ML13308B906
| ML13308B906 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/28/2013 |
| From: | Huber T Dominion, Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13308B906 (10) | |
Text
FDominion Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 October 28, 2013 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.
NL&OS/GDM:
Docket No.
License No.13-594 RO 50-280 DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT I CORE OPERATING LIMITS REPORT SURRY 1 CYCLE 26 PATTERN APX 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 26, Pattern APX, Revision 0.
If you have any questions or require additional information, Mr. Gary Miller at (804) 273-2771.
Sincerely, T. R. Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company please contact
Attachment:
Core Operating Limits Report, Surry 1 Cycle 26 Pattern APX Commitment Summary: There are no new commitments contained in this letter.
~~J[1<
Serial No.13-594 Docket No. 50-280 COLR S1C26 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-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 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.13-594 Docket No. 50-280 Attachment COLR-S 1 C26, Revision 0 CORE OPERATING LIMITS REPORT Surry 1 Cycle 26 Pattern APX October 2013 COLR-S1C26, Rev. 0 Page I of 8
Serial No.13-594 Docket No. 50-280 Attachment
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 26 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.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 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. 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.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 COLR-S 1 C26. Rev. 0 Page 2 of 8
Serial No.13-594 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 CHF 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 COLR-S 1 C26, Rev. 0 Page 3 of 8
Serial No.13-594 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 <ATo [K,-
K2 (1 + tis) (T-T) +K&
-P)
-f(AI)]
Where:
AT is measured RCS AT, °F.
AT 0 is the indicated AT at RATED POWER, °F.
s is the Laplace transform operator, sec 1 T is the measured RCS average temperature (Tavg), °F.
T' is the nominal Tavg at RATED POWER, < 573.00 F.
P is the measured pressurizer pressure, psig.
P' is the nominal RCS operating pressure > 2235 psig.
K1 < 1.1425 K2 > 0.01059 /IF K3 > 0.000765 /psig t >- 29.7 seconds t 2 < 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.
COLR-S 1 C26, Rev. 0 Page 4 of 8
Serial No.13-594 Docket No. 50-280 Attachment 3.3 Overpower AT (TS 2.3.A.2.e)
AT *ý AT0 [K 4 -K, ( 1 3
) T - K(T -T') - f(AI)]
Where:
AT is measured RCS AT, OF.
AT 0 is the indicated AT at RATED POWER, °F.
s is the Laplace transform operator, sec 1 T is the measured RCS average temperature (Tavg), °F.
T' is the nominal Tavg at RATED POWER, <573.0*F.
K4 < 1.0965 K5 > 0.0198 /°F for increasing Tavg K 6 > 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/nF 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.
COLR-S 1 C26, Rev. 0 Page 5 of 8
Serial No.13-594 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) <_--FQ-K(z) for P > 0.5
-P CFQ FQ(z) <_ -- Q-K(z) for P <_ 0.5 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 - FAH(N)
FAH(N) <_ CFDH
- fl + PFDH(1 - 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 IF
" Pressurizer Pressure > 2205 psig
" Reactor Coolant System Total Flow Rate > 273,000 gpm (Tech Spec Limit) and > 276,000 gpm (COLR Limit)
COLR-S1C26, Rev. 0 Page 6 of 8
Serial No.13-594 Docket No. 50-280 Attachment Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 650 p 640 ho
- 0) 630 620 (U
E 610 (u 600
> 590 580 570 560 550 0
10 20 30 40 50 60 70 Percent of Rated Power 80 90 100 110 120 COLR-S I C26, Rev. 0 Page 7 of 8
Serial No.13-594 Docket No. 50-280 Attachment Figure A-2 Surry 1 Cycle 26 Rod Group Insertion Limits
,n = 229 steps 230 220 210 200 190 180 170 160 150 140 C.
130 S120 S1.20 Vol 110 0
4-100 10 010 80 70 60 4 0 30 80 70 60 0
0.1 0.2 0.3 0.4 0.5 0.6 Fraction of Rated Thermal Power 0.7 0.8 0.9 1
COLR-S I C26, Rev. 0 Page 8 of 8