RC-02-0067, Interim Report Pursuant to 10 CFR Part 21 (SSH 2002-001)
| ML021220549 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/16/2002 |
| From: | Byrne S South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RC-02-0067, SSH 2002-001 | |
| Download: ML021220549 (2) | |
Text
Stephen A. Byrne Vice President Nuclear Operations A SCANA COMPANY April 16, 2002 RC-02-0067 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 INTERIM REPORT PURSUANT TO 10 CFR PART 21 (SSH 2002-001)
South Carolina Electric & Gas Company (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 February 19, 2002, during the investigation of Non-Conforming Notice (NCN) 02 0365, engineering personnel determined that the potential existed for a saturation condition of the board mounted Current Transformers (CT's) on the ABB Power Shield units to cause the associated breaker to trip at a higher instantaneous current than expected.
The potential saturation of the board mounted CTs on the ABB Power Shield units appears to be limited to cases where the relay is set up for operation at the maximum amperage for the breaker rating along with the maximum setting (12X) for the instantaneous current trip.
ABB has been able to recreate the CT saturation problem using single phase testing method similar to those utilized at VCSNS. However, ABB has not been able to create the same conditions using a three phase testing method. The operation of these relays when in service is in three phase applications.
Therefore, further investigation is required to determine if this problem affects the trip settings while in service in generic industry applications.
SCE&G I Virgil C. Summer Nuclear Station
- P. 0. Box 88 - Jenkinsville, South Carolina 29065. T (803) 345.5209 - www.scana.com
Document Control Desk SSH 2002-001 RC-02-0067 Page 2 of 2 A substantial safety hazard does not exist at VCSNS at this time because the applicable Power Shield units have been replaced with spare units or reconfigured out of the limiting conditions. Prior to installation, they were satisfactorily tested on-site.
A final report on the 10 CFR Part 21 evaluation will be submitted within 30 days of receipt of the final report from the vendor, which is expected in June 2002.
Should you have any questions, please call Mr. Jeffrey Pease at (803) 345-4124.
Very truly yours, Stephen A. Byrne SAB/jwp
- c.
N. 0. Lorick N. S. Cams T. G. Eppink R. J. White L. A. Reyes G. E. Edison K. W. Sutton NRC Resident Inspector J. M. Wagner NSRC RTS (0-L-02-0045)
File (818.18)
DMS (RC-02-0067)
NUCLEAR EXCELLENCE - A SUMMER TRADITION!