Event Notification Report for October 22, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/21/2012 - 10/22/2012
EVENT NUMBERS
484294843048431484324843348472
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 48429
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/22/2012
Notification Time: 03:49 [ET]
Event Date: 10/22/2012
Event Time: 00:10 [CDT]
Last Update Date: 11/09/2012
Notification Time: 03:49 [ET]
Event Date: 10/22/2012
Event Time: 00:10 [CDT]
Last Update Date: 11/09/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
GREG PICK (R4DO)
GREG PICK (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
POTENTIAL CONDITION COULD BYPASS FLOODING BARRIERS AND AFFECT RESIDUAL HEAT REMOVAL EQUIPMENT
"During a walkdown evaluating potential for adverse consequences of site flooding, per 10CFR50.54(f) request, a condition was identified which had the potential to adversely impact the ability to address external flooding conditions. The old Emergency Offsite Facility (which currently houses information technology offices) has a drain pipe which connects to Sump AA in the Augmented Radwaste (ARW) building and bypasses the flooding barriers erected per maintenance procedure 7.0.11 in the event of site flooding.
"Per the USAR, the basis for site flooding is a flood with concurrent surge effects on exposed safety related structures reaching an elevation of 905 feet. This elevation is 2.0 feet above the grade elevation of 903 feet. Flooding protection for important site facilities is provided by installing temporary barriers protecting to elevation 906 feet. Primary and Secondary Flood Barriers are installed at the ARW building external entrances on the 903 feet elevation to protect the Reactor Building from external flood water. The drain piping from the old EOF floor drain and shower is piped directly to Sump AA in the ARW building basement. This is a 3 inch pipe which drains by gravity. There are no isolation features on the pipe, and no barriers to flooding are provided for this facility, thus the potential exists to bypass the flood barriers which would be erected around the ARW Building. Flooding of the building basement could result, disabling processing equipment. If the basement fills up, flood waters could enter the Reactor Building through the internal entrance, which has no additional protection installed. Floodwaters could then affect equipment which is required to remove residual heat.
"This condition has been determined to be reportable per 50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to remove residual heat. The potential condition was identified on 10/20/2012. Evaluation of the condition and the potential impact was completed and reportability determined on 10/22/2012. The condition has been entered into the Corrective Action Program."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 2211 EDT ON 10/22/12 FROM KYLE SAYLER TO S. SANDIN * * *
"During a walk down evaluating the potential for adverse consequences of site flooding per 10CFR50.54(f) request, a condition was identified which had the potential to adversely impact the ability to address external flooding conditions. The Optimum Water Chemistry (OWC) building has 5 floor drains, at ground level elevation 903 ft, which connect to a common 3 inch drain pipe which connects to a sanitary sump located in the Turbine building, at an elevation of 882 ft, and bypasses all flooding barriers erected per maintenance procedure 7.0.11 in the event of site flooding.
"Per the USAR, the basis for site flooding is a flood with a concurrent surge effect on exposed safely related structures reaching an elevation of 905 ft. This elevation is 2 ft above the grade of the floor drains. Flooding protection for important site facilities is provided by installing temporary barriers which provide protection to an elevation of 906 ft. Primary and secondary barriers are installed at the Turbine building external entrances to protect the Reactor building from external flood waters. Additional secondary barriers are erected inside the Turbine building to provide additional protection to the Diesel Generator rooms. The drain piping from the OWC building floor drains is piped directly to the sanitary sump located in the Turbine building. There are no isolation features on the piping and no barriers to flooding are erected between the Turbine building and Reactor building thus the potential exists to bypass the flood barriers erected around the Turbine building. Flooding of the Turbine building could result in the accumulation of water in sufficient quantities to fill the Turbine building 882.5ft elevation to the height of the external floodwaters which would then be allowed to flow unimpeded by flooding barriers to the Reactor building through the internal entrance which has no additional barriers installed. These floodwaters could then affect equipment, located within the Reactor building, which is required to remove residual heat.
"This condition has been determined to be reportable per 50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSC's. that needed to remove residual heat. This condition was identified at 1550 [CDT on] 10/22/2012 and has been entered into the Corrective Action Program."
The licensee informed the NRC Resident Inspector. Notified R4DO (Hagar).
* * * RETRACTION FROM DAVID MADSEN TO HOWIE CROUCH AT 1228 EST ON 11/9/12 * * *
"This notification is being made to retract Event Notification EN #48429 which reported a loss of safety function due to the discovery of two flow paths (one from the old Emergency Operating Facility and one from the Optimum Water Chemistry building) where an external event flood event at 905 feet would result in flooding of the Turbine and Radwaste basement and eventually the Reactor building basement.
