Each Contracting Party shall take the appropriate steps to ensure that:
(i) the design and construction of a spent fuel management facility provide for suitable measures to limit possible radiological impacts on individuals, society and the environment, including those from discharges or uncontrolled releases;
(ii) at the design stage, conceptual plans and, as necessary, technical provisions for the decommissioning of a spent fuel management facility are taken into account;
(iii) the technologies incorporated in the design and construction of a spent fuel management facility are supported by experience, testing or analysis.
G.7
DESIGN AND CONSTRUCTION OF FACILITIES
G.7.1 The regulatory requirement
The general safety regulations (SKIFS 1988:1) apply to the operation of all types of nuclear installations, including facilities for treatment, storage and disposal of spent fuel and radioactive waste.
G.7.1.1 Suitable measures to limit radiological impact
The requirements for limiting the possible radiological impact on individuals, society and the environment, including those from discharges or uncontrolled releases, are founded upon the basic provisions stipulated in 4§ first paragraph in the Act on Nuclear Activities (1984:3). This is clarified further in the general safety regulations (SKIFS 1988:1) in which it is stated that nuclear accidents shall be prevented through a basic facility-specific design that shall incorporate multiple barriers as well as a facility-specific defence-in-depth system. Defence-in-depth shall be achieved by
- ensuring that the design, construction, operation, monitoring and maintenance of a facility is such that abnormal events, incidents and accidents are prevented,
- ensuring that multiple devices and measures exist to protect the integrity of the barriers and, if the integrity should be breached, to mitigate the ensuing consequences,
- ensuring that any release of radioactive substances, which may still occur as a result of abnormal events, incidents and accidents, is prevented or, if this is not possible, controlled and mitigated through devices and prepared measures.
G.7.1.2 Conceptual plans and provisions for decommissioning
The Act on Nuclear Activities states that the holder of a licence for nuclear activities is responsible for ensur- ing that all necessary measures are taken to ensure the safe handling and final disposal of nuclear waste, or
nuclear material that is not reused, as well as the safe decommissioning and the dismantling of facilities. It has therefore not been considered necessary to introduce an explicit requirement in the general regulations (SKIFS 1998:1) for the preparation of conceptual plans or technical provisions for the decommissioning of spent nuclear facilities, at the design stage.
With regard to radiation protection, SSI recently issued new regulations, SSI regulations on Planning before and during decommissioning of nuclear facilities (SSI FS 2002:4), that will enter into force January 1, 2004. The regulations introduce requirements for decommissioning with respect to documentation, alternative actions and waste management.
G.7.1.3 Technology supported by experience
The general safety regulations (SKIFS 1988:1) specifies specify requirements regarding design and cons- truction. It is stated states in that in order to meet the basic safety provisions the design of the facility, with adaptation to the specific conditions of each facility, shall;
- be able to withstand component and system failures, - have reliability and operational stability,
- be able to withstand such events or conditions which can affect the safety function of the barriers or defence-in-depth, as well as
- have maintainability, controllability and testability of inherent parts as long as these parts are used for their intended purposes.
Additional requirements related to design and construction are specified as follows;
- The design principles and design solutions shall be tested under conditions corresponding to those which can occur during the intended application in a facility. If this is not possible or reasonable, they must have been subjected to the necessary testing or evaluation related to safety.
- The design solutions shall be adapted to the personnel’s ability to manage, the facility, in a safe manner, under normal conditions as well as the abnormal events, incidents and accidents that might occur - Building components, devices, components and systems shall be designed, manufactured, installed, con-
trolled and tested in accordance with requirements which are adapted for their importance for safety.
G.7.2 Measures taken by the licence holders
G.7.2.1 Suitable measures to limit radiological impact
The safety philosophy applied in the design of all Swedish nuclear facilities is based on the principles of defence-in-depth and of multiple barriers to prevent the release of radioactive material to the environment. They are all designed to fulfi l the intention of the requirements in the General Design Criteria. The foundation of the safety principle on the defence in depth is emphasised and made clearer through the implementation of that principle in the SKI regulations SKIFS 1998:1.
G.7.2.2 Conceptual plans and provisions for decommissioning
Generic decommissioning plans have been developed by SKB, as part of the basis for the annual cost cal- culations (see section E.19.1.4.)
G.7.2.3 Technology supported by experience
The principle of proven technology is broadly accepted and implemented in the design and construction procedures for the Swedish nuclear facilities. The use of properly environmentally qualified equipment ensures functioning of safety-related systems and components under emergency conditions. A comprehensive pro- gramme for environmental qualification has been carried out. No major new steps are envisaged in addition to the previous programme, although research and development continues. In the modernisation work, the specification of all new installations is carefully checked with respect to environmental requirements.
G.7.3 Regulatory control
During the licensing process the PSAR, FSAR and STF document are reviewed by the regulatory authorities, to ensure compliance with fundamental safety principles and criteria. A prerequisite for obtaining a licence is that the regulatory review concludes that the facility is designed according to the provisions in the general regulations (SKIFS 1998:1).
G.7.4 Conclusion
The Swedish Party complies with the obligations of Article 7. There is however room for improvment. More comprehensive, consistent and clear safety regulations for decommissioning of nuclear facilities need to be developed. The regulatory body have recently taken actions towards this end.