ML081290512

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R. E. Ginna - Transmittal of Core Operating Limits Report (Colr), Cycle 34, Revision 0
ML081290512
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/04/2008
From: Joseph Pacher
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML081290512 (18)
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Joe Pacher R.E. Ginna Nuclear Power Plant, LLC Manager, Nuclear Engineering Services 1503 Lake Road Ontario, New York 14519-9364 585.771.5208 585.771.3392 Fax joseph.pacher@constellation.com NuConstellatio- Group Energyr Nuclear Generation May 4, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 Transmittal of Core Operating Limits Report (COLR)

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. If you should have any questions regarding this submittal, please contact Thomas Harding at (585) 771-3384.

?Ve truly yours, oseph E. Pacher Enclosure cc: S. J. Collins, NRC D. V. Pickett, NRC Resident Inspector, NRC

/00 f ý6-?

COLR Cycle 34

~ Constellation Energy' R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 34 Revision 0 Responsible Manager-Dave Wilson Effective Date: 4f- /_2__5__ /___O___

4/25/2008 Controlled Copy No.

Record Cat.# 4.43.2 'IA R.E. Ginna Nuclear Power Plant COLR-11 Revision 0

COLR Cycle 34 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 (FN AH) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reactor Trip System (RTS) 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 34 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 l 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.

R.E. Ginna Nuclear Power Plant COLR-3 Revision 0

COLR Cycle 34 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/IF 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 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) 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.

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.

R.E. Ginna Nuclear Power Plant COLR-4 Revision 0

COLR Cycle 34 2

2.6 Heat Flux Hot Channel Factor (FQ(Z))

(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.

2.6.5 The FQ(Z) penalty factors are provided in Table COLR - 2.

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 for 422 V+ fuel and 1.60 for OFA fuel, 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.

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

COLR Cycle 34 5

2.9 Reactor Trip System (RTS) Setpoints (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/ 0 F penalty setpoint coefficient Measured lead time constant 1, - 25 seconds Measured lag time constant "C 2 < 5 seconds fl(Al) constants -3.08 (14% + (qt - qb)} when qt - qb is < - 14% RTP 0% RTP when -14% RTP < qt - qb is < + 6% RTP 2.27 {(qt - qb) -6%} when qt - qb is > 6% RTP 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 = 0/0 F for T < T' penalty coefficient _ 0.0014/0 F for T _>

T' Overpower AT reactor trip thermal K6 > 0.00/1F for increasing T time delay setpoint penalty = 0.00/°F for decreasingT Measured impulse/lag time constant 3= 0 seconds f 2 (AI) = 0.0% RTP for all Al R.E. Ginna Nuclear Power Plant COLR-6 Revision 0

COLR Cycle 34 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 IF.

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, 2500 ppm. Boron the refueling canal, and the refueling cavity shall be _>

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.

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

COLR Cycle 34

3.0 REFERENCES

1. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.
2. WCAP-1 0054-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", 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-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)", January 2005.
7. WCAP-1 2610-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-14710-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 34 670 T- I - 11-T T T .I -

650 2425 psia T T T 11- I T T 50 psia 250 psia 630 2015

. .015 psia psia 610 T T I, 1775 psia 590 T

570 4

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 P ower Plant COLR-9 F*evision 0

COLR Cycle 34 2.5 ACCEPTABLE OPERATION S2 LU (2500,1.80) a I -*

z_

z (2500, 1.30) (0, 1.30) 0 (A

0 I-l UNACETABLE OPRATIONJ 0 4-2500 20000 1500 1000 500 0 COOLANT BORON CONCENTRATION (ppm)

I ------- One Loos) Operation Two Loop Operation Figure COLR - 2 REQUIRED SHUTDOWN MARGIN RE. Ginna Nuclear Power Plant COLR-10 Revision 0

COLR Cycle 34 240 (16.74. 225) (6620. 225)

(14.46, 219) (03.91. 219) 220 . . . . ...

200 B Bank (5181) (100, ¶84) 220 16 0 .. .. . . .. . . . . .. . . . ........ ... . . . . ........

C 180

,*~ .......................

S10 06 60 100 .

20 (3,0 0

80 9 0 8020 10 20 30 40 50o 6 60 70 0 9 0 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: (184/70) * (P-100) + 184 (for 30 < P < 100)
  • Bank C: (184/70) * (P-100) + 184 + 130 (for 0 < P < 66.20)
  • 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 34 1.2 N

~1.0

  • £I..

0 U

I. 0.8 1--

Total Fo = 2.600 430.6 I-o.

Elevation (ft) K(Z) 0.0 1.0

<4U "0 12.0 1.0 N

0.2F 0

z 0.0 I-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 34 120 110 100 90 so 70 r,

a.

