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Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Part 21 Report - 2001-051

 

SCE&G
A SCANA COMPANY

   Stephen A. Byrne
Vice President, Nuclear Operations
803.345.4622
   March 15, 2001
RC-01-0060

Document Control Desk
U. S. Nuclear Regulatory Commission
Washington, DC 20555

Gentlemen:

 

Subject: VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO.50/395
OPERATING LICENSE NO. NPF-12 FINAL REPORT PURSUANT TO 10 CFR PART 21 (SSH 2000-001)

South Carolina Electric & Gas (SCE&G) submits this letter in accordance with the requirements of 10 CFR 21.21 (a)(2) as a final report of an identified defect which was potentially associated with a substantial safety hazard.

On 10/12/00, at 0630 hours, visual inspection revealed small amounts of boron buildup on the weld between the vessel nozzle and the hot leg pipe. Within hours, the suspect area was cleaned and a dye penetrant (PT) examination of the pipe identified a 4 inch indication at the weld between the hot leg piping and the reactor vessel nozzle. The weld is located approximately 3 feet from the vessel in pipe near the nozzle. The indication was located about 17" from the top of the pipe. This pipe has a nominal inside diameter of 29 inches and is approximately 2.5 inches thick.

Subsequent ultrasonic examination from the inside diameter identified an axial flaw less than 3 inches long. The same examination determined that the original indication was not the source of the leak.

The interim 10 CFR Part 21 report (RC-00-0368) was submitted to allow additional evaluation and cause determination.

NUCLEAR EXCELLENCE - A SUMMER TRADITION!

SCE&G I Virgil C. Summer Nuclear Station ? P.O. Box 88 ? Jenkinsville, South Carolina 29065 ? T (803)345.5209 ? www.scana.com

SC E&G Engineering review of the Root Cause Evaluation Report for potential 10 CFR Part 21 concerns, has determined that a Significant Safety Hazard did not exist. Attached is the engineering justification for this position.

Should you have any questions, please call Mr. Jeffrey Pease at (803) 345-4124.

  Very truly yours,



Stephen A. Byrne

JWP/SAB/dr
Attachment

 

cc: N. O. Lorick
N. S. Cams
T. G. Eppink
R. J. White
L. A. Reyes
K. R. Cotton
J. B. Knotts, Jr.
NRC Resident Inspector
G. G. Williams
NSRC
RTS (SSH 2000-001)
File (818.18)
DMS (RC-00-0060)

Attachment 1

 

Page Last Reviewed/Updated Wednesday, March 24, 2021

Page Last Reviewed/Updated Wednesday, March 24, 2021