Decree No. 67 / 1987 Coll.
Decree of the Czechoslovak Atomic Energy Commission on Nuclear Safety in the Treatment of Radioactive Waste
Valid
Effective from 01.09.1987
67
DECLARATION
Czechoslovak Atomic Energy Commission
of 30 June 1987
on nuclear safety in the management of radioactive waste
The Czechoslovak Commission on Atomic Energy, in cooperation with the Federal Ministry of Fuel and Energy, provides, pursuant to § 54 (3) (c) of Act No. 133 / 1970 Coll., on the competence of federal ministries, as amended by Act No. 115 / 1983 Coll. and under § 21 of Act No. 28 / 1984 Coll., on State control over nuclear safety of nuclear installations:
INTRODUCTORY PROVISIONS
Subject matter and purpose of the Order
The Decree sets out the basic technical and organisational requirements to prevent the release of radioactive substances into the air, water or soil (hereinafter referred to as the "environment ') when handling radioactive waste generated in nuclear installations.
Scope
(1) The Decree provides for a binding procedure for bodies, organisations and their personnel who design and design (hereinafter "design"), manufacture and implement construction (hereinafter "building"), put into service, operate, repair or reconstruct (hereinafter "operate"), plant or displace nuclear installations or parts thereof when handling radioactive waste generated in nuclear installations.
(2) The Decree does not apply to the treatment of radioactive waste arising from other activities covered by specific regulation.1)
Basic concepts
(1) Wastes under this Decree are unused waste substances and unused articles which may contain radionuclides and which may be put into the environment under conditions laid down by the Specific Regulations (1).
(2) Radioactive wastes are unused waste substances and unused articles which cannot be placed in the environment for increased levels of radionuclides or irremovable surface contamination. The spent nuclear fuel is not considered radioactive waste for the purposes of this Decree.
(3) Treatment of radioactive waste means the sum of activities linked to the safe disposal of radioactive waste from nuclear installations from their generation to final disposal.
(4) The introduction of waste into the environment means discharge, removal or other means by which waste is disposed of and stored or dispersed into the environment.
(5) Discharge means putting gaseous and liquid waste into the environment.
(6) The processing of radioactive waste means the separation of radioactive waste from their mixture with other substances (waste, usable substances, etc.).
(7) The treatment of radioactive waste is a change in their physical or chemical properties, or their packaging, which makes it subject to further treatment (storage, transport and final storage).
(8) The storage of radioactive waste is a short-term storage of radioactive waste between different operations in the handling of radioactive waste.
(9) The final storage of radioactive waste is the storage which aims to separate radioactive waste from the environment.
(10) The system means a set of procedures and equipment used in the activity.
(11) Consideration of economic and social considerations means a procedure to determine the effectiveness of the use of means to ensure higher nuclear safety than those laid down in the relevant regulations.
ESSENTIAL REQUIREMENTS FOR NUCLEAR SAFETY INSURANCE WITH RADIOACTIVE WASTE
Requirements for nuclear installations
(1) Nuclear equipment must be designed, constructed, operated and discarded in such a way that the amount of radioactive waste generated is as low as can be achieved in the light of economic and social considerations.
(2) The design of a nuclear installation must include an analysis of the composition and quantity of radioactive waste generated during operation (2) and under emergency conditions, (3) the way in which it is collected, sorted, processed, modified, stored and transported for final disposal and the way in which waste is put into the environment.
(3) The components of a nuclear installation, including the equipment of its own radioactive waste management system, shall be decontaminated when necessary for nuclear safety and radiation protection requirements. Decontamination devices and procedures shall be selected in such a way that the effectiveness of decontamination is as high as possible, their effect on decontaminated devices as favourable as possible and the quantity and composition of subsequent radioactive waste as low as possible.
(4) The design, construction and operation of nuclear installations shall consider aspects of nuclear safety and radiation protection in the management of radioactive waste resulting from major repairs, restoration or decommissioning.
