ENS Event | |
|---|---|
19:42 Apr 20, 2014 | |
| Title | Emergency Core Cooling System Piping Leak While Shutdown |
| Event Description | A leak was discovered in the area of EPV0109, COMBINED SI/RHR [Safety Injection/Residual Heat Removal] TO ACCUMULATOR D OUTLET LINE VENT. The leak rate was estimated at 2.5 gallons per hour. The plant is in Mode 5, RCS [Reactor Coolant System] depressurized.
This leak is considered a material problem that causes abnormal degradation of or stress upon the reactor coolant system pressure boundary, reportable in accordance with 10CFR 50.72(b)(3)(ii)(A). Efforts are underway to characterize the leak and plan for repairs. The leak has been secured after realigning RHR cooling from the B to the A train. The Resident Inspector has been notified. The cause of the leak is being investigated. |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.27 h0.0113 days <br />0.00161 weeks <br />3.69846e-4 months <br />) | |
| Opened: | P.C. Moore 19:58 Apr 20, 2014 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Apr 20, 2014 |
| 50047 - NRC Website
Loading map... | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold 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 | |