Cabinet Regulation No. 129 of 2002 on Requirements for Operations with Radioactive Waste and Materials Related Thereto

Disclaimer: The English language text below is provided by the Translation and Terminology Centre for information only; it confers no rights and imposes no obligations separate from those conferred or imposed by the legislation formally adopted and published. Only the latter is authentic. The original Latvian text uses masculine pronouns in the singular. The Translation and Terminology Centre uses the principle of gender-neutral language in its English translations. In addition, gender-specific Latvian nouns have been translated as gender-neutral terms, e.g. chairperson. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) Republic of Latvia Cabinet Regulation No. 129 Adopted 19 March 2002 Requirements for Operations with Radioactive Waste and Materials Related Thereto Issued pursuant to Section 27, Paragraph three of the Law On Radiation Safety and Nuclear Safety I. General Provisions 1. These Regulations determine requirements for operations with radioactive waste and materials related thereto. 2. Materials related to radioactive waste are materials, installations and objects which have come into contact with radioactive waste and the total or specific radioactivity of which is less than the limits prescribed by Cabinet Regulations No 288 of 3 July 2001, Regulations on Operations with Sources of Ionising Radiation for which Special Permit (Licence) or Permit is not Required (hereinafter — limits prescribed by regulatory enactments for the non-exceeding of which a special permit (licence) or licence is not required). 3. An operator whose operations with sources of ionising radiation may produce radioactive waste (hereinafter — operator) when planning the operations referred to shall also plan operations with the relevant radioactive waste. 4. In conformity with the amount of radioactivity of radioactive waste, radioactive waste shall be classified as follows: 4.1. radioactive waste as a result of the radioactive decay of which the total or specific radioactivity is smaller than the limits prescribed by regulatory enactments for the non-exceeding of which a special permit (licence) or permit is not required (hereinafter — unusable materials); and 4.2. radioactive waste the total or specific radioactivity of which is greater than the limits prescribed by regulatory enactment for the non-exceeding of which a special permit (licence) or permit is not required. 5. In conformity with the half-life period radioactive waste shall be classified as follows: Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 2 5.1. radioactive waste the half-life of which does not exceed 30 days and in which after radionuclide decay no long-lived daughter products are generated (hereinafter — short-lived radioactive waste); and 5.2. radioactive waste the half-life of which exceeds 30 days or in which after radionuclide decay long-lived daughter products are generated (hereinafter — long-lived radioactive waste). 6. In conformity with the heat generation rate radioactive waste shall be classified as follows: 6.1. radioactive waste the heat generation rate as a result of radioactive decay of which is less than 2 kW per one cubic metre of radioactive waste (hereinafter — low and intermediate radioactivity waste); and 6.2. radioactive waste the heat generation rate as a result of radioactive decay of which is greater or equal to 2 kW per one cubic metre of radioactive waste (hereinafter — high radioactivity waste). 7. Materials related to radioactive waste shall be classified in the following groups: 7.1. material related to radioactive waste which is removed from State supervision and control in the field of radiation safety and nuclear safety (hereinafter — State supervision) because its specific radioactivity is less than the minimum significant specific radioactivity prescribed in Annex 1 of these Regulations and the ionising radiation dose received as a result of the utilisation of such material: 7.1.1. is less than 100 µSv per year — for an individual user (for the whole body); 7.1.2. is less than 5 mSv per year — for an individual user (for the skin surface); and 7.1.3. is less than 1 mSv per year — for a collective dose (for the critical group of population); and 7.2. material related to radioactive waste the specific radioactivity of which is greater than the minimum significant specific radioactivity prescribed in Annex 1 of these Regulations, but smaller than the limits prescribed by regulatory enactments for the non-exceeding of which a special permit (licence) or permit is not required. II. Requirements for Recording of Radioactive Waste and Materials Related Thereto 8. The work supervisor in the operator-controlled area (hereinafter — work supervisor of the operator) shall perform recording of radioactive waste and materials related to radioactive waste. The recording referred to shall ensure: 8.1. a possibility to select the most suitable management methods for the relevant radioactive waste and materials related thereto; and 8.2. a possibility to make a documentary check of the time and manner by which: 8.2.1. radioactive waste arrives at an undertaking (company) which in conformity with the articles of association deals with the disposal and management of radioactive waste (management, treatment, preparation for long-term storage or disposal, storage, long-term storage and disposal of radioactive waste) (hereinafter — a radioactive waste disposal or management undertaking); 8.2.2. spent sources of ionising radiation are sent back to the manufacturers thereof; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 3 8.2.3. unusable materials are dispersed in the environment or disposed of together with municipal or hazardous waste; and 8.2.4. materials related to radioactive waste are repeatedly utilised. 9. Records of radioactive waste shall include information regarding: 9.1. radioactive waste which has been produced while carrying out operations with sources of ionising radiation (quantity (in units by mass and volume), state of aggregation, total and specific radioactivity and radionuclides); 9.2. radioactive waste located in the special premises or premises for the collection, treatment, packing and storage of radioactive waste (hereinafter — temporary radioactive waste repository); 9.3. radioactive waste which has been transferred for disposal and long-term storage, including information included in the labelling of the packaging suited for transportation and disposal of radioactive waste (hereinafter — radioactive waste package); 9.4. spent sources of ionising radiation sent back to the manufacturer of ionising radiation sources; 9.5. unusable material dispersed in the environment: 9.5.1. main radionuclides; 9.5.2. specific and total radioactivity (Bq/g and Bq); 9.5.3. date of dispersal; 9.5.4. results of dispersal control to prove that the permissible amounts of radionuclides to be dispersed in the environment prescribed by regulatory enactments have not been exceeded; and 9.5.5. each dispersed portion and a summary thereof for a year; and 9.6. individual numbers assigned to the radioactive waste packages. 10. Records of the materials related to radioactive waste shall include the following information: 10.1. name; 10.2. main radionuclides; 10.3. radioactive contamination the specific radioactivity of which radioactive substance on a surface exceeds 0.4 Bq/cm 2 for beta radiation sources, gamma radiation sources and low toxicity alpha radiation sources or 0.04 Bq/cm 2 for other alpha radiation sources if such radioactive substances: 10.3.1. cannot be removed from the surface with the usual decontamination methods (hereinafter — fixed radioactive contamination); or 10.3.2. may be removed from the surface with the usual decontamination methods (hereinafter — non-fixed radioactive contamination); 10.4. specific and total radioactivity (Bq/g and Bq); 10.5. types of use; and 10.6. institution or undertaking (company) to which the material related to radioactive waste has been transferred for further use and the date of transfer. 11. The work supervisor of the operator shall: 11.1. each year by 31 January send to the Radiation Safety Centre (hereinafter — Centre) the information referred to in Paragraphs 9 and 10 of these Regulations for the previous calendar year; and Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 4 11.2. each year by 31 December send to the Centre and the radioactive waste disposal and management undertaking an informative letter regarding those operations with sources of ionising radiation, which may cause generation of radioactive waste in the next calendar year. 12. The informative letter referred to in Sub-paragraph 11.2 of these Regulations shall specify: 12.1. the information regarding the operator, the work supervisor of the operator and the person responsible for radioactive waste; 12.2. the amount of the planned radioactive waste, its radioactivity and form — radionuclides in the form of open radiation sources or radionuclides in the form of sealed radiation sources; 12.3. a list of the measuring instruments utilised in the measurement of the ionising radiation dose rate, measurements of non-fixed and fixed radioactive contamination and determination of the qualitative and quantitative content of radionuclides; 12.4. a description of the temporary radioactive waste repository; and 12.5. a description of the planned operations with radioactive waste, including disposal or long-term storage and specifying the measures planned in order to meet the requirements of the radioactive waste management or disposal undertaking. III. Requirements for Operations with Radioactive Waste and Materials Related Thereto in Places of Generation Thereof 13. The operator shall ensure: 13.1. financial, technical and worker resources for safe operations with radioactive waste and materials related thereto; 13.2. minimum total or specific radioactivity and volume of radioactive waste; and 13.3. transfer of radioactive waste for disposal. 14. Sorting, treatment and storage of radioactive waste shall be performed by dividing the waste into the following groups: 14.1. gaseous radioactive waste (without applying storage); 14.2. liquid radioactive waste; 14.3. solid radioactive waste; 14.4. spent sealed radiation sources; and 14.5. biological radioactive waste. 15. The work supervisor of the operator shall ensure that: 15.1. each radioactive waste container contains radioactive waste of one group only; 15.2. in a radioactive waste container the following are not mixed together: 15.2.1. treated and untreated radioactive waste; 15.2.2. short-lived radioactive waste and long-lived radioactive waste; 15.2.3. low and intermediate radioactivity waste and high radioactivity waste; and 15.2.4. radioactive waste referred to in Sub-paragraph 4.1 and 4.2 of these Regulations; 15.3. radioactive waste is treated, transforming it into such chemical and physical form, which is safe and appropriate for storage and transportation of radioactive waste; 15.4. liquid radioactive waste is neutralised; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 5 15.5. radioactive waste does not contain explosive or inflammable materials or compressed gases; 15.6. radioactive waste which contains rotting or decomposing substances or objects (including food or dead bodies of animals) is treated protecting it from biological decomposition processes or is stored frozen; 15.7. radioactive waste containing chemically or biologically hazardous materials and materials which may cause dangerous infectious diseases or in any other manner endanger epidemiological safety is treated maximally reducing those hazardous properties of radioactive waste which are not related to its radioactivity; and 15.8. prior to disposal of radioactive waste the necessity to perform additional treatment is as small as possible. 16. The operator shall ensure that the radioactive waste container that is utilised in a temporary radioactive waste repository is: 16.1. durable; 16.2. compatible with the radioactive waste placed therein; and 16.3. safely filled and emptied. 17. If a radioactive waste container is filled, the work supervisor of the operator shall ensure that the radioactive waste container: 17.1. is labelled with the following information: 17.1.1. the radiation warning sign; 17.1.2. the date on which the radioactive waste container was filled; 17.1.3. the type of radioactive waste generation; 17.1.4. a symbol or name of radionuclides and the total and specific radioactivity thereof (Bq and Bq/g), the date of its measurement; 17.1.5. the ionising radiation dose rate at the distance of 1 cm and 1 m from the surface; 17.1.6. the group of radioactive waste and an indication whether it is short-lived or long-lived radioactive waste and whether it is low and intermediate or high radioactivity waste; and 17.1.7. the name, legal address and telephone number of the radioactive waste packing undertaking (company); and 17.2. is without delay conveyed to the temporary radioactive waste repository. 