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Building Number/Name: |
304 |
PAST OPERATIONS
Location(s) in facility that contained beryllium materials: Possibly throughout the concretion operation. No currently marked beryllium hazard areas were noted during 1999 FDH assessment.
Description of beryllium activities: This building was built in 1952 as a pilot plant for the lead-dip fuel canning process for building 313. In the late 1950s it became the pilot plant for the hot-die size (nickel plating) fuel fabrication process, which moved in 1962. Soon after, it was used to store uranium scraps for reclamation. In 1971, it began to be used to solidify pyrophoric uranium scraps in a concrete matrix and has been known as the Concretion Facility since that time. This waste may have contained some beryllium from the fuel manufacturing process and was subsequently disposed.
Building monitoring data summary: An October 1973 air sample found beryllium at less than 0.006 mg/m3. Swipe samples were collected in 1985 and confirmed the presence of beryllium just above the detectable limit. The results were less than 0.003 mg/in2 and said to be insignificant at the time. The ventilation system was also confirmed as adequate to minimize the potential for exposure in 1986.
Personnel monitoring data summary: None identified.
Specify Engineering/Administrative controls used during operations: Ventilation confirmed as well as gloves and coveralls in 1985.
Maximum Estimated Past Be exposure: LOW
CURRENT OPERATIONS
Building still present: YES
Beryllium present: Unknown
Current building occupancy/activity: This building is vacant and awaiting transfer to D & D.
1999 Study Results: Ambient air sample were collected on 6/23/99 in the center of Room 304A just below the light fixture, and in the center of the main bay immediately east of the raised concrete pad. A personal air sample was also collected on 6/23/99 in the breathing zone of a technician while wipe sampling surfaces for beryllium. Results reported for these samples were below the Method Detection Limit (MDL) of 0.004 µg/m3 and 0.013 µg/m3 for the ambient and personal samples, respectively. Surface samples were collected from 30 sites throughout the building on 6/23/99. Results reported for these samples were below the MDL of 0.5 mg/100 cm2. Because the entire interior of 304A was painted to fix low-level radioactive contamination, any beryllium contamination is likely contained as well. Therefore, the potential for exposure to berylium in this facility is very low unless the integrity of the paint is compromised.
Maximum Estimated Current Be Exposure from Routine Activities: NONE
OPERATIONAL CONTROLS: Work activities occurring in this facility will be planned and reviewed with consideration given to the potential for beryllium exposure. Controls will be prescribed when the work activity may potentially enter or disturb an area not yet characterized through beryllium sampling or monitoring. Work will be carefully planned with IH&S professional support to help assure potential exposure risks are identified and minimized through the use of appropriate controls and additional sampling/monitoring as appropriate.
Basis for above information: Stone and Webster report and publication WHC-MR-0388; FDH beryllium assessment report.
Comments, including any additional information needed (specify): Smear samples collected during operation were at detectable levels. The building has subsequently been vacated,cleaned, and the entire interior painted to fix low-level radioactive contamination. Prior to demolition, beryllium sampling should be performed to confirm the absence of beryllium, especially inside room and process exhaust handling systems.
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