Decree No. 436 / 1990 Coll.

Decree of the Czechoslovak Atomic Energy Commission on ensuring the quality of selected equipment in terms of nuclear safety of nuclear installations

Valid Effective from 01.12.1990
436
DECLARATION
Czechoslovak Atomic Energy Commission
of 10 October 1990
on ensuring the quality of selected installations in terms of nuclear safety of nuclear installations
The Czechoslovak Commission on Atomic Energy pursuant to Section 21 of Act No. 28 / 1984 Coll., on State Control over Nuclear Safety of Nuclear Equipment, provides:

ČÁST PRVNÍ

INTRODUCTORY PROVISIONS
§ 1
Subject matter and purpose of the Order
The Decree sets out the essential requirements for ensuring the quality of equipment, machinery, parts and materials, construction parts and structures, means of automated management of technological processes, including technical and software equipment and electrical power supply systems relevant for nuclear safety (1) (hereinafter referred to as "selected equipment ') of nuclear installations (2), and determines binding procedures for implementing technical and organisational measures related to the quality of the selected equipment in order to ensure nuclear safety of nuclear installations.
§ 2
Basic concepts
(1) The quality of the device is a summary of the characteristics of the device which make it conditional on its ability to meet the specified needs in accordance with its designation.
(2) By establishing the quality of the equipment selected, for the purposes of this decree, it means establishing the requirements for its characteristics which make it conditional on the performance of the functions for which it is intended.
(3) The quality assurance of the selected equipment shall be a summary of the activities planned and systematically carried out to ensure that the selected equipment complies with the specified quality requirements.
(4) For the purposes of this decree, the quality assurance programme shall mean a dossier containing a summary of the technical and organisational measures and activities, including controls, related to the achievement and maintenance of the specified quality of the selected equipment.
(5) For the purposes of this decree, the quality assurance documentation shall mean the list of selected establishments, the individual quality assurance programmes, including their annexes and the documentation related thereto, in particular the quality documentation and the normative technical documentation.
(6) For the purposes of this Order, quality documentation shall mean documentation containing evidence of the quality of the elements and equipment, of the performance of the activities affecting the quality, the characteristics of the materials, welds or elements and equipment and of the results of the activities carried out to evaluate the condition and the quality of the selected equipment.
(7) The operation of a nuclear installation for the purposes of this Decree covers activities from the entry into service of a nuclear installation to its final decommissioning, including the operation of shut-down operations, maintenance, fuel exchanges, inspections, tests, inspections and the like.
(8) For the purposes of this decree, operational checks shall mean all checks on selected installations carried out during the period of operation of the nuclear installation.
(9) Security functions for the purposes of this Decree are those functions which are necessary to prevent or mitigate the consequences of an accident on a nuclear installation.
(10) For the purposes of this decree, normal operation shall mean all the states and operations of the planned operation of the nuclear installation, respecting the operating limits and conditions for its safe operation. These are mainly the launching, steady operation and shutdown of the nuclear reactor, increasing and reducing its performance, its partial and full load, maintenance, repairs and fuel exchange.
(11) Abnormal operation means, for the purposes of this decree, unplanned stocks, operations and events but the occurrence of which can be expected to occur when a nuclear installation is operated. They are mainly emergency shutdown, sudden drop in load, turbine failure, power loss from the mains. However, such operational conditions shall not lead to damage to the fuel cells or to a breach of the integrity of the pressure circuit of the nuclear reactor coolant and, after they have been completed or their causes and consequences removed, the nuclear device shall be capable of normal operation.
(12) For the purposes of this decree, emergency conditions shall mean all events caused by failure or breach of construction structures, technological files and equipment, external influences or operator errors which adversely affect the safety of the operation of the nuclear installation and lead to a breach of operating limits and conditions and may cause a breach of fuel cells.
(13) For the purposes of this Decree, safety systems are those which are essential to nuclear safety, which are designed to ensure the safe shutdown of the nuclear reactor under any conditions, to remove heat from the core zone or to reduce the consequences of abnormal operation and emergency conditions.

