ML092400426
| ML092400426 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/27/2009 |
| From: | Funderburk C Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 09-269A COLR-S1C23, Rev1 | |
| Download: ML092400426 (8) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 27, 2009 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.
09-269A NLOS/vlh Docket No.
50-280 License No.
DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 1 CYCLE 23 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 1 Cycle 23 Pattern
- NXS, Revision 1.
This revision to the COLR incorporates updates to TS references, adds shutdown bank insertion limits, and adds a section on shutdown margin consistent with implementation of recently approved TS Amendment 265.
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 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 16 E15 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No. 09-269A Cycle 23 COLR, Revision 1 Page 2 of 2
COLR-SIC23, Rev 1 COLR.SIC23, Revision 1.
CORE OPERATING LIMITS REPORT Surry 1 Cycle 23 Pattern NXS Page 1 of6
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 23 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.~.,1?~,1,-IS..3.12.A.2., TS 3.12.A.3.. gngJ:'S 3..l;M;;~,:21~.J.!12.- Control Bank Insertion Limits TS 3.12.B.l and TS 3.12.B.2 - Power Distribution Limits TS 3.12.A.1.a, TS 3.12.A.2.a, and TS 3.12.G - Shutdown Margin
2.0 REFERENCES
1.
VEP-FRD-42, Rev. 2. I-A, "Reload Nuclear Design Methodology," August 2003 (Methodology for TS 3.1.E - Moderator Temperature Coefficient; TS :2:.1.2..,A.,lJS..3.12.A.2.,. IS.
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 Aux Hot Channel Factor and Nuclear Enthalpy Rise Hot Channel Factor: TS 3.12.A.l.a, TS 3.12.A.2.a, and TS 3.12.G.. 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 for TS 3.12.B.l and TS 3.12.B.2 - Heat Aux 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 Aux Hot Channel Factor) 2c. WCAP-I0079-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 Aux 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 Aux 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 COLR-SIC23, Rev 1 Page 2 of6
(Methodology for TS 3.12.B.1 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 Technical Specification 6.2.C.
3.1 Moderator Temperature Coefficient (TS 3.1.E) 3.1.1 The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcrnfF at less than 50 percent ofRATED POWER, and
+6.0 pcrnfF at 50 percent of RATED POWER and linearly decreasing to 0 pcrnfF at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.1, TS 3.12.A.2, and TS 3.P.C.3.b.l.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 shutdo\\\\'!l banks is the fullv withdrawn position as shown on Figure A**I.
3.3 Shutdovm l\\1argin (TS 3.12.A.1.a, TS 3.12.A.2.a. and TS 3.12.0}
COLR-S1C23, Rev 1 Page 3 of6
3.4 Heat Flux Hot Channel Factor-FQ(z) (IS 3.12.B.1)
CFQ FQ(z) '!S:--K(z) for P > 0.5 P
CFQ FQ(z) '!S: --K(z) for P '!S: 0.5 0.5
.1_
P Thermal Power wnere:
=-----
Rated Power 3..4.1 CFQ = 2.32 3.1.2 K(z) is provided in Figure A-2.
3.5 Nuclear Enthalpy Rise Hot Channel Factor-FL\\H(N) (TS 3.12.B.1)
FM/(N) '!S: CFDHx{1+PFDH(1-P)}
h P
Thermal Power were:
=-----
Rated Power 3.~.1 CFDH = 1.56 for Surry Improved Fuel (SIP) 3.~.2 PFDH =0.3 COLR-S1C23, Rev 1 Page 4 of6
Figure A-I SURRY UNIT 1 CYCLE 23 ROD GROUP INSERTION LIMITS Fully wid position = 228 steps 230 220 210 200 190 180 170 160 150
~
til 140 a..
Gli 130
~ 120 "iii3. 110 a..
- J 100 E
G "C
90 oa:
80 70 60 50 40 30 20 10
/
(0.4813,228)
/ V
/
/
C-BANK
~/
(1.0, 183) ~
/
/
/
I;""
/
V V
(0,151)
/
./V
/
/
~V
/
D-BANK
/
I;""
V
/
.//
/
/
V e--- (0, 23) o 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 COLR-SIC23, Rev 1 Fraction of Rated Thermal Power Page 5 of6
1.2 1.1 1.0 0.9 0.8 N
~ 0.7 cw N
- i OIl( 0.6
- Ea:oz
..:... 0.5 t::!.
- II::
0.4 0.3 0.2 0.1 Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 6,1.0- r---i--r-----~~
(12 0.925 0.0 a
COLR-SIC23, Rev 1 2
3 4
5 6
7 8
CORE HEIGHT (FT) 9 10 11 12 13 Page 6 of6