Decree No. 196 / 1999 Coll.
Decree of the State Office for Nuclear Safety on the decommissioning of nuclear installations or sites with significant or very significant sources of ionising radiation
Valid
Order
Effective from 03.09.1999
Text versions:
03.09.1999
Contents
196
DECLARATION
State Office for Nuclear Security
of 21 August 1999
on the decommissioning of nuclear installations or sites with significant or very significant sources of ionising radiation
According to § 47 (7) for the implementation of § 4 (10), § 9 (1) (g) and § 13 (3) (d) of Act No. 18 / 1997 Coll., on the Peaceful Use of Nuclear Energy and Ionising Radiation (Atomic Act) and on the Amendment and Addition of Certain Acts ("Act '):
INTRODUCTORY PROVISIONS
Subject matter
This Decree sets out details of the manner and extent of radiation protection in decommissioning [§ 2 (n) of the Act] of nuclear installations or workplaces with significant or very significant sources of ionising radiation (hereinafter referred to as "workplaces'), sets out the method of decommissioning and sets out the scope and manner of carrying out the documentation.
For the purposes of this decree:
(a) decommissioning activities carried out during the decommissioning of workplaces, in particular decontamination, dismantling, demolition, treatment, storage, transport and disposal of waste (1) arising from post-closure disposal, implementation of protective barriers and other measures to ensure radiation protection;
(b) a contaminated object of an object, substance or plant containing radionuclides or contaminated radionuclides to such an extent that, for its use outside the workplace with sources of ionising radiation or other placing into the environment, under special legislation2), authorisation by the State Nuclear Safety Authority (hereinafter "the Authority") is required.
Elimination methods
[K § 9 (1) (g) of the Act]
(1) The methods of decommissioning nuclear installations or sites with sources of ionising radiation are:
(a) according to the link between decommissioning activities and their breakdown into time and material stages
1. one-off decommissioning operations where the decommissioning activities are carried out continuously at a single stage of substance and time immediately after the closure of operations;
2. phasing-out where the decommissioning activities are divided into several successive factually and timed phases;
(b) depending on the extent of the necessary decontamination, dismantling and demolition work, the possibility of using the premises and the necessity of checking the surroundings
1. direct decommissioning where, from the point of view of radiation protection, decontamination, dismantling and demolition are not necessary, because there are no radionuclide radionuclides [to § 2 (c) (1) of the Act] and even radionuclides contaminated by equipment and other sources of ionising radiation are disabled and secured against entry into service;
2. disposal without dismantling, if sufficient decontamination of contaminated equipment can be carried out even without dismantling;
3. dismantling of contaminated equipment before decontamination or removal of construction, where appropriate;
4. protective closure where unremoved contaminated articles and unremoved contaminated equipment are closed instead of complete decontamination by protective barriers preventing the release of radionuclides into the environment until the self-active conversion of activity either decreases to such a level that they cease to be contaminated objects or devices, or to a level determined in accordance with a specific legislation.3)
(2) The choice of the means of disposal of individual parts of a nuclear installation or workplace, both from material and time points, shall be made depending on the type and extent of contamination of the installation.
(3) The mode of decommissioning for irradiated workplaces (4) or other sources which, when switched off, do not emit ionising radiation or are not contaminated by radionuclides is a one-off direct decommissioning.
(4) The method of decommissioning for closed-circuit radionuclide radionuclide radionuclide lamps (5) is usually a one-off dismantling process where closed radionuclide radionuclide lamps are dismantled and removed and contaminated where appropriate.
(5) The method of decommissioning for radioactive waste storage [§ 2 (r) of the Act] for uranium mines and for droughts, spillages or spillage resulting from mining activities involving natural radionuclides is a protective closure, usually carried out in stages.
DETAILS TO ENSURE RADIATION PROTECTION FOR OPERATING EQUIPMENT
(K § 4 (10) of the Act)
Preparation for elimination
(1) At nuclear installations and workplaces with open radionuclide radionuclide radionulates (5), the preparation for decommissioning is ensured as an integral permanent part of the radiation protection system already in place, construction and operation. When preparing for disposal, the method of disposal and the amount of radioactive waste generated, as well as the level of exposure of workers and the population during disposal, shall be considered and optimised.
