GB 6249-2025 English PDFUS$319.00 · In stock
Delivery: <= 4 days. True-PDF full-copy in English will be manually translated and delivered via email. GB 6249-2025: Regulations for environmental radiation protection of nuclear power plant Status: Valid GB 6249: Historical versions
Basic dataStandard ID: GB 6249-2025 (GB6249-2025)Description (Translated English): Regulations for environmental radiation protection of nuclear power plant Sector / Industry: National Standard Classification of Chinese Standard: F72 Classification of International Standard: 13.280 Word Count Estimation: 16,126 Date of Issue: 2025-01-21 Date of Implementation: 2025-05-01 Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration GB 6249-2011: Regulations for environmental radiation protection of nuclear power plant---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.Regulations for environmental radiation protection of nuclear power plant National Standards of People's Republic of China Replacing GB 6249-86 Nuclear power plant environmental radiation protection regulations Issued on. 2011-02-18 2011-09-01 implementation Ministry of Environmental Protection State Administration of Quality Supervision, Inspection and Quarantine release People's Republic of China Ministry of Environmental Protection announcement No. 21 2011 To implement the "People's Republic of China Environmental Protection Law" and "People's Republic of China Radioactive Pollution Prevention Law," the prevention of pollution, protection of Human health, are now approved "nuclear power plant environmental radiation protection regulations" and other three criteria for the national radioactive contamination control standards by the Ministry And the State Administration of Quality Supervision, Inspection and Quarantine jointly issued. Standard name, numbered as follows. Second, nuclear power plant radioactive liquid effluent discharge technical requirements (GB 14587-2011); Third, low and intermediate level radioactive waste form performance cement cured body (GB 14569.1-2011). According to relevant laws and regulations, these standards have the effect of enforcement. Above standard since September 1, 2011 implementation, while following standards will be abolished. First, nuclear power plant environmental radiation protection regulations (GB 6249-1986); Second, the light water reactor nuclear power plant radioactive waste water system technical requirements (GB 14587-1993); Third, low and intermediate level radioactive waste form performance cement cured body (GB 14569.1-1993). Special announcement. (This announcement already Administration of Quality Supervision, Inspection and Quarantine Ji Zhengkun countersigned) February 18, 2011 Table of ContentsPreface ..iv 1. Scope ..1 2 Normative references ..1 3 Terms and Definitions .1 4 .2 General Environmental Radiation Protection 5 site selection requirements 3 Value and the value of the dose constraint 6 emission control running state .3 7 accident conditions of radiation protection requirements 4 8 effluent discharge effluent monitoring and management ..5 9 Environmental Radiation Monitoring 5 10 solid radioactive waste management .6 Decommissioning of nuclear power plants 11 6 ivForewordTo implement the "People's Republic of China Environmental Protection Law" and "People's Republic of China Radioactive Pollution Prevention Law," prevention of radioactive pollution, Improve the quality of the environment, protecting human health, the development of this standard. This standard specifies a fixed land-based nuclear power plant site selection, design, construction, operation, decommissioning, and other expansion and modification of environmental radiation Protection requirements. This standard is the "nuclear power plant environmental radiation protection regulations" (GB 6249-86) amendments. This standard was first published in 1986, the original standard was drafted by Tsinghua University and the China Institute of Atomic Energy. This is the first revision. The main content of the amendments are as follows. - Taxonomic revision of the original standard design basis accident is rare accident and two types of limits, and gives the definition of rare incidents and Frequency limit of the accident; - The site of the original standard approval stage accident maximum credible accident source term release to modify the location postulated accidents, and gives the corresponding Dose acceptance criteria; - This standard type of reactor, according to the power to exercise control emissions of radioactive effluents years; for LWRs, clearly defined liquid radioactive Of the total annual emissions of effluent control value of 14C, and an increase in light water reactors and heavy water reactors of airborne radioactive effluent control value 14C and tritium; - This standard specifies the respective coastal and inland site site density control value trough at the discharge outlet. From the date of implementation of this standard, "nuclear power plant environmental radiation protection regulations" (GB 6249-86) abolished. This standard by the Ministry of Environmental Protection Science, Technology, Nuclear Safety Management Division organizations to