Event Notification Report for July 10, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/09/2007 - 07/10/2007
EVENT NUMBERS
43479
Power Reactor
Event Number: 43479
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/10/2007
Notification Time: 22:55 [ET]
Event Date: 07/10/2007
Event Time: 19:54 [EDT]
Last Update Date: 07/10/2007
Notification Time: 22:55 [ET]
Event Date: 07/10/2007
Event Time: 19:54 [EDT]
Last Update Date: 07/10/2007
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN ROGGE (R1)
JOHN ROGGE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 50 | Power Operation | 0 | Hot Shutdown |
MAIN TURBINE TRIP CAUSING A REACTOR SCRAM
"During a planned power reduction to support thermal backwash of the main condenser, an automatic reactor scram resulted from a main turbine trip. The cause for the turbine trip is currently under investigation. Following the reactor scram, the expected reactor level shrink resulted in valid group 2, Reactor Building Ventilation, and group 6, Reactor Water Cleanup System isolations. All safety systems and equipment functioned as designed. A schedule for plant restart has not yet been determined."
All control rods fully inserted and no safety relief valves lifted from the scram. Minimum level after the scram was -10 inches.
Decay heat is being removed using the main turbine bypass valves to the main condenser and maintaining level using normal reactor feed water. The plant is using the normal shut down electrical lineup and slowly cooling down (currently at 820 psi).
The licensee notified the NRC Resident Inspector.
"During a planned power reduction to support thermal backwash of the main condenser, an automatic reactor scram resulted from a main turbine trip. The cause for the turbine trip is currently under investigation. Following the reactor scram, the expected reactor level shrink resulted in valid group 2, Reactor Building Ventilation, and group 6, Reactor Water Cleanup System isolations. All safety systems and equipment functioned as designed. A schedule for plant restart has not yet been determined."
All control rods fully inserted and no safety relief valves lifted from the scram. Minimum level after the scram was -10 inches.
Decay heat is being removed using the main turbine bypass valves to the main condenser and maintaining level using normal reactor feed water. The plant is using the normal shut down electrical lineup and slowly cooling down (currently at 820 psi).
The licensee notified the NRC Resident Inspector.