GB 14588-1993 Technical regulations for environmental management of reactor decommissioning
Some standard content:
UDC621.039.583
Z 05
National Standard of the People's Republic of China
GB14588-93
Technical regulations for environmental management of reactor decommissioning| |tt||Released on 1993-08-30
National Basketball BureauwwW.bzxz.Net
Implemented on 1994-04-01
Released
National Standard of the People's Republic of China|| tt||Technical regulations for environmental management of reactor decommissioning
Technical regulatioas for environmental management of reactor decommissioning Subject content and scope of application
This standard specifies the environmental management principles, procedures and requirements for reactor decommissioning. This standard applies to production reactors and research and test reactors. ? Reference standards
GB3095 Atmospheric Environmental Quality Standard
GB3096
Urban Area Environmental Noise Standard
GB3838
Surface Water Environmental Quality Standard
GB6249
GB8703
GB9132
GB9133
Nuclear power plant environmental radiation protection regulations
Radiation protection regulations
Low and medium level radioactive solid waste Radioactive waste classification standards for shallow formation disposal regulations
GB11215
GB11806
GB11850
GB11928
GB12711
GB13367
Nuclear General Provisions for Radiation Environmental Quality Assessment
Provisions for the Safe Transport of Radioactive Materials
Provisions for Radiation Protection in Reactor Decommissioning
Provisions for the Temporary Storage of Low and Intermediate Level Radioactive Solid Wastes Safety Packaging of Low and Intermediate Level Radioactive Solid Wastes Standard Radiation Sources and Practices Exemption Management Principles
GBJ4 Industrial "Three Wastes" Emission Trial Standard
3 Terminology
3.1 Decommissioning
GB14588-93
In Nuclear After the facility's service period expires, or after the nuclear facility is shut down in advance due to changes in plans, accidents, etc., in order to ensure that workers and the public are not harmed by remaining radioactive materials and other potential dangers in the nuclear facility, it is necessary to implement the necessary measures in a planned manner The process of taking measures to safely and permanently remove nuclear facilities from service.
3.2 Decommissioning level
The actual state reached by the decommissioning of nuclear facilities, the corresponding monitoring requirements and the sign of the site's availability. There are usually three basic types: 2. First-level decommissioning involves the supervised sealing of nuclear facilities; b. Second-level decommissioning involves dismantling, cleaning or decontaminating components and facilities that are easily dismantled and no longer needed. The acceptance level is such that this part of the facilities and sites can meet the standards for unrestricted reuse, and the remaining nuclear facilities should be sealed and sealed under supervision, and the relevant sites can be opened with restrictions,
National Environmental Protection Administration 1993 -08-14 approved 1994-04-01 implementation
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c. Level three decommissioning - dismantle all nuclear facilities one by one, or partially dismantle them, so that contaminated nuclear The facilities must be decontaminated to an acceptable level so that all facilities and sites can meet unrestricted reuse standards. 3.3 Unrestricted reuse
Equipment, materials, factories or decommissioned nuclear facilities. A site whose radioactivity is sufficiently low or has been decontaminated and cleaned to an acceptable level such that the health of any individual or group of persons will not be affected by its reuse, Therefore, their reuse does not need to be restricted.
3.4 ??Decommissioning operations
Various measures and operations implemented for the decommissioning of nuclear facilities. 3.5 Legacy nuclear facilities
refers to the remaining nuclear facilities retained at the original site after the completion of non-level three recovery operations. 3.6 Waste below low-level radioactivity
Waste whose radioactive specific activity is between the lower limit of low-level radioactive materials and the waste exemption management limit. 4 General requirements
4.1 Reactor decommissioning must comply with the following radiation protection principles: legitimacy of practice, radiation protection sensitivity optimization and dose limits. 4.2 The procedures and technical requirements for reactor decommissioning environmental management must comply with relevant national regulations and standards. 4.3 Before the reactor is decommissioned, effective environmental protection facilities and measures should be prepared to ensure the safety of the public and the environment. 4.4 Radioactive waste and other hazardous waste generated from reactor decommissioning should be properly treated and disposed of in accordance with the requirements of relevant national standards.
4.5 A quality assurance system for reactor decommissioning environmental management should be established. 4.6 During reactor decommissioning, corresponding treatment plans should be developed for accidents that may occur and affect environmental safety. 5 Environmental Management Procedures
5.1 Before the decommissioning of the reactor, the reactor operating unit shall submit a "Preliminary Environmental Impact Report for Reactor Decommissioning" to the national environmental protection department and the competent authority.
