ENS 49539
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ENS Event | |
|---|---|
18:22 Nov 14, 2013 | |
| Title | Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment |
| Event Description | A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits has determined the described condition is applicable to the Salem Nuclear Power Plant resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R. The original plant wiring design and associated analysis for ammeters associated with the station batteries are not provided with overcurrent protection features to limit the fault current.
A postulated fire that results in a short to ground concurrent with an opposite polarity short from the same battery could result in excessive current flow (i.e., heating) in the ammeter wiring. This excessive current could result in a secondary fire in another fire area. The secondary fire could adversely affect safe shutdown equipment and cause loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R. The areas affected are the Control Room, Relay Rooms and 460 Volt Switchgear Rooms. 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 the affected areas of the plant. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
| Salem New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-2.23 h-0.0929 days <br />-0.0133 weeks <br />-0.00305 months <br />) | |
| Opened: | Kelly Johnson 16:08 Nov 14, 2013 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Nov 14, 2013 |
| 49539 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 534382018-06-01T04:00:0001 June 2018 04:00:00
[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)(B), Unanalyzed Condition Tornado Missile Vulnerabilities ENS 522942016-10-11T13:38:00011 October 2016 13:38:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Failure of a Watertight Door to Close ENS 522222016-09-03T13:02:0003 September 2016 13:02:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unidentified Leakage Greater than Technical Specifications ENS 519022016-05-03T17:01:0003 May 2016 17:01:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Anomalies Identified During Visual Inspection of Reactor Vessel Internals ENS 516632016-01-19T21:30:00019 January 2016 21:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Discovered During Review of Outage Data ENS 513492015-08-26T16:15:00026 August 2015 16:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Appendix R Postulated Fire ENS 496992014-01-07T12:45:0007 January 2014 12:45:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Caused by High Energy Line Break Barrier Door Open During Maintenance ENS 495392013-11-14T18:22:00014 November 2013 18:22:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment 2018-06-01T04:00:00 | |
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