Text

Enclosure - Callaway Cycle 27 Core Operating Limits Report, Revision 0 - August 2023
	ML23291A296
Person / Time
Site:	Callaway
Issue date:	10/18/2023
From:	; Ameren Missouri, Union Electric Co
To:	; Office of Nuclear Reactor Regulation
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ML23291A294	List: ML23291A296; ULNRC-06842, Cycle 27 Core Operating Limits Report (Letter);
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	ULNRC-06$42
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Enclosure to ULNRC-06$42 Callaway Cycle 27 Core Operating Limits Report Revision 0 August 2023 (25 Pages, Not Including This Page)

Callaway Cycle 27 Core Operating Limits Report August 2023

Edjted by:

Sean F. Miller

Approved:

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

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

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 2.1.1 3.3.1 3.4.1 SHUTDOWN MARGIN ($DM)

Moderator Temperature Coefficient (MTC)

Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor (FQ(z))

Nuclear Enthalpy Rise Hot Channel Factor FHN AXIAL FLUX DIFFERENCE (AFD)

Reactor Core SLs Reactor Trip System (RTS) Instrumentation RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 27 has been prepared in accordance with the requirements ofTechnical Specification 5.6.5.

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

2

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

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 (5DM)

(Specifications 3.1.1, 3.1.4, 3.1.5, 3.1.6, and3.1.8) 2.1.1 The Shutdown Margin in MODES 1-4 shall be greater than or equal to 1.3% Aldk.

2. 1.2 The Shutdown Margin prior to blocking Safety Injection below P-i 1 in MODES 3 and 4 shall be greater than 0% Ak/k as calculated at 200°F.

2. 1.3 The Shutdown Margin in MODE 5 shall be greater than or equal to 1.0% Ak/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 pcml°F.

This limit shall be referred to as the lower limit.

2.2.2 The MTC 300 ppm surveillance limit is -40.4 pcml°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).

-3

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

r14 U

rxl I-I U

H g:tl0U ru icll ru 14 0

fri 0

PERCENT OF RATED THERMAL POWER Figure 1 Callaway Cycle 27 Moderator Ternperature Coefficient Versus Power Level 4

0 10 20 30 40 50 60 70 80 90 100

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

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 1 15 steps when not frilly inserted and not fully withdrawn. Overlap is defined as the fully withdrawn (ARO) position minus this 1 15 step tip-to-tip separation.

5

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

200 175 150

&l 125 H

U) 100 75 Figure 2 Callaway Cycle 27 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 6

- - This record was final approved on 8/2312023 3:13:34 PM. (This statement was added by the PRIME system upon its validation) 50 25 PERCENT OF RATED THERMIL POWER 100

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

(Specification 3.2.1) r RTP fQ FQ(Z)

-

K(Z) for P > 0.5 P

1 RTP fQ FQ(Z)

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

P

=

RATED THERMAL POWER 2.5.1 fQRTP250 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.la and A. lb.**

The W(z) functions shown in Table A.la are only applicable to Figure 4a. The W(z) functions shown in Table A.lb 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. 1 a 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. la W(z) values.

The W(z) values have been determined for several bumups up to 19000 MWD/MTU in Cycle 27. This permits determination of W(z) at any cycle burnup up to 19000 MWD/MTU through the use of three point interpolation. For cycle bumups greater than 19000 MWD/MTU, use of 19000 MWD/MTU W(z) values without extrapolation is conservative. The W(z) values were determined assuming Cycle 27 operates with RAOC strategy.

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

7

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

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 1 50 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.la or A.lb should be used.

W(z) values should be adjusted by the factor lIP, when P is > 0.5. When P is 0.5, the W(z) values should be adjusted by the factor 1/(O.5), or 2.0. This is consistent with the adjustment in the FQ(Z) limit at part power conditions.

Table A.3 shows the bumup dependent FQ penalty factors for Cycle 27 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 ofTable A.3.

