ML112360580
| ML112360580 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/24/2011 |
| From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 11-486 | |
| Download: ML112360580 (10) | |
Text
Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 August 24, 2011 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.11-486 NL&OS/GDM: RO Docket No.
50-281 License No.
DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT SURRY 2 CYCLE 24 PATTERN UPG REVISION 1 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 1.
The revision incorporates changes associated with the recently approved Surry Units 1 and 2 Technical Specifications (TS) Amendments 275/275 that relocate the Shutdown Margin (SDM) value in TS 3.12 and its basis from the TS to the COLR. Also, several editorial changes were made to improve readability.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Sincerely,
~--
~tr~n~rburk, 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 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 R. E. Martin 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.11-486 Docket No. 50-281 COLR-S2C24 Rev. 1 Page 2 of 2
COLR-S2C24, Revision 1 ENCLOSURE CORE OPERATING LIMITS REPORT Surry 2 Cycle 24 Pattern UPG Revision 1 August 2011 Serial No.11-486 Docket No. 50-281 Page 1 of8
Serial No.11-486 Docket No. 50-281 Enclosure
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 I1T TS 2.3.A.2.e - Overpower 11T 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, 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.1(b) - Control Bank Insertion Limit-TS 3.12.A.La, TS 3.12.A.2.a, TS 3.12.A.3.c and TS 3.12.G-Shutdown Margin I
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.
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, Revision 1 Page 2 of8
Serial No.11-486 Docket No. 50-281 Enclosure 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.l 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.l2.B.I and TS 3.12.B.2 - Heat Flux Hot Channel Factor 6.
WCAP-12610-P-A and CENPD-404-P-A, Addendum I-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-I 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-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 3.12.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 ~T TS 2.3.A.2.e - Overpower ~T COLR-S2C24, Revision I Page 3 of8
Serial No.11-486 Docket No. 50-281 Enclosure 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)
The Reactor Core Safety Limits are presented in Figure A-I.
3.2 Overtemperature AT (TS 2.3.A.2.d)
Where:
~T is measured RCS ~T, 0p.
~To is the indicated ~T at RATED POWER, 0p.
s is the Laplace transform operator, sec-I.
T is 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 2: 2235 psig.
tl2: 29.7 seconds K22: 0.01059 lOP t2:S 4.4 seconds K3 2: 0.000765 Ipsig f(M) 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 ofthe core, respectively, and qt + qb is the total THERMAL POWER in percent RATED POWER.
COLR-S2C24, Revision 1 Page 4 of8
Serial No.11-486 Docket No. 50-281 Enclosure 3.3 Overpower AT (TS 2.3.A.2.e) tJ.T :::; tJ.To[K4 - Ks (1::3J T - K6(T - T') - [(tJ.I)]
Where:
~T is measured RCS ~T, 0p.
~To is the indicated ~T at RATED POWER, 0p.
s is the Laplace transfonn operator, sec-I.
T is the measured RCS average temperature (Tavg), 0p.
T' is the nominal Tavg at RATED POWER,:::; 573.0°F.
~:s 1.0965 t32: 9.0 seconds Ks 2: 0.0198 lOP for increasing Tavg 2: 0 lOP for decreasing Tavg Ko 2: 0.001074;oP for T > T' 2: 0 for T :s T' f(M) = as defined above for OTb.T 3.4 Moderator Temperature Coefficient (TS 3.1.E)
The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcmfP at less than 50 percent ofRATED POWER, and
+6.0 pcml°P at 50 percent of RATED POWER and linearly decreasing to 0 pcml°P at RATED POWER 3.5 Control Bank Insertion Limits (TS 3.12.A.l, 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)
Whenever the reactor is subcritical the shutdown margin (SDM) shall be 2: 1.77 %b.k/k.
COLR-S2C24, Revision 1 Page 5 of8
Serial No.11-486 Docket No. 50-281 Enclosure 3.7 Power Distribution Limits (TS 3.12.B.I and TS 3.12.B.2) 3.7.1 Heat Flux Hot Channel Factor - FQ(z)
CFQ FQ(z) ~ pK(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= 1.56 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: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, Revision I Page 6 of8
Serial No.11-486 Docket No. 50-281 Enclosure Figure A-1 REACTOR CORE SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670 660 650 III al 640 b.O
~ 630 QI...
.a 620 ra...
QI
~ 610
~
~ 600 ra
~ 590
<t Qj
~ 580 QI>
570 560 550
~
238 ; psig io-....
223~p-Sip" r----.
r---..~
r---....-...
r---..
-r---..
198f psig
- i"-.~
r---...
r---
io--....._r----L~
~~"
r----.....
- r--...
- '"""""'-","~
j"--..... ~ -----.
~"!lo.. "
'k""
a 10 20 30 40 50 60 70 80 Percent of Rated Power 90 100 110 120 COLR-S2C24, Revision 1 Page 7 of8
Figure A-2 Surry 2 Cycle 24 ROD GROUP INSERTION LIMITS Fully wid position =225 steps Serial No.11-486 Docket No. 50-281 Enclosure 230 220 210 200 190 180 170 160
"'C 150 140 IIIc..
Qj...
130 III
- It c'
120 0+:
'iii 110 0
Q.
c..
100 0...
C) 90
"'C 0a:
80 70 60 50 40 30 20 10 0
/'
(0.4625,225)
./V
/
/
)/
C-BANK (1.0,183)
/
/
/ "
/,
/'
(0,151)
/'
/
./V
/
/
..,/
/
D-BANK
/,
/'
/
./V
/
/
/' (0,23) o 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
COLR-S2C24, Revision 1 Fraction of Rated Power Page 8 of8