ML21287A012
| ML21287A012 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/13/2021 |
| From: | Bradshaw C Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML21287A012 (21) | |
Text
R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario, NY 14519-9364 www.exeloncorp.com
October 13, 2021
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR -18 NRC Docket No. 50-244
Subject:
R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 43, Revision 0
Enclosed is a copy of the R.E. Ginna Nuclear Power Plant Core Operating Limits Report (COLR) Cycle 43, Revision 0. It changed section 2.6.6, added Reference 12, and reflects changes to information in Tables COLR-1, COLR-2, and COLR-3 (used for flux maps) based on the core reload.
This cycle revision of the COLR is being submitted to the NRC in accordance with the R.E.
Ginna Nuclear Power Plant Technical Specifications, Section 5.6.5.d.
There are no regulatory commitments contained in this letter.
Should you have any questions regarding this submittal, please contact George Wrobel at 585-315- 0552.
Respectfully,
George Wrobel for Chris Bradshaw Manager, Regulatory Assurance R.E. Ginna Nuclear Power Plant, LLC
Attachment:
R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 43, Revision 0
cc: NRC Regional Administrator, Region I NRC Project Manager, Ginna NRC Senior Resident Inspector, Ginna ATTACHMENT
R.E. Ginna Nuclear Power Plant
Core Operating Limits Report, Cycle 43
Revision 0
R.E. Ginna Nuclear Power Plant, LLC October 13, 2021
COLR Cycle 43
R. E. Ginna Nuclear Power Plant
Core Operating Limits Report COLR
Cycle 43
Revision 0
Responsible Manager:
Effective Date:
R. E. Ginna Nuclear Power Plant COLR-1 Revision 0 COLR Cycle 43 1.0 CORE OPERATING LIMITS REPORT
This Core Operating Limits Report (COLR) for the R. E. Ginna Nuclear Power Plant has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Specifications affected by this report are listed below:
2.1 Safety Limits (SLs)
3.1.1 SHUTDOWN MARGIN (SDM)
3.1.3 Moderator Temperature Coefficient (MTC)
3.1.4 Rod Group Alignment Limits
3.1.5 Shutdown Bank Insertion Limit
3.1.6 Control Bank Insertion Limits
3.1.8 PHYSICS TESTS Exceptions MODE 2
3.2.1 Heat Flux Hot Channel Factor (F Q(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F N H)
3.2.3 AXIAL FLUX DIFFERENCE (AFD)
3.3.1 Reactor Trip System (RTS) Instrumentation
3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
Limits
3.4.5 RCS Loops MODES 1 8.5% RTP, 2, and 3
3.9.1 Boron Concentration
R. E. Ginna Nuclear Power Plant COLR-2 Revision 0 COLR Cycle 43 2.0 Operating Limits
The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5. All items that appear in capitalized type are defined in Technical Specification 1.1, Definitions.
2.1 SAFETY LIMITS (SLs)1
(2.1)
2.1.1 In MODES 1 and 2, the combination of THERMAL POWER, React or Coolant System (RCS) average temperature, and pressurizer pressure shall not exceed the SLs specified in Figure COLR-1.
2.2 SHUTDOWN MARGIN (SDM)1
(LCO 3.1.1, LCO 3.1.4, LCO 3.1.5, LCO 3.1.6, LCO 3.1.8, and LCO 3.4.5)
2.2.1 The SHUTDOWN MARGIN in MODE 2 with K eff < 1.0 and MODES 3 and 4 shall be greater than or equal to the limits specified in Figure COLR-2 for the number of reactor coolant pumps in operation.
2.2.2 The SHUTDOWN MARGIN in MODE 4 when both reactor coolant pumps are not in operation and in MODE 5 shall be greater than or equal to the one loop operation curve of Figure COLR-2.
2.2.3 The SHUTDOWN MARGIN required in LCO 3.1.4, LCO 3.1.5, LCO 3.1.6, LCO 3.1.8, and LCO 3.4.5 shall be greater than the limits specified in Figure COLR-2 for the number of reactor coolant pumps in operation.
2.3 Moderator Temperature Coefficient (MTC)1
2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOL ARO/HZP - MTC shall be equal to or less positive than + 5.0 pcm/°F for power levels below 70% RTP and less than or equal to 0 pcm/°F for power levels at or above 70% RTP.