18. If it is necessary to store and later transfer for disposal radioactive waste the size of which is greater than the radioactive waste storage containers, the work supervisor of the operator shall ensure crushing of the radioactive waste to the appropriate size. 19. Solid radioactive waste shall be accumulated in plastic bags and together with this outer packaging shall be placed: 19.1. into a 0.1 m 3 steel drum if the amount of radioactive waste per year does not exceed 1 m 3 and the total or specific radioactivity thereof does not exceed the values specified in Annex 2 of these Regulations; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 6 19.2. into special reinforced concrete containers which meet the requirements prescribed by Cabinet Regulation No 307 of 3 July 2001, Regulations on Protection Against Ionising Radiation while Transporting Radioactive Materials in respect of IP-3 or type A packages if: 19.2.1. the amount of radioactive waste per year exceeds 1 m 3 ; or 19.2.2. the size of radioactive waste is large and it cannot be emplaced into a 0.1 m 3 steel drum. 20. Radioactive waste shall be prepared for transportation, labelled and transported in compliance with the requirements prescribed by Cabinet Regulation No 307 of 3 July 2001, Regulations on Protection Against Ionising Radiation while Transporting Radioactive Materials. 21. The work supervisor of the operator shall ensure: 21.1. preparation of radioactive waste for transportation and labelling thereof; 21.2. examination of a radioactive waste package so that it meets the following requirements: 21.2.1. non-fixed radioactive contamination on the external surface of the package for beta radiation sources, gamma radiation sources and low toxicity alpha radiation sources does not exceed 4 Bq/cm 2 per 300 cm 2 of the available surface, but for other alpha radiation sources — 0.4 Bq/cm 2 per 300 cm 2 of the available surface; and 21.2.2. the ionising radiation dose rate does not exceed the value permissible for the relevant package and 2 mSv/h at any point of the external surface. 22. If after elimination of radiation emergency consequences the amount of radioactive waste exceeds three cubic metres, it is permitted to accumulate the waste in 0.1 m 3 steel drums which shall be transported as exceptional packages in conformity with the requirements prescribed by Cabinet Regulation No 307 of 3 July 2001, Regulations on Protection Against Ionising Radiation while Transporting Radioactive Materials. In such case the work supervisor of the operator shall specify in the labelling of the package at least the following: 22.1. the main radionuclides; 22.2. the assessed maximum total radioactivity of the radioactive content expressed in the measurement units of the SI system or at least the ionising radiation dose rate on the surface of the drum and at a distance of 1 m, as well as the time of measurement of such values; and 22.3. the category of the package — I-white, II-yellow or III-yellow. 23. Radioactive waste shall be transported by the specialised transport of the radioactive waste disposal or management undertaking or by a means of transport of the operator (if the operator has an appropriate special permit (licence) or a permit for transportation of radioactive waste) which meets the requirements prescribed by Cabinet Regulation No 401 of 7 December 1999, Regulations on Road Haulage of Dangerous Goods. 24. Large quantities of radioactive waste which has been generated when eliminating the consequences of radiation emergencies, if the total and specific radioactivity thereof does not exceed the values specified in Annex 2 of these Regulations, may be conveyed as solid low specific radioactivity waste (except for powder) in LSA-III 0.1 m 3 steel drums which prior to disposal of radioactive waste together with the radioactive waste shall be placed in 0.2 m 3 steel Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 7 drums or reinforced concrete containers and the empty space (also beneath and above the 0.1 m 3 steel drum) shall be filled with concrete. 25. If the operator has been declared insolvent and cannot manage radioactive waste or prepare it for transfer for disposal or long-term storage, the Centre shall inform the relevant local government of the potential danger to the inhabitants of this local government and together with the operator shall ensure the possibility of transferring for disposal all radioactive waste and sources of ionising radiation which are not required for further operations or whose safety no longer meets the requirements prescribed by regulatory enactments. 26. The Centre shall issue a permit to repeatedly utilise materials related to radioactive waste which are not subject to State supervision outside the operator-controlled area. 27. Materials related to radioactive waste, which may be repeatedly utilised without additional treatment, shall be removed from State supervision taking into account the radioactive contamination thereof. 28. In calculating the maximum permissible fixed and non-fixed radioactive contamination on a surface the values of ionising radiation doses prescribed in Annex 1 of these Regulations or Sub paragraph 7.1 of these Regulations shall be used as criteria. These criteria shall refer to the total fixed and non-fixed radioactive contamination. 29. When using radioactive contamination on a surface as a criterion, the average level of radioactive contamination shall be determined for 300 cm 2 of the available surface of the material or for the whole surface of the material if it is smaller than 300 cm 2 . The work supervisor of the operator shall ensure that the non-fixed radioactive contamination is as small as possible. 30. When using specific radioactivity as a criterion, the average specific radioactivity for each 100 kg of the total mass of radioactive materials or for the whole amount of materials if the total mass of radioactive materials is less than 100 kg shall be determined. IV. Requirements for Storage of Radioactive Waste and Materials Related Thereto 31. In conformity with the purpose of radioactive waste storage the following types of storage shall be distinguished: 31.1. storage of radioactive waste until the time when due to decay its specific radioactivity has decreased to the minimum significant specific radioactivity and it cannot be subjected to the State supervision (hereinafter — storage until decay); 31.2. storage of radioactive waste until its treatment is carried out; 31.3. storage of treated radioactive waste prior to shipment to a radioactive waste disposal or management undertaking; 31.4. storage of a spent sealed radiation source prior to sending it back to the manufacturer; and 31.5. long-term storage of radioactive waste until: Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 8 31.5.1. such radioactive waste repository has been created which is situated in geologically stable formations in the depth of at least 100 m from the earth’s surface (hereinafter — geological repository); or 31.5.2. a possibility has been found to send radioactive waste for processing in a solid state in conformity with the packaging chosen in order to be able to safely transport and dispose it (hereinafter — processing) outside Latvia. 32. In a temporary radioactive waste repository and in an engineering construction located at little depth from the earth’s surface or created on the earth’s surface (hereinafter — near-surface repository) multiple protection barriers shall be utilised to ensure safe storage of radioactive waste. 33. For the long-term storage of radioactive waste only a near-surface repository of a radioactive waste management or disposal undertaking may be utilised. As safe storage criteria the following shall be utilised: 33.1. the impact of the relevant repository on environmental pollution, taking into account the natural radioactivity level — the specific radioactivity of radionuclides in materials and starting materials encountered in the relevant territory on average (with the condition that its amount has not significantly increased after some radiation emergency); and 33.2. the effect of long-term stored radioactive waste on a worker who carries out operations with sources of ionising radiation in the relevant repository. 34. In storing radioactive waste the following requirements shall be observed: 34.1. for each specific group of radioactive waste storage shall be ensured separately from other groups, taking into account also the requirements specified in Sub-paragraph 15.2; 34.2. for non-treated radioactive waste temporary storage shall be planned for not longer than a year and during this time radioactive waste shall be treated, packaged and transferred for disposal or long-term storage; 34.3. the radioactive waste container, if possible, shall not be moved in the repository until the transfer for disposal or long-term storage; 34.4. radioactive waste shall be stored separately from those sources of radioactive radiation which can be utilised for further operations; and 34.5. radioactive waste shall be stored in containers, which are suited for the relevant type of storage and are appropriately labelled. 35. If it is intended to store a group of radioactive waste until decay, in order to reduce the amount of radioactive waste to be sent for disposal, a special compartment in the temporary radioactive waste repository shall be created which is intended for storage until decay and in which emplacement of other groups of radioactive waste or materials related to radioactive waste is prohibited. 36. Storage until decay shall be applied to short-lived radioactive waste, as well as other radioactive waste if the operator ensures that it shall be stored as long as necessary so that after radionuclide decay its radioactivity does not exceed the minimum significant radioactivity. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 9 37. Materials related to radioactive waste which contain short-lived radioactive waste shall be stored in a temporary radioactive waste repository until its specific radioactivity as a result of radionuclide decay becomes smaller than the minimum significant radioactivity. 38. The operator shall ensure that storage until decay does not exceed one year but in separate cases, if it is provided for in the special permit (licence) or permit for operations with sources of ionising radiation, the storage time until radionuclide decay may be five years. 39. The compartment which is intended for storage until decay shall provide a possibility to disperse under controlled circumstances the unusable materials generated upon radionuclide decay, taking into account the permissible amounts of radionuclides for dispersal specified in regulatory enactments. 40. A temporary radioactive waste repository: 40.1. shall be so created that all radioactive waste which may be generated within a year can be stored separately by groups; 40.2. shall be provided with protection against unauthorised entry therein and the possibility to ascertain that no unauthorised operations with radioactive waste are carried out; 40.3. shall be equipped with installations and materials for protection against ionising radiation; 40.4. shall be so created that all surfaces are made of materials, which are easy to decontaminate or are covered with such materials; 40.5. shall be provided with air purification systems and exhaust gas monitoring facilities if during storage radioactive gases may be released from radioactive waste or the air in the repository may be polluted with radioactive aerosols; and 40.6. shall be so created that all operations are carried out under safe conditions and it is possible to easily transfer radioactive waste containers so as to transport them to a radioactive waste disposal or management undertaking. 