ML061350426

Virginia Electric and Power Company Surry Power Station Unit 1 Revision to Cycle 21 Core Operating Limits Report

ML061350426
Person / Time
Site:	Surry
Issue date:	05/15/2006
From:	Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-376A
Download: ML061350426 (7)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 15, 2006 United States Nuclear Regulatory Commission Serial No.: 06-376A Attentiion: Document Control Desk NLOSNLH Washington, D. C. 20555-0001 Docket No.: 50-280 License No.: DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 REVISION TO CYCLE 21 CORE OPERATING LIMITS REPORT Attachled is Revision 1 of the Surry Unit 1 Cycle 21 Core Operating Limits Report (COLR). During the offloading of the Cycle 20 core, it was determined that a fuel assembly had unanticipated rod bowing on two rods. Since this assembly was originally scheduled for reuse in Cycle 21, the Cycle 21 core has been re-designed with a replacement assembly with similar reactivity characteristics. For this reason, the COLR was revised to reflect the modified core pattern (Pattern RB) for Cycle 21. This letter supercedes our previous letter dated April 28, 2006.

If you have any questions or require additional information, please contact Mr. Gary Miller at 804/273-2771.

Very truly yours, C. L. Funderburk, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc.

for Virginia Electric and Power Company Attachlment Commitment Summary: There are no new commitments as a result of this letter.

cc: U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W., Suite 23T85 Atlanta, Georgia 30303-8931 Mr. S. R. Monarque U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

CORE OPERATING LIlWTS REPORT Surry 1 Cycle 21 Pattern RB Revision 1 May 2006 S 1C21 COLR, Revision 1 Page 1 of 6

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 21 has been prepared in accordance with the requirements of Techcal Specification 6.2.C.

The Technical Specifications affected by ths report are:

TS 3.1.E and TS 5.3.A.6.b- Moderator Temperature Coefficient TS 3.12.A.2 and TS 3.12.A.3 - Control Bank Insertion Limits TS 3.12.B.l and TS 3.12.B.2 - Power Distribution Limits

2.0 REFERENCES

1. VEP-HID-42, Rev. 2.1-A, Reload Nuclear Design Methodology, August 2003 (Methodologyfor TS 3.1.E and TS 5.3.A.6.b - Moderator Temperature Coefficient; TS 3.12.A.2 and 3.12.A.3 - Control Bank Insertion Limit; TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor and Nuclear Enthalpy h s e Hot Channel Factor) 2a. WCAP-9220-P-A, Rev. 1, Westinghouse ECCS Evaluation Model - 1981 Version, Februai-y 1982 (W Proprietary)

(Methodology for TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2b. WCAP-9561-P-A, ADD. 3, Rev. 1, BART A-1: A Computer Code for the Best Estimate Analysi,sof Reflood Transients-SpecialReport: Thimble Modeling in W ECCS Evaluation Model, July 19136 (W Proprietary)

(Methodology for TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2c. WCAP-10266-P-A, Rev. 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987 (W Proprietary)

(Methodology for TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2d. WCAP- 10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985 (W Proprietary)

(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2e. WCAP-10079-P-A, NOTRUMP, A Nodal Transient Small Break and General Network Code, August 1985 (W Proprietary)

(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor)

S 1C2 1 COLR, Revision 1 Page 2 of 6

2f. WCAP-126 10, VANTAGE+ Fuel Assembly Report, June 1990 (Westinghouse Proprietary)

(Methotdology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 3a. VEP-NE-2-A, StatisticalDNBR Evaluation Methodology, June 1987 (Methodologyfor TS 3.12.B.l and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor) 3b. VEP-NE-3-A, Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code, July 1990 (Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Nuclear Enthalpy k s e Hot Channel Factor) 3.0 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 6.2.C.

3.1 Moderator Temperature Coefficient (TS 3.1.E and TS S.3.A.6.b)

3. I. 1 The Moderator Temperature Coefficient (MTC) lirmts are:

+6.0 pcm/F at less than SO percent of RATED POWER, or

+6.0 pcm/F at SO percent of RATED POWER and hearly decreasing to 0 pcdF at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.2) 3.2.1 The control rod banks shall be limited in physical insertion as shown in Figure A-1.

S 1C21 COlLR, Revision 1 Page 3 of 6

3.3 Heat Flux Hot Channel Factor-FO(z) (TS 3.12.B.l)

FQ(z) 5 p CFQ K ( z ) f o r P > 0.5 cFQ K ( z ) for P 20.5 F Q ( z )5 -

0.5 Thermal Power where : P =

Rated Power 3.3.1 CFQ = 2.32 3.3.2 K(z)is provided in Figure A-2.

3.4 Nuclear Enthalpv Rise Hot Channel Factor-FAH(N)(TS 3.12.B. 1)

FAH(N)5CFDHX{l+PFDH(l-P)}

Thermal Power where 1 P =

Rated Power 3.4.1 CFDH = 1.56 for Surry Improved Fuel (SIF) 3.4.2 PFDH = 0.3 S lC21 COLR, Revision 1 Page 4 of 6

Figure A-1 S1C21 ROD GROUP INSERTION LIMITS 230 220 21 0 200 190 180 170 160

150 140 0) 130

.-:120

+ I n

I: 110

? 100 2

(3 90

'0 80 70 60 50 40 30 20 10 0

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.o Fraction of Rated Thermal Power S 1C2 1 COLR, Revision 1 Page 5 of 6

Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 1.2 1.1 1.o 4- 6, 1.0 0.9 h

0.8 1(12 0.92!

N Y

2 0.7 L-0.4 0.3 I

0.2 i

0.1 0.0 0 1 2 3 4 5 6 7 8 9 1 0 1 1 1 2 1 3 CORE HEIGHT (FT)

S lC2 1 COLR, Revision 1 Page 6 of 6