3 Assessment of Environmental Impact Degree
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Abstract This report contains calculations and justification of radiation impact of radioactive releases from SS Rivne NPP on the environment and the population during normal operation and in emergency cases in a transboundary context. All calculations have been performed for conservative conditions of impurity propagation and radiation dose formation (at maximum doses). It has been shown that maximum permissible values of radiation criteria for equivalent and absorbed doses in body organs and the entire body at borders with other countries, as defined by regulatory documents, are met during normal operation of power units, or in case of design basis or beyond design basis accidents. It has been justified that planned activities have no major transboundary impact, and there is no affected party in terms of the Convention on Environmental Impact Assessment in a Transboundary Context. In execution of para. 8, Art. 3 of Convention on Access to Public Information, posting the information on environmental impact of the planned activities in a transboundary context at common access Internet resources, e. g. on websites of the government authorities concerned - the Ministry of Ecology and Natural Resources of Ukraine and the Ministry of Energy and Coal Industry of Ukraine - will suffice. The report contains 68 pages, including 14 figures and 27 tables. Keywords: NPP, radiation dose, maximum design basis accident, beyond design basis accident, transboundary impact. 4 Contents ABSTRACT ....................................................................................................................................................................... 4 ABBREVIATIONS ........................................................................................................................................................... 6 INTRODUCTION ............................................................................................................................................................. 8 1 ENVIRONMENTAL IMPACT FACILITY DESCRIPTION AND PURPOSE OF OPERATIONS ............ 8 1.1 BRIEF DESCRIPTION OF POWER UNITS AND PRODUCTION PROCESSES ................................................................... 9 2 POTENTIAL RADIATION IMPACT ............................................................................................................... 12 3 ASSESSMENT OF ENVIRONMENTAL IMPACT DEGREE ....................................................................... 14 3.1 MONITORING METHODS AND EQUIPMENT ............................................ ОШИБКА! ЗАКЛАДКА НЕ ОПРЕДЕЛЕНА. 3.2 DOSES AT BORDERS WITH THE NEIGHBOURING STATES DURING NORMAL OPERATION ....................................... 16 3.2.1 Distances to the neighbouring countries ............................................................................................... 17 3.22 Calculated doses at borders with the neighbouring states during normal operation............................ 18 3.3 DOSES AT BORDERS WITH THE NEIGHBOURING STATES DURING ACCIDENTS ..................................................... 22 3.3.1 Selection of the lowest weather conditions that result in the maximum radiation doses ....................... 25 3.3.2 Doses at borders with the neighbouring states during accidents at RNPP ........................................... 27 4 MEASURES TO MITIGATE ENVIRONMENTAL IMPACT ....................................................................... 32 5 DESCRIPTION OF ENVIRONMENTAL IMPACT ASSESSMENT METHODS....................................... 33 5.1 PC CREAM ........................................................................................ ОШИБКА! ЗАКЛАДКА НЕ ОПРЕДЕЛЕНА. 5.1.1 Brief model description ................................................................. Ошибка! Закладка не определена. 5.1.2 Mathematical plume dispersal models .................................................................................................. 34 5.1.3 Compartment exponential models ......................................................................................................... 38 5.1.4 Migration model for agricultural plants ............................................................................................... 38 5.1.5. Mathematical models for dose calculation ............................................................................................................. 40 5.1.5.1 Individual dose calculation based on food chains ................................................................................................. 40 5.1.5.2 Individual radiation doses (direct exposure) ......................................................................................................... 