Decree No. 106 / 1998 Coll.
Ordinance of the State Office for Nuclear Safety on Nuclear Safety and Radiation Protection of Nuclear Equipment in their Activation and Operation
Valid
Effective from 05.05.1998
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106
DECLARATION
State Office for Nuclear Security
of 20 April 1998
on the protection of nuclear safety and radiation protection of nuclear installations when putting them into service and when they are operating
According to § 47 (7), the State Nuclear Safety Authority provides for the implementation of § 9 (1) (c), § 13 (3) (d), § 14 (3) (d), § 17 (1) (d) and § 18 (1) (a), point (c) of Act No. 18 / 1997 Coll., on the peaceful use of nuclear energy and ionising radiation (Atomic Act), and amending and supplementing certain laws (hereinafter "the Act '):
INTRODUCTORY PROVISIONS
Subject matter
This decree sets out the stages of the putting into service of nuclear equipment, the technical and organisational conditions to ensure the nuclear safety of nuclear installations when they are put into service and when they are operational, the re-introduction of the fissile chain reactor (hereinafter referred to as the "nuclear reactor ') into critical condition after the replacement of nuclear fuel, the scope and manner of carrying out approved documentation for the granting of authorisation for the individual phases of putting into service and operation of the nuclear installation and the procedure for the submission and assessment of documentation for the authorisation for the re-introduction of the nuclear reactor after the replacement of nuclear fuel.
(1) For the purpose of this decree, the critical state of the nuclear reactor is the state where a fissile chain reaction takes place in the nuclear reactor active zone, in which the neutron balance is balanced in the nuclear reactor active zone and the effective neutron multiplication factor is equal to one.
(2) For the purposes of this Decree, the handling of nuclear materials and radioactive waste means the transfer of nuclear materials.
(3) The putting into service of nuclear equipment is a process during which it is verified that all nuclear equipment and systems are implemented and capable of operating in accordance with the project and that they meet the requirements for nuclear safety in accordance with the specific regulation and the preliminary and pre-operational safety report.
(4) The different phases of putting into service of nuclear equipment are:
(a) a stage of inactive testing of nuclear equipment, which includes a comprehensive functional verification of the nuclear installation and its revision carried out prior to the introduction of nuclear fuel into the nuclear reactor active zone of the nuclear reactor for the construction of which the nuclear reactor is part or carried out prior to the introduction of nuclear materials or radioactive waste into a nuclear installation of the type referred to in § 2 (h) (2) (3) (4) of the Act;
(b) an active testing stage which includes tests carried out since the start of the nuclear fuel weighing into the nuclear reactor's active zone for the construction of which the nuclear reactor is part or carried out since the start of the weighing of nuclear materials or radioactive waste into a nuclear installation of the type referred to in § 2 (h) (2) (3) (4) of the Act until the end of the nuclear installation's test operation; for nuclear installations involving a nuclear reactor, the phase of active testing shall be further divided into:
1. the physical launch of a nuclear installation, the purpose of which is to verify the physical characteristics, in particular the neutron-physical characteristics of the nuclear reactor active zone, and the selected nuclear reactor protection functions, in particular those which depend on the neutron-physical characteristics of the active zone; the introduction of the first fuel file into the reactor core shall be considered as the start of the physical start;
2. the launch of a nuclear installation designed to verify at different power levels the design characteristics of the installation and the project cooperation of all systems and in transition processes;
3. the test operation of a nuclear installation aimed at verifying project parameters and operational stability in accordance with an approved test operation programme.
