1 1. ------IND- 2016 0202 CZ - EN- ------ 20160523 --- --- 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 workplace s 
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 PROVISI ONS  
§ 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 ma naging 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 document ation for authorisation for the 
management of radioactive waste and the individual stages of the 
decommissioning of nuclear installations or category  III or category  IV 
workplaces2), 
e) the scope and method for record -keeping on radioactive waste and the docu ment 
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 meth od 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 managemen t of spent fuel and 
radioactive waste. 
2)  § 24 and 25 of Implementing Decree No  .../2016 on radiation protection. 2 PART TWO  
MANAGEMENT OF RADIOA CTIVE WASTE BEFORE D ISPOSAL  
§ 2 
Technical requirements for equipment for workplaces managing radioactive 
waste before d isposal  
(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 b e 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 preventi ng 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 electric al 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 r egular 
intervals.  
(5) Where mobile equipment is used for managing radioactive waste before 
disposal,  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 insta llation, 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 an d 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 activit y 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 r adioactive 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 o f 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 sev eral 
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 substan ces 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.  4 (2) Before radioactive waste is processed, it is necessary to consid er 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 cond itions 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 ef ficiency 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 u sing 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 radio active 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 contro l 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 radioactiv e 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 m aximum 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 c ondition and 
equipment of the storage facility shall be checked regularly.  
(4) When storing radioactive waste  5 a) reserve storage capacity shall be created that is sufficient for moving, repacking, 
checking, maintenance and retrieval of radioactive waste throughou t 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 ra te 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 ra dioactive 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 acceptanc e 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 rep ository 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 was te 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 tan k 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 shal l be 
subject to the requirements under §  6(1) to (5), while applying a graded approach.  6 PART THREE  
DISPOSAL OF RADIOACT IVE WASTE  
§ 7 
Technical requirements for equipment for workplaces managing radioactive 
waste when disposing of it  
The safety of a radioac tive 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 parti cular 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 p art 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 th at 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 verifi cation 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 disp osal 
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 th e 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 o f 
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 cl osure of the repository.  7 PART FOUR  
REQUIREMENTS FOR RAD IOACTIVE WASTE MANAG EMENT 
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 documenta tion 
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 th e 
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 critic ality 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 th e 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 no t 
comply with the acceptance criteria specified under the limits and conditions.  
(4) The acceptance criteria referred to in paragraph  3 shall also contain  8 a) the dimensions, weight, design and labelling of radioactive waste or its packaging;  
b) the content and maxim um 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 ef fects 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 
mana gement 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 dispos ing 
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 req uirements 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 criteri a 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 rad ionuclides 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;  9 k) information about the content of compl exing 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 pr operty 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 safe ty 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 conta ins 
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 accom panying 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 e quipment 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 radioact ive 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 w aste 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 s cope 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 radioactiv e 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. 10 The collection of radioactive waste shall include a procedure f or 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 
separatel y 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 activ ity 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 an d 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 shal l 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 11 of the relevant repository or storage facility, in particular that it does not contain 
free liquids, pyrophoric substances, toxic substances, hazardous biologic al 
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 N UCLEAR 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 c ontinuously, 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 decommissi oning 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 dec ontamination 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 o therwise 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 cate gory 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 tim etable 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 Dec ree 
No 268/2011. 12 d) the quantity of the material to be handled in the cou rse 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 l ocated 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 decom missioning 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 rele ased 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 spec ified 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 revie wed 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 an d 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 radioacti ve 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;  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 a re 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 prevent ion 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 o f 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 o f 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 workpla ce 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, stru ctures 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 pre sumed 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 de contamination, 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;  14 g) a description of org anisational 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 t hereof, 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 decommissi oning 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 metho d 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 av ailable 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 b efore 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 manageme nt 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 decommissionin g 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 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 descripti on 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 i nto 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 Im plementing 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 Info rmation Society services.  
§ 15 
Entry into force  
This Implementing Decree shall enter into force on 1  January  2017.  
Chairperson: