Nội dung toàn văn Circular No.22/2014/TT-BKHCN on the management of radioactive wastes and used radioactive sources
MINISTRY OF SCIENCE AND TECHNOLOGY | SOCIALIST REPUBLIC OF VIETNAM |
No.: 22/2014/TT-BKHCN | Hanoi, 25 August, 2014 |
CIRCULAR
ON THE MANAGEMENT OF RADIOACTIVE WASTES AND USED RADIOACTIVE SOURCES
Pursuant to the Law on Atomic Energy dated 3 June 2008;
Pursuant to governmental Decree No. 20/2013/NĐ-CP dated 26 February 2013 regulating the functions, duties, authority and organizational structure of the Ministry of Science and Technology;
As proposed by the Directors of Vietnam Agency for Radiation & Nuclear Safety and Department of Legal Affairs;
The Minister of Science and Technology hereby promulgates this Circular regulating the management of radioactive waste and used radioactive sources.
Chapter I
GENERAL PROVISIONS
Article 1. Governing scope and regulated subjects
1. This Circular regulates the principles and requirements applicable to the management of radioactive waste and used radioactive sources [“the waste and sources”], responsibilities of related organizations and/or individuals for the management of the waste and sources, except the following issues:
a) Management of used nuclear materials;
b) Management of the waste containing naturally occurring radioactive materials (NORM waste) generated from mining and/or processing of ores, minerals and petroleum mining;
c) Burial of radioactive waste and used radioactive sources.
2. This Circular is applicable to the organizations and/or individuals conducting such activities in Vietnam that generate the radioactive wastes and used radioactive sources and are related to the management of the waste and/or sources.
Article 2. Terminology explanation
The terms herein and hereunder are interpreted as follows:
1. Radioactive waste means the waste that contains radioactive nuclei or the materials contaminated with radioactive nuclei with higher radioactivity level than the disposal level as defined herein and compulsorily requiring to be disposed of. Radioactive waste does not include the used radioactive sources.
2. Used radioactive source means the sealed radioactive source that an organization and/or individual possessor no longer uses for licensed radiation and has no intention to continue using for any other purposes or not licensed for use by Vietnam Agency for Radiation and Nuclear Safety [“VARANS”].
3. Radiobiological waste means the biological waste that contains or is contaminated with the radioactive nuclei with higher radioactivity level than the disposal level. Biological waste includes the biodegradable and biomedical waste.
Biodegradable waste means the waste degradable after a period of time, turning into a stem compound due to microorganisms. This type of waste includes living solid waste generated from grass, plants, food, paper, degradable plastic, human and/or animal waste.
Biomedical waste means the waste likely to decompose or carry infections which is produced from health check and/or treatment at health facilities, medical laboratories and mortuaries. This type of waste includes waste materials and/or utilities discharged from the mentioned facilities such as medical cotton, bandages, compresses, clothes, gloves, syringe needles, syringes, human and/or animal tissues.
4. Radioactive waste source owner means the organization and/or individual who is licensed to carry out radioactive activities whereby the radioactive waste is generated due to the nature of such radiation activities or a radioactive waste generating incident negligently occurs during problem solving.
5. Used radioactive source owner means the organization and/or individual who creates the used radioactive source from the licensed radioactive activities.
6. Radioactive waste storage enterprise means the enterprise that is licensed by Vietnam Agency for Radiation and Nuclear Safety to carry out irradiation activities for treatment and storage of radioactive waste and/or used radioactive sources.
7. Liquidation level means the value of specific activity of radionuclides therefrom if a radionuclide-containing waste has smaller specific activity than or equal to it, such waste will not be considered causing radioactive harms to human and environment and be handled as non-radioactive waste.
Article 3. Management principles applicable to radioactive wastes and/or used radioactive sources
1. Radioactive waste shall be managed in such a way to ensure human and environmental safety since it is generated until it is permissibly disposed as non-hazardous waste or buried or recycled in case of contaminated metal. Used radioactive sources shall be managed in a such a way to ensure human and environmental safety until they are returned to foreign manufacturers, suppliers or buried.
2. Radioactive waste and/or used radioactive sources shall be managed closely to ensure not to harm human and environment, presently and in the future, be ensured that the total radioactivity affecting the radioactivation operators and the public shall not exceed the limit value defined in Circular No. 19/2012/TT-BKHCN dated 8 November 2012 issued by the Minister of Science and Technology, regulating radiation safety control and assurance in occupational exposure and public exposure.
3. Used radioactive sources shall be returned to foreign manufacturers or suppliers in case such manufacturers and/or suppliers wish to receive them.
4. The management of radioactive waste in which harmful non-radioactive properties still exist shall conform not only the regulations herein but also other legal regulations related to harmful waste management.
5. The waste containing radionuclides generated from a radiation activity may be permissibly discharged directly to environment, provided that the specific activity of such waste is not higher than the liquidation level or total activity of the radionuclides in the gas and/or liquid properties of the waste shall not exceed the radioactivity permitted by related governmental authorities for being discharged to the environment, and the disposal of the mentioned waste requires permit in accordance with the license for radioactive activities.
6. The contaminated objects, which are iron, copper, lead, aluminium (hereafter referred to as “contaminated metal”), and the products melted directly from the mentioned metal may be used in recycling if radionuclide specific activity of such metal and the surface contamination level of the metal is lower or equal to the recycling-permitting level as defined in Appendix IV herein.
7. It is prohibited to add non-radioactive agents to the radioactive waste to reduce specific activity of such waste so that the waste can meet environmental disposal or recycling standards.
Chapter II
REQUIREMENTS FOR MANAGING THE RADIOACTIVE WASTE, USED RADIOACTIVE SOURCES
Article 4. Radioactive waste collection
1. Solid radioactive waste shall be collected, separated from the non-radioactive wastes and classified according to the half-life of radionuclides, radioactivity of the waste and physio-chemical characteristics of the waste (combustible wastes, compressible wastes, metal or bio-wastes) in accordance with the regulation on radioactive waste classification defined in Appendix I herein so as to support the management stage. Solid radioactive waste collection shall adhere to the following requirements:
a) Solid proactive waste shall be collected and classified separately;
b) When collecting solid radioactive waste contained in containers, the containers must have covers which can be opened/controlled by foot, be lined with bags or plastic bags inside, be appropriately covered to protect radioactive workers from radiation exposure, and bear the radioactive warning sign on the outside. Radioactive waste bags shall be in different colors for different radioactive wastes;
c) Upon collecting, solid radioactive waste boxes, bags shall be packed with care, labeled for identification before being relocated to a temporary storage area, label information shall be as follows:
- Identification number of the boxes, bags;
- Radionuclides found in the waste;
- Waste classification;
- Waste-generating source;
- Other potentially harmful factors (e.g. chemically, pathogenically, combustibly, explosively);
- Radiation dose rate on the surfaces of boxes, bags and measurement date.
d) Collected solid radioactive waste shall be documented with the following information:
- Quantity of collected solid radioactive waste;
- Identification information of every box, bag which contains radioactive waste;
- Storage date.
