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GB 14585-1993 Technical regulations for the safety management of radioactive waste from uranium and thorium mining and metallurgy

Basic Information

Standard: GB 14585-1993

tandard name: Technical regulations for the safety management of radioactive waste from uranium and thorium mining and metallurgy

Standard category:National Standard (GB)

state:in force

release date:1993-08-14

Implementation date:1994-04-01

standard classification number

Standard ICS number:Energy and Heat Transfer Engineering>>Nuclear Energy Engineering>>27.120.30 Fissile Materials

Standard Classification Number:Environmental Protection>>Environmental Protection Comprehensive>>Z05 Pollution Control Technical Specifications

associated standards

Procurement status:IAEA 85-1987 NO

Publication information

publishing house:China Standard Press

other information

Release date:1993-08-30

Review date:2004-10-14

Drafting unit:China National Nuclear Corporation

Focal point unit:State Environmental Protection Administration

Publishing department:State Environmental Protection Administration State Technical Supervision Bureau

competent authority:State Environmental Protection Administration

Introduction to standards:

This standard specifies the principles and requirements for the safety management and control of radioactive waste generated during the mining and processing of uranium and thorium ores. It also specifies general requirements for the design, operation, and decommissioning of waste management facilities. This standard applies to the management of radioactive waste generated during the operation and decommissioning of all newly built, reconstructed, and expanded uranium and thorium mining and metallurgical facilities. Reference should also be made to the management of radioactive waste from in-service uranium and thorium mining and metallurgical facilities and the management of waste generated from non-uranium and thorium mining and metallurgical operations with radionuclide content exceeding the relevant standards. GB 14585-1993 Technical Regulations on the Safety Management of Radioactive Waste from Uranium and Thorium Mining and Metallurgy GB14585-1993 Standard download and decompression password: www.bzxz.net

Some standard content:

