ENS 41023
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ENS Event | |
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15:50 Sep 6, 2004 | |
Title | Automatic Reactor Trip Following Partial Loss of Offsite Power |
Event Description | At approximately 1150 [EDT], CR3 Site experienced a 230KV 'B' Buss loss. The resultant loss of power was a loss of both non-vital 4160V busses. All RCPs tripped and a reactor trip occurred. The plant is stable on natural circulation cooling.
This report is based on the Reactor Protection System Actuation and Specified System Actuation (Emergency Feedwater). The "B" ESF 4160KV Bus deenergized resulting in an autostart of the "B" EDG, as expected. Natural Circulation has been confirmed with both Steam Generators [SGs] receiving Emergency Feedwater [EFW] via both the Turbine-Driven and Diesel-Driven EFW Pumps. The SGs are using the Atmospheric Dumps to remove decay heat. There was no known SG tube leakage prior to the transient. The cause for the partial loss of offsite power is under investigation. The licensee informed 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:+-3.1 h-0.129 days <br />-0.0185 weeks <br />-0.00425 months <br />) | |
Opened: | Robert Sweeney 12:44 Sep 6, 2004 |
NRC Officer: | Steve Sandin |
Last Updated: | Sep 6, 2004 |
41023 - NRC Website
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Unit 3 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (97 %) |
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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