Decree No. 377 / 2016 Coll.
Decree on requirements for safe management of radioactive waste and decommissioning of nuclear installations or plants of Category III or IV
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Effective from 01.01.2017
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377
DECLARATION
of 7 November 2016
on requirements for safe management of radioactive waste and decommissioning of nuclear installations or plants of Category III or IV
The State Authority on Nuclear Safety sets out, pursuant to § 236 of Act No. 263 / 2016 Coll., Atomic Act, for the implementation of § 24 (7), § 55 (2), § 75 (5) (b) and (c), § 111 (3) (a) to (c) and § 112 (2):
GENERAL PROVISIONS
Subject matter
This decree regulates
(a) technical requirements for facilities for the workplace where radioactive waste is handled;
(b) the procedure for the collection, sorting, processing, treatment, storage and storage of radioactive waste;
(c) the method of carrying out the closure of the radioactive waste storage site;
(d) requirements for the content of the documentation for the authorisation of radioactive waste management and individual decommissioning stages of a nuclear installation or a Category III or Category IV workplace;
(e) the extent and manner of keeping records of radioactive waste and of the accompanying list of radioactive waste;
(f) the extent and manner of decommissioning and decommissioning of a nuclear installation;
(g) the scope and method of decommissioning of Category III or Category IV workplaces; and
(h) the scope and manner of cessation of Category III or Category IV work.
INDICATION TO RADIOACTIVE WATER BEFORE ITS LEVEL
Technical requirements for workplace facilities where radioactive waste is handled before storage
(1) The holder of the authorisation for the management of radioactive waste must, throughout the period of its operation in normal operation and in a radiological emergency according to the properties of radioactive waste, at the installation for the workplace where radioactive waste is handled prior to storage.
(a) to ensure undercriticism, already in the project, where there is a risk of a critical situation;
(b) to ensure that the characteristics of equipment are such as to reduce exposure to radiation workers and residents;
(c) to ensure the removal of residual heat;
(d) prevent the release of radioactive substances; and
(e) ensure handling of radioactive waste.
(2) The holder of the authorisation for the management of radioactive waste must ensure that the installation for the workplace is handled with radioactive waste before storage, in order to:
(a) be accessible to maintenance and repair and easily decontaminated;
(b) allow the control of radioactive waste;
(c) ensure that the generation of subsequent radioactive waste is minimised and can be handled;
(d) facilitate the easy disposal of loading or sediments;
(e) allow for the identification, collection and return of releases of radioactive waste or radioactive waste which cannot be safely handled;
(f) allow the monitoring or measurement of quantities and properties of radioactive waste that demonstrate the correct functioning of the installation as determined by the project;
(g) be resistant to the possible effects of explosion or fire; substances having an effect on explosion or ignition shall be monitored; and
(h) use passive functions which do not require activation, mechanical propulsion or the supply of media or energy from another system to meet the requirements of paragraph 1, where reasonably practicable.
(3) For the operation of the workplace where radioactive waste is handled before storage, a programme for the maintenance, testing and inspection must be established for:
(a) equipment to prevent the leakage of radioactive waste, including tanks and packages for radioactive waste;
(b) facilities for the management of radioactive waste, including pumps and fittings;
(c) heating or cooling system;
(d) calibration equipment;
(e) ventilation system,
(f) normal and back-up electrical systems;
(g) a system for supplying water, gas or compressed air;
(h) shielding; and
(i) a fire protection system.
(4) The results of the maintenance, tests and checks referred to in paragraph 3 must be evaluated, recorded and kept for the period specified in the management system documentation. The maintenance, testing and inspection programme shall be updated at regular intervals.
(5) In case of use of mobile devices for the management of radioactive waste before storage,
(a) account is taken of interaction between the workplace where radioactive waste is handled before storage and mobile equipment;
(b) account is taken of the possibility of installing, removing and decontaminating mobile devices; and
(c) its safety has been assessed before the use of the mobile device, including taking into account the characteristics of the resulting form of radioactive waste and the further management of radioactive waste generated.
