DRAFT IMPLEMENTING DECREE. of 2016

Transcription

1 IND CZ- EN PROJET II. DRAFT IMPLEMENTING DECREE of 2016 on the requirements for the safe management of radioactive waste and on the decommissioning of nuclear installations or category III or IV workplaces In accordance with 236 of Act No.../2016, the Atomic Act, in order to implement 24(7), 55(2) and 75(5)(b) and (c), 111(3)(a) to (c), and 112(2) of the Act, the State Office for Nuclear Safety lays down the following: PART ONE GENERAL PROVISIONS 1 Subject matter This Implementing Decree follows from the relevant regulation of the European Atomic Energy Community (hereinafter referred to as Euratom ) 1) and governs a) the technical requirements for equipment for workplaces managing radioactive waste; b) the procedure for the gathering, segregation, processing, treatment, storage and disposal of radioactive waste; c) the method of carrying out the closure of a radioactive waste repository; d) the requirements for the content of documentation for authorisation for the management of radioactive waste and the individual stages of the decommissioning of nuclear installations or category III or category IV workplaces 2), e) the scope and method for record-keeping on radioactive waste and the document accompanying radioactive waste; f) the scope and method for the decommissioning and completion of the decommissioning of nuclear installations; g) the scope and method for the decommissioning of category III or category IV workplaces; and h) the scope and method for the completion of the decommissioning of category III or category IV workplaces. 1) Council Directive 2011/70/Euratom of 19 July 2011, establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste. 2) 24 and 25 of Implementing Decree No.../2016 on radiation protection. 1

2 PART TWO MANAGEMENT OF RADIOACTIVE WASTE BEFORE DISPOSAL 2 Technical requirements for equipment for workplaces managing radioactive waste before disposal (1) The equipment for workplaces managing radioactive waste before disposal shall, throughout the planned period of operation under normal conditions and in the event of a radiological emergency, according to the properties of the radioactive waste, a) ensure criticality safety, already in the project design, if there is a risk of criticality; b) restrict workers and the general public s exposure to radiation; c) ensure removal of residual heat; d) prevent radioactive release; and e) ensure that the radioactive waste can be handled. (2) In addition, the equipment for workplaces managing radioactive waste before disposal shall a) be easily accessible for maintenance and repair and easy to decontaminate; b) allow for the inspection of radioactive waste; c) ensure minimisation of the production of subsequent radioactive waste and manageability of the waste; d) allow for the easy removal of any deposits or sediments; e) allow for the identification, collection and return of any releases of radioactive waste or radioactive waste that cannot be handled safely; f) allow for the monitoring or measurement of variables and properties of radioactive waste demonstrating the proper function of the equipment as specified in the project design; and g) be resistant to the possible effects of explosion or fire; substances that have an effect on explosivity or ignition shall be monitored. (3) A programme for maintenance, tests and checks shall be developed for the operation of workplaces managing radioactive waste before disposal, in particular for a) equipment preventing the release of radioactive waste, including tanks and packages for waste; b) equipment for the management of radioactive waste, including pumps and fittings; c) heating or cooling systems; d) calibration equipment; e) ventilation systems; f) normal and backup electrical systems; g) water, gas or compressed air supply systems; h) shielding; and i) the fire protection system. (4) The results of maintenance, tests and checks shall be assessed, recorded and retained. The programme for maintenance, tests and checks shall be updated at regular intervals. (5) Where mobile equipment is used for managing radioactive waste before disposal, 2

