ML25307A002
| ML25307A002 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/03/2025 |
| From: | Hamman D Wolf Creek |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 001256 | |
| Download: ML25307A002 (1) | |
Text
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 Dustin T. Hamman Director Nuclear and Regulatory Affairs November 3, 2025 001256 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Docket No. 50-482: Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Commissioners and Staff:
The enclosed document is being submitted pursuant to Section 5.6.5.d of the Wolf Creek Generating Station (WCGS) Technical Specifications.
Enclosure I is Revision 0 of the WCGS Cycle 28 Core Operating Limits Report applicable to all modes.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.
Sincerely, Dustin T. Hamman DTH/jkt Enclosure I: Wolf Creek Generating Station Cycle 28 Core Operating Limits Report, Revision 0 cc:
A. N. Agrawal (NRC), w/e S. S. Lee (NRC), w/e J. D. Monninger (NRC), w/e Senior Resident Inspector (NRC), w/e WC Licensing Correspondence - RA 25-001256, w/e
Enclosure to 001256 WOLF CREEK GENERATING STATION CYCLE 28 CORE OPERATING LIMITS REPORT, REVISION 0 (24 pages including this page)
APF 05-013-01, REV. 04A TR-94-0015 WCNOC Cycle 28 Core Operating Limits Report (COLR)
Revision 0 ELECTRONIC APPROVAL
- 1. APPROVED-MFG. MAY PROCEED
- 2. NOT APPROVED--RESUBMIT FINAL DOCUMENT/DRAWING-MFG. MAY PROCEED YES NO
- 3. APPROVED INFORMATION NOT CONTROLLED UNDER DESIGN PROCESS
- 4. ACCEPTABLE-MAINTAIN AS RECORD (INFO. ONLY)
- 5. RESTRICTED FOR WOLF CREEK PLANNING ONLY-MFG. MAY PROCEED YES NO APPROVAL OF THIS DOCUMENT/DRAWING DOES NOT RELIEVE SUPPLIER/CONTRACTOR FROM FULL COMPLIANCE WITH CONTRACT, SPECIFICATIONS AND/OR PURCHASE ORDER REQUIREMENTS.
COMMENTS:
VETIP (AI 05C-001): This document does not contain design information that requires an engineering Change Package.
Safety Related NOTE: DO NOT RELEASE this document until directed by Nuclear Engineering. This document is to be released during Refuel 27 after core offload before core reload.
P.O.#:
N/A VENDOR MANUAL:
PAGE: N/A CHANGE PACKAGE #:
N/A INCORPORATED CHANGE DOCUMENT(S):
N/A REV. #
W34 ENGINEERING REVIEW:
DRAFTER:
DigsigOrg 2.8 0.45 N/A CHECKER:
DigsigOrg 2.8 0.45 N/A ENGINEER:
DigsigVer 2.8 0.45 See attached.
SUPERVISOR:
DigsigApp 2.8 0.45 10/16/2025 Elizabeth Gernander on behalf of Chad Lisle DigsigCert 3.5 1.75
1 Page 1 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 WOLF CREEK GENERATING STATION CYCLE 28 CORE OPERATING LIMITS REPORT Revision 0 October 2025 Prepared by:
10/13/2025 Ian Miller Date Reviewed by:
10/16/2025 Gregory S. Kinn Date Approved by:
10/16/2025 Elizabeth Gernander on behalf of Chad Lisle Date
Page 2 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 28 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The core operating limits that are included in the COLR affect the following Technical Specifications:
2.1.1 Reactor Core Safety Limits 3.1.1 Shutdown Margin (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.4 Rod Group Alignment Limits 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.8 PHYSICS TESTS Exceptions - MODE 2 3.2.1 Heat Flux Hot Channel Factor
Z FQ (RAOC - T(z) Methodology) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor
N H
F 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 Boron Concentration
Page 3 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections below:
2.1 Reactor Core Safety Limits (SL 2.1.1)
In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits in Figure 2.1.
Figure 2.1 Reactor Core Safety Limits Unacceptable Consequences 1925 psia 2460 psia 2250 psia 2000 psia Acceptable Consequences
Page 4 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.2 Moderator Temperature Coefficient (MTC) (LCO 3.1.3, SR 3.1.3.1, SR 3.1.3.2)
The MTC shall be less positive than the limit provided in Figure 2.2.
The MTC shall be less negative than -50 pcm/F.
The 300 PPM MTC Surveillance limit is -41 pcm/F (equilibrium, all rods withdrawn, RATED THERMAL POWER condition).
The 60 PPM MTC Surveillance limit is -46 pcm/F (equilibrium, all rods withdrawn, RATED THERMAL POWER condition).
Figure 2.2 Moderator Temperature Coefficient Vs.
THERMAL POWER (%)
UNACCEPTABLE OPERATION ACCEPTABLE OPERATION 6.0, 70%
0 2
4 6
8 0
10 20 30 40 50 60 70 80 90 100
% of RATED THERM AL POWER MODERATOR TEMPERATURE COEFFICIENT (pcm/
oF)
Page 5 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.3 Shutdown Bank Insertion Limits (LCO 3.1.5)
The shutdown banks shall be fully withdrawn (i.e., positioned within the interval of > 222 and < 231 steps withdrawn).
2.4 Control Bank Insertion Limits (LCO 3.1.6)
The Control Bank insertion limits are specified in Figure 2.4. The Control Bank withdrawal sequence is A-B-C-D. The insertion sequence is the reverse of the withdrawal sequence. The difference between each sequential Control Bank position is 115 steps when not fully inserted and not fully withdrawn.
Figure 2.4 Control Bank Insertion, Sequence, and Overlap Limits Vs.
THERMAL POWER (%) - Four Loop Operation Fully withdrawn shall be the condition where control banks are at a position within the interval of 222 and 231 steps withdrawn.
( F U L L Y W IT H D R A W N )
( F U L L Y IN S E R T E D )
( 2 6.7 %, 2 2 2 )
( 0 %, 1 6 1 )
( 7 6.7 %, 2 2 2 )
( 0 %, 4 6 )
( 1 0 0 %, 1 6 1 )
( 3 0.2 %, 0 )
0 2 0 4 0 6 0 8 0 1 0 0 1 2 0 1 4 0 1 6 0 1 8 0 2 0 0 2 2 0 0
2 0 4 0 6 0 8 0 1 0 0 T H E R M A L P O W E R ( P e r c e n t )
S T
E P
S W
I T
H D
R A
W N
B A N K B
B A N K C
B A N K D
Page 6 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.5 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC)
Methodology) (LCO 3.2.3)
The indicated AXIAL FLUX DIFFERENCE (AFD) allowed for RAOC Operating Space 1 (ROS1) and RAOC Operating Space 2 (ROS2) and corresponding reduction limits Required Action 1 (RA1) and Required Action 2 (RA2) are defined by Figure 2.5. Implementation of RA1 or RA2 corresponds to Required Action B.2.1 of LCO 3.2.1.
