ML112360515
| ML112360515 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/24/2011 |
| From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 11-485 | |
| Download: ML112360515 (10) | |
Text
Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 2S£, Glen Allen, VA 23060 August 24, 2011 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.
NL&OS/GDM:
Docket No.
License No.11-485 RO 50-280 DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 1 CORE OPERATING LIMITS REPORT SURRY 1 CYCLE 24 PATTERN OWL 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 1 Cycle 24 Pattern OWL, 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,
~~
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 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.11-485 Docket No. 50-280 COLR-S1C24 Rev. 1 Page 2 of 2
COLR-SIC24, Revision 1 ENCLOSURE CORE OPERATING LIMITS REPORT Surry 1 Cycle 24 Pattern OWL Revision 1 August 2011 Serial No.11-485 Docket No. 50-280 Page 1 of8
Serial No.11-485 Docket No. 50-280 Enclosure
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 1 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 !1T TS 2.3.A.2.e - Overpower!1T 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.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.l 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.l, 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, 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.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor 3.
WCAP-I0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," (Westinghouse Proprietary), August 1985.
Methodology for:
TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor COLR-SIC24, Revision 1 Page 2 of8
Serial No.11-485 Docket No. 50-280 Enclosure 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),
June 1990.
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.l and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor 7.
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 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 ~T TS 2.3.A.2.e - Overpower ~T COLR-S1C24, Revision 1 Page 3 of8
Serial No.11-485 Docket No. 50-280 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, OF.
~To is the indicated ~T at RATED POWER, of.
s is the Laplace transform operator, sec-I.
T is the measured RCS average temperature (Tavg), of.
T' is the nominal Tavg at RATED POWER,:'S 573.0oF.
P is the measured pressurizer pressure, psig.
P' is the nominal RCS operating pressure ~ 2235 psig.
t[ ~ 29.7 seconds h :S 4.4 seconds K3 ~ 0.000765 /psig f(M) ~
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-S1C24, Revision 1 Page 4 of8
Serial No.11-485 Docket No. 50-280 Enclosure 3.3 Overpower AT (TS 2.3.A.2.e) l:1T :s; l:1To [K4 - Ks (
t 3s
) T - K6(T - T') - f(l:1I)]
1 + t 3s 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,:S 573.0°F.
~:s 1.0965 t32: 9.0 seconds Ks 2: 0.0198 lOP for increasing Tavg 2: 0 lOP for decreasing Tavg l<<) 2: 0.001074 lOP for T > T' 2: 0 for T :s T' f(M) = as defmed above for OTl:1T 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 pcmfP at 50 percent of RATED POWER and linearly decreasing to 0 pcmfP 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 %~k/k.
COLR-SIC24, Revision 1 Page 5 of8
Serial No.11-485 Docket No. 50-280 Enclosure 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) $; pK(z) for P > 0.5 CFQ FQ(z) $; o:sK(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!:J.H(N) $; CFDH * {1 + 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:S 577.0 of Pressurizer Pressure 2: 2205 psig Reactor Coolant System Total Flow Rate 2: 273,000 gpm (Tech Spec Limit) and 2: 276,000 gpm (COLR Limit)
COLR-SIC24, Revision 1 Page 6 of8
Serial No.11-485 Docket No. 50-280 Enclosure Figure A-1 REACTOR CORE THERMALAND HYDRAULIC SAFETY LIMITS THREE LOOP OPERATION, 100% FLOW 670.,..
- -..-.-r- _-.--_..,.- ---.---..--
640 t---t-----t---+--.....;p-........+/----+-----j--="..,.__:::::---+---+---+_-___1 650 660 r:::!!l!oo-.,F-;;;;;::::-t---t----t----t---t---t---t---t-----j---t---j
'"'"'"t;;,
'"c
~
620 t---l----=""""t'_==--+---t---="'!-.....=--+------1---+---+--""ood--~-+_-___1
~
'"E 610 t---l----+---+---+-----=~_=-+__--_l--~-
.......d_--_+_
{!!.
'"& 600
!t<<
~
590 +---t------+---+---t-----+---+------t---+---+-----l--"""---Pl.:----l 570 +---[----+---+---+---+_--+----+---+---+---+---+_-___1 560 550 +---[----+---+---+---+---+----+---+---+---+---+-----1 o
10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Power COLR-S 1C24, Revision 1 Page 7 of8
Serial No.11-485 Docket No. 50-280 Enclosure Figure A-2
/1 I
(0.4938, 230)
/ V
/
/
/
C-BANK (1.0,183)
~
~
/
/
/,
/,
/
V (0,151)
/
/,/
/
/
~/D-BANK
/
/,
/
/
/,/
/
/
V f- (0, 23)
SURRY UNIT 1 CYCLE 24 ROD GROUP INSERTION LIMITS Fullv wid position = 230 steps 230 220 210 200 190 180 170 160 150
't:lj 140 l/l Co
<Il 130 l/l
'*t r:
120 0
E l/l 110 0a..
Co 100
- l 0...
C) 90
't:l 0
D:::
80 70 60 50 40 30 20 10 o
0.0 0.1 0.2 0.3 0.4 0.5 0.6 Fraction of Rated Power 0.7 0.8 0.9 1.0 COLR-SIC24, Revision 1 Page 8 of8