GB 6249-1986 Regulations on environmental radiation protection for nuclear power plants
Some standard content:
1General Provisions
National Standards of the People's Republic of China
Regulations for environmental rediation protection of nuclear power plant.
UDC 614. 898. 5
GB 6249--86
1.1 This standard is to implement the "Environmental Protection Law of the People's Republic of China (Trial)" and relevant national regulations, to develop China's nuclear energy industry, protect the environment, protect human health, and promote The development of the national economy is formulated with reference to relevant international standards and the specific conditions of our country. 1.2 This standard applies to all types of light water reactor land-based fixed nuclear power plants (in principle, it also applies to nuclear thermal power plants). 1.3 The site selection, design, construction, operation, decommissioning and expansion, reconstruction or change of operating conditions of nuclear power plants must comply with the requirements of the relevant chapters of this standard.
1.4 Radiation* Protection Principles
1.4.1 All practical activities in nuclear power plants that result in personnel radiation exposure must be justified and the public should be protected from all unnecessary radiation exposure.
1.4.2. Optimization of radiation protection means that after taking into account social and economic factors, the radiation exposure caused by nuclear power plants to the public should follow the principle of "as low as reasonably possible". 1.4.3 Under normal operating conditions, a dose equivalent limit system shall be implemented for public individuals and groups who may be exposed to radiation from nuclear power plants. 1.4.4 In applying these principles, consideration should be given to the dose burden that current practice will impose in future years. 1.5 Facilities related to radiation protection and environmental protection in nuclear power plants should pass technical and economic demonstrations, adopt the optimal solution, and must be designed, constructed, and put into operation at the same time as the main project. 1.6 The operating unit of a nuclear power plant must submit a corresponding environmental impact report in accordance with the "Environmental Protection Management Measures for Nuclear Power Plant Capital Construction" promulgated by the national environmental protection department. 1.7 The environmental impact report of nuclear power broadcasting shall be subject to professional technical review and approval system by the national environmental protection department. 1.8 Provincial environmental protection departments exercise the right to inspect and supervise the environmental protection work of nuclear power plants. When encountering incidents that violate this standard and endanger environmental quality and public health, they have the right to stop them and impose sanctions in accordance with the law depending on the severity of the case. punish. 2. Site selection requirements
2.1 When evaluating whether a site is suitable for building a nuclear power plant, the geology, geography, hydrology, meteorology, transportation, industrial enterprises, land use, and population density and distribution around the site must be comprehensively considered. and socioeconomic rationality and other factors; the impact of natural or man-made external events that may occur in the area where the plant site is located on the safety of the nuclear power plant itself must be considered; the radioactive effluent from the nuclear power plant (especially the outflow under accident conditions) must be considered The impact of new fuel, spent fuel and radioactive waste on the environment, ecology and public must be considered.
2.2 Nuclear power plants should be built in locations with low population density and low average regional population density. Nuclear power plants should maintain appropriate straight-line distances from the urban development boundaries of towns with a population of more than 100,000 and from large cities with a population of more than 1 million.
*' Radiation: In this standard, it is the abbreviation of ionizing radiation. National Environmental Protection Administration issued on 1986-04-23 and 1986-12-01 Implementation
3
GB 6249--86
2.3 Non-residential areas should be set up around nuclear power plants. Non-residential areas The radius (centered on the reactor) shall not be less than 0.5km. Restricted areas should be set up around non-residential areas of nuclear power plants, and the radius of the restricted area (centered on the reactor) should generally not be less than 5km. 2.4 If the nuclear power plant site cannot meet the requirements of distance from cities and towns in 2.2, additional engineering safety facilities and site safety evaluation information should be provided and explained and demonstrated in detail. 2.5 Under the conditions of the most credible accident, the effective dose equivalent received by any individual (adult) at the boundary of a non-residential area within 8 hours after the accident should not be greater than 0.25Sv (25rem), and the thyroid dose equivalent should not be greater than 2.5 Sv(250rem). During the entire duration of the accident (the accident duration can be 30 days), the collective effective dose equivalent received by the public within a radius of 80km must be less than 2×104 people·Sv (2×10° people·rem), and the collective thyroid dose equivalent Must be less than 2×10° people·Sv (2×106 people*rem).
