ENS 53644
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ENS Event | |
|---|---|
04:00 Oct 4, 2018 | |
| Title | Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment |
| Event Description | Degraded or unanalyzed condition due to the possibility for a postulated fire induced hot short to cause a secondary fire in a different fire area, which would be outside the boundaries analyzed for safe shutdown in calculation SSC-001 due to an unfused circuit associated with the 1M43C0001A, Diesel Generator Building Ventilation Fan. This condition is not bounded by existing design and licensing documents.
Without overcurrent protection for this circuit, the potential exists that an initial fire event affecting this circuit could cause a short circuit without protection that would cause excessive current through the circuit beyond the capacity rating of the conductors. This could lead to a secondary fire in another plant area where this circuit is routed challenging the ability to achieve and maintain safe shutdown. The postulated event would affect the following fire zones: 1CC-3c (Unit 1, Division 1 4160V and 480V Switchgear Room, 620 feet 6 inch elevation), 1CC-3e (Unit 1 West Corridor North of Elevator, 620 feet 6 inch elevation), DG-1d (Hallway Diesel Generator Building 620 feet 6 inch elevation), and 1DG-1c (Unit 1, Division 1 Diesel Generator Building 620 feet 6 inch elevation). This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plant. The licensee has notified the NRC Senior Resident Inspector. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+8.48 h0.353 days <br />0.0505 weeks <br />0.0116 months <br />) | |
| Opened: | Alex Hallmark 12:29 Oct 4, 2018 |
| NRC Officer: | Dong Park |
| Last Updated: | Oct 4, 2018 |
| 53644 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (96 %) |
| After | Power Operation (96 %) |
WEEKMONTHYEARENS 564552023-04-06T20:46:0006 April 2023 20:46:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Main Steam Line 'B' Leakage in Excess of Tech Spec Limits ENS 536752018-10-19T04:00:00019 October 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot-Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 536442018-10-04T04:00:0004 October 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 502132014-06-19T20:28:00019 June 2014 20:28:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to a Postulated Hot Short That Could Affect Safe Shutdown Equipment ENS 494462013-10-17T17:00:00017 October 2013 17:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 475452011-12-21T18:59:00021 December 2011 18:59:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Groundwater Level May Exceed Design Assumptions ENS 475082011-11-17T01:00:00017 November 2011 01:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Flooding Scenario Results in Unanalyzed Condition ENS 470242011-07-05T22:15:0005 July 2011 22:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Two Appendix R Wiring Issues That Could Potentially Affect the Ability to Shutdown ENS 436032007-08-27T20:45:00027 August 2007 20:45:00 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)(B), Unanalyzed Condition Grating Inside Containment Found Unsecured ENS 420722005-10-21T13:00:00021 October 2005 13:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Relocation of a Fire Door Boundary ENS 414172005-02-17T22:30:00017 February 2005 22:30:00 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 Emergency Diesel Generators Declared Inoperable Due to Unanalyzed Condition ENS 413442005-01-19T07:37:00019 January 2005 07:37:00 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)(B), Unanalyzed Condition Emergency Diesel Generators Declared Inoperable Due to an Unanalyzed Condition ENS 404042003-12-22T01:21:00022 December 2003 01:21:00 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 Potential Impact to Safe Shutdown Due to Control Complex Ventilation Inoperability 2023-04-06T20:46:00 | |
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