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Regulations on environmental radiation protection of nuclear power plants (promulgated by the National Environmental Protection Agency on April 23, 1986, implemented on December 1, 1986)
1 General Provisions 1.1 This standard implements the "Environmental Protection Law of the People's Republic of China (Trial)" and relevant national laws and regulations, and for the development of China's nuclear energy industry, protects the environment, protects human health, and promotes the development of the national economy. Situation.
1.2 This standard applies to land-based fixed-type nuclear power plants of various light water reactor types (in principle also applicable to nuclear thermal power plants).
1.3 The site selection, design, construction, operation, decommissioning and expansion, reconstruction or modification of operating conditions of nuclear power plants must meet the requirements of the relevant sections of this standard.
1.4 Principles of radiation protection 1.4.1 All leaders of nuclear power plants must have legitimate reasons for radiation exposure practices to protect the public from all unnecessary radiation exposure.
1.4.2 The optimization of radiation protection, that is, after taking into account social and positive factors, the radiation exposure to the public caused by nuclear power plants should follow the principle of “reasonably as low as possibleâ€.
1.4.3 Under normal operating conditions, a system of measurement equivalent limits shall be applied to individuals and groups of individuals who may be exposed to radiation from nuclear power plants.
1.4.4 In applying these principles, consideration should be given to the measurement burden caused by the current practice in the coming years.
1.5 Facilities of nuclear power plants related to radiation protection and environmental protection shall pass technical and economic argumentation, adopt the optimal plan, and must be designed, constructed, and put into operation simultaneously with the main project.
1.6 The operational poisons of nuclear power plants must be submitted in accordance with the "Administrative Measures for the Environmental Protection of Nuclear Power Plants' Basic Construction" promulgated by the State Environmental Protection Department, and a corresponding environmental impact report must be submitted.
1.7 The environmental impact report of a nuclear power plant implements professional technical audits and the national environmental protection department approval system.
1.8 The provincial environmental protection department has the right to inspect and supervise the environmental protection work of a nuclear power plant, and has the right to stop the violation of this standard and the environmental quality and public health. punishment.
2 Site Selection Requirements 2.1 When assessing whether the site is suitable for NPPs, it must consider comprehensively the geology, earthquake, hydrology, meteorology, transportation, industrial enterprises, land use, population density and distribution around the site, and social and economic aspects of the site area. Factors such as sexuality; must consider the natural or man-made external events that may occur in the area where the site is located and affect the safety of the nuclear power plant itself; must take into account the radioactive effluent from the nuclear power plant (especially the effluent under accident conditions) to the environment and ecology. And public influence; the storage and operation of new fuel, spent fuel, and radioactive waste must be considered.
2.2 Nuclear power plants should be built as far as possible in locations where the population density is low and the average population density is small.
The urban development boundary of a nuclear power plant with a population of 100,000 inhabitants and a city with a population of more than one million inhabitants should maintain an appropriate straight-line distance.
2.3 The non-residential area should be around the nuclear power plant. The radius of the non-residential area (reactor-centric) should not be less than 0.5 KM.
A restricted area shall be set around the non-residential area of ​​a nuclear power plant. The radius of the restricted area shall be (reactor-centric) generally not less than 0.5 KM.
2.4 If the site of the nuclear power plant cannot meet the requirements of the distance between the town and the town, the safety data of additional engineering safety facilities and site safety assessments shall be submitted and detailed explanations and arguments shall be made.
2.5 In the event of the maximum credible accident, any person (adult) on the non-residential area boundary shall receive an effective metered dose equivalent of no more than 0.25 SV within 8 hours after the accident and the thyroid dose equivalent shall not exceed 2.5 SV.
During the entire duration of the accident (the duration of the accident may be 30D), the collective effective dose equivalent received by the public population within a radius of 80 KM must be less than 2 x 104 SV, and the collective thyroid dose equivalent must be less than 2 x 104 SV.
3 Dose limits and emission control values ​​under normal operating conditions 3.1 The effective dose equivalent of radioactive substances released from the environment of each nuclear power plant project to any individual (adult) in the public should be less than 0.25MSV per year.
3.2 The annual emissions of airborne and liquid radioactive effluents from each pressurized water reactor nuclear power plant shall, in addition to meeting the requirements of 3.1, generally be lower than the following control values.
Table 1
Airborne radioactive effluent control value inert gas 2.5×1015Bq
Iodine 7.5×1010Bq
Particles (half-life ≥8d) 2×1011Bq
Table 2
Liquid radioactive effluent control value 氚1.5×1014Bq
The remaining nuclide 7.5×1011Bq
4 Accident Emergency Protection Level 4.1 The degree of harm to the environment may be caused by the magnitude of the accident. The accidents at the NPP are divided into expected operation events, major accidents, major accidents and maximum credible accidents.
4.2 The expected operational events are used for the environmental assessment of normal operation conditions of nuclear power plants. Dosage control limits to the public are implemented according to 3.1 of this standard.