ČÁST DRUHÁ

SELECTED EQUIPMENT
§ 3
Principles for the breakdown of selected installations
Selected installations shall be subdivided into three safety classes according to their importance for the safe operation of the nuclear installations, the safety functions of the system of which they are part and the severity of the consequences of any failure.
§ 4
Safety classes of selected devices
(1) The provisions of paragraphs 2, 3 and 4 apply to equipment for the storage, processing, storage and transport of nuclear materials which are consumed in a fissile chain reaction or arising from the operation of a nuclear reactor, as well as to investment and operation units which include a nuclear reactor which operates on the principle of fissile chain reaction by heat neutrons and is moderated and cooled by light water. In the case of other nuclear installations, the security classes shall be determined by the Czechoslovak Atomic Energy Commission (hereinafter referred to as the Commission) according to the nature of those installations and the purpose for which they are intended.
(2) Selected devices classified in Security Class 1 are devices forming the limit of the pressure circuit of the nuclear reactor coolant, except those devices whose damage can be compensated by a normal coolant replenishment system.
(3) The selected equipment in Security Class 2 is nuclear fuel and equipment:
(a) forming the limit of the pressure circuit of the nuclear reactor coolant which does not belong to safety class 1;
(b) for the decommissioning of a nuclear reactor under abnormal operation in states likely to lead to emergency conditions and for the decommissioning of a nuclear reactor in order to mitigate the consequences of emergency conditions;
(c) to maintain sufficient coolant for cooling the core of the nuclear reactor during emergency conditions in which the pressure circuit of the nuclear reactor has not been breached and even after these conditions;
(d) for heat removal from the core of the nuclear reactor (3) in breach of the reactor coolant pressure circuit in order to reduce fuel damage;
(e) for the removal of residual tepla3) in normal and abnormal operation and in emergency conditions where the integrity of the pressure circuit of the nuclear reactor coolant has not been breached;
(f) necessary to limit the leakage of radioactive substances from the protective envelope under and after emergency conditions;
(g) intended to limit the penetration of ionising radiation outside the protective envelope in and after emergency conditions;
(h) necessary for the performance of safety functions for the supply of energy or for the control of other components included in safety class 2.
(4) Selected installations in Security Class 3 are:
(a) to prevent unacceptable transition processes associated with changes in reactivity;
(b) to maintain the nuclear reactor under conditions of safe weaning, after each weaning;
(c) to maintain sufficient coolant for cooling the core of the nuclear reactor in normal and abnormal operation;
(d) draining heat from safety systems up to the first accumulation volume (4) sufficient for the performance of safety functions;
(e) necessary to maintain the exposure of the population and workers of nuclear equipment under specified limits during and after emergency conditions associated with the leakage of radioactive substances and ionising radiation from sources located outside the protective envelope;
(f) necessary to maintain environmental conditions within the nuclear installation, necessary for the operation of safety systems and for the access of workers to safety-critical activities;
(g) to prevent radioactive releases from irradiated fuel transported or stored inside a nuclear installation outside the nuclear reactor cooling system during all normal and abnormal operations;
(h) for the removal of disintegration heat from irradiated fuel stored inside a nuclear installation outside the nuclear reactor cooling system;
(i) necessary to maintain sufficient undercriticism of the fuel stored inside the nuclear installation outside the nuclear reactor cooling system;
(j) necessary to limit discharges or releases of solid, liquid or gaseous radioactive substances and ionising radiation below the limits laid down during all normal and abnormal conditions of operation;
(k) necessary for the performance of safety functions for the supply of energy or for the control of other components included in safety class 3;
(l) necessary for the performance of safety functions to ensure the performance of other components included in safety classes 1, 2 and 3 which are not related to power management or supply;
(m) intended to prevent or reduce the consequences of disturbances of other components or structures of safety systems classified in Security Class 1, 2 or 3.

ČÁST TŘETÍ

INSURANCE OF QUALITY

HLAVA I

PRINCIPLES OF Quality Assurance
Basic quality assurance requirements
§ 5
(1) The essential requirements for ensuring the quality of selected equipment are:
(a) identification of activities affecting the quality of the selected establishments;
(b) organisational and technical security of quality assurance and of all activities affecting the quality of the equipment selected;
(c) the processing and approval of procedures for carrying out activities affecting the quality of the selected establishments so that their specified quality is achieved and maintained;
(d) verification of the scope and quality of the activities carried out which affect the quality of the equipment selected;
(e) documentary evidence of activities carried out affecting the quality of the establishments selected, including the results of checks;
(f) an evaluation of the results of the verifications referred to in (d) and an evaluation of the effectiveness of the measures taken.
(2) The responsible organisation5) must have the necessary overview of the technical condition of the equipment built or operated by it to demonstrate that the quality of the equipment selected has been achieved and maintained in particular by design, design, production, assembly and construction documentation.
§ 6
(1) Training and professional selection plans must be drawn up and implemented in organisations carrying out activities related to the implementation and verification of the performance of quality assurance programmes. The staff selection and training timetables shall be set out in such a way that, at the start of activities affecting the quality of the equipment selected and related to the quality assurance, workers of the necessary number and qualifications are available. The method of meeting these requirements shall be indicated in the quality assurance sub-programmes and individual ones.
(2) In the context of familiarisation of the worker with his / her workload, the organisation shall also inform him / her of the appropriate quality assurance programme.
(3) An organisation which carries out activities related to the implementation and verification of the performance of quality assurance programmes is required to ensure and demonstrate to the State supervision of nuclear safety the validity of a certificate of professional competence of the worker to carry out the relevant activity and medical fitness of the worker.
§ 7
(1) Organisations carrying out activities related to ensuring the quality of selected installations shall be required to carry out checks on all their activities which may affect the quality of selected installations. Only persons and organisational entities other than those carried out by the controlled activity may be entrusted with the control.
(2) In the absence of a clear check of the activity to be monitored, the organisation shall also include a check of compliance with the prescribed working procedures in the control system.
(3) The principles of the control and submission of information to the State control over nuclear safety of nuclear installations must be established before the start of the activity under control.

