RC-97-0253, Follow-up Part 21 Rept SSH 960004 Re Defect Determined Not to Be Potentially Associated W/Substantial Safety Hazard (Ssh).Westinghouse Determined That SSH Reportable Under 10CFR21 Does Not Exist Based on Listed Info

Follow-up Part 21 Rept SSH 960004 Re Defect Determined Not to Be Potentially Associated W/Substantial Safety Hazard (Ssh).Westinghouse Determined That SSH Reportable Under 10CFR21 Does Not Exist Based on Listed Info

ML20197B250
Person / Time
Site:	Summer
Issue date:	12/15/1997
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-97 RC-97-0253, RC-97-253, SSH-960004, NUDOCS 9712230325
Download: ML20197B250 (2)

Text

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J.T.g Nucker Oprabons g .ytas SCE&G

"* December 15,1997 RC 97 0253 Document Control Desk l U.S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO NPF 12 FOLLOW UP PART 21 REPORT (SSH 960004)

Ref: (a) Gary J. Taylor to Document Control Desk, RC 96 0157 dated Juns 17,1996.

(b) David D. Molitoris, Westinghouse, to R. J. Wasolus, SCE&G, CGE 96 029 dated November 11,1996.

South Carolina Electric and Gas Company (SCE&G) submits the following follow up response in accordance with 10CFR21.21(a)(2) as a final report of an identified defect determined not to be potentially associated with a substantial satoty hazard.

Per reference (a), we contacted Westinghouse, the original equipment manufacturer, to

, evaluate the the nozzle weld defects in the Chemical and Volume Control System connections at the reactor coolant pump seal injection line nozzles and Component Cooling Water System connections at the reactor coolant pump thermal barrier heat exchanger inlet and outlet nozzles for 10CFR21 reportability.

Westinghouse has determined that a Substantial Safety Hazard (SSH) reportable under 10CFR21 does not exist based on the following:

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1. The Westinghouse safety evaluation on this issue has determined that the condition is non safety related per reference (b).

2. Westinghouse has had only about 10 reported problems (including the 6 from .

VCSNS) in the 1200 nozzles that have been in service for up to 20 years.

(Reference (b).

VCSNS initially determined that the problems associated with the RCP Seal Injection /

CCW Nozzle Wolds were a potential SSH reportable under 10CFR21; however, based 7 on the Westinghouse evaluation, no SSH exists.

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8 PDR NUCLEAR EXCELLENCE - A SUMMER TRADmONI wm

. ' booumont Control Desk i

• ~ . AC 97 0253

, ShH 96'0004 Page 2 of 2 l Should you require any further information, pisase contact Mr. Michael J. Zaccono at (803) 345 4328.

Very Truly Yours, CL Gary . a OJTMJZ c: J.L. Skolds NRC Resident inspector R.R. Mahan J.B. Knotts, Jr.

R.J. White DMS (RC 97 0253)

L. A. Reyes RTS (SSH 960004)

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