GENERAL REQUIREMENTS FOR THE INSTALLATION OF NUCLEAR INSTALLATIONS IN OPERATIONS AND ITS OPERATIONS
General requirements for nuclear safety
(1) Nuclear equipment shall be put into service or operated according to programmes of entry into service or operating regulations and in accordance with the limits and conditions of safe operation [§ 2 (t) of the Act] approved by the State Office for Nuclear Safety (hereinafter referred to as the Office) and only in the arrangements envisaged by the project and the safety reports. In the event of a deviation from the prescribed course of action, in the event of situations of nuclear safety hazard during or during the testing of the placing in service of equipment, the necessary handling and measures shall be taken to ensure that the nuclear equipment is immediately placed in a safe, stable and controlled state. In the event of such a situation, the placing in service or operation may be continued only after clarification and removal of the causes which led to such a situation.
(2) A part of a nuclear installation which is put into service or operated must be separated from the parts where the construction or inactive testing continues, in such a way that assembly work or any failure or accident on the built-up part does not affect the nuclear safety of the equipment put into service or already operated.
(3) The holder of a permit for the placing in service or for operation of a nuclear installation (hereinafter referred to as the "authorisation holder ') shall, throughout and during the period of the putting into service of a nuclear installation, have an overview of the current status of the installation and have control of the nuclear installation.
(4) The implementation of nuclear safety-critical activities is only possible according to written orders and operational documentation and programmes. They shall be processed and issued in accordance with the requirements laid down in a separate Regulation (1) and shall be verified and documented in advance that they do not breach or threaten nuclear safety.
(5) The general requirements for radiation protection are laid down in a separate Regulation.2)
Documentation of putting into service of nuclear equipment and documentation of operation
(1) Since the start of the launch of a nuclear installation and throughout its operation, the following elements, in particular relevant to nuclear safety and radiation protection, shall be recorded:
(a) compliance with the limits and conditions for putting into service and operation of nuclear installations;
(b) results and records of tests, inspections, tests, maintenance and repair of equipment and systems carried out;
(c) the values of physical quantities and parameters that are relevant at any time in terms of sufficient information on the status of the nuclear reactor active zone and other downstream systems relevant to nuclear safety or nuclear materials or radioactive waste found in the nuclear installation;
(d) the failures and events encountered, the consequences thereof, the analyses of those disturbances and the measures taken;
(e) qualifications, medical examinations, training and the results of its verification of nuclear safety-critical personnel;
(f) radioactive discharges, levels of radiation in nuclear facilities and batch loads of persons;
(g) existing and emerging defects of the equipment and its dissemination, transition conditions and step changes of parameters in order to ensure, in accordance with the specific Regulation (1), the possibility of determining the ageing of selected equipment and its residual life;
(h) the operability of the selected devices, the handling on the selected devices and the orders transmitted concerning those devices.
(2) During and during the operation of the equipment, the quantities which are relevant for nuclear safety and radiation protection shall be recorded continuously in such a way as to capture a sufficiently large period of time for their changes before, during and after transition processes.
(3) The facts relevant for nuclear safety and radiation protection, documentation, records and reports referred to in this Decree are to be kept for at least 10 years after the end of the operation of the nuclear installation.
Staff
(1) Employees carrying out nuclear safety-critical activities in the putting into and operation of nuclear equipment must be shown to be familiar with the content of the documentation referred to in Article 3 (4) which applies to the activities they carry out and subsequently trained before the activities are carried out.
(2) After the change affecting nuclear safety or radiation protection has been implemented, the design, operational and other documentation concerned shall be brought into line with the actual situation involving the change already in question. The personnel of a nuclear installation in whose activities the change must be taken into account shall be shown to be familiar with all the modifications relating to the change and subsequently trained before the change begins to be used when the nuclear installation is put into service or in operation.
(3) The authorisation holder must establish and document an organisational structure for the planning, management and operation of nuclear equipment. Within this framework, the responsibilities and responsibilities of nuclear personnel under all operational regimes and, in particular, for dealing with emergency situations, the flow of information between them and the relationship between authority and subordination are determined in a clear and written manner. The holder of the authorisation shall indicate which activities are provided by himself and which by means of suppliers.
