Event Notification Report for June 11, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/10/2013 - 06/11/2013
Power Reactor
Event Number: 49105
Facility: MILLSTONE
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JOHN CLAIRE
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JOHN CLAIRE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/11/2013
Notification Time: 13:09 [ET]
Event Date: 06/11/2013
Event Time: 10:18 [EDT]
Last Update Date: 06/11/2013
Notification Time: 13:09 [ET]
Event Date: 06/11/2013
Event Time: 10:18 [EDT]
Last Update Date: 06/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GLENN DENTEL (R1DO)
GLENN DENTEL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
RADIATION MONITOR OUT-OF-SERVICE FOR PLANNED MAINTENANCE
The licensee removed the Spent Fuel Pool Island Radiation Monitor from service for pre-planned maintenance to change the air filter. The radiation monitor was returned to service at 1030 EDT.
The licensee notified the NRC Resident Inspector, state and local authorities.
The licensee removed the Spent Fuel Pool Island Radiation Monitor from service for pre-planned maintenance to change the air filter. The radiation monitor was returned to service at 1030 EDT.
The licensee notified the NRC Resident Inspector, state and local authorities.
Power Reactor
Event Number: 49106
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WILLIAM ARENS
HQ OPS Officer: CHARLES TEAL
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WILLIAM ARENS
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/12/2013
Notification Time: 01:33 [ET]
Event Date: 06/11/2013
Event Time: 21:05 [CDT]
Last Update Date: 06/12/2013
Notification Time: 01:33 [ET]
Event Date: 06/11/2013
Event Time: 21:05 [CDT]
Last Update Date: 06/12/2013
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 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
FRANK EHRHARDT (R2DO)
FRANK EHRHARDT (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 |
UNIT 1 AUTOMATIC REACTOR TRIP DUE TO THE LOSS OF A START-UP TRANSFORMER
"This is a report of an automatic RPS actuation and automatic ESF actuation per 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). Additionally, this is to report intentions for a press release per 10CFR50.72(b)(2)(xi).
"At 2105 CDT on 6/11/13, Farley Unit 1 experienced an automatic reactor trip from 100% power. The initiating event was the loss of the 1B Start up Transformer which resulted in de-energization of the B-Train ESF 4KV buses and the 1B and 1C Reactor Coolant Pump Buses. The 1B Emergency Diesel Generator auto started and tied to the B-Train 4KV Emergency buses.
"Both MDAFW (Motor Driven Auxiliary Feedwater) Pumps and the TDAFW (Turbine Driven Auxiliary Feedwater) Pump auto-started and are supplying AFW flow to the steam generators. Decay heat removal is via the steam dumps to the main condenser.
"The cause of the loss of the 1B Start-up Transformer is unknown and is currently under investigation. All other systems functioned as expected in response to the loss of the 1B Start-up Transformer and reactor trip.
"The NRC Senior Resident Inspector has been notified.
"A press release is planned."
All control rods fully inserted. There is no impact on Unit 2. Currently the licensee does not plan to restart the 1B and 1C Reactor Coolant Pumps. Pressurizer spray has been isolated from the 1B loop per procedure. Main Condenser vacuum is adequate for decay heat removal.
"This is a report of an automatic RPS actuation and automatic ESF actuation per 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). Additionally, this is to report intentions for a press release per 10CFR50.72(b)(2)(xi).
"At 2105 CDT on 6/11/13, Farley Unit 1 experienced an automatic reactor trip from 100% power. The initiating event was the loss of the 1B Start up Transformer which resulted in de-energization of the B-Train ESF 4KV buses and the 1B and 1C Reactor Coolant Pump Buses. The 1B Emergency Diesel Generator auto started and tied to the B-Train 4KV Emergency buses.
"Both MDAFW (Motor Driven Auxiliary Feedwater) Pumps and the TDAFW (Turbine Driven Auxiliary Feedwater) Pump auto-started and are supplying AFW flow to the steam generators. Decay heat removal is via the steam dumps to the main condenser.
"The cause of the loss of the 1B Start-up Transformer is unknown and is currently under investigation. All other systems functioned as expected in response to the loss of the 1B Start-up Transformer and reactor trip.
"The NRC Senior Resident Inspector has been notified.
"A press release is planned."
All control rods fully inserted. There is no impact on Unit 2. Currently the licensee does not plan to restart the 1B and 1C Reactor Coolant Pumps. Pressurizer spray has been isolated from the 1B loop per procedure. Main Condenser vacuum is adequate for decay heat removal.