ENS 42897
ENS Event | |
|---|---|
17:40 Oct 11, 2006 | |
| Title | |
| Event Description | The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73.
On October 11, 2006, at approximately 12:40 Central Standard Time (CST), engineering personnel performing preplanned in-service examination of the Pressurizer nozzle to safe end welds notified the Control Room that five circumferential indications had been discovered that cannot be found acceptable under ASME Section XI. Since the indications cannot be found acceptable under ASME Section XI the condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(A). Three indications are located on the surge line, one indication is on the safety nozzle, and one indication is on the relief nozzle. The locations are part of the Reactor Coolant System (RCS) pressure boundary. There is no evidence of RCS pressure boundary leakage. WCGS is currently shutdown for its 15th refueling outage and is in Mode 6. Weld overlay of the safe ends is an activity scheduled for the current outage. An investigation of this event will be conducted in accordance with the WCGS corrective action program. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-2.58 h-0.108 days <br />-0.0154 weeks <br />-0.00353 months <br />) | |
| Opened: | Dave Drees 15:05 Oct 11, 2006 |
| NRC Officer: | Jason Kozal |
| Last Updated: | Oct 11, 2006 |
| 42897 - NRC Website
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WEEKMONTHYEARENS 500472014-04-20T19:42:00020 April 2014 19:42:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Emergency Core Cooling System Piping Leak While Shutdown ENS 487132013-02-04T19:40:0004 February 2013 19:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Leakage Identified on Seal Injection Line Drain Valve ENS 428972006-10-11T17:40:00011 October 2006 17:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unanalyzed Condition - Indications on Pressurizer Nozzle to Safe End Welds ENS 416022005-04-15T10:17:00015 April 2005 10:17:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Steam Generator Bowl Drain Line Weld Leak Discovered During Visual Exam ENS 403272003-11-17T15:00:00017 November 2003 15:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Leakage Due to a Cracked Socket Weld 2014-04-20T19:42:00 | |