ML17142A306

R.E. Ginna, Submittal of Core Operating Limits Report Cycle 40, Revision 1

ML17142A306
Person / Time
Site:	Ginna
Issue date:	05/09/2017
From:	Garnish K G Exelon Generation Co, Ginna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17142A306 (21)

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{{#Wiki_filter:Exelon Generation May 9, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario, NY 14519-9364 www.exeloncorp.com Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244

Subject:

R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 40, Revision 1 Enclosed is a copy of the R.E. Ginna Nuclear Power Plant Core Operating Limits Report (COLR) Cycle 40, Revision 1. The cycle-specific core operating limits contained in the report have been determined iri accordance with Technical Specification 5.6.5. The COLR is being submitted to the NRC in accordance with the R.E. Ginna Nuclear Power Plant Technical Specification Section 5.6.5. There are no regulatory commitments contained in this letter. Should you have any questions regarding this submittal, please contact Kyle Garnish at 315-791-5321. Kyle Gar sh Manager, Regulatory Assurance R.E. Ginna Nuclear Power Plant, LLC

Attachment:

R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 40, cc: Revision 1

• 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 40 Revision 1 R.E. Ginna Nuclear Power Plant, LLC May9, 2017 R. E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 40 Revision 1 Responsible Manager: Effective Date: R. E. Ginna Nuclear Power Plant COLR-1 COLR Cycle 40 Revision 1 1.0 CORE OPERATING LIMITS REPORT COLR Cycle 40 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 (SOM) 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 (Fa(Z)) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN aH) 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 RTP, 2, and 3 3.9.1 Boron Concentration R. E. Ginna Nuclear Power Plant COLR-2 Revision 1 .* .. *;* ..... 2.0 Operating Limits COLR Cycle 40 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 NRG-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, Reactor 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) 2.2.1 The SHUTDOWN MARGIN in MODE 2 with Kett< 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 (LCO 3.1.3) 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 1 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 Limit 1 (LCO 3.1.5) COLR Cycle 40 2.4.1 The shutdown bank shall be fully withdrawn which is defined as 220 steps. 2.5 Control Bank Insertion Limits 1 (LCO 3.1.6) 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 to-tip distance while moving in overlap through the active core region. 2.6 Heat Flux Hot Channel Factor (FQ(Z))2 (LCO 3.2.1) 2.6.1 Fo(Z) s CFQ

• K(Z) IP Fo(Z) s CFQ
• K(Z) I 0.5 where: CFQ is. the F 0 (Z) limit for P > 0.5 for P s 0.5 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 burnup, 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 the nearest three burnup steps. R. E. Ginna Nuclear Power Plant COLR-4 Revision 1 COLR Cycle 40 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 extrapolation.

2.6.5 The Fa(Z) penalty factors are provided in Table COLR-2. 2.6.6 Table COLR-3 provides W(Z) values for the BOC startup flux map to be taken prior to exceeding 75% power. For part power surveillances during other times in life or at powers other than 75%, 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 surveillance power level. This factor will be applied by the INCORE-30 software and/or BEACONŽ Core Monitoring System. 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN.6H)1 (LCO 3.2.2) where: PF = 0.3, and P =THERMAL POWER I RATED THERMAL POWER 2.8 AXIAL FLUX DIFFERENCE (AFD)3 (LCO 3.2.3) 2.8.1 The AFD acceptable operation limits are provided in Figure COLR-5. BEACON is 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 countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners. R. E. Ginna Nuclear Power Plant COLR-5 Revision 1 2.9 Reactor Trip System (RTS) lnstrumentation 5 (LCO 3.3.1) 2.9.1 Overtemperature b.T Setpoint Parameter Values Parameter Value Overtemperature

b. T reactor trip setpoint K1 s Overtemperature

b. T reactor trip Kz ;;:: depressurization setpoint penalty coefficient Overtemperature

b. T reactor trip heatup K3 ;;:: setpoint coefficient Measured lead time constant T1 ;;:: 1.19 0.00093/psi COLR Cycle 40 0.0185/°F penalty 25 seconds Measured lag time constant -r 2 s 5 seconds f1(b.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 qt and qb are percent RA TED THERMAL POWER in the upper and lower halves of the core, respectively, and qt+ qb is the total percent RA TED THERMAL POWER, such that:

