ML16312A063

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Core Operating Limits Report for Cycle 28 Pattern APT, Revision 0
ML16312A063
Person / Time
Site: Surry Dominion icon.png
Issue date: 11/02/2016
From: Huber T
Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
16-411
Download: ML16312A063 (10)
v • d • e


Text

,..

Dominion Resources Services, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 November 2, 2016 United States Nuclear Regulatory Commission Serial No.16-411 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 1 CORE OPERATING LIMITS REPORT SURRY 1CYCLE28 PATTERN APT 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 28, Pattern APT, 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 Regulatory Affairs Dominion Resources Services, Inc. for Virginia Electric and Power Company

Attachment:

Core Operating Limits Report, Surry Unit 1 Cycle 28, Pattern APT, Revision 0 Commitment Summary: There are no new commitments contained in this letter.

Serial No.16-411 Docket No. 50-280 COLR S1C28 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. K. 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.16-411 Docket No. 50-280 Attachment CORE OPERATING LIMITS REPORT Surry Unit 1 Cycle 28 Pattern APT Revision 0

Serial No.16-411 Docket No. 50-280 COLR S1C28 Attachment

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 28 has been prepared in

. accordance with the requirements of Stirry 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 fl. T TS 2.3.A.2.e-Overpower fl.T TS 3. l .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 (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

2.0 REFERENCES

1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003.

Methodology for:

TS 2.1 - Safety Limit, Reactor Core TS 3. l .E - Moderator Temperature Coefficient TS 3.12.A.l, 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 Page 1 of 7

Serial No.16-411 Docket No. 50-280 COLR S1C28 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. DOM-NAF-2-P-A, Rev. 0.3, "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," and Appendix D, "Qualification of the ABB-NV and WLOP CHF Correlations in the Dominion VIPRE-D Computer Code,"

September 2014.

Methodology for:

TS 3.12.B.1 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 l'1.T TS 2.3 .A.2.e - Overpower l'1.T Page 2 of 7

Serial No.16-411 Docket No. 50-280 COLR S1C28 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 Oyertemperature AT (TS 2.3 .A.2.d)

AT~ AT0 [K1 - K2 1+t1

( -1+t s s) (T-T)* + K (P - P)* -

3 f(AI)]

2 Where:

AT is measured RCS AT, °F.

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

sis the Laplace transform operator, sec* 1.

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

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

P is the measured pressurizer pressure, psig.

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

K 1 ~1.1425 Ki ~ 0.01059 /°F K3 ~ 0.000765 /psig t 1 ~ 29.7 seconds ti ~ 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.

Page 3of7

Serial No.16-411 Docket No. 50-280 COLR S1C28 Attachment 3.3 Oyerpower AT (TS 2.3.A.2.e)

Where:

~Tis measured RCS ~T, °F.

~TO is the indicated ~Tat RATED POWER, °F.

sis the Laplace transform operator, sec- 1*

Tis the measured RCS average temperature (Tavg), °F.

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

K5 ~ 0.0198 /°F for increasing Tavg K6 ~ 0.001074 /°F for T > T'

~ 0 /°F for decreasing Tavg ~ 0 forT:ST' t3 ~ 9.0 seconds f(M) = as defined above for OT~T 3.4 Moderator Temnerature 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.l, 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 %Afdk.

Page 4 of 7 I

L__

Serial No.16-411 Docket No. 50-280 COLR S1C28 Attachment

3. 7 Power Distribution Limits (TS 3 .12.B.l and TS 3.12.B.2) 3.7.1 Heat Flux Hot Channel Factor- FQ(z)

CFQ FQ(z) :::; p K(z) for P > 0.5 CFQ FQ(z) $ 0. K(z) for P :::; 0.5 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- F~H(N)

F~H(N) < CFDH * {1 + PFDH(l - P)}

THERMAL POWER where: P = - - - - - - -

RATED POWER CFDH= 1.635

'PFDH=0.3 3.8 DNB Parameters (TS 3.12.F and TS Table 4.l-2A)

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

  • Pressurizer Pressure ;::: 2205 psig

Page 5of7

Serial No.16-411 Docket No. 50-280 COLR S1C28 Attachment Figure A-1 REACTOR CORE SAFETY LIMITS 560 -*--

550 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power Page 6 of 7

Seri al No.16-411 Docket No. 50-280 COLR S1C28 Attachment Figure A-2 Surry 1 Cycle 28 Rod Group Insertion Limits Max w/d position 228 steps 23 0

/ I I 0.4813, 228 220

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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 Page 7 of 7

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