Procedure for collecting and sorting radioactive waste
(1) Radioactive waste or its mixture with other substances must be collected and sorted according to physical and chemical characteristics and to the intended processing and treatment.
(2) The packaging containing radioactive waste shall be marked in such a way as to make clear which radioactive waste is collected and how it is sorted.
(3) The method of classifying radioactive waste shall be documented and classified radioactive waste recorded.
(4) Radioactive waste is divided into gaseous, liquid or solid waste. Solid radioactive waste is further divided into:
(a) temporarily active waste containing short-term radionuclides and, after storage for a maximum period of 20 years, has an activity below the release levels;
(b) very low-active waste, the activity of which is higher than that of intermediate radioactive waste but does not require special storage measures;
(c) low-activity waste, the activity of which is higher than the release levels but which also contains a limited number of long-term radionuclides;
(d) intermediate waste containing a significant number of long-term radionuclides and therefore requires a higher degree of environmental isolation than low-active waste; and
(e) high-activity waste for which heat release from the transformation of radionuclides contained therein must be taken into account during storage and storage; after treatment and treatment, this waste shall meet the conditions of acceptability and shall be stored in a deep storage of radioactive waste located at depths of several hundred metres below the earth's surface.
Procedure for treating radioactive waste
(1) When processing radioactive waste, the usable substances shall be removed as far as possible from radioactive waste and returned for reuse so that the amount of remaining waste and radioactive waste is as low as possible.
(2) Prior to the treatment of radioactive waste, the impact of processed and emerging substances on the reliability of the equipment in which it is processed and the influence of technologically related systems shall be considered in order not to adversely affect the conditions of nuclear safety, radiation protection, monitoring of the radiation situation and management of the radiological emergency.
(3) Where ion converters or filter or similar limited-life dividers are used for the treatment of radioactive waste, the efficiency of their function shall be monitored regularly and the values to be recovered or replaced when exceeding shall be determined.
Procedure for treating radioactive waste
(1) The treatment of radioactive waste by changing its physical or chemical properties or by using a packaging file must be carried out in such a way as to ensure its safe transport, storage and storage under appropriate conditions of acceptability. The treatment of radioactive waste is usually done by firming and injecting the waste into the packaging file.
(2) Prior to treatment of radioactive waste, a technological procedure shall be established for each treatment method used. This procedure shall include conditions for efficient and safe treatment of radioactive waste, such as mixing ratio or specific consumption of solids and conditions of solidification, restriction or exclusion of certain types of waste, or permissible representation of individual components of radioactive waste for the treatment. The conditions of acceptance for stiffeners and the method of checking these conditions must also be laid down to ensure that their required quality is respected.
(3) If treated radioactive waste is filled into the packaging, it shall be ensured that it is not overloaded.
(4) Where part of the treatment of radioactive waste packaging is included, the packaging shall be selected in such a way that:
(a) the packaging can be handled;
(b) the packaging has not been damaged during handling and transport; and
(c) the handling of the packaging file was safe.
(5) The procedure referred to in paragraph 4 shall take into account, in particular, the possible action of radioactive waste caused by the presence of corrosive substances, its expansion, gas generation, heat release and external effects on the packaging.
Procedure for the storage of radioactive waste
(1) Radioactive waste must not be stored with other waste or material.
(2) Radioactive waste must be stored in such a way that:
(a) in the case of treated radioactive waste, there is no risk of any change in the characteristics which could prevent its disposal; and
(b) the highest stored quantity and maximum radioactive waste activity determined on the basis of a safety report shall be respected.
(3) The storage of radioactive waste must correspond with its equipment to the type, form, activity and quantity of radioactive waste stored. The status and equipment of the radioactive waste storage facility shall be checked regularly within the time limits set in the management system documentation.