The EOL ARO/RTP - MTC shall be less negative than -44.6 pcm/°F.
where:
ARO stands for All Rods Out
R. E. Ginna Nuclear Power Plant COLR-3 Revision 0 COLR Cycle 43
BOL stands for Beginning of Cycle Life
EOL stands for End of Cycle Life
HZP stands for Hot Zero Power
RTP stands for RATED THERMAL POWER
2.4 Shutdown Bank Insertion Limit1
2.4.1 The shutdown bank shall be fully withdrawn which is defined as 220 steps.
2.5 Control Bank Insertion Limits1
2.5.1 The control banks shall be limited in physical insertion as shown in Figure COLR-
- 3. Control Bank A shall be at least 220 steps withdrawn.
2.5.2 The control rod banks shall be withdrawn maintaining a nominal 130 step tip-to-tip dista nce while moving i n overlap through the active core region.
2.6 Heat Flux Hot Channel Factor (FQ(Z))2
2.6.1 FQ(Z) CFQ
- K(Z) I P for P > 0.5
FQ(Z) CFQ
- K(Z) I 0.5 for P 0.5
where:
CFQ is the FQ(Z) limit
P = THERMAL POWER I RATED THERMAL POWER
Z is the height of the core
2.6.2 CFQ = 2.60
2.6.3 K(Z) is provided in Figure COLR-4
2.6.4 W(Z) values are provided in Table COLR-1. For W(Z) data at a desired burnup not listed in the table, but less than the maximum listed b u r n u p, values at 3 or more burnup steps should be used to interpolate the W(Z) data to the desired burnup with a polynomial type fit that uses the W(Z) data for t he nearest three burnup steps.
R. E. Ginna Nuclear Power Plant COLR-4 Revision 0 COLR Cycle 43
For W(Z) data at a desired burnup outside of the listed burnup steps, a linear extrapolation of the W(Z) data for the nearest two burnup steps can be used.
If data are listed for only two burnup steps, a linear fit can be used for both interpolation and e xtrapolation.
2.6.5 The FQ(Z) penalty factors are provided in Table COLR-2.
2.6.6 Table COLR-3 provides W(Z) v a l u e s f o r t h e B O C s t a r t u p f l ux map to be taken prior to exceeding 50% then 75% power. For part power surveillances during other times in life or at powers other than those listed in Tab le COLR-3, the W(Z) values in Table COLR-1 should be used. The W(Z) values in Table COLR-3 do not include the 1/P factor, where P is the surveillan ce power level.
This factor will be applied by the BEACON TM Core Monitoring System.
2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN H)1
2.7.1 FN H F RTP H * (1 + PF H * (1-P))
where:
FRTP H = 1.72
PF H = 0.3, and
P = THERMAL POWER / RATED THERMAL POWER
2.8 AXIAL FLUX DIFFERENCE (AFD)3
2.8.1 The AFD acceptable operation limits are provided in Figur e COLR-5.
BEACONis a trademark or registered trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countri es throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their res pective owners.
R. E. Ginna Nuclear Power Plant COLR-5 Revision 0 COLR Cycle 43 2.9 Reactor Trip System (RTS) lnstrumentation5
2.9.1 Overtemperature T Setpoint Parameter Values Parameter Value
Overtemperature T reactor trip setpoint K1 1.19
Overtemperature T reactor trip K2 0.00093/psi depressurization setpoint penalty coefficient
Overtemperature T reactor trip heatup K3 0.0185/°F penalty setpoint coefficient
Measured lead time constant 1 25 seconds
Measured lag time constant 2 5 seconds f1( I) is a function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where q t and qb are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and qt + qb is the total percent RATED THERMAL POWER, such that:
x Forqt - qb between -14% and +6%, f1( I) = 0.
x For each percent that the magnitude of q t - qb exceeds -14%, the T trip setpoint shall be automatically reduced by an equivalent of 3.08% of RATED THE RMAL POWER.
x For each percent that the magnitude of q t - qb exceeds +6%, the T trip setpoint shall be automatically reduced by an equivalent of 2.27% of RATED THERMAL POWER.
R. E. Ginna Nuclear Power Plant COLR-6 Revision 0 COLR Cycle 43
2.9.2 Overpower T Setpoint Parameter Values Parameter Value Overpower T reactor trip setpoint K4 1.077
Overpower T reactor trip heatup setpoint K 5 = 0/°F for T < T' penalty coefficient 0.0014/°F for T T'
Overpower T reactor trip thermal K6 0.00/°F for increasing T time delay setpoint penalty = 0.00/°F for decreasing T
Measured impulse/lag time constant 3 = 0 seconds
f2( I) = 0.0% RTP for all I
2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits4
2.10.1 The pressuriz er pressure shall be 2175 psig.
2.10.2 The RCS average temperature shall be 580.0°F.
2.10.3 The RCS total flow rate shall be 177,300 gpm (includes 4% minimum flow uncertainty per Revised Thermal Design Methodology).
