ML13308B906

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Core Operating Limits Report, Surry 1 Cycle 26 Pattern Apx Revision 0
ML13308B906
Person / Time
Site: Surry Dominion icon.png
Issue date: 10/28/2013
From: Huber T
Dominion, Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13308B906 (10)
v • d • e


Text

Dominion Resources Services, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 FDominion October 28, 2013 United States Nuclear Regulatory Commission Serial No.13-594 Attention: Document Control Desk NL&OS/GDM: RO Washington, D.C. 20555 Docket No. 50-280 License No. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT I CORE OPERATING LIMITS REPORT SURRY 1 CYCLE 26 PATTERN APX 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 1 Cycle 26, Pattern APX, 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 1 Cycle 26 Pattern APX Commitment Summary: There are no new commitments contained in this letter.

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Serial No.13-594 Docket No. 50-280 COLR S1C26 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-Gross 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.13-594 Docket No. 50-280 Attachment COLR-S 1C26, Revision 0 CORE OPERATING LIMITS REPORT Surry 1 Cycle 26 Pattern APX October 2013 COLR-S1C26, Rev. 0 Page I of 8

Serial No.13-594 Docket No. 50-280 Attachment

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 1 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.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-S 1C26. Rev. 0 Page 2 of 8

Serial No.13-594 Docket No. 50-280 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 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. VEP-NE-3-A, Rev. 0, "Qualification of the WRB-1 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-S 1C26, Rev. 0 Page 3 of 8

Serial No.13-594 Docket No. 50-280 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 <ATo [K,- K 2 (1 + tis) (T-T) +K& -P) -f(AI)]

Where:

AT is measured RCS AT, °F.

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

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

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

P is the measured pressurizer pressure, psig.

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

K1 < 1.1425 K2 > 0.01059 /IF 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-S 1C26, Rev. 0 Page 4 of 8

Serial No.13-594 Docket No. 50-280 Attachment 3.3 Overpower AT (TS 2.3.A.2.e)

AT *ý AT0 [K 4 -K, ( 1 3 ) T - K(T -T') - f(AI)]

Where:

AT is measured RCS AT, OF.

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

1 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 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/nF 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. 1 (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.1.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-S 1 C26, Rev. 0 Page 5 of 8

Serial No.13-594 Docket No. 50-280 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) <_--FQ-K(z) for P > 0.5

-P CFQ FQ(z) <_ -- Q-K(z) for P <_ 0.5

0.5 where

P = THERMAL RATED POWER 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

  • fl + PFDH(1 - P)}

where: P = THERMAL RATED POWER 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:

" Pressurizer Pressure > 2205 psig

" Reactor Coolant System Total Flow Rate > 273,000 gpm (Tech Spec Limit) and > 276,000 gpm (COLR Limit)

COLR-S1C26, Rev. 0 Page 6 of 8

Serial No.13-594 Docket No. 50-280 Attachment Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 650 p 640 ho 0) 630 620 (U

E 610 (u 600

> 590 580 570 560 550 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power COLR-S I C26, Rev. 0 Page 7 of 8

Serial No.13-594 Docket No. 50-280 Attachment Figure A-2 Surry 1 Cycle 26 Rod Group Insertion Limits 230

,n = 229 steps 220 210 200 190 180 170 160 150 140 C.

130 S1.20 S120 Vol110 4-0 10 0 100 10 70 80 40 60 70 60 30 80 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Fraction of Rated Thermal Power COLR-S I C26, Rev. 0 Page 8 of 8

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