Text

Core Operating Limits Report, Cycle 22
	ML16118A483
Person / Time
Site:	Callaway
Issue date:	04/27/2016
From:	Wink R; Ameren Missouri, Union Electric Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ULNRC-06299
	Download: ML16118A483 (29)
	v • d • e

WAmeren MISSOURI Callaway Plant April 27, 2016 ULNRC-06299 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. DC 20555-000 1 Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

RENEWED FACILITY OPERATING LICENSE NPF-30 CORE OPERATING LIMITS REPORT Please find enclosed the Callaway Cycle 22 Core Operating Limits Report (COLR). This report is provided to the NRC Staff for information. It has been prepared in accordance with the requirements of Technical Specification 5.6.5.

This letter does not contain new commitments.

If you have any questions concerning this report, please contact Mr. Tom Elwood, Supervisor

Regulatory Affairs and Licensing, at 314-225-1905.

Sincerely, 4aDJ

/ 1ger C. Wink,

/

Manager, Regulatory Affairs JPKItlw

Attachment:

Callaway Cycle 22 Core Operating Limits Report P.C. Box 620 Fulton, l\\Ic 65251 iiiiereiiIissoiri.cori

ULNRC-06299 April 26, 2016 Page 2 cc:

Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Caflaway Resident Office U.S. Nuclear Regulatory Commission

$201 NRC Road Steedman, MO 65077 Mr. L. John Kios Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O$H4 Washington, DC 20555-0001

ULNRC-06299 April 26, 2016 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 6100 Western Place, Suite 1050 fort Worth, IX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed)

Electronic distribution for the following can be made via Other Situations ULNRC Distribution:

F. M. Diya T. E. Herrmann B. L. Cox S. G. Kovaleski R. C. Wink T. B. Elwood J. W. Knaup Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John ONei11 (Pillsbury Winthrop Shaw Pittman LLP)

Missouri Public Service Commission

Attachment to ULNRC-06299 Callaway Cycle 22 Core Operating Limits Report 25 Pages

Callaway Cycle 22 COLR Callaway Cycle 22 Core Operating Limits Report February 2016

Edited by:

Arielle L. Worthington

Approved:

David J. Wotus, Manager Nuclear Design C Engineering Center of Excellence

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

Callaway Cycle 22 COLR 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 22 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 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

Callaway Cycle 22 COLR 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% Ak/k.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-Il 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.

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 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).

2

Callaway Cycle 22 COLR U

E-4 HUH ni ni0U E-i PERCENT OF RATED THERNAL POWER Figure 1 Callaway Cycle 22 Moderator Temperature Coefficient Versus Power Level 7

c

{ UNACCEPTABIE OPERATION (70%,

5.0) 5 4---

3 ACCEPTABIE OPERATION 1

0 0

10 20 30 40 50 60 70 80 90 100 3

Callaway Cycle 22 COLR 2.3 Shutdown Bank Insertion Limits (Specification 3.1.5)

The shutdown banks shall be withdrawn to at least 225 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 fully inserted and not fully withdrawn.

4

Callaway Cycle 22 COLR E-i H

U)

U) z0 H

H U)0 225 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 22 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation (O,161)[

175 150 125 100 (100, 161

-t-[-t-t-t-t 1-

- F t 1-

t:[:Wtt 75

I IAIIII fATIIIT 5° ft tLhi t (0,46) 25

- -J (30.2,0)

- I 0

iii i

0 10 20 30 40 50 60 70 80 90 100 5

Callaway Cycle 22 COLR 2.5 Heat Flux Hot Channel Factor (FO(z))

(Specification 3.2.1)

RTP FQ FQ(Z) <

K(Z) for P> 0.5 P

r RTP FQ FQ(Z) <

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

P RATED THERMAL POWER 2.5.1 fRTP_250 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 FQ(z) are shown in Table A. I a 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, FQ(z) must be confirmed to meet Technical Specification requirements by one of the following methods:

1.

