The VVER-TOI or WWER-TOI () is a generation III+ nuclear power reactor based on VVER technology developed by Rosatom. The VVER-TOI design is intended to improve the competitiveness of Russian VVER technology in international markets. It would use VVER-1300/510 water pressurized reactors constructed to meet modern nuclear and radiation safety requirements. The VVER-TOI project is developed on the basis of the design documents worked out for AES-2006, considering the experience gained in development of projects based on VVER technology both in Russia and abroad, such as Novovoronezh Nuclear Power Plant II. The first VVER-TOI will be unit 1 of the Kursk II Nuclear Power Plant. Main technical-economic indicators The reactor design life is 60 years, with potential of life extension to 100 years, and a thermal capacity of 3300 MWt and a gross electrical capacity of 1300 MWe. Project initial requirements Stability in the terms of critical external impacts and natural disasters. Correspondence to the world accepted rules and regulations. Correspondence to the climatic conditions from the tropics up to Northern regions. Independence in the terms of external power and water supply sources loss. Safety assurance principles Population and environment protection The radiation safety is arranged and implemented to prevent inadmissible impacts caused by ionizing radiation sources on the materials, population and environment in the area that surrounds a Nuclear power plant. The concept of providing radiation and nuclear safety in VVER-TOI project is based on the following: requirements provided by domestic safety rules and regulations in force in the field of nuclear-power engineering, which are applicable for the designed power unit considering their further development; modern philosophy and safety principles developed by the world nuclear community and reflected in the IAEA Safety Standards; materials published by International Nuclear Safety Advisory Group (INSAG) on nuclear safety issues, EUR requirements; complex of the technical solutions worked-out and checked through operation considering the efforts targeted at their upgrading, and elimination of the “weak links” revealed during operation; verified and certified calculation methods, codes and programs; worked-out safety analysis methodology, reliable database; organizational and technical measures to prevent and restrict severe accidents repercussions, which are developed according to the results of investigations in the field of severe accidents; experience in development of new generation and increased safety plants; to provide low sensibility to the errors and personnel mistaken solutions; to ensure low risks of considerable radionuclide emission in case of accident; to provide