Guide for STANDARDization—Part 5:Environmental aspects for their inclusion in product STANDARDs
Some standard content:
ICS13.280
National Standard of the People's Republic of China
GB/T 19597—2004
Safety reguirements for decommissioning of nuclear facilities
Safety reguirements for decommissioning of nuclear facilities2004-11-02Promulgated
General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of ChinaStandardization Administration of the People's Republic of China
2005-08-01Implementation
GB/T19597-2004
This standard is compiled with reference to the Safety Guide "Decommissioning of Nuclear Fuel Cycle Facilities" (SafetyGuideNoWS--2.4) and the Safety Guide "Decommissioning of Nuclear Power Reactors and Research Reactors" (SafelyGuide NaWSG-2.1) of the International Atomic Energy Agency (IAEA), and is combined with the actual situation of my country.
This standard was proposed by China National Nuclear Corporation. This standard is under the jurisdiction of the National Nuclear Energy Standardization Technical Committee. This standard was drafted by: China Institute of Radiation Protection. The main drafters of this standard: Ren Xianwen, Liu Wencang, Zhang Yuan. 1 Scope
Safety requirements for decommissioning of nuclear facilities
GB/T19597—2004
This standard specifies the safety objectives, management principles, radiation safety, decommissioning waste safety and industrial safety requirements for decommissioning of nuclear facilities. This standard mainly deals with the radiation hazards associated with the decommissioning of nuclear facilities, and does not directly deal with the non-radiation hazards that may arise in decommissioning activities.
This standard applies to the decommissioning of nuclear facilities that are not closed due to accidents, and the decommissioning of nuclear facilities closed due to accidents shall be implemented as a reference. This standard does not apply to the remediation of closed tailings ponds, waste rock dumps, slag dumps, abandoned mines and the closure of radioactive material disposal facilities. 2 Normative references
The clauses in the following documents become the clauses of this standard through reference in this standard. For any dated referenced document, all subsequent amendments (excluding errata) or revisions are not applicable to this standard. However, parties to agreements based on this standard are encouraged to study whether the latest versions of these documents can be used. For any undated referenced document, the latest version is applicable to this standard. GB9133 Classification of radioactive waste
GB14500 Regulations on the management of radioactive waste
GB1887! Basic standards for ionizing radiation protection and radiation source safety 3 Terms and definitions
The following terms and definitions apply to this standard. 3.1
Radioactive inventoryThe amount of radioactive (material) remaining in the closed nuclear facilities (including various systems, buildings (structures), equipment, arm networks, sites, etc.) before decommissioning.
Radioactive residualThe amount of radioactive (material) remaining in the remaining buildings (structures), equipment, systems, roads, and sites after the decommissioning project of nuclear facilities is completed.3.3
Post decommissioning operation
The state of a nuclear facility after it has stopped operating normally due to various reasons. 3.4
shutdown
After the nuclear facility has completed various operation closing tasks (e.g. process facilities have been unloaded, spent fuel has been transported out, process systems have been emptied, process materials have been transported out, operational waste has been transported out, process facilities have been preliminarily decontaminated, various items have been removed from each work number, and various material characteristics in the facility have been recorded, etc.), the nuclear facility is in a state of waiting for decommissioning. 3.5
clean up
Refers to the activities of removing radioactive contaminants from the surface of buildings (structures), road surfaces, and soil by various means. 3.6
dismantling
The practical activities of removing process systems, equipment and auxiliary facilities from the source by various means and using appropriate methods and machinery. GB/T 19597-2004
Disassembling
The practice of further dismantling the disassembled process systems, equipment and auxiliary facilities in various ways and with appropriate methods and machinery to facilitate subsequent operations.
Demolition
The practice of demolishing and clearing buildings (structures), roads and other facilities in various ways and with appropriate machinery. 3.9
Deconomissioningplauning The decommissioning strategy and overall arrangement of nuclear facilities to be decommissioned made by the operating unit or entrusted to other units, including the sequence of all major activities, major safety issues and solutions in decommissioning, maintenance and (or) recommendations of safety-related systems, management of decommissioning waste and related facilities, selection and development of important decommissioning technologies, determination of national standards for decommissioning, time schedule, calculation of decommissioning costs and other measures, etc. 3.10
Decommissioning 3. 11
Technical documentation for decommissinning of a nuclear facility Technical documentation for decommissinning of a nuclear facility Preparation of various technical documents and corresponding preparations for the establishment of a nuclear facility decommissioning project. The work includes: decommissioning plan demonstration, investigation of decommissioning radioactive sources, material balance, identification of pollutant characteristics, recommendation of management target values, decommissioning cost estimation, as well as radiation safety, decommissioning material management, quality assurance, decommissioning project schedule, decommissioning process radiation monitoring, decommissioning project completion status radiation monitoring, feasibility study report, environmental impact assessment report, safety analysis report and other research and preparation activities. 3. 12
Target value for decommissianing of nuclear facilities Authorized crtterla of decommissianing of nnclear facility Under the principle of complying with national standards, based on the geographical location, complex procedures, contamination status, environmental conditions for the utilization prospects of the retained facilities and sites, financial, social, cultural, political and other factors of the nuclear facilities to be decommissioned, after optimizing radiation protection, the implementation standards for the decommissioning practices of the nuclear facilities are recommended and approved by the regulatory authorities. 4 Safety objectives for decommissioning of nuclear facilities
4.1 The ultimate goal of decommissioning nuclear facilities is to enable nuclear facilities and (or) sites to be opened and used with or without restrictions. To achieve this goal, decommissioning operations should reduce the radiation doses of the occupants of the facilities and sites after decommissioning to the management target value approved by the regulatory authorities. In view of the different levels of complexity of nuclear facilities, with the approval of the regulatory authorities, nuclear facilities can implement decommissioning strategies of immediate dismantling or delayed dismantling. 4.2 Regardless of the nuclear facility decommissioning strategy adopted, the decommissioning safety goal is to ensure the safety of workers, the public and the environment, and to protect them from or reduce the hazards of radioactive or non-radioactive substances generated during the decommissioning stages, while not leaving undue burdens to future generations, including additional health, safety and financial risks and financial demands. 4.3 Some specific activities in the decommissioning process of nuclear facilities, such as decontamination, dismantling, dismantling and transportation of equipment, and dismantling of individual safety systems, have the possibility of generating new hazards. Therefore, the proper management of safety issues involved in certain specific activities in the decommissioning process is an important part of the national standard for decommissioning safety.
