Text

Cycle 25 - Core Operating Limits Report
	ML20337A189
Person / Time
Site:	Callaway
Issue date:	09/30/2020
From:	; Union Electric Co, Westinghouse
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML20337A187	List: ML20337A188; ULNRC-06616, Cycle 25 - Core Operating Limits Report;
References
	ULNRC-06616
	Download: ML20337A189 (25)
	v • d • e

Callaway Cycle 25 Core Operating Limits Report September 2020

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

I .0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 25 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 (5DM) 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 F 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 2

This record was final approved on 9/17/2020 2:12:09 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, and 3.1.8) 2.1 1. The Shutdown Margin in MODES 1-4 shall be greater than or equal to 1 .3% Ak/k.

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 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).

3 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

7 6 UNACCEPTABLE OPERATION -

C-)

(70%, 5.0) ru I-I h

C-)

I-I rz 4

nj ru 0

C) 4 nil El ri nil 3 El 0

El :::::: ::::: ACCEPTABLE OPERATION - - -

nil 0 2 1

0 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 1 Callaway Cycle 25 Moderator Temperature Coefficient Versus Power Level 4

This record was final approved on 9/17/2020 2:12:09 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 ofthe withdrawal sequence.

2.4.3 The difference between each sequential Control Bank position is 1 15 steps when not fully 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 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

175 150 I(

L1d I

)q 1 (] )I BANKB

z::

I( 1 )161) I IN13 Ic 125 4

100 --- - --- --- --- -i,- ---

75 I BANKD

-- --- --- --- --- r-- ---F++--

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

0:E 5 --- --- --- -- --- --4-fl---

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25

---+1--- --- --- --- ---+---

: :rii: : : : : : : : : : : : : : : : : : : : :LIJ: : : :

(30.2, 0) 0 LLJL 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 25 Rod Bank Insertion Limits Versus Rated Thermal Power Four Loop Operation -

6 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

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

(Specification 3.2.1)

RTP FQ FQ(Z) :S K(Z) for P > 0.5 P

r RTP fQ FQ(Z) :E K(Z) for P :E 0.5 0.5 THERMAL POWER where: P =

RATED THERMAL POWER 2.5.1 FQ=2.5O.

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 Ala are only applicable to Figure 4a. The W(z) functions shown in Table A.Ib 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.la 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 burnups up to 18000 MWD/MTU in Cycle 25. 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 1 8000 MWD/MTU, use of 1 8000 MWD/MTU W(z) values without extrapolation is conservative. The W(z) values were determined assuming Cycle 25 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.

7 This record was final approved on 9/17/2020 2:12:09 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% +1- 5% RTP, the W(z) values listed in Table A.2 should be used. When a part power surveillance is performed after 150 MWDIMTU, 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 1/P, when P is > 0.5. When P is 0.5, the W(z) values should be adjusted by the factor 11(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 25 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 1 50 MWD/MTU burnup and 45% +1- 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 5 defined by PDMS when OPERABLE)

