ULNRC-06750, Cycle 26 Core Operating Limits Report

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Cycle 26 Core Operating Limits Report
ML22164A880
Person / Time
Site: Callaway Ameren icon.png
Issue date: 06/13/2022
From:
Ameren Missouri, Union Electric Co
To:
Office of Nuclear Reactor Regulation
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References
ULNRC-06750
Download: ML22164A880 (25)
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1 Callaway Cycle 26 Core Operating Limits Report March 2022

  • Edited by:

Sean F. Miller

  • Approved:

David J. Wotus, Manager Nuclear Design C Core Engineering & Software Development

  • Electronically Approved Records Are Authenticated in the Electronic Document Management System Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066

©2022 Westinghouse Electric Company LLC All Rights Reserved

======================================================================
      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 1 of 25

2 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 26 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Core Operating Limits affecting the following Technical Specifications are included in this report.

3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8 SHUTDOWN MARGIN (SDM) 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (FQ(z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FHN 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 2.1.1 Reactor Core SLs 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 2 of 25

3 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections which follow. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN (SDM)

(Specifications 3.1.1, 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.1.1 The Shutdown Margin in MODES 1-4 shall be greater than or equal to 1.3% k/k.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-11 in MODES 3 and 4 shall be greater than 0% k/k as calculated at 200°F.

2.1.3 The Shutdown Margin in MODE 5 shall be greater than or equal to 1.0% k/k.

2.2 Moderator Temperature Coefficient (MTC)

(Specification 3.1.3) 2.2.1 The Moderator Temperature Coefficient shall be less positive than the limits shown in Figure 1. These limits shall be referred to as the upper limit. Figure 1 cannot be revised under 10 CFR 50.59 due to Technical Specification Figure 3.1.3-1.

The Moderator Temperature Coefficient shall be less negative than -47.9 pcm/F.

This limit shall be referred to as the lower limit.

2.2.2 The MTC 300 ppm surveillance limit is -40.4 pcm/F (all rods withdrawn, Rated Thermal Power condition).

2.2.3 The MTC 60 ppm surveillance limit is -45.5 pcm/F (all rods withdrawn, Rated Thermal Power condition).

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 3 of 25

4 Figure 1 Callaway Cycle 26 Moderator Temperature Coefficient Versus Power Level PERCENT OF RATED THERMAL POWER MODERATOR TEMPERATURE COEFFICIENT (PCM/

0 F)

(70%, 5.0)

UNACCEPTABLE OPERATION ACCEPTABLE OPERATION 0

10 20 30 40 50 60 70 80 90 100 0

1 2

3 4

5 6

7

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 4 of 25

5 2.3 Shutdown Bank Insertion Limits (Specification 3.1.5)

The shutdown banks shall be withdrawn to at least 222 steps.

2.4 Control Bank Insertion Limits (Specification 3.1.6) 2.4.1 Control Bank insertion limits are specified by Figure 2.

2.4.2 Control Bank withdrawal sequence is A-B-C-D. The insertion sequence is the reverse of the withdrawal sequence.

2.4.3 The difference between each sequential Control Bank position is 115 steps when not fully inserted and not fully withdrawn. Overlap is defined as the fully withdrawn (ARO) position minus this 115 step tip-to-tip separation.

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 5 of 25

6 Figure 2 Callaway Cycle 26 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 0

25 50 75 100 125 150 175 200 0

10 20 30 40 50 60 70 80 90 100 ROD BANK POSITION (STEPS WITHDRAWN)

PERCENT OF RATED THERMAL POWER BANK B (26.4, 222)

(0, 46)

BANK C BANK D (0, 161)

(76.3, 222)

(100, 161)

(30.2, 0)

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 6 of 25

7 2.5 Heat Flux Hot Channel Factor (FQ(z))

(Specification 3.2.1)

FQRTP FQ(Z) < ___________

  • K(Z) for P > 0.5 P

FQRTP FQ(Z) < _____________

  • K(Z) for P < 0.5 0.5 THERMAL POWER where:

P =

RATED THERMAL POWER 2.5.1 FQRTP = 2.50.

2.5.2 K(Z) is provided in Figure 3.

2.5.3 The W(z) functions that are to be used in Technical Specification 3.2.1 and Surveillance Requirement 3.2.1.2 for determining FQW(z) are shown in Table A.1a and A.1b.** The W(z) functions shown in Table A.1a are only applicable to Figure 4a. The W(z) functions shown in Table A.1b are only applicable to Figure 4b.

