| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/26/2015 - 10/27/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51475 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: WAYNE COUNTY WELL SURVEYS
Region: 3
City: FAIRFIELD State: IL
County:
License #: IL-01804-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/16/2015
Notification Time: 12:12 [ET]
Event Date: 10/15/2015
Event Time: [CDT]
Last Update Date: 10/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HIRONORI PETERSON (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Category 3 " level of radioactive material. | Event Text ILLINOIS AGREEMENT STATE REPORT - LOST AMERICIUM/BERYLLIUM SOURCE
The following information was provided by the State of Illinois via email:
"The Radiation Safety Officer of Wayne County Well Surveys contacted the Agency [Illinois Emergency Management Agency] on Friday morning, October 16, 2015, to report the loss of a 3 Ci Am-241/Be source. A description of the container which holds the source was provided as well as anticipated radiation levels, markings and the route along which was followed when the container was most likely lost. The licensee had conducted visual surveys along this route with no success. The Agency dispatched teams with appropriate radiation detection instrumentation to traverse the route. The search is currently underway. Local law enforcement and emergency managers have also been advised of the matter."
The RSO last verified possession of the source on June 2, 2015 during a leak test. The search is being concentrated on several rural roads between Fairfield and Decatur, IL. The loss is believed to have happened sometime in the middle of September.
Source information: QSA Global; model number AMNK8208; serial number 82989B
IL Report Number: IL15020
THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL
Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State | Event Number: 51476 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: SOURCE PRODUCTION AND EQUIPMENT COMPANY, INC.
Region: 4
City: ST. ROSE State: LA
County:
License #: LA-2966-L01
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/16/2015
Notification Time: 14:19 [ET]
Event Date: 10/02/2015
Event Time: 15:00 [CDT]
Last Update Date: 10/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GEOFFREY MILLER (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text LOUISIANA AGREEMENT STATE REPORT - RADIATION WORKERS CONTAMINATED WHILE WORKING IN HOT CELL
The following information was received from the State of Louisiana via email:
"On October 02, 2015, around 1500 CDT, Source Production & Equipment Company [SPEC] was manufacturing a 30 Curie sealed Co-60 source within Hot Cell Number 2. During the welding process of double encapsulating the sealed source the welder malfunctioned. Two radiation workers within Hot Cell Number 2, behind the room divider, attempted to grind off the ruined outer encapsulation.
"The result was two workers inhaled Co-60 material. Nasal swipes indicated 11,743 cpm on the highest wipe. It was initially calculated internal exposure of around 200 mRem.
"The event was basically contained to Hot Cell Number 2 except for some footprints outside the cell which were remediated. The Hot Cell is currently restricted because of contamination.
"The workers have had two whole body scans on 10/07/15 and 10/12/15 with a third scan planned for 10/19/15.
"Currently internal exposure from inhalation has been calculated to be 373 mRem from 2.3 microCi of Co-60. The other worker's calculated exposure was 80 mRem from 0.42 microCi of Co-60.
"SPEC has enacted a policy in regards to this event to no longer allow reworking a ruined source during manufacturing by grinding on it. They will just retire/dispose of that source and get a new source to work with."
The licensee is also collecting bioassay samples from both workers for analysis.
LA Event Report ID NO.: LA150017 |
| Non-Agreement State | Event Number: 51477 | Rep Org: US EPA
Licensee: US EPA
Region: 3
City: CINCINNATI State: OH
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: STEPHEN MUSSON
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/16/2015
Notification Time: 14:18 [ET]
Event Date: 12/31/1983
Event Time: [EDT]
Last Update Date: 10/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
HIRONORI PETERSON (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text MISSING TWO GENERAL LICENSE KR-85 AEROSOL NEUTRALIZERS
Two TSI Model 3054 Aerosol Neutralizers containing 10 mCi Kr-85 each as of 1977, delivered to the Andrew W. Breidenbach Environmental Research Center (AWBERC or US EPA Cincinnati) facility in Cincinnati, OH can not be accounted for in available US EPA Cincinnati inventory records. The devices were delivered to their facility on 4/21/1977. The device serial numbers are 290T and 291T. The licensee began their investigation after receiving a letter from the U.S. NRC on 8/5/15 which identified that these devices should be in their possession. Members of the US EPA Cincinnati staff completed an exhaustive search of all available records and located radioactive inventories dating back to 1983, but could not locate any records prior to 1983. The 1983 inventory did not list the devices in question. As part of their investigation, the licensee contacted the manufacturer who has no record that the devices were returned. In addition, the US EPA facility in Research Triangle Park was contacted and requested to review their records. That location has no record of ever possessing these devices.
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: 51497 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: NATHAN BIBUS
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/24/2015
Notification Time: 11:45 [ET]
Event Date: 10/24/2015
Event Time: 06:57 [CDT]
Last Update Date: 10/26/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| 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 | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE NOTIFICATION FOR ONSITE INCIDENT OF LOCAL INTEREST
Prairie Island Nuclear Generating Plant (PINGP) notified Local Law Enforcement Agency and the Prairie Island Community Tribal Council due to an incident onsite of local interest.
"This notification is being conducted in accordance with 10 CFR 50.72(b)(2)(xi) for notification to an outside government agency.
"The plant remains safe, and this condition does not pose any additional risk to the public.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 51498 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PAUL FINHOLM
HQ OPS Officer: JEFF HERRERA | Notification Date: 10/26/2015
Notification Time: 15:20 [ET]
Event Date: 10/26/2015
Event Time: 07:03 [CDT]
Last Update Date: 10/26/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ANN MARIE STONE (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 | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text UNANALYZED CONDITION ASSOCIATED WITH A HIGH ENERGY LINE BREAK
"At 0703 CDT on 10/26/2015, Prairie Island Nuclear Generating Plant (PINGP) identified Door 62, '11/21 Auxiliary Feedwater Pump (AFW) Room to 12/22 AFW Pump Room' to be in a closed position. Door 62 functions as a fire door, and closes in the event of a fire in either A or B Train AFW Pump Rooms. When Unit 1 or Unit 2 is in modes 1-4, Door 62 is required to remain open in the event of an internal flood in AFW Pump Room or a Turbine Building High Energy Line Break (HELB) Flood into the AFW Pump. Currently, Unit 2 is in MODE 6, so only the Unit 1 Turbine Building HELB applies. Door 62 is normally open with a fusible link to allow closure during a fire.
"Door 62 was closed during maintenance. With the door closed the Unit 1 side of the Auxiliary Feedwater Pump Room lost its ability to adequately drain water in a Unit 1 HELB event and was in an unanalyzed condition. Upon discovery, Door 62 was immediately repositioned to be open per the analyzed condition and a fire watch established per plant procedure.
"This notification is being conducted in accordance with 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition.
"The plant remains safe, and this condition does not pose any additional risk to the public.
"The licensee has notified the NRC Resident Inspector." | |