Requirements for the radioactive waste management system
(1) The radioactive waste management system must be designed and constructed in such a way that:
(a) reliably collected and stored radioactive waste from the operation of nuclear installations and radioactive waste generated under emergency conditions;
(b) it was well accessible to maintenance and repair and its decontamination was easy;
(c) as far as possible the infestation has been avoided and any deposits or deposits are easily removable;
(d) prevent releases of radioactive waste; any leaks must be collected and returned to the system or otherwise disposed of.
(2) In order to ensure the smooth operation of the radioactive waste management system, its components shall have an advance on the results of the safety analyses or shall be secured by spare parts. Accordingly, the system design shall specify the minimum reserves of technological equipment and spare parts that must be available to the operator.
(3) Where radioactive wastes contain explosive or flammable substances, the relevant processing system shall be designed, constructed and operated in such a way that the possibility of explosion or fire is excluded; If it cannot be excluded, the system shall be resistant to the potential effects of explosion or fire. The quantities having a decisive influence on the explosive or ignition of such radioactive waste shall be checked.
(4) The technological processes used in the treatment of radioactive waste must be improved, according to available scientific knowledge, in order to increase the level of nuclear safety of the radioactive waste management system, taking into account economic and social considerations.
(5) In the operation of the radioactive waste management systems, the quantities that demonstrate the correct functioning of those systems shall be measured continuously or at least periodically. The quantities limiting the placing of waste into the environment under Section 8 of this Decree must be measured continuously and the results of the measurements recorded. The methods of measuring these limited quantities are regulated by technical standards.
Collection, sorting and storage of radioactive waste
(1) Radioactive wastes or mixtures thereof with other substances must be collected at the place of origin and, where technically possible and justified, sorted and safely transported for processing, treatment, etc. The collection and storage of radioactive waste shall not involve contact with the environment, in particular penetration into groundwater and surface water.
(2) Radioactive wastes and their mixtures with other substances must be classified in such a way that further treatment is as favourable as possible, subject to nuclear safety requirements. In particular, their physical and chemical characteristics, the method of further processing and treatment shall be taken into account.
(3) The classes and method of classifying radioactive waste must be laid down by separate operating rules.
(4) Radioactive waste must not be mixed when collected or transported if the mixture produced is likely to gain undesirable properties (solidified, ignited, etc.). Radioactive wastes and wastes may only be mixed if there is no other way to remove them from nuclear installations and if the requirements laid down in Section 8 of this Decree are met.
(5) Where radioactive waste has to be stored before processing or treatment, the quantity stored shall be as small as possible. For each class of radioactive waste stored, the operator shall determine, on the basis of a technical economic analysis, the maximum allowable storage quantities which are subject to approval by the Czechoslovak Atomic Energy Commission (hereinafter referred to as the Commission).
(6) Liquid radioactive waste tanks shall be secured against overfill and their filling shall be continuously controlled. The tanks shall be placed in protective sinks which accommodate the volume of the tank with sufficient backup. The protective sinks shall be tight, provided with a signal of escape from the tanks and equipped with a device for their withdrawal. The fumes from the tanks must be removed and treated as radioactive waste.
(7) Storage and assembly tanks must be designed, constructed and operated in such a way that their contents can be exhausted and that, in each storage or assembly tank system, there is always, as an emergency backup, free capacity of capacity corresponding to the largest tank of the system.
(8) Solid radioactive wastes shall be stored in such a way that they cannot be decomposed or dispersed.
Processing of radioactive waste
(1) Radioactive waste must be treated in such a way that separable and reusable substances can be returned to the manufacturing process as far as possible and that the amount of residual waste and radioactive waste is minimised and their composition and other physical and chemical properties so as not to prevent the introduction of waste into the environment or the treatment of radioactive waste for final disposal.
(2) Radioactive wastes and their mixtures with other substances must be treated in such a way that the volume and activity or other limited quantities resulting from and to the environment of the reported waste comply with the requirements of Section 8 of this Decree.
(3) The design of the treatment of radioactive waste must consider the impact of emerging substances on nuclear safety and the reliability of technological equipment of both radioactive waste treatment and technologically related systems.
