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Event Notification Report for July 7, 2006

U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/06/2006 - 07/07/2006 ** EVENT NUMBERS ** 42687 Power Reactor Event Number: 42687 Facility: INDIAN POINT Region: 1 State: NY Unit: [ ] [3] [ ] RX Type: [2] W-4-LP,[3] W-4-LP NRC Notified By: PHIL SANTINI HQ OPS Officer: ARLON COSTA Notification Date: 07/06/2006 Notification Time: 04:25 [ET] Event Date: 07/06/2006 Event Time: 03:52 [EDT] Last Update Date: 07/06/2006 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization): PAMELA HENDERSON (R1) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 3 A/R Y 100 Power Operation 0 Hot Standby Event Text REACTOR TRIP DUE TO GENERATOR DIFFERENTIAL "Indian Point Unit 3 tripped on Generator Differential (Direct Generator Trip). Current conditions are stable, mode 3 operation with all automatic actions occurring properly. Steam Generators levels are stable on aux. feed water. "Unit 2 was unaffected by the trip." All control rods inserted fully and decay heat is being removed via steam dump to the condenser. All required safety related systems are working properly and the electrical buses and diesel generators are in their normal alignment. The licensee will notify the NRC Resident Inspector. * * * UPDATE AT 0938 ON 07/06/08 B. ROKES TO W. GOTT * * * "The Auxiliary Feedwater System actuated and the Auxiliary Feedwater Pump started as designed due to the reactor trip. The actuation of the Auxiliary Feedwater System was the result of Steam Generator shrink/swell effect due to the reactor trip at full power. The actuation of the Auxiliary Feedwater System is an eight-hour non-emergency event reportable under 10 CFR 50.72(b)(3)(iv)." The licensee will notify the NRC Resident Inspector. Notified R1DO (P. Henderson)

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