ML20258A251

ASME Section XI Inservice Inspection Program Supplement to Relief Request for Limited Coverage Examinations Performed in the Third Period of the Third 10-Year Inspection Interval

ML20258A251
Person / Time
Site:	Millstone
Issue date:	09/10/2020
From:	Mark D. Sartain Dominion Energy Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
20-145A
Download: ML20258A251 (2)

Text

Domin io n Energy Nu clear Co nn ecti cut, In c.

500 0 Domin io n Boul eva rd, Gl en All en, VA 23060 Dom ini onE nergy.com ij; Dominion

--' Energy September 10, 2020 U. S. Nuclear Regulatory Commission Serial No. 20-145A Attention: Document Control Desk NRA/SS RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 ASM E SECTION XI INSERVICE INSPECTION PROGRAM SUPPLEMENT TO RELIEF REQU EST FOR LIMITED COVERAGE EXAMINATIONS PERFORMED IN THE THIRD PERIOD OF THE THIRD 10-YEAR INSPECTION INTERVAL By letter dated June 17, 2020 (ADAMS Accession No. ML20169A512), Dominion Energy Nuclear Connecticut, Inc. (DENC) submitted relief requests for the limited coverage examinations performed in the third period of the third 10-year inservice inspection interval at Millstone Power Station Unit 3.

This supplement corrects an American Society of Mechanical Engineers (ASME) Code reference in Attachment 3 (Relief Request IR-3-42) of the June 17, 2020 submittal.

Specifically, in Attachment 3 for Relief Request IR-3-42, DENC stated that Weld 03-073-008, an Examination Category C-A Pressure Retaining Weld in Pressure Vessels less than 2 inches in thickness, was examined using equipment and procedures written in accordance with ASME Section XI, Appendix I and Section V, Article 4. This code reference is incorrect since it applies to vessel welds greater than 2 inches in thickness . For vessel welds not greater than 2 inches in thickness, ASME Code,Section XI, Article 1-2210 states that ultrasonic examination shall be conducted in accordance with Appendix Ill, as supplemented by Table 1-2000-1. DENC's review of the examination records for Weld 03-073-008 , confirmed that the weld was correctly examined in accordance with ASME Section XI, Appendix Ill, as supplemented by Table 1-2000-1.

Should you have any questions regarding this submittal, please contact Shayan Sinha at (804) 273-4687.

Sincerely, Mark D. Sartain Vice President - Nuclear Engineering & Fleet Support

Attachment:

None Commitments made in this letter: None

Serial No: 20-145A Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd , Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station