2.11 Boron Concentration1
2.11.1 The boron concentrations of the hydraulically coupled Re actor Coolant System, the refueling canal, and the refueling cavity shall be 2750 ppm.
Boron concentration based on A ll Rods In less the highest worth rod with a K-effective of 0.95. A 100 ppm Factor of Safety has been inclu ded in this parameter.
3.0 REFERENCES
- 1. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.
- 2. WCAP-10054-P-A and WCAP-10081-A, "Westinghouse Small Break E CCS Evaluation Model Using the NOTRUMP Code," August 1985.
- 3. WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997.
R. E. Ginna Nuclear Power Plant COLR-7 Revision 0 COLR Cycle 43
- 4. WCAP-11145-P-A, "Westinghouse Small Break LOCA ECCS Evaluation Model Generic Study with the NOTRUMP Code," October 1986.
- 5. WCAP-10079-P-A, "NOTRUMP - A Nodal Transient Small Break and General Network Code," August 1985.
- 6. WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.
- 7. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995.
- 8. WCAP-10216-P-A, Revision 1A (Proprietary), Relaxation of Co nstant Axial Offset Control FQ - Surveillance Technical Specification, February 1994.
- 9. WCAP-11397-P-A, "Revised Thermal Design Procedure," April 19 89.
- 10. WCAP-14710-P-A, "1-D Heat Conduction Model for Annular Fuel Pellets," May 1998.
- 11. WCAP-8745-P-A, "Design Basis for the Thermal Overpower T and Thermal Overtemperature T Trip Functions," September 1986.
- 12. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO'," July 2006.
R. E. Ginna Nuclear Power Plant COLR-8 Revision 0 COLR Cycle 43
Figure COLR-1 Reactor Safety Limits
R. E. Ginna Nuclear Power Plant COLR-9 Revision 0 COLR Cycle 43
3
ACCEPTABLE
2.5 OPERATION
2
(2500,1.80) (0,1.80) 1.5
(2500,1.30) (0,1.30) 1
UNACCEPTABLE
OPERATION 0.5
0 2500 2000 1500 1000 500 0 COOLANTBORONCONCENTRATION(ppm)
One LoopOperation TwoLoopOperation
Figure COLR-2 REQUIRED SHUTDOWN MARGIN
R. E. Ginna Nuclear Power Plant COLR-10 Revision 0 COLR Cycle 43
240
220 (16.74,225) (66.20,225)
(14.46,219) (63.91,219) 200 BBank
180 (100,184)
(0,181)
160
140 CBank
120
100 DBank 80
60 (0,51)
40
20 (30,0) 0 0102030405060708090100 COREPOWER(Percent of1,775MWT)
- The top of the active fuel corresponds to 219. The ARO parking position may be any position above the corresponding top of active fuel for each respective bank. The control rod tip-to-tip distance is defined as 130 steps while rods are moving in overl ap. The bank positions are given as follows:
x Bank D: (184/70) * (P-100) + 184 (for 30 P 100) x Bank C: (184/70) * (P-100) + 184 + 130 (for 0 P 66.20) x Bank B: (184/70) * (P-100) + 184 + 130 + 130 (for 0 P 16.74)
Where P is defined as the core power (in percent).