"Upon further review, the design basis Probable Maximum Flood for CNS is 903 feet. The two water entry points discussed in the Event Notification are above the 903 foot elevation. Wave energy would be dissipated before reaching any of the main buildings so there would be a minimal influx of water into the structures. As such, there is no loss of safety function for equipment in the Reactor building basement. NPPD therefore retracts Event Notification EN #48429."
The NRC Resident Inspector has been notified. Notified R4DO (Farnholtz).
"During a walkdown evaluating potential for adverse consequences of site flooding, per 10CFR50.54(f) request, a condition was identified which had the potential to adversely impact the ability to address external flooding conditions. The old Emergency Offsite Facility (which currently houses information technology offices) has a drain pipe which connects to Sump AA in the Augmented Radwaste (ARW) building and bypasses the flooding barriers erected per maintenance procedure 7.0.11 in the event of site flooding.
"Per the USAR, the basis for site flooding is a flood with concurrent surge effects on exposed safety related structures reaching an elevation of 905 feet. This elevation is 2.0 feet above the grade elevation of 903 feet. Flooding protection for important site facilities is provided by installing temporary barriers protecting to elevation 906 feet. Primary and Secondary Flood Barriers are installed at the ARW building external entrances on the 903 feet elevation to protect the Reactor Building from external flood water. The drain piping from the old EOF floor drain and shower is piped directly to Sump AA in the ARW building basement. This is a 3 inch pipe which drains by gravity. There are no isolation features on the pipe, and no barriers to flooding are provided for this facility, thus the potential exists to bypass the flood barriers which would be erected around the ARW Building. Flooding of the building basement could result, disabling processing equipment. If the basement fills up, flood waters could enter the Reactor Building through the internal entrance, which has no additional protection installed. Floodwaters could then affect equipment which is required to remove residual heat.
"This condition has been determined to be reportable per 50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to remove residual heat. The potential condition was identified on 10/20/2012. Evaluation of the condition and the potential impact was completed and reportability determined on 10/22/2012. The condition has been entered into the Corrective Action Program."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 2211 EDT ON 10/22/12 FROM KYLE SAYLER TO S. SANDIN * * *
"During a walk down evaluating the potential for adverse consequences of site flooding per 10CFR50.54(f) request, a condition was identified which had the potential to adversely impact the ability to address external flooding conditions. The Optimum Water Chemistry (OWC) building has 5 floor drains, at ground level elevation 903 ft, which connect to a common 3 inch drain pipe which connects to a sanitary sump located in the Turbine building, at an elevation of 882 ft, and bypasses all flooding barriers erected per maintenance procedure 7.0.11 in the event of site flooding.
"Per the USAR, the basis for site flooding is a flood with a concurrent surge effect on exposed safely related structures reaching an elevation of 905 ft. This elevation is 2 ft above the grade of the floor drains. Flooding protection for important site facilities is provided by installing temporary barriers which provide protection to an elevation of 906 ft. Primary and secondary barriers are installed at the Turbine building external entrances to protect the Reactor building from external flood waters. Additional secondary barriers are erected inside the Turbine building to provide additional protection to the Diesel Generator rooms. The drain piping from the OWC building floor drains is piped directly to the sanitary sump located in the Turbine building. There are no isolation features on the piping and no barriers to flooding are erected between the Turbine building and Reactor building thus the potential exists to bypass the flood barriers erected around the Turbine building. Flooding of the Turbine building could result in the accumulation of water in sufficient quantities to fill the Turbine building 882.5ft elevation to the height of the external floodwaters which would then be allowed to flow unimpeded by flooding barriers to the Reactor building through the internal entrance which has no additional barriers installed. These floodwaters could then affect equipment, located within the Reactor building, which is required to remove residual heat.
"This condition has been determined to be reportable per 50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSC's. that needed to remove residual heat. This condition was identified at 1550 [CDT on] 10/22/2012 and has been entered into the Corrective Action Program."
The licensee informed the NRC Resident Inspector. Notified R4DO (Hagar).
* * * RETRACTION FROM DAVID MADSEN TO HOWIE CROUCH AT 1228 EST ON 11/9/12 * * *
"This notification is being made to retract Event Notification EN #48429 which reported a loss of safety function due to the discovery of two flow paths (one from the old Emergency Operating Facility and one from the Optimum Water Chemistry building) where an external event flood event at 905 feet would result in flooding of the Turbine and Radwaste basement and eventually the Reactor building basement.