3 Dose limits and emission control values ??under normal operating conditions 3.1 The effective dose equivalent of radioactive materials released into the environment by each nuclear power plant to any individual (adult) in the public should be less than 0.25 per year mSv (25 mrem).
3.2 The annual emissions of airborne and liquid radioactive effluents from each pressurized water reactor type nuclear power plant, in addition to meeting the provisions of 3.1, should generally be lower than the following control values.
Table 1
Airborne radioactive effluents
Inert gases
Iodine
Particles (half-life ≥8d)
Liquid radioactive effluents
Atmosphere
Other nuclides
Note: Other reactor types are determined separately according to specific circumstances. 4 Accident emergency protection level
Table 2
Control
Control
Value
2. 5×1015Bq (7×10*Ci)||tt ||7. 5×101°Bq (2Ci)
2×101Bq (5Ci)
Control
Control
Value
1.5×101* Bq (4 × 103Ci) | | tt | | 7. 5X1011Bq (20Ci) | The largest credible accident.
4.2 Expected operating events are used for environmental assessment under normal operating conditions of nuclear power plants. The dose control limits for the public are implemented in accordance with 3.1 of this standard. 4.3 Major accidents and major accidents are used for environmental assessment under accident conditions of nuclear power plants. In the event of a major accident, the effective dose equivalent that any individual (adult) in the public may receive should be controlled below 5 mSv (0.5 rem), and the thyroid dose equivalent should be controlled below 50 mSv (5 rem). In the event of a major accident, the effective dose equivalent that any individual (adult) in the public may receive should be controlled below 0.1Sv (10rem), and the thyroid dose equivalent should be controlled below 1Sv (100rem). 4.4 The maximum credible accident is only used for environmental assessment when selecting a plant site. The dose equivalent of the public at the boundary of the non-residential area of ??the nuclear power plant and the collective dose equivalent of the public shall be implemented in accordance with 2.5 of this standard.
4.5 Before the trial operation of a nuclear power plant, the operating unit of the nuclear power plant must formulate an accident emergency plan together with relevant departments and report it to the national environmental protection department and relevant government departments. No accident emergency plan will be approved. 4.6 The emergency intervention level is as follows: 4
GB 6249-86
4.6.1 The effective dose equivalent to individuals (adults) in the public is expected to be greater than 50mSv (5rem), and the thyroid dose equivalent is expected to be greater than 0.5 Sv (50 rem), appropriate measures must be taken (such as closing doors and windows, hiding indoors, taking iodine, etc.). 4.6.2 When the effective dose equivalent to individuals (adults) in the public is expected to be greater than 0.1Sv (10rem), and the thyroid dose equivalent is expected to be greater than 1Sv (100rem), decisive measures (such as tissue evacuation, etc.) can be considered. 4.7 During the operation of a nuclear power plant, if any accident that may harm the environment occurs, the operating unit must quickly identify the location and cause of the accident, deal with it in a timely manner, try to control the release of radioactive materials into the environment, and immediately report it to the competent authorities and provincial environmental protection authorities. departments and relevant government departments.
5 Effluent Emission Management
5.1 The operating unit of a nuclear power plant should, based on the specific environmental characteristics (such as meteorology, hydrology, etc.) of the nuclear power plant site and the technical level of the "three wastes" treatment process, Following the principle of “as low as reasonably possible”, propose a design emission that ensures that it meets 3.1 and is lower than the annual emission control value stipulated in 3.2, and submits it to the national environmental protection department for approval. Once approved, it will be regarded as the radioactive effluent of the nuclear power plant. management target value. 5.2 Airborne radioactive effluent must be treated and discharged into the atmosphere through smoke windows. 5.3 The operating unit of a nuclear power plant must monitor airborne and liquid radioactive effluents, and its total annual emissions 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 limit, the cause must be identified quickly and effective measures must be taken.
