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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA | {{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 12, 2009 U. S. Nuclear Regulatory Commission Serial No. 09-716 Attention: Document Control Desk NLOSlvlh Washington, D. C. 20555-0001 Docket No. 50-281 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) | ||
Sincerely,C.L.Funderburk, | SURRY POWER STATION UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 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 23 Pattern BOA, Revision O. | ||
cc:U.S.Nuclear Regulatory Commission Region" | If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771. | ||
Sincerely, | |||
/--~-7' | |||
(~~.)[- | |||
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. | |||
Serial No. 09-716 Cycle 23 Core Operating Limits Report Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Region" Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W. | |||
Suite 23T85 Atlanta, GA 30303-8931 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mai I Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mai I Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station | |||
COLR-S2C23, Revision 0 CORE OPERATING LIMITS REPORT Surry 2 Cycle 23 Pattern BOA COLR-S2C23, Rev. 0 Page 1 of 6 | |||
==1.0 INTRODUCTION== | ==1.0 INTRODUCTION== | ||
This Core Operating Limits Report(COLR) | This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 23 has been prepared in accordance with the requirements of Technical Specification 6.2.C. | ||
-Control | The Technical Specifications affected by this report are: | ||
TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.l, TS 3.12.A.2, TS 3.12.AJ, and TS 3.12.C.3.b.1.b - Control Bank Insertion Limits TS 3.12.B.l and TS 3.12.B.2 - Power Distribution Limits TS 3.12.A.l.a, TS 3.12.A.2.a, and TS 3.12.0 - Shutdown Margin | |||
==2.0 REFERENCES== | ==2.0 REFERENCES== | ||
: 1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003 (Methodology for TS 3.l.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.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor and Nuclear Enthalpy Rise Hot Channel Factor; TS 3.12.A.1.a, TS 3.12.A.2.a, and TS 3.12.0 - Shutdown Margin) 2a. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," (Westinghouse Proprietary), January 2005 (Methodology forTS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2b. WCAP-I0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 (WestinghouseProprietary) | |||
(Methodology for TS 3.l2.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2c. WCAP-I0079-P-A, "NOTRUMP, A Nodal Transient Small Break and Oeneral Network Code," August 1985 (Westinghouse Proprietary) | |||
(Methodology for TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2d. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," June 1990 (Westinghouse Proprietary) | |||
(Methodology forTS 3.12.B.l and TS 3.l2.B.2 - Heat Flux Hot Channel Factor) 3a. 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) 3b. VEP-NE-3-A, Rev. 0, "Qualification of the WRB-l CHF Correlation in the Virginia Power COBRA Code," July 1990 (Methodology for TS 3.12.B.I and TS 3.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor) | |||
COLR-S2C23, Rev. ° Page 2 of 6 | |||
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 Moderator Temperature Coefficient (TS 3.I.E) 3.1.1 The Moderator Temperature Coefficient (MTC) limits are: | |||
+6.0 pcm/F at less than 50 percent ofRATED POWER, or | |||
