Event Notification Report for June 14, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/13/2012 - 06/14/2012
EVENT NUMBERS
48024480264804248031
Power Reactor
Event Number: 48024
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVEN JOHNSTON
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVEN JOHNSTON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/14/2012
Notification Time: 09:53 [ET]
Event Date: 06/14/2012
Event Time: 06:07 [EDT]
Last Update Date: 06/14/2012
Notification Time: 09:53 [ET]
Event Date: 06/14/2012
Event Time: 06:07 [EDT]
Last Update Date: 06/14/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1DO)
HAROLD GRAY (R1DO)
| 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 OUT OF SERVICE AND OFFSITE NOTIFICATION DUE TO LOSS OF POWER TO SITE EMERGENCY BUILDING
"At 0607 hrs. EDT, a vehicle struck a pole on Route 9, immediately in front of the site, causing a loss of power to the Technical Support Center (TSC). At 0615 hrs., the Fire Brigade was dispatched to investigate reports of a 'smoldering' transformer behind the Site Emergency Building (SEB) and Oyster Creek Administration Building (OCAB.) At approximately 0708 hrs., the on-scene Fire Brigade Leader called the local fire department, because, in his determination, it was an event or situation that was related to the health and safety of the onsite personnel. At 0717 hrs., the local fire department came on-site in response to the call. Upon investigation, it was found that the transformer was smoking due to overheating. There was no fire and no Emergency Action Level (EAL) was applicable for this event. Due to the notification and response of the local fire department, a 4-hour report is required per 10CFR50.72(b)(2)(xi).
"At 0731 hrs., power was restored to the TSC and the TSC was restored to a fully operable condition. Due to the loss of the power to the TSC for greater than one hour (time required for TSC staffing), an 8-hour report is required in accordance with 10CFR50.72(b)(3)(xiii).
"The NRC Senior Resident was on-site and notified of the event."
"At 0607 hrs. EDT, a vehicle struck a pole on Route 9, immediately in front of the site, causing a loss of power to the Technical Support Center (TSC). At 0615 hrs., the Fire Brigade was dispatched to investigate reports of a 'smoldering' transformer behind the Site Emergency Building (SEB) and Oyster Creek Administration Building (OCAB.) At approximately 0708 hrs., the on-scene Fire Brigade Leader called the local fire department, because, in his determination, it was an event or situation that was related to the health and safety of the onsite personnel. At 0717 hrs., the local fire department came on-site in response to the call. Upon investigation, it was found that the transformer was smoking due to overheating. There was no fire and no Emergency Action Level (EAL) was applicable for this event. Due to the notification and response of the local fire department, a 4-hour report is required per 10CFR50.72(b)(2)(xi).
"At 0731 hrs., power was restored to the TSC and the TSC was restored to a fully operable condition. Due to the loss of the power to the TSC for greater than one hour (time required for TSC staffing), an 8-hour report is required in accordance with 10CFR50.72(b)(3)(xiii).
"The NRC Senior Resident was on-site and notified of the event."
Power Reactor
Event Number: 48026
Facility: FARLEY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: PETE SNYDER
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: PETE SNYDER
Notification Date: 06/14/2012
Notification Time: 18:48 [ET]
Event Date: 06/14/2012
Event Time: 13:53 [CDT]
Last Update Date: 06/14/2012
Notification Time: 18:48 [ET]
Event Date: 06/14/2012
Event Time: 13:53 [CDT]
Last Update Date: 06/14/2012
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 |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
CONTROL ROOM ANNUNCIATOR OUTAGE
"During a maintenance task to replace a main control board annunciator power supply an electrical short occurred while installing a jumper. This caused two circuit breakers to trip and a loss of all control room annunciators. The cause of the short was identified and corrected. The two circuit breakers were closed and the annunciator function was restored at 1358 CDT resulting in a total out of service time of 5 minutes. The unit was at a stable 100% power during the loss of annunciators."
The licensee notified the NRC Resident Inspector.
"During a maintenance task to replace a main control board annunciator power supply an electrical short occurred while installing a jumper. This caused two circuit breakers to trip and a loss of all control room annunciators. The cause of the short was identified and corrected. The two circuit breakers were closed and the annunciator function was restored at 1358 CDT resulting in a total out of service time of 5 minutes. The unit was at a stable 100% power during the loss of annunciators."
The licensee notified the NRC Resident Inspector.
Part 21
Event Number: 48042
Rep Org: ROSEMOUNT NUCLEAR INSTRUMENTS, INC.
Licensee: ROSEMOUNT NUCLEAR INSTRUMENTS, INC.
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFF CHIVERS
HQ OPS Officer: DONG HWA PARK
Licensee: ROSEMOUNT NUCLEAR INSTRUMENTS, INC.
