ENS 41602
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ENS Event | |
|---|---|
10:17 Apr 15, 2005 | |
| Title | Steam Generator Bowl Drain Line Weld Leak Discovered During Visual Exam |
| Event Description | During the performance of Alloy 600 bare metal visual examinations, the presence of boric acid deposits indicated a leak in a weld in the steam generator D (EBB01D) bowl drain line.
This condition is being reported as a degraded condition on the primary coolant system under 10 CFR 50.72 (B)(3)(ii)(A). During investigation the defect was characterized as a 1/16" rounded indication in the drain line to boss weld. This condition cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws' or ASME Section XI, Table IWB-3410-1, 'Acceptable Standards.' The [NRC] Resident Inspector has been notified.
On 04/20/05 at 12:10 CDT, during the performance of Alloy 600 Bare Metal Visual Examinations, the presence of boric acid deposits indicated a leak in a weld in the Steam Generator C (EBB01C) bowl drain line. The inspection of Steam Generators A & B showed no presence of boric acid deposits. The licensee notified NRC Resident Inspector. Notified the R4DO (Shannon). |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.25 h-0.0104 days <br />-0.00149 weeks <br />-3.4245e-4 months <br />) | |
| Opened: | Ken Petersen 10:02 Apr 15, 2005 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Apr 20, 2005 |
| 41602 - 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 | |
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