the 1980s. The design directly uses a majority of the already built civil structures and facilities related to generic plant needs. Existing foundations and civil structures will be further evaluated with a view to incorporation into the new design. AES 92 Reactor Belene NPP will be a Pressurized Water Reactor design with four first-stage coolant circulation loops per reactor. Reactor nominal thermal power is 3010 MWt and electrical net power is 1011 MWe. A typical refueling process takes 14 days with annual outage of between 20-28 and 40–50 days, depending on the scope of ongoing repair works. The AES 92 Reactor Facility has a 60-year lifetime design. Being a Light Water Reactor of third generation type the AES 92 design has improved safety as well as technical and economic features. Main advantages of the AES 92 design over existing VVER nuclear power plants of the previous generation are: Ensuring for fast and sure termination of the nuclear reaction in the reactor core thanks to two individual completely independent reactivity control systems; Redundancy for all safety functions provided by the use of both active and passive safety systems (including a Passive Residual Heat Removal System and Passive Filtering System), which require neither operator intervention nor electric power supply; Use of a special enclosure to contain potential accidents. This structure is composed of a primary containment of pre-stressed reinforced concrete and a leak tight metal liner, secondary reinforced concrete containment, and cast concrete external structure designed to withstand a large range of internal and external events. A specific feature of the third generation reactor presented in the AES 92 variant is the provision of a "core catcher" for severe accident cases. This insures against a containment integrity violation and release of highly radioactive substances into the environment. Improved safety in the AES 92 design accounts for projected improvements in radiation protection parameters during its operation. The calculated individual effective dose of personnel exposure for this design is 1 mSv/a, which is commensurate with the permissible annual effective dose limit for a person in the general population and in compliance with the Bulgarian normative base and European directives. As to the design dose rate per person of the greater population due to radioactive releases by the NPP: this value for the AES 92 variant is lower than 0.05 mSv/a, which represents less than 1/3 of the permissible dose rate as per article 10