3 a) the links between the workplace managing radioactive waste before disposal and the mobile equipment shall be taken into consideration; b) the possibility of installation, removal and decontamination of mobile equipment shall be taken into consideration; and c) before the mobile equipment is used, its safety shall be assessed taking into account the properties of the resulting form of the radioactive waste and further management of the radioactive waste produced. 3 Procedure when gathering and segregating radioactive waste (1) Radioactive waste or mixtures thereof with other substances shall be gathered and segregated according to their physical and chemical properties and the presumed method of processing and treatment. (2) A package containing radioactive waste shall be labelled so as to make it apparent what waste is being gathered and how it is segregated. (3) The method of segregation of radioactive waste shall be documented, and records shall be made of segregated waste. (4) Radioactive waste is divided into gaseous, liquid and solid waste. Solid radioactive waste is further divided, in particular according to the method of disposal, into a) short-lived activity waste, whose activity is smaller than the clearance level after no more than five years of storage; b) very low activity waste, whose activity is higher than that of short-lived radioactive waste, but does not require special disposal measures; c) low activity waste, whose activity is higher than the clearance levels, but which, at the same time, contains a limited amount of long-lived radionuclides; if it meets the acceptance criteria after it has been processed and treated, it may be disposed of, in particular, in a near-surface radioactive waste repository, in which it is isolated from the surrounding environment for a period of several hundred years; d) intermediate activity waste, which contains a significant amount of long-lived radionuclides and, hence, requires a higher degree of isolation from the surrounding environment than low activity waste; if this waste meets the acceptance criteria after it has been processed and treated, it may be disposed of, in particular, in an underground radioactive waste repository at depths of several dozen metres below the surface; and e) high-level activity waste, which requires that heat release from conversion of the radionuclides contained in it be taken into account in storage and disposal; if, after it has been processed and treated, this waste meets the acceptance criteria for a deep repository placed at depths of several hundred metres below the surface, it may be disposed of in such a repository. 4 Procedure when processing radioactive waste (1) When processing radioactive waste, usable substances shall be separated from radioactive waste to the greatest extent possible and returned for reuse so that the quantity of the remaining waste and radioactive waste is as small as possible. 3

4 (2) Before radioactive waste is processed, it is necessary to consider the effects of the substances being processed and produced on the reliability of the equipment in which the processing takes place and the effects of technologically related systems so that nuclear safety and radiation protection conditions and the conditions for ensuring radiological emergency management and radiation situation monitoring are not adversely affected. (3) Where ion exchangers or filtration or other similar separating substances with limited life are used to process radioactive waste, their efficiency shall be regularly monitored and thresholds shall be set above which these substances shall be restored or replaced. 5 Procedure when treating radioactive waste (1) Treatment of radioactive waste by modifying its physical or chemical properties or using a package shall be performed so as to ensure its safe transport, storage and disposal according to the relevant acceptance criteria. Treatment of radioactive waste shall usually involve solidification and placement into packages. (2) Before treating radioactive waste, the technological procedure shall be specified for each method of treatment used. This procedure shall comprise the conditions for the efficient and safe treatment of radioactive waste, for example the mixing ratio or specific consumption of hardeners and solidification conditions, limitation or exclusion of certain types of waste, or permissible proportions of the individual components of waste for the given method of treatment. The acceptance conditions for hardeners and the method of control of compliance with these conditions shall also be specified to ensure adherence to the required quality standards. (3) If treated radioactive waste is placed in packages, it shall be ensured that the packages are not overfilled. (4) Where treatment of radioactive waste includes packaging, the package shall be chosen so that the waste can be handled to ensure that it is not damaged during handling and transport and that it can be managed safely. At the same time, the possible effects of radioactive waste caused by, in particular, the presence of corrosive substances, expansion of the waste, gas emissions, heat release and external influences shall be taken into account. 6 Procedure when storing radioactive waste (1) Radioactive waste shall not be stored together with other waste or materials. (2) Radioactive waste shall be stored in a manner ensuring that a) in the case of treated radioactive waste, there is no risk of changes in its properties that could prevent the disposal thereof; and b) the maximum storage quantities and maximum activity levels of radioactive waste, as determined on the basis of the safety report, are adhered to. (3) The equipment in radioactive waste storage facilities shall correspond to the type, form, activity and quantity of radioactive waste stored. The condition and equipment of the storage facility shall be checked regularly. (4) When storing radioactive waste 4

