Event Notification Report for December 01, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/30/2009 - 12/01/2009
EVENT NUMBERS
45529455304553345534
Power Reactor
Event Number: 45529
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BILL DUVALL
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BILL DUVALL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/01/2009
Notification Time: 08:57 [ET]
Event Date: 12/01/2009
Event Time: 09:18 [EST]
Last Update Date: 12/01/2009
Notification Time: 08:57 [ET]
Event Date: 12/01/2009
Event Time: 09:18 [EST]
Last Update Date: 12/01/2009
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 |
HEALTH PHYSICS CONTROL POINT AND CHEM LAB HVAC OUT OF SERVICE FOR PLANNED MAINTENANCE
"On 12/1/2009 the emergency HVAC [heating, ventilation, and air conditioning] for the Hatch Nuclear Plant's Health Physics (HP) Control Point/Chemistry Lab area will be removed from service for preventative maintenance, planned corrective maintenance and glycol addition to the cooling coil. The Technical Response Manual (TRM) section 3.10.1 lists the HP Control Point/Chemistry Lab area emergency HVAC system as being required for functionality of the Operations Support Center [OSC]. This area is normally utilized by HP/Chem for analysis of radiological samples during normal as well as emergency conditions. These work activities are planned to be performed and completed within a 12 hour work shift. During the time these activities are being performed the HP emergency HVAC and filter train will not be available for operation for approximately eight (8) hours. As such the OSC will be rendered non-functional during the performance of this work activity. The OSC facility working area itself, however, does not lose EP functionality throughout this evolution.
"If an emergency were to occur, plans are to continue utilize the Health Physics Control Point/Chemistry Lab areas during the time required to restore the HVAC system, as long as environmental and radiological conditions allow. Habitability surveys will be performed in the areas while they are being utilized. If required respiratory protection equipment can be utilized as appropriate for emergency responders utilizing this area until such time as the emergency HVAC is returned to service.
"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."
The licensee will notify the NRC Resident Inspector.
"On 12/1/2009 the emergency HVAC [heating, ventilation, and air conditioning] for the Hatch Nuclear Plant's Health Physics (HP) Control Point/Chemistry Lab area will be removed from service for preventative maintenance, planned corrective maintenance and glycol addition to the cooling coil. The Technical Response Manual (TRM) section 3.10.1 lists the HP Control Point/Chemistry Lab area emergency HVAC system as being required for functionality of the Operations Support Center [OSC]. This area is normally utilized by HP/Chem for analysis of radiological samples during normal as well as emergency conditions. These work activities are planned to be performed and completed within a 12 hour work shift. During the time these activities are being performed the HP emergency HVAC and filter train will not be available for operation for approximately eight (8) hours. As such the OSC will be rendered non-functional during the performance of this work activity. The OSC facility working area itself, however, does not lose EP functionality throughout this evolution.
"If an emergency were to occur, plans are to continue utilize the Health Physics Control Point/Chemistry Lab areas during the time required to restore the HVAC system, as long as environmental and radiological conditions allow. Habitability surveys will be performed in the areas while they are being utilized. If required respiratory protection equipment can be utilized as appropriate for emergency responders utilizing this area until such time as the emergency HVAC is returned to service.
"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."
The licensee will notify the NRC Resident Inspector.
Power Reactor
Event Number: 45530
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: ROBERT MATUSZAK
HQ OPS Officer: CHARLES TEAL
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: ROBERT MATUSZAK
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/01/2009
Notification Time: 11:08 [ET]
Event Date: 12/01/2009
Event Time: 12:00 [EST]
Last Update Date: 12/03/2009
Notification Time: 11:08 [ET]
Event Date: 12/01/2009
Event Time: 12:00 [EST]
Last Update Date: 12/03/2009
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):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 99 | Power Operation |
IPCS SYSTEM OOS FOR SECURITY MODIFICATION
"Beginning December 1,2009, at approximately 1200, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the PCS platform and will be out of service when the PCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately six hours. By 1800, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, and the Technical Support Center. The IPCS will remain unavailable to the Emergency Operations Facility (EOF) as well as alternate EOF. On December 2, at approximately 1600, IPCS will be restored to the EOF but will remain unavailable to the alternate facilities. On December 3, 2009, at approximately 1600, IPCS will be restored, including alternate facilities.
