ДСТУ ISO 8107:2023 Атомные электрические станции. Ремонтопригодность. Терминология (ISO 8107:1993, IDT)
НАЦІОНАЛЬНИЙ СТАНДАРТ УКРАЇНИ
ISO 8107:1993
NUCLEAR POWER PLANTS —
MAINTAINABILITY — TERMINOLOGY
ДСТУ ISO 8107:2023
(ISO 8107:1993, IDT)
АТОМНІ ЕЛЕКТРИЧНІ СТАНЦІЇ
РЕМОНТОПРИДАТНІСТЬ
ТЕРМІНОЛОГІЯ
Не є офіційним виданням.
Офіційне видання розповсюджує національний орган стандартизації
(ДП «УкрНДНЦ» http://uas.gov.ua)
ПЕРЕДМОВА
1 РОЗРОБЛЕНО: Технічний комітет стандартизації «Водневі технології» (ТК 197)
2 ПРИЙНЯТО ТА НАДАНО ЧИННОСТІ: наказ Державного підприємства «Український науково-дослідний і навчальний центр проблем стандартизації, сертифікації та якості» (ДП «УкрНДНЦ») від 09 жовтня 2023 р. № 267 з 2024-06-01
3 Стандарт відповідає ISO 8107:1993 Nuclear power plants — Maintainability — Terminology (Атомні електричні станції. Ремонтопридатність. Термінологія)
Ступінь відповідності — ідентичний (IDT)
Метод прийняття — передрук
Мова оригіналу міжнародного стандарту — англійська (еn)
4 Цей стандарт розроблено згідно з правилами, установленими в національній стандартизації України
5 УВЕДЕНО ВПЕРШЕ
Право власності на цей національний стандарт належить державі.
Заборонено повністю чи частково видавати, відтворювати
задля розповсюдження і розповсюджувати як офіційне видання
цей національний стандарт або його частини на будь-яких носіях інформації
без дозволу ДП «УкрНДНЦ» чи уповноваженої ним особи
ДП «УкрНДНЦ», 2024
НАЦІОНАЛЬНИЙ ВСТУП
Цей національний стандарт ДСТУ ISO 8107:2023 (ISO 8107:1993, IDT) «Атомні електричні станції. Ремонтопридатність. Термінологія», прийнятий методом передруку, — ідентичний щодо ISO 8107:1993 (версія en) «Nuclear power plants — Maintainability — Terminology».
Технічний комітет стандартизації, відповідальний за цей стандарт в Україні, — ТК 197 «Водневі технології».
У цьому національному стандарті зазначено вимоги, які відповідають законодавству України.
З огляду на потреби користувачів до цього стандарту внесено такі редакційні зміни:
— долучено довідковий додаток НА, у якому подано український переклад тексту ISO 8107:1993.
Національні структурні елементи викладено відповідно до обов’язкових вимог чинної редакції Українського правопису (НАН України. — К.: Наук, думка, 2019. — 392 с.), схваленої постановою Кабінету Міністрів України від 22.05.2019 № 437.
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INTERNATIONAL NORME |
ISO First edition |
Nuclear power plants - Maintainability -
Terminology
Centrales nucleates - Maintenabilite - Terminologie
Reference number
Numero de reference
ISO 8107:1993(E/F)
Foreword
ISO (the International Organization for Standardization) is a worldwide federation of national standards bodies (ISO member bodies). The work of preparing International Standards is normally carried out through ISO technical committees. Each member body interested in a subject for which a technical committee has been established has the right to be represented on that committee. International organizations, governmental and non-governmental, in liaison with ISO, also take part in the work. ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of electrotechnical standardization.
Draft International Standards adopted by the technical committees are circulated to the member bodies for voting. Publication as an International Standard requires approval by at least 75 % of the member bodies casting a vote.
International Standard ISO 8107 was prepared by Technical Committee ISO/TC 85, Nuclear energy.
Annex A of this International Standard is for information only.
© ISO 1993
All rights reserved. No part of this publication may be reproduced or utilized in any form or by any means, electronic or mechanical, including photocopying and microfilm, without permission in writing from the publisher./Droits de reproduction reserves. Aucune partie de cette publication ne peut etre reproduite ni utilisde sous quelque forme que ce soit et par aucun procede, electronique ou mecanique, у compris la photocopie et les microfilms, sans 1‘accord ecrit de I'dditeur.
International Organization for Standardization
Case postale 56 • CH-1211 Geneve 20 • Switzerland
Printed in Switzerland/lmprime en Suisse
Introduction
System availability is governed by component reliability and maintainability. While for component reliability extended analysis has been carried out to define the terminology and the procedures that make the exchange of homogeneous data possible, the maintainability field has not yet been fully investigated.
In quantitative terms, maintainability may be expressed as the probability that an item will be retained in, or restored to, a specified condition within a given period of time, when the maintenance is performed in accordance with the stipulated procedures and resources.
