Event Notification Report for December 21, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/20/2006 - 12/21/2006
Power Reactor
Event Number: 43059
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: BILL GOTT
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: BILL GOTT
Notification Date: 12/21/2006
Notification Time: 09:24 [ET]
Event Date: 12/21/2006
Event Time: 02:05 [EST]
Last Update Date: 12/21/2006
Notification Time: 09:24 [ET]
Event Date: 12/21/2006
Event Time: 02:05 [EST]
Last Update Date: 12/21/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY POWELL (R1)
RAY POWELL (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
ACCIDENT MITIGATION - AUXILIARY FEEDWATER SYSTEM
"A condition was identified [at 0205 on 12/21/06] involving improper placement of temporary scaffolding that could have resulted in all three Auxiliary Feedwater (AFW) pumps becoming inoperable during a high energy line break (HELB) in the Turbine-Driven Auxiliary Feedwater (TDAFW) pump room.
"Scaffolding, erected to perform maintenance on the floor above the TDAFW pump room, had two vertical members placed on the high energy line break blowout panel in the TDAFW pump room roof that could potentially have restricted the ability of the panel to lift during a HELB event in the TDAFW pump room. Failure of the panel to lift during the event may cause the structural limit of the walls separating the TDAFW pump room from the motor driven AFW pump room to be exceeded. This could have resulted in all three AFW pumps becoming inoperable.
"At 0530 on 12/21/06, scaffolding removal was complete and AFW operability was restored.
"This condition is being conservatively reported, pending further evaluation, per 10CFR50.72(b)(3)(v) as a condition that at the time of discovery could have prevented the fulfillment of a safety function."
The licensee notified the NRC Resident Inspector.
"A condition was identified [at 0205 on 12/21/06] involving improper placement of temporary scaffolding that could have resulted in all three Auxiliary Feedwater (AFW) pumps becoming inoperable during a high energy line break (HELB) in the Turbine-Driven Auxiliary Feedwater (TDAFW) pump room.
"Scaffolding, erected to perform maintenance on the floor above the TDAFW pump room, had two vertical members placed on the high energy line break blowout panel in the TDAFW pump room roof that could potentially have restricted the ability of the panel to lift during a HELB event in the TDAFW pump room. Failure of the panel to lift during the event may cause the structural limit of the walls separating the TDAFW pump room from the motor driven AFW pump room to be exceeded. This could have resulted in all three AFW pumps becoming inoperable.
"At 0530 on 12/21/06, scaffolding removal was complete and AFW operability was restored.
"This condition is being conservatively reported, pending further evaluation, per 10CFR50.72(b)(3)(v) as a condition that at the time of discovery could have prevented the fulfillment of a safety function."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43060
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM HUFFORD
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM HUFFORD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/21/2006
Notification Time: 14:46 [ET]
Event Date: 12/21/2006
Event Time: 14:00 [EST]
Last Update Date: 12/21/2006
Notification Time: 14:46 [ET]
Event Date: 12/21/2006
Event Time: 14:00 [EST]
Last Update Date: 12/21/2006
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):
RAY POWELL (R1)
RAY POWELL (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
INADVERTENT ACTUATION OF EMERGENCY SIRENS
"A Press Release will be issued for an inadvertent actuation of the Emergency Sirens during testing. This item is reportable under 10CFR50.72(b)(2)(xi) as an offsite notification of an event of public interest."
Following maintenance on a single siren, Columbia County emergency management personnel were requested to test it. The County inadvertently activated all 112 sirens within 10 miles of the plant.
The licensee notified the NRC Resident Inspector and the State.
"A Press Release will be issued for an inadvertent actuation of the Emergency Sirens during testing. This item is reportable under 10CFR50.72(b)(2)(xi) as an offsite notification of an event of public interest."
Following maintenance on a single siren, Columbia County emergency management personnel were requested to test it. The County inadvertently activated all 112 sirens within 10 miles of the plant.
The licensee notified the NRC Resident Inspector and the State.
General Information or Other
Event Number: 43079
Rep Org: MAINE RADIATION CONTROL PROGRAM
Licensee: CITY OF PRESQUE ISLE
Region: 1
City: PRESQUE ISLE State: ME
County:
License #: 03701G
Agreement: N
Docket:
NRC Notified By: SHAWN SEELEY
HQ OPS Officer: PETE SNYDER
Licensee: CITY OF PRESQUE ISLE
Region: 1
City: PRESQUE ISLE State: ME
County:
License #: 03701G
Agreement: N
Docket:
NRC Notified By: SHAWN SEELEY
HQ OPS Officer: PETE SNYDER
Notification Date: 01/05/2007
Notification Time: 15:45 [ET]
Event Date: 12/21/2006
Event Time: 14:00 [EST]
Last Update Date: 01/05/2007
Notification Time: 15:45 [ET]
Event Date: 12/21/2006
Event Time: 14:00 [EST]
Last Update Date: 01/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANTHONY DIMITRIADIS (R1)
GREG MORELL (NMSS)
ILTAB (EMAIL)
ANTHONY DIMITRIADIS (R1)
GREG MORELL (NMSS)
ILTAB (EMAIL)
AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS
On December 21, 2006 at approximately 2 pm local time the Maine Radiation Control Program received notification from a licensee, the City of Presque Isle, that they had lost 5 tritium exit signs during building renovations. Sometime between August 2006 and December 2006 at the time of the report to the state the licensee noted that 6 tritium exit signs had been disposed of as part of renovations to Building 1309. The signs were manufactured by Safety Light Corporation, Model 2040-50-20. The serial numbers are 0941221, 0941229, 0941223, 0941227, 0941225, and 0941228. While the exact location of the signs is not known they were probably disposed of in the trash. The state estimated the activity per sign to be about 5 Curies. The state is following up on this report.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source
On December 21, 2006 at approximately 2 pm local time the Maine Radiation Control Program received notification from a licensee, the City of Presque Isle, that they had lost 5 tritium exit signs during building renovations. Sometime between August 2006 and December 2006 at the time of the report to the state the licensee noted that 6 tritium exit signs had been disposed of as part of renovations to Building 1309. The signs were manufactured by Safety Light Corporation, Model 2040-50-20. The serial numbers are 0941221, 0941229, 0941223, 0941227, 0941225, and 0941228. While the exact location of the signs is not known they were probably disposed of in the trash. The state estimated the activity per sign to be about 5 Curies. The state is following up on this report.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source