ENS 53598
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ENS Event | |
|---|---|
04:00 Sep 11, 2018 | |
| Title | Weld Defect on Pressurizer Interface |
| Event Description | At 2200 EDT on September 11, 2018, during inspections as part of the pressurizer bare metal inspection program, an apparent weld defect was identified on Class 1 pressurizer level piping at the piping to pressurizer interface. The reactor is currently defueled in a refueling outage. Appropriate repairs will be made during the refueling outage.
NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Saint Lucie  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+19.38 h0.808 days <br />0.115 weeks <br />0.0265 months <br />) | |
| Opened: | Andrew Tererakis 23:23 Sep 11, 2018 |
| NRC Officer: | Steven Vitto |
| Last Updated: | Sep 11, 2018 |
| 53598 - NRC Website
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WEEKMONTHYEARENS 569122024-01-03T17:57:0003 January 2024 17:57:00
[Table view]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 Pressure Boundary Degraded / Both Trains of High Pressure Safety Injection Inoperable ENS 568932023-12-16T01:45:00016 December 2023 01:45:00 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 Reactor Coolant System Leak ENS 535982018-09-11T04:00:00011 September 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Defect on Pressurizer Interface ENS 525232017-01-31T17:00:00031 January 2017 17:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant Pressure Boundary Piping Defect ENS 503102014-07-25T15:29:00025 July 2014 15:29:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to a Safety Injection Valve Defect ENS 452002009-07-13T11:00:00013 July 2009 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified ENS 439412008-01-29T10:31:00029 January 2008 10:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip to Repair Rcp "2B1" Seal Package ENS 438632007-12-21T19:45:00021 December 2007 19:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Pressure Boundary Leakage on Rcp Seal Injection Line ENS 435802007-08-19T21:00:00019 August 2007 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Plant Shutdown Due to Unisolable Reactor Coolant System Leakage ENS 434102007-06-06T17:10:0006 June 2007 17:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Isolation Valves Found Misaligned ENS 414012005-02-10T21:00:00010 February 2005 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Leakage Identified During Plant Startup Walkdowns 2024-01-03T17:57:00 | |
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