Power
(% RTP)
ROS1 AFD Limit (%)
ROS2 AFD Limit (%)
Power
(% RTP)
RA1 AFD Limit (%)
RA2 AFD Limit (%)
50
-29
-26 50
-25
-23 100
-15
-12 95
-12.4
-10.4 100 5
5 95 6.9 6.9 50 24 24 50 24 24 Figure 2.5 AXIAL FLUX DIFFERENCE Limits as a Function of THERMAL POWER (%)
45 50 55 60 65 70 75 80 85 90 95 100 105
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25
% of Rated Thermal Power Flux Difference (I) %
ROS1 ROS2 RA1 RA2 Acceptable Operation Unacceptable Operation Unacceptable Operation
Page 7 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.6 Heat Flux Hot Channel Factor (FQ(Z))(RAOC - T(Z) Methodology) (LCO 3.2.1, SR 3.2.1.1, SR 3.2.1.2)
, for P 0.5
0.5, for P 0.5 where,
= defined below RTP Q
F
=
(Z)
FQ limit at RATED THERMAL POWER (RTP)
= 2.50, and P
=
POWER THERMAL RATED POWER THERMAL
Z K
= as defined in Figure 2.6 1.031 100
- where, (Z)
F M Q
= is the measured value of (Z)
FQ
, inferred from a power distribution measurement obtained with the Movable Incore Detector System (MIDS) or the Power Distribution Monitoring System (PDMS) 1.03
= the engineering uncertainty factor (includes manufacturing tolerances)
= the measurement uncertainty factor which is 5 when (Z)
F M Q
is obtained from MIDS or determined dynamically when obtained from PDMS
Page 8 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0
, for P 0.5
0.5, for P 0.5
- where,
= 1.03
1 100
= the measured planar radial peaking factor
= provided in Appendix A, Tables A.1 and A.2 for ROS1 and ROS2, respectively.
= Adjust the surveillance to the reference conditions assumed in generating the factors. may be assumed to equal 1.0 or may be determined for specific surveillance conditions using the approved methods listed in TS 5.6.5.
= penalty factors to account for the potential decrease in transient FQ margin between surveillances. The Rj factors for ROS1 and ROS2 are provided in Appendix A, Tables A.3 and A.4, respectively.
evaluations are not applicable for axial core regions in:
a) The exclusion zones defined in Appendix A, Table A.6, b) Grid plane regions, +/-2%, inclusive, c) Core plane regions within +/-2% of the bank demand positions of the control banks.
Appendix A, Table A.5, provides the required limits on THERMAL POWER and the required AFD reductions for each ROS in the event that additional margin is required.
Page 9 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Figure 2.6 K(Z) - Normalized Peaking Factor Vs. Core Height 0.0 0.2 0.4 0.6 0.8 1.0 1.2 0
2 4
6 8
10 12 CORE HEIGHT (FT)
NORMALIZED PEAKING FACTOR K(Z)
FQ RTP = 2.50 Ele vation (ft) K(Z) 0.0 1.000 6.0 1.000 12.0 0.925
Page 10 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.7 Nuclear Enthalpy Rise Hot Channel Factor (
N H
F) (LCO 3.2.2)
N H
F shall be limited by the following relationship:
F F
PF P
H N
H RTP H
10 10 Where, F H RTP
= F H N
limit at RATED THERMAL POWER (RTP)
= 1.650 PF H
= power factor multiplier for F H N
= 0.3 P
=
MAL POWER RATED THER WER THERMAL PO N
H F
=
N H
F is the measured value of N
H F, inferred from a power distribution measurement obtained with the Movable Incore Detector System (MIDS) or the Power Distribution Monitoring System (PDMS). Measurement uncertainty is applied as follows.
When N
H F is obtained from MIDS, the measured value is multiplied by 1.04.
When N
H F is obtained from PDMS, the measured value is increased by an uncertainty factor (UH), and the factor is determined by PDMS, with a lower limit of 4%.
Page 11 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.8 Reactor Trip System Overtemperature T Setpoint Parameter Values (LCO 3.3.1, Table 3.3.1-1, Note 1)
Parameter Value Overtemperature T reactor trip setpoint K1 = 1.10 Overtemperature T reactor trip setpoint Tavg coefficient K2 = 0.0137/F Overtemperature T reactor trip setpoint pressure coefficient K3 = 0.00095/psi Nominal Tavg (Tref from Rod Control) at RTP T 586.5F Nominal RCS operating pressure P 2235 psig Measured RCS T lead/lag constant 1 = 6 sec 2 = 3 sec Measured RCS T lag constant 3 = 2 sec Measured RCS average temperature lead/lag constant 4 = 16 sec 5 = 4 sec Measured RCS average temperature lead/lag constant 6 = 0 sec f1(I) = -0.0227 / %RTP {23% RTP + (qt-qb)} when (qt-qb) < -23% RTP 0% of RTP when -23% RTP (qt-qb) 5% RTP 0.0184 / %RTP {(qt-qb) - 5% RTP}
when (qt-qb) > 5% RTP Where, qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.
Page 12 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.9 Reactor Trip System Overpower T Setpoint Parameter Values (LCO 3.3.1, Table 3.3.1-1, Note 2)
Parameter Value K4 = 1.10 K5 = 0.02/F for increasing Tavg
= 0/F for decreasing Tavg K6 = 0.00128/F for T T
= 0/F for T T T 586.5F 1 = 6 sec 2 = 3 sec 3 = 2 sec 6 = 0 sec 7 = 10 sec Overpower T reactor trip setpoint Overpower T reactor trip setpoint Tavg rate/lag coefficient Overpower T reactor trip setpoint Tavg heatup coefficient Nominal Tavg (Tref from Rod Control) at RTP Measured RCS T lead/lag constant Measured RCS T lag constant Measured RCS average temperature lag constant Measured RCS average temperature rate/lag constant f2(I) = 0% RTP for all I*
- Note: the f2(I) function generator has been physically removed by CP 012858; AFD is not an input to the OPT trip setpoint. Reference AN-24-001-CN001.
