ML061180229
| 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 F Q k ) 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 1 0 1 1 1 2 1 3 CORE HEIGHT (FT)
Page 6 of 6