ML111040421
| ML111040421 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/14/2011 |
| From: | Funderburk C Dominion, Virginia Electric & Power Co (VEPCO), Dominion Resources Services |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 11-196 | |
| Download: ML111040421 (10) | |
Text
Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 25E, Glen Allen, VA 23060 April 14,2011 Dominion United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 CYCLE 24 CORE OPERATING LIMITS REPORT, REVISION 0 Serial No.
NL&OS/vlh Docket No.
License No.11-196 RO 50-281 DPR-37 Pursuant to Surry Technical Specification (TS) 6.2.C, enclosed is a copy of Dominion's Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 24 Pattern
- UPG, Revision O.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Sincerely,
~
C. L. Funderburk, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitment Summary: There are no new commitments as a result of 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. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J. S. Wiebe NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No.11-196 Docket No. 50-281 COLR-S2C24 Rev. 0 Page 2 of 2
CORE OPERATING LIMITS REPORT Surry 2 Cycle 24 Pattern UPG Revision 0 March 2011 Virginia Electric and Power Company Surry Power Station Unit 2 Serial No.11-196 Docket No. 50-281
Serial No.11-196 Docket No. 50-281
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 24 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 ilT TS 2.3.A.2.e - Overpower ilT 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.1.a, TS 3.12.A.2.a, 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.1(b) - Control Bank Insertion Limit TS 3.12.A.1.a, TS 3.12.A.2.a 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-S2C24, Rev. 0 Page 1 of 7
Serial No.11-196 Docket No. 50-281 4.
WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code,"
(Westinghouse Proprietary), August 1985.
Methodology for:
TS 3.l2.B.1 and TS 3.l2.B.2 - Heat Flux Hot Channel Factor 5.
WCAP-1261O-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-1261O-P-A and CENPD-404-P-A, Addendum I-A, "Optimized ZIRLO,"
(Westinghouse Proprietary), July 2006.
Methodology for:
TS 3.l2.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.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor 9.
DOM-NAF-2-A, 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.l2.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 LlT TS 2.3.A.2.e - Overpower LlT COLR-S2C24, Rev. 0 Page 2 of7
Serial No.11-196 Docket No. 50-281 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.
3.1 Safety Limit, Reactor Core (TS 2.1) 3.1.1 The Reactor Core Safety Limits are presented in Figure A-I.
3.2 Overtemperature AT (TS 2.3.A.2.d)
Where:
L1T is measured RCS L1T, of.
L1Tois the indicated L1T at RATED POWER, of.
s is the Laplace transform operator, sec':
T is the measured RCS average temperature (Tavg), of.
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 ti > 29.7 seconds K2 :::: 0.01059/oF t2:S 4.4 seconds K3 2: 0.000765 /psig f(t.I) 2:
0.0268 { (qt-qb)}, when (qt-qb) < -24.0% RATED POWER 0, when -24.0% RATED POWER:S (qt - qb):S 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-S2C24, Rev. 0 Page 3 of7
Serial No.11-196 Docket No. 50-281 3.3 Overpower AT (TS 2.3.A.2.e)
Where:
~T is measuredRCS ~T, OF.
~To is the indicated ~T at RATED POWER, oF.
s is the Laplace transform operator, sec":
T is the measuredRCS averagetemperature(Tavg), OF.
T' is the nominalTavg at RATED POWER,::; 573.0°F.
~:S 1.0965 t3 ~ 9.0 seconds x, ~ 0.0198 fOP for increasing Tavg
~ 0 lOP for decreasing Tavg
!< T'
~ 0 forT :ST' f(M) =as defined above for OTLlT 3.4 Moderator Temperature Coefficient (TS 3.1.E) 3.4.1 The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcm/°P at less than 50 percent ofRATED POWER, and
+6.0 pcm/°P at 50 percent of RATED POWER and linearly decreasing to 0 pcm/°P at RATED POWER 3.5 Control Bank Insertion Limits (TS 3.12.A.1, TS 3.12.A.2 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 and TS 3.12.G) 3.6.1 Whenever the reactor is subcritical the shutdown margin (SDM) shall be ~ 1.77 %Llk/k.
COLR-S2C24, Rev. 0 Page 4 of7
Serial No.11-196 Docket No. 50-281 3.7 Power Distribution Limits (TS 3.12.B.1 and TS 3.12.B.2) 3.7.1 3.7.1.1 3.7.1.2 3.7.2 3.7.2.1 3.7.2.2 Heat Flux Hot Channel Factor - FQ(z)
CFQ FQ(z) ~ pK(z) for P > 0.5 CFQ FQ(z) ~ o:sK(z) for P s 0.5 THERMAL POWER where: P =
RATED POWER CFQ=2.5 K(z) = 1.0 for all core heights, z Nuclear Enthalpy Rise Hot Channel Factor - F~H(N)
F~H(N) ~ CFDH * (l +PFDH(l-P)}
THERMAL POWER where: P =
RATED POWER CFDH= 1.56 PFDH=0.3 3.8 DNE Parameters (TS 3.12.F and TS Table 4.1-2A) 3.8.1 Departure from Nucleate Boiling (DNB) Parameters shall be maintained within their limits during POWER OPERATION:
Reactor Coolant System Tavg:S 577.0 OF Pressurizer Pressure 2: 2205 psig Reactor Coolant System Total Flow 2: 273,000 gpm (Tech Spec Limit) and 2: 276,000 gpm (COLR Limit)
COLR-S2C24, Rev. 0 Page 5 of7
670 660 650 Ll.
VI 3l 640 110
~ 630
<IJ..
- J 10 620
<IJE610
<IJ....
~ 600 III
~ 590
<t Cii
~ 580
<IJ>
570 560 550 Serial No.11-196 Docket No. 50-281 Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW I,--
I 238 i___........
22::\\ n~i___
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198, psig
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10 20 30 40 50 60 70 80 Percent of Rated Power 90 100 110 120 COLR-S2C24, Rev. 0 Page 6 of7
Figure A*2 Surry 2 Cycle 24 ROD GROUP INSERTION LIMITS Fully wid position = 225 steps Serial No.11-196 Docket No. 50-281 230 220 210 200 190 180 170 160 150 "Cl' 140 VIc..
OJ 130 VI r::.'
120 0
~
"Vi 110 0
Q.
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- J 100 0...
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80 70 60 50 40 30 20 10 0
(0.4625, 225)
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COLR-S2C24, Rev. 0 Fraction of Rated Power Page 7 of7