2. Liquid radioactive waste (hereafter referred to as “radioactive wastewater”) shall be collected and separated from the non-radioactive wastewater and conducted to storage tanks or containers. Radioactive wastewater collection shall adhere to the following requirements:
a) If barrels are used for containing wastewater, such barrels shall be appropriately covered to prevent radiation exposure to the operators and leaking to the environment. A barrel collecting radioactive wastewater shall be housed in a metal barrel, with an absorbable substance in between to absorb leaking water. Both barrels shall be tightly closed, labeled with radiation warning;
b) The containers for collecting radioactive wastewater shall have identification labels in accordance with the regulation applicable to the boxes and/or bags for collecting solid waste before the waste is relocated to temporary storage;
c) Radioactive wastewater reservoirs shall be located and designed in such a way that conforms to the requirements defined in Clause 5 of Article 9 herein.
d) Collected radioactive wastewater shall be documented and filed with the following information:
- Number of collected radioactive wastewater containers and identification information of each container;
- Volume of collected radioactive wastewater (m3) and collection date ;
- Key radionuclides found in the wastewater and its origin.
3. Collected radioactive waste shall be stored, treated, conditioned, discharged into the environment or relocated as defined in Articles 5, 6, 7, 8 and 9 herein.
Article 5. Waste disposal to the environment
1. Radionuclide-containing gas waste generated from the facilities which use radioactive substances in medicine, industry and researches shall be filtered and controlled to ensure that the quantity of radionuclides in the mentioned waste gas to be discharged to the environment does not exceed the regulated permissible limit as defined in Table 01 of Appendix III herein under normal operation conditions. Discharge of the gas waste to the environment from the related facilities shall require permission based on the radioactive activity license.
2. Radionuclide-containing gas waste generated from nuclear power plants, research nuclear reactors shall be treated to eliminate radioactive constituents to ensure that the dose of public exposure due to the discharge of gas waste and wastewater to the environment from the mentioned facilities [plants and/or reactors] does not exceed 100 µSv/year. Gas waste discharged from the related facilities shall required permission based on the radioactive activity license, and the volume of the waste gas discharged to the environment, its radioactivity will be measured, inspected and documented.
3. Solid radioactive waste, categorized as the low-level and/or very-short-lifespan waste, shall be stored at the related facilities and left disintegrating until it reaches such an specific activity that is smaller or equal to the liquidation level as defined in Appendix II herein before it is discharged as unharmful waste.
4. Radioactive wastewater from health, industrial and research facilities, where radioactive substances are used, shall be stored at such facilities for disintegration or treated to eliminate the radioactive substances, ensuring that the radionuclides in the wastewater shall not exceed the regulated level as defined in Table 2 of Appendix III herein.
5. Radioactive wastewater from nuclear power plants, research nuclear reactors shall be treated to eliminate the radioactive properties, ensuring that the wastewater discharged from the facilities to the environment shall adhere to the regulation on the radioactivity rate exposed to the public as defined in Clause 2 of this Article.
6. The process of disposing radionuclide-containing solid waste and wastewater to the environment requires the permission based on the radioactive activity license and every disposal shall be documented with the following information:
a) Form (solid or liquid) and quantity of the waste, wastewater (kg or m3) disposed to the environment;
b) Radionuclide properties of the waste;
c) Disposal process and location;
d) Measurement method and results for checking the radioactivity of the waste when it is disposed of to the environment.
7. Once the disposal of radionuclide-containing waste to the environment exceeds the permissible limit, the radioactive waste owner shall investigate the causes and apply required measures to improve the consequences, and within 5 working days since the day the excessive disposal incident happens, written reports shall be sent to Vietnam Agency for Radiation & Nuclear Safety and the Department of Science & Technology of the area where radioactive-waste-generating radiation activities take place.
Article 6. Transfer of the radioactive wastes, used radioactive sources
1. Transfer of radioactive waste to the storage facilities shall adhere to the following requirements:
a) Signed radioactive waste transfer agreement between the transferor and the transferee, in which full names, addresses of both parties, information and quantity of the radioactive waste, identification number of each package of radioactive waste, clear indication of the post-transfer in-charge managerial organization and/or individual towards such waste are indicated.
b) The transferer shall be financially liable to the treatment and/or storage costs, under sharing basis, incurred to the radioactive waste storage party;
c) Legal regulations related to radioactive material transport permit shall be adhered to;
d) Delivery of radioactive waste shall be documented (3 copies) as per Form No. 01 in Appendix V herein, signed by the transferer, the courier and the transferee/recipient; 01 copy is kept by each party;
dd) The delivery shall be checked and confirmed by the related parties, ensuring that radioactive waste is transferred properly in terms of quantity, category and to the right address of the contractual transferee;
e) Within 5 working days since the completion day of the radioactive waste transfer, the waste owner shall send copies of the minutes on radioactive waste transfer to Vietnam Agency for Radiation & Nuclear Safety and the Department of Science & Technology, one for each agency, of the area where radiation activities causing radioactive waste take place.
2. Transfer of contaminated metal to the recycling facilities shall be documented and filed with the following information:
a) Metal type;
b) Transfer quantity;
c) Codes of the transfer batches;
d) Inspection results of the contamination of the radioactive waste;
dd) Transfer date and names, addresses of the transferer and the transferee.
3. Transfer of the used radioactive source to the foreign manufacturer or supplier shall adhere to the following requirements:
a) Signed contract between the Vietnamese transferer and the foreign transferee, with names, addresses of both parties, information on the name, radioactivity, model and serial number of the radioactive source clearly indicated;
b) Legal regulations on radioactive source transport, export permit application shall be adhered to;
c) Within 5 working days since the completion date of the export customs procedure for the radioactive source, the owner of the used radioactive source shall send a report on the used radioactive source export, following Form No. 2 in Appendix V herein, and copies of the proofs verifying the actual export of the radioactive source by the customs authority, to Vietnam Agency for Radiation & Nuclear Safety and the Department of Science & Technology of the area where the radioactive source is used in case such source is used at a fixed location, or the Department of Science & Technology of the area where the head office of the used radioactive source owner is located in case the radioactive source is used at different locations.
4. Transfer of the used radioactive source to another organization and/or individual or a storage facility shall adhere to the following requirements:
a) Signed radioactive source transfer contract, in which the names, addresses of the transferer and transferee, information on the name, radioactivity, model, serial number of the radioactive source, and the organization and/or individual responsible for post-transfer safety and/or security management of the radioactive source are clearly specified;
b) In case the used radioactive source is transferred to a storage facility, the transferer shall be financially liable for the storage costs incurred to the storage facility under sharing basis;
c) Legal regulations on radioactive material transport permit application shall be adhered to;
d) Transfer of the used radioactive source shall be documented (3 copies), following Form No. 3 in Appendix V herein, signed by the representatives of the transferer, transportation party and the transferer; 01 copy is kept by each party;
dd) The transfer shall be checked and confirmed by the related parties, ensuring that radioactive waste is transferred properly in terms of quantity, category and to the right address of the contractual transferee;
e) Within 5 working days since the completion day of the radioactive source transfer, the used radioactive source owner shall send copies of the minutes on radioactive source transfer to Vietnam Agency for Radiation & Nuclear Safety and the Department of Science & Technology, one for each agency, as defined in Point c of Clause 3 of this Article.