Confirm fQ(z) meets the Technical Specification Limit with the Table A. I a W(z) values for the most recent surveillance performed.

2.

Perform a new surveillance and confirm FQ(z) meets the Technical Specification Limit with the Table A. I a W(z) values.

The W(z) values have been determined for several bumups up to 20000 MWD/MTU in Cycle 22. This permits determination of W(z) at any cycle bumup up to 20000 MWD/MTU through the use of three point interpolation. For cycle bumups greater than 20000 MWDIMTU, use of 20000 MWD/MTU W(z) values without extrapolation is conservative.

The W(z) values were determined assuming Cycle 22 operates with RAOC strategy.

The W(z) values are provided for 73 axial points within the core height boundaries of 0 and 12.08 feet (hot core height) at equally spaced intervals.

6

Callaway Cycle 22 COLR 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% +1-5% 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 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 bumup dependent FQ penalty factors for Cycle 22 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 bumups 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 bumup 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 is defined by PDMS when OPERABLE)

Ue = Engineering uncertainty factor 1.03 7

Callaway Cycle 22 COLR Table A.la W(z) versus Core Height for +lO%/-15% RAOC Band (lop and Bottom 8% Excluded)

Height 150 4000 10000 14000 20000 (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 1.3775 1.4760 1.3260 1.2966 1.3045 1.17 1.3680 1.4607 1.3175 1.2904 1.2975 1.34 1.3565 1.4421 1.3066 1.2819 1.2823 1.51 1.3432 1.4211 1.2941 1.2721 1.2779 1.68 1.3286 1.3986 1.2806 1.2615 1.2668 1.84 1.3133 1.3749 1.2663 1.2503 1.2552 2.01 1.2973 1.3502 1.2514 1.2386 1.2432 2.18 1.2809 1.3250 1.2362 1.2265 1.2308 2.35 1.2642 1.2996 1.2209 1.2142 1.2182 2.52 1.2474 1.2741 1.2052 1.2017 1.2055 2.68 1.2299 1.2488 1.1903 1.1892 1.1921 2.85 1.2125 1.2241 1.1785 1.1782 1.1786 3.02 1.2005 1.2005 1.1725 1.1720 1.1700 3.19 1.1940 1.1857 1.1696 1.1699 1.1677 3.35 1.1909 1.1836 1.1663 1.1695 1.1691 3.52 1.1888 1.1826 1.1621 1.1689 1.1739 3.69 1.1865 1.1801 1.1590 1.1673 1.1806 3.86 1.1835 1.1775 1.1578 1.1654 1.1861 4.03 1.1799 1.1743 1.1562 1.1653 1.1909 4.19 1.1766 1.1706 1.1539 1.1658 1.1949 4.36 1.1741 1.1662 1.1512 1.1671 1.1979 4.53 1.1711 1.1613 1.1479 1.1677 1.1999 4.70 1.1672 1.1558 1.1441 1.1674 1.2014 4.86 1.1627 1.1497 1.1398 1.1664 1.2028 5.03 1.1585 1.1431 1.1349 1.1644 1.2032 5.20 1.1538 1.1359 1.295 1.1617 1.2033 5.37 1.1495 1.1283 1.1236 1.1582 1.2036 5.54 1.1502 1.1198 1.1164 1.1529 1.2041 5.70 1.1562 1.1121 1.1120 1.1500 1.2059 5.87 1.1651 1.1092 1.1127 1.1518 1.2140 6.04 1.1745 1.1110 1.1213 1.1605 1.2255 6.21 1.1830 1.1173 1.1351 1.1731 1.2369 6.37 1.1904 1.1246 1.1465 1.1832 1.2462 8

Callaway Cycle 22 COLR Table A.la W(z) versus Core Height for +10%/-J5% RAOC Band (lop and Bottom 8% Excluded)

Height 150 4000 10000 14000 20000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.54 1.1973 1.1345 1.1575 1.1931 1.2550 6.71 1.2037 1.1452 1.1685 1.2026 1.2627 6.8$