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National Standards of the People's Republic of China
Uranium, Needle Mining and Metallurgical Radioactive Waste
Technical Regulations on Safety Management
Regulations lor safe msinagement olradioactive wistes froui the minlngand mtlling of uranium and thorium oresGB 14585-93
This standard refers to the IAEA Safety Series No. 85 (IAEA, Safety Series No: 85) "Ore Mining, Lease, Dressing and Smelting" "Safe Disposal of Magnets" Part 1 "Practical Provisions (1987 Edition). 1 Main content and scope of application
This standard specifies the radioactive waste generated during the mining and treatment of tong and needle mines This standard also specifies the general requirements for the design, operation, and decommissioning of waste management facilities. This standard applies to radioactivity generated during the operation and decommissioning of all newly built, renovated, expanded, and reused mining and metallurgical facilities. Management of waste. For the management of radioactive materials in active mining and metallurgical facilities and the management of wastes generated from non-corrosion and needle mining operations, the content of radionuclides exceeding the relevant standards should also be referred to. Implementation. 2 Reference standards
GB 8703 Radiation Protection Regulations
3 Terminology
3. 1 Chain, needle mining and smelting radioactive waste
In, Du mine exploration, mining, Waste containing radioactive substances generated during processes such as smelting and decommissioning. 3. 2 Waste management
Uranium and needle mining radioactive waste treatment, processing, transportation, storage and disposal. Administrative management and business activities. 3.3 Decommissioning
All the work required to make the tongs, needle mining and metallurgical facilities or material management facilities withdraw from use in a planned manner. 3.4 Waste rock | | tt | | Circle rock and off-surface ores with no utilization value generated during the mining process. 3.5 Effluent
Fluid (liquid or gas) discharged into the environment. This fluid may contain solid particles. 3.6 Tailings
The parent rock precipitates with very small particles formed during the extraction of uranium or ore. The tailings of uranium and needle dressing smelting plants are composed of the following two main parts:
). Mine slime -
- The lighter and finer particles (micron and sub-micron particles) in the tailings are composed of clay and other small particles,
Guohao Environmental Protection Bureau.1993-08-14 approved the implementation on 1994-04-01
1
. . Crown Sand—Heavier, larger particles. 37 Dimensions
GB14585-93
Zheng Man collects the ore mined or the ore according to the grade, and collects the liquid. The process of collecting valuable chain metals from the country. 3.8
Use the extracted mineral material to insert the extracted mineral material into the body and collect the extracted liquid. The craftsmanship of valuable Jinpeng is used to avoid marrow.
39 Control release
according to the technology and best value approved by the supervisor. It is recommended that substances containing radionuclides be placed in controlled environments. 3 10 variable management investment increase
Received. Transporting things and dealing with difficulties. processing. Various systems for storing and handling stored or processed materials. 3. 11-degree physical isolation
isolates radioactive substances from the outside world in an effective way to prevent radionuclides from expanding into the environment, or can only be achieved in some way to an acceptable level xenogeneic release of reproductive rate.
3 12 No rate
A special formula system specially built for the purpose of restocking or handling dense minerals. 3.13 Waste rock dump
A specially constructed dam system is required for the storage or handling of measuring stones. 3-14 Dam
Guangguangku and Dushiyang are sugar structures built to protect the testicular waste collectors. 3. 15 Initialization
Various possible measures to prevent crown minerals, stones or other visible objects from causing sensitivity due to natural forces or other forces. 4 Sugar, mineralization and metallurgy radioactivity material control
4.1 Before the operation of paving, mining and processing and smelting facilities, each stage of the entire process (exploration, mining, processing and decommissioning) must be analyzed , evaluate the waste generated by each process and its radioactive contamination impact. 4.2·During the mining and treatment period of the chain and du mines. Measures must be taken to minimize the amount of waste generated and to control the release of radioactive materials from liquid and gaseous effluents into the environment. It is necessary to ensure that the virtual objects are under appropriate control, and the spillage of waste rock and tailing mines is strictly prohibited; to control the release of oxygen and radioactive dust into the atmosphere: to control the contamination of surface water and groundwater by radionuclides and other radionuclides, and to control the Solid waste is polluted by overflowing and pollutes surface water and groundwater. 4. 3. After the operation is stopped, during the decommissioning period and after, the management and control of trapped waste must be maintained, the radioactive hazards of waste rock and tailings must be controlled, and the oxygen and protons released by waste rock and mines must be controlled. The diffusion of radionuclides in the atmosphere prevents radionuclides and other radionuclides from entering surface water and groundwater through any possible means.
4.4 Radioactive wastes from mining and metallurgy contain long-lived radionuclides. Its release to the environment from final disposal tailings ponds and waste rock sites must be controlled, and various long-term natural processes (such as weathering, water overflow, changes in river flow direction, earthquakes, etc.), as well as human activities (such as engaging in construction or agricultural production, etc.) on the tailings ponds and waste rock dumps after final disposal, and this effect should be eliminated or minimized as much as possible. Auxiliary radiation protection quality principles and general basic requirements
5.1 In the practice of radioactive material management in tongs, needle mining and metallurgy, the relevant radiation protection principles of GB 8703 must be followed, that is, the legitimacy of practice, optimization of radiation protection and personal dosing Limits.
5.2 When considering the long-term impact of the amount of radioactive materials disposed of in mining and metallurgy, requirements should be made for the dose levels that individuals may be exposed to in the future. 5.3 Due to the tailings pond and radioactive waste after final disposal The field will be damaged by natural processes and human activities, and the impact of such probabilistic events on the sound field should be considered
.2
6 Design of waste storage facilities
GB. 14585-93
