Event Notification Report for September 29, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/28/2011 - 09/29/2011
EVENT NUMBERS
473084730547306473024730347603
Fuel Cycle Facility
Event Number: 47308
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
Region: 2 State: NC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: VINCE KLCO
Region: 2 State: NC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: VINCE KLCO
Notification Date: 09/30/2011
Notification Time: 11:00 [ET]
Event Date: 09/29/2011
Event Time: 11:20 [EDT]
Last Update Date: 09/30/2011
Notification Time: 11:00 [ET]
Event Date: 09/29/2011
Event Time: 11:20 [EDT]
Last Update Date: 09/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(5) - DEV FROM ISA
10 CFR Section:
PART 70 APP A (b)(5) - DEV FROM ISA
Person (Organization):
REBECCA NEASE (R2DO)
EARL EASTON (NMSS)
REBECCA NEASE (R2DO)
EARL EASTON (NMSS)
EQUIPMENT CONFIGURATION DIFFERENT THAN ANALYZED IN THE ISA
"During a review of Integrated Safety Analysis (ISA) and criticality evaluation assumptions for a floor cleaning scrubber used in the Dry Conversion Process facility, it was determined that an equipment configuration was different than that analyzed in the ISA. Field verification of the floor cleaning scrubber recovery tank determined that its capacity was greater than the safe volume limit referenced in the analysis. The tank volume is credited as an IROFS [Items Relied On For Safety] in the ISA summary. Based on a review of this as-found condition, discovered at approximately 1120 EDT on September 29, 2011, it was determined that the system was different than analyzed in the ISA and resulted in a failure to meet performance requirements.
"The tanks for the floor cleaning scrubbers were inspected and no unsafe condition existed. Operation of the equipment has been suspended pending additional review and implementation of corrective actions. Additional corrective actions and extent of condition are being evaluated.
"This event is being reported pursuant to the reporting requirements of 10CFR70 Appendix A (b)(1) within 24 hours of discovery."
The licensee will notify the NRC Region 2, North Carolina Radiation Protection Agency and New Hanover County Emergency Management.
"During a review of Integrated Safety Analysis (ISA) and criticality evaluation assumptions for a floor cleaning scrubber used in the Dry Conversion Process facility, it was determined that an equipment configuration was different than that analyzed in the ISA. Field verification of the floor cleaning scrubber recovery tank determined that its capacity was greater than the safe volume limit referenced in the analysis. The tank volume is credited as an IROFS [Items Relied On For Safety] in the ISA summary. Based on a review of this as-found condition, discovered at approximately 1120 EDT on September 29, 2011, it was determined that the system was different than analyzed in the ISA and resulted in a failure to meet performance requirements.
"The tanks for the floor cleaning scrubbers were inspected and no unsafe condition existed. Operation of the equipment has been suspended pending additional review and implementation of corrective actions. Additional corrective actions and extent of condition are being evaluated.
"This event is being reported pursuant to the reporting requirements of 10CFR70 Appendix A (b)(1) within 24 hours of discovery."
The licensee will notify the NRC Region 2, North Carolina Radiation Protection Agency and New Hanover County Emergency Management.
Power Reactor
Event Number: 47305
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: PETE SNYDER
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: PETE SNYDER
Notification Date: 09/29/2011
Notification Time: 17:40 [ET]
Event Date: 09/29/2011
Event Time: 17:10 [EDT]
Last Update Date: 09/29/2011
Notification Time: 17:40 [ET]
Event Date: 09/29/2011
Event Time: 17:10 [EDT]
Last Update Date: 09/29/2011
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):
REBECCA NEASE (R2DO)
REBECCA NEASE (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 | 91 | Power Operation | 91 | Power Operation |
GEORGIA DEPARTMENT OF NATURAL RESOURCES NOTIFIED DUE TO TRITIUM LEVELS ABOVE BACKGROUND DETECTED AT SAMPLE POINTS ONSITE
"On Sept. 28, 2011, results from routine monitoring of groundwater at Plant Hatch indicated tritium was detected above historical background levels at two sample points on site. Additional samples were taken from the same points and analysis confirmed that tritium was present at elevated levels in both samples and that tritium had not migrated out of the general area of initial discovery. Tritium concentrations up to 5.34 million picocuries per liter were observed. Immediate actions were taken to locate the source of the leak and actions are in progress to stop the leak. The tritium is confined to a small area on the plant site in the vicinity of the Unit 1 condensate storage tank, and there is no significant potential for off-site impact. Additionally, there is no impact to on-site personnel. No tritium levels above background have been detected or migrated outside the area where the two sample points are located.