Page 13 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
Limits (LCO 3.4.1)
Parameter Indicated Value Pressurizer pressure Pressure 2219 psig (Average of 4 channels) 2221 psig (Average of 3 channels)
RCS average temperature Tavg 590.8 F (Average of 4 channels) 590.6 F (Average of 3 channels)
RCS total flow rate Flow 376,000 gpm 2.11 Boron Concentration (LCO 3.9.1)
The refueling boron concentration shall be greater than or equal to 2300 ppm.
2.12 SHUTDOWN MARGIN (LCO 3.1.1, 3.1.4, 3.1.5, 3.1.6, & 3.1.8)
The SHUTDOWN MARGIN shall be greater than or equal to 1300 pcm (1.3% k/k).
Page 14 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 APPENDIX A Table A.1 [T(Z)]COLR Factors for ROS1 Height Trace Burnup (MWD/MTU)
(ft.)
Point 150 1,000 2,000 3,000 4,000 5,000 6,000 7,000 8,000 10,000 12,000 14,000 16,000 18,000 19,000 12.0720 1
0.1624 0.1457 0.1265 0.1289 0.1248 0.1241 0.1215 0.1275 0.1284 0.1406 0.1490 0.1626 0.1791 0.1950 0.2028 11.9043 2
0.4020 0.3677 0.3421 0.3313 0.3199 0.3163 0.3068 0.3164 0.3139 0.3287 0.3348 0.3508 0.3704 0.3881 0.3914 11.7367 3
0.6688 0.6133 0.5794 0.5511 0.5302 0.5231 0.5059 0.5188 0.5123 0.5294 0.5330 0.5517 0.5748 0.5956 0.5930 11.5690 4
0.9141 0.8402 0.7996 0.7570 0.7282 0.7182 0.6939 0.7102 0.7003 0.7200 0.7212 0.7423 0.7685 0.7916 0.7839 11.4013 5
1.1014 1.0170 0.9737 0.9263 0.8943 0.8834 0.8537 0.8736 0.8617 0.8847 0.8840 0.9069 0.9349 0.9579 0.9483 11.2337 6
1.2165 1.1313 1.0904 1.0497 1.0194 1.0095 0.9766 1.0005 0.9883 1.0152 1.0134 1.0375 1.0656 1.0856 1.0774 11.0660 7
1.2383 1.1635 1.1312 1.1061 1.0826 1.0761 1.0430 1.0705 1.0601 1.0909 1.0889 1.1131 1.1399 1.1558 1.1478 10.8983 8
1.1827 1.1280 1.1144 1.0923 1.0760 1.0753 1.0461 1.0789 1.0703 1.1022 1.0999 1.1208 1.1459 1.1609 1.1497 10.7307 9
1.1694 1.1287 1.1375 1.1099 1.0957 1.0998 1.0725 1.1046 1.0970 1.1291 1.1266 1.1467 1.1695 1.1826 1.1703 10.5630 10 1.2307 1.1967 1.2197 1.1953 1.1788 1.1834 1.1522 1.1866 1.1788 1.2111 1.2090 1.2242 1.2429 1.2504 1.2375 10.3953 11 1.2686 1.2453 1.2759 1.2572 1.2388 1.2408 1.2085 1.2424 1.2344 1.2649 1.2628 1.2725 1.2873 1.2913 1.2777 10.2277 12 1.2453 1.2331 1.2679 1.2527 1.2389 1.2404 1.2144 1.2423 1.2346 1.2626 1.2607 1.2660 1.2785 1.2810 1.2668 10.0600 13 1.1788 1.1731 1.2084 1.1915 1.1925 1.1997 1.1834 1.2029 1.1969 1.2227 1.2234 1.2244 1.2357 1.2347 1.2257 9.8923 14 1.1623 1.1637 1.1955 1.1786 1.1857 1.1946 1.1870 1.1962 1.1935 1.2138 1.2252 1.2125 1.2223 1.2220 1.2218 9.7247 15 1.2233 1.2367 1.2545 1.2557 1.2449 1.2408 1.2426 1.2454 1.2449 1.2569 1.2751 1.2501 1.2603 1.2628 1.2630 9.5570 16 1.2569 1.2756 1.2809 1.2958 1.2766 1.2607 1.2709 1.2736 1.2757 1.2804 1.2986 1.2698 1.2812 1.2800 1.2808 9.3893 17 1.2337 1.2529 1.2588 1.2752 1.2607 1.2420 1.2528 1.2569 1.2614 1.2621 1.2777 1.2497 1.2593 1.2567 1.2582 9.2217 18 1.1769 1.1968 1.2118 1.2297 1.2191 1.2018 1.2083 1.2127 1.2204 1.2157 1.2300 1.2029 1.2108 1.2072 1.2120 9.0540 19 1.1523 1.1765 1.1954 1.2115 1.2010 1.1863 1.1922 1.1978 1.2049 1.1926 1.2078 1.1833 1.1887 1.1848 1.1897 8.8863 20 1.2028 1.2366 1.2456 1.2578 1.2434 1.2325 1.2376 1.2505 1.2496 1.2301 1.2429 1.2275 1.2269 1.2216 1.2222 8.7187 21 1.2535 1.2879 1.2906 1.3014 1.2838 1.2749 1.2814 1.2942 1.2930 1.2630 1.2746 1.2635 1.2559 1.2568 1.2482 8.5510 22 1.2538 1.2894 1.2890 1.3021 1.2852 1.2831 1.2868 1.2983 1.2956 1.2621 1.2762 1.2681 1.2537 1.2591 1.2464 8.3833 23 1.2021 1.2333 1.2426 1.2545 1.2466 1.2470 1.2510 1.2618 1.2565 1.2270 1.2383 1.2351 1.2227 1.2275 1.2186 8.2157 24 1.1682 1.1986 1.2160 1.2229 1.2224 1.2222 1.2259 1.2327 1.2297 1.2015 1.2117 1.2108 1.1973 1.2062 1.1965 8.0480 25 1.2197 1.2530 1.2690 1.2737 1.2749 1.2729 1.2752 1.2834 1.2750 1.2454 1.2514 1.2499 1.2391 1.2438 1.2382 7.8803 26 1.2582 1.2964 1.3117 1.3148 1.3174 1.3146 1.3157 1.3232 1.3107 1.2816 1.2823 1.2803 1.2713 1.2734 1.2708 7.7127 27 1.2519 1.2889 1.3040 1.3088 1.3107 1.3095 1.3098 1.3162 1.3056 1.2748 1.2765 1.2709 1.2656 1.2711 1.2675 7.5450 28 1.2064 1.2420 1.2587 1.2637 1.2659 1.2665 1.2667 1.2726 1.2640 1.2346 1.2377 1.2312 1.2303 1.2394 1.2363 7.3773 29 1.1700 1.2043 1.2228 1.2280 1.2304 1.2323 1.2319 1.2372 1.2302 1.2018 1.2059 1.1985 1.2015 1.2139 1.2112 7.2097 30 1.2059 1.2401 1.2597 1.2646 1.2661 1.2681 1.2667 1.2704 1.2633 1.2325 1.2353 1.2245 1.2289 1.2421 1.2387 7.0420 31 1.2530 1.2873 1.3083 1.3128 1.3131 1.3147 1.3117 1.3135 1.3061 1.2723 1.2732 1.2588 1.2642 1.2780 1.2737 6.8743 32 1.2626 1.2963 1.3185 1.3231 1.3230 1.3248 1.3208 1.3213 1.3142 1.2798 1.2798 1.2636 1.2707 1.2858 1.2813 6.7067 33 1.2223 1.2547 1.2780 1.2847 1.2843 1.2867 1.2827 1.2828 1.2770 1.2451 1.2456 1.2299 1.2397 1.2567 1.2531 6.5390 34 1.1703 1.2013 1.2253 1.2373 1.2372 1.2364 1.2333 1.2331 1.2288 1.2000 1.2013 1.1874 1.1990 1.2177 1.2151 6.3713 35 1.1960 1.2264 1.2542 1.2692 1.2705 1.2668 1.2587 1.2558 1.2512 1.2216 1.2210 1.2076 1.2171 1.2357 1.2328 6.2037 36 1.2367 1.2681 1.3019 1.3176 1.3202 1.3154 1.3059 1.2932 1.2865 1.2566 1.2522 1.2394 1.2460 1.2633 1.2601 6.0360 37 1.2324 1.2663 1.3035 1.3200 1.3248 1.3200 1.3101 1.2942 1.2806 1.2537 1.2470 1.2371 1.2419 1.2576 1.2559
Page 15 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Table A.1 [T(Z)]COLR Factors for ROS1 (continued)
Height Trace Burnup (MWD/MTU)
(ft.)