4.4 Each practical activity in the decommissioning process must comply with the three principles of radiation protection. 4.5 The decommissioning radioactivity level and dose management limit of nuclear facilities are the specific embodiment of the decommissioning safety goals, and the decommissioning activities must meet the corresponding value requirements.
5 Principles of safety management for decommissioning of nuclear facilities
5.1 Decommissioning plan
GB/T 19597—2004
5.1.1 A decommissioning plan shall be formulated for each nuclear facility. The content and depth of the decommissioning plan shall vary according to the complexity and potential danger of the nuclear facility, and shall be consistent with relevant national laws and regulations. 5.1.2 The decommissioning plan for each nuclear facility can be formulated in three stages: preliminary decommissioning plan for nuclear facilities, mid-term decommissioning plan for nuclear facilities, and overall decommissioning plan for nuclear facilities. The contents of these three plans shall be successively deeper and more detailed. 5.1.3 During the construction period of the nuclear facility (or before commissioning), a preliminary decommissioning plan for the nuclear facility shall be formulated and submitted to the relevant departments.Report to the competent department. The preliminary plan should include:
consideration of basic safety issues;
expected decommissioning strategy;
demonstration of the safety of decommissioning using existing or to-be-developed decommissioning technologies;
d) interface arrangements between decommissioning facilities and common auxiliary systems of in-service facilities; the impact of the decommissioning process on the environment;
f) management of decommissioning waste;
g) decommissioning costs and fundraising methods and support agencies. 5.1.4 After a nuclear facility has been in operation for an appropriate period of time or after a major incident or accident, a medium-term plan for decommissioning of the nuclear facility must be formulated. If a medium-term plan is still formulated after commissioning, it must be formulated and reported to the main department in a timely manner after a major incident or accident occurs. When formulating the medium-term plan, various factors that have changed must be considered, such as the development of decommissioning technology, changes in current national laws and policies, the status of the nuclear facility itself, decommissioning resource guarantees, and estimates of decommissioning costs. Any incidents or accidents that occur during the operation of nuclear facilities and their impact on the decommissioning of nuclear facilities must be reflected in the medium-term plan.
5.1.5 When the nuclear facility is finally closed, a detailed study and completion of the overall decommissioning plan should be started and submitted to the competent authorities for approval. In addition to the above contents, the overall decommissioning plan should pay special attention to the sequence of decommissioning activities of the facilities to be decommissioned, the connection between the facilities to be decommissioned and the common auxiliary facilities of the facilities in operation, the maintenance and (or) establishment of safety-related systems, the disposal of decommissioned waste and related facilities, the selection and development of important decommissioning technologies, the determination of decommissioning goals, the time schedule, the budget and fundraising methods of decommissioning costs, etc. 5.2 When the decommissioning funds and decommissioning technologies can guarantee the safety of decommissioning activities, the decommissioning strategy of immediate dismantling should be adopted. When the decommissioning funds and decommissioning technologies are insufficient, the decommissioning strategy of delayed dismantling can be selected, but the reasons must be explained to the relevant departments and the subsequent decommissioning funds and decommissioning technology research and development must be promised. After the completion of the decommissioning project with delayed disassembly, the potential hazards of the retained nuclear facilities should be significantly reduced, and the status report of the retained nuclear facilities should be submitted to the main (audit) management department on a regular basis. The report should include: monitoring items, monitoring results, safety evaluation, incidents, number of incidents and handling results, follow-up monitoring plan, etc. 5.3 Under the decommissioning state of unlimited opening, no radioactive waste inconsistent with unlimited opening and use should be retained within the original site.
5.4 A quality assurance outline must be formulated and implemented throughout the decommissioning process. Adequate guarantees should be provided to meet the requirements related to decommissioning safety; a quality control mechanism and procedure for reviewing and evaluating the overall effectiveness of decommissioning safety measures should be established. 5.5 When the delayed disassembly decommissioning strategy is selected, the nuclear facility may be monitored and sealed for a long time. Detailed, accurate and complete information on the location, form, quantity, nuclides of radioactivity retained in the facility, the current status of the facility and each completed work should be properly preserved to provide complete information for subsequent decommissioning projects.
5.6 The decommissioning management organization should include nuclear facility decommissioning experts and appropriate former facility operation or management personnel. Attention should be paid to retaining key personnel familiar with the operating facilities in the decommissioning team. There should also be experts or professionals in decontamination, robotic or remote operation, engineering technology, dismantling and demolition, quality assurance, waste management and security. 5.7 The feasibility study report of the nuclear facility decommissioning project is an important document for the decommissioning project and should be submitted to the competent authority for approval. The feasibility study report should include the following contents:
a) Description of the nuclear facilities, site impacts and surrounding areas affected by decommissioning; h) The operating history of the nuclear facilities, the scale of the decommissioned facilities, the causes of decommissioning, and the prospects for the use of the sites and buildings (structures) during the decommissioning process and after decommissioning.
