ML093170022
| ML093170022 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/12/2009 |
| From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 09-716 | |
| Download: ML093170022 (8) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 12, 2009 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.09-716 NLOSlvlh Docket No.
50-281 License No.
DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 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 23 Pattern
- BOA, Revision O.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Sincerely,
/--~-7'
(~~.)[-
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" Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W.
Suite 23T85 Atlanta, GA 30303-8931 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North MaiI Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North MaiI Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No.09-716 Cycle 23 Core Operating Limits Report Page 2 of 2
COLR-S2C23, Rev. 0 COLR-S2C23, Revision 0 CORE OPERATING LIMITS REPORT Surry 2 Cycle 23 Pattern BOA Page 1 of 6
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 23 has been prepared in accordance with the requirements ofTechnical Specification 6.2.C.
The Technical Specifications affectedby this report are:
TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.l, TS 3.12.A.2, TS 3.12.AJ, and TS 3.12.C.3.b.1.b - Control Bank Insertion Limits TS 3.12.B.l and TS 3.12.B.2 - Power Distribution Limits TS 3.12.A.l.a, TS 3.12.A.2.a, and TS 3.12.0 - Shutdown Margin
2.0 REFERENCES
- 1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003 (Methodology for TS 3.l.E
- Moderator Temperature Coefficient; TS 3.12.A.l, TS 3.12.A.2, TS 3.12.A.3, and TS 3.12.C.3.b.1.b - Control Bank Insertion Limit; TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor and Nuclear Enthalpy Rise Hot Channel Factor; TS 3.12.A.1.a, TS 3.12.A.2.a, and TS 3.12.0 - Shutdown Margin) 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 forTS 3.12.B.l and TS 3.12.B.2-Heat Flux Hot Channel Factor) 2b. WCAP-I0054-P-A, "WestinghouseSmallBreak ECCS Evaluation Model Using the NOTRUMP Code," August 1985 (WestinghouseProprietary)
(Methodology for TS 3.l2.B.l and TS 3.12.B.2-Heat Flux Hot Channel Factor) 2c. WCAP-I0079-P-A, "NOTRUMP, A Nodal Transient Small Break and Oeneral Network Code," August 1985 (Westinghouse Proprietary)
(Methodology for TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2d. WCAP-12610-P-A, "VANTAGE+Fuel AssemblyReport," June 1990 (WestinghouseProprietary)
(Methodology forTS 3.12.B.l and TS 3.l2.B.2 - Heat Flux Hot Channel Factor) 3a. VEP-NE-2-A, Rev. 0, "Statistical DNBR Evaluation Methodology," June 1987 (Methodology for TS 3.12.B.l and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor) 3b. VEP-NE-3-A, Rev. 0, "Qualification ofthe WRB-l CHF Correlation in the Virginia Power COBRA Code," July 1990 (Methodology for TS 3.12.B.I and TS 3.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor)
COLR-S2C23, Rev. ° Page 2 of 6
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.I.E) 3.1.1 The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcm/F at less than 50 percent ofRATED POWER, or
+6.0 pcm/F at 50 percent of RATED POWER and linearly decreasing to apcm/F at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.I, TS 3.I2.A.2, and TS 3.12.C.3.b.1.b) 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.
3.2.3 The rod insertion limit for the A and B shutdown banks is the fully withdrawn position as shown on Figure A-I.
3.3 Shutdown Margin (TS 3.I2.A.1.a, TS 3.I2.A.2.a, and TS 3.I2.G) 3.3.1 Whenever the reactor is subcritical the shutdown margin (SDM) shall be 21.77 %&Ik.
COLR-S2C23, Rev. 0 Page 3 of 6
3.4 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B.l)
CFQ FQ(z) S --K(z) for P> 0.5 P
CFQ FQ(z) S --K(z) for P S 0.5
0.5 where
P =Thermal Power Rated Power 3.4.1 CFQ=2.32 3.4.2 K(z) is provided in Figure A-2.
3.5 Nuclear Enthalpy Rise Hot Channel Factor-FMI(N) (TS 3.12.B.l)
F!ili(N) S CFDHx{I+PFDH(I-P)}
h P
Thermal Power were:
=-----
Rated Power 3.5.1 CFDH= 1.56 for Surry Improved Fuel (SIP) 3.5.2 PFDH= 0.3 COLR-S2C23, Rev. 0 Page 4 of 6
Figure A-I SURRY UNIT 2 CYCLE 23 ROD GROUP INSERTION LIMITS Fully wId position = 230 steps 230 220 210 200 190 180 170 160 150
- E
~ 140 III0.
.2! 130 III
'It:
c:: 120 o..
'iii 110 oa..
g-100 e
C>
90
- §...
80 70 60 50 40 30 20 10
/(1 1
(0.4938, 230)
I
/ V
/
/
/
C-BANK (1.0,183)
~
~
/
/
/
iii"'"
/"
/
/
i (0,151)
/
I
.//
/
/
I
~/
D-BANK
/
/"
/
/'
.//
/
I
/
V
-(0,23) o 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 COLR-S2C23, Rev. 0 Page 5 of 6
Figure A-2 K(Z)
- Normalized FQ as a Function of Core Height (6, 1.0)-r---r------r---~
(12,0.925)
I I
I I
1.2 1.1 1.0 0.9 0.8 NCi 0.7 u,
e LLI N
~ 0.6
- E
~
0z 0.5 Is 0.4 0.3 0.2 0.1 0.0 o
1 2
3 4
5 6
7 8
CORE HEIGHT (FT) 9 10 11 12 13 COLR-S2C23, Rev. 0 Page 6 of 6