ML17163A177
| ML17163A177 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| 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) | |
Text
Dominion Energy Services, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 DominionEnergy.com June 6, 2017 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 A
Dominion
- t
- ii"' Energy Serial No.
NRNGDM:
Docket No.
License No.17-229 RO 50-281 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 Technical 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 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. 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 COLR S2C28 Page 2 of 2
/
CORE OPERA TING LIMITS REPORT Surry Unit 2 Cycle 28 Pattern PRI Revision 0 Page 1 of 8 Serial No.17-229 Docket No. 50-281 Attachment
I
1.0 INTRODUCTION
Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment 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
I Serial No.17-229 Docket No. 50-281 COLR S2C28 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 /J. T TS 2.3.A.2.e - Overpower /J. T Page 3 of 8
3.0 OPERATING LIMITS Serial No.17-229 Docket No. 50-281 COLR S2C28 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 AT (TS 2.3.A.2.d)
AT S AT0 [K1 - K2 (
1+ tis) (T-T') + K3(P - P') - f(.M)]
l+tzS 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 t1 ~ 29.7 seconds t2 S 4.4 seconds K3 ~ 0.000765 /psig 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
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 t3 2: 9.0 seconds K 5 2: 0.0198 /°F for increasing T avg 2: 0 /°F for decreasing T avg 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 Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment K6 2: 0.001074 /°F for T > T' 2: 0 for T :::; T'
+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
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)
Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:
Reactor Coolant System T avg S 577.0 °F Pressurizer Pressure 2'.: 2205 psig Reactor Coolant System Total Flow Rate 2'.: 273,000 gpm (Tech Spec Limit) and 2'.: 274,000 gpm (COLR Limit)
Page 6 of 8
670 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment
~ 650 t-=="~::~r::::+/-;;:Ji::::::::c::~~i;~:::r==~====~==~==:=J
~ 640......
1 ----+--
Q) 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
230 220 210 200 190 180 170 160 "lJ -
~ 150 Ill Cl.
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140 Ill
- c 0
130
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Ill 0
120 Q.
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- I 0
110
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"lJ 0
100 a::
90 80 70 60 50 40 30 20 10 0
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v 0, 23 Figure A-2 Surry 2 Cycle 28 Rod Group Insertion Limits Max w/d position = 230 steps
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0.4938, 230
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v Serial No.17-229 Docket No. 50-281 COLR S2C28 Attachment 1.0, 183
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v 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