GB 14586-1993 Technical regulations for environmental management of decommissioning of uranium mining and metallurgical facilities
Some standard content:
UDC621.039.58/.59
Z05
National Standard of the People's Republic of China
GB14586-93
Technical regulations for the environmental management of decommissioning uranium mining and metallurgical facilities ofdecommissioning of uranium mining and milling facilities released on 1993-08-30
National Environmental Protection Agency
National Technology
Supervision Bureau
Implemented on 1994-04-01||tt| |Release
National Standards of the People's Republic of China
Technical regulations for the environmental management ofdecommissioning of uranium mining and milling facilities1 Subject content and scope of application
GB14586 -93
This standard specifies the procedures for decommissioning uranium mining and metallurgical facilities, environmental impact assessment, and general requirements for environmental remediation project design, construction, acceptance, and environmental management.
This standard applies to all decommissioned uranium mining and metallurgical facilities. Decommissioning of non-uranium mining and metallurgical facilities whose radioactive material content exceeds the relevant standards should be implemented accordingly.
2 Reference Standards
GB8703 Radiation Protection Regulations
EJ432 Uranium Mining and Metallurgical Radiation Environmental Monitoring Regulations
3 Terms
3.1 Uranium Mining and Metallurgy Facilities||tt || Sites, equipment, structures, buildings and other facilities engaged in mining, dressing and smelting of a certain scale, including: experimental facilities and places that obtain more than 10kg of uranium from natural ores every year; a.
Pits and wells dug to evaluate uranium deposits,
b.
c.
uranium mines;
d. uranium dressing and smelting plants;
e .Radioactive waste disposal system.
3.2 Decommissioning
The aftermath of uranium mining and metallurgical facilities that have permanently ceased operation to ensure that workers and the public are protected from exposure to residual radioactivity and other possible hazards.
3.3 Waste Disposal
Place solid waste in tailings ponds, waste rock dumps, goafs or other given places, and dispose of them without taking them back. Disposal also includes the controlled discharge of waste gas and wastewater into the environment.
3.4 ??Stabilization
is a planned action to carry out necessary treatment and disposal of waste rock sites and tailings ponds to maintain long-term stability and prevent collapse and loss due to natural forces or other reasons, causing environmental damage pollution accidents. 3.5 Security analysis
The analysis and calculation of risks for an activity to be implemented. 3.6 Waste rock
Materials transported from the mine (well). Including: National Environmental Protection Administration approved on 1993-08-14 and implemented on 1994-04-01
1
a.
Gangue that basically does not contain uranium and needles; ||tt| |b. Low-grade uranium and needle materials with no recycling value. 3.7 Tailings (slag)
Here refers to:
a.
The waste part generated during the mineral processing process;
b. Waste after ore heap leaching;
GB14586—93
Discarded ore sand and slime after uranium leaching in uranium hydrosmelting plant. c.
3.8 Tailings pond (tailings pond)
Specialized facilities to precipitate and store the ore sand and slime in the tailing slurry of the water smelting plant. 3.9 Hydrogen evolution rate
The amount of hydrogen that is precipitated into the air across the unit area interface within the unit time interval. 4. Decommissioning environmental management procedures
The environmental management procedures for decommissioning uranium mining and metallurgical facilities include: a.
b.
Submit an application for decommissioning;
Prepare a governance plan and prepare at the same time Environmental pre-assessment report and approval; e
organization design and implementation;
d.
project completion acceptance;
e.
decommissioning Transfer and long-term custody of the facility.
5 Application and Approval
5.1 Uranium mining and metallurgical facilities should submit a decommissioning application report to the competent authority before final production. The entire decommissioning process should generally be completed within three years. 5.2 Contents of the application report for facility decommissioning:
5.2.1 Provide the name, nature, category, scale, service years, reasons for decommissioning and termination of operation of the decommissioning facilities. 5.2.2 Provide the type, quantity, total radioactive activity, specific radioactive activity, and composition and content of non-radioactive hazardous substances remaining after the facility is decommissioned and decontaminated.
5.2.3 Describe the pollution levels of contaminated structures and production sites. 5.2.4 Based on the compliance status of decommissioned facilities after decontamination and remediation, the discussion will be decommissioning without restrictions or with restricted use. And explain its impact on the environment and conduct safety analysis.
5.3 When submitting an application for facility decommissioning to the competent authority, the facility decommissioning unit shall submit a decommissioning plan and conduct an optimization analysis of the proposed plan.
5.4 After receiving the facility decommissioning application report, the competent department should promptly organize experts to conduct demonstration and approval of the facility decommissioning report and environmental remediation plan.
