ULNRC-06039, Core Operating Limits Reports
| ML13259A024 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/13/2013 |
| From: | Maglio S Ameren Missouri |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-06039 | |
| Download: ML13259A024 (28) | |
Text
~~
VAmeren MISSOURI September 13, 20 13 ULNRC-06039 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 Callaway Plant Please find enclosed the Callaway Plant Cycle 20 Core Operating Limits Report Revision 2, dated September 5, 2013. This revision addresses calculations associated with the new Pressurizer Pressure Uncertainty of +30/-60 psi. The change is reflected in section 2.11 on page 21 of the 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, A~t{A. ~)
Scott A. Magli~
Regulatory Affairs Manager
Attachment:
Callaway Cycle 20 Core Operating Limits Report Revision 2, dated September 5, 2013.
PO Box 620 Fulton, MD 65251 AmerenMissouri.com
ULNRC-06039 September 13, 2013 Page2 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 Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office ofNuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738
ULNRC-06039 September 13,2013 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-06039 Page 1 of25 Callaway Cycle 20 COLR Approved:
Callaway Cycle 20 Core Operating Limits Report Revisionl August2013 Edited by:
Christopher S. Trunick David J. Wotus, Manager Nuclear Design C Nuclear Fuel Core Engineering E170.0130 Revision2 /
Electronically Approved Records Are Authenticated in the Electronic Document Management System Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066
©2013 Westinghouse Electric Company LLC All Rights Reserved
========-
Reviewed by: ~._j/<rllti I __
___:/ 1/>-#j Approved by: ~
36S ;<_
I I * /D Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 2 of25 E170.0130 Callaway Cycle 20 COLR Revision 2 I 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 F t:.HN 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 Cu!Ve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 3 of25 E170.0130 Callaway Cycle 20 COLR Revision2 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 (SD:M)
(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% Aklk.
2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-11 in MODES 3 and 4 shall be greater than 0% Aklk: as calculated at 200°F.
2.1.3 The Shutdown Margin in MODE 5 shall be greater than or equal to 1.0% Aklk.
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 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 pcmi"F (all rods withdrawn, Rated Thennal Power condition).
2.2.3 The MTC 60 ppm surveillance limit is -45.5 pcm/°F (all rods withdrawn, Rated Thennal Power condition).
2 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 4 of25 Callaway Cycle 20 COLR 7
1 0
0 10 UNACCEPTABLE OPERATION (70%,
1\\
I' ACCEPTABLE OPERATION 20 30 40 so 60 70 PERCENT OF RATED THERMAL POWER Figure 1 Callaway Cycle 20 Moderator Temperature Coefficient Versus Power Level 3
Curve Book Figure 13-1, Rev 057
\\
E170.0130 Revision2 I 5.0)
\\
I' 1\\
1\\
~
\\
\\
80 90 100
Attachment to ULNRC-06039 Page 5 of25 Callaway Cycle 20 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.
E170.0130 Revision 2 I 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 Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 6 of25 Callaway Cycle 20 COLR
....... ! B
~
til PI 1!11 E-1 til
~
H E-1 H
til 0
~
Ill
~
225 200 175
/
II I
0 (0, 161) 150 125 100 75 so 25 0
0 I.I 1/
II (0, 46) 10 E170.0130 Revision2 I II (28, ZZ5)
~ u (78,225) v v
v II' BANK B j
I.I 1/
II (100, 161) v II' II' BANK c IL II ll II v
v v
BANK D I.I 1.1 v
v (30.Z, 0) 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 057
Attachment to ULNRC-06039 Page 7 of25 E170.0130 Callaway Cycle 20 COLR 2.5 Heat Flux Hot Channel Factor (FO(z))
(Specification 3.2.1)
FQRTP FQ(Z) ~
- K(Z) for P > 0.5 p
FQ(Z)~ ---
- K(Z) for P ~ 0.5 0.5 THERMM., POWER where:
P =
RATED TIIERMAL POWER 2.5.1 FQRTP = 2.50.
