ML063180226

Transmittal of Core Operating Limits Report

ML063180226
Person / Time
Site:	Ginna
Issue date:	11/03/2006
From:	Korsnick M Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML063180226 (21)

Text

Maria Korsnick R.E. Ginna Nuclear Power Plant, LLC Site Vice President 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria. korsnick@constellatidn.com Con.--stellation Generation Group Energy-November 3, 2006 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, which requires the submittal of revisions to the COLR, the attached report is hereby submitted. Should you have questions regarding this matter, please contact Mr. Robert Randall at (585) 771-3734, or robert.randal I@constellation.com.

Very truly yours, M4arytG. K(s ck Enclosure cc: S. J. Collins, NRC P. D. Milano, NRC Resident Inspector, NRC A-oaI j0 iC (

7, COLR Cycle 33 R.E Gnna Nucea Poe Pn R.E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 33 Revision 0 Responsible Managers. &9iLQ I

Robert'Randall Effective Date:-

10/13/2006 Controlled Copy No.

Record Cat.# 4.43.2 R.E. Ginna Nuclear Power PlantCOR1evso0 ICOLRA Revision 0

COLR Cycle 33 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 PlantCLR2evso0 COLR-2 Revision 0

COLR Cycle 33 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)l (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' (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 inoperation.

2.2.2 The SHUTDOWN MARGIN in MODE 4 when both reactor coolant pumps are not inoperation and inMODE 5shall 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 PlantCLR3evso0 COLR-3 Revision 0

COLR Cycle 33 2.3 MODERATOR TEMPERATURE COEFFICIENT' (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 +5.00 pcm/OF for power levels below 70% RTP and less than or equal to 0 pcm/ 1F 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 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' (LCO 3.1.5) 2.4.1 The shutdown bank shall be fully withdrawn which is defined as Ž220 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.

R.E. Ginna Nuclear Power PlantCLR4evso0 COLR-4 Revision 0

COLR Cycle 33 2.6 Heat Flux Hot Channel Factor (FQ(Z)) 2 (LCO 3.2.1) 2.6.1 FQ(Z):* CFQ/P K(Z) for P > 0.5 FQ(Z):

• CFQIO.5 K(Z) 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) isprovided inFigure COLR - 4 2.6.4 W(Z-) values are provided in Tables COLR - 1 and COLR - 2.

2.6.5 The FQ(Z) penalty factors are provided inTable COLR - 3.

2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN aH)

(LCO 3.2.2) 2.7.1 FN AH <- FRTP AH * (1 + PFaH * (1-P))

where:

FRTP AH= 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 inFigure COLR - 5.

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

COLR Cycle 33 2.9 Reactor Trip System (RTS) SetpointS5 (LCO 3.3.1) 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K,

• 1.19 Overtemperature AT reactor trip K2 Ž0.00093/psi depressurization setpoint penalty coefficient Overtemperature AT reactor trip heatup K3Ž0.01 85/OF penalty setpoint coefficient Measured lead time constant 1 25 seconds T,

Measured lag time constant T2 *5 seconds f I(AI) constants -3.08 {1 4% + (qt - qb)} when qt - qb iS< - 14% RTP 0% RTP when -14% RTP

• qt - qbis:!* + 6% RTP 2.27 {(qt - qb) -6%) when qt - cib 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 Ž0.00 14/OF for T ŽT' Overpower AT reactor trip thermal K6 Ž! 0.00/0 F for increasing T time delay setpoint penalty = 0.00/0 F for decreasingT Measured impulse/lag time constant r3= 0 seconds f2(AI) = 0.0% RTP for all Al R.E. Ginna Nuclear Power PlantCOR6evso0 COLR-6 Revision 0

COLR Cycle 33 2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits4 (LCO 3.4.1) 2.10.1 The pressurizer pressure shall be Ž!2205 psig.

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).

2.11 Boron Concentration1 (LCO 3.9.1) 2.11.1 The boron concentrations of the hydraulically coupled Reactor Coolant System, I

the refueling canal, and the refueling cavity shall be Ž!2300 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 inthis parameter.