The data in these tables should be used independently; cross interpolation or extrapolation between W(z) sets is prohibited.

The Axial Flux Difference (AFD) Band in Figure 4b is more restrictive than the AFD Band in Figure 4a. Prior to switching from Figure 4b to Figure 4a, FQW(z) must be confirmed to meet Technical Specification requirements by one of the following methods:

1. Confirm FQW(z) meets the Technical Specification Limit with the Table A.1a W(z) values for the most recent surveillance performed.
2. Perform a new surveillance and confirm FQW(z) meets the Technical Specification Limit with the Table A.1a W(z) values.

The W(z) values have been determined for several burnups up to 18000 MWD/MTU in Cycle 26. This permits determination of W(z) at any cycle burnup up to 18000 MWD/MTU through the use of three point interpolation. For cycle burnups greater than 18000 MWD/MTU, use of 18000 MWD/MTU W(z) values without extrapolation is conservative. The W(z) values were determined assuming Cycle 26 operates with RAOC strategy.

The W(z) values are provided for 73 axial points within the core height boundaries of 0 and 12.07 feet (hot core height) at equally spaced intervals.

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 7 of 25

8 The W(z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is performed from beginning of cycle to 150 MWD/MTU and at 45% +/- 5% RTP, the W(z) values listed in Table A.2 should be used. When a part power surveillance is performed after 150 MWD/MTU, or at a power level other than the level specified above, the HFP W(z) values in Table A.1a or A.1b should be used.

W(z) values should be adjusted by the factor 1/P, when P is > 0.5. When P is 0.5, the W(z) values should be adjusted by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the FQ(z) limit at part power conditions.

Table A.3 shows the burnup dependent FQ penalty factors for Cycle 26 that are applicable to both Figures 4a and 4b. These values shall be used to increase FQW(z) when required by Technical Specification Surveillance Requirement 3.2.1.2. A 2%

penalty factor should be used at all cycle burnups that are outside the range of Table A.3.

    • Refer to Table A.2 for W(z) values for evaluating the startup testing flux map at 150 MWD/MTU burnup and 45% +/- 5% RTP.

2.5.4 The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by the following UFQ = Uqu

  • Ue where:

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE)

Ue = Engineering uncertainty factor = 1.03

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 8 of 25

9 Table A.1a W(z) versus Core Height for +10%/-15% RAOC Band (Top and Bottom 8% Excluded)

Height (feet) 150 MWD/MTU 3000 MWD/MTU 6000 MWD/MTU 10000 MWD/MTU 14000 MWD/MTU 18000 MWD/MTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.01 1.3027 1.3790 1.3950 1.3712 1.3614 1.3402 1.17 1.2924 1.3655 1.3816 1.3601 1.3516 1.3302 1.34 1.2823 1.3514 1.3675 1.3485 1.3415 1.3203 1.51 1.2714 1.3361 1.3519 1.3357 1.3305 1.3097 1.68 1.2592 1.3192 1.3348 1.3216 1.3183 1.2981 1.84 1.2458 1.3009 1.3163 1.3064 1.3052 1.2860 2.01 1.2318 1.2818 1.2969 1.2907 1.2916 1.2736 2.18 1.2176 1.2626 1.2772 1.2745 1.2775 1.2606 2.35 1.2029 1.2430 1.2569 1.2575 1.2621 1.2460 2.52 1.1917 1.2240 1.2370 1.2408 1.2465 1.2313 2.68 1.1847 1.2045 1.2175 1.2237 1.2312 1.2167 2.85 1.1786 1.1887 1.1977 1.2097 1.2154 1.2024 3.02 1.1723 1.1798 1.1822 1.2002 1.2013 1.1876 3.19 1.1670 1.1742 1.1750 1.1935 1.1927 1.1792 3.35 1.1621 1.1679 1.1719 1.1888 1.1899 1.1808 3.52 1.1567 1.1637 1.1690 1.1837 1.1893 1.1837 3.69 1.1514 1.1609 1.1659 1.1780 1.1891 1.1865 3.86 1.1459 1.1580 1.1625 1.1722 1.1886 1.1892 4.02 1.1422 1.1544 1.1584 1.1677 1.1868 1.1902 4.19 1.1400 1.1505 1.1538 1.1638 1.1841 1.1898 4.36 1.1374 1.1462 1.1490 1.1592 1.1808 1.1896 4.53 1.1343 1.1415 1.1438 1.1543 1.1770 1.1900 4.70 1.1308 1.1363 1.1381 1.1490 1.1726 1.1895 4.86 1.1269 1.1307 1.1321 1.1432 1.1674 1.1882 5.03 1.1227 1.1248 1.1258 1.1369 1.1615 1.1856 5.20 1.1182 1.1184 1.1190 1.1303 1.1562 1.1841 5.37 1.1134 1.1120 1.1122 1.1230 1.1511 1.1823 5.53 1.1085 1.1039 1.1039 1.1162 1.1461 1.1814 5.70 1.1073 1.0998 1.0990 1.1092 1.1438 1.1822 5.87 1.1135 1.1016 1.0998 1.1068 1.1439 1.1863 6.04 1.1229 1.1043 1.1035 1.1170 1.1473 1.1937 6.20 1.1335 1.1124 1.1125 1.1257 1.1550 1.2009 6.37 1.1432 1.1207 1.1221 1.1338 1.1623 1.2071 6.54 1.1531 1.1287 1.1314 1.1420 1.1699 1.2130 6.71 1.1631 1.1370 1.1409 1.1499 1.1763 1.2179 6.87 1.1723 1.1456 1.1498 1.1570 1.1817 1.2231 7.04 1.1802 1.1551 1.1577 1.1630 1.1860 1.2275

