ML092400544
| ML092400544 | |
| 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 | |
| 09-388A | |
| Download: ML092400544 (9) | |
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.
09-388A 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 2 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 2.
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 264.
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. 09-388A Cycle 22 COLR, Revision 2 Page 2 of 2
CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 22 Pattern ASP Revision 2 July 2009 SU-SPEC-000-COLR-S2C22, Rev. 2 Page 1 of?
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.l, TS 3.12.A.2, TS 3.12.A.3, 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.1.a, TS 3.l2.A.2.a, and TS 3.12.G-Shutdown Margin
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.l, TS 3.12.A.2, TS 3.12.A.3, and TS 3.12.C.3.b.1.b - Control Bank fusertion Limit; TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux 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.l2.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 Flux Hot Channel Factor) 2b. WCAP-I0054-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.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)
SU-SPEC-000-COLR-S2C22, Rev. 2 Page 2 of7
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)
SU-SPEC-000-COLR-S2C22, Rev. 2 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.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 0 pcm/F at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.1, TS 3.12.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 3.12.A.1.a, TS 3.12.A.2.a, and TS 3.12.G) 3.3.1 Whenever the reactor is suhcritical the shutdown margin (SDM) shall be ~1.77 %Mdk.
SU-SPEC-000-COLR-S2C22, Rev. 2 Page 4 of7
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 h
P Thermal Power were: =-----
Rated Power 3.4.1 CFQ = 2.32 3.4.2 KC,J) is provided in Figure A-2.
3.5 Nuclear Enthalpy Rise Hot Channel Factor-FMI(N) (TS 3.12.B.1)
FM/(N):S; CFDHx{I+PFDH(1-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 SU-SPEC-OOO-COLR-S2C22, Rev. 2 Page 5 of7
Figure A-I S2C22 ROD GROUP INSERTION LIMITS Fully wId position = 228 steps 230 220 210 200 190 180 170 160 "C 150
~
~ 140
~
130 g 120
.~ 110 c.
go 100 e
C) 90 "C
~
80 70 60 50 40 30 20 10
/
(0.481.,228)
/
/
fi(SA ~K
/
/
(1.0 183)
/
I
/
/
/
/
/v
/'
/'
(0, 151
~~--
/
/
/
~Rlo '1.11(
/
//
/
/
/
/
/ /
/
/
v:,,~\\
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 SU-SPEC-OOO-COLR-S2C22, Rev. 2 Page 6 of7
FigureA-2 K(Z)
- Normalized FQ as a Function of Core Height 1.2 -,----,----,---,--- r--,.----,.----,--,--,---,----,----,------,
1.1 +--+--+-----+
-- -----f----
1.0 +--+--t---t---I-----1----.....__
=---I~
r---r-------.
0.9 +--+--+--+--+-----j--+----+----+-----I---+---+---+---I (12 0.925 0.8 +--+--+--+---j----j---I--+----+-----I---+---f---+---I fi fZ 0.7 +--+--+--+----+---1---1---1---1---+---+---1---1---1 C
W N:J
~ 0.6 +--+--+--+---+---1---+---4---4---1---+---1---1---1 0:::o Z
~ 0.5 0.4 +--+--+--+----+-----1---1--+-----1---+---1---+---+----1 0.3 +--+--+---j---+---+---I---I---I---+---t---t---t---j 0.2 +---+--+-----t---I---I---+---I---I---I---I---I---I-----I 0.1 +--+--+--+----I---t---I---t---I---I---I---I---t---j 10 11 12 13 9
567 8
CORE HEIGHT (FT) 4 3
2 0.0 +---+--+---j---I---I---I---I---I---+---t---+---+-----I o
SU-SPEC-OOO-COLR-S2C22, Rev. 2 Page 7 of7