An inventory of radioactive materials in the facility and an assessment of the remaining quantity, type and location of semi-radioactive and hazardous materials. This includes the information used to determine the GB/T 19597—2004
Calculation methods and measurement methods for inventory; Accident situations and treatment results during the operation phase, especially those related to the release of radioactive materials; d)
Major modifications to process facilities, equipment, buildings, and auxiliary systems during the operation phase; e
Outline of supervision and maintenance of site buildings during the shutdown or closure period; g
Description of the regulatory framework related to the implementation of decommissioning, including time schedule; h)
Description of the proposed decommissioning activities and procedures, including time schedule ：Decommissioning plan selection and reasons;
Decommissioning safety management program:
Plan for the modification of new systems or existing systems required to ensure radiation safety: Environmental monitoring program to be carried out during decommissioning period: m)
Decommissioning waste management strategy to be adopted:
Prepare criticality control program when necessary;
Conclusion of safety analysis and environmental impact assessment: p)
Quality assurance summary:
Decommissioning resource guarantee measures:Www.bzxZ.net
I) Other important technical and administrative management considerations, such as nuclear safeguards, physical protection, emergency preparedness, etc. 5.8 The safety analysis report of the nuclear facility decommissioning process is another important document of the decommissioning project. Before preparing the safety analysis document, it is necessary to clearly identify, classify and calculate the existing contamination level and current status of the facility, and estimate the inventory and distribution of radioactive, fissile materials and other hazardous materials in the facility through measurement. These accurate characteristics of the facility are the inputs of the safety analysis. The safety analysis unit is adapted to the complexity of the nuclear facility and the potential hazards associated with the decommissioning activities. Radioactive and non-radioactive hazards arising from decommissioning activities shall be identified and evaluated. The safety analysis results shall clarify the factors and extent of possible hazards to workers, the public and the environment at all stages of decommissioning, and the preventive and emergency measures to ensure safety. The safety analysis report shall be submitted to the main (review) department for approval. 5.9 The environmental impact report of the nuclear facility decommissioning process is another indispensable and important decommissioning document. The environmental impact assessment shall be adapted to the complexity of the nuclear facility and the potential hazards associated with decommissioning activities. The radioactive and non-radioactive substances arising from decommissioning activities shall be identified and evaluated for their potential hazards to the public and the environment during the decommissioning construction and after the completion of the decommissioning project. The environmental impact report shall be submitted to the main (review) department for approval.
5.10 Decommissioning work may only be carried out after the approval document for facility decommissioning is obtained after the approval document for facility decommissioning is reviewed and approved by the main (review) department mentioned in 5.7, 5.8 and 5.9.
5.11 After obtaining the approval document for decommissioning, a decommissioning implementation plan shall be formulated. The decommissioning implementation plan can be prepared according to the four steps of preparation, design, implementation and acceptance.
5,12 After the decommissioning project is completed, the operating unit shall submit a decommissioning project summary report, an environmental impact report, and a decommissioning project monitoring report to the relevant main (review) management department. After review and acceptance, the nuclear facility decommissioning project is completed. 5.33 Completion acceptance of nuclear facility decommissioning projects
5.13.1 The completion acceptance of decommissioning projects shall be organized by the nuclear facility decommissioning management department and personnel from the operation, construction, monitoring and other relevant units. 5.13.2 The completion acceptance of decommissioning projects includes: 1)
Inspect and approve the completion documents and materials;
Evaluate the quality of decommissioning projects 1
Coordinate the differences in the completion acceptance:
d) Issue an acceptance certificate.
5.14 Final acceptance of nuclear facility decommissioning projects
Final acceptance of decommissioning projects is organized by relevant national departments. The main acceptance contents include: a) Reviewing the final acceptance documents and materials of decommissioning projects submitted by the operating unit; 6) On-site inspection of the decommissioning site; 7) Checking whether the final acceptance of decommissioning projects meets the decommissioning management standards; 8) Checking the completeness and accuracy of the final acceptance archives and materials; 9) Identifying the quality of decommissioning projects; 10) Reviewing the final accounts of decommissioning projects; 11) Arbitrating issues related to decommissioning projects; 12) Issuing the final acceptance certificate of decommissioning projects. 6 Radiation safety in decommissioning of nuclear facilities
6.1 Overview
Radiation safety in decommissioning of nuclear facilities may involve all or part of the following issues: a) Various types of radioactive contamination, with special attention to large-scale contamination; b) Inhalation hazards associated with air contamination: high radiation levels requiring remote operation; d) Criticality hazards;
) Radiation hazards associated with the use of special processes in decommissioning; increased risks due to radiation growth (e.g., growth of tank-241); d) New radiation hazards that may arise during the decommissioning process. 6.2 General principles of radiation safety
GB/T 19597—2004
6.2.1 An independent radiation safety organization with the ability to handle worker and public health and radiation safety issues should be established, and safety management should be implemented in accordance with appropriate procedures.
6.2.2 During the decommissioning process, emphasis should be placed on the radiation safety of workers engaged in decommissioning operations and the radiation safety of members of the public who may be exposed due to the discharge of effluents, the release of solid materials, and the occupation of decommissioned sites. 6.2.3 The source principles and basic requirements of radiation safety have been clearly defined in GB18871. The radiation protection of nuclear facility decommissioning should ensure that radiation protection is optimized and that the radiation dose is kept within appropriate limits. Although the principles and objectives of radiation safety during the operation and decommissioning of nuclear facilities are basically the same, the implementation procedures and methods of radiation safety may vary greatly. In special circumstances during decommissioning, the use of special radiation safety equipment and certain unconventional procedures should be considered. These procedures include technical procedures and administrative management procedures. 6.2.4 Radiation safety in nuclear facility decommissioning should take the following factors into consideration: a) Use of protective shielding equipment to limit and reduce occupational exposure: A certain number of personnel familiar with radiation safety should be deployed to ensure the safety objectives of nuclear facility decommissioning; Ensure that decommissioning workers have appropriate radiation protection and safety skills and qualifications and receive corresponding training; e) Keep the decommissioning site clean to reduce the maximum exposure of occupational personnel and prevent the spread of contaminants; d) Divide the facilities to be decommissioned according to the level of radiation and contamination; e) Configure appropriate safety systems to keep the doses of workers and the public at the lowest possible level; f) All radiation safety measures should be documented and their effectiveness monitored. g)
6.2.5 During the preparation stage for decommissioning, a decommissioning radiation protection outline should be prepared. The contents of the decommissioning radiation protection outline should include: a brief introduction to the decommissioned nuclear facility; b) decommissioning effective radioactive source items and distribution; c)
division of decommissioning sub-areas of nuclear facilities; d) main radiation hazard factors and specific protection measures of each decommissioning sub-area under normal working conditions; e)
abnormal decommissioning conditions and emergency measures; radiation measurement plan; g) personnel training
h) safety culture literacy of nuclear facility decommissioning workers; GB/T19597-2004
i) target values of radiation protection management for decommissioning of nuclear facilities. 6.2.6 Radiation safety during decommissioning should implement the principle of vertical defense. The operating unit must implement multiple protections according to the progress of decommissioning activities to prevent unplanned release of radioactive materials and (or) mitigate the consequences of release and minimize the incidence of accidents that may lead to major radiation consequences.
