ML110040077
| ML110040077 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/03/2011 |
| From: | Price J Virginia Electric & Power Co (VEPCO), Dominion |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 10-721 | |
| Download: ML110040077 (7) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 3, 2011 10 CFR 50 Appendix H U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
NL&OS/GDM Docket Nos.
License Nos.10-721 R2' 50-280/281 DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNITS 1 AND 2 REVISED REACTOR VESSEL MATERIALS SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By letter dated October 26, 2009 (Serial No.09-507), Dominion requested NRC review and approval of the proposed reactor vessel material surveillance capsule withdrawal schedules for Surry Units 1 and 2 in accordance with 10 CFR 50, Appendix H,Section III.B.3. The proposed schedules were developed to accommodate the 60-year license period for Surry Power Station Units 1 and 2 and to satisfy the requirements and guidance of ASTM E-185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," dated July 1, 1982.
Subsequently, the NRC requested additional information in support of their review of Dominion's October 26, 2009 submittal.
Dominion's response to the NRC's request is provided in the attachment.
If you have any further questions regarding this submittal, please contact Mr. Gary D. Miller at (804) 273-2771.
Sincerely,
~
J.
a Price Vic President - Nuclear Engineering Commitments made in this letter:
None.
Attachment:
Response to NRC Request for Additional Information, Revised Reactor Vessel Surveillance Capsule Withdrawal Schedules
cc:
U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station 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, Maryland 20852 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Serial Number 10-721 Docket Nos. 50-280/281 Page 2 of2
Serial Number 10-721 Docket Nos. 50-280/281 Attachment Response to NRC Request for Additional Information Revised Reactor Vessel Surveillance Capsule Withdrawal Schedules Virginia Electric and Power Company (Dominion)
Surry Power Station Units 1 and 2
Serial Number 10-721 Docket Nos. 50-280/281 Attachment Response to NRC Request for Additional Information Surveillance Capsule Withdrawal Schedule Surry Power Station Units 1 and 2 NRC Question No.1 After comparing the 10-16-09 submittal to an earlier submittal, ML0223902830, ther also show capsule Vat Unit 1 withdrawn in 1986 (6.0 EFPY) at fluence of 1.94 x 101.
The EFPY seems wrong, they only gained 3 EFPY between 1978 and 1986?
Dominion Response The Effective Full Power Years (EFPY) values in question listed in Table 4.1-12 were historical values from previously submitted reports.
As part of performing fluence analyses for license renewal, revised EFPY values were calculated based on the most recent compilation of historical fuel management data.
The EFPY value for each removed capsule is presented below. To date, four (4) capsules (T, W, V, and X) have been removed from Surry Unit 1, and four capsules (X, W, V, and Y) have been removed from Surry Unit 2.
SPS Unit 1 Capsule Identification EFPY Capsule Fluence T
1.1 2.81E18 n/cm2 W
3.5 4.31E18 n/cm2 V
8.2 1.94E19 n/cm2 X
16.3 1.60E19 n/cm2 SPS Unit 2 Capsule Identification EFPY Capsule Fluence X
1.2 2.97E18 n/cm2 W
3.8 6.36E18 n/cm2 V
8.7 1.89E19 n/cm2 Y
20.8 2.73E19 n/cm2 Page 1 of 4
Serial Number 10-721 Docket Nos. 50-280/281 Attachment The EFPYs noted above and the capsule fluence value for Surry Unit 2 Capsule Y differ from the values in Tables 4.1-12 and 4.1-13 included in Dominion's October 26,2009 letter (Serial No.09-507) as these were projected estimated values prior to the removal and analysis of the surveillance capsules.
The projected EFPY values have been updated, and the Unit 2 Capsule Y fluence value has been changed to reflect the actual value at the time of removal and analysis.
These changes are reflected in the respective tables and are attached.
NRC Question No.2 In addition, the earlier submittal shows capsule X at Unit 1 as being withdrawn in 1997, 15.8 EFPY, but with a f1uence of 2.42 x 1019 instead of 15.8 EFPY and f1uence of 1.60 x 1019 that is shown in Oct. 26, 2009 submittal.