5.4. The discharge outlet of liquid radioactive effluent should avoid centralized water intakes, economic fish spawning grounds, migratory routes and aquatic life breeding grounds. 5.5 Nuclear power plant operators should continuously improve equipment and processes based on the development of new technologies and weak links 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 Pre-operation environmental investigation
6.1.1 Before the trial operation of the nuclear power plant, the operating unit must complete a survey of the environmental radioactive background radiation level. """"According to .
6.1.2 Information on key nuclides, key exposure (and transfer) pathways and key population groups should be obtained through surveys. 6.1.3 The environmental media investigated should generally include: air, surface water and groundwater, terrestrial and aquatic organisms, food, soil, water body sediment and settled ash, etc.
6.1.4 The survey range of environmental radiation levels is generally 50km, and the survey range of other projects is generally 20~30km. 6.1.5 The contents of analysis and measurement generally include: environmental radiation levels and radionuclides related to nuclear power plants. 6.2 Routine environmental radiation monitoring
6.2.1 After the trial operation of a nuclear power plant, the operating unit must conduct routine environmental radiation monitoring, analyze the monitoring results in a timely manner, make evaluations, establish files, and report them in accordance with regulations.
6.2.2 When conducting routine environmental radiation monitoring, the data obtained from the pre-operation background survey should be fully utilized, and environmental monitoring should be optimized as much as possible while meeting the needs of environmental assessment. Environmental monitoring focuses on those nuclides and projects that are most harmful to key groups of people. 6.2.3 The environmental medium, 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 a nuclear power plant must monitor all airborne and liquid radioactive effluents. Measurement content should include analysis of total emissions, emission concentrations and major nuclides.
6.4 Accident Environmental Emergency Monitoring
6.4.1 Before the trial operation of a nuclear power plant, the operating unit shall formulate an environmental emergency monitoring plan and submit it to the provincial environmental protection department for filing. Considering the suddenness and particularity of some accidents, emergency monitoring must be flexible and fast. 6.4.2 Environmental emergency monitoring is an important part of the nuclear power plant accident emergency plan. Generally include: monitoring principles, monitoring methods and steps for various types of radiation accidents, monitoring projects, monitoring outlets, leadership of monitoring work, reporting and release methods of monitoring data, etc. .5 | | tt | | GB6249-86 | concentration of toxins) to facilitate evaluation of monitoring results and early decision on whether corresponding actions need to be taken. 6.5·Environmental monitoring must implement a quality assurance system, adopt standard (or unified) methods and procedures, and shall not change without authorization. If changes are necessary, technical demonstration must be passed. 6.6 Provincial environmental protection departments should be responsible for setting up environmental radiation monitoring institutions for nuclear power plants and carrying out monitoring work in accordance with the corresponding requirements of this standard. 7 Storage and transportation of radioactive waste
7.1 Radioactive waste must be strictly managed, monitoring strengthened, and effective measures taken to prevent the spread of radioactive waste. 7.2 Radioactive waste must be strictly classified and disposed of separately. It is strictly prohibited to transport and store flammable, explosive, perishable and non-radioactive materials together with solid radioactive waste. The transportation of radioactive waste liquid is strictly prohibited. 7.3 Storage and disposal of radioactive waste; open water sources and groundwater should be ensured not to be contaminated. 7.4 Transport of radioactive materials: (including new fuel elements and spent fuel elements) must comply with relevant national regulations. Workers transporting radioactive materials must be familiar with the transportation regulations of radioactive materials, the properties of the radioactive materials being transported, and the necessary protection knowledge. 8 Decommissioning of Nuclear Power Plants
After a nuclear power plant's application for decommissioning is approved, when formulating a decommissioning plan, an environmental impact report must be prepared at the same time, and it can only be implemented after approval by the national environmental protection department.
GB 6249-86
Appendix A
Term definitions
(Supplement)
A. 1. Each nuclear power plant: refers to any plant or station that uses nuclear reactors to generate electricity, including one or several reactors, as well as 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-up, zero-power operation, power operation, and qualified acceptance that are carried out after the completion of the nuclear power plant to meet safety purposes.
A.3 Operation: refers to the entire process of power operation, shutdown, maintenance, testing, refueling and other related work of a nuclear power plant under specified operating conditions.
