ENS 55321
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ENS Event | |
|---|---|
16:08 Jun 22, 2021 | |
| Title | High-Energy Line Break Door Unable to Be Latched |
| Event Description | At 1208 [EDT] on 6/22/2021, the high-energy line break door separating Auxiliary Feedwater Train Rooms 1 and 2 was not able to be latched following normal usage. The door was able to be closed, protecting Train 1 equipment from a break in Room 2. However, it is assumed a break in Room 1 would push the unlatched door open and allow high-energy fluids to enter Room 2. 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. The door was able to be latched at 1215 [EDT] on 6/22/2021 following repairs to the door latch interlocking mechanism. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). No other equipment was inoperable during this event.
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 | |
| Time - Person (Reporting Time:+0.78 h0.0325 days <br />0.00464 weeks <br />0.00107 months <br />) | |
| Opened: | Andrew Miller 16:55 Jun 22, 2021 |
| NRC Officer: | Joanna Bridge |
| Last Updated: | Jun 22, 2021 |
| 55321 - 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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