Dominion Response Per BAW-2324, "Analysis of Capsule X, Virginia Power Surry Unit No.1, Reactor Vessel Material Surveillance Program," dated April 1998, the fluence on Capsule X at Unit 1 (when withdrawn and tested) was 1.599E19 n/cm2, which rounds to 1.60E19 n/cm2). The UFSAR and earlier correspondence included the projected fluence value of 2.42E19 n/cm2 prior to the withdrawal and testing of Capsule X.
Page 2 of4
TABLE 4.1-12 Surveillance Capsule Withdrawal Schedules for Surry Unit 1 Serial Number 10-721 Docket Nos. 50-280/281 Attachment Capsule Capsule Withdrawal Insert Est. Capsule Ident.
Location EFPYlYear EFPYlYear Fluence (,x1 019) b TC 2850 1.1/1974 NA 0.281 W C 55 0
3.5/1978 NA 0.431 V C 165 0
8.2/1986 NA 1.94 X
65 0
13.3/1994 NA 1.28 X
165 0
NA 13.3/1994 NA XC 165 0
16.3/1997 NA 1.60 Z
245 0
13.3/1994 NA 2.11 Z
285 0
NA 13.3/1994 NA ZC 285 0
43.2/2025 NA 6.31 U
45 0
13.3/1994 NA 0.95 U
65 0
NA 13.3/1994 NA U d 65 0
NA NA 4.58 (48.0 EFPY)
S 2950 43.2/2025 NA 5.02 S
285 0
NA 43.2/2025 NA Sd 285 0
NA NA 6.05 (48.0 EFPY)
Y 305 0
15.8/1997 NA 1.52 Y
165 0
NA 15.8/1997 NA y d 165 0
NA NA 6.34 (48.0 EFPY)
- a. Withdrawal schedule meets requirements of ASTM E 185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, dated July 1, 1982.
- b. 48.0 EFPY corresponds to the estimated cumulative core burnup at the end of the 60-year license period. Fluence values for withdrawn capsules are obtained from capsule test reports.
- c. These capsules are required to satisfy the requirements of ASTM E 185-82 during the license period.
- d. Standby Capsules S, U, and Yare available to satisfy potential fluence monitoring requirements during the 20-year license renewal period.
Page 3 of4
Serial Number 10-721 Docket Nos. 50-280/281 Attachment TABLE 4.1-13 Surveillance Capsule Withdrawal Schedule3 for Surry Unit 2 Capsule Capsule Withdrawal Insert Est. Capsule Ident.
Location EFPYIYear EFPYIYear Fluence (X1 019) b XC 285 0
1.2/1975 NA 0.297 We 245 0
3.8/1979 NA 0.636 VC 165 0
8.7/1986 NA 1.89 Y
295 0
14.3/1995 NA 1.97 Y
165 0
NA 14.3/1995 NA y C 165 0
20.8/2002 NA 2.73 U
65 0
27.9/2009 NA 3.49 U
285 0
NA 27.9/2009 NA U C 285 0
45.0/2027 NA 5.95 T
55 0
19.7/2002 NA 1.82 T
165 0
NA 19.7/2002 NA T d 165 0
NA NA 5.88 (48.0 EFPY)
Z 305 0
13.7/1994 NA 1.34 Z
245 0
NA 13.7/1994 NA Z
245 0
45.0/2027 NA 4.48 Z
285 0
NA 45.0/2027 NA zd 285 0
NA NA 5.09 (48.0 EFPY)
S 45 0
15.0/1996 NA 1.07 W1 285 0
NA 10.9/1991 NA W1 e 285 0
16.4/1997 NA 0.690
- a. Withdrawal schedule meets requirements of ASTM E 185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, dated July 1, 1982.
- b. 48.0 EFPY corresponds to the estimated cumulative core burnup at the end of the 60-year license period. Fluence values for withdrawn capsules are obtained from capsule test reports.
c.
These capsules are required to satisfy the requirements of ASTM E 185-82 during the license period.
d.
Standby capsules T and Z are available to satisfy potential fluence monitoring requirements during the 20-year license renewal period.
e.
Master Integrated Reactor Vessel Materials Surveillance Program capsule Page 4 of4