ULNRC-06014, Core Operating Limits Report

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Core Operating Limits Report
ML13196A347
Person / Time
Site: Callaway Ameren icon.png
Issue date: 07/15/2013
From: Maglio S
Ameren Missouri, Union Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-06014
Download: ML13196A347 (29)
v • d • e


Text

~~

iiWAmeren Callaway Plant MISSOURI

July 15, 2013 ULNRC-060 14 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:

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

FACILITY OPERATING LICENSE NPF-30 CORE OPERATING LIMITS REPORT Please find enclosed the Callaway Plant Cycle 20 Core Operating Limits Report, dated July 5, 2013.

This revision addresses calculations associated with the new Pressurizer Pressure Transmitter, BBPT0457. The change is reflected in section 2.11 on page 21 ofthe 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 us.

Sincerely,

/-)tot-\ A.. v;?

Scott A. Maglio Regulatory Affairs Manager

Attachment:

Callaway Cycle 20 Core Operating Limits Report, dated July 5, 2013.

                                                                                                                                                                                                                                                  • PO Box 620 Fulton, MD 65251 AmerenMissouri.com

ULNRC-060 14 July 15, 2013 Page 2 cc: Mr. Arthur T. Howell Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738

ULNRC-060 14 July 15, 20 13 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (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 Responses and Reports ULNRC Distribution:

A. C. Heflin F. M. Diya C. 0. Reasoner III L. H. Graessle S. A. Maglio T. B. Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)

Attachment to ULNRC-060 14 Attachment Callaway Cycle 20 Redesign Core Operating Limits Report Dated July 5, 2013

E170.0130 Callaway Cycle 20 COLR REDESIGN Revision 1 Callaway Cycle 20 REDESIGN Core Operating Limits Report Revision 1 May2013 Edited by:

Gregory M. Core Approved: David J. Wotus, Manager Nuclear Design C Nuclear Fuel Core Engineering Electronically Approved Records Are Authenticated In the Electronic Document Management System Westinghouse Electric Company LLC I 000 Westinghouse Drive Cranberry Township, PA 16066 C2013 Westinghouse Electric Company LLC All Rights Reserved Reviewed by: -#~~-'2.~~/_ _. /_a. . :;.~. .;. .>. -.8_ _~/_ _-,~--/~7~0.....;.3;....__

Approved by: ----&/..,1!::;3:;.-=:£~8":......./ _ __..:/_"""z"'"/...:;~~,4:........p.J.:l.:..,__

Curve Book Figure 13*1, Rev 056

Callaway Cycle 20 COLR REDESIGN Revision 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 20 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 FM:J.N 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 Curve Book Figure 13-1, Rev. 058

Callaway Cycle 20 COLR REDESIGN Revision I 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 lSDMl (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% L\k/k.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-11 in MODES 3 and 4 shall be greater than 0% LYc/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 (MTCl (Specification 3.1.3) 2.2.1 The Moderator Temperature Coefficient shall be less positive than the limits shown in Figure I. These limits shall be referred to as 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 pcm/°F (all rods withdrawn, Rated Thermal Power condition).

2.2.3 The MTC 60 ppm surveillance limit is -45.5 pcrnfOF {all rods withdrawn, Rated Thennal Power condition).

2 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 7

~ UNACCEPTABLE OPERATION (70\, 5. 0)

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0 0 10 20 30 40 so 60 70 80 90 '

100 PBRCBNT 01' RATBD THBRIIAL POWER Figure 1 Callaway Cycle 20 Moderator Temperature Coefficient Versus Power Level 3

Curve Book Agure 13-1, Rev. 058

Callaway Cycle 20 COLR REDESIGN Revision I 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 115 steps when not fully inserted and not fully withdrawn.