Point 150 1,000 2,000 3,000 4,000 5,000 6,000 7,000 8,000 10,000 12,000 14,000 16,000 18,000 19,000 5.8683 38 1.1904 1.2245 1.2603 1.2782 1.2853 1.2812 1.2720 1.2581 1.2442 1.2156 1.2063 1.2023 1.2049 1.2202 1.2203 5.7007 39 1.1422 1.1751 1.2077 1.2283 1.2363 1.2354 1.2272 1.2163 1.2035 1.1770 1.1662 1.1647 1.1646 1.1765 1.1801 5.5330 40 1.1584 1.1948 1.2306 1.2523 1.2603 1.2581 1.2495 1.2376 1.2267 1.2009 1.1892 1.1831 1.1835 1.1884 1.1934 5.3653 41 1.2100 1.2488 1.2871 1.3084 1.3161 1.3133 1.3037 1.2888 1.2794 1.2499 1.2371 1.2258 1.2271 1.2277 1.2326 5.1977 42 1.2335 1.2724 1.3108 1.3318 1.3394 1.3382 1.3284 1.3125 1.3036 1.2727 1.2590 1.2459 1.2467 1.2454 1.2511 5.0300 43 1.2300 1.2689 1.3073 1.3287 1.3366 1.3363 1.3272 1.3116 1.3038 1.2745 1.2602 1.2472 1.2469 1.2438 1.2511 4.8623 44 1.2272 1.2658 1.3046 1.3258 1.3340 1.3344 1.3260 1.3107 1.3041 1.2757 1.2609 1.2479 1.2470 1.2425 1.2507 4.6947 45 1.2334 1.2716 1.3093 1.3318 1.3401 1.3409 1.3331 1.3180 1.3125 1.2850 1.2693 1.2558 1.2534 1.2486 1.2559 4.5270 46 1.2481 1.2859 1.3230 1.3459 1.3541 1.3554 1.3481 1.3329 1.3285 1.3017 1.2846 1.2703 1.2659 1.2601 1.2663 4.3593 47 1.2608 1.2979 1.3341 1.3572 1.3654 1.3671 1.3605 1.3457 1.3422 1.3165 1.2981 1.2830 1.2765 1.2697 1.2746 4.1917 48 1.2428 1.2784 1.3132 1.3364 1.3447 1.3474 1.3422 1.3282 1.3271 1.3041 1.2860 1.2714 1.2641 1.2574 1.2614 4.0240 49 1.1973 1.2307 1.2634 1.2863 1.2953 1.2992 1.2961 1.2859 1.2855 1.2670 1.2505 1.2379 1.2306 1.2252 1.2286 3.8563 50 1.1943 1.2261 1.2569 1.2796 1.2881 1.2930 1.2915 1.2868 1.2837 1.2675 1.2513 1.2385 1.2303 1.2240 1.2266 3.6887 51 1.2470 1.2777 1.3070 1.3295 1.3392 1.3431 1.3435 1.3405 1.3336 1.3188 1.2988 1.2857 1.2721 1.2655 1.2645 3.5210 52 1.2804 1.3094 1.3367 1.3585 1.3731 1.3752 1.3774 1.3745 1.3651 1.3541 1.3301 1.3203 1.3000 1.2962 1.2904 3.3533 53 1.2788 1.3053 1.3297 1.3507 1.3696 1.3720 1.3752 1.3738 1.3659 1.3579 1.3350 1.3276 1.3056 1.3031 1.2963 3.1857 54 1.2703 1.2952 1.3158 1.3371 1.3583 1.3606 1.3651 1.3655 1.3595 1.3550 1.3349 1.3293 1.3066 1.3051 1.2971 3.0180 55 1.2760 1.2981 1.3165 1.3370 1.3544 1.3597 1.3647 1.3656 1.3596 1.3579 1.3390 1.3364 1.3142 1.3142 1.3066 2.8503 56 1.2961 1.3168 1.3322 1.3489 1.3591 1.3657 1.3713 1.3720 1.3729 1.3698 1.3581 1.3579 1.3362 1.3379 1.3309 2.6827 57 1.3216 1.3428 1.3532 1.3642 1.3739 1.3782 1.3844 1.3863 1.3931 1.3847 1.3868 1.3886 1.3669 1.3701 1.3631 2.5150 58 1.3341 1.3535 1.3590 1.3643 1.3728 1.3761 1.3823 1.3888 1.3974 1.3859 1.4006 1.4055 1.3850 1.3905 1.3840 2.3473 59 1.3092 1.3243 1.3249 1.3246 1.3321 1.3355 1.3431 1.3522 1.3637 1.3565 1.3795 1.3890 1.3719 1.3812 1.3763 2.1797 60 1.2827 1.2927 1.2830 1.2769 1.2828 1.2890 1.2951 1.3068 1.3211 1.3205 1.3542 1.3687 1.3558 1.3694 1.3663 2.0120 61 1.3224 1.3263 1.3140 1.3001 1.3075 1.3133 1.3166 1.3284 1.3446 1.3484 1.3834 1.4015 1.3904 1.4070 1.4047 1.8443 62 1.3865 1.3830 1.3620 1.3389 1.3483 1.3525 1.3546 1.3654 1.3816 1.3896 1.4284 1.4498 1.4402 1.4597 1.4581 1.6767 63 1.4102 1.3984 1.3686 1.3400 1.3474 1.3501 1.3515 1.3617 1.3796 1.3910 1.4336 1.4598 1.4541 1.4783 1.4785 1.5090 64 1.4019 1.3812 1.3429 1.3113 1.3146 1.3156 1.3162 1.3256 1.3461 1.3604 1.4069 1.4385 1.4381 1.4678 1.4707 1.3413 65 1.3910 1.3585 1.3113 1.2757 1.2749 1.2736 1.2730 1.2811 1.3030 1.3197 1.3690 1.4054 1.4105 1.4456 1.4511 1.1737 66 1.3943 1.3517 1.2927 1.2506 1.2438 1.2388 1.2355 1.2413 1.2633 1.2807 1.3315 1.3720 1.3825 1.4230 1.4314 1.0060 67 1.4283 1.3674 1.2915 1.2393 1.2241 1.2130 1.2053 1.2072 1.2279 1.2438 1.2947 1.3385 1.3543 1.4009 1.4126 0.8383 68 1.3943 1.3197 1.2322 1.1733 1.1513 1.1352 1.1238 1.1219 1.1402 1.1536 1.2018 1.2466 1.2666 1.3168 1.3314 0.6707 69 1.1873 1.1155 1.0336 0.9797 0.9573 0.9412 0.9297 0.9266 0.9421 0.9539 0.9961 1.0377 1.0596 1.1079 1.1233 0.5030 70 0.8553 0.8001 0.7383 0.6986 0.6819 0.6704 0.6626 0.6610 0.6740 0.6861 0.7209 0.7569 0.7790 0.8212 0.8359 0.3353 71 0.5769 0.5384 0.4958 0.4693 0.4586 0.4518 0.4479 0.4482 0.4591 0.4717 0.5006 0.5313 0.5530 0.5896 0.6035 0.1677 72 0.4463 0.4159 0.3824 0.3619 0.3538 0.3488 0.3461 0.3468 0.3559 0.3672 0.3914 0.4177 0.4371 0.4688 0.4812 0.0000 73 0.3580 0.3326 0.3048 0.2880 0.2811 0.2768 0.2744 0.2748 0.2820 0.2909 0.3100 0.3308 0.3461 0.3710 0.3807
