ML15222A542

Virgil C. Summer Nuclear Station, Unit 1 - Alternative Request Regarding Root Mean Square Depth Sizing Requirements (TAC No. MF5612)

ML15222A542
Person / Time
Site:	Summer
Issue date:	09/01/2015
From:	Pascarelli R J Plant Licensing Branch II
To:	Gatlin T D South Carolina Electric & Gas Co
Shawn Williams, 415-1009
References
TAC MF5612
Download: ML15222A542 (8)

Text

September 1, 2015

Mr. Thomas Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065

SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - ALTERNATIVE REQUEST REGARDING ROOT MEAN SQUARE DEPTH SIZING REQUIREMENTS (TAC NO. MF5612)

Dear Mr. Gatlin:

By letter dated January 20, 2015, as supplemented by letter dated June 30, 2015, South Carolina Electric and Gas Company (SCE&G, the licensee) requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code). SCG&E proposed to use an alternative to the to the flaw depth sizing root mean square error (RMSE) criteria in Appendix VIII,Section XI of the ASME Code at the Virgil C. Summer Nuclear Station (VCSNS), Unit 1. The application was submitted pursuant to Title 10 of the Code of Federal Regulations, 50.55a(g)(5)(iii). The licensee requested relief and to use alternative requirements (if necessary), for inservice inspection on the basis that the ASME Code requirement is impractical. The U. S. Nuclear Regulatory Commission staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that SCE&G has adequately addressed all of the regulatory requirements set forth in 50.55a(g)(6)(i), and therefore authorizes the proposed alternative. If you have any questions, please contact the Project Manager, Shawn Williams, at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.

Sincerely,/RA/ Robert J. Pascarelli, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395

Enclosure:

Safety Evaluation cc w/encl: Distribution via Listserv