42 5.1.5.3 Calculation of collective doses .............................................................................................................................. 47 5.2 METEOROLOGICAL PARAMETERS ................................................................................................................................. 47 5.2.1 Meteorological parameters for the years 2006-2017 ............................................................................................... 48 5.3 PC COSYMA .............................................................................................................................................................. 59 6 MONITORING AND ENVIRONMENTAL IMPACT MANAGEMENT PROGRAM ............................... 60 6.1 CONTROL FOR THE MAIN TECHNOLOGICAL ENVIRONMENTS......................................................................................... 61 6.2 MONITORING OF THE NPP IMPACT ON POPULATION AND ENVIRONMENT ..................................................................... 62 6.3 MANAGEMENT OF ENVIRONMENTAL IMPACT ............................................................................................................... 65 CONCLUSIONS ............................................................................................................................................................. 68 LIST OF REFERENCES ....................................................................... ОШИБКА! ЗАКЛАДКА НЕ ОПРЕДЕЛЕНА. 5 Abbreviations NPP Nuclear power plant ARSMS Automated Radiation State Monitoring System VVER Water-water power reactor SS Separate Subdivision VS Ventilation system WP Waste piping LLN Long-lived nuclides SE NNEGC State Enterprise “National Nuclear Energy Generating Energoatom Company Energoatom” RNPP Rivne Nuclear Power Plant BDBA Beyond design basis accident OZ Observation zone IRG Inert radioactive gases RWMT RW level monitoring tanks EDR Equivalent dose rate ICRP International Commission on Radiological Protection MDBA Maximum design basis accident VA Volumetric activity ISS Industrial/storm sewerage CS Control station RW Radioactive waste RC Radiation control RR Reactor room LRW Liquid radioactive waste RU Reactor unit RAWT Radioactive water treatment SPB Special purpose building RCS Radiation Control System 6 LRWR Liquid radioactive waste repository SRWR Solid radioactive waste repository FE Fuel element TPP Thermal power plant TLD Thermoluminescent dosimeter SRW Solid radioactive waste 7 Introduction In accordance with the requirements of the International Convention on Environmental Impact Assessment in a Transboundary Context, as ratified by the Law of Ukraine No. 534-XIV dated 19 March 1999, the radiation environmental impact of Rivne NPP in a transboundary context, i. e. its impact on the territories of the neighbouring states, has been assessed. The impact of RNPP has been assessed both during normal operation and during accidents. 1 Environmental impact facility description and purpose of operations The impact facility, SS Rivne NPP, is a separate subdivision (unit) of the State Enterprise “National Nuclear Energy Generating Company Energoatom” (SE NNEGC Energoatom). SE NNEGC Energoatom carries out activities in accordance with its Articles of Association and is subordinate of the Ministry of Fuel and Energy of Ukraine. SE NNEGC Energoatom is assigned the functions of an operating organization responsible for the safety of all nuclear power plants in the country. Rivne NPP is located on the Styr River in the north-west part of the Rivne Region, 120 km from the City of Rivne, in the Volodymyretskyi District. The location of SS Rivne NPP and the boundaries of its observation zone (OZ) are shown in Fig. 1.1 [1]. The gross installed capacity is 2 mln 835 thous. kW. The design CUF capacity utilization factor is 74.2 %. The construction started in 1983. The plant was commissioned in 1980. Type of activity - electricity generation. RNPP produces approx. 19 bln kW⋅h of electricity annually, which accounts for 21.6 % of gross electricity generation by nuclear power stations (NPP), or 12.0 % of Ukraine's gross electricity generation. RNPP operates four power units: 8 Power unit І (VVER-440) with a capacity of 420 MW since 1980. Power unit IІ (VVER-440) with a capacity of 415 MW since 1981. Power unit IIІ (VVER-1000) with a capacity of 1000 MW since 1986. Power unit IV (VVER-1000) with a capacity of 1000 MW since 2004. Figure 1.1 Rivne NPP location 1.1 Brief description of power units and production processes The general site layout plan of Rivne NPP is shown in Fig. 1.2 [2]. 9 Figure 1.2 Schematic layout of buildings and structures at the SS Rivne NPP industrial site 1. NPP industrial site 11. Special-purpose building for power units No. 1 2. Power units No. 1 and 2 and 2 3. Power unit No. 3 12.