+6.0 pcm/F at 50 percent of RATED POWER and linearly decreasing to a pcm/F at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.I, TS 3.I2.A.2, and TS 3.12.C.3.b.1.b) 3.2.1 The control rod banks shall be limited in physical insertion as shown in Figure A-I. | |||
3.2.2 The rod insertion limit for the A and B control banks is the fully withdrawn position as shown on Figure A-I. | |||
3.2.3 The rod insertion limit for the A and B shutdown banks is the fully withdrawn position as shown on Figure A-I. | |||
3.3 Shutdown Margin (TS 3.I2.A.1.a, TS 3.I2.A.2.a, and TS 3.I2.G) 3.3.1 Whenever the reactor is subcritical the shutdown margin (SDM) shall be 21.77 %&Ik. | |||
COLR-S2C23, Rev. 0 Page 3 of 6 | |||
3.4 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B.l) | |||
CFQ FQ(z) S --K(z) for P> 0.5 P | |||
CFQ FQ(z) S --K(z) for P S 0.5 | |||
===0.5 where=== | |||
P = Thermal Power Rated Power 3.4.1 CFQ=2.32 3.4.2 K(z) is provided in Figure A-2. | |||
3.5 Nuclear Enthalpy Rise Hot Channel Factor-FMI(N) (TS 3.12.B.l) | |||
F!ili(N) S CFDHx{I+PFDH(I-P)} | |||
Thermal Power were: | |||
h P =- ---- | |||
Rated Power 3.5.1 CFDH = 1.56 for Surry Improved Fuel (SIP) 3.5.2 PFDH= 0.3 COLR-S2C23, Rev. 0 Page 4 of 6 | |||
Figure A-I SURRY UNIT 2 CYCLE 23 ROD GROUP INSERTION LIMITS Fully wId position = 230 steps 230 | |||
/(1 1 (0.4938, 230) 220 I V 210 / | |||
200 / | |||
190 / | |||
/ C-BANK (1.0,183) | |||
~ ~ | |||
180 170 iii"'" | |||
/ / | |||
/ /" | |||
160 150 / ! | |||
i | |||
! | |||
/ | |||
:E | |||
~ 140 (0,151) | |||
/ | |||
III 0. | |||
/ | |||
.2! 130 I ./ | |||
III | |||
'It: | |||
! | |||
/ | |||
..c:: 120 o | |||
'iii 110 o | |||
/ | |||
a.. I ~ | |||
/ D-BANK g-100 C> | |||
e 90 / | |||
:§... 80 | |||
/" | |||
70 | |||
/ | |||
60 | |||
/ | |||
/' | |||
50 ./ I 40 / | |||
30 | |||
/ | |||
V 20 -(0,23) 10 o | |||
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power COLR-S2C23, Rev. 0 Page 5 of 6 | |||
Figure A-2 K(Z) | |||
* Normalized FQ as a Function of Core Height 1.2 1.1 | |||
-- | |||
(6, 1.0) 1.0 | |||
- r--- r---- r--- ~ | |||
0.9 (12,0.925) 0.8 I | |||
N I Ci u, | |||
0.7 | |||
!, | |||
eLLI I N | |||
~ 0.6 | |||
:E | |||
~ | |||
0 z 0.5 s | |||
I 0.4 0.3 0.2 0.1 0.0 I o 1 2 3 4 5 6 7 8 9 10 11 12 13 CORE HEIGHT (FT) | |||
COLR-S2C23, Rev. 0 Page 6 of 6}} |
Revision as of 01:32, 14 November 2019
ML093170022 | |
Person / Time | |
---|---|
Site: | Surry ![]() |
Issue date: | 11/12/2009 |
From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
09-716 | |
Download: ML093170022 (8) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 12, 2009 U. S. Nuclear Regulatory Commission Serial No.09-716 Attention: Document Control Desk NLOSlvlh Washington, D. C. 20555-0001 Docket No. 50-281 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 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 23 Pattern BOA, Revision O.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Sincerely,
/--~-7'
(~~.)[-
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.
Serial No.09-716 Cycle 23 Core Operating Limits Report Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Region" Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W.
Suite 23T85 Atlanta, GA 30303-8931 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mai I Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mai I Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station
COLR-S2C23, Revision 0 CORE OPERATING LIMITS REPORT Surry 2 Cycle 23 Pattern BOA COLR-S2C23, Rev. 0 Page 1 of 6
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) for Surry Unit 2 Cycle 23 has been prepared in accordance with the requirements of Technical Specification 6.2.C.
