ML081980122

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R. E. Ginna Nuclear Power Plant - Transmittal of Core Operating Limits Report (COLR) Cycle 34, Revision 1
ML081980122
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/10/2008
From: Joseph Pacher
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML081980122 (17)
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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 Nuclear Generation Group July 10, 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 David Wilson at (585) 771-5219.

/VVe truly yours, Joseph E. Pacher Enclosure cc: S. J. Collins, NRC D. V. Pickett, NRC Resident Inspector, NRC

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COLR Cycle 34 Constellation Energy R.E. Oinrid Nuclear Powvvr Plarnt R.E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 34 Revision I Responsible Manager:

Dave Wilson Effective Date:

7/9/2008 Controlled Copy No.

Record Cat.# 4,43.2 R.E. Ginna Nuclear Power Plant COLR-1 Revision 1

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 (FNAH) 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 1

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 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/OF 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 1

COLR Cycle 34 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 2!220 steps.

2.5 Control Bank Insertion Limits1 (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.

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 R.E. Ginna Nuclear Power Plant COLR-4 Revision 1

COLR Cycle 34 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)d (LCO 3.2.2) 2.7.1 FNAH < FRTPAH * (1 + PFAH * (1-P))

where:

FRTPAH= 1.72 for 422 V+ fuel and 1.248 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.

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

R.E. Ginna Nuclear Power Plant COLR-5 Revision 1

COLR Cycle 34 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 r1 > 25 seconds Measured lag time constant 2 < 5 seconds

-C fl(AI) 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 = 01/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 -r3 = 0 seconds f2 (Al) = 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 Ž_2205 psig.

R.E. Ginna Nuclear Power Plant COLR-6 Revision 1

COLR Cycle 34 2.10.2 The RCS average temperature shall be _ 577.5 OF.

2.10.3 The RCS total flow rate shall be Ž_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 _>

2500 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", 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-12610-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, "I-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-7 Revision 1

COLR Cycle 34 670 650 Fi llll~

e T Lr -- 1F~~ 1 -

I 1 l l III I -

630 I IT T I l d I I 610 uL IM 590 Power (fraction of 175M t 570 550 530 Plantio Power of175 MW R.E. Ginna Nuclear P R Gi. N c Pa. . . I 1 T1 Zevision 1

COLR Cycle 34 3

9 0

0 2500 2000 1500 1000 500 COOLANT BORON CONCENTRATION (ppm)

I....... One Loop Operation Two Loop Operation -

Figure COLR - 2 REQUIRED SHUTDOWN MARGIN R.E. Ginna Nuclear Power Plant COLR-9 Revision 1

COLR Cycle 34 240 (16.74, 228) (66.20, 225) 220 (63..1. 219)

(14.46, 219) 200 /___ _

(8, i18) (100,184I 180 C 160 140 Z 120 100 z

a 0 80 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: (184/70) * (P-100) + 184 (for 30 < P < 100)
  • Bank C: (184170) * (P-100) + 184 + 130 (for 0 < P < 66.20)
  • Bank B: (184/70) * (P-100) + 184 + 130 + 130 (for 0 <P 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 0 Revision 1

COLR Cycle 34 1.2 t

  • '1.0-0..

0 ii. 0.8 C

2 Total F 0 = 2.600
  • 0.6 0.

Elevation (ft) K(Z) 0.0 1.0

<0.4 12.0 1.0 0I N

E0.2 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-1 1 Revision 1

COLR Cycle 34 120 110 _ _ _ _ _ _

(12 100) (+6100) 100 0 ..... Operation / ... ...... "- Operation ..

80*o  ! ...

..... ......*-' ,i ........

so -

40 ........(-30,60)

........ -----...... ...... ..... .....K+4,

..... 60) ......... ---

40- -

20 r 10-0'- -.- '

-- 'i -

I I I

-80 -40 -30 -20 -10 0 10 20 30 40 50 Axial lux Difference (percent A,)

Figure COLR - 5 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER R.E. Ginna Nuclear Power Plant COLR-1 2 Revision 1

COLR Cycle 34 Height 150 2000 10000 16000

.. Afeeýt. MWD/MTU MWD/MTU MWD/MTU MWD/MTU (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 1.1102 1.1074 1.1284 5.8 1.1097 1.1055 1.1147 1.1366 Figure 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-1 3 Revision 1

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 1,1780 1.1801 8,2 1.1059 1.1213 1.1748 1,1735 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 (T o p)............

Figure 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-14 Revision 1

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 Figure Table COLR - 2 Penalty factor for increasing FQ R.E. Ginna Nuclear Power Plant COLR-115 Revision 1

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-16 Revision 1

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