Page 16 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Table A.2 [T(Z)]COLR Factors for ROS2 Height Trace Burnup (MWD/MTU)
(ft.)
Point 150 1,000 2,000 3,000 4,000 5,000 6,000 7,000 8,000 10,000 12,000 14,000 16,000 18,000 19,000 12.0720 1
0.1626 0.1458 0.1266 0.1290 0.1249 0.1242 0.1216 0.1276 0.1284 0.1408 0.1492 0.1627 0.1792 0.1951 0.2061 11.9043 2
0.4024 0.3679 0.3423 0.3314 0.3200 0.3163 0.3069 0.3165 0.3139 0.3290 0.3351 0.3509 0.3704 0.3882 0.3977 11.7367 3
0.6693 0.6136 0.5797 0.5513 0.5303 0.5232 0.5060 0.5190 0.5123 0.5298 0.5334 0.5518 0.5749 0.5957 0.6025 11.5690 4
0.9148 0.8406 0.7999 0.7572 0.7284 0.7184 0.6941 0.7104 0.7003 0.7205 0.7217 0.7424 0.7686 0.7917 0.7964 11.4013 5
1.1022 1.0175 0.9741 0.9266 0.8946 0.8835 0.8538 0.8738 0.8617 0.8852 0.8846 0.9071 0.9350 0.9579 0.9634 11.2337 6
1.2173 1.1318 1.0907 1.0500 1.0196 1.0096 0.9767 1.0007 0.9882 1.0157 1.0140 1.0376 1.0657 1.0857 1.0945 11.0660 7
1.2390 1.1640 1.1315 1.1064 1.0828 1.0762 1.0431 1.0706 1.0601 1.0914 1.0894 1.1132 1.1400 1.1558 1.1661 10.8983 8
1.1833 1.1284 1.1146 1.0925 1.0761 1.0753 1.0462 1.0790 1.0702 1.1027 1.1004 1.1208 1.1459 1.1609 1.1681 10.7307 9
1.1699 1.1290 1.1377 1.1100 1.0958 1.0998 1.0726 1.1047 1.0969 1.1295 1.1268 1.1468 1.1695 1.1826 1.1886 10.5630 10 1.2311 1.1969 1.2199 1.1954 1.1789 1.1834 1.1522 1.1866 1.1787 1.2114 1.2088 1.2242 1.2429 1.2503 1.2558 10.3953 11 1.2690 1.2455 1.2760 1.2574 1.2388 1.2408 1.2085 1.2423 1.2342 1.2652 1.2627 1.2725 1.2873 1.2912 1.2952 10.2277 12 1.2456 1.2332 1.2680 1.2527 1.2389 1.2403 1.2143 1.2422 1.2345 1.2627 1.2606 1.2659 1.2784 1.2809 1.2832 10.0600 13 1.1789 1.1731 1.2084 1.1915 1.1925 1.1996 1.1833 1.2028 1.1994 1.2227 1.2233 1.2243 1.2357 1.2346 1.2379 9.8923 14 1.1623 1.1637 1.1955 1.1785 1.1856 1.1945 1.1869 1.1960 1.2055 1.2137 1.2250 1.2124 1.2222 1.2219 1.2210 9.7247 15 1.2231 1.2365 1.2544 1.2556 1.2447 1.2407 1.2425 1.2452 1.2631 1.2567 1.2749 1.2499 1.2601 1.2626 1.2581 9.5570 16 1.2567 1.2754 1.2808 1.2957 1.2764 1.2605 1.2707 1.2734 1.2919 1.2802 1.2983 1.2696 1.2810 1.2798 1.2764 9.3893 17 1.2334 1.2527 1.2586 1.2751 1.2605 1.2418 1.2526 1.2566 1.2731 1.2619 1.2773 1.2495 1.2591 1.2565 1.2529 9.2217 18 1.1766 1.1966 1.2116 1.2295 1.2189 1.2017 1.2081 1.2125 1.2279 1.2155 1.2296 1.2028 1.2105 1.2070 1.2063 9.0540 19 1.1520 1.1764 1.1952 1.2113 1.2008 1.1862 1.1921 1.1978 1.2084 1.1924 1.2073 1.1836 1.1885 1.1846 1.1834 8.8863 20 1.2026 1.2365 1.2454 1.2576 1.2432 1.2324 1.2375 1.2506 1.2501 1.2300 1.2426 1.2277 1.2270 1.2215 1.2156 8.7187 21 1.2536 1.2879 1.2906 1.3014 1.2839 1.2750 1.2815 1.2943 1.2932 1.2632 1.2749 1.2639 1.2560 1.2571 1.2424 8.5510 22 1.2539 1.2894 1.2890 1.3022 1.2852 1.2832 1.2870 1.2985 1.2958 1.2623 1.2765 1.2684 1.2541 1.2595 1.2405 8.3833 23 1.2022 1.2334 1.2427 1.2546 1.2467 1.2471 1.2511 1.2620 1.2568 1.2273 1.2386 1.2355 1.2231 1.2279 1.2119 8.2157 24 1.1683 1.1987 1.2161 1.2230 1.2225 1.2223 1.2261 1.2329 1.2300 1.2017 1.2120 1.2112 1.1977 1.2066 1.1901 8.0480 25 1.2198 1.2531 1.2691 1.2737 1.2750 1.2730 1.2753 1.2837 1.2752 1.2456 1.2517 1.2503 1.2394 1.2442 1.2319 7.8803 26 1.2583 1.2965 1.3118 1.3149 1.3175 1.3148 1.3159 1.3234 1.3110 1.2819 1.2827 1.2807 1.2717 1.2738 1.2645 7.7127 27 1.2520 1.2890 1.3041 1.3089 1.3108 1.3097 1.3100 1.3165 1.3058 1.2750 1.2768 1.2713 1.2660 1.2715 1.2616 7.5450 28 1.2065 1.2421 1.2588 1.2638 1.2661 1.2666 1.2669 1.2729 1.2642 1.2348 1.2380 1.2315 1.2306 1.2397 1.2309 7.3773 29 1.1701 1.2044 1.2229 1.2281 1.2305 1.2325 1.2321 1.2374 1.2304 1.2020 1.2062 1.1987 1.2017 1.2142 1.2062 7.2097 