Codeofchina.com is in charge of this English translation. In case of any doubt about the English translation, the Chinese original shall be considered authoritative.
This standard is formulated with a view to implementing the Environmental protection law of the People's Republic of China, Law of the People´s Republic of China on the prevention and control of radioactive pollution and Nuclear Security Law of the People's Republic of China, preventing the radioactive waste pollution, and improving the environmental quality.
This standard specifies the general requirements for near surface disposal of radioactive solid waste, and provides the general requirements for site selection, design, construction, operation, shutdown, monitoring, and environmental monitoring, safety case and quality assurance of near surface disposal sites.
This standard is a revision of GB 9132-1988 Regulation for shallow ground disposal of solid low-and intermediate-level radioactive wastes.
This standard was issued in 1988 as first edition.
The main revisions are as follows:
——the name of this standard is changed to Safety requirements for near-surface disposal of low and medium level radioactive solid waste;
——Clause 2 “Normative references" is added;
——the “waste package”, “safety case”, “passive safety features” and other terms are added in Clause 3 “Terms and definitions”;
——the “Basic requirements of waste disposal” in Clause 4 “General” is modified. The “site selection” is changed to Clause 6, and the “waste package” as Clause 5;
——the “Site selection procedure” in Clause 6 “Site selection” is subject to revision and the environmental protection requirements are added in accordance with the requirements of HJ/T 23;
——the activity concentration for near surface disposal of low level radioactive solid waste is required for meeting the requirements of the Classification of Radioactive Waste. The characteristics requirements of the waste is supplemented, and the “Waste packaging requirements” is revised according to the relevant standards of our country, and the “Waste packaging requirements” is changed to the “Waste package requirements”, which stipulates that the disposal site shall establish waste acceptance criteria;
——the requirements for the disposal unit are clearly defined in Clause 7 “Design and construction of the disposal site”, for the disposal site that receives the high surface dose rate waste package, “the equipment that shall be set up for remote or telecontrol transshipment and placement of waste packages” is proposed;
——the requirements for establishing a digital information management system for waste disposal and formulating an emergency plan are added in Clause 8 “Operation of disposal sites”. For the stage of simultaneous construction and operation of the disposal site, the requirements of “ensuring that relevant construction activities do not affect the safety of operation facilities” is proposed;
——the relevant contents of the three phases after the closure of the disposal site in Clause 9 “Closure of disposal sites” are deleted, and “the closure of disposal sites shall meet the requirements of closure permit documents” is specified;
——Clause 10 “Monitoring after the closure of the disposal site” and Clause 11 “Environmental monitoring of the disposal site” are added;
——Clause 9 “Safety assessment" is changed to Clause 12 “Safety case";
——Clause 13 “Quality assurance” is added;
——the “Annex A (Normative) Requirements for the contents of the waste package file” is added.
From the implementation of this standard, GB 9132-1988 Regulation for shallow ground disposal of solid low-and intermediate-level radioactive wastes and GB 16933-1997 Acceptance criteria for near surface disposal of radioactive waste are abolished.
Annex A of this standard is normative.
This standard was prepared by Department of Radioactive Sources Safety Supervision and Management and Department of Technology and Standard of the Ministry of Ecology and Environment.
Drafting organization: China Nuclear Power Engineering Co., Ltd.
This standard was approved by the Ministry of Ecology and Environment on July 10, 2018.
This standard shall be implemented from January 1, 2019.
The Ministry of Ecology and Environment is in charge of the explanation of this standard.
Safety requirements for near surface disposal of low and medium level radioactive solid waste
1 Application scope
This standard specifies the general requirements for near surface disposal of radioactive solid waste, and provides the general requirements for site selection, design, construction, operation, shutdown, monitoring, and environmental monitoring, safety case and quality assurance of near-surface disposal sites.
This standard is applicable to near surface disposal of low and medium level radioactive solid waste. With a considerable amount of long-lived nuclides, medium-level radioactive solid waste can’t only rely on monitoring measures to ensure the safe disposal of waste, and requires a higher allowance and isolation than low-level radioactive solid waste.
This standard is not applicable to the disposal of radioactive waste, natural radioactive waste generated during the development and utilization of uranium (thorium) mine and the cave disposal and drilling disposal of radioactive waste.
2 Normative references
The following normative document contain provisions which, through reference in this text, constitute provisions of this standard. For undated references, the latest edition of the normative document referred to applies.