2.5.2 K(Z) is provided in Figure 3.
Revision2 I 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 w(z} are shown in Table A.la and A. lb.*"' The W(z) functions shown in Table A.la are only applicable to Figure 4a. The W(z) functions shown in Table A. I 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, FQ w(z) must be con:finned to meet Technical Specification requirements by one of the following methods:
- 1.
Confirm FQ w(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. Ia W(z) values.
The W(z) values have been determined for several burnups up to 20000 MWDIMTU in Cycle 20. This permits determination ofW(z) at any cycle bumup up to 20000 MWDIMTU through the use of three point interpolation. For cycle burnups greater than 20000 MWD/MTU, use of 20000 MWDIMTU 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 057
Attachment to ULNRC-06039 Page 8 of25 E170.0130 Callaway Cycle 20 COLR Revision21
. 2.5.4 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 MWDIMTU and at 45% +/- 5% RTP, the W(z) values listed in Table A.2 should be used. When a part power surveillance is performed after 150 MWDIMTIJ, or at a power level other than the level specified above, the HFP W(z) values in Table A.la or 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 FQ(z) limit at part power conditions.
Table A.3 shows1he bumup dependent FQ penalty.factors for Cycle 20 which are applicable to both Figures 4a and 4b. These values shall be used to increase FQ w(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 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.
The uncertainty, UFQ* to be applied to measured FQ(Z) shall be calculated by the following UFQ=Uqu
- u.
where:
Uqu =Base FQ measurement uncertainty= 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE)
- u. = Engineering uncertainty factor= 1.03 7
Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 9 of25 Callaway Cycle 20 COLR TableA.la W(z) versus Core Height for +lOo/o/-15% RAOC Band (Top 5% and Bottom 8% Excluded at 150 MWDIMTU; Top and Bottom 8% Excluded Remainder of Cycle)
Height 150 5000 10000 (feet)
MWDIMTU MWD/MTU MWD/MTU 0.00 (bottom) 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 0.34 1.0000 1.0000 1.0000 0.50 1.0000-1.0000 1.0000 0.67 1.0000 1.0000 1.0000 0.84 1.0000 1.0000 1.0000 1.01 1.3581 1.4110 1.3418 1.17 1.3490 1.3976 1.3332 1.34 1.3379 1.3811 1.3220 1.51 1.3251 1.3625 1.3091 1.68 1.3111 1.3425 1.2952 1.84 1.2963 1.3214 1.2806 2.01 1.2808 1.2996 1.2652 2.18 1.2650 1.2771 1.2494 2.35 1.2490 1.2546 1.2334 2.52 1.2322 1.2333 1.2174 2.68 1.2166 1.2121 1.2011 2.85 1.2041 1.1919 1.1851 3.02 1.1948 1.1803 1.1716 3.19 1.1897 1.1750 1.1636 3.35 1.1892 1.1709 1.1618 3.52 1.1892 1.1677 1.1608 3.69 1.1892 1.1647 1.1591 3.86 1.1887 1.1610 1.1572 4.03 1.1876 1.1563 1.1564 4.19 1.1858 1.1522 1.1560 4.36 1.1834 1.1498 1.1549 4.53 1.1802 1.1468 1.1531 4.70 1.1764 1.1430 1.1508 4.86 1.1718 1.1389 1.1479 5.03 1.1666 1.1341 1.1443 5.20 1.1608 1.1291 1.1404 5.37 1.1544 1.1235 1.1362 5.54 1.1467 1.1158 1.1306 5.70 1.1456 1.1122 1.1303 5.87 1.1556 1.1170 1.1394 6.04 1.1665 1.1232 I.1494 6.21 1.1757 1.1299 1.1578 8
Curve Book Figure 13-1, Rev 057 El70.0130 Revision2 /
20000 MWDIMTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3137 1.3063 1.2967 1.2859 1.2745 1.2626 1.2503 1.2377 1.2249 1.2118 1.1988 1.1858 1.1703 1.1622 1.1637 1.1667 1.1727 1.1834 1.1937 1.2023 1.2102 1.2169 1.2223 1.2264 1.2292 1.2300 1.2297 1.2316 1.2355 1.2399 1.2464 1.2530
Attachment to ULNRC-06039 Page 10 of25 Callaway Cycle 20 COLR Height (feet) 6.37 6.54 6.71 6.88 7.05 7.21 7.38 7.55 7.72 7.88 8.05 8.22 8.39 8.55 8.72 8.89 9.06 9.23 9.39 9.56 9.73 9.90 10.06 10.23 10.40 10.57 10.74 10.90 11.07 11.24 11.41 11.57 11.74 11.91 12.08 (toJ>)
TableA.la W(z) versus Core Height for+ 10%/-15% RAOC Band (Top 5% and Bottom 8% Excluded at 150 MWDIMTU; Top and Bottom 8% Excluded Remainder of Cycle) 150 5000 10000 MWD/MTU MWD/MTU MWD/MTU 1.1841 1.1386 1.1654 1.1921 1.1478 1.1727 1.1996 1.1572 1.1800 1.2064-1.1666 1.1875 1.2119 1.1752 1.1956.