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 9 of 25

10 Table A.1a W(z) versus Core Height for +10%/-15% RAOC Band (Top and Bottom 8% Excluded)

Height (feet) 150 MWD/MTU 3000 MWD/MTU 6000 MWD/MTU 10000 MWD/MTU 14000 MWD/MTU 18000 MWD/MTU 7.21 1.1872 1.1641 1.1650 1.1684 1.1895 1.2311 7.38 1.1936 1.1727 1.1717 1.1730 1.1919 1.2333 7.55 1.1977 1.1792 1.1758 1.1748 1.1911 1.2318 7.71 1.2009 1.1850 1.1791 1.1757 1.1892 1.2291 7.88 1.2026 1.1900 1.1813 1.1755 1.1862 1.2255 8.05 1.2028 1.1935 1.1823 1.1743 1.1823 1.2206 8.22 1.2009 1.1964 1.1816 1.1712 1.1757 1.2145 8.38 1.2071 1.1979 1.1869 1.1748 1.1775 1.2067 8.55 1.2078 1.1986 1.1869 1.1736 1.1746 1.1975 8.72 1.2102 1.1977 1.1880 1.1742 1.1786 1.1887 8.89 1.2150 1.2030 1.1924 1.1809 1.1912 1.1999 9.05 1.2280 1.2170 1.2062 1.1911 1.2025 1.2114 9.22 1.2395 1.2323 1.2190 1.2011 1.2127 1.2196 9.39 1.2487 1.2490 1.2294 1.2097 1.2221 1.2265 9.56 1.2565 1.2664 1.2390 1.2154 1.2276 1.2312 9.73 1.2670 1.2783 1.2534 1.2236 1.2331 1.2375 9.89 1.2814 1.2813 1.2733 1.2453 1.2380 1.2437 10.06 1.2814 1.2925 1.2780 1.2641 1.2359 1.2427 10.23 1.2801 1.3159 1.2787 1.2779 1.2338 1.2533 10.40 1.2879 1.3393 1.2852 1.2953 1.2323 1.2648 10.56 1.2978 1.3555 1.2967 1.3121 1.2322 1.2719 10.73 1.3066 1.3732 1.3161 1.3265 1.2334 1.2762 10.90 1.3141 1.3913 1.3298 1.3363 1.2348 1.2795 11.07 1.3199 1.4031 1.3339 1.3421 1.2356 1.2813 11.23 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.57 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.74 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.90 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 12.07 (top) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

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11 Table A.1b W(z) versus Core Height for +8%/-12% RAOC Band (Top and Bottom 8% Excluded)