5 a) reserve storage capacity shall be created that is sufficient for moving, repacking, checking, maintenance and retrieval of radioactive waste throughout the period of operation of the storage facility; b) detailed records of the waste stored shall be maintained, and it shall be ensured that each package with radioactive waste or radioactive waste stored in pieces is clearly labelled for easy identification throughout the period of planned storage; c) appropriate capacity and condition of the storage facility and internal storage conditions shall be regularly monitored and evaluated, in particular the relevant barriers shall be checked for leaks, and the dose rate at the specified distances from the surface of packages shall be monitored for the purposes of demonstrating compliance with the limits and conditions under 9(4); d) the conditions under which radioactive waste is stored and the state of packages with radioactive waste or radioactive waste stored in pieces shall be taken into account in safety-relevant procedures and regulations for operational controls; e) procedures shall be developed for the management of radioactive waste that does not meet the acceptance criteria for storage, cannot be retrieved from the storage facility in the standard manner or shows signs of damage; and f) solidified radioactive waste ready for disposal and meeting the acceptance criteria for storage in an operating radioactive waste repository shall be handed over to the Authority without delay, no later than within two years from the beginning of storage. (5) When storing liquid radioactive waste a) the tanks shall be waterproof, protected against corrosion and secured against overfilling, and their fill level shall be monitored; the tanks shall be placed in protective vaults that can hold the volume of the tank with sufficient spare capacity; the vaults shall be waterproof, fitted with an alert system in the event of leakage of radioactive waste from the tanks and equipped with a means for extraction of the waste; vapours from the tanks and vaults shall be collected and processed as radioactive waste; b) it shall be possible to homogenise and pump out the contents of storage and collection tanks; c) each system of storage or collection tanks, except collection tanks intended for collection of liquid waste that may be contaminated with radionuclides, shall have, as an emergency spare, an empty tank with a volume corresponding to that of the largest tank in the system; and d) in the case of storage in containers, the floors and walls of the storage facility shall be impermeable to such a height as to prevent the release into the environment of the liquid radioactive waste stored even in the event of leakage of the maximum quantity of the waste; the floor shall be sloped to a drainless impermeable vault. (6) Facilities for storage of radioactive waste forming part of another nuclear installation or workplace where activities involving radiation are performed shall be subject to the requirements under 6(1) to (5), while applying a graded approach. 5

6 PART THREE DISPOSAL OF RADIOACTIVE WASTE 7 Technical requirements for equipment for workplaces managing radioactive waste when disposing of it The safety of a radioactive waste repository shall not be adversely affected by activities in the areas of safety and non-proliferation of nuclear weapons and by the requirements for ensuring that the radioactive waste can be handled or other requirements, if specified, in particular where the stages of construction, operation, decommissioning and closing down of a radioactive waste repository are taking place in parallel. When acquiring information for the siting of a radioactive waste repository and when building the repository, the original properties of the geological environment shall be retained to the maximum possible extent. 8 Procedure when disposing of radioactive waste (1) Radioactive waste shall not be disposed of together with other waste or materials that do not form part of the repository. (2) Only solid or solidified radioactive waste that meets the disposal acceptance criteria may be disposed of. (3) When disposing of radioactive waste, a) detailed records of the waste disposed of shall be maintained, and it shall be ensured that each package with radioactive waste or radioactive waste disposed of in pieces is clearly labelled for easy identification; and b) in accordance with the management system, before the disposal of radioactive waste, a procedure shall be developed for verification that the properties of radioactive waste correspond to the acceptance criteria for disposal or, if the waste does not comply with the disposal acceptance criteria, for management of radioactive waste; radioactive waste that does not comply with disposal acceptance criteria may only be accepted for disposal after separate assessment of the safety of the management thereof; c) the radioactive waste repository shall be inspected throughout its life cycle in order to 1. confirm and obtain further details of the anticipated developments in the repository and the geological environment in which it is sited; 2. identify and further specify the models and data needed for safety analyses; and 3. make it possible to propose, on the basis of the data obtained, a programme of controls after the repository is closed down, including the timetable for the gradual conclusion of post-closure institutional control of the repository. (4) Equipment that will not be used after the repository is closed shall be decommissioned before the closure of the repository. 6