Article 7. Radioactive waste treatment
1. Solid radioactive waste, but not categorized as the low-level and/or very-short-lifespan waste, shall be treated in accordance with its characteristics before being conditioned and be stored as follows:
a) Solid radioactive waste shall be compressed or pressed to decrease the volume if it is determined to be the waste compressible and/or able to be pressed and ensure that:
- The waste does not contain any constituent likely to cause chemical reactions or damage the waste package when being conditioned;
- No radioactive source is found in the waste.
- The constituents likely to cause disease transmission have been removed from the waste or sterilized;
- Pressurized cylinders are not found in the waste;
- The waste is dried prior to compression, pressing.
b) Solid radioactive waste shall be burned if it is determined to be a combustible waste and:
- Radioactive sources are not found in the waste;
- Pressurized barrels are not found in the waste;
- The technology which can control complete combustion of wet materials and waste gas treatment to the level disposable to the environment is available;
- The management solution for generated radioactive ash.
2. The radionuclide-containing radioactive wastewater with half-life ≥ 100 days shall be treated to separate radionuclides from the wastewater, ensuring the radioactivity remained in the wastewater to be lower or equal to the environmental disposal level after being treated as defined in Appendix II herein. Treatment of the radioactive wastewater shall ensure that:
a) The treatment method is appropriate with the characteristics of the radioactive wastewater;
b) The secondary waste elements, created from the radioactive wastewater treatment, shall be treated and conditioned in accordance with the requirements applicable to solid radioactive waste.
3. Radiobiological waste shall be sterilized with gas, radiation, and microbially controlled with chemicals, heat treated before the treatment measures defined in Clauses 1 and 2 of this Article are applied.
Article 8. Conditioning of radioactive wastes and used radioactive sources
1. After being treated, the solid radioactive waste shall be conditioned to form a conditioned radioactive waste load and the used radioactive source shall be conditioned to form a conditioned used radioactive source or stored in related container for transportation, long storage, minimizing the leaking of the radioactive materials to the environment and alleviating human harm. Various radioactive wastes shall be conditioned to form a particularly conditioned load.
2. Radioactive waste shall be conditioned by freezing the treated waste in a material load (such as cementation, bituminization, polymerization…) before housing it in a container and covering it (e.g. housed by a drum) to form a conditioned radioactive waste load.
3. Conditioned radioactive waste load shall meet the following requirements:
a) The radioactive waste load shall have the maximum surface radiation dose rate of not over 2 mSv/h (200 mrem/h) and not over 0.1 mSv/h (10 mrem/h) at the area 1 meter away from its surface; average surface contamination of not over 4 Bq/cm2 for the materials radiating beta, gamma, alpha with low toxicity and not over 0.4 Bq/cm2 for other alpha-radiating materials;
b) Every conditioned radioactive waste load shall be marked with radioactivity sign, labeled and noted in the information sheet filed in the storage record to ensure long-term management and accessibility. Labels on the conditioned radioactive waste loads shall include the following information:
- Identification number of the load;
- The load weight;
- Maximum radiation dose rate on the load’s surface and 1 meter from such surface, surface contamination level and measurement date.
Information sheet of the conditioned radioactive waste load filed in the storage record shall include not only the information indicated on the load’s label but also the following additional information:
- Origin of the load’s radioactive waste;
- Form and design details of the radioactive waste load;
- Dimension and volume of the radioactive waste load;
- Radionuclides and radioactive concentration of the radioactive waste load;
- Quantity of the fissile materials found in the radioactive waste load;
- Other potential harms of the radioactive waste load;
4. Radioactive source, used radioactive radioactively leaked, shall be conditioned in the same manner as applied to radioactive waste to form the conditioned load of used radioactive source; used radioactive source, which remains intact, without radioactive leakage, may be stored in the related containers or conditioned in the same manner as applied to radioactive waste depending on the characteristics of such radioactive source and the choice of the storage facility. The conditioned load of used radioactive source and its container shall conform to the following requirements:
a) Adhering to the requirements applied to conditioned radioactive waste load as defined in Point a of Clause 3 of this Article;
b) Radioactive source container shall be safely locked to prevent the source from being illegitimately taken out of the container, protect the source from mechanical and/or fire, explosion effects;
c) Every conditioned load of used radioactive source, its container shall be marked with radiation warning sign, labeled and noted in the information sheet filed in the storage record to ensure long-term management and accessibility. Labels on the conditioned loads of used radioactive source and related containers shall include the following information:
- Identification number of the conditioned load of used radioactive source, related container;
- Maximum radioactivity dose rate on the load’s surface, 1 meter from the surface and surface contamination of the conditioned load of used radioactive source, related container and the measurement date.
- Information sheet of the conditioned load of used radioactive source, filed in the storage record, shall include not only the information indicated on the labels of the load and related container but also the following additional information:
- Names, serial numbers, radioactivity of the radioactive sources included in the conditioned load of used radioactive source, related container;
- Supplier or manufacturer of the radioactive sources;
- Owner of each used radioactive source.
6. Only organizations, individuals licensed for used radioactive waste and/or source treatment shall be entitled to conditioning, except the conditioning by storing such used waste/source in the radioactive source containers.
Article 9. Storage of radioactive wastes, used radioactive sources
1. After being collected to the containers, solid radioactive waste and wastewater shall be stored in the temporary storage at the facilities, where the waste is generated, to wait for disintegration before being disposed to the environment or being transported to the treatment, conditioning locations or to the radioactive waste storage facilities. If not collected to the container, radioactive wastewater shall be collected and stored in tanks to wait for treatment or disintegration. Once no longer used, the radioactive sources shall be stored in the temporary storage until they are transferred to other users, radioactive waste storage facilities or returned to the foreign manufacturers and/or suppliers.
2. Temporary storage of radioactive wastes and/or used radioactive sources shall be arranged and designed in such a way to conform to the following requirements:
a) The storage area shall be adequately large to house the collected boxes, bags, containers in order, for easy access when required and maintained below the critical level if nuclear materials are stored;
b) The storage shall be located at unfrequented locations, far from harmful material storage (e.g. explosion, combustible objects) and living water source, with one door, without window and firmly built; its wall surface and floor shall be made in decontaminative materials;
c) The enclosure design of the storage shall ensure that the radiation dose rates from external surfaces of the door and walls shall not exceed 0.5 µSv/h;
d) The storage shall be able to prevent flood, harms from nature (heat, moisture, rain);
dd) The storage door shall be equipped with security lock.
3. Conditioned radioactive waste loads, used conditioned radioactive source loads and used radioactive source containers shall be stored at the facilities licensed for radioactive waste storage.
