Event Notification Report for November 12, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/11/2012 - 11/12/2012
Power Reactor
Event Number: 48502
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/12/2012
Notification Time: 14:13 [ET]
Event Date: 11/12/2012
Event Time: 11:00 [EST]
Last Update Date: 11/12/2012
Notification Time: 14:13 [ET]
Event Date: 11/12/2012
Event Time: 11:00 [EST]
Last Update Date: 11/12/2012
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):
MARVIN SYKES (R2DO)
MARVIN SYKES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER INOPERABLE NUMEROUS TIMES OVER PREVIOUS THREE YEARS WITHOUT PROPER REPORTING
"This non-emergency event report is being made per 10CFR50.72(a)(1)(ii) which requires reporting events that occurred within three years of the date of discovery.
"Based on operating experience, Engineering personnel reviewed past maintenance activities involving the Technical Support Center (TSC) ventilation system (VH system) and identified 11 occasions between September 2009 and October 2012 (3 years) where the VH system functions could not have been restored within the required facility activation time. The specific instances have been documented in our corrective action program.
"If an emergency had been declared during these periods and TSC ERO activation was required, the TSC would have been staffed and activated unless the TSC became uninhabitable due to ambient temperatures, radiological or other conditions. If relocation of the TSC staff was necessary, the Station Emergency Coordinator would relocate the staff to an alternate TSC location.
"Practices and processes have been revised to improve control of TSC maintenance activities and to improve facility availability going forward. In addition, site reporting guidance has been revised to assure timely reporting of these types of events if required.
"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2, since the maintenance activities affected an emergency response facility."
The licensee will be notifying the NRC Resident Inspector and state and local authorities in North Carolina and South Carolina.
"This non-emergency event report is being made per 10CFR50.72(a)(1)(ii) which requires reporting events that occurred within three years of the date of discovery.
"Based on operating experience, Engineering personnel reviewed past maintenance activities involving the Technical Support Center (TSC) ventilation system (VH system) and identified 11 occasions between September 2009 and October 2012 (3 years) where the VH system functions could not have been restored within the required facility activation time. The specific instances have been documented in our corrective action program.
"If an emergency had been declared during these periods and TSC ERO activation was required, the TSC would have been staffed and activated unless the TSC became uninhabitable due to ambient temperatures, radiological or other conditions. If relocation of the TSC staff was necessary, the Station Emergency Coordinator would relocate the staff to an alternate TSC location.
"Practices and processes have been revised to improve control of TSC maintenance activities and to improve facility availability going forward. In addition, site reporting guidance has been revised to assure timely reporting of these types of events if required.
"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2, since the maintenance activities affected an emergency response facility."
The licensee will be notifying the NRC Resident Inspector and state and local authorities in North Carolina and South Carolina.
Power Reactor
Event Number: 48503
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MATTHEW QUICK
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MATTHEW QUICK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/12/2012
Notification Time: 20:52 [ET]
Event Date: 11/12/2012
Event Time: 15:51 [CST]
Last Update Date: 11/12/2012
Notification Time: 20:52 [ET]
Event Date: 11/12/2012
Event Time: 15:51 [CST]
Last Update Date: 11/12/2012
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):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
REACTOR BUILDING ISOLATION WITH STANDBY GAS TREATMENT SYSTEM ACTUATION DURING RADIOACTIVE MATERIAL MOVE
"At 1551 EST on 11/12/12, the 'A' Refuel Floor Process Radiation Monitor reached 62 mR/hr during movement of the old steam dryer in the plant reactor building. This resulted in the isolation of the drywell containment air monitor and the oxygen analyzer primary containment isolation valves. The signal also resulted in a reactor building isolation (Secondary Containment), start of 'A' Standby Gas Treatment, and transfer of the control room ventilation to the High Radiation Mode.
"All automatic isolation valves have been reset. Reactor building and control room ventilation have been reset. Standby gas treatment has been secured. There were no challenges to the health and safety of the general public.
"The NRC Resident Inspector has been notified."
"At 1551 EST on 11/12/12, the 'A' Refuel Floor Process Radiation Monitor reached 62 mR/hr during movement of the old steam dryer in the plant reactor building. This resulted in the isolation of the drywell containment air monitor and the oxygen analyzer primary containment isolation valves. The signal also resulted in a reactor building isolation (Secondary Containment), start of 'A' Standby Gas Treatment, and transfer of the control room ventilation to the High Radiation Mode.
"All automatic isolation valves have been reset. Reactor building and control room ventilation have been reset. Standby gas treatment has been secured. There were no challenges to the health and safety of the general public.
"The NRC Resident Inspector has been notified."