callaway, unit, cycle 24 redesign core operating limits ... · callaway cycle 24 redesign colr —...

Enclosure to

ULNRC-06507

Callaway Cycle 24 Redesign

Core Operating Limits Report

Revision 1

May 2019

(25 Pages)

Callaway Cycle 24 REDESIGN COLR — Revision 1

Callaway Cycle 24REDESIGN

Core Operating Limits ReportRevision 1

May 2019

*Edjted by:

Sean F. Miller

*Approved:

Adam W. Schutt for David J. Wotus, ManagerNuclear Design C

Core Engineering & Software Development

*Electronjcally Approved Records Are Authenticated in the Electronic Document Management System

Westinghouse Electric Company LLC1000 Westinghouse Drive

Cranberry Township, PA 16066©2019 Westinghouse Electric Company LLC

All Rights Reserved

*** This record was naI approved on 5/7/2019 10:06:36 AM. (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 (SDM)

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 FAHN

AXIAL FLUX DIFFERENCE (AFD)

Reactor Core SLs

Reactor Trip System (RTS) Instrumentation

RCS Pressure and TemperatureDeparture from Nucleate Boiling (DNB) Limits

1 .0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report (COLR) for Callaway Plant Cycle 24 has been prepared inaccordance with the requirements ofTechnical Specification 5.6.5.

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

1

*** This record was final approved on 5/7/2019 10:06:36 AM. (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 inthe subsections which follow. These limits have been developed using the NRC-approvedmethodologies 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 3and 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 shownin Figure 1 . These limits shall be referred to as the upper limit. Figure 1 cannot berevised 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 pcm/°F (all rods withdrawn, RatedThermal Power condition).

2.2.3 The MTC 60 ppm surveillance limit is -45.5 pcml°F (all rods withdrawn, RatedThermal Power condition).

2



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ElzrxHC)H

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[xl

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[xl1j

[xlEl

0El

[xl

0

7

—

‘ —

‘

A

0 10 20 30 40 50 60 70 80 90 100

PERCENT OF RATED THERMAL POWER

Figure 1

Callaway Cycle 24Moderator Temperature Coefficient

Versus Power Level

3

U UNACCEPTABLE OPERATION

:::::::: : :*::z:::::::::

(70%,

5.0)5

4

3

2

1

ACCEPTABLEOPERATION - -

—

— — — — — ‘

— — —



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 thereverse ofthe withdrawal sequence.

2.4.3 The difference between each sequential Control Bank position is 1 1 5 steps whennot fully inserted and not fully withdrawn. Overlap is defined as the fhllywithdrawn (ARO) position minus this 1 15 step tip-to-tip separation.

4



100

75

50

25

PERCENT OF RATED THERN.L POWER

Figure 2

Callaway Cycle 24Rod Bank Insertion Limits

Versus Rated Thermal Power - Four Loop Operation

5

200

175

150

125

0

0 10 20 30 40 50 60 70 80 90 100



2.5 Heat Flux Hot Channel Factor (FQ(z))(Specification 3.2.1)

RTPFQ

FQ(Z) :E K(Z) for P > 0.5P

1’ RTPfQ

FQ(Z) :S K(Z) for P 0.50.5

THERMAL POWER

where: P =

________________

RATED THERMAL POWER

2.5.1 FQ{T)= 2.50.

2.5.2 K(Z) is provided in Figure 3.

2.5.3 The W(z) functions that are to be used in Technical Specification 3.2.1 and

Surveillance Requirement 3 .2.1 .2 for determining FQW(z) are shown in Table A. laand A.lb.** The W(z) functions shown in Table A.la are only applicable toFigure 4a. The W(z) functions shown in Table A.lb are ànly applicable toFigure 4b. The data in these tables should be used independently; crossinterpolation or extrapolation between W(z) sets is prohibited.