Ue Engineering uncertainty factor = 1.03 8

This record was final approved on 9/17/2020 2:12:09 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 5000 10000 14000 18000 (feet) MWD/MTU MWDIMTU MWD/MTU MWD/MTU MWD/MTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.0000 1.0000 1.01 1.3808 1.4746 1.3573 1.3399 1.3204 1.17 1.3694 1.4581 1.3457 1.3300 1.3106 1.34 1.3582 1.4406 1.3337 1.3199 1.3010 1.51 1.3462 1.4215 1.3204 1.3090 1.2906 1.68 1.3327 1.4005 1.3059 1.2969 1.2794 1.84 1.3179 1.3779 1.2903 1.2842 1.2677 2.01 1.3021 1.3542 1.2741 1.2710 1.2559 2.18 1.2861 1.3302 1.2575 1.2573 1.2435 2.35 1.2697 1.3057 1.2401 1.2423 1.2295 2.52 1.2534 1.2816 1.2228 1.2272 1.2153 2.68 1.2372 1.2602 1.2055 1.2124 1.2013 2.85 1.2195 1.2452 1.1903 1.1974 1.1875 3.02 1.2062 1.2333 1.1811 1.1833 1.1737 3.19 1.2015 1.2213 1.1776 1.1749 1.1665 3.35 1.1971 1.2125 1.1749 1.1739 1.1681 3.52 1.1922 1.2038 1.1720 1.1720 1.1696 3.69 1.1887 1.1994 1.1685 1.1725 1.1721 3.86 1.1859 1.1956 1.1661 1.1753 1.1787 4.02 1.1829 1.1907 1.1639 1.1774 1.1853 4.19 1.1794 1.1853 1.1610 1.1781 1.1898 4.36 1.1756 1.1796 1.1578 1.1785 1.1939 4.53 1.1709 1.1732 1.1542 1.1782 1.1972 4.70 1.1656 1.1663 1.1501 1.1773 1.1997 4.86 1.1600 1.1589 1.1455 1.1756 1.2012 5.03 1.1538 1.1512 1.1404 1.1730 1.2014 5.20 1.1472 1.1429 1.1347 1.1698 1.2008 5.37 1.1400 1.1344 1.1293 1.1653 1.1985 5.53 1.1353 1.1243 1.1242 1.1621 1.1998 5.70 1.1359 1.1177 1.1221 1.1621 1.2056 5.87 1.1424 1.1173 1.1250 1.1663 1.2118 6.04 1.1539 1.1206 1.1374 1.1782 1.2230 6.20 1.1642 1.1231 1.1487 1.1896 1.2327 6.37 1.1734 1.1246 1.1592 1.1999 1.2409 6.54 1.1821 1.1303 1.1694 1.2092 1.2492 6.71 1.1897 1.1362 1.1796 1.2166 1.2553 6.87 1.1964 1.1423 1.1886 1.2226 1.2597 7.04 1.2013 1.1471 1.1965 1.2271 1.2626 9

This record was final approved on 9/17/2020 2:12:09 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 5000 10000 14000 18000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 7.2 1.2050 1.1512 1.2036 1.2303 1.2642 7.38 1.2077 1.1545 1.2096 1.2322 1.2641 7.55 1.2077 1.1555 1.2124 1.2300 1.2596 7.71 1.2066 1.1557 1.2139 1.2264 1.2536 7.88 1.2036 1.1548 1.2142 1.2213 1.2463 8.05 1.1984 1.1519 1.2125 1.2144 1.2371 8.22 1.1907 1.1490 1.2094 1.2051 1.2262 8.38 1.1871 1.1470 1.2042 1.1989 1.2134 8.55 1.1787 1.1442 1.1978 1.1902 1.2043 8.72 1.1696 1.1411 1.1926 1.1857 1.1989 8.89 1.1721 1.1466 1.1859 1.1818 1.1958 9.05 1.1780 1.1568 1.1793 1.1819 1.1938 9.22 1.1821 1.1628 1.1854 1.1879 1.2001 9.39 1.1858 1.1835 1.1972 1.1944 1.2076 9.56 1.1983 1.2147 1.2062 1.2009 1.2192 9.73 1.2203 1.2431 1.2218 1.2102 1.2297 9.89 1.2439 1.2718 1.2460 1.2215 1.2333 10.06 1.2644 1.2988 1.2617 1.2386 1.2506 10.23 1.2703 1.3246 1.2753 1.2558 1.2710 10.40 1.2837 1.3487 1.2898 1.2681 1.2851 10.56 1.2903 1.3691 1.3035 1.2750 1.2866 10.73 1.2928 1.3894 1.3168 1.2833 1.2868 10.90 1.2997 1.4076 1.3268 1.2930 1.2940 11.07 1.3050 1.4200 1.3327 1.3006 1.2960 11.23 1.0000 1.0000 1.0000 1.0000 1.0000 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 11.57 1.0000 1.0000 1.0000 1.0000 1.0000 11.74 1.0000 1.0000 1.0000 1.0000 1.0000 11.90 1.0000 1.0000 1.0000 1.0000 1.0000 12.07(top) 1.0000 1.0000 1.0000 1.0000 1.0000 10 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