- Refer to Table A.2 for W(z) values for evaluating the startup testing flux map at 1 50 MWD/MTU bumup 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 15 defined by PDMS when OPERABLE)

Ue Engineering uncertainty factor 1.03 8

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

Table Ala W(z) versus Core Height for +lO%/-15% RAOC Band (Top and Bottom 8% Excluded)

Height 150 3000 6000 10000 14000 19000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 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 1.4905 1.5586 1.4645 1.3456 1.3088 1.2981 1.17 1.4764 1.5413 1.4492 1.3345 1.2998 1.2890 1.34 1.4621 1.5229 1.4328 1.3228 1.2905 1.2800 1.51 1.4465 1.5027 1.4148 1.3099 1.2803 1.2703 1.68 1.4291 1.4805 1.3950 1.2957 1.2690 1.2597 1.84 1.4098 1.4560 1.3734 1.2810 1.2570 1.2486 2.01 1.3894 1.4301 1.3508 1.2666 1.2445 1.2375 2.18 1.3685 1.4039 1.3278 1.2516 1.2317 1.2259 2.35 1.3473 1.3770 1.3042 1.2358 1.2175 1.2126 2.52 1.3262 1.3506 1.2813 1.2200 1.2033 1.1992 2.68 1.3053 1.3243 1.2571 1.2047 1.1895 1.1856 2.85 1.2826 1.2973 1.2399 1.1885 1.1754 1.1750 3.02 1.2651 1.2740 1.2284 1.1763 1.1629 1.1680 3.19 1.2575 1.2585 1.2168 1.1711 1.1575 1.1644 3.35 1.2515 1.2468 1.2110 1.1663 1.1586 1.1651 3.52 1.2456 1.2345 1.2066 1.1613 1.1603 1.1693 3.69 1.2390 1.2246 1.2017 1.1567 1.1620 1.1737 3.86 1.2318 1.2171 1.1963 1.1545 1.1637 1.1779 4.02 1.2244 1.2096 1.1904 1.1525 1.1641 1.1804 4.19 1.2167 1.2015 1.1839 1.1495 1.1636 1.1823 4.36 1.2086 1.1932 1.1772 1.1464 1.1628 1.1849 4.53 1.1996 1.1842 1.1699 1.1429 1.1615 1.1866 4.70 1.1902 1.1747 1.1621 1.1391 1.1596 1.1877 4.86 1.1803 1.1648 1.1539 1.1348 1.1572 1.1877 5.03 1.1700 1.1553 1.1453 1.1302 1.1540 1.1872 5.20 1.1592 1.1460 1.1364 1.1251 1.1519 1.1873 5.37 1.1482 1.1365 1.1272 1.1199 1.1491 1.1871 5.53 1.1351 1.1258 1.1166 1.1134 1.1478 1.1884 5.70 1.1278 1.1163 1.1082 1.1099 1.1482 1.1922 5.87 1.1289 1.1134 1.1077 1.1129 1.1513 1.1954 6.04 1.1312 1.1151 1.1102 1.1233 1.1622 1.2040 6.20 1.1334 1.1160 1.1119 1.1328 1.1717 1.2117 6.37 1.1382 1.1159 1.1160 1.1417 1.1802 1.2185 6.54 1.1429 1.1188 1.1213 1.1506 1.1892 1.2250 6.71 1.1482 1.1234 1.1269 1.1593 1.1966 1.2303 6.87 1.1526 1.1277 1.1328 1.1685 1.2030 1.2362 7.04 1.1557 1.1308 1.1396 1.1784 1.2080 1.2409 9

- - This record was final approved on 8/23/2023, 3:1 3:34 PM. (This statement was added by the PRIME system upon its validation)