• For qt -qb between -14% and +6%, f1(b.I) = 0.
• For each percent that the magnitude of qt -qb exceeds -14%, the b.T trip setpoint shall be automatically reduced by an equivalent of 3.08% of RA TED THERMAL POWER.
• For each percent that the magnitude of qt -qb exceeds +6%, the b.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 1 2.9.2 Overpower Setpoint ParameterVa.lues Parameter Overpower T reactor trip setpoint Overpower T reactor trip heatup setpoint Ks penalty coefficient Overpower T reactor trip thermal Ks time delay setpoint penalty Measured impulse/lag time constant T3

= 0.0% RTP for all s = = = 1.077 O/°F for T < T' COLR Cycle 40 0.0014/°F for T T' 0.00/°F for increasing T 0.00/°F for decreasing T 0 seconds 2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 4 (LCO 3.4.1) 2.10.1 The pressurizer pressure shall 2175 psig. 2.10.2 The RCS average temperature shall bes 580.0°F. 2.10.3 The RCS total flow rate shall 177,300 gpm (includes 4% minimum flow uncertainty per Revised Thermal Design Methodology). 2.11 Boron Concentration 1 (LCO 3.9.1) 2.11.1 The boron concentrations of the hydraulically coupled Reactor Coolant System, the refueling canal, and the refueling cavity shall be 2750 ppm. Boron concentration based on All Rods In less the highest worth rod with a K-effective of 0.95. A 100 ppm Factor of Safety has been included 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 ECCS 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 1 COLR Cycle 40 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 Constant Axial Offset Control Fa -Surveillance Technical Specification," February 1994. 9. WCAP-11397-P-A, "Revised Thermal Design Procedure," April 1989. 10. WCAP-14710-P-A, "1-D Heat Conduction Model for Annular Fuel Pellets," May 1998. 11. WCAP-8745, "Design Basis for the Thermal Overpower Lff and Thermal Overtemperature b.T Trip Functions," March 1977. R. E. Ginna Nuclear Power Plant COLR-8 Revision 1 670 650 610 -LL 0 -! 590 *> *I* I I .I ' -' .. 570 ' ' ' I 550 ' .L *'-I 0 *, -I_ --_I I I* I ' .. I ' -,-,. I '* 0.2 -, -., -\ . .J. I . l . ... . 1_ I -I* -r -r -_,_ I -l--, --,-'* ' _,. 0.4 0.6 0.8 Power (fraction of 1775 MWt) Figure COLR-1 Reactor Safety Limits R. E. Ginna Nuclear Power Plant COLR-9 1 I.. I I COLR Cycle 40 I I, I I r * -r * ,. *

• r * -_:_ .J -..I -J I I I -, --.. I , ,
• I '* I *, * --' .. L -L --I -I I -t-* ' . I I I -+ -11. -lo -1.2 1.4 Revision 1

-....... RI ... a; "CJ '#. -c LLI 0:: ::::> a LLI 0:: z 0:: ct :?i z 0 c I-::::> :::c VI 3 2.5 2

• -*-*-{2500, 1.80) 1.5 (2500, 1.30) 1 0.5 ACCEPTABLE OPERATION

-*-*-* UNACCEPTABLE OPERATION -*-*-*-' COLR Cycle 40 *-*-*-* (O, 1.80) (O, 1.30) 0 2500 2000 1500 1000 500 0 COOLANT BORON CONCENTRATION (ppm) -* *One Loop Operation -Two Loop Operation Figure COLR-2 REQUIRED SHUTDOWN MARGIN R. E. Ginna Nuclear Power Plant COLR-10 Revision 1 -----------_ ___J COLR Cycle 40 240 -+ / ,, l (1 r 46, 2 19) j_1_.__--+-_ 22 I -=----_J \6 3 91 , 219) 22 0 2 00 -* c 1 80 IU ... ::g 1 60 ... § 140 QI ... z 12 0 0 E 11'1 100 -0 Cl. z 80 ct cc g 60 0:: 40 2 0 B Bank 1 --+ ----+-C Bank 0 +----r-------r--

---

r---+------.----r---+----T------;

0 10 2 0 3 0 40 so 6 0 7 0 80 90 10 0 CORE POWER (Percent of 1,775 MWT} *The top of the act i ve 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 mov i ng in overlap. The bank positions are g i ven as follows:

