Event Notification Report for March 13, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/12/2006 - 03/13/2006
EVENT NUMBERS
424194241142412424134241442415
General Information or Other
Event Number: 42419
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: BAKER HUGHS INTEC
Region: 4
City: HOUMA State: LA
County:
License #: LA-6025-L01
Agreement: Y
Docket:
NRC Notified By: MIKE HENRY
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: BAKER HUGHS INTEC
Region: 4
City: HOUMA State: LA
County:
License #: LA-6025-L01
Agreement: Y
Docket:
NRC Notified By: MIKE HENRY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/14/2006
Notification Time: 11:39 [ET]
Event Date: 03/13/2006
Event Time: 00:00 [CST]
Last Update Date: 03/14/2006
Notification Time: 11:39 [ET]
Event Date: 03/13/2006
Event Time: 00:00 [CST]
Last Update Date: 03/14/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CLAUDE JOHNSON (R4)
MICHELE BURGESS (NMSS)
CLAUDE JOHNSON (R4)
MICHELE BURGESS (NMSS)
AGREEMENT STATE REPORT - WELL LOGGING SOURCE ABANDONED
The State provided the following information via facsimile:
"Baker Hughs Intec abandoned a 2.5 Ci source of Cs-137 and a 5 Ci source of Am-241 down hole on March 13, 2006. The depth of the sources is between 14,423 feet and 14,430 feet. The hole has [been] back filled with cement to a depth of 12,095 feet to prevent reentry into the hole."
Louisiana license number: LA060004
The State provided the following information via facsimile:
"Baker Hughs Intec abandoned a 2.5 Ci source of Cs-137 and a 5 Ci source of Am-241 down hole on March 13, 2006. The depth of the sources is between 14,423 feet and 14,430 feet. The hole has [been] back filled with cement to a depth of 12,095 feet to prevent reentry into the hole."
Louisiana license number: LA060004
Fuel Cycle Facility
Event Number: 42411
Facility: NUCLEAR FUEL SERVICES INC.
Region: 2 State: TN
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
NRC Notified By: ROBERT MAURER
HQ OPS Officer: PETE SNYDER
Region: 2 State: TN
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
NRC Notified By: ROBERT MAURER
HQ OPS Officer: PETE SNYDER
Notification Date: 03/13/2006
Notification Time: 12:54 [ET]
Event Date: 03/13/2006
Event Time: 11:45 [EST]
Last Update Date: 05/11/2008
Notification Time: 12:54 [ET]
Event Date: 03/13/2006
Event Time: 11:45 [EST]
Last Update Date: 05/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (a)(4) - ALL SAFETY ITEMS UNAVAILABLE
10 CFR Section:
PART 70 APP A (a)(4) - ALL SAFETY ITEMS UNAVAILABLE
Person (Organization):
STEPHEN CAHILL (R2)
MICHELLE BURGESS (NMSS)
PETER WILSON (IRD)
FUELS GROUP (email)
STEPHEN CAHILL (R2)
MICHELLE BURGESS (NMSS)
PETER WILSON (IRD)
FUELS GROUP (email)
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
POTENTIAL UNSECURED ACCUMULATION POINT IDENTIFIED
"During inspections of the facility, NFS personnel identified an out-of-service equipment elevator and questioned if it contained any potential unsafe accumulation points. The elevator door was later opened and it revealed a pit area that was approximately 8-10 inches below the building floor level. This is considered a 1-hour reportable event because there is no [item relied on for safety or formal controls] in place to prevent a solution leak from entering this location. A solution leak to this area is considered a credible abnormal condition."
No actual material accumulation occurred. The licensee currently has compensatory measures in-place to prevent material accumulation in the area.
The licensee notified the NRC Resident Inspector.
* * * UPDATE 05/11/08 BY P. SNYDER * * *
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
POTENTIAL UNSECURED ACCUMULATION POINT IDENTIFIED
"During inspections of the facility, NFS personnel identified an out-of-service equipment elevator and questioned if it contained any potential unsafe accumulation points. The elevator door was later opened and it revealed a pit area that was approximately 8-10 inches below the building floor level. This is considered a 1-hour reportable event because there is no [item relied on for safety or formal controls] in place to prevent a solution leak from entering this location. A solution leak to this area is considered a credible abnormal condition."
No actual material accumulation occurred. The licensee currently has compensatory measures in-place to prevent material accumulation in the area.
The licensee notified the NRC Resident Inspector.
