United States Nuclear Regulatory Commission - Protecting People and the Environment

December 7, 2000
SCE&G RC-00-0368
A SCANA COMPANY

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
INTERIM REPORT PURSUANT TO 10 CFR PART 21
(SSH 2000-001)

Stephen A. Byrne South Carolina Electric & Gas Co.
Vice President Virgil C. Summer Nuclear Station
Nuclear Operations P. 0. Box 88
803.345.4622 Jacksonville, South Carolina 29065
803.345.5209
803.635.1461

South Carolina Electric & Gas (SCE&G) submits this letter in accordance with the requirements of 10 CFR 21.21 (a) (2) as an interim report of an identified defect 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 issue resolution strategy consists of a root cause evaluation, repair of the weld, and restart justification. A group of industry experts in the areas of root cause, failure analysis, materials, welding, inspection, and fracture mechanics has been assembled to assist in the recovery effort.

NUCLEAR EXCELLENCE - A SUMMER TRADITION!

Document Control Desk

SSH 2000-001

RC-00-0368

Page2 of 2

The section of piping containing the weld in question was shipped to Westinghouse for analysis at their Spartanburg, S.C. and Waltzmill, Pa. facilities as input to a root cause determination. The root cause evaluation will not be completed within the 60 day 10 CFR Part 21 evaluation period. This interim 10 CFR Part 21 report is being submitted to allow additional evaluation and cause determination by the Root Cause Team. The Root Cause Team anticipates that an initial root cause determination should be completed later this month. A final report on the 10 CFR Part 21 evaluation will be submitted within thirty days of the final Root Cause Analysis Report, expected in January 2001.

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

Very truly yours,

Stephen A. Byrne

JW P/SAB/dr

c: 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-00-0368)

 

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