4 Curve Book Figura 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 225 I (28,12S) I (78,225) I 1/ ~

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J (30.2, 0) 0 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 20 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 5

Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 2.5 Heat Flux Hot Cbannel Factor CFQ(z))

(Specification 3.2.1)

FQR:rP FQ(Z) ::S

  • K(Z) for P > 0.5 p

FQ(Z) =s - - -

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

RATED THERMAL POWER 2.5.1 FQIUP = 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 detennining FQw(z) are shown in Table A. Ia 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.1 b 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:

I. Confinn FQw(z) meets the Technical Specification Limit with the Table A.la W(z) values for the most recent surveillance perfonned.

2. Perfonn a new surveillance and confinn FQw(z) meets the Technical Specification Limit with the Table A. Ia W(z) values.

The W(z) values have been detennined for several bumups up to 20000 MWDIMTU in Cycle 20. This pennits detennination of W(z) at any cycle burnup up to 20000 MWD/MTU through the use of three point interpolation. For cycle bumups greater than 20000 MWDIMTU, use of20000 MWD/MTU W(z) values without extrapolation is conservative. The W(z) values were determined assuming Cycle 20 operates with RAOC strategy.

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

6 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 The W(z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is perfonned from beginning of cycle to 150 MWD/MTU and at 45% +!- 5% RTP, the W(z) values listed in Table A.2 should be used. When a part power surveillance is perfonned after 150 MWD/MTU, or at a power level other than the level specified above, the HFP W(z) values in Table A.laor A.1b should be used.

W(z) values should be adjusted by the factor 1/P, when Pis> 0.5. When Pis~

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

Table A.3 shows the bumup dependent FQ penalty factors for Cycle 20 which 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 TableA.3.

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

2.5.4 The uncertainty, UFQJ to be applied to measured F~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

Curve Book Agure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 TableA.la W(z) versus Core Height for+ 1Oo/o/-1 5% RAOC Band (Top 5% and Bottom 8% Excluded at ISO MWD/MTU; Top and Bottom 8% Excluded Remainder of Cycle)

Height 150 5000 10000 20000 (feet) MWDIMTU MWD/MTU MWDIMTU MWDIMTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.0000 1.01 1.3581 1.4110 1.3418 1.3137 1.17 1.3490 1.3976 1.3332 1.3063 1.34 1.3379 1.3811 1.3220 1.2967 1.51 1.3251 1.3625 1.3091 1.2859 1.68 1.3111 1.3425 1.2952 1.2745 1.84 1.2963 1.3214 1.2806 1.2626 2.01 1.2808 1.2996 1.2652 1.2503 2.18 1.2650 1.2771 1.2494 1.2377 2.35 1.2490 1.2546 1.2334 1.2249 2.52 1.2322 1.2333 1.2174 1.2118 2.68 1.2166 1.2121 1.2011 1.1988 2.85 1.2041 1.1919 1.1851 1.1858 3.02 1.1948 1.1803 1.1716 1.1703 3.19 1.1897 1.1750 1.1636 1.1622 3.35 1.1892 1.1709 1.1618 1.1637 3.52 1.1892 1.1677 1.1608 1.1667 3.69 1.1892 1.1647 1.1591 1.1727 3.86 1.1887 1.1610 1.1572 1.1834 4.03 1.1876 1.1563 1.1564 1.1937 4.19 1.1858 1.1522 1.1560 1.2023 4.36 1.1834 1.1498 1.1549 1.2102 4.53 1.1802 1.1468 1.1531 1.2169 4.70 1.1764 1.1430 1.1508 1.2223 4.86 1.1718 1.1389 1.1479 1.2264 5.03 1.1666 1.1341 1.1443 1.2292 5.20 1.1608 1.1291 1.1404 1.2300 5.37 1.1544 1.1235 1.1362 1.2297 5.54 1.1467 1.1158 1.1306 1.2316 5.70 1.1456 1.1122 1.1303 1.2355 5.81 1.1556 1.1170 1.1394 1.2399 6.04 1.1665 1.1232 1.1494 1.2464 6.21 1.1757 1.1299 1.1578 1.2530 8

Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 Table A. Ia W(z) versus Core Height for+IOo/o/-15% RAOC Band (Top 5% and Bottom 8% Excluded at ISO MWD/MTU; Top and Bottom 8% Excluded Remainder of Cycle)

Height 150 5000 10000 20000 (feet) MWDIMTU MWDIMTU MWD/MTU MWDIMTU 6.37 1.1841 1.1386 1.1654 1.2577 6.54 1.1921 1.1478 1.1727 1.2609 6.71 1.1996 1.1572 1.1800 1.2644 6.88 1.2064 1.1666 1.1875 1.2686 7.05 1.2119 1.1752 1.1956 1.2711 7.21 1.2160 1.1825 1.2032 1.2715 7.38 1.2187 1.1886 1.2093 1.2701 1.55 1.2199 1.1934 1.2141 1.2668 7.72 1.2194 1.1968 1.2176 1.2615 7.88 1.2172 1.1987 1.2196 1.2545 8.05 1.2133 1.1990 1.2201 1.2459 8.22 1.2074 1.1975 1.2190 1.2346 8.39 1.1997 1.1941 1.2165 1.2219 8.55 1.1916 1.1911 1.2128 1.2146 8.72 1.1838 1.1911 1.2062 1.2121 8.89 1.1786 1.1955 1.2044 1.2098 9.06 1.1807 1.2108 1.2186 1.2045 9.23 1.1862 1.2390 1.2459 1.2045 9.39 1.1907 1.2719 1.2682 1.2155 9.56 1.1978 1.3046 1.2897 1.2261 9.73 1.2074 1.3361 1.3110 1.2340 9.90 1.2179 1.3667 1.3310 1.2418 10.06 1.2299 1.3959 1.3499 1.2523 10.23 1.2473 1.4248 1.3675 1.2651 10.40 1.2715 1.4541 1.3833 1.2786 10.57 1.2966 1.4822 1.3974 1.2905 10.74 1.3211 1.5051 1.4099 1.3029 10.90 1.3458 1.5211 1.4206 1.3165 11.07 1.3704 1.5362 1.4286 1.3260 11.24 1.3898 1.0000 1.0000 1.0000 11.41 1.3944 1.0000 1.0000 1.0000 11.57 1.0000 1.0000 1.0000 1.0000 11.74 1.0000 1.0000 1.0000 1.0000 11.91 1.0000 1.0000 1.0000 1.0000 12.08 (top) 1.0000 1.0000 1.0000 1.0000 9

Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision I TableA.lb W(z) versus Core Height for +So/o/-12% RAOC Band (fop and Bottom 8% Excluded)

Height 150 5000 10000 20000 (feet) MWD/MTU MWDIMTU MWD/MTU MWDIMTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.0000 1.01 1.3024 1.3295 1.2834 1.2568 1.17 1.2945 1.3182 1.2758 1.2502 1.34 1.2846 1.3041 1.2657 1.2415 1.51 1.2733 1.2882 1.2542 1.2317 1.68 1.2610 1.2711 1.2418 1.2214 1.84 1.2480 1.2532 1.2287 1.2106 2.01 1.2346 1.2346 1.2151 1.1995 2.18 1.2208 1.2156 1.2011 1.1883 2.35 1.2070 1.1966 1.1871 1.1769 2.52 1.1932 1.1784 1.1732 1.1652 2.68 1.1787 1.1624 1.1589 1.1541 2.85 1.1645 1.1502 1.1450 1.1434 3.02 1.1564 1.1431 1.1353 1.1311 3.19 1.1542 1.1395 1.1319 1.1263 3.35 1.1543 1.1369 1.1324 1.1351 3.52 1.1559 1.1346 1.1327 1.1467 3.69 1.1582 1.1326 1.1326 1.1577 3.86 1.1597 1.1312 1.1328 1.1683 4.03 1.1608 1.1302 1.1337 1.1783 4.19 1.1613 1.1292 1.1349 1.1874 4.36 1.1611 1.1276 1.1355 1.1956 4.53 1.1604 1.1255 1.1356 1.2028 4.70 1.1590 1.1230 1.1353 1.2087 4.86 1.1570 1.1200 1.1344 1.2134 5.03 1.1544 1.1163 1.1330 1.2169 5.20 1.1510 1.1129 1.1310 1.2188 5.37 1.1471 1.1111 1.1287 1.2193 5.54 1.1453 1.1113 1.1286 1.2204 5.70 1.1460 1.1142 1.1299 1.2225 5.87 1.1557 1.1197 1.1360 1.2261 6.04 1.1662 1.1259 1.1444 1.2336 6.21 1.1756 1.1322 1.1527 1.2421 10 Curve Book Agure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 Table A.1b W(z) versus Core Height for +8%/-12% RAOC Band (Top and Bottom 8% Excluded)

