ENS 51902
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ENS Event | |
|---|---|
17:01 May 3, 2016 | |
| Title | Anomalies Identified During Visual Inspection of Reactor Vessel Internals |
| Event Description | With Salem Unit One in a defueled condition during a planned refueling outage, anomalies were identified on baffle-former bolts while conducting a scheduled visual inspection of reactor vessel internals. Due to the visual anomalies, PSEG commenced ultrasonic inspection of the baffle-former bolts to determine the extent of condition and determine a repair plan.
Based on initial results of ultrasonic inspections received on May 03, 2016, this condition was determined to be reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B), since the as-found conditions were not previously analyzed. Additional details regarding the extent of condition will be supplied in the 60 day report. The NRC Resident Inspector has been informed. The licensee will notify State and local government agencies as appropriate. |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-0.95 h-0.0396 days <br />-0.00565 weeks <br />-0.0013 months <br />) | |
| Opened: | William Muffley 16:04 May 3, 2016 |
| NRC Officer: | Dong Park |
| Last Updated: | May 3, 2016 |
| 51902 - NRC Website
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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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