R.E. Ginna Nuclear Power PlantCO-7Rvso0 COLR-7 Revision 0

COLR Cycle 33

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 EGCS Evaluation Model Using the NOTRUMP Code," August 1985.

3. WCAP-1 0054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break EGGS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and GOSI Condensation Model", Thompson, G.M., et. al., July 1997.

4. WCAP-11145-P-A, "Westinghouse Small Break LOCA EGGS Evaluation Model Generic Study with the NOTRUMP Code", Rupprecht, S. D., et. al., October 1986.

5. WGAP-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 LOGA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)", January 2005.

7. WGAP-1 2610O-P-A, "VANTAGE + Fuel Assembly Reference Core Report," April 1995.

8. WGAP-1 021 6-P-A, Revision. lA (Proprietary), Relaxation of Constant Axial Offset Control FQ - Surveillance Technical Specification, February 1994.

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

10. WGAP-14710-P-A, "1-D Heat Conduction Model forAnnular Fuel Pellets," Shimeck, D.

J., May 1998.

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

R.E. Ginna Nuclear Power Plant LR8evso0 COLR-8 Revision 0

COLR Cycle 33 670 1, 4, 1 11- 11 11 2425 psia 650 42 a 5p 2250 psia 630

-.1 1 1- L- L- IL-2015 psi 015 'a,, T i -

i T 610 1775 psia 590 570 V

1. 4' -

A, j ,

J, 550 IL 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 COLR-9F evision 0

COLR Cycle 33 3

2.5 OPERATION 2

wA (2500,1.80)

.. (0,. 1

...,1.8. )

1.5 42500, 1.30) (0,1.30)

0. I UACEPTAuLEI OPRTO 0 1 250 0 2000 1500 1000 500 0 COOLANT BORON CONCENTRATION (ppm)

I. - -.- -. One Loop Operatlon - TWo Loop OperM.lon I Figure COLIR - 2 REQUIRED SHUTDOWN MARGIN R.E. Ginna Nuclear Power Plant CL-ORvso COLR-10 Revision 0

GOLR Cycle 33

_ . .0..........

2000 ISO ....................... .... ....... ......... I x '00 ...........

do ...... . ......

0 0 20 30 40 50 00 10 00 0 90 100 CORE POWER (P*IowO of10 W The top of the arctive fuel corresponds to 219 steps for Banks 8 and G only (all 4122V.-fuel) and 210 steps for Rank 0 (OFA fuel only and based on the 422V+ rod boffom). The ARC parking position may be any position abov.e the oorreporrdirrg top of active fuel fot each respective bank rhe Control rod tip-totlip distance is definied as 130 steps whirle rods are mnoving in overlap. The bank.positions are given as follows:

" ank D (184070) (P, 100) - 184 (for 3401;P 100)

" Bank C (184170) (P-100) - 184 +.130 (for 0 SP :; 6.20)

" Dank . 1184(70) (P-100) + 164 + 130 - 130 (for 0s Ps 18,74)

Whfere 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 33 1.2

~1.0 0

0.'

VL0.8 Total Fa = 2.600

• 0.6 Elevation (ft) K(Z) 0.0 1.0 Qf4 12.0 1.0 0

z Q00 00 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 CL-COLR-12 Revision 0

COLR Cycle 33 120 U

(.24.50)

GD

-60 .40 -30 -20 -10 0 10 20 30 40 50 Axial Rux Difference (percent Al)

NOE AFO bands applicable to a cycle burnup of less than or equal to 14,000 MWOINMr.

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 33 120 110 100 90 s0 CL 70 s0 80 V-40 30 20 10 01 i-- i 4i i-

-60 -40 -30 -20 -10 0 10 20 30 40 80 Axial Rux Difference (percent Al)

NOTE: AFO bands applicable to a cycle burnup of greater than 14,000 NWiDIMTU.