41. Flammable or combustible radioactive waste shall be stored separately from other radioactive waste, ensuring the fulfilment of the necessary fire-safety requirements and ensuring the processing thereof in a maximally short period of time. 42. Liquid radioactive waste shall be stored in hermetically sealed double-containers. The work supervisor of the operator shall ensure that the volume of the outer radioactive waste container is sufficient for safe storage of all liquid radioactive waste if the internal container loses leak tightness. V. Requirements for Dispersal of Unusable Materials and Materials Related to Radioactive Waste in the Environment 43. Prior to dispersal of unusable materials or materials related to radioactive materials in the environment the work supervisor of the operator shall: 43.1. check whether the chemical and biological properties of unusable materials to be dispersed in the environment allow the application of the dispersal method; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 10 43.2. check whether there is the necessary guarantee to prevent the exceeding of the permissible amounts of radionuclides for dispersal (for each portion of dispersal or day and year) prescribed in regulatory enactments regarding protection against ionising radiation; 43.3. check whether at the point of dispersal a possibility to dilute the radioactive waste is ensured, so that its total and specific radioactivity does not exceed the permissible amounts of radionuclides for dispersal in the environment prescribed in regulatory enactments; 43.4. make calculations to ascertain that the ionising radiation dose limits specified in Sub-paragraph 7.1 of these Regulations are not exceeded; and 43.5. inform the Centre: 43.5.1. every year by 15 December — regarding the planned dispersal of radioactive waste in the environment during the next calendar year; and 43.5.2. at regular intervals but not less than four times a year (by 15 April, 15 July, 15 October and 15 January) — regarding the dispersal operations carried out in the previous quarter. 44. When releasing liquid unusable materials into the sewerage system together with household waste water, the work supervisor of the operator shall ensure that: 44.1. at the waste water discharge site in the sewerage system they are diluted, reducing the concentration at least 10 times; 44.2. water solutions do not contain insoluble admixtures; 44.3. pH of the unusable materials is neutral; and 44.4. unusable materials are released only at one specially equipped site in which before and after their discharge water flows from the water main for at least one minute with a normal average flow. 45. Solid unusable materials or materials related to radioactive waste may be disposed of in a municipal or hazardous waste landfill site or dump if: 45.1. they do not contain explosive, inflammable materials and compressed gases; 45.2. there is no non-fixed radioactive contamination on the surface of the unusable material packaging but the fixed radioactive contamination does not exceed 0.4 Bq/cm 2 for beta radiation sources, gamma radiation sources and low toxicity alpha radiation sources or 0.04 Bq/cm 2 for other alpha radiation sources; and 45.3. they do not contain a sealed radiation source. 46. When dispersing gaseous unusable materials in the atmosphere the work supervisor of the operator shall ensure that: 46.1. the ventilation power disperses them reducing the concentration at least 10 times; and 46.2. all unusable materials are released into the atmosphere at one specially equipped site only. 47. If regulatory enactments do not specify radionuclide dispersal amounts for any of the radionuclides, the work supervisor of the operator shall prepare a temporary calculation of dispersal amounts, utilising the following conditions: 47.1. the maximum ionising radiation dose for the critical group of the population (the population who are exposed to the effect of a source of ionising radiation at a similar level and to Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 11 whom the exposure from such source is the greatest) may not exceed 100 µSv per year but the maximum average ionising radiation dose — 10 µSv per year. These values shall be utilised in calculating the dispersal limits for one solid unusable material portion or one day; 47.2. the specific radioactivity is equal to the radioactivity for which the special permit (licence) or permit for operations with sources of ionising radiation is required or smaller than that; 47.3. radionuclides get into the organism of an adult by intake thereof with water (liquid radioactive waste), food (solid radioactive waste) or by inhalation (gaseous radioactive waste); and 47.4. in numerical calculations of ionising radiation doses coefficients specified in regulatory enactments regarding protection against ionising radiation shall be used. 48. The operator shall co-ordinate the temporary dispersal amounts for radionuclides with the Centre. The Centre may permit to carry out separate operations, applying the calculated temporary dispersal amounts if the time of performance of the operations does not exceed three months. VI. Requirements for Processing of Radioactive Waste 49. The operator in the operator’s controlled area may create a radioactive waste processing site and carry out the processing thereof or, if such is provided for in the contract, transfer for processing to the radioactive waste disposal or management undertaking unprocessed radioactive waste. 50. When processing radioactive waste the requirements put forward by all the following operations shall be observed in each operation and the necessity to carry out additional treatment or processing of the previously processed radioactive waste at the radioactive waste disposal or management undertaking shall be prevented. 51. The operator of the radioactive waste disposal or management undertaking shall receive from the operator information regarding physical and chemical properties of the radioactive waste, the amount in units by mass or volume and the total or specific radioactivity. 52. The processor of radioactive waste shall be responsible for the use of appropriate processing technology and shall ensure that the external surface of the radioactive waste container is not contaminated with radioactive substances and the ionising radiation dose rate on the external surface of the package does not exceed the permissible limit. 53. When processing radioactive waste the work supervisor of the radioactive waste processor shall ensure that the level of specific radioactivity in each radioactive waste package (except for the package of a spent sealed source of radiation) is as even as possible, avoiding high specific radioactivity in any separate part of the package. 54. When processing radioactive waste such processing methods shall be selected that: Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 12 54.1. the obtained radioactive waste package is structurally stable and all radioactive materials in the package are in a chemically and mechanically stable monolithic form which restricts the spread of radioactive substances outside the radioactive waste package; 54.2. the radioactive waste package has as far as possible no empty spaces; 54.3. the radioactive waste package is not damaged within the range of the ambient temperature from -40°C to +55 °C; and 54.4. the radioactive waste package endures a pressure of 0.35 MPa and the vertical deformations after such check do not exceed 3%. 55. Solid radioactive waste in conformity with its total radioactivity, mass and dimensions shall be processed in the following manner: 55.1. it shall be packaged in a 0.1 m 3 steel drum which shall be emplaced in the middle of a 0.2 m 3 steel drum and the empty space among the radioactive waste shall be filled with concrete, ensuring that the whole empty space between the 0.1 m 3 and 0.2 m 3 steel drum (also beneath and above the 0.1 m 3 drum) is filled with concrete; 55.2. it shall be emplaced in a 0.2 m 3 steel drum and the empty space between the radioactive waste shall be filled with concrete, ensuring that the whole empty space between the drum and radioactive waste (also beneath and above the radioactive waste) is filled with concrete; 55.3. it shall be packaged in a 0.1 m 3 steel drum which shall be emplaced into special sockets in a reinforced concrete container; or 55.4. it shall be emplaced in a reinforced concrete container and the empty space among the radioactive waste shall be filled with concrete, ensuring that the whole empty space between the container and radioactive waste (also beneath and above the radioactive waste) is filled with concrete. 56. If the total radioactivity of radioactive waste is so great that concrete does not ensure the possibility of observing the permissible limits for ionising radiation dose rate on the package surface, additional protection layers shall be created which attenuate ionising radiation more effectively than concrete. 57. Liquid radioactive waste subsequent to its cementation shall be filled in a 0.2 m 3 steel drum. Cementation of liquid radioactive waste directly in the steel drum may be utilised as an alternative method if there is appropriate technical capacity for the performance of such work. 58. If ion exchange resins have been used for purification of liquid radioactive waste, such resins shall be processed utilising the cementation method and shall be filled into a 0.2 m 3 steel drum. Cementation of waste directly in the steel drum may be utilised as an alternative method if there is appropriate technical capacity for the performance of such work. 59. Organic liquid radioactive waste shall be processed into inorganic liquid radioactive waste, taking into account its radioactive, chemical, physical and toxic properties. 60. Organic liquid radioactive waste in small amounts may be added to liquid inorganic radioactive waste if it is experimentally proven that the cement matrix that has formed is Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 13 sufficiently stable. In such case the cemented radioactive waste shall be filled into a 0.1 m 3 steel drum which shall be emplaced in a special socket in a reinforced concrete container. 61. Spent sealed gamma radiation sources in conformity with their total radioactivity, number and dimensions: 61.1. shall be emplaced into a lead container, in exceptional cases — in an industrial container where these sources of ionising radiation were located during their use, ensuring in addition that all openings and ducts of this container are made airtight with melted lead. Thereafter the container shall be emplaced in the middle of a 0.2 m 3 steel drum and the empty space between the container and the drum (also beneath and above the container) shall be filled with concrete; 61.2. shall be packaged in a stainless steel container which shall be filled with lead pellets and emplaced into a special socket in a reinforced concrete container; or 61.3. shall be packaged in a stainless steel container which shall be filled with lead pellets, placed into the middle of a 0.2 m 3 steel drum and the empty space (also beneath and above the container) shall be filled with concrete. 62. Spent sealed sources of beta radiation in conformity with their total radioactivity, number and dimensions: 62.1. shall be emplaced into a stainless steal or plastic container, in exceptional cases — in special plastic bags, ensuring that the spent sealed sources of radiation are packaged in at least three bags. Thereafter the radioactive container or plastic bags shall be emplaced into a 0.2 m 3 steel drum and the empty space shall be filled with concrete, ensuring that the whole empty space between the plastic bag or container and the drum (also beneath and above the bag or container) is filled with concrete; or 62.2. shall be packaged in a stainless steel container, which shall be filled with heated quartz sand and shall be placed in a special socket in a reinforced concrete container. 63. Spent sealed radium containing radiation sources shall be emplaced into a copper ampoule, which shall be hermetically sealed. The copper ampoule shall be emplaced into a stainless steel ampoule, which shall be welded. In exceptional cases the stainless steel ampoule may only be hermetically screwed. If no organic materials are utilised for sealing of the stainless steel ampoule, its dimensions and thickness shall be sufficient to endure, without damage, the gas pressure generated as a result of the radioactive decay of radium. The sealed stainless steel ampoule shall be emplaced into a lead container which shall be emplaced into the middle of a 0.2 m 3 steel drum and the empty space between the container and the drum (also beneath and above the lead container) shall be filled with concrete. 64. Spent sealed neutron radiation sources shall be emplaced into a stainless steel ampoule, which shall be welded. In exceptional cases the ampoule may only be hermetically screwed. If no organic materials are utilised for sealing of the stainless steel ampoule, its dimensions and thickness shall be sufficient to endure, without damage, the gas pressure generated as a result of the radioactive decay. The sealed stainless steel ampoule shall be emplaced into a lead container which shall be emplaced into the middle of a 0.2 m 3 steel drum and the empty space between the container and the drum (also beneath and above the lead container) shall be filled with concrete. