Event Notification Report for November 26, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/25/2012 - 11/26/2012
Non-Agreement State
Event Number: 48535
Rep Org: DOW CORNING
Licensee: DOW CORNING, MIDLAND PLANT
Region: 3
City: MIDLAND State: MI
County:
License #: 21-08362-12
Agreement: N
Docket:
NRC Notified By: DAVID DILLON
HQ OPS Officer: STEVE SANDIN
Licensee: DOW CORNING, MIDLAND PLANT
Region: 3
City: MIDLAND State: MI
County:
License #: 21-08362-12
Agreement: N
Docket:
NRC Notified By: DAVID DILLON
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/26/2012
Notification Time: 12:50 [ET]
Event Date: 11/26/2012
Event Time: 09:30 [EST]
Last Update Date: 11/26/2012
Notification Time: 12:50 [ET]
Event Date: 11/26/2012
Event Time: 09:30 [EST]
Last Update Date: 11/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
ANN MARIE STONE (R3DO)
FSME EVENTS RESOURCE (EMAI)
ANN MARIE STONE (R3DO)
FSME EVENTS RESOURCE (EMAI)
PROCESS INSTRUMENT SHUTTER FAILURE
During a routine semiannual periodic inspection, a process gauge with a 15 milliCurie Cs-137 source was identified to have a stuck shutter. The gauge was an Ohmart Model SHF1-A45, S/N 0923GK. The instrument is permanently installed on a distillation column about 30 - 35 ft. from the ground. The integrity of the gauge is fine. Surveys indicated that radiation levels surrounding the gauge were less than 1 millirem per hour.
The same issue involving this specific gauge was reported previously in EN #46913.
The licensee plans on having the gauge repaired by the manufacturer.
During a routine semiannual periodic inspection, a process gauge with a 15 milliCurie Cs-137 source was identified to have a stuck shutter. The gauge was an Ohmart Model SHF1-A45, S/N 0923GK. The instrument is permanently installed on a distillation column about 30 - 35 ft. from the ground. The integrity of the gauge is fine. Surveys indicated that radiation levels surrounding the gauge were less than 1 millirem per hour.
The same issue involving this specific gauge was reported previously in EN #46913.
The licensee plans on having the gauge repaired by the manufacturer.
Power Reactor
Event Number: 48536
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: TYLER HALYE
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: TYLER HALYE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/26/2012
Notification Time: 17:29 [ET]
Event Date: 11/26/2012
Event Time: 10:29 [EST]
Last Update Date: 11/26/2012
Notification Time: 17:29 [ET]
Event Date: 11/26/2012
Event Time: 10:29 [EST]
Last Update Date: 11/26/2012
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):
DAVID AYRES (R2DO)
DAVID AYRES (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 |
LOSS OF ASSESSMENT CAPABILITY- RADIATION MONITOR INOPERABLE FOR PRE-PLANNED MAINTENANCE
"This is a non-emergency notification. At 1029 EST on November 26, 2012, radiation monitor RM-1 WV-3546-1, Waste Processing Building Wide Range Gas Monitor was declared inoperable for pre-planned maintenance. This monitor is the only monitor credited in the EALs for monitoring a gaseous release from the Waste Processing Building.
"This radiation monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and Is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. This condition does not affect the health of safety of the public or the operation of the facility. An alternative method for sampling and determination of activity levels has been implemented."
The licensee stated that the radiation monitor was returned to service at 1728 EST on 11/26/12.
The licensee has notified the NRC Resident Inspector.
"This is a non-emergency notification. At 1029 EST on November 26, 2012, radiation monitor RM-1 WV-3546-1, Waste Processing Building Wide Range Gas Monitor was declared inoperable for pre-planned maintenance. This monitor is the only monitor credited in the EALs for monitoring a gaseous release from the Waste Processing Building.
"This radiation monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and Is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. This condition does not affect the health of safety of the public or the operation of the facility. An alternative method for sampling and determination of activity levels has been implemented."
The licensee stated that the radiation monitor was returned to service at 1728 EST on 11/26/12.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48537
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE JOHNSTON
HQ OPS Officer: CHARLES TEAL
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE JOHNSTON
HQ OPS Officer: CHARLES TEAL
Notification Date: 11/27/2012
Notification Time: 00:02 [ET]
Event Date: 11/26/2012
Event Time: 19:30 [EST]
Last Update Date: 11/27/2012
Notification Time: 00:02 [ET]
Event Date: 11/26/2012
Event Time: 19:30 [EST]
Last Update Date: 11/27/2012
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):
JAMES DWYER (R1DO)
JAMES DWYER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DEGRADED CONDITION DUE TO PINHOLE LEAK IN REACTOR HEAD SPRAY LINE
"Pinhole leak discovered on a Reactor Head Spray line weld during Nuclear Steam Supply System Leak Test.
"Oyster Creek Nuclear Generating Station is currently in the Shutdown Condition executing Refueling Outage 1R24, which includes Nuclear Steam Supply System (NSSS) Leak Testing, prior to startup.
"At 1930 on 11/26/2012, a pinhole leak was discovered on a Reactor Head Spray Class 1 piping weld. The leak was discovered during the NSSS Leak Test, while the Reactor was in the Shutdown Condition. The leak is on a flange to piping weld on the Reactor Head Spray system upstream of the N-7B nozzle. Water was found to be weeping from the pinhole leak (approximately 2 to 3 drops per minute).
"The cause is under investigation and corrective action plans are being developed.
"The leak has been evaluated by Exelon and determined to meet the criteria for reporting identified in NUREG-1022: Welding or material defects in the primary coolant system that cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws,' or ASME Section XI, Table IWB-3410-1, 'Acceptable Standards.'"
The NRC Resident Inspector has been informed.
"Pinhole leak discovered on a Reactor Head Spray line weld during Nuclear Steam Supply System Leak Test.
"Oyster Creek Nuclear Generating Station is currently in the Shutdown Condition executing Refueling Outage 1R24, which includes Nuclear Steam Supply System (NSSS) Leak Testing, prior to startup.
"At 1930 on 11/26/2012, a pinhole leak was discovered on a Reactor Head Spray Class 1 piping weld. The leak was discovered during the NSSS Leak Test, while the Reactor was in the Shutdown Condition. The leak is on a flange to piping weld on the Reactor Head Spray system upstream of the N-7B nozzle. Water was found to be weeping from the pinhole leak (approximately 2 to 3 drops per minute).
"The cause is under investigation and corrective action plans are being developed.
"The leak has been evaluated by Exelon and determined to meet the criteria for reporting identified in NUREG-1022: Welding or material defects in the primary coolant system that cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws,' or ASME Section XI, Table IWB-3410-1, 'Acceptable Standards.'"
The NRC Resident Inspector has been informed.