GB 12711 Standard of safety for low and intermediate-level solid radioactive waste packages
GB 14569.1 Performance requirements for low and intermediate level radioactive waste form-Cemented waste form
GB 18871 Basic standards for protection against ionizing radiation and for the safety of radiation sources
GB 50011 Code for seismic design of buildings
GB 50223 Standard for classification of seismic production of building constructions
EJ 1186 Characterization of radioactive waste forms and packages
Classification of radioactive wastes, (Environmental Protection, notification of the Ministry of the Ministry of Industry and Information Technology, and State Administration of Science, Technology and Industry for National Defense, PRC (No. 65, 2017)
3 Terms and definitions
For the purpose of this standard, the following terms and definitions apply.
3.1
near surface disposal
the radioactive waste is placed in a facility of the surface or below the surface of tens meters, and an engineering barrier is set
3.2
waste package
waste-prepared products, including waste objects and containers, and linings that may be present to meet the requirements of handling, transport, storage, and/or disposal
3.3
institutional control
control of waste disposal sites by government agencies or their designated units the control includes active (monitoring, supervision, and facility maintenance) or passive (restricted land use) controls
3.4
closure
it contains normal closure and abnormal closure. Closure operations generally include backfilling, covering disposal facilities, terminating and finishing activities related to ancillary facilities to ensure the permanent closure the disposal site
3.5
safety case
it refers to document integration of arguments and demonstrations supporting and stating the science, technology, administration, and management of site safety, covering site suitability, design, construction and operation safety of facilities, and reasonableness of radiation risk assessment, and the adequacy and reliability of all works related to the safety of the disposal site
3.6
passive safety features
it refers to the natural safety characteristics in which disposal site allows the radioactivity, isolates radioactive waste and restrict the release of radionuclide to the biosphere, including physical barriers (such as engineering barriers, natural barriers and shielding), material performance (such as adsorptive performance of natural or artificial materials for radionuclide) and favorable properties of the site (such as topography and geological conditions that are conducive to the stability of the disposal site) etc.
4 General
4.1 Basic safety requirements of waste disposal
4.1.1 Waste disposal shall follow the principle of defense in depth, the multiple barriers (including waste objects, package containers, disposal units, geological bodies, etc.) shall be set to establish and maintain effective defense against radioactive hazards, and protect humans and environment from the harmful effects of ionizing radiation.
4.1.2 During the site selection, design, construction, operation and closure of the disposal site, effective measures shall be taken to ensure the stability of the disposal site.
4.1.3 Disposal site shall allow the radioactivity, isolate radioactive waste, and restrict the release of radionuclide to the biosphere (allowance and isolation time for low-level radioactive solid waste is generally 300 to 500 years).
4.1.4 The disposal system shall provide safety by multiple safety functions and its overall performance should not overly depend on a single safety function.
4.1.5 The design, construction, operation and closure of the disposal site shall be as much as possible to ensure safety by passive measures and minimize the necessity for continuous active maintenance after the closure of facility.
4.1.6 Site selection, construction, operation and closure shall be carried out in a progressive manner, and the iterative design and assessment of performance and safety of disposal system shall be conducted to support each step of site selection, construction, operation and closure.
4.1.7 In order to maintain the passive safety features of the disposal site and ensure the safety function after closure, the passive safety features of the disposal site shall be monitored and controlled.
4.2 Radiation protection requirements of waste disposal
4.2.1 The radiation exposure of the disposal site to the staff and the public under normal operating conditions and accident conditions shall meet the requirements of GB 18871.
4.2.2 The annual effective dose of radionuclide released to the environment by various means to a representative individual in the public is not more than 0.25 mSv.
4.2.3 Protection is provided to individuals who break into the disposal site unintentionally or touch the waste at any time after the release of the organized control of the disposal site. The annual effective dose of the unintentional individual is not more than 1 mSv, the effective dose of the single acute exposure is not more than 5 mSv.
Foreword i
1 Application scope
2 Normative references
3 Terms and definitions
4 General
5 Waste package
6 Site selection
7 Design and construction of the disposal site
8 Operation of the disposal site
9 Closure of the disposal site
10 Monitoring after closure of the disposal site
11 Environmental monitoring of the disposal site
12 Safety case
13 Quality assurance
Annex A (Normative) Requirements for the contents of the waste package file
Codeofchina.com is in charge of this English translation. In case of any doubt about the English translation, the Chinese original shall be considered authoritative.