7 PART FOUR REQUIREMENTS FOR RADIOACTIVE WASTE MANAGEMENT DOCUMENTATION 9 Requirements for the content of documentation of workplaces managing radioactive waste (1) The safety report or the safety analysis forming part of the documentation under point 2 of part 1(a), point 4 of part 1(b), point 4 of part 1(e) and point 4 of part 1(f) and under point 5 of part 3(a) and point 1 of part 3(b) of Annex 1 to the Atomic Act shall take into account both the period of operation and, in the case of a radioactive waste repository, the period after closure of the repository. The safety assessment of a repository after closure shall be based on an analysis of scenarios determined on the basis of the properties, events and processes that may affect the safety of the repository. (2) The safety report relating to a workplace managing radioactive waste and the radioactive waste being managed shall a) propose and justify the scope of the safety report, the time interval of the assessment and the set of input parameters; b) use only computing programs that have demonstrably undergone the processes of verification and validation; and c) provide sensitivity analyses and analyses of uncertainties conducted for the radioactive waste repository if there is a risk that criticality could arise, the assessment of criticality safety shall take into account the uncertainties from the safety analyses. (3) The limits and conditions for the management of radioactive waste before disposal shall contain, depending on the characteristics of the radioactive waste, a) the acceptance criteria containing 1. the safety, technical and administrative conditions and limits for the characteristic properties of the radioactive waste being accepted for management; and 2. the method for ensuring compliance of the properties of the radioactive waste or package with radioactive waste with these conditions and limits. b) the placement and method of handling of radioactive waste or package; c) the scope, methods and time limits for measurement and assessment of values subject to limits; d) the requirements for the operational capability of selected equipment for the management of radioactive waste; e) the requirements for the set-up of the protection system for the workplace managing radioactive waste; f) limits of critical values; g) the requirements regarding the activities of workers and organisational measures leading to compliance with all of the conditions specified for the designed operational states; and h) a proposal of measures for the management of radioactive waste that does not comply with the acceptance criteria specified under the limits and conditions. (4) The acceptance criteria referred to in paragraph 3 shall also contain 7

8 a) the dimensions, weight, design and labelling of radioactive waste or its packaging; b) the content and maximum permissible quantities of radionuclides in waste, packaging and the whole installation for radioactive waste management; c) a description of the method for the prevention of criticality; d) a description of the method for restricting the heat and radiation effects of radioactive waste on the repository; and e) the dose rates at specified distances from the surface of the radioactive waste or package. (5) The limits and condition for the management of radioactive waste within the scope of disposal of radioactive waste shall contain, depending on the characteristics of the radioactive waste, a) the acceptance criteria containing: 1. the safety, technical and administrative conditions and limits for the characteristic properties of the radioactive waste being accepted for management and 2. the method of ensuring compliance of the properties of the radioactive waste or packages with radioactive waste with these conditions and limits. b) the placement and method of handling of radioactive waste or packaging; c) the scope, methods and time limits for measurement and assessment of values subject to limits; d) the requirements for the operational capability of selected equipment for the disposal of radioactive waste; e) the requirements for the set-up of the protection systems for workplaces disposing of radioactive waste; f) limits of critical values; g) the requirements regarding the activities of workers and organisational measures leading to compliance with all of the conditions specified for the designed operational states and compliance with the requirements for nuclear safety, radiation protection and radiation situation monitoring after the closure of the radioactive waste repository; and h) a proposal of measures for the management of radioactive waste that does not comply with the acceptance criteria specified under the limits and conditions. (6) In addition, the acceptance criteria referred to in paragraph 5 shall contain a) the dimensions, weight, design and labelling of radioactive waste or packaging; b) the content and maximum permissible quantities of radionuclides in waste, packaging and the whole repository; c) a description of the physical and chemical stability of radioactive waste or packaging over the period considered in the safety report and its compatibility with the design of the repository; d) data on the leachability of radioactive waste; e) a description of the heat and radiation effects of radioactive waste; f) information about the possibility of the generation of gases; g) information about the possibility of the microbial decomposition of radioactive waste; h) information about the risk of criticality; i) information about the content of corrosive, explosive, pyrophoric and flammable substances in radioactive waste; j) information about the content of free liquids in packages; 8