(2) Preparation for decommissioning of nuclear installations or workplaces must take into account:
(a) the expected, possibly planned period of operation of the nuclear installation or site and the expected closure date;
(b) the radiation situation on the nuclear installation or workplace after closure, the expected type and quantity of radionuclides and contamination of the installation;
(c) the physical state of the nuclear installation or site and its operational history to cease operations, including the evaluation of the integrity of the buildings, structures and systems, and for protective storage or closure, if any, for its duration;
(d) preparedness of personnel and the availability and reliability of technology for decommissioning activities, in particular decontamination and dismantling;
(e) estimates of the expected benefits received, the impact of the proposed decommissioning activities on employees, the population and the environment;
(f) expected type and quantity of radioactive and other waste from decontamination and dismantling operations and their storage, treatment, processing, transport and storage;
(g) re-use and recycling of materials and components;
(h) the expected decommissioning costs and the set-up of the disposal reserve, including the availability of funds equivalent to the amount of the reserve created;
(i) requirements for the use of the site for other purposes and the foreseeable development of the territory.
(3) The design of the decommissioning method, which is part of the Authority's approved documentation, for the authorisation of individual phases of putting into service of nuclear equipment (point C.II. 9 of the Annex to the Act) or for the authorisation of the operation of a workplace with a significant or very significant source of ionising radiation, (6) must enable the assessment of proposed decommissioning activities in terms of nuclear safety, radiation protection, physical protection and emergency preparedness.
(4) The design of the decommissioning method shall be updated at least every five years in view of updating the estimate of decommissioning costs. In addition, the proposal shall be updated for any change in the operative events on the basis of which it was drawn up, in particular when the planned closure date or other supporting documents referred to in paragraph 1 is amended.
Termination of operations
(1) The termination of the operation of a nuclear installation or site or parts thereof, as a change significantly affecting radiation protection, is subject to the Authority's authorisation [Paragraph 9 (1) (f) of the Act]. The consequences of the closure shall be taken into account in the draft changes to the documentation, in particular in the update of the design of the decommissioning method, in the definition of the controlled band, (7) the monitoring programme (8) and emergency plans. 9)
(2) Except in the case of early forced termination accidents, the operation of a nuclear installation with a nuclear reactor will be terminated only after the nuclear fuel has been exported from the reactor and the operation of a site with closed radionuclide radionuclide radionuclides has been removed.
(3) The transfer of the workplace by transfer to another legal successor (holder of the relevant permit) is not an end to the operation of the workplace.
Realization of decommissioning
(1) If the implementation of decommissioning activities is divided into several separate comprehensive material stages, each individual phase of decommissioning must be completed by sufficient securing of the remaining contaminated equipment and objects of a nuclear installation or workplace against the illicit spread of contaminating radionuclides to the surrounding areas by protective barriers. When authorising individual decommissioning phases, the financial envelope (point G.1 of the Annex to the Act) is sufficient to carry out the stage. The termination of each individual phase of decommissioning, as an event relevant to radiation protection, shall be subject to notification by the Office [Paragraph 17 (1) (j) of the Act].
(2) A part of a nuclear installation or site operated must be separated from the parts where the decommissioning takes place in such a way that the work or any incidents in the disposal areas do not affect nuclear safety, radiation protection, physical protection and emergency preparedness in the operating part.
(3) In the case of protective closure, the scope of the decommissioning activities in areas closed by the protection barriers shall be limited and shall be aimed at maintaining and controlling the protection barriers. Depending on the nature of the contamination, natural transformations of radionuclides are mainly used to reduce it. Technological systems ensuring the maintenance of the environment within the closure shall be maintained in an operational state, environmental monitoring and control of movement of persons and materials shall be ensured. In the case of protective closure of nuclear installations or workplaces, protective barriers shall also be created by decommissioning activities to prevent unwanted intrusion into closed spaces.
