ML17163A177

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Core Operating Limits Report, Cycle 28 Pattern PRI, Revision 0
ML17163A177
Person / Time
Site: Surry Dominion icon.png
Issue date: 06/06/2017
From: Sly C
Dominion Energy Co, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
17-229
Download: ML17163A177 (10)
v • d • e


Text

Dominion Energy Services, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 DominionEnergy.com A

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Dominion Energy June 6, 2017 United States Nuclear Regulatory Commission Serial No.17-229 Attention : Document Control Desk NRNGDM : 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 28 PATTERN PRI REVISION 0 Pursuant to Surry Techn ical Specification (TS) 6.2.C, attached is a copy of Dominion Energy Virginia 's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 28 ,

Pattern PRI , Revision 0.

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

Sincerely, 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 28 , Pattern PRI , Revision 0 Comm itment Summary: There are no new commitments contained in this letter.

Serial No.17-229 Docket No. 50-28 1 COLR S2C28 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 Mr. J. R. Hall NRC Senior 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.17-229 Docket No. 50-281 Attachment

/

CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 28 Pattern PRI Revision 0 Page 1 of 8

Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment I

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 28 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 fl. T TS 2.3.A.2.e - Overpower fl. 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- 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 BEFEBENCES

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

Methodology for:

TS 2.1 - Safety Limit, Reactor Core TS 3.1.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 - 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-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 2 of 8

Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment I

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 /J. T TS 2.3 .A.2.e - Overpower /J. T Page 3 of 8

Serial No.17-229 Docket No. 50-281 COLR S2C28 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 S AT0 [K 1 - K2 (

1

+ tis) (T- T') + K3(P -

l+tzS P') - f(.M)]

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 (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 ~ 2235 psig.

K 1 S 1.1425 K2 ~ 0.01059 /°F K3 ~ 0.000765 /psig t 1 ~ 29.7 seconds t2 S 4.4 seconds f(AI) ~ 0.0268 { (qt -qb)} , when (qt - qb) < -24.0% RATED POWER 0, when -24.0% RATED POWER S (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 RA TED POWER in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED POWER.

Page 4 of 8

Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment 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*

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

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

K4  :::; 1.0965 K 5 2: 0.0198 /°F for increasing T avg K 6 2: 0.001074 /°F for T > T' 2: 0 /°F for decreasing T avg 2: 0 for T :::; T' t3 2: 9.0 seconds 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 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.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 2: 1. 77 %Af</k.

Page 5 of 8

Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment 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) for P > 0.5 CFQ FQ(z) ~ 0.5 K(z) for P ~ 0.5 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 Table4.1-2A)

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

  • Pressurizer Pressure 2'.: 2205 psig

Page 6 of 8

Serial No .17-229 Docket No. 50-28 1 COLR S2C28 Attachment Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670

~~

Q) 650 t-=="~::~r::::+/-;;:Ji::::::::c::~~i;~:::r==~====~==~==:=J 640 ......

1 ----+--

0

~ 630 I

~

J 620 . *****-*+*--

~ 610 1 _ J_

600 1-

~ 590 + *-!

QI I i

~ 580 /--** -*f-*** *-*--*~--*******---*****+-***--*****-*******--*-*****-*->-****-*********-*+

~ 5 70 J*-*---1-** **- *****'"******************************!---->--**--*--'--*-*---*--*--**--**** -***********-******-- *-*-************** -*-*-***-*********** - - - - -*-

> 560 t----~1-___j--~-~---~--+----l---+---l---+-----j~---+---I 550 i 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power Page 7 of 8

Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment Figure A-2 Surry 2 Cycle 28 Rod Group Insertion Limits Max w/d position =230 steps 230

/ 0.4938, 230 220

/

v 210 200 I/

190 /

V c -B< nk 1.0, 183

~ ,.J 180 170

/ /

/" /"

"lJ

~

Ill 160 150 / 0, 151

/

v Cl.

cu Ill 140 c0 130 /

~

Q.

Ill 0

120

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Cl.

I

...0 110 /

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"lJ 0

D-Bank

~

/

a:: 100 90

/

80

/ "

70

/

60

/

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v 50 40

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30 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 8 of 8

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