This standard is formulated with a view to implementing the Environmental protection law of the People's Republic of China, Law of the People´s Republic of China on the prevention and control of radioactive pollution and Nuclear Security Law of the People's Republic of China, preventing the radioactive waste pollution, and improving the environmental quality.
This standard specifies the general requirements for near surface disposal of radioactive solid waste, and provides the general requirements for site selection, design, construction, operation, shutdown, monitoring, and environmental monitoring, safety case and quality assurance of near surface disposal sites.
This standard is a revision of GB 9132-1988 Regulation for shallow ground disposal of solid low-and intermediate-level radioactive wastes.
This standard was issued in 1988 as first edition.
The main revisions are as follows:
——the name of this standard is changed to Safety requirements for near-surface disposal of low and medium level radioactive solid waste;
——Clause 2 “Normative references" is added;
——the “waste package”, “safety case”, “passive safety features” and other terms are added in Clause 3 “Terms and definitions”;
——the “Basic requirements of waste disposal” in Clause 4 “General” is modified. The “site selection” is changed to Clause 6, and the “waste package” as Clause 5;
——the “Site selection procedure” in Clause 6 “Site selection” is subject to revision and the environmental protection requirements are added in accordance with the requirements of HJ/T 23;
——the activity concentration for near surface disposal of low level radioactive solid waste is required for meeting the requirements of the Classification of Radioactive Waste. The characteristics requirements of the waste is supplemented, and the “Waste packaging requirements” is revised according to the relevant standards of our country, and the “Waste packaging requirements” is changed to the “Waste package requirements”, which stipulates that the disposal site shall establish waste acceptance criteria;
——the requirements for the disposal unit are clearly defined in Clause 7 “Design and construction of the disposal site”, for the disposal site that receives the high surface dose rate waste package, “the equipment that shall be set up for remote or telecontrol transshipment and placement of waste packages” is proposed;
——the requirements for establishing a digital information management system for waste disposal and formulating an emergency plan are added in Clause 8 “Operation of disposal sites”. For the stage of simultaneous construction and operation of the disposal site, the requirements of “ensuring that relevant construction activities do not affect the safety of operation facilities” is proposed;
——the relevant contents of the three phases after the closure of the disposal site in Clause 9 “Closure of disposal sites” are deleted, and “the closure of disposal sites shall meet the requirements of closure permit documents” is specified;
——Clause 10 “Monitoring after the closure of the disposal site” and Clause 11 “Environmental monitoring of the disposal site” are added;
——Clause 9 “Safety assessment" is changed to Clause 12 “Safety case";
——Clause 13 “Quality assurance” is added;
——the “Annex A (Normative) Requirements for the contents of the waste package file” is added.
From the implementation of this standard, GB 9132-1988 Regulation for shallow ground disposal of solid low-and intermediate-level radioactive wastes and GB 16933-1997 Acceptance criteria for near surface disposal of radioactive waste are abolished.
Annex A of this standard is normative.
This standard was prepared by Department of Radioactive Sources Safety Supervision and Management and Department of Technology and Standard of the Ministry of Ecology and Environment.
Drafting organization: China Nuclear Power Engineering Co., Ltd.
This standard was approved by the Ministry of Ecology and Environment on July 10, 2018.
This standard shall be implemented from January 1, 2019.
The Ministry of Ecology and Environment is in charge of the explanation of this standard.
Safety requirements for near surface disposal of low and medium level radioactive solid waste
1 Application scope
This standard specifies the general requirements for near surface disposal of radioactive solid waste, and provides the general requirements for site selection, design, construction, operation, shutdown, monitoring, and environmental monitoring, safety case and quality assurance of near-surface disposal sites.
This standard is applicable to near surface disposal of low and medium level radioactive solid waste. With a considerable amount of long-lived nuclides, medium-level radioactive solid waste can’t only rely on monitoring measures to ensure the safe disposal of waste, and requires a higher allowance and isolation than low-level radioactive solid waste.
This standard is not applicable to the disposal of radioactive waste, natural radioactive waste generated during the development and utilization of uranium (thorium) mine and the cave disposal and drilling disposal of radioactive waste.
2 Normative references
The following normative document contain provisions which, through reference in this text, constitute provisions of this standard. For undated references, the latest edition of the normative document referred to applies.
GB 12711 Standard of safety for low and intermediate-level solid radioactive waste packages
GB 14569.1 Performance requirements for low and intermediate level radioactive waste form-Cemented waste form
GB 18871 Basic standards for protection against ionizing radiation and for the safety of radiation sources
GB 50011 Code for seismic design of buildings
GB 50223 Standard for classification of seismic production of building constructions
EJ 1186 Characterization of radioactive waste forms and packages
Classification of radioactive wastes, (Environmental Protection, notification of the Ministry of the Ministry of Industry and Information Technology, and State Administration of Science, Technology and Industry for National Defense, PRC (No. 65, 2017)
3 Terms and definitions
For the purpose of this standard, the following terms and definitions apply.
3.1
near surface disposal
the radioactive waste is placed in a facility of the surface or below the surface of tens meters, and an engineering barrier is set
3.2
waste package
waste-prepared products, including waste objects and containers, and linings that may be present to meet the requirements of handling, transport, storage, and/or disposal
3.3
institutional control
control of waste disposal sites by government agencies or their designated units the control includes active (monitoring, supervision, and facility maintenance) or passive (restricted land use) controls
3.4
closure
it contains normal closure and abnormal closure. Closure operations generally include backfilling, covering disposal facilities, terminating and finishing activities related to ancillary facilities to ensure the permanent closure the disposal site
3.5
safety case
it refers to document integration of arguments and demonstrations supporting and stating the science, technology, administration, and management of site safety, covering site suitability, design, construction and operation safety of facilities, and reasonableness of radiation risk assessment, and the adequacy and reliability of all works related to the safety of the disposal site
3.6
passive safety features
it refers to the natural safety characteristics in which disposal site allows the radioactivity, isolates radioactive waste and restrict the release of radionuclide to the biosphere, including physical barriers (such as engineering barriers, natural barriers and shielding), material performance (such as adsorptive performance of natural or artificial materials for radionuclide) and favorable properties of the site (such as topography and geological conditions that are conducive to the stability of the disposal site) etc.
4 General
4.1 Basic safety requirements of waste disposal
4.1.1 Waste disposal shall follow the principle of defense in depth, the multiple barriers (including waste objects, package containers, disposal units, geological bodies, etc.) shall be set to establish and maintain effective defense against radioactive hazards, and protect humans and environment from the harmful effects of ionizing radiation.
4.1.2 During the site selection, design, construction, operation and closure of the disposal site, effective measures shall be taken to ensure the stability of the disposal site.
4.1.3 Disposal site shall allow the radioactivity, isolate radioactive waste, and restrict the release of radionuclide to the biosphere (allowance and isolation time for low-level radioactive solid waste is generally 300 to 500 years).
4.1.4 The disposal system shall provide safety by multiple safety functions and its overall performance should not overly depend on a single safety function.
4.1.5 The design, construction, operation and closure of the disposal site shall be as much as possible to ensure safety by passive measures and minimize the necessity for continuous active maintenance after the closure of facility.
4.1.6 Site selection, construction, operation and closure shall be carried out in a progressive manner, and the iterative design and assessment of performance and safety of disposal system shall be conducted to support each step of site selection, construction, operation and closure.
4.1.7 In order to maintain the passive safety features of the disposal site and ensure the safety function after closure, the passive safety features of the disposal site shall be monitored and controlled.
4.2 Radiation protection requirements of waste disposal
4.2.1 The radiation exposure of the disposal site to the staff and the public under normal operating conditions and accident conditions shall meet the requirements of GB 18871.
4.2.2 The annual effective dose of radionuclide released to the environment by various means to a representative individual in the public is not more than 0.25 mSv.
4.2.3 Protection is provided to individuals who break into the disposal site unintentionally or touch the waste at any time after the release of the organized control of the disposal site. The annual effective dose of the unintentional individual is not more than 1 mSv, the effective dose of the single acute exposure is not more than 5 mSv.
Contents of GB 9132-2018
Foreword i
1 Application scope
2 Normative references
3 Terms and definitions
4 General
5 Waste package
6 Site selection
7 Design and construction of the disposal site
8 Operation of the disposal site
9 Closure of the disposal site
10 Monitoring after closure of the disposal site
11 Environmental monitoring of the disposal site
12 Safety case
13 Quality assurance
Annex A (Normative) Requirements for the contents of the waste package file