(4) For radioactive waste storage:
(a) the provision of storage capacities sufficient to meet the needs of the transfer, re-packaging, control, maintenance and collection of radioactive waste throughout the operation of the radioactive waste warehouse;
(b) detailed records of stored radioactive waste shall be kept and ensure that each packaging of radioactive waste or stored piece radioactive waste is clearly identified for ease of identification throughout the intended storage period;
(c) regularly monitored and evaluated the adequacy of the capacity and condition of the radioactive waste warehouse, in particular the tightness of the relevant barriers, internal storage conditions and the monitoring of surface contamination and dose equivalent at defined distances from the surface of the packaging files for compliance with the limits and conditions referred to in Article 9 (3);
(d) take into account the conditions under which radioactive waste is stored and the state of the radioactive waste packaging file or the state of the stored piece radioactive waste, in the safety and operational control procedures and regulations;
(e) a procedure for the management of radioactive waste which:
1. does not satisfy the conditions of acceptability to storage;
2. it is not possible to pick up radioactive waste from the warehouse in a normal manner; or
3. shows signs of damage; and
(f) radioactive waste prepared for storage and meeting the conditions of acceptability to be stored in an operational radioactive waste storage site without delay, but no later than two years after the start of storage, shall be transmitted to the storage facility.
(5) For the storage of liquid radioactive waste,
(a) tanks
1. impermeable,
2. corrosion protected;
3. secured against overcharging;
4. monitored for filling; and
5. placed in protective sinks or other systems, structures and components which ensure the capture of potential leakage and accommodate with sufficient reserve tank volume (hereinafter referred to as the "containment system"),
(b) protective detention system
1. impermeable,
2. provided with a signal indicating the leakage of radioactive waste from the tanks; and
3. equipped with a radioactive waste recovery facility;
(c) fumes from tanks and containment systems removed and treated as radioactive waste;
(d) possible homogenisation and exhaustion of the storage and collection tanks;
(e) always for each storage or collection tank system as an emergency backup, an empty tank of volume corresponding to the largest tank of the system; and
(f) in the case of storage in containers of floor and wall of storage which are impermeable to such an extent that the maximum quantity of stored liquid radioactive waste is avoided from entering the environment; the floor shall be equipped with an immediate protective gripping system.
(6) A facility for the storage of radioactive waste which is part of another nuclear installation or another site where radiation activity is carried out shall be subject to the requirements set out in paragraphs 1 to 5 using a graduated approach.
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Technical requirements for workplace equipment where radioactive waste is handled during storage
The safety of radioactive waste storage shall not be adversely affected by the technical requirements for:
(a) the security of nuclear installations or nuclear non-proliferation;
(b) ensuring handling of radioactive waste; and
(c) parallel stages of construction, operation, decommissioning and closure of radioactive waste storage.
Procedure for the storage of radioactive waste
(1) Radioactive waste must not be stored with other waste or materials.
(2) Only solid or reinforced radioactive waste which is not temporarily active waste and which fulfils the conditions of acceptability for storage may be stored.
(3) When storing radioactive waste
(a) it must be kept in accordance with Section 10 of the register of stored radioactive waste and it must be ensured that each packaging of radioactive waste or stored piece radioactive waste is clearly identified for ease of identification;
(b) a procedure for verifying that the properties of radioactive waste comply with the conditions of acceptability for the storage of radioactive waste or for the management of radioactive waste must be established in accordance with the requirements of the management system in the event that they do not meet the conditions of acceptability for disposal; radioactive waste which does not meet the conditions of acceptability for storage may be accepted for storage only after a separate safety assessment in its handling; and
(c) the radioactive waste storage must be checked throughout the life cycle in such a way that:
1. the expected development of this repository and the geological environment in which it is located has been confirmed and specified;
2. the models and data required for the security analyses have been identified and specified; and
3. On the basis of the data obtained, it was possible to propose a programme of checks after the closure of this repository, including a timetable for the phasing out of the institutional control of the closed repository.