6.3 Division and management of nuclear facility decommissioning sub-areas 6.3.1 Nuclear facility decommissioning sub-areas are divided according to radiation level, contamination level or contaminating nuclides. 6.3.2 Within each decommissioning sub-area, it is further divided into controlled areas and uncontrolled areas according to the contamination level. 6.3.3 According to the needs of decommissioning operations, local "high-dose areas" or "high-contamination areas" are set up in the control area. 6.3.4 Control the entry and exit of personnel and items in each decommissioning sub-area. 6.3.5 Temporary isolation rooms and (or) isolation gates should be set up in high-radiation areas, high-contamination areas or areas with high incidence of aerosols and dust, and equipped with necessary monitoring instruments.
6.3.6 Control areas should be expanded or reduced in a timely manner according to the progress of decommissioning operations and actual needs. 6.4 Radiation safety measures
6.4.1 Carefully plan the specific operations required Number of people and time, work procedures and protective measures. 6.4.2 Predict possible unexpected events during the operation and make corresponding emergency arrangements. 6.4.3 Ensure the effective operation of ventilation systems and air purification devices in decommissioning practice. 6.4.4 Effective decontamination should be carried out before dismantling contaminated equipment, systems and facilities. 6.4.5 Measures should be taken to prevent the spread of radioactive dust before dismantling contaminated equipment, systems and facilities. 6.4.6 When dismantling contaminated equipment, systems and facilities, workers should take necessary and sufficient self-protection measures according to the needs of the operation. 6, 5 Dose Limits and Control
6.5.1 The dose limits for radiation workers shall comply with the provisions of GB18871. 6.5.2 Dose Control for Public Members
6.5.2.1 The maximum annual dose received by the public from the decommissioning project and other nuclear facilities nearby shall not exceed the limit specified in GB18871; 6.5.2.2 If there may be other operating nuclear facilities near the site during the implementation of this decommissioning project, sufficient annual dose margin shall be reserved.
6.5.2.3 During the decommissioning of nuclear facilities, the annual effective dose caused by the discharge of radioactive effluents to any public relative in the key resident group outside the site shall not exceed 0.25 mSv,
6.5.2.4 Under the unrestricted and final state, the maximum annual effective dose caused to individual members of the public by the residual radioactivity on the site through various exposure pathways shall comply with the principle of optimization of radiation protection. 6.5.3 Radiation safety should be optimized so that the personal dose and the number of exposed personnel and the public during the implementation of decommissioning and after the completion of decommissioning are limited to below the prescribed dose constraint values after considering economic and social factors, and maintained at the lowest level reasonably achievable. Radiation safety optimization can be a direct qualitative analysis or a quantitative analysis. 6.5.4 It is necessary to cultivate and maintain a safety culture and encourage a thoughtful and willing-to-learn attitude towards radiation safety matters. To this end, the following should be done:
Regarding the radiation safety of the public and workers as paramount; b) timely identifying and correcting factors that affect radiation safety, and taking appropriate measures: clearly defining the radiation safety responsibilities of each person, and all personnel involved in the decommissioning of nuclear facilities should receive appropriate training and possess appropriate qualifications:
a) defining clear authority for radiation safety decision-making. 6.5.5 The level of surface contamination control of the body surface, clothing, tools, equipment, workbenches, walls, floors, etc. of decommissioned workers shall comply with the provisions of GB18871, and the level of clean clearance for recycling and reuse of contaminated materials, tools, equipment, etc. shall comply with relevant national regulations and standards.
7 Waste safety of nuclear facility decommissioning
GB/T 19597-2004
7.1 The decommissioning waste management plan is an indispensable component of the decommissioning documents. It should be considered that a large amount of various types of wastes different from those in the operation period of the nuclear facility will be generated in a short period of time during the decommissioning process. The purpose of the waste management plan is to manage these wastes safely. The focus of the examination is on the minimization of radioactive waste and the fate of decommissioning waste. 7.2 Under the premise of ensuring safety, after preliminary optimization analysis and personnel training, the radioactive waste generated in the decommissioning process is minimized by optimizing existing technologies such as disassembly and dismantling technology, sufficient defloating, controlling cross contamination, waste separation, and recycling, reuse, clean clearance and other administrative management control measures.