5.5 Entrust a unit with evaluation qualifications to prepare an environmental impact report, and after preliminary review by the competent department, submit it to the national environmental protection administrative department for approval.
6 Implementation
6.1 Disposal of contaminated equipment
Contaminated equipment, equipment, scrap steel, etc. must be decontaminated until their non-fixed alpha and beta surface radioactive contamination meets the relevant requirements stipulated standard requirements. | |tt | After the pit and wellheads are closed, earth and stone should be thickened and tamped to restore the landform to prevent natural collapse and man-made damage. 2 | | tt | Provide support to control surface collapse and collapse. 6.2.3 For mines where sewage may flow out, effective measures must be taken to prevent environmental pollution. 6.3 Open-pit mining site
6.3.1 The slope of the open-pit mining site should be stabilized to prevent sheeting and landslides. 6.3.2 Fences should be built around areas with large height differences on slopes and cliffs, and permanent no-entry signs should be set up to prevent people and animals from accidentally entering and causing danger. 6.3.3 When the average hydrogen evolution rate on the surface of the open-pit mine ruins exceeds the limit specified in Article A2 of Appendix A, it should be covered with soil and vegetation to reduce the evolution of oxygen.
6.3.4 Surface structures that still fail to meet the requirements of Article 10.1.2 after taking decontamination treatment measures shall be properly disposed of according to radioactive waste requirements. 6.4 In-ground leaching site
The decommissioning treatment of in-ground leaching mining must restore the mine water to acceptable water quality standards and prevent groundwater and surface water from being polluted. 6.5 Dressing and smelting plant
6.5.1 Decommissioning of the dressing and smelting plant, the contaminated ground, floor and building base shall be removed in accordance with the requirements of Article 10.1.2 and Appendix A A3, and these wastes may be buried in the tailings library.
6.5.2 The decommissioned heap leach site must deposit its waste residue in the tailings pond or cover it with suitable materials and dispose of it properly. 6.5.3 Sites contaminated by ore piles must be cleared. If necessary, detectors can be used to detect deeply buried contaminants and removed until the residual pollution on the surface is reduced to an acceptable level. 6.6 Waste rock field
6.6.1 The waste rock field should build rock dams to prevent the loss of waste rock in landslides. 6.6.2 Set up flood control ditches around the waste rock field to prevent flooding from flooding the waste rock field. 6.6.3 When the average precipitation rate on the surface of the waste rock field exceeds the limit specified in Article A2 of Appendix A, it should be covered with soil and vegetation. 6.7 Tailings Pond
S.7.1 The decommissioning and disposal of tailings ponds must keep the hydrogen evolution rate and radiation level below the specified limits, and prevent the dam from collapsing, tailings flowing through, and water seepage from polluting the environment.
6.7.2 When the tailings pond is decommissioned, the depression in the pond should not be retained and can be filled with soil or waste rock. The top of the reservoir must be leveled to a slope of 2% to 4% before being covered with soil and vegetation. On slopes without dams, a slope with a slope of 1:3 to 1:5 should be built, and then stones should be used to build a slope protection with a thickness of 50 to 100 cm. The stabilization requirements must be met and flood drainage and seepage recovery facilities must be retained. 6.7.3. The covering materials for covering tailings should be reasonably selected according to local conditions. The thickness of the covering layer should meet the requirements of A2 in Appendix A and prevent wind erosion, rainwater erosion and tailings loss.
7 Project Completion Acceptance
7.1 After the facility decommissioning project is completed, monitoring should be carried out in accordance with the requirements of EJ432. The purpose of monitoring is: a. Evaluate whether the facility decommissioning project complies with the requirements for radioactive waste disposal promulgated by the state and relevant departments, and verify whether the environmental impact report conforms to the actual situation.
b. Timely discover possible incidents and ways of polluting the environment. c. Provide data for the acceptance and delivery of facilities. 7.2 When submitting the completion report of the facility decommissioning and remediation project, an assessment report on the current status of the facility decommissioning environment should be submitted at the same time and submitted to the relevant competent authorities. 7.3 After receiving the project completion report and environmental status assessment report, the competent department is responsible for organizing experts together with the local government to review and accept the environmental protection measures and project quality for facility decommissioning. 8 Transfer and long-term supervision of decommissioned facilities
8.1 When decommissioning facilities are delivered to the place, the decommissioning unit must hand over the completion report and environmental status assessment report to the receiving unit, and the receiving unit shall conduct supervisory monitoring within one year after receiving it. , when it is confirmed that the decommissioning environmental management standards are met, formal handover procedures will be carried out, and thereafter the receiving unit 3
will be responsible for long-term custody.