(4) A facility which will not be used after the closure of the radioactive waste storage site must be discarded before the closure of that storage site.
REQUIREMENTS FOR DOCUMENTATION DOCUMENTATION WITH RADIOACTIVE WASTE
Requirements for the content of documentation of workplaces where radioactive waste is handled
(1) In the safety report or in the safety analysis which is part of the documentation referred to in Part 1 (a) (2), (b) (4), (e) (4), (f) (4) and in Part 3 (a) (5) and (b) (1) of Annex 1 to the Atomic Act, the period of operation of the workplace where radioactive waste is handled shall be taken into account and, in the case of radioactive waste storage, also after the closure of the repository. The safety assessment of the radioactive waste storage site after closure shall be based on an analysis of scenarios defined on the basis of characteristics, events and processes that may affect its safety.
(2) The safety report covering the workplace where radioactive waste is handled and the radioactive waste to which it is handled must include:
(a) design and justification for the scope of the safety report, the time interval of the safety assessment and the set of input parameters;
(b) use only calculation programmes which have undergone verification and validation processes; and
(c) sensitive analyses and analyses of uncertainty for radioactive waste storage sites; where there is a risk of a critical condition, the assessment of ensuring undercriticism shall take into account the uncertainty of the safety analyses.
(3) The limits and conditions for the management of radioactive waste must be specified depending on the characteristics of radioactive waste
(a) the conditions of acceptability which include:
1. the security, technical and administrative conditions and limits on the characteristics of radioactive waste which is accepted for disposal; and
2. the method of ensuring compliance of the properties of radioactive waste or radioactive waste packaging with these conditions and limits;
(b) the location and handling of radioactive waste or packaging;
(c) the extent, manner and time limits of measurement and evaluation of limited quantities;
(d) operational capability requirements and operational parameters of selected radioactive waste facilities;
(e) the requirements for setting up the workplace protection system for radioactive waste management;
(f) the limits of conditioning quantities;
(g) requirements for the activity of personnel and organisational measures leading to the fulfilment of all defined conditions for design operational conditions;
(h) requirements to ensure nuclear safety, radiation protection and monitoring of the radiation situation following the closure of the radioactive waste storage site where radioactive waste is stored in the radioactive waste storage site; and
(i) a proposal for measures for the management of radioactive waste which does not meet the conditions for acceptance set out in the limits and conditions.
(4) The conditions of acceptance referred to in paragraph 3 (a) also include:
(a) for radioactive waste before storage
1. dimensions, mass, design and labelling of radioactive waste or packaging;
2. the content and maximum permitted quantities of radionuclides in radioactive waste, packaging and the whole radioactive waste facility;
3. a description of how to avoid the occurrence of a critical condition;
4. a description of how to reduce the heat and radiation effects of radioactive waste; and
5. dose equivalent power at defined distances from the surface of radioactive waste or packaging;
(b) for radioactive waste for storage in radioactive waste storage
1. dimensions, mass, design and labelling of radioactive waste or packaging;
2. the content and maximum permitted levels of radionuclides in radioactive waste, packaging and the entire radioactive waste storage site;
3. a description of how to avoid the occurrence of a critical condition;
4. a description of the physical and chemical stability of radioactive waste or packaging for the period considered in the safety report and its compatibility with the radioactive waste storage project;
5. data on the calorific value of radioactive waste;
6. a description of the heat and radiation effects of radioactive waste;
7. data on gas generation;
8. Data on the possibility of microbial degradation of radioactive waste,
9. Data on the content of corrosive, explosive and self-ignition substances and flammable substances in radioactive waste,
10. information on the content of free liquids in packages,
11. data on the content of complexing agents,
12. data on corrosion resistance and surface contamination of packaging sets;
13. batch equivalent power at defined distances from the packaging file surface; and
14. description and justification of the conditions of acceptability, unless the characteristic characteristic of stored radioactive waste is limited.