Height 150 5000 10000 20000 (feet) MWDIMTU MWD/MTU MWD/MTU MWDIMTU 6.37 1.1841 1.1389 1.1597 1.2484 6.54 1.1916 1.1475 1.1666 1.2541 6.71 1.1979 1.1573 1.1733 1.2587 6.88 1.2030 1.1667 1.1790 1.2612 7.05 1.2068 1.1753 1.1836 1.2619 7.21 1.2092 1.1826 1.1869 1.2606 7.38 1.2100 1.1888 1.1887 1.2574 7.55 1.2091 1.1936 1.1891 1.2521 7.72 1.2066 1.1971 1.1880 1.2447 7.88 1.2022 1.1990 1.1853 1.2353 8.05 1.1957 1.1994 1.1804 1.2238 8.22 1.1877 1.1977 1.1751 1.2101 8.39 1.1783 1.1944 1.1700 1.1955 8.55 1.1663 1.1920 1.1609 1.1844 8.72 1.1525 1.1894 1.1605 1.1810 8.89 1.1413 1.1885 1.1772 1.1826 9.06 1.1421 1.1953 1.1949 1.1841 9.23 1.1488 1.2142 1.2100 1.1887 9.39 1.1530 12398 1.2248 1.2097 9.56 1.1566 1.2650 1.2388 12307 9.73 1.1613 1.2886 1.2517 1.2491 9.90 1.1696 1.3113 1.2638 1.2674 10.06 1.1869 1.3328 1.2751 1.2847 10.23 1.2080 1.3541 1.2850 1.3006 10.40 1.2268 1.3759 1.2956 1.3150 10.57 1.2463 1.3965 1.3146 1.3278 10.74 1.2663 1.4121 1.3365 1.3392 10.90 1.2860 1.4217 1.3530 1.3491 11.07 1.3056 1.4315 1.3652 1.3560 11.24 1.0000 1.0000 1.0000 1.0000 11.41 1.0000 1.0000 1.0000 1.0000 11.57 1.0000 1.0000 1.0000 1.0000 11.74 1.0000 1.0000 1.0000 1.0000 11.91 1.0000 1.0000 1.0000 1.0000 12.08 (top) 1.0000 1.0000 1.0000 1.0000 II CuNe Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision I TableA.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWD/MTU, D-bank at 185 steps)

(Top 5% and Bottom 8o/o Excluded)

    • The W(z) 's are not increased by the nominal power 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 1feetl 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 1.5365 1.17 1.5179 1.34 1.4971 1.51 1.4741 1.68 1.4485 1.84 1.4223 2.01 1.3959 2.18 1.3702 2.35 1.3447 2.52 1.3187 2.68 1.2941 2.85 1.2730 3.02 1.2555 3.19 1.2425 3.35 1.2344 3.52 1.2269 3.69 1.2195 3.86 1.2113 4.03 1.2027 4.19 1.1937 4.36 1.1840 4.53 1.1739 4.70 1.1636 4.86 1.1525 5.03 1.1414 5.20 1.1302 5.37 1.1194 5.54 1.1077 5.70 1.1023 5.87 1.1075 6.04 1.1132 12 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 TableA.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWD/MTU, D-bank at 185 steps)