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

Height 150 5000 10000 14000 18000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.0000 1.0000 1.01 1.3196 1.4119 1.2954 1.2676 1.2758 1.17 1.3094 1.3967 1.2848 1.2591 1.2668 1.34 1.2994 1.3806 1.2739 1.2505 1.2579 1.51 1.2887 1.3630 1.2618 1.2412 1.2484 1.68 1.2766 1.3437 1.2486 1.2309 1.2382 1.84 1.2634 1.3230 1.2345 1.2202 1.2276 2.01 1.2495 1.3013 1.2199 1.2092 1.2170 2.18 1.2353 1.2793 1.2050 1.1978 1.2058 2.35 1.2209 1.2568 1.1893 1.1852 1.1931 2.52 1.2067 1.2368 1.1740 1.1727 1.1802 2.68 1.1919 1.2188 1.1581 1.1598 1.1678 2.85 1.1794 1.2033 1.1487 1.1505 1.1552 3.02 1.1715 1.1931 1.1450 1.1462 1.1445 3.19 1.1675 1.1873 1.1416 1.1450 1.1412 3.35 1.1655 1.1805 1.1413 1.1456 1.1450 3.52 1.1628 1.1734 1.1406 1.1460 1.1481 3.69 1.1614 1.1659 1.1395 1.1461 1.1532 3.86 1.1606 1.1576 1.1387 1.1483 1.1619 4.02 1.1596 1.1527 1.1381 1.1523 1.1701 4.19 1.1582 1.1503 1.1374 1.1558 1.1764 4.36 1.1564 1.1468 1.1364 1.1587 1.1821 4.53 1.1538 1.1431 1.1350 1.1612 1.1872 4.70 1.1508 1.1390 1.1332 1.1631 1.1915 4.86 1.1474 1.1345 1.1311 1.1642 1.1948 5.03 1.1435 1.1296 1.1283 1.1645 1.1969 5.20 1.1391 1.1246 1.1265 1.1641 1.1982 5.37 1.1349 1.1185 1.1251 1.1628 1.1980 5.53 1.1341 1.1151 1.1229 1.1615 1.1995 5.70 1.1362 1.1149 1.1213 1.1617 1.2035 5.87 1.1416 1.1173 1.1223 1.1653 1.2065 6.04 1.1481 1.1205 1.1292 1.1727 1.2154 6.20 1.1537 1.1230 1.1351 1.1813 1.2240 6.37 1.1581 1.1246 1.1402 1.1886 1.2313 6.54 1.1629 1.1303 1.1456 1.1964 1.2386 6.71 1.1676 1.1362 1.1509 1.2027 1.2438 6.87 1.1715 1.1423 1.1569 1.2079 1.2475 7.04 1.1739 1.1471 1.1633 1.2117 1.2497 11 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

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

Height 150 5000 10000 14000 18000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 7.21 1.1751 1.1512 1.1690 1.2145 1.2507 7.38 1.1756 1.1546 1.1739 1.2160 1.2501 7.55 1.1739 1.1556 1.1763 1.2139 1.2452 7.71 1.1713 1.1558 1.1777 1.2106 1.2389 7.88 1.1674 1.1549 1.1783 1.2060 1.2314 8.05 1.1608 1.1521 1.1776 1.1996 1.2220 8.22 1.1552 1.1491 1.1759 1.1917 1.2109 8.38 1.1495 1.1471 1.1728 1.1822 1.1977 8.55 1.1427 1.1443 1.1686 1.1746 1.1859 8.72 1.1344 1.1402 1.1631 1.1686 1.1779 8.89 1.1335 1.1384 1.1621 1.1688 1.1687 9.05 1.1366 1.1370 1.1679 1.1712 1.1657 9.22 1.1401 1.1384 1.1737 1.1720 1.1713 9.39 1.1484 1.1462 1.1780 1.1729 1.1773 9.56 1.1602 1.1560 1.1842 1.1825 1.1852 9.73 1.1743 1.1674 1.1914 1.1982 1.1922 9.89 1.1911 1.1838 1.1976 1.2067 1.1946 10.06 1.2070 1.1990 1.2047 1.2226 1.2099 10.23 1.2151 1.2182 1.2141 1.2384 1.2286 10.40 1.2308 1.2390 1.2222 1.2495 1.2406 10.56 1.2397 1.2569 1.2354 1.2552 1.2401 10.73 1.2446 1.2746 1.2552 1.2625 1.2395 10.90 1.2535 1.2909 1.2713 1.2713 1.2431 11.07 1.2606 1.3018 1.2798 1.2782 1.2430 1 1 .23 1 .0000 1 .0000 1 .0000 1 .0000 1.0000 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 11.57 1.0000 1.0000 1.0000 1.0000 1.0000 11.74 1.0000 1.0000 1.0000 1.0000 1.0000 11.90 1.0000 1.0000 1.0000 1.0000 1.0000 12.07 (top) 1.0000 1.0000 1.0000 1.0000 1.0000 12 This record was final approved on 9/17/2020 2:12:09 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 norninalpower 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)*