1.2093 1.1544 1.1787 1.2107 1.2683 7.05 1.2137 1.1627 1.1880 1.2173 1.2721 7.21 1.2166 1.1700 1.1960 1.2226 1.2739 7.38 1.2180 1.1761 1.2028 1.2262 1.2738 7.55 1.2177 1.1809 1.2082 1.2283 1.2717 7.72 1.2158 1.1843 1.2122 1.2286 1.2675 7.88 1.2122 1.1863 1.2146 1.2273 1.2612 8.05 1.2066 1.1863 1.2156 1.2244 1.2531 8.22 1.1993 1.1858 1.2145 1.2194 1.2427 8.39 1.1910 1.1864 1.2119 1.2128 1.2304 8.55 1.1829 1.1886 1.2105 1.2076 1.2187 8.72 1.1749 1.1908 1.2085 1.2018 1.2072 8.89 1.1690 1.1926 1.2066 1.1987 1.1981 9.06 1.1713 1.2032 1.2106 1.2060 1.1997 9.23 1.1805 1.2209 1.2236 1.2233 1.2062 9.39

.1941 1.2397 1.2418 1.2388 1.2106 9.56

.2125 1.2568

.2615 1.2506 1.2174 9.73

.2287 1.2716

.2823 1.2610 1.2280 9.90

.2369 1.2866

.3040 1.2711 1.2416 10.06 1.2418 1.3082 1.3258 1.2772 1.2576 10.23

.2489 1.3355 1.3468 1.2807 1.2737 10.40

.2618 1.3643 1.3668 1.2850 1.2880 10.57

.2785 1.3915 1.3853 1.2922 1.3008 10.74

.2961 1.4138 1.4018 1.3027 1.3118 10.90

.3117 1.4305 1.4157 1.3139 1.3203 11.07 1.3237 1.4467 1.4259 1.3186 1.3252 1 1.24

.0000 1.0000 1.0000 1.0000 1.0000 11.41

.0000 1.0000 1.0000 1.0000 1.0000 11.57

.0000 1.0000 1.0000 1.0000 1.0000 11.74

.0000 1.0000 1.0000 1.0000 1.0000 11.91 1.0000 1.0000 1.0000 1.0000 1.0000 12.08 (top) 1.0000 1.0000 1.0000 1.0000 1.0000 9

Callaway Cycle 22 COLR Table A.lb W(z) versus Core Height for +$%/-12% RAOC Band (Top and Bottom 8% Excluded)

Height 150 4000 10000 14000 20000 (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 1.3019 1.3985 1.2902 1.2402 1.2545 1.17 1.2940 1.3852 1.2822 1.2344 1.2482 1.34 1.2841 1.3688 1.2716 1.2267 1.2398 1.51 1.2728 1.3503 1.2595 1.2178 1.2303 1.6$

1.2604 1.3304 1.2465 1.2082 1.2203 1.84 1.2474 1.3096 1.2327 1.1982 1.2098 2.01 1.2338 1.2879 1.2183 1.1879 1.1990 2.18 1.2201 1.2658 1.2036 1.1774 1.1879 2.35 1.2063 1.2436 1.1889 1.1672 1.1767 2.52 1.1911 1.2215 1.1742 1.1582 1.1657 2.68 1.1791 1.1993 1.1592 1.1515 1.1538 2.85 1.1733 1.1778 1.1447 1.1441 1.1421 3.02 1.1691 1.1594 1.1344 1.1357 1.1358 3.19 1.1655 1.1488 1.1299 1.1307 1.1364 3.35 1.1630 1.1478 1.1298 1.1302 1.1416 3.52 1.1615 1.1469 1.1291 1.1313 1.1459 3.69 1.1601 1.1458 1.1280 1.1326 1.1511 3.86 1.1579