SCOPE AND METHOD OF IMPLEMENTATION OF THE DOCUMENTATION RELATING TO EQUIPMENT
[Paragraph 13 (3) (d) of the Law]
Scope and manner of documentation
(1) The scope and manner of carrying out the decommissioning documentation depends on the type, designation and size of the nuclear installation or site, the current nature of the decommissioning, the nature of the decommissioning phase and the specific conditions of disposal. The documentation shall also be updated on points common to each phase of decommissioning, in particular safety analyses and assessment of the radiation situation, and shall include any changes to the previous stage of decommissioning that could significantly affect nuclear safety and radiation protection.
(2) When preparing the documentation, the scope and manner of execution shall be determined accordingly to the state and operational history of the nuclear installation or site.
(3) In the event of early termination of operations in emergency situations, the method of disposal originally planned and the documentation must be reassessed.
Design of the method of decommissioning workplaces with radiation generators
(4) In addition to the places where contaminated objects have been detected, the design of the method of disposal of the irradiated workplaces contains:
(a) a description of the workplace, the estimated start date for the decommissioning activities;
(b) a description of the state of the workplace in the technological and construction parts during the closure period;
(c) specification of radiation generators occurring at the workplace at the time of closure;
(d) a description of the operation of the radiation generators.
Design of the method of elimination of workplaces with closed radionuclide lamps
The design of the method of decommissioning the workplaces with closed radionuclide radionuclide radionuclide contains depending on the scope of the decommissioning activities and their time sequence always
(a) a description of the workplace, the estimated start date for the decommissioning activities;
(b) a description of the state of the workplace in the technological and construction parts during the closure period;
(c) specification of suspected contaminated objects occurring at the workplace at the time of closure;
(d) the expected timetable for decommissioning activities and their objectives;
(e) design of organisational training and staffing,
(f) analysis of possible emergency situations and their initiation events, including analysis of radiation risks.
Design of the method of elimination of workplaces with open radionuclide lamps
(1) The design of the method of elimination of workplaces with open radionuclide radionuclide lamps contains, depending on the scope of the decommissioning activities and their time sequence, always
(a) a description of the workplace, the estimated start date for the decommissioning activities;
(b) a description of the state of the workplace in the technological and construction parts during the closure period;
(c) the expected radionuclide composition of substances occurring in the workplace at the time of closure, an assessment of their species, activity, toxicity, volume, mass, physical and chemical forms;
(d) the expected timetable for decommissioning activities and their objectives;
(e) a description of the proposed management of radioactive waste;
(f) the expected type and quantity of radionuclides released into the environment and the expected type and quantities of radioactive waste generated and the method of disposal;
(g) design of organisational training and staffing,
(h) analysis of possible emergency situations and their initiation events, including radiation risk analysis and estimation of the impact of decommissioning activities on the workplace environment;
(i) justification for the proposed method of decommissioning and technological practices.
(2) The design of the method of decommissioning an open radionuclide radionuclide in case of protective closure shall include, in addition to the parts referred to in paragraph 1:
(a) a list and a description of the technological equipment and buildings included in the protective closure, a description of the protective barriers, the extent of operation of the technological systems at the time of closure, the method of maintenance of the technological and construction components, and a description of other measures ensuring that the closure requirements are met;
(b) the expected radionuclide composition of substances present at the workplace at the time of completion of the protective closure, in particular an assessment of their type, activity, toxicity, volume, weight, physical and chemical forms;
(c) the estimated period during which protective closure will have to be maintained.
Design of the method of decommissioning the uranium ore mining and treatment sites
The proposal for the disposal of uranium ore mining and processing sites includes, depending on the scope of the decommissioning activities and their time sequence and in addition to the parts mentioned in Section 10 for open-source radionuclide radionuclides, the following other parts:
(a) planned use of the site during and after decommissioning;
(b) a description of the changes in the workplace's surroundings as a result of operation and the expected influence of the workplace's surroundings by decommissioning the workplace.