* * * UPDATE 05/11/08 BY P. SNYDER * * *
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
Power Reactor
Event Number: 42412
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: ERIC MATZKE
HQ OPS Officer: PETE SNYDER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: ERIC MATZKE
HQ OPS Officer: PETE SNYDER
Notification Date: 03/13/2006
Notification Time: 14:03 [ET]
Event Date: 03/13/2006
Event Time: 10:01 [CST]
Last Update Date: 03/13/2006
Notification Time: 14:03 [ET]
Event Date: 03/13/2006
Event Time: 10:01 [CST]
Last Update Date: 03/13/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
CLAUDE JOHNSON (R4)
CLAUDE JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FAILED FITNESS FOR DUTY TEST
A licensed employee supervisor had a confirmed positive for alcohol during a re-entry fitness-for-duty test. The employee's access to the plant has been blocked. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
A licensed employee supervisor had a confirmed positive for alcohol during a re-entry fitness-for-duty test. The employee's access to the plant has been blocked. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 42413
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: STUART BRANTLEY
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: STUART BRANTLEY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/13/2006
Notification Time: 15:35 [ET]
Event Date: 03/13/2006
Event Time: 11:10 [EST]
Last Update Date: 03/13/2006
Notification Time: 15:35 [ET]
Event Date: 03/13/2006
Event Time: 11:10 [EST]
Last Update Date: 03/13/2006
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):
PAUL KROHN (R1)
PAUL KROHN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER VENTILATION FAN INOPERABLE
"The Technical Support Center ventilation system was discovered to be non-functional at 1110 on March 13, 2006. The cause of the ventilation problem was determined to be damaged drive belts on the supply fan. The belts were replaced and the ventilation system supply fan was returned to service at 1253 on March 13, 2006. This condition is considered a Loss of Offsite Response Capability and is therefore reportable under 10CFR50.72(b)(3)(xiii)."
A corrective action request has been generated to follow remedial action.
The licensee notified the NRC Resident Inspector.
"The Technical Support Center ventilation system was discovered to be non-functional at 1110 on March 13, 2006. The cause of the ventilation problem was determined to be damaged drive belts on the supply fan. The belts were replaced and the ventilation system supply fan was returned to service at 1253 on March 13, 2006. This condition is considered a Loss of Offsite Response Capability and is therefore reportable under 10CFR50.72(b)(3)(xiii)."
A corrective action request has been generated to follow remedial action.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 42414
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ERIC OLSON
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ERIC OLSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/13/2006
Notification Time: 21:21 [ET]
Event Date: 03/13/2006
Event Time: 18:08 [EST]
Last Update Date: 03/13/2006
Notification Time: 21:21 [ET]
Event Date: 03/13/2006
Event Time: 18:08 [EST]
Last Update Date: 03/13/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAUL KROHN (R1)
PAUL KROHN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 48 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM AFTER OFFGAS SYSTEM FAILURE
"During a power ascension, the non-safety Augmented Offgas System experienced a failure which caused a Recombiner high temperature condition. To protect components of the non-safety Augmented Offgas System, station procedures require a manual scram of the reactor when this condition occurs. Station procedures were followed and the reactor was manually scrammed at 18:08. All rods fully inserted and all safety systems performed per design. Primary containment isolation systems responded properly resulting in an automatic isolation of Primary Containment Isolation System Groups 2 and 6 valves and a Reactor Building Isolation due to the transient low reactor water level condition caused by the scram.
"The plant is in a stable condition. Investigation is continuing."
No safety valves lifted on the scram, decay heat is being removed with the bypass valve, normal feed and condensate are maintaining reactor water level, and the electrical grid is stable on the startup transformer. The licensee notified the NRC Resident Inspector.
"During a power ascension, the non-safety Augmented Offgas System experienced a failure which caused a Recombiner high temperature condition. To protect components of the non-safety Augmented Offgas System, station procedures require a manual scram of the reactor when this condition occurs. Station procedures were followed and the reactor was manually scrammed at 18:08. All rods fully inserted and all safety systems performed per design. Primary containment isolation systems responded properly resulting in an automatic isolation of Primary Containment Isolation System Groups 2 and 6 valves and a Reactor Building Isolation due to the transient low reactor water level condition caused by the scram.
"The plant is in a stable condition. Investigation is continuing."
No safety valves lifted on the scram, decay heat is being removed with the bypass valve, normal feed and condensate are maintaining reactor water level, and the electrical grid is stable on the startup transformer. The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 42415
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PAUL BELLARD
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PAUL BELLARD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/13/2006
Notification Time: 21:39 [ET]
Event Date: 03/13/2006
Event Time: 17:40 [CST]
Last Update Date: 03/13/2006
Notification Time: 21:39 [ET]
Event Date: 03/13/2006
Event Time: 17:40 [CST]
Last Update Date: 03/13/2006
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):
CLAUDE JOHNSON (R4)
CLAUDE JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FAILURE OF ONE EMERGENCY SIREN
"The station received a report that a siren was sounding. The station investigated and determined that one siren, EBR#3 was intermittently activating. A communications team was dispatched to remove this siren from service for repairs. The Louisiana Office of Homeland Security and Emergency Preparedness was notified in accordance with station procedures. Responsible personnel at that facility determined that no further action was required since the activation involved only one siren."
The siren is in East Baton Rouge Parish and was reported to the site by the Sheriff. The failure is suspected to be a circuit board problem.
The licensee notified the NRC Resident Inspector.
"The station received a report that a siren was sounding. The station investigated and determined that one siren, EBR#3 was intermittently activating. A communications team was dispatched to remove this siren from service for repairs. The Louisiana Office of Homeland Security and Emergency Preparedness was notified in accordance with station procedures. Responsible personnel at that facility determined that no further action was required since the activation involved only one siren."
The siren is in East Baton Rouge Parish and was reported to the site by the Sheriff. The failure is suspected to be a circuit board problem.
The licensee notified the NRC Resident Inspector.