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

Height 150 3000 6000 10000 14000 19000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 7.21 1.1579 1.1333 1.1462 1.1876 1.2122 1.2448 7.38 1.1594 1.1352 1.1523 1.1962 1.2151 1.2473 7.55 1.1589 1.1351 1.1563 1.2019 1.2146 1.2459 7.71 1.1577 1.1344 1.1596 1.2066 1.2129 1.2431 7.88 1.1551 1.1323 1.1623 1.2105 1.2098 1.2395 8.05 1.1506 1.1313 1.1637 1.2130 1.2057 1.2345 8.22 1.1450 1.1321 1.1643 1.2146 1.1988 1.2282 8.38 1.1374 1.1355 1.1639 1.2146 1.1999 1.2203 8.55 1.1306 1.1413 1.1624 1.2133 1.1967 1.2125 8.72 1.1212 1.1442 1.1599 1.2107 1.2009 1.2043 8.89 1.1109 1.1468 1.1648 1.2118 1.2129 1.2100 9.05 1.1121 1.1457 1.1693 1.2111 1.2220 1.2166 9.22 1.1161 1.1512 1.1726 1.2186 1.2326 1.2246 9.39 1.1203 1.1647 1.1798 1.2314 1.2451 1.2316 9.56 1.1251 1.1760 1.1967 1.2388 1.2521 1.2361 9.73 1.1285 1.1793 1.2191 1.2459 1.2575 1.2409 9.89 1.1317 1.1732 1.2430 1.2532 1.2618 1.2416 10.06 1.1333 1.1933 1.2656 1.2549 1.2639 1.2394 10.23 1.1533 1.2296 1.2849 1.2664 1.2728 1.2432 10.40 1.1768 1.2511 1.3042 1.2836 1.2792 1.2586 10.56 1.2015 1.2666 1.3215 1.3012 1.2826 1.2700 10.73 1.2338 1.2871 1.3386 1.3178 1.2849 1.2762 10.90 1.2541 1.3038 1.3515 1.3282 1.2852 1.2817 11.07 1.2584 1.3213 1.3613 1.3352 1.2857 1.2801 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 10

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

Table Aib W(z) versus Core Height for +$%/-12% RAOC Band (Top and Bottom 8% Excluded)

Height 150 3000 6000 10000 14000 19000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 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 1.4456 1.4852 1.4042 1.3028 1.2377 1.2508 1.17 1.4324 1.4695 1.3901 1.2923 1.2301 1.2426 1.34 1.4190 1.4528 1.3751 1.2813 1.2224 1.2346 1.51 1.4044 1.4346 1.3586 1.2692 1.2140 1.2261 1.68 1.3880 1.4144 1.3403 1.2558 1.2047 1.2169 1.84 1.3698 1.3923 1.3205 1.2414 1.1948 1.2075 2.01 1.3505 1.3690 1.2998 1.2264 1.1847 1.1983 2.18 1.3308 1.3454 1.2788 1.2112 1.1743 1.1887 2.35 1.3107 1.3213 1.2572 1.1950 1.1628 1.1777 2.52 1.2908 1.2975 1.2363 1.1791 1.1512 1.1666 2.68 1.2709 1.2743 1.2143 1.1638 1.1403 1.1561 2.85 1.2501 1.2493 1.1988 1.1479 1.1289 1.1462 3.02 1.2316 1.2305 1.1909 1.1380 1.1249 1.1358 3.19 1.2197 1.2230 1.1843 1.1366 1.1277 1.1307 3.35 1.2124 1.2163 1.1789 1.1336 1.1302 1.1356 3.52 1.2042 1.2095 1.1730 1.1306 1.1330 1.1435 3.69 1.1985 1.2042 1.1666 1.1283 1.1358 1.1517 3.86 1.1941 1.1990 1.1602 1.1282 1.1385 1.1598 4.02 1.1894 1.1930 1.1555 1.1281 1.1409 1.1664 4.19 1.1844 1.1868 1.1519 1.1272 1.1429 1.1715 4.36 1.1790 1.1802 1.1477 1.1261 1.1445 1.1761 4.53 1.1730 1.1730 1.1432 1.1248 1.1458 1.1801 4.70 1.1665 1.1653 1.1383 1.1233 1.1465 1.1834 4.86 1.1596 1.1573 1.1331 1.1214 1.1467 1.1857 5.03 1.1524 1.1493 1.1275 1.1191 1.1460 1.1870 5.20 1.1449 1.1418 1.1217 1.1165 1.1463 1.1875 5.37 1.1362 1.1341 1.1153 1.1138 1.1466 1.1870 5.53 1.1293 1.1251 1.1090 1.1099 1.1469 1.1882 5.70 1.1275 1.1175 1.1065 1.1077 1.1476 1.1919 5.87 1.1274 1.1156 1.1078 1.1127 1.1508 1.1951 6.04 1.1277 1.1170 1.1101 1.1231 1.1617 1.2038 6.20 1.1288 1.1174 1.1118 1.1326 1.1712 1.2115 6.37 1.1314 1.1170 1.1159 1.1415 1.1798 1.2183 6.54 1.1342 1.1168 1.1213 1.1505 1.1889 1.2249 6.71 1.1374 1.1213 1.1270 1.1592 1.1964 1.2295 6.87 1.1399 1.1251 1.1323 1.1670 1.2029 1.2327 7.04 1.1410 1.1279 1.1365 1.1737 1.2081 1.2345 11

