ENS 51349
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ENS Event | |
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16:15 Aug 26, 2015 | |
Title | Unanalyzed Condition Due to Appendix R Postulated Fire |
Event Description | On 8/26/2015 at 1215 [EDT], a review of the Salem Appendix R Safe Shutdown Analysis in response to the Byron Event Notification #51334 and Braidwood Event Notification #51335, identified a fire scenario that could cause spurious operation of the pressurizer power operated relief valves (PORVs) (PR1 and PR2) and also prevent the ability to close the PORV block valves (PR6 and PR7) until AC power is restored to close the block valves. This scenario would result in the loss of reactor coolant system (RCS) inventory and pressure control that is not accounted for in safe shutdown analysis. The above fire scenario is applicable to a fire in the Control Room and Relay Room fire areas.
Hourly fire watches of the Relay Room have been implemented. In addition, the Control Room is continuously staffed by the Operating Shift. In addition, the Relay Room is equipped with automatic detection and suppression. This event is being reported under 10CFR50.72(b)(3)(ii)(B), for 'any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' The NRC Resident Inspector has been notified. The licensee will be notifying the Lower Alloways Township, the State of New Jersey and the State of Delaware. |
Where | |
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Salem New Jersey (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
LER: | 05000272/LER-2015-006 |
Time - Person (Reporting Time:+0.25 h0.0104 days <br />0.00149 weeks <br />3.4245e-4 months <br />) | |
Opened: | Tom Mulholland 16:30 Aug 26, 2015 |
NRC Officer: | Jeff Herrera |
Last Updated: | Aug 26, 2015 |
51349 - NRC Website | |
Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 2 | |
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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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