7.3 Different strategies for minimizing decommissioning waste will produce different radiation doses for workers and the public. The optimal overall solution should be adopted to balance the relationship between minimizing decommissioning waste and maintaining the lowest level of radiation dose that can be reasonably achieved. 7.4 The safety management standards and basic requirements of decommissioning waste shall be implemented in accordance with GB14500. 7.5 The safety management standards and basic requirements of gas and liquid effluents shall comply with the requirements of relevant national regulations and standards. 7.6 The decommissioning waste safety management plan should also focus on whether the existing waste management system of nuclear facilities is compatible with decommissioning waste. If it is incompatible, it may be necessary to establish new waste management facilities. 7.7 When considering the safety of decommissioning waste, the following factors may be involved: complex waste management strategies due to the diversity of decommissioning waste streams; a)
b) the source, quantity, type and characteristics of waste generated in decommissioning activities; the possibility of clean release of radioactive pollutants should be considered. Radioactive pollutants released from clean control should comply with relevant national requirements; the possibility of recycling and reuse of plant, equipment and materials should be considered and should comply with relevant national requirements; d)
The generation of secondary waste should be minimized as much as possible: e
f) the existence of non-radioactive hazardous materials (such as asbestos) should be considered: the presence or absence of material recycling facilities, radioactive waste storage facilities and disposal facilities: g
Special requirements for packaging and transportation of certain radioactive wastes; tracking of radioactive materials;
) the potential impact of decommissioning waste management activities on workers, the public and the environment; k) the safety of recommended waste treatment, preparation, transportation, storage and disposal methods. 7.8 Most of the wastes and other materials generated during the decommissioning process may meet the clean release criteria. Under special circumstances, certain materials generated during certain dismantling activities may be recycled and reused with restrictions after approval by the regulatory authorities. 7.9 In view of the amount of decommissioning waste generated and the particularity of the decommissioning waste itself, in addition to classifying decommissioning waste according to GB9133, wastes in decommissioning waste with a specific activity slightly higher than the clean release level and that will not cause unacceptable radiation hazards to the public and the environment may be considered as slightly radioactive pollutants. Slightly radioactive pollutants confirmed by the regulatory authorities may be landfilled on-site at a suitable location within the nuclear facility site, and will no longer be subject to regulatory control. The main limit values for slightly radioactive pollutants shall be recommended after optimization analysis and approved by the regulatory authorities. 7.10 A strict distinction shall be made between truly useless wastes and potentially useful wastes among slightly radioactive pollutants.11 Radioactive waste shall be prepared, temporarily stored, transported and disposed of in accordance with relevant national standards. 7.12 Appropriate measures must be taken to safely manage large waste components generated during decommissioning activities. 8 Industrial safety during decommissioning of nuclear facilities
8.1 During decommissioning activities of nuclear facilities, industrial safety issues different from those during operation of nuclear facilities may arise. The decommissioning unit of nuclear facilities shall carefully study possible industrial safety issues and formulate industrial safety plans and emergency measures. The industrial safety plan shall be incorporated into the quality assurance system of the decommissioning unit of nuclear facilities.
8.2 The practical activities of decommissioning nuclear facilities may involve many special types of work, and the safety requirements of each type shall comply with relevant regulations of my country. GB/r 19597--2004
8.3 In the practice of nuclear facility decommissioning, special attention should be paid to the following industrial safety: a) Hazards associated with inherent chemical processing activities (e.g. explosion, fire, burns, etc.); b) Potential impact of non-radioactive material operations on various safety issues (e.g. asbestos); c) Safety of high-altitude operations; d) Earthwork safety; e) Power supply safety for important operations.
9 Radiation monitoring for decommissioning of nuclear facilities
9.1 Survey of decommissioning radioactive sources
The survey of radioactive sources is completed by the operating unit or other units entrusted. The goal is to clarify the inventory, existence type and distribution of radioactive materials in the decommissioning facilities. It is the most important input item for the decommissioning project. For those complex facilities, at least a reasonable preliminary inventory of radioactive materials, main nuclear cords, approximate existence type and main distribution location should be clarified during the feasibility study stage of the decommissioning project. After the decommissioning project is approved, a detailed investigation of the decommissioned radioactive sources should be carried out first, and the investigation should be deepened as the decommissioning process progresses. 9.2 Auxiliary radiation monitoring requirements
The decommissioning documents should specify the requirements for on-site and off-site (environmental) radiation monitoring. Both on-site and off-site radiation monitoring of decommissioning are for the purpose of determining the actual protection and safety level associated with decommissioning activities. A radiation monitoring implementation plan should be prepared during the decommissioning implementation preparation stage. 9.3 Radiation monitoring types and objectives
9.3.1 On-site radiation monitoring during decommissioning
9.3.1.1 On-site radiation measurement during decommissioning is performed by the construction unit. The goal is to ensure that the decontamination and elimination results of the decommissioned objects meet the standard values of the nuclear facility decommissioning project.
9.3.1.2 On-site radiation protection monitoring during decommissioning is performed by the construction unit. The goal is to ensure that the radiation dose received by decommissioned personnel is below the control limit and as low as possible.
9.3.1.3 Effluent monitoring during decommissioning is performed by the construction unit. The goal is to ensure that the concentration of radioactive activity discharged off-site through aerosol and liquid channels meets the relevant national requirements and is as low as possible. 9.3.2 On-site radiation inspection of the completed state
The operating unit organizes and executes it. The goal is to confirm that the buildings (structures), facilities, equipment, sites, etc. retained in the decommissioning completion state have met the management target values of the nuclear facility decommissioning project.
9.3.3 On-site radiation acceptance monitoring of the completed state is organized by the completion acceptance unit or the nuclear facility decommissioning project completion state acceptance monitoring team designated by the completion acceptance unit. The daily goal is to review the on-site radiation detection results of the decommissioning completion state submitted by the operating unit. 9, 3.4 Environmental radiation monitoring
The operating unit organizes and executes environmental monitoring during the construction process and environmental monitoring of the decommissioning completion state. The daily goal is to monitor the impact of decommissioning activities on the surrounding environment.
9. 4 Radiation Monitoring Objects
9.4.1 Radiation Monitoring Objects in Decommissioning Process
9. 4. 1.1 Radiation Monitoring Objects in Decommissioning Site
Decommissioning site monitoring should ensure that all possible work areas and emission points are within the monitoring scope. Mainly include the surface contamination level of facilities, systems, equipment, materials, buildings (structures), sites, etc. contaminated by radioactive substances in the decommissioning construction area after decontamination and removal, radioactive nuclide specific activity in the soil, Y-dose rate: total activity of radioactive waste packaging, nuclide types, specific activity, waste package surface contamination level, emission volume, emission concentration and nuclear turbulence composition of radioactive effluent discharge outlets. 9.4.1.2 Monitoring objects of radiation protection in the decommissioning process Monitoring objects of radiation protection in the decommissioning process include air pollution level in the workplace, ambient dose rate, personal dose, surface contamination of personal protective equipment, body contamination, etc. 9.4.2 Monitoring objects of radiation in the decommissioning completion state Monitoring objects of radiation in the decommissioning completion state include the residual radioactive surface contamination level, ambient dose rate, and nuclide type of facilities, systems, equipment, materials, buildings, and sites retained in the decommissioning completion state within the scope of decommissioning; residual radioactive specific activity in the soil: pollution level of the environment outside the site.