1.2160 1.1825 1.2032 1.2187 1.1886 1.2093 1.2199 1.1934 1.2141 1.2194 1.1968 1.2176 1.2172 1.1987 1.2196 1.2133 1.1990 1.2201 1.2074 1.1975 1.2190 1.1997 1.1941 1.2165 1.1916 1.1911 1.2128 1.1838 1.1911 1.2062 1.1786 1.1955 1.2044 1.1807 1.2108 1.2186 1.1862 1.2390 1.2459 1.1907 1.2719 1.2682 1.1978 1.3046 1.2897 1.2074 1.3361 1.3110 1.2179 1.3667 1.3310 1.2299 1.3959 1.3499 1.2473 1.4248 1.3675 1.2715 1.4541 1.3833 1.2966 1.4822 1.3974 1.3211 1.5051 1.4099 1.3458 1.5211 1.4206 1.3704 1.5362 1.4286 1.3898 1.0000 1.0000 1.3944 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 9
Curve Book Figure 13-1, Rev 057 El70.0130 Revision 2 I 20000 MWDIMTU 1.2577 1.2609 1.2644 1.2686 1.2711 1.2715 1.2701 1.2668 1.2615 1.2545 1.2459 1.2346 1.2219 1.2146 1.2121 1.2098 1.2045 1.2045 1.2155 1.2261 1.2340 1.2418 1.2523 1.2651 1.2786 1.2905 1.3029 1.3165 1.3260 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
Attachment to ULNRC-06039 Page 11 of25 Callaway Cycle 20 COLR Height (feet) 0.00 (bottom) 0.17 0.34 0.50 0.67 0.84 1.01 1.17 1.34 1.51 1.68 1.84 2.01 2.18 2.35 2.52 2.68 2.85 3.02 3.19 3.35 3.52 3.69 3.86 4.03 4.19 4.36 4.53 4.70 4.86 5.03 5.20 5.37 5.54 5.70 5.87 6.04 6.21 TableA.lb W(z) versus Core Height for +8%/-12% RAOC Band (Top and Bottom 8% Excluded) 150 5000 10000 MWD/MTU MWDIMTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000-1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3024 1.3295 1.2834 1.2945 1.3182 1.2758 1.2846 1.3041 1.2657 1.2733 1.2882 1.2542 1.2610 1.2711 1.2418 1.2480 1.2532 1.2287 1.2346 1.2346 1.2151 1.2208 1.2156 1.2011 1.2070 1.1966 1.1871 1.1932 1.1784 1.1732 1.1787 1.1624 1.1589 1.1645 1.1502 1.1450 1.1564 1.1431 1.1353 1.1542 I.l395 1.1319 1.1543 1.1369 1.1324 1.1559 1.1346 1.1327 1.1582 1.1326 1.1326 1.1597 1.1312 1.1328 1.1608 1.1302 1.1337 1.1613 1.1292 1.1349 1.1611 1.1276 1.1355 1.1604 1.1255 1.1356 1.1590 1.1230 1.1353 1.1570 1.1200 1.1344 1.1544 1.1163 1.1330 1.1510 1.1129 1.1310 1.1471 1.1111 1.1287 1.1453 1.1113 1.1286 1.1460 1.1142 1.1299 1.1557 1.1197 1.1360 1.1662 1.1259 1.1444 1.1756 1.1322 1.1527 10 Curve Book Figure 13-1, Rev 057 E170.0130 Revision2 I 20000 MWDIMTU 1.0000 1.0000 1.0000
.1.0000 1.0000 1.0000 1.2568 1.2502 1.2415 1.2317 1.2214 1.2106 1.1995 1.1883 1.1769 1.1652 1.1541 1.1434 1.1311 1.1263 1.1351 1.1467 1.1577 1.1683 1.1783 1.1874 1.1956 1.2028 1.2087 1.2134 1.2169 1.2188 1.2193 1.2204 1.2225 1.2261 1.2336 1.2421
Attachment to ULNRC-06039 Page 12 of25 Callaway Cycle 20 COLR Height (feet) 6.37 6.54 6.71 6.88 7.05 7.21 7.38 7.55 7.72 7.88 8.05 8.22 8.39 8.55 8.72 8.89 9.06 9.23 9.39 9.56 9.73 9.90 10.06 10.23 10.40 10.57 10.74 10.90 11.07 11.24 11.41 11.57 11.74 11.91 12.08 (top)
