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55. Routine irradiation approvals: Routine operations, such as isotope production or irradiation of samples for activation analysis, should have a practical procedure for control such as a simple irradiation form containing only the most important information. They should be approved within the reactor facility. Non-routine irradiations should be treated as a new experiment (see para. 54). 56. Modifications to the facility: The radiological implications of any modification to the facility should be examined.

With all types of releases, consideration should be given in the first instance to minimizing both the radioactivity content and the volume generated. 6. The normal exposure of individuals should be restricted so that neither the total effective dose nor the total equivalent dose to relevant organs and tissues exceeds any relevant dose limit set by the national regulations. (Dose limits set by international bodies are provided in Ref. 7. The operating organization should take appropriate measures to ensure that radiation protection is optimized so that the magnitude of individual doses, the number of people exposed and the likelihood of incurring exposures are kept as low as reasonably achievable, economic and social factors being taken into account.

As discussed earlier, the design target doses set at the start of the design process should include: (a) (b) Constraints on the annual collective dose and annual individual dose to site personnel; Constraints on the annual individual dose to members of the public. 12. In practice, these two design target doses can be addressed independently, although in principle they are interrelated. For example, any enhancement of the waste treatment systems to reduce the release of radioactive material to the environment may necessitate additional work being carried out by site personnel, with a consequent increase in their exposures.

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