ML14141A032

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Transmittal of Core Operating Limits Report (COLR) for Cycle 38
ML14141A032
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/13/2014
From: Mogren T
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14141A032 (21)
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Text

AR.E. Ginna Nuclear Power Plant

,*rm 1503 Lake Rd.

Exeonn Exe~o Generation Gene ationwww.exeloncorp.-om Ontario, NY 14519-9364 May 13, 2014 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:

Transmittal of Core Operating Limits Report (COLR) for Cycle 38 In accordance with the R.E. Ginna Nuclear Power Plant Improved Technical Specification 5.6.5.d, which requires the submittal of revisions to the COLR, the attached report is hereby submitted. Should you have questions regarding this matter, please contact Thomas Harding (585) 771-5219, or Thomas.HardingJr@cengllc.com.

Respectfully, Thomas G. Mogren Manager - Engineering Services R.E. Ginna Nuclear Power Plant TGM/JPO

Attachment:

R.E. Ginna Nuclear Power Plant, Core Operating Limits Report, Cycle 38 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 38 R.E. Ginna Nuclear Power Plant, LLC May 13, 2014

COLR Cycle 38

-m-" Exelon Generation R.E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 38 Revision 0 Responsible Manager:../ n*k

/ Jo4ýazzaro-May 7, 2014 Effective Date:

Controlled Copy No.

Record Cat.# 4.43.2 R.E. Ginna Nuclear Power Plant COL-R-1 Revision 0

COLR Cycle 38 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 (FQ(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 Plant COLR-2 Revision 0

COLR Cycle 38 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 thatappear 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 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/OF 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/OF.

where:

ARO stands for All Rods Out BOL stands for Beginning of Cycle Life R.E. Ginna Nuclear Power Plant COLR-3 Revision 0

COLR Cycle 38 EOL stands for End of Cycle Life HZP stands for Hot Zero Power RTP stands for RATED THERMAL POWER 1

2.4 Shutdown Bank Insertion Limit (LCO 3.1.5) 2.4.1 The shutdown bank shall be fully withdrawn which is defined as _>220 steps.

1 2.5 Control Bank Insertion Limits (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 2.6 Heat Flux Hot Channel Factor (FQ(Z))

(LCO 3.2.1) 2.6.1 FQ(Z)_<CFQ*K(Z)/PforP>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 Plant COLR-4 Revision 0

COLR Cycle 38 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 INCORE-3D software.

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

where:

FRTPAH= 1.72 PFAH = 0.3, and P = THERMAL POWER / RATED THERMAL POWER 3

2.8 AXIAL FLUX DIFFERENCE (LCO 3.2.3) 2.8.1 The AFD acceptable operation limits are provided in Figure COLR - 5.

5 2.9 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1)

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

COLR Cycle 38 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 >_ 0.0185/°F penalty setpoint coefficient Measured lead time constant -i1 >- 25 seconds Measured lag time constant '2 -<5 seconds fl(AI) 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%, fl(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 COLR-6 Revision 0

COLR Cycle 38 2.9.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4 *< 1.077 Overpower AT reactor trip heatup setpoint K5 = 0/°F for T < T' penalty coefficient _>0.0014/°F for T _>T' Overpower AT reactor trip thermal K6 > 0.00/°F for increasing T time delay setpoint penalty = 0.00/°F for decreasingT Measured impulse/lag time constant T3 = 0 seconds f2 (AI) = 0.0% RTP for all Al 2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) 4 Limits (LCO 3.4.1) 2.10.1 The pressurizer pressure shall be _>2205 psig.

2.10.2 The RCS average temperature shall be *577.5 'F.

2.10.3 The RCS total flow rate shall be _>177,300 gpm (includes 4% minimum flow uncertainty per Revised Thermal Design Methodology).

1 2.11 Boron Concentration (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-1 0054-P-A and WCAP-1 0081-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

R.E. Ginna Nuclear Power Plant COLR-7 Revision 0

COLR Cycle 38

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", Thompson, C.M., et. al., July 1997.
4. WCAP-11145-P-A, "Westinghouse Small Break LOCA ECCS Evaluation Model Generic Study with the NOTRUMP Code", Rupprecht, S. D., et. al., October 1986.
5. WCAP-1 0079-P-A, "NOTRUMP - A Nodal Transient Small Break and General Network Code", Meyer, P. E., August 1985.
6. WCAP-1 6009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)", January 2005.
7. WCAP-1 261 0-P-A, "VANTAGE + Fuel Assembly Reference Core Report," April 1995.
8. WCAP-1 0216-P-A, Revision 1A (Proprietary), Relaxation of Constant Axial Offset Control FQ - Surveillance Technical Specification, February 1994.
9. WCAP-11397-P-A, "Revised Thermal Design Procedure", April 1989.
10. WCAP-1471 0-P-A, "1-D Heat Conduction Model for Annular Fuel Pellets," Shimeck, D.

