ML043100533
| ML043100533 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 10/22/2004 |
| From: | Coutu T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-04-125 | |
| Download: ML043100533 (30) | |
Text
Committed to Nusear Excellence Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC October 22, 2004 NRC-04-125 Technical Specification 6.9.a.4 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 27. Revision 0 In accordance with the requirements of Technical Specification 6.9.a.4, enclosed is Revision 0 of the Cycle 27, 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 Nuclear Power Plant Nuclear Management Company, LLC Enclosure cc:
Administrator, Region Ill, USNRC Senior Resident Inspector, Kewaunee, USNRC Project Manager, Kewaunee, USNRC Public Service Commission of Wisconsin N490 Highway 42. Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560 I16
TRM 2.1 Kewaunee Nuclear Power Plant CORE OPERATING LIMITS REPORT (COLR)
CYCLE 27 REVISION 0 ALL Approved 1J12/4 Date 0/-0t i Mtg.#
_/tfoRC Chairman
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 (F0N(Z))...........................
3.............3 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F &HN).........................................
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
i List of Figures 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.
Composite RAOC Summary.........................................
11 5a.
RAOC Summary of W(Z) at 150 MWD/MTU..........................................
12 5b.
RAOC Summary of W(Z) at 4000 MWD/MTU..........................................
13 5c.
RAOC Summary of W(Z) at 8000 MWD/MTU.........................................
14 5d.
RAOC Summary of W(Z) at 10000 MWD/MTU..........................................
15 5e.
RAOC Summary of W(Z) at 12000 MWD/MTU.........................................
16 5f.
RAOC Summary of W(Z) at 16000 MWD/MTU............................................................... 17
- 6.
Penalty Factor, Fp(%), for F0EQ(Z).........................................
18
- 7.
Axial Flux Difference..........................................
19 ii
.List of Tables Table Title Page
, 1.
NRC Approved Methodologies for COLR Parameters 20 iii
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS 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. I 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 5 Figure 5a Figure 5b Figure. 5c Figure 5d Figure 5e Figure 5f Figure 6 Figure 7 KNPP TS 2.1 3.10.a 3.1.f.3 3.1 0.d.1 3.1 0.d.2 3.1 0.b.1.A 3.1 0.b.5 3.1 0.b.6.C.i 3.1 0.b.1.B 3.1 0.b.8 2.3.a.3.A 2.3.a.3.B 3.1 0.k 3.10.1 3.1 O.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 (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 (1772 MWt)
Required Shutdown Margin K(Z) Normalized Operating Envelope Control Bank Insertion Limits Composite RAOC Summary RAOC Summary of W(Z) at 150 MWD/MTU RAOC Summary of W(Z) at 4000 MWD/MTU RAOC Summary of W(Z) at 8000 MWD/MTU RAOC Summary of W(Z) at 10000 MWD/MTU RAOC Summary of W(Z) at 12000 MWD/MTU RAOC Summary of W(Z, at 16000 MWD/MTU Penalty Factor, Fp. for Fa 0(Z)
Axial Flux Difference Cycle 27 Page 1 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 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 < 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 (2 226 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 27 Page 2 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 TRM 2.1 Revision 5 2.6 Nuclear Heat Flux Hot Channel Factor (FON(Z))
2.6.1 FON(Z) Limits for Fuel FoN(Z) x 1.03 x 1.05 * (2.35)/P x K(Z) for P > 0.5 FoN(Z) x 1.03 x 1.05 * (4.70) x K(Z) for P *0.5 FoN(Z) x 1.03 x 1.05 * (2.28)/P x K(Z) for P > 0.5 FON(Z) x 1.03 x 1.05 *(4.56) x K(Z) for P
- 0.5 FoN(Z) x 1.03 x 1.05 * (2.50)/P x K(Z) for P > 0.5 FoN(Z) x 1.03 x 1.05 * (5.00) x K(Z) for P
- 0.5
[FRA-ANP Hvy]
[FRA-ANP Hvy]
[FRA-ANP Std]
[FRA-ANP Std]
[422 V+]
[422 Vi-]
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 F0 of interest 2.6.2 The measured FoE (Z) hot channel factors under equilibrium conditions shall satisfy the following relationship for the central axial 80% of the core for fuel:
FoEO(Z) x 1.03 x 1.05 x W(Z)x Fp * (2.35)/P x K(Z)
[FRA-ANP Hvy]
F0Eo(Z) x 1.03 x 1.05 x W(Z)x F. * (2.28)/P x K(Z)
[FRA-ANP Std]
FoEo(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 Fo of interest Fp is the FoEO(Z) penalty factor described in 2.6.3.