9.4.3 Monitoring objects of radiation acceptance in the completion state Monitoring objects of radiation acceptance in the completion state include sampling re-inspection of radiation monitoring objects and projects in the completion state within the scope of decommissioning. 9.4.4 Monitoring objects of environmental radiation
According to the specific conditions of the nuclear facilities, arrange the discharge point of effluents, radioactive monitoring in the atmosphere, soil, surface water, groundwater, and environmental radiation level monitoring.
10 Contingency Plan
10.1 Depending on the specific situation of the nuclear facility, it is necessary to prepare and implement an emergency plan or procedure that is consistent with the abnormal conditions that may occur during decommissioning activities. Decommissioning site staff should be trained in the implementation of emergency procedures. The emergency plan should be approved by the quality assurance legal person of the nuclear facility operating unit before implementation. For decommissioning facilities with large radioactive inventories, complex facilities, and the possibility of major abnormal conditions, the emergency plan should be approved by the main (audit) management department before implementation. 10.2 The operating unit should ensure that emergency procedures related to unforeseen events have been considered and corresponding contingency measures and resource preparations have been made. Personnel training should be included in the emergency procedures, and the emergency procedures should be updated through regular drills and tests. 11 Physical Protection
11.1 During the decommissioning of nuclear facilities, appropriate physical barriers should be set up at the decommissioning site and necessary security measures should be implemented to ensure the safety of decommissioning. This is particularly important when implementing a delayed dismantling decommissioning strategy. 11.2 During the decommissioning of nuclear facilities, appropriate physical protection should be maintained for the facilities and radioactive materials, hazardous substances, decommissioning operation equipment and objects that may cause harm to the public or the environment. If the facility involves nuclear safeguarded materials, physical protection should be implemented in accordance with relevant national regulations. 11.3 Confidentiality issues involved in the decommissioning of nuclear facilities shall be implemented in accordance with relevant national regulations. 12 Quality Assurance
12.3 The operating unit shall implement an appropriate and up-to-date quality assurance program. Decontamination, dismantling, dismantling and waste management activities shall be carried out by trained and qualified personnel in accordance with approved work procedures. A work procedure covering each decommissioning activity should be formulated, and when formulating the quality assurance plan for decommissioning projects, attention should be paid to the collection and preservation of records and information of decommissioning activities. 12.2 During the growth period, records of each task performed in the decommissioning activities shall be retained. Complete and accurate information on the quantity, location, distribution and type of radioactive materials remaining in the facility is very important for subsequent decommissioning projects with delayed disassembly.2 Auxiliary radiation monitoring requirements
Decommissioning documents should specify the requirements for radiation monitoring at the decommissioning site and off-site (environment). Both on-site and off-site radiation monitoring of decommissioning are for the purpose of determining the actual protection and safety levels associated with decommissioning activities. A radiation monitoring implementation plan should be prepared during the decommissioning implementation preparation stage. 9. 3 Radiation monitoring types and objectives
9.3.1 On-site radiation monitoring during decommissioning
9.3.1.1 On-site radiation measurement during decommissioning is performed by the construction unit. The goal is to ensure that the decontamination and elimination results of the decommissioned objects meet the self-standard values of the nuclear facility decommissioning project.
9.3.1.2 On-site radiation protection monitoring during decommissioning is performed by the construction unit. The goal is to ensure that the radiation dose received by decommissioned personnel is below the control limit and as low as possible.
9.3.1.3 Effluent monitoring during decommissioning is performed by the construction unit. The goal is to ensure that the radioactive activity concentration discharged to the off-site through aerosol and liquid pathways meets the relevant national requirements and is as low as possible. 9.3.2 On-site radiation inspection at completion status
The operating unit shall organize and execute it. The goal is to confirm that the buildings (structures), facilities, equipment, sites, etc. retained at the completion status of decommissioning have met the management target values of nuclear facility decommissioning projects.
9.3.3 On-site radiation acceptance monitoring at completion status shall be organized by the completion acceptance unit or executed by the nuclear facility decommissioning project completion status acceptance monitoring team designated by the completion acceptance unit. The daily goal is to review the on-site radiation detection results of the decommissioning completion status submitted by the operating unit. 9, 3.4 Environmental radiation monitoring
The operating unit shall organize and execute environmental monitoring during the construction process and environmental monitoring of the decommissioning completion status. The daily goal is to monitor the impact of decommissioning activities on the surrounding environment.
9. 4 Radiation monitoring objects
9.4.1 Radiation monitoring objects during decommissioning
9. 4.1.1 Radiation monitoring objects at the decommissioning site
Decommissioning site monitoring shall ensure that all possible work areas and emission points are within the monitoring range. The main monitoring targets include the surface contamination level of facilities, systems, equipment, materials, buildings (structures), sites, etc. contaminated by radioactive substances in the decommissioning construction scope after decontamination and removal, the radioactive nuclear specific activity in the soil, the total activity of radioactive waste packaging, the type of nuclides, the specific activity, the surface contamination level of waste packages, the emission volume, emission concentration and nuclear composition of radioactive effluent discharge ports. 9.4.1.2 Monitoring targets for radiation protection during decommissioning The monitoring targets for radiation protection during decommissioning include the air pollution level in the workplace, the ambient Y dose rate, the personal dose rate, the surface contamination of personal protective equipment, the body contamination, etc. 9.4.2 Monitoring targets for radiation in the decommissioning completion state The monitoring targets for radiation in the decommissioning completion state include the residual radioactive surface contamination level, the ambient Y dose rate, the type of nuclides in the facilities, systems, equipment, materials, buildings (structures), sites, etc. retained in the decommissioning completion state within the scope of decommissioning; the residual radioactive specific activity in the soil: the pollution level of the environment outside the site.
