United States Nuclear Regulatory Commission - Protecting People and the Environment

ACCESSION #: 9712230325

          South Carolina Electric & Gas Company        Gary J. Taylor
          P.O. Box 88                                  Vice President
          Jenkinsville, SC 29065                       Nuclear Operations
          (803) 345-4344

SCE&G
A SCANNA Company

                                        December 15, 1997
                                        RC-97-0253

Document Control Desk
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 June 17, 1996.
     (b)  David D. Molitoris, Westinghouse, to R. J. Waselus, 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 safety 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:

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 29 years.  (Reference (b).

VCSNS initially determined that the problems associated with the RCP Seal
Injection/CCW Nozzle Welds were a potential SSH reportable under 10CFR21;
however, based on the Westinghouse evaluation, no SSH exists.

                NUCLEAR EXCELLENCE - A SUMMER TRADITION!

Document Control Desk
RC-97-0253
SSH 96-0004
Page 2 of 2

Should you require any further information, please contact Mr.  Michael
J. Zaccone at (803) 345-4328.

                                   Very Truly Yours,

                                   Gary J. Taylor

GJT/MJZ

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)
     A. R. Johnson                 File (818.18)

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