"Upon further review, the design basis Probable Maximum Flood for CNS is 903 feet. The two water entry points discussed in the Event Notification are above the 903 foot elevation. Wave energy would be dissipated before reaching any of the main buildings so there would be a minimal influx of water into the structures. As such, there is no loss of safety function for equipment in the Reactor building basement. NPPD therefore retracts Event Notification EN #48429."
The NRC Resident Inspector has been notified. Notified R4DO (Farnholtz).
Power Reactor
Event Number: 48430
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROY GILES
HQ OPS Officer: STEVE SANDIN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROY GILES
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/22/2012
Notification Time: 13:28 [ET]
Event Date: 10/22/2012
Event Time: 06:42 [CDT]
Last Update Date: 10/22/2012
Notification Time: 13:28 [ET]
Event Date: 10/22/2012
Event Time: 06:42 [CDT]
Last Update Date: 10/22/2012
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):
BOB HAGAR (R4DO)
BOB HAGAR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
PARTIAL LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"At 0642 [CDT] on 10/22/2012 a failure of power supply RMA-ES-53B was indicated by multiple area radiation alarms in the Control Room. This failure results in the loss of ability to remotely measure and quantify radiation levels in multiple area in the Reactor Building, Turbine Building and Main Control Room. This power supply serves 10 of 30 area radiation monitors located throughout the plant. The remaining 20 monitors remain fully functional. These radiation monitors do not cause entry to any Technical Specification conditions or required actions.
"The loss of ability to monitor and quantify radiological conditions in multiple area of the plant represents a major loss of emergency assessment capability per 10CFR50.72(b)(3)(xiii). These radiation monitors are used for EAL determinations. As specified by station procedures compensatory monitoring has been implemented by use of surveys and portable monitoring devices.
"Repairs are being implemented per station procedures and processes."
The licensee informed the NRC Resident Inspector.
"At 0642 [CDT] on 10/22/2012 a failure of power supply RMA-ES-53B was indicated by multiple area radiation alarms in the Control Room. This failure results in the loss of ability to remotely measure and quantify radiation levels in multiple area in the Reactor Building, Turbine Building and Main Control Room. This power supply serves 10 of 30 area radiation monitors located throughout the plant. The remaining 20 monitors remain fully functional. These radiation monitors do not cause entry to any Technical Specification conditions or required actions.
"The loss of ability to monitor and quantify radiological conditions in multiple area of the plant represents a major loss of emergency assessment capability per 10CFR50.72(b)(3)(xiii). These radiation monitors are used for EAL determinations. As specified by station procedures compensatory monitoring has been implemented by use of surveys and portable monitoring devices.
"Repairs are being implemented per station procedures and processes."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 48431
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: CHRISTOPHER BUSH
HQ OPS Officer: VINCE KLCO
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: CHRISTOPHER BUSH
HQ OPS Officer: VINCE KLCO
Notification Date: 10/22/2012
Notification Time: 14:46 [ET]
Event Date: 10/22/2012
Event Time: 13:39 [CDT]
Last Update Date: 10/22/2012
Notification Time: 14:46 [ET]
Event Date: 10/22/2012
Event Time: 13:39 [CDT]
Last Update Date: 10/22/2012
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):
PATTY PELKE (R3DO)
PATTY PELKE (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 |
OFFSITE NOTIFICATION DUE TO PLANNED DECOMMISSIONING
"At 0745 CDT on 10/22/2012, Dominion announced its plan to permanently shutdown and decommission the Kewaunee Power Station. A local press release was made at 1100 [CDT] on 10/22/2012. At 1139 [CDT], security reported that members of the local media were gathering on company property at the plants training facility which is located outside the Owner Controlled Area. At this time security reports no security issues and no other press releases are planned at this time. This event is being conservatively reported under 10 CFR 50.72(b)(2)(xi) for offsite notifications based on the press release and the notification to Midwest Independent System Operator (MISO) of the planned shutdown of the Kewaunee Power Station."
The licensee notified the NRC Resident Inspector.
"At 0745 CDT on 10/22/2012, Dominion announced its plan to permanently shutdown and decommission the Kewaunee Power Station. A local press release was made at 1100 [CDT] on 10/22/2012. At 1139 [CDT], security reported that members of the local media were gathering on company property at the plants training facility which is located outside the Owner Controlled Area. At this time security reports no security issues and no other press releases are planned at this time. This event is being conservatively reported under 10 CFR 50.72(b)(2)(xi) for offsite notifications based on the press release and the notification to Midwest Independent System Operator (MISO) of the planned shutdown of the Kewaunee Power Station."