60 E

.50 a-40 30 20 10 0

40 -30 -20 -10 0 10 20 30 40 50 Axial Rux Difference (percent AM Figure COLR - 5 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER R.E. Ginna Nuclear Power Plant COLR-113 Revision 0

COLR Cycle 34 Height 150 2000 10000 16000

_feet) MWD/MTU MWD/MTU MWD/MTU MWDIMTU (Bottom) 0.0 1.0000 1.0000 1.0000 1.0000 0.2 1.0000 1.0000 1.0000 1.0000 0.4 1.0000 1.0000 1.0000 1.0000 0.6 1.0000 1.0000 1.0000 1.0000 0.8 1.0000 1.0000 1.0000 1.0000 1,0 1.4388 1.4082 1.2904 1.2846 1.2 1.4231 1.3926 1.2794 1.2737 1.4 1.4039 1.3736 1.2656 1.2600 1.6 1.3824 1.3523 1.2500 1.2448 1.8 1.3591 1.3292 1.2331 1.2285 2.0 1.3342 1.3044 1.2150 1.2111 2.2 1.3092 1.2784 1.1961 1.1930 2.4 1.2864 1.2548 1.1770 1.1745 2.6 1.2647 1.2322 1.1572 1.1562 2.8 1.2425 1.2098 1.1388 1.1380 3.0 1.2207 1.1901 1.1272 1.1217 3.2 1.2011 1.1747 1.1208 1.1156 3.4 1.1872 1.1642 1.1162 1.1149 3.6 1.1799 1.1583 1.1110 1.1126 3.8 1.1742 1.1552 1.1058 1.1143 4.0 1.1694 1.1523 1.1045 1.1177 4.2 1.1653 1.1491 1.1048 1.1209 4.4 1.1605 1.1456 1.1051 1.1240 4.6 1.1552 1.1415 1.1051 1.1264 4.8 1.1491 1.1367 1.1043 1.1277 5.0 1.1422 1.1310 1.1032 1.1281 5.2 1.1345 1.1247 1.1030 1.1276 5.4 1.1266 1.1179 1.1035 1.1269 5.6 1.1170 1 1.1102 1.1074 1.1284 5.8 1.1097 1.1055 1.1147 1.1366 Table COLR - 1 RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%

(TOP 8% and BOTTOM 8% EXCLUDED)

R.E. Ginna Nuclear Power Plant COLR-14 Revision 0

COLR Cycle 34 Height 150 2000 10000 16000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.0 1.1130 1.1105 1.1230 1.1474 6.2 1.1165 1.1172 1.1331 1.1575 6.4 1.1194 1.1224 1.1437 1.1661 6.6 1.1227 1.1268 1.1527 1.1734 6.8 1.1249 1.1302 1.1607 1.1794 7.0 1.1259 1.1325 1.1674 1.1839 7.2 1.1258 1,1337 1.1727 1.1867 7.4 1.1245 1.1336 1.1765 1.1879 7.6 1.1219 1.1322 1.1787 1.1872 7.8 1.1180 1.1293 1.1793 1.1847 8.0 1.1127 1.1252 1A1780 1.1801 8.2 1.1059 1.1213 1.1748 1A1735 8.4 1.0980 1.1183 1.1701 1.1655 8.6 1.0870 1.1142 1.1619 1.1532 8.8 1.0765 1.1096 1.1536 1.1426 9.0 1.0777 1.1096 1.1547 1.1489 9.2 1.0849 1.1122 1.1603 1.1588 9.4 1.0973 1.1198 1.1750 1.1707 9.6 1.1099 1.1322 1.1985 1.1829 9.8 1.1262 1.1488 1.2273 1.1971 10.0 1.1409 1.1626 1.2571 1.2151 10.2 1.1520 1.1718 1.2845 1,2381 10.4 1.1611 1.1813 1.3080 1.2632 10.6 1.1674 1.1960 1.3278 1.2800 10.8 1.1757 1.2074 1.3393 1.2852 11.0 1.1871 1.2131 1.3406 1.2846 11.2 1.0000 1.0000 1.0000 1.0000 11.4 1.0000 1.0000 1.0000 1 .0000 11.6 1.0000 1.0000 1.0000 1.0000

11. 8 1.0000 1.0000 1.0000 1.0000 12.0 1.0000 1.0000 1.0000 1.0000 (Top)

Table COLR - 1 (Continued)

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

(TOP 8% and BOTTOM 8% EXCLUDED)

R.E. Ginna Nuclear Power Plant COLR-15 Revision 0

COLR Cycle 34 Cycle Burnup, Penalty Factor Penalty MWD/MTU Multiplier 3557 2.00 1,0200 3705 2.18 1.0218 3853 2,09 1,0209 4001 2.00 1,0200 I Table COLR - 2 Penalty factor for increasing FQ RE. Ginna Nuclear Power Plant COLR-16 Revision 0

COLR Cycle 34 END NOTES

1. (Limits generated using Reference 1)
2. (Limits generated using References 1 through 7 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-117 Revision 0

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