ML091660356
| ML091660356 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/15/2009 |
| From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 09-388 | |
| Download: ML091660356 (9) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 15,2009 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.09-388 NLOS/vlh Docket No.
50-281 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 1 Pursuant to Surry Technical Specification (TS) 6.2.C, enclosed is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 22 Pattern ASP, Revision 1. This revision of the COLR deletes references to TS sections that have been deleted since the issue of Revision 0 of the COLR previously submitted to the NRC.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Sincerely,
(~~
C. L. Funderburk, 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.
cc:
U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W.
Suite 23T85 Atlanta, GA 30303-8931 Mr. J. F. Stang, Jr.
NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. D. N. Wright NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North MaiI Stop 0-8 H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No.09-388 Cycle 22 Core Operating Limits Report Page 2 of 2
CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 22 Pattern ASP Revision 1 May 2009 I SU-SPEC-000-COLR-S2C22, Rev. 1 Page 10f7
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 22 has been prepared in accordance with the requirements ofTechnical Specification 6.2.C.
The Technical Specifications affected by this report are:
TS 3.1.E _- 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
- 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-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," (Westinghouse Proprietary), January 2005 (Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2b. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 (Westinghouse Proprietary)
(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2c. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985 (Westinghouse Proprietary)
(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2d. WCAP-1261O, "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)
I SU-SPEC-000-COLR-S2C22, Rev. 1 Page 20f7
3b. VEP-NE-3-A, "Qualification of the WRB-l 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)
I SU-SPEC-000-COLR-S2C22, Rev. 1 Page 3 of7
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.EJ 3.1.1 The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcm/F at less than 50 percent of RATED POWER, or
+6.0 pcm/F at 50 percent 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-I.
3.2.2 The rod insertion limit for the A and B control banks is the fully withdrawn position as shown on Figure A-I.
I SU-SPEC-000-COLR-S2C22, Rev. 1 Page 4 of7
3.3 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B.l)
CFQ FQ(z) 5:: --K(z) for P > 0.5 P
CFQ FQ(z) 5:: --K(z) for P 5:: 0.5
0.5 where
P = Thennal Power 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-FMI(N) (TS 3.12.B.l)
FMf(N) 5:: CFDH x{I+ PFDH(l-P)}
where: P = Thennal Power Rated Power 3.4.1 CFDH=1.56 for Surry Improved Fuel (SIP) 3.4.2 PFDH = 0.3 I SU-SPEC-000-COLR-S2C22, Rev. 1 Page 5 of7
Figure A-l S2C22 ROD GROUP INSERTION LIMITS Fully wid position =228 steps 1.0 0.9 0.8 0.3
. 0.4 0.5 0.6 0.7 Fraction of Rated Thermal Power 0.2 0.1
/
(0.481.:,228)
V
/
C-BA K
/
/V (1.0 183)
/
/
/
/
/v V
V (0, 151
/
/
/
~RA \\lK'
/
/
-~
/
/
/ V
/
/
~ 0~\\
10 a
0.0 20 200 190 50 40 30 60 70 230 220 210 180 170 160 "0
150
~
~ 140 CII Ui 130 g 120
.~ 110 a..
g-100 e
C) 90 "0o II:
80 I SU-SPEC-OOO-COLR-S2C22, Rev. 1 Page 6 of7
Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 1.2 1.1 1.0 0.9 0.8 N
~ 0.7 Cw N
- J
<t 0.6
- 2a:oz
~ 0.5
~
0.4 0.3 0.2 i
6,1.0---r--t---r---
r----.~
(12 0.925 0.1 0.0 a
2 3
4 5
678 CORE HEIGHT (FT) 9 10 11 12 13 I SU-SPEC-OOO-COLR-S2C22, Rev. 1 Page 70f7