GB14586—93
8.2 Decommissioned facilities must be monitored and managed for a long time. The main contents include: waste rock dumps and tailings ponds should be avoided from exposure; |The closed isolation system adopted can effectively prevent groundwater and surface water from being polluted by the migration of radionuclides; b.
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The precipitation of nitrogen in waste rocks and tailings;|| tt||The effects of radioactive dust and radiation. d.
8.3 Environmental monitoring and evaluation reports after the transfer of decommissioned facilities should be prepared by relevant local departments. 9 Quality Assurance
9.1 In order to ensure the long-term stability of the quality of the decommissioning project, while preparing the decommissioning project plan, a quality assurance outline for the decommissioning project should be prepared, requiring the design and construction units to formulate specific measures for quality assurance. 9.2 The design of major decommissioning projects should be entrusted to units with design qualifications. The design must meet the requirements of the approved environmental impact report, and the construction design must be reviewed and approved by the superior authority before construction can begin. 9.3 The application report, decommissioning plan, design, construction, acceptance data, environmental monitoring data, environmental impact assessment report and relevant quality assurance documents for facility decommissioning should be established and archived permanently. 9.4 The design department and the facility decommissioning unit should inspect and supervise the construction quality, and any quality problems found should be resolved within a time limit. 10 Environmental Management Standards
10.1 The radiation dose limits for facility decommissioning must comply with the requirements of GB8703 for the public and the environment. 10.1.1 After decommissioning and final disposal, taking into account the characteristics of the environment and social and economic conditions, the additional exposure dose to surrounding residents from the decommissioned facility should be limited to the lifetime average annual effective dose equivalent limit specified for it. Appropriate portions and leave enough for other possible shots.
10.1.2 After decontamination treatment, the non-fixed α and β radioactive surface contamination degree of contaminated equipment, equipment, buildings, etc. is ≤0.08Bq/cm2, and can be used in general industry after being monitored and approved by the protection department. Use (except in the food industry). 10.1.3 The surface contamination limit for contaminated scrap steel that can be used without restriction after cleaning and decontamination is specified in Appendix A, Article A1. 10.1.4 After final disposal of waste rock dumps, tailings ponds, heap leaching, ground leaching, and open-air ruin sites, the average hydrogen evolution rate limit on the surface is specified in Appendix A, Article A2.
10.1.5 After land decontamination and remediation, the maximum specific activity limit for the nuclide radium-226 in soil at different depths is specified in Article A3 of Appendix A. 10.1.6 When the seepage water from mines, waste rock dumps, tailings ponds, heap leaching, ground leaching, open-air ruins and other facilities after final disposal flows into the environment, the radioactive material will cause the dose to key groups of people in one year Shall comply with the provisions of Article 10.1.1. 10.2 Discharge standards for non-radioactive toxic and hazardous substances shall be implemented in accordance with relevant national regulations. GB14586—93
Appendix A
Environmental management limits
(reference)
Quoted from the International Atomic Energy Agency (IAEA) Safety Series No. 85 and "Radiation Sources" Some environmental management limits of "Principles of Exemption Management and Practice":
After cleaning and decontamination, the alpha and beta radioactive surface contamination of A1-contaminated scrap steel is less than 0.04Bq/cm, and can be used without restrictions. . After final disposal of A2 waste rock dumps, tailings ponds, heap leaching, ground leaching, and open-air ruin sites, the average hydrogen evolution rate on their surfaces should not exceed 0.74Bq/m2.s
A3 After land decontamination and remediation The maximum specific activity requirement of the nuclide radium-226: within any average 100m2 range, the average value in the upper 15cm thick soil layer is 0.18Bq/g; the average value below the 15cm thick soil layer is 0.56Bq/g. For decontamination of A4 habitable buildings, the maximum concentration value of hydrogen progeny (including background) is required to reach 4.16×10-7J/m (0.02WL) as much as possible, but cannot exceed 6.24×10-1J/m3 (0.03WL) . Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Mining and Metallurgical Department of China National Nuclear Corporation and the State-owned No. 272 ??Plant. The main drafters of this standard are Xiao Baomeng, Pan Yingjie, Sang Shiqin, Zeng Zhaoli, and Li Lejie. The National Environmental Protection Administration is responsible for interpreting this standard. 5
08Bq/cm2, it can be used in general industry (except food industry) after being monitored and approved by the protection department. 10.1.3 After cleaning and decontamination, the surface contamination limit of contaminated scrap steel that can be used without restriction is specified in Appendix A, Article A1. 10.1.4 After final disposal of waste rock dumps, tailings ponds, heap leaching, ground leaching, and open-air ruin sites, the average hydrogen evolution rate limit on the surface is specified in Appendix A, Article A2.
