Event Notification Report for January 14, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/13/2011 - 01/14/2011
EVENT NUMBERS
4654746538465394654046542
Non-Agreement State
Event Number: 46547
Rep Org: ELI LILLY AND COMPANY
Licensee: ELI LILLY AND COMPANY
Region: 3
City: INDIANAPOLIS State: IN
County:
License #:
Agreement: N
Docket:
NRC Notified By: STAN HANPTON
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: ELI LILLY AND COMPANY
Region: 3
City: INDIANAPOLIS State: IN
County:
License #:
Agreement: N
Docket:
NRC Notified By: STAN HANPTON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/17/2011
Notification Time: 10:48 [ET]
Event Date: 01/14/2011
Event Time: 00:00 [EST]
Last Update Date: 02/08/2011
Notification Time: 10:48 [ET]
Event Date: 01/14/2011
Event Time: 00:00 [EST]
Last Update Date: 02/08/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
LAURA PEARSON (ILTA)
LARRY CAMPER (FSME)
MICHAEL KUNOWSKI (R3DO)
LAURA PEARSON (ILTA)
LARRY CAMPER (FSME)
LOST TRITIUM EXIT SIGNS
A major renovation was performed in two floors of Building 22 on the Eli Lilly Campus. This renovation was completed in December, 2010. An inventory of tritium exit signs was performed and eight exit signs on the two floors were found missing and presumed disposed of during the renovation. The exit signs each contained approximately 10 Curies of tritium. The licensee will perform wipe tests but expects negative results since the concrete surfaces were all covered with carpet, tile, or wall coverings.
Four Evenlite Model 201 serial numbers 57281, 59311, 57381, 57421
Four SRBT Model BX serial numbers C035796, C035795, C035790, C035789
* * * UPDATE AT 1555 ON 2/8/2011 FROM STAN HANPTON TO MARK ABRAMOVITZ * * *
The inventory of tritium exit signs was extended and eight additional tritium exit signs were missing. These additional exit signs were assigned to building 31 on the Eli Lilly Campus. This building had also been recently renovated. Each sign contained approximately 10 Ci tritium. Wipe tests in building 22 and 31 were performed with no activity detected.
Notified the R3DO (Duncan), ILTAB (Allston), and FSME (McConnell).
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
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
A major renovation was performed in two floors of Building 22 on the Eli Lilly Campus. This renovation was completed in December, 2010. An inventory of tritium exit signs was performed and eight exit signs on the two floors were found missing and presumed disposed of during the renovation. The exit signs each contained approximately 10 Curies of tritium. The licensee will perform wipe tests but expects negative results since the concrete surfaces were all covered with carpet, tile, or wall coverings.
Four Evenlite Model 201 serial numbers 57281, 59311, 57381, 57421
Four SRBT Model BX serial numbers C035796, C035795, C035790, C035789
* * * UPDATE AT 1555 ON 2/8/2011 FROM STAN HANPTON TO MARK ABRAMOVITZ * * *
The inventory of tritium exit signs was extended and eight additional tritium exit signs were missing. These additional exit signs were assigned to building 31 on the Eli Lilly Campus. This building had also been recently renovated. Each sign contained approximately 10 Ci tritium. Wipe tests in building 22 and 31 were performed with no activity detected.
Notified the R3DO (Duncan), ILTAB (Allston), and FSME (McConnell).
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
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
Power Reactor
Event Number: 46538
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: KENNETH BRESLIN
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: KENNETH BRESLIN
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/14/2011
Notification Time: 11:49 [ET]
Event Date: 01/14/2011
Event Time: 04:26 [EST]
Last Update Date: 01/14/2011
Notification Time: 11:49 [ET]
Event Date: 01/14/2011
Event Time: 04:26 [EST]
Last Update Date: 01/14/2011
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):
LAWRENCE DOERFLEIN (R1DO)
LAWRENCE DOERFLEIN (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 |
LOSS OF ENS AND ERDS CAPABILITY DUE TO A FAILURE OF THE PHONE SYSTEM UPS
"On January 14, 2011 from 0426 to 0551 [EST] the NRC ENS phone line was lost for Hope Creek and Salem Units 1 and 2. The loss of the phone lines occurred during planned island ring bus switching and was caused by a failure of the phone system Uninterruptible Power Supply (UPS). The phone system UPS was manually restored by Information Technology personnel and the phone line was verified to be operational. The loss of the phone line had no effect on plant operations and all three units remain at 100% power.
