ENS Event | |
|---|---|
08:30 Oct 1, 2003 | |
| Title | Reactor Pressure Vessel Boundry Leakage Found During Inspection |
| Event Description | At approximately 0430 on October 1, 2003 with the reactor Mode Switch in Refuel, reactor water level 210" above Top of Active Fuel, and reactor water temperature less than 110F, investigations and walkdowns were being performed to identify potential sources of drywell leakage. Drywell leakage was well within Technical Specification limits. During these walkdowns a small leak in a cap of a nozzle of the reactor pressure vessel boundary, nozzle N10, located at reactor vessel height 440" was identified. This location is 84" above Top of Active Fuel. This is a cut and capped 4" Control Rod Drive return line. The leak appears to be on the cap weld. This notification is being made per 10 CFR 50.72(b)3(ii)(A). All required ECCS systems are presently operable.
Investigation is continuing. The [NRC] resident inspector has been notified. |
| Where | |
|---|---|
| Pilgrim Massachusetts (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+2.7 h0.113 days <br />0.0161 weeks <br />0.0037 months <br />) | |
| Opened: | Michael Mcdonnell 11:12 Oct 1, 2003 |
| NRC Officer: | Gerry Waig |
| Last Updated: | Oct 1, 2003 |
| 40211 - 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 | |