Height (feet) 150 MWD/MTU 3000 MWD/MTU 6000 MWD/MTU 10000 MWD/MTU 14000 MWD/MTU 18000 MWD/MTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.01 1.2432 1.3123 1.3369 1.3046 1.2939 1.2700 1.17 1.2342 1.3006 1.3246 1.2949 1.2852 1.2613 1.34 1.2254 1.2884 1.3115 1.2848 1.2764 1.2526 1.51 1.2160 1.2752 1.2973 1.2737 1.2667 1.2433 1.68 1.2053 1.2606 1.2815 1.2614 1.2559 1.2331 1.84 1.1937 1.2448 1.2645 1.2483 1.2445 1.2226 2.01 1.1816 1.2283 1.2468 1.2346 1.2328 1.2120 2.18 1.1693 1.2118 1.2288 1.2208 1.2206 1.2008 2.35 1.1565 1.1949 1.2103 1.2074 1.2071 1.1881 2.52 1.1506 1.1784 1.1923 1.1953 1.1936 1.1759 2.68 1.1465 1.1631 1.1743 1.1838 1.1811 1.1655 2.85 1.1417 1.1501 1.1580 1.1719 1.1714 1.1551 3.02 1.1376 1.1411 1.1468 1.1620 1.1650 1.1479 3.19 1.1346 1.1363 1.1419 1.1569 1.1614 1.1481 3.35 1.1316 1.1332 1.1401 1.1545 1.1604 1.1522 3.52 1.1282 1.1296 1.1377 1.1515 1.1588 1.1561 3.69 1.1254 1.1256 1.1351 1.1481 1.1591 1.1606 3.86 1.1223 1.1214 1.1322 1.1454 1.1610 1.1670 4.02 1.1199 1.1163 1.1286 1.1437 1.1621 1.1724 4.19 1.1189 1.1129 1.1244 1.1421 1.1619 1.1762 4.36 1.1183 1.1118 1.1200 1.1401 1.1614 1.1795 4.53 1.1172 1.1099 1.1155 1.1377 1.1603 1.1822 4.70 1.1158 1.1079 1.1117 1.1350 1.1587 1.1841 4.86 1.1141 1.1056 1.1083 1.1318 1.1565 1.1851 5.03 1.1119 1.1032 1.1050 1.1282 1.1534 1.1850 5.20 1.1107 1.1003 1.1012 1.1242 1.1506 1.1842 5.37 1.1092 1.0983 1.0982 1.1198 1.1485 1.1821 5.53 1.1089 1.0982 1.0972 1.1152 1.1456 1.1812 5.70 1.1103 1.0995 1.0975 1.1091 1.1434 1.1820 5.87 1.1149 1.1014 1.0996 1.1066 1.1435 1.1861 6.04 1.1227 1.1042 1.1033 1.1168 1.1469 1.1935 6.20 1.1334 1.1124 1.1124 1.1255 1.1548 1.2007 6.37 1.1432 1.1207 1.1221 1.1337 1.1621 1.2069 6.54 1.1531 1.1287 1.1313 1.1413 1.1698 1.2130 6.71 1.1632 1.1372 1.1396 1.1479 1.1762 1.2172 6.87 1.1725 1.1451 1.1471 1.1535 1.1817 1.2202 7.04 1.1804 1.1518 1.1536 1.1581 1.1861 1.2218

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 11 of 25

12 Table A.1b W(z) versus Core Height for +8%/-12% RAOC Band (Top and Bottom 8% Excluded)

Height (feet) 150 MWD/MTU 3000 MWD/MTU 6000 MWD/MTU 10000 MWD/MTU 14000 MWD/MTU 18000 MWD/MTU 7.21 1.1876 1.1579 1.1593 1.1620 1.1897 1.2223 7.38 1.1940 1.1634 1.1642 1.1648 1.1922 1.2215 7.55 1.1981 1.1668 1.1666 1.1649 1.1915 1.2168 7.71 1.2014 1.1693 1.1683 1.1654 1.1897 1.2109 7.88 1.2031 1.1706 1.1682 1.1667 1.1868 1.2038 8.05 1.2033 1.1708 1.1717 1.1672 1.1829 1.1956 8.22 1.2015 1.1691 1.1762 1.1667 1.1764 1.1847 8.38 1.2076 1.1750 1.1778 1.1664 1.1783 1.1818 8.55 1.2084 1.1784 1.1794 1.1687 1.1751 1.1764 8.72 1.2108 1.1844 1.1800 1.1701 1.1764 1.1846 8.89 1.2133 1.1863 1.1812 1.1734 1.1874 1.1955 9.05 1.2216 1.2002 1.1932 1.1831 1.1985 1.2071 9.22 1.2290 1.2155 1.2020 1.1914 1.2064 1.2136 9.39 1.2338 1.2288 1.2062 1.1962 1.2111 1.2157 9.56 1.2407 1.2399 1.2125 1.2009 1.2155 1.2195 9.73 1.2494 1.2460 1.2230 1.2078 1.2185 1.2234 9.89 1.2605 1.2408 1.2373 1.2188 1.2194 1.2251 10.06 1.2626 1.2472 1.2447 1.2235 1.2193 1.2262 10.23 1.2624 1.2570 1.2569 1.2255 1.2185 1.2268 10.40 1.2704 1.2660 1.2748 1.2321 1.2184 1.2274 10.56 1.2807 1.2708 1.2953 1.2395 1.2185 1.2257 10.73 1.2969 1.2763 1.3175 1.2458 1.2242 1.2220 10.90 1.3116 1.2877 1.3306 1.2491 1.2315 1.2193 11.07 1.3190 1.2988 1.3351 1.2510 1.2353 1.2184 11.23 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.57 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.74 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.90 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 12.07 (top) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 12 of 25

