iTeh StandardsiTeh Standards
EURUSD
Your shopping cart is empty.
CLC

EN IEC 62138:2019

(Main)

Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category B or C functions

Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category B or C functions

This document specifies requirements for the software of computer-based instrumentation and control (I&C) systems performing functions of safety category B or C as defined by IEC 61226. It complements IEC 60880 which provides requirements for the software of computer-based I&C systems performing functions of safety category A. It is consistent with, and complementary to, IEC 61513. Activities that are mainly system level activities (for example, integration, validation and installation) are not addressed exhaustively by this document: requirements that are not specific to software are deferred to IEC 61513. The link between functions categories and system classes is given in IEC 61513. Since a given safety-classified I&C system may perform functions of different safety categories and even non safety-classified functions, the requirements of this document are attached to the safety class of the I&C system (class 2 or class 3). This document is not intended to be used as a general-purpose software engineering guide. It applies to the software of I&C systems of safety classes 2 or 3 for new nuclear power plants as well as to I&C upgrading or back-fitting of existing plants. For existing plants, only a subset of requirements is applicable and this subset has to be identified at the beginning of any project. The purpose of the guidance provided by this document is to reduce, as far as possible, the potential for latent software faults to cause system failures, either due to single software failures or multiple software failures (i.e. Common Cause Failures due to software). This document does not explicitly address how to protect software against those threats arising from malicious attacks, i.e. cybersecurity, for computer-based systems. IEC 62645 provides requirements for security programmes for computer-based systems.

Kernkraftwerke - Leittechnische Systeme mit sicherheitstechnischer Bedeutung - Softwareaspekte für rechnerbasierte Systeme zur Realisierung von Funktionen der Kategorien B oder C

Centrales nucléaires de puissance - Systèmes d’instrumentation et de contrôle-commande importants pour la sûreté - Aspects logiciels des systèmes informatisés réalisant des fonctions de catégorie B ou C

This document specifies requirements for the software of computer-based instrumentation and control (I&C) systems performing functions of safety category B or C as defined by IEC 61226. It complements IEC 60880 which provides requirements for the software of computer-based I&C systems performing functions of safety category A. It is consistent with, and complementary to, IEC 61513. Activities that are mainly system level activities (for example, integration, validation and installation) are not addressed exhaustively by this document: requirements that are not specific to software are deferred to IEC 61513. The link between functions categories and system classes is given in IEC 61513. Since a given safety-classified I&C system may perform functions of different safety categories and even non safety-classified functions, the requirements of this document are attached to the safety class of the I&C system (class 2 or class 3). This document is not intended to be used as a general-purpose software engineering guide. It applies to the software of I&C systems of safety classes 2 or 3 for new nuclear power plants as well as to I&C upgrading or back-fitting of existing plants. For existing plants, only a subset of requirements is applicable and this subset has to be identified at the beginning of any project. The purpose of the guidance provided by this document is to reduce, as far as possible, the potential for latent software faults to cause system failures, either due to single software failures or multiple software failures (i.e. Common Cause Failures due to software). This document does not explicitly address how to protect software against those threats arising from malicious attacks, i.e. cybersecurity, for computer-based systems. IEC 62645 provides requirements for security programmes for computer-based systems.

Nuklearne elektrarne - Instrumenti in nadzorni sistemi za zagotavljanje varnosti - Značilnosti programske opreme računalniških sistemov, ki izvajajo funkcije kategorij B ali C (IEC 62138:2018)

Ta dokument določa zahteve za programsko opremo računalniških instrumentov in nadzornih sistemov (I&C) za izvajanje funkcij varnostne kategorije B ali C, kot je definirana v standardu IEC 61226. Dopolnjuje standard IEC 60880, ki določa zahteve za programsko opremo računalniških instrumentov in nadzornih sistemov za izvajanje funkcij varnostne kategorije A. Skladen je s standardom IEC 61513, katerega tudi dopolnjuje. Dejavnosti, ki so predvsem dejavnosti na ravni sistema (na primer integracija, validacija in namestitev), v tem dokumentu niso izčrpno naslovljene: zahteve, ki se ne navezujejo na programsko opremo, so navedene v standardu IEC 61513. Povezava med funkcijskimi kategorijami in sistemskimi razredi je podana v standardu IEC 61513. Ker lahko dani sistem I&C z varnostno razvrstitvijo izvaja funkcije različnih varnostnih kategorij in celo funkcij, ki nimajo varnostne razvrstitve, so zahteve tega dokumenta dodane varnostnemu razredu sistema I&C (razred 2 ali razred 3). Namen tega dokumenta ni, da bi se uporabljal kot vodilo za inženiring programske opreme za splošni namen. Uporablja se za programsko opremo računalniških instrumentov in nadzornih sistemov varnostnega razreda 2 ali 3 za nove jedrske elektrarne in tudi za nadgradnjo ali posodobitev obstoječih elektrarn z računalniškimi instrumenti in nadzornimi sistemi. Za obstoječe elektrarne se uporablja samo podnabor zahtev in ta podnabor je treba identificirati na začetku posameznega projekta. Namen vodil, navedenih v tem dokumentu, je v največji možni meri zmanjšati potencial, da bi latentne okvare programske opreme povzročile odpovedi sistema, in sicer zaradi okvar posamezne programske opreme
ali okvar več programskