ML18302A122

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Core Operation Limits Report, Surry 2 Cycle 29 Pattern Sup, Revision 0
ML18302A122
Person / Time
Site: Surry Dominion icon.png
Issue date: 10/22/2018
From: Stanley B L
Dominion Energy Co, Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
18-399
Download: ML18302A122 (10)
v • d • e


Text

Dominion Energy Services, Inc. 5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com October 22, 2018 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555 ft Dominion j a,,, Energy Serial No.: 18-399 NRNGDM: RO 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 29 PATTERN SUP 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 29, Pattern SUP, Revision 0. If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.

Sincerely, B. L. Stanley, Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company

Attachment:

Core Operating Limits Report, Surry Unit 2 Cycle 29 Pattern SUP 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 Ms. A. Schiller NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 07 E-5 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 B-1 A 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No.18-399 Docket No. 50-281 COLR S2C29 Page 2 of 2 Attachment CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 29 Pattern SUP Revision 0 Serial No.18-399 Docket No. 50-281

1.0 INTRODUCTION

Serial No.18-399 Docket No. 50-281 COLR S2C29 Attachment This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 29 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.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 4.1-2A -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. l .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-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.18-399 Docket No. 50-281 COLR S2C29 Attachment

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, 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 ti T TS 2.3 .A.2.e -Overpower ti T Page 2 of 7

3.0 OPERA

TING LIMITS Serial No.18-399 Docket No. 50-281 COLR S2C29 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 Oyertemperature L\ T (TS 2.3 .A.2.d) Where: ~T < ~To [K 1 -K 2 (~::::) (T-T') + K 3 (P -P') -f(Lll)] LiT is measured RCS LiT, 0 P. Li To is the indicated LiT at RATED POWER, 0 P. sis the Laplace transform operator, sec-1. T is the measured RCS average temperature (T avg), 0 P. 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. K1 S 1.1425 t1229.7 seconds K2 2 0.01059 /0 P 12 S 4.4 seconds K3 2 0.000765 /psig f(Lil) 2 0.0268 {-24 -(qt -qb)}, when (qt -qb) < -24.0% RATED POWER 0, when -24.0% RATED POWERS (qt-qb) S +8.0% RATED POWER 0.0188 {(qi -qb)-8.0}, when (q1-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 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), °F. T' is the nominal Tavg at RATED POWER, S 573.0°F. Ki S 1.0965 Ks~ 0.0198 /°F for increasing Tavg 0 /°F for decreasing T avg t3 9.0 seconds f(M) = 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. Serial No.18-399 Docket No. 50-281 COLR S2C29 Attachment K6 0.001074 /°F for T > T' 0 forTST' +6.0 pcm/°F at 50 percent of RATED POWER and linearly decreasing to O 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 Mar~in (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
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)for P > O.S CFQ FQ(z) :5 Q5 K(z)f or P :5 0.5 where:P = THERMAL POWER RATED POWER K(z) = 1.0 for all core heights, z 3. 7 .2 Nuclear Enthalpy Rise Hot Channel Factor -F Afi(N) CFDH= 1.635 PFDH=0.3 F"1H(N) :5 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) Serial No.18-399 Docket No. 50-281 COLR S2C29 Attachment Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:
  • Pressurizer Pressure 2205 psig
  • Reactor Coolant System Total Flow Rate 273,000 gpm (Tech Spec Limit) and 274,000 gpm (COLR Limit) Page 5 of 7 670 660 LI. Ill 650 a, a, ... b.O 640 a, 0 a, 630 ... ::I +,I ra 620 ... a, C. E 610 a, I-a, 600 b.O ra ... 590 a, > <( a, 580 Ill Ill a, > 570 560 550 ........_

"""------Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 238 1> osie --')')'.l ri,ia -~ """" -r-------198 -Serial No.18-399 Docket No. 50-281 COLR S2C29 Attachment

r---. t---...._

b psig ""--r---. ---t--........~

186 b pslg""' ----'--"-. -r----r---. '------r---~" " "-. ' " 0 10 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 "'C ........ 3 150 "' Q. QI t; 140 :ia: c' 0 130 "' 0 120 0. Q. ::, 0 110 t; "'C 0 100 a: 90 80 70 60 50 40 30 20 10 0 / / , V 0, 151 / / / / 0 , 23 Figure A-2 Surry 2 Cycle 29 Rod Group Insertion Limits Max w/d position = 225 steps /I I / , 0.4625, 225 / / /c-B, nk ./ / / 0-Bank / / /' V / V V 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 Fraction of Rated Thermal Power Page 7 of 7 Serial No.18-399 Docket No. 50-281 COLR S2C29 Attachment 1.0, 183 ..J / /' V / 0.8 0.9 1

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