(4) Where ion converters, filter or similar separation agents with limited life are used for the treatment of radioactive waste, the efficiency of their function must be monitored regularly and the limit conditions to be met must be changed, replaced, and, These limit conditions must be included in the limits and conditions4) of the nuclear installation.
(5) When radioactive waste is incinerated, an optimal combustion regime must be established for each class in the operating regulations.
Discharge
(1) Gas and liquid waste may only be discharged under conditions laid down in specific regulations. 1) Discharge of radioactive waste is inadmissible.
(2) The limits and conditions4 of the nuclear installation must include annual limits on discharges, as well as investigation and intervention levels set as a multiple of the long-term normal or projected values of daily discharges. In the event of an increase in the level of investigation, the causes of the investigation must be identified and evaluated; corrective actions appropriate to the level of the level of the level shall be taken when the level of the level of the level of intervention is exceeded.
Treatment of radioactive waste
(1) Radioactive wastes must be adapted to meet the limits and conditions for final disposal. The selection of methods for the treatment of radioactive waste and its justification shall be subject to safety analyses.
(2) If liquid radioactive waste is solidified by mixing with solids such as cement, solid bitumen or glass material, the appropriate treatment system shall be designed and constructed to allow for inspection, maintenance and repair and easy cleaning. The separate operating rules shall specify the treatment modes including, inter alia, the mixing or specific consumption ratio of the solids and the hardening conditions and shall specify the method and time limits for cleaning the equipment. In the case of stiffeners, acceptance conditions guaranteeing their required quality must be determined and checked. If the mixture is filled in packaging, the system must be secured against overfilling.
(3) When part of the treatment of radioactive waste packaging, technically standardised packaging must be used. The packaging must be chosen to withstand reliably stress during storage, removal, transport and storage on the storage site and to ensure that they are handled safely. In doing so, account must be taken of both the possible action of radioactive waste caused by the presence of corrosive substances, their expansion, the development of gases, the release of heat, etc., on the inside and the external effects.
Storage of treated radioactive waste
(1) If treated radioactive waste cannot be immediately transported to the storage site, it must be safely stored in the nuclear facility in which it was treated.
(2) Modified radioactive waste shall be stored in such a way that there are no changes in the properties which could prevent its final storage. They shall be stored taking into account the organisation of transport and final storage and radiation protection requirements.
(3) Where treated radioactive waste is stored in barrels, the highest possible number of barrels stored on each other and the way in which the stored unit is loaded and tied.
(4) Storage facilities shall comply with technical standards; their condition and equipment must be checked regularly.
Transport of radioactive waste
(1) All transport of radioactive waste in a nuclear installation and all activities associated with it must be designed and carried out in such a way as to avoid the leakage of radioactive waste from the management system.
(2) Liquid radioactive waste can only be transported in containers at a nuclear facility if its transport by pipeline is technically or economically intolerable.
(3) The method, organisation and means of transport of radioactive waste in a nuclear installation must be governed by separate operational rules.
(4) Transport of radioactive waste outside nuclear installations is governed by specific regulations. 5) It must be organised in such a way that the risks associated with it are as low as can be done in economic and social terms.
Final storage of radioactive waste
(1) Radioactive wastes which meet the limits and conditions of final storage shall be stored by the responsible organisation in the repository. The nuclear safety requirements for the final disposal of radioactive waste which cannot comply with the limits and conditions of final disposal shall be determined by the Commission on a case-by-case basis after consultation with the competent authorities.
(2) The repository is considered to be a nuclear installation. It shall be located, designed, constructed and operated in such a way that stored radioactive waste is securely separated from the environment until its activity falls to the required level. The possible releases of radioactive substances from the storage site to the environment must be as low as can be achieved in the light of economic and social considerations.
(3) Storage facilities shall be large enough to reliably contain radioactive waste from the operation of designated nuclear installations. When placing and designing a storage site, the possibility of the final storage of radioactive waste resulting in exceptional circumstances or after the closure of these nuclear installations shall be remembered.