(Top 5% and Bottom 8% Excluded)

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

6.21 1.1172 6.37 1.1198 6.54 1.1217 6.71 1.1235 6.88 1.1249 7.05 1.1254 7.21 1.1250 7.38 1.1234 7.55 1.1206 7.72 1.1168 7.88 1.1118 8.05 1.1055 8.22 1.0980 8.39 1.0895 8.55 1.0810 8.72 1.0736 8.89 1.0693 9.06 1.0725 9.23 1.0794 9.39 1.0861 9.56 1.0978 9.73 1.1117 9.90 1.1251 10.06 1.1383 10.23 1.1551 10.40 1.1769 10.57 1.1964 10.74 1.2133 10.90 1.2317 11.07 1.2502 11.24 1.2649 11.41 1.2740 11.57 1.0000 11.74 1.0000 11.91 1.0000 12.08 {to_p) 1.0000 13 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 TableA.3 FQ Penalty Factors as a Function of Cycle Bumup Cycle 20 Burnuo Fgw(z) Penalty Factor(%)

5639 2.00 5811 2.11 5982 2.05 6154 2.00 7183 2.00 7355 2.05 7526 2.13 7698 2.20 7869 2.25 8041 2.11 8212 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 ofbumup 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 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 1.20 1.10 1

(0, 1.00) (6, 1.00)1 I (12,

  • 925) ~

1.00 0.90

--2' N

0.80 0.70

=

H I*I 0.60 0.50 I'Q B1evation (~t.) K(z) 2.50 0.0 1.00

--N 2.50 6.0 1.00 k: 0.40 2.31 12.0 0.925 0.30 0.20 0.10 0.00 0 1 2 3 4 5 6 7 8 9 10 11 12 CORB BBI:Gft (I'BBT)

Figure 3 Callaway Cycle 20 K(z) - Normalized Fg(z) as a Function of Core Height 15 CuMt Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 2.6 Nuclear Enthalpy Rise Hot Channel factor &Ji (Specification 3.2.2)

F4HN

  • u4H =s F4HaTP [1 + PF4H(1-P)J THERMAL POWER where: P =

RATED THERMAL POWER 2.6.1 p4HRTP = 1.65 2.6.2 PF4H = 0.3 2.6.3 The uncertainty, U4}1, to be applied to measured F4H shall be 1.04 when PDMS is inoperable (U4H 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 confinned that the plant is within the specified AFD band.

16 Curve Book Figure 13-1, Rev. 058

Callaway Cycle 20 COLR REDESIGN Revision 1 120 110

-* (-15,__ 100%) lJ (+10 1 100%) I 100 I I I *I II

-r- r---

r- .....

-r-UNACCEPTABLE \

UNACCEPTABLE -r--

r-r--

90

-r-

-I-OPERATION II 1\ OPERATION r-r-'-

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60 ,I ~

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I II ll 50

(-30, 50%) (+26 50%, I 40 30 20 10 0

-so -4o -3o -20 -1o 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (% DELTA-I)

Figure 4a Callaway Cycle 20 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +101-15%

17 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 120 110

(-12, 100%) I L

(+8' 100%)

I 100

-- II --

--

f--

f--

UNACCEPTABLE ' UNACCEPTABLE f--

f-- OPERATION ~ OPERATION f--

90 f--

" f-f-I 80 I

II I'1

~

ACCEPTABLE

'*_,

I 10 II I

OPERATION

~

60 I '

...

0 50 I '

(-27' 50%) (+24, 50%)1 I 40 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DII'I'BRBNCE (% DBL!l'A-I)

Figure 4b Callaway Cycle 20 Alternate Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +8/-12°At 18 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision I 2.8 Reactor Core SLs (Safety Limit 2.1.1)

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

Unacceptable 660 Operation

-

' f-.