30 1.2059 1.2402 1.2598 1.2647 1.2663 1.2682 1.2669 1.2707 1.2636 1.2327 1.2355 1.2247 1.2291 1.2423 1.2340 7.0420 31 1.2531 1.2874 1.3084 1.3129 1.3132 1.3149 1.3119 1.3138 1.3063 1.2725 1.2734 1.2590 1.2644 1.2782 1.2693 6.8743 32 1.2627 1.2964 1.3186 1.3231 1.3231 1.3249 1.3210 1.3215 1.3144 1.2800 1.2800 1.2638 1.2708 1.2859 1.2773 6.7067 33 1.2224 1.2547 1.2781 1.2847 1.2844 1.2868 1.2829 1.2830 1.2772 1.2452 1.2457 1.2299 1.2398 1.2567 1.2495 6.5390 34 1.1704 1.2013 1.2253 1.2374 1.2372 1.2365 1.2334 1.2332 1.2290 1.2001 1.2014 1.1874 1.1990 1.2177 1.2121 6.3713 35 1.1960 1.2264 1.2542 1.2692 1.2705 1.2669 1.2588 1.2559 1.2513 1.2217 1.2210 1.2076 1.2171 1.2357 1.2302 6.2037 36 1.2367 1.2681 1.3019 1.3176 1.3202 1.3154 1.3059 1.2933 1.2865 1.2566 1.2522 1.2394 1.2460 1.2632 1.2579 6.0360 37 1.2324 1.2663 1.3035 1.3200 1.3248 1.3200 1.3101 1.2942 1.2806 1.2537 1.2470 1.2370 1.2418 1.2575 1.2542
Page 17 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Table A.2 [T(Z)]COLR Factors for ROS2 (continued)
Height Trace Burnup (MWD/MTU)
(ft.)
Point 150 1,000 2,000 3,000 4,000 5,000 6,000 7,000 8,000 10,000 12,000 14,000 16,000 18,000 19,000 5.8683 38 1.1904 1.2244 1.2601 1.2780 1.2851 1.2811 1.2719 1.2581 1.2441 1.2155 1.2061 1.2022 1.2047 1.2201 1.2192 5.7007 39 1.1420 1.1753 1.2082 1.2288 1.2368 1.2355 1.2273 1.2162 1.2037 1.1766 1.1662 1.1645 1.1646 1.1763 1.1791 5.5330 40 1.1589 1.1925 1.2261 1.2480 1.2557 1.2565 1.2477 1.2377 1.2241 1.1984 1.1873 1.1831 1.1822 1.1885 1.1931 5.3653 41 1.2048 1.2417 1.2787 1.2981 1.3056 1.3064 1.2971 1.2869 1.2716 1.2448 1.2324 1.2246 1.2231 1.2244 1.2295 5.1977 42 1.2230 1.2620 1.3006 1.3182 1.3258 1.3243 1.3173 1.3068 1.2908 1.2643 1.2517 1.2412 1.2399 1.2393 1.2428 5.0300 43 1.2182 1.2568 1.2949 1.3124 1.3200 1.3180 1.3126 1.3020 1.2862 1.2617 1.2501 1.2381 1.2376 1.2372 1.2379 4.8623 44 1.2142 1.2524 1.2903 1.3071 1.3153 1.3149 1.3087 1.2980 1.2825 1.2593 1.2487 1.2359 1.2357 1.2350 1.2340 4.6947 45 1.2176 1.2554 1.2929 1.3090 1.3189 1.3199 1.3123 1.3007 1.2855 1.2646 1.2546 1.2413 1.2389 1.2376 1.2356 4.5270 46 1.2303 1.2676 1.3045 1.3198 1.3313 1.3327 1.3256 1.3133 1.2981 1.2772 1.2673 1.2532 1.2487 1.2461 1.2429 4.3593 47 1.2410 1.2776 1.3137 1.3279 1.3410 1.3429 1.3365 1.3238 1.3089 1.2879 1.2783 1.2633 1.2567 1.2528 1.2483 4.1917 48 1.2217 1.2568 1.2914 1.3054 1.3195 1.3223 1.3173 1.3053 1.2914 1.2723 1.2643 1.2497 1.2421 1.2378 1.2325 4.0240 49 1.1754 1.2084 1.2409 1.2559 1.2697 1.2739 1.2709 1.2603 1.2508 1.2327 1.2274 1.2146 1.2071 1.2035 1.1983 3.8563 50 1.1710 1.2024 1.2331 1.2492 1.2619 1.2669 1.2653 1.2562 1.2513 1.2302 1.2261 1.2131 1.2045 1.1997 1.1946 3.6887 51 1.2215 1.2514 1.2805 1.2982 1.3089 1.3138 1.3139 1.3063 1.3019 1.2754 1.2706 1.2573 1.2432 1.2372 1.2307 3.5210 52 1.2553 1.2811 1.3087 1.3282 1.3362 1.3405 1.3435 1.3375 1.3338 1.3039 1.2991 1.2888 1.2680 1.2615 1.2533 3.3533 53 1.2576 1.2758 1.3033 1.3227 1.3294 1.3323 1.3382 1.3351 1.3330 1.3050 1.3016 1.2935 1.2708 1.2675 1.2577 3.1857 54 1.2534 1.2637 1.2912 1.3097 1.3149 1.3173 1.3257 1.3255 1.3254 1.2999 1.2992 1.2934 1.2701 1.2676 1.2580 3.0180 55 1.2566 1.2632 1.2904 1.3030 1.3075 1.3099 1.3190 1.3236 1.3244 1.3010 1.3005 1.2966 1.2730 1.2716 1.2688 2.8503 56 1.2711 1.2791 1.2974 1.3048 1.3095 1.3106 1.3190 1.3300 1.3292 1.3107 1.3159 1.3141 1.2907 1.2906 1.2933 2.6827 57 1.2915 1.3029 1.3140 1.3098 1.3138 1.3158 1.3245 1.3455 1.3424 1.3317 1.3415 1.3416 1.3185 1.3199 1.3221 2.5150 58 1.2978 1.3119 1.3185 1.3033 1.3053 1.3119 1.3224 1.3455 1.3457 1.3387 1.3533 1.3562 1.3341 1.3374 1.3408 2.3473 59 1.2675 1.2824 1.2842 1.2691 1.2700 1.2771 1.2857 1.3085 1.3141 1.3110 1.3316 1.3388 1.3199 1.3267 1.3319 2.1797 60 1.2403 1.2460 1.2425 1.2274 1.2271 1.2343 1.2408 1.2630 1.2753 1.2749 1.3019 1.3177 1.3028 1.3137 1.3208 2.0120 61 1.2775 1.2825 1.2714 1.2535 1.2505 1.2570 1.2611 1.2821 1.3008 1.3018 1.3327 1.3480 1.3346 