HLAVA II

DOCUMENTATION OF QUALITY
§ 8
Requirements for quality assurance documentation
(1) All activities affecting the quality of the selected equipment, in particular in their design, production, storage, transport, assembly, testing, inspection, launching, operation, maintenance, decommissioning, repairs and reconstructions, must be carried out according to pre-processed and approved documentation. This documentation shall be part of the quality assurance documentation and shall include in particular the procedure and methodology for carrying out the activity, the method of quality verification and the admissibility criteria. In particular, its compliance with the requirements to ensure nuclear safety of nuclear installations must be checked on an ongoing basis. The inspection carried out and the results thereof shall be recorded in the documentation of the equipment selected.
(2) If the performance of activities affecting the quality of the selected equipment is not regulated by technical standards and regulations, the organisation shall negotiate and comply with the technical conditions. The technical conditions shall be agreed before the start of the activities to which they relate.
(3) Organisations ensuring the processing of the documentation referred to in paragraphs 1 and 2 are required to develop procedures for making amendments to that dossier. The method of carrying out these procedures shall be indicated in quality assurance programmes.
(4) Changes to quality assurance documentation shall be re-checked and approved by the same procedure and by the same organisations and authorities as the original documentation. If this is not possible, the Commission shall decide on the next procedure. The consequences of the amendments shall be assessed and documented in the amendment documentation.
(5) Information on changes to quality assurance documentation is required to be transmitted without delay to all organisations concerned by the change by the organisation that initiated the change or the change.
(6) The documentation related to activities affecting the quality of the selected equipment shall be kept by the operator at two different, security-independent locations throughout the operation of the selected equipment.
Quality assurance programmes
§ 9
Quality assurance procurement programme
(1) The quality assurance programme shall be processed for each construction with nuclear equipment and shall be valid from the date of approval to the end of the life of the construction.
(2) The quality assurance programme shall develop the principles of quality assurance for selected installations and control activities set out for construction, operator, supplier of equipment and services during the period from design to destruction of nuclear installations.
(3) The quality assurance programme provides in particular for:
(a) detailed identification of the nuclear installation for which it is processed;
(b) the sequence of quality determination of the selected establishments;
(c) a sequence of activities which make the quality of the selected installations conditional on their design, manufacture, assembly, construction, testing, operation, maintenance, repair and reconstruction;
(d) requirements for the organisational and technical security of the quality of the selected equipment, including requirements for the qualification of personnel performing activities affecting the quality of the selected equipment;
(e) requirements for normative technical documentation;
(f) requirements to ensure uniform metrology;
(g) measures to ensure the quality of imported selected equipment and services relevant to nuclear safety, including the conduct of quality control;
(h) the principles of registration, identification and archiving of quality documentation, quality assurance documentation and control results;
(i) the requirements to be developed in the quality assurance sub-programmes and individual programmes, the frequency and methods of bringing them into line with the actual situation;
(j) the selection of selected installations concerned by the quality assurance activity corresponding to the depth of the design of the construction, 6)
(k) an overview of the construction participants, the supply system envisaged, indicating the links between them and the name of the organisation of the future nuclear operator;
(l) an overview of the functions of the investor's staff, with the determination of personal responsibility for the fulfilment of the individual requirements of the programme;
(m) the manner and frequency of checks on the implementation of this programme;
(n) the manner in which the Commission will be informed of the results of the check and the measures taken.
§ 10
Quality assurance sub-programmes
(1) The quality assurance sub-programmes shall be processed for each construction with nuclear equipment and shall be valid from the date of their approval.
(2) The quality assurance sub-programmes shall develop the requirements set out in this Order and in the quality assurance procurement programme.
(3) The quality assurance sub-programmes shall be processed for areas:
(a) design and design by the relevant project organisation;
(b) construction, including preparation for launch7) and launch8) by the investor and his supplier;
(c) operator operations;
(d) decommissioning by the relevant project organisation, operator and its suppliers of nuclear safety-relevant activities and services.
(4) The quality assurance sub-programmes shall also be processed for other areas where this is provided for in the quality assurance procurement programme.
(5) The quality assurance sub-programme processed for each area shall include in particular:
(a) a summary of all own activities affecting the quality of the selected establishments;
(b) organisational security and a description of quality assurance with a definition of the activities, powers and responsibilities to meet the individual requirements of this programme;
