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DOE-STD-1121-98
trigger levels and preliminary actions to be taken for exposures to the different radionuclides
encountered at the facility
other methods that may be used for the evaluation of doses from intakes and their scientific basis
action levels for administrative response to intakes of radionuclides by workers
records to document the appropriateness, quality, and accuracy of monitoring methods,
techniques, and procedures in use during any given period, pursuant to applicable requirements
and standards
documentation that all steps in the activities that control or evaluate worker internal doses by
written procedures provide appropriate quality control and quality assurance
Radiochemical laboratories and in-vivo counting facilities whose measurements are used by internal
dosimetry programs are expected to have written procedures that can be referenced by internal dosimetry
programs.
The internal dosimetry program should receive periodic assessment by the site radiation protection
organization to review dose assessment procedures as necessary to ensure that the program maintains the
capability to stay abreast of scientific developments in internal dosimetry and provides a quality radiation
protection service to workers. Paragraph 10 CFR 835.102 requires that an internal audit be done every 36
months. External peer-review by qualified individuals on a periodic basis is also recommended.
The procedures should be reviewed at least once every two years and updated as necessary. The
needs for maintenance of procedures should be specified, including responsibilities for authorship,
review, approval, and distribution.
3.2.1 Bioassay Contingency Plans
Some facilities with low potential for significant occupational intake of radioactivity may not have
any routine bioassay program. Examples of such facilities are those where only sealed sources are
handled, or the types, quantities, and frequency of dealing with radioactive materials does not support
establishment of routine capability from a cost-effectiveness viewpoint. However, if quantities of
unsealed radioactive material are handled infrequently or if accidents could happen causing intakes
corresponding to 100 mrem CEDE, then it may be wise to have a contingency plan for obtaining bioassay
measurements. Elaborate advance arrangements are not necessarily warranted. However, thought should
be given to what types of bioassay measurements might be needed, and how and where they would be
obtained. A good approach would be to identify the closest DOE facility with capability appropriate for
the radionuclides and to have a letter of agreement or memorandum of understanding in place to obtain
measurements on an as-needed basis. As a minimum, the radiation protection organization should know
whom to contact for support, how long until data could be obtained, and what to do until data would
become available.
A contingency plan for sites having routine bioassay is worth considering because of the possibility
of losing one or more components of a bioassay program. Such loss could result from equipment or
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