ML24302A176

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Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0
ML24302A176
Person / Time
Site: Surry 
(DPR-037)
Issue date: 10/22/2024
From: Sly C
Dominion Energy, Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
24-312
Download: ML24302A176 (1)
v • d • e


Text

October 22, 2024 Dominion Energy Services. Inc.

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

~

Dominion

~

Energy ':

Serial No.:

24-312 NRA/GDM:

RO Docket No.:

50-281 License No.:

DPR-37 VIRGINIA ELECTRIC ANO POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNIT 2 CORE OPERA TING LIMITS REPORT SURRY 2 CYCLE 33 PATTERN HOT 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 2, Cycle 33, Pattern HOT, Revision 0.

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

Respectfully, C. D. Sly, Acting Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company

Attachment:

Core Operating Limits Report, Surry Unit 2 Cycle 33, Pattern HOT, 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 NRC 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 NRC 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 NRC Senior Resident Inspector Surry Power Station Serial No.24-312 Docket No. 50-281 COLR S2C33 Page 2 of 2

Attachment CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 33 Pattern HOT Revision 0 Virginia Electric and Power Company (Dominion Energy Virginia)

Serial No.24-312 Docket No. 50-281

1.0 INTRODUCTION

Serial No.24-312 Docket No. 50-281 This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 33 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 t,,,.T TS 2.3.A.2.e-Overpower t,,,.T TS 3.1.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 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. l-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

2.0 REFERENCES

1. VEP-FRD-42-A, Rev. 2, Minor Rev. 2, "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.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.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. l-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

2. WCAP-16996-P-A, Rev. l, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrnm 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-RELAPS 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 Page 1 of 7

Serial No.24-312 Docket No. 50-281

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, Minor Rev. 5, "Reactor Core The1mal-Hydraulics Using the VIPRE-D Computer Code," including Appendix B, "Qualification of the Westinghouse WRB-1 CHF Correlation in the Domjnion VIPRE-D Computer Code," June 2010, and Appendix D, "Qualification of the ABB-NV and WLOP CHF Correlations in the Dominion VIPRE-D Computer Code," August 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-Ove1temperature ~ T TS 2.3.A.2.e-Overpower ~T Page 2 of 7

3.0 OPERATING LIMITS Serial No.24-312 Docket No. 50-281 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)

Where:

11 T is measured RCS /1 T, °F.

/1To is the indicated 11T at RATED POWER, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature (T avg), °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 2: 2235 psig.

Kt :51.1425 K3 :2: 0.000765 /psig t1 2: 29.7 seconds K2 2: 0.01059 /°F ti :5 4.4 seconds f(/11) 2:

0.0268 { ( 91 - qb)}, when ( q1 - qb) < -24.0% RA TED POWER 0,

when -24.0% RA TED POWER :5 ( 9t - qb) :5 +8.0% RA TED POWER 0.0188 {(qi-qb)- 8.0}, when (qt - qb) > +8.0% RATED POWER Where 91 and qb are percent RA TED POWER in the upper and lower halves of the core, respectively, and 9t + 9b is the total THERMAL POWER in percent RA TED POWER.

Page 3 of 7

3.3 Overpower 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),

0f.

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

h 2: 9.0 seconds Ks 2: 0.0198 /°F for increasing Tavg 2: 0 /

0f for decreasing Tavg f(~I) = as defined above for OT~ 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 RA TED POWER, and Serial No.24-312 Docket No. 50-281 K6 2: 0.001074 /

0f for T > T' 2: 0 for T::; T'

+6.0 pcmfF at 50 percent of RA TED POWER and linearly decreasing to O pcmfF at RA TED 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 inse1tion as shown in Figure A-2.

3.5.2 The rod inse1tion limit for the A and B control banks is equal to 225 steps. The rod insertion limit is met by establishing the fully withdrawn position to greater than or equal to 225 steps, as shown on FigureA-2.

3.5.3 The rod insertion limit for the A and B shutdown banks is 225 steps. The rod insertion limit is met by establishing the fully withdrawn position to greater than or equal to 225 steps, as shown on Figure A-2.

3.6 Shutdown Margjn (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.

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) :5 p K(z)f or P > 0.5 CFQ FQ(z) :5 -

5 K(z)f or P :5 0.5

0.

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

RATED POWER K(z) = l.O for all core heights, z 3.7.2 Nuclear Enthalpy Rise Hot Channel Factor-FAfl(N)

CFDH= 1.635 PFDH=0.3 F/JH(N) :5 CFDH * {1 + PFDH(l - P)}

where: P =

THERMAL POWER RATED POWER 3.8 DNB Parameters (TS 3.12.F and TS Table 4.l-2A)

Serial No.24-312 Docket No. 50-281 Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:

  • Pressurizer Pressure 2: 2205 psig

Page 5 of 7

LI..

670 660 650

~ 640 QI...

1111

~ 630 QI...

E 620 la...

QI

~ 610 QI 1-gi, 600 la...

QI

i 590 ai "'

~ 580 570 560 550

~ -

r--- ~

r-----

0 10 20 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 238 *) osig

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')'}~_psi~

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1981 > psig

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1860~

r---__

r---.. -

-r---

r---.. - -

Serial No.24-312 Docket No. 50-28 l 1'."

r----' " ~"'

i-0~"

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30 40 50 60 70 80 90 100 110 120 Percent of Rated Thermal Power Page 6 of7

230 220 210 200 190 180 170 160 150 "C

....... ;: 140

0.

QI....

130 2 120 0

0 110 0..

C.

J 100 0...

Cl "C

90 0

Cl:

80 70 60 50 40 30 20 10 0

~

/

/'

/

0,151 Figure A-2 Surry 2 Cycle 33 Rod Group Insertion Limits Fully withdrawn position = 228 steps

/

V 0.4625,225

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/

/

Vc-Bank

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Serial No.24-312 Docket No. 50-281 1.0,225 1.0,183 -

I

/

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V

/ V

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D-Bank V

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V

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V 0,23 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 of7

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