5.2 There should be a special procedure for reactor decommissioning The design must be reviewed and approved by the competent authority. The decommissioning design must include safety measures and facilities to ensure public safety and environmental safety; if the "three wastes" treatment and environmental monitoring facilities during operation have failed, or are not sufficient to ensure the safety during decommissioning. Environmental safety. Necessary facilities should be added and designed accordingly. 5.3 During the decommissioning process, the reactor operating unit should regularly submit the "Reactor Decommissioning Implementation Report" to the competent authority. 5.4 After the decommissioning work is completed, the reactor operating unit should submit it to the national environmental protection department. The "Reactor Decommissioning Completion Report" and the "Reactor Decommissioning Final Environmental Impact Report" are submitted to the competent department. The decommissioning work can only be completed after review and acceptance. 5.5 The reactor operating unit shall be fully responsible for the environmental safety work during the entire decommissioning process. 6 Implementation Standards
6.1 The dose equivalent to members of the public during the reactor decommissioning process shall comply with the provisions of Article 3.2 of GB11850 under normal operating conditions. , under accident conditions, it should comply with the provisions in Article 4.3 of GB6249 when a major accident occurs. 6.2 Radioactive effluents discharged to the environment during the decommissioning process of the reactor should comply with the provisions of Articles 4.3 and 4.4 of GB8703. 6.3 Radioactive materials or waste transported out of the factory during the reactor decommissioning process should be packaged and transported in accordance with the regulations of GB11806. 6.4 When non-radioactive pollutants are discharged into the environment during reactor decommissioning, they should comply with the regulations of GB3095, GB3838, GBJ4 and GB3096.
6.5 The treatment and disposal of radioactive waste during reactor decommissioning should comply with the regulations of GB9133; GB9132. 6.6 When the decommissioned equipment, components and materials of the reactor meet the requirements of Appendix B of GB13367, they are allowed to be reprocessed for reuse or used directly.
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6.7 The radioactive surface contamination levels on the walls, floors, ceilings, doors and windows of the reactor decommissioning plant comply with the requirements of Table B2 of Appendix B of GB13367 and there is no For other radioactive objects, the factory building is allowed to be reused without restrictions, and the factory site can be opened without restrictions. 7 Requirements for technical documents during decommissioning
7.1 The "Preliminary Environmental Impact Report for Reactor Decommissioning" should at least include the following content: a.
Describe the natural environment and social environment of the plant site, briefly Describe the environmental quality during reactor operation, b.
Briefly describe the overview of the decommissioned reactor and its auxiliary projects; c.
d.
Briefly describe the comparison of decommissioning options and briefly describe the recommendations The main operational contents of the decommissioning plan, e.
Describe the type, quantity, main nuclides, specific activity and total activity, distribution and radioactive activity over time of the radioactive materials accumulated after the reactor is finally shut down. changes,
proposes solutions for the treatment, transportation, storage and disposal of decommissioning waste; f.
g.
proposes environmental protection measures to control the discharge of radioactive effluents into the environment Measures and facilities; propose environmental protection monitoring plans, quality assurance measures and environmental management methods; h.
i analyze the impact of normal working conditions and possible accident conditions on the environment during the decommissioning process, including radioactive effects and non- The impact of radioactive harmful pollutants, and evaluate the degree of compliance of the selected decommissioning plan with national standards; j.Indicate the decommissioning level reached after the decommissioning operation is completed; k. If it is not Level 3 decommissioning, the total radioactivity, nuclide types, distribution characteristics and possible impact on the environment contained in the remaining nuclear facilities should be explained, and the corresponding safety measures taken should be explained. 7.2 In the "Final Environmental Impact Report of Reactor Decommissioning", at least the following content should be included: a. Describe the actual measurement results of radioactive effluents discharged into the environment during different decommissioning stages and the investigation results of environmental radiation levels; b. Describe the decommissioning process Actual measurement results of the treatment, transportation, storage and disposal of primary and secondary radioactive waste, as well as the resulting environmental pollution; Measurement results of the type and quantity of radioactive harmful substances; d. Evaluate the impact of normal working conditions and accidental conditions on the environment during decommissioning operations, explain the maximum individual effective dose equivalent and collective dose equivalent burden on the public during the implementation of decommissioning, point out key resident groups, key pathways and key nuclides, and evaluate decommissioning The extent to which the environmental impact caused during the entire process complies with national standards; explain the restoration of the terrain and landforms around the plant site; e.