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 14 65. Spent sealed alpha radiation sources, which do not contain radium, in conformity with their total radioactivity shall be packaged: 65.1. into a stainless steel container which shall be filled with heated quartz sand and shall be emplaced into special sockets in a reinforced concrete container; or 65.2. in a stainless steel or plastic container. In exceptional cases (if the total radioactivity of the sources after the end of the State supervision period has decreased as a result of the radioactive decay of radionuclides to the limits for the non-exceeding of which no special permit (licence) or permit is required) the spent sealed radiation source may be packaged into at least three special plastic bags which shall be emplaced into the middle of a 0.2 m 3 steel drum and the empty space between the bag or container and the drum (also beneath and above the bag or container) shall be filled with concrete. 66. Radioactive waste, which contains ion exchange resins, shall be processed so that the absorbed and adsorbed radioactive substances are stabilised in the processed radioactive waste by means of the cementation method. If the operator carries out the processing of radioactive waste, the relevant cementation technology shall be co-ordinated with the operator of the radioactive waste disposal or management undertaking. VII. Requirements for Near-Surface Repository and Geological Repository of Radioactive Waste 67. When selecting a location for a near-surface repository or geological repository (hereinafter — disposal site) the following criteria shall be taken into account: 67.1. the climate and the annual amount of precipitation (average values, maximum and minimum observed values); 67.2. the economic activity to be performed in the surrounding territory; 67.3. the density of population; 67.4. the ability of the environment to absorb the impact caused by planned operations with radioactive waste without negative changes; 67.5. mineral resources; 67.6. hydrology of surface water and ground water; 67.7. seismic activities and karst formations; 67.8. potential possibilities for the industrial development; and 67.9. the proximity of other countries. 68. Within the controlled area of the radioactive waste disposal or management undertaking (within a territory around the disposal site where the received ionising radiation dose may reach 20 mSv per year) there shall be: 68.1. a part of the disposal site where it is possible to dispose packaged radioactive waste (hereinafter — radioactive waste vault); 68.2. long-lived radioactive waste storage vault or a room where radioactive waste may be permanently stored until the transfer thereof for disposal in the geological repository; 68.3. a temporary radioactive waste repository for short-term storage of spent sealed radiation sources; 68.4. a temporary radioactive waste repository where radioactive waste shall be stored until their treatment, processing and preparation for disposal; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 15 68.5. decontamination site or room; and 68.6. a room for storage of working materials and equipment. 69. Within the supervision area of the radioactive waste disposal or management undertaking (within a territory outside the controlled area where there is a possibility that the received effective dose may exceed 1 mSv) there shall be: 69.1. a security centre; 69.2. a parking place for means of transport; 69.3. an administrative building, a maintenance building and a laboratory; 69.4. a warehouse for materials, objects and spare parts; 69.5. a water supply system (including a pump station and water treatment plants); 69.6. a site for washing of means of transport; 69.7. an access road connecting the supervision area with the controlled area; 69.8. a municipal sewage water treatment system; and 69.9. a boiler house and electric power supply system. 70. A near-surface repository shall consist of several radioactive waste vaults, which shall be made of reinforced concrete, and whose minimum volume for disposal of radioactive waste shall be 100 m 3 and which may be divided into separate compartments. 71. When planning and creating radioactive waste vaults at a radioactive waste disposal or management undertaking the operator shall ensure that the contact of radioactive waste vaults with ground waters is prevented and a precipitation collection system is developed to drain them from the disposal site and ensure a possibility to control radioactive pollution in these waters. 72. The minimum wall thickness of radioactive waste vaults shall be 40 cm unless a thicker physical barrier layer is required in conformity with the long-term safety assessment. In assessing the necessary thickness of the physical barrier, both the natural physical barriers (including surrounding soil and ground layers) and the engineering structures which prevent or hinder the potential migration of radioactive waste from its disposal site shall be taken into account. 73. Radioactive waste to which storage until decay may be applied shall not be disposed of in a near-surface repository but long-lived radioactive waste may be stored therein until it is possible to dispose them in a geological repository. 74. In a near-surface repository the following shall be disposed of: 74.1. radioactive waste which does not contain isotopes with a half-life longer than 30 years; 74.2. radioactive waste whose total radioactivity is smaller than the values specified in Annex 3 to these Regulations; 74.3. low and intermediate radioactivity waste which contains only such radionuclides whose total or specific radioactivity after the time period during which the control in the radiation safety and nuclear safety area is performed and radiation monitoring programmes are implemented in order to ascertain that the radioactive waste does not endanger the environment, workers carrying out operations with radioactive waste and the population (hereinafter — State Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 16 supervision period), as a result of their decay will have decreased to the limits specified in regulatory enactments for the non-exceeding of which no special permit (licence) or permit is required; and 74.4. radioactive waste containing radionuclides whose total and specific radioactivity after the end of the State supervision period as a result of their decay exceeds the limits specified in regulatory enactments for the non-exceeding of which no special permit (licence) or permit is required if the long-term safety assessment proves that after an additional physical barrier has been created and the empty spaces in the radioactive waste vault between radioactive waste packages are filled with concrete, the potential ionising radiation dose caused by radioactive waste does not exceed 30 µSv per year. 75. In a geological repository the following shall be disposed of: 75.1. radioactive waste containing isotopes with a half-life longer than 30 years; 75.2. radioactive waste whose total radioactivity is greater than the values specified in Annex 3 of these Regulations; 75.3. low and intermediate radioactivity waste which contains radionuclides whose total or specific radioactivity after the end of the State supervision period is greater than the limits specified in regulatory enactments for the non-exceeding of which no special permit (licence) or permit is required; and 75.4. high radioactivity waste. 76. For a near-surface repository the State supervision period shall include the supervision of the near-surface repository until the moment when the acceptance of radioactive waste in the radioactive waste disposal or management undertaking is fully terminated (the undertaking is closed down) and 300 years after its closure. 77. The maximum permissible total radioactivity of radioactive waste in a package and in a radioactive waste vault, when disposing thereof in a near-surface repository, is prescribed in Annex 3 of these Regulations. In determining the maximum radioactivity for radioactive waste packages, safe transportation of radioactive waste shall be ensured and one of the following conditions shall be observed: 77.1. after the end of the State supervision period the radioactivity of radionuclides due to their decay will have decreased to the limits specified in regulatory enactments for the non exceeding of which no special permit (licence) or permit is required; or 77.2. the limit specified in Annex 3 of these Regulations for a specific radionuclide may be exceeded if by means of the long-term safety assessment it is possible to substantiate that the foreseeable ionising radiation dose created by radioactive waste shall not exceed 300 µSv per year. VIII. Requirements for Acceptance of Radioactive Waste for Disposal or Long-term Storage 78. The operator shall: 78.1. be responsible for radioactive waste until the moment when it is placed in the specialised means of transport of the radioactive waste disposal or management undertaking or are accepted for storage if a means of transport of another undertaking is utilised; and Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 17 78.2. provide the radioactive waste disposal or management undertaking with all the necessary information (including the radioactive waste container and radioactive waste treatment and processing quality control documents regarding radioactive waste ) and provide a possibility to become acquainted with administrative, radiation safety, nuclear safety and technical capacity for the transfer of radioactive waste for disposal within the operator-controlled area on site. 79. The work supervisor of the radioactive waste disposal or management undertaking or another person working in the radiation safety and nuclear safety division of this undertaking upon acceptance of the radioactive waste from the operator shall check: 79.1. the ionising radiation dose rate at a distance of 1 cm and 1 m from the surface of the packaging; and 79.2. the radioactive contamination of the package on the surface thereof. 80. If it has been co-ordinated with the radioactive waste disposal or management undertaking, the maximum permissible ionising radiation dose rate on the external surface of the radioactive waste package may be 10 mSv/h but the maximum transport index may not exceed 10. 81. When accepting radioactive waste for disposal or long-term storage, the work supervisor of the radioactive waste disposal or management undertaking shall verify: 81.1. whether the dimensions and mass of the radioactive waste package, as well as auxiliary devices utilised for lifting and moving of such package conform to the requirements specified by the radioactive waste disposal or management undertaking; 81.2. the information provided by the operator regarding radioactive waste in each radioactive waste package with respect to the following: 81.2.1. the compliance of the technology utilised for treatment and processing with these Regulations; and 81.2.2. the compliance with disposal or long-term storage requirements; and 81.3. whether the deed of acceptance and delivery of radioactive waste specifies sufficient information regarding the radioactive waste (also regarding all radionuclides, their specific and total radioactivity), its treatment and processing, as well as regarding the packaging of the radioactive waste. 82. Safety of reinforced concrete containers shall be assessed by determining the tritium and 137Cs diffusion speed through a sample of concrete utilised in manufacturing of the radioactive waste containers the diameter of which sample shall be 7 cm and the thickness — 1 cm (for tritium) and 0.5 cm (for caesium). 83. Radioactive waste, which contains chemically or biologically hazardous materials, and materials, which may cause dangerous infectious diseases or in any other way endanger the epidemiological safety in the radioactive waste disposal or management undertaking shall not be accepted for disposal. 84. Radioactive waste which contains radionuclides with a half-life less than 50 days shall not be accepted for disposal if as a result of their decay no long-lived daughter products are produced. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 18 IX. Requirements for Long-term Safety Assessment of Disposed Radioactive Waste 85. Long-term safety assessment for radioactive waste disposal in a near-surface repository shall be performed by analysing a 1000-year period, but in a geological repository — at least a 10 000-year period. 86. If there are no special considerations in respect of additional factors, which may affect the migration of radionuclides, the following radioactive substance pathways shall be analysed in the long-term safety assessment: 86.1. discharges from radioactive waste vaults into the ground layer; 86.2. migration through the ground layer to: 86.2.1. open water basins; and 86.2.2. ground water layers utilised for drinking water intake; and 86.3. utilisation of water: 86.3.1. for watering; 86.3.2. for human consumption (drinking water); and 86.3.3. for watering of domestic animals. 87. For radiation emergency cases additional pathways shall be assessed (including the production of radioactive material dust in explosions resulting from a subversive activity or a plane crash) and the probability of such possible emergency and its impact on the safety of radioactive waste storage shall be analysed. 