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFF CHIVERS
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/21/2012
Notification Time: 15:03 [ET]
Event Date: 06/14/2012
Event Time: 00:00 [CDT]
Last Update Date: 06/21/2012
Notification Time: 15:03 [ET]
Event Date: 06/14/2012
Event Time: 00:00 [CDT]
Last Update Date: 06/21/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
DANIEL HOLODY (R1DO)
ALAN BLAMEY (R2DO)
JULIO LARA (R3DO)
GEOFFREY MILLER (R4DO)
PART 21 GRP BY EMAIL
DANIEL HOLODY (R1DO)
ALAN BLAMEY (R2DO)
JULIO LARA (R3DO)
GEOFFREY MILLER (R4DO)
PART 21 GRP BY EMAIL
PART 21 - RELIABILITY DEGRADATION OF RESISTORS IN TRIP UNITS AND READOUT ASSEMBLIES
"Certain 710DU Trip Units may not perform their intended safety function as a result of certain wire wound precision resistors experiencing a degradation of reliability. Additionally, certain 710DU Readout Assemblies used to calibrate 710DU Trip Units may experience degraded digital display accuracy during calibration due to a similar cause. Rosemount Nuclear Instruments, Inc. does not have complete information relating to specific plant applications and therefore cannot determine the potential effects of the condition on plant operation.
"This notification affects certain Model 710DU Trip Units and certain 710DU Readout Assemblies shipped from Rosemount Nuclear Instruments, Inc. between March 16, 2005 and May 10, 2012."
The shipments were distributed to Ginna, Nine Mile Point, Fermi, Columbia Generating Station, Fitzpatrick, River Bend Station, Grand Gulf, Quad Cities, Peach Bottom, LaSalle, Limerick, Dresden, Perry, Hope Creek, Hatch, Brunswick, Browns Ferry, and Monticello.
"Certain 710DU Trip Units may not perform their intended safety function as a result of certain wire wound precision resistors experiencing a degradation of reliability. Additionally, certain 710DU Readout Assemblies used to calibrate 710DU Trip Units may experience degraded digital display accuracy during calibration due to a similar cause. Rosemount Nuclear Instruments, Inc. does not have complete information relating to specific plant applications and therefore cannot determine the potential effects of the condition on plant operation.
"This notification affects certain Model 710DU Trip Units and certain 710DU Readout Assemblies shipped from Rosemount Nuclear Instruments, Inc. between March 16, 2005 and May 10, 2012."
The shipments were distributed to Ginna, Nine Mile Point, Fermi, Columbia Generating Station, Fitzpatrick, River Bend Station, Grand Gulf, Quad Cities, Peach Bottom, LaSalle, Limerick, Dresden, Perry, Hope Creek, Hatch, Brunswick, Browns Ferry, and Monticello.
Agreement State
Event Number: 48031
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NUCOR STEEL TEXAS DIVISION
Region: 4
City: JEWETT State: TX
County:
License #: 02504
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Licensee: NUCOR STEEL TEXAS DIVISION
Region: 4
City: JEWETT State: TX
County:
License #: 02504
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/15/2012
Notification Time: 17:37 [ET]
Event Date: 06/14/2012
Event Time: 09:00 [CDT]
Last Update Date: 06/15/2012
Notification Time: 17:37 [ET]
Event Date: 06/14/2012
Event Time: 09:00 [CDT]
Last Update Date: 06/15/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RYAN LANTZ (R4DO)
FSME EVENT RESOURCE (EMAI)
RYAN LANTZ (R4DO)
FSME EVENT RESOURCE (EMAI)
AGREEMENT STATE REPORT INVOLVING FIVE DAMAGED NUCLEAR GAUGE HOUSINGS
The following information was provided by the State of Texas via email:
"On June 15, 2012, the Agency [Texas Dept. of Health] was notified by a licensee that the shutters on five Berthold Technologies Model LB300ML nuclear gauges were stuck in the open position. Open is the normal operating position for the shutters. The sources were manufactured in December of 2011 and each contained an original activity of 4.0 millicuries of cobalt - 60. The licensee was not able to provide serial numbers for the gauges or sources. The gauges are used in a steel mold and protected inside of the mold housing. An electrical power failure at the facility caused molten steel to pour on the gauge protective housing and leak into the area around the gauges. The licensee contacted a service provider who inspected the gauges on June 15, 2012. The service provider stated that the shutters would not operate, but the sources did not appear to be affected. The licensee stated that there was no increased risk of exposure to their workers due to the failed shutters. The licensee stated that the sources would be leak tested on June 15, 2012. The licensee intends to replace the gauge housing and reuse the sources from the gauges. Additional information will be provided as it is received in accordance with SA 300."
Texas Incident No.: I-8960
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)
The following information was provided by the State of Texas via email:
"On June 15, 2012, the Agency [Texas Dept. of Health] was notified by a licensee that the shutters on five Berthold Technologies Model LB300ML nuclear gauges were stuck in the open position. Open is the normal operating position for the shutters. The sources were manufactured in December of 2011 and each contained an original activity of 4.0 millicuries of cobalt - 60. The licensee was not able to provide serial numbers for the gauges or sources. The gauges are used in a steel mold and protected inside of the mold housing. An electrical power failure at the facility caused molten steel to pour on the gauge protective housing and leak into the area around the gauges. The licensee contacted a service provider who inspected the gauges on June 15, 2012. The service provider stated that the shutters would not operate, but the sources did not appear to be affected. The licensee stated that there was no increased risk of exposure to their workers due to the failed shutters. The licensee stated that the sources would be leak tested on June 15, 2012. The licensee intends to replace the gauge housing and reuse the sources from the gauges. Additional information will be provided as it is received in accordance with SA 300."
Texas Incident No.: I-8960
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)