A Site Safety Report referred to in Regulation 3(2)(a) must contain the following—
| (1) | A motivation for the choice of the site to ensure a low risk of public exposure from the operation of the nuclear installation(s). |
| (2) | A statement as to the proposed use of the site in terms of the range of technologies and plant designs being considered for the nuclear installation(s) and use of the site, including where appropriate the maximum thermal power, general design characteristics such as the engineered safety features of the nuclear installation(s) included as safety measures against the hazardous consequences of postulated events, and the layout on the site. |
| (3) | The characteristics of the site relevant to the design assessment, risk and dose calculations, including inter alia: |
| (d) | population demographics; |
| (f) | projections of the above data commensurate with the design life of the nuclear installation(s). |
| (4) | A source term analysis that is representative of the overall potential hazards posed to the public and the environment owing to the new nuclear installation(s). A representative scope of internal and external events enveloping the new nuclear installation(s) must be taken into consideration. |
| (5) | A Probabilistic Risk Assessment (PRA) using the site characteristics referred to in Regulation 5(3) and the source terms referred to in Regulation 5(4) to demonstrate compliance with the probabilistic risk limits. This analysis must include the impact of all nuclear installations and actions on the site, existing and proposed, for which authorizations have been granted by the Regulator. |
| (6) | An analysis of the impact on the public due to normal operations of the new nuclear installation(s), including minor occurrences that can be kept under control, to demonstrate compliance with the dose limits. This analysis must include the impact of all nuclear installations and actions the site, existing and proposed, for which authorizations have been granted by the Regulator. |
| (7) | The identification and determination of emergency planning zones using the characteristics of the site, source term analysis and PRA established in accordance with Regulations 5(3), 5(4) and 5(5) respectively. In determining the emergency planning zones due account must be taken of physical boundaries such as rivers, dams, mountain ranges, as well as municipal boundaries. The emergency planning zones must include the following: |
| (a) | An exclusion zone which is a radius determined for the purposes of evacuating persons in the event of a nuclear accident. Within the boundaries of that zone or within any erven intersecting with that zone there must be no members of the public resident, no uncontrolled recreational activities, no commercial activities, or institutions which are not directly linked to the operation of nuclear installations situated within this zone, or for which an authorization has been not been granted; |
| (b) | An overall Emergency Planning Zone (EPZ) of such size that emergency or remedial measures must be considered where the potential exists that any members of the public may receive more than an annual effective dose of 1mSv due to the source term; |
| (c) | A Long Term Protective Action Planning Zone (LPZ), where preparations for effective implementation of protective actions to reduce the risk of stochastic health effects from long term exposure to deposition and ingestion must be developed in advance consistent with international standards. |
| (8) | An analysis to demonstrate the viability of an emergency plan taking into account relevant data established in accordance with Regulations 5(3), 5(4), and 5(5), including disaster management infrastructure. It must be shown that risks to the public, as well as the financial consequences caused by damage and radioactive contamination, are as low as reasonably achievable. |
| (9) | An assessment on the suitability of the site, from a nuclear security perspective as determined by the NNR. |