13 Table A.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWD/MTU, D-bank at 185 steps)

(Top and Bottom 8% Excluded)

    • The W(z)s are not increased by the nominal power ratio. In order to be applicable, the W(z)s must be adjusted for relative power per Section 2.5.3 at the time of the surveillance Height (feet)

W(z)**

0.00 (bottom) 1.0000 0.17 1.0000 0.34 1.0000 0.50 1.0000 0.67 1.0000 0.84 1.0000 1.01 1.4772 1.17 1.4557 1.34 1.4348 1.51 1.4128 1.68 1.3900 1.84 1.3667 2.01 1.3434 2.18 1.3193 2.35 1.2957 2.52 1.2762 2.68 1.2614 2.85 1.2476 3.02 1.2340 3.19 1.2212 3.35 1.2081 3.52 1.1946 3.69 1.1815 3.86 1.1679 4.02 1.1564 4.19 1.1474 4.36 1.1387 4.53 1.1294 4.70 1.1192 4.86 1.1083 5.03 1.0973 5.20 1.0861 5.37 1.0748 5.53 1.0635 5.70 1.0553 5.87 1.0544 6.04 1.0565

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 13 of 25

14 Table A.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWD/MTU, D-bank at 185 steps)

(Top and Bottom 8% Excluded)

    • The W(z)s are not increased by the nominal power ratio. In order to be applicable, the W(z)s must be adjusted for relative power per Section 2.5.3 at the time of the surveillance Height (feet)

W(z)**

6.20 1.0570 6.37 1.0639 6.54 1.0836 6.71 1.0806 6.87 1.0740 7.04 1.0745 7.21 1.0776 7.38 1.0876 7.55 1.0867 7.71 1.0795 7.88 1.0746 8.05 1.0726 8.22 1.0757 8.38 1.0873 8.55 1.0788 8.72 1.0784 8.89 1.0830 9.05 1.0977 9.22 1.1119 9.39 1.1198 9.56 1.1271 9.73 1.1433 9.89 1.1586 10.06 1.1524 10.23 1.1556 10.40 1.1712 10.56 1.1828 10.73 1.1943 10.90 1.2062 11.07 1.2161 11.23 1.0000 11.40 1.0000 11.57 1.0000 11.74 1.0000 11.90 1.0000 12.07 (top) 1.0000

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15 Table A.3 FQ Penalty Factors as a Function of Cycle Burnup Cycle 26 Burnup FQW(z) Penalty Factor (%)

150 2.00 579 2.00 794 2.40 1008 2.14 1223 2.00 Note:

All cycle burnups not in the range of the above table shall use a 2.0% penalty factor for compliance with Surveillance Requirement 3.2.1.2.

For values of burnup between two of those listed in the first column, the greater of the two corresponding penalty factors shall be used for compliance with Surveillance Requirement 3.2.1.2.