Figure COLR-3 CONTROL BANK INSERTION LIMITS
R. E. Ginna Nuclear Power Plant COLR-11 Revision 0 COLR Cycle 43
1.2
1.0
0.8
0.6 TotalFQ =2.600
Elevation(ft) K(Z) 0.4 0.0 1.0 12.0 1.0
0.2
0.0 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Elevation(ft)
Figure COLR-4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT
R. E. Ginna Nuclear Power Plant COLR-12 Revision 0 COLR Cycle 43
Figure COLR-5 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER
R. E. Ginna Nuclear Power Plant COLR-13 Revision 0 COLR Cycle 43 Table COLR-1 RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%
(Top 8% and Bottom 8% Excluded)
Height (feet) 150 4000 10000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU (Bottom) 0.00 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 0.33 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 0.83 1.0000 1.0000 1.0000 1.0000 1.00 1.3708 1.3043 1.2647 1.2663 1.17 1.3600 1.2944 1.2579 1.2586 1.33 1.3480 1.2834 1.2498 1.2497 1.50 1.3340 1.2701 1.2401 1.2390 1.67 1.3188 1.2570 1.2293 1.2275 1.83 1.3036 1.2455 1.2183 1.2157 2.00 1.2866 1.2324 1.2059 1.2025 2.17 1.2688 1.2186 1.1930 1.1889 2.33 1.2521 1.2055 1.1805 1.1764 2.50 1.2358 1.1915 1.1670 1.1634 2.67 1.2191 1.1772 1.1546 1.1494 2.83 1.2040 1.1642 1.1456 1.1370 3.00 1.1958 1.1535 1.1397 1.1342 3.17 1.1922 1.1468 1.1360 1.1332 3.33 1.1886 1.1434 1.1328 1.1331 3.50 1.1844 1.1417 1.1294 1.1332 3.67 1.1800 1.1402 1.1260 1.1333 3.83 1.1753 1.1382 1.1228 1.1329 4.00 1.1697 1.1356 1.1192 1.1318 4.17 1.1637 1.1325 1.1155 1.1302 4.33 1.1576 1.1292 1.1122 1.1283 4.50 1.1507 1.1254 1.1095 1.1260 4.67 1.1434 1.1212 1.1070 1.1231 4.83 1.1362 1.1169 1.1043 1.1199 5.00 1.1280 1.1119 1.1010 1.1173 5.17 1.1200 1.1068 1.0976 1.1162 5.33 1.1131 1.1016 1.0941 1.1164 5.50 1.1052 1.0950 1.0895 1.1163 5.67 1.0986 1.0907 1.0885 1.1155 5.83 1.0970 1.0906 1.0939 1.1145
R. E. Ginna Nuclear Power Plant COLR-14 Revision 0 COLR Cycle 43 Table COLR-1 (Continued)
RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%
(Top 8% and Bottom 8% Excluded)
Height 150 4000 10000 16000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.00 1.0980 1.0931 1.1006 1.1122 6.17 1.1018 1.0986 1.1062 1.1121 6.33 1.1044 1.1049 1.1112 1.1167 6.50 1.1064 1.1123 1.1162 1.1217 6.67 1.1086 1.1195 1.1205 1.1251 6.83 1.1116 1.1258 1.1240 1.1278 7.00 1.1146 1.1318 1.1272 1.1308 7.17 1.1168 1.1372 1.1301 1.1334 7.33 1.1186 1.1417 1.1325 1.1351 7.50 1.1203 1.1457 1.1345 1.1361 7.67 1.1214 1.1489 1.1355 1.1363 7.83 1.1218 1.1512 1.1358 1.1357 8.00 1.1215 1.1528 1.1353 1.1342 8.17 1.1204 1.1534 1.1338 1.1318 8.33 1.1186 1.1530 1.1316 1.1288 8.50 1.1162 1.1519 1.1289 1.1262 8.67 1.1125 1.1493 1.1261 1.1257 8.83 1.1076 1.1452 1.1258 1.1278 9.00 1.1063 1.1450 1.1298 1.1316 9.17 1.1096 1.1521 1.1415 1.1369 9.33 1.1136 1.1639 1.1514 1.1438 9.50 1.1213 1.1765 1.1614 1.1502 9.67 1.1318 1.1890 1.1718 1.1588 9.83 1.1406 1.2036 1.1813 1.1739 10.00 1.1499 1.2170 1.1907 1.1908 10.17 1.1596 1.2281 1.1999 1.2056 10.33 1.1687 1.2399 1.2085 1.2187 10.50 1.1735 1.2462 1.2133 1.2263 10.67 1.1719 1.2458 1.2132 1.2284 10.83 1.1697 1.2456 1.2115 1.2311 11.00 1.1638 1.2374 1.2069 1.2268 11.17 1.0000 1.0000 1.0000 1.0000 11.33 1.0000 1.0000 1.0000 1.0000 11.50 1.0000 1.0000 1.0000 1.0000 11.67 1.0000 1.0000 1.0000 1.0000 11.83 1.0000 1.0000 1.0000 1.0000 12.00 (Top) 1.0000 1.0000 1.0000 1.0000
R. E. Ginna Nuclear Power Plant COLR-15 Revision 0 COLR Cycle 43 Table COLR-2 Penalty Factor for Increasing F Q
Cycle Burnup Penalty Factor Penalty (MWD/MTU)(a) (%) Multiplier
150 2.40 1.024 331 3.10 1.031 512 3.60 1.036 693 4.00 1.040 874 4.20 1.042 1055 4.10 1.041 1236 3.80 1.038 1417 3.40 1.034 1598 2.90 1.029 1779 2.40 1.024 1960 2.10 1.021
2142 2.00 1.020
(a) A penalty multiplier is not required for part power surveillances during startup.
