ENS 48537
ENS Event | |
|---|---|
00:30 Nov 27, 2012 | |
| Title | Degraded Condition Due to Pinhole Leak in Reactor Head Spray Line |
| Event Description | Pinhole leak discovered on a Reactor Head Spray line weld during Nuclear Steam Supply System Leak Test.
Oyster Creek Nuclear Generating Station is currently in the Shutdown Condition executing Refueling Outage 1R24, which includes Nuclear Steam Supply System (NSSS) Leak Testing, prior to startup. At 1930 on 11/26/2012, a pinhole leak was discovered on a Reactor Head Spray Class 1 piping weld. The leak was discovered during the NSSS Leak Test, while the Reactor was in the Shutdown Condition. The leak is on a flange to piping weld on the Reactor Head Spray system upstream of the N-7B nozzle. Water was found to be weeping from the pinhole leak (approximately 2 to 3 drops per minute). The cause is under investigation and corrective action plans are being developed. The leak has been evaluated by Exelon and determined to meet the criteria for reporting identified in NUREG-1022: Welding or material defects in the primary coolant system that 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 informed. |
| Where | |
|---|---|
| Oyster Creek New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.47 h-0.0196 days <br />-0.0028 weeks <br />-6.43806e-4 months <br />) | |
| Opened: | Steve Johnston 00:02 Nov 27, 2012 |
| NRC Officer: | Charles Teal |
| Last Updated: | Nov 27, 2012 |
| 48537 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
Oyster Creek with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 485372012-11-27T00:30:00027 November 2012 00:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Pinhole Leak in Reactor Head Spray Line ENS 484912012-11-07T17:40:0007 November 2012 17:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetrant Surface Indications Found on Control Rod Drive Return Nozzle Safe End to Pipe Weld 2012-11-07T17:40:00 | |