1. 444 1.1276 1.1334 1.1596 4.03 1.1554

1. 426 1.1277 1.1349 1.1681 4.19 1.1542

1. 401 1.1278 1.1379

.1755 4.36 1.1543 1.1375 1.1274 1.1417

.1821 4.53 1.1540 1.1352 1.1265 1.1449

.1877 4.70

.1528 1.1328 1.1252 1.1474

.1923 4.86

.1511 1.1298 1.1235 1.1491 1.1957 5.03

.1493 1.1262 1.1212 1.1501

.1977 5.20

.1471 1.1222 1.1186 1.1504

.1998 5.37

.1457 1.1178 1.1155 1.1498

.2022 5.54 1.1474 1.1124 1.1111 1.1481

.2028 5.70

.1534 1.1088 1.1092 1.1475 1.2038 5.87

.1614 1.1084 1.1115 1.1504 1.2090 6.04

.1705

1. 116 1.1188 1.1572 1.2154 6.21 1.1792

1. 168 1.1289 1.1652 1.2228 6.37 1.1867 1.1206 1.1374 1.1722 1.2312 10

Catlaway Cycle 22 COLR Table A.lb W(z) versus Core Height for +$%/-12% RAOC Band (Top and Bottom 8% Excluded)

Height 150 4000 10000 14000 20000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.54 1.1931 1.1239 1.1457 1.1793 1.2380 6.71 1.1984 1.1267 1.1540 1.1858 1.2429 6.8$

1.2024 1.1294 1.1614 1.1909 1.2462 7.05

.2050 1.1353 1.1679 1.1947 1.2476 7.21

.2061 1.1425 1.1734 1.1972 1.2471 7.38

.2056 1.1486 1.1776 1.1982 1.2448 7.55

.2033 1.1540 1.1806 1.1978 1.2403 7.72 1.1994 1.1585 1.1823 1.1959 1.2352 7.88

.1936 1.1621 1.1825 1.1924 1.2304 8.05

.1852 1.1648 1.1816 1.1874 1.2240 8.22

.1764 1.1664 1.1785 1.1807 1.2158 8.39

.1687 1.1670 1.1741 1.1725 1.2062 8.55

.1591 1.1663 1.1735 1.1647 1.1964 8.72 1.1476 1.1655 1.1740 1.1593 1.1860 8.89

.1421 1.1664 1.1751 1.1582 1.1766 9.06

.1487 1.1736 1.1781 1.1594 1.1759 9.23

.1671 1.1855 1.1875 1.1665 1.1772 9.39

.1841 1.1983 1.2041 1.1793 1.1797 9.56 1.1988 1.2195 1.2198 1.1921 1.1853 9.73 1.2132 1.2477 1.2335 1.2061 1.1969 9.90 1.2278 1.2778 1.2470 1.2234 1.2143 10.06 1.2393 1.3070 1.2602 1.2404 1.2312 10.23 1.2495 1.3357 1.2728 1.2561 1.2463 10.40 1.2621 1.3645 1.2846 1.2704 1.2603 10.57 1.2787 1.3917 1.2957 1.2828 1.2729 10.74 1.2965 1.4140 1.3056 1.2930 1.2838 10.90 1.3121 1.4309 1.3135 1.2999 1.2922 11.07 1.3242 1.4470 1.3187 1.3020 1.2971 11.24 1.0000 1.0000 1.0000 1.0000 1.0000 11.41 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 11.91 1.0000 1.0000 1.0000 1.0000 1.0000 12.08 (top) 1.0000 1.0000 1.0000 1.0000 1.0000 11

Callaway Cycle 22 COLR 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 nominalpower ratio. In order to be applicable, the W(z) must be adjustedfor relative power per 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 1.5313 1.17 1.5106 1.34 1.4881 1.51 1.4645 1.68 1.4399 1.84 1.4151 2.01 1.3899 2.18 1.3648 2.35 1.3397 2.52 1.3144 2.68 1.2882 2.85 1.2621 3.02 1.2421 3.19 1.2280 3.35 1.2179 3.52 1.2089 3.69 1.1997 3.86 1.1901 4.03 1.1800 4.19 1.1701 4.36 1.1610 4.53 1.1516 4.70 1.1415 4.86 1.1309 5.03 1.1208 5.20 1.1104 5.37 1.1004 5.54 1.0954 5.70 1.0956 5.87 1.0989 6.04 1.1028 12