I 0'\

640

--

-o

620 I

I--

(/)

u

~

600 Acceptable 580 Operation sro~~~~----~~~--~-----+----~~~--~~~~

0 o.2 0.4 0.6 0.8 t 1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 5 Callaway Cycle 20 Reactor Core Safety Limits 19 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision I 2.9 Reactor Trip System Overtemperature AT Setooint Parameter Values (Specification 3.3 .I)

Parameter Value Overtemperature ~T reactor trip setpoint K1 = 1.2260 Overtemperature ~T reactor trip setpoint Tava coefficient Overtemperature ~T reactor trip setpoint pressure coefficient K3 = 0.00 11/psig Nominal Tavs at RTP T' ~ 585.3 Of Nominal RCS operating pressure P' = 2235 psig Measured RCS AT lead/lag time constants t1 ~ 0 sec t2:S 0 sec Measured RCS AT lag time constant t3 :S 4 sec Measured RCS average temperature lead/lag time constants 4~27sec ts ~4 sec Measured RCS average temperature lag time constant t6:S 2 sec fl(M) = -0.0280 {18% +('It- Qb)} when(qt- qb) <-18% RTP 0 when -18% RTP ~ (qt- qb) :S 10% RTP 0.0224 {(qt- Qb)- 10%} when (qt- Qb) > 10% RTP Where, q1 and Qb are percent RTP in the upper and lower halves of the core, respectively, and qt + Qb is the total THERMAL POWER in percent RTP.

20 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 2.10 Reactor Trip System Ovemower ~T Setooint Parameter Values (Specification 3.3 .1)

Parameter . .L.Y=al=u:s.e_ _ _ _ _ __

Overpower ~T reactor trip setpoint K.. = 1.1073 Overpower ~T reactor trip setpoint Tavs rate/lag coefficient K5 = 0.02/°F for increasing Tavs

= 0/°F for decreasing Tavs Overpower ~T reactor trip setpoint Tav1 heatup coefficient ~ = 0.0015fOF forT> T"

= 0/°F forT~ T" Nominal T." at RTP T" ~ 585.3°F Measured RCS ~T lead/lag time constants t 1 .2= 0 sec t2~ 0 sec Measured RCS ~T lag time constant t3 ~ 4 sec Measured RCS average temperature lag time constant t6 ~ 2 sec Measured RCS average temperature rate/lag time constant t 7 .2= 10 sec f2(M) = 0 for all .11.

2.11 RCS Pressure and Temoerature Departure from Nucleate Boiling IDNBl Limits (Specification 3.4.1)

Parameter Indicated Value Pressurizer pressure ii!:2224 psig RCS average temperature :S590.1 °F 21 CUrve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1 APPENDIX A Aooroyed Analytical Methods for Detennining Core Ooerating Limits The analytical methods used to detennine 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-1 0216-P-A, Revision lA, "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-1 0266, BASH Power Shape Sensitivity Studies."

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

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

22 CuNe Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1

4. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April1995.

NRC Safety Evaluation Reports dated July 1, 1991, "Acceptance for Referencing of Topical Report WCAP-12610, 'VANTAGE+ Fuel Assembly Reference Core Report' (TAC NO. 77258)."

NRC Safety Evaluation Report dated September 15, 1994, "Acceptance for Referencing of Topical Report WCAP-12610, Appendix B, Addendum 1, 'Extended Bumup Fuel Design Methodoiogy and ZIRLO Fuel Performance Models' {TAC NO. M86416)."

5. WCAP-11397-P-A, Revised Thermal Design Procedure," April1989.

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

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

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

1. WCAP-10851-P-A, "Improved Fuel Perfonnance 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 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 Curve Book Figure 13-1, Rev. 056

Callaway Cycle 20 COLR REDESIGN Revision 1

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-11596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for Presswized Water Reactor Cores," June 1988.

NRC Safety Evaluation Report dated May 17, I 988, "Acceptance for Referencing of Westinghouse Topical Report WCAP-11596- Qualification ofthe 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-13524 and WCAP-13524, Revision l, 'APOLLO-A One-Dimensional Neutron Diffusion Theory Program."'

24 Curve Book Figure 13-1, Rev. 056

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