4.3 Major accidents and major accidents are used for environmental assessment under accident conditions in nuclear power plants.
In every major accident, the effective dose equivalent of any individual (adult) in the public should be controlled below 5MSV, and the thyroid dose equivalent should be controlled below 50MSV.
In each major accident, the effective dose equivalent of any individual (adult) in the public should be controlled below 0.1SV, and the thyroid dose equivalent should be controlled below 1SV.
4.4 The maximum credible accidents are only used for environmental assessment at the time of site selection. The dose equivalents of the public on the non-residential boundary of dry cells and the collective dose equivalent of the public shall be implemented in accordance with 2.5 of this standard.
4.5 Before the nuclear power plant is commissioned, the operating organization of the nuclear power plant must, together with relevant departments, formulate an accident contingency plan and report it to the relevant government department of the national environmental protection department. No accident emergency plan will not be approved.
4.6 The emergency intervention level is as follows:
4.6.1 When the effective dose equivalent of individuals (adults) in the public is expected to be greater than 50MSV and the thyroid dose equivalent is expected to be greater than 0.5SV, appropriate measures (such as closing doors and windows, concealment in the room, iodine, etc.) are taken in order.
4.6.2 When individuals (adults) in the public are expected to receive effective dose equivalents greater than 0.1 SV, consider taking decisive measures (such as organizational evacuation, etc.).
4.7 During the operation of a nuclear power plant, once any accident that may harm the environment occurs, the operating organization must quickly identify the location and cause of the accident, handle it in a timely manner, try to control the release of the radioactive material in the environment, and immediately report to the competent authority and provincial environmental protection. Departments and related government departments.
5 Emissions management of effluents 5.1 The operating organization of NPPs should follow the principle of “three-waste†treatment technology for specific environmental features (eg, meteorological, hydrological, etc.) of the NPP site, and follow the principle of “can be reasonably achieved as low as possibleâ€. The proposed design emissions that ensure compliance with 3.1 and fall below the annual emission control value specified in 3.2 shall be reported to the national environmental protection department for approval and shall be the target value for the management of radioactive effluents from the nuclear power plant.
5.2 Airborne radioactive effluents must be discharged into the atmosphere through the chimney after treatment.
5.3 The operating organization of nuclear power plants must monitor airborne and liquid radioactive effluents. The total annual emission should be controlled on a quarterly basis. The total emissions within three consecutive months should not exceed one half of the annual emission management target value. . If it exceeds, the cause must be quickly identified and effective measures must be taken.
5.4 The outlets for liquid radioactive effluents should avoid concentrated intakes, economic fish spawning grounds, migration routes, and aquatic bio farms.
5.5 The operating organization of a nuclear power plant shall continuously improve its equipment and processes in accordance with the development of new technologies and the weaknesses exposed in the operation and monitoring of nuclear power plants, and strengthen management to minimize actual annual emissions.
6 Environmental monitoring and effluent monitoring 6.1 Environmental investigation before operation 6.6.1 Before the nuclear power plant is commissioned, the operating organization must complete the investigation of the background radiation level of the environment, and at least two years of survey data should be obtained.
6.6.2 Data from key nuclides, key exposure (and transfer) pathways and key population groups should be obtained through the survey.
6.1.3 The surveyed environmental media should generally include: air, surface water and groundwater, terrestrial organisms and aquatic organisms, food, soil, water sediment, and sedimentation ash.
6.1.4 The survey scope of the environmental radiation level generally takes 50KM, and the survey scope of the remaining projects generally takes 20 to 30KM.
6.1.5 The contents of analytical measurements generally include: the level of environmental radiation and radionuclides associated with nuclear power plants.
6.2 Routine radiation environmental radiation monitoring 6.2.1 After the nuclear power plant is commissioned, the operating organization must conduct routine environmental radiation monitoring, analyze the monitoring results in a timely manner, and make evaluations, establish files, and report according to regulations.
6.2.2 In conducting routine environmental radiation monitoring, full use should be made of the data obtained from the pre-operation background survey and, as long as the needs of the environmental assessment are met, the best possible environmental monitoring is to be achieved. The focus of environmental monitoring is on those radionuclides and projects that are the most harmful to the group of key people.
6.2.3 The environmental media, monitoring content and monitoring scope of conventional environmental radiation monitoring shall be implemented with reference to 6.1.
6.3 effluent monitoring The operating organization of the nuclear power plant must monitor all airborne and liquid radioactive effluents. The content of the measurement should include the analysis of the total amount of emissions and the major nuclides of emission concentration machines.
6.4 Emergency monitoring of accident environment 6.4.1 Before a nuclear power plant is commissioned, the operating organization shall formulate an environmental emergency monitoring plan and submit it to the provincial environmental protection agency for record. Taking into account the abruptness and particularity of some accidents, emergency monitoring must be flexible and fast.
6.4.2 Environmental emergency monitoring is an important part of the emergency plan for nuclear power plant accidents. Generally include: monitoring principles, monitoring methods and procedures for various types of radiation accidents, monitoring items, monitoring outlets, leaders of monitoring work, reports of monitoring data, and methods of distribution.