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

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

Height 150 3000 6000 10000 14000 19000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 7.21 1.1413 1.1300 1.1401 1.1798 1.2125 1.2352 7.38 1.1409 1.1315 1.1430 1.1850 1.2156 1.2344 7.55 1.1387 1.1310 1.1438 1.1872 1.2152 1.2296 7.71 1.1359 1.1300 1.1438 1.1885 1.2137 1.2235 7.88 1.1317 1.1279 1.1427 1.1884 1.2108 1.2161 8.05 1.1264 1.1241 1.1405 1.1873 1.2067 1.2076 8.22 1.1217 1.1205 1.1363 1.1840 1.1999 1.1963 8.38 1.1166 1.1200 1.1401 1.1881 1.2012 1.1930 8.55 1.1111 1.1178 1.1392 1.1869 1.1976 1.1887 8.72 1.1056 1.1159 1.1404 1.1890 1.1981 1.1948 8.89 1.0995 1.1164 1.1486 1.1947 1.2052 1.2024 9.05 1.0954 1.1172 1.1597 1.2056 1.2135 1.2088 9.22 1.0826 1.1271 1.1705 1.2185 1.2231 1.2160 9.39 1.0876 1.1405 1.1800 1.2306 1.2317 1.2191 9.56 1.0914 1.1487 1.1875 1.2384 1.2380 1.2229 9.73 1.0981 1.1549 1.1959 1.2456 1.2407 1.2256 9.89 1.1043 1.1583 1.2060 1.2530 1.2412 1.2219 10.06 1.1109 1.1852 1.2121 1.2552 1.2431 1.2237 10.23 1.1163 1.2210 1.2171 1.2670 1.2450 1.2274 10.40 1.1349 1.2423 1.2259 1.2844 1.2449 1.2409 10.56 1.1625 1.2568 1.2414 1.3022 1.2433 1.2505 10.73 1.1972 1.2757 1.2591 1.3190 1.2413 1.2546 10.90 1.2203 1.2915 1.2717 1.3297 1.2403 1.2585 11.07 1.2269 1.3083 1.2816 1.3369 1.2424 1.2565 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 12

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

Table A.2 W(z) versus Core Height for Partial Power Operation (45% Power, 1 50 MWD/MTU, D-bank at 1 85 steps)

(Top and Bottom 8% Excluded)

- The W(z) S are not increased by the nominalpower ratio. In order to be applicable, the W(z) must be adjustedfor relativepowerper Section 2.5.3 at the time ofthe 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 1.7353 1.17 1.7080 1.34 1.6806 1.51 1.6509 1.68 1.6194 1.84 1.5864 2.01 1.5513 2.18 1.5167 2.35 1.4849 2.52 1.4528 2.68 1.4203 2.85 1.3864 3.02 1.3587 3.19 1.3412 3.35 1.3245 3.52 1.3080 3.69 1.2913 3.86 1.2741 4.02 1.2573 4.19 1.2415 4.36 1.2251 4.53 1.2079 4.70 1.1902 4.86 1.1722 5.03 1.1538 5.20 1.1345 5.37 1.1157 5.53 1.0948 5.70 1.0795 5.87 1.0737 6.04 1.0697 13

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

Table A.2 W(z) versus Core Height for Partial Power Operation (45% Power, 1 50 MWD/MTU, D-bank at I 85 steps)

(Top and Bottom 8% Excluded)

- The W(z) are not increased by the nominalpower ratio. In order to be applicable, the W(z) s must be adjustedfor relativepowerper Section 2.5.3 at the time ofthe surveillance Height (feet)

W(z)**

6.20 1.0652 6.37 1.0639 6.54 1.0633 6.71 1.0618 6.87 1.0593 7.04 1.0563 7.21 1.0537 7.38 1.0520 7.55 1.0474 7.71 1.0419 7.88 1.0360 8.05 1.0298 8.22 1.0251 8.38 1.0197 8.55 1.0117 8.72 1.0044 8.89 0.9984 9.05 1.0040 9.22 1.0157 9.39 1.0345 9.56 1.0544 9.73 1.0770 9.89 1.0933 10.06 1.1032 10.23 1.1154 10.40 1.1242 10.56 1.1363 10.73 1.1533 10.90 1.1503 11.07 1.1416 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 14

