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| Entered date | Event description | |
|---|---|---|
| ENS 45306 | 27 August 2009 21:40:00 | At 1945 on 8/27/09 Indian Point Unit #3 automatically tripped due to a turbine trip signal. The cause for this automatic trip is under investigation. All auxiliary feedwater pumps started as expected. All control rods inserted as expected. Currently, Indian Point #3 is in Mode 3. The reactor coolant system is at Normal Operating Temperature, Pressure and Level. Offsite power is available and supplying all safeguards busses. Heat removal is to the main condenser via the steam dumps. Indian Point Unit 2 is unaffected and remains in Mode 1 at 100% power. The (NRC) Resident Inspector has been notified. |
| ENS 42720 | 21 July 2006 11:06:00 | At 1031 hours on July 21, 2006, the reactor operator manually tripped the reactor from 100% power resulting in turbine trip and actuation of auxiliary feedwater. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). 31 Reactor Coolant Pump tripped after the reactor trip. All other systems operated as expected. Steam is being condensed by the condenser. The reactor was tripped due to an abnormal condition under the main generator; electrical arcing/sparking was observed. The reactor will remain shutdown until the cause of the arcing/sparking is identified and corrected. There was no indication of fire but the fire brigade was called out. The observed arcing and sparking from underneath the main generator secured after the turbine trip. All control rods fully inserted on the reactor trip. The electric plant is in a normal shutdown lineup and the EDGs are operable. The unit is stable and Unit 2 was not affected. The licensee notified the NRC Resident Inspector and the New York Public Service Commission.
Licensee reported the AFW actuation as a Specified System Actuation per 10 CFR 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector. Notified the R1DO (Kinneman) |