Text

Cycle 39 Core Operating Limits Report, Revision 0
	ML15308A102
Person / Time
Site:	Ginna
Issue date:	10/29/2015
From:	Harding T; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML15308A102 (21)
	v • d • e

~R.E. Ginna Nuclear Power Plant Exto xe onne~s Geneaion1503 onoOntario, NY Lake Rd.

14519 www.exeloncorp.com October 29, 2015 TS 5.6.5 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 2055-000 1 R.E. Ginna Nuclear Power Plant Facility Operating License No. DPR-l18 NRC Docket No. 5 0-244

Subject:

R.E. Ginna Nuclear Power Plant Cycle 39 Core Operating Limits Report, Revision 0 Enclosed is a copy of the R.E. Ginna Nuclear Power Plant Cycle 39 Core Operating Limits Report, Revision 0. The cycle-specific core operating limits contained in the report have been determined in 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 Thomas Harding at 3 15-791-5219.

Respectfully,

Thomas ding Manager, Regulatory Assurance R.E. Ginna Nuclear Power Plant, LLC THikc

Attachment:

(1) R.E. Ginna Nuclear Power Plant Cycle 39 Core Operating Limits Report, Revision 0 cc: NRC Regional Administrator, Region I NRC Project Manager, Ginna NRC Resident Inspector, Ginna

Attachment (1)

R.E. Ginna Nuclear Power Plant Cycle 39 Core Operating Limits Report, Revision 0

COLR Cycle 39 R. E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 39 Revision 0 Responsible Manager:

Effective Date: October 24, 2015 R. E. Ginna Nuclear Power Plant COLR-1 Revision 0

COLR Cycle 39 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) 3.1.5 Shutdown Bank Insertion Limit 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (F0 (Z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) 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 3.9.1 Boron Concentration R. E. Ginna Nuclear Power PlantCLR2evso0 COLR-2 Revision 0

COLR Cycle 39 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)"

(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 1 (LCO 3.1.1) 2.2.1 The SHUTDOWN MARGIN in MODE 2 with Keff < 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 COEFFICIENT1 (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 PlantCLR3evso0 COLR-3 Revision 0

COLR Cycle 39 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 (LCO 3.1.5) 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 tip-to-tip distance while moving in overlap through the active core region. The minimum allowable tip-to-tip distance shall never be less than 121 steps between two banks moving in the active core region.

2.6 Heat Flux Hot Channel Factor (FQ(Z)) 2 (LCO 3.2.1) 2.6.1 FQ(Z) -<CFQ* K(Z) /P for P > 0.5 FQ(Z) <-CFQ

K(Z) / 0.5 for P _<0.5 where:

CFQ is the FQ(Z) limit P = THERMAL POWER / 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 R. E. Ginna Nuclear Power PlantCOR4evso0 COLR-4 Revision 0

COLR Cycle 39 desired burnup with a polynomial type fit that uses the W(Z) data for the nearest three burnup steps.

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 FQ(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 INCO RE-3D software.

2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)1 (LCO 3.2.2) 2.7.1 FNAH -- FRTPAH * (1 + PFAH * (i-P))

where:

FRTPAH = 1.72 PFAR = 0.3, and P = THERMAL POWER / RATED THERMAL POWER 2.8 AXIAL FLUX DIFFERENCE 3 (LCO 3.2.3) 2.8.1 The AFD acceptable operation limits are provided in Figure COLR-5.

R. E. Ginna Nuclear Power PlantCOR5evso0 COLR-5 Revision 0

COLR Cycle 39 2.9 Reactor Trip System (RTS) Instrumentations (LCO 3.3.1) 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K1 < 1.19 Overtemperature AT reactor trip K2 > 0.00093/psi depressurization setpoint penalty coefficient Overtemperature AT reactor trip heatup K3 > 0.01 85/°F penalty setpoint coefficient Measured lead time constant 1:t > 25 seconds Measured lag time constant "r2 5 seconds f1 (Al) 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 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:

For qt - qb between -14% and +6%, f1(AI) = 0.