A. 4 Non-residential area: refers to an area where the nuclear power plant is located. Permanent residents are strictly prohibited in this area. The operating unit of the nuclear power plant exercises effective jurisdiction over this area, including the evacuation of any individuals and property from this area; roads, Railways and waterways can pass through the area, but they must not interfere with the normal operation of the nuclear power plant. In the event of an accident, appropriate and effective arrangements can be made to control traffic to ensure the safety of workers and residents. In non-residential areas, activities unrelated to the operation of nuclear power plants are allowed under appropriate restrictions as long as they do not affect the normal operation of the nuclear power plant or endanger the health and safety of residents. The non-residential area is not required to be circular, and can be determined based on the specific conditions of the plant site such as topography, landform, meteorology, transportation, etc.
A. 5 Restricted area: refers to the area directly adjacent to non-residential areas. Mechanical growth of the population must be limited within restricted areas. Large enterprises, institutions, residential areas, large hospitals or nursing homes, tourist resorts, airports and prisons are not allowed to be built or expanded in this area. A.6 Expected operating events: During the operation of the nuclear power plant, all operating failures that deviate from normal operating conditions are expected to occur from the design. In view of the appropriate considerations in the design, when such an accident occurs, it will not cause the failure of the engineering safety protection system and major damage to the engineering equipment, nor will it cause a large amount of radioactive materials to be released into the environment. A.7·Major accident: During the life of the nuclear power plant, the expected probability of occurrence is not greater than 0.01 to 0.1/reactor·year, and it is an accident that significantly deviates from the normal operating limit conditions. At this time, if the engineering safety protection facilities cannot fully comply with the design requirements, If it acts, it will cause a large amount of radioactive materials to be released into the environment, which may cause the radiation dose to the public to exceed the dose limit specified in 3.1. A.8 Major accident: During the life of the nuclear power plant, an accident that seriously deviates from the normal operating limit conditions is not expected to occur or the probability of occurrence is not greater than 5 × 10-4 ~ 10-2/reactor·year. Important specially designed accidents Engineering safety protection facilities may partially fail, resulting in a large-scale release of radioactive materials into the environment.
A.9 Maximum credible accident: It is the nuclear power plant accident that has the most serious consequences for the environment and is assumed to be used for site evaluation. The probability of its occurrence (<10-^/reactor·year) is extremely small. The maximum credible accidents vary for different types of reactors. For pressurized water reactor nuclear power plants, it refers to the most serious accident in which the reactor core melts on a large scale and radioactive materials are released into the environment. Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Nuclear Energy Technology Institute of Tsinghua University and the China Atomic Energy Research Institute. The main drafters of this standard are Liu Yuanzhong and Jiang Xiwen. The National Environmental Protection Administration is responsible for interpreting this standard.2. When conducting routine environmental radiation monitoring, the data obtained from the pre-operation background survey should be fully utilized, and environmental monitoring should be optimized as much as possible while meeting the needs of environmental assessment. Environmental monitoring focuses on those nuclides and projects that are most harmful to key groups of people. 6.2.3 The environmental medium, 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 a nuclear power plant must monitor all airborne and liquid radioactive effluents. Measurement content should include analysis of total emissions, emission concentrations and major nuclides.
