ENS 42094
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ENS Event | |
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05:26 Oct 29, 2005 | |
Title | Manual Reactor Trip Following Loss Of Feedwater Pumps |
Event Description | This event is reportable under 10 CFR 50.72 (b)(2)(iv)(B) and 10 CFR 50.72 (b)(3)(iv)(B)(6). During a plant shutdown for a refueling outage at 0126 [EDT] on October 29, a manual reactor trip was initiated in anticipation of Critical Operation on Emergency Feedwater. CR3 [Crystal River Unit 3] experienced an automatic Emergency Feedwater Actuation based upon a loss of both Main Feedwater Pumps. Main Feedwater Pumps tripped on a loss of the running Main Feedwater Booster Pump, which was automatically tripped on low Feedwater De-aerator Tank level. The redundant Main Feedwater Booster Pump was shutdown as part of the plant shutdown sequence. The low Feedwater De-aerator Tank level occurred due to a loss of the operating Condensate Pump while the redundant Condensate Pump was tagged out of service for scheduled maintenance.
The cause of the failed condensate pump that initiated the event sequence is still under investigation but the licensee indicated that it appears to be due to a mechanical failure. The licensee notified the NRC Resident Inspector. |
Where | |
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Crystal River ![]() Florida (NRC Region 2) | |
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:+-0.78 h-0.0325 days <br />-0.00464 weeks <br />-0.00107 months <br />) | |
Opened: | Bill Bandhauer 04:39 Oct 29, 2005 |
NRC Officer: | Bill Huffman |
Last Updated: | Oct 29, 2005 |
42094 - NRC Website
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Unit 3 | |
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Reactor critical | Critical |
Scram | Yes, Manual Scram |
Before | Power Operation (16 %) |
After | Hot Standby (0 %) |
Crystal River ![]() | |
WEEKMONTHYEARENS 490862013-06-02T01:29:0002 June 2013 01:29:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Emergency Diesel Generator ENS 452862009-08-24T15:00:00024 August 2009 15:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Loss of Power to Control Rods ENS 448072009-01-27T15:17:00027 January 2009 15:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Loss of 4160V Bus ENS 444382008-08-24T19:57:00024 August 2008 19:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Feedwater Flow Oscillations ENS 440242008-03-01T09:27:0001 March 2008 09:27:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Feedwater Actuation While Shutting Down ENS 431792007-02-22T00:15:00022 February 2007 00:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on High Rcs Pressure Following a Feedwater Transient ENS 420942005-10-29T05:26:00029 October 2005 05:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following Loss of Feedwater Pumps ENS 410272004-09-08T18:45:0008 September 2004 18:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Feedwater System Actuation ENS 410232004-09-06T15:50:0006 September 2004 15:50:00 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 Partial Loss of Offsite Power ENS 406082004-03-24T08:31:00024 March 2004 08:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip ENS 402992003-11-05T22:34:0005 November 2003 22:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to High Reactor Coolant System Pressure 2013-06-02T01:29:00 | |
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