J., May 1998.

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

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

COLR Cycle 38 670 650

-' - --, - , -,- n ,, , , "1 "' ' , ,- . - . . . . . . - T 1 r- r - "

. .... ~201 J .ia J I [ L L

  • I I 1 1 _J 630

, i~~~~

T T 610 ,, , -T-

! !...... "!T

: - -, i r * '

590 570 550 530 0 0.2 0.4 0.6 0.8 1.2 1.4 Power (fraction of 1775 MWt)

Figure COLR - 1 Reactor Safety Limits R.E. Ginna Nuclear Power Plant COLR-9 Revision 0

COLR Cycle 38 3

2.5 ACCEPTABLE 2 OPERATION L 2 S1.5 (2500, 1.80) 1(0,t.80)

-t -_- ------

z (2500,1.30) (0, 1.30)

I-UNCEPTABLE OPRAIONj 0

250 0O 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 0

COLR Cycle 38 240 (16,74, 225) (66.20, 225) 220 (14.46, 219) (63.91, 219) 200 B Bank (0,181) (100, 104) 180

  • 160 140 Z 120 (0

0 x 100 z

m o 8o 0 Bank 60 (0. 51) 40 20 (30,0) 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:
  • Bank D: (184170) * (P-100) + 184 (for 30 < P < 100) o Bank C: (184/70) * (P-100) + 184 + 130 (for 0 < P < 66.20) o Bank B: (184170) * (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-1 1 Revision 0

COLR Cycle 38 1.2 N

S1.0 L,.

0 U

IL 0.8 Total Fa = 2.600 W 0.6 I-Elevation (ft) 1.0z 0.0 1.0

< 0.4 L-12.0 1.0 N

E 0.2 0

z 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 38 120 110 100 90 80 70 60 E

50 40 30 20 10 0

40 -30 -20 -10 0 10 20 30 40 50 Axial Rux 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 COLR-13 Revision 0

COLR Cycle 38 Table COLR - 1 RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%

(TOP 8% and BOTTOM 8% EXCLUDED) 150 3000 10000 16000 Height (feet) 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 1.4136 1.3502 1.2666 1.2605 1.17 1.4023 1.3394 1.2598 1.2531 1.33 1.3895 1.3273 1.2517 1.2445 1.50 1.3744 1.3130 1.2420 1.2344 1.67 1.3580 1.2973 1.2313 1.2234 1.83 1.3412 1.2815 1.2203 1.2122 2.00 1.3224 1.2637 1.2078 1.1998 2.17 1.3028 1.2455 1.1948 1.1867 2.33 1.2840 1.2280 1.1824 1.1744 2.50 1.2642 1.2092 1.1692 1.1634 2.67 1.2438 1.1939 1.1558 1.1546 2.83 1.2256 1.1844 1.1436 1.1479 3.00 1.2133 1.1756 1.1331 1.1422 3.17 1.2054 1.1686 1.1267 1.1383 3.33 1.1984 1.1640 1.1241 1.1360 3.50 1.1918 1.1592 1.1219 1.1336 3.67 1.1851 1.1538 1.1195 1.1308 3.83 1.1783 1.1484 1.1171 1.1276 4.00 1.1705 1.1421 1.1141 1.1233 4.17 1.1623 1.1352 1.1107 1.1193 4.33 1.1541 1.1290 1.1071 1.1172 4.50 1.1451 1.1241 1.1028 1.1170 4.67 1.1359 1.1201 1.0990 1.1173 4.83 1.1278 1.1156 1.0968 1.1168 5.00 1.1210 1.1105 1.0947 1.1160 5.17 1.1151 1.1051 1.0917 1.1145 5.33 1.1089 1.0998 1.0887 1.1127 5.50 1.1016 1.0941 1.0883 1.1117 5.67 1.0952 1.0875 1.0904 1.1111 5.83 1.0920 1.0816 1.0932 1.1104 R.E. Ginna Nuclear Power Plant COLR-14 Revision 0

COLR Cycle 38 Table COLR - 1 (Continued)

RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%

(TOP 8% and BOTTOM 8% EXCLUDED) 150 3000 10000 16000 Height (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.00 1.0937 1.0826 1.0961 1.1105 6.17 1.0979 1.0889 1.1001 1.1130 6.33 1.1007 1.0945 1.1060 1.1181 6.50 1.1031 1.1000 1.1120 1.1232 6.67 1.1051 1.1051 1.1172 1.1272 6.83 1.1066 1.1095 1.1216 1.1305 7.00 1.1076 1.1137 1.1257 1.1334 7.17 1.1081 1.1173 1.1291 1.1355 7.33 1.1079 1.1201 1.1317 1.1367 7.50 1.1072 1.1224 1.1338 1.1372 7.67 1.1057 1.1241 1.1350 1.1369 7.83 1.1038 1.1250 1.1355 1.1358 8.00 1.1010 1.1253 1.1353 1.1337 8.17 1.0975 1.1248 1.1341 1.1308 8.33 1.0935 1.1236 1.1320 1.1282 8.50 1.0885 1.1214 1.1304 1.1271 8.67 1.0828 1.1185 1A1302 1.1268 8.83 1.0786 1.1182 1.1322 1.1281 9.00 1.0803 1.1218 1.1392 1.1323 9.17 1.0870 1.1323 1.1498 1.1390 9.33 1.0925 1.1411 1.1592 1.1456 9.50 1.0988 1.1498 1.1688 1.1524 9.67 1.1063 1.1580 1.1785 1.1588 9.83 1.1134 1.1645 1.1873 1.1661 10.00 1.1196 1.1730 1.1961 1.1819 10.17 1.1266 1.1832 1.2046 1.2046 10.33 1.1373 1.1914 1.2124 1.2239 10.50 1.1467 1.1981 1.2171 1.2402 10.67 1.1497 1.2017 1.2182 1.2531 10.83 1.1474 1.2006 1.2183 1.2624 11.00 1.1400 1.1953 1.2138 1.2638 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 38 Table COLR - 2 (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 38 Table COLR - 3 Part-Power W(Z) generated at 150 MWD/MTU, 75% Power (Top 8% and Bottom 8% Excluded)

Height (feet) HFP ARO 75% D at 180 (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 1.4136 1.4700 1.17 1.4023 1.4546 1.33 1.3895 1.4378 1.50 1.3744 1.4186 1.67 1.3580 1.3981 1.83 1.3412 1.3772 2.00 1.3224 1.3542 2.17 1.3028 1.3307 2.33 1.2840 1.3081 2.50 1.2642 1.2845 2.67 1.2438 1.2602 2.83 1.2256 1.2381 3.00 1.2133 1.2223 3.17 1.2054 1.2110 3.33 1.1984 1.2008 3.50 1.1918 1.1910 3.67 1.1851 1.1812 3.83 1.1783 1.1712 4.00 1.1705 1.1602 4.17 1.1623 1.1489 4.33 1.1541 1.1377 4.50 1.1451 1.1259 4.67 1.1359 1.1139 4.83 1.1278 1.1029 5.00 1.1210 1.0934 5.17 1.1151 1.0849 5.33 1.1089 1.0764 5.50 1.1016 1.0668 5.67 1.0952 1.0583 5.83 1.0920 1.0527 6.00 1.0937 1.0520 R.E. Ginna Nuclear Power Plant COLR-17 Revision 0

COLR Cycle 38 Table COLR - 3 (Continued)

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

Height (feet) HFP ARO 75% D at 180 6.17 1.0979 1.0540 6.33 1.1007 1.0545 6.50 1.1031 1.0549 6.67 1.1051 1.0552 6.83 1.1066 1.0555 7.00 1.1076 1.0559 7.17 1.1081 1.0557 7.33 1.1079 1.0546 7.50 1.1072 1.0525 7.67 1.1057 1.0500 7.83 1.1038 1.0475 8.00 1.1010 1.0449 8.17 1.0975 1.0417 8.33 1.0935 1.0384 8.50 1.0885 1.0347 8.67 1.0828 1.0304 8.83 1.0786 1.0271 9.00 1.0803 1.0285 9.17 1.0870 1.0346 9.33 1.0925 1.0399 9.50 1.0988 1.0465 9.67 1.1063 1.0544 9.83 1.1134 1.0622 10.00 1.1196 1.0693 10.17 1.1266 1.0775 10.33 1.1373 1.0894 10.50 1.1467 1.0995 10.67 1.1497 1.1028 10.83 1.1474 1.1035 11.00 1.1400 1.1025 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 Revision 0

COLR Cycle 38 END NOTES

1. (Limits generated using Reference 1)
2. (Limits generated using References 1 tthrough 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

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