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 1.5828 1.17 1.5586 1.34 1.5352 1.51 1.5114 1.68 1.4862 1.84 1.4597 2.01 1.4307 2.18 1.4023 2.35 1.3766 2.52 1.3509 2.68 1.3250 2.85 1.2974 3.02 1.2744 3.19 1.2605 3.35 1.2466 3.52 1.2325 3.69 1.2201 3.86 1.2077 4.02 1.1956 4.19 1.1844 4.36 1.1736 4.53 1.1617 4.70 1.1489 4.86 1.1356 5.03 1.1219 5.20 1.1073 5.37 1.0929 5.53 1.0815 5.70 1.0748 5.87 1.0739 6.04 1.0782 13 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

TableA.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 norninalpower ratio. In order to be applicable, the W(z) s must be adjustedfor relative power per Section 2. 5. 3 at the time ofthe surveillance Height (feet) W(z)*

6.20 1.0810 6.37 1.0844 6.54 1.0898 6.71 1.0900 6.87 1.0893 7.04 1.0888 7.21 1.0874 7.38 1.0849 7.55 1.0805 7.71 1.0762 7.88 1.0684 8.05 1.0613 8.22 1.0610 8.38 1.0660 8.55 1.0460 8.72 1.0357 8.89 1.0385 9.05 1.0453 9.22 1.0515 9.39 1.0588 9.56 1.0739 9.73 1.1012 9.89 1.1245 10.06 1.1370 10.23 1.1377 10.40 1.1495 10.56 1.1598 10.73 1.1683 10.90 1.1819 11.07 1.2018 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 9/17/2020 2:12:09 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 25 Bumup W(z) Penalty Factor (%)

150 2.00 492 2.00 664 2.70 835 2.91 1006 2.19 1177 2.00 2547 2.00 2719 2.13 2890 2.42 3061 2.48 3232 2.40 3404 2.20 3575 2.00 10596 2.00 10767 2.33 10938 2.28 11109 2.21 11281 2.13 11452 2.04 11623 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 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.

15 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

1H-0 90 0 80 N

01 ni ni N

0.70 : : E I-I 0 60 FQ Elevation (ft.) K(z) 4 4.++ 4 4 4 +

0.50

.50 0.0 1.00 N 2.50 6.0 1.00 0.40 .31 12.0 0.925 HfrttHHHt 0.30 - . . .

ff 0.20 0.10 0.00 -

: I : : lit II_ :

UUU 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FEET)

Figure 3 Callaway Cycle 25 K(z) Normalized FQ(z) as a Function of Core Height 16 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

2.6 Nuclear Enthalpy Rise Hot Channel Factor F (Specification 3.2.2)

FAHN

UAH S FAHRTP [1 + PFAH(1-P)]

THERMAL POWER where: P =

RATED THERMAL POWER 1 T RTP L.U.1 r 2.6.2 PFAH 0.3 2.6.3 The uncertainty, UAH, to be applied to measured FAH shall be 1 .04 when PDMS is inoperable (UAH i5 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 specified AFD band.

