ENS Event | |
|---|---|
19:40 Feb 4, 2013 | |
| Title | Reactor Coolant System Pressure Boundary Leakage Identified on Seal Injection Line Drain Valve |
| Event Description | Unit is shut down in Mode 4 and in process of cooling down to Mode 5 for a scheduled refueling outage. During a containment walkdown to inspect for boron leakage, personnel identified that Reactor Coolant Pump 'A' seal injection line drain valve has a crack in the socket weld on the upstream side of the valve with active leakage visible as a fine mist. This valve is part of the Reactor Coolant System pressure boundary. TS 3.4.13 requires that the unit be placed in Mode 5 prior to 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> on 2/6/13. All Mode 4 required safety related equipment is operable.
The NRC Resident Inspector has been notified. The last primary leak rate test was conducted at 100% power and determined that there was 0.114 gpm of unidentified leakage. The leak location is inside the containment bio-shield and is not accessible at power. |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-2.9 h-0.121 days <br />-0.0173 weeks <br />-0.00397 months <br />) | |
| Opened: | James Kuras 16:46 Feb 4, 2013 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Feb 4, 2013 |
| 48713 - NRC Website
Loading map... | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot Shutdown (0 %) |
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 | |