The Technical Specifications affected by this report are:
TS 3.1.E - Moderator Temperature Coefficient TS 3.12.A.l, TS 3.12.A.2, TS 3.12.AJ, and TS 3.12.C.3.b.1.b - Control Bank Insertion Limits TS 3.12.B.l and TS 3.12.B.2 - Power Distribution Limits TS 3.12.A.l.a, TS 3.12.A.2.a, and TS 3.12.0 - Shutdown Margin
2.0 REFERENCES
- 1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003 (Methodology for TS 3.l.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.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor and Nuclear Enthalpy Rise Hot Channel Factor; TS 3.12.A.1.a, TS 3.12.A.2.a, and TS 3.12.0 - Shutdown Margin) 2a. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," (Westinghouse Proprietary), January 2005 (Methodology forTS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2b. WCAP-I0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 (WestinghouseProprietary)
(Methodology for TS 3.l2.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2c. WCAP-I0079-P-A, "NOTRUMP, A Nodal Transient Small Break and Oeneral Network Code," August 1985 (Westinghouse Proprietary)
(Methodology for TS 3.12.B.l and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2d. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," June 1990 (Westinghouse Proprietary)
(Methodology forTS 3.12.B.l and TS 3.l2.B.2 - Heat Flux Hot Channel Factor) 3a. 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) 3b. VEP-NE-3-A, Rev. 0, "Qualification of the WRB-l CHF Correlation in the Virginia Power COBRA Code," July 1990 (Methodology for TS 3.12.B.I and TS 3.l2.B.2 - Nuclear Enthalpy Rise Hot Channel Factor)
COLR-S2C23, Rev. ° Page 2 of 6
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 Moderator Temperature Coefficient (TS 3.I.E) 3.1.1 The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcm/F at less than 50 percent ofRATED POWER, or
+6.0 pcm/F at 50 percent of RATED POWER and linearly decreasing to a pcm/F at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.I, TS 3.I2.A.2, and TS 3.12.C.3.b.1.b) 3.2.1 The control rod banks shall be limited in physical insertion as shown in Figure A-I.
3.2.2 The rod insertion limit for the A and B control banks is the fully withdrawn position as shown on Figure A-I.
3.2.3 The rod insertion limit for the A and B shutdown banks is the fully withdrawn position as shown on Figure A-I.
3.3 Shutdown Margin (TS 3.I2.A.1.a, TS 3.I2.A.2.a, and TS 3.I2.G) 3.3.1 Whenever the reactor is subcritical the shutdown margin (SDM) shall be 21.77 %&Ik.
COLR-S2C23, Rev. 0 Page 3 of 6
3.4 Heat Flux Hot Channel Factor-FQ(z) (TS 3.12.B.l)
CFQ FQ(z) S --K(z) for P> 0.5 P
CFQ FQ(z) S --K(z) for P S 0.5
0.5 where
P = Thermal Power Rated Power 3.4.1 CFQ=2.32 3.4.2 K(z) is provided in Figure A-2.
3.5 Nuclear Enthalpy Rise Hot Channel Factor-FMI(N) (TS 3.12.B.l)
F!ili(N) S CFDHx{I+PFDH(I-P)}
Thermal Power were:
h P =- ----
Rated Power 3.5.1 CFDH = 1.56 for Surry Improved Fuel (SIP) 3.5.2 PFDH= 0.3 COLR-S2C23, Rev. 0 Page 4 of 6
Figure A-I SURRY UNIT 2 CYCLE 23 ROD GROUP INSERTION LIMITS Fully wId position = 230 steps 230
/(1 1 (0.4938, 230) 220 I V 210 /
200 /
190 /
/ C-BANK (1.0,183)
~ ~
180 170 iii"'"
/ /
/ /"
160 150 / !
i
!
/
- E
~ 140 (0,151)
/
III 0.
/
.2! 130 I ./
III
'It:
!
/
..c:: 120 o
'iii 110 o
/
a.. I ~
/ D-BANK g-100 C>
e 90 /
- §... 80
/"
70
/
60
/
/'
50 ./ I 40 /
30
/
V 20 -(0,23) 10 o
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power COLR-S2C23, Rev. 0 Page 5 of 6
Figure A-2 K(Z)
- Normalized FQ as a Function of Core Height 1.2 1.1
--
(6, 1.0) 1.0
- r--- r---- r--- ~
0.9 (12,0.925) 0.8 I
N I Ci u,
0.7
!,
eLLI I N
~ 0.6
- E
~
0 z 0.5 s
I 0.4 0.3 0.2 0.1 0.0 I o 1 2 3 4 5 6 7 8 9 10 11 12 13 CORE HEIGHT (FT)
COLR-S2C23, Rev. 0 Page 6 of 6