• Bank D:
• Bank C:
• Bank B: (184/70) * (P-100) + 184 (184/70) * (P-100) + 184 + 130 (184/70) * (P-100) + 184 + 130 + 130 Where P is defined as the core power (in percent). Figure COLR-3 (for 30 SP S 100) (for 0 S P S 66.20) (for 0 SP S 16.74) CONTROL BANK INSERTION LIMITS R. E. Ginna Nuclear Power Plant COLR-11 Revision 1 1.2 ::::::: 1.0 N ... 0 +-' 0.8 u. b.O c :.i RI :.. 0.6 RI ')( <( "Cl QI 0.4 .!::! RI E ... 0 z 0.2 0.0 0.0 Total F 0 = 2.600 Elevation (ft) K(Z) 0.0 1.0 12.0 1.0 2.0 4.0 6.0 8.0 Elevation (ft) Figure COLR-4 10.0 COLR Cycle 40 12.0 K(Z) -NORMALIZED F 0 (Z) AS A FUNCTION OF CORE HEIGHT R. E. Ginna Nuclear Power Plant COLR-12 Revision 1 120 110 100 90 :::-c 80 Q) CJ .. Q) .S: 70 .. Q. 60 iii E .. Q) 60 .c I-'C Q) 40 -Ill n::: 30 20 10 0 (-12, 100) (+6, 100) ' I \ I _ ..__ Unacceptable Unacceptable Operation I \ Operation I \ I Acceptable