6.4 Accident Environmental Emergency Monitoring
6.4.1 Before the trial operation of a nuclear power plant, the operating unit shall formulate an environmental emergency monitoring plan and submit it to the provincial environmental protection department for filing. Considering the suddenness and particularity of some accidents, emergency monitoring must be flexible and fast. 6.4.2 Environmental emergency monitoring is an important part of the nuclear power plant accident emergency plan. Generally include: monitoring principles, monitoring methods and steps for various types of radiation accidents, monitoring projects, monitoring outlets, leadership of monitoring work, reporting and release methods of monitoring data, etc. .5 | | tt | | GB6249-86 | concentration of toxins) to facilitate evaluation of monitoring results and early decision on whether corresponding actions need to be taken. 6.5·Environmental monitoring must implement a quality assurance system, adopt standard (or unified) methods and procedures, and shall not change without authorization. If changes are necessary, technical demonstration must be passed. 6.6 Provincial environmental protection departments should be responsible for setting up environmental radiation monitoring institutions for nuclear power plants and carrying out monitoring work in accordance with the corresponding requirements of this standard. 7 Storage and transportation of radioactive wastebzxZ.net
7.1 Radioactive waste must be strictly managed, monitoring strengthened, and effective measures taken to prevent the spread of radioactive waste. 7.2 Radioactive waste must be strictly classified and disposed of separately. It is strictly prohibited to transport and store flammable, explosive, perishable and non-radioactive materials together with solid radioactive waste. The transportation of radioactive waste liquid is strictly prohibited. 7.3 Storage and disposal of radioactive waste; open water sources and groundwater should be ensured not to be contaminated. 7.4 Transport of radioactive materials: (including new fuel elements and spent fuel elements) must comply with relevant national regulations. Workers transporting radioactive materials must be familiar with the transportation regulations of radioactive materials, the properties of the radioactive materials being transported, and the necessary protection knowledge. 8 Decommissioning of Nuclear Power Plants
After a nuclear power plant's application for decommissioning is approved, when formulating a decommissioning plan, an environmental impact report must be prepared at the same time, and it can only be implemented after approval by the national environmental protection department.
GB 6249-86
Appendix A
Term definitions
(Supplement)
A. 1. Each nuclear power plant: refers to any plant or station that uses nuclear reactors to generate electricity, including one or several reactors, as well as 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-up, zero-power operation, power operation, and qualified acceptance that are carried out after the completion of the nuclear power plant to meet safety purposes.
A.3 Operation: refers to the entire process of power operation, shutdown, maintenance, testing, refueling and other related work of a nuclear power plant under specified operating conditions.
A. 4 Non-residential area: refers to an area where the nuclear power plant is located. Permanent residents are strictly prohibited in this area. The operating unit of the nuclear power plant exercises effective jurisdiction over this area, including the evacuation of any individuals and property from this area; roads, Railways and waterways can pass through the area, but they must not interfere with the normal operation of the nuclear power plant. In the event of an accident, appropriate and effective arrangements can be made to control traffic to ensure the safety of workers and residents. In non-residential areas, activities unrelated to the operation of nuclear power plants are allowed under appropriate restrictions as long as they do not affect the normal operation of the nuclear power plant or endanger the health and safety of residents. The non-residential area is not required to be circular, and can be determined based on the specific conditions of the plant site such as topography, landform, meteorology, transportation, etc.
A. 5 Restricted area: refers to the area directly adjacent to non-residential areas. Mechanical growth of the population must be limited within the restricted area. Large enterprises, institutions, residential areas, large hospitals or nursing homes, tourist resorts, airports and prisons are not allowed to be built or expanded in this area. A.6 Anticipated operating events: During the operation of the nuclear power plant, all operating failures that deviate from normal operating conditions are expected to occur from the design. In view of the appropriate considerations in the design, when such an accident occurs, it will not cause the failure of the engineering safety protection system and major damage to the engineering equipment, nor will it cause a large amount of radioactive materials to be released into the environment. A.7·Major accident: During the life of the nuclear power plant, the expected probability of occurrence is not greater than 0.01 to 0.1/reactor·year, and it is an accident that significantly deviates from the normal operating limit conditions. At this time, if the engineering safety protection facilities cannot fully comply with the design requirements, If it acts, it will cause a large amount of radioactive materials to be released into the environment, which may cause the radiation dose to the public to exceed the dose limit specified in 3.1. A.8 Major accident: During the life of the nuclear power plant, an accident that seriously deviates from the normal operating limit conditions is not expected to occur or the probability of occurrence is not greater than 5 × 10-4 ~ 10-2/reactor·year. Important specially designed accidents Engineering safety protection facilities may partially fail, resulting in a large-scale release of radioactive materials into the environment.