"Southern Nuclear will continue to sample strategic locations in the ground water monitoring network to determine if there are changes in the impacted area and beyond. SNC is confident that these levels are of low safety significance and do not pose any issues to the public health and safety.
"In accordance with Southern Nuclear's groundwater protection procedures and the Nuclear Energy Institute (NEI)/Industry Groundwater Protection Initiative, Southern Nuclear contacted the Nuclear Regulatory Commission (NRC) Region II Resident Inspector and the Georgia Department of Natural Resources to inform them of this matter."
"On Sept. 28, 2011, results from routine monitoring of groundwater at Plant Hatch indicated tritium was detected above historical background levels at two sample points on site. Additional samples were taken from the same points and analysis confirmed that tritium was present at elevated levels in both samples and that tritium had not migrated out of the general area of initial discovery. Tritium concentrations up to 5.34 million picocuries per liter were observed. Immediate actions were taken to locate the source of the leak and actions are in progress to stop the leak. The tritium is confined to a small area on the plant site in the vicinity of the Unit 1 condensate storage tank, and there is no significant potential for off-site impact. Additionally, there is no impact to on-site personnel. No tritium levels above background have been detected or migrated outside the area where the two sample points are located.
"Southern Nuclear will continue to sample strategic locations in the ground water monitoring network to determine if there are changes in the impacted area and beyond. SNC is confident that these levels are of low safety significance and do not pose any issues to the public health and safety.
"In accordance with Southern Nuclear's groundwater protection procedures and the Nuclear Energy Institute (NEI)/Industry Groundwater Protection Initiative, Southern Nuclear contacted the Nuclear Regulatory Commission (NRC) Region II Resident Inspector and the Georgia Department of Natural Resources to inform them of this matter."
Power Reactor
Event Number: 47306
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID WEBSTER
HQ OPS Officer: VINCE KLCO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID WEBSTER
HQ OPS Officer: VINCE KLCO
Notification Date: 09/30/2011
Notification Time: 00:18 [ET]
Event Date: 09/29/2011
Event Time: 17:00 [CDT]
Last Update Date: 09/30/2011
Notification Time: 00:18 [ET]
Event Date: 09/29/2011
Event Time: 17:00 [CDT]
Last Update Date: 09/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVE PASSEHL (R3DO)
DAVE PASSEHL (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 |
INADEQUATE SURVEILLANCE TESTING OF EMERGENCY DIESEL GENERATORS
"Monticello has discovered that it has not met Technical Specification Surveillance Requirement (SR) 3.8.1.7 relating to the largest single post-accident load reject for the Emergency Diesel Generators (EDG). Although the current test designated post-accident load is successfully load rejected during the surveillance, the test load rejection must be higher to bound all post-accident load scenarios. The capability of an EDG subsystem to recover from a reject of the largest single post-accident load testing has not met the requirements of SR 3.8.1.7. Therefore, both EDGs have been declared inoperable. Both EDGs are considered Functional and Available for use at this time.
"There were no automatic EDG initiation signals associated with this event."
The licensee notified the NRC Resident Inspector and will notify the State.
"Monticello has discovered that it has not met Technical Specification Surveillance Requirement (SR) 3.8.1.7 relating to the largest single post-accident load reject for the Emergency Diesel Generators (EDG). Although the current test designated post-accident load is successfully load rejected during the surveillance, the test load rejection must be higher to bound all post-accident load scenarios. The capability of an EDG subsystem to recover from a reject of the largest single post-accident load testing has not met the requirements of SR 3.8.1.7. Therefore, both EDGs have been declared inoperable. Both EDGs are considered Functional and Available for use at this time.
"There were no automatic EDG initiation signals associated with this event."
The licensee notified the NRC Resident Inspector and will notify the State.