9.4.3 Completed state radiation acceptance monitoring objects The completed state radiation acceptance monitoring objects include sampling re-inspection of completed state radiation monitoring objects and projects within the scope of decommissioning. 9.4.4 Environmental radiation monitoring objects
According to the specific conditions of the nuclear facility, arrange the effluent discharge point, radioactivity monitoring in the atmosphere, soil, surface water, groundwater and environmental radiation level monitoring.
10 Contingency plan
10.1 Depending on the specific conditions of the nuclear facility, it is necessary to prepare and implement an emergency plan or procedure that is consistent with the abnormal conditions that may occur during decommissioning activities. Decommissioning site staff should be trained in the implementation of emergency procedures. The emergency plan should be approved by the quality assurance legal person of the nuclear facility operating unit before implementation. For those decommissioning facilities with large radioactive inventory, complex facilities and the possibility of major abnormal conditions, the emergency plan should be approved by the main (review) management department before implementation. 10.2 The operating unit should ensure that the emergency procedures related to unforeseen events have been considered and corresponding contingency measures and resource preparations have been made. Personnel training should be included in the emergency procedures, and the emergency procedures should be updated through regular drills and tests. 11 Physical protection
11.1 During the decommissioning of nuclear facilities, appropriate physical barriers should be set up at the decommissioning site and necessary security measures should be implemented to ensure the safety of decommissioning. This is particularly important when implementing the delayed decommissioning and dismantling decommissioning strategy. 11.2 During the decommissioning of nuclear facilities, appropriate physical protection should be maintained for the facilities and radioactive materials, hazardous substances, decommissioning operation equipment and objects that may cause harm to the public or the environment. If the facilities involve nuclear safeguarded materials, physical protection should be implemented in accordance with relevant national regulations. 11.3 Confidentiality issues involved in the decommissioning of nuclear facilities shall be implemented in accordance with relevant national regulations. 12 Quality assurance
12.3 The operating unit shall implement an appropriate and up-to-date quality assurance program. Decontamination, dismantling, dismantling and waste management activities should be carried out by trained and qualified personnel in accordance with approved work procedures. A work procedure covering each decommissioning activity should be formulated, and when formulating the quality assurance outline for decommissioning projects, attention should be paid to the collection and preservation of records and information of decommissioning activities. 12.2 Keep records of each task performed during decommissioning activities. Complete and accurate information on the quantity, location, distribution and type of radioactive materials remaining in the facility is very important for the subsequent decommissioning works with delayed disassembly.2 Auxiliary radiation monitoring requirements
Decommissioning documents should specify the requirements for radiation monitoring at the decommissioning site and off-site (environment). Both on-site and off-site radiation monitoring of decommissioning are for the purpose of determining the actual protection and safety levels associated with decommissioning activities. A radiation monitoring implementation plan should be prepared during the decommissioning implementation preparation stage. 9. 3 Radiation monitoring types and objectives
9.3.1 On-site radiation monitoring during decommissioning
9.3.1.1 On-site radiation measurement during decommissioning is performed by the construction unit. The goal is to ensure that the decontamination and elimination results of the decommissioned objects meet the self-standard values of the nuclear facility decommissioning project.
9.3.1.2 On-site radiation protection monitoring during decommissioning is performed by the construction unit. The goal is to ensure that the radiation dose received by decommissioned personnel is below the control limit and as low as possible.
9.3.1.3 Effluent monitoring during decommissioning is performed by the construction unit. The goal is to ensure that the radioactive activity concentration discharged to the off-site through aerosol and liquid pathways meets the relevant national requirements and is as low as possible. 9.3.2 On-site radiation inspection at completion status
The operating unit shall organize and execute it. The goal is to confirm that the buildings (structures), facilities, equipment, sites, etc. retained at the completion status of decommissioning have met the management target values of nuclear facility decommissioning projects.
9.3.3 On-site radiation acceptance monitoring at completion status shall be organized by the completion acceptance unit or executed by the nuclear facility decommissioning project completion status acceptance monitoring team designated by the completion acceptance unit. The daily goal is to review the on-site radiation detection results of the decommissioning completion status submitted by the operating unit. 9, 3.4 Environmental radiation monitoring
The operating unit shall organize and execute environmental monitoring during the construction process and environmental monitoring of the decommissioning completion status. The daily goal is to monitor the impact of decommissioning activities on the surrounding environment.
9. 4 Radiation monitoring objects
9.4.1 Radiation monitoring objects during decommissioning
9. 4.1.1 Radiation monitoring objects at the decommissioning site
Decommissioning site monitoring shall ensure that all possible work areas and emission points are within the monitoring range. The main monitoring targets include the surface contamination level of facilities, systems, equipment, materials, buildings (structures), sites, etc. contaminated by radioactive substances in the decommissioning construction scope after decontamination and removal, the radioactive nuclear specific activity in the soil, the total activity of radioactive waste packaging, the type of nuclides, the specific activity, the surface contamination level of waste packages, the emission volume, emission concentration and nuclear composition of radioactive effluent discharge ports. 9.4.1.2 Monitoring targets for radiation protection during decommissioning The monitoring targets for radiation protection during decommissioning include the air pollution level in the workplace, the ambient Y dose rate, the personal dose rate, the surface contamination of personal protective equipment, the body contamination, etc. 9.4.2 Monitoring targets for radiation in the decommissioning completion state The monitoring targets for radiation in the decommissioning completion state include the residual radioactive surface contamination level, the ambient Y dose rate, the type of nuclides in the facilities, systems, equipment, materials, buildings (structures), sites, etc. retained in the decommissioning completion state within the scope of decommissioning; the residual radioactive specific activity in the soil: the pollution level of the environment outside the site.
9.4.3 Completed state radiation acceptance monitoring objects The completed state radiation acceptance monitoring objects include sampling re-inspection of completed state radiation monitoring objects and projects within the scope of decommissioning. 9.4.4 Environmental radiation monitoring objects
According to the specific conditions of the nuclear facility, arrange the effluent discharge point, radioactivity monitoring in the atmosphere, soil, surface water, groundwater and environmental radiation level monitoring.