develop. Drafting of this standard. Suzhou Institute of Thermal Engineering Co., Ltd., the Ministry of Environmental Protection of Nuclear and Radiation Safety Center. This standard MEP January 25, 2011 for approval. This standard since September 1, 2011 implementation. The standard explanation by the Ministry of Environmental Protection. Nuclear power plant environmental radiation protection regulations1 ScopeThis standard specifies a fixed land-based nuclear power plant site selection, design, construction, operation, decommissioning, and other expansion and modification of environmental radiation Protection requirements. This standard applies to the use of light water reactors or CANDU nuclear power facilities onshore fixed, the other reactor type nuclear power plant can be implemented by reference.2 Normative referencesThe standard content of the following documents cited in the articles. For undated references, the effective version applies to this standard. GB 18871-2002 ionizing radiation protection and safety of radiation sources basic standards3 Terms and DefinitionsThe following terms and definitions apply to this standard. 3.1 Non-residential exclusion area Refers to the reactor within a certain range around the region, the region has a non-permanent residents, from the nuclear power plant units operating in the region line The effective control, including any personal property and the withdrawal from the region; roads, railways, waterways can pass through the area, but must not interfere with nuclear The normal operation of the power plant; in case of an accident, they can make appropriate and effective arrangements for controlling traffic, in order to ensure that staff and residents Safety. In the non-residential area, with the plant operating related activities, provided they do not affect the normal operation of nuclear power plants and health-threatening residents Health and safety are allowed. 3.2 Planning restricted zone planning restricted area Refers to a non-residential area directly adjacent to the area by the provincial people's government confirmed. Planning restrictions must be limited to the area of mechanical growth of the population of New and expansion projects in the region should be guided or restrictions to consider taking appropriate protective measures under the state of emergency may Sex. 3.3 Multi-site heap multi-reactor site It refers to a site with more than two reactors and the distance between each reactor is less than 5 km of the nuclear power plant site. 3.4 Dose constraints dose constraint A limitation on the source of the personal dose may cause pre-determined, it is related to the source, it was used as the source under consideration for protection and safety The most full-time constraint optimization. For public exposure, the dose constraint is a member of the public annual dose from a planned to run a controlled source of accepted It limits. Dose constraint referred to any critical group in anticipation of the process of controlled source running through all exposure pathways accepted The sum of the annual dose. Dose constraint for each source shall ensure that doses to critical groups of from all controlled sources and kept in dose limits Fewer. 3.5 Environmentally sensitive area environmental sensitive area Refers to the region has need of special protection areas, ecologically sensitive and fragile area of social concern and area features. 3.6 Radioactive effluent radioactive effluents Under normal circumstances, nuclear power plants in the form of gases, aerosols, dust and liquids into the environment and be diluted and dispersed in the environment Radioactive substances. 3.7 Running state operational states Normal operation and anticipated operational occurrences referred to two types of states. Normal operation means within operational limits and conditions of the plant in a predetermined range Operation. Anticipated operational occurrences refers to the operating lifetime of the plant is expected to occur at least once during the operation deviates from a variety of normal operation; Because the design has to take appropriate measures, such incidents will not cause serious damage to items important to safety, and that does not lead to accident conditions. 3.8 Accident conditions accident conditions Than anticipated operational occurrences more serious conditions, including design basis accidents and severe accidents. 3.9 Design basis accident design basis accidents Nuclear power plants according to the design guidelines for the design and take those accident conditions specific measures in the design and ensure fuel Damage and release of radioactive material does not exceed the value of control accidents. Design basis accidents and limit accidents including rare accident categories. 3.10 Rare accident infrequent accidents Very low frequency of accidents (estimated to be 10-4 to 10-2/reactor-years) occurred in the operating lifetime of the plant, such incidents may result in a small amount of fuel Element material damage, but does not result in a single rare accident reactor coolant containment barrier system or loss of function. 