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| DOE-STD-1136-2004
Guide of Good Practices for Occupational Radiation Protection in Uranium Facilities
10.1.1.3 Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)
(USC 1980) and 40 CFR 300 (EPA 1992a)
This act requires the identification and cleanup of inactive hazardous waste sites by responsible
parties, and imposes certain response and reporting requirements for releases of hazardous substances.
10.1.1.4 Superfund Amendments and Reauthorization Act (SARA) and 40 CFR 300.
Interagency agreements can also exist between DOE, EPA, state, and local agencies (Daugherty
1993). Any special arrangement agreed to as part of an interagency agreement will need to be honored
during the D&D activities.
Additional guidance relating to regulations and standards for D&D activities at uranium facilities may be
found in:
DOE-HDBK-1113-98, Radiological Safety Training for Uranium Facilities (DOE 1998c)
DOE-HDBK-1132-99, Design Considerations (DOE 1999o)
DOE-STD-3007-93 (including Change Notice 1, September 1998), Guidelines for Preparing
Criticality Safety Evaluations at DOE Non-Reactor Nuclear Facilities (DOE 1993b) DOE-
STD-1120-98, Integration of Environment, Safety, and Health into Facility Disposition
Activities (DOE 1998f)
10.1.2 Residual Radioactivity Levels
A primary concern in the D&D of any nuclear facility is the level of residual radioactivity that may be
permitted for unrestricted use. The U.S. Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.86,
Termination of Operating Licenses for Nuclear Reactors (AEC 1974) provides definitive values for
acceptable surface contamination levels for termination of operating licenses for nuclear reactors and for
materials, equipment, and facilities. This document is based on the methodology of ICRP Publication 2,
ICRP Publication 26 and ICRP Publication 30. More current guidance material includes: ANSI/HPS
(MARSSIM), December 1997; November 17, 1995 memo from RF Pelletier entitled Application of DOE
requirements for release and control of property containing residual radioactive material ; NUREG-1507,
Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants
and Field Conditions, December 1997.
Congress has mandated that the EPA develop guidelines that will be applicable to all nuclear facilities
as well as to the release of formerly contaminated or controlled radioactive facilities for unrestricted
release. Such guidelines will likely be based on the radiation dose to the maximum exposed member of the
general population. The maximum allowable annual dose has not yet been determined, but values of 50,
10, 1, and 0.1 mrem/y are being considered by the EPA as the "de facto de minimis" levels for the disposal
of contaminated material.
Section 4 of DOE Order 5400.5,Ch.2, Radiation Protection of the Public and Environment, provides
the following DOE guidelines for cleanup of residual radioactive material, management of the resulting
wastes, and release of property. The basic public dose limit for exposure to residual radioactive material in
addition to natural background exposures is 100-mrem (1-mSv) effective dose equivalent in a year. The
effective dose equivalent in a year is the sum of the effective dose equivalent from exposures to radiation
sources external to the body during the year plus the cumulative effective dose equivalent
10-3
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