10 Contingency plan
10.1 Depending on the specific conditions of the nuclear facility, it is necessary to prepare and implement an emergency plan or procedure that is consistent with the abnormal conditions that may occur during decommissioning activities. Decommissioning site staff should be trained in the implementation of emergency procedures. The emergency plan should be approved by the quality assurance legal person of the nuclear facility operating unit before implementation. For those decommissioning facilities with large radioactive inventory, complex facilities and the possibility of major abnormal conditions, the emergency plan should be approved by the main (review) management department before implementation. 10.2 The operating unit should ensure that the emergency procedures related to unforeseen events have been considered and corresponding contingency measures and resource preparations have been made. Personnel training should be included in the emergency procedures, and the emergency procedures should be updated through regular drills and tests. 11 Physical protection
11.1 During the decommissioning of nuclear facilities, appropriate physical barriers should be set up at the decommissioning site and necessary security measures should be implemented to ensure the safety of decommissioning. This is particularly important when implementing the delayed decommissioning and dismantling decommissioning strategy. 11.2 During the decommissioning of nuclear facilities, appropriate physical protection should be maintained for the facilities and radioactive materials, hazardous substances, decommissioning operation equipment and objects that may cause harm to the public or the environment. If the facilities involve nuclear safeguarded materials, physical protection should be implemented in accordance with relevant national regulations. 11.3 Confidentiality issues involved in the decommissioning of nuclear facilities shall be implemented in accordance with relevant national regulations. 12 Quality assurance
12.3 The operating unit shall implement an appropriate and up-to-date quality assurance program. Decontamination, dismantling, dismantling and waste management activities should be carried out by trained and qualified personnel in accordance with approved work procedures. A work procedure covering each decommissioning activity should be formulated, and when formulating the quality assurance outline for decommissioning projects, attention should be paid to the collection and preservation of records and information of decommissioning activities. 12.2 Keep records of each task performed during decommissioning activities. Complete and accurate information on the quantity, location, distribution and type of radioactive materials remaining in the facility is very important for the subsequent decommissioning works with delayed disassembly.1Depending on the specific circumstances of the nuclear facility, it is necessary to prepare and implement an emergency plan or procedure that is consistent with the abnormal conditions that may occur during decommissioning activities. Decommissioning site staff should be trained in the implementation of emergency procedures. The emergency plan should be approved by the quality assurance legal person of the nuclear facility operating unit before implementation. For decommissioning facilities with large radioactive inventories, complex facilities, and the possibility of major abnormal conditions, the emergency plan should be approved by the main (audit) management department before implementation. 10.2 The operating unit should ensure that emergency procedures related to unforeseen events have been considered and corresponding contingency measures and resource preparations have been made. Personnel training should be included in the emergency procedures, and the emergency procedures should be updated through regular drills and tests. 11 Physical protection
11.1 During the decommissioning of nuclear facilities, appropriate physical barriers should be set up at the decommissioning site and necessary security measures should be implemented to ensure the safety of decommissioning. This is particularly important when implementing a delayed dismantling and decommissioning strategy. 11.2 During the decommissioning of nuclear facilities, appropriate physical protection should be maintained for the facilities and radioactive materials, hazardous substances, decommissioning operation equipment and objects that may cause harm to the public or the environment. If the facility involves nuclear safeguarded materials, physical protection should be implemented in accordance with relevant national regulations. 11.3 Confidentiality issues involved in the decommissioning of nuclear facilities shall be implemented in accordance with relevant national regulations. 12 Quality Assurance
12.3 The operating unit shall implement an appropriate and up-to-date quality assurance program. Decontamination, dismantling, dismantling and waste management activities shall be carried out by trained and qualified personnel in accordance with approved work procedures. A work procedure covering each decommissioning activity should be formulated, and when formulating the quality assurance plan for decommissioning projects, attention should be paid to the collection and preservation of records and information of decommissioning activities. 12.2 During the growth period, records of each task performed in the decommissioning activities shall be retained. Complete and accurate information on the quantity, location, distribution and type of radioactive materials remaining in the facility is very important for subsequent decommissioning projects with delayed disassembly.1Depending on the specific circumstances of the nuclear facility, it is necessary to prepare and implement an emergency plan or procedure that is consistent with the abnormal conditions that may occur during decommissioning activities. Decommissioning site staff should be trained in the implementation of emergency procedures. The emergency plan should be approved by the quality assurance legal person of the nuclear facility operating unit before implementation. For decommissioning facilities with large radioactive inventories, complex facilities, and the possibility of major abnormal conditions, the emergency plan should be approved by the main (audit) management department before implementation. 10.2 The operating unit should ensure that emergency procedures related to unforeseen events have been considered and corresponding contingency measures and resource preparations have been made. Personnel training should be included in the emergency procedures, and the emergency procedures should be updated through regular drills and tests. 11 Physical protection
11.1 During the decommissioning of nuclear facilities, appropriate physical barriers should be set up at the decommissioning site and necessary security measures should be implemented to ensure the safety of decommissioning. This is particularly important when implementing a delayed dismantling and decommissioning strategy. 11.2 During the decommissioning of nuclear facilities, appropriate physical protection should be maintained for the facilities and radioactive materials, hazardous substances, decommissioning operation equipment and objects that may cause harm to the public or the environment. If the facility involves nuclear safeguarded materials, physical protection should be implemented in accordance with relevant national regulations. 11.3 Confidentiality issues involved in the decommissioning of nuclear facilities shall be implemented in accordance with relevant national regulations. 12 Quality Assurance
12.3 The operating unit shall implement an appropriate and up-to-date quality assurance program. Decontamination, dismantling, dismantling and waste management activities shall be carried out by trained and qualified personnel in accordance with approved work procedures. A work procedure covering each decommissioning activity should be formulated, and when formulating the quality assurance plan for decommissioning projects, attention should be paid to the collection and preservation of records and information of decommissioning activities. 12.2 During the growth period, records of each task performed in the decommissioning activities shall be retained. Complete and accurate information on the quantity, location, distribution and type of radioactive materials remaining in the facility is very important for subsequent decommissioning projects with delayed disassembly.
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