Nuclear Reactor In Ga. Shuts Down Abruptly

AI Thread Summary
Vogtle Unit 1 in Georgia experienced an automatic reactor trip on April 20, 2011, while operating at 100% power, with no significant activities challenging the Reactor Protection System at the time. The reactor trip was classified as a non-emergency event, and all control rods were fully inserted, allowing for a stable plant response. Auxiliary feedwater systems were activated as expected, and the plant remained in Mode 3 during the investigation into the cause, which is believed to be a defective breaker. The incident is considered a level 0 on the International Nuclear Event Scale (INES), indicating no significant safety implications. The plant has since returned to operation and is back up to full power.
javadave
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http://www.cbsatlanta.com/news/27633540/detail.html?utm_source=twitterfeed&utm_medium=twitter

Does anybody have any further information on current status of this reactor in GA?
 
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Engineering news on Phys.org
this cannot be good news.
 
javadave said:
http://www.cbsatlanta.com/news/27633540/detail.html?utm_source=twitterfeed&utm_medium=twitter

Does anybody have any further information on current status of this reactor in GA?

http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2011/20110421en.html

Power Reactor Event Number: 46772
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL DUNN
HQ OPS Officer: MARK ABRAMOVITZ Notification Date: 04/20/2011
Notification Time: 20:45 [ET]
Event Date: 04/20/2011
Event Time: 17:34 [EDT]
Last Update Date: 04/20/2011
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):
JONATHAN BARTLEY (R2DO)


Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP

"At 1734 EDT, [Vogtle] unit one automatically tripped from 100% power. No significant activities were in progress that should have challenged the Reactor Protection System. All control rods fully inserted. AFW system actuated as expected on S/G Lo-Lo-Level and AMSAC [ATWS Mitigation System Actuation]. System responses allowed for an uncomplicated reactor trip response. Plant is stable and will remain in Mode 3 during cause investigation.

"Cause of the reactor trip is under investigation."

The plant is in its normal shutdown electrical lineup. Decay heat is being sent to the main condenser through the turbine bypass valves. The steam generators are being fed from auxiliary feedwater. There was no effect on unit two.

The licensee informed the NRC Resident Inspector.
 
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NUCENG said:
[URL]http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2011/20110421en.html

Power Reactor Event Number: 46772
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL DUNN
HQ OPS Officer: MARK ABRAMOVITZ Notification Date: 04/20/2011
Notification Time: 20:45 [ET]
Event Date: 04/20/2011
Event Time: 17:34 [EDT]
Last Update Date: 04/20/2011
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):
JONATHAN BARTLEY (R2DO)


Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP

"At 1734 EDT, [Vogtle] unit one automatically tripped from 100% power. No significant activities were in progress that should have challenged the Reactor Protection System. All control rods fully inserted. AFW system actuated as expected on S/G Lo-Lo-Level and AMSAC [ATWS Mitigation System Actuation]. System responses allowed for an uncomplicated reactor trip response. Plant is stable and will remain in Mode 3 during cause investigation.

"Cause of the reactor trip is under investigation."

The plant is in its normal shutdown electrical lineup. Decay heat is being sent to the main condenser through the turbine bypass valves. The steam generators are being fed from auxiliary feedwater. There was no effect on unit two.

The licensee informed the NRC Resident Inspector.

Thanks! So would this be considered a level 0 on INES?
 
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javadave said:
Thanks! So would this be considered a level 0 on INES?
More or less. It could be a spurious trip.

The plant shutdown as intended, and the decay heat is being removed as expected.

They will perform a root cause investigation of the trip. Standard operating procedure.
 
Astronuc said:
More or less. It could be a spurious trip.

The plant shutdown as intended, and the decay heat is being removed as expected.

They will perform a root cause investigation of the trip. Standard operating procedure.

Thanks Astronuc!
 
Reactor trips are not an unusual occurrence. There are a number of possible things that can cause a spurious trip. E.g. lightning strikes, tin whiskers, who knows.
 
QuantumPion said:
There are a number of possible things that can cause a spurious trip. E.g. lightning strikes, tin whiskers, who knows.
tin whiskers: hurray for ROHS... on nuclear power plant equipment.
Wouldn't it be a good idea to solder such stuff using good ol 67% tin 33% lead? No whiskers with that, greater metal strength, and this is not ipods that are replaced with new ipods every year.
 
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