1. Explain the impact of residual radioactivity after decommissioning; g. Explain the census results of radiation levels at the plant site and the reusability status of the factory site; h. If it is not Level 3 decommissioning, the impact that the legacy nuclear facilities will have on the human ecological environment should be described, and the types, activity levels and changing trends of radioactive effluents discharged into the environment under positive operating conditions should be predicted, as well as possible accidents and Corresponding safety measures provide the maximum individual effective dose equivalent and collective dose equivalent burden on the public under normal working conditions and accident conditions; i. If it is not Level 3 decommissioning, the structure and function of the safety barrier of the legacy nuclear facility should be explained; safety signs should be set up on the surface of the legacy nuclear facility and in waste burial sites below low-level radioactivity, indicating the type, activity, volume, and depth of the buried material. and time, etc., and explain the transfer and implementation of safety measures taken to ensure environmental safety. If Level 3 decommissioning has been achieved, corresponding explanations can be provided only for the burial conditions of wastes below low-level radioactivity. 7.3 The contents of the "Reactor Decommissioning Implementation Report" should at least include: a. Provide the actual measurement results of monthly radioactive effluents (requirements see Article 9.3.1), b. Give the survey results of the environmental radiation level of the year (requirements see Articles 8.2 and 9.2.1); c. , describe the type, quantity, specific activity and total activity of the radioactive waste transported out of the factory, the location and route it took, and if it has caused radioactive pollution to the environment, the actual measurement results of the pollution level should be explained and the impact on the public should be estimated. Radiation effects; d. Briefly describe the accidents that occurred during the decommissioning operations that year and explain the impact on the environment. e.
Briefly describe the types and quantities of non-radioactive pollutants produced during the decommissioning operations that year and their impact on the environment. 3
GB14588-93
7.4 In the reactor decommissioning design, at least the following content related to environmental safety should be included, a. Describe the quantity, type, main nuclides, specific activity and total activity of radioactive materials in different decommissioning stages, and explain the distribution and changes of radioactive sources in different decommissioning operations;
b. Propose solutions for different decommissioning stages Plans for the treatment, transportation, storage and disposal of decommissioning waste and measures to ensure environmental safety; c. Based on the characteristics of decommissioning operations, propose management target values ??for radioactive effluent emissions in different stages, and formulate measures to reduce the discharge of radioactive effluents into the environment:
d. Based on the characteristics of decommissioning operations and environmental changes, propose radioactive effluent monitoring plans and environmental monitoring plans, as well as corresponding quality assurance measures;
Predict possible accidents in different decommissioning operations and analyze the impact of these accidents on the environment impact, and formulate corresponding safety measures and e.
Remedial measures:
1. Based on the characteristics of decommissioning operations, formulate measures to reduce the impact of non-radioactive pollutants (such as chemical poisons, dust, noise, etc.) on the environment Impact measures and propose safety measures to prevent man-made accidents; g. If the environmental protection and monitoring facilities during operation have failed or are insufficient to ensure environmental safety during decommissioning, designs should be made for the newly added environmental protection and environmental monitoring facilities during decommissioning: h. If it is not Level 3 decommissioning, reliable safety barriers should be designed for legacy nuclear facilities to reduce the impact of radioactive materials in legacy nuclear facilities on the environment to the lowest possible level.
8: Scope of environmental assessment and environmental investigation
The ranges listed in this chapter refer to the size of the radius around the dump site as the center. 8.1 The evaluation scope of the environmental impact of reactor decommissioning should be determined according to the decommissioning stage. The assessment scope during the decommissioning period should comply with the provisions of Article 3.1 of GB11215; the environmental impact assessment after the decommissioning operation is completed can take a certain range based on the direction of groundwater in the site area and the migration rules of radionuclides. 8. During the decommissioning period of the 2-car reactor, the scope of environmental investigation shall be 2 to 5 km around the reactor site. 9 Technical requirements for environmental management
9.1, requirements for "three wastes" treatment facilities. Before decommissioning operations begin, the "three wastes" treatment facilities serving decommissioning should be comprehensively inspected and ensure their effective operation, otherwise decommissioning cannot begin. Operations.
9.2 Discharge requirements for radioactive effluents
9.2.1 During the decommissioning operation, the airborne and liquid effluents discharged into the environment should be monitored, including the total amount of emissions, Analysis of emission concentration and main nuclides.
9.2.2 The annual emission of radioactive effluents should be controlled according to the approved annual emission management target value. 9.3 Requirements for environmental monitoring
9.3.1. During the decommissioning operation, an environmental monitoring program should be developed. The content of the program should include items, frequency, media, methods, etc. If abnormalities are found, the pollution trend should be tracked and remedial measures should be taken in a timely manner. 9.3.2 If it is not level 3 decommissioning, it should be carried out in a timely manner. Set up monitoring or sampling devices around legacy nuclear facilities. Regularly observe the radioactivity levels of nearby groundwater, surface water, rock and soil samples. When abnormalities are found, the cause should be found in a timely manner, leakage should be eliminated, contamination should be removed, and corresponding remedial measures should be taken in a timely manner.
