Event Notification Report for September 21, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/20/2011 - 09/21/2011
EVENT NUMBERS
47285472864797350111
Non-Agreement State
Event Number: 47285
Rep Org: N/A
Licensee: INLAND CODE INSPECTION
Region: 4
City: PONDERAY State: ID
County:
License #: 11-29265-01
Agreement: N
Docket:
NRC Notified By: JAMES THOMPSON (NRC R4)
HQ OPS Officer: PETE SNYDER
Licensee: INLAND CODE INSPECTION
Region: 4
City: PONDERAY State: ID
County:
License #: 11-29265-01
Agreement: N
Docket:
NRC Notified By: JAMES THOMPSON (NRC R4)
HQ OPS Officer: PETE SNYDER
Notification Date: 09/21/2011
Notification Time: 09:15 [ET]
Event Date: 09/21/2011
Event Time: 00:00 [MDT]
Last Update Date: 09/21/2011
Notification Time: 09:15 [ET]
Event Date: 09/21/2011
Event Time: 00:00 [MDT]
Last Update Date: 09/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
ABANDONED DENSITY GAUGE
A property owner called the Nuclear Regulatory Commission to report that he had found a CPN MC3 Porta- Probe gauge containing 10 mCi of Cs-137 abandoned at his property at Sand Point, ID. The gauge belongs to Inland Code Inspection & Consultation Services of Ponderay, ID.
Another NRC licensee licensed to possess this type of equipment has retrieved the gauge and stored it at their site.
* * * UPDATE FROM JAMES THOMPSON TO VINCE KLCO ON 9/21/2100 AT 1451 EDT* * *
The serial number for the gauge is M370103535.
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
A property owner called the Nuclear Regulatory Commission to report that he had found a CPN MC3 Porta- Probe gauge containing 10 mCi of Cs-137 abandoned at his property at Sand Point, ID. The gauge belongs to Inland Code Inspection & Consultation Services of Ponderay, ID.
Another NRC licensee licensed to possess this type of equipment has retrieved the gauge and stored it at their site.
* * * UPDATE FROM JAMES THOMPSON TO VINCE KLCO ON 9/21/2100 AT 1451 EDT* * *
The serial number for the gauge is M370103535.
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
Power Reactor
Event Number: 47286
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: TOM DINGEL
HQ OPS Officer: JOE O'HARA
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: TOM DINGEL
HQ OPS Officer: JOE O'HARA
Notification Date: 09/21/2011
Notification Time: 22:48 [ET]
Event Date: 09/21/2011
Event Time: 10:20 [EDT]
Last Update Date: 09/21/2011
Notification Time: 22:48 [ET]
Event Date: 09/21/2011
Event Time: 10:20 [EDT]
Last Update Date: 09/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHRISTOPHER NEWPORT (R1DO)
CHRISTOPHER NEWPORT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | N | 0 | Refueling | 0 | Refueling |
RELAY MALFUNCTION RESULTED IN A VALID UNDERVOLTAGE SIGNAL
"On 9/21/11 at 10:20 a.m. during the performance of a simulated loss of offsite power testing off the E33 4KV emergency bus, an unplanned start of the E3 Emergency Diesel Generator (EDG) occurred due to a valid bus under voltage signal caused by a relay malfunction. The bus being tested was inoperable in support of the test and was not carrying any required safety system loads at the time of the event. The EDG was secured and troubleshooting initiated. The initial determination was the EDG actuation was from an invalid signal but following further review it was determined that the relay malfunction had caused an untimely bus transfer that resulted in a valid 4KV bus under voltage condition."
The NRC Resident Inspector has been notified.
"On 9/21/11 at 10:20 a.m. during the performance of a simulated loss of offsite power testing off the E33 4KV emergency bus, an unplanned start of the E3 Emergency Diesel Generator (EDG) occurred due to a valid bus under voltage signal caused by a relay malfunction. The bus being tested was inoperable in support of the test and was not carrying any required safety system loads at the time of the event. The EDG was secured and troubleshooting initiated. The initial determination was the EDG actuation was from an invalid signal but following further review it was determined that the relay malfunction had caused an untimely bus transfer that resulted in a valid 4KV bus under voltage condition."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 47973
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/29/2012
Notification Time: 14:44 [ET]
Event Date: 09/21/2011
Event Time: 11:22 [EDT]
Last Update Date: 05/29/2012
Notification Time: 14:44 [ET]
Event Date: 09/21/2011
Event Time: 11:22 [EDT]
Last Update Date: 05/29/2012
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):
STEVEN VIAS (R2DO)
STEVEN VIAS (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 |
TECHNICAL SUPPORT CENTER VENTILATION SYSTEM INOPERABLE
"On Sept. 20, 2011, with the reactor at 100% power in mode 1, a scheduled test of the technical support center ventilation system revealed that the adsorber stage leak test did not meet acceptance criteria. The system was returned to service on Sept. 21, 2011, following corrective maintenance and a satisfactory test. It was not recognized at the time that the condition met 10 CFR 50.72(b)(3)(xiii) reporting criteria for the emergency filtration function.
