Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Use of DAC-Hours for Radiation Work Permit Suspension Guides and Validation of Respiratory Equipment Selection at the Savannah River Site

Conference ·
OSTI ID:817233
Historically, the Savannah River Site, like many Department of Energy sites, has used some multiple of the expected Derived Air Concentration (DAC) of a radionuclide as a suspension guide for Radiological Work Permits (RWP) or validation of selected respiratory protection equipment. The term DAC expresses the concentration of a radionuclide in air, typically in mCi/cc. Even though the term DAC is derived from an intake of radioactivity (Annual Limit on Intake) that would result in defined estimated dose to a worker, knowing only the DAC value does not allow a worker's potential dose to be determined. Recently, the Savannah Rive Site has converted to the use of DAC-hours for RWP suspension guides and respiratory equipment validation. The term DAC-hr takes into account not only the concentration of the radionuclide in air (DAC) but also the time the individual was exposed allowing an estimate of a worker's dose to be determined. The conversion to DAC-hrs resulted in four benefits to the radiation protection program without increasing the risk to workers; (1) consistency with the constant air monitor (CAM) alarm setpoint protocol; (2) consistency with Internal Dosimetry terminology; (3) an a priori determination of the potential risk to a worker; and (4) reduced complexity/error in field calculations. This paper outlines the justification for the conversion to DAC-hrs, the protocols used for field and count room calculations, and the implementation process utilized at the Savannah River Site
Research Organization:
Savannah River Site (US)
Sponsoring Organization:
US Department of Energy (US)
DOE Contract Number:
AC09-96SR18500
OSTI ID:
817233
Report Number(s):
WSRC-MS-2003-00660
Country of Publication:
United States
Language:
English

Similar Records

Internal dosimetry technical basis manual
Technical Report · Wed Dec 19 23:00:00 EST 1990 · OSTI ID:10154855

Internal dosimetry technical basis manual
Technical Report · Wed Dec 19 23:00:00 EST 1990 · OSTI ID:5175441

DETERMINATION OF IN-VITRO LUNG SOLUBILITY AND INTAKE-TO-DOSE CONVERSION FACTOR FOR TRITIATED LANTHANUM NICKEL ALUMINUM ALLOY
Technical Report · Thu Nov 10 23:00:00 EST 2011 · OSTI ID:1057749