Callaway Cycle 22 COLR Table A.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWDIMTU, D-bank at 185 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) s must be adjustedfor relative power per Section 2.5.3 at the time ofthe surveillance Height (feet)

W(z)*

6.21 1.1058 6.37 1.1076 6.54 1.1089 6.71 1.1102 6.88 1.1111 7.05 1.1112 7.21 1.1103 7.38 1.1083 7.55 1.1048 7.72 1.1005 7.88 1.0952 8.05 1.0885 8.22 1.0808 8.39 1.0727 8.55 1.0652 8.72 1.0584 8.89 1.0541 9.06 1.0578 9.23 1.0624 9.39 1.0637 9.56 1.1037 9.73 1.1226 9.90 1.1350 10.06 1.1468 10.23 1.1614 10.40 1.1797 10.57 1.1991 10.74 1.2174 10.90 1.2341 11.07 1.2473 11.24 1.0000 11.41 1.0000 11.57 1.0000 11.74 1.0000 11.91 1.0000 12.0$ (top) 1.0000 13

Callaway Cycle 22 COLR Table A.3 FQ Penalty Factors as a Function of Cycle Bumup Cycle 22 Burnup FQ(z) Penalty Factor (%)

150 2.00 322 2.00 493 2.00 665 2.33

$36 2.18 1008 2.06 1180 2.03 1351 2.10 1523 2.22 1694 2.34 1866 2.40 2038 2.40 2209 2.31 2381 2.14 2552 2.00 5641 2.00 5813 2.11 5984 2.45 6156 2.77 6327 2.81 6499 2.65 6671 2.76 6842 2.61 7014 2.39 7185 2.16 7357 2.00 Note:

All cycle bumups 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.

14

0

,1o 0

0ZD 0

1 CD CD H

C)

I-]

Ti CDN F]

CD KfZ)

NORMALIZED FQ(Z) 0 H

0 0

0

)

D 0

0 0

o H

w 3

1.0 o

0 0

0 H

H H

O H

r%)

o 0

0 CD tJ c-iC Lu 0*i H0 H

ts)

Callaway Cycle 22 COLR 2.6 Nuclear Enthalpy Rise Hot Channel Factor FJ (Specification 3.2.2)

FHN

UH < FHRTl [1 + PFH( I -P)]

THERMAL POWER where:

P RATED THERMAL POWER 2.6.1 fRTP_ 1.65 2.6.2 PfH = 0.3 2.6.3 The uncertainty, UH, to be applied to measured fH shall be

.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 specified AFD band.

16

Callaway Cycle 22 COLR 120 110 I

Jii.

100%

-+io, 100%)

100

;;;1

p::

I;;;

UNACCEPTABLE UNACCEPTABLE OPERATION JOPERATION ACCEPTABLE:

70 OPERATION 60---

50

-30 50%

+26 50%)]

z 40 rzl 30 L jJi LJJHWL 10 20 30 50 AXIAL FLUX DIFFERENCE

(% DELTA-I)

Figure 4a Callaway Cycle 22 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +101-15%

17

Callaway Cycle 22 COLR 120 r

70 60 50 40 30 20 10 0

UNACCEPTABLE OPERATION HHH H i

L111:

(27, 50%)

ACCEPTABLE OPERATION UNACCEPTABLE OPERATION 1HH

+24, 50%)

50 40 30 20 10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE

(% DELTA-I)

Figure4b Callaway Cycle 22 Alternate Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +81-12%

°Li

I

=

(12,100%)

100 90 80 1$

Callaway Cycle 22 COLR 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 ioop average temperature, and pressurizer pressure shall not exceed the limits in Figure 5.