9 k) information about the content of complexing agents; l) information about corrosion resistance and surface contamination of packages; m) the dose rates at specified distances from the surface of packages; and n) a description of, and justification for, the acceptance criteria, unless a characteristic property of the radioactive waste being disposed of is subject to a limit. (7) an assessment of compliance with the limits and conditions for the safe management of radioactive waste shall be regularly, no less than once a year, forwarded to the Office. (8) The safety reports referred to in part 1(a), (b), (e), (f) and (h) and part 3(b) of Annex 1 to the Atomic Act shall include a characterisation of the locality, which involves verification of the state of the geological environment and the repository area and contains a) the results of a baseline survey of the locality; b) a description of the normal development of the repository; and c) identification of the properties, events and processes that may disrupt the normal development of the repository and may have an impact on its safety. 10 Requirements for the scope and method of record-keeping on radioactive waste and the document accompanying radioactive waste (1) The following records on the management of radioactive waste shall be maintained and retained: a) the documents accompanying radioactive waste produced or collected under paragraphs 6 and 7; b) details of the method for the management of radioactive waste and, in the case of stored or disposed-of radioactive waste, also the details of the place and time when the radioactive waste was placed in the storage facility or repository; c) the results of analyses of radioactive waste and its packaging; d) operational details of the equipment at the workplace managing radioactive waste, including the details of the proportion of time the equipment is used or shut down, maintenance of the equipment carried out and operating failures and accidents and the method for the rectification thereof; and e) the full name of the workers responsible for the operation of the equipment for managing radioactive waste. (2) When radioactive waste is collected, records on radioactive waste within the scope referred to in paragraph 1(a) shall also be handed over. (3) The Authority shall operate an electronic database on radioactive waste, from collection of radioactive waste for storage to the disposal thereof, and shall update and retain records on radioactive waste. Other holders of licences for the management of radioactive waste or producers of radioactive waste shall maintain records on radioactive waste within the scope referred to in paragraph 2 for a period of no less than 10 years from the delivery or disposal of this radioactive waste. (4) In the context of the management system referred to in 29 of the Atomic Act, a programme for the characterisation of radioactive waste shall be developed and a procedure for the collection or delivery of radioactive waste, including the requirements for the radioactive waste accompanying document, shall be introduced. 9

10 The collection of radioactive waste shall include a procedure for verification of compliance of the waste with the acceptance criteria according to the established procedure. (5) The document accompanying radioactive waste shall be carried with the radioactive waste during each physical delivery. The document accompanying radioactive waste shall be issued by the person delivering the waste and signed by persons authorised by both the delivering and the collecting party. The accompanying document shall be issued for each package with radioactive waste that forms a separately handled unit. (6) The document accompanying radioactive waste shall contain a) identification of the physical and chemical form and properties of the radioactive waste or the code of the radioactive waste; b) for solid waste, the waste category referred to in 3(4); c) a description of the type of the package and outer labelling making it possible to identify the package (identification number); d) the number of pieces and activity of the radionuclide sources being disposed of and their registration or identification numbers; e) the mass or volume activity concentration or activity of the individual radionuclides whose content is subject to limits under the acceptance criteria, including the method of documentation thereof; f) the mass or volume activity concentration or activity of those radionuclides that account for more than 1 % of the total activity, including the method of documentation thereof; g) the leachability coefficient of radioactive waste treated for disposal, compressive strength, content of hazardous substances and other parameters if subject to limits under the acceptance criteria; h) the dose rate on the surface of the package; i) information about surface contamination of the package by radionuclides; j) the weight of the radioactive waste; k) the weight of the package with radioactive waste; l) the date or period when the package was filled; m) the date of issue of the accompanying document; n) the business name and identification number, if assigned, of the person delivering the radioactive waste and the name, surname, capacity and signature of the person s authorised representative; and o) the business name and identification number of the person collecting the radioactive waste and the name, surname, capacity and signature of the person s authorised representative. (7) The following shall be attached to the accompanying document for treated radioactive waste a) the original or copy of the accompanying document of radioactive waste or radionuclide emitter or certificate of the sealed radionuclide emitter contained in the radioactive waste package; b) other details providing information about the properties and method for handling radioactive waste; and c) a written declaration of the producer of treated radioactive waste stating that the radioactive waste was treated in accordance with the approved limits and conditions for treating said waste and that it complies with the acceptance criteria 10

