ML20128A885
| ML20128A885 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/20/1985 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8505240350 | |
| Download: ML20128A885 (2) | |
Text
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-SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFetCE 784 cowuei4. soum canousa aeais
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May 20, 1985 VICE PRGS10ENT NUCLE Ae ope.An0N4 Mr. Harold ~ R.
Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, D.C.-
20555
Subject:
Virgil C.' Summer Nuclear Station Docket No. 50/395 Operating License No. N P F-12 Generic Letter 83-28
Dear Mr. Denton:
In a letter from the NRC Staf f dated March 21, 1985, South Carolina Electric and Gas Company ( S C E& G) r e c e iv ed a request for additional information on Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events."
This letter is p r ov id e d in response to that request.
SCE&G provid ed a final response to Section 2.2.2 of the Generic Letter in a submittal from Mr.
O.
W.
Dixon, Jr. to Mr. H.
R.
Denton dated September 28, 1984.
As indicated in that response, SCE&C receives information from many sources on safety related equipment.
This Information comes from vendors, the NRC, other utilities, and industry sponsored organizations.
SCE&G has implemented procedures which assure this material is reviewed for applicability to the VirgillC. Summer Nuclear Station and that resulting corrective action, if necessary, is taken.
Continued interface with these sources of information help ensure that the reliability of safety related equipment is maintained.
Therefore, the concerns of Generic Letter 83-28, Section 2.2.2, have been addressed.
Section 4.5.2 of the Generic Letter pertains to the on-line testing capability of the Reactor Trip System (RTS).
The current plant d es ign at the Virgli C.
Summer Nuclear Station does permit on-line testing of the RTS.
Therefore, modifications to the RTS are not necessary to permit this type of testing.
SCE&G la reviewing In detall WCAP-10271 and Supplement 1 thereto.
In addi tion, the NRC Safety Evaluation Report ( S E R) on this WCAP la being reviewed.
Upon completion of these reviews, SCE&G plans to request a Technical Specification change to allow for the revised testing requirements approved by the NRC in their review of
-WCAP-10271.
SCE&G will make this submittal in accordance with guidance to be issued by the Westinghouse Owners' Group to ensure that-NRC requirements are addressed and to facllitate Staff revi i
of the request.
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Mr. Harold R.
Denton LCeneric Letter.83-28 May.20, 198's-Page #2 L
If you should. have any fur ther que st ion s, please advise.
I Very truly yours, f
O.
W.
rixon, Jr.
l AMM/0WD/inw cci
.V.C.
Summer T.C.
Nichols, Jr./0.
W.
Dixon, Jr.
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H.
Crews, J r.
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Roberts W.
A.
Williams, Jr.
D.
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Nauman
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Nelson Grace Grou p Managers 0.
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Bradham C.
A.
Price C.-L. Ligon (NSRC)
K..E.
Nodland R. A.
Stough-C.
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Pe r c iv a l C. W.
Hehl J.
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