ML13177A099

Acceptance of Requested Licensing Action Request Relief from ASME Code Requirements in VCSNS 4th Ten Year Inservice Inspection Interval (TAC Nos. MF1900, MF1901, and MF1902) (RC-13-0069)

ML13177A099
Person / Time
Site:	Summer
Issue date:	07/10/2013
From:	Ellen Brown Plant Licensing Branch II
To:	Gatlin T South Carolina Electric & Gas Co
Brown E, NRR/DORL,LPLII-1, 415-2315
References
RC-13-0069, TAC MF1900, TAC MF1901, TAC MF1902
Download: ML13177A099 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 10, 2013 Mr. Thomas D. Gatlin 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 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REQUEST RELIEF FROM ASIVIE CODE REQUIREMENTS IN VCSNS 4 TH TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NOS. MF1900, MF1901, AND MF1902) (RC-13-0069)

Dear Mr. Gatlin:

By letter dated May 16, 2013, South Carolina Electric & Gas Company (SCE&G) submitted three relief requests for Virgil C. Summer Nuclear Station, Unit 1 (VCSNS). The proposed relief requests would authorize relief from American Society of Mechanical Engineers (ASIVIE) Code for Operation and Maintenance of Nuclear Power Plants, 2004 edition with addenda through 2006 (Code), incorporated by reference in Section 50.55a(b)(3) to Title 10 to the Code of Federal Regulations (10 CFR). Specifically, Relief Request RR-4-01,' 1ST Pump and Valve Surveillance Requirements, requests an alternative to the frequency specifications of the ASME

,OM Code. Relief Request RR-4-02, 1ST Class 2 and 3 Pump Testing Requirements using OMN-18, requests to adopt and use the provisions of Code Case OMN-18to perform a modi'fied Group A test in lieu of performing the Code required comprehensive pump test. Relief Request RR-4-03, 1ST Class 3 Service Water Check Valve, requests performance of full stroke test during refueling outages without performing bi-directional exercise testing to the non-safety related closed position as required by the ASME OM Code. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to 10 CFR 50.55a(a)(3)(i) and 50.55a(a)(3)(ii), the licensee shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's

T. Gaitlin - 2 ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be. advised of any further information needed to support the NRC staff detailed technical review by separate correspondence.

If you have any questions, please feel free to contact me at (301) 415-2315.

Sincerely, IRA!

Eva A Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395 cc: Distribution via Listserv

ML13177A099 *via email OFFICE LPLlI-1/PM ' LPLlI-1/PM LPLlI-1/LA NRRlDE/EPNB LPLlI-1/BC NAME MBarilias EBrown SFigueroa ~IBilierbeck* RPascarelli DATE 06/28/13 06/28/13 06/28/13 06/10/13 07/10/13