ML081080254

Cycle 22 Core Operating Limits Report

ML081080254
Person / Time
Site:	Surry
Issue date:	04/17/2008
From:	Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
08-0222
Download: ML081080254 (8)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 17, 2008 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Serial No.

08-0222 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 Pursuant to Surry Technical Specification 6.2.C, enclosed is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 22 Pattern ASP, Revision O.

If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.

Sincerely,

~;;Lify-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 Mr. Siva P. Lingam U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No. 08-0222 Cycle 22 Core Operating Limits Report Page 2 of 2

CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 22 Pattern ASP Revision 0 April 2008 SU-SPEC-000-COLR-S2C22, Rev. 0 Page 1 of7

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.l.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.1 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.l.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.1 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.1 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 (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.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2d. WCAP-12610, "VANTAGE+ Fuel Assembly Report," June 1990 (Westinghouse Proprietary)

(Methodology for TS 3.12.B.1 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.1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor)

SU-SPEC-000-COLR-S2C22, Rev. 0 Page 2 of7

3b. VEP-NE-3-A, "Qualification of the WRB-l CHF Correlation in the Virginia Power COBRA Code," July 1990 (Methodology for TS 3.l2.B.l and TS 3.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor)

SU-SPEC-000-COLR-S2C22, Rev. 0 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.I.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 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.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.

SU-SPEC-000-COLR-S2C22, Rev. 0 Page 4 of7

3.3 Heat Flux Hot Channel Factor-FQ(z) (TS 3.l2.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.I2.B.I)

F!ili(N) ~ CFDH x {I+ PFDH(I-P)}

h P

Thermal Power were:

=-----

Rated Power 3.4.1 CFDH= 1.56 for Surry Improved Fuel (SIF) 3.4.2 PFDH = 0.3 SU-SPEC-000-COLR-S2C22, Rev. 0 Page 5 of7

Figure A-I S2C22 ROD GROUP INSERTION LIMITS 1.0

__________-----J 0.9

________1--

(1.0 183) 0.8

=1-

-/~--'-,---~-----+-._-~

___L

'~/j.::-(0.48d~ 228)-r-__=--

I i

I

~t,..*_****-=-

I-+--

-~J-.

I 0.3

.0.4 0.5 0.6 0.7 Fraction of RatecfThermarPower 0.2

!~1~-

~;-__

-t~-t-I

_~I__~

70 60 50 40 30 20 10 o

~-

0.0 0.1 190 180 f----~~~----+-

170 160 Fully wid position = 228 steps 200 230 220 210 "0 150

~

~ 140 oS

~ 130 g 120

.~ 110 ll.

§- 100 o..

Cl 90 "0o 0::

80 SU-SPEC-OOO-COLR-S2C22, Rev. 0 Page 6 of7

Figure A-2 1.0 +--;--+--+---t---,-+=:::+--

IT 0.9 0.8 Na u, 0.7 cw N

J<< 0.6-'-

E 0:::o Z

.; 0.5

!:i

~

0.4 K(Z) - Normalized FQ as a Function of Core Height

.r.'.----1---

6,1.0..

I 0.3 0.2 0.1 0.0 o

2 3

4 5

6 7

8 CORE HEIGHT (FT) 9 10 11 12 13 SU-SPEC-OOO-COLR-S2C22, Rev. 0 Page 7 of7