confirmatory and monitoring work, are considered in the stage. Following approval of the final safety analysis report for the nuclear installation, the site evaluation at the operational stage starts. This includes the monitoring and re-evaluation work conducted throughout the operational stage and, especially during periodic safety reviews of the installation. This work is generally reported in the periodic safety reviews. Outcomes in comparison with those for the stages of the siting process and the site evaluation process are described in Fig. 1.2. Figure 1.2: Outcome of the siting process and site evaluation process for a nuclear installation. FSAR: final safety analysis report; PSAR: preliminary safety analysis report; PSR: periodic safety review; SER: site evaluation report. There are three important steps that typically receive input from the site survey, site selection and site evaluation processes before construction starts. These are: The decision regarding the ‘suitability’ of the preferred site, i.e. confirmation that the site has no characteristics that preclude the safe operation of a nuclear installation; The definition of the site related design basis parameters on the basis of the site evaluation report; The development of the Site Section of the preliminary safety analysis report or preliminary safety case which, among other things, demonstrates that the site related design basis parameters have been appropriately taken into account, in particular through the design features of the nuclear installation and the measures to be taken for the site. Phases of the siting process The siting process consists of a series of related activities with the objective of selecting suitable for a new nuclear installation. The process applies a number of screening criteria to eliminate those sites with attributes which contribute unfavourably to the safety of the installation. The siting process for a nuclear installation is illustrated in Fig. 1.3. Figure 1.3: Flow chart for the siting process for a nuclear installation. the outline of a typical project description for a site selection study is given. Typically previous studies have been performed for each region in a country. These studies may be related to site selection trial
During normal operation of the plant, since the buildings containing radioactive materials have shielding to reduce the direct radiation level outside them, the radiological risks for the public arise mainly from the management of radioactive wastes. There are several ways in which exposure of the public can occur, as shown in Fig.3.1. Figure 3.1: Waste treatment options. The first option, when possible, is to concentrate and dispose the solid or solidified wastes in a surface or underground repository. The second option is to treat gaseous or liquid wastes until their activity is below the levels that are permitted for discharge, so that they can be released in a controlled manner and dispersed in the atmosphere or in liquid pathways. Requirements The applicable requirements are stated in the General Safety Requirements Part 3 No. GSR Part 3 publication from 2014 entitled “Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards” [17]. This publication superseded the old BSS-115 standard of 1996. It contains the requirements for performing safety and dose assessments, establishing protection measures and programmes, and optimizing them periodically; for the discharge of radioactive substances to the environment; for monitoring programmes of public exposure; for exemption of consumer products from regulatory control, i.e. to be considered non-radioactive for all practical purposes; and finally for emergency for the population in case of accidents. Each NPP must have a radiation monitoring programme covering its area of influence. Radiological risk assessment The main safety guides dealing with management of releases leading to radiological environmental impacts are the following: RS-G-1.8 (2005), Environmental and Source Monitoring for Radiation Protection [18]. WS-G-2.3 (2000), Regulatory Control of Radioactive Discharges to the Environment [19]. RS-G-1.7 (2004), Application of the Concepts of Exclusion, Exemption and Clearance of Radioactive Waste [20].