ENS 52294
ENS Event | |
|---|---|
13:38 Oct 11, 2016 | |
| Title | Unanalyzed Condition Due to Failure of a Watertight Door to Close |
| Event Description | At 0938 [EDT], the watertight door in the Unit 1 Inboard Service Water Penetration Area was unable to be closed. The watertight door serves as a High Energy Line Break (HELB) and Medium Energy Line Break (MELB) barrier between the mechanical penetration room and the service water penetration room. A HELB/MELB event occurring in a room with its barrier door open could adversely affect equipment in an adjacent room. Consequently, a HELB/MELB event could have rendered equipment in the adjacent room inoperable.
At 1005, station maintenance was able to successfully close and latch the door restoring the barrier. This event is being reported under the requirements of 10CFR50.72(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 notified Lower Alloways Creek Township and the NRC Resident Inspector.
The purpose of this notification is to retract event report number 52294 made on 10/11/2016 at 1648 (ET). Previously PSEG reported that Salem Unit 1 was determined to be in an unanalyzed condition due to being unable to close the Unit 1 Inboard Service Water Penetration Area Water Tight Door. The watertight door was reported to serve as a High Energy Line Break (HELB) and Medium Energy Line Break (MELB) barrier between the mechanical penetration room and the service water penetration room. Subsequent review identified that the condition did not meet the reporting criterion. Engineering evaluation determined that the service water penetration room had been previously evaluated for the impact due to a HELB event occurring in the adjacent mechanical penetration area with the watertight door open and that the event would not impact the operability of the service system. Engineering evaluation also determined that the Salem Unit 1 Design Basis does not require analysis of a MELB event occurring in the service water penetration room. This is due to the timing of the Unit 1 operating license issue date. At the time of the issuance of the Unit 1 operating license analysis of a MELB event was not required. Therefore an unanalyzed condition for a MELB event did not exist. Additionally while the door was difficult to close, it was able to be closed and dogged in a reasonable time interval (27 minutes), therefore, any potential internal flooding which would have been detected immediately by the attendant with required actions taken to close the door and isolate the leak rapidly. Therefore PSEG is retracting the notification made under 10 CFR 50.72(b)(3)(ii)(B). The NRC Resident Inspector was notified of this retraction by the licensee. Notified R1DO (Schroeder). |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+3.17 h0.132 days <br />0.0189 weeks <br />0.00434 months <br />) | |
| Opened: | Matt Mog 16:48 Oct 11, 2016 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Dec 12, 2016 |
| 52294 - NRC Website
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Unit 1 | |
|---|---|
| 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 | |