ML12143A141
| ML12143A141 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/16/2012 |
| From: | Huber T Dominion, Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 12-343 | |
| Download: ML12143A141 (10) | |
Text
Dominion Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 May 16, 2012 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.
NL&OS/GDM:
Docket No.
License No.12-343 RO 50-280 DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 1 CORE OPERATING LIMITS REPORT SURRY I CYCLE 25 PATTERN GNU REVISION 0 Pursuant to Surry Technical Specification (TS) 6.2.C, attached is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 25, Pattern GNU, Revision 0.
If you have any questions or require Mr. Gary Miller at (804) 273-2771.
additional information, please contact Sincerely, T. R. Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Attachment Commitment Summary: There are no new commitments as a result of this letter.
Ac) C) I N10 VýL
Serial No.12-343 Docket No. 50-280 COLR S1C25 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 K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Dr. V. Sreenivas NRC 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.12-343 Docket No. 50-280 Attachment CORE OPERATING LIMITS REPORT Surry I Cycle 25 Pattern GNU Revision 0 May 2012 Virginia Electric and Power Company (Dominion)
Surry Power Station Unit 1
Serial No.12-343 Docket No. 50-280 Attachment
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 25 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 AT TS 2.3.A.2.e - Overpower AT 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.I(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 TS 3.12.F - DNB Parameters TS Table 4.1-2A - Minimum Frequency for Equipment Tests: Item 22 - RCS Flow
2.0 REFERENCES
I.
VEP-FRD-42, Rev. 2. 1-A, "Reload Nuclear Design Methodology," August 2003.
Methodology for:
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.1(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 4.1-2A - 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.12-343 Docket No. 50-280 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.
VEP-NE-3-A, Rev. 0, "Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code," July 1990.
Methodology for:
TS 3.12.B. 1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor
- 9.
DOM-NAF-2, Rev. 0.2-P-A, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix B, "Qualification of the Westinghouse WRB-1 CHIF Correlation in the Dominion VIPRE-D Computer Code," August 2010.
Methodology for:
TS 3.12.B. 1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor
- 10.
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 AT TS 2.3.A.2.e - Overpower AT Page 2 of 7
Serial No.12-343 Docket No. 50-280 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 AT(TS 2.3.A.2.d)
AT* - AT4 K - K2 ( 1*+*'s (T - T') + K3(P - P') - f(A1I Where:
AT is measured RCS AT, OF.
AT0 is the indicated AT at RATED POWER, °F.
s is the Laplace transform operator, sec-1 T is the measured RCS average temperature (Tavg), OF.
T' is the nominal Tavg at RATED POWER, < 573.00F.
P is the measured pressurizer pressure,psig.
P' is the nominal RCS operating pressure > 2235 psig.
K, < 1.1425 K 2 > 0.01059 /OF K3 > 0.000765 /psig t >_ 29.7 seconds t2 < 4.4 seconds f(AI) >
0.0268 { (qt - qb)}, when (qt - qb) < -24.0% RATED POWER 0, when -24.0% RATED POWER _< (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 RATED POWER in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED POWER.
Page 3 of 7
Serial No.12-343 Docket No. 50-280 Attachment 3.3 Overpower AT (TS 2.3.A.2.e)
AT
- AT4K.
K, ( [--
K6 (T - T') - f(AI)]
1+ t3S]
Where:
AT is measured RCS AT, OF.
AT0 is the indicated AT at RATED POWER, °F.
s is the Laplace transform operator, sec1 T is the measured RCS average temperature (Tavg), OF.
T' is the nominal Tavg at RATED POWER, < 573.00F.
K4 < 1.0965 K5 > 0.0198 /'F for increasing Tavg K6 0 0.001074 /F for T > T'
> 0 /F for decreasing Tavg
> 0 for T <T' t3 > 9.0 seconds f(AI) = as defined above for OTAT 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.1(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 %Ak/k.
Page 4 of 7
Serial No.12-343 Docket No. 50-280 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) <
K(z) for P > 0.5
-P CFQ FQ(z) <
K(z) for P < 0.5 THERMAL POWER RATED POWER CFQ = 2.5 K(z) = 1.0 for all core heights, z 3.7.2 Nuclear Enthalpy Rise Hot Channel Factor - FAH(N)
FAH(N) < CFDH * (1 + PFDH(l - P)}
THERMAL POWER where: P =
RATED POWER CFDH= 1.56 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:
- Reactor Coolant System Tavg < 577.0 OF
" Pressurizer Pressure > 2205 psig
- Reactor Coolant System Total Flow Rate > 273,000 gpm (Tech Spec Limit) and > 276,000 gpm (COLR Limit)
Page 5 of 7
Serial No.12-343 Docket No. 50-280 Attachment Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 650 U-640 630 620 610 I-.
600 590
( 580 570 560 550 0
10 20 30 40 50 60 70 Percent of Rated Power 80 90 100 110 120 Page 6 of 7
Serial No.12-343 Docket No. 50-280 Attachment Figure A-2 Surry 1 Cycle 25 ROD GROUP INSERTION LIMITS cu
.2 0.
0.
4L 0
W-o.
230 220 210 200 190 180 170 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0
0 0.1 0.2 0.3 0.4 0.5 0.6 Fraction of Rated Power 0.7 0.8 0.9 1
Fully w/d position = 225 steps Page 7 of 7