ENS 43322
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ENS Event | |
|---|---|
23:30 Apr 26, 2007 | |
| Title | Degraded Condition During Weld Deposit Overlay Repair |
| Event Description | On April 26, 2007, at approximately 1930 it was reported that the N2K recirculation system inlet nozzle had slight water seepage. The seepage developed during welding operations being performed to install a full structural weld overlay over the nozzle and stopped almost immediately during the welding. The weld overlay was being installed as a conservative measure following UT inspections that had been performed earlier during the outage.
This event is being reported in accordance with 10 CFR 50.72(b)(3)(ii)A. The plant is in stable condition. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
| Pilgrim Massachusetts (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.42 h-0.0175 days <br />-0.0025 weeks <br />-5.75316e-4 months <br />) | |
| Opened: | Mike Mcdonnel 23:05 Apr 26, 2007 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Apr 26, 2007 |
| 43322 - NRC Website
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Pilgrim with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 532872018-03-25T20:16:00025 March 2018 20:16:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Control Rod Drive Piping Potentially Inoperable ENS 527442017-05-10T18:11:00010 May 2017 18:11:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Appendix J Local Leakage Exceeded Acceptance Criteria ENS 490612013-05-23T08:55:00023 May 2013 08:55:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Declared Inoperable During Hpci Testing ENS 433222007-04-26T23:30:00026 April 2007 23:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition During Weld Deposit Overlay Repair ENS 402112003-10-01T08:30:0001 October 2003 08:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Vessel Boundry Leakage Found During Inspection 2018-03-25T20:16:00 | |
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