ML22179A278
| ML22179A278 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/27/2022 |
| From: | Standley B Dominion Energy Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 22-201 | |
| Download: ML22179A278 (10) | |
Text
Dominion Energy Se rvices, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com June 27, 2022 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
~
Dominion
~
Energy Serial No.:
22-201 NRA/GDM:
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 31 PATTERN MSK REVISION 1 Pursuant to Surry Power Station (Surry) Units 1 and 2 Technical Specification (TS) 6.2.C, attached is a copy of the Core Operating Limits Report (COLR) for Surry Power Station Unit 2, Cycle 31, Pattern MSK, Revision 1. The revision incorporates a change to the Control Bank Rod Insertion Limits (Rlls) to accommodate operation with a Rod Cluster Control Assembly (RCCA) RI L of 225 steps for the C-Bank.
If you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.
Respectfully, B. E. Standley, Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company
Attachment:
Core Operating Limits Report, Surry Unit 2 Cycle 31 Pattern MSK, Revision 1 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 Mr. L. John Klos NRC Project Manager - Surry U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 09 E-3 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.22-201 Docket No. 50-281 COLR S2C31 R1 Page 2 of 2
Attachment CORE OPERATING LIMITS REPORT Surry Unit 2 Cycle 31 Pattern MSK Revision 1 Virginia Electric and Power Company (Dominion Energy Virginia)
Surry Power Station Unit 2 Serial No.22-201 Docket No. 50-281
ATTACHMENT CORE OPERATING LIMITS REPORT Serial No.22-201 Docket No. 50-281 COLR S2C31R1 SURRY UNIT 2 CYCLE 31, PATTERN MSK, REVISION 1
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 31 has been prepared m 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.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, Rev. 2.2-A, "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.l, 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.cand 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 Page 1 of 7
Serial No.22-201 Docket No. 50-281 COLR S2C31R1
- 3.
EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," as supplemented by ANP-3676P, "Surry Fuel-Vendor Independent Small Break LOCA Analysis," as approved by NRC Safety Evaluation Report dated March 19, 2021.
Methodology for:
TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor
- 4.
WCAP-12610-P-A, "VANT AGE+ 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
- 5.
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
- 6.
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
- 7.
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
- 8.
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 /1 T TS 2.3.A.2.e - Overpower /1 T Page 2 of 7
3.0 OPERA TING LIMITS Serial No.22-201 Docket No. 50-281 COLR S2C31 R1 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:
/). T is measured RCS !). T, 0P.
!).TO is the indicated !).Tat RATED POWER, 0P.
s is the Laplace transform operator, sec -l _
Tis the measured RCS average temperature (Tavg),
0P.
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.
K1 ~ 1.1425 K2 ~ 0.01059 /
0P ti ::; 4.4 seconds K3 ~ 0.000765 /psig t 1 ~ 29. 7 seconds f(M) ~
0.0268 { (qt -qb)}, when (qt - qb) <-24.0% RATED POWER 0,
when-24.0% RATED POWER~ (q1 -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 RA TED POWER.
Page 3 of 7
3.3 Overpower AT (TS 2.3.A.2.e)
Where:
~Tis measured RCS ~T, 0P.
~TO is the indicated ~Tat RATED POWER, 0P.
s is the Laplace transform operator, sec -l _
T is the measured RCS average temperature (T avg),
0P.
T' is the nominal T avg at RA TED POWER, :::; 573.0°F.
K4:::; 1.0965 t3 ~ 9.0 seconds K5 ~ 0.0198 /
0P for increasing Tavg
~ 0 /
0P 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 RA TED POWER, and Serial No.22-201 Docket No. 50-281 COLR S2C31 R1 K6 ~ 0.001074 /°F for T > T'
~ 0 for T :ST'
+6.0 pcm!°P 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.1.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) < p K(z)f OTP> 0.5 CFQ FQ(z) < -
5 K(z)f or P ~ 0.5
- 0.
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 ~H(N)
CFDH= l.635 PFDH=0.3 FLJH(N) < CFDH * {1 + PFDH(l - P)}
THERMAL POWER where: P = -------
RATED POWER 3.8 DNB Parameters (TS 3.12.F and TS Table 4.1-2A)
Serial No.22-201 Docket No. 50-281 COLR S2C31 R1 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 5 of 7
u..
(I) aJ aJ I..
bJ) aJ C
aJ I..
- s
+.i ra I..
aJ
- 0.
E aJ I-aJ bJ) ra I..
aJ >
<(
cu (I)
(I) aJ >
670 660 650 640 630 620 610 600 590 580 570 560 550 0
Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW Serial No.22-201 Docket No. 50-281 COLR S2C31R1 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
~ 150 Ill C.
a, 140 Ill c"
0 130
'iii 0
120
- 0.
C.
0 110 C,
"C 0
100 a:
90 80 70 60 so 40 30 20 10 0
~
/
/
V 0,151 Figure A-2 Surry 2 Cycle 31 Rod Group Insertion Limits Max w/d position = 229 steps
/ I I
0.4875, 229
/ V
/
/r V e-Be nk
~
Serial No.22-201 Docket No. 50-281 COLR S2C31 R 1 The insertion limit for C-Bank is met for C-Bank positions greater than or equal to 225 steps.
1.0, 183
,.)
/
/
V
/
V
/
/
D-Bank V
~
/
/
i,-
V
/
/ V
/
/r V
0,23 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