(c) organisational security of activities affecting the quality of the selected establishments, including requirements for the qualification of personnel performing those activities;
(d) the technical provision of the activities carried out which affect the quality of the equipment selected and the summary of the technical documentation according to which those activities will be carried out;
(e) the way in which the activities carried out have an impact on the quality of the selected installations, including checks on working procedures for design, design, manufacture, testing, construction and operation;
(f) the way in which checks, tests and tests carried out by other organisations are carried out;
(g) procedures for addressing and addressing identified deficiencies;
(h) the method of documenting the activities carried out, including checks;
(i) the method of identification, registration and archiving of documentation relating to the quality assurance of the selected establishments;
(j) a supply system indicating the relationship and the way in which the quality of the selected installations is ensured within those relationships;
(k) the organisation, manner and frequency of checks on the implementation of these programmes and their effectiveness;
(l) the manner in which the Commission will be informed of the results of the check and the measures taken.
(6) The quality assurance sub-programmes processed by the operator shall also include:
(a) the process for preparing, assessing, approving and issuing documents necessary for the implementation of nuclear safety-related work on nuclear equipment, including the specification of such documents and procedures for the implementation and approval of their amendments;
(b) a description of quality assurance in areas relevant to nuclear safety, such as, in particular, the management of the operation of nuclear equipment, the negotiation of external services and the supply of spare parts, storage, maintenance, operational checks, functional tests, repairs of selected equipment, evaluation of their condition, metrology, personnel preparation, preparation and documentation management.
§ 11
Individual quality assurance programmes
(1) Individual quality assurance programmes shall develop the concepts and principles of quality assurance for selected installations laid down in this Decree and the quality assurance programme for the nuclear installation concerned.
(2) Individual quality assurance programmes are valid from the date of their approval until the end of the life of the selected equipment for which they are processed.
(3) Individual quality assurance programmes are processed:
(a) for individual devices selected, classified in Security Class 1;
(b) for individual devices selected, classified in safety class 2; for piping lines, fittings, automated process control devices or electrical equipment, a combined individual quality assurance programme may be developed by the manufacturer concerned in the scope of its supply;
(c) for selected equipment classified in Security Class 3 within the scope of supply of selected equipment of the supplier concerned.
(4) Individual quality assurance programmes shall include:
(a) a list of the selected establishments covered by those programmes;
(b) a summary of the nuclear safety performance established on the basis of the design, design, production, assembly and construction documentation for the selected installation;
(c) proof of compliance of the design of the selected installation with the requirements of the project;
(d) indicators of reliability of selected installations;
(e) a list of each activity affecting the quality of the equipment selected during the period of manufacture, assembly, construction, launching and operation;
(f) organisational security and a description of quality assurance with a definition of the activities, powers and responsibilities to meet the individual requirements of these programmes;
(g) organisational security for the implementation of individual activities affecting the quality of the selected establishments, including the requirements for the qualification of personnel performing those activities;
(h) the technical provision of the activities carried out affecting the quality of the selected equipment, the summary of the standard and technical documentation according to which those activities will be carried out and the proof of the agreement of the relevant technical conditions between the manufacturer and the customer where the technical conditions are agreed;
(i) the requirements of manufacturers to ensure the quality of repairs and changes to selected equipment;
(j) the way in which the activities carried out affect the quality of the equipment selected,
(k) binding procedures for the processing and evaluation of the results of operational checks, for the evaluation of residual life and for the evaluation of the witness sample systems where such systems are prescribed;
(l) procedures for addressing and addressing identified deficiencies;
(m) the method of documenting the activities carried out, including checks;
(n) the method of identification, registration and archiving of documentation relating to the quality assurance of the selected establishments;
(o) the means of marking and identification of the individual devices selected and their parts;
(p) a list of all organisations involved in ensuring the supply of selected facilities;
(q) the requirements of the processor of the individual quality assurance programme for its subcontractors concerning the way in which the quality achieved and the functional characteristics of deliveries are demonstrated and their compliance with the relevant rules and standards;
(r) the manner, organisation and frequency of checks on the implementation of these programmes.
(5) According to individual quality assurance programmes, the selected equipment is also checked in production, assembly, preparation for launching, launching, repairs and reconstructions.
