ENS 49699
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ENS Event | |
|---|---|
12:45 Jan 7, 2014 | |
| Title | Unanalyzed Condition Caused by High Energy Line Break Barrier Door Open During Maintenance |
| Event Description | At approximately 0745 on January 7, 2014, a review of maintenance activities performed on October 3, 2013 on Salem Unit 2, identified an instance in which a High Energy Line Break (HELB) barrier access door was not properly controlled during a Turbine Driven Auxiliary Feedwater Pump room maintenance activity. A HELB event occurring in a room with its barrier door open could adversely affect equipment in an adjacent room. The steam supply to the Turbine Driven Auxiliary Feedwater Pump was not isolated in support of the maintenance activities and the room HELB barrier door was not properly controlled during maintenance in the room. Consequently, a HELB event occurring in the Unit 2 Turbine Driven Auxiliary Feedwater Pump room with the impaired barrier door, could have rendered the Turbine Driven Auxiliary Feed water Pump and both of the Motor Driven Auxiliary Feedwater Pumps in the adjacent room inoperable.
This event is being reported under the requirements of 10 CFR 50.72(b)(3)(ii)(B) as "the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety." An ENS notification is required if an unanalyzed condition occurred within 3 years of the date of discovery even if the event is not on-going at the time of discovery. The Licensee has notified the NRC Resident. The licensee also will notify the Lower Alloways Creek Township. |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+0.45 h0.0188 days <br />0.00268 weeks <br />6.1641e-4 months <br />) | |
| Opened: | Jack Osborne 13:12 Jan 7, 2014 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Jan 7, 2014 |
| 49699 - NRC Website
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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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