ML043440275

Transmittal of Cycle 20 Core Operating Limits Report

ML043440275
Person / Time
Site:	Surry
Issue date:	12/09/2004
From:	Funderburk C Dominion Resources
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
04-734
Download: ML043440275 (7)

Text

P Dominion December 9 , 2004 United States Nuclear Regulatory Commission Serial No.: 04-734 Attention: Document Control Desk NLOS/VL H 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 20 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 20 Pattern IT.

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

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

for Virginia Electric and Power Company Attach ment 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 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station

CORE OPERATING LIMITS REPORT Surry 1 Cycle 20 Pattern IT Revision 0 October 2004 S 1C20 COLR, Revision 0 Page 1 of 6

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Suny Unit 1 Cycle 20 has been prepared in accordance with the requirements of Technical Specification 6.2.C.

The Techcal 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-A7ADD. 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)

(Methodologyfor 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)

(Methodologyfor 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)

(Methodologyfor 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 1C20 COLR, Revision 0 Page 2 of 6

2f. WCAP- 12610, 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 h t s 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) h t s are:

4 . 0 p c f l at less than 50 percent of RATED POWER, or

+6.0 pcm/F at 50% of Rated Power and linearly decreasing to 0 pc& 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 1C20 COLR, Revision 0 Page 3 of 6

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

FQ(z)5 p cFQ K ( z ) for P > 0.5 F Q ( z )I0.5 cFQ K ( z ) for P 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)

F M ( N )I CFDH X (1+ PFDH(1- P)}

Thermal Power where :P =

Rated Power 3.4.1 CFDH = 1.56 for Suny Improved Fuel (SIF')

3.4.2 PFDH = 0.3 S 1C20 COLR, Revision 0 Page 4 of 6

Figure A-1 230 220 210 200 190 180 170 160 150 3

3 140 u)

Q

130

.-.-g CI 120 n 8 110 g 100 5

'CI 0

90 K

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 1C20 COLR, Revision 0 Page 5 of 6

Figure A-2 K(Z) Normalized FQ as a Function of Core Height 1.2 1.1 1.o 0.9 0.8 n

c?

0.7 n

W N

0.6 K

zA 0.5 N

W Y

0.4 0.3 0.2 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 1C20 COLR, Revision 0 Page 6 of 6