Table A.lb W(z) versus Core Height for +So/o/-12% RAOC Band (Top and Bottom 8% Excluded) 150 5000 10000 MWDIMTU MWDIMTU MWD/MTU 1.1841 1.1389 1.1597 1.1916 1.1475 1.1666 1.1979 1.1573 1.1733 1.2030 1.1667 1.1790 1.2.068-1.1753 1.1836 1.2092 1.1826 1.1869 1.2100 1.1888 1.1887 1.2091 1.1936 1.1891 1.2066 1.1971 1.1880 1.2022 1.1990 1.1853 1.1957 1.1994 1.1804 1.1877 1.1977 1.1751 1.1783 1.1944 1.1700 1.1663 1.1920 1.1609 1.1525 1.1894 1.1605 1.1413 1.1885 1.1772 1.1421 1.1953 1.1949 1.1488 1.2142 1.2100 1.1530 1.2398 1.2248 1.1566 1.2650 1.2388 1.1613 1.2886 1.2517 1.1696 1.3113 1.2638 1.1869 1.3328 1.2751 1.2080 1.3541 1.2850 1.2268 1.3759 1.2956 1.2463 1.3965 1.3146 1.2663 1.4121 1.3365 1.2860 1.4217 1.3530 1.3056 1.4315 1.3652 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 II Curve Book Figure 13-1, Rev 057 E170.0130 Revision2 I 20000 MWDIMTU 1.2484 1.2541 1.2587 1.2612 1.2619 1.2606 1.2574 1.2521 1.2447 1.2353 1.2238 1.2101 1.1955 1.1844 1.1810 1.1826 1.1841 1.1887 1.2097 1.2307 1.2491 1.2674 1.2847 1.3006 1.3150 1.3278 1.3392 1.3491 1.3560 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
Attachment to ULNRC-06039 Page 13 of25 Callaway Cycle 20 COLR Table A.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWDIMTU, D-bank at 185 steps)
(Top 5% and Bottom 8% Excluded)
E170.0130 Revision2 I
- The W(z) 's are not increased by the nominal power ratio. In order to be applicable, the W(z) 's must be adjusted for relative power per Section 2.5.3 at the time of the 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 1.5365 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 057
Attachment to ULNRC-06039 Page 14 of25 Callaway Cycle 20 COLR TableA.2 W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWDIMTU, D-bank at 185 steps)
(Top 5% and Bottom 8% Excluded)
E170.0130 Revision2 I
- The W(z) 's are not increased by the nominal power ratio. In order to be applicable, the W(z) 's must be adjusted for relative power per Section 2.5.3 at the time of the 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 (top) 1.0000 13 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 15 of25 E170.0130 Callaway Cycle 20 COLR Revision2 I TableA.3 FQ Penalty Factors as a Function of Cycle Bumup Cycle 20 Bumup Fg w(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 ofburnup 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 057
Attachment to ULNRC-06039 Page 16 of25 Callaway Cycle 20 COLR (0, 1.00) 1.00
_L i
_L E170.0130 Revision2 I (6, 1.00)
(12,.925)
.... 0. 80 ++-H-+-++~-++++!-++++-1-++++-1-+++-Hf-++++H-1-++H-+++-~-++++!-++-i-1-l+++-l N
'I 2'
9 0.70 I.