4. The storage of conditioned radioactive waste loads, used conditioned radioactive source loads, used radioactive source containers, located at the storage facilities of radioactive wastes, shall be arranged and designed in the way that ensures:
a) The same requirements as applied to temporary storage of radioactive wastes as defined in Clause 2 of this Article;
b) Ventilation system to handle the radioactive gas and heat radiated from the stored radioactive waste loads;
c) Available fire and explosion prevention system;
d) Available appropriate equipment to collect leaked radioactive materials;
dd) Available appropriate loading equipment;
e) Protection fences, radioactive warning signboards;
g) Appropriate protection system.
5. Radioactive wastewater tank shall be designed in the way that ensures the following requirements:
a) Located at unfrequented locations and far from where effects of nature such as rain, floods can reach;
b) Capacity of the tank shall be appropriate with the volume of radioactive wastewater to be collected and estimated storage time;
c) The design shall ensure that the radiation dose rates from accessible outer surface of the tank shall not exceed 0.5 µSv/h, no radioactive wastewater leaked to the environment and underground water.
6. Radioactive waste storage facility shall frequently check the safety conditions of its radioactive waste storage and/or radioactive wastewater tanks, details are as follows:
a) Quarterly checks on the internal and external radiation doses of the storage, surrounding areas of the radioactive wastewater tanks;
b) Semi-annual checks on the leaking of radionuclides to the environment.
Article 10. Radioactive waste storage facility
1. A radioactive waste storage facility shall be designed and operated in accordance with the following general requirements:
a) Radioactive dose rates, leaking of radioactive materials to the environment shall be controlled at the lowest possible level; total personal radiation dose on a radioactive operator and/or the public shall not exceed 3/10 of the limit value as defined in Circular No. 19/2012/TT-BKHCN dated 8 November 2012 issued by the Minister of Science and Technology which regulates the control and assurance of radiation safety in occupational exposure and public exposure;
b) Various measures shall be applied to prevent any incidents during the operation;
c) Operation procedure of the facility shall include the following:
- Operation conditions and limits;
- Management system;
- Regulations on internal inspection;
- Regulations on staff training;
- Plans on radiation safety and security, supervision of radioactive material disposal to the environment;
- Acceptance standards applicable to radioactive waste loads;
- Plan for incident responses to minimize the damages once incident happens;
- Regulation on radioactive waste management document preparation and filing.
2. Radioactive waste storage facility shall be designed in a way to meeting the following specific requirements:
a) A location for used radioactive waste, source treatment and storage shall be far away from the office/ working area, crowded area, other harmful material storage areas;
b) Temporary storage area for radioactive waste, radioactive waste treatment area, area for radioactive waste conditioning and storage of conditioned waste loads, conditioned loads or used radioactive source containers.
c) Temporary storage of used radioactive wastes, sources and storage of conditioned waste loads, used conditioned radioactive sources, used radioactive source containers shall be designed in a way that ensure the requirements defined in Article 9 herein;
d) Adequate technical equipment and qualification for treatment, conditioning of radioactive wastes as regulated in Articles 7 and 8 herein.
Article 11. Documents about used radioactive waste, source management
1. The record regarding radioactive waste management shall be documented, updated, filed since the collection of radioactive waste until the disposal, recycling or storage of such waste at the storage facility.
2. The record regarding used radioactive source management shall be documented, updated, filed since the use suspension time of radioactive waste until the transfer or storage of such waste at the storage facility.
3. The record regarding used radioactive waste, source management shall include all the following information:
a) Statistics on radioactive waste: Information on the collected radioactive waste, disposal of such to the environment, transfer and receipt of such, and stored conditioned waste loads.
b) Used radioactive waste summary information: Identification information of the used radioactive source, information on transfer and receipt of such, stored conditioned loads and related container;
c) Safety evaluation report available by the radiation service license application time;
d) Design documents of radioactive waste tank, storage, treatment system.
dd) Results of inspection, evaluation of radiation rate and environmental radiation inspection;
e) Reports on incidents related to radioactive waste, used radioactive source management.
Chapter III
MANAGEMENT RESPONSIBILITIES TOWARDS USED RADIOACTIVE WASTES, SOURCES
Article 12. Responsibilities of radioactive waste source owner
1. Managing and ensuring safety, security of radioactive waste since it exists until disposal as unharmful waste, transfer to the storage facility or recycling facility in case of contaminated metal.
2. Collecting solid radioactive waste and radioactive wastewater as required in Article 4 herein.
3. Applying filtering and control measures in case of radioactive waste gas as defined in Clauses 01 and 2 of Article 5 herein before the it is disposed directly to the environment.
4. Applying management measures on solid radioactive waste and radioactive wastewater after they are collected in accordance with the waste characteristics and category, and specific conditions of the facility, with details as follows:
a) Storing solid radioactive waste, categorized as the low-level and/or very-short-lifespan waste, at the facility for disintegration and disposal as unharmful waste in accordance with Clause 3 of Article 5 herein.
b) Carrying out treatment, conditioning and long-term storage at the facility if it is solid waste not categorized in Point a of this Clause and if the facility is capable for storage or transferring such solid waste to a radioactive waste storage facility within 3 years after the collection, storage at the temporary storages;
c) Storing radioactive wastewater for disintegration and carrying out treatment of such wastewater before disposing it to the environment as defined in Clauses 4 and 5 of Article 5 herein.
5. Available temporary radioactive waste storage as regulated in Clause 2 of Article 9 herein. In case of on-the-site treatment, conditioning, long storage at the facility, the facility shall be adequately qualified and capable to store radioactive waste as defined in Article 10 herein and licensed by Vietnam Agency for Radiation and Nuclear Safety for radioactive waste treatment and/or storage. Once the radioactive waste is transferred to the storage facility, regulations defined in Clause 01 of Article 6 herein shall be adhered to.
6. Document and file the radioactive waste management records since the waste exists until disposal or transfer to the related storage facility, recycling facility in case of contaminated metal as defined in Article 11 herein.
7. Adhering to the legal regulations on radioactive safety assurance, radioactive material safety transportation.
8. In case of bankruptcy, dissolution, operation termination when the own of the radioactive waste source is not categorized as defined in Point d of Clause 01 of Article 34 of the Law on Nuclear Energy, such owner shall:
a) Adhere to the regulation defined in Article 36 of the Law on Nuclear Energy.
b) Fulfill his/her financial duties towards the radioactive waste as decided by the court or authorities competent for making decision on operation termination.
9. In case of bankruptcy, dissolution, operation termination when the own of the radioactive waste source is not categorized as defined in Clause 8 of this Article, such owner shall:
a) Inform Vietnam Agency for Radiation and Nuclear Safety of the reasons, tentative time of operation termination;
b) Carry out safety assurance measures against radioactive waste and transfer it to another organization and/or individual who is qualified, eligible for management as instructed by Vietnam Agency for Radiation and Nuclear Safety.
c) Fulfill his/her financial obligations related to the radioactive waste as decided by the court or authorities competent for making decision on operation termination.