Handling of nuclear materials and radioactive waste at the nuclear facility
(1) Basic requirement for handling
(a) fissile nuclear materials shall exclude the possibility of developing fissile chain reactions and their releases to the environment;
(b) with radioactive waste is the exclusion of the possibility of their release into the environment.
(2) In the handling of spent nuclear fuel, measures shall be taken to limit the risk of a breach of the hermetics of fuel elements to the lowest acceptable level and to ensure sufficient removal of residual heat to avoid damage to fuel by its influence.
(3) Nuclear safety and radiation protection in the handling of fissile nuclear materials and radioactive waste shall be ensured in particular by:
(a) the use of the project of the equipment under consideration and of the test;
(b) by performing manipulations in accordance with the operational documentation;
(c) by continuous control of the handling of these nuclear materials and radioactive waste and of the state of the nuclear installation and, in the case of handling of nuclear fuel in the nuclear reactor of nuclear equipment, by continuous control of the active zone, the density of heat neutrons, the concentration of boric acid and the level and temperature of the coolant.
(4) The handling of fissile nuclear materials and radioactive waste at the nuclear facility and the activities related thereto shall be carried out in accordance with documentation which shall always include:
(a) the procedure for each operation;
(b) equipment and system preparedness requirements;
(c) information on the state of storage of nuclear materials or radioactive waste, in the case of nuclear materials, identifying data and cartograms of their storage, and in the case of handling nuclear fuel in a nuclear reactor or pool storage, as well as data on the concentration of boric acid in the coolant of the primary circuit and pool storage;
(d) data on organisational measures to ensure nuclear safety and radiation protection and data on the necessary additional measures not covered by operational rules.
(5) Each individual technology operation associated with the transfer of nuclear materials shall be recorded in a separate document indicating its starting and final location and the security measures taken, unless they are included in the operational documentation.
(1) When transporting and storing fresh nuclear fuel in storage tanks, the distribution of fuel sets shall be ensured in such a way as to ensure that at least 0,05 is undercritical in the expected emergency situations, including water flooding.
(2) In the transport and storage of spent nuclear fuel, at least 0,05 shall be ensured for expected emergency situations.
(3) In the exchange of nuclear fuel in the nuclear reactor, the concentration of a soluble neutron absorber in the coolant is of such a value that, taking into account all possible errors, sufficient undercriticism is ensured.
TECHNICAL AND ORGANISATION CONDITIONS FOR SAFE INSTALLATION OF NUCLEAR INSTALLATIONS IN OPERATIONS
Principles for putting into service of nuclear equipment
(1) The putting into service of nuclear equipment shall be such that each stage constitutes a comprehensive set of tests according to the Office of approved programmes of putting into service, the termination of which and the subsequent documentation of compliance with all the criteria of success set out for them is one of the conditions for continuing to service in the next stage. The following stage shall not commence before the completion and fulfilment of the pre-stage conditions.
(2) Prior to the start of the phase of active testing of nuclear equipment, the initial status of the installation shall be documented on the basis of its control.
(3) During active tests, disconnection of individual elements of the nuclear reactor protection and management system shall be prohibited, including for the purpose of replacement or repair, unless the remaining part of the protection and control system elements ensure that the requirements laid down in the specific regulation and the limits and conditions of safe operation are met reliably.
(4) During the period of physical start-up, blocking of emergency protection signals from technological systems not used in physical start-up operations is permitted.
Documentation for authorising individual phases of putting into service of nuclear equipment
Programme for putting into service
(1) Each phase of putting into service of a nuclear installation shall be carried out according to a pre-established phase programme. The phase programme shall be processed to ensure that:
(a) the phase programme covers all relevant activities concerning selected installations to be carried out at that stage;
(b) all equipment shall be gradually tested by tests and verified by selected, project considered, modes and characteristics;
(c) the handling of equipment and the carrying out of tests shall be carried out by qualified personnel;
(d) individual installations shall be gradually tested in such a way as to create conditions for testing other units and to successfully complete functional verification of the entire nuclear installation before the test operation begins.