3.11 Limit accident limiting accidents Very low frequency of accidents (estimated to be 10-6 to 10-4/reactor-years) occurred in the operating lifetime of the plant, the consequences of such incidents included large The possibility of the amount of radioactive material released, but a single accident limit will not cause accidents desired response system (including the emergency core cooling system And containment) loss of function. 3.12 Location hypothetical accident postulated siting accident The accident site is only available to the approval stage, as the site to determine the non-residential areas, planning restrictions boundary basis. For water-cooled reactors, The accident should generally be considered a full core melt, or else should be fully valid argument. 3.13 Severe accident severe accidents Severity exceeding design basis accident and causing significant core degradation accident conditions.4 General Environmental Radiation Protection4.1 All nuclear power plant led to the practice of public radiation exposure should be consistent with the principles of the legitimacy of radiation protection practices. 4.2 After taking into account economic and social factors, the size of the individual radiation dose, the number of irradiated and irradiated possibilities remain In as far as low as reasonably achievable. 4.3 irradiation dose limitations and potential dangers restrictions, in accordance with the relevant provisions of GB 18871-2002 for. a) In the operating state conditions, deal with individual nuclear power plants may be subject to public radiation dose limit imposed; Personal risk b) respond to potential exposure hazard of individuals subject to restrictions so that all potential exposure due to the normal radiation dose limit The health hazards of the corresponding value of the same order level. 4.4 For a multi-site heap each nuclear power plant environmental radiation protection should implement a uniform application of radioactive effluent emissions, effluent Material management and environmental monitoring and emergency management. 4.5 nuclear power plant shall take all reasonably achievable measures for the implementation of radioactive waste management, waste minimization, including the nuclear power plant Plant design, operation and decommissioning of the entire process. Waste management should be used to implement best available technology for all gas, liquid and solid waste streams And optimize the overall control scheme for waste from generation to disposal to optimize the entire process, and strive to get the best environmental, economic and social benefits, And contribute to sustainable development.5 site selection requirements5.1 In the process of the nuclear power plant site selection must consider the Area site of urban or industrial development planning, land use planning, Water environment function zoning compatibility between, in particular, should avoid drinking water source protection areas, nature reserves, scenic spots and other environmentally sensitive Area. 5.2 Evaluation of the suitability of nuclear power plant site, you must consider the site geology Area, earthquakes, hydrology, meteorology, traffic Environmental characteristics of transport around the site, use of land and water around the site population density and distribution, must be considered within the Area site The impact of natural or man-made external events can occur on the safety of nuclear power plants, nuclear power plants must demonstrate full discharge of radioactive effluents (Especially accident conditions effluent discharge), thermal and chemical discharge effluent emissions impact on the environment and local ecosystems and the public, will be Shall take into account the new fuel, spent fuel and radioactive solid waste storage and transport. 5.3 In the nuclear power plant site selection, should be combined with the current situation and the expected development of the environment around the site features, and demonstrate the implementation of off-site emergency plans feasibility. 5.4 Nuclear Power Plant site selection, should be considered the safe disposal of radioactive waste nuclear power plant. 5.5 In the plant site selection process, consideration should be given to environmental protection and radiation safety factor, by comparison, the candidate site optimization analysis. 5.6 must be set to a non-residential area and planning restricted zone around the nuclear power plant. Non-residential areas and planning restrictions should be considered to determine the boundaries of the site Radiological consequences of hypothetical accidents. Does not require non-residential area is circular, according to the specific conditions of the site's topography, weather, traffic, etc. OK, but non-residential zone boundary from the reactor distance of not less than 500 m; planning restricted zone radius of not less than 5 km. 5.7 nuclear power plants should be built in relatively low population density, relatively far away from the big city locations. There should be the planning restricted zone 1 Million or more towns, there should be no more than 10 million people in the urban site within a radius of 10 km range. 