11 of the relevant repository or storage facility, in particular that it does not contain free liquids, pyrophoric substances, toxic substances, hazardous biological substances or explosive substances. (8) The information in the accompanying document shall correspond to the data in the operational logbooks of the producer or administrator of the storage facility or repository. The accompanying document shall be made out in three copies, and the original and the copies shall be stored in different fire zones. 2) PART FIVE DECOMMISSIONING OF NUCLEAR INSTALLATIONS AND CATEGORY III OR CATEGORY IV WORKPLACES 11 Scope and method of decommissioning of nuclear installations and category III or category IV workplaces (1) In addition to the gradual decommissioning of nuclear installations and category III or category IV workplaces, another method for the decommissioning of nuclear installations is immediate decommissioning performed continuously, in an uninterrupted sequence, from the moment of commencement to the moment of the completion thereof. (2) Where nuclear installations or category III or category IV workplaces are decommissioned gradually, the holder of the licence for decommissioning shall also introduce a programme for inspections and maintenance of systems, structures and components for the relevant period so that there are no adverse impacts on other stages of decommissioning. (3) The individual states of decommissioning shall be completed by securing the protective barriers of yet-to-be-decommissioned systems, structures and components of nuclear installations or category III or category IV workplaces against the release of radionuclides into the environment. (4) When carrying out decontamination works before the commencement and in the course of decommissioning, the records on radiation situation monitoring in the workplace shall be analysed, the radiation situation in the workplace shall be surveyed, the inventory of radioactive or otherwise hazardous substances shall be measured and the location of their occurrence shall be established. The results of the analyses, survey and measurements shall be processed and documented, for example in a 3D model of the nuclear installation or category III or IV workplace. (5) The following radiation protection requirements shall be satisfied when decommissioning a category III workplace: a) the technical and organisational measures enabling the implementation of decommissioning shall be specified; b) the timetable for the different methods of decommissioning shall be established; c) the requirements for the final state of the workplace after the completion of all decommissioning activities shall be specified; 2) Implementing Decree No 23/2008 concerning the technical requirements for fire protection of constructions, as amended by Implementing Decree No 268/

12 d) the quantity of the material to be handled in the course of decommissioning shall be established; e) the methods for reducing contamination due to seepage and leaks shall be specified; f) the requirements for the technical and organisational measures for carrying out the decontamination of systems, structures and components shall be laid down; g) restriction of the use of hazardous substances to the lowest reasonably achievable level shall be ensured; h) easy access to contaminated sites shall be ensured; i) the links to other workplaces with sources of ionising radiation located within the same area shall be taken into account; and j) measures for the retention of documentation and collection of operational data from the workplace for the needs of decommissioning shall be laid down. 12 Scope and method of completion of decommissioning of nuclear installations and category III or category IV workplaces (1) If the area in which the nuclear installation or category III or category IV workplace is located and the systems, structures or components of these installations cannot be released for unrestricted use, the holder of the licence for decommissioning shall evaluate their long-term safety and, subsequently, take appropriate measure to ensure their long-term safety. The financing requirements for these activities for the period specified in the documentation according to parts 1(g) and 2(g) of Annex 1 to the Atomic Act shall form part of the decommissioning costs. (2) If operation is discontinued in the context of a radiological emergency, the original decommissioning plan shall be reviewed and the method for raising funds for decommissioning shall be reassessed with a view to this fact. 13 Requirements for the content of documentation for licensed activities related to the decommissioning of nuclear installations and category III or category IV workplaces (1) The draft concept for the safe discontinuation of the operation of a nuclear installation or category IV workplace shall comply with the radioactive waste and spent nuclear fuel management concept and shall contain a) variant methods for decommissioning that shall always include the variant of immediate decommissioning and justification for the proposed method of decommissioning; b) the time frame for decommissioning; c) a description of the final state of the localities and systems, structures and components after the completion of decommissioning; d) the method for limiting the quantity of components and volume of building materials to be disposed of in the course of decommissioning; e) the method of reducing the risk of radioactive release due to seepage and leaks, namely by 1. limiting the number of piping channels built into the floors and walls; 2. limiting the use of underground tanks, vaults and drainage channels for radioactive materials; 12

13 3. separating the technological systems using radioactive and non-radioactive materials; 4. giving preference to direct pipeline routes to reduce the formation of deposits; and 5. as far as possible, by not using right-angle pipe elbows and T-pieces where direct pipeline routes cannot be used. f) in the case of a nuclear installation with a nuclear reactor, the choice of suitable material for the composition of structural parts of the reactor and the primary circuit that are directly exposed to the neutron flux or in contact with the reactor coolant and that are a source of induced activity and the application of suitable chemical regimes leading to stabilisation of the corrosive layers of cooling circuit materials to reduce the induced activity; g) in the case of a nuclear installation without a nuclear reactor, the choice of suitable material for the composition of structural parts that are directly exposed to the neutron flux and are a source of induced activity; h) prevention of contamination of concrete with radioactive material in the case of leakage and prevention of the degradation mechanisms at the metal-concrete interface; i) the method for reducing the use of hazardous substances; j) the implementation of surface finishes that will allow for easy decontamination and prevent seepage of contaminants; k) a description of how contaminated equipment can easily be accessed and dismantled; l) a description of how decontamination by means of remote operations will be made possible; and m) the system for the retention of documentation and collection of operating data for the needs of decommissioning using digital 3D technology that makes it possible, already in the design phase, to propose and keep records of systems and components with a view to decommissioning. (2) The concept for the safe decommissioning of an installation or workplace to be licensed shall a) contain identification and classification into safety classes of systems, structures and components that will also be used in decommissioning and take account of the requirements for new, but as far as possible proven, systems, structures and components intended solely for decommissioning operations; b) take account of the existence and links to other nuclear installations or workplaces located in its vicinity; c) a description of the physical state of the nuclear installation or category IV workplace after the individual stages of decommissioning, including the expected stability of buildings, technological systems, structures and components, and their excepted contamination with radioactive materials; d) the decommissioning timetable and presumed method of post-closure utilisation of the nuclear installation or workplace, in accordance with territorial planning documentation; e) a description of the systems, structures and components that are expected to be used for decommissioning, including decontamination, dismantling and demolition, as well as the possibilities for remote-controlled technical operations; f) a description of new systems, structures and components necessary for decommissioning and radioactive waste management; 13