680 I

I I

Unacceptable 114 660 Opeiation I

I I

I 4+4+44-

-4#+44-4+-44-+4#++44444 I

II II II I

II II I

t

++-tt-tt-tf t+

2435psia I

I II II II I

I II I

II II I

++++

++-+++++-

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

I I

II II II I

II II II II I

II II I

640-4444 44444444 111111 liii II 2250sia 1111111 r

÷

÷÷÷--÷ i

I I

0

++ 4+-4#+44-4+-

4-+44

+4444-+

I I

II II II I

II I

II II I

++÷-tt-

-+ttt+-t÷-+tt t

+÷-+t-÷ 620 1t 2000 P5W [H

+H+

4444 4-44444-444-44444

+

4-44-4 F-I II II I

I I

II I

I II II I

I II I

t+++-t+-+t-+

+t+-+t-+

t+t+

-+t-t I

I I

4444-44-44-4444

+-+4-+4 44 4-4 I

I II II II II I

II I

II II II II II I

600 ttt++

+

++

I I

II II II I

I II II II II I

I I

t+++-4+++-+++++

_4_++

++

I I

II II II II I

II 1860s I

II I

+44+-++-4+-+4+4+

I

+4+

+

4

-4 I

I II II II II II II I

I II I

Acceptable

++-+÷-÷÷-÷+÷÷÷÷ 580 -f Operation T Tm T

T V +t

++

I I

+++-++-++-+++++-++-+++4-+l-+%+++-+

I I

4+4+-4+-++-+++4+4+-++-+++++4444+

I I

I 56W 0

2 0.4 0.6 0.8 1

1.2 l

FRACTION OF RKLD IHLRMAL PCVLR Figure 5 Callaway Cycle 22 Reactor Core Safety Limits 19

Callaway Cycle 22 COLR (Specification 3.3.1)

Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Nominal Tavg at RTP Nominal RCS operating pressure Measured RCS AT lead/lag time constants Measured RCS average temperature lag time constant f1(AI) = -0.0280 { 18% + (q

- qi)}

Vlii K1 = 1.2260 K2 = 0.019/°F K3 = 0.001 1/psig T<585.3 °F p1 = 2235 psig ri > 0 sec

<0 sec t3 <4 sec t4 > 27 sec t5 <4 sec t6 <2 sec when (q1 - q) <-18% RIP when -18% RIP (q - q) 10% RTP when (q-q)> 10% RIP Where, q1 and q, are percent RIP in the upper and lower halves of the core, respectively, and q + q, is the total THERMAL POWER in percent RTP.

2.9 Reactor Trip System (RTS) Instrumentation Measured RCS AT lag time constant Measured RCS average temperature lead/lag time constants 0

0.0224 {(q

- q)

- 10%}

20

Callaway Cycle 22 COLR 2.10 Reactor Trip System (RTS) Instrumentation (Specification 3.3.1)

Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Ta.g 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 = 0.0015/°F for T> T 0/°F forT<T T <585.3°F

> 0 sec t2 <0 sec r3 <4 sec

<2 sec r7> 10 sec Indicated Value

>2195 psig

<590.1 °F (Specification 3.4.1)

Parameter 2.11 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits Pressurizer pressure RCS average temperature 21

Callaway Cycle 22 COLR 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:

L 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 1 A, 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 ofthe 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, 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 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).

22

Callaway Cycle 22 COLR 4.

WCAP-126 10-P-A, VANTAGE+ fuel Assembly Reference Core Report, April 1995.

NRC Safety Evaluation Reports dated July 1, 1991, Acceptance for Referencing of Topicat 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 Bumup 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 17, 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-1 0251-P-A, Improved Fuel Performance Models for Westinghouse fuel Rod Design and Safety Evaluations, August 1988.

NRC letter dated May 9, 198$, Westinghouse Topical Report WCAP-10851, Improved fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations.

8.

WCAP-1 5063-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. MA2O$6).

