ML14119A186

Core Operating Limits Report Cycle 26 Pattern Eba Revision 0

ML14119A186
Person / Time
Site:	Surry
Issue date:	04/23/2014
From:	Huber T Dominion, Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
14-212
Download: ML14119A186 (10)

Text

Dominion Resources Services, Inc.

Innsbrook Technical Center RtDominion 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 April 23, 2014 United States Nuclear Regulatory Commission Serial No.14-212 Attention: Document Control Desk NL&OS/GDM: RO Washington, D.C. 20555 Docket No. 50-281 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT SURRY 2 CYCLE 26 PATTERN EBA 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 26, Pattern EBA, Revision 0.

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

Attachment:

Core Operating Limits Report, Surry 2 Cycle 26 Pattern EBA, April 2014 Commitment Summary: There are no new commitments contained in this letter.

4oD /

Serial No.14-212 Docket No. 50-281 COLR $2C26 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 Ms. M. C. Barillas 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.14-212 Docket No. 50-281 CORE OPERATING LIMITS REPORT Surry 2 Cycle 26 Pattern EBA April 2014 COLR-S2C26, Rev. 0 Page 1 of 8

Serial No.14-212 Docket No. 50-281

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 26 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 Limit TS 3.12.A.1 .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-S2C26, Rev. 0 Page 2 of 8

Serial No.14-212 Docket No. 50-281

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

9. 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-S2C26, Rev. 0 Page 3 of 8

Serial No.14-212 Docket No. 50-281 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<*ATo K1 - K 2 (1 + tls)(T-T+K 3 (P-P-f(A)]

Where:

AT is measured RCS AT, °F.

AT 0 is the indicated AT at RATED POWER, °F.

s is the Laplace transform operator, sec-I.

T is the measured RCS average temperature (Tavg), OF.

T' is the nominal Tavg at RATED POWER, _< 573.01F.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure > 2235 psig.

KI < 1.1425 K 2 _>0.01059 /OF K3 _ 0.000765 /psig t >_29.7 seconds t2 < 4.4 seconds f(AI) > 0.0268 { (qt - qb)}, when (qt - qb) < -24.0% RATED POWER 0, when -24.0% RATED POWER _ (qt - qb) < +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-S2C26, Rev. 0 Page 4 of 8

Serial No.14-212 Docket No. 50-281 3.3 Overpower AT (TS 2.3.A.2.e)

AT ý AT [K 4 - K5 (( 3 - K6 (T - T') -[(AI)]

Where:

AT is measured RCS AT, 'F.

AT 0 is the indicated AT at RATED POWER, 'F.

s is the Laplace transform operator, secl.

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

T' is the nominal Tavg at RATED POWER, < 573.0 0 F.

K4 _<1.0965 K5 >_0.0198 /F for increasing Tavg K6 > 0.001074 /°F for T > T'

>_0 /°F 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/fF 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.l(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-S2C26, Rev. 0 Page 5 of 8

Serial No.14-212 Docket No. 50-281 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) < --- nK(z) for P > 0.5

-P CFQ FQ(z) <* -QK(z) for P !5 0.5

0.5 where

P = THERMAL POWER 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))

where: P = THERMAL POWER 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-S2C26, Rev. 0 Page 6 of 8

Serial No.14-212 Docket No. 50-281 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 650 640 to 630 620 E 610 u600 m

590 580 a) 570 560 550 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power COLR-S2C26, Rev. 0 Page 7 of 8

Serial No.14-212 Docket No. 50-281 Figure A-2 Surry 2 Cycle 26 Rod Group Insertion Limits Max w/d position = 226 steps 230

(.4688,226) 220 210 /

200 190 C-Bank/ 1.0,183 180 170 ___ __ _

160 ___

-a 150 _

(0,151) i140 130 120 0 110o/

0. 0oo 10 D-Bank 90 0

80 70 60 50 00 40 30____

20________ ________

10 (0,23) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Fraction of Rated Thermal Power COLR-S2C26, Rev. 0 Page 8 of 8