i I 1
o. 60 ++++-1-H-+.-HH-t~H-t-+t-H-t+t-1-H++t-H-t+-H-i-t+++-1-+t+-HH-++-t-iH-t-++-H++i
- t FQ Elevation (ft.)
0. 50 t.~~+.~i+t.tt+tt12. 50
- 0. 0 K(z) 1.00 1.00 0.925 N -
Ill::
0.40 0.30 0.20 0.10 1-+t-H-H' '-t+t-H++H 2. 50
~-T-' +-' ;-;l '-+++++-++H 2. 31 6.0 12.0
'J.
- _l
.. I :, :_1
'_l
.... i '.
0 1
2 i: '.I
. :I 3
4 5
6 7
CORE HEIGHT (FEET)
Figure 3 Callaway Cycle 20 K(z) - Normalized Fa(z) 8 as a Function of Core Height 15 Curve Book Figure 13-1, Rev 057 I:,
, L I.!.
I I.
9 10 11 12
Attachment to ULNRC-06039 Page 17 of25 Callaway Cycle 20 COLR 2.6 Nuclear Enthalpy Rise Hot Channel Factor F IJJJH (Specification 3.2.2)
F611N"' U6H :S FMlTP [1 + PF6H(l-P)]
THERMAL POWER where:
P =
RATED THERMAL POWER 2.6.1 Ft.HRTP = 1.65 2.6.2 PF 6H = 0.3 E170.0130 Revision2 I 2.6.3 The uncertainty, U611, to be applied to measured F4 H shall be 1.04 when PDMS is inoperable (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 the plant is within the specified AFD band.
16 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 18 of25 E170.0130 Callaway Cycle 20 COLR Revision2l
~~~~~~+-~~~~~r+H+H+H+H~
110 1-+
f-
+-c 1-. :t:r--t*-t:**: tt~~~~5t:t~*:..ti
.LttJ:r!::+/-+/-i~=t;;JW;+/-;t:tikt-+-+*-H--+
20
(-15 100%
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Figure 4a Callaway Cycle 20 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +1 0/-15%
17 Curve Book Figure 13-1, Rev 057 40 50
Attachment to ULNRC-06039 Page 19 of25 Callaway Cycle 20 COLR I
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110 100 go 80 70 60 30
(-12, 100%)
UNACCEPTABLE OPERA nON
(-27 I SOt)
ACCEPTABLE OPERATION
(+8, 100%)
UNACCEPTABLE OPERA nON
(+24, 50%)
E170.0130 Revision2 I
. -t--+---1--+-+-1-+-1-+---+-f-+ +-+-HH 20 10 0
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Figure 4b Callaway Cycle 20 Alternate Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC Band +8/-12%
18 Curve Book Figure 13-1, Rev 057 50
Attachment to ULNRC-06039 Page 20 of25 Callaway Cycle 20 COLR 2.8 Reactor Core SLs (Safety Limit 2.1.1)
E170.0130 Revision2 I In MODES 1 and 2, the combination ofTIIERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits in Figure 5.
