Occupational Intakes of Radionuclides Part 1 - ICRP

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DRAFT REPORT FOR CONSULTATION
directly related to the dose or to the intake. For example, an investigation could be
based on an intake of a radionuclide that would give a committed effective dose of 1
mSv. Thus in a routine monitoring programme for a single radionuclide and with a
period of T days, a DIL could be based on the body content that would give a
committed dose of 1 mSv. This would be appropriate where the probability of more
than one intake occurring within a year is considered to be low. Where this
probability is higher, and the probability of intake through the year is considered to be
uniform, the DIL could be derived from a committed effective dose of (T/365) mSv.
(296) The value corresponding to the investigation level can be obtained directly
from the relevant graphs or calculated from the tables of dose per unit content in the
data sets given in this report series or the accompanying CD-ROMs. The use of
constraints as described in Publication 103 (ICRP, 2007) could be used as a basis for
setting investigation levels. In setting such investigation levels, due attention must be
given to other sources of exposure, i.e. other radionuclides and external irradiation. In
situations where intakes and doses are known to be low and there is considerable
experience of the processes being undertaken, it may be possible simply to set
investigation levels for the measured quantities on the basis of experience. A
measurement result in excess of the investigation level would indicate a departure
from normal conditions and the need to investigate further.
5.5 Record Keeping and Reporting
(297) Dose record keeping is the making and keeping of individual dose records for
radiation workers. It is an essential part of the process of monitoring the exposures of
individuals to both external radiation and to intakes of radionuclides and for
demonstrating compliance with dose limits and constraints. Formal procedures should
be established for dose record keeping and these have been described in publications
by the IAEA (IAEA, 1999b, 2004). The procedures and criteria for reporting
individual and workplace monitoring results should be clearly specified by the
management and/or regulatory authority. Information reported should be clearly
identifiable and understandable and sufficient for the dose to be recalculated from the
measurements at a later time if necessary. Included in the information to be
documented must be a specification of the models, assumptions and computational
codes used. In accident situations interim information will be needed to judge the
need for management actions and the need for follow-up monitoring.
5.6 Quality Management System
(298) The need for a quality management system (QMS) within an overall radiation
protection programme has been discussed in an ISO standard (ISO, 2006). Reference
should be made to the ISO standard for a complete account, but some of the more
important issues are:
in deciding on the nature and extent of the quality assurance programme,
consideration should be given to the number of workers monitored, and the
magnitude and probability of exposures expected
assumptions on factors such as radionuclide composition, inhaled particle size,
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