88. In performing the long-term safety assessment of geological repositories the following hypothetical earthquake parameters shall be utilised: 88.1. the maximum magnitude — 5.4 on the Richter scale; 88.2. earthquake probability — once in 400 years; 88.3. horizontal acceleration — 2.4 m/s 2 ; 88.4. vertical acceleration — 1.2 m/s 2 ; and 88.5. vertical movement — 2.0 cm. 89. If on the basis of the long-term safety assessment it is determined that the foreseeable ionising radiation dose for the population who live in the immediate proximity of the radioactive waste management or disposal undertaking is: 89.1. 100 mSv per year or greater, measures shall be obligatorily taken to reduce the ionising radiation dose to approximately 300 µSv per year; 89.2. from 10 to 100 mSv per year, measures shall be taken within the next five years to reduce the ionising radiation dose to approximately 300 µSv per year; and 89.3. 10 mSv per year or smaller, taking of intervention measures shall be evaluated in conformity with the financial and technical possibilities. 90. If on the basis of the environmental radiation monitoring results it is determined that the foreseeable ionising radiation dose for the population who live in the immediate proximity of the radioactive waste management or disposal undertaking is: 90.1. 5 mSv per year or greater, measures shall be obligatorily taken to reduce the ionising radiation dose to approximately 300 µSv per year; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 19 90.2. from 1 to 5 mSv per year, measures shall be taken within the next five years to reduce the ionising radiation dose to approximately 300 µSv per year; and 90.3. 1 mSv per year or smaller, taking of the necessary measures shall be evaluated in conformity with the financial and technical possibilities. 91. In the long-term safety assessment at least three following events shall be utilised which pose a danger to people and the environment: 91.1. transfer of radionuclides by water; 91.2. direct exposure; and 91.3. destruction of the radioactive waste vault and transfer of radionuclides by air (when constructing a road over the disposal site). 92. In analysing the possible transfer of radionuclides by water, the following assumptions shall be utilised: 92.1. complete degradation of the hydro-isolating layer takes place on the fiftieth year after the end of the State supervision period (350th year after the closure of a near-surface repository), hence the filtration speed through the hydro-isolating layer equals to the average speed in the ground layers of the relevant territory; 92.2. for the time period until the 350th year it shall be assumed that the water filtration speed through the hydro-isolating layers is 1% of the average filtration speed in the relevant ground layers; 92.3. walls of steel drums shall not be considered a barrier layer or it shall be assumed that the corrosion speed is 3 µm per year; 92.4. the foreseeable ionising radiation dose shall be calculated for a hypothetical group of the population living at a distance of 1000 m from the disposal site; and 92.5. migration of radionuclides from a radioactive waste vault to ground waters and further transfer of radionuclides to the human organism by water if water is utilised as drinking water, for watering of gardens and for watering of domestic animals. Thereafter the other radioactive substance pathway shall be analysed — by dust generated by the soil polluted as a result of the watering of gardens. 93. In assessing direct exposure, the following main assumptions shall be utilised: 93.1. at the end of the State supervision period (300 years after the closure of the near surface repository) an inhabitant builds a single family house directly on the reinforced concrete cover above a radioactive waste vault (the upper layer of soil has been removed); 93.2. an inhabitant stays in the house 6575 hours per year, outside the house — 2192 hours per year; 93.3. water for drinking and individual farming is obtained from the closest (in respect of the radioactive waste vault) ground water layer; and 93.4. the floor of the building is located three meters above the radioactive waste layer. 94. In assessing road construction, the following main assumptions shall be utilised: 94.1. operations take place after the end of the State supervision period (300 years after the closure of a near-surface repository); 94.2. road construction works are carried out with the average speed of 10 km per six months; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 20 94.3. work is carried out eight hours per day 20 days per month; 94.4. radioactive waste vaults are partly or fully destroyed because the intervention depth is six meters; 94.5. dust is directly inhaled; and 94.6. radioactive dust together with food from hands is transferred to the organism. 95. Operations and events which pose a danger to people and the environment during the operational and State supervision period and which are utilised in the safety assessment shall be the following: 95.1. a radiation emergency during performance of technological operations with radioactive waste packages; 95.2. an emergency during performance of technological operations in relation with labelling, concreting and dismantling of buildings; 95.3. a plane crash that partly or fully damages the cover of radioactive waste vaults; 95.4. an explosion (caused by subversive activity) which partly or fully damages the cover of radioactive waste vaults; 95.5. seismic activities (including karst formations) which may partly damage the cover of radioactive waste vaults; 95.6. roots of plants and trees and other biological effect which reduces hydro-isolation of the cover of radioactive waste vaults; and 95.7. precipitation. 96. Operations and events which pose a danger to people and the environment after the end of the State supervision period and which are utilised in the long-term safety assessment shall be the following: 96.1. road construction; and 96.2. building construction; 96.3. a plane crash that partly damages the cover of radioactive waste vaults; 96.4. seismic activity (including karst formations) which may partly damage the cover of radioactive waste vaults; 96.5. roots of plants and trees and other biological effect which reduces hydro-isolation of the cover of radioactive waste vaults; and 96.6. precipitation. X. Requirements for Radioactive Waste Management After Closure of Radioactive Waste Vault And Termination of Disposal Site Operation 97. After the filling of near-surface radioactive waste vaults with radioactive waste packages preservation of radioactive waste shall be performed. Preservation of radioactive waste has the following stages: 97.1. the first stage shall commence before covering of vaults with a ground layer and shall end 30 years after creation of the vault protection layer and stabilisation of the ground layer. The principal measures: 97.1.1. physical protection of the territory shall be ensured, utilising also guard patrols directly around the radioactive waste vaults; Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 21 97.1.2. a supervision territory around the radioactive waste management or disposal undertaking shall be determined; 97.1.3. environmental radiation monitoring shall be ensured; 97.1.4. radionuclide radioactivity measurements of ground water and drainage water, as well as other examinations shall be performed to ascertain that there is no radionuclide leakage from radioactive waste vaults; and 97.1.5. ground water control wells and other systems shall be maintained in order; 97.2. the second stage shall commence 30 years after the creation of the radioactive waste vault protection layer and stabilisation of the ground layer and shall end 260 years thereafter. The principal measures — the measures referred to in Clauses 97.1.1, 97.1.2, 97.1.3 and 97.1.4 of these Regulations; and 97.3. the third stage shall commence 260 years after the creation of a radioactive waste vault protection layer and stabilisation of the ground layer and shall last until the end of the State supervision period. The principal measures — the measures referred to in Clauses 97.1.1 and 97.1.3 of these Regulations, as well as imposing of a prohibition on earth excavation works and other operations which may affect the safety of the radioactive waste vaults. 98. Prior to the closure of a radioactive waste vault the empty spaces in the radioactive waste vault shall be filled: 98.1. with concrete if at the end of the State supervision period in the near-surface repository there are radioactive waste packages in which the specific radioactivity of radionuclides exceeds the limits prescribed in regulatory enactments for the non-exceeding of which no special permit (licence) or permit is required, and in the whole radioactive waste vault the average specific radioactivity is smaller than the relevant limits; or 98.2. with sand if at the end of the State supervision period in the near-surface repository in all radioactive waste packages the specific radioactivity of radioactive waste as a result of radionuclide decay is less than the relevant limits and placing the relevant additional layers specified in Paragraph 99 of these Regulations above it, except for the case when the liquidation concept provides for dismantling of radioactive waste vaults and transfer of the radioactive waste packages and disposal thereof in municipal waste disposal sites. 99. In order to ensure that the amount of atmospheric precipitation, which reaches the radioactive waste vault, does not exceed 1.5 litres per 1 m 2 per year and that there is minimum human interference possible, after closure of the radioactive waste vault a multiple protection system shall be created: 99.1. above the radioactive waste vault at least 1 m thick monolith reinforced concrete layer shall be created with a slope at the sides of the radioactive waste vault to prevent accumulation of water above the radioactive waste vault; 99.2. above the reinforced concrete layer a multi-layer hydro-isolating cover shall be created; 99.3. to prevent damage of hydro-isolating cover at least 1 m thick gravel layer shall be spread on top of it; 99.4. above the gravel layer a 50 cm thick clay protection layer shall be created in addition; 99.5. above the clay layer at least 1 m thick crushed stone layer shall be created to protect the radioactive waste vault against human intervention; and Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 22 99.6. a 2 m thick soil layer shall be created last. 100. The layer covering the radioactive waste vault shall have the following technical requirements: 100.1. rain water filtration through the layer to the reinforced concrete layer covering the radioactive waste vault shall be reduced to the minimum; 100.2. the covering layer shall retain its properties unchangeable under all weather conditions possible in the relevant territory. In assessment the maximum parameters observed during the last 100 years shall be utilised; and 100.3. the covering layer shall endure freezing and thawing cycles, biological effect (also the effect of the tree root system growing above the radioactive waste vaults) after the end of the State supervision period until the moment when the total and specific radioactivity in all radioactive waste packages will have decreased to the limits prescribed by regulatory enactments for the non-exceeding of which no special permit (licence) or permit is required. 101. After closure of a radioactive waste vault a labelling in the reinforced concrete layer shall be made which shall warn of the disposed radioactive waste. In making the labelling of radioactive waste vaults the following requirements shall be met: 101.1. the labelling shall be made directly in the reinforced concrete layer, utilising stone squares in a contrast colour; 101.2. the labelling shall contain an inscription “RADIOAKTĪVIE ATKRITUMI” [radioactive waste] and the internationally accepted radiation symbol; 101.3. the inscription shall be clearly legible, the radiation symbol — unambiguous; 101.4. the inscription shall be made in four languages — Latvian, English, German and Russian; and 101.5. the year when the relevant vault was sealed shall be specified below the inscription (using both Arabic and Roman numerals). 