ML20154A062

Safety Evaluation Supporting 850930 & 1204 Responses to 850802 & 1104 Requests,Respectively,For Addl Info Re Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events

ML20154A062
Person / Time
Site:	Summer
Issue date:	02/24/1986
From:	NRC
To:
Shared Package
ML20154A041	List: ML20154A036 ML20154A062
References
GL-83-28, NUDOCS 8603030280
Download: ML20154A062 (2)

Text

.

e l

Enclosure SAFETY EVALUATION GENERIC LETTER 83-28, ITEMS 3.2.2, 4.2.1, AND 4.2.2 VIRGIL C. SUMER NUCLEAR STATION Docket No. 50-395 Item 3.2.2 By letters dated September 2,1983, November 4,1983, February 29, 1984, April 30, 1984, and September 28, 1984, South Carolina Electric and Gas Company (SCE&G), the licensee of V. C. Sumer Nuclear Station, provided information regarding their compliance to Sections 3.1.1, 3.1.2, 3.2.1, 3.2.2, 4.1, and 4.5.1 of GL 83-28. We evaluated the licensee's responses against the NRC positions described in the GL for completeness and adequacy.

We concluded that the licensee's responses to Action Items 3.1.1, 3.1.2, 3.2.1, 4.1, and 4.5.1 were acceptable and met the intent of GL 83-28; however, the licensee's response to Action Item 3.2.2 was found incomplete, thus requiring additional information to determine acceptability.

The Safety Evaluation with a request for additional information was transmitted to the licensee in a letter dated November 4, 1985. The licensee responded to our request for additional information in a supplemental response dated December 4,1985. In this letter, the licensee provided supplemental infomation on Action Item 3.2.2.

We have evaluated this response and have concluded that it is acceptable and meets the intent of GL 83-28.

F In this response, SCE&G indicated that they have instituted procedures and l programs to review vendor and other technical information to ensure that i infomation pertaining to safety-related equipment is reviewed for applicability and that any resulting necessary changes in plant operation or procedures are initiated. The licensee also indicated that many of the programs were initiated during the construction and early operational stages of the plant and have therefore been in existence for several years prior to the issuance of Generic Letter 83-28. However, other programs, such as the vendor '

information program, which reviews vendor supplied information on a fomal basis, have been proceduralized as a result of the Salem Incident.

The licensee stated that as part of the vendor information program they conducted a review of all Westinghouse supplied Technical Bulletins issued.

since 1973 on both safety and non-safety-related equipment. The licensee indicated that the reviews and their results were documented in accordance with the established program procedures. ,

I The licensee believes that with the existence of these programs, both past and present, reasonable confidence exists that appropriate vendor and industry supplied infomation on safety related equipment have been reviewed and that appropriate corrective measures have and will continue to be identified and rectified.

8603030200 860224 PDR ADOCK 05000395 P PDR

__ __ _ . ~ . . _ _ . . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ ~ . _ _ _ . . _ . _ _ _ _ ._ -

~

Based on the above, we find that the licensee's supplemental response is acceptable and meets the intent of GL 83-28.

Items 4.2.1 and 4.2.2 By letter dated September 30, 1985, SCE&G responded to our request for i additional information concerning the open items in our Safety Evaluation of August 2,1985. SCE&G stated in their response that; 1) current

, surveillance testing procedures at V. C. Summer Nuclear Station require checking the. dropout voltage for the undervoltage coil, 2) the appropriate test procedure will be revised to specify that the undervoltage trip attachment (UVTA) will be replaced if the dropout voltage is greater than 60% or less than 30% of rated UVTA coil voltage, and 3) trending of the ,

UVTA dropout voltage will be added to the appropriate procedure. )

Based on the above, we find that the licensee's response resolves the open l items identified in our Safety Evaluation of August 2,1985, and therefore, l

, Items 4.2.1 and 4.2.2 responses are acceptable for the Y. C. Summer Nuclear Station.

l 1

e 9

~ , - ,,-- -,-, ,,-n, ----, - - ,,, , , , - - , --

, , , , c--.--