"During this entire duration dose assessment capability will only be available in the manual data input mode. A follow-up notification will be submitted when the PCS is completely restored. For the first six hours of the PCS outage, the emergency assessment capability of all Fermi 2 ERFs will be degraded by the loss of IPCS and SPDS. During this period the ERDS function will also be lost. For the following 24 hrs., the EOF will have no IPCSs capability, which includes the SPDS function. Based on the aggregate effect of these losses, this notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR,50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 1753 EST ON 12/3/09 FROM MATUSZAK TO HUFFMAN * * *
"On December 3, 2009, at 1530, emergency assessment capability has been restored to all on site emergency response facilities."
The licensee will notify the NRC Resident Inspector. R3DO (Riemer) notified.
"Beginning December 1,2009, at approximately 1200, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the PCS platform and will be out of service when the PCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately six hours. By 1800, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, and the Technical Support Center. The IPCS will remain unavailable to the Emergency Operations Facility (EOF) as well as alternate EOF. On December 2, at approximately 1600, IPCS will be restored to the EOF but will remain unavailable to the alternate facilities. On December 3, 2009, at approximately 1600, IPCS will be restored, including alternate facilities.
"During this entire duration dose assessment capability will only be available in the manual data input mode. A follow-up notification will be submitted when the PCS is completely restored. For the first six hours of the PCS outage, the emergency assessment capability of all Fermi 2 ERFs will be degraded by the loss of IPCS and SPDS. During this period the ERDS function will also be lost. For the following 24 hrs., the EOF will have no IPCSs capability, which includes the SPDS function. Based on the aggregate effect of these losses, this notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR,50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 1753 EST ON 12/3/09 FROM MATUSZAK TO HUFFMAN * * *
"On December 3, 2009, at 1530, emergency assessment capability has been restored to all on site emergency response facilities."
The licensee will notify the NRC Resident Inspector. R3DO (Riemer) notified.
Power Reactor
Event Number: 45533
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DONNA GUINN
HQ OPS Officer: PETE SNYDER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DONNA GUINN
HQ OPS Officer: PETE SNYDER
Notification Date: 12/01/2009
Notification Time: 17:37 [ET]
Event Date: 12/01/2009
Event Time: 15:00 [CST]
Last Update Date: 12/01/2009
Notification Time: 17:37 [ET]
Event Date: 12/01/2009
Event Time: 15:00 [CST]
Last Update Date: 12/01/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
RICK DEESE (R4DO)
RICK DEESE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
CONTAMINATED PERSON REPORTS TO OFFSITE HOSPITAL
"On November 26, 2009, at 2330, it was determined that a machinist who was working on reactor coolant pump (RCP 3A) seal was contaminated on his left hand index finger. The contamination level was 1500 net counts per minute (CPM). Upon exit, the individual alarmed monitors and decontamination was attempted. Decontamination for the next two shifts included wrapping of the hand, waiting 2 hours, rechecking and repeating 2 hours later. However, decontamination was unsuccessful. The individual was conditionally released and allowed to leave the site with his hand wrapped.
"On December 1, 2009, at approximately 1500, the Fort Calhoun Station Health Physics and Radiological Protection Personnel met the machinist at the University of Nebraska Medical Center (UNMC) for further treatment."
The licensee notified the NRC Resident Inspector.
