ML20140A161

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Core Operating Limits Report: Surry 2 Cycle 30, Pattern Syk, Revision 0
ML20140A161
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/12/2020
From: Standley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
20-166
Download: ML20140A161 (11)
v • d • e


Text

Dominion Energy Services, Inc.

5000 Dominion Bou levard, Glen Allen, VA 23060 Dominion Energy.com May 12, 2020 United States Nuclear Regulatory Commission Serial No.: 20-166 Attention: Document Control Desk NRA/GDM: RO Washington, D.C. 20555 Docket No.: 50-281 License No.: DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT SURRY 2 CYCLE 30 PATTERN SYK 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 30, Pattern SYK, Revision 0.

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

Sincerely, B.r~

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

Attachment:

Core Operating Limits Report, Surry Unit 2 Cycle 30 Pattern SYK, Revision 0 Commitment Summary: There are no new commitments contained in this letter.

Serial No.20-166 Docket No. 50-281 COLR S2C30 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 Mr. Vaughn Thomas NRC Project Manager- Surry U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 04 F-12 11555 Rockville Pike Rockville, MD 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, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.20-166 Docket No. 50-281 COLRS2C30 be page 1 of 1 be: (electronic copy except as noted with *)

D. H. Wilson - SPS R. P. Philpot- SPS C. D. Clemens - IN3SW T. N. Ho - IN3SW D. T. Smith - IN3SW R. S. Brackmann - IN3SW G.D. Miller- lN2SE Licensing File - IN2SE Records Management- c/o Kathryn Barret- lN2SE*

Concurrence:

W. M. Adams WMS concurrence by email T. A. Brookmire TAB concurrence by email C. D. Clemens CDC concurrence by email C. D. Sly CDS concurrence by email Action Plan/Commitments {Stated or Implied):

None Verification of Accuracy:

1. EVAL-ENG-RSE-S2C30, Revision 0, "Reload Safety Evaluation, Surry Unit 2 Cycle 30 Pattern SYK," approved by FSRC on 4/14/2020.

Required Changes to the UFSAR or QA Topical Report:

None

Serial No.20-166 Docket No. 50-281 Attachment CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 30 Pattern SYK Revision 0

Serial No.20-166 Docket No. 50-281

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 30 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 .LlT TS 2.3 .A.2.e - Overpower .LlT 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-A, Revision 2, Minor Revision 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.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-ShutdownMargin 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.20-166 Docket No. 50-281

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:

~S 3.12.B.1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor

8. DOM-NAF-2-P-A, Revision 0, Minor Revision 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 LlT TS 2.3.A.2.e-Overpower .LlT Page 2 of 7

Serial No.20-166 Docket No. 50-281 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)

Where:

LlT is measured RCS LlT, 0 P.

Li.To is the indicated Li.T at RATED POWER, P. 0 sis the Laplace transform operator, sec- 1.

0 T is the measured RCS average temperature (T avg), P.

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 ~235 psig.

K1 ~1.1425 K2 ~0.01059 / 0 P K3 ~0.000765 /psig t1 ~9.7 seconds t2 ~.4 seconds f(Lll) ~ 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 3 of 7

Serial No.20-166 Docket No. 50-281 3.3 Overpower .aT (TS 2.3.A.2.e)

Where:

Li.Tis measured RCS Li.T, °F.

Li.To is the indicated Li.Tat 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, ~73.0°F.

~ sl.0965 Ks ~.0198 /°F for increasing T avg Ko ~).001074 /°F for T > T'

~ /°F for decreasing T avg ~forT sT' t3 ~.O seconds f( Af) = as defined above for OTLi.T 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 ofRATED POWER, and

+6.0 pcml°F at 50 percent of RATED POWER and linearly decreasing to Opcm/°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.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 %&/k.

Page 4 of 7

Serial No.20-166 Docket No. 50-281 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) :::; p K(z)f or P > 0.5 CFQ FQ(z) :::; 0. K(z)f or P :s; 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 - FMI(N)

FLJH(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 4.1-2A)

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

  • Pressurizer Pressure ~205 psig

Page 5 of 7

Serial No.20-166 Docket No. 50-281 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 -

u..

- 238

) osi£Y VI QJ 650 i--.....

QJ

???. c : ; ~

b.O 640 r---

--- ---~ r,....._

QJ Q i-........ i-.........

QJ

I 630

- r--..- -- -r---r---

r--- 198 5 psig ~~ ~

r---- --- r---~"' ~ """"~"'

.....  :-,.___ r---.......

m 620 r---

QJ

a. 186bps~ ..... ~

E 610 QJ QJ b.O m

QJ

<(

600 590 580

~"' ' "'"

~

QJ VI VI QJ 570 '

560 550 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power Page 6 of 7

Serial No.20-166 Docket No. 50-281 Figure A-2 Surry 2 Cycle 30 Rod Group Insertion Limits Max w/d position = 227 steps 230

/ o \ 75,227 220

/

210 /

200

/

190

/

~

V c-B, nk 1.0, 183 -!

180 170

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/

II"

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....cu 160 150 V 0, 151

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V V,

140 V

r::.'

.Q 130 /

"iii 0

C. 120 I/

C.

I

...0 110

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"O 0

c::: 100 D-Bank

~

V 90 II"

/

80 /

70 V

60

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50

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40

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30

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20 V

0, 23 10 0

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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