The licensee notified the NRC Resident Inspector.
Non-Agreement State
Event Number: 48432
Rep Org: ANDERSON ENGINEERING INC
Licensee: ANDERSON ENGINEERING INC
Region: 3
City: SPRINGFIELD State: MO
County:
License #: 24-20063-01
Agreement: N
Docket:
NRC Notified By: STEVEN BRADY
HQ OPS Officer: VINCE KLCO
Licensee: ANDERSON ENGINEERING INC
Region: 3
City: SPRINGFIELD State: MO
County:
License #: 24-20063-01
Agreement: N
Docket:
NRC Notified By: STEVEN BRADY
HQ OPS Officer: VINCE KLCO
Notification Date: 10/22/2012
Notification Time: 16:48 [ET]
Event Date: 10/22/2012
Event Time: 11:30 [CDT]
Last Update Date: 10/22/2012
Notification Time: 16:48 [ET]
Event Date: 10/22/2012
Event Time: 11:30 [CDT]
Last Update Date: 10/22/2012
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):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)
DAMAGED NUCLEAR DENSITY GAUGE
"Incident: At approximately 1130 CDT, at the new Joplin High School Construction Site in Joplin, Jasper County, Missouri, a nuclear density [gauge] was run over by a tire of a towed scraper. The damage was primarily to the housing of the meter. The technician immediately secured the area and contacted his supervisor. [The supervisor] went to the site and took readings using a TROX-A-LERT Model 3105B Radiation Survey Meter of the gauge and the soil where the gauge was run over and of the scraper which ran over the [gauge]. Readings at 1 meter from the [gauge] ranged from 0.12 to 0.20 mrem/hr. A reading of 2.5 mrem/hr [was indicated at the] housing of the [gauge] . The source did not appear to be damaged and was still encapsulated in the [gauge].
"The gauge was placed in a truck box mounted in the bed of a pickup truck and taken back to [the licensee's lab]. Once at the lab the gauge was wrapped in lead sheeting and placed in a nuclear [gauge] storage box. A reading of 0.1 mrem/hr was obtained at 1 meter with the lead sheeting wrapped around the meter."
The damaged gauge is a CPN, serial number MD1205992.
"Incident: At approximately 1130 CDT, at the new Joplin High School Construction Site in Joplin, Jasper County, Missouri, a nuclear density [gauge] was run over by a tire of a towed scraper. The damage was primarily to the housing of the meter. The technician immediately secured the area and contacted his supervisor. [The supervisor] went to the site and took readings using a TROX-A-LERT Model 3105B Radiation Survey Meter of the gauge and the soil where the gauge was run over and of the scraper which ran over the [gauge]. Readings at 1 meter from the [gauge] ranged from 0.12 to 0.20 mrem/hr. A reading of 2.5 mrem/hr [was indicated at the] housing of the [gauge] . The source did not appear to be damaged and was still encapsulated in the [gauge].
"The gauge was placed in a truck box mounted in the bed of a pickup truck and taken back to [the licensee's lab]. Once at the lab the gauge was wrapped in lead sheeting and placed in a nuclear [gauge] storage box. A reading of 0.1 mrem/hr was obtained at 1 meter with the lead sheeting wrapped around the meter."
The damaged gauge is a CPN, serial number MD1205992.
Power Reactor
Event Number: 48433
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MIKE SMITH
HQ OPS Officer: VINCE KLCO
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MIKE SMITH
HQ OPS Officer: VINCE KLCO
Notification Date: 10/22/2012
Notification Time: 19:29 [ET]
Event Date: 10/22/2012
Event Time: 19:01 [EDT]
Last Update Date: 10/22/2012
Notification Time: 19:29 [ET]
Event Date: 10/22/2012
Event Time: 19:01 [EDT]
Last Update Date: 10/22/2012
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JOHN CARUSO (R1DO)
WILLIAM DEAN (RA)
ERIC LEEDS (NRR)
SHER BAHADUR (NRR)
JEFFERY GRANT (IRD)
JOHN CARUSO (R1DO)
WILLIAM DEAN (RA)
ERIC LEEDS (NRR)
SHER BAHADUR (NRR)
JEFFERY GRANT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
NOTIFICATION OF UNUSUAL EVENT DUE TO A FIRE GREATER THAN 15 MINUTES
At 1846 EDT on 10/22/12, the Main Control Room received a report of an arc flash and smoke in the screen house. The fire brigade leader was dispatched and confirmed that smoke was coming from heater board H-111. The board was de-energized at 1854 EDT and smoke was observed to be reduced. The licensee declared an Unusual Event at 1901 EDT per EAL 8.2.1. The fire was out at 1908 EDT. The Unusual Event was terminated at 1932 EDT. Unit 1 continues running at full power operation and all parameters are stable. There was no impact on Unit 2.