102. When levelling off the disposal site, additional markers shall be placed beneath the ground which shall have the labelling hollowed out and each side of the triangular pyramid shall bear an inscription “RADIOAKTĪVIE ATKRITUMI” [radioactive waste] in Latvian and in one of the foreign languages specified in Sub-paragraph 101.4 of these Regulations and the base — the radiation symbol. The additional markers shall be placed as follows: 102.1. in the depth of 1 m from the ground surface a marker in the form of a triangular pyramid shall be placed, the linear dimensions of which shall be 0.5 m. The distance between such markers shall be approximately 5 m; and 102.2. in the depth of 0.3 m from the ground surface markers whose linear dimensions are 0.2 m shall be placed. The distance between such markers shall be approximately 2.5 m. 103. Before the end of the State supervision period a concrete pyramid shall be placed above the ground layer which covers the radioactive waste vault, in each corner and in the middle of the vault on which there shall be the labelling specifying the information referred to in Paragraph 101 of these Regulations and the number of the radioactive waste vault in conformity with the record information. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 23 104. After the closure of a radioactive waste disposal or management undertaking the work performance schedule shall be the following: 104.1. during the time period until the 285th year after closure of the radioactive waste disposal or management undertaking, environmental radiation monitoring, repair of radioactive waste packages and packaging of radioactive waste packages in outer additional packages shall be performed if such is necessary, as well as physical protection shall be ensured, if necessary also utilising guards patrols; 104.2. on the 285th year after the closure of the radioactive waste disposal or management undertaking the total and specific radioactivity for all radioactive waste packages shall be calculated as it will be on the 300th year after the closure of the undertaking referred to and the state of the packages shall be examined. Damaged radioactive waste packages shall be packaged additionally (for example, 0.2 m 3 steel drums shall be emplaced into 0.25 m 3 steel drums and the whole empty space between the drums (also beneath and above the 0.2 m 3 drum) shall be filled with concrete); 104.3. on the 286th year the empty spaces in radioactive waste vaults shall be filled with sand or concrete, taking into account the provisions specified in Paragraph 98 of these Regulations; 104.4. on the 290th year additional filling and compacting in the radioactive waste tanks shall be performed if necessary, the covering reinforced concrete layer and all additional layers shall be created; 104.5. on the 295th year buildings shall be dismantled, the upper ground layer shall be adjusted, a level surface shall be created above all radioactive waste vaults in the disposal site and concrete markers shall be placed; 104.6. on the 300th year the soil layer shall be adjusted, additional concrete markers shall be placed by perimeter and in the disposal site; and 104.7. on the 301st year State supervision shall be terminated. XI. Requirements for Return of Spent Ionising Radiation Sources to Manufacturers and Shipment of Radioactive Waste for Processing Outside Latvia 105. The operator who plans to import a spent ionising radiation source which contains radioactive materials with such total radioactivity that after the use of these ionising radiation sources for 10 years it will exceed 100 MBq, before acquiring thereof in the operator’s ownership or possession shall take all the possible measures so that the possibility to return such spent ionising radiation source to its manufacturer is provided for in the purchase and sales or gift contract. 106. The purchase and sales or gift contract shall at least provide for the following provisions: 106.1. the maximum time limit during which the spent ionising radiation source may be returned to its supplier shall be 15 years after entering into the purchase and sales or gift contract; and 106.2. the supplier shall undertake to accept back a spent ionising radiation source after the end of the safe usage period thereof within a year after receipt of a written request by the ionising radiation source user. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 24 107. Extracts from the purchase and sales or gift contract regarding the possibility to return a spent ionising radiation source to its supplier shall be submitted to the Centre and the State institution responsible for radiation safety and nuclear safety where the supplier is registered. 108. It shall be prohibited to ship radioactive waste to: 108.1. places which are located further than 60° in the southern hemisphere; 108.2. those African, Caribbean and Pacific States which on 15 December 1989 in Lome signed the Fourth African, Caribbean and Pacific - European Economic Community Convention; and 108.3. states that do not have sufficient technical, legal or administrative capacity to safely carry out operations with radioactive waste without endangering the environment and the population. 109. If the requirements set out in Paragraph 108 of these Regulations are not complied with, the Centre shall ensure that the radioactive waste is returned to that operator whose operations have produced it. 110. If shipment of radioactive waste for processing outside Latvia is planned, the operator shall submit to the Centre an application for receipt of the relevant authorisation (Section one of Annex 4). In the application the operator may also request authorisation for several shipments of radioactive waste if: 110.1. radioactive waste in all planned shipments will have the same physical and chemical properties, it will contain the same radionuclides and its total and specific radioactivity will be the same; 110.2. the radioactive waste shipments in all cases are planned by one and the same operator, one and the same carrier will be utilised and there will be one and the same radioactive waste processor; 110.3. in all radioactive waste transportation cases transit countries will be the same and the same border crossing points will be utilised; and 110.4. the total shipment period for all radioactive waste shall not be longer than three years. 111. The Centre shall send the application and an authorisation form of the competent institution (sample of the authorisation — in Section two of Annex 4) to the competent institution of that state in which the processing of radioactive waste is planned to be performed and to the competent institutions of all those state through which it is planned to transport such radioactive waste, as well as request provision of an opinion in respect of the application. 112. If official authorisation is received from all competent institutions of those states to which the application to authorise shipment of radioactive waste for processing outside Latvia was sent, the Centre may issue an authorisation for the radioactive waste export for processing (sample of the authorisation — Section three of Annex 4). 113. A copy of the authorisation issued by the Centre shall be sent to the radioactive waste processor together with other necessary documents specified in Cabinet Regulation No 307 of 3 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 25 July 2001, Regulations Regarding Protection Against Ionising Radiation During Transportation of Radioactive Materials and other regulatory enactments. 114. The undertaking to which radioactive waste has been shipped for processing shall within a period of 15 days after receipt of the radioactive waste at the processing site send to the competent institution of its state an acknowledgement (Sections four and five of Annex 4) regarding receipt of such radioactive waste but to all competent institutions of those states which were involved in the authorisation of such consignment — copies of the acknowledgement. 115. The procedures referred to in Paragraphs 108, 109, 110, 111, 112, 113 and 114 of these Regulations shall not be applied if spent sealed radiation sources (except for nuclear materials) in conformity with the purchase and sales or gift contracts are returned to the manufacturers thereof. 116. The operator may not refuse to accept the radioactive waste back if due to any reason the shipment of radioactive waste cannot be completed. XII. Closing Provision 117. The Environmental Protection and Regional Development Ministry in accordance with the procedures set out in law shall authorise an institution, which until creation of a geological repository shall store all long-lived radioactive waste. Prime Minister A. Bērziņš Minister for Environmental Protection and Regional Development V. Makarovs Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 26 Annex 1 Cabinet Regulation No. 129 19 March 2002 Minimum Significant Specific Radioactivity Table 1 Minimum Significant Specific Radioactivity for Various Materials No Radionu clide Radioactive contamination on the surface if materials are used again (Bq/cm 2 ) Specific radioactivity if concrete construction debris is used (Bq/g) Specific radioactivity on a municipal or hazardous waste landfill site or dump if materials related to radioactive waste are disposed of (Bq/g) 1. 3H 1 x 104 3 x 104 1 x 105 2. 14C 1 x 102 3 x 102 1 x 103 3. 22Na 1 x 10-1 3 x 10-1 1 x 100 4. 24Na 1 x 10-1 3 x 10-1 1 x 100 5. 32P 1 x 10-1 3 x 101 1 x 102 6. 35S 1 x 103 3 x 103 1 x 104 7. 36Cl 1 x 102 3 x 102 1 x 103 8. 45Ca 1 x 102 3 x 102 1 x 103 9. 51Cr 1 x 101 3 x 101 1 x 102 10. 54Mn 1 x 100 3 x 10-1 1 x 100 11. 55Fe 1 x 102 3 x 102 1 x 103 12. 59Fe 1 x 100 3 x 10-1 1 x 100 13. 57Co 1 x 101 3 x 100 1 x 101 14. 58Co 1 x 100 3 x 10-1 1 x 100 15. 60Co 1 x 100 3 x 10-1 1 x 100 16. 63Ni 1 x 103 3 x 103 1 x 104 17. 65Zn 1 x 101 3 x 10-1 1 x 100 18. 89Sr 1 x 101 3 x 101 1 x 102 19. 90Sr 1 x 100 3 x 100 1 x 101 20. 90Y 1 x 100 3 x 101 1 x 102 21. 94Nb 1 x 100 3 x 10-1 1 x 100 22. 99mTc 1 x 100 3 x 100 1 x 101 23. 99Tc 1 x 101 3 x 102 1 x 103 24. 106Ru 1 x 101 3 x 100 1 x 101 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 27 25. 110mAg 1 x 100 3 x 10-1 1 x 100 26. 109Cd 1 x 102 3 x 102 1 x 103 27. 111In 1 x 100 3 x 100 1 x 101 28. 124Sb 1 x 100 3 x 10-1 1 x 100 29. 125I 1 x 101 3 x 101 1 x 102 30. 129I 1 x 100 3 x 100 1 x 101 31. 131I 1 x 101 3 x 100 1 x 101 32. 134Cs 1 x 100 3 x 10-1 1 x 100 33. 137Cs 1 x 100 3 x 10-1 1 x 100 34. 144Ce 1 x 100 3 x 100 1 x 101 35. 147Pm 1 x 102 3 x 102 1 x 103 36. 152Eu 1 x 100 3 x 10-1 1 x 100 37. 192Ir 1 x 100 3 x 10-1 1 x 100 38. 204Tl 1 x 101 3 x 100 1 x 101 39. 210Pb 1 x 10-1 3 x 10-1 1 x 100 40. 210Po 1 x 10-1 3 x 10-1 1 x 100 41. 226Ra 1 x 10-1 3 x 10-1 1 x 100 42. 228Ra 1 x 10-1 3 x 10-1 1 x 100 43. 228Th 1 x 10-1 3 x 10-2 1 x 10-1 44. 230Th 1 x 10-1 3 x 10-2 1 x 10-1 45. 232Th 1 x 10-1 3 x 10-2 1 x 10-1 46. 234U 1 x 10-1 3 x 10-1 1 x 100 47. 235U 1 x 10-1 3 x 10-1 1 x 100 48. 238U 1 x 10-1 3 x 10-1 1 x 100 49. 237Np 1 x 10-1 3 x 10-2 1 x 10-1 50. 239Pu 1 x 10-1 3 x 10-2 1 x 10-1 51. 240Pu 1 x 10-1 3 x 10-2 1 x 10-1 52. 241Pu 1 x 10-1 3 x 100 1 x 101 53. 241Am 1 x 10-1 3 x 10-2 1 x 10-1 54. 244Cm 1 x 10-1 3 x 10-1 1 x 100 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 28 Table 2 Minimum Significant Specific Radioactivity for Scrap Metal No. Radionuclide Specific radioactivity for scrap metal containing iron (Bq/g) Specific radioactivity for scrap metal containing copper (Bq/g) Specific radioactivity for scrap metal containing aluminium (Bq/g) 1. 3H 1 x 103 9 x 104 2 x 104 2. 14C 8 x 101 3 x 103 6 x 102 3. 22Na 2 x 10-1 2 x 100 4 x 10-1 4. 24Na 6 x 10-1 6 x 10-1 6 x 10-1 5. 32P 2 x 102 2 x 102 2 x 102 6. 35S 6 x 102 1 x 104 3 x 103 7. 36Cl 1 x 101 3 x 102 4 x 102 8. 45Ca 6 x 102 6 x 102 1 x 103 9. 51Cr 7 x 101 7 x 101 7 x 101 10. 54Mn 2 x 100 4 x 100 4 x 100 11. 55Fe 3 x 104 3 x 104 7 x 104 12. 59Fe 2 x 100 2 x 100 2 x 100 13. 57Co 2 x 101 2 x 102 3 x 101 14. 58Co 1 x 100 4 x 100 4 x 100 15. 60Co 6 x 10-1 1 x 100 1 x 100 16. 63Ni 3 x 105 2 x 104 1 x 105 17. 65Zn 5 x 10-1 5 x 100 5 x 100 18. 89Sr 6 x 101 6 x 101 6 x 101 19. 90Sr 1 x 101 9 x 100 4 x 101 20. 90Y 9 x 101 3 x 101 9 x 101 21. 94Nb 4 x 10-1 9 x 10-1 6 x 10-1 22. 99mTc 2 x 101 2 x 101 2 x 101 23. 99Tc 4 x 101 4 x 102 5 x 102 24. 106Ru 1 x 100 7 x 100 9 x 100 25. 110mAg 5 x 10-1 5 x 10-1 1 x 100 26. 109Cd 1 x 101 3 x 102 2 x 102 27. 111In 6 x 100 6 x 100 6 x 100 28. 124Sb 8 x 10-1 8 x 10-1 5 x 10-1 29. 125I 3 x 100 1 x 102 1 x 102 30. 129I 4 x 10-1 2 x 101 6 x 101 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 29 31. 131I 6 x 100 6 x 100 6 x 100 32. 134Cs 2 x 10-1 2 x 100 6 x 10-1 33. 137Cs 6 x 10-1 7 x 100 2 x 100 34. 144Ce 1 x 101 2 x 101 2 x 101 35. 147Pm 6 x 103 7 x 104 3 x 104 36. 152Eu 5 x 10-1 3 x 100 8 x 10-1 37. 192Ir 2 x 100 6 x 100 4 x 100 38. 204Tl 3 x 102 4 x 102 5 x 102 39. 210Pb 7 x 10-2 1 x 100 3 x 10-1 40. 210Po 2 x 100 2 x 101 2 x 100 41. 226Ra 4 x 10-1 9 x 10-1 5 x 10-1 42. 228Ra 7 x 10-1 2 x 100 1 x 100 43. 228Th 4 x 10-1 1 x 100 6 x 10-1 44. 230Th 3 x 10-1 2 x 100 4 x 100 45. 232Th 3 x 10-1 2 x 100 4 x 100 46. 234U 3 x 100 7 x 100 2 x 100 47. 235U 3 x 100 8 x 100 8 x 10-1 48. 238U 4 x 100 8 x 100 2 x 100 49. 237Np 6 x 10-1 3 x 100 7 x 100 50. 239Pu 2 x 10-1 2 x 100 3 x 100 51. 240Pu 3 x 10-1 2 x 100 3 x 100 52. 241Pu 1 x 101 8 x 101 2 x 102 53. 241Am 3 x 10-1 2 x 100 4 x 100 54. 