The Axial Flux Difference (AFD) Band in Figure 4b is more restrictive than theAFD 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 thefollowing methods:

1 . Confirm FQW(z) meets the Technical Specification Limit with theTable 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 burnups up to18000 MWD/MTU in Cycle 24. This permits determination of W(z) at any cycleburnup up to 18000 MWD/MTU through the use of three point interpolation. Forcycle 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 determinedassuming Cycle 24 operates with RAOC strategy.

The W(z) values are provided for 73 axial points within the core height boundariesof 0 and 1 2.07 feet (hot core height) at equally spaced intervals.

6

*** This record was final approved on 5/7/2019 10:06:36 AM. (This statementwas added bythe PRIME system upon its validation)


The W(z) values are generated assuming that they will be used for a full powersurveillance. When a part power surveillance is performed from beginning ofcycle to 150 MWD/MTU and at 45% +1- 5% RTP, the W(z) values listed in TableA.2 should be used. When a part power surveillance is performed after150 MWD/MTU, or at a power level other than the level specified above, the HFPW(z) values in Table Ala or A.lb should be used.

W(z) values should be adjusted by the factor liP, when P is > 0.5. When P is0.5, the W(z) values should be adjusted by the factor 1/(O.5), or 2.0. This isconsistent with the adjustment in the FQ(z) limit at part power conditions.

Table A.3 shows the burnup dependent FQ penalty factors for Cycle 24 that areapplicable 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 mapat 1 50 MWD/MTU burnup and 45% +7- 5% RTP.

2.5.4 The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by thefollowing

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

7



Table A.laW(z) versus Core Height

for +1O%/-15% RAOC Band(Top 8% and Bottom 6% Excluded at 1 50 MWD/MTU;

Top and Bottom 8% Excluded Remainder of Cycle)

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 1.00000.17 1.0000 1.0000 1.0000 1.0000 1.00000.34 1.0000 1.0000 1.0000 1.0000 1.00000.50 1.0000 1.0000 1.0000 1.0000 1.00000.67 1.0000 1.0000 1.0000 1.0000 1.00000.84 1.4846 1.0000 1.0000 1.0000 1.00001.01 1.4721 1.5178 1.3328 1.3149 1.32461.17 1.4574 1.5000 1.3218 1.3054 1.31471.34 1.4426 1.4810 1.3104 1.2958 1.30491.51 1.4266 1.4604 1.2980 1.2854 1.29441.68 1.4089 1.4378 1.2844 1.2739 1.28301.84 1.3896 1.4135 1.2700 1.2618 1.27122.01 1.3690 1.3878 1.2552 1.2493 1.25932.18 1.3480 1.3620 1.2400 1.2363 1.24672.35 1.3268 1.3357 1.2242 1.2221 1.23272.52 1.3056 1.3097 1.2092 1.2080 1.21852.68 1.2845 1.2843 1.1950 1.1932 1.20452.85 1.2622 1.2576 1.1835 1.1824 1.19073.02 1.2453 1.2367 1.1762 1.1751 1.17693.19 1.2364 1.2265 1.1717 1.1697 1.16953.35 1.2260 1.2173 1.1680 1.1688 1.17123.52 1.2152 1.2087 1.1638 1.1673 1.17293.69 1.2049 1.2035 1.1593 1.1681 1.17373.86 1.1979 1.1987 1.1537 1.1716 1.17854.02 1.1919 1.1930 1.1505 1.1747 1.18474.19 1.1854 1.1868 1.1493 • 1.1763 1.18954.36 1.1786 1.1803 1.1472 1.1776 1.19374.53 1.1710 1.1731 1.1449 1.1782 1.19724.70 1.1630 1.1655 1.1420 1.1781 1.19984.86 1.1547 1.1575 1.1388 1.1772 1.20135.03 1.1463 1.1490 1.1356 1.1754 1.20175.20 1.1364 1.1402 1.1329 1.1730 1.20125.37 1.1323 1.1308 1.1303 1.1692 1.20005.53 1.1322 1.1214 1.1262 1.1663 1.20135.70 1.1369 1.1180 1.1241 1.1659 1.20795.87 1.1448 1.1206 1.1309 1.1705 1.21516.04 1.1521 1.1230 1.1442 1.1836 1.22626.20 1.1585 1.1248 1.1565 1.1952 1.23586.37 1.1638 1.1299 1.1680 1.2057 1.24406.54 1.1698 1.1353 1.1795 1.2151 1.25226.71 1.1750 1.1411 1.1905 1.2226 1.25816.87 1.1794 1.1462 1.2004 1.2286 1.2624