Article 13. Responsibilities of the owner of the used radioactive source
1. The owner may choose and apply one of the following options to manage the used radioactive source:
a) Transferring the source to another organization and/or individual for use if it remains intact, without radioactive leaking;
b) Transferring the source to the foreign manufacturer and/or supplier;
c) Transferring the source to a radioactive waste storage facility;
d) Storing the source for long term at his/her facility if it is qualified as a radioactive waste storage facility as defined in Article 10 herein and licensed by Vietnam Agency for Radiation and Nuclear Safety for radiation treatment, radioactive waste storage;
dd) Storing the source temporarily at his/her facility for not over 3 years until one of the options stated in Points a, b, c and d of this Clause is well met;
2. The owner shall inspect, evaluate radioactive leaking of the radioactive source as soon as it is no longer used, stored temporarily in the storage and before it is transferred to another organization and/or individual or returned to the foreign manufacturer and/or supplier.
3. The owner shall manage the used radioactive sources in a way that ensures safety, security since they are generated until the time they are returned to the foreign manufacturer and/or supplier or transferred to another organization and/or individual for use or transferred to the radioactive waste storage facility.
4. Once the used radioactive source is transferred, the requirements defined in Clause 4 of Article 6 herein shall be adhered to; once being stored at the owner’s facility, it shall be stored in the storage designed safely as stated in Clause 2 of Article 9 herein and the owner must be licensed for radiation activities and storage of used radioactive sources as regulated by related laws.
5. The owner of the source shall document and file the used radioactive source since it is generated until it is transferred to another organization and/or individual as defined in Article 11 herein.
6. The owner of the source shall adhere to related legal regulations on radiation safety, radioactive source security and safe transportation of the radioactive materials.
7. In case of bankruptcy, dissolution, operation termination when the own of the used radioactive source is categorized as defined in Points b and c of Clause 01 of Article 34 of the Law on Nuclear Energy, such owner shall:
a) Adhere to the regulations defined in Article 36 of the Law on Nuclear Energy;
b) Fulfill his/her financial obligations related to the used radioactive source as decided by the court or authorities competent for making decision on operation termination.
8. In case of bankruptcy, dissolution, operation termination when the own of the used radioactive source is not categorized as defined in Clause 7 of this Article, such owner shall:
a) Inform Vietnam Agency for Radiation and Nuclear Safety of the reasons, tentative time of operation termination;
b) Carry out safety measures for the used radioactive source and transferred it to another organization and/or individual qualified, eligible for management as guided by Vietnam Agency for Radiation and Nuclear Safety;
c) Fulfill his/her financial obligations related to the used radioactive source as decided by the court or authorities competent for making decision on operation termination.
Article 14. Responsibilities of the organization, individual transporting used radioactive wastes, sources
1. Fulfilling the responsibilities defined in Clause 2 of Article 63 of the Law on Nuclear Energy and Article 35 of Circular No. 23/2012/TT-BKHCN dated 23 November 2012 issued by the Minister of Science and Technology giving guidance on safe transportation of radioactive materials.
2. Transferring adequately the used radioactive wastes, sources to the receiver in accordance with related contract and signing for verification the transfer minutes of the radioactive waste, used radioactive source as regulated in Article 6 herein.
Article 15. Responsibilities of the owner of a radioactive waste storage facility
1. Adhering to the requirements applied to radioactive waste storage facilities as defined in Article 10 herein.
2. Only receiving the radioactive waste, used radioactive source once the owner is licensed for radiation activities, storage of radioactive wastes and/or used radioactive sources.
3. Informing Vietnam Agency for Radiation and Nuclear Safety of every receipt of the radioactive waste or used radioactive source using Form No. 4 indicated in Appendix V herein.
4. Documenting and filing the documents on the radioactive wastes, used radioactive sources storage at the facility as defined in Article 11 herein.
5. Adhering to the legal regulations on radiation safety, radioactive source security and safe radioactive material transportation.
6. A radioactive waste storage facility invested from the state budget shall receive, carry out treatment and store unconditionally uncontrolled radioactive sources, radioactive wastes with unknown owners and other special cases as requested for state management.
7. In case of bankruptcy, dissolution, operation termination when the radioactive waste storage facility is categorized as defined in Point đ of Clause 01 of Article 34 of the Law on Nuclear Energy, the owner of such facility shall:
a) Adhere to the regulation defined in Article 36 of the Law on Nuclear Energy;
b) Fulfill financial obligations related to the radioactive waste, used radioactive source as decided by the court or authorities competent for making decision on operation termination.
8. In case of bankruptcy, dissolution, operation termination when the own of the radioactive waste storage facility is not categorized as defined in Clause 7 of this Article, such owner shall adhere to the regulation defined in Clause 9 of Article 12 and Clause 8 of Article 13 herein.
Article 16. Responsibilities of state management authorities in charge of radiation and nuclear safety
1. Vietnam Agency for Radiation and Nuclear Safety shall:
a) Organize, supervise the collection of radioactive wastes with unknown owners and the uncontrolled ones with unknown owners.
b) Give guidance on management measures of radioactive wastes and used radioactive sources to organizations and/or individuals.
c) Examine the safety and license radiation activities that generate radioactive wastes and radioactive waste storage facilities.
d) Inspect the conformity with legal regulations on radioactive waste, used radioactive source management nation-wide and apply disciplinary measures on offences.
2. Departments of Science and Technology of the provinces, cities under central management shall:
a) Organize and cooperate with Vietnam Agency for Radiation and Nuclear Safety to collect radioactive wastes, sources with unknown owners found in the areas of their administration.
b) Give guidance on management measures of the radioactive wastes and used radioactive sources to organizations and/or individuals in the areas of their administration.
c) Inspect and cooperate with Vietnam Agency for Radiation and Nuclear Safety on the conformity with legal regulations on the management of radioactive wastes, used radioactive sources in the areas of their administration and apply disciplinary measures on offences.
Chapter IV
IMPLEMENTATION
Article 17. Transitional stage
The organizations and/or individuals already licensed and carrying out the activities related to the radioactive waste, used radioactive source management, who fail to meet the requirements defined herein, shall carry out improvement measures as requested herein within 6 months since the validity of this Circular to ensure their operation continuity.