244Cm 6 x 10-1 3 x 100 6 x 100 Minister for Environmental Protection and Regional Development V. Makarovs Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 30 Annex 2 Cabinet Regulation No. 129 19 March 2002 Maximum Permissible Total and Specific Radioactivity if Radioactive Waste is Transported in 0.1 m 3 Steel Drums Without Additional Treatment (LSA-III) No Radionuclide Maximum permissible specific radioactivity (Bq/kg) Maximum permissible total radioactivity for a package (Bq) 1. 3H 4 x 1011 1 x 1013 2. 7Be 2 x 1011 1 x 1012 3. 14C 3 x 107 1 x 109 4. 22Na 5 x 109 1 x 1010 5. 35S 3 x 1010 1 x 1012 6. 36Cl 1 x 105 1 x 106 7. 40K 1 x 106 1 x 107 8. 45Ca 1 x 1010 1 x 1012 9. 46Sc 1 x 109 1 x 1010 10. 51Cr 3 x 1011 1 x 1012 11. 53Mn 1 x 107 1 x 109 12. 54Mn 1 x 1010 1 x 1012 13. 55Fe 1 x 1011 1 x 1012 14. 56Co 1 x 109 1 x 1010 15. 57Co 1 x 1011 1 x 1012 16. 58Co 1 x 1010 1 x 1011 17. 60Co 1 x 109 1 x 1010 18. 59Ni 1 x 107 1 x 108 19. 63Ni 1 x 108 1 x 109 20. 65Zn 6 x 109 1 x 1011 21. 73As 4 x 1011 1 x 1012 22. 75Se 1 x 1010 1 x 1011 23. 81Kr 1 x 108 1 x 109 24. 85Kr 1 x 1011 1 x 1012 25. 85Sr 1 x 1010 1 x 1011 26. 89Sr 6 x 109 1 x 1011 27. 90Sr+ 3 x 108 1 x 109 28. 91Y 6 x 109 1 x 1011 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 31 29. 93Zr+ 1 x 107 1 x 108 30. 95Zr 8 x 109 1 x 1011 31. 93mNb 3 x 1011 1 x 1012 32. 94Nb 1 x 105 1 x 106 33. 93Mo 1 x 107 1 x 108 34. 97Tc 1 x 107 1 x 108 35. 97mTc 1 x 1011 1 x 1012 36. 99Tc 1 x 107 1 x 108 37. 106Ru+ 2 x 109 1 x 1010 38. 110mAg 1 x 109 1 x 1010 39. 109Cd 2 x 1010 1 x 1012 40. 113Sn 1 x 1010 1 x 1011 41. 124Sb 6 x 109 1 x 1011 42. 125Sb 1 x 1010 1 x 1011 43. 123mTe 1 x 1010 1 x 1012 44. 125mTe 9 x 109 1 x 1012 45. 127mTe 7 x 109 1 x 1012 46. 125I 3 x 1010 1 x 1012 47. 129I 1 x 106 1 x 107 48. 134Cs 7 x 109 1 x 1011 49. 135Cs 1 x 108 1 x 109 50. 137Cs+ 1 x 109 1 x 1010 51. 139Ce 2 x 1010 1 x 1012 52. 144Ce+ 1 x 109 1 x 1010 53. 151Sm 1 x 108 1 x 109 54. 152Eu 1 x 109 1 x 1010 55. 154Eu 6 x 109 1 x 1011 56. 155Eu 3 x 1010 1 x 1012 57. 153Gd 9 x 1010 1 x 1012 58. 160Tb 6 x 109 1 x 1011 59. 170Tm 6 x 109 1 x 1011 60. 171Tm 1 x 1010 1 x 1011 61. 182Ta 5 x 109 1 x 1011 62. 181W 3 x 1011 1 x 1012 63. 185W 8 x 109 1 x 1012 64. 185Os 1 x 1010 1 x 1011 65. 192Ir 5 x 109 1 x 1012 66. 204Tl 7 x 109 1 x 1012 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 32 67. 210Pb+ 1 x 108 1 x 109 68. 207Bi 1 x 107 1 x 108 69. 210Po 2 x 109 1 x 1012 70. 222Rn+ 4 x 107 1 x 1010 71. 226Ra+ 1 x 105 1 x 106 72. 228Ra+ 1 x 109 1 x 1010 73. 228Th+ 1 x 107 1 x 1010 74. 229Th+ 1 x 104 1 x 105 75. 230Th 1 x 104 1 x 105 76. dab.Th 1 x 104 1 x 105 77. 231Pa 1 x 104 1 x 105 78. 232U+ 1 x 105 1 x 106 79. 233U 1 x 104 1 x 105 80. 234U 1 x 104 1 x 105 81. 235U+ 1 x 104 1 x 105 82. 236U 1 x 104 1 x 105 83. 238U+ 1 x 104 1 x 105 84. 237Np+ 1 x 104 1 x 105 85. 236Pu 1 x 103 1 x 104 86. 238Pu 1 x 104 1 x 105 87. 239Pu 1 x 104 1 x 105 88. 240Pu 1 x 104 1 x 105 89. 241Pu 1 x 105 1 x 106 90. 242Pu 1 x 105 1 x 106 91. 244Pu 1 x 104 1 x 105 92. 241Am 1 x 104 1 x 105 93. 242mAm+ 1 x 104 1 x 105 94. 243Am+ 1 x 104 1 x 105 95. 242Cm 1 x 106 1 x 107 96. 243Cm 1 x 106 1 x 107 97. 244Cm 1 x 106 1 x 107 98. 245Cm 1 x 104 1 x 105 99. 246Cm 1 x 104 1 x 105 100. 247Cm 1 x 104 1 x 105 101. 248Cm 1 x 104 1 x 105 102. 249Bk 1 x 105 1 x 106 103. 248Cf 1 x 106 1 x 107 104. 249Cf 1 x 104 1 x 105 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 33 105. 250Cf 1 x 105 1 x 106 106. 251Cf 1 x 104 1 x 105 107. 252Cf 1 x 107 1 x 108 108. 253Cf 1 x 106 1 x 107 109. 254Cf 1 x 107 1 x 108 Minister for Environmental Protection and Regional Development V. Makarovs Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 34 Annex 3 Cabinet Regulation No. 129 19 March 2002 Maximum Permissible Total Radioactivity of Radioactive Waste Upon Disposal Thereof in Near-Surface Repository (in a Vault, for Package and Spent Sealed Radiation Source) No . Radionuclide Maximum permissible total radioactivity in a 100 m 3 radioactive waste vault (Bq) Maximum permissible total radioactivity for a 0.2 m 3 radioactive waste package (Bq) Maximum permissible total radioactivity for a spent sealed radiation source (Bq) 1. 3H 1 x 1017 1 x 1013 1 x 107 2. 7Be no limit 1 x 1013 3 x 1010 3. 14C 1 x 1013 1 x 1010 1 x 108 4. 22Na no limit 1 x 1011 3 x 1010 5. 35S no limit 1 x 1013 3 x 1011 6. 36Cl 3 x 1012 5 x 109 1 x 107 7. 40K 1 x 1011 1 x 109 1 x 108 8. 45Ca no limit 1 x 1013 3 x 1011 9. 46Sc no limit 1 x 1011 3 x 1010 10. 51Cr no limit 1 x 1013 3 x 1010 11. 53Mn 1 x 1012 1 x 1010 1 x 106 12. 54Mn no limit 1 x 1012 3 x 108 13. 55Fe no limit 4 x 1013 1 x 1012 14. 56Co no limit 3 x 1011 2 x 1010 15. 57Co no limit 1 x 1013 2 x 1012 16. 58Co no limit 1 x 1012 2 x 1011 17. 60Co 1 x 1022 1 x 1011 1 x 1011 18. 59Ni 1 x 1013 1 x 1010 3 x 108 19. 63Ni 1 x 1014 1 x 1011 3 x 108 20. 65Zn no limit 1 x 1012 1 x 1012 21. 73As no limit 4 x 1013 3 x 1010 22. 75Se no limit 3 x 1012 3 x 1010 23. 81Kr 1 x 1013 1 x 1010 3 x 107 24. 85Kr 1 x 1019 1 x 1013 1 x 108 25. 85Sr no limit 2 x 1012 3 x 1010 26. 89Sr no limit 1 x 1012 3 x 1010 27. 90Sr+ 1 x 1011 1 x 1010 3 x 109 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 35 28. 91Y no limit 1 x 1012 3 x 1010 29. 93Zr+ 1 x 1012 1 x 1010 3 x 108 30. 95Zr no limit 1 x 1012 3 x 1010 31. 93mNb 1 x 1015 1 x 1013 3 x 106 32. 94Nb 1 x 109 1 x 107 3 x 106 33. 93Mo 1 x 1012 1 x 1010 3 x 108 34. 97Tc 1 x 1012 1 x 1010 3 x 106 35. 97mTc 1 x 1014 1 x 1013 3 x 106 36. 99Tc 3 x 1012 5 x 109 1 x 107 37. 106Ru+ no limit 2 x 1011 3 x 1010 38. 110mAg no limit 1 x 1011 1 x 1011 39. 109Cd no limit 3 x 1013 3 x 1011 40. 113Sn no limit 1 x 1013 3 x 1010 41. 124Sb no limit 1 x 1012 1 x 1011 42. 125Sb no limit 1 x 1012 1 x 1011 43. 123mTe 1 x 1020 1 x 1013 3 x 1010 44. 125mTe no limit 2 x 1013 3 x 1010 45. 127mTe no limit 2 x 1013 3 x 1010 46. 125I no limit 1 x 1013 1 x 1010 47. 129I 5 x 1010 5 x 107 3 x 106 48. 134Cs no limit 1 x 1012 1 x 1011 49. 135Cs 1 x 1013 1 x 1010 7 x 104 50. 137Cs+ 1 x 1012 3 x 1010 3 x 109 51. 139Ce no limit 1 x 1013 3 x 1010 52. 144Ce+ no limit 1 x 1011 7 x 1010 53. 151Sm 1 x 1013 1 x 1010 3 x 109 54. 152Eu 1 x 1013 1 x 1012 3 x 1010 55. 154Eu 1 x 1016 1 x 1012 7 x 1010 56. 155Eu no limit 1 x 1013 7 x 1010 57. 153Gd no limit 1 x 1013 7 x 1010 58. 160Tb no limit 1 x 1012 3 x 1010 59. 170Tm no limit 1 x 1012 3 x 1010 60. 171Tm no limit 1 x 1013 7 x 1010 61. 182Ta no limit 1 x 1012 3 x 1010 62. 181W no limit 3 x 1013 3 x 1011 63. 185W no limit 4 x 1013 3 x 1011 64. 185Os no limit 1 x 1012 1 x 1011 65. 192Ir no limit 1 x 1013 3 x 1012 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 36 66. 204Tl no limit 1 x 1013 3 x 1010 67. 210Pb+ 1 x 1012 1 x 1011 3 x 108 68. 207Bi 1 x 1012 1 x 1010 3 x 108 69. 210Po no limit 1 x 1013 3 x 109 70. 222Rn+ 1 x 1012 1 x 1011 3 x 109 71. 226Ra+ 1 x 109 5 x 106 4 x 105 72. 228Ra+ 1 x 1019 1 x 1011 3 x 109 73. 228Th+ no limit 5 x 1011 3 x 108 74. 229Th+ 3 x 108 1 x 106 2 x 105 75. 230Th 3 x 108 1 x 106 2 x 105 76. 232Thsec 3 x 108 1 x 106 2 x 105 77. 231Pa 3 x 108 1 x 106 2 x 105 78. 232U+ 3 x 108 1 x 106 1 x 106 79. 233U 3 x 108 1 x 106 1 x 106 80. 234U 3 x 108 1 x 106 1 x 106 81. 235U+ 3 x 108 1 x 106 3 x 105 82. 236U 3 x 108 1 x 106 1 x 106 83. 238U+ 3 x 108 1 x 106 1 x 106 84. 237Np+ 3 x 108 1 x 106 4 x 104 85. 236Pu 1 x 108 1 x 106 3 x 105 86. 238Pu 3 x 108 1 x 106 3 x 105 87. 239Pu 3 x 108 1 x 106 3 x 105 88. 240Pu 3 x 108 1 x 106 3 x 105 89. 241Pu 1 x 108 1 x 107 3 x 105 90. 242Pu 3 x 108 1 x 106 3 x 105 91. 244Pu 3 x 108 1 x 106 3 x 105 92. 241Am 3 x 108 1 x 106 3 x 105 93. 242mAm+ 3 x 108 1 x 106 4 x 104 94. 243Am+ 3 x 108 1 x 106 4 x 104 95. 242Cm 1 x 109 1 x 108 1 x 106 96. 243Cm 1 x 109 1 x 108 1 x 106 97. 244Cm 1 x 109 1 x 108 1 x 106 98. 245Cm 3 x 108 1 x 106 4 x 104 99. 246Cm 3 x 108 1 x 106 4 x 104 10 0. 247Cm 3 x 108 1 x 106 4 x 104 10 1. 248Cm 3 x 108 1 x 106 4 x 104 Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 37 10 2. 249Bk 1 x 108 1 x 107 1 x 106 10 3. 248Cf 1 x 1010 1 x 108 3 x 105 10 4. 249Cf 3 x 108 1 x 106 4 x 104 10 5. 250Cf 1 x 108 1 x 107 3 x 105 10 6. 251Cf 3 x 108 1 x 106 4 x 104 10 7. 252Cf 1 x 1010 1 x 109 3 x 105 10 8. 254Cf 1 x 1012 1 x 109 1 x 106 Minister for Environmental Protection and Regional Development V. Makarovs Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 38 Annex 4 Cabinet Regulation No. 129 19 March 2002 All documents the samples of which are given in this Annex shall be printed on white A4 format paper in black letters. In the international transport the English language shall be used and the usage of another official language of the United Nations Organisation understood by all persons involved in the transportation shall be permissible. STANDARD DOCUMENT FOR CONTROL OF SHIPMENTS OF RADIOACTIVE WASTE Section 1 Registration number (to be completed by the Radiation Safety Centre) APPLICATION FOR RADIOACTIVE WASTE SHIPMENT AUTHORISATION 1. Type of shipment 1 Shipment to an EU Member State (Type B)  Receipt from an EU Member State (Type C)  Transit through an EU Member State (Type D)  Shipment to a state which is not an EU Member State (Type E)  Receipt from a state which is not an EU Member State (Type F)  2. Application for authorisation for A single shipment  Several shipments  Number of shipments planned Planned period of execution 3. Radioactive waste producer (name) Contact person Address Post code Town Country Telephone Fax Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 39 4. (To be completed if the radioactive waste is not with the producer thereof) Place where radioactive waste is located Address Post code Town Country Telephone Fax 5. Description of radioactive waste Physical and chemical characteristics Main radionuclides Maximum alpha radioactivity in a package (GBq) Maximum beta radioactivity in a package (GBq) Maximum gamma radioactivity in a package (GBq) 6. Total alpha radioactivity (GBq) Total beta radioactivity (GBq) Total gamma radioactivity (GBq) Total number of packages *Total weight of radioactive waste (kg) *Total weight with packaging (kg) *Total volume (additional information) (*To be completed if the application for authorisation is intended for several shipments) Description of the radioactive waste package (including plastic bags, 200l steel drums, ISO transport containers) Information on labelling of packages (attach the samples of the used labelling, stickers, posters) 7. Other hazardous properties Category 1 Explosive substances and products  Category 2 Compressed, liquefied or dissolved under pressure gases  Category 3 Inflammable liquids  Category 4 4.1. Inflammable solids and materials  4.2. Substances liable to spontaneous combustion  4.3. Substances which, on contact with water, give off inflammable gases  Category 5 5.1. Oxidising substances  5.2. Organic peroxides  Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 40 Category 6 6.1. Poisonous substances  6.2. Infectious substances  Category 8 Corrosive substances  Category 9 Other dangerous substances and products  Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 41 8. Description of causes giving rise to radioactive waste (medical or industrial usage, scientific research or other cause) 9. Purpose of the shipment Radioactive waste from processing of spent nuclear fuel  Shipment of radioactive waste for processing or packaging  Receipt of radioactive waste after processing or packaging  Shipment of radioactive waste for temporary storage  Receipt of radioactive waste after temporary storage  Shipment of radioactive waste for disposal  Receipt of equivalent amount of radioactive waste in connection with disposal thereof outside the Republic of Latvia  Other purposes   10. Planned form of transport (road, rail, air, sea vessels, river vessels) Point of departure Point of destination Planned carrier 1. 2. 3. 4. 5. 11. Countries in the order of shipment performance (the first shall be indicated the country where the radioactive waste is held and the last the country to which it is shipped) 1. 3. 5. 7. 2. 4. 6. 8. 12. Consignee of radioactive waste at the point of destination (legal name) Contact person Address Post code Town Country Telephone Fax Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 42 13. (To be completed if the radioactive waste is received by an intermediary organisation) Place to which the radioactive waste shall be delivered Address Post code Town Country Telephone Fax 14. Applicant of the authorisation (legal name) Contact person Address Post code Town Country Telephone Fax 15. Notification a) I hereby apply for authorisation to ship the radioactive waste specified in the application (once/several times); b) I hereby certify that all submitted information is correct and accurate (to the best of my knowledge) and that the shipment (once/several times) was carried out in accordance with the requirements set out in regulatory enactments; c) 2 if the type of shipment is B, D or E — I undertake to take back all sent radioactive waste if the shipment cannot be completed; if the type of shipment is C or F — I attach a declaration, which specifies that the producer of radioactive waste undertakes to take back all shipped radioactive waste if the shipment cannot be completed. (date and place (signature and full name) Notes. 