(6) The annex documentation of individual quality assurance programmes which, when processed, is an integral part of them, shall include instructions, methodological procedures and drawings concerning quality and functional checks, including the determination of permitted limits and stocks throughout the lifetime of the selected equipment. These instructions, methodological procedures and drawings shall include:
(a) the necessary acceptance criteria to determine whether the quality laid down has been achieved;
(b) determination of the size of the smallest registered and permissible defect following the sensitivity of the non-destructive method used.
Processing, discussion and approval of quality assurance programmes and list of selected establishments
§ 12
(1) In parallel with the award of the construction, the investor is obliged to ensure the processing of the tender security report, 9) of which the quality assurance programme is part.
(2) An investor may entrust the processing of a quality assurance procurement programme to another organisation, with the obligation to cooperate with it and to provide the necessary documentation for its processing.
(3) Before starting work on the quality assurance procurement programme, its outline and the selection of selected installations shall be subject to prior agreement by the Commission.
(4) Prior to the start of the project work (10), the investor is obliged to submit a quality assurance programme for approval to the Commission in good time.
(5) In parallel to the project processing and in the framework of the preliminary security report11), the investor is obliged to provide the relevant project organisation on the basis of binding documentation from the suppliers of the technological and construction parts with:
(a) a list of selected installations in the scope and depth of project processing for the nuclear installation.
This list shall be:
1. processed in a text and drawing form in a separate documentation with an indication of the individual safety classes of the selected equipment,
2. approved by the investor and subsequently submitted for approval to the Commission before approval of the project;
3. half-yearly specified by the relevant project organisation on the basis of changes and additions to the project; Such adjustments shall be subject to consultation with the investor who submits them to the Commission for approval before their implementation;
(b) an inventory of the solutions used in the project which constitute a basic concept for the implementation of quality control activities, in particular with regard to:
1. accessibility to controlled selected equipment (disposition solution, possibility of deactivation of surfaces, removable insulation, etc.),
2. measurement, control and diagnostic systems for inspection during operation, taking into account the requirements of suppliers of selected equipment.
(6) Before processing the list of selected installations, the project organisation and the investor concerned shall discuss with the Commission the restrictive and specifying conditions to be included in that list.
(7) The investor is obliged to agree to amend and specify the list of selected installations and to submit for approval to the Commission.
(8) The selected equipment shall be indicated by the relevant project organisation in the specifications and drawing part of the project.
(9) The quality assurance sub-programmes shall be approved by the investor or, where appropriate, the operator after processing and approved by the Commission before the start of the activities for which they are intended.
(10) The processed quality assurance sub-programmes shall be submitted in sufficient time to the Commission for approval in the cases referred to in Article 10 (3) (a) and (b) by the investor and, in other cases, by the operator.
§ 13
(1) Manufacturers of selected equipment are required to process individual quality assurance programmes covering all activities affecting the quality of selected equipment within the scope of their supply before the production of selected equipment.
(2) Prior to the production of selected equipment, individual quality assurance programmes shall be discussed and agreed by the investor and approved by the Commission. The individual quality assurance programmes shall be submitted by the investor to the Commission for approval.
(3) Where the technical conditions for the supply of the selected equipment are agreed between the manufacturer and the customer of the selected equipment, these conditions shall be agreed before the submission of an individual quality assurance programme for the selected equipment to be approved by the Commission. Compliance with this requirement shall be demonstrated in the relevant quality assurance programme.
§ 14
Amendments and adjustments to quality assurance programmes and list of selected installations
Amendments and modifications to approved quality assurance programmes and to the list of selected establishments shall be made in accordance with the principles applicable to the preparation and approval of quality assurance programmes of the relevant level and the list of selected establishments. In order to discuss and approve changes and modifications to programmes of the relevant level and list of selected installations, the organisation shall be responsible for drawing up and implementing them and shall demonstrate a written analysis of the causes of the proposed change or modification before its implementation.

HLAVA III

REQUIREMENTS FOR ENSURE OF QUALITY IN SINGLE ETAPS
Quality assurance at the design stage

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Regulation Information

CitationDecree of the Czechoslovak Atomic Energy Commission No. 436 / 1990 Coll., on ensuring the quality of selected equipment in terms of nuclear safety of nuclear installations
Regulation Type-
Author-
CollectionCode of Laws
Date of Promulgation29.10.1990
Effective from01.12.1990
Effective until-
Status Valid
The regulation text is for informational purposes only.
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