8



Table A.laW(z) versus Core Height

for +1O%/-15% RAOC Band(Top 8% and Bottom 6% Excluded at 1 50 MWD/MTU;


Height 150 5000 10000 14000 18000(feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU7.04 1.1822 1.1502 1.2091 1.2331 1.26517.21 1.1839 1.1533 1.2170 1.2363 1.26657.38 1.1848 1.1557 1.2237 1.2380 1.26627.55 1.1834 1.1557 1.2269 1.2356 1.26147.71 1.1812 1.1549 1.2289 1.2318 1.25527.88 1.1774 1.1530 1.2294 1.2264 1.24768.05 1.1720 1.1490 1.2280 1.2192 1.23808.22 1.1671 1.1462 1.2250 1.2094 1.22678.38 1.1616 1.1433 1.2196 1.2027 1.21388.55 1.1554 1.1394 1.2132 1.1937 1.20648.72 1.1485 1.1359 1.2089 1.1918 1.20078.89 1.1416 1.1439 1.2021 1.1897 1.19389.05 1.1486 1.1533 1.1961 1.1926 1.19029.22 1.1640 1.1601 1.2030 1.2002 1.19459.39 1.1797 1.1711 1.2164 1.2080 1.19979.56 1.1919 1.1952 1.2265 1.2143 1.21089.73 1.2041 1.2247 1.2389 1.2175 1.22369.89 1.2224 1.2501 1.2557 1.2235 1.230410.06 1.2425 1.2741 1.2764 1.2434 1.247210.23 1.2633 1.2979 1.2961 1.2645 1.266810.40 1.2838 1.3209 1.3116 1.2780 1.281910.56 1.2989 1.3418 1.3228 1.2815 1.286510.73 1.3123 1.3623 1.3357 1.2843 1.288810.90 1.3244 1.3779 1.3491 1.2898 1.294211.07 1.3268 1.3894 1.3606 1.2940 1.297711.23 1.0000 .1.0000 1.0000 1.0000 1.000011.40 1.0000 1.0000 1.0000 1.0000 1.000011.57 1.0000 1.0000 1.0000 1.0000 1.00001 1 .74 1 .0000 1 .0000 1 .0000 1 .0000 1.000011.90 1.0000 1.0000 1.0000 1.0000 1.0000

12.07 (top) 1.0000 1.0000 1.0000 1.0000 1.0000

9



‘ Table A.lbW(z) versus Core Height

for +8%/-12% RAOC Band(Top 8% and Bottom 6% Excluded at 150 MWD/MTU;


Height 150 5000 10000 14000 18000(feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU

0.00 (bottom) 10000 1.0000 1.0000 1.0000 1.00000.17 1.0000 1.0000 1.0000 1.0000 1.00000.34 1.0000 1.0000 1.0000 1.0000 1.00000.50 1.0000 1.0000 1.0000 1.0000 1.00000.67 1.0000 1.0000 1.0000 1.0000 1.00000.84 1.4173 1.0000 1.0000 1.0000 1.00001.01 1.4062 1.4535 1.3029 1.2617 1.27631.17 1.3930 1.4371 1.2920 1.2530 1.26721.34 1.3798 1.4197 1.2808 1.2444 1.25821.51 1.3656 1.4008 1.2684 1.2349 1.24871.68 1.3498 1.3800 1.2548 1.2246 1.23831.84 1.3325 1.3577 1.2404 1.2137 1.22762.01 1.3143 1.3342 1.2254 1.2025 1.21692.18 1.2956 1.3106 1.2101 1.1910 1.20562.35 1.2768 1.2865 1.1941 1.1783 1.19292.52 1.2582 1.2629 1.1781 1.1656 .17992.68 1.2392 1.2397 1.1628 1.1530 1.16752.85 1.2211 1.2158 1.1468 1.1423 1.5473.02 1.2086 1.1960 1.1368 1.1388 1.14423.19 1.2021 1.1852 1.1363 1.1398 1.14073.35 1.1943 1.1779 1.1344 1.1404 1.14233.52 1.1860 1.1700 1.1324 1.1408 1.14963.69 1.1782 1.1627 1.1301 1.1437 1.15873.86 1.1735 1.1587 1.1277 1.1490 1.16784.02 1.1698 1.1556 1.1274 1.1537 1.17524.19 1.1654 1.1519 1.1285 1.1570 1.18114.36 1.1608 1.1480 1.1287 1.1600 1.18634.53 1.1556 1.1436 1.1288 1.1624 1.19094.70 1.1500 1.1388 1.1285 1.1642 1.19474.86 1.1440 1.1338 1.1278 1.1653 1.19745.03 1.1378 1.1285 1.1267 1.1656 1.19905.20 1.1312 1.1223 1.1250 1.1651 1.19955.37 1.1298 1.1187 1.1238 1.1637 1.19935.53 1.1324 1.1176 1.1226 1.1628 1.19985.70 1.1367 1.1178 1.1224 1.1634 1.20305.87 1.1447 1.1203 1.1271 1.1681 1.20846.04 1.1520 1.1229 1.1349 1.1781 1.21716.20 1.1585 1.1248 1.1419 1.1892 1.22496.37 1.1637 1.1276 1.1480 1.1993 1.23176.54 1.1684 1.1329 1.1548 1.2083 1.23836.71 1.1722 1.1388 1.1612 1.2156 1.24286.87 1.1751 1.1440 1.1687 1.2214 1.2459

10



Table A.lbW(z) versus Core Height

for +8%/-12% RAOC Band(Top 8% and Bottom 6% Excluded at 150 MWD/MTU;


Height 150 5000 10000 14000 18000(feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU7.04 1.1763 1.1481 1.1760 1.2257 1.24747.21 1.1763 1.1514 1.1826 1.2288 1.24767.38 1.1754 1.1540 1.1885 1.2305 1.24627.55 1.1721 1.1542 1.1915 1.2282 1.24077.71 1.1680 1.1536 1.1937 1.2245 1.23387.88 1.1621 1.1518 1.1948 1.2192 1.22568.05 1.1544 1.1481 1.1946 1.2120 1.21568.22 1.1441 1.1456 1.1933 1.2024 1.20388.38 1.1407 1.1429 1.1905 1.1961 1.19048.55 1.1324 1.1394 1.1864 1.1866 1.18148.72 1.1249 1.1346 1.1810 1.1760 1.17728.89 1.1203 1.1327 1.1805 1.1741 1.17189.05 1.1211 1.1307 1.1808 1.1779 1.16979.22 1.1240 1.1268 1.1816 1.1807 1.17549.39 1.1349 1.1306 1.1862 1.1827 1.18429.56 1.1512 1.1397 1.1948 1.1935 1.19069.73 1.1666 1.1507 1.2043 1.2053 1.19519.89 1.1822 1.1667 1.2135 1.2132 1.201310.06 1.1964 1.1827 1.2223 1.2330 1.217910.23 1.2121 1.2007 1.2306 1.2542 1.237310.40 1.2280 1.2210 1.2381 1.2678 1.252610.56 1.2390 1.2399 1.2444 1.2716 1.257410.73 1.2484 1.2581 1.2504 1.2746 1.260010.90 1.2570 1.2725 1.2608 1.2803 1.265511.07 1.2567 1.2831 1.2734 1.2847 1.269211.23 . 1.0000 1.0000 1.0000 1.0000 1.000011.40 1.0000 1.0000 1.0000 1.0000 1.000011.57 1.0000 1.0000 1.0000 1.0000 1.00001 1 .74 1 .0000 1 .0000 1 .0000 1 .0000 1.000011.90 1.0000 1.0000 1.0000 1.0000 1.0000

