ENS 56197
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ENS Event | |
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18:33 Nov 1, 2022 | |
Title | Reactor Coolant System (RCS) Pressure Boundary Degraded |
Event Description | The following information was provided by the licensee via email:
At 1433 EDT on November 1, 2022, it was determined that a single relevant indication in the RCS pressure boundary did not meet the acceptance criteria under ASME,Section XI IWB-3514-2. 'Allowable Planar Flaws.' The condition will be resolved prior to plant startup. This event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
Where | |
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Oconee South Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+-1.62 h-0.0675 days <br />-0.00964 weeks <br />-0.00222 months <br />) | |
Opened: | Jeffy Collier 16:56 Nov 1, 2022 |
NRC Officer: | Donald Norwood |
Last Updated: | Nov 1, 2022 |
56197 - NRC Website
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WEEKMONTHYEARENS 562212022-11-14T11:30:00014 November 2022 11:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (RCS) Pressure Boundary Degraded ENS 561972022-11-01T18:33:0001 November 2022 18:33:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (RCS) Pressure Boundary Degraded ENS 495272013-11-11T10:20:00011 November 2013 10:20:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 1 Commenced a Technical Specification Required Shutdown Due to Rcs Leakage ENS 426412006-06-14T18:00:00014 June 2006 18:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Leaking Decay Heat Removal Isolation Valve Bypass Line ENS 414132005-02-16T18:31:00016 February 2005 18:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Reactor Building Normal Sump Level Increasing 2022-11-14T11:30:00 | |
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