A.9 Maximum credible accident: It is the nuclear power plant accident that has the most serious consequences for the environment and is assumed to be used for site evaluation. The probability of its occurrence (<10-^/reactor·year) is extremely small. The maximum credible accidents vary for different types of reactors. For pressurized water reactor nuclear power plants, it refers to the most serious accident in which the reactor core melts on a large scale and radioactive materials are released into the environment. Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Nuclear Energy Technology Institute of Tsinghua University and the China Atomic Energy Research Institute. The main drafters of this standard are Liu Yuanzhong and Jiang Xiwen. The National Environmental Protection Administration is responsible for interpreting this standard.2. When conducting routine environmental radiation monitoring, the data obtained from the pre-operation background survey should be fully utilized, and environmental monitoring should be optimized as much as possible while meeting the needs of environmental assessment. Environmental monitoring focuses on those nuclides and projects that are most harmful to key groups of people. 6.2.3 The environmental medium, 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 a nuclear power plant must monitor all airborne and liquid radioactive effluents. Measurement content should include analysis of total emissions, emission concentrations and major nuclides.
6.4 Accident Environmental Emergency Monitoring
6.4.1 Before the trial operation of a nuclear power plant, the operating unit shall formulate an environmental emergency monitoring plan and submit it to the provincial environmental protection department for filing. Considering the suddenness and particularity of some accidents, emergency monitoring must be flexible and fast. 6.4.2 Environmental emergency monitoring is an important part of the nuclear power plant accident emergency plan. Generally include: monitoring principles, monitoring methods and steps for various types of radiation accidents, monitoring projects, monitoring outlets, leadership of monitoring work, reporting and release methods of monitoring data, etc. .5 | | tt | | GB6249-86 | concentration of toxins) to facilitate evaluation of monitoring results and early decision on whether corresponding actions need to be taken. 6.5·Environmental monitoring must implement a quality assurance system, adopt standard (or unified) methods and procedures, and shall not change without authorization. If changes are necessary, technical demonstration must be passed. 6.6 Provincial environmental protection departments should be responsible for setting up environmental radiation monitoring institutions for nuclear power plants and carrying out monitoring work in accordance with the corresponding requirements of this standard. 7 Storage and transportation of radioactive waste
7.1 Radioactive waste must be strictly managed, monitoring strengthened, and effective measures taken to prevent the spread of radioactive waste. 7.2 Radioactive waste must be strictly classified and disposed of separately. It is strictly prohibited to transport and store flammable, explosive, perishable and non-radioactive materials together with solid radioactive waste. The transportation of radioactive waste liquid is strictly prohibited. 7.3 Storage and disposal of radioactive waste; open water sources and groundwater should be ensured not to be contaminated. 7.4 Transport of radioactive materials: (including new fuel elements and spent fuel elements) must comply with relevant national regulations. Workers transporting radioactive materials must be familiar with the transportation regulations of radioactive materials, the properties of the radioactive materials being transported, and the necessary protection knowledge. 8 Decommissioning of Nuclear Power Plants
After a nuclear power plant's application for decommissioning is approved, when formulating a decommissioning plan, an environmental impact report must be prepared at the same time, and it can only be implemented after approval by the national environmental protection department.
GB 6249-86
Appendix A
Term definitions
(Supplement)
A. 1. Each nuclear power plant: refers to any plant or station that uses nuclear reactors to generate electricity, including one or several reactors, as well as 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-up, zero-power operation, power operation, and qualified acceptance that are carried out after the completion of the nuclear power plant to meet safety purposes.
A.3 Operation: refers to the entire process of power operation, shutdown, maintenance, testing, refueling and other related work of a nuclear power plant under specified operating conditions.
A. 4 Non-residential area: refers to an area where the nuclear power plant is located. Permanent residents are strictly prohibited in this area. The operating unit of the nuclear power plant exercises effective jurisdiction over this area, including the evacuation of any individuals and property from this area; roads, Railways and waterways can pass through the area, but they must not interfere with the normal operation of the nuclear power plant. In the event of an accident, appropriate and effective arrangements can be made to control traffic to ensure the safety of workers and residents. In non-residential areas, activities unrelated to the operation of nuclear power plants are allowed under appropriate restrictions as long as they do not affect the normal operation of the nuclear power plant or endanger the health and safety of residents. The non-residential area is not required to be circular, and can be determined based on the specific conditions of the plant site such as topography, landform, meteorology, transportation, etc.