9.

WCAP-$745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature AT 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 AT and Thermal Overtemperature AT Trip functions.

23

Callaway Cycle 22 COLR 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-1 1596-P-A, Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores, June 1988.

NRC Safety Evaluation Report dated May 17, 1988, Acceptance for Referencing of Westinghouse Topical Report WCAP-1 1596

- Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores.

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-l3524 and WCAP-13524, Revision 1, APOLLO A One-Dimensional Neutron Diffusion Theory Program.

13.

WCAP-J 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.

24

WAmeren MISSOURI Callaway Plant April 27, 2016 ULNRC-06299 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. DC 20555-000 1 Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

RENEWED FACILITY OPERATING LICENSE NPF-30 CORE OPERATING LIMITS REPORT Please find enclosed the Callaway Cycle 22 Core Operating Limits Report (COLR). This report is provided to the NRC Staff for information. It has been prepared in accordance with the requirements of Technical Specification 5.6.5.

This letter does not contain new commitments.

If you have any questions concerning this report, please contact Mr. Tom Elwood, Supervisor

Regulatory Affairs and Licensing, at 314-225-1905.

Sincerely, 4aDJ

/ 1ger C. Wink,

/

Manager, Regulatory Affairs JPKItlw

Attachment:

Callaway Cycle 22 Core Operating Limits Report P.C. Box 620 Fulton, l\\Ic 65251 iiiiereiiIissoiri.cori

ULNRC-06299 April 26, 2016 Page 2 cc:

Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Caflaway Resident Office U.S. Nuclear Regulatory Commission

$201 NRC Road Steedman, MO 65077 Mr. L. John Kios Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O$H4 Washington, DC 20555-0001

ULNRC-06299 April 26, 2016 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 6100 Western Place, Suite 1050 fort Worth, IX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed)

Electronic distribution for the following can be made via Other Situations ULNRC Distribution:

F. M. Diya T. E. Herrmann B. L. Cox S. G. Kovaleski R. C. Wink T. B. Elwood J. W. Knaup Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John ONei11 (Pillsbury Winthrop Shaw Pittman LLP)

Missouri Public Service Commission

Attachment to ULNRC-06299 Callaway Cycle 22 Core Operating Limits Report 25 Pages

Callaway Cycle 22 COLR Callaway Cycle 22 Core Operating Limits Report February 2016

Edited by:

Arielle L. Worthington

Approved:

David J. Wotus, Manager Nuclear Design C Engineering Center of Excellence

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

Callaway Cycle 22 COLR 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 22 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 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

Callaway Cycle 22 COLR 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% Ak/k.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-Il 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.

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 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).

2

Callaway Cycle 22 COLR U

E-4 HUH ni ni0U E-i PERCENT OF RATED THERNAL POWER Figure 1 Callaway Cycle 22 Moderator Temperature Coefficient Versus Power Level 7

c

{ UNACCEPTABIE OPERATION (70%,

5.0) 5 4---

3 ACCEPTABIE OPERATION 1

0 0

10 20 30 40 50 60 70 80 90 100 3

Callaway Cycle 22 COLR 2.3 Shutdown Bank Insertion Limits (Specification 3.1.5)

The shutdown banks shall be withdrawn to at least 225 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 fully inserted and not fully withdrawn.

4

Callaway Cycle 22 COLR E-i H

U)

U) z0 H

H U)0 225 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 22 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation (O,161)[

175 150 125 100 (100, 161

-t-[-t-t-t-t 1-

- F t 1-

t:[:Wtt 75

I IAIIII fATIIIT 5° ft tLhi t (0,46) 25

- -J (30.2,0)

- I 0

iii i

0 10 20 30 40 50 60 70 80 90 100 5

Callaway Cycle 22 COLR 2.5 Heat Flux Hot Channel Factor (FO(z))

(Specification 3.2.1)

RTP FQ FQ(Z) <

K(Z) for P> 0.5 P

r RTP FQ FQ(Z) <

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