Power Reactor
Event Number: 47302
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOE PENNINGTON
HQ OPS Officer: VINCE KLCO
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOE PENNINGTON
HQ OPS Officer: VINCE KLCO
Notification Date: 09/29/2011
Notification Time: 06:56 [ET]
Event Date: 09/29/2011
Event Time: 06:02 [EDT]
Last Update Date: 09/29/2011
Notification Time: 06:56 [ET]
Event Date: 09/29/2011
Event Time: 06:02 [EDT]
Last Update Date: 09/29/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
REBECCA NEASE (R2DO)
BRUCE BOGER (NRR)
VICTOR MCCREE (R2)
ERIC THOMAS (NRR)
WILLIAM GOTT (IRD)
REBECCA NEASE (R2DO)
BRUCE BOGER (NRR)
VICTOR MCCREE (R2)
ERIC THOMAS (NRR)
WILLIAM GOTT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 0 | Startup | 0 | Startup |
UNUSUAL EVENT DECLARED DUE TO FIRE ALARM IN THE CONTAINMENT
During plant startup, a single train fire alarm was received in containment at 0540 EDT on 9/29/2011. An Unusual Event was declared at 0602 EDT based on the containment not being accessible within 15 minutes. An inspection in containment revealed no fire or smoke or the cause for receipt of the alarm.
The licensee has notified the State, Counties and the NRC Resident Inspector.
* * *UPDATE FROM JOE PENNINGTON TO VINCE KLCO ON 9/29/2011 AT 0744* * *
The Unusual Event was terminated at 0714 EDT on 9/29/2011. The licensee has notified the State, Counties and the NRC Resident Inspector.
Notified the R2DO (Nease), NRR (Thomas), IRD (Gott), FEMA (Casto) and DHS (Rickerson).
During plant startup, a single train fire alarm was received in containment at 0540 EDT on 9/29/2011. An Unusual Event was declared at 0602 EDT based on the containment not being accessible within 15 minutes. An inspection in containment revealed no fire or smoke or the cause for receipt of the alarm.
The licensee has notified the State, Counties and the NRC Resident Inspector.
* * *UPDATE FROM JOE PENNINGTON TO VINCE KLCO ON 9/29/2011 AT 0744* * *
The Unusual Event was terminated at 0714 EDT on 9/29/2011. The licensee has notified the State, Counties and the NRC Resident Inspector.
Notified the R2DO (Nease), NRR (Thomas), IRD (Gott), FEMA (Casto) and DHS (Rickerson).
Power Reactor
Event Number: 47303
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: VINCE BONELLI
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: VINCE BONELLI
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/29/2011
Notification Time: 12:19 [ET]
Event Date: 09/29/2011
Event Time: 11:35 [EDT]
Last Update Date: 09/29/2011
Notification Time: 12:19 [ET]
Event Date: 09/29/2011
Event Time: 11:35 [EDT]
Last Update Date: 09/29/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
WILLIAM GOTT (IRD)
BRUCE BOGER (NRR)
BILL DEAN (R1RA)
ERIC THOMAS (NRR)
LAWRENCE DOERFLEIN (R1DO)
WILLIAM GOTT (IRD)
BRUCE BOGER (NRR)
BILL DEAN (R1RA)
ERIC THOMAS (NRR)
| 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 |
NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO CHEMICAL SPILL
"EAL HU7 was declared at 1135 hrs. [EDT] for a toxic of flammable gas which has been released onsite which could affect plant operations. Current plant conditions do not threaten public safety.
"Less than 1 gallon of 15% sodium hypochlorite sprayed onto the floor during securing of a completed delivery to the water treatment plant, located within the Protected Area boundary. There have been no injuries to personnel."
The licensee has notified the local and state authorities and will be notifying the NRC Resident Inspector.
* * * UPDATE FROM VINCE BONELLI TO HOWIE CROUCH AT 1457 EDT ON 9/29/11 * * *
"Limerick is terminating from the Unusual Event (HU7) due to the threat of toxic gas having been terminated. The sodium hypochlorite leak in the water treatment plant has been stopped and clean up activities are in progress. U1 and U2 remain at 100% power. There were no injuries."
The licensee has notified state and local authorities and will be notifying the NRC Resident Inspector. Notified R1DO (Doerflein), IRD (Gott), NRR (Thomas), FEMA (O'Connell) and DHS (Flinter).
"EAL HU7 was declared at 1135 hrs. [EDT] for a toxic of flammable gas which has been released onsite which could affect plant operations. Current plant conditions do not threaten public safety.