(4) Storage compartments must guarantee tightness against two-way water leak corresponding to the geological subsoil. The filled storage spaces of the storage site shall be dry.
(5) The ground storage shall be protected against flooding and flooding by precipitation water even under abnormal precipitation. If this protection is an external drainage system, it shall be designed and constructed in such a way that it is not contained or blocked. For the possible penetration of water into storage areas, their draining and handling must be ensured in accordance with the requirements of Sections 6 to 8 of this Decree.
(6) The filled storage spaces of the repository shall be closed in accordance with the requirements of paragraphs 4 and 5.
(7) The repository and its surroundings must be monitored throughout the storage operation, that is, during the filling period. The monitoring system shall provide a sufficient overview of the potential entry of water into storage areas and the potential leakage of radionuclides from the storage site into the environment, while not reducing tightness and disrupting storage integrity. The monitoring system shall monitor the operation of the external drainage system.
(8) The storage facility shall be designed, constructed and operated in such a way that its control and monitoring are possible even after its operation.
(9) The nuclear safety of the final storage system of radioactive waste shall be demonstrated in the safety documentation containing, on the one hand, safety analyses of the possible consequences of the proposed final storage method and, on the other hand, the limits and conditions of the final storage of radioactive waste. The safety analysis shall, in a verifiable and credible manner, assess the risks arising from the operation of the repository and the risks considered during the post-service period.
Limits and conditions for the final storage of radioactive waste
(1) Only radioactive waste which, in view of the system of final disposal, will cause the population and the environment to receive radiation doses as low as can be achieved in the future, taking account of economic and social considerations.
(2) The limits and conditions for the final storage of radioactive waste must define the characteristics of the stored radioactive waste, in particular the content of radionuclides, structural stability, leveraging, thermal and radiation effects, the possibility of gas formation, microbial degradation and critical state, the content of corrosive, explosive and self-ignition substances, flammable substances, free liquids and complex agents, corrosion resistance and surface contamination of packaging and batch consumption. These limits and conditions shall be based on safety analyses of possible impacts of the system of final storage of radioactive waste on the environment.
(3) The limits and conditions for the final storage of radioactive waste contained in the pre-operational safety report must include an inventory of the conditioning quantities or criteria, methods and time limits or frequency of their measurement and evaluation, limits of the conditioning quantities and their justification or justification for why the characteristic characteristic of stored radioactive waste is not limited. The methods of measurement and evaluation of conditioning quantities shall be governed by technical standards.
(4) The limits and conditions for the definitive imposition are approved by the Commission.4)
Organisational requirements
Treatment of radioactive waste, including monitoring, organisation, training of personnel, inspection and maintenance of equipment, record keeping, etc. must be organised in such a way as to clearly define the responsibility of each worker.
Registration and evaluation of radioactive waste generation
(1) The nuclear installation operator must register and regularly, but at least once a year, evaluate the quantities and specific activities of radioactive waste in their generation, sorting, processing, treatment, storage, transport and final storage, including costs associated with it.
(2) Prior to the transfer of radioactive waste from a nuclear installation to a storage site, the nuclear installation operator shall demonstrate to the storage operator compliance with the limits and conditions of the final storage of the radioactive waste being taken into custody.
(3) Evidence of compliance with the limits and conditions for the final disposal of radioactive waste must be kept in the records of nuclear plant operators. In the same way, the storage operator shall treat the records of the final storage of radioactive waste in the storage site.