Article 18. Implementation validity
1. This Circular takes enforcement effect as of 01 November 2014.
2. During the implementation, in case of any entanglements or issues incurred, related organizations and/or individuals are requested to report timely to the Ministry of Science and Technology for amendment and/or supplementation./.
| THE MINISTER |
APPENDIX I
RADIOACTIVE WASTE CLASSIFICATION
(attached with Circular No. 22/2014/TT-BKHCN dated 25 August 2014 issued by the Minister of Science and Technology)
I. Classification by the characteristics of the radionuclides included in the wastes
No. | Classification | Characteristic |
1 | Radioactive wastes with low radiation rate, very short lifespan | The wastes which contain only radionuclides with half-life of less than 100 days and disintegratable to the level smaller than the liquidation level within 5 years since the existence. |
2 | Radioactive wastes with low radiation rate, short lifespan | The radioactive wastes which are unlikely disintegrated to the level lower than the liquidation level within 5 years since the existence, contain beta-gamma-generating radionuclides with half-life of 100 days – 30 years or alpha-generating radionuclides with average specific activity not over 400 Bq/g. |
3 | Radioactive wastes with low – average radiation rate, long lifespan | The radioactive wastes which contain radionuclides with half-life of over 30 years or alpha-generating radionuclides with average specific activity over 400 Bq/g but not over 104 TBq/m3. |
4 | Radioactive wastes with high radiation rate | The radioactive wastes which contain radionuclides with specific activity of over 104 TBq/m3. |
II. Classification by physical, chemical, biological characteristics of the wastes
Based their physical, chemical, biological characteristics, the wastes are classified as follows:
- Solid, liquid or gas wastes;
- Combustible wastes;
- Compressible wastes;
- Biological wastes;
- Metal wastes.
APPENDIX II
LIQUIDATION LEVEL
(attached with Circular No. 22/2014/TT-BKHCN dated 25 August 2014 issued by the Minister of Science and Technology)
I. Liquidation level applied to artificial radionuclides
Radio-nuclide | Specific activity (Bq/g) |
|
| Radio-nuclide | Specific activity (Bq/g) |
|
| Radio-nuclide | Specific activity (Bq/g) |
|
H-3 | 100 |
|
| Sc-47 | 100 |
|
| Co-58m | 10000 | * |
Be-7 | 10 |
|
| Sc-48 | 1 |
|
| Co-60 | 0.1 |
|
C-14 | 1 |
|
| V-48 | 1 |
|
| Co-60m | 1000 | * |
F-18 | 10 | * |
| Cr-51 | 100 |
|
| Co-61 | 100 | * |
Na-22 | 0.1 |
|
| Mn-51 | 10 | * |
| Co-62m | 10 | * |
Na-24 | 1 | * |
| Mn-52 | 1 |
|
| Ni-59 | 100 |
|
Si-31 | 1000 | * |
| Mn-52m | 10 | * |
| Ni-63 | 100 |
|
P-32 | 1000 |
|
| Mn-53 | 100 |
|
| Ni-65 | 10 | * |
P-33 | 1000 |
|
| Mn-54 | 0.1 |
|
| Cu-64 | 100 | * |
S-35 | 100 |
|
| Mn-56 | 10 | * |
| Zn-65 | 0.1 |
|
Cl-36 | 1 |
|
| Fe-52 | 10 | * |
| Zn-69 | 1000 | * |
Cl-38 | 10 | * |
| Fe-55 | 1000 |
|
| Zn-69m | 10 | * |
K-42 | 100 |
|
| Fe-59 | 1 |
|
| Ga-72 | 10 | * |
K-43 | 10 | * |
| Co-55 | 10 | * |
| Ge-71 | 10000 |
|
Ca-45 | 100 |
|
| Co-56 | 0.1 |
|
| As-73 | 1000 |
|
Ca-47 | 10 |
|
| Co-57 | 1 |
|
| As-74 | 10 | * |
Sc-46 | 0.1 |
|
| Co-58 | 1 |
|
| As-76 | 10 | * |
As-77 | 1000 |
|
| Nb-95 | 1 |
|
| Ag-105 | 1 |
|
Se-75 | 1 |
|
| Nb-97 | 10 | * |
| Ag-110m | 0.1 |
|
Br-82 | 1 |
|
| Nb-98 | 10 | * |
| Ag-111 | 100 |
|
Rb-86 | 100 |
|
| Mo-90 | 10 | * |
| Cd-109 | 1 |
|
Sr-85 | 1 |
|
| Mo-93 | 10 |
|
| Cd-115 | 10 |
|
Sr-85m | 100 | * |
| Mo-99 | 10 |
|
| Cd-115m | 100 |
|
Sr-87m | 100 | * |
| Mo-101 | 10 | * |
| In-111 | 10 |
|
Sr-89 | 1000 |
|
| Tc-96 | 1 |
|
| In-113m | 100 | * |
Sr-90 | 1 |
|
| Tc-96m | 1000 | * |
| In-114m | 10 |
|
Sr-91 | 10 | * |
| Tc-97 | 10 |
|
| In-115m | 100 | * |
Sr-92 | 10 | * |
| Tc-97m | 100 |
|
| Sn-113 | 1 |
|
Y-90 | 1000 |
|
| Tc-99 | 1 |
|
| Sn-125 | 10 |
|
Y-91 | 100 |
|
| Tc-99m | 100 | * |
| Sb-122 | 10 |
|
Y-91m | 100 | * |
| Ru-97 | 10 |
|
| Sb-124 | 1 |
|
Y-92 | 100 | * |
| Ru-103 | 1 |
|
| Sb-125 | 0.1 |
|
Y-93 | 100 | * |
| Ru-105 | 10 | * |
| Te-123m | 1 |
|
Zr-93 | 10 | * |
| Ru-106 | 0.1 |
|
| Te-125m | 1000 |
|
Zr-95 | 1 |
|
| Rh-103m | 10000 | * |
| Te-127 | 1000 |
|
Zr-97 | 10 | * |
| Rh-105 | 100 |
|
| Te-127m | 10 |
|
Nb-93m | 10 |
|
| Pd-103 | 1000 |
|
| Te-129 | 100 | * |
Nb-94 | 0.1 |
|
| Pd-109 | 100 |
|
| Te-129m | 10 |
|
Te-131 | 100 | * |
| Cs-138 | 10 | * |
| Dy-166 | 100 |
|
Te-131m | 10 |
|
| Ba-131 | 10 |
|
| Ho-166 | 100 |
|
