ENS 52222
ENS Event | |
|---|---|
13:02 Sep 3, 2016 | |
| Title | Unidentified Leakage Greater than Technical Specifications |
| Event Description | At 0902 EDT, on September 3, 2016, a leak developed from 13 Charging Pump seals that resulted in an unidentified leak rate of 1.3 gpm. Salem Unit 1 entered Technical Specification 3.4.6.2.b for unidentified leakage greater than 1 gpm. The Technical Specification requires the leak rate to be restored to below 1 gpm in a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period or place the Unit in Hot Standby in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition there is an allowable total ECCS leakage outside of Containment value of 0.45 gpm associated with Control Room habitability to comply with GDC-19 [General Design Criteria] limits. 12 Charging Pump was placed in service and 13 Charging Pump was removed from service and isolated. The unidentified leak rate lowered to below the 0.45gpm requirement for the total ECCS leakage outside of containment and the Technical Specification value of 1 gpm.
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' for exceeding the 0.45gpm total ECCS leakage allowable in accordance with GDC-19 limitations. The Licensee has notified the NRC Resident and the Lower Alloways Creek Township.
The purpose of this notification is to retract event report number 52222 made on 09/03/2016 at 1247 (EDT). Previously PSEG reported that Salem Unit 1 was in an unanalyzed condition due to a leak from the 13 Charging Pump seals exceeding the 0.45 gpm limit for total ECCS leakage outside containment associated with the Control Room Habitability analysis. A subsequent engineering evaluation determined that the post-accident ECCS leak rate from the 13 Charging Pump seals that would have existed is 0.33 gpm. This is within the limits of the existing Control Room Habitability analysis and no unanalyzed condition existed. 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:+-0.25 h-0.0104 days <br />-0.00149 weeks <br />-3.4245e-4 months <br />) | |
| Opened: | Mike Brummitt 12:47 Sep 3, 2016 |
| NRC Officer: | Steven Vitto |
| Last Updated: | Nov 2, 2016 |
| 52222 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (60 %) |
| After | Power Operation (60 %) |
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 | |