ML073410347
| ML073410347 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/05/2007 |
| From: | Funderburk C Dominion, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-0771 | |
| Download: ML073410347 (8) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 5, 2007 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.:
07-0771 NLOS/VLH Docket No.:
50-280 License No.:
DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, enclosed is a
copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 22 Pattern EON, Revision O.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804)273-2771.
Very truly yours, (F/y-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.
Serial No. 07-0771 Cycle 22 Core Operating Limits Report Page 2 of 2 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. Siva P. Lingam U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Richard A. Jervey U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. C. R. Welch NRC Resident Inspector Surry Power Station
COLR-SU-SPEC-OOO-COLR-SIC22, Revision 0 CORE OPERATING LIMITS REPORT Surry 1 Cycle 22 Pattern EON Page 10f6
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 1 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 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.l 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.l 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.l 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 (W Proprietary)
(Methodology for TS 3.12.B.l 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 (W Proprietary)
(Methodology for TS 3.12.B.l 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.l 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.l and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor) 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)
Page 2 of6
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 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.
Page 3 of6
3.3 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B.1)
CFQ FQ(z) ~ --K(z) for P > 0.5 P
CFQ FQ(z) ~--K(z) for P ~ 0.5
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 Enthalpy Rise Hot Channel Factor-FMI(N) (TS 3.12.B.l)
FMf(N) ~ CFDHx{l+PFDH(l-P)}
where: P = Thermal Power Rated Power 3.4.1 CFDH=1.56 for Surry Improved Fuel (SIP) 3.4.2 PFDH=0.3 Page 4 of6
Figure A-I S1 C22 ROD GROUP INSERTION LIMITS Fully wid position =226 steps 1.0 0.9 0.3 0.4 0.5 0.6 0.7 0.8 Fraction of Rated Thermal Power 0.2
/
(0.468 3,226)
/ /
/
/
C-BANK
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(1.0, 183) /
/
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/
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(0,151
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O-BI NK
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(0,23) 70 60 50 40 30 20 10 o
0.0 0.1 90 120 110 130 140 100 150 80 230 220 210 200 190 180 170
~3:
160 en'l.
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Page 5 of6
Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 12 13 10 11 9
5 678 CORE HEIGHT (FT) 4 3
2 6,1.0---------~
(12 0.925 0.0 a
1.2 0.3 0.4 0.1 0.8 0.9 0.2 1.0 1.1 N"
LL 0.7 Cw N
- i
<C 0.6
- 2a:oz
~ 0.5
~
Page 6 of6