ML12312A065

Submittal of Core Operating Limits Report (Colr), Cycle 25 Pattern Who, Revision 0

ML12312A065
Person / Time
Site:	Surry
Issue date:	10/30/2012
From:	Huber T Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
12-679
Download: ML12312A065 (10)

Text

JFDominion Dominion Resources Services, Inc.

lnnsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 October 30, 2012 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.

NL&OS/GDM:

Docket No.

License No.12-679 RD 50-281 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT SURRY 2 CYCLE 25 PATTERN WHO REVISION 0 Pursuant to Surry Technical Specification (TS) 6.2.C, attached is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 25, Pattern WHO, Revision 0.

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

Sincerely, T. R. Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company information, please contact Attachment Commitment Summary: There are no new commitments as a result of this letter.

4&rzDI

Serial No.12-679 Docket No. 50-281 COLR S2C25 Page 2 of 2 cc:

U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.12-679 Docket No. 50-281 Attachment Attachment CORE OPERATING LIMITS REPORT Surry 2 Cycle 25 Pattern WHO Revision 0 October 2012 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit 2

Serial No.12-679 Docket No. 50-281 Attachment

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 25 has been prepared in accordance with the requirements of Surry Technical Specification 6.2.C.

The Technical Specifications affected by this report are:

TS 2.1 - Safety Limit, Reactor Core TS 2.3.A.2.d - Overtemperature AT TS 2.3.A.2.e - Overpower AT TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.1, TS 3.12.A.2, TS 3.12.A.3 and TS 3.12.C.3.b.l(b) - Control Bank Insertion Limits TS 3.12.A.l.a, TS 3.12.A.2.a, TS 3.12.A.3.c and TS 3.12.G - Shutdown Margin TS 3.12.B.1 and TS 3.12.B.2 - Power Distribution Limits TS 3.12.F - DNB Parameters TS Table 4.1-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

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.1, TS 3.12.A.2, TS 3.12.A.3 and TS 3.12.C.3.b.l(b) - Control Bank Insertion Limits TS 3.12.A. L.a, TS 3.12.A.2.a, TS 3.12.A.3.c and TS 3.12.G - Shutdown Margin 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.F - DNB Parameters TS Table 4.1-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

2.

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

3.

WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," (Westinghouse Proprietary), August 1985.

Methodology for:

TS 3.12.B. 1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor COLR-S2C25, Rev.0 Page I of 7

Serial No.12-679 Docket No. 50-281 Attachment

4.

WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code,"

(Westinghouse Proprietary), August 1985.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor

5.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," (Westinghouse Proprietary), April 1995.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor

6.

WCAP-12610-P-A and CENPD-404-P-A, Addendum I-A, "Optimized ZIRLO," (Westinghouse Proprietary), July 2006.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor

7.

VEP-NE-2-A, Rev. 0, "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

8.

VEP-NE-3-A, Rev. 0, "Qualification of the WRB-I CHF Correlation in the Virginia Power COBRA Code," July 1990.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 -Nuclear Enthalpy Rise Hot Channel Factor

9.

DOM-NAF-2, Rev. 0.2-P-A, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix B, "Qualification of the Westinghouse WRB-1 CHF Correlation in the Dominion VIPRE-D Computer Code," August 2010.

Methodology for:

TS 3.12.B. 1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor

10.

WCAP-8745-P-A, "Design Bases for Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Function," September 1986.

Methodology for:

TS 2.3.A.2.d - Overtemperature AT TS 2.3.A.2.e - Overpower AT COLR-S2C25, Rev.0 Page 2 of 7

Serial No.12-679 Docket No. 50-281 Attachment 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 and repeated in Section 2.0.

3.1 Safety Limit. Reactor Core (TS 2.1)

The Reactor Core Safety Limits are presented in Figure A-1.

3.2 Overtemperature AT (TS 2.3.A.2.d)

AT AT4 K,-,K 2,(it

) (T - T') + K 3 (P P') f(AO

+ tS Where:

AT is measured RCS AT, OF.

ATO is the indicated AT at RATED POWER, OF.

s is the Laplace transform operator, sec-1 T is the measured RCS average temperature (Tavg), OF.

T' is the nominal Tavg at RATED POWER, <_ 573.00F.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure _>

2235 psig.