6. 1 It must be ensured that the design of radioactive waste management facilities in towns and mines meets the requirements of this standard and other requirements specified by the relevant competent authorities, as well as the dose equivalent limits specified in GB 8703 for corresponding situations. Value requirements. 6. 2 Correct design must include:
information. Select a suitable site. The selection of the site should be based on various social, economic and practical conditions, and strive to achieve the desired results. The factors to be considered in site selection include: meteorology, hydrology (including Qishui) topography, land beauty, geology and location, mineral resources, population distribution and land use, animal and plant distribution, shelter The ease of disposal and permanent disposal of the waste, as well as the long-term stability and requirements of the waste
b. Complete a safety analysis report and environmental impact report, and take appropriate radiation protection optimization measures. , in order to limit individual effective dose equivalents and reduce collective effective dose equivalents. These measures include minimizing exposed rock and tailings surface areas throughout the operation of the facility and after decommissioning, and using appropriate containment isolation systems to control seepage. Prevent the pollution of groundwater and surface water caused by the migration of radionuclides, take appropriate transportation measures, prevent the pollution caused by the pollution and radioactive dust precipitated from rock and tailings, and formulate appropriate transportation and disposal plans etc. 6.3 Environmental impact assessment and safety analysis reports in facility design must demonstrate with sufficient credibility:The proposed amount of construction will have acceptable impacts on human health and environmental safety. 7 Collection, storage and treatment of waste
7. 1 The plans and procedures required for the collection, transportation, treatment, storage and final volume of all waste must be developed before the waste management facility is put into operation. , and must be approved by the relevant competent authorities before implementing these plans and procedures. 7. 2 All materials generated during operation, construction, mining, smelting, waste treatment and disposal must be collected and sold in accordance with the requirements of these regulations and the specific requirements of the relevant competent authorities for the site. 8. Operation of waste management facilities
8. 1. The operation of waste management facilities must be carried out in accordance with the design objectives of the operating unit and the requirements of the relevant main sales departments. 8. 2 The operation of waste management facilities must meet or have the following conditions or regulations: complete operating procedures for operation, maintenance and monitoring, and operation, maintenance and monitoring personnel must be trained and qualified: b.
The waste management system and each unit must be fully supervised and maintained, and there must be a quality assurance department for preparation and maintenance. c)
d.
Remove personnel who need to enter the site and remove them from the site Materials shall be restricted, and facility operation inspection reports, monitoring results and abnormal accident reports shall be submitted to the relevant competent authorities. e
9 Decommissioning of Mining, Smelting Facilities and Waste Management Facilities 9. 1. When designing facilities, a decommissioning outline and financial guarantee for each facility on the site must be proposed and approved by the relevant competent authorities. 9. 2 Before a facility is decommissioned, a detailed decommissioning plan must be prepared and approved by the relevant competent authorities. 9.3 The decommissioning plan must comply with the requirements of the relevant competent authorities and must provide for the following matters:. Safe disposal of abandoned buildings and mine working areas, decontamination of decommissioned waste disposal areas to acceptable levels, b.
Disposal of sources of contamination and contaminated materials,
c
d. , Stabilized disposal of waste rock sites, heap leach fields and tailings ponds; e. ·Raising of retirement funds.
9.4, When decommissioning mining, smelting and waste management facilities. For the purposes of personnel health, safety and environmental protection, the following measures need to be taken:. Keep facilities in a safe and stable state, 3
b.
c.
GB 14585-93
to ensure that the amount of precipitation and release of radioactive substances and other pollutants is satisfied GB.8703 and other relevant national regulations require that signs must be set up or adequate measures must be taken to prevent residents from entering the pollution rack area, and the use of tailings and waste rocks for civilian purposes is strictly prohibited. 10Monitoring, supervision and maintenance
10. 1 In order to ensure that the requirements of this regulation and other requirements specified by the relevant competent authorities are met, the operating unit must complete the material management in the entire operation and decommissioning period in the possible manner Monitoring, supervision and maintenance of equipment. 10 2 The task of monitoring and supervision during operation, operation, decommissioning and afterward is to check whether the regulations, standards and radioactive material handling requirements issued by the environmental protection and relevant competent authorities are complied with, and to evaluate the personal and radioactive materials left behind by the facility. Provide data for collective dose; test the role and effect of engineering and process design and technical measures, test the correctness of the model used in the design, d
indicate whether the recognized emissions should be restored and re-determined to determine whether an option is needed Special investigation.
Discover unexpected environmental hazards in a timely manner and inspect the physical status and integrity of waste management facilities so that they can be repaired if necessary. Collect information. Conduct pre-evaluation, current situation evaluation and accident evaluation according to sales requirements. 10 3 After the final disposal of decommissioning, within the amount of time specified by the relevant competent authorities, when the requirements of the relevant regulations are met and the acceptance is passed, it will be transferred to the local competent authorities for management. | | tt | 11.2 The relevant competent authorities must promptly review and approve the submitted plans and verification documentation. 11.3 The operating unit must accept the supervision and inspection of the property management facilities by the relevant main sales department. Additional notes;
This standard is proposed by the National Environmental Protection Bureau. This standard was developed by the Mining and Metallurgical Department of China National Nuclear Corporation and the Nuclear Industry Standardization Institute. The main drafters of this standard are Liu Guangfa, Qing Yingjie, and Li Qijie. This standard is interpreted by the Weijia Environmental Protection Department.
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