(2) The programme shall contain:
(a) the objective, description and methodology of carrying out the work of the stage;
(b) interconnections between the various activities of the stage;
(c) technology and energy preparedness requirements;
(d) the criteria for success and the methodology for assessing their compliance;
(e) a description of the initial and final state of the stage;
(f) organisational and personnel security of the stage;
(g) the way of moving to the next stage,
(h) a list of sub-programmes, which shall include in particular:
1. the objective, description and methodology of carrying out the individual activity;
2. technology and energy preparedness requirements;
3. the criteria for success and the methodology for assessing their compliance;
4. the initial and final situation for the activity;
5. organisational and staffing activities.
Limits and conditions for safe operation of nuclear installations
(1) The limits and conditions for the safe operation of nuclear installations [Paragraph 2 (t) of the Act] are divided into the following parts:
(a) safety limits;
(b) setting of protective systems;
(c) the operating limit conditions;
(d) control requirements;
(e) organisational measures;
(f) justification for the limits and conditions of safe operation.
(2) Safety limits are limit values for those physical and technological parameters which directly affect the state of the physical barriers preventing the release of radioactive substances from a nuclear installation into the environment and which must not be exceeded. In the case of a nuclear installation with a nuclear reactor, the nuclear reactor shall be immediately shut down if any of the safety limits are exceeded. Rebuilding the nuclear reactor into a critical state is only possible after clarification and removal of the causes that have led to the safety limits being exceeded and the necessary analyses being carried out to determine the state of the nuclear installation after it has been exceeded.
(3) The setting of protection systems indicates the values of physical and technological parameters relevant to nuclear safety, which automatically activate individual protection and safety systems. These values are determined in such a way that the controlled parameters do not exceed safety limits even in the subsequent transition process.
(4) The operating limits set out the conditions for the safe operation of nuclear installations in the modes considered and analysed in the safety reports of the nuclear installation concerned and include in particular:
(a) ranges in which physical and technological parameters must be maintained so as to ensure that during operation no undesirable achievement of the parameters of the installation of protective systems is achieved and in which the safety of the nuclear installation is demonstrated;
(b) the operational requirements of nuclear safety-critical equipment to fulfil the required functions under defined conditions;
(c) the values of other safety-relevant parameters to which the safety of the nuclear installation is demonstrated.
(5) The control requirements shall determine the scope and frequency of regular checks on compliance with the admissible parameters and, in particular, the safety limits, the operational conditions of the equipment and the setting of protection systems.
(6) The organisational measures provide in particular for:
(a) for cases where the permissible parameters have been reached or exceeded, or the requirements for the operability of the equipment have not been met, or any of the conditions for setting or incorporating the protection systems, the necessary activities and measures to be taken, and the time for such activities and measures to be carried out,
(b) the responsibility of the managers within the organisation of the authorisation holder, the qualifications of the selected staff, the requirements for minimum staffing, internal and external control of compliance with the limits and conditions and the obligation to transmit information in relation to the supervisory authorities.
(7) The limits and conditions of safe operation are adjusted according to the level of science and technology achieved and with practical experience.
Start of physical launch
(1) Before the start of the physical launch, the holder of the authorisation shall check how the nuclear device for the physical launch is prepared ("preparedness check '). The permit holder shall carry out a physical start-up check on the readiness of a nuclear installation to verify:
(a) whether all the work and tests of the previous stage are completed;
(b) whether all the criteria for success of the previous stage are met in accordance with approved programmes;
(c) the readiness of the equipment referred to in the specific regulation, (1) including the dosimetric control system and the irradiated fuel storage system, and the readiness to initiate the physical start-up in accordance with the stage programmes;
(d) preparedness of staff to initiate physical start-up in accordance with stage programmes;
(e) the existence and accuracy of the documentation referred to in paragraph 3.
