ML020990327

Cycle 18 Core Operating Limits Report

ML020990327
Person / Time
Site:	Surry
Issue date:	03/28/2002
From:	Sarver S Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
02-201
Download: ML020990327 (6)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 28, 2002 United States Nuclear Regulatory Commission Serial No.: 02-201 Attention: Document Control Desk NLOS/MM Washington, DC 20555-0001 Docket No.: 50-281 License No.: DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 18 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, attached is a copy of the Virginia Electric and Power Company's (Dominion) Core Operating Limits Report for Surry Unit 2 Cycle 18 Pattern GW, Revision 0.

If you have any questions or require additional information, please contact us.

Very truly yours S. . Sa ere,Director Nuclear Licensing and Operations Support Attachment 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, SW, Suite 23T85 Atlanta, GA 30303-8931 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station AC1

CORE OPERATING LIMITS REPORT Surry 2 Cycle 18 Pattern GW Revision 0 March 2002 Virginia Electric and Power Company (Dominion)

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 18 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 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 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.

2.1 Moderator Temperature Coefficient (TS 3.1 .E and TS 5.3.A.6.b) 2.1.1 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% of Rated Power and linearly decreasing to 0 pcm/°F at Rated Power 2.2 Control Bank Insertion Limits (TS 3.12.A.2) 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure A-1.

S2C 18 COLR Page 2 of 5

2.3 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B. 1)

FQ(z)*< CFQ K(z) for P > 0.5 P

0.5 K(z) for P

• 0.5 FQ(z) < CFQ where: P Thermal Power Rated Power 2.3.1 CFQ= 2.32 2.3.2 K(z) is provided in Figure A-2.

2.4 Nuclear Enthalpy Rise Hot Channel Factor-FAH(N) (TS 3.12.B. 1)

FAH(N) < CFDHx {1 + PFDH(1- P)}

where: P-Thermal Power Rated Power 2.4.1 CFDH=1.56 for Surry Improved Fuel (SIF) 2.4.2 PFDH=0.3 S2C18 COLR Page 3 of 5

Figure A-1 S2C18 ROD GROUP INSERTION LIMITS Max w/d position = 230 steps 230 220 210 200 190 180 170 160 150 S140 cn 130

, 120

.2 0 110 0 100 I

-o 90 0

80 70 60 50 40 30 20 10 0

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 S2C 18 COLR Page 4 of 5

Figure A-2 K(Z) - Normalized FQ as a Function of Core Height 1.2 1.1 1.0 0.9 0.8 a

U 0.7 C3 w

UJ N

0.6 0

Z 0.5 N

0.4 0.3 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 13 CORE HEIGHT (FT)

S2C 18 COLR Page 5 of 5