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

Table A.3 FQ Penalty Factors as a Function of Cycle Burnup Cycle 27 Bumup W(z) Penalty Factor (%)

150 2.00 1004 2.00 1218 2.25 1431 3.94 1645 4.86 1859 4.49 2072 4.19 2286 3.79 2499 3.20 2713 2.53 2926 2.00 Note:

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

for values ofburnup between two ofthose 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.

15

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

1.20 1.10 1.00 0.90 0.80 tz3 c

0.70 rxl H

0.40 0.30 0.20 0.10 0.00 Figure 3 Callaway Cycle 27 K(z) - Normalized FQ(Z) as a Function of Core Height 16

- - This record Was fina approved Ofl 8/23/2023 31334 PM. (ThiS statement was added by the PRIME system upon ts vatidatlofl) 4 5

6 7

0 1

2 3

CORE HEIGHT (FEET) 10 11 12

2.6 Nuclear Enthalpy Rise Hot Channel Factor FAJ-IN (Specification 3.2.2)

FAHN

u :S FIRTP [1 + PFAH(1-P)J THERMAL POWER where:

P

=

RATED THERMAL POWER

f r

RTP_

L.U.I fAR

2.6.2 PF=O.3 2.6.3 The uncertainty, U, to be applied to measured F shall be 1.04 when PDMS is inoperable (Ui 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.

17

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

--ri--ri--r-rrr -

z:::1(-5, 100%)

(+10, 100%)

Z

z UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION H

i-r t

i:t:: : ::

J ::: : :::

HH LHHHHH HHH i-::

i:::::

E

J ::+/-::: :i:z:

50 40 30 20 10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE

(% DELTA-I)

Figure4a Callaway Cycle 27 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +101-15%

18 120 110 100 90 80

-y--

---hi-t ni 0

f:4 ni El ni 0

Elz ni U

ni 1:4 70 60 50 ACCEPTABLE OPERATION 40 (30, 50%)

(+26, 50%)

30--

20 10 0

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

120 110 100 90 80 70 ci Eu f140 F-Izru0 ru 60 50 40 30 20 AXIAL FLUX DIFFERENCE

(% DELTAI)

Figure4b CallawaY Cycle 27 Alternate Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +81-12%

19

- - This record was final approved on 8/23/2023, 3:1 3:34 PM. (This statement was added by the PRIME system UpOfl ts validation)

2.8 Reactor Core SLs (Safety Limit 21.1)

In MODES 1 and 2, the combination ofIHERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits in Figure 5.

I I

÷++/--++/- -+/-+-+/-f +/- +/--*+/--+/-+/--+/-+/-t+/-++-+f-+

I I

-+-f+-++-++-+f+-f+-++-+

Uiiacceprahle 14 f f f f

f t))eiEItjC)fl f f.

+ + +

+ - +

+

+ - + - + + - +

+ - + + + f + - + - + 1- - +

I I

h

-F+/--++/--+/-+/--+/-t

-F-F pj

+/-f+/-++/---F1--+/-

I I

++++-

-++-+++++-

-++-+++f+++-++-+

I I

I h4 *

+

- + + + -

+ + -I-

+ - + - -I- - 4

+

- +

I I

I

+/-+/--++/--+/-+/--+/-t+/-

+/-

÷_+/-__÷__÷_+/-_

I I

I

+++

-++-++-+++++-++-

+-+++

+4+-4+-+

I I

++-+-

-+/-t+/-++/--+-+/-+/--+/-

t I

I I

I

+++

-+++-+-

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I)III,11ISj,1

+f

+

-f+-I-++

I I

1-+-I-+--+-

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I I

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I I

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_-_+_-_+_+_+_+_+_+_.l-_+_+_

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I I

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r-

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+

I I

++++-++-++-+-+-f+

f++

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f-+

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I jc.tci1_cj9 I

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I I

Accepib1e I

I II 5FC-

-++

OI:)el-atioll

+

I I

I f+/-++/-TmTTT

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I I

I 3::