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0 0.2 0.4 0.6 o.s FRACTION OF RATED THERMAL POWER Figure 5 Callaway Cycle 20 Reactor Core Safety Limits 19 Curve Book Figure 13-1, Rev 057 1.2
Attachment to ULNRC-06039 Page 21 of25 E170.0130 Callaway Cycle 20 COLR Revision2l 2.9 Reactor Trip System Overtemperature AT Set,point Parameter Values (Specification 3.3.1)
Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tava 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 AT lag time constant Measured RCS average temperature lead/lag time constants Measured RCS average temperature lag time constant Value Kt = 1.2260 K3 = 0.0011/psig T'.:S 585.3 °F P' = 2235 psig t 1 ~ 0 sec t2.::: 0 sec t3,:::4 sec 4~27 sec ts.:S4sec t6.:S2sec ft(M) = -0.0280 {18% + (qr-qb)}
when (q,- qb) < -18% RTP 0
when -18% RTP,::: (q1 - qb),::: 10% RIP when (q1 - qb) > 10% RIP Where, q1 and qb are percent RTP in the upper and lower halves of the core, respectively, and qr + qb is the total THERMAL POWER in percent RIP.
20 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 22 of25 El70.0130 Callaway Cycle 20 COLR Revision2 I 2.10 Reactor Trip System Ovemower AT Setpoint Parameter Values (Specification 3.3.1)
Pmameter
~V~al~u=e ____________ __
Overpower AT reactor trip setpoint K. = 1.1073 Overpower AT reactor trip setpoint T1v1 rate/lag coefficient Ks = 0.021°F for increasing Tov1
= OfDF for decreasing T ov1 Overpower AT reactor trip setpoint Tovg heatup coefficient
~ = 0.0015/°F forT> T"
= 0/°F for T.:5 T" Nominal Tov1 at RTP T".:5 585.3°F Measured RCS AT lead/lag time constants
-r1 ~ 0 sec
't2.:50 sec Measured RCS AT lag time constant
't3.:5 4 sec Measured RCS average temperature lag time constant
't6.:5 2 sec Measured RCS average temperature rate/lag time constant
't7 ~ 10 sec f2(M) = 0 for all AI.
2.11 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits (Specification 3.4.1)
Parameter Indicated Value Pressurizer pressure
- _ 2195 psig RCS average temperature
.:5 590.1 op 21 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 23 of25 E170.0130 Callaway Cycle 20 COLR Revision21 APPENDIX A Ap_proved Analytical Methods for Detepnining Core Operating 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 of Licensing Topical Report WCAP-9272(P)/9273(NP), 'Westinghouse Reload Safety Evaluation Methodology."'
- 2.
WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control-FQ Smveillance Technical Specification," Februmy 1994.
NRC Safety Evaluation Report dated November 26, 1993, "Acceptance for Referencing of Revised Version of Licensing Topical Report WCAP-10216-P, Rev. I, Relaxation of Constant Axial Offset Control - FQ Surveillance Technical Specification" (TAC No. M88206).
- 3.
WCAP-10266-P-A, Revision 2, "The 1981 Version of the 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, 1988, "Acceptance for Referencing Topical Report Addendum 2 to WCAP-1 0266, Revision 2, 'BASH Methodology Improvements and Reliability Enhancements."'
22 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 24 of25 E170.0130 Callaway Cycle 20 COLR Revision2 I
- 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-1261 0, 'VANTAGE+ Fuel Assembly Reference Core Report' (fAC NO. 77258)."
NRC Safety Evaluation Report dated September 15, 1994, "Acceptance for Referencing of Topical Report WCAP-12610, Appendix B, Addendum 1, 'Extended Burnup Fuel Design Methodology and ZIRLO Fuel Performance Models' (TAC NO. 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 Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999.
NRC letter dated January 19, 1999, "Acceptance for Referencing ofLicensing Topical Report WCAP-14565, 'VIPRE-01 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-10851, 'Improved Fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations."'
- 8.
WCAP-15063-P-A, Revision 1, with Errata, "Westinghouse Iinproved 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 ~T and Thermal Overtemperature ~T 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 ~ T and Thermal Overtemperature L\\ T Trip Functions."'
23 Curve Book Figure 13-1, Rev 057
Attachment to ULNRC-06039 Page 25 of25 E170.0130 Callaway Cycle 20 COLR Revision 21
- 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 ofthe 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 WCA.P-11596-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-13524 and WCAP-13524, Revision 1, 'APOLLO -A One-Dimensional Neutron Diffusion Theory Program..,,
24 Curve Book Figure 13-1, Rev 057