' I Operation \ (-30, 50) (+24, 50) 40 20 -10 0 10 20 30 40 50 Axial Aux Difference (percent Figure COLR-5 COLR Cycle 40 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER R. E. Ginna Nuclear Power Plant COLR-13 Revision 1 Table COLR-1 RAOC Summary of W(Z) with HFP %AFD Band of-12/+6% (Top 8% and Bottom 8% Excluded) Height (feet) 150 3000 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 1.3780 1.3453 1.2680 1.2568 1.17 1.3672 1.3346 1.2610 1.2498 1.33 1.3552 1.3228 1.2527 1.2422 1.50 1.3420 1.3087 1.2428 1.2338 1.67 1.3287 1.2934 1.2318 1.2247 1.83 1.3155 1.2778 1.2205 1.2153 2.00 1.3006 1.2604 1.2078 1.2046 2.17 1.2848 1.2424 1.1945 1.1935 2.33 1.2697 1.2252 1.1818 1.1829 2.50 1.2537 1.2066 1.1684 1.1716 2.67 1.2371 1.1917 1.1547 1.1600 2.83 1.2219 1.1826 1.1422 1.1493 3.00 1.2106 1.1741 1.1317 1.1412 3.17 1.2026 1.1672 1.1254 1.1368 3.33 1.1961 1.1629 1.1229 1.1348 3.50 1.1897 1.1582 1.1208 1.1327 3.67 1.1833 1.1531 1.1185 1.1298 3.83 1.1767 1.1478 1.1163 1.1267 4.00 1.1691 1.1416 1.1134 1.1256 4.17 1.1612 1.1349 1.1100 1.1256 4.33 1.1533 1.1286 1.1066 1.1277 4.50 1.1442 1.1238 1.1023 1.1295 4.67 1.1357 1.1199 1.0986 1.1304 4.83 1.1289 1.1155 1.0965 1.1308 5.00 1.1225 1.1105 1.0944 1.1307 5.17 1.1161 1.1052 1.0917 1.1298 5.33 1.1098 1.0999 1.0889 1.1285 5.50 1.1022 1.0943 1.0877 1.1277 5.67 1.0956 1.0876 1.0876 1.1273 5.83 1.0924 1.0812 1.0905 1.1268 R. E. Ginna Nuclear Power Plant COLR-14 COLR Cycle 40 Revision 1 ----I Table COLR-1 (Continued) RAOC Summary of W(Z) with HFP %AFD Band of-12/+6% (Top 8% and Bottom 8% Excluded) Height 150 3000 10000 16000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.00 1.0938 1.0818 1.0936 1.1258 6.17 1.0976 1.0877 1.0976 1.1238 6.33 1.1000 1.0928 1.1035 1.1211 6.50 1.1021 1.0980 1.1095 1.1213 6.67 1.1038 1.1032 1.1147 1.1245 6.83 1.1050 1.1076 1.1191 1.1279 7.00 1.1057 1.1117 1.1233 1.1310 7.17 1.1058 1.1153 1.1268 1.1332 7.33 1.1054 1.1182 1.1295 1.1346 7.50 1.1043 1.1206 1.1317 1.1353 7.67 1.1026 1.1223 1.1332 1.1352 7.83 1.1004 1.1233 1.1338 1.1343 8.00 1.0973 1.1237 1.1338 1.1324 8.17 1.0936 1.1233 1.1328 1.1298 8.33 1.0893 1.1222 1.1309 1.1275 8.50 1.0847 1.1202 1.1300 1.1267 8.67 1.0836 1.1175 1.1298 1.1267 8.83 1.0891 1.1174 1.1319 1.1278 9.00 1.0962 1.1211 1.1391 1.1318 9.17 1.1012 1.1318 1.1500 1.1384 9.33 1.1049 1.1408 1.1596 1.1451 9.50 1.1119 1.1493 1.1694 1.1511 9.67 1.1211 1.1580 1.1793 1.1580 9.83 1.1280 1.1672 1.1884 1.1696 10.00 1.1345 1.1769 1.1975 1.1881 10.17 1.1410 1.1858 1.2062 1.2104 10.33 1.1466 1.1935 1.2141 1.2305 10.50 1.1492 1.1994 1.2191 1.2466 10.67 1.1482 1.2038 1.2204 1.2570 10.83 1.1456 1.2087 1.2207 1.2636 11.00 1.1386 1.2086 1.2161 1.2633 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 COLR Cycle 40 Revision 1 Table COLR-2 P It F t f I F enaty ac or or ncreasma Cycle Burnup Penalty Factor (MWD/MTU)1 al (%) ;;:: 150 2.00 Q Penalty Multiplier 1.020 COLR Cycle 40 (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 1 Table COLR-3 Part-Power W(Z) Generated at 150 MWD/MTU, 75% Power (Top 8% and Bottom 8% Excluded) Height (feet) HFPARO 75% D at 180 Steps (Bottom) 0.00 1.0000 1.0000 0.17 1.0000 1.0000 0.33 1.0000 1.0000 0.50 1.0000 1.0000 0.67 1.0000 1.0000 0.83 1.0000 1.0000 1.00 1.3780 1.4355 1.17 1.3672 1.4206 1.33 1.3552 1.4046 1.50 1.3420 1.3873 1.67 1.3287 1.3699 1.83 1.3155 1.3527 2.00 1.3006 1.3338 2.17 1.2848 1.3140 2.33 1.2697 1.2952 2.50 1.2537 1.2755 2.67 1.2371 1.2552 2.83 1.2219 1.2366 3.00 1.2106 1.2218 3.17 1.2026 1.2103 3.33 1.1961 1.2004 3.50 1.1897 1.1906 3.67 1.1833 1.1807 3.83 1.1767 1.1707 4.00 1.1691 1.1596 4.17 1.1612 1.1485 4.33 1.1533 1.1376 4.50 1.1442 1.1256 4.67 1.1357 1.1143 4.83 1.1289 1.1047 5.00 1.1225 1.0955 5.17 1.1161 1.0866 5.33 1.1098 1.0777 5.50 1.1022 1.0676 5.67 1.0956 1.0587 5.83 1.0924 1.0531 R. E. Ginna Nuclear Power Plant COLR-17 COLR Cycle 40 Revision 1 Table COLR-3 (Continued) Part-Power W(Z) Generated at 150 MWD/MTU, 75% Power (Top 8% and Bottom 8% Excluded) Height HFPARO 75% D at (feet) 180 Steps 6.00 1.0938 1.0522 6.17 1.0976 1.0537 6.33 1.1000 1.0539 6.50 1.1021 1.0540 6.67 1.1038 1.0541 6.83 1.1050 1.0539 7.00 1.1057 1.0534 7.17 1.1058 1.0527 7.33 1.1054 1.0518 7.50 1.1043 1.0508 7.67 1.1026 1.0491 7.83 1.1004 1.0470 8.00 1.0973 1.0434 8.17 1.0936 1.0397 8.33 1.0893 1.0359 8.50 1.0847 1.0322 8.67 1.0836 1.0323 8.83 1.0891 1.0393 9.00 1.0962 1.0485 9.17 1.1012 1.0561 9.33 1.1049 1.0629 9.50 1.1119 1.0739 9.67 1.1211 1.0874 9.83 1.1280 1.0982 10.00 1.1345 1.1076 10.17 1.1410 1.1163 10.33 1.1466 1.1240 10.50 1.1492 1.1289 10.67 1.1482 1.1301 10.83 1.1456 1.1300 11.00 1.1386 1.1256 11.17 1.0000 1.0000 11.33 1.0000 1.0000 11.50 1.0000 1.0000 11.67 1.0000 1.0000 11.83 1.0000 1.0000 12.00 (Top) 1.0000 1.0000 R. E. Ginna Nuclear Power Plant COLR-18 COLR Cycle 40 Revision 1 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 COLR Cycle 40 Revision 1}}