10.1.5 After land decontamination and remediation, the maximum specific activity limit for the nuclide radium-226 in soil at different depths is specified in Article A3 of Appendix A. 10.1.6 When the seepage water from mines, waste rock dumps, tailings ponds, heap leaching, ground leaching, open-air ruins and other facilities after final disposal flows into the environment, the radioactive material will cause the dose to key groups of people in one year Shall comply with the provisions of Article 10.1.1. 10.2 Discharge standards for non-radioactive toxic and hazardous substances shall be implemented in accordance with relevant national regulations. GB14586—93
Appendix A
Environmental management limits
(reference)
Quoted from the International Atomic Energy Agency (IAEA) Safety Series No. 85 and "Radiation Sources" Some environmental management limits of "Principles of Exemption Management and Practice":
After cleaning and decontamination, the alpha and beta radioactive surface contamination of A1-contaminated scrap steel is less than 0.04Bq/cm, and can be used without restrictions. . After final disposal of A2 waste rock dumps, tailings ponds, heap leaching, ground leaching, and open-air ruin sites, the average hydrogen evolution rate on their surfaces should not exceed 0.74Bq/m2.s
A3 After land decontamination and remediation The maximum specific activity requirement of the nuclide radium-226: within any average 100m2 range, the average value in the upper 15cm thick soil layer is 0.18Bq/g; the average value below the 15cm thick soil layer is 0.56Bq/g. For decontamination of A4 habitable buildings, the maximum concentration value of hydrogen progeny (including background) is required to reach 4.16×10-7J/m (0.02WL) as much as possible, but cannot exceed 6.24×10-1J/m3 (0.03WL) . Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Mining and Metallurgical Department of China National Nuclear Corporation and the State-owned No. 272 ??Plant. The main drafters of this standard are Xiao Baomeng, Pan Yingjie, Sang Shiqin, Zeng Zhaoli, and Li Lejie. The National Environmental Protection Administration is responsible for interpreting this standard. 5
08Bq/cm2, it can be used in general industry (except food industry) after being monitored and approved by the protection department. 10.1.3 The surface contamination limit for contaminated scrap steel that can be used without restriction after cleaning and decontamination is specified in Appendix A, Article A1. 10.1.4 After final disposal of waste rock dumps, tailings ponds, heap leaching, ground leaching, and open-air ruin sites, the average hydrogen evolution rate limit on the surface is specified in Appendix A, Article A2.
10.1.5 After land decontamination and remediation, the maximum specific activity limit for the nuclide radium-226 in soil at different depths is specified in Article A3 of Appendix A. 10.1.6 When the seepage water from mines, waste rock dumps, tailings ponds, heap leaching, ground leaching, open-air ruins and other facilities after final disposal flows into the environment, the radioactive material will cause the dose to key groups of people in one year Shall comply with the provisions of Article 10.1.1. 10.2 Discharge standards for non-radioactive toxic and hazardous substances shall be implemented in accordance with relevant national regulations. GB14586—93
Appendix A
Environmental management limits
(reference)
Quoted from the International Atomic Energy Agency (IAEA) Safety Series No. 85 and "Radiation Sources" Some environmental management limits of "Principles of Exemption Management and Practice":
After cleaning and decontamination, the alpha and beta radioactive surface contamination of A1-contaminated scrap steel is less than 0.04Bq/cm, and can be used without restrictions. . After final disposal of A2 waste rock dumps, tailings ponds, heap leaching, ground leaching, and open-air ruin sites, the average hydrogen evolution rate on their surfaces should not exceed 0.74Bq/m2.s
A3 After land decontamination and remediation The maximum specific activity requirement of the nuclide radium-226: within any average 100m2 range, the average value in the upper 15cm thick soil layer is 0.18Bq/g; the average value below the 15cm thick soil layer is 0.56Bq/g. For decontamination of A4 habitable buildings, the maximum concentration value of hydrogen progeny (including background) is required to reach 4.16×10-7J/m (0.02WL) as much as possible, but cannot exceed 6.24×10-1J/m3 (0.03WL) . Additional notes:
This standard is proposed by the National Environmental Protection Administration. This standard is drafted by the Mining and Metallurgical Department of China National Nuclear Corporation and the State-owned No. 272 ??Plant. The main drafters of this standard are Xiao Baomeng, Pan Yingjie, Sang Shiqin, Zeng Zhaoli, and Li Lejie. The National Environmental Protection Administration is responsible for interpreting this standard. 5
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