W(Z) is the function given in Figure 5 FoE0(Z) is a measured Fo distribution obtained during the target flux determination I
Cycle 27 Page 3 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 2.6.3 The penalty factor of 1.0 shall be used forTS 3.1 0.b.6.A and TS 3.1 0.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%.
2.7 Nuclear Enthalpy Rise Hot Channel Factor (FAHn 2.7.1 FAHN Limits for Fuel FAHN x 1.04 S 1.38 [1 + 0.3(1 -P)]
(FRA-ANP Hvy]
FmN x 1.04 < 1.70 [1 + 0.3(1-P)j (422 V+]
F&H N x 1.04 <1.38 [1 + 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 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 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,
=
1.195 K2
=
0.015/fF K3
=
0.00072/psig Tj
=
30 seconds T2
=
4 seconds f(Al)
=
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, +10 %, f(Al) = 0 (b)
For each percent that the magnitude of qt - qb 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 -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, "F To s
573.0 °F K4 s
1.095 Ks 2
0.0275/0F for increasing T; 0 for decreasing T K6 2
0.001 03/°F for T > T'; 0 for T < T' T3
=
10 seconds f(AI)
=
0 for all Al Cycle 27 c Page 5 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.11.1 During steady state power operation, Tavg shall be < 576.70F 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 2 186,000 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 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 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 1 Reactor Core Safety ULmits Curve (1772 Mwt)
(Cores Containing 422V+ fuel) 665
£ 645 a) a-0-0 co E0 625 a-C 60
- 60 0
0 0
a) 585 0
20 40 60 80 100 120 Core Power (percent of 1772 MWt)
Cycle 27 Page 7 of 25 R
Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 2 Required Shutdown Reactivity vs. Boron Concentration 1700 1600 1542 1500 1400 1300 1200 aI XI ff I
VIA I
0 cc
_Up 0a02 s-g 19 1000 900 700 600 500 400 300 200 100 0
4 4
4 4
4 4
+
4 0
200 400 600 800 1000 1200 1400 Full Power Equilibrium Boron Concentration (ppm) 1600 1800 2000 Cycle 27 Page 8 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 --
TRM 2.1 Revision 5 Figure 3 Hot Channel Factor Normalized Operating Envelope 1.2 1.1 1
0.9 0.8 0.7 N
84 0 6 0.5 0.4 0.3 0.2 0.1 0
I-iII I
I I I I-I (0,1.0) l (6,1.0) 1 I - I I -
I I__ ___I (12,1.0) 0 1
2 3
4 5
6 7
Core height (ft) 8 9
10 11 12 Cycle 27 Page 9 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 TRM 2.1 Revision 5 Figure 4 Control Bank Insertion Limits 240 220 200 180 c
160 V
140 U) 0.w V) 120 m
100 a-80 00 60 40 20 0
(13.1%,226)
-(65.0%.
226))
BANK B
/
/
_ I _
/-
I_
(0.0%,194) 0.%.85 l(1 00.0%, 185) 7__
BANK C i/
X BANK D (0.0%,68)
(23.8%, 0)
I
, I /
I I
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
> 226 and < 231 steps withdrawn.
Note: The Rod Bank Insertion Limits are based on a control bank tip-to-tip distance of 126 steps.
