Actions for Results of the Independent Radiological Verification Survey of Remediation at Building 14, Former Linde Uranium Refinery, Tonawanda, New York (LI001V) [electronic resource].

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Results of the Independent Radiological Verification Survey of Remediation at Building 14, Former Linde Uranium Refinery, Tonawanda, New York (LI001V) [electronic resource].

Published
Oak Ridge, Tenn. : Oak Ridge National Laboratory, 2000.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
Physical Description
106 pages : digital, PDF file
Additional Creators
Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
As part of the Formerly Utilized Sites Remedial Action Program, a team from Oak Ridge National Laboratory (ORNL) conducted a radiological verification survey of Building 14 at the former Linde Uranium Refinery, Tonawanda, New York. The purpose of the survey was to verify that remedial action completed by the project management contractor had reduced contamination levels to within authorized limits. Prior to remediation, fixed and removable beta-gamma emitting material was Prevalent throughout Building 14 and in some of the process piping. Decontamination consisted of removal of surface contamination from floors, floor-wall interfaces, walls, wall-ceiling interfaces, and overhead areas; decontamination or removal of process piping; excavation and removal of subsurface soil; and vacuuming of dust. This independent radiological assessment was performed to verify that the remedial action had reduced contamination levels to within authorized limits. Building 14 at the former Linde site in Tonawanda, New York, was thoroughly investigated inside for radionuclide residues. Surface residual activity levels were generally well below applicable guidelines for protection against radiation. Similarly, removable alpha and beta-gamma activity levels were below guidelines. Gamma exposure rates within the building were at typical background levels, and no elevated indoor radon concentrations were measured. However, numerous areas exceeding U.S. Department of Energy (DOE) applicable guidelines still remain inside and underneath the building. These areas were either (1) inaccessible or (2) removal was not cost-effective or (3) removal would affect the structural integrity of the building. These above-guideline areas have been listed, described, and characterized by the remediation subcontractor (Appendix A), and dose to an exposed worker during typical exposure scenarios has been calculated. Based on the remediation subcontractor's characterization data and dose assessment calculations, these areas pose insignificant risk to building inhabitants under current use scenarios. However, future renovations, repairs, or demolition of the building must require prior evaluation and consideration of the areas. Analysis of the project management contractor's post-remedial action data and results of this independent radiological verification survey by ORNL confirm that residual contamination inside the building is either below the limits prescribed by DOE applicable guidelines for protection against radiation or areas exceeding applicable guidelines have been characterized and a risk assessment completed. Building 14 can be released for unrestricted use under current use scenarios; however, arrangements must be made to inform current and future building owners of the locations of areas exceeding DOE guidelines and any associated restrictions concerning renovations, repairs, or demolition of the building.
Report Numbers
E 1.99:ornl/rasa-99/1
ornl/rasa-99/1
Subject(s)
Note
Published through SciTech Connect.
08/21/2000.
"ornl/rasa-99/1"
McKenzie, S.P.
(US)
Type of Report and Period Covered Note
Topical;
Funding Information
AC05-00OR22725
View MARC record | catkey: 23778470