42 CFR 82.14
§ 82.14 What types of information could be used in dose reconstructions?
United States · 42 CFR — Public Health · Status: effective
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- 42 CFR 82.14, § 82.14 What types of information could be used in dose reconstructions?, United States, version 1 as recorded 2026-07-09, yourstate.us, https://yourstate.us/provision/201607
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Full text
NIOSH will obtain the types of information described in this section for dose reconstructions, as necessary and available:
(a) Subject and employment information, including:
(1) Gender;
(2) Date of birth; and,
(3) DOE and/or AWE employment history, including: job title held by year, and work location(s): including site names(s), building numbers(s), technical area(s), and duration of relevant employment or tasks.
(b) Worker monitoring data, including:
(1) External dosimetry data, including external dosimeter readings (film badge, TLD, neutron dosimeters); and,
(2) Pocket ionization chamber data.
(c) Internal dosimetry data, including:
(1) Urinalysis results;
(2) Fecal sample results;
(3) In Vivo measurement results;
(4) Incident investigation reports;
(5) Breath radon and/or thoron results;
(6) Nasal smear results;
(7) External contamination measurements; and
(8) Other measurement results applicable to internal dosimetry.
(d) Monitoring program data, including:
(1) Analytical methods used for bioassay analyses;
(2) Performance characteristics of dosimeters for different radiation types;
(3) Historical detection limits for bioassay samples and dosimeter badges;
(4) Bioassay sample and dosimeter collection/exchange frequencies;
(5) Documentation of record keeping practices used to record data and/or administratively assign dose; and,
(6) Other information to characterize the monitoring program procedures and evaluate monitoring results.
(e) Workplace monitoring data, including:
(1) Surface contamination surveys;
(2) General area air sampling results;
(3) Breathing zone air sampling results;
(4) Radon and/or thoron monitoring results;
(5) Area radiation survey measurements (beta, gamma and neutron); and,
(6) Fixed location dosimeter results (beta, gamma and neutron); and,
(7) Other workplace monitoring results.
(f) Workplace characterization data, including:
(1) Information on the external exposure environment, including: radiation type (gamma, x-ray, proton, neutron, beta, other charged particle); radiation energy spectrum; uniformity of exposure (whole body vs partial body exposure); irradiation geometry;
(2) Information on work-required medical screening x rays; and,
(3) Other information useful for characterizing workplace radiation exposures.
(g) Information characterizing internal exposures, including:
(1) Radionuclide(s) and associated chemical forms;
(2) Results of particle size distribution studies;
(3) Respiratory protection practices; and
(4) Other information useful for characterizing internal exposures.
(h) Process descriptions for each work location, including:
(1) General description of the process;
(2) Characterization of the source term (i.e., the radionuclide and its quantity);
(3) Extent of encapsulation;
(4) Methods of containment;
(5) Other information to assess potential for irradiation by source or airborne dispersion radioactive material.
Legislative history
This is a federal regulation, adopted through agency rulemaking under the Administrative Procedure Act — not enacted by a recorded vote of Congress.