(2) After the checks referred to in paragraph 1 have been carried out, the authorisation holder shall draw up a summary document of the results of the check, which shall be part of the fuel-weighing equipment and personnel readiness certificate.
(3) Before starting a physical launch, the authorisation holder shall verify the existence and correctness of the following documentation:
(a) the physical launch phase programme and the sub-programmes of individual tests, including the fuel weighing programme, the content of which is in accordance with Section 9;
(b) safe operation limits and conditions;
(c) the operational rules necessary for the physical start-up, including a regulation to ensure nuclear safety and radiation protection in the handling of nuclear fuel, nuclear materials and radioactive waste;
(d) an internal emergency plan;
(e) evidence of completion of the prescribed qualification and evidence of training and entrustment of staff to activities relating to the performance of their duties, including an overview of the occupation of shifts;
(f) documents and protocols on the testing and preparedness of all nuclear safety systems and equipment involved in the physical launch;
(g) proof of compliance with the conditions of prior authorisations issued by the Office;
(h) the quality assurance programme for the stage;
(i) a summary proof of the results of the preparedness check of the nuclear installation and its personnel for physical launch.
Start of the energy launch
(1) A ready-to-use check shall be carried out and documented before the start of the energy start. The permit holder shall carry out a test of the readiness of a nuclear device to launch in such a way as to verify:
(a) whether all physical start-up work and tests are completed;
(b) whether all the criteria for the success of the physical start-up are met in accordance with approved programmes;
(c) the preparedness of the equipment referred to in the specific Regulation (1) to initiate the energy launch in accordance with the stage programmes;
(d) the readiness of the staff to initiate the energy launch in accordance with the stage programmes;
(e) the existence and accuracy of the documentation referred to in paragraph 3.
(2) After the checks referred to in paragraph 1 have been carried out, the authorisation holder shall draw up a summary document of the results of the check, which shall form part of the certificate of preparedness for the installation and personnel to initiate the energy launch.
(3) Before starting the energy start, the authorisation holder shall verify the existence and correctness of the following documentation:
(a) an energy launch phase programme and sub-programmes of energy launch, the content of which is in accordance with Article 9 of this Decree;
(b) safe operation limits and conditions;
(c) a complete set of operational regulations necessary to carry out an energy start-up corresponding to the actual execution of the construction;
(d) an internal emergency plan;
(e) evidence of completion of the prescribed qualification and evidence of training and entrustment of staff to activities relating to the performance of their duties, including an overview of the occupation of shifts;
(f) documents and protocols on the testing and preparedness of all systems and equipment having an impact on nuclear safety and contributing to energy launch;
(g) proof of compliance with the conditions of prior authorisations issued by the Office;
(h) the quality assurance programme for the stage;
(i) protocols on the implementation of the physical start-up stage and compliance with the success criteria;
(j) a summary of the results of the nuclear equipment preparedness check and its personnel for the launch of energy.
Start of test operation
(1) A ready-to-use check shall be carried out and documented before starting the test operation. The test run shall be carried out by the holder of the authorisation in order to verify the readiness of the nuclear device to operate:
(a) whether all works and tests of the energy launch are completed;
(b) whether all the energy start-up success criteria are met in accordance with approved programmes;
(c) the readiness of the equipment referred to in the special Regulation (1) and of the personnel to commence the test operation according to the specified programme;
(d) the existence and accuracy of the documentation referred to in paragraph 3.
(2) After the check has been carried out, the holder of the authorisation shall draw up a summary of the results of the check, which shall be part of the equipment and personnel ready-to-use check.
