. "21 Criteria for Environmental Rehabilitation of the Temporary Storage Site for Spent Nuclear Fuel and Radioactive Waste in Gremikha Village--Yu. Ye. Gorlinsky, V. A. Kutkov, and N. K. Shandala." Cleaning Up Sites Contaminated with Radioactive Materials: International Workshop Proceedings. Washington, DC: The National Academies Press, 2009.
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Cleaning Up Sites Contaminated with Radioactive Materials: International Workshop Proceedings
If the Gremikha storage site is reprofiled and its site and facilities are subsequently used for the creation of a radiation-hazard facility, the following reference level values are proposed for doses from the remaining contamination:
At worksites for Group A personnel: 3 mSv per year
At worksites for Group B personnel: 1 mSv per year
For people living in the observation zone: 0.1 mSv per year
If the strategy for eliminating the Gremikha storage site is implemented (S5.1 and S5.2) and the site is subsequently used for a general industrial facility, the following reference level values are proposed for doses from the remaining contamination:
For personnel at the industrial facility: 1 mSv per year (0.9 mSv per year as a result of work at the site and 0.1 mSv per year due to living in the observation zone)
For people living in the observation zone: 0.1 mSv per year
If the option for further use of the Gremikha storage site as a radiation-hazard facility is implemented, the design of such a facility and its operations must ensure that annual exposure doses resulting from the activities of the facility do not exceed established dose constraint levels:
For Group A personnel: 7 mSv per year
For Group B personnel: 1 mSv per year
For people living in the observation zone: 0.15 mSv per year
During the stage of planning work and designing radiation protection measures, a final decision must be made on the values of the above-mentioned regulatory levels, with interested parties to be involved in the decision-making process in accordance with the new ICRP recommendations.