Figure COLR 1 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER (cont)

R.E. Ginna Nuclear Power PlantCOR14evso0 COLR-14 Revision 0

COLR Cycle 33 Height (feet)

'go 18000 MWD/MTU D/NffMU rfWMIMTU 1 0000 1.0000 1 0000 1 0000 1.0000 _ 1ý0000 1ý0000_

(1.0 1.0000 1.0000 i 1,0000 1.0000 0.2 1,0000 1.0000 1,0000 1.3142 1,3258 1.2736 1.2528 1,3017 1.3126 12644 1 2446 08

__1, 2,652- 1.2742 1,2358 1.2524 1.2191 2.0 1,2293 1.2014 1 2Mi1 1,2058 13 29 1 1722 2.4. 1:18ý52 11861 50 { 1 0 26 1,1674 1,1586 K 1.1467. . 1.1400 1 8 1.53 1.1369 1.311.1252 1,1364 I 1.1253 1.1188 1.1142 1....15 1.1210...

.113

..... 1.......

3.4 3.6 1.1204 1118111 [ 1.13 3.8 1,1202 1.113 1.1097 I 1,1215 1.1195 1 1134 11089 1.1250

-420 1442 1.1188 11128 1.1080 1,1279 1.176 1.18 1,1068 1.1301 1'..1169 1 105 _......- _110'G54.__.-.. .....1 3.26.........

4,8 1.1139 if 119.1 1 1 310711136 1.1114' 1,1064 110G14 1.1406 5,2 .......

... 3 085........... 10985...... 1:1436 5A4 1 104 1.0996 10991 L.1,1453 5.6 1,10483 1098.0 1.1033 1,1469 5.8 1.1121 1ý.1027 1.1105 11508 60 1.1222 1 1127 1;1208,. 1:1598 62 1,1319 1 1227 1 1330 I 1.1882 1.1406 1.1312 14......1 1 1-83 1 1390 1.1559 1 1.1796 764.

1,1 549 1.4,59 116551 1841 1.1603 1.11511 1 1i8~ 1,1895 Table COLR - 1 RAOC Summary of W(Z) with HFP %AFD Band of -12/+6% (TOP 8% and BOTTOM 8%

EXCLUDED) 0 MWD/MTU through 14000 MWD/MTU of Cycle Burnup R.E. Ginna Nuclear Power PlantCLR15evso0 COLR-15 Revision 0

COLR Cycle 33 IHeight 1SO 2000 NVND/MTU MWOIMT MWDIMTU 7.2 1 1,143 1.15 33 1.1807 I~~ 1 16 70j 13 16 18 76 1160 1.1694 1ý1896 1,2006 7.8 _1.1674 _1,1741 1.1915 1.2010 80 1.1850 1,1776 11916 119 8.2 1,1608 117811896 1,1965 8.4 1.1538 1,1802 1 1859 1.1918 88 1.1478 1 11805 11,9 1.18m 88.. .45... .....

.. ........... 1. ....

......... 1 17161 7 6 _

90, 118 11964 1.1714 11826 92 1.1591 1,2145 1.1791 . 1,1952 9.4 1 1765 1.2352 1-2020 1.2168 9.6 1195 12555 1.23463 1.2372 986 1,2084 1.2746 1 26,t6 I 12568 10.0 I 1.2234 1.2929 I2 5 1.2661 102 .228 13105 1148 1,2725 104A 1,2566 1.3243 38 1 ,12886 106 1ý2738.1.327 7 13577 I 1,3043 10.8 I 1,3008 1,13359 1.3756 1317 110 12923 1,3452 1 .1378911,3150 11.2 10000 ~ 40.q0 100 f 1.0000 11.4 i 1,0000 ..J........

1.0000 ..... 10.0I00 1,0(000 1.0000 12.0 1.0000 1 10000 1.0000 a.go"J.

Table COLR - 1 (Continued)

RAQO Summary of W(Z) with HFP %AFD Band of -12/+6% (TOP 8% and BOTTOM 8%

EXCLUDED) 0 MWD/MTU through 14000 MWD/MTU of Cycle Burnup (cont)

R.E. Ginna Nuclear Power PlantCLR16evso0 COLR-16 Revision 0

COLR Cycle 33 Height 10200 WZ i~io~~ru (fet) 2000~. 10000 (fel WBo VV/M W/Nr 00 10000 1,0000 1.0000 1.0000 04 110000 1.0000 1,x000

.,000.0 06,4 10000 1.0000 1,0000 I....8 . 0 OO 1, 110000 10000 1.000 1.0 .1.2441 1,2U86 1.2294 11877.

12. 132 1.2568 12210 14 12199 1 ý406 108 1147 16 7ý2064i 12222 1 1947 1.432, 1 1.20253 22 1.1600 1,1608 1.1467 2.4.. 1.1442 1:1401 1 1301

2. .282 1,1190 1.1140 1.0943 i.268 1 1,1132 198 106 30" 110P22 1.0884 _ 10832 1,0799 3:, 1.09P53 1,0864........805. 1-08.17, 34 1933 1.0662 106 1,0896 36 91941 1067.0834 ,097 38 1,0949 1.0847 10 '854 40 1.0966 1.0847 7ITe.7 14.2 1096 1.0853 1.0896 4 .I0968 1,0856 101 46 .0970 f 1.0858 03 1.1.317 48 1.0971 1,U872 10947 50 110964 100-02 1.0955 5.2 t 1.0957 1,0924 109.59. 1

--l14.13 5:6 1,1059 1:0963 1.1036 58 1,1121 1,1027 115- ,11 508

.. 0. 11221 1112 1.1180 16,2 1,1 320 1,1227 1 11247 64 1,1406 132110 1 145 16 11483" 11391 135 8179

6. 1,1 54q 1.1458 1 1368 70 ,1 5603 1,1515: 1143 Table COLR - 2 RAOC Summary of W(Z) with HFP %AFD Band of -9/+4% (TOP 8% and BOTTOM 8%

EXCLUDED) 14000 MWDIMTU of Cycle Burnup through EOL.

R.E. Ginna Nuclear Power PlantCOR17evso0 COLR-11 7 Revision 0

COLR Cycle 33 Height 150 2000 10000 180 (feet) MWDIMTrU IMWINIT TOMU WDMU 76 1.1680 1 1605 1, 15l 1.1798 78 1174 10 1.1583 1,1743 8.0 1,1650 1i.1590 1159 1 1.6 66 82 1.1607 11557 1187 1569 8 j1155 1.1500150 1,1483 (a. _ 1.1355 1.1412 1.14971 1429 92 90 --

1.1284

[--

11 6 - ....... 1-1448 1 ,1.1550 1.1522 1 ----0 1.1584 1--4 94 1.169 11713 1 12030 1.1876

.. . M .. ... ...... ..............

9.6 L 1.1512 . 1.1851 1,2347 - 1.2029 98 .11653 1.1974 1 2653 128 100 1 1864 1.2177 1.2916 125 12 1.2102 1.2434 1,3148 1.58 104~~~

1 32(3252 1 3381 126 10.6 12ý548 1 2839 1,3577 1.3047 10 1283 1,29097 1 3,6 _1 1177 11 0 1,2837 1.3001 1 3789.....1 3150.

112 1.0000 100 100 100 1.0,000 1 ,1 0-000' 11A

]1 1.0000 116 1.0000 1

1.0000 00 1,0000 1,0000 118. .0 10 ....................

0 0 10000

-10000 ........

12.0 1.0000 1 10000 1.0000 1.0000 Table COLR - 2(Continued)

RAQO Summary of W(Z) with HIFP %AFD Band of -9/+4% (TOP 8% and BOTTOM 8%

EXCLUDED) 14000 MWD/MTU of Cycle Burnup through EOL.

R.E. Ginna Nuclear Power Plant COLR-18 Revisi on 0

COLR Cycle 33 Cycle Burnup, Peat Factor1 MWDIMTU )

150 2.00 213 82.00 ..........

Table COLR - 3 Penalty factor for increasing FQ R.E. Ginna Nuclear Power PlantCOR19evso0 COLR-19 Revision 0

COLR Cycle 33 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 CL-0Rvso COLR-20 Revision 0