Event Notification Report for May 04, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/03/2014 - 05/04/2014
EVENT NUMBERS
50097
Power Reactor
Event Number: 50097
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: ROBERT W. OESTERLE
HQ OPS Officer: DONG HWA PARK
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: ROBERT W. OESTERLE
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/08/2014
Notification Time: 17:46 [ET]
Event Date: 05/04/2014
Event Time: 08:32 [EDT]
Last Update Date: 05/08/2014
Notification Time: 17:46 [ET]
Event Date: 05/04/2014
Event Time: 08:32 [EDT]
Last Update Date: 05/08/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
MANUAL INITIATION OF THE REACTOR PROTECTION SYSTEM WHILE SHUTDOWN
"On 5/4/14 while the plant was in Mode 3 and the reactor not critical, unexpected position indications were observed on a Control Rod while withdrawing an Axial Power Shaping Rod (APSR). Due to the uncertainty of rod positions, the APSR was inserted into the core. The reactor trip breakers were then opened from the Control Room using the manual trip pushbuttons. All Control and Safety Rods were unlatched and fully inserted into the reactor core before the reactor trip breakers were opened.
"This manual initiation of the Reactor Protection System with the reactor not critical is being reported per 10 CFR 50.72(b)(3)(iv)(A). The reportability of this event was determined based on an extent of condition review for Event Number 50086 that occurred 5/5/14. The failure to meet the 8-hour reporting requirement has been entered into the Corrective Action Program."
The licensee notified the NRC Resident Inspector, the State of Ohio, and Ottawa and Lucas Counties.
"On 5/4/14 while the plant was in Mode 3 and the reactor not critical, unexpected position indications were observed on a Control Rod while withdrawing an Axial Power Shaping Rod (APSR). Due to the uncertainty of rod positions, the APSR was inserted into the core. The reactor trip breakers were then opened from the Control Room using the manual trip pushbuttons. All Control and Safety Rods were unlatched and fully inserted into the reactor core before the reactor trip breakers were opened.
"This manual initiation of the Reactor Protection System with the reactor not critical is being reported per 10 CFR 50.72(b)(3)(iv)(A). The reportability of this event was determined based on an extent of condition review for Event Number 50086 that occurred 5/5/14. The failure to meet the 8-hour reporting requirement has been entered into the Corrective Action Program."
The licensee notified the NRC Resident Inspector, the State of Ohio, and Ottawa and Lucas Counties.