Te-132 | 1 |
|
| Ba-140 | 1 |
|
| Er-169 | 1000 |
|
Te-133 | 10 | * |
| La-140 | 1 |
|
| Er-171 | 100 | * |
Te-133m | 10 | * |
| Ce-139 | 1 |
|
| Tm-170 | 100 |
|
Te-134 | 10 | * |
| Ce-141 | 100 |
|
| Tm-171 | 1000 |
|
I-123 | 100 |
|
| Ce-143 | 10 |
|
| Yb-175 | 100 |
|
I-125 | 100 |
|
| Ce-144 | 10 |
|
| Lu-177 | 100 |
|
I-126 | 10 |
|
| Pr-142 | 100 | * |
| Hf-181 | 1 |
|
I-129 | 0.01 |
|
| Pr-143 | 1000 |
|
| Ta-182 | 0.1 |
|
I-130 | 10 | * |
| Nd-147 | 100 |
|
| W-181 | 10 |
|
I-131 | 10 |
|
| Nd-149 | 100 | * |
| W-185 | 1000 |
|
I-132 | 10 | * |
| Pm-147 | 1000 |
|
| W-187 | 10 |
|
I-133 | 10 | * |
| Pm-149 | 1000 |
|
| Re-186 | 1000 |
|
I-134 | 10 | * |
| Sm-151 | 1000 |
|
| Re-188 | 100 | * |
I-135 | 10 | * |
| Sm-153 | 100 |
|
| Os-185 | 1 |
|
Cs-129 | 10 |
|
| Eu-152 | 0.1 |
|
| Os-191 | 100 |
|
Cs-131 | 1000 |
|
| Eu-152m | 100 | * |
| Os-191m | 1000 | * |
Cs-132 | 10 |
|
| Eu-154 | 0.1 |
|
| Os-193 | 100 |
|
Cs-134 | 0.1 |
|
| Eu-155 | 1 |
|
| Ir-190 | 1 |
|
Cs-134m | 1000 | * |
| Gd-153 | 10 |
|
| Ir-192 | 1 |
|
Cs-135 | 100 |
|
| Gd-159 | 100 | * |
| Ir-194 | 100 | * |
Cs-136 | 1 |
|
| Tb-160 | 1 |
|
| Pt-191 | 10 |
|
Cs-137 | 0.1 |
|
| Dy-165 | 1000 | * |
| Pt-193m | 1000 |
|
Pt-197 | 1000 | * |
| U-231 | 100 |
|
| Cm-242 | 10 |
|
Pt-197m | 100 | * |
| U-232 | 0.1 |
|
| Cm-243 | 1 |
|
Au-198 | 10 |
|
| U-233 | 1 |
|
| Cm-244 | 1 |
|
Au-199 | 100 |
|
| U-236 | 10 |
|
| Cm-245 | 0.1 |
|
Hg-197 | 100 |
|
| U-237 | 100 |
|
| Cm-246 | 0.1 |
|
Hg-197m | 100 |
|
| U-239 | 100 | * |
| Cm-247 | 0.1 |
|
Hg-203 | 10 |
|
| U-240 | 100 | * |
| Cm-248 | 0.1 |
|
Tl-200 | 10 |
|
| Np-237 | 1 |
|
| Bk-249 | 100 |
|
Tl-201 | 100 |
|
| Np-239 | 100 |
|
| Cf-246 | 1000 |
|
Tl-202 | 10 |
|
| Np-240 | 10 | * |
| Cf-248 | 1 |
|
Tl-204 | 1 |
|
| Pu-234 | 100 | * |
| Cf-249 | 0.1 |
|
Pb-203 | 10 |
|
| Pu-235 | 100 | * |
| Cf-250 | 1 |
|
Bi-206 | 1 |
|
| Pu-236 | 1 |
|
| Cf-251 | 0.1 |
|
Bi-207 | 0.1 |
|
| Pu-237 | 100 |
|
| Cf-252 | 1 |
|
Po-203 | 10 | * |
| Pu-238 | 0.1 |
|
| Cf-253 | 100 |
|
Po-205 | 10 | * |
| Pu-239 | 0.1 |
|
| Cf-254 | 1 |
|
Po-207 | 10 | * |
| Pu-240 | 0.1 |
|
| Es-253 | 100 |
|
At-211 | 1000 |
|
| Pu-241 | 10 |
|
| Es-254 | 0.1 |
|
Ra-225 | 10 |
|
| Pu-242 | 0.1 |
|
| Es-254m | 10 |
|
Ra-227 | 100 |
|
| Pu-243 | 1000 | * |
| Fm-254 | 10000 | * |
Th-226 | 1000 |
|
| Pu-244 | 0.1 |
|
| Fm-255 | 100 | * |
Th-229 | 0.1 |
|
| Am-241 | 0.1 |
|
|
|
|
|
Pa-230 | 10 |
|
| Am-242 | 1000 | * |
|
|
|
|
Pa-233 | 10 |
|
| Am-242m | 0.1 |
|
|
|
|
|
U-230 | 10 |
|
| Am-243 | 0.1 |
|
|
|
|
|
* Half-life of less than 01 day.
II. Liquidation level applied to nature-based radionuclides
Radionuclide | Specific activity |
K-40 | 10 |
All other nature-based radionuclides | 1 |
Note:
In case the waste contains a compound of radionuclides, the following formula shall be applied:
Where: Ci is the specific activity (Bq/g) of the waste of the radionuclide i;
Xi is the liquidation level of radionuclide i;
n is the quantity of radionuclides available in the waste.
APPENDIX III
PERMISSIBLE LEVEL FOR DISPOSAL TO THE ENVIRONMENT
(attached with Circular No. 22/2014/TT-BKHCN dated 25 August 2014 issued by the Minister of Science and Technology)
Table 1. Permissible radioactivity level for disposal to the environment applied to gas wastes
Isotope | Annual disposal rate (Bq/year) | Isotope | Annual disposal rate (Bq/year) |
H-3 | 1 x 1011 | Y-90 | 1 x 1010 |
C-14 | 1 x 1010 | Mo-99 | 1 x 109 |
Na-22 | 1 x 106 | Tc-99 | 1 x 107 |
Na-24 | 1 x 109 | Tc-99m | 1 x 1011 |
P-32 | 1 x 108 | In-111 | 1 x 109 |
S-35 | 1 x 108 | I-123 | 1 x 1010 |
Cl-36 | 1 x 107 | I-125 | 1 x 108 |
K-42 | 1 x 1010 | I-131 | 1 x 108 |
Ca-45 | 1 x 108 | Xe-127 | 1 x 1011 |
Ca-47 | 1 x 109 | Xe-133 | 1 x 1012 |
Cr-51 | 1 x 109 | Pm-147 | 1 x 1010 |
Fe-59 | 1 x 108 | Er-169 | 1 x 1010 |
Co-57 | 1 x 109 | Au-198 | 1 x 109 |
Co-58 | 1 x 109 | Hg-197 | 1 x 1010 |
Ga-67 | 1 x 1010 | Hg-203 | 1 x 108 |
Se-75 | 1 x 108 | Tl-201 | 1 x 1010 |
Sr-85 | 1 x 108 | Ra-226 | 1 x 106 |
Sr-89 | 1 x 108 | Th-232 | 1 x 105 |
Note:
In case the waste gas contains a compound of radionuclides, the following formula shall be applied:
Where: Ci is the activity (Bq/year) of radionuclide i available in the waste, disposed to the environment in the year;
Xi is the permissible level for disposal to the environment in the year (Bq/year) applied to radionuclide i;
n is the quantity of radionuclides available in the waste disposed to the environment in the year.
