Occupational Intakes of Radionuclides Part 1 - ICRP

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3955 3956 3957 3958 3959 3960 3961 3962 3963 3964 3965 3966 3967 3968 3969 3970 3971 3972 3973 3974 3975 3976 3977 3978 3979 3980 3981 3982 3983 3984 3985 3986 3987 3988 3989 3990 3991 3992 3993 3994 3995 3996 3997 3998 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, 112
3999 4000 4001 4002 4003 4004 4005 4006 4007 4008 DRAFT REPORT FOR CONSULTATION identity of chemical compounds, absorption behaviour, etc., should be verified by appropriate measurements reviews or audits should be conducted at appropriate times (e.g. when a new monitoring programme is implemented, or when a significant change to a programme is made) (299) Laboratories should participate in national or international intercomparisons of measurements and dose assessments at appropriate intervals. Such participation enables the determination of the accuracy of measurement and dose assessment procedures, improves reliability, and facilitates harmonisation of methods. 113
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Occupational Intakes of Radionuclides Part 1 - ICRP

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