Bioassay Contingency Plans

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