      • This record was final approved on 3/4/2022, 6:17:09 AM. (This statement was added by the PRIME system upon its validation) to ULNRC-06750 Page 15 of 25

16 Figure 3 Callaway Cycle 26 K(z) - Normalized FQ(z) as a Function of Core Height (12,.925)

(0, 1.00)

(6, 1.00) 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 0

1 2

3 4

5 6

7 8

9 10 11 12 CORE HEIGHT (FEET)

K(Z) - NORMALIZED FQ(Z)

FQ Elevation (ft.) K(z) 2.50 0.0 1.00 2.50 6.0 1.00 2.31 12.0 0.925

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17 2.6 Nuclear Enthalpy Rise Hot Channel Factor FHN (Specification 3.2.2)

FHN

  • UH < FHRTP [1 + PFH(1-P)]

THERMAL POWER where:

P =

RATED THERMAL POWER 2.6.1 FHRTP = 1.65 2.6.2 PFH = 0.3 2.6.3 The uncertainty, UH, to be applied to measured FH shall be 1.04 when PDMS is inoperable (UH is defined by PDMS when OPERABLE).

2.7 Axial Flux Difference (Specification 3.2.3)

The Axial Flux Difference (AFD) Limits are provided in Figures 4a and 4b.

Prior to switching to the more restrictive AFD band (Figure 4b), it should be confirmed that the plant is within the more restrictive AFD band.

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18 Figure 4a Callaway Cycle 26 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +10/-15%

0 10 20 30 40 50 60 70 80 90 100 110 120

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (% DELTA-I)

PERCENT OF RATED THERMAL POWER ACCEPTABLE OPERATION UNACCEPTABLE OPERATION

(-15, 100%)

UNACCEPTABLE OPERATION

(+10, 100%)

(-30, 50%)

(+26, 50%)

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19 Figure 4b Callaway Cycle 26 Alternate Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +8/-12%

0 10 20 30 40 50 60 70 80 90 100 110 120

-50

-40

-30

-20

-10 0

10 20 30 40 50 PERCENT OF RATED THERMAL POWER AXIAL FLUX DIFFERENCE (% DELTA-I)

ACCEPTABLE OPERATION UNACCEPTABLE OPERATION

(-12, 100%)

UNACCEPTABLE OPERATION

(+8, 100%)

(-27, 50%)

(+24, 50%)

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20 2.8 Reactor Core SLs (Safety Limit 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 5.

Figure 5 Callaway Cycle 26 Reactor Core Safety Limits

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21 2.9 Reactor Trip System (RTS) Instrumentation (Specification 3.3.1)

Parameter.

Value.

Overtemperature T reactor trip setpoint K1 = 1.2260 Overtemperature T reactor trip setpoint Tavg coefficient K2 = 0.019/°F Overtemperature T reactor trip setpoint pressure coefficient K3 = 0.0011/psig Nominal Tavg at RTP T' < 585.3 °F Nominal RCS operating pressure P' = 2235 psig Measured RCS T lead/lag time constants 1 > 0 sec 2 < 0 sec Measured RCS T lag time constant 3 < 4 sec Measured RCS average temperature lead/lag time constants t4 > 27 sec t5 < 4 sec Measured RCS average temperature lag time constant 6 < 2 sec f1() = -0.0280 {18% + (qt - qb)}

when (qt - qb) < -18% RTP 0

when -18% RTP < (qt - qb) < 10% RTP 0.0224 {(qt - qb) - 10%}

when (qt - qb) > 10% 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.

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22 2.10 Reactor Trip System (RTS) Instrumentation (Specification 3.3.1)

Parameter.

Value.

Overpower T reactor trip setpoint K4 = 1.1073 Overpower T reactor trip setpoint Tavg rate/lag coefficient K5 = 0.02/°F for increasing Tavg

= 0/°F for decreasing Tavg Overpower T reactor trip setpoint Tavg heatup coefficient K6 = 0.0015/°F for T > T"

= 0/°F for T < T" Nominal Tavg at RTP T" < 585.3°F Measured RCS T lead/lag time constants 1 > 0 sec 2 < 0 sec Measured RCS T lag time constant 3 < 4 sec Measured RCS average temperature lag time constant 6 < 2 sec Measured RCS average temperature rate/lag time constant 7 > 10 sec f2() = 0 for all I.

2.11 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits (Specification 3.4.1)

Parameter.

Indicated Value Pressurizer pressure

> 2195 psig RCS average temperature

< 590.1 °F

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23 APPENDIX A 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-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.

NRC letter dated May 28, 1985, Acceptance for Referencing of Licensing Topical Report WCAP-9272(P)/9273(NP), Westinghouse Reload Safety Evaluation Methodology.

2.

WCAP-10216-P-A, Revision 1A, Relaxation of Constant Axial Offset Control - FQ Surveillance Technical Specification, February 1994.

