放射性廢棄物處理貯存及其設施安全管理規則

This Regulations is enacted pursuant to Article 21 of the Nuclear Materials and Radioactive Waste Management Act.

1The terms used in this Regulations are defined as follows:

21.Thermal treatment of radioactive waste: using high temperature methods such as incineration and melting to treat the radioactive waste.

32.Contaniners: the vessels used to store or dispose of the radioactive waste.

43.Maintenance: the operations such as removal of rust, repainting, repacking, and re-solidifying in case of rust and erosion of the radioactive waste containers or deterioration of radioactive waste.

54.Stabilization treatment: the treatment to make radioactive waste reach condition stabilizing in physical state and chemical properties.

The treatment and storage of radioactive waste shall comply with the provisions of the Ionizing Radiation Protection Act.

1The design of the radioactive waste treatment facilities (hereinafter referred to as "treatment facilities") shall comply with the following provisions:

21.The treatment facilities shall be provided with such functions as fireproof, explosion-proof, and overflow collection;

32.The treatment facilities shall employ seismic-resistant design, to ensure the safety of equipment and structures;

43.The design of the waste treatment system, equipment, or component shall be able to suppress deterioration, prevent leakage, and reduce the volume of the waste;

54.Equipment used to detect the discharge of gas or liquid watse shall be provided.

1Where a thermal treatment system is used in the treatment facilities, its design shall comply with the preceding Article and the following provisions:

21.The treatment equipment of radioactive exhaust gas shall be redundant.

32.The workshop buildings shall be designed with negative pressure.

1The radiation protection design of the treatment facilities shall ensure the annual individual effective dose to the general public outside the facilities shall not exceed 0.25 mSv, and conform to the as low as reasonably achievable principle.

2The radiation protection design of the waste treatment system of nuclear reactors shall meet the provisions of the laws and regulations on the control of nuclear reactors.

The treatment facilities shall be operated in accordance with the safety analysis report of the facilities and the regulations on radiation safety protection.

1To implement homogeneous solidification of radioactive waste, a solidification process control plan including the following contents shall be submitted to the competent authority for approval prior to implementation:

21.General description.

32.Solidification system and solidification operation flow.

43.Sampling and analysis of the radioactive waste prior to solidification.

54.Container of the solidified waste.

65.Standard of the solidified waste form and the test results.

76.Countermeasures measure for the unqualified solidified waste.

87.Quality assurance.

98.Other matters designated by the competent authority.

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1The containers shall comply with the following provisions:

21.The materials, design, and manufacturing shall be able to prevent corrosion and deterioration, and ensure the integrity of the structure within the design lifetime.

32.Convenience for operation and handling shall be considered.

43.The mechanical strength is sufficient to endure the load of hoisting, conveying, storage, and final disposal.

54.The covers and fastening pieces of the containers shall be convenient to operate, and shall not be loosened or break off during the process of hoisting and conveying.

65.The exterior of the containers shall be smooth, and easy to decontaminate and avoid water from being accumulated on the top.

7The containers aforementioned in the preceding paragraph shall consider technical feasibility in each stage of the treatment, storage, transport and final disposal operations of radioactive waste.

1The containers shall only be used after having been approved. The applicant shall submit a report including the following contents to the competent authority for review and approval prior to using the containers:

21.Scope of application.

32.Design standards, detailed engineering design and illustrations.

43.Materials, composition, dimensions, manufacturing, and corrosion prevention of the containers.

54.Test methods, standards, and results.

65.Quality assurance.

76.The technical feasibility assessment on the containers in each stage of the treatment, storage, transport and final disposal operations of radioactive waste.

87.Other matters designated by the competent authority.

Where the surface radiation dose of a container holding radioactive waste exceeds 2 mSv/h, it shall be operated by means of remote control or by enhanced radiation protection control.

1The threshold values of non-fixed contamination on the surface of a container holding radioactive waste are as follows:

21.The contamination of Beta and Gamma nuclides shall not exceed 4 Bq/cm2.