"Less than 1 gallon of 15% sodium hypochlorite sprayed onto the floor during securing of a completed delivery to the water treatment plant, located within the Protected Area boundary. There have been no injuries to personnel."
The licensee has notified the local and state authorities and will be notifying the NRC Resident Inspector.
* * * UPDATE FROM VINCE BONELLI TO HOWIE CROUCH AT 1457 EDT ON 9/29/11 * * *
"Limerick is terminating from the Unusual Event (HU7) due to the threat of toxic gas having been terminated. The sodium hypochlorite leak in the water treatment plant has been stopped and clean up activities are in progress. U1 and U2 remain at 100% power. There were no injuries."
The licensee has notified state and local authorities and will be notifying the NRC Resident Inspector. Notified R1DO (Doerflein), IRD (Gott), NRR (Thomas), FEMA (O'Connell) and DHS (Flinter).
Agreement State
Event Number: 47603
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSAL WELL SYSTEMS
Region: 1
City: WILLIAMSPORT State: PA
County:
License #: PA-G0043
Agreement: Y
Docket:
NRC Notified By: DAVID J ALLARD
HQ OPS Officer: JOHN SHOEMAKER
Licensee: UNIVERSAL WELL SYSTEMS
Region: 1
City: WILLIAMSPORT State: PA
County:
License #: PA-G0043
Agreement: Y
Docket:
NRC Notified By: DAVID J ALLARD
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/18/2012
Notification Time: 10:29 [ET]
Event Date: 09/29/2011
Event Time: 08:00 [EST]
Last Update Date: 01/18/2012
Notification Time: 10:29 [ET]
Event Date: 09/29/2011
Event Time: 08:00 [EST]
Last Update Date: 01/18/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD BELLAMY (R1DO)
ANGELA MCINTOSH (FSME)
RONALD BELLAMY (R1DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - SHUTTER FAILURE DUE TO DROPPING OF A BERTHOLD TECHNOLOGIES DENSITY GAUGE
The following report was received via facsimile from the PA Department of Radiation Protection.
"Notifications: On Friday January 13, 2012, the licensee sent notification via email after close of business to the central office about an event that took place on September 29, 2011. This email was received by central office on Tuesday, January 17, 2012. It is reportable within 24 hours under 10 CFR 30.50(b)(2).
"Event Description: On September 29, 2011, a gauge with Serial Number 10153 was dropped, bending the shutter control handle, leaving the shutter stuck closed. The workers did not notify anyone of the incident and the gauge was put in storage. When the gauge was to be put back in service on November 10, 2011, it was then observed to be in the damaged condition. The gauge was then put back into a secured storage until the repair could be made. The gauge was repaired by replacing the shutter with a new Serial Number 10306 on December 1, 2011.
"The device is identified as - Manufacturer: Berthold Technologies USA, LLC; Model: LB8010; Serial #: 10153 (replaced by 10306); Isotope: Cs-137; Activity: 20 mCi.
"CAUSE OF THE EVENT: Human error.
"ACTIONS: On December 1, 2011 repairs were made. This was discovered on an inspection by the Department on December 16, 2011."
Event Report ID No.: PA110043.
The following report was received via facsimile from the PA Department of Radiation Protection.
"Notifications: On Friday January 13, 2012, the licensee sent notification via email after close of business to the central office about an event that took place on September 29, 2011. This email was received by central office on Tuesday, January 17, 2012. It is reportable within 24 hours under 10 CFR 30.50(b)(2).
"Event Description: On September 29, 2011, a gauge with Serial Number 10153 was dropped, bending the shutter control handle, leaving the shutter stuck closed. The workers did not notify anyone of the incident and the gauge was put in storage. When the gauge was to be put back in service on November 10, 2011, it was then observed to be in the damaged condition. The gauge was then put back into a secured storage until the repair could be made. The gauge was repaired by replacing the shutter with a new Serial Number 10306 on December 1, 2011.
"The device is identified as - Manufacturer: Berthold Technologies USA, LLC; Model: LB8010; Serial #: 10153 (replaced by 10306); Isotope: Cs-137; Activity: 20 mCi.
"CAUSE OF THE EVENT: Human error.
"ACTIONS: On December 1, 2011 repairs were made. This was discovered on an inspection by the Department on December 16, 2011."
Event Report ID No.: PA110043.