ENS Event | |
|---|---|
14:45 May 17, 2016 | |
| Title | Reactor Coolant Leakage with the Reactor in Cold Shutdown |
| Event Description | On May 17, 2016 with the plant in Mode 4 [Cold Shutdown] during a refueling outage, personnel entered the drywell to perform a walkdown. At 0945 CDT, water was identified leaking from flexible hoses located at the inner elbow of MSL [Main Steam Line] B and MSL C. It was concluded that the leakage was from an elbow tap welded to the flexible hoses associated with flow instrumentation on MSL C and MSL B. Due to the refueling outage, the plant subsequently entered Mode 5 at 0955 and is currently in Mode 5 [Refueling] and 0 percent rated thermal power. The degraded component on MSL B was previously replaced in 2008 and on MSL C in 2007. The station has determined that this event is reportable under the provisions of 10 CFR 50.72 (b)(3)(ii)(A) as an event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded, as an 8-hour notification.
The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Clinton  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.97 h0.165 days <br />0.0236 weeks <br />0.00544 months <br />) | |
| Opened: | Dale Shelton 18:43 May 17, 2016 |
| NRC Officer: | Richard Smith |
| Last Updated: | May 17, 2016 |
| 51939 - NRC Website
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WEEKMONTHYEARENS 533032018-03-30T18:05:00030 March 2018 18:05:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Declared Inoperable Due to Both Airlock Doors Open Simultaneously ENS 527502017-05-12T05:45:00012 May 2017 05:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Main Steam Isolation Valves Exceeded Primary Containment Local Leak Rate Acceptance Criteria ENS 519392016-05-17T14:45:00017 May 2016 14:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant Leakage with the Reactor in Cold Shutdown ENS 456762010-02-03T17:00:0003 February 2010 17:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Feedwater Check Valve Leak Rate Exceeded Technical Specification Requirement ENS 434302007-06-19T11:35:00019 June 2007 11:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Tech Spec Required Shutdown Due to Instrument Line Steam Leak 2018-03-30T18:05:00 | |