HPS ANSI/HPS N13.39

W/D NO S/S

Purpose, and Application

In the past, internal dosimetry standards have focused onproviding guidance for detection and dose assessment for specificradionuclides or groups of radionuclides (e.g., tritium, uranium,and fission and activation products). Frequently, however, thesestandards provided conflicting or uneven treatment of theprogrammatic elements that are basic to monitoring for andassessing the dose from any radionuclide. Therefore, this standardwas developed to provide uniform and consistent guidance onprogrammatic issues that are universally applicable to allradionuclides and all occupational intake pathways.

This standard contains the essential elements of the internaldosimetry component of a radiation protection program. It providesgeneral policies and the framework for the design andimplementation of an acceptable internal dosimetry program. Thetopics included herein are definitions, organization, staffing andtraining, program documentation, quality assurance, personnelparticipation, internal dose assessment, incident response, andrecords and reports.

Other than those examples necessary for clarification, thisstandard does not address bioassay or internal dose assessmentmethodologies for specific radionuclides.^(a) It isintended that the development and implementation ofradionuclide-specific dosimetry programs be consistent with thebroad-scoped guidance provided herein.

By its very nature, internal dosimetry is a complex task withvarying degrees of difficulty, depending upon the radionuclide andthe means by which the radionuclide is metabolized. For someradionuclides, such as tritium, it is relatively easy to monitorfor and assess intakes that result in small doses. For others, suchas ²³⁹Pu, the task is significantly more difficult.Therefore, while this standard provides the minimal acceptableelements of an internal dosimetry program regardless of theradionuclide, it should not be used to restrict the level ofexcellence readily achievable for some radionuclides.

This standard provides guidance for programs where monitoringfor possible intakes by workers is part of the radiation protectionprogram.

Engineered containment and administrative controls are used tominimize the probability of an intake due to normal operations andaccident releases. Workplace surveillance practices identify thatthe containment and administrative controls are effective. Routinebioassay monitoring provides verification that radiologicalcontrols are being maintained and work effectively. Specialbioassay is performed in response to indications of an abnormalcondition that might have resulted in an intake.This standardfocuses on establishing intake monitoring programs, identifyingintakes, and assessing internal dose. It does not address equallyimportant aspects of radiation protection involving minimizingintakes or implementing aslow- as-reasonably-achievable total dosecontrol programs.

A graded approach is presented to account for programs involvingonly a small risk of intake through programs with a risk of intakethat might result in an exposure above regulatory limits or evenpotential radiation-induced health effects. Although most of thestandard addresses details relevant to programs with known orsubstantial risks of intakes, it is recognized that one importantpurpose of internal dosimetry programs is to document thatworkplace controls are adequate and no recordable intakes areoccurring. Therefore, some guidance is provided for programs (or apart of a program) that would not be expected to involve doseassessment.

(a) Also excluded is information on dosimetric quantities andunits, regulatory interactions, regulatory or administrative doselimits, methods of and recommendations on decorporation therapy,performance requirements for bioassay methodologies, bioassayfrequencies, and uncertainties in assessment results. The reader isreferred to the References for information on these and relatedtopics.

Edition:

01

Published:

01/01/2001

ANSI:

ANSI Approved

Number of Pages:

74