I Cycle 27 Page 10 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5 Composite RAOC Summary I
2(3 0.0 02 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 4.2 4.4 4.6 4.8 5.0 5.2 5.4 5.6 5.8 6.0 6.2 6.4 6.6 6.8 7.0 7.2 7.4 7.6 7.8 8.0 8.2 8.4 8.6 8.8 9.0 9.2 9.4 9.6 9.8 10.0 10.2 10.4 10.6 10.8 11.0 11.2 11.4 11.6 11.8 12.0 150 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2898 1.2767 1.2613 1.2441 1.2255 1.2060 1.1859 1.1660 1.1477 1.1347 1.1277 1.1236 1.1188 1.1131 1.1069 1.1005 1.0955 1.0935 1.0910 1.0869 1.0823 1.0781 1.0742 1.0688 1.0674 1.0727 1.0802 1.0870 1.0930 1.0981 1.1024 1.1062 1.1101 1.1134 1.1156 1.1168 1.1171 1.1168 1.1133 1.1146 1.1275 1.1438 1.1607 1.1799 1.2020 1.2219 1.2312 1.2328 1.2435 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 12165 1.2053 1.1923 1.1778 1.1622 1.1457 1.1291 1.1127 1.0951 1.0859 1.0849 1.0830 1.0808 1.0783 1.0750 1.0732 1.0740 1.0752 1.0757 1.0749 1.0741 1.0748 1.0762 1.0793 1.0834 1.0873 1.0818 1.0988 1.1056 1.1111 1.1160 1.1215 1.1262 1.1298 1.1323 1.1337 1.1341 1.1339 1.1291 1.1302 1.1449 1.1592 1.1741 1.1893 1.2037 1.2171 1.2292 1.2396 12493 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 8000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1548 1.1451 1.1339 1.1217 1.1085 1.0972 1.0895 1.0815 1.0730 1.0674 1.0652 1.0639 1.0623 1.0603 1.0580 1.0583 1.0634 1.0685 1.0726 1.0757 1.0778 1.0795 1.0807 1.0838 1.0860 1.0900 1.1025 1.1141 1.1245 1.1341 1.1431 1.1527 1.1612 1.1684 1.1743 1.1790 1.1825 1.1847 1.1837 1.1831 1.1875 1.1952 1.2027 1.2122 1.2235 1.2337 1.2425 1.2568 1.2683 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1514 1.1418 1.1310 1.1190 1.1062 1.0931 1.0797 1.0662 1.0588 1.0562 1.0548 1.0542 1.0570 1.0612 1.0652 1.0691 1.0735 1.0779 1.0816 1.0840 1.0853 1.8610 1.0871 1.0912 1.0963 1.1004 1.1069 1.1193 1.1323 1.1439 1:1 546 1.1641 1.1723 1.1790 1.1843 1.1880 1.1902 1.1911 1.1871 1.1873 1.1980 1.2083 1.2222 1.2371 1.2477 1.2525 1.2561 1.2594 1.2654 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 12000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1411 1.1317 1.1212 1.1097 1.0975 1.0849 1.0724 1.0603 1.0473 1.0421 1.0419 1.0457 1.0493 1.0526 1.0557 1.0587 1.0623 1.0672 1.0719 1.0756 1.0782 1.0804 1.0825 1.0830 1.0868 1.0963 1.1069 1.1167 1.1254 1.1336 1.1417 1.1496 1.1563 1.1616 1.1657 1.1684 1.1700 1.1697 1.1700 1.1726 1.1821 1.1950 1.2085 1.2216 1.2330 1.2437 1.2585 1.2742 1.2894 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 16000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1855 1.1765 1.1665 1.1555 1.1436 1.1312 1.1198 1.1119 1.1041 1.0967 1.0925 1.0922 1.0927 1.0928 1.0924 1.0917 1.0915 1.0929 1.0965 1.0996 1.1011 1.1020 1.1 022 1.1047 1.1111 1.1184 1.1244 1.2950 1.1331 1.1366 1.1405 1.1429 1.1440 1.1437 1.1420 1.1391 1.1349 1.1301 1.1321 1.1380 1.1412 1.1443 1.1468 1.1511 1.1653 1.1889 1.2093 1.2255 1.2358 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Rev. 0 Cycle 27 Page 11 of 25
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5a RAOC Summary of W(Z) at 150 MWD/MTU 1.50 1.40 1.30 1.20 1.10 1.00 I I A A Al I
A A A iA 0
1 2
3 4
5 6
7 8
9 10 11 12 Bottom Core Height (Feet)
Page 12 of 25 Top Cycle 27 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5b RAOC Summary of W(Z) at 4000 MWDIMTU 1.50 1.40 1.30 1.20 I
I I I
I I
A
,A AA IL-$
A A A-EHE
.11d.
