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Event Notification Report for October 18, 2005
U.S. Nuclear Regulatory Commission Operations Center
Event Reports For 10/17/2005 - 10/18/2005
** EVENT NUMBERS **
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Power Reactor |
Event Number: 42058 |
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARK SLIVKA
HQ OPS Officer: ARLON COSTA
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Notification Date: 10/17/2005
Notification Time: 19:18 [ET]
Event Date: 10/17/2005
Event Time: 18:16 [EDT]
Last Update Date: 10/17/2005
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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):
THOMAS DECKER (R2)
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Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
M/R |
Y |
100 |
Power Operation |
0 |
Hot Standby |
Event Text
MANUAL REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL
"At 1816 EDT on 10/17/2005 Vogtle Unit 1 was manually tripped from 100% power due to lowering Steam Generator level on Loop 2. The Main Feedwater Regulating Valve for Loop 2 failed closed and operator attempts to re-open it were unsuccessful. The operators initiated a manual reactor trip when it was apparent that Steam Generator level would not be restored. Following the manual reactor trip, an automatic actuation of the Motor Driven and Turbine Driven Auxiliary Feedwater Pumps occurred due to low level in the Steam Generators. The Main Feedwater Regulating Valve for Loop 1 did not close as expected for the feedwater isolation signal (P-4 / Tavg 564 degrees F) that resulted from the manual trip. The Loop 1 Main Feedwater Regulating Valve was manually closed by the operators. All control rods are fully inserted."
This incident did not affect Unit 2. Unit 1 is stable in Mode 3 and removing heat by dumping steam to the condensers. All safety related systems or equipment are available and functioning as required.
The licensee notified the NRC Resident Inspector. |
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