A. 5 Restricted area: refers to the area directly adjacent to non-residential areas. Mechanical growth of the population must be limited within the restricted area. Large enterprises, institutions, residential areas, large hospitals or nursing homes, tourist resorts, airports and prisons are not allowed to be built or expanded in this area. A.6 Expected operating events: During the operation of the nuclear power plant, all operating failures that deviate from normal operating conditions are expected to occur from the design. In view of the appropriate considerations in the design, when such an accident occurs, it will not cause the failure of the engineering safety protection system and major damage to the engineering equipment, nor will it cause a large amount of radioactive materials to be released into the environment. A.7·Major accident: During the life of the nuclear power plant, the expected probability of occurrence is not greater than 0.01 to 0.1/reactor·year, and it is an accident that significantly deviates from the normal operating limit conditions. At this time, if the engineering safety protection facilities cannot fully comply with the design requirements, If it acts, it will cause a large amount of radioactive materials to be released into the environment, which may cause the radiation dose to the public to exceed the dose limit specified in 3.1. A.8 Major accident: During the life of the nuclear power plant, an accident that seriously deviates from the normal operating limit conditions is not expected to occur or the probability of occurrence is not greater than 5×10-4 ~ 10-2/reactor·year. Important specially designed accidents Engineering safety protection facilities may partially fail, resulting in a large-scale release of radioactive materials into the environment.
A.9 Maximum credible accident: It is the nuclear power plant accident that has the most serious consequences for the environment and is assumed to be used for site evaluation. The probability of its occurrence (<10-^/reactor·year) is extremely small. The maximum credible accidents vary for different types of reactors. For pressurized water reactor nuclear power plants, it refers to the most serious accident in which the reactor core melts on a large scale and radioactive materials are released into the environment. Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Nuclear Energy Technology Institute of Tsinghua University and the China Atomic Energy Research Institute. The main drafters of this standard are Liu Yuanzhong and Jiang Xiwen. The National Environmental Protection Administration is responsible for interpreting this standard.2 Trial operation: refers to the loading, physical start-up, zero-power operation, power operation until qualified acceptance that are carried out for safety purposes after the nuclear power plant is completed.
A.3 Operation: refers to the entire process of power operation, shutdown, maintenance, testing, refueling and other related work of a nuclear power plant under specified operating conditions.
A. 4 Non-residential area: refers to an area where the nuclear power plant is located. Permanent residents are strictly prohibited in this area. The operating unit of the nuclear power plant exercises effective jurisdiction over this area, including the evacuation of any individuals and property from this area; roads, Railways and waterways can pass through the area, but they must not interfere with the normal operation of the nuclear power plant. In the event of an accident, appropriate and effective arrangements can be made to control traffic to ensure the safety of workers and residents. In non-residential areas, activities unrelated to the operation of nuclear power plants are allowed under appropriate restrictions as long as they do not affect the normal operation of the nuclear power plant or endanger the health and safety of residents. The non-residential area is not required to be circular, and can be determined based on the specific conditions of the plant site such as topography, landform, meteorology, transportation, etc.
A. 5 Restricted area: refers to the area directly adjacent to non-residential areas. Mechanical growth of the population must be limited within restricted areas. Large enterprises, institutions, residential areas, large hospitals or nursing homes, tourist resorts, airports and prisons are not allowed to be built or expanded in this area. A.6 Expected operating events: During the operation of the nuclear power plant, all operating failures that deviate from normal operating conditions are expected to occur from the design. In view of the appropriate considerations in the design, when such an accident occurs, it will not cause the failure of the engineering safety protection system and major damage to the engineering equipment, nor will it cause a large amount of radioactive materials to be released into the environment. A.7·Major accident: During the life of the nuclear power plant, the expected probability of occurrence is not greater than 0.01 to 0.1/reactor·year, and it is an accident that significantly deviates from the normal operating limit conditions. At this time, if the engineering safety protection facilities cannot fully comply with the design requirements, If it acts, it will cause a large amount of radioactive materials to be released into the environment, which may cause the radiation dose to the public to exceed the dose limit specified in 3.1. A.8 Major accident: During the life of the nuclear power plant, an accident that seriously deviates from the normal operating limit conditions is not expected to occur or the probability of occurrence is not greater than 5×10-4 ~ 10-2/reactor·year. Important specially designed accidents Engineering safety protection facilities may partially fail, resulting in a large-scale release of radioactive materials into the environment.
