ML061180229

Cycle 21 Core Operating Limits Report

ML061180229
Person / Time
Site:	Surry
Issue date:	04/28/2006
From:	Funderburk C Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-376
Download: ML061180229 (7)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 2326 1 April 28, 2006 United States Nuclear Regulatory Commission Serial No.:

06-376 Attention: Document Control Desk NLOSIVLH Washington, D. C. 20555-0001 Docket No.: 50-280 License No.: DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) SURRY POWER STATION UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, attached is a copy of Revision 0 of Dominion's Core Operating Limits Report for Surry Unit 1 Cycle 21 Pattern AP. If you have any questions or require additional information, please contact Mr. Gary Miller at 8041273-2771.

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

for Virginia Electric and Power Company Attachment 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 1 1555 Rockville Pike Rockville, MD 20852-2738 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station CORE OPERATING LIMITS REPORT Surry 1 Cycle 21 Pattern AP Revision 0 April 2006 S 1 C2 1 COLR, Revision 0 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 Technical Specification 6.2.C. The Technical Specifications affected by this 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. I and TS 3.12.B.2 - Power Distribution Limits

2.0 REFERENCES

1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003 (Methodology for 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 Ent halpy Rise Hot Channel Factor) 2a. WCAP-9220-P-A, Rev.

1, "Westinghouse ECCS Evaluation Model - 198 1 Version," February 1982 (W Proprietary) (Methodology for TS 3.12.B. 1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2b. WCAP-9561-P-A, ADD. 3, Rev. I, "BART A-1: A Computer Code for the Best Estimate Analysis of Reflood Transients-Special Report: Thimble Modehg in W ECCS Evaluation Model," July 1986 (W Proprietary) (Methodology for TS 3.12.B. I 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. 1 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.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) S 1C21 COLR, Revision 0 Page 2 of 6 2f. WCAP- 126 10, "VANTAGE+

Fuel Assembly Report," June 1990 (Westinghouse Proprietary) (Methodology for TS 3.12.B. 1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 3a. VEP-NE-2-A, "Statistical DNBR Evaluation Methodology," June 1987 (Methodology for TS 3.12.B. 1 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.l and TS 3.12.B.2 - Nuclear Enthalpy Rise 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 Techcal Specification 6.2.C. 3.1 Moderator Temperature Coefficient (TS 3.1 .E and TS 5.3.A.6.b) 3.1.1 The Moderator Temperature Coefficient (MTC) limits are: +6.0 pc& at less than 50 percent of RATED POWER, or +6.0 pc& at 50 percent of RATED POWER and linearly decreasing to 0 pcmPF 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 1 C2 1 COLR, Revision 0 Page 3 of 6 3.3 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B. 1) CFQ K (z) for P > 0.5 FQ(z) 5 CFQ K(Z) for P 5 0.5 FQk) 5 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 Enthalpy Rise Hot Channel Factor-FAH(N) (TS 3.12.B. 1) FAH(N) 5 CFDH x{l+ PFDH(1- P)) Thermal Power where : P= Rated Power 3.4.1 CFDH = 1.56 for Surry Improved Fuel (SIF) 3.4.2 PFDH = 0.3 S 1 C2 1 COLR, Revision 0 Page 4 of 6 Figure A- 1 SIC21 ROD GROUP INSERTION LIMITS Fully wld position = 229 steps 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 lC2 1 COLR, Revision 0 Page 5 of 6 Figure A-2 K(Z) - Normalized FQ as a Function of Core Height S 1 C2 1 COLR, Revision 0 4 5 6 7 8 9 10111213 CORE HEIGHT (FT) Page 6 of 6