Event Notification Report for April 07, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/06/2006 - 04/07/2006
Power Reactor
Event Number: 42482
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MARK ADAMS
HQ OPS Officer: JOE O'HARA
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MARK ADAMS
HQ OPS Officer: JOE O'HARA
Notification Date: 04/07/2006
Notification Time: 17:07 [ET]
Event Date: 04/07/2006
Event Time: 17:07 [EDT]
Last Update Date: 04/12/2006
Notification Time: 17:07 [ET]
Event Date: 04/07/2006
Event Time: 17:07 [EDT]
Last Update Date: 04/12/2006
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):
ANNE MARIE STONE (R3)
ANNE MARIE STONE (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
LOSS OF OFFSITE COMMUNICATION CAPABILITY - PLANNED MAINTENANCE ON SPDS AND ERDS SYSTEMS
"The Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service for planned Preventive Maintenance on the Uninterruptible Power Supply (UPS) system. SPDS and ERDS are scheduled to be restored on 4/9/2006. During this period any out of service indication on the SPDS can be obtained from control board indications. The Emergency Notification System will remain operable. These conditions are reportable in accordance with 10CFR50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. The Reactor is currently defueled while in a refuel outage. Reactor Coolant Temperature is 87 degrees and Div 2 RHR is in shutdown cooling."
The licensee maintains secondary indication capability via control panel indicators.
* * * UPDATE FROM KEVIN DAHM TO HUFFMAN AT 1152 EDT ON 4/12/06 * * *
SPDS and ERDS are now fully functional and have been returned to service as of 1130 EDT on 4/12/06.
The licensee will notify the NRC Resident Inspector. R3DO (Phillips) notified.
"The Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service for planned Preventive Maintenance on the Uninterruptible Power Supply (UPS) system. SPDS and ERDS are scheduled to be restored on 4/9/2006. During this period any out of service indication on the SPDS can be obtained from control board indications. The Emergency Notification System will remain operable. These conditions are reportable in accordance with 10CFR50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. The Reactor is currently defueled while in a refuel outage. Reactor Coolant Temperature is 87 degrees and Div 2 RHR is in shutdown cooling."
The licensee maintains secondary indication capability via control panel indicators.
* * * UPDATE FROM KEVIN DAHM TO HUFFMAN AT 1152 EDT ON 4/12/06 * * *
SPDS and ERDS are now fully functional and have been returned to service as of 1130 EDT on 4/12/06.
The licensee will notify the NRC Resident Inspector. R3DO (Phillips) notified.
Power Reactor
Event Number: 42483
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM CROSSMAN
HQ OPS Officer: PETE SNYDER
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM CROSSMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 04/08/2006
Notification Time: 01:11 [ET]
Event Date: 04/07/2006
Event Time: 22:31 [EDT]
Last Update Date: 04/08/2006
Notification Time: 01:11 [ET]
Event Date: 04/07/2006
Event Time: 22:31 [EDT]
Last Update Date: 04/08/2006
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):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | N | 0 | Hot Standby | 0 | Hot Standby |
GROUP STEP COUNTER FAILURE DURING REACTOR STARTUP
"While in Mode 3 at 547 degrees and 2235 psig in the Reactor Coolant System, during Rod Control System rod drop testing, the group 2, 'A' shutdown bank step counter failed. The step counter is required to be operable in Modes 3, 4 and 5 per [Technical Requirements Manual requirement] 3.1.3 or the reactor trip breakers must be opened within 15 minutes. The step counter failed at 2217 and at 2231 the reactor trip breakers were opened. This was considered a valid actuation of the [Reactor Protection System] due to the [Technical Requirements Manual] requirements and due to the equipment malfunction."
Shutdown margin is adequate and all emergency buses are on offsite power. Emergency Diesel Generators are available.
The licensee notified the NRC Resident Inspector.
"While in Mode 3 at 547 degrees and 2235 psig in the Reactor Coolant System, during Rod Control System rod drop testing, the group 2, 'A' shutdown bank step counter failed. The step counter is required to be operable in Modes 3, 4 and 5 per [Technical Requirements Manual requirement] 3.1.3 or the reactor trip breakers must be opened within 15 minutes. The step counter failed at 2217 and at 2231 the reactor trip breakers were opened. This was considered a valid actuation of the [Reactor Protection System] due to the [Technical Requirements Manual] requirements and due to the equipment malfunction."
Shutdown margin is adequate and all emergency buses are on offsite power. Emergency Diesel Generators are available.
The licensee notified the NRC Resident Inspector.