A.9 Maximum credible accident: It is the nuclear power plant accident that has the most serious consequences for the environment and is assumed to be used for site evaluation. The probability of its occurrence (<10-^/reactor·year) is extremely small. The maximum credible accidents vary for different types of reactors. For pressurized water reactor nuclear power plants, it refers to the most serious accident in which the reactor core melts on a large scale and radioactive materials are released into the environment. Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Nuclear Energy Technology Institute of Tsinghua University and the China Atomic Energy Research Institute. The main drafters of this standard are Liu Yuanzhong and Jiang Xiwen. The National Environmental Protection Administration is responsible for interpreting this standard.2 Trial operation: refers to the loading, physical start-up, zero-power operation, power operation until qualified acceptance that are carried out for safety purposes after the nuclear power plant is completed.
A.3 Operation: refers to the entire process of power operation, shutdown, maintenance, testing, refueling and other related work of a nuclear power plant under specified operating conditions.
A. 4 Non-residential area: refers to an area where the nuclear power plant is located. Permanent residents are strictly prohibited in this area. The operating unit of the nuclear power plant exercises effective jurisdiction over this area, including the evacuation of any individuals and property from this area; roads, Railways and waterways can pass through the area, but they must not interfere with the normal operation of the nuclear power plant. In the event of an accident, appropriate and effective arrangements can be made to control traffic to ensure the safety of workers and residents. In non-residential areas, activities unrelated to the operation of nuclear power plants are allowed under appropriate restrictions as long as they do not affect the normal operation of the nuclear power plant or endanger the health and safety of residents. The non-residential area is not required to be circular, and can be determined based on the specific conditions of the plant site such as topography, landform, meteorology, transportation, etc.
A. 5 Restricted area: refers to the area directly adjacent to non-residential areas. Mechanical growth of the population must be limited within restricted areas. Large enterprises, institutions, residential areas, large hospitals or nursing homes, tourist resorts, airports and prisons are not allowed to be built or expanded in this area. A.6 Expected operating events: During the operation of the nuclear power plant, all operating failures that deviate from normal operating conditions are expected to occur from the design. In view of the appropriate considerations in the design, when such an accident occurs, it will not cause the failure of the engineering safety protection system and major damage to the engineering equipment, nor will it cause a large amount of radioactive materials to be released into the environment. A.7·Major accident: During the life of the nuclear power plant, the expected probability of occurrence is not greater than 0.01 to 0.1/reactor·year, and it is an accident that significantly deviates from the normal operating limit conditions. At this time, if the engineering safety protection facilities cannot fully comply with the design requirements, If it acts, it will cause a large amount of radioactive materials to be released into the environment, which may cause the radiation dose to the public to exceed the dose limit specified in 3.1. A.8 Major accident: During the life of the nuclear power plant, an accident that seriously deviates from the normal operating limit conditions is not expected to occur or the probability of occurrence is not greater than 5 × 10-4 ~ 10-2/reactor·year. Important specially designed accidents Engineering safety protection facilities may partially fail, resulting in a large-scale release of radioactive materials into the environment.
A.9 Maximum credible accident: It is the nuclear power plant accident that has the most serious consequences for the environment and is assumed to be used for site evaluation. The probability of its occurrence (<10-^/reactor·year) is extremely small. The maximum credible accidents vary for different types of reactors. For pressurized water reactor nuclear power plants, it refers to the most serious accident in which the reactor core melts on a large scale and radioactive materials are released into the environment. Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Nuclear Energy Technology Institute of Tsinghua University and the China Atomic Energy Research Institute. The main drafters of this standard are Liu Yuanzhong and Jiang Xiwen. The National Environmental Protection Administration is responsible for interpreting this standard.
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