9.4 General requirements for the treatment, transportation, storage and disposal of radioactive waste 9.4.1·Airborne radioactive effluents and radioactive waste liquids generated during decommissioning operations should be treated before being discharged into the environment. The generated waste liquid residues should be solidified and properly stored. The solidified waste should have the characteristics of low leaching rate, good chemical stability, good radiation resistance and high mechanical strength
9.4.2 Respond to the waste generated during reactor decommissioning. The solid matter should be reduced in volume as much as possible. Decommissioning waste should be strictly classified according to the provisions of GB9133, and treated and disposed of separately. GB14588-93
9.4.3 During the decommissioning operation, it should be strictly controlled. Manage radioactive waste and take effective measures to prevent radioactive waste from being lost or stolen. 9.4.4 The storage and disposal of radioactive solids should comply with the requirements of GB9132, GB11928 and GB1271i. Radioactive waste in temporary waste storage should be ensured. Take it out successfully within the specified storage period and send it to the low- and medium-level radioactive waste disposal site. 9.4.5 The radioactive waste for external transportation must have sufficient mechanical strength to meet the requirements of loading, unloading, and transportation. The weight, volume, shape and size should be compatible with safe operations during loading, unloading and transportation, the classification, grading and radioactive activity limits of radioactive waste packages, surface contamination requirements for transport containers, transportation and labeling requirements, Safety management and approval procedures should comply with the requirements of GB11806.
9.4.6 The treatment and disposal of non-radioactive hazardous wastes should comply with the requirements of relevant national standards. 9.4.7 Airborne wastes that are lower than low level. and liquid wastes should be discharged into the environment under supervised and controlled conditions. Solid wastes with lower than low radioactivity can be transported without packaging or with simple packaging, but when there is no packaging, measures should be taken to prevent the waste from being lost or flying. Solid waste with lower than low level radioactivity can be disposed of by landfill at a suitable location approved by demonstration. Safety signs should be set up on the surface, and management periods should be given based on the nature of the buried objects. The management period is defined as when the radioactivity level of the waste decays below the exemption value. 9.5 Reuse requirements for decommissioned equipment, components, materials, factories and sites 9.5.1 Equipment, components and materials shipped out of the factory area for unrestricted reuse must meet the requirements of Article 6.6 and be approved by the provincial environmental protection department Only then can it be allowed to leave the factory.
9.5.2· Factory buildings prepared for unrestricted reuse or sites that are about to be opened without restrictions must meet the requirements of Article 6.7 and must be approved by the provincial environmental protection department before they can be reused or opened. 9.6 Requirements for safety and security
9.6.1 During the decommissioning operation, the safety and security measures during the decommissioning operation should be formulated according to the characteristics of the decommissioning operation, personnel changes and surrounding environmental conditions, and with reference to the safety and security measures during the reactor operation. Security measures and systems. 9.6.2. Protection of legacy nuclear facilities should be provided to prevent irrelevant personnel from accidentally entering or artificially destroying the safety barriers of legacy nuclear facilities. Landfills for waste below low level should also be properly protected during the management period. 10 Accident handling plan
According to the characteristics of the reactor, decommissioning operations and surrounding environmental conditions, accidents and potential hazards that may occur during decommissioning and affect environmental safety should be analyzed, corresponding treatment plans should be formulated, and necessary equipment should be equipped and professionals. 11 Quality Assurance Measures
11.1 The quality assurance program for reactor decommissioning must include content to ensure environmental safety during the entire decommissioning process, so that the implementation of decommissioning operations and the processing and disposal of decommissioning waste will not have any impact on the environment. Unacceptable impact. 11.2 Personnel engaged in decommissioning quality assurance work should be trained, assessed and approved, and have the ability to ensure that decommissioning activities are carried out according to predetermined procedures and quality requirements.
11.3 The following requirements must be emphasized for various radioactive monitoring during decommissioning: a.
The instruments and equipment used should be calibrated and calibrated by relevant departments to ensure that the instruments and equipment are in normal working condition; monitoring Personnel can correctly implement monitoring procedures so that relevant steps such as placement, sampling, sample preparation, and measurement can be carried out correctly; b.
Measurement errors can be controlled so that the accuracy of measurement is guaranteed and verified. Measures; c.
d. The analysis methods used should comply with the requirements of relevant national regulations to ensure that the measurement results are correctly analyzed; the monitoring data and information should be carefully recorded, checked and properly kept. e.
11.4, all information related to decommissioning, including the design, construction and operation data of the facility, decommissioning design and decommissioning operation implementation data, environmental assessment during decommissioning, safety reports, implementation reports, official correspondence, etc. , should be carefully collected and archived. 11.5 After the decommissioning operation is completed, the implementation unit of the environmental safety measures and management system should be determined and the handover work should be done. 5
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