The design of the treatment facilities of radioactive waste (hereinafter shortened as “treatment facilities”) shall meet the following provisions:
1. The treatment facilities shall be provided with such functions as fire proof, explosion proof, and overflow collecting;
2. The treatment facilities shall employ seismic resistant design, able to ensure the safety of equipment and structure;
3. 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;
4. Equipment used to detect the discharge of gas or liquid waste shall be provided.

Where thermal treatment system is used in the treatment facilities, the design shall meet the above article and the following provisions:
1. The treatment equipment of radioactive exhaust gas shall be redundant.
2. Negative pressure design shall be equipped for the workshop buildings.

The radiation protection design of the treatment facilities shall ensure the annual effective dose equivalent to a general public outside the facilities is not more than 0.25mSv, and confirm to the as low as reasonably achievable principle.
The 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.

To implement homogenous 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:
1. General description.
2. Solidification system and solidification operation flow.
3. Sampling analysis of the radioactive waste prior to solidification.
4. Container of the solidified waste.
5. Standard of the solidified waste form and the test results.
6. Counter measure for the unqualified solidified waste.
7. Quality assurance.
8. Other matters designated by the competent authority.
To modify the solidification process control plan, an application shall be submitted in accordance with the provisions of the preceding paragraph.

The containers shall meet the following provisions:
1. The materials, design, and manufacturing shall be able to prevent corrosion and deterioration, and ensure the integrity of the structure within the design lifetime.
2. Convenience for operation and handling shall be considered.
3. The mechanic strength is sufficient to endure the load of hoisting, conveying, storage, and final disposal.
4. The covers and fastening pieces of the containers shall be convenient to operate, and will not be loosened or break off during the process of hoisting and conveying.
5. The exterior of the containers shall be even, and easy to decontamination and avoid water from being accumulated on the top.
The containers aforementioned in the preceding paragraph should consider technical feasibility in each stage of the treatment, storage, transport and final disposal operations of radioactive waste.

The containers can only be used after having been approved. The applicant shall submit a report including the following contents to the competent authority for reviewing and approval prior to using the containers:
1. Scope of application.
2. Design standards, detailed engineering design and illustrations.
3. Materials, composition, dimensions, manufacturing, and corrosion prevention of the containers.
4. Test methods, standards, and results.
5. Quality assurance.
6. The technical feasibility assessment on the containers in each stage of the treatment, storage, transport and final disposal operations of radioactive waste.
7. Other matters designated by the competent authority.

Where the surface radiation dosage of a container that is filled with radioactive waste is more than 2mSv/h, it shall be operated by means of remote control or by strengthening radiation protection control.

The threshold values of non-adhesive contamination on the surface of a container that is filled with radioactive waste are as follows:
1. The contamination of Beta and Gamma nuclides shall be not more than 4Bq/cm2.
2. The contamination of Alfa nuclides shall be not more than 0.4Bq/cm2.

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