32.The contamination of Alpha nuclides shall be not more than 0.4 Bq/cm2.

The surface of a container holding radioactive waste shall be marked with a radiation warning symbol and a serial number. The radius of the inner circle of the radiation warning symbol shall be not less than 2 cm.

1The design of radioactive waste storage facilities (hereinafter referred to as "storage facilities") shall meet the following provisions:

21.Radiation monitoring equipment shall be provided.

32.Fire detecting or firefighting equipment shall be provided.

43.The function of discharged water collecting and sampling equipment shall be provided.

54.The functions of receiving, detecting, operation monitoring, and storage of waste shall be provided.

65.The maximum storage activity and storage capacity shall be determined.

76.Appropriate measures shall be adopted to reduce the rate of corrosion of the containers.

87.The waste in the storage facilities is retrievable.

98.Seismic-resistant design shall be provided to ensure the safety of the equipment and structure.

1Paragraph 1 of Article 5 shall apply mutatis mutandis to the radiation protection design of the storage facilities.

2The radiation-protection design of the storage facilities of nuclear reactors shall meet the provisions of the laws and regulations on the control of nuclear reactors.

The storage facilities shall be operated in accordance with the safety analysis report of the facilities and the regulations on radiation safety protection.

1The low-level radioactive waste generated by the operation of the treatment facilities and the nuclear reactor facilities shall not be stored for more than five years without being stabilized.

2If it is assessed that it cannot be stabilized within five years, the operator shall submit a plan for the stabilization, and report to the competent authority for approval before continuing to store.

1Where corrosion or deformation of containers or deterioration of the solidified waste form occurs when the low-level radioactive waste storage facilities are receiving radioactive waste or during the period of operation, the operator shall carry out maintenance.

2The maintenance operations shall meet the following provisions:

31.Where the climate is not suitable for maintenance, the operations shall be suspended.

42.Training on radiation protection, maintenance operation, emergency response, and labor safety and hygiene shall be provided for the maintenance workers.

53.Maintenance shall be performed under the supervision of the radiation protection personnel recognized by the competent authority.

64.The maintained containers shall be marked in accordance with the provisions of Article 12.

75.The threshold values of non-fixed contamination on the surface of the maintained containers shall meet the provisions of Article 11.

86.The concentration of the suspended substances in the air in the maintenance operation area shall meet the provisions of the Ionization Radiation Protection Act.

1The operators shall evaluate the storage facilities once every ten years after the operating license is issued or renewed, and submit an evaluation report including the following contents to the competent authority for review and approval:

21.General description.

32.Examination and evaluation of the facility structures.

43.Examination and evaluation of the hoisting equipment.

54.Evaluation of the storage status of the waste.

65.Evaluation of storage operations.

76.Evaluation of the impacts of radiation.

87.Lesson learnt of the abnormal events occurred in past ten years.

98.Preliminary decommissioning plan.

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1Where corrosion or deformation of containers or deterioration of the solidified waste is found in the evaluation of the storage facilities performed once every ten years, the operator shall submit a maintenance plan including the following contents to the competent authority, and implement the plan after it is approved:

21.General descriptions of the operation, including work contents, personnel organization, time schedule, work place, and layout of the storage area after maintenance is finished.

32.Equipment used for maintenance, including treatment equipments and solidifying agents.

43.Procedure of maintenance.

54.Radiation protection measures.

65.Waste management after maintenance is finished.

76.Industrial safety and hygiene measures.

87.Evaluation for personnel dose and environmental radiation impacts.

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To treat the radioactive waste caused by accidents or in case of damage of a container holding radioactive waste due to accidents, the waste shall be firstly moved into the storage facilities. And then the operator shall, within one month, submit a maintenance plan according to the provisions of the preceding Article to the competent authority for approval prior to implementation.

The provisions of Article 9 are not applicable to the containers that have already been approved before this Regulations is enforced.

This Regulations shall be put into practice from the date of promulgation.