6.4.3 In the environmental emergency monitoring plan, some derived action levels (such as the concentration of radionuclides in the air, water, and food corresponding to the dose level of emergency operations) can be specified in advance to facilitate the evaluation of the monitoring results, and whether it is necessary to decide early Action.
6.5 Environmental monitoring The quality assurance system must be implemented. Standard (or uniform) methods and procedures must be used to operate and must not be changed without authorization. If changes are required, they must be technically verified.
6.6 The provincial environmental protection department shall be responsible for setting up the environmental radiation monitoring agency of the nuclear power plant and carry out the monitoring work according to the corresponding requirements of this standard.
7 Storage and Transportation of Radioactive Waste 7.1 It is necessary to strictly manage radioactive waste, strengthen monitoring, and take effective measures to prevent the proliferation of radioactive waste.
7.2 The radioactive waste must be strictly classified and disposed separately. Combustible, explosive, perishable, non-radioactive materials and fixed radioactive waste are strictly prohibited for transport and storage. It is strictly prohibited to transport radioactive liquid waste.
7.3 The storage and disposal of radioactive waste should ensure that open source and groundwater are not contaminated.
7.4 Transport of radioactive materials (including new fuel elements and spent fuel elements) must comply with the relevant national regulations. Workers transporting radioactive materials must be familiar with the regulations for the transport of radioactive materials, the nature of the radioactive materials being transported, and the necessary protective knowledge.
8 After decommissioning a nuclear power plant for a nuclear power plant to obtain approval for decommissioning, when preparing a decommissioning plan, an environmental impact report must be prepared at the same time. Only after the approval of the national environmental authority can it be implemented.
Appendix A Terminology Definitions (Supplements)
A.1 Each NPP: Refers to any plant, station, including one or several reactors that use a nuclear reactor to generate electricity, and all systems, facilities, and buildings necessary for safety needs and the generation of heat or electricity.
A.2 Trial operation: refers to the loading, physical start, zero-power operation, and power operation performed by the nuclear power plant after inspection to meet the safety objectives until the qualified acceptance.
A.3 Operation: Refers to the entire process of power operation, shutdown, maintenance, testing, refueling, and community-related work of a nuclear power plant under specified operating conditions.
A.4 Non-residential area: refers to an area where a nuclear power plant is located, where permanent residents are strictly forbidden, and the operating organization of the nuclear power plant exercises effective jurisdiction over this area, including the withdrawal of any individuals and property from the area; Highways, railways, and waterways can pass through the area, but they must not interfere with the normal operation of nuclear power plants. In the event of an accident, appropriate and effective arrangements can be made to control traffic so as to ensure the safety of workers and residents. In non-residential areas, activities that are not related to the operation of nuclear power plants are permitted under appropriate limits as long as they do not affect the normal operation of nuclear power plants and endanger the health and safety of residents. Non-residential areas are not required to be round and can be determined according to the site's topography, landforms, weather, traffic and other specific conditions.
A.5 Restricted area: refers to the area directly adjacent to a non-residential area. The mechanical growth of the population must be limited in the restricted area. No large enterprises, institutions, living quarters, nursing homes, tourist resorts, airports, and prisons shall be built or expanded in the reformed areas.
A.6 Expected operational events: During the operation of a nuclear power plant, it is expected from the design that all operational faults that deviate from normal operating conditions will occur. In view of proper design considerations, when such accidents occur, they will not cause the failure of engineering safety protection factors and major damage to engineering equipment, and will not result in the release of radioactive substances into the environment.
A.7 Major Accidents: During the lifetime of a nuclear power plant, the probability of the body of law is expected to be no more than 0.01 to 0.1 per pile per year, which is a significant deviation from normal operating conditions. At this time, if the engineering safety protection facilities cannot fully function according to the design requirements , it will lead to a large release of radioactive material to the environment, and it is possible that the radiation dose received has exceeded the dose limit specified in 3.1.
A.8 Major accidents: During the lifetime of nuclear power plants, accidents that do not occur or occur with a probability of no greater than 5×10-4 to 10-2/pound year, which are expected to deviate from normal operating conditions, are not expected. Engineering safety protection facilities will probably be released partially to the environment.
A.9 Maximum credible accident: It is a nuclear power plant accident that is assumed to have the most serious consequences for the environment as assumed by the site evaluation, and its probability of occurrence (<10-4/pound year) is extremely small. The maximum credible accidents for different types of reactors are different. For PWR nuclear power plants, it means that the core is dissolved on a large scale and the release of radioactive materials to the environment has reached the most serious accident.
Additional information:
This standard was proposed by the National Environmental Protection Agency.
This standard was drafted by the Nuclear Energy Technology Institute of Tsinghua University and the China Atomic Energy Research Institute.
The drafters of this standard are Liu Yuanzhong and Jiang Xiwen.
This standard is interpreted by the National Environmental Protection Agency.
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