17 This record was final approved on 9/17/2020 2:12:09 PM. (This statementwas added by the PRIME system upon its validation)

120 110 100 90 0

04 80

-1 70 60 E-4 Iza 50 0

z rz:I 40 U

lxi 30 20 10 0

50 40 30 20 10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (% DELTA-I)

Figure4a CaNaway Cycle 25 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +101-15%

18 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

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

50 40 30 20 10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (% DELTA-I)

Figure4b Callaway Cycle 25 Alternate Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +81-12%

19 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

I I I I I I I I I I I I I I I I I I I I I I I I 4-+++ - + - ++- +++++ -++-+ -- +-+

- - - - - : Unacceptable 660 Operation

++-4+-

I I I I I I I I I I I I I I I I I I I I 1- -F+--F+-++-+- -F+/- 2435psia I I I I I I I I I I I I I I I I I

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

I I I I I I I I I I I I I I I I I I I I I I I

+ - + - ++ - + + + +

640 + + + + - - +

I I I I I I I I I I I ?jj I I I I I I I

+++--F+-++-+++* + 1-+-F+--1--+

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I I I I I I I I I I I I I I I I I I I I I I I I I I 56i i2 04 1 h 1 12 14 F RALD iHER1AL PCi Figure 5 Callaway Cycle 25 Reactor Core Safety Limits 20 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

2.9 Reactor Irip System (RIS) Instrumentation (Specification 3.3.1)

Parameter Va1ie Overtemperature Al reactor trip setpoint 1 K = 1.2260 Overtemperature Al reactor trip setpoint Iavg coefficient 2 K 0.019/°F Overtemperature Al reactor trip setpoint pressure coefficient 3 K 0.001 1/psig Nominal Iavg at RIP T<585.3 °F Nominal RCS operating pressure 1 P = 2235 psig Measured RCS Al lead/lag time constants Ci ? 0 sec t2 $ 0 sec Measured RCS AT lag time constant t3 < 4 sec Measured RCS average temperature lead/lag time constants >27 sec 4

t t

5 4 sec Measured RCS average temperature lag time constant t6 S 2 sec fi(

M 1 ) = -0.0280 {18% + (qt - q)} when (qt - qb) < -

I 8% RTP 0 when -18% RTP < (qt - qb) E 10% RIP 0.0224 {(qt - qb) -

10%} when (qt qb) > 10% RTP Where, qt and qb are percent RIP in the upper and lower halves ofthe core, respectively, and qt + qb 5 the total THERMAL POWER in percent RIP.

21 This record was final approved on 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

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

Parameter Value Overpower AT reactor trip setpoint 4 K 1.1073 Overpower AT reactor trip setpoint Tavg rate/lag coefficient 5 K 0.02/°F for increasing Tavg

= 0/°F for decreasing Tavg Overpower AT reactor trip setpoint Tavg heatup coefficient 6 K 0.0015/°F for T > T

=0/°F forT<T Nominal Tavg at RTP T < 585.3°F Measured RCS AT lead/lag time constants Cl ?: 0 sec t2 S 0 sec Measured RCS AT lag time constant t3 < 4 sec Measured RCS average temperature lag time constant t6 S 2 sec Measured RCS average temperature rate/lag time constant C7 > 10 sec (f

2z\I) = 0 for all Al.

2. 1 1 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 22 This record was final approved on 9/17/2020 2:12:09 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:

1 . WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.

NRC letter dated May 28, 1985, Acceptance for Referencing ofLicensing 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 of Licensing Topical Report WCAP-1 021 6-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 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 1 98 1 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code Addendum 1 : Power Shape Sensitivity Studies, December 1987.

NRC letter dated September 1 5, 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 ofthe 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 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 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

4. WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995.

NRC Safety Evaluation Reports dated July 1 1 991 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, 1 994, 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-1 1397-P-A, Revised Thermal Design Procedure, April 1989.

NRC Safety Evaluation Report dated January 1 7, 1 989, 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-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-1085 1, 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 1 5063, 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, 1 986, 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 9/17/2020 2:12:09 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 of Topical 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 1 0, 20 1 0, 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 ofLicensing Topical Reports WCAP-13524 and WCAP-13524, Revision 1, APOLLO A One-Dimensional Neutron Diffusion Theory Program.

13 . WCAP- 1 4565-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 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 9/17/2020 2:12:09 PM. (This statement was added by the PRIME system upon its validation)

ULNRC-06616, Cycle 25 - Core Operating Limits Report

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