ML033010450

Cycle 19, Revision 1 to Core Operating Limits Report

ML033010450
Person / Time
Site:	Surry
Issue date:	10/20/2003
From:	Funderburk C Dominion Resources
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
03-518, TAC MB9502, TAC MB9503
Download: ML033010450 (8)

Text

Dominion Resources Services, Inc.

Dominion 5000 Dominion Boulevard, Glen Allen, VA 23060 October 20, 2003 United States Nuclear Regulatory Commission Serial No.:

03-518 Attention: Document Control Desk NLOS/MM Washington, DC 20555-0001 Docket No.:

50-280 License No.: DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT I CYCLE 19 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, attached is a copy of Revision 1 of the Virginia Electric and Power Company's (Dominion) Core Operating Limits Report for Surry Unit 1 Cycle 19 Pattern EM. The revised Core Operating Limits Report is being provided as part of implementation activities for changes to the Technical Specifications approved by a letter from Mr. C. Gratton (USNRC) to Mr. D. A. Christian (Dominion), entitled "Surry Units 1 and 2 - Issuance of Amendments Re: Revisions of the Core Operating Limits Report References (TAC Nos. MB9502 and MB9503),"

dated August 27, 2003. The changes to the Technical Specifications removed dates and revision numbers in the Administrative Requirements section, and relocated the dates and revision numbers to the cycle-specific Core Operating Limits Report.

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 Attachment Commitment Summary: There are no new commitments as a result of this letter.

fAdz

Serial No.: 03-518 Docket No. 50-280 cc:

U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 Mr. C. Gratton U. S. Nuclear Regulatory One White Flint North 11555 Rockville Pike Mail Stop 8G9 Rockville, MD 20852 Commission Mr. G. J. McCoy NRC Senior Resident Inspector Surry Power Station

Serial No.:

03-518 Docket No.:

50-280 Attachment CORE OPERATING LIMITS REPORT Suny 1 Cycle 19 Pattern EM Revision I September 2003 SIC19 COLR, Revision 1 Pagel1 of 6

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit I Cycle 19 has been prepared in accordance with the requirements of Technical Specification 6.2.C. Surry 1 Cycle 19 was designed under VEP-FRD42 Rev. 1-A. Approval and implementation of VEP-FRD42 Revision 2.1-A has been determined to not impact the analyses performed in support of Surry I Cycle 19. VEP-FRD42 Rev. 2.1-A appropriately and accurately defines the methodologies employed in the analyses supporting Surry 1 Cycle 19.

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-FRD42, 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-I: 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)

SIC19 COLR, Revision 1 Page 2 of 6

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)

(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 forTS 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 pcmnF at less than 50 percent of RATED POWER, or

+6.0 pcm/0F at 50% of RATED POWER and linearly decreasing to 0 pcm/F 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.

SIC19 COLR, Revision I Page 3 of 6

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

FQ(z) < CFQ K(z) for P > 0.5 P

FQ(z) < CFQ K~for P*< 0.5 where: P Thermal Power 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) < CFDH x { + PFDH(1-P)}

where:

=Thermal Power Rated Power 3.4.1 CFDH= 1.56 for Sury Improved Fuel (SIF) 3.4.2 PFDH = 0.3 SIC19 COLR, Revision 1 Page 4 of 6

Figure A-I 230 220 210 200 190 180 170 160

.0 150 v) 140 CL 0.

C o 120 0.

CL 1 o

100 I.0 V

90 0

80 70 60 50 40 30 20 10 0

SIC19 ROD GROUP INSERTION LIMITS Max wld position 230 steps (0.4938, 230)

-h

//C-BAI JK (1.0,183)

_Qi)

_=

_=2=

D-B NK (0, 23) 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 Fraction of Rated Thermal Power 0.8 0.9 1.0 SIC19 COLR, Revision I Page 5 of 6

Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 1.2 1.1 1.0 0.9 0.8 q

a 0.7 aW N

E 0.6 0

A 05 0.4 0.3 0.2 0.1 0.0 6, 1.0

~~~~~~~~~~~~~(12, 0.925'_

0 1

2 3

4 5

6 7

8 CORE HEIGHT (FT) 9 10 11 12 13 SIC19 COLR, Revision I Page 6 of 6