12.07 (top) 1.0000 1.0000 1.0000 1.0000 1.0000

11



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

(Top 8% and Bottom 6% Excluded)** The W(z) 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)**

0.00 (bottom) 1.00000.17 1.00000.34 1.00000.50 1.00000.67 1.00000.84 1.70851.01 1.67881.17 1.65001.34 1.62211.51 1.59361.68 1.56371.84 1.53212.01 1.49772.18 1.46392.35 1.43282.52 1.40192.68 1.37082.85 1.33863.02 1.31203.19 1.29413.35 1.27473.52 1.25543.69 1.23633.86 1.22004.02 1.20554.19 1.19194.36 1.17814.53 1.16354.70 1.14834.86 1.13275.03 1.11715.20 1.10035.37 1.08935.53 1.08115.70 1.07775.87 1.08016.04 1.0820

12



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

(Top 8% and Bottom 6% 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 1.08146.37 1.08136.54 1.08456.71 1.08256.87 1.07817.04 1.07347.21 1.07417.38 1.08787.55 1.08387.71 1.06847.88 1.06048.05 1.05648.22 1.05798.38 1.05938.55 1.04958.72 1.04098.89 1.03249.05 1.03599.22 1.04689.39 1.06009.56 1.07049.73 1.08129.89 1.097010.06 1.113310.23 • 1.130910.40 1.148310.56 1.160510.73 1.171710.90 1.181911.07 1.183011.23 1.000011.40 1.000011.57 1.000011.74 1.000011.90 1.0000

12.07(top) 1.0000

13



TableA.3

FQ Penalty Factors as a Function of Cycle Burnup

Cycle 24 Burnup FQw(z) Penalty Factor (%)

150 2.00

493 2.00

665 2.08

837 3.23

1008 4.08

1180 3.58

1351 3.21

1523 2.95

1695 2.79

1866 2.70

2038 2.65

2210 2.61

2381 2.63

2553 2.82

2724 2.96

2896 3.04

3068 3.05

3239 3.00

3411 2.91

3583 2.78

3754 2.60

3926 2.22

4098 2.00

5127 2.00

5299 . 2.03

5471 2.13

5642 2.00

10619 2.00

10791 2.07

10963 2.05

11134 2.03

11306 2.00

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

For values of bumup between two of those listed in the first column, the greaterofthe two corresponding penalty factors shall be used for compliance withSurveillance Requirement 3.2.1.2.

14


CallawaY Cycle 24 REDESIGN COLR —

Revision 1

1.20

1.10

1.00

0 . 90

-.% 0.80

1x4

ci0.70

0.40

0.30

0.20

0.10

0.00

Figure 3

CallaWaY Cycle 24K(z) -

Normalized FQ(z)as a Function of Core Height

15

*** This record was final approved on 5/7/2019 1006:36 AM. (This statement was added by the PRIME system upon its validation)

0 1 2 3 5 6 7

CORE HEIGHT (FEET)

10 11 12


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

FAHN * UAH E F\HRTP [1 + PFAH(1 -P)]

THERMAL POWERwhere: P =

________________________

RATED THERMAL POWER

2.6.1 FAHRTP= 1.65

2.6.2 PFAH=O.3

2.6.3 The uncertainty, ULH, to be applied to measured FAH shall be 1 .04 when PDMS isinoperable (UAH 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 theplant is within the specified AFD band.

16

*** This record was final approved on 5/7/2019 10:06:36 AM. (This statementwas added by the PRIME system upon its validation)


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AXIAL FLUX DIFFERENCE (% DELTA-I)

Figure4a

Callaway Cycle 24Axial Flux Difference Limits as a Function of

Rated Thermal Power for RAOC Band +101-15%

17

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UNACCEPTABLEOPERATION

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100 -

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90 -

OPERATION

80

70

60

50

40

30

20

ACCEPTABLEOPERATION

(—30;; -

50-) (+26, 50%)

*** This record was final approved on 5/7/2019 1 0:06:36 AM. (This statement was added by the PRIME system upon its validation)

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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{l8%+(qt-qb)}

Where, q and q are percent RTP in the upper and lower halves ofthe core, respectively, andq + q 5 the total THERMAL POWER in percent RTP.

