ML18128A195

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Core Operating Limits Report Cycle 29 Pattern Zeu, Revision 0
ML18128A195
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/01/2018
From: Stanley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
18-191
Download: ML18128A195 (10)
v • d • e


Text

. Dominion Energy Services, Inc.

  • 5000 Dominion Boulevard, Glen'Alleri, VA 23060 Dominion Energy.com A

ii# Dominion Energy May 1, 2018 United States Nuclear Regulatory Cornmission

SURRY POWER STATION UNIT 1 CORE OPERATING LIMITS REPORT SURRY 1 CYCLE 29 PATTERN ZEU 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 29, Pattern ZEU, Reyision 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 1 Cycle 29 Pattern ZEU Revision 0 Commitment Summary: There are no new commitments contained in this letter.

Serial No.18-191 Docket No. 50-280 COLR S1C29 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 B-1 A 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.18-191 Docket No. 50-280 Attachment CORE OPERATING LIMITS REPORT Surry Unit 1 Cycle 29 Pattern ZEU Revision 0

Serial No.18-191 Docket No. 50-280 COLR S1C29 Attachment

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 1 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 6 T TS 2.3 .A.2.e - Overpower!}.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 4.1-2A- Minimum Frequency for Equipment Tests: Item 22 - RCS Flow

2.0 REFERENCES

1. VEP-FRD-42, Rev. 2.2-A, "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.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 4.1-2A - 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.18-191 Docket No. 50-280 COLR S1C29 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, 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 LiT TS 2.3.A.2.e- Overpower LiT Page 2 of 7

Serial No.18-191 Docket No. 50-280 COLR S1C29 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 Overtemperature I'\ T (TS 2.3 .A.2.d)

~T < ~To [K1 - K2 (:::::) (T - T') + K3 (P - P') - f(L1I)]

Where:

LiT is measured RCS LiT, °F.

LiTo is the indicated LiT at 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.

P is the measured pressurizer pressure, psig.

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

K1 :S 1.1425 K2 2 0.01059 /°F K3 2 0.000765 /psig t1 2 29. 7 seconds 12 :S 4.4 seconds f(Lil) 2 0.0268 { (qi - qb)}, when (qt - qb) < -24.0% RA TED POWER 0, when-24.0% RATED POWER :S (qt -qb) :S +8.0% RATED POWER 0.0188 {(qt - qb)- 8.0}, when (qi - qb) > +8.0% RA TED POWER Where qi and qb are percent RATED POWER in the upper and lower halves of the core, respectively, and qi+ qb is the total THERMAL POWER in percent RA TED POWER.

Page 3 of 7

Serial No.18-191 Docket No. 50-280 COLR S1C29 Attachment 3.3 Overpower AT (TS 2.3.A.2.e)

Where:

i1T is measured RCS i1T, °F.

L1To is the indicated i1T at 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.

K4 :S 1.0965 Ks 2: 0.0198 /°F for increasing Tavg K6 2: 0.001074 /°F for T > T' 2: 0 /°F for decreasing T avg 2: 0 for T :S T' 13 2: 9.0 seconds f(L1I) = as defined above for OT i'1 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 RA TED 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 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 %L1k/k.

Page 4 of 7

Serial No.18-191 Docket No. 50-280 COLR S1C29 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)

FQ(z)::;; pCFQ K(z)for P > 0.5 CFQ FQ(z)::;; O.S 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)

FLJH(N)::;; CFDH * {1 + PFDH(l - P)}

THERMAL POWER where: P = -RAT ED 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 2: 2205 psig

Page 5 of 7

Serial No.18-191 Docket No. 50-280 COLR S1C29 Attachment Figure A-1 REACTOR CORE SAFETY LIM ITS THREE LOOP OPERATION, 100% FLOW 670 660 LI.

Ill

~ 238 tJ DSiE!

a, 650 a,

- ~

- ----~'~,,~

'J'J2 ,._ *<;l<.J llO 640 -

a, C r--- ~

~ ~

a, 630 r--- i--....... -- ----

198 5 psig

....:l i--........

...a, RI 620

~~ 186 bps-ig-C.

E a,

610 r--- r---

~""'""

I-a, 600 ~

llO RI 590 """

'~

a,

~ 580 a, ~

Ill Ill a, 570 560 550 0 10 20 30 40 so 60 70 80 90 100 110 120 Percent of Rated Power Page 6 of 7

Serial No.18-191 Docket No. 50-280 COLR S1C29 Attachment Figure A-2 Surry 1 Cycle 29 Rod Group Insertion Limits Max w/d position =230 steps 230

/ 0.4938, 230 220 V

210 /

200

/

190 /

~

V C- B( nk 1.0, 183

~

180 170

/ /

/

'f"'

./~

"C 3::

Ill a.

QI 160 150 / 0,151

/

V Ill 140

  1. V c'

0 130

/

"iii 0

C. 120 /

a.

...0 110

/

l!>

"C 0

cc: 100 D- Bank

~

/

90 ~

/

80

./

70 V

60

/

V so /

40

/

30

/

/

20 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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