(3) In order to start the test operation, the authorisation holder will check the existence and accuracy of the following documentation:
(a) the timetable and programme of test operations;
(b) safe operation limits and conditions;
(c) a complete set of operating regulations corresponding to the actual execution of the construction;
(d) an internal emergency plan;
(e) evidence of completion of the prescribed qualification and evidence of training and entrustment of staff to activities relating to the performance of their duties, including an overview of the occupation of shifts;
(f) documents and protocols on the testing and preparedness of all selected installations, in particular systems having an impact on the nuclear safety referred to in the specific regulation, 1)
(g) proof of compliance with the conditions of prior authorisations issued by the Office;
(h) the operational control programme and the relevant quality assurance programmes referred to in the specific regulation, 1)
(i) an inventory of the changes made to the approved project during the previous stages of nuclear safety and radiation protection launch;
(j) protocols on the implementation of the energy start-up phase and compliance with the success criteria;
(k) proof of compliance with the conditions of previous authorisations issued by the Office;
(l) a summary proof of the results of the check on the readiness of the nuclear installation and its personnel for testing operations.
TECHNICAL AND ORGANISATION CONDITIONS OF THE SAFE OPERATIONS OF NUCLEAR EQUIPMENT
Principles for the operation of nuclear installations
(1) The operation of the nuclear installation shall be carried out according to the operating schedule, which shall include its planned shutdown. The schedule of operations shall be sent to the Office on a regular basis once a year and any changes to the timetable shall be transmitted no later than 10 days after the modification or amendment made.
(2) The operation of the nuclear installation shall be carried out in accordance with operational regulations and in accordance with the limits and conditions of safe operation. The operating rules, limits and conditions of safe operation and their changes shall be processed by the authorisation holder. Operating regulations are processed for normal operating modes and emergency situations. The authorisation holder shall re-evaluate and adjust the operational rules according to the level of science and technology achieved and with the application of experience and practice from operations.
(3) The check of the shut-down fuel reactor in the reactor active zone, including the time period for weighing and replacing the fuel files, is carried out continuously, in particular in terms of the sub-criticism of the core and the heat removal from the nuclear reactor active zone.
(4) When operating a nuclear installation involving a nuclear reactor, the authorisation holder shall ensure that:
(a) the effectiveness of the performance elements of the nuclear reactor management and protection system, compensation elements, emergency protection and the efficiency of the liquid absorber has always been known;
(b) the actual efficiency of the management and protection of the nuclear reactor system has ensured that the nuclear reactor is shut down and maintained in a subcritical condition with sufficient reserve;
(c) the maximum supply of active zone reactivity has always been known and compensated by the powerful elements of the protection and management system;
(d) the temperature reserve for the crisis has always been assured boiling within the approved limits and conditions of safe operation;
(e) the rate of positive reactivity was such that the performance corresponding to the level of control was achieved with a period greater than that specified in the limits and conditions so as to avoid criticism on immediate neutrons;
(f) in the operation of the power reactor, there has been no disconnection of more than one emergency protection channel (power or power change rate) or disconnection of individual performance mechanisms of the protection and management system, including for the purpose of checking, exchanging or correcting, provided that the remaining number of performance elements of the protection and management system does not ensure compliance with the requirements laid down in the specific regulation.
(5) Furthermore, the authorisation holder ensures:
(a) regular reassessment and adaptation of operational regulations and equipment, taking into account the level of science and technology achieved and the use of previous experience;
(b) at least one complete and updated set of operating rules is available at the management centre;
(c) the immediate transmission of information to the Office on the emergence of nuclear safety-related situations, including the shutdown of reactors by emergency protection in the case of nuclear installations with a nuclear reactor;
(d) a regular evaluation of the operation and analysis of the failures created and the transmission of reports on these analyses to the Office at least once a month, together with proposals for the necessary measures and information on the state of implementation of those measures.
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Regulation Information
| Citation | Decree of the State Office for Nuclear Safety No. 106 / 1998 Coll., on the safeguarding of nuclear safety and radiation protection of nuclear installations when they are put into service and when they are operated |
|---|---|
| Regulation Type | - |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 05.05.1998 |
|---|---|
| Effective from | 05.05.1998 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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