ENS 51663
ENS Event | |
|---|---|
21:30 Jan 19, 2016 | |
| Title | Unanalyzed Condition Discovered During Review of Outage Data |
| Event Description | On January 19, 2016, while reviewing outage data, plant staff recognized that anomalous data collected in October, 2015, for the 21 Auxiliary Feed Pump time response loop resulted in an unanalyzed condition. Preliminary investigation has revealed that the condition most likely existed since April 20, 2015, when maintenance activities were performed on the auxiliary feedwater pump discharge pressure transmitter. Consequently, there were multiple instances when one of the other auxiliary feedwater pumps was removed from service, thus creating a condition which did not meet the accident analysis assumptions for auxiliary feedwater flow initial response.
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.' This condition was corrected on November 20, 2015. The auxiliary feedwater pump discharge pressure transmitter instrument isolation valve was inadvertently left closed after the April 20, 2015 maintenance. The licensee has notified the NRC Resident Inspector and will notify the State of New Jersey, State of Delaware, and the local township.
This event is being retracted. An engineering review determined that while the auxiliary feedwater flow loop response time test results did not meet the procedural acceptance criteria, the accident analysis assumptions remained valid. The ATWS [Anticipated Transient Without Scram] was the limiting accident, and the loop response time results were still bounded by the existing analyses. The failed loop response time did result in a condition prohibited by TS which will be reported in a Licensee Event Report (LER). This condition has been documented in the licensee's Corrective Action Program. The licensee has notified the NRC Resident Inspector. Notified R1DO (Dimitriadis). |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-3.8 h-0.158 days <br />-0.0226 weeks <br />-0.00521 months <br />) | |
| Opened: | Thomas Mulholland 17:42 Jan 19, 2016 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Mar 10, 2016 |
| 51663 - 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 | |