I l I I 50 40
-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 29 Page 14 of 18 Rev. 2
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 I
CORE OPERATING LIMITS REPORT CYCLE 29 Table I NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodoloay 2.1 Reactor Core Safety Limits 2.2 2.3 2.4 Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Umits WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985.
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 WCAP-9272-P-A, VWestinghouse Reload Safety Evaluation Methodology," July 1985.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Kewaunee Nuclear Power Plant-Review for Kewaunee Reload Safety Evaluation Methods Topical Report WPSRSEM-NP, Revision 3 (TAC NO M10306) dated September 10, 2001.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
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 Cycle 29 Page 15 of 18 Rev. 2 1
KEWAUNEE POWER STATION TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 2 CORE OPERATING LIMITS REPORT CYCLE 29 Table 1 (cont)
NRC Approved Methodoloales for COLR Parameters COLR Section Parameter NRC Aproved Methodologv 2.6 Nuclear Heat Flux Hot Channel WCAP-1 0216-P-A, Revision 1A, "Relaxation Limits (F0 N(Z))
of Constant Axial Offset Control-F0 Surveillance Technical Specification,"
February 1994.
WCAP-12945-P-A (Proprietary),
'Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis," Volume 1, Rev.2, and Volumes 1I-V, Rev.1, and WCAP-14747 (Non-Proprietary), March 1998.
(Fa(Z)) WCAP-1 4449-P-A, "Application Of Best Estimate Large Break LOCA Methodology To Westinghouse PWRs With Upper Plenum Injection," Revisioni, and WCAP-14450-NP-A, Rev.1 (Non-Proprietary), October 1999.
WCAP-1 2610-P-A, "Vantage+ Fuel Assembly Reference Core Report,* April 1995.
Model WCAP-10054-P-A/WCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code,"
August 1985.
NOTRUMP WCAP-10054-P-ANICAP-10081-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.
Cycle 29 Page 16 of 18 Rev. 2 1
KEWAUNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 2 I
CORE OPERATING LIM[ITS REPORT CYCLE 29 Table I (cont)
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC ADproved Methodology 2.7 Nuclear Enthalpy Rise Hot Channel Factor Umits 2.8 Axial Flux Difference Target Band WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
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 (AFD) Control-F0 Surveillance Technical Specification,"
February 1994.
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-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.
2.9 Reactor Protection System (RPS)
Instrumentation-Overtemperature AT Cycle 29 Page 17 of 18 Rev. 2 1
KEWAUTNEE POWER STATION TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 29 TRM 2.1 Revision 2 Table I (cont)
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodolo,,y 2.10 Reactor Protection System (RPS)
Instrumentation-Overpower AT 2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits 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.
WCAP-1 1 397-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.
2.12 Refueling Boron Concentration Cycle 29 Page 18 of 18 Rev. 2