1 Type A is not specified because in EU Member States it is used to mark movement of radioactive waste between EU Member States only. 2 The notification text which complies with the type of shipment shall be chosen. Place for a seal Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 43 STANDARD DOCUMENT FOR CONTROL OF RADIOACTIVE WASTE SHIPMENTS Section 2 Registration number AUTHORISATION FOR SHIPMENT BY THE COMPETENT INSTITUTION 16. Type of shipment Type B Shipment to an EU Member State  Type C Receipt from an EU Member State  Type D Transit through an EU Member State  Type E Shipment to a state which is not an EU Member State  Type F Receipt from a state which is not an EU Member State  Authorisation issuer 3 (legal name) Contact person Address Post code Town Country Telephone Fax 17. Date of registration of the submission (signature and full name) 18. Competent institution 4 Country Place of origin of the waste  Transit country  Country of destination  Name of the competent institution Contact person Place for a seal Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 44 Address Post code Town Country Telephone Fax Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 45 19. Approval of the radioactive waste shipment by the competent institution 5 Authorised  Conditions if any  Not authorised  Reasons for the refusal  Conditions Reasons for the refusal (date and place) (signature and full name) Notes. 3 The issuer of the authorisation subsequent to receipt of an application for radioactive waste shipment authorisation (hereinafter — authorisation) shall without delay complete boxes 16 and 17 of this documents and register the application for the authorisation, as well as prepare the necessary number of authorisation copies for sending to all competent institutions of those states from which consent is required (hereinafter — competent institutions). For each competent institution box 18 shall be completed. The issuer of the authorisation shall prepare a copy of Section 1 and 2 of the document and send it to the relevant competent institution to receive its opinion. 4 The competent institution may supplement or adjust the information specified in box 18 of this document. 5 Within two months after receipt of these documents the competent institution shall complete box 19 of this document and shall send the original of the copy of Section 2 of Place for a seal Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 46 this document back to the issuer of the authorisation. The time for taking of the decision may be extended by one month if the competent institution requests such. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 47 STANDARD DOCUMENT FOR CONTROL OF RADIOACTIVE WASTE SHIPMENTS Section 3 Registration number (to be completed by the Radiation Safety Centre) RADIOACTIVE WASTE SHIPMENT AUTHORISATION 20. Issuer of the authorisation 6 in conformity with the type of shipment Type B Radiation Safety Centre  Type C Radiation Safety Centre  Type D Competent institution of an EU Member State  Type E Competent institution of the country (which is not an EU Member State)  Type F Radiation Safety Centre  Legal name of the competent institution Contact person Address Post code Town Country Telephone Fax 21. Authorisation granted  For a single shipment  Authorisation not granted  For several shipments  Authorisation valid until 22. Countries in the order of shipment performance (the first shall be specified the country where the waste is located but the last the country to which it is shipped) Countries Conditions Countries Conditions yes no yes no 1.   5.   2.   6.   3.   7.   4.   8.   Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 48 23. Conditions Reason for the refusal (indicating the country imposing the conditions and indicate references to attached documents) 24. Competent institutions are informed that the radioactive waste shipment authorisation has been granted or refused. (date and place) (signature and full name) P.S. 1. Authorisation shall not release the radioactive waste keeper, carrier, producer, consignee or any other natural person or legal person involved in the shipment of the radioactive waste from liability in respect of failure to perform the relevant requirements. 2. When shipping radioactive waste, appropriately completed and approved Sections 1, 3 and 4 of the standard document shall be used as freight accompanying documents. Notes. 6 The issuer of the authorisation: a) when completing box 21 the condition shall be taken into account that the maximum period of validity of the authorisation is three years; b) shall send the authorisation to the applicant thereof (the person who has applied for radioactive waste shipment or receipt authorisation), attaching to the document Sections 1, 4 and 5 of this document; c) shall send copies of this document to the competent institutions. Place for a seal Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 49 STANDARD DOCUMENT FOR CONTROL OF RADIOACTIVE WASTE SHIPMENTS Section 4 Registration number (to be completed by the Radiation Safety Centre) LIST OF RADIOACTIVE WASTE PACKAGES 7 25. Applicant of the authorisation (legal name) Contact person Address Post code Town Country Telephone Fax 26. Authorisation granted for a single shipment  Authorisation granted for several shipments  Serial number of the shipment 27. Description of radioactive waste Physical and chemical characteristics Main radionuclides Maximum alpha radioactivity in a package (GBq) Maximum beta radioactivity in a package (GBq) Maximum gamma radioactivity in a package (GBq) Description of the waste packaging (for example, plastic bags, 200l steel drums, ISO transport containers) 28. Total alpha radioactivity (GBq) Total beta radioactivity (GBq) Total gamma radioactivity (GBq) Total weight with the packaging (kg) Total volume (additional information) Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 50 29. Information regarding labelling of radioactive waste packages (identification number of each package, total weight of the package (kg/package), weight of radioactive waste in the package (kg/package), radioactivity (GBq/package)) (If the space provided above is insufficient additional sheets shall be used or documents containing the necessary information shall be attached) 30. Date of dispatch I hereby certify that all the information provided in this document and in the attached documents (if any) is correct and accurate (to the best of my knowledge). (date and place) (signature and full name) Note. 7 The list shall be completed by the radioactive waste producer before each shipment (also if the authorisation has been granted for several shipments). This Section of the document (like Sections 1 and 3 of this document) shall be used as a freight accompanying document during the whole period of shipment. After completion of the shipment this document shall be attached to the acknowledgement of radioactive waste receipt. Place for a seal Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 51 STANDARD DOCUMENT FOR CONTROL OF RADIOACTIVE WASTE SHIPMENTS Section 5 Registration number (to be completed by the Radiation Safety Centre) ACKNOWLEDGEMENT OF RADIOACTIVE WASTE RECEIPT 8 31. Consignee of radioactive waste at the point of destination (legal name) Contact person Address Post code Town Country Telephone Fax Place where the radioactive waste is stored Contact person Address Post code Town Country Telephone Fax 32. Authorisation granted for a single shipment  Authorisation granted for several shipments  Serial number of the shipment It is the last shipment to which the authorisation is granted Yes  No  33 (To be completed only if the type of shipment is C, D or F) Border crossing point upon entry to the country to which the radioactive waste is shipped Country Border crossing point 34. Date of receipt of the radioactive waste Date when the acknowledgement is sent (together with Section 4 of the standard document) The acknowledgement shall be sent if the type of shipment is B or E, - to the competent institution of the state of destination of the radioactive waste; if the type of shipment is C, D or E, - to the applicant of the authorisation. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 52 I hereby certify that all the information provided in this document and in the attached documents (if any) is correct and accurate (to the best of my knowledge). (signature and full name) 35. (To be completed only if the type of shipment is C, D or F) The applicant of the authorisation (sending the acknowledgement and radioactive waste consignee’s declaration to the issuer of the authorisation): Date when the acknowledgement is sent (together with Section 4 of the standard document) Border crossing point upon entry to the country to which the radioactive waste is sent Country Border crossing point (signature and full name) P.S. 1. If the consignee of the radioactive waste does not utilise this document, his or her declaration shall contain at least the same information as requested in boxes 31 and 35 of this document. 2. The competent institution, which has received the acknowledgement, shall send the copies thereof to other involved competent institutions. 3. Thereafter Sections 4 and 5 of this document shall be sent to the competent institution, which issued the radioactive waste shipment authorisation. Place for a seal Zīmoga vieta Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 53 Note. 8 This Section shall be completed by the consignee of the radioactive waste, supplementing the information provided by the applicant of the authorisation. The type of acknowledgement shall be chosen in conformity with the type of shipment and the fact whether the authorisation has been granted for a single or several shipments. If the authorisation is granted for a single shipment 1. Shipments of Type B or E Within 15 days of receiving of the radioactive waste the consignee of the waste shall complete boxes 31, 32 and 34 of this document and send Sections 4 and 5 of this document to the competent institution of that country to which the radioactive waste has been shipped. The competent institution of the country where the radioactive waste has been received shall send Sections 4 and 5 of this document to the competent institution, which issued the radioactive waste shipment authorisation, but a copy of Sections 4 and 5 of this document — to other involved competent institutions. 2. Shipment of type C, D or F The consignee of the radioactive waste shall ensure that the consignor after receipt of the radioactive waste freight sends Sections 4 and 5 of this document (with completed boxes 31 and 34) without delay. Within 15 days of receiving the radioactive waste the applicant of the authorisation shall send Sections 4 and 5 of this document to the competent institution which issued the radioactive waste shipment authorisation. The competent institution, which issued the radioactive waste shipment authorisation, shall send Sections 4 and 5 of this document to other involved competent institutions. If the authorisation is granted for several shipments 1. Shipments of type B or E The consignee of radioactive waste shall after receipt of each shipment complete boxes 31, 32 and 34 of this document and send Sections 4 and 5 of this document to the competent institution of that country to which the radioactive waste is shipped. Prior to that the consignee of radioactive waste shall prepare the necessary number of uncompleted copies of Section 5. 2. Shipments of type C, D or F The consignee of radioactive waste shall ensure that the consignor after receipt of each radioactive waste freight sends Sections 4 and 5 of this document (with completed boxes 31 and 34) without delay. The applicant of the authorisation shall complete box 35 of this document and together with Section 4 of this document send it to the competent institution, which issued the radioactive waste shipment authorisation. 3. Radioactive waste shipments of any type When all authorised radioactive waste shipments have been carried out the last acknowledgement of radioactive waste receipt shall be sent as if the authorisation were granted to a single shipment only, however: — in box 32 of this document it shall be stated that it is the acknowledgement of the last authorised shipment; — the notification shall state that all radioactive waste shipments have indeed been received; and — in order to provide an overview, Section 4 of this document in respect of all shipments, which have been completed, shall be attached. Translation © 2003 Tulkošanas un terminoloģijas centrs (Translation and Terminology Centre) 54 Minister for Environmental Protection and Regional Development V. Makarovs