(5) The Authority must be regularly sent an assessment of compliance with the limits and conditions of safe management of radioactive waste, but at least once a year.
(6) The safety report for radioactive waste storage sites, which is part of the documentation referred to in Part 1 (a) (2), (b) (4), (e) (4), (f) (4) and (h) (5) and in Part 3 (b) (1) of Annex 1 to the Atomic Act, must include an evaluation of the characterisation of the site for the location of this nuclear installation. The characterisation of the territory consists in verifying the state of the geological environment and storage areas and must include:
(a) the results of a basic survey of the site for the location of a nuclear installation;
(b) a description of the normal development of the radioactive waste storage site; and
(c) identification of the properties, events and processes which may interfere with the normal development of the radioactive waste storage site and may affect its safety.
Requirements for the scope and manner of keeping records of radioactive waste and of radioactive waste accompanying sheet
(1) Operational records for the management of radioactive waste must be kept and kept for the period specified in the management system documentation. These traffic records are:
(a) accompanying sheets of radioactive waste generated or taken over in accordance with paragraphs 6 and 7;
(b) details of how radioactive waste is managed and, in addition, of the location and time of the radioactive waste stored or stored;
(c) the results of analyses of radioactive waste and its packaging;
(d) data on the operation of the installation for the workplace where radioactive waste is handled, including data on the time use of the installation, its weaning, on the maintenance carried out of the installation and on the operational failures and accidents and the manner in which they are disposed of; and
(e) the names and surnames of the personnel required to ensure the safe operation of the radioactive waste facility.
(2) In the case of the receipt of radioactive waste, the accompanying sheets referred to in paragraph 1 (a) shall be transmitted together with the radioactive waste.
(3) The management must ensure the operation of the electronic database system of radioactive waste from the receipt of radioactive waste to storage and storage and must update and maintain a record of radioactive waste. Other holders of a permit for the management of radioactive waste or of radioactive waste agents shall keep a record of radioactive waste within the scope of paragraph 2 for at least 10 years from the transmission or disposal of such radioactive waste.
(4) A programme for the characterisation of radioactive waste for the collection, sorting, treatment and treatment of radioactive waste shall be developed under the management system and a procedure for the collection or transmission of radioactive waste, including requirements for the accompanying list of radioactive waste, shall be established. The radioactive waste characterisation programme shall establish procedures for determining the values of the chemical, physical and biological parameters of radioactive waste for safe disposal. The programme shall include, for each type of radioactive waste handled at the workplace, a methodology for determining the values of all parameters specified in the radioactive waste accompanying sheet. The transmission and reception of radioactive waste shall include a procedure for verifying the compliance of the properties of radioactive waste with the conditions for acceptance by the holder of the authorisation for the management of radioactive waste in accordance with the procedure laid down.
(5) The accompanying sheet of radioactive waste shall accompany radioactive waste at each physical transmission. The accompanying certificate of radioactive waste shall be issued by the transferor and shall be signed by the delegate and the transferor. The accompanying sheet shall be displayed for each radioactive waste packaging file which forms a separate handling unit.
(6) The accompanying sheet of radioactive waste must contain:
(a) the designation of the physical and chemical form and properties of radioactive waste or the code of radioactive waste;
(b) in the case of solid waste, its category according to Article 3 (4);
(c) a description of the type of packaging and the external numerical marking enabling the packaging to be identified;
(d) the number of pieces and the activity of stored radionuclide sources and their registration or identification numbers;
(e) data on mass or volume activity and activity of individual radionuclides, the content of which is limited by the conditions of acceptability, including their method of identification;
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Regulation Information
| Citation | Decree No. 377 / 2016 Coll., on the requirements for safe management of radioactive waste and for decommissioning of nuclear installation or site III or IV. |
|---|---|
| Regulation Type | Order |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 18.11.2016 |
|---|---|
| Effective from | 01.01.2017 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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