"Additionally, Emergency Response Data System (ERDS) capability was lost during this time period and has been restored.
"The station has initiated a prompt investigation into the cause of the failure of the phone system UPS to properly transfer.
"No personnel injuries resulted from the event.
"The NRC Resident Inspector has been notified."
"On January 14, 2011 from 0426 to 0551 [EST] the NRC ENS phone line was lost for Hope Creek and Salem Units 1 and 2. The loss of the phone lines occurred during planned island ring bus switching and was caused by a failure of the phone system Uninterruptible Power Supply (UPS). The phone system UPS was manually restored by Information Technology personnel and the phone line was verified to be operational. The loss of the phone line had no effect on plant operations and all three units remain at 100% power.
"Additionally, Emergency Response Data System (ERDS) capability was lost during this time period and has been restored.
"The station has initiated a prompt investigation into the cause of the failure of the phone system UPS to properly transfer.
"No personnel injuries resulted from the event.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 46539
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DARRIN GARD
HQ OPS Officer: VINCE KLCO
Region: 2 State: AL
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DARRIN GARD
HQ OPS Officer: VINCE KLCO
Notification Date: 01/14/2011
Notification Time: 12:47 [ET]
Event Date: 01/14/2011
Event Time: 11:25 [CST]
Last Update Date: 01/14/2011
Notification Time: 12:47 [ET]
Event Date: 01/14/2011
Event Time: 11:25 [CST]
Last Update Date: 01/14/2011
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):
BRIAN BONSER (R2DO)
BRIAN BONSER (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"The Technical Support Center HVAC unit has been removed from service for a planned maintenance outage with an expected duration of 8 hours. A 10 CFR 50.54(q) evaluation has been performed for this outage and the current level of effectiveness of the FNP [Farley Nuclear Plant] Emergency Plan is maintained. Alternate Technical Support Center capability has been verified in accordance with site procedure FNP-0-EIP-6.0, Technical Support Center Setup and Activation. Technical Support Center HVAC is expected to be returned to service at 1925 [CST] on 1/14/11."
The licensee notified the NRC Resident Inspector.
"The Technical Support Center HVAC unit has been removed from service for a planned maintenance outage with an expected duration of 8 hours. A 10 CFR 50.54(q) evaluation has been performed for this outage and the current level of effectiveness of the FNP [Farley Nuclear Plant] Emergency Plan is maintained. Alternate Technical Support Center capability has been verified in accordance with site procedure FNP-0-EIP-6.0, Technical Support Center Setup and Activation. Technical Support Center HVAC is expected to be returned to service at 1925 [CST] on 1/14/11."
The licensee notified the NRC Resident Inspector.
Non-Agreement State
Event Number: 46540
Rep Org: INDIANA MICHIGAN POWER
Licensee: AMERICAN ELECTRIC POWER
Region: 3
City: ROCKPORT State: IN
County: SPENCER
License #: GL-704402-14
Agreement: N
Docket:
NRC Notified By: PHILIP C. CASPER
HQ OPS Officer: STEVE SANDIN
Licensee: AMERICAN ELECTRIC POWER
Region: 3
City: ROCKPORT State: IN
County: SPENCER
License #: GL-704402-14
Agreement: N
Docket:
NRC Notified By: PHILIP C. CASPER
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/14/2011
Notification Time: 13:50 [ET]
Event Date: 01/14/2011
Event Time: 10:00 [EST]
Last Update Date: 01/14/2011
Notification Time: 13:50 [ET]
Event Date: 01/14/2011
Event Time: 10:00 [EST]
Last Update Date: 01/14/2011
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):
MICHAEL KUNOWSKI (R3DO)
GLENDA VILLAMAR (FSME)
MICHAEL KUNOWSKI (R3DO)
GLENDA VILLAMAR (FSME)
FIXED GAUGE SHUTTER UNABLE TO CLOSE DUE TO MECHANICAL FAILURE
"On Friday, January 14, 2011 at approximately 1000 Hrs (EST) one of [the] facility Assistant RSOs was advised that one of our devices was inoperable. This was due to a failure in the cable handle bracket mechanism, not the source itself. The handle that operates the cable that opens and closes the level indicator is held in place by a bracket that is mounted (bolted) to the side of the equipment. The lower lever pivot (hinge) bracket failed, probably due to age, resulting in an inability to operate the mechanism as designed. The radiation source is located between two Gas Recirculation Hoppers approximately 10-15 feet away.