"On November 26, 2009, at 2330, it was determined that a machinist who was working on reactor coolant pump (RCP 3A) seal was contaminated on his left hand index finger. The contamination level was 1500 net counts per minute (CPM). Upon exit, the individual alarmed monitors and decontamination was attempted. Decontamination for the next two shifts included wrapping of the hand, waiting 2 hours, rechecking and repeating 2 hours later. However, decontamination was unsuccessful. The individual was conditionally released and allowed to leave the site with his hand wrapped.
"On December 1, 2009, at approximately 1500, the Fort Calhoun Station Health Physics and Radiological Protection Personnel met the machinist at the University of Nebraska Medical Center (UNMC) for further treatment."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45534
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: TODD CREASY
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: TODD CREASY
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/01/2009
Notification Time: 21:53 [ET]
Event Date: 12/01/2009
Event Time: 18:00 [EST]
Last Update Date: 12/01/2009
Notification Time: 21:53 [ET]
Event Date: 12/01/2009
Event Time: 18:00 [EST]
Last Update Date: 12/01/2009
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):
DANIEL HOLODY (R1DO)
DANIEL HOLODY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 94 | Power Operation | 94 | Power Operation |
| 2 | N | Y | 94 | Power Operation | 79 | Power Operation |
ONSITE FLOODING CAUSED BY MAKE-UP SUPPLY LINE FAILURE
"The following transmission was made as a voluntary notification at 1800 EST: On 12/01/09 at 1410 [EST], due to a Unit 2 cooling tower make-up supply line failure, a valve vault was flooded and overflowed at several thousands of gallons per minute flow. The local fire company was contacted to provide equipment assistance in pumping out the vault. The river water overflowing the vault entered nearby storm drains and a nearby building housing non-safety related equipment. There are no injuries or an emergency of any kind. The water entering the storm sewer does not constitute a reportable spill. Unit 2 reactor power was reduced to 80% to minimize cooling tower impact. The Pennsylvania Emergency Management Agency was notified at 1800 EST. Various other local and state agencies have been advised of the event.
"Subsequently, notifications were made to the following agencies:
"Salem Township Supervisor Chairman
"State Senator Baker
"State Rep. Boback
"Columbia County Commissioner Soberick
"Federal Affairs to notify US Rep. Kanjorski's staff.
"Although the impact of this make-up supply line failure to the environment is insignificant (Radiological levels are less than lower limit of detection), its occurrence coupled with subsequent notifications to aforementioned agencies is likely to cause heightened public or government concern. Thus, Susquehanna Steam Electric Station is making a four hour ENS notification pursuant to 10CFR50.72(b)(2)(xi). A press release is not planned at this time."
The licensee has notified the NRC Resident Inspector.
"The following transmission was made as a voluntary notification at 1800 EST: On 12/01/09 at 1410 [EST], due to a Unit 2 cooling tower make-up supply line failure, a valve vault was flooded and overflowed at several thousands of gallons per minute flow. The local fire company was contacted to provide equipment assistance in pumping out the vault. The river water overflowing the vault entered nearby storm drains and a nearby building housing non-safety related equipment. There are no injuries or an emergency of any kind. The water entering the storm sewer does not constitute a reportable spill. Unit 2 reactor power was reduced to 80% to minimize cooling tower impact. The Pennsylvania Emergency Management Agency was notified at 1800 EST. Various other local and state agencies have been advised of the event.
"Subsequently, notifications were made to the following agencies:
"Salem Township Supervisor Chairman
"State Senator Baker
"State Rep. Boback
"Columbia County Commissioner Soberick
"Federal Affairs to notify US Rep. Kanjorski's staff.
"Although the impact of this make-up supply line failure to the environment is insignificant (Radiological levels are less than lower limit of detection), its occurrence coupled with subsequent notifications to aforementioned agencies is likely to cause heightened public or government concern. Thus, Susquehanna Steam Electric Station is making a four hour ENS notification pursuant to 10CFR50.72(b)(2)(xi). A press release is not planned at this time."
The licensee has notified the NRC Resident Inspector.