For each percent that the magnitude of qt - qb exceeds -14%, the AT trip setpoint shall be automatically reduced by an equivalent of 3.08% of RATED THERMAL POWER.

For each percent that the magnitude of qt - qb exceeds +6%, the AT trip setpoint shall be automatically reduced by an equivalent of 2.27% of RATED THERMAL POWER.

R. E. Ginna Nuclear Power Plant OR6evso0 COLR-6 Revision 0

COLR Cycle 39 2.9.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K, < 1.077 Overpower AT reactor trip heatup setpoint K5 = 0/°F for T < T' penalty coefficient > 0.00 14/°F for T > T' Overpower AT 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 * = 0 seconds f2 (AI) = 0.0% RTP for all Al 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 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 (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-1 0081-A, 'W/estinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

3. WCAP-1 0054-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 PlantCLR7evso0 COLR-7 Revision 0

COLR Cycle 39

4. WCAP-1 1145-P-A, "Westinghouse Small Break LOCA ECCS Evaluation Model Generic Study with the NOTRUMP Code," October 1986.

5. WCAP-1 0079-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 F0 - Surveillance Technical Specification," February 1994.

9. WCAP-1 1397-P-A, "Revised Thermal Design Procedure," April 1989.

10. WCAP-1471 0-P-A, "I-D Heat Conduction Model for Annular Fuel Pellets," May 1998.

11. WCAP-8745, "Design Basis for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," March 1977.

R. E. Ginna Nuclear Power PlantCLR8evso0 COLR-8 Revision 0

COLR Cycle 39 670 650 630

. . . .'! J

i I I , ,iI i r , I 610 I I IL ,

I- I I ,1 I i I I I I I P i, , I , * . i ,

-- "I I 7 -I II. : I . . . .. '5.

590 SI i I * *

i I p 570 550 530 0 0.2 0.4 0,6 0.8 1 1.2 1.4 Power (fraction of 1775 MWt)

Figure COLR-1 Reactor Safety Limits R E. Ginna Nuclear Power Plant R. E Gina uclar owerPlatCRvison9 Revision 0

COLR Cycle 39 Figure COLR-2 REQUIRED SHUTDOWN MARGIN COLR-10 R. E. Ginna Nuclear Power PlantCOR10evso0 Revision 0

COLR Cycle 39 240 220 2), (66.20, 25

/ (14*.46, 219) / (63.91, 219) 200g Ba k .. ....... ... .. ... .

C8 Th1 ! coank I84/

z120o , , ......

Z 20.. .. .... . . . .. . . . .. .. ..... ..... .. . .. . . .... . . ..... .. .. .. .

u' 100.. ..

Z 0 (o 5' (30, 0) 0 10 20 30 40 50 60 70 80 90 100 CORE POWER (Percent of 1,775 MWT)

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 overlap. The bank positions are given as follows:

S Bank D: (184/70) * (P-IO0) + 184 (for 30<P < 100)

S Bank C: (184/70) * (P-IO0) + 184 + 130 (for 0 < P < 66.20)

S Bank B: (184/70) * (P-IO0) + 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 PlantCOR11evso0 COLR-11 Revision 0

COLR Cycle 39 1.2 S1.0 N

U0.8 u_

,m~Total FQ =2.600 S0.6

.-

Elevation (ft) K(Z)

S0.0 1.0

0.4 12.0 1.0 ZO2 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 PlantCOR12evso0 COLR-12 Revision 0

COLR Cycle 39 120 110

(-12, 100) (+6, 100) 100 Unacceptable /__ Unacceptable 90 Operation Operation C

a 80 U=

I-70

~Acceptable o

60 Operation a.

I-50

(-30, 50) (+24, 50) 40 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (percent Al)

Figure COLR-5 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER R. E. Ginna Nuclear Power Plant CL-3Rvso COLR-13 Revision 0

COLR Cycle 39 Table COLR-1 RAOC Summary of W(Z) with HFP %AFD Band of -1 2/+6%

(Top 8% and Bottom 8% Excluded)

