Event Notification Report for November 01, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/31/2001 - 11/01/2001
EVENT NUMBERS
38457
Power Reactor
Event Number: 38457
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: ALAN SMITH
HQ OPS Officer: STEVE SANDIN
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: ALAN SMITH
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/01/2001
Notification Time: 15:13 [ET]
Event Date: 11/01/2001
Event Time: 12:30 [CST]
Last Update Date: 11/01/2001
Notification Time: 15:13 [ET]
Event Date: 11/01/2001
Event Time: 12:30 [CST]
Last Update Date: 11/01/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 22 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DURING CEA TROUBLESHOOTING FOR REASONS UNKNOWN
"While operating at full power at approximately 1010 CST on 11/01/2001, Control Element Assembly (CEA) 43 dropped into the core for unknown reasons. Reduction of reactor power began at approximately 1017. With reactor power stable at approximately 22 percent, troubleshooting of the cause of the CEA-43 drop was in progress at approximately 1230 CST when an automatic reactor trip occurred. The reason for the trip is unknown. Plant response to the trip was normal and uncomplicated. All CEAs fully inserted. There were no ESF system actuations. The plant is stable in Hot Standby (Mode 3) conditions with decay heat being removed via the Steam Generators to the Main Condenser. No radiation releases occurred."
The licensee informed the state and NRC Resident Inspector.
"While operating at full power at approximately 1010 CST on 11/01/2001, Control Element Assembly (CEA) 43 dropped into the core for unknown reasons. Reduction of reactor power began at approximately 1017. With reactor power stable at approximately 22 percent, troubleshooting of the cause of the CEA-43 drop was in progress at approximately 1230 CST when an automatic reactor trip occurred. The reason for the trip is unknown. Plant response to the trip was normal and uncomplicated. All CEAs fully inserted. There were no ESF system actuations. The plant is stable in Hot Standby (Mode 3) conditions with decay heat being removed via the Steam Generators to the Main Condenser. No radiation releases occurred."
The licensee informed the state and NRC Resident Inspector.