Event Notification Report for July 03, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/02/2012 - 07/03/2012
Power Reactor
Event Number: 48069
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: THOMAS MORSE
HQ OPS Officer: DONG HWA PARK
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: THOMAS MORSE
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/03/2012
Notification Time: 20:35 [ET]
Event Date: 07/03/2012
Event Time: 17:38 [EDT]
Last Update Date: 07/03/2012
Notification Time: 20:35 [ET]
Event Date: 07/03/2012
Event Time: 17:38 [EDT]
Last Update Date: 07/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (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 |
INADVERTENT EMERGENCY SIREN ACTUATION
"This event is being reported in accordance with 10CFR50.72(b)(2)(xi). On July 3, 2012, at approximately 1738 hours, an inadvertent actuation of the Perry Nuclear Power Plant's (PNPP) alert notification system occurred. Seventy-five of seventy-six sirens sounded for three minutes, affecting Ashtabula, Geauga, and Lake Counties. Following the actuation, county agencies received calls from members of the public.
"PNPP's capability to notify the public in an emergency has been retained. The siren actuation was not related to any condition or event at the PNPP. An investigation is in progress to determine the cause of the inadvertent actuation. At the time of the event, the plant was in Mode 1 at 100 percent rated thermal power.
"The public was informed of the inadvertent actuation by way of the Emergency Alert System (EAS).
"The NRC Resident Inspector has been notified."
The licensee has notified State and Local agencies.
"This event is being reported in accordance with 10CFR50.72(b)(2)(xi). On July 3, 2012, at approximately 1738 hours, an inadvertent actuation of the Perry Nuclear Power Plant's (PNPP) alert notification system occurred. Seventy-five of seventy-six sirens sounded for three minutes, affecting Ashtabula, Geauga, and Lake Counties. Following the actuation, county agencies received calls from members of the public.
"PNPP's capability to notify the public in an emergency has been retained. The siren actuation was not related to any condition or event at the PNPP. An investigation is in progress to determine the cause of the inadvertent actuation. At the time of the event, the plant was in Mode 1 at 100 percent rated thermal power.
"The public was informed of the inadvertent actuation by way of the Emergency Alert System (EAS).
"The NRC Resident Inspector has been notified."
The licensee has notified State and Local agencies.
Power Reactor
Event Number: 48066
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/03/2012
Notification Time: 13:21 [ET]
Event Date: 07/03/2012
Event Time: 09:40 [EDT]
Last Update Date: 07/03/2012
Notification Time: 13:21 [ET]
Event Date: 07/03/2012
Event Time: 09:40 [EDT]
Last Update Date: 07/03/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ROBERT DALEY (R3DO)
MARK KING (NRR)
JANE MARSHALL (IRD)
ROBERT DALEY (R3DO)
MARK KING (NRR)
JANE MARSHALL (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
OFFSITE NOTIFICATION DUE TO A FATALITY
"At 0940 hours on July 3, 2012, Detroit Edison notified the Michigan Occupational Safety and Health Administration (MIOSHA) that an employee had suffered a fatality.
"On July 2, 2012, at 1504 hours, a Detroit Edison employee reported to the nurse's office with symptoms of shortness of breath and chest pain. The individual was transported offsite via ambulance to a local hospital for care. At approximately 1700 hours on July 2, 2012, notification was received that the individual had passed away.
"There was no radioactive contamination involved in this event. The licensee has not notified any other government agencies besides MIOSHA.
"This ENS report is being made in accordance with 50.72(b)(2)(xi). The NRC Resident Inspector was notified."
"At 0940 hours on July 3, 2012, Detroit Edison notified the Michigan Occupational Safety and Health Administration (MIOSHA) that an employee had suffered a fatality.
"On July 2, 2012, at 1504 hours, a Detroit Edison employee reported to the nurse's office with symptoms of shortness of breath and chest pain. The individual was transported offsite via ambulance to a local hospital for care. At approximately 1700 hours on July 2, 2012, notification was received that the individual had passed away.
"There was no radioactive contamination involved in this event. The licensee has not notified any other government agencies besides MIOSHA.
"This ENS report is being made in accordance with 50.72(b)(2)(xi). The NRC Resident Inspector was notified."
Power Reactor
Event Number: 48067
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM ANDERSON
HQ OPS Officer: DONG HWA PARK
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM ANDERSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/03/2012
Notification Time: 16:53 [ET]
Event Date: 07/03/2012
Event Time: 10:32 [EDT]
Last Update Date: 07/03/2012
Notification Time: 16:53 [ET]
Event Date: 07/03/2012
Event Time: 10:32 [EDT]
Last Update Date: 07/03/2012
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):
JONATHAN BARTLEY (R2DO)
JONATHAN BARTLEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 98 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 99 | Power Operation |
TSC OUTAGE RESULTING FROM MAINTENANCE
"Planned maintenance activities are being performed today (July 3, 2012) to remove temporary power from and restore normal power to the Technical Support Center (TSC) 480 VAC Distribution Panel 1R25-S012. This panel provides power to the TSC Emergency HVAC (TSC air handling unit, TSC condensing unit, TSC filter train and the fan unit for the TSC filter train) rendering the TSC non-functional (TRM - Section T 3.10.1 EMERGENCY RESPONSE FACILITIES) during the performance of this work activity. This work activity is planned to be performed and completed expeditiously within about 5 hours including establishing and removing the clearances. The temporary power was installed on 6/19/12 to support work activities on the Hatch Nuclear Plant's 1R24-S026-600/208V MCC under Work Order Number 1050889203 which is the normal power supply.
"If an emergency condition occurs that requires activation of the Technical Support Center, plans are to utilize the TSC during the time this work activity is being performed, as long as habitability conditions allow. Procedure 73EP-EIP-063-0, Technical Support Center Activation provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC.
"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution.
"The TSC was returned to service today at 1645 EDT on 7/3/2012."
The licensee has notified the NRC Resident Inspector.
"Planned maintenance activities are being performed today (July 3, 2012) to remove temporary power from and restore normal power to the Technical Support Center (TSC) 480 VAC Distribution Panel 1R25-S012. This panel provides power to the TSC Emergency HVAC (TSC air handling unit, TSC condensing unit, TSC filter train and the fan unit for the TSC filter train) rendering the TSC non-functional (TRM - Section T 3.10.1 EMERGENCY RESPONSE FACILITIES) during the performance of this work activity. This work activity is planned to be performed and completed expeditiously within about 5 hours including establishing and removing the clearances. The temporary power was installed on 6/19/12 to support work activities on the Hatch Nuclear Plant's 1R24-S026-600/208V MCC under Work Order Number 1050889203 which is the normal power supply.
"If an emergency condition occurs that requires activation of the Technical Support Center, plans are to utilize the TSC during the time this work activity is being performed, as long as habitability conditions allow. Procedure 73EP-EIP-063-0, Technical Support Center Activation provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC.
"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution.
"The TSC was returned to service today at 1645 EDT on 7/3/2012."
The licensee has notified the NRC Resident Inspector.