Height 150 3000 10000 16000 (feet) MWDIMTU MWD/MTU MWDIMTU MWD/MTU (Bottom) 1.0000 1.0000 1.0000 1.0000 0.00 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 1.4159 1.3493 1.2689 1.2657 1.17 1.4043 1.3384 1.2605 1.2585 1.33 1.3914 1.3264 1.2509 1.2500 1.50 1.3762 1.3121 1.2396 1.2399 1.67 1.3596 1.2966 1.2272 1.2289 1.83 1.3428 1.2808 1.2147 1.2178 2.00 1.3238 1.2632 1.2012 1.2053 2.17 1.3041 1.2449 1.1881 1.1924 2.33 1.2853 1.2275 1.1758 1.1800 2.50 1.2654 1.2095 1.1621 1.1670 2.67 1.2447 1.1941 1.1506 1.1541 2.83 1.2259 1.1826 1.1432 1.1421 3.00 1.2128 1.1704 1.1368 1.1310 3.17 1.2048 1.1614 1.1320 1.1249 3.33 1.1983 1.1573 1.1292 1.1250 3.50 1.1917 1.1532 1.1261 1.1246 3.67 1.1849 1.1485 1.1229 1.1236 3.83 1.1780 1.1437 1.1201 1.1225 4.00 1.1702 1.1379 1.1166 1.1207 4.17 1.1620 1.1328 1.1128 1.1182 4.33 1.1539 1.1296 1.1088 1.1156 4.50 1.1447 1.1258 1.1041 1.1131 4.67 1.1358 1.1215 1.0998 1.1114 4.83 1.1288 1.1171 1.0972 1.1102 5.00 1.1223 1.1122 1.0945 1.1085 5.17 1.1163 1.1069 1.0914 1.1067 5.33 1.1101 1.1016 1.0882 1.1056 5.50 1.1022 1.0961 1.0865 1.1058 5.67 1.0975 1.0894 1.0863 1.1071 5.83 1.0980 1.0827 1.0919 1.1083 R. E. Ginna Nuclear Power Plant CL-4Rvso COLR-14 Revision 0

COLR Cycle 39 Table COLR-1 (Continued)

RAOC Summary of W(Z) with HFP %AFD Band of -1 21+6%

(Top 8% and Bottom 8% Excluded)

Height 150 3000 10000 16000 (feet) MWD/MTU MWDIMTU MWDIMTU MWD/MTU 6.00 1.1003 1.0833 1.0986 1.1088 6.17 1.1036 1.0893 1.1045 1.1098 6.33 1.1061 1.0942 1.1097 1.1130 6.50 1.1083 1.0993 1.1148 1.1172 6.67 1.1100 1.1044 1.1194 1.1208 6.83 1.1111 1.1086 1.1232 1.1236 7.00 1.1118 1.1125 1.1263 1.1269 7.17 1.1118 1.1159 1.1295 1.1311 7.33 1.1112 1.1185 1.1339 1.1356 7.50 1.1099 1.1207 1.1387 1.1399 7.67 1.1080 1.1222 1.1428 1.1434 7.83 1.1054 1.1229 1.1461 1.1461 8.00 1.1021 1.1230 1.1490 1.1483 8.17 1.0978 1.1223 1.1511 1.1499 8.33 1.0930 1.1209 1.1525 1.1508 8.50 1.0885 1.1187 1.1537 1.1511 8.67 1.0874 1.1160 1.1537 1.1507 8.83 1.0913 1.1154 1.1539 1.1498 9.00 1.0967 1.1188 1.1578 1.1481 9.17 1.1007 1.1287 1.1681 1.1462 9.33 1.1038 1.1370 1.1764 1.1474 9.50 1.1105 1.1461 1.1843 1.1541 9.67 1.1200 1.1563 1.1915 1.1714 9.83 1.1273 1.1658 1.1970 1.1890 10.00 1.1357 1.1754 1.2041 1.2068 10.17 1.1427 1.1843 1.2126 1.2242 10.33 1.1434 1.1920 1.2195 1.2414 10.50 1.1454 1.1978 1.2248 1.2573 10.67 1.1488 1.2010 1.2266 1.2681 10.83 1.1461 1.2027 1.2231 1.2731 11.00 1.1385 1.2025 1.2163 1.2704 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 PlantCOR15eiio0COLR-15 Revision 0

