ML18162A099

Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules - Editorial Correction

ML18162A099
Person / Time
Site:	Surry
Issue date:	06/05/2018
From:	Mark D. Sartain Dominion Energy Virginia, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
18-098A
Download: ML18162A099 (4)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 5, 2018 10 CFR 50 Appendix H U.S. Nuclear Regulatory Commission Serial No.: 18-098A Attention: Document Control Desk NRA/GDM: RO Washington, DC 20555-0001 Docket Nos.: 50-280/281 License Nos.: DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNITS 1 AND 2 REVISED REACTOR VESSEL MATERIALS SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES - EDITORIAL CORRECTION By letter dated July 28, 2017, Serial No.17-243, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17213A080), Dominion Energy Virginia submitted a request for NRG review and approval of proposed reactor vessel material surveillance capsule withdrawal schedules for Surry Power Station (Surry)

Units 1 and 2 in accordance with Title 10 of the Code of Federal Regulations (10 CFR)

Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements.

The proposed withdrawal schedules address revisions to the surveillance capsule withdrawal schedules approved for the 40 to 60-year period of extended operation (PEO).

Subsequent to that submittal, an editorial error was recently identified in the revi.sed Table 4.1-13, "Surveillance Capsule Withdrawal Schedule for Surry Unit 2."

Specifically, the existing Estimated Withdrawal EFPY/Year values provided for Capsules S and W1 in the table were inadvertently reversed. It should be noted this information is not being revised as part of the original request. The corrected revised Table 4.1-13 is provided in the attachment with the corrected values highlighted for easy reference.

Should you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.

Sincerely,

~*-

Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support Commitments made in this letter: None

Serial Number 18-098A Docket Nos. 50-280/281 Page 2 of 2

Attachment:

Corrected Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedule - UFSAR Table 4.1-13, Surry Power Station Unit 2 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 Gross NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. J. R. Hall NRC Senior Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B1A 11555 Rockville Pike Rockville, MD 20852-2738

Serial Number 18-098A Docket Nos. 50-280/281 Attachment CORRECTED REVISED REACTOR VESSEL MATERIALS SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE- UFSAR TABLE 4.1-13 SURRY POWER STATION UNIT 2 Virginia Electric and Power Company (Dominion Energy Virginia)

Serial Number 18-098A Docket Nos. 50-280/281 Table 4.1-13 SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULEa FOR SURRY UNIT 2 Estimated Estimated Capsule Insert Capsule Location Withdrawal Capsule Fluence Identification EFPY/Year (x 10 19)b EFPY/Year xe 285° 1.2/1975 NA 0.297 we 245° 3.8/1979 NA 0.636 ye 165° 8.7/1986 NA 1.89 y 295° 14.3/1995 NA 1.97 y 165° NA 14.3/1995 NA ye 165° 20.8/2002 NA 2.73 u 65° 27.9/2009 NA 3.49 u 285° NA 27.9/2009 NA ue 285° 49.0/2032 NA 7.26 T 55° 19.7/2002 NA 1.82 T 165° NA 19.7/2002 NA Tct 165° NA NA 6.65 (48.0 EFPY) 9.06 (60.0 EFPY) z 305° 13.7/1994 NA 1.34 z 245° NA 13.7/1994 NA zd 245° NA NA 5.39 (48.0 EFPY) 8.21 (68.0 EFPY) s 45 ° 15.0/199 NA 1.07 Wl 285° NA 10.9/1991 NA Wle 285° 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 withd rawn capsu les 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. Capsules T and Z are available to satisfy potential fluence monitoring requirements during the 20-year license renewal period . Future projected capsu le fluence values are related to asset management objectioves.

e. Master Integrated Reactor Vessel Materials Surveillance Program capsule.