NRC Safety Evaluation Report dated November 26, 1993, Acceptance for Referencing of Revised Version of Licensing Topical Report WCAP-10216-P, Rev. 1, Relaxation of Constant Axial Offset Control - FQ Surveillance Technical Specification (TAC No. M88206).

3.

WCAP-10266-P-A, Revision 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987.

NRC letter dated November 13, 1986, Acceptance for Referencing of Licensing Topical Report WCAP-10266 'The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code.

WCAP-10266-P-A, Addendum 1, Revision 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code Addendum 1: Power Shape Sensitivity Studies, December 1987.

NRC letter dated September 15, 1987, Acceptance for Referencing of Addendum 1 to WCAP-10266, BASH Power Shape Sensitivity Studies.

WCAP-10266-P-A, Addendum 2, Revision 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code Addendum 2: BASH Methodology Improvements and Reliability Enhancements, May 1988.

NRC letter dated January 20, 1988, Acceptance for Referencing Topical Report Addendum 2 to WCAP-10266, Revision 2, BASH Methodology Improvements and Reliability Enhancements.

WCAP-10266-P-A, Addendum 3, Revision 0, Incorporation of the LOCBART Transient Extension Method into the 1981 Westinghouse Large Break LOCA Evaluation Model with BASH (BASH-EM), December 2002 (cited as Reference 4.5 in the NRC Safety Evaluation for Callaway License Amendment 168).

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4.

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).

5.

WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.

NRC Safety Evaluation Report dated January 17, 1989, Acceptance for Referencing of Licensing Topical Report WCAP-11397, Revised Thermal Design Procedure.

6.

WCAP-14565-P-A, VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis, October 1999.

NRC letter dated January 19, 1999, Acceptance for Referencing of Licensing Topical Report WCAP-14565, 'VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal/Hydraulic Safety Analysis' (TAC No. M98666).

7.

WCAP-10851-P-A, Improved Fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations, August 1988.

NRC letter dated May 9, 1988, Westinghouse Topical Report WCAP-10851, Improved Fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations.

8.

WCAP-15063-P-A, Revision 1, with Errata, Westinghouse Improved Performance Analysis and Design Model (PAD 4.0), July 2000.

NRC letter dated April 24, 2000, Safety Evaluation Related to Topical Report WCAP-15063, Revision 1, 'Westinghouse Improved Performance Analysis and Design Model (PAD 4.0)' (TAC NO. MA2086).

9.

WCAP-8745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions, 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.

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25

10. 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.

11. WCAP-10965-P-A, Addendum 2-A, Revision 0, Qualification of the New Pin Power Recovery Methodology, September, 2010.

NRC Safety Evaluation Report dated September 10, 2010, FINAL SAFETY EVALUATION FOR WESTINGHOUSE ELECTRIC COMPANY TOPICAL REPORT WCAP-10965-P-A, ADDENDUM 2/WCAP-10966-A, ADDENDUM 2, QUALIFICATION OF THE NEW PIN POWER RECOVERY METHODOLOGY, (TAC NO. ME1420).

12. WCAP-13524-P-A, Revision 1-A, APOLLO: A One Dimensional Neutron Diffusion Theory Program, September 1997.

NRC letter dated June 9, 1997, Acceptance for Referencing of Licensing Topical Reports WCAP-13524 and WCAP-13524, Revision 1, APOLLO - A One-Dimensional Neutron Diffusion Theory Program.

13. WCAP-14565-P-A, Addendum 2-P-A, Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications, April 2008.
14. WCAP-16045-P-A, Revision 0, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.

NRC letter dated March 18, 2004, FINAL SAFETY EVALUATION FOR WESTINGHOUSE TOPICAL REPORT WCAP-16045-P, REVISION 0, QUALIFICATION OF THE TWO-DIMENSIONAL TRANSPORT CODE PARAGON (TAC NO. MB8040)

15. WCAP-16045-P-A, Addendum 1-A, Revision 0, Qualification of the NEXUS Nuclear Data Methodology, August 2007.

NRC letter dated February 23, 2007, FINAL SAFETY EVALUATION FOR WESTINGHOUSE ELECTRIC COMPANY (WESTINGHOUSE) TOPICAL REPORT (TR) WCAP-16045-P, ADDENDUM 1, QUALIFICATION OF THE NEXUS NUCLEAR DATA METHODOLOGY' (TAC NO. MC9606)

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