"The equipment has been tagged pending repair, and affected employees were notified.
"A manufacturer's authorized repair technician has been scheduled to make repairs on Thursday, January 20, 2011. Upon completion of repairs and after the device has been inspected and placed back in service [the licensee] shall notify [the NRC] in writing.
"Location:
Indiana Michigan Power
A Division of American Electric Power
Rockport Plant
Spencer County
2791 North US Hwy 231
Rockport, IN 47635
"Isotopes: Cs-137
Quantities: 100mCi
Chemical/Physical Form: Gas Recirculation Hopper Level Indicator
Manufacturer: Texas Nuclear
Device Model: 5197
Device Serial Number: LE/LX 5705
Source Serial Number: B2147
"No personnel exposure or injuries sustained."
"On Friday, January 14, 2011 at approximately 1000 Hrs (EST) one of [the] facility Assistant RSOs was advised that one of our devices was inoperable. This was due to a failure in the cable handle bracket mechanism, not the source itself. The handle that operates the cable that opens and closes the level indicator is held in place by a bracket that is mounted (bolted) to the side of the equipment. The lower lever pivot (hinge) bracket failed, probably due to age, resulting in an inability to operate the mechanism as designed. The radiation source is located between two Gas Recirculation Hoppers approximately 10-15 feet away.
"The equipment has been tagged pending repair, and affected employees were notified.
"A manufacturer's authorized repair technician has been scheduled to make repairs on Thursday, January 20, 2011. Upon completion of repairs and after the device has been inspected and placed back in service [the licensee] shall notify [the NRC] in writing.
"Location:
Indiana Michigan Power
A Division of American Electric Power
Rockport Plant
Spencer County
2791 North US Hwy 231
Rockport, IN 47635
"Isotopes: Cs-137
Quantities: 100mCi
Chemical/Physical Form: Gas Recirculation Hopper Level Indicator
Manufacturer: Texas Nuclear
Device Model: 5197
Device Serial Number: LE/LX 5705
Source Serial Number: B2147
"No personnel exposure or injuries sustained."
Power Reactor
Event Number: 46542
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: GREG MERTA
HQ OPS Officer: VINCE KLCO
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: GREG MERTA
HQ OPS Officer: VINCE KLCO
Notification Date: 01/14/2011
Notification Time: 14:31 [ET]
Event Date: 01/14/2011
Event Time: 08:40 [CST]
Last Update Date: 01/21/2011
Notification Time: 14:31 [ET]
Event Date: 01/14/2011
Event Time: 08:40 [CST]
Last Update Date: 01/21/2011
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):
MICHAEL KUNOWSKI (R3DO)
MICHAEL KUNOWSKI (R3DO)
| 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 DUE TO MAINTENANCE
"At 0840 [CST] on Friday, January 14, 2011, a portion of the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) ventilation was removed from service to conduct maintenance on the charcoal filter medium. The TSC Stand-by Filter Unit (TSC-SFU) was found with deluge water in the bottom of the charcoal filtration bed, and is therefore non-functional.
"Under certain accident conditions the TSC may become unavailable due to the inability of the ventilation system to maintain a habitable atmosphere.
"The licensee has notified the NRC Resident Inspector. This notification is being made in accordance with 10 CFR 50.72 (b) (3) (xiii) due to a loss of emergency response facility."
* * * UPDATE AT 1105 ON 1/21/11 FROM ROB SPADING TO PETE SNYDER * * *
Maintenance has been completed and the TSC is returned to service as of 1005 CST.
Notified R3DO (Bloomer).
"At 0840 [CST] on Friday, January 14, 2011, a portion of the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) ventilation was removed from service to conduct maintenance on the charcoal filter medium. The TSC Stand-by Filter Unit (TSC-SFU) was found with deluge water in the bottom of the charcoal filtration bed, and is therefore non-functional.
"Under certain accident conditions the TSC may become unavailable due to the inability of the ventilation system to maintain a habitable atmosphere.
"The licensee has notified the NRC Resident Inspector. This notification is being made in accordance with 10 CFR 50.72 (b) (3) (xiii) due to a loss of emergency response facility."
* * * UPDATE AT 1105 ON 1/21/11 FROM ROB SPADING TO PETE SNYDER * * *
Maintenance has been completed and the TSC is returned to service as of 1005 CST.
Notified R3DO (Bloomer).