ML043440275
| 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 N LOS/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 men t 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 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 - 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-A7 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)
S 1C20 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 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 FQ(z) I 0.5 cFQ K ( z ) for P 5 0.5 Thermal Power Rated Power where : P =
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 Rated Power where : P =
3.4.1 3.4.2 PFDH = 0.3 CFDH = 1.56 for Suny Improved Fuel (SIF')
S 1C20 COLR, Revision 0 Page 4 of 6
Figure A-1 230 220 21 0 200 190 180 170 160 150 3
3 140 130 u)
Q ::
g 120 8 110 g 100 5
CI n
'CI 90 0
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
1.2 1.1 1.o 0.9 0.8 n
c?
n N
0.7 W
0.6 K
A 0.5 N
Y z
W 0.4 0.3 0.2 0.1 0.0 Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 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