ML093170022

Cycle 23 Core Operating Limits Report Revision 0

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 Serial No.09-716 Attention: Document Control Desk NLOSlvlh Washington, D. C. 20555-0001 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.

Serial No.09-716 Cycle 23 Core Operating Limits Report Page 2 of 2 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 Mai I 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 Mai I Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

COLR-S2C23, Revision 0 CORE OPERATING LIMITS REPORT Surry 2 Cycle 23 Pattern BOA COLR-S2C23, Rev. 0 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 of Technical 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.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, "Westinghouse Small Break 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 Assembly Report," June 1990 (Westinghouse Proprietary)

(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 of the 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 a pcm/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)}

Thermal Power were:

h P =- ----

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

/(1 1 (0.4938, 230) 220 I V 210 /

200 /

190 /

/ C-BANK (1.0,183)

~ ~

180 170 iii"'"

/ /

/ /"

160 150 /  !

i

/

E

~ 140 (0,151)

/

III 0.

/

.2! 130 I ./

III

'It:

/

..c:: 120 o

'iii 110 o

/

a.. I ~

/ D-BANK g-100 C>

e 90 /

§... 80

/"

70

/

60

/

/'

50 ./ I 40 /

30

/

V 20 -(0,23) 10 o

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power COLR-S2C23, Rev. 0 Page 5 of 6

Figure A-2 K(Z)

• Normalized FQ as a Function of Core Height 1.2 1.1 (6, 1.0) 1.0

- r--- r---- r--- ~

0.9 (12,0.925) 0.8 I

N I Ci u,

0.7 eLLI I N

~ 0.6

E

~

0 z 0.5 s

I 0.4 0.3 0.2 0.1 0.0 I o 1 2 3 4 5 6 7 8 9 10 11 12 13 CORE HEIGHT (FT)

COLR-S2C23, Rev. 0 Page 6 of 6