ML22306A211

Core Operating Limits Report, Surry 1 Cycle 32 Pattern Sjk Revision 0

ML22306A211
Person / Time
Site:	Surry
Issue date:	11/01/2022
From:	Standley B Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
22-326
Download: ML22306A211 (1)

Text

Dominion Energy Services, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com November 1, 2022 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

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Dominion

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Energy°'

Serial No.:

22-326 NRA/GDM:

RO Docket No.:

50-280 License No.:

DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNIT 1 CORE OPERATING LIMITS REPORT SURRY 1 CYCLE 32 PATTERN SJK REVISION 0 Pursuant to Surry Technical Specification (TS) 6.2.C, attached is a copy of the Core Operating Limits Report (COLR) for Surry Power Station Unit 1, Cycle 32, Pattern SJK, Revision 0.

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

Respectfully, B. E. Standley, Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company

Attachment:

Core Operating Limits Report, Surry Unit 1 Cycle 32, Pattern SJK, Revision 0 Commitment Summary: There are no new commitments contained in this letter.

cc:

U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. L. John Klos NRG Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. G. Edward Miller NRG Senior Project Manager - North Anna U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, Maryland 20852-2738 NRG Senior Resident Inspector Surry Power Station Serial No.22-326 Docket No. 50-280 COLR S1C32

Attachment CORE OPERA TING LIMITS REPORT Surry Unit 1 Cycle 32 Pattern SJK Revision 0 Virginia Electric and Power Company (Dominion Energy Virginia)

Serial No.22-326 Docket No. 50-280

1.0 INTRODUCTION

Serial No.22-326 Docket No. 50-280 Attachment This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 32 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.1.. T TS 2.3.A.2.e - Overpower.1.. T 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-ShutdownMargin 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. 2.2-A, "Reload Nuclear Design Methodology," October 2017.

Methodology for:

TS 2.1 - Safety Limit, Reactor Core 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-16996-P-A, Rev. 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA METHODOLOGY)," November 2016.

Methodology for:

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

3. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," as supplemented by ANP-3676P, "Surry Fuel-Vendor Independent Small Break LOCA Analysis," as approved by NRC Safety Evaluation Report dated March 19, 2021.

Methodology for:

TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor COLR-S 1 C32, Revision 0 Page 1 of 7

Serial No.22-326 Docket No. 50-280 Attachment

4. 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

5. 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

6. 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

7. 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

8. 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 ~ T TS 2.3.A.2.e - Overpower /J. T COLR-S1C32, Revision 0 Page 2 of 7

3.0 OPERA TING LIMITS Serial No.22-326 Docket No. 50-280 Attachment 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)

~T < ~To [K1 - K2 (::;:;) (T - T') + K3 (P - P') - f(Lt0]

Where:

~Tis measured RCS ~T, 0 P.

~To is the indicated ~Tat RATED POWER, 0 P.

sis the Laplace transform operator, sec-1.

Tis the measured RCS average temperature (Tavg),

0P.

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

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure 2: 2235 psig.

Ki :S 1.1425 K2 2: 0.01059 /

0P ti :S 4.4 seconds K3 2: 0.000765 /psig ti 2: 29.7 seconds f(M) 2:

0.0268 { (qt-qb)}, when (qt-qb) <-24.0% RATED POWER 0,

when -24.0% RATED POWER :S (qt -qb) :S +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-S1 C32, Revision 0 Page 3 of 7

3.3 Overpower AI (TS 2.3.A.2.e)

Where:

l'J.T is measured RCS l'J.T, °F.

l'J.To is the indicated l'J.T at RATED POWER, °F.

sis the Laplace transform operator, sec*1*

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

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

l<4 S 1.0965 Ks 2: 0.0198 /°F for increasing T avg 2: 0 /°F for decreasing T avg tJ 2: 9.0 seconds f( Af) = as defined above for OT l'J. T 3.4 Moderator Temperature Coefficient (TS 3.1.E)

The Moderator Temperature Coefficient (MTC) limits are:

+6.0 pcmfF at less than 50 percent of RATED POWER, and Serial No.22-326 Docket No. 50-280 Attachment K6 2: 0.001074 /°F for T > T' 2: 0 forT ST'

+6.0 pcmfF at 50 percent of RATED POWER and linearly decreasing to O pcmfF at RATED POWER 3.5 Conh"ol 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 FigureA-2.

3.5.3 The rod insertion limit for the A and B shutdown banks is the fully withdrawn position as shown on FigureA-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 2: 1. 77 %&/k.

COLR-S 1 C32, Revision 0 Page 4 of 7

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=2.5 CFQ FQ(z) :s;; p K(z)for P > 0.5 CFQ FQ(z) :s;; 0_5 K(z)for P :s;; 0.5 THERMAL POWER where: P = -------

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

CFDH= 1.635 PFDH=0.3 FfiH(N) :s;; CFDH * {1 + PFDH(l - P)}

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

RATED POWER 3.8 DNB Parameters (TS 3.12.F and TS Table 4.1-2A)

Serial No.22-326 Docket No. 50-280 Attachment Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:

• Reactor Coolant System T avg :'.S 577.0 °F

• Pressurizer Pressure 2: 2205 psig

• Reactor Coolant System Total Flow Rate 2: 273,000 gpm (Tech Spec Limit) and 2: 274,000 gpm (COLR Limit)

COLR-S1C32, Revision 0 Page 5 of 7

670 -

660 LL.

Ill 650 QJ QJ...

l).O 640 QJ Q

QJ 630

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I!

620 QJ

0.

E 610 QJ....

QJ 600 l).O n:i...

590 QJ

~ 580 a:;

Ill Ill QJ 570 560 550 0

10 COLR-S1 C32, Revision 0 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 238, osig

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J')~ "'no;jp -

i-.........

--r----.

198, psig

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---r----.

~,,

186 Ops-ig-i-........ ---

-r---

~ -,'

i-........

Serial No.22-326 Docket No. 50-280 Attachment

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

230 220 210 200 190 180 170 160 150 80 70 60 50 40 30 20 10 0

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Figure A-2 Surry 1 Cycle 32 Rod Group Insertion Limits Max w/d position = 226 steps

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D-Bank

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0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Fraction of Rated Thermal Power COLR-S1C32, Revision 0 Page 7 of 7 (1

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Serial No.22-326 Docket No. 50-280 Attachment 0,183)

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