The penalty factor should be applied beginning with the first full power surveillance.
R. E. Ginna Nuclear Power Plant COLR-16 Revision 0 COLR Cycle 43
Table COLR-3 Part-Power W(Z) Generated at 150 MWD/MTU, 75% and 50% Power (Top 8% and Bottom 8% Excluded)
Height (feet) HFP ARO 75% D at 50% D at 180 Steps 169 Steps (Bottom) 0.00 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 0.33 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 0.83 1.0000 1.0000 1.0000 1.00 1.3708 1.4164 1.5093 1.17 1.3600 1.4015 1.4903 1.33 1.3480 1.3867 1.4707 1.50 1.3340 1.3692 1.4475 1.67 1.3188 1.3512 1.4239 1.83 1.3036 1.3345 1.4006 2.00 1.2866 1.3141 1.3752 2.17 1.2688 1.2925 1.3492 2.33 1.2521 1.2724 1.3247 2.50 1.2358 1.2527 1.3006 2.67 1.2191 1.2329 1.2759 2.83 1.2040 1.2148 1.2536 3.00 1.1958 1.2035 1.2380 3.17 1.1922 1.1966 1.2274 3.33 1.1886 1.1899 1.2171 3.50 1.1844 1.1826 1.2060 3.67 1.1800 1.1763 1.1945 3.83 1.1753 1.1697 1.1835 4.00 1.1697 1.1610 1.1717 4.17 1.1637 1.1521 1.1596 4.33 1.1576 1.1432 1.1481 4.50 1.1507 1.1337 1.1361 4.67 1.1434 1.1236 1.1240 4.83 1.1362 1.1139 1.1121 5.00 1.1280 1.1032 1.0986 5.17 1.1200 1.0927 1.0852 5.33 1.1131 1.0836 1.0733 5.50 1.1052 1.0734 1.0607 5.67 1.0986 1.0645 1.0495 5.83 1.0970 1.0609 1.0436
R. E. Ginna Nuclear Power Plant COLR-17 Revision 0 COLR Cycle 43
Table COLR-3 (Continued)
Part-Power W(Z) Generated at 150 MWD/MTU, 75% and 50% Power (Top 8% and Bottom 8% Excluded)
Height 50% D at (feet) HFP ARO 75% D at 180 Steps 169 Steps 6.00 1.0980 1.0597 1.0399 6.17 1.1018 1.0611 1.0390 6.33 1.1044 1.0618 1.0374 6.50 1.1064 1.0618 1.0354 6.67 1.1086 1.0621 1.0337 6.83 1.1116 1.0636 1.0333 7.00 1.1146 1.0652 1.0333 7.17 1.1168 1.0664 1.0330 7.33 1.1186 1.0676 1.0328 7.50 1.1203 1.0688 1.0328 7.67 1.1214 1.0696 1.0327 7.83 1.1218 1.0700 1.0323 8.00 1.1215 1.0701 1.0320 8.17 1.1204 1.0700 1.0314 8.33 1.1186 1.0696 1.0307 8.50 1.1162 1.0691 1.0300 8.67 1.1125 1.0680 1.0286 8.83 1.1076 1.0660 1.0264 9.00 1.1063 1.0680 1.0281 9.17 1.1096 1.0749 1.0345 9.33 1.1136 1.0826 1.0414 9.50 1.1213 1.0948 1.0516 9.67 1.1318 1.1102 1.0642 9.83 1.1406 1.1238 1.0750 10.00 1.1499 1.1377 1.0864 10.17 1.1596 1.1522 1.0984 10.33 1.1687 1.1657 1.1097 10.50 1.1735 1.1741 1.1182 10.67 1.1719 1.1753 1.1213 10.83 1.1697 1.1757 1.1241 11.00 1.1638 1.1747 1.1242 11.17 1.0000 1.0000 1.0000 11.33 1.0000 1.0000 1.0000 11.50 1.0000 1.0000 1.0000 11.67 1.0000 1.0000 1.0000 11.83 1.0000 1.0000 1.0000 12.00 (Top) 1.0000 1.0000 1.0000
R. E. Ginna Nuclear Power Plant COLR-18 Revision 0 COLR Cycle 43 End Notes
- 1. Limits generated using Reference 1.
- 2. Limits generated using References 1 through 8 and 10.
- 3. Limits generated using References 1 and 8.
- 4. Limits generated using Reference 9.
- 5. Limits generated using Reference 11.
R. E. Ginna Nuclear Power Plant COLR-19 Revision 0