ENS 51609
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ENS Event | |
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19:18 Dec 17, 2015 | |
Title | Unusual Event Declared Due to Fire Alarm in Containment Not Verified within 15 Minutes |
Event Description | Unusual Event HU2.1 declared at 1318 [CST]. A fire alarm was received in unit 2 containment at 1307 [CST]. Due to the location of the alarm, personnel were unable to verify the status within 15 minutes. At 1343 [CST], the fire alarm in containment cleared. This alarm came in shortly after a unit 2 reactor trip. The reactor trip was due to a turbine trip. Decay heat removal is via forced circulation with aux feed and steam dumps providing secondary cooling. Offsite power remains available.
The reactor trip was uncomplicated and all control rods inserted. 25B feedwater heater relief valve lifted and has reseated. No offsite assistance was requested. The licensee has notified the NRC Resident Inspector. State and local authorities were notified.
The licensee terminated the NOUE [Notification of Unusual Event] at 1450 CST. The basis for the termination was determination that there was no smoke or fire in the Unit 2 containment observed during containment entry. NRC Resident Inspectors were notified. State and local governments were notified. The health and safety of the public was not at risk. Notified the R3DO (Valos), NRR EO (Morris), IRD (Grant), DHS SWO, FEMA Ops enter, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA. |
Where | |
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Prairie Island Minnesota (NRC Region 3) | |
Reporting | |
Emergency class: | Unusual Event |
10 CFR 50.72(a) (1) (i), Emergency Class Declaration 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+-4.75 h-0.198 days <br />-0.0283 weeks <br />-0.00651 months <br />) | |
Opened: | Wayne Sexson 14:33 Dec 17, 2015 |
NRC Officer: | Dong Park |
Last Updated: | Dec 17, 2015 |
51609 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
After | Hot Standby (0 %) |
Prairie Island with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 574042024-10-29T15:23:00029 October 2024 15:23:00
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Hydrazine Leak in Non-Vital Area of the Turbine Building ENS 443772008-07-31T13:17:00031 July 2008 13:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip During Testing ENS 432802007-04-05T14:08:0005 April 2007 14:08:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip Caused by Spurious Safety Injection During Testing ENS 425042006-04-14T19:25:00014 April 2006 19:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Condensate Pump and Feedwater Pump Trip 2024-03-03T17:42:00 | |
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