Event Notification Report for December 13, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/12/2014 - 12/13/2014
Power Reactor
Event Number: 50677
Facility: FARLEY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: CHARLES BAREFIELD
HQ OPS Officer: DANIEL MILLS
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: CHARLES BAREFIELD
HQ OPS Officer: DANIEL MILLS
Notification Date: 12/13/2014
Notification Time: 10:00 [ET]
Event Date: 12/13/2014
Event Time: 01:52 [CST]
Last Update Date: 12/13/2014
Notification Time: 10:00 [ET]
Event Date: 12/13/2014
Event Time: 01:52 [CST]
Last Update Date: 12/13/2014
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):
BINOY DESAI (R2DO)
BINOY DESAI (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 0 | Hot Standby |
MALFUNCTION OF SMOKE DETECTION SYSTEM IN CONTAINMENT DUE TO HIGH HUMIDITY
"At 0152 CST on December 13, 2014, both strings of the Unit 2 containment smoke detection system were declared non-functional due to a non-radioactive steam leak inside containment. The steam leak was causing spurious alarms to the smoke detection system. This condition prevents identification and assessment of a fire in containment. Required compensatory measures have been established. Since a fire in the containment building is an entry condition for the site's emergency plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii).
"The NRC Resident Inspector has been informed."
The steam leak was caused by a faulty main steam flow detector. The licensee has shut down the reactor to effect repairs.
"At 0152 CST on December 13, 2014, both strings of the Unit 2 containment smoke detection system were declared non-functional due to a non-radioactive steam leak inside containment. The steam leak was causing spurious alarms to the smoke detection system. This condition prevents identification and assessment of a fire in containment. Required compensatory measures have been established. Since a fire in the containment building is an entry condition for the site's emergency plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii).
"The NRC Resident Inspector has been informed."
The steam leak was caused by a faulty main steam flow detector. The licensee has shut down the reactor to effect repairs.
Power Reactor
Event Number: 50686
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUG LAMARCA
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUG LAMARCA
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/16/2014
Notification Time: 17:31 [ET]
Event Date: 12/13/2014
Event Time: 17:00 [EST]
Last Update Date: 12/16/2014
Notification Time: 17:31 [ET]
Event Date: 12/13/2014
Event Time: 17:00 [EST]
Last Update Date: 12/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN ROGGE (R1DO)
JOHN ROGGE (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Cold Shutdown |
DEGRADED REACTOR COOLANT PRESSURE BOUNDARY
"On 12/13/14 at 1700 [EST] hours, during a planned Unit 1 maintenance outage the licensee identified leakage from a weld on the [.75 inch] lower seal vent piping connected to the 1B reactor recirculation pump lower seal area. The location is within the reactor recirculation loop isolation valves, therefore isolable from the reactor vessel. The piping is ASME Class 2 and is a reactor coolant pressure boundary. The reactor was in mode 3 at the time of discovery. Control Room notified at 1345 [EST] on 12/16/14, that requirements for 10CFR50.72(b)(3)(ii)(A) were not met.
"This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A)."
The unit was taken to Mode 4 and the seal vent piping repair was completed.
The NRC Resident Inspector has been notified.
"On 12/13/14 at 1700 [EST] hours, during a planned Unit 1 maintenance outage the licensee identified leakage from a weld on the [.75 inch] lower seal vent piping connected to the 1B reactor recirculation pump lower seal area. The location is within the reactor recirculation loop isolation valves, therefore isolable from the reactor vessel. The piping is ASME Class 2 and is a reactor coolant pressure boundary. The reactor was in mode 3 at the time of discovery. Control Room notified at 1345 [EST] on 12/16/14, that requirements for 10CFR50.72(b)(3)(ii)(A) were not met.
"This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A)."
The unit was taken to Mode 4 and the seal vent piping repair was completed.
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 50679
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: ECS-MID ATLANTIC, INC.
Region: 1
City: LEESBURG State: VA
County: LOUDOUN
License #: 107-314-1
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: JOHN SHOEMAKER
Licensee: ECS-MID ATLANTIC, INC.
Region: 1
City: LEESBURG State: VA
County: LOUDOUN
License #: 107-314-1
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/15/2014
Notification Time: 14:41 [ET]
Event Date: 12/13/2014
Event Time: 00:00 [EST]
Last Update Date: 12/15/2014
Notification Time: 14:41 [ET]
Event Date: 12/13/2014
Event Time: 00:00 [EST]
Last Update Date: 12/15/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN ROGGE (R1DO)
NMSS EVENTS NOTIFICA (EMAI)
JOHN ROGGE (R1DO)
NMSS EVENTS NOTIFICA (EMAI)
AGREEMENT STATE REPORT - DAMAGED PORTABLE GAUGE
The following report was received from the Commonwealth of Virginia via email:
"On Saturday, December 13th [2014], a CPN MCIDR moisture/density gauge was run over at a temporary jobsite in Leesburg, Virginia (Battlefield Parkway and Sycolin Road). The licensee's authorized user was performing a test and walked about 20 feet away from the gauge. The general contractor's bulldozer operator did not see the gauge because the bulldozer blade was raised, which obstructed his view when driving the bulldozer up the slope.
"The gauge was completely destroyed with the source in the transmission position. The authorized user contacted the construction testing services manager who then contacted the radiation safety officer. Both individuals arrived on scene and were able to retract the source into the shielded position using a pair of pliers. A radiation survey was performed at 1 meter indicating a reading of 0.4 mrem/hr. The gauge was then placed into the transportation case and returned to storage where a wipe test was performed. The wipe test has been sent to a licensed service provider for analysis and if no contamination is present, the gauge will be returned [pending final resolution].
"The licensee submitted an incident report, which is under review by the [Virginia] Radioactive Materials Program. The incident and suggested corrective actions will also be re-examined during the next inspection."
Event Report ID No.: VA-14-25
The following report was received from the Commonwealth of Virginia via email:
"On Saturday, December 13th [2014], a CPN MCIDR moisture/density gauge was run over at a temporary jobsite in Leesburg, Virginia (Battlefield Parkway and Sycolin Road). The licensee's authorized user was performing a test and walked about 20 feet away from the gauge. The general contractor's bulldozer operator did not see the gauge because the bulldozer blade was raised, which obstructed his view when driving the bulldozer up the slope.
"The gauge was completely destroyed with the source in the transmission position. The authorized user contacted the construction testing services manager who then contacted the radiation safety officer. Both individuals arrived on scene and were able to retract the source into the shielded position using a pair of pliers. A radiation survey was performed at 1 meter indicating a reading of 0.4 mrem/hr. The gauge was then placed into the transportation case and returned to storage where a wipe test was performed. The wipe test has been sent to a licensed service provider for analysis and if no contamination is present, the gauge will be returned [pending final resolution].
"The licensee submitted an incident report, which is under review by the [Virginia] Radioactive Materials Program. The incident and suggested corrective actions will also be re-examined during the next inspection."
Event Report ID No.: VA-14-25