5.8 For a multi-stack site, should consider the characteristics of each reactor to determine the non-residential area and planning restricted zone boundary. 5.9 In the event of hypothetical accident location, considering the conservative atmospheric dispersion conditions, any person in any non-residential area on the border after the accident Italian immersion within 2 h by external radiation and inhalation of smoke exposure pathways within the effective dose received is not greater than 0.25 Sv; planning restrictions boundary Any person on the entire duration of the accident (desirable 30 d) an effective amount of the above two exposure pathways shall not exceed the accepted 0.25 Sv. Throughout the duration of the accident site within a radius of 80 km range by the above two groups of public exposure pathways acceptable set Body effective dose should be less than 2 × 104 man · Sv. Value and the value of the dose constraint 6 emission control running state All effective dose of any nuclear power plant site stack 6.1 release of radioactive material to the environment to the public caused by any individual, each year must Less than 0.25 mSv dose constraint value. Nuclear power plant operating organization should be based on the approval of the regulatory authorities of the dose constraint value, were developed airborne radioactive effluents and liquid radioactive Dose administration effluent target. 6.2 per reactor nuclear power plant must exercise control emissions of radioactive effluents years, for 3 000 MW thermal power reactors, which Control values are shown in Table 1 and Table 2. Table 1 airborne radioactive effluents Control Unit. Bq/a HWR LWR Inert gas 6 × 1014 Iodine 2 × 1010 Particles (half-life ≥8 d) 5 × 1010 14C 7 × 1011 1.6 × 1012 Tritium 1.5 × 1013 4.5 × 1014 Table 2 liquid radioactive effluents Control Unit. Bq/a HWR LWR Tritium 7.5 × 1013 3.5 × 1014 14C 1.5 × 1011 2 × 1011 (except tritium outside) The remaining nuclides 5.0 × 1010 For thermal power is greater than 6.3 or less than 3 000 MW reactors should be adjusted in accordance with the provisions of 6.2 according to its power. 6.4 for the same type of multiple stack pile site, the total annual emissions of all the units should be controlled within 6.2 4 times the specified value. For different heap Multiple stack-type site, the total annual emissions of all units of the control value by the regulatory authorities for approval. 6.5 radioactive emissions from nuclear power plants designed to target not exceeding the 6.2, 6.3 and 6.4 to determine the annual emissions control values. The operating organization should For the nuclear power plant site environmental characteristics and radioactive waste treatment technology level, follow the principles as low as reasonably achievable, to trial Authorities to apply or periodic review (to apply for the first time before loading, after the review once every five years) of radioactive effluent emissions. apply Radioactive effluent radioactive emissions shall not exceed the target emissions designed and approved by the regulatory authorities and implementation. Total annual emissions of 6.6 nuclear power plant shall be quarterly and monthly control, the total amount of emissions for each quarter shall not exceed the approved total annual emissions of 1/2 of total emissions of each month shall not exceed the total annual emissions approved by 1/5. If exceeded, it must quickly identify the causes and take effective Measures. 6.7 nuclear power plant liquid radioactive effluent must discharge trough manner, liquid radioactive effluent radioactive emission concentration control should be implemented System, and the concentration values should be based on the best available control technology, combined with site conditions and to optimize the operating experience feedback, and report to the approval of the regulatory authorities. 6.8 For coastal site, at the outlet of the trough discharge of radioactive effluents, in addition to tritium and other radionuclides 14C outside concentration should not exceed 1 000 Bq/L; for inland site, at the outlet of the trough discharge of radioactive effluents, in addition to tritium and other radionuclides 14C outside concentration should not Chaoguo 100 Bq/L, and to ensure that the discharge port 1 km downstream of the receiving water bodies β radioactivity does not exceed 1 Bq/L, tritium concentration does not exceed 100 Bq/L. If the concentration exceeds the above requirements, the operating organization prior to discharge must be approved by the regulatory......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB 6249-2025_English be delivered?Answer: Upon your order, we will start to translate GB 6249-2025_English as soon as possible, and keep you informed of the progress. The lead time is typically 2 ~ 4 working days. The lengthier the document the longer the lead time.Question 2: Can I share the purchased PDF of GB 6249-2025_English with my colleagues?Answer: Yes. The purchased PDF of GB 6249-2025_English will be deemed to be sold to your employer/organization who actually pays for it, including your colleagues and your employer's intranet.Question 3: Does the price include tax/VAT?Answer: Yes. 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