ENS 44438
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ENS Event | |
|---|---|
19:57 Aug 24, 2008 | |
| Title | Manual Reactor Trip Due to Feedwater Flow Oscillations |
| Event Description | The 'A' Condensate Pump became uncoupled, lowering Condensate flow. Operators began to manually lower reactor power to maintain deaerator level. Reactor power was lowered to approximately 62 percent. At this power, [feedwater] flow oscillations began and were excessive. With these flow oscillations increasing the decision was made to manually trip the Reactor. The Reactor was manually tripped at 1557 hours0.018 days <br />0.433 hours <br />0.00257 weeks <br />5.924385e-4 months <br />. There were no safety system actuations other than RPS (Manual). The plant is stable in a normal post trip configuration.
All control rods inserted into the core during the reactor trip. Offsite power is available and powering safety loads. The steam generator safeties lifted during the transient and reseated. There is no known primary to secondary leakage. Decay heat is being removed via steam dumps to the condenser using normal feedwater to the steam generator. The emergency feedwater system was not initiated during the reactor trip. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Crystal River  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.9 h-0.0792 days <br />-0.0113 weeks <br />-0.0026 months <br />) | |
| Opened: | William Kisner 18:03 Aug 24, 2008 |
| NRC Officer: | Vince Klco |
| Last Updated: | Aug 24, 2008 |
| 44438 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 452862009-08-24T15:00:00024 August 2009 15:00:00
[Table view]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 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 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 2009-08-24T15:00:00 | |
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