- i. I I I I 1.10 1.00 0
1 2
3 4
5 6
7 8
9 10 11 12 Boron Core Height (Feet)
Top Cycle 27 Page 13 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5c RAOC Summary of W(Z) at 8000 MWDIMTU 1.50 1.40 1.30 1.20 1.10 I
A r I I JAI IA-I I I JA V-1 I I A
I I
I I
I I I I II L H itt 1.00 I L -, L j I I I I I I I I I I I I I I I I I I I I I I I I I&,
0 Bottom 1
2 3
4 5
6 7
8 9
10 11 Core Height (Feet)
Page 14 of 25 12 Top Cycle 27 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5d RAOC Summary of W(Z) at 10000 MWD/MTU 1.50 1.40 1.30 1.20 1.10 I I
' Im I I I I I 1 1 1 1 1 1 1 1 1 1 1 1 1 g 1 1 1 I I I
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1 2
3 4
5 6
7 8
9 otom.
Core Height (Feet) 10 11 12 Top Bc Cycle 27 Page 15 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 5e RAOC Summary of W(Z) at 16000 MWDtMTU 1.50
. ~ ~
I M1 1 1-1: 1 11 1 1 1 1 1 1 ! 1 I I 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 m........lllllllllll~llllllll
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1 2
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Top Cycle 27 Page 16 of 25 Rev. O
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT CYCLE 27 TRM 2.1 Revision 5 Figure 5f RAOC Summary of W(Z) at 16000 MWDIMTU 1.50 1.40 I I I
I I
I I I I I I I I I I I I I I I I
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Top Cycle 27 Page 17 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 6 Penalty Factor, Fp (%), for FoEO(Z)
Cycle Burnup Penalty Factor (MWDIMTU)
Fp (%)
150 2.00 19700 2.00 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 O.b.6.C.
I I
Cycle 27 Page 18 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Figure 7 Axial Flux Difference 110 100 90 a.
I-cc 0
10 a.
CI..
0 U
80 70 (l9.0, 100.0) 10.0)
(-27.0, 50.0)
(28.0, 50.0) 60 50 40
-40
-30
-20
-10 0
10 20 30 40 Axial Flux Difference (% delta-l)
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 TS 3.1 O.b.7.
Cycle 27 Page 19 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 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 "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.
2.2 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.
Cycle 27 Page 20 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Table I (cont)
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodoloqv 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-1 0216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-F 0 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 27 Page 21 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 (cont)
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology (Fo(Z))
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," Revisioni, and WCAP-14450-NP-A, Rev.1 (Non-Proprietary), October 1999.
WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995.
Model NOTRUMP Nuclear Enthalpy Rise Hot Channel Factor (FNAH) 2.7 WCAP-1 0054-P-A, "Westinghouse Small Break ECCS Evaluation Using the NOTRUMP Code," August 1985.
Note: WCAP-1 0081 -A as referenced in TS which is the non-prop version of WCAP-10054-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 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, Revision 3 (TAC NO MB0306) dated September 10, 2001.
Rev. 0 Cycle 27 Page 22 of 25
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 (cont)
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved Methodology 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 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.
2.8 Axial Flux Difference 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)
Instrumentation-Overtemperature AT WCAP-8745-P-A, "Design Bases For The Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
Cycle 27 Page 23 of 25 Rev. 0
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 Table 1 (cont)
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 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.
2.11 RCS Pressure, Temperature, and Flow Departure From Nucleate (DNB) Limits WCAP-1 1397-P-A, 'Revised Thermal Design Procedure, "April 1989, for those events analyzed using RTDP WCAP-1 5591, '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 Rev. 0 Cycle 27 Page 24 of 25
KEWAUNEE NUCLEAR POWER PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 Revision 5 CORE OPERATING LIMITS REPORT CYCLE 27 2002, Proprietary. Safety Evaluation dated July 8, 2003.
Table 1 (cont)
NRC Approved Methodologies for COLR Parameters COLR Section Parameter NRC Approved MethodologV 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 Kewaunee" Report, dated August 21, 1979, report date September 29,1978.
Cycle 27 Page 25 of 25 Rev. 0