05000425/LER-2005-003, Reactor Coolant System Leakage Leads to Shutdown Required by Technical Specifications
| ML060300600 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/30/2006 |
| From: | Grissette D Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-06-0135 LER 05-003-00 | |
| Download: ML060300600 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| 4252005003R00 - NRC Website | |
text
Don E. Grissette Southern Nuclear Vice President Operating Company, Inc.
40 lnverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 SOUTHERN-January 30, 2006 Docket No.:
50-425 COMPANY Energy to Serve Your World SM U. S. Nuclear Regulatory Commission ATTN: Docutnent Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Unit 2 Licensee Event Report 2-2005-003 Reactor Coolant System Leakage Leads to Shutdown Required by Technical Specifications Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73, Southern Nuclear Operating Company hereby submits a Vogtle Electric Generating Plant licensee event report for a condition that was determined to be reportable on December 9,2005.
Sincerely, Don E. Grissette Enclosure: LER 2-2005-003 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, General Manager - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle
LICENSEE EVENT REPORT (LER)
On December 8,2005, control room operators received indication of an increase in radioactivity in the containment building atmosphere. On December 9, 2005, a robotic camera sent inside the containment building bioshield wall observed water running down the inside of the wall. Unit 2 was placed in Mode 3 (Hot Standby). On December 9,2005, at 1544 EST, an inspection team found leakage at a Reactor Coolant System (RCS) welded %" piping connection located inside the bioshield wall. Because the The leak occurred in a %" socket weld between a flow restrictor and a half-coupling. A linear weld defect, approximately !h" long, was found near the toe of the weld nearest the half-coupling. The probable cause of the defect is a lack of fusion in the startlstop point of the weld. This is a fabrication flaw that occurred when this weld was installed in 2002 as part of a design change. The weld was repaired and the unit returned to power operations. Similar Unit 2 welds made during the design change were inspected and found to be satisfactory. Other non-isolable socket welds made during the design change on Unit 1 will be inspected no later than the next refueling outage on Unit 1.
(If more space is requrred, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
G) ADDITIONAL INFORMATION
- 1) Failed Components:
None
- 2) Previous Similar Events:
There have been no previous similar events in the last three years.
- 3) Energy Industry Identification System Codes:
Reactor Coolant System - AB Chemical Volume and Control System - CB Plant Effluent Radiation Monitoring System - IL Residual Heat Removal System - BP