ENS 57373
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ENS Event | |
|---|---|
14:45 Oct 10, 2024 | |
| Title | |
| Event Description | The following information was provided by the licensee via phone and email:
On October 10, 2024, at 1045 EDT, it was determined that an additional failure mechanism existed for a previous issue with the emergency diesel generator (EDG) speed switches. As a result, for some initiating events such as a fire or high energy line break potentially causing a ground on the negative buses on both trains of the station direct current (DC) system, both EDG speed switches could have been affected, resulting in a failure of the EDGs to function. This condition is not bounded by existing design and licensing documents; however, it poses no impact to the health and safety of the public or plant personnel, as the EDG speed switches were replaced in January 2022 with a different design that is not susceptible to grounds on the station DC system. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Davis Besse  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| LER: | 05000346/LER-2021-001-02 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground |
| Time - Person (Reporting Time:+-3.1 h-0.129 days <br />-0.0185 weeks <br />-0.00425 months <br />) | |
| Opened: | Michael Boles 11:39 Oct 10, 2024 |
| NRC Officer: | Kerby Scales |
| Last Updated: | Oct 10, 2024 |
| 57373 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 573732024-10-10T14:45:00010 October 2024 14:45:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition ENS 553212021-06-22T16:08:00022 June 2021 16:08:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition High-Energy Line Break Door Unable to Be Latched ENS 528652017-07-20T16:30:00020 July 2017 16:30:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Tornado Missile Vulnerabilities ENS 520102016-06-16T15:37:00016 June 2016 15:37:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition of Emergency Diesel Generator During Tornado Low Pressure ENS 506392014-11-25T17:00:00025 November 2014 17:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Non-Conservatisms in Methodology Used for Emergency Core Cooling System Performance Requirements ENS 498282014-02-14T08:25:00014 February 2014 08:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Shield Building Construction Opening ENS 470962011-07-26T20:00:00026 July 2011 20:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 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)(B), Unanalyzed Condition Unanalyzed Conditions Involving the Safety Related Direct Current (Dc) System ENS 416982005-05-13T20:00:00013 May 2005 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Electrical Containment Penetration ENS 404572004-01-19T16:20:00019 January 2004 16:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Certain Plant Doors May Not Be Able to Withstand Pressure Created by Main Steam Line Break ENS 402562003-10-17T13:00:00017 October 2003 13:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Steam and Feedwater Rupture Control System Unanalyzed Condition at Davis Besse 2024-10-10T14:45:00 | |
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