Design of the decommissioning of nuclear installations
The proposal for a method of decommissioning nuclear installations other than radioactive waste storage, depending on the scope of the proposed decommissioning activities and their time sequence, and in addition to the parts referred to in Section 10 for open-source radionuclide radionuclides, includes the following other parts:
(a) planned use of the site during and after decommissioning;
(b) a description of changes in the workplace environment as a result of operation and the expected influence of the workplace environment by decommissioning the workplace,
(c) a description of availability and verification in the practice of the proposed technological procedures;
(d) a description of the management of spent nuclear fuel and other nuclear materials during decommissioning;
(e) the way in which physical protection is ensured during decommissioning.
Proposal on how to close storage sites
The design of how to close storage contains, depending on the scope of the decommissioning activities and their time sequence, always
(a) a description of the storage site of radioactive waste, estimated date of start of decommissioning activities;
(b) a description of the status of the radioactive waste storage site during the closure period;
(c) the expected radionuclide composition of substances occurring in the radioactive waste storage site at the end of operation and at the time of closure of the storage site, an assessment of their type, activity, toxicity, volume, mass, physical and chemical forms;
(d) the expected timetable for decommissioning activities and their objectives;
(e) a proposal for a method of organisational preparation and staffing;
(f) analysis of possible incidents and estimation of the impact of decommissioning activities on the workplace area;
(g) a list and description of the technological equipment and building facilities included in the protective closure, the extent of operation of the technological systems at the time of closure, the method of maintenance of the technological and construction parts, the description of the protection barriers, in particular the technological barriers, and other measures ensuring that the requirements for closure are met;
(h) a description of the security against unauthorised intrusion into the contained storage areas;
(i) the estimated period during which protective closure will have to be maintained.
Estimate of decommissioning costs
The estimate of the decommissioning costs [point C.II.10 and point D. (b) (7) of the Annex to the Act], as part of the dossier submitted in the application for authorisation pursuant to § 9 (1) (c) and (d) of the Act, shall be drawn up as the sum of the costs for individual decommissioning activities considered for the proposed disposal method and the expected timetable [§ 9 (d), § 10 (1) (d) and § 13 (d)] of the decommissioning activities in the current cost of the year of the estimation. The schedule of decommissioning activities shall include a description of the decommissioning activities envisaged, the costs of such decommissioning activities and the expected year of implementation. The estimate of the costs of individual decommissioning activities is, where possible, processed in the form of the product of the number of units of measurement considered and the price per unit of measurement.
TRANSITIONAL AND FINAL PROVISIONS
Transitional provision
Nuclear installations or workplaces operated for a transitional period under Section 47 (3) of the Act on the authorisation, consent or other authorisation issued under Act No. 28 / 1984 Coll., on State supervision of nuclear safety of nuclear installations, or Decree of the Ministry of Health of the Czech Socialist Republic No. 59 / 1972 Coll., on the protection of health against ionising radiation, may create a decommissioning reserve under Section 18 (1) (h) of the Act as an expense for achieving, securing and maintaining income only after the Office has approved the proposal for decommissioning by them (§ 7 to 13).
Efficacy
This decree shall take effect on the day of its publication.
Chairman:
Ing. Böhm v. r.
responsible for the administration of the Office
1) Paragraph 20 (3) of Decree No. 184 / 1997 Coll., on requirements for radiation protection.
2) § 5 of Decree No. 184 / 1997 Coll.
3) Paragraph 5 (1) (a) of Decree No 184 / 1997 Coll.
4) § 2 (f) of Decree No. 184 / 1997 Coll.
5) Paragraph 6 (2) of Decree No 184 / 1997 Coll.
6) Paragraph 6 (7) and (8) of Decree No. 184 / 1997 Coll.
7) § 35 of Decree No. 184 / 1997 Coll.
8) § 46 of Decree No. 184 / 1997 Coll.
9) Paragraph 18 of Decree No. 219 / 1997 Coll., on details to ensure emergency preparedness of nuclear installations and sites with sources of ionising radiation and on requirements for the content of the internal emergency plan and emergency order.
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Regulation Information
| Citation | Decree of the State Office for Nuclear Safety No. 196 / 1999 Coll., on the decommissioning of nuclear installations or workplaces with significant or very important sources of ionising radiation |
|---|---|
| Regulation Type | Order |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 03.09.1999 |
|---|---|
| Effective from | 03.09.1999 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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