ML063210130

Cycle 21 Core Operating Limits Report

ML063210130
Person / Time
Site:	Surry
Issue date:	11/16/2006
From:	Funderburk C Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-999
Download: ML063210130 (8)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 2326 1 November 16, 2006 U. S. Nuclear Regulatory Commission Serial No.06-999 Attention: Document Control Desk NLOS/vlh Washington, D. C. 20555-0001 Docket No. 50-281 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 2 CYCLE 21 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, enclosed is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 21 Pattern KB, Revision 0.

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

Very truly yours, C. L. ~unterburk,Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitment Summary: There are no new commitments as a result of this letter

Serial No.06-999 Cycle 21 Core Operating Limits Report Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Region I1 Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, GA 30303-8931 Mr. Siva P. Lingam U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Leonard N. Olshan W. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station

CORE OPERATING LIMITS REPORT Surry 2 Cycle 2 1 Pattern KB Revision 0 September 2006 S2C21 COLR, Revision 0 Page 1 of 6

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Suny Unit 2 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.1 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 Enthalpy Rise Hot Channel Factor) 2a. WCAP-9220-P-A, Rev. 1, "Westinghouse ECCS Evaluation Model - 1981 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. 1, "BART A-1: A Computer Code for the Best Estimate Analysis of Reflood Transients-Special Report: Thimble Modeling in W ECCS Evaluation Model," July 1986 (W Proprietary)

(Methodology for TS 3.12.B.1 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.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2f. WCAP- 12610, "VANTAGE+ Fuel Assembly Report," June 1990 (Westinghouse Proprietary)

S2C21 COLR, Revision 0 Page 2 of 6

(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. VE,P-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 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 Technical 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 p c m / o at

~ less than 50 percent of RATED POWER, or

+6.0 p c m / oat

~ 50 percent of RATED POWER and linearly decreasing to 0 p c m / o at ~

RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.2) 3.2.1 'fie control rod banks shall be limited in physical insertion as shown in Figure A-1.

3.2.2 The rod insertion limit for the A and B control banks is the l l l y withdrawn position as shown on Figure A- 1.

S2C2 1 COLR, Revision 0 Page 3 of 6

3.3 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B. 1 )

FQ(z) I - CFQ K ( z ) for P

FQ(z) I - CFQ K ( z )for 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-FAHO (TS 3.12.B. 1 )

F A H ( N ) I CFDH x (1 + 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 S2C2 1 COLR, Revision 0 Page 4 o f 6

Figure A- 1 S2C21 ROD GROUP INSERTION LIMITS Fully wld position = 226 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 S2C21. COLR, Revision 0 Page 5 of 6

Figure A-2 K(Z) - Normalized FQ as a Function of Core Height CORE HEIGHT (FT)

S2C211 COLR, Revision 0 Page 6 of 6