Security documentation
(1) The safety documentation of the radioactive waste management system submitted to the Commission shall include, in addition to the elements required by the specific Regulation (6) and other Commission provisions: 7)
(a) in the case of a request for consent forming a binding basis for the building office to decide in the territorial proceedings on the location of the building, a proof of compliance with the requirements of Article 12 (2) of this Decree;
(b) in the case of a request for consent forming a binding basis for the construction office to decide in the building permit procedure:
1. proof of compliance with the requirements for the design of the system;
2. Proof that the values characterising the level of nuclear safety and referred to in Sections 4 (1) and 12 (2) of this Decree are as they can be achieved in the light of economic and social considerations;
3. the security analyses required under Articles 9 (1) and 12 (9) of this Decree,
4. a preliminary proposal for the limits and conditions for the final disposal of radioactive waste;
(c) in the case of a request for approval forming a binding basis for the construction office to decide on the provisional use of the building for testing operations and on the issue of an agreement forming a binding basis for the building office to decide in the approval procedure on the approval decision:
1. proof of compliance with system construction requirements;
2. proof that the values referred to in Articles 11 (4) and 13 (1) are as they can be achieved in the light of economic and social considerations;
3. the final text of the limits and conditions for the final storage of radioactive waste;
4. the addition or modification of the limits and conditions of a nuclear installation pursuant to Articles 7 (4) and 8 (2) of this Decree;
5. complete operating regulations,
6. evidence of equipment ready to operate the system;
7. evidence of the preparedness of workers;
8. test operation programme,
9. evidence of successful completion of the test operation;
10. The documentation referred to in Nos 1 to 8, provided that it has been modified on the basis of the results of the test operation.
The documents referred to in Nos 1 to 8 shall be submitted to the application for approval of the building office making up a binding base to decide on the provisional use of the building for testing operations. Documents No 9 and 10 shall be submitted to the request for consent forming a binding basis for the building office to decide in the approval decision.
(2) The card required under paragraph 1 (b) 2 and paragraph 1 (c) 2 must be based on an analysis of the costs needed to increase the level of nuclear safety and the benefits resulting therefrom.
TRANSITIONAL PROVISIONS
Transitional provisions
Nuclear installations, or parts thereof, placed, designed, constructed, operated or put into service before the entry into force of this Decree, if they do not comply with the requirements laid down therein, shall be brought gradually, not later than 1.9.1993, into line with it, unless the Commission decides on a later date.
Efficacy
This Decree takes effect on 1 September 1987.
Chairman:
Ing. Havel CSc.
1) § 13 of Decree of the Ministry of Health of the Czech Socialist Republic No. 59 / 1972 Coll., on the protection of health from ionizing radiation. Section 13 of Decree of the Ministry of Health of the Slovak Socialist Republic No. 65 / 1972 Coll., on the Protection of Health from Ionizing Radiation.
2) Paragraph 2 (6), (7) and (8) of Decree No. 2 / 1978 of the Czechoslovak Atomic Energy Commission on Nuclear Safety in the Design, Authorisation and Implementation of Construction with Nuclear Energy Equipment, registered in the amount of 28 / 1978 Coll.
3) Paragraph 2 (9) of the Decree cited in footnote 2).
4) Article 7 (1) (a) and (d) and (2) of Act No. 28 / 1984 Coll., on State control over nuclear safety of nuclear installations.
5) Regulation on the International Carriage of Dangerous Goods by Rail (RID), Annex I to the Uniform Legislation on the International Carriage of Goods by Rail (CIM), which forms Appendix B to the Convention on International Carriage by Rail (COTIF) (Decree of the Minister of Foreign Affairs No 8 / 1985 Coll.). European Agreement on the International Carriage of Dangerous Goods by Road (ADR) (Decree No. 64 / 1987 Coll.).
6) § 7, 20 and 39 of Decree of the Federal Ministry for Technical and Investment Development No. 85 / 1976 Coll., on a more detailed modification of the zoning and construction office.
7) § 9 to 13 of the Decree of the Czechoslovak Atomic Energy Commission No. 5 / 1979 on ensuring the quality of selected nuclear energy installations, registered in the amount of 29 / 1979 Coll.
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Regulation Information
| Citation | Decree of the Czechoslovak Atomic Energy Commission No. 67 / 1987 Coll., on Nuclear Safety in the Treatment of Radioactive Waste |
|---|---|
| Regulation Type | - |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 24.07.1987 |
|---|---|
| Effective from | 01.09.1987 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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