Level 3 baseline risk evaluation for Building 3506 at Oak Ridge National Laboratory, Oak Ridge, Tennessee Metadata

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  • Main Title Level 3 baseline risk evaluation for Building 3506 at Oak Ridge National Laboratory, Oak Ridge, Tennessee


  • Author: Golden, K.M.
    Creator Type: Personal
  • Author: Robers, S.K.
    Creator Type: Personal
  • Author: Cretella, F.M.
    Creator Type: Personal


  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)


  • Name: Oak Ridge National Laboratory
    Place of Publication: Tennessee
    Additional Info: Oak Ridge National Lab., TN (United States)


  • Creation: 1994-12-01


  • English


  • Content Description: This report presents the results of the Level 3 Baseline Risk Evaluation (BRE) performed on Building 3506 located at the Oak Ridge National Laboratory (ORNL). This BRE is intended to provide an analysis of the potential for adverse health effects (current or future) posed by contaminants at the facility. The decision was made to conduct a Level 3 (least rigorous) BRE because only residual contamination exists in the building. Future plans for the facility (demolition) also preclude a rigorous analysis. Site characterization activities for Building 3506 were conducted in fall of 1993. Concrete core samples were taken from the floors and walls of both the cell and the east gallery. These cores were analyzed for radionuclides and organic and inorganic chemicals. Smear samples and direct radiation measurements were also collected. Sediment exists on the floor of the cell and was also analyzed. To adequately characterize the risks posed by the facility, receptors for both current and potential future land uses were evaluated. For the current land use conditions, two receptors were evaluated. The first receptor is a hypothetical maintenance worker who spends 250 days (8 hours/day) for 25 years working in the facility. The remaining receptor evaluated is a hypothetical S and M worker who spends 2 days (8 hours/day) per year for 25 years working within the facility. This particular receptor best exemplifies the current worker scenario for the facility. The two current exposure scenarios and parameters of exposure (e.g., inhalation and ingestion rates) have been developed to provide a conservative (i.e. health protective) estimate of potential exposure.
  • Physical Description: 356 p.


  • Keyword: Radioactive Wastes
  • Keyword: Remedial Action
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Environmental Impacts
  • Keyword: Ornl
  • Keyword: Site Characterization
  • Keyword: Radiation Hazards
  • Keyword: Hazardous Materials
  • Keyword: Health Hazards
  • Keyword: Risk Assessment
  • Keyword: Compiled Data


  • Other Information: PBD: Dec 1994


  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Other: DE95008965
  • Report No.: ORNL--6844
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/41276
  • Office of Scientific & Technical Information Report Number: 41276
  • Archival Resource Key: ark:/67531/metadc685754


  • Display Note: INIS; OSTI as DE95008965