20

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

Parameter Value

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

K1 = 1.2260

K2 0.0l9/°F

K3 0.001 l/psig

T’<585.3 °F

F = 2235 psig

ti ?: 0 sect2 : 0 sec

t3 < 4 sec

t4>27sect5 : 4 sec

t6 :S 2 sec

when (q - q) < -1 8% RTP

when -18% RTP < (q - q) 10% RTP

when (q - q) > 10% RTP

0

0.0224 {(q - q) - lO%}

*** This record was final approved on 5/7/2019 10:06:36 AM. (This statementwas added bythe 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 Tavg 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.

2.1 1 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits(Specification 3.4.1)

Parameter

_______________

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Value

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K6 0.0015/°F for T > T”=0/°F for T<T’

T”<585.3°F

ti ?: 0 sec‘C2 :S 0 sec

t3 < 4 sec

t6 :E 2 sec

t7 : 10 sec

Indicated Value

?: 2195 psig

<590.1°F

21



APPENDIX A

Approved Analytical Methods for Determining Core Operating Limits

The analytical methods used to determine the core operating limits shall be those previouslyreviewed 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 ReportWCAP-9272(P)/9273(NP), ‘ Westinghouse Reload Safety Evaluation Methodology.”

2. WCAP-10216-P-A, Revision 1A, “Relaxation ofConstant Axial Offset Control - FQSurveillance Technical Specification,” February 1994.

NRC Safety Evaluation Report dated November 26, 1993, “Acceptance for Referencing ofRevised Version ofLicensing Topical Report WCAP-10216-P, Rev. 1, Relaxation ofConstant Axial Offset Control - FQ Surveillance Technical Specification”(TAC No. M88206).

3. WCAP-10266-P-A, Revision 2, “The 1981 Version ofthe Westinghouse ECCS EvaluationModel Using the BASH Code,” March 1987.

NRC letter dated November 13, 1986, “Acceptance for Referencing ofLicensing TopicalReport WCAP-10266 ‘The 1981 Version ofthe Westinghouse ECCS Evaluation ModelUsing the BASH Code.”

WCAP-10266-P-A, Addendum 1, Revision 2, “The 198 1 Version of the WestinghouseECCS Evaluation Model Using the BASH Code Addendum 1 : Power Shape SensitivityStudies,” December 1987.

NRC letter dated September 15, 1987, “Acceptance for Referencing ofAddendum 1 toWCAP-10266, BASH Power Shape Sensitivity Studies.”

WCAP-10266-P-A, Addendum 2, Revision 2, “The 1981 Version ofthe WestinghouseECCS Evaluation Model Using the BASH Code Addendum 2: BASH MethodologyImprovements and Reliability Enhancements,” May 1988.

NRC letter dated January 20, 1988, “Acceptance for Referencing Topical ReportAddendum 2 to WCAP-10266, Revision 2, ‘BASH Methodology Improvements andReliability Enhancements.”

WCAP-10266-P-A, Addendum 3, Revision 0, “Incorporation ofthe LOCBART TransientExtension Method into the 1981 Westinghouse Large Break LOCA Evaluation Model withBASH (BASH-EM),” December 2002 (cited as Reference 4.5 in the NRC SafetyEvaluation for Callaway License Amendment 168).

22



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

NRC Safety Evaluation Reports dated July 1, 1991, “Acceptance for Referencing ofTopical Report WCAP-126 1 0, ‘VANTAGE+ Fuel Assembly Reference Core Report’(TAC NO. 77258).”