"The system was returned to service within approximately 30 hours of discovery. Investigation of Condition Report 526951 in the Harris Corrective Action Program determined that this event should have been reported upon discovery.
"The NRC Resident Inspector has been Informed."
"On Sept. 20, 2011, with the reactor at 100% power in mode 1, a scheduled test of the technical support center ventilation system revealed that the adsorber stage leak test did not meet acceptance criteria. The system was returned to service on Sept. 21, 2011, following corrective maintenance and a satisfactory test. It was not recognized at the time that the condition met 10 CFR 50.72(b)(3)(xiii) reporting criteria for the emergency filtration function.
"The system was returned to service within approximately 30 hours of discovery. Investigation of Condition Report 526951 in the Harris Corrective Action Program determined that this event should have been reported upon discovery.
"The NRC Resident Inspector has been Informed."
Agreement State
Event Number: 50111
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: BLUES CITY BREWERY
Region: 1
City: MEMPHIS State: TN
County:
License #: TN-R-79149
Agreement: Y
Docket:
NRC Notified By: LAURA TURNER
HQ OPS Officer: PETE SNYDER
Licensee: BLUES CITY BREWERY
Region: 1
City: MEMPHIS State: TN
County:
License #: TN-R-79149
Agreement: Y
Docket:
NRC Notified By: LAURA TURNER
HQ OPS Officer: PETE SNYDER
Notification Date: 05/12/2014
Notification Time: 17:10 [ET]
Event Date: 09/21/2011
Event Time: 00:00 [EDT]
Last Update Date: 05/12/2014
Notification Time: 17:10 [ET]
Event Date: 09/21/2011
Event Time: 00:00 [EDT]
Last Update Date: 05/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DON JACKSON (R1DO)
FSME EVENTS RESOURCE (EMAI)
DON JACKSON (R1DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - LOST AND FOUND INDUSTRIAL GAUGE SOURCE CONTAINING AMERICIUM-241
"The Tennessee Division of Radiological Health (DRH) performed an inspection of Blues City Brewery (BCB) on 9/21/2011. The facility was previously owned by Coors Brewing Company through 9/1/2006.
"During the inspection, it was discovered that a 3.7 GBq (100 mCi) Am-241 source (Industrial Dynamics Company - IDC model 06110-1, serial #5533) was missing. The source had originally been contained inside a level gauge (IDC model FT -100, serial #90205). According to IDC records, IDC had removed the source from the gauge on 9/29/1999, wipe tested the source, packaged it for shipment, and left the package in the possession of the Coors Brewing Company's RSO. The IDC RSO stated that they had no further record regarding the source. BCB conducted a thorough search of their facility for the source without success. DRH contacted the former Coors Brewing Company's RSO, but he did not have any additional information regarding this source.
"On 10/25/2012, DRH received a quarterly report (7/1/2012 to 9/30/2012) from IDC that stated they recovered the source."
Tennessee Event TN-12-126.
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
"The Tennessee Division of Radiological Health (DRH) performed an inspection of Blues City Brewery (BCB) on 9/21/2011. The facility was previously owned by Coors Brewing Company through 9/1/2006.
"During the inspection, it was discovered that a 3.7 GBq (100 mCi) Am-241 source (Industrial Dynamics Company - IDC model 06110-1, serial #5533) was missing. The source had originally been contained inside a level gauge (IDC model FT -100, serial #90205). According to IDC records, IDC had removed the source from the gauge on 9/29/1999, wipe tested the source, packaged it for shipment, and left the package in the possession of the Coors Brewing Company's RSO. The IDC RSO stated that they had no further record regarding the source. BCB conducted a thorough search of their facility for the source without success. DRH contacted the former Coors Brewing Company's RSO, but he did not have any additional information regarding this source.
"On 10/25/2012, DRH received a quarterly report (7/1/2012 to 9/30/2012) from IDC that stated they recovered the source."
Tennessee Event TN-12-126.
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