Table 2. Permissible radioactivity level for disposal to the environment applied to liquid wastes
Isotope | Annual disposal level (Bq/year) | Isotope | Annual disposal level (Bq/year) |
H-3 | 1 x 1012 | Sr-89 | 1 x 109 |
C-14 | 1 x 1010 | Y-90 | 1 x 1010 |
Na-22 | 1 x 105 | Mo-99 | 1 x 108 |
Na-24 | 1 x 108 | Tc-99 | 1 x 1010 |
P-32 | 1 x 106 | Tc-99m | 1 x 109 |
S-35 | 1 x 109 | In-111 | 1 x 108 |
Cl-36 | 1 x 1010 | I-123 | 1 x 109 |
K-42 | 1 x 109 | I-125 | 1 x 108 |
Ca-45 | 1 x 1010 | I-131 | 1 x 107 |
Ca-47 | 1 x 108 | Pm-147 | 1 x 1010 |
Cr-51 | 1 x 108 | Er-169 | 1 x 1010 |
Fe-59 | 1 x 106 | Au-198 | 1 x 108 |
Co-57 | 1 x 109 | Hg-197 | 1 x 109 |
Co-58 | 1 x 108 | Hg-203 | 1 x 107 |
Ga-67 | 1 x 108 | Tl-201 | 1 x 108 |
Se-75 | 1 x 106 | Ra-226 | 1 x 106 |
Sr-85 | 1 x 106 | Th-232 | 1 x 106 |
Note:
In case the waste contains a compound of radionuclides, the following formula shall be applied:
Where: Ci is the activity (Bq/year) of radionuclide i available in the waste disposed to the environment in the year;
Xi is the permissible disposal level of radionuclide i to the environment in the year (Bq/year);
n is the quantity of radionuclides available in the waste disposed to the environment in the year.
APPENDIX IV
THE LEVELS OF SPECIFIC ACTIVITY AND SURFACE RADIOACTIVITY-CONTAMINATION OF THE METALS PERMITTED FOR RECYCLING
(attached with Circular No. 22/2014/TT-BKHCN dated 25 August 2014 issued by the Minister of Science and Technology)
Isotope | Specific activity (Bq/g) | Surface contamination level (Bq/cm2) |
| Isotope | Specific activity (Bq/g) | Surface contamination level (Bq/cm2) |
H-3 | 1000 | 100000 |
| Zr-95 | 1 | 10 |
C-14 | 100 | 1000 |
| Nb-93m | 1000 | 10000 |
Na-22 | 1 | 10 |
| Nb-94 | 1 | 10 |
S-35 | 1000 | 1000 |
| Mo-93 | 100 | 1000 |
Cl-36 | 10 | 100 |
| Tc-97 | 1000 | 1000 |
K-40 | 1 | 100 |
| Tc-97m | 1000 | 1000 |
Ca-45 | 1000 | 100 |
| Tc-99 | 100 | 1000 |
Sc-46 | 1 | 10 |
| Ru-106 | 1 | 10 |
Mn-53 | 10000 | 100000 |
| Ag-108m | 1 | 10 |
Mn-54 | 1 | 10 |
| Ag-110m | 1 | 10 |
Fe-55 | 10000 | 10000 |
| Cd-109 | 10 | 100 |
Co-56 | 1 | 10 |
| Sn-113 | 1 | 100 |
Co-57 | 10 | 100 |
| Sb-124 | 1 | 10 |
Co-58 | 1 | 10 |
| Sb-125 | 10 | 100 |
Co-60 | 1 | 10 |
| Te-123m | 10 | 100 |
Ni-59 | 10000 | 10000 |
| Te-127m | 100 | 100 |
Ni-63 | 10000 | 10000 |
| I-125 | 1 | 100 |
Zn-65 | 1 | 100 |
| I-129 | 1 | 10 |
As-73 | 100 | 1000 |
| Cs-134 | 1 | 10 |
Se-75 | 1 | 100 |
| Cs-135 | 10 | 1000 |
Sr-85 | 1 | 100 |
| Cs-137 | 1 | 100 |
Sr-90 | 10 | 10 |
| Ce-139 | 10 | 100 |
Y-91 | 10 | 100 |
| Ce-144 | 10 | 10 |
Zr-93 | 10 | 100 |
| Pm-147 | 10000 | 1000 |
Sm-151 | 10000 | 1000 |
| U-236 | 10 | 1 |
Eu-152 | 1 | 10 |
| U-238 | 1 | 1 |
Eu-154 | 1 | 10 |
| Np-237 | 1 | 0.1 |
Eu-155 | 10 | 1000 |
| Pu-236 | 1 | 0.1 |
Gd-153 | 10 | 100 |
| Pu-238 | 1 | 0.1 |
Tb-160 | 1 | 10 |
| Pu-239 | 1 | 0.1 |
Tm-170 | 100 | 1000 |
| Pu-240 | 1 | 0.1 |
Tm-171 | 1000 | 10000 |
| Pu-241 | 10 | 10 |
Ta-182 | 1 | 10 |
| Pu-242 | 1 | 0.1 |
W-181 | 100 | 1000 |
| Pu-244 | 1 | 0.1 |
W-185 | 1000 | 1000 |
| Am-241 | 1 | 0.1 |
Os-185 | 1 | 10 |
| Am-242m | 1 | 0.1 |
Ir-192 | 1 | 10 |
| Am-243 | 1 | 0.1 |
Tl-204 | 1000 | 1000 |
| Cm-242 | 10 | 1 |
Pb-210 | 1 | 1 |
| Cm-243 | 1 | 0.1 |
Bi-207 | 1 | 10 |
| Cm-244 | 1 | 0.1 |
Po-210 | 1 | 0.1 |
| Cm-245 | 1 | 0.1 |
Ra-226 | 1 | 0.1 |
| Cm-246 | 1 | 0.1 |
Ra-228 | 1 | 1 |
| Cm-247 | 1 | 0.1 |
Th-228 | 1 | 0.1 |
| Cm-248 | 1 | 0.1 |
Th-229 | 1 | 0.1 |
| Bk-249 | 100 | 100 |
Th-230 | 1 | 0.1 |
| Cf-248 | 10 | 1 |
Th-232 | 1 | 0.1 |
| Cf-249 | 1 | 0.1 |
Pa-231 | 1 | 0.1 |
| Cf-250 | 1 | 0.1 |
U-232 | 1 | 0.1 |
| Cf-251 | 1 | 0.1 |
U-233 | 1 | 1 |
| Cf-252 | 1 | 0.1 |
U-234 | 1 | 1 |
| Cf-254 | 1 | 0.1 |
U-235 | 1 | 1 |
| Es-254 | 10 | 1 |
Notes:
1. The value of specific activity of the metal load for comparing with those indicated in the table shall be the average value of the measurement results of about 200kg of sample randomly taken.
2. The value of surface contamination of the metal load for comparing with those indicated in the table shall be the average value of the measurement results of about 1 m2 of samples randomly taken.
3. In case a metal in contaminated by many radionuclides, the permissible level for recycling such metal shall be calculated with the following formula:
Where: Ci is the specific activity and surface contamination of the metal affected by radionuclide i
Xi is the specific activity and surface contamination affected by radionuclide i whereby the metal is permitted for recycling
n is the quantity of radionuclides available in the metal
4. Above-mentioned specific activity shall not applied to the wastes which are synthetic materials such as electric cables. These materials shall be analyzed with metal and non-metal properties separated before the permissible metal recycling standards can be applied.
