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DOE-STD-1136-2004
Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities
staff selection, qualification, and training,
total CEDE from all intakes during a year,
committed dose equivalent (CDE) to organs or tissues of concern from all intakes during a year,
magnitude of intake for each radionuclide during a year,
data necessary to allow subsequent verification, correction, or recalculation of doses, and
gestation period dose equivalent to the embryo/fetus from intake by the mother during the entire
gestation period.
Recommendations for testing criteria for radiobioassay laboratories are in ANSI N13.30. These
recommendations include calculational methods and performance criteria for bias, precision, and testing
levels. The establishment of minimum detection capability must be driven by programmatic needs, ideally
related to some concept of a minimum detectable dose, rather than as a single magnitude number.
Some sites have established brief flyers or brochures describing their bioassay measurements.
These may be distributed to workers during classroom training, upon notification of scheduled
measurements, or at the time of the measurement or sample.
The choice of the measurement technique, or of a combination of techniques, depends on the
radioisotopes, physicochemical forms, and exposure pathway.
Because of the wide range of chemical and physical forms of uranium, an appropriate bioassay
program is one that does not rely on assumed transportability and will provide data from which radiation
dose can be calculated that will not be dependent on the chemical form. This will normally require both in
vivo and in vitro bioassay. If the uranium being handled has been shown to be of medium to high
transportability, then the bioassay program must be designed to demonstrate that 3 g U/g kidney has not
been exceeded.
Uranium class Y materials cannot be effectively detected at the levels listed in ICRP Publication 54 by
ordinary methods available for either lung in vivo counts or urinalysis. This is shown by the fact that the
DIL (based on 0.3 ALI as per ANSI/HPS 1995) was 0.06 pCi L-1, which is below the MDA suggested as
reasonable for routine uranium alpha urinalysis (0.1 pCi L-1) in the standard.
5.5.1 In Vivo Monitoring
The scheduling and measurement process for obtaining in vivo measurements is usually
straightforward. Workers are scheduled for the measurements and results are available shortly after the
measurement is completed. The long counting times can impose limitations on the throughput of workers
through a measurement facility, making scheduling an important issue. Procedures should be in place to
ensure that workers arrive for scheduled measurements and that follow-up occurs when a measurement is
not completed or a worker fails to show.
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