DOE-Idaho Operations Summarry
Issued June 29, 2006
DOE-Idaho Bi-Weekly Operations Summary
For the Period of June 12-June 25, 2006
Environmental Management
Advanced Mixed Waste Treatment Project (AMWTP)
Summary of Occurrence Reports
(Note: Date below indicates when notification was made of the incident)
No New Reportable Items During This Reporting Period.
Operational Status
Through June 17, 2006, a cumulative total of 10,982 cubic meters (includes 3,100 m3 Project) of initial transuranic (TRU) waste volume (i.e., Idaho Settlement Agreement Volume) has been shipped to the Waste Isolation Pilot Plant (WIPP). During the week ending June 17, 2006, AMWTP made 20 shipments. For the week ending June 24, 2006, AMWTP was scheduled for 20 shipments and is scheduled for 10 shipments for the week ending July 1, 2006.
Environmental Management
Idaho Cleanup Project (ICP)
June 8: An employee exiting a passenger van at the Radioactive Waste Management Complex rolled his ankle resulting in a simple fracture. The employee was transported to the Site medical facility for evaluation where the fracture was diagnosed. Appropriate notifications were made.
(EM-ID–CWI-RWMC-2006-0007)
June 12: While rearranging electrical cords plugged into the back of an Uninterruptible Power Supply (UPS), a radiation control technician (RCT) received a shock on the right forearm. The RCT immediately notified his foreman and management. The area and affected equipment were isolated. The employee was taken to medical for evaluation and returned to work with no restrictions. There was no visual burn or skin damage. Examination of the UPS determined it to be functioning properly. However, as a follow up activity to this investigation, the UPS will be sent to an authorized service center for further evaluation. (EM-ID–CWI-RWMC-2006-0008)
June 12: Two separate employee skin contamination events occurred approximately nine days apart in the CPP-604 Vessel Off-Gas Cell during construction work. In both events, the level of contamination was below reporting levels. The employees were decontaminated. There were no internal exposures. Work was placed on hold in each case, further reviewed and appropriate corrective actions identified. (EM-ID–CWI- WASTMNGT-2006-0002)
June 12: Construction workers within a Radiological Buffer Area of the CPP-604 Vessel Off-Gas (VOG) Cell were removing contaminated waste when material in a waste bag shifted. A contaminated pipe stub punctured the bag and came into contact with a worker’s left boot. The construction worker was found to have cesium-137 beta/gamma contamination with levels of 13,500 disintegrations per minute on his boot. Workers immediately notified a radiological control technician, placed the punctured bag back into the contamination area and exited the cell. A survey of workers and the area indicated no further spread of contamination. Contamination levels were below reportable levels. However, due to two previous contamination events associated with this project, the nuclear facility manager chose to report this event and issued a formal “Stop Work” for
activities involving the VOG cell in order to fully evaluate radiological work practices and work scope planning. (EM-ID–CWI-WASTEMNGT-2006-0003)
June 19: On March 1, 2006, a radiological control technician slipped on ice and fell while walking on the west side of the RWMC Subsurface Disposal Area (WMF-697), and cut his head. Though no one witnessed the fall, other workers noticed the individual bent over, holding his head and rendered assistance. Medical personnel were summoned to the scene, and the injured person was taken to Idaho Falls for further evaluation. Though this event occurred on March, it was only recently recognized as a reportable incident because the fall resulted in a fractured jaw that was detected later. (EM-ID–CWI-RWMC-2006-0009)
June 19: After unloading waste containers shipped by the ICP at Idaho National Laboratory to the Nevada Test Site (NTS), Test Site workers discovered low levels of contamination on the transport trailer and the bottom of a BR-91 container of mixed low- level waste. The NTS notified ICP management. The maximum level of contamination was 142 disintegrations per minute (dpm) alpha and 6,120-dpm beta-gamma. Appropriate notifications were made.
(EM-ID–CWI-RWMC-2006-0010)
June 22: During excavation in a soil contamination area at Test Area North, an underground eight-inch fire water main was damaged by an excavator, allowing several thousand gallons of fresh water to flow through the excavation area. There were no ground personnel in the excavation area, no injuries, and no spread of radioactive contamination. Work was stopped, the fire water main was isolated, and fire watches were established in the buildings where fire suppression capability was lost. Appropriate notifications were made. (EM-ID–CWI-TAN-2006-0006)
Operational Status
At Test Area North, two of three 10,000-gallon V-Tanks were successfully stabilized using a material to solidify the free liquids in the tanks. The third V-tank will be stabilized in late June/early July. Following stabilization, the tanks will be shipped to the Idaho CERCLA Disposal Facility where they will be filled with grout, prior to final disposal in the landfill.
Nuclear Energy
Idaho National Laboratory (INL)
Summary of Occurrence Reports
(Note: Date below indicates when notification was made of the incident)
June 22: During a Safety Analysis Report (SAR) review, Advanced Test Reactor personnel identified a Potentially Inadequate Safety Analysis (PISA) condition regarding Primary Coolant System (PCS) overpressure protection in relation to a complete loss of heat sink (LOHS). Upon a LOHS condition, the PCS water will heat up, expand, and cause a pressure increase. Additional flow from the gland seal water (GSW) pump was not considered in the analysis. However, combining the GSW flow of 68 gallons per minute (gpm) with the LOHS transient flow (maximum of 622 gpm) would result in a total flow of 690 gpm. This would exceed the capacity of the SAR minimum required relief valve flow. The currently installed PCS relief valves have a combined certified relief capacity of 700 gpm, which would provide adequate protection for this transient.
Appropriate notifications were made and an Unreviewed Safety Question evaluation was initiated. There were no restrictions or interim controls associated with this PISA conditions.
(NE-ID–BEA-ATR-2006-0007)
June 22: During a Safety Analysis Report review, Advanced Test Reactor personnel identified a Potentially Inadequate Safety Analysis condition regarding an extreme overspeed of the diesel-powered standby pressurizing pump. The analysis assumed that only the pressurizing pump would be affected by the diesel overspeed, and did not take into account the flow increase from the diesel-powered gland seal water pump. Appropriate notifications were made and an Unreviewed Safety Question evaluation was initiated. (NE-ID–BEA-ATR-2006-0008)
June 22: A thermoplastic polymer was being heated under pressure in a small furnace when a failure of the material container caused destruction of the furnace at the INL Research Complex. There were no injuries. Work was stopped, appropriate notifications were made, and a critique was held. (NE-ID–BEA-INLLABS-2006-0003)
Operational Status
Idaho National Laboratory and NorthStar Nuclear Medicine, Inc. announced the signing of agreements concerning the licensing and research to recover a promising medical isotope, actinium-225, from nuclear fuel stored at INL. The Medical Actinium for Therapeutic Treatment (MATT) technology was developed by INL.