ML24136A230

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Core 1 Cycle 33 Pattern Mdr Revision 0
ML24136A230
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/13/2024
From: Standley B
Dominion Energy Services
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
24-175
Download: ML24136A230 (1)
v • d • e


Text

May 13, 2024 Dominion Energy Services, Inc.

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

Serial No.:

24-175 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 OPERA TING LIMITS REPORT SURRY 1 CYCLE 33 PATTERN MDR 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 33, Pattern MOR, Revision 0.

If you have any questions or require additional information, please contact Mr. Gary D. 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 33, Pattern MOR, 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.24-175 Docket No. 50-280 COLR S1C33

Attachment CORE OPERA TING LIMITS REPORT Surry Unit 1 Cycle 33 Pattern MOR Revision 0 Virginia Electric and Power Company (Dominion Energy Virginia)

Serial No.24-175 Docket No. 50-280

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit I 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 l:!i. T TS 2.3.A.2.e - Overpower l:!i. T 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 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

I. 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. 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectmm 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

4. WCAP-12610-P-A, "V At'J"TAGE+ Fuel Assembly Report," (Westinghouse Proprietary), April 1995.

Methodology for:

TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor Page 1 of7

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. 4, "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 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.l 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 6T TS 2.3.A.2.e-Overpower 6T Page 2 of7

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)

Where:

6T is measured RCS 6T, 0 f.

f... To is the indicated f... T at RA TED PO \\VER, 0f.

s is the Laplace transform operator, sec *1.

T is the measured RCS average temperature (Tavg),

0f.

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

P is the measured pressurizer pressure, psig.

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

K1 :S 1.1425 K3 ~ 0.000765 /psig ti~ 29.7 seconds ti.'.S 4.4 seconds f(M) ~

0.0268 { (q1 -qb)}, when (qi-qb) < -24.0% RATED POWER 0,

when -24.0% RA TED POWER :S (q1 - qb) :S +8.0% RA TED POWER 0.0188 { ( q1 - qb) - 8.0}, when ( q1 - qb) > +8.0% RA TED POWER Where q1 and qb are percent RA TED POWER in the upper and lower halves of the core, respectively, and q1 + qb is the total THERMAL POWER in percent RA TED POWER.

Page 3 of7

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

Where:

~Tis measured RCS ~T, 0 f.

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

s is the Laplace transform operator, sec-1.

Tis the measured RCS average temperature (Tavg),

0 f.

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

K4 :S 1.0965 h 2: 9.0 seconds Ks 2: 0.0198 /°F for increasing Tavg 2: 0 /°F for decreasing Tavg f(M) = as defined above for OT~ T 3.4 Moderator Temperature Coefficient (TS 3.1.E)

The Moderator Temperature Coefficient (NITC) limits are:

+6.0 pcmfF at less than 50 percent of RATED POWER, and K6 2: 0.001074 /°F for T > T' 2: 0 for T :S 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. l 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 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 Figure A-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 Margjp (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/k.

Page 4 of7

3.7 Power Distribution Ljmjts (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) ::; p K(z)for P > 0.5 CFQ FQ(z) ::; 0.5 K(z)f or P::; 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= l.635 PFDH=0.3 FZJH(N)::; CFDH * {1 + PFDH(l - P)}

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

RATED POWER 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:

  • Pressurizer Pressure ?. 2205 psig

Page 5 of7

u..

670 660 650

~ 640 GI..

11,1)

~ 630 GI..

E 620 IQ..

GI

~ 610 GI I-t, 600 IQ...

GI

~ 590 ai "'

~ 580 570 560 550 L

l-I Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 238,) psig

£---

I npsi~

I ~

1----------

1981

  • psig

1~ '

____, - ~

..... '~

186(

i-----

r-----

~~

"". ~~

~

0 10 20 30 40 so 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 Ill
0.

CII... 130 Ill

ii:

c' 120 0

0 110 D.

0.
I 100 0...

l.!1 "C

90 0

Q:

80 70 60 so 40 30 20 10 0

Figure A-2 Surry 1 Cycle 33 Rod Group Insertion Limits Fully withdrawn position = 228 steps

/

~ 0.4625,225

/

/

/

~ Vc-Ban~

/

~

/ i V I 0,151

/

/

D-Bank V

~

/

/

~

V

/

/ ~

/

/ I V

l

~ 0,23 0

0.1 0.2 0.3 0.4 0.5 0.6 1.0,225 1.0,183 -

~

/

/

~

V

/

/ V 0.7 0.8 0.9 1

Fraction of Rated Thermal Power Page 7 of7

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