NRC Safety Evaluation Report dated September 15, 1994, “Acceptance for Referencing ofTopical Report WCAP-12610, Appendix B, Addendum 1, ‘Extended Burnup Fuel DesignMethodology and ZIRLO Fuel Performance Models’ (TAC NO. M86416).”

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

NRC Safety Evaluation Report dated January 17, 1989, “Acceptance for Referencing ofLicensing Topical Report WCAP-11397, ‘Revised Thermal Design Procedure.”

6. WCAP-14565-P-A, “VIPRE-Ol Modeling and Qualification for Pressurized Water ReactorNon-LOCA Thermal-Hydraulic Safety Analysis,” October 1999.

NRC letter dated January 19, 1999, “Acceptance for Referencing ofLicensing TopicalReport WCAP-14565, ‘VIPRE-Ol Modeling and Qualification for Pressurized Water ReactorNon-LOCA Thermal/Hydraulic Safety Analysis’ (TAC No. M98666).”

7. WCAP-1085 1-P-A, “Improved Fuel Performance Models for Westinghouse Fuel RodDesign and Safety Evaluations,” August 1988.

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

8. WCAP-15063-P-A, Revision 1, with Errata, “Westinghouse Improved Performance Analysisand Design Model (PAD 4.0),” July 2000.

NRC letter dated April 24, 2000, “Safety Evaluation Related to Topical Report WCAP15063, Revision 1, ‘Westinghouse Improved Performance Analysis and Design Model (PAD4.0)’ (TAC NO. MA2086).”

9. WCAP-8745-P-A, “Design Bases for the Thermal Overpower AT and ThermalOvertemperature AT Trip Functions,” September 1986.

NRC Safety Evaluation Report dated April 17, 1 986, “Acceptance for Referencing ofLicensing Topical Report WCAP-8745(P)/8746(NP), ‘Design Bases for the ThermalOverpower AT and Thermal Overtemperature AT Trip Functions.”

23



10. WCAP-10965-P-A, “ANC: A Westinghouse Advanced Nodal Computer Code,” September1986.

NRC letter dated June 23 , 1986, “Acceptance for Referencing of Topical Report WCAP10965-P and WCAP 10966-NP.”

1 1 . WCAP-10965-P-A, Addendum 2-A, Revision 0, “Qualification ofthe New Pin PowerRecovery Methodology,” September, 2010.

NRC Safety Evaluation Report dated September 10, 2010, “FINAL SAFETYEVALUATION FOR WESTINGHOUSE ELECTRIC COMPANY TOPICAL REPORTWCAP- 1 0965-P-A, ADDENDUM 2/WCAP- 1 0966-A, ADDEN1JUM 2,“QUALIFICATION OF THE NEW PIN POWER RECOVERY METHODOLOGY,” (TACNO. ME1420).”

12. WCAP-13524-P-A, Revision 1-A, “APOLLO: A One Dimensional Neutron DiffusionTheory Program,” September 1997.

NRC letter dated June 9, 1997, “Acceptance for Referencing of Licensing Topical ReportsWCAP-13524 and WCAP-13524, Revision 1, ‘APOLLO — A One-Dimensional NeutronDiffusion Theory Program.”

13. WCAP-14565-P-A, Addendum 2-P-A, “Extended Application ofABB-NV Correlation andModified ABB-NV Correlation WLOP for PWR Low Pressure Applications,” April 2008.

14. WCAP-16045-P-A, Revision 0, “Qualification ofthe Two-Dimensional Transport CodePARAGON,” August 2004.

NRC letter dated March 1 8, 2004, “FINAL SAFETY EVALUATION FORWESTiNGHOUSE 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 DataMethodology,” August 2007.

NRC letter dated February 23, 2007, “FLNAL SAFETY EVALUATION FORWESTINGHOUSE ELECTRIC COMPANY (WESTINGHOUSE) TOPICAL REPORT(TR) WCAP-16045-P, ADDENDUM 1, ‘QUALIFICATION OF ThE NEXUS NUCLEARDATA METHODOLOGY’ (TAC NO. MC9606)”

24


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