The licensee notified the NRC Resident Inspector, State of New York and Oswego County.
Notified DHS SWO, FEMA, DHS NICC and NuclearSSA via email.
At 1846 EDT on 10/22/12, the Main Control Room received a report of an arc flash and smoke in the screen house. The fire brigade leader was dispatched and confirmed that smoke was coming from heater board H-111. The board was de-energized at 1854 EDT and smoke was observed to be reduced. The licensee declared an Unusual Event at 1901 EDT per EAL 8.2.1. The fire was out at 1908 EDT. The Unusual Event was terminated at 1932 EDT. Unit 1 continues running at full power operation and all parameters are stable. There was no impact on Unit 2.
The licensee notified the NRC Resident Inspector, State of New York and Oswego County.
Notified DHS SWO, FEMA, DHS NICC and NuclearSSA via email.
Agreement State
Event Number: 48472
Rep Org: COLORADO DEPT OF HEALTH
Licensee: TOWN OF LYONS
Region: 4
City: LYONS State: CO
County:
License #: GENERAL
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: JOHN KNOKE
Licensee: TOWN OF LYONS
Region: 4
City: LYONS State: CO
County:
License #: GENERAL
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: JOHN KNOKE
Notification Date: 11/01/2012
Notification Time: 16:55 [ET]
Event Date: 10/22/2012
Event Time: 00:00 [MDT]
Last Update Date: 11/01/2012
Notification Time: 16:55 [ET]
Event Date: 10/22/2012
Event Time: 00:00 [MDT]
Last Update Date: 11/01/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICK DEESE (R4DO)
FSME EVENT RESOURCE (EMAI)
RICK DEESE (R4DO)
FSME EVENT RESOURCE (EMAI)
AGREEMENT STATE REPORT - DAMAGED TRITIUM EXIT SIGN
The following information was received from the State of Colorado via email:
"The Colorado Department of Public Health and Environment received notification on 10-23-12 from Town of Lyons, Town Hall, 432 Fifth Avenue, Lyons, CO 80540, that a tritium exit sign was found on the floor when an employee entered the building on 10-22-2012. This exit sign was installed on 10-19-12. It is presumed the installation was incorrectly completed causing the sign to fall. An employee who entered the building picked the sign up and reported the damaged sign to the Public Works Director who contacted the Radioactive Materials Unit on 10-23-12 at 1330 PDT to report the damaged exit sign. The tube containing the Tritium is reported as damaged.
"The sign was reported installed on 10-19-12. The sign fell from the ceiling during the weekend, and was found on Monday, 10-22-12 just inside the front entrance to the building. The licensee was provided documentation regarding how to package and ship the sign back to the manufacturer. The documentation emailed to him included the NRC NUREG -1556, Vol. 16 Appendix L.
"Maker of the sign is Best Lighting Products. The model number is SLXTU1RB10 and serial number is 232970. The date it was reported shipped to the licensee was 12/28/10.
"The activity of H-3 is 7.03 Curies."
The following information was received from the State of Colorado via email:
"The Colorado Department of Public Health and Environment received notification on 10-23-12 from Town of Lyons, Town Hall, 432 Fifth Avenue, Lyons, CO 80540, that a tritium exit sign was found on the floor when an employee entered the building on 10-22-2012. This exit sign was installed on 10-19-12. It is presumed the installation was incorrectly completed causing the sign to fall. An employee who entered the building picked the sign up and reported the damaged sign to the Public Works Director who contacted the Radioactive Materials Unit on 10-23-12 at 1330 PDT to report the damaged exit sign. The tube containing the Tritium is reported as damaged.
"The sign was reported installed on 10-19-12. The sign fell from the ceiling during the weekend, and was found on Monday, 10-22-12 just inside the front entrance to the building. The licensee was provided documentation regarding how to package and ship the sign back to the manufacturer. The documentation emailed to him included the NRC NUREG -1556, Vol. 16 Appendix L.
"Maker of the sign is Best Lighting Products. The model number is SLXTU1RB10 and serial number is 232970. The date it was reported shipped to the licensee was 12/28/10.
"The activity of H-3 is 7.03 Curies."