ENS 43196
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ENS Event | |
|---|---|
05:33 Feb 28, 2007 | |
| Title | Reactor Trip During the Performance of a Surveillance |
| Event Description | On 2/27/2007 at 2333 CST a Reactor Trip occurred during performance of a surveillance procedure calibrating a Nuclear Power Range instrument. The Reactor trip resulted in an automatic Turbine Trip and actuation of the Auxiliary Feedwater System. No safeguards equipment was out of service at the time of the trip. Following the trip, a steam inlet valve on a Moisture Separator associated with the main turbine failed to close which resulted in RCS temperature decreasing to 537 degF. This valve was manually isolated and RCS temperature returned to normal 547 degF. Normal heat sink to the Main Condenser was available during the event. Investigation is continuing into the exact cause of the Reactor trip.
This event is being reported under 10CFR50.72(b)(2)(iv)(B) for actuation of the Reactor Protection System and 10CFR50.72(b)(3)(iv)(A) for actuation of the Auxiliary Feedwater System. All control rods fully inserted on the reactor trip. Decay heat is being removed by Auxiliary Feedwater feeding the steam generators, steaming to the main condenser. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Kewaunee  Wisconsin (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-3.48 h-0.145 days <br />-0.0207 weeks <br />-0.00477 months <br />) | |
| Opened: | Al Prokash 02:04 Feb 28, 2007 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Feb 28, 2007 |
| 43196 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Kewaunee with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 466662011-03-10T21:49:00010 March 2011 21:49:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Inadvertant Opening a Substation Breaker Causing Loss of Station Power ENS 454382009-10-15T17:04:00015 October 2009 17:04:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Momentary Loss of Shutdown Cooling with Autostart of Emergency Diesel Generator ENS 431962007-02-28T05:33:00028 February 2007 05:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip During the Performance of a Surveillance ENS 430962007-01-12T16:39:00012 January 2007 16:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip/Reactor Trip ENS 429832006-11-10T20:20:00010 November 2006 20:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip at Low Power ENS 429472006-10-30T14:48:00030 October 2006 14:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip ENS 425302006-04-27T01:49:00027 April 2006 01:49:00 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 Failure of Rps Signal to Initiate Reactor Trip ENS 421732005-11-29T04:20:00029 November 2005 04:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Main Feed Pump Trip ENS 414252005-02-20T17:58:00020 February 2005 17:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation on Steam Generator Low Level 2011-03-10T21:49:00 | |
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