1.3481 1.3566 1.8443 62 1.3382 1.3369 1.3172 1.2952 1.2887 1.2938 1.2967 1.3138 1.3388 1.3407 1.3749 1.3931 1.3808 1.3970 1.4068 1.6767 63 1.3602 1.3516 1.3230 1.2972 1.2872 1.2908 1.2931 1.3069 1.3369 1.3410 1.3788 1.4015 1.3928 1.4132 1.4253 1.5090 64 1.3512 1.3350 1.2976 1.2685 1.2551 1.2571 1.2587 1.2701 1.3036 1.3107 1.3522 1.3799 1.3764 1.4020 1.4167 1.3413 65 1.3375 1.3131 1.2666 1.2337 1.2165 1.2163 1.2167 1.2254 1.2614 1.2709 1.3149 1.3473 1.3490 1.3796 1.3969 1.1737 66 1.3425 1.3067 1.2480 1.2089 1.1862 1.1824 1.1802 1.1855 1.2226 1.2328 1.2783 1.3145 1.3213 1.3570 1.3771 1.0060 67 1.3746 1.3221 1.2464 1.1975 1.1667 1.1572 1.1508 1.1512 1.1879 1.1967 1.2423 1.2817 1.2936 1.3350 1.3583 0.8383 68 1.3413 1.2761 1.1887 1.1333 1.0966 1.0823 1.0722 1.0682 1.1026 1.1094 1.1526 1.1930 1.2090 1.2540 1.2794 0.6707 69 1.1415 1.0787 0.9966 0.9458 0.9112 0.8967 0.8864 0.8809 0.9106 0.9169 0.9547 0.9924 1.0106 1.0541 1.0786 0.5030 70 0.8219 0.7738 0.7116 0.6741 0.6486 0.6383 0.6314 0.6276 0.6511 0.6592 0.6906 0.7234 0.7425 0.7808 0.8022 0.3353 71 0.5542 0.5207 0.4777 0.4528 0.4360 0.4299 0.4265 0.4253 0.4434 0.4530 0.4793 0.5076 0.5268 0.5603 0.5789 0.1677 72 0.4286 0.4023 0.3683 0.3490 0.3362 0.3317 0.3294 0.3290 0.3437 0.3526 0.3747 0.3989 0.4163 0.4453 0.4615 0.0000 73 0.3438 0.3218 0.2936 0.2777 0.2670 0.2632 0.2611 0.2607 0.2723 0.2793 0.2967 0.3159 0.3296 0.3523 0.3650
Page 18 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Table A.3 RJ Margin Decrease Factors for ROS1 Cycle Burnup (MWD/MTU)
RJ Cycle Burnup (MWD/MTU)
RJ Cycle Burnup (MWD/MTU)
RJ 150 1.0000 6,482 1.0167 12,813 1.0100 348 1.0000 6,680 1.0173 13,011 1.0067 546 1.0000 6,877 1.0163 13,209 1.0050 744 1.0000 7,075 1.0150 13,407 1.0035 941 1.0000 7,273 1.0133 13,605 1.0023 1,139 1.0000 7,471 1.0110 13,803 1.0013 1,337 1.0000 7,669 1.0076 14,000 1.0006 1,535 1.0000 7,867 1.0056 14,198 1.0002 1,733 1.0000 8,065 1.0039 14,396 1.0000 1,931 1.0000 8,262 1.0025 14,594 1.0000 2,129 1.0065 8,460 1.0014 14,792 1.0000 2,327 1.0102 8,658 1.0005 14,990 1.0000 2,524 1.0139 8,856 1.0000 15,188 1.0009 2,722 1.0164 9,054 1.0078 15,386 1.0022 2,920 1.0169 9,252 1.0106 15,583 1.0087 3,118 1.0170 9,450 1.0178 15,781 1.0095 3,316 1.0162 9,647 1.0206 15,979 1.0099 3,514 1.0145 9,845 1.0231 16,177 1.0100 3,712 1.0144 10,043 1.0255 16,375 1.0096 3,909 1.0150 10,241 1.0276 16,573 1.0091 4,107 1.0156 10,439 1.0278 16,771 1.0084 4,305 1.0151 10,637 1.0273 16,968 1.0075 4,503 1.0150 10,835 1.0266 17,166 1.0013 4,701 1.0141 11,033 1.0212 17,364 1.0007 4,899 1.0131 11,230 1.0201 17,562 1.0002 5,097 1.0119 11,428 1.0204 17,760 1.0000 5,294 1.0121 11,626 1.0192 17,958 1.0000 5,492 1.0125 11,824 1.0180 5,690 1.0126 12,022 1.0167 5,888 1.0135 12,220 1.0152 6,086 1.0155 12,418 1.0136 6,284 1.0162 12,615 1.0118
Page 19 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Table A.4 RJ Margin Decrease Factors for ROS2 Cycle Burnup (MWD/MTU)
RJ Cycle Burnup (MWD/MTU)
RJ Cycle Burnup (MWD/MTU)
RJ 150 1.0000 6,482 1.0156 12,813 1.0085 348 1.0000 6,680 1.0112 13,011 1.0054 546 1.0000 6,877 1.0089 13,209 1.0038 744 1.0000 7,075 1.0071 13,407 1.0025 941 1.0000 7,273 1.0058 13,605 1.0015 1,139 1.0000 7,471 1.0042 13,803 1.0008 1,337 1.0000 7,669 1.0050 14,000 1.0002 1,535 1.0000 7,867 1.0039 14,198 1.0000 1,733 1.0000 8,065 1.0030 14,396 1.0000 1,931 1.0000 8,262 1.0021 14,594 1.0000 2,129 1.0054 8,460 1.0019 14,792 1.0000 2,327 1.0114 8,658 1.0019 14,990 1.0000 2,524 1.0166 8,856 1.0021 15,188 1.0000 2,722 1.0182 9,054 1.0059 15,386 1.0006 2,920 1.0185 9,252 1.0081 15,583 1.0040 3,118 1.0178 9,450 1.0151 15,781 1.0052 3,316 1.0161 9,647 1.0174 15,979 1.0062 3,514 1.0145 9,845 1.0195 16,177 1.0071 3,712 1.0148 10,043 1.0214 16,375 1.0078 3,909 1.0147 10,241 1.0232 16,573 1.0083 4,107 1.0146 10,439 1.0248 16,771 1.0087 4,305 1.0130 10,637 1.0257 16,968 1.0090 4,503 1.0113 10,835 1.0251 17,166 1.0070 4,701 1.0092 11,033 1.0195 17,364 1.0071 4,899 1.0071 11,230 1.0184 17,562 1.0071 5,097 1.0105 11,428 1.0189 17,760 1.0071 5,294 1.0121 11,626 1.0178 17,958 1.0071 5,492 1.0134 11,824 1.0166 5,690 1.0137 12,022 1.0152 5,888 1.0147 12,220 1.0138 6,086 1.0144 12,418 1.0122 6,284 1.0146 12,615 1.0104
