ML20237A710

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Forwards SE Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves Issued on 950817.Util Adequately Addressed Actions in Gl,Per 960213,02 & s
ML20237A710
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 08/13/1998
From: Padovan L
NRC (Affiliation Not Assigned)
To: Gabe Taylor
SOUTH CAROLINA ELECTRIC & GAS CO.
Shared Package
ML20237A712 List:
References
GL-95-07, GL-95-7, TAC-M93525, NUDOCS 9808170042
Download: ML20237A710 (1)


Text

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August 13, 1998 o

Mr. G ry J. Taylor i

Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065

SUBJECT:

COMPLETION OF GENERIC LETTER 95-07 LICENSING ACTION -

VIRGIL C. SUMMER NUCLEAR STATION (TAC NO. M93525)

Dear Mr. Taylor:

The U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves" on August 17,1995. The GL requested licensees to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

You submitted a February 13,1996,180-day response to GL 95-07 for the Virgil C. Summer Nuclear Station (VCSNS). We reviewed your response, and requested additional information in our July 3,1996, letter. Your "RC-96-0182, Responds to RAI Re GL 95-07, Pressure Locking and [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. of Safety-Related Power Operated Gate Valves|August 2,1996, letter]] provided the additionalinformation. During March 3 through 7,1997, we performed an inspection of some of the information in your GL 95-07 responses. We documented this inspection in NRC Inspection Report 50-395/97-01.

Your December 29,1997, letter responded to the inspection report findings.

We have reviewed your submittals, and find that you have adequately addressed the actions requested in GL 95-07, as discussed in the enclosed NRC Safety Evaluation. Therefore, we consider GL 95-07 to be closed for your facility. Please contact me if you have any questions.

Sincerely, Original signed by L. Mark Padovt.;i, Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-395

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Enclosure:

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