14 g) a description of organisational preparation and staffing for decommissioning; h) the method for the management of spent nuclear fuel and radioactive waste, their location, composition and quantity, and a description of the transport, processing, treatment, storage and disposal thereof, including the minimisation of radioactive waste from decommissioning operations; i) the method for the reuse and recycling of materials, systems and components being disposed of; j) safety analyses of decommissioning; k) a preliminary estimate of decommissioning costs and the availability of funding; l) the scope and method for the measurement and evaluation of the exposure of workers and persons and contamination of the workplace and its surrounding area with radionuclides and ionising radiation; and m) the method for final radiation monitoring at the site of the nuclear installation or workplace after the completion of decommissioning. (3) The plan for the decommissioning of a nuclear installation and category III or IV workplace shall comply with the concept for the safe discontinuation of the operation of the installation or workplace to be licensed and shall contain a) the initial and final state of the installation or workplace; b) the operational history of the nuclear installation or workplace; c) a description of the available or envisaged technologies capable of ensuring the safe implementation of decommissioning operations; d) safety analyses for decommissioning; e) a description of the nuclear installation or workplace, including its technological and structural parts; f) the expected date of the commencement of decommissioning, justification for the method and scope for decommissioning and the decommissioning timetable; g) the expected radionuclide composition of the substances occurring in the nuclear installation or workplace before the discontinuation of operations, assessment of their physico-chemical form, activity, toxicity, volume and weight; h) a proposal for the organisational preparation and staffing in the decommissioning period; i) a proposal to ensure physical protection in the decommissioning period; j) a proposal for a monitoring programme in the decommissioning period; k) the plan for adapting the emergency planning zone, if specified, and the radiological emergency response preparedness plan; l) a description of the safe management of radioactive waste and spent nuclear fuel, including the financing thereof, if radioactive waste or spent nuclear fuel will be produced in connection with the operations; m) a description of land use and the use of systems, structures and components, or, if complete decommissioning is not possible, a programme for maintenance, tests and checks of the systems, structures and components, taking into account the changes in the course of decommissioning; n) the source documents for the estimate of decommissioning costs; and o) a proposal to ensure radiation protection in the decommissioning period. The decommissioning plan, together with the estimate of decommissioning costs, shall be updated no less than every five years. (4) The safety report, which forms part of the documentation for authorisation of each stage of the decommissioning of a nuclear installation or category III or IV 14

15 workplace under parts 1(g) and 2(d) of Annex 1 to the Atomic Act and which follows from the decommissioning plan, shall contain a) a description of the changes in the nuclear installation or category III or IV workplace in the course of the decommissioning thereof, including a list of structures, components or systems that have yet to be decommissioned and updates of the classification thereof into safety classes, as well as changes in the planned method of decommissioning and their justification in the safety report; b) a description and justification of the need for the installation and operation of new structures, systems and components and their impact on radiation protection, radiation situation monitoring and radiological emergency management; and c) an assessment of the safety impact of decommissioning operations taking place in parallel. PART SIX FINAL PROVISIONS 14 This Implementing Decree was notified in accordance with Directive (EU) 2015/1535 of the European Parliament and of the Council of 9 September 2015 laying down a procedure for the provision of information in the field of technical regulations and of rules on Information Society services. 15 Entry into force This Implementing Decree shall enter into force on 1 January Chairperson: 15