IMPLEMENTATION OF THE 1990 RECOMMENDATIONS OF THE ICRP

Detailed investigations have been made of the consequences of ICRP Publication 60 for nuclear power plants. A methodology has not yet been defined for handling the aspect of design against accidents within the framework of ICRP 60. Other new requirements, i.e. new individual limits and the application of higher risk factors, may pose minor problems for plants of older design. In plants of recent design collective doses for plant personnel and for the public are already so low that the increase in risk factors will not require additional protective measures. The new limit for the individual dose accumulated during five calendar years may require additional surveillance of a.few persons in plants of older design. Intakes of radionuclides are a minor contributor to dose, even at these low levels of exposure. Uncertainties in the determination of a committed dose rather than the actual dose can therefore be tolerated.