Page 20 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 Table A.5 Required THERMAL POWER Limits and AFD Reductions RAOC Operating Space Required Action Space Required FQW(z)
Margin Improvement
(%)
Required THERMAL POWER Limit
(% RTP)
Required AFD Reduction ROS1 RA1 6.07 95 See Figure 2.5
> 6.07
< 50 N/A ROS2 RA2 3.66 95 See Figure 2.5
> 3.66
< 50 N/A Table A.6 Burnup Dependent FQ Surveillance Exclusion Zones Cycle Burnup (MWD/MTU)
)
(Z FQ Exclusion Zone
(% [INCORE mesh points])
Top Bottom 2,000 10 [7]
10 [7]
> 2,000 to 10,000 15 [11]
15 [11]
> 10,000 10 [7]
10 [7]
Page 21 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0 B.
Approved Analytical Methods for Determining Core Operating Limits The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents.
- 1.
WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.
NRC Safety Evaluation Report dated January 17, 1989, for the Acceptance for Referencing of Licensing Topical Report WCAP-11397, Revised Thermal Design Procedure.
- 2.
WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC FQ Surveillance Technical Specifications, February 2019.
NRC Safety Evaluation Report dated November 23, 2018, Final Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report WCAP-17661, Rev. 1 Improved RAOC and CAOC FQ Surveillance Technical Specifications (CAC No. MF3348)
- 3.
WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.
NRC Safety Evaluation Report dated May 28, 1985, Acceptance for Referencing of Licensing Topical Report WCAP-9272(P)/9273(NP), Westinghouse Reload Safety Evaluation Methodology.
- 4.
WCAP-16009-P-A, Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM), Revision 0, January 2005.
NRC letter dated November 5, 2004,Final Safety Evaluation for WCAP-16009-P, Revision 0, Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM) (TAC NO. MB9483).
- 5.
WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.
NRC Safety Evaluation dated March 18, 2004, Final Safety Evaluation for Westinghouse Topical Report WCAP-16045-P, Revision 0, Qualification of the Two-Dimensional Transport Code PARAGON.
- 6.
WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.
NRC Safety Evaluation dated February 23, 2007, Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR) WCAP-16045-P-A, Addendum 1, Qualification of the NEXUS Nuclear Data Methodology (TAC NO. MC9606).
- 7.
WCAP 10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, September 1986.
NRC letter dated June 23, 1986, Acceptance for Referencing of Topical Report WCAP 10965-P and WCAP 10966-NP.
Page 22 of 22 Wolf Creek Generating Station Cycle 28 Core Operating Limits Report Revision 0
- 8.
WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995.
NRC Safety Evaluation Reports dated July 1, 1991, Acceptance for Referencing of Topical Report WCAP-12610, VANTAGE+ Fuel Assembly Reference Core Report (TAC NO. 77258).
NRC Safety Evaluation Report dated September 15, 1994, Acceptance for Referencing of Topical Report WCAP-12610, Appendix B, Addendum 1, Extended Burnup Fuel Design Methodology and ZIRLO Fuel Performance Models (TAC NO.
M86416).
- 9.
WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, Optimized ZirloTM, July 2006.
NRC Safety Evaluation dated June 10, 2005, Final Safety Evaluation for Addendum 1 to Topical Report WCAP-12610-P-A and CENPD-404-P-A, Optimized ZirloTM, (TAC NO. MB8041).
- 10. WCAP-8745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Function. September 1986.
NRC Safety Evaluation Report dated April 17, 1986, Acceptance for Referencing of Licensing Topical Report WCAP-8745(P)/8746(NP), Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions.