| Legislative： |
1.中華民國九十二年十月八日行政院原子能委員會會物字第 0920026524
號令訂定發布全文 21 條；並自發布日施行
2.中華民國九十七年一月二十四日行政院原子能委員會會物字第 0970001
431 號令修正發布第 5 條條文
3.中華民國九十七年十月二十二日行政院原子能委員會會物字第 0970016
963 號令修正發布第 2、15 條條文；並增訂第 2-1、15-1 條條文 |
| Content： |
Regulations on Treatment and Storage of Radioactive
Waste and Safety Management of the Facilities
Enforced by Letter Hui-Wu-Tzu No.0920026524
October 8, 2003
Chapter 1 General Principles
Article 1 These Regulations are enacted pursuant to Article 21 of the Nuclear
Materials and Radioactive Waste Management Act.
Article 2 The terms used in these Regulations are defined as follows:
1. Thermal treatment of radioactive waste: using high temperature
methods such as incineration and melting to treat the
radioactive waste.
2. Containers: the vessels used to store or disposal the radioactive
waste.
3. Maintenance: the operations such as removal of rust, repainting,
repacking, and re-solidifying in case of rust and erosion of the
containers of radioactive waste or deterioration of radioactive
waste.
Chapter 2 Requirements on Treatment Facilities and Operations
Article 3 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.
Article 4 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
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redundant.
2. Negative pressure design shall be equipped for the workshop
buildings.
Article 5 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.
Article 6 The treatment facilities shall be operated in accordance with the
safety analysis report of the facilities and the regulations on radiation
safety protection.
Article 7 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.
Article 8 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
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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.
Article 9 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:
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. Other matters designated by the competent authority.
Article 10 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.
Article 11 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.
Article 12 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.
Chapter 3 Requirements on Storage Facilities and Operations
Article 13 The design of the storage facilities of radioactive waste (hereinafter
shortened as “storage facilities”) shall meet the following provisions:
1. Radiation monitoring equipment shall be provided.
2. Fire detecting or fire fighting equipment shall be provided.
3. The function of discharged water collecting and sampling
equipment shall be provided.
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4. The functions of receiving, detecting, operation monitoring, and
storage of waste shall be provided.
5. The maximum storage activity and storage capacity shall be
determined.
6. Appropriate measures shall be adopted to reduce the rate of
corrosion of the containers.
7. The waste in the storage facilities is retrievable.
8. Seismic resistant shall be provided to ensure the safety of the
equipment and structure.
The design of the storage facilities of high level waste shall meet the
following provisions additionally:
1. The functions of heat removal and maintaining the sub-critical
shall be provided.
2. The requirements on nuclear protection shall be satisfied.
Article 14 The radiation protection design of the storage facilities shall be made
in accordance with the provisions of Paragraph 1, Article 5.
The 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.
Article 15 The storage operations of radioactive waste shall meet the safety
analysis report of the storage facilities and the relevant provisions on
radiation safety protection.
Article 16 Where corrosion or deformation of container or deterioration of the
solidified waste form occurs when the storage facilities are receiving
radioactive waste or during the period of operation, the operator shall
carry out maintenance.
The maintenance operations shall meet the following provisions:
1. Where the climate is not suitable for maintenance, the operations
shall be suspended.
2. Training on radiation protection, maintenance operation,
emergency response, and labor safety and hygiene shall be
provided for the maintenance workers.
3. Maintenance shall be performed under the supervision of the
radiation protection personnel recognized by the competent
authority.
4. The maintained containers shall be marked in accordance with the
provisions of Article 12.
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5. The threshold values of non-fixed contamination on the surface of
the maintained containers shall meet the provisions of Article 11.
6. The concentration of the suspended substances in the air in the
maintenance operation area shall meet the provisions of the
Ionization Radiation Protection Act.
Article 17 The operators shall evaluate the storage facilities once every ten years,
and submit an evaluation report including the following contents to
the competent authority for review and approval:
1. General description.
2. Examination and evaluation of the facility structures.
3. Examination and evaluation of the hoisting equipment.
4. Evaluation of the storage status of the waste.
5. Evaluation of storage operations.
6. Evaluation of the impacts of radiation.
7. Lesson learnt of the abnormal events occurred in past ten years.
8. Preliminary decommission plan.
9. Other matters designated by the competent authority.
Article 18 Where corrosion or deformation of container 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:
1. General descriptions of the operation, including work contents,
personnel organization, time schedule, work place, and layout of
the storage area after maintenance is finished.
2. Equipments used for maintenance, including treatment
equipments and solidifying agents.
3. Procedure of maintenance.
4. Radiation protection measures.
5. Waste management after maintenance is finished.
6. Industrial safety and hygiene measures.
7. Evaluation for personnel dose and environmental radiation
impacts.
8. Response measures for accidents.
9. Quality assurance measures.
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10. Other matters designated by the competent authority.
The operators shall, within six months after the maintenance plan is
finished, submit a report on the proceeding of maintenance to the
competent authority for review and approval.
Article 19 To dispose the radioactive waste caused by accidents or in case of
damage of a container filled with 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.
Chapter 4 Supplementary Provisions
Article 20 The provisions of Article 9 are not applicable to the containers that
have already been approved before these Regulations are enforced.
Article 21 These Regulations will take effect as of the date of promulgation. |