.2 Lh I

(_)[ F.\\E:._)

Figure 5 Callaway Cycle 27 Reactor Core Safety Limits 20

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

Measured RCS AT lag time constant Measured RCS average temperature lead/lag time constants Measured RCS average temperature lag time constant f1(AI)=-O.0280 {18%+(q-qb)}

Value K1 = 1.2260 K2 0.0 191°F K3 0.001 1/psig T<585.3°F Pp = 2235 psig ti : 0 sec t2 0 sec t3 < 4 sec t4 > 27 sec t5 < 4 sec t6 E 2 sec when (qt - q) < - 1 8% RTP when-18%RTP(qt - qb) 10% RTP when (qt - q) > 1 0% RIP Where, qt and qb are percent RIP in the upper and lower halves of the core, respectively, and qt + qb 15 the total THERMAL POWER in percent RIP.

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

Parameter Overtemperature AT reactor trip setpoint Overtemperature z\\T reactor trip setpoint Iavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Nominal Iavg at RIP Nominal RCS operating pressure Measured RCS AT lead/lag time constants 0

0.0224 {(qt

- qb)

- 10%}

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

2. 10 Reactor Trip System (RTS) Instrumentation (Specification 3.3.1)

Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint avg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Nominal Tavg at RTP Measured RCS AT lead/lag time constants Measured RCS AT lag time constant Measured RCS average temperature lag time constant Measured RCS average temperature rate/lag time constant f2(AI) = 0 for all Al.

Value K4 1.1073 K5 0.02/°F for increasing Tavg

= 0/°F for decreasing Tavg K6 = 0.00l5/°F for T > T

=0/°f forT<T T < 585.3°F ti ?: 0 sec t2 E 0 sec t3 < 4 sec t6 2 sec t7 > 10 sec

2. 1 1 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits (Specification 3.4.1)

Parameter Indicated Value

>2195 psig E 590.1°F Pressurizer pressure RCS average temperature 22

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

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:

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 ofConstant Axial Offset Control - fQ Surveillance Technical Specification, February 1994.

NRC Safety Evaluation Report dated November 26, 1993, Acceptance for Referencing of Revised Version ofLicensing 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 198 1 Version ofthe Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987.

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

WCAP-10266-P-A, Addendum 1, Revision 2, The 1981 Version ofthe 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 ofAddendum 1 to WCAP-10266, BASH Power Shape Sensitivity Studies.

WCAP-l0266-P-A, Addendum 2, Revision 2, The 1981 Version ofthe Westinghouse ECCS Evaluation Model Using the BASH Code Addendum 2: BASH Methodology Improvements and Reliability Enhancements, May 1988.

NRC letter dated January 20, 1982, 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 ofthe LOCBART Transient Extension Method into the 1 98 1 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).

23

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

4.

WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core ReportS 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 1 5, 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. M864 16).

5.

WCAP-1 1397-P-A, Revised Thermal Design Procedure, April 1989.

NRC Safety Evaluation Report dated January 1 7, 1989, Acceptance for Referencing of Licensing Topical Report WCAP-11397, Revised Thermal Design Procedure.

6.

WCAP-14565-P-A, VIPRE-Ol 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-Ol Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal/Hydraulic Safety Analysis (TAC No. M98666).

7.

WCAP-1085 1-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 AT and Thermal Overtemperature AT Trip functions, September 1986.

NRC Safety Evaluation Report dated April 1 7, 1986, Acceptance for Referencing of Licensing Topical Report WCAP-8745(P)/8746(NP), Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions.

24

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

10.

WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, September 1986.

NRC letter dated June 23, 1 986, Acceptance for Referencing ofTopical Report WCAP 10965-P and WCAP 10966-NP.

11.

WCAP-10965-P-A, Addendum 2-A, Revision 0, Qualification ofthe 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. ME 1420).

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 ofLicensing 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 ofABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications, April 2008.

14.

WCAP-16045-P-A, Revision 0, Qualification ofthe Two-Dimensional Transport Code PARAGON, August 2004.

NRC letter dated March 1 8, 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 ofthe 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) 25

- - This record was final approved on 8/23/2023, 3:13:34 PM. (This statement was added by the PRIME system upon its validation)

ML23291A296

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