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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
Pages 152-160

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From page 152...
... K Shandala, Russian Research Center -- Kurchatov Institute To ensure radiation safety for personnel and the public during the conversion and environmental rehabilitation of the temporary storage site for spent nuclear fuel and radioactive waste in Gremikha village, a radiation safety strategy must be in place that, if followed, would define the following: • Radiation protection criteria for the planning of work • Radiation protection criteria for the conduct of work • Criteria for assessing radiation safety status during the conduct of planned work and at its completion The regulatory documents in effect in the Russian Federation consider the following two categories of ionizing radiation sources as subject to radiation safety regulation:   *
From page 153...
... Natural radiation sources covered by the Radiation Safety Norms and Rules In using the term ionizing radiation source or simply source, we follow the common practice in radiation protection and safety by which source means a radioactive substance or device emitting or capable of emitting ionizing radiation and covered by the Norms and Rules. Everything that could cause irradiation during emission of ionizing radiation or discharge of radioactive substances or materials is considered to be a source. For example, substances that emit radon are sources that exist in the environment, a gamma-radiation sterilization device is a source used in practical operations to preserve food products, and a nuclear power plant is a source in practical operation to produce electricity using nuclear energy.
From page 154...
... In view of the low specific activity of radioactive materials that the Norms and Rules place in this source category, even if they should go out of control they are incapable of producing substantial doses from accidental exposure. In considering radiation sources of these two types, the system for regulation of radiation safety formulates its requirements for operations involving them depending on their characteristic danger-harm ratio. For example, annual public exposure from potentially dangerous technogenic radiation sources is limited to a maximum dose of 1 mSv per year, while the total exposure from natural sources for the same period is deemed acceptable if it does not exceed 5 mSv per year.
From page 155...
... 2007. Application of multifactor analysis in the selection of end state options and environmental rehabilitation strategies for the temporary storage site for spent nuclear fuel and radioactive waste in Gremikha village.
From page 156...
... Accidental radiation exposure situations including situations of uncontrolled exposure from sources that had been under regulated control but went out of control as a result of radiation accidents 3. Existing radiation exposure situations including situations of exposure from unregulated sources dispersed in the environment and already existing when it was decided that they needed to be controlled.
From page 157...
... exposure from all regulated sources in a planned exposure situation of the dose constraint is expressed in terms of normative values, specifically in annual effective dose units. The reference level is the value established for limiting ongoing human exposure in situations involving accidental or existing exposure as well as during planned activities.
From page 158...
... Planned exposure situations caused by the operation of the facility after its reprofiling as part of implementation of strategies S4.1 and S4.2 3. Existing exposure situations caused by remaining radioactive contamination at the location of a new radiation-hazard facility as part of implementation of strategies S4.1 and S4.2 or at the location of a new industrial facility as part of implementation of strategies S5.1 and S5.2 In accordance with the new ICRP recommendations for planning radiation protection measures for personnel during the facility conversion and rehabilitation stage, it would be expedient to establish two levels of dose constraints: 1.
From page 159...
... Public exposure from sources associated with the facility: 1 mSv per year on average over any 5 consecutive years, but no more than 5 mSv in any single year Under the new ICRP recommendations, facility rehabilitation goals may be considered achieved if exposure doses from the remaining contamination do not exceed reference levels established by the national regulatory agency. Their values may be appropriately established depending on the end stage of the facility after the Gremikha temporary storage site has been rehabilitated: 19 19  Bylkin, B
From page 160...
... •  For people living in the observation zone: 0.1 mSv per year 3. If the option for further use of the Gremikha storage site as a radiationhazard 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.


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