COLR Cycle 39 Table COLR-2 Penaltv Factor for Increasina Fn Cycle Burnup Penalty Factor Penalty (MWD/MTU)(a) (%) Multiplier 150 2.00 1.020 294 2.00 1.020 437 2.00 1.020 581 2.10 1.021 724 2.60 1.026 868 2.90 1.029 1011 2.90 1.029 1155 2.70 1.027 1298 2.50 1.025 1442 2.30 1.023

> 1585 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 PlantCOR16evso0 COLR-16 Revision 0

COLR Cycle 39 Table COLR-3 Part-Power W(Z) Generated at 150 MWD/MTU, 75% Power (Top 8% and Bottom 8% Excluded)

Height HFP ARO 75% D at (feet) 180 Steps (Bottom) 1000.00 0.001.00100 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 1.4159 1.4664 1.17 1.4043 1.4507 1.33 1.3914 1.4338 1.50 1.3762 1.4146 1.67 1.3596 1.3939 1.83 1.3428 1.3731 2.00 1.3238 1.3501 2.17 1.3041 1.3266 2.33 1.2853 1.3040 2.50 1.2654 1.2804 2.67 1.2447 1.2560 2.83 1.2259 1.2337 3.00 1.2128 1.2172 3.17 1.2048 1.2062 3.33 1.1983 1.1968 3.50 1.1917 1.1872 3.67 1.1849 1.1771 3.83 1.1780 1.1666 4.00 1.1702 1.1556 4.17 1.1620 1.1448 4.33 1.1539 1.1352 4.50 1.1447 1.1245 4.67 1.1358 1.1137 4.83 1.1288 1.1044 5.00 1.1223 1.0957 5.17 1.1163 1.0873 5.33 1.1101 1.0786 5.50 1.1022 1.0682 5.67 1.0975 1.0612 5.83 1.0980 1.0595 R. E. Ginna Nuclear Power PlantCOR17evio0 COLR-17 Revision 0

COLR Cycle 39 Table COLR-3 (Continued)

Part-Power W(Z) Generated at 150 MWD/MTU, 75% Power (Top 8% and Bottom 8% Excluded)

Height HFP ARO 75% D at (feet) 180 Steps 6.00 1.1003 1.0597 6.17 1.1036 1.0609 6.33 1.1061 1.0615 6.50 1.1083 1.0620 6.67 1.1100 1.0620 6.83 1.1111 1.0616 7.00 1.1118 1.0608 7.17 1.1118 1.0595 7.33 1.1112 1.0578 7.50 1.1099 1.0557 7.67 1.1080 1.0534 7.83 1.1054 1.0506 8.00 1.1021 1.0475 8.17 1.0978 1.0438 8.33 1.0930 1.0399 8.50 1.0885 1.0367 8.67 1.0874 1.0370 8.83 1.0913 1.0425 9.00 1.0967 1.0502 9.17 1.1007 1.0568 9.33 1.1038 1.0625 9.50 1.1105 1.0714 9.67 1.1200 1.0831 9.83 1.1273 1.0930 10.00 1.1357 1.1048 10.17 1.1427 1.1160 10.33 1.1434 1.1205 10.50 1.1454 1.1257 10.67 1.1488 1.1318 10.83 1.1461 1.1314 11.00 1.1385 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 PlantCOR18evso0 COLR-18 Revision 0

COLR Cycle 39 End Notes

1. Limits generated using Reference 1.

2. Limits generated using References 1 through 8 and 10.

3. Limits generated using References I and 8.

4. Limits generated using Reference 9.

5. Limits generated using Reference 11.

R. E. Ginna Nuciear Power Plant OR19evso0 COLR-19 Revision 0