K1 < 1.1425 K, > 0.01059 /OF K3 _ 0.000765 /psig t> 29.7 seconds t2 5 4.4 seconds f(AI) _

0.0268 { (qt - qb)), when (qt - qb) < -24.0% RATED POWER 0, when -24.0 % RATED POWER < (qt - qb) 5 8.0 % RATED POWER 0.0188 { (qt - qb) - 8.0 }, when (qt - qb) > +8.0% RATED POWER Where qt and qb are percent RATED POWER in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED POWER.

COLR-S2C25, Rev.0 Page 3 of 7

Serial No.12-679 Docket No. 50-281 Attachment 3.3 Overpower AT (TS 2.3.A.2.e)

AT ATo [K 4 -

K 5 ( 1

.)T-K6(T-TD-f(AI)

Where:

AT is measured RCS AT, 'F.

ATo is the indicated AT at RATED POWER, 'F.

s is the Laplace transform operator, sec-'

T is the measured RCS average temperature (Tavg), 'F.

T' is the nominal Tavg at RATED POWER, < 573.0°F.

K4 _ 1.0965 K(5 >0.0198 /°F for increasing Tavg K6> 0.001074 /F for T > T' 0 /TF for decreasing Tavg

_0 for T < T' t3 ? 9.0 seconds f(AI) = as defined above for OTAT 3.4 Moderator Temperature Coefficient (TS 3.1.E)

The Moderator Temperature Coefficient (MTC) limits are:

+6.0 pcm/F at less than 50 percent of RATED POWER, and

+6.0 pcm/F at 50 percent of RATED POWER and linearly decreasing to 0 pcm/F at RATED POWER 3.5 Control Bank Insertion Limits (TS 3.12.A.1, TS 3.12.A.2, TS 3.12.A.3 and TS 3.12.C.3.b. I (b))

3.5.1 The control rod banks shall be limited in physical insertion as shown in Figure A-2.

3.5.2 The rod insertion limit for the A and B control banks is the fully withdrawn position as shown on Figure A-2.

3.5.3 The rod insertion limit for the A and B shutdown banks is the fully withdrawn position as shown on Figure A-2.

3.6 Shutdown Margin (TS 3.12.A.l.a, TS 3.12.A.2.a, TS 3.12.A.3.c and TS 3.12.G)

Shutdown Margin (SDM) shall be > 1.77 %Ak/k.

COLR-S2C25, Rev.0 Page 4 of 7

Serial No.12-679 Docket No. 50-281 Attachment 3.7 Power Distribution Limits (TS 3.12.B.1 and TS 3.12.B.2) 3.7.1 Heat Flux Hot Channel Factor - FQ(z)

CFQ,,,

FQ(z) <_-FK(z) for P > 0.5

-P FQ(z) <_ -

K(z) for P *_ 0.5 0.5 THERMAL POWER where: P =

RATED POWER CFQ = 2.5 K(z) = 1.0 for all core heights, z 3.7.2 Nuclear Enthalpy Rise Hot Channel Factor - FAH(N)

FAH(N) *_ CFDH * {1 + PFDH(1 - P)}

THERMAL POWER where: P =

RATED POWER CFDH = 1.56 PFDH = 0.3 3.8 DNB Parameters (TS 3.12.F and TS Table 4.1-2A)

Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:

• Reactor Coolant System Tavg _< 577.0 'F

• Pressurizer Pressure > 2205 psig Reactor Coolant System Total Flow Rate > 273,000 gpm (Tech Spec Limit) and > 276,000 gpm (COLR Limit)

COLR-S2C25, Rev.0 Page 5 of 7

Serial No.12-679 Docket No. 50-281 Attachment Figure A-1 670 660 650 LL 640 630 620 E 610 l,-

1 600

> 590 580 570 560 550 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 0

10 20 30 40 50 60 70 Percent of Rated Power 80 90 100 110 120 COLR-S2025, Rev.0 Page 6 of 7

Serial No.12-679 Docket No. 50-281 Attachment Figure A-2 Surry 2 Cycle 25 Rod Group Insertion Limits Max w/d position = 229 steps

230, 220

/00000, (0.4875,229) 210 200 190 C-Bank 180 170

-e*_

160 15 (0,151)

,. 140

" 130 S120

.2 0 110 0.

CL 100 00DBn I

90 0

S80 000 70 60 50 40 30 20 (0,23) 10 0

I 0

0.1 0.2 0.3 0.4 0.5 0.6 Fraction of Rated Thermal Power 0.7 0.8 0.9 1

COLR-S2C25, Rev.0 Page 7 of 7