Maintainability calls, therefore, for a series of actions to be taken during the design, construction and operation stages of the system itself. Therefore maintainability touches on many aspects that have to be properly highlighted in any attempt to classification, and may be summarized as follows:
a) design of the equipment;
b) environmental conditions in which the equipment has to be maintained, and its accessibility;
c) internal organization of the plant, including spare parts policy, readiness and qualification of the maintenance staff;
d) maintenance strategy (corrective, preventive, predictive or a combination of these);
e) maintenance facilities, on-site or remote;
f) external maintenance contracts;
g) interaction with operational requirements.
For the purpose of maintaining components in a satisfactory operating condition, maintenance activities can be performed according to one or more of the following methods:
a) corrective maintenance, including breakdown, after the failure of the component;
b) preventive maintenance subdivided into
- systematic maintenance, i.e. carried out at scheduled time intervals;
- predictive or controlled maintenance, when monitoring the conditions of the component in order to promptly identify possible degradation due to wear, corrosion, etc.; predictive maintenance can be carried out automatically, continuously or manually.
Should corrective maintenance be necessary, the period of time taken to restore the component to an operational state will be a critical parameter, and the design features to minimize this period are a prime factor in maintainability.
The total downtime of an item has been subdivided into:
a) undetected failure time, which is mostly dependent on the proper monitoring, warning and alarm systems, test procedures and intervals;
b) administrative delay time, the duration of which is linked to the internal organizaton of the plant and to logistic delays inherent in the particular spare parts policy;
c) actual maintenance time, which is directly related to the position of the component in the system and to the component itself.
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INTERNATIONAL STANDARD |
ISO 8107:1993(E/F) |
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Nuclear power plants - |
Centrales nucleates - |
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1 Scope |
1 Domaine d’application |
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This International Standard identifies the typical parameters and terms necessary for collecting and exchanging maintainability data. The definitions are valid for corrective maintenance. For preventive maintenance, a similar classification can be drawn up. The general guidelines on the exchange of reliability data for nuclear power plants are given in ISO 6527. |
La presente Norme internationale definit les parametres et termes principaux necessaires pour recueillir et echanger des donnees dans le domaine de la maintenabilite. Les definitions s'appliquent a la maintenance corrective. Une classification similaire peut etre effectuee pour la maintenance preventive. Les criteres generaux concernant rechange de donndes sur la fiabilite de fonctionnement des centrales nucleates sont donnees dans I'ISO 6257. |
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2 Normative reference |
2 Reference normative |
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The following standard contains provisions which, through reference in this text, constitute provisions of this International Standard. At the time of publication, the edition indicated was valid. All standards are subject to revision, and parties to agreements based on this International Standard are encouraged to investigate the possibility of applying the most recent edition of the standard indicated below. Members of IEC and ISO maintain registers of currently valid International Standards. ISO 6527:1982, Nuclear power plants - Reliability data exchange - General guidelines. |
La norme suivante contient des dispositions qui, par suite de la reference qui en est faite, constituent des dispositions valables pour la presente Norme internationale. Au moment de la publication, I'edition indiquee etait en vigueur. Toute norme est sujette a revision et les parties prenantes des accords fondes sur la presente Norme internationale sont invitees a rechercher la possibilite d'appliquer I'edition la plus recente de la norme indiquee ci-apres. Les membres de la CEI et de I'ISO possedent le registre des Normes internationales en vigueur a un moment donne. ISO 6527:1982, Centrales nucleates - Echanges de donnees de fiabilite - Criteres generaux. |
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3 Definitions |
3 Definitions |
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3.1 General |
3.1 Generalites |
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The following definitions cover the various times that go to make up the total downtime of an item. In table 1, the subdivision of downtime is summarized. The breakdown has been made as detailed as possible in order to set up a model to which reference can be made when collecting or exchanging data. However, this does not imply that data are available or should be collected at all the levels mentioned. 3.2 downtime: The period of time during which an item is not in a condition to perform its required function. 3.2.1 undetected failure time: The time that elapses between the moment when the component fails and the moment when the faulty component is identified. 3.2.1.1 undetected fault time: The time that elapses between the moment when an item fails and the moment when the system malfunction is detected. NOTE 1 - Of course this time cannot be determined precisely. It can be estimated, however, on the basis of inspection and testing intervals. 3.2.1.2 fault diagnosis time: The time that elapses between the moment when a system malfunction is detected and the moment when the fault is identified in a certain item of equipment by control room indications, technical deductions, testing, etc. 3.2.2 administrative delay time: The period of time following identification of faulty equipment until that time at which any maintenance operations can feasibly commence. 3.2.2.1 organization time: That part of the administrative delay time during which the work is being organized and the maintenance cannot yet be carried out. 3.2.2.1.1 preparation time: Inactive time due to administration and organization procedures; it includes the time for decision making, document processing, authorizations. 3.2.2.1.2 maintenance organization time: The period of time needed for preparing the crew (including providing drawings, tools, instructions, etc.). The time spent training or practising for the actual maintenance procedure is also included. 3.2.2.2 programmed delay time: Delay dependent on the plant maintenance schedule. 3.2.2.3 external logistic delay: The part of the administrative delay time during which the maintenance cannot be carried out because of external logistic delays (e.g. outside maintenance contractor's delays). |
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