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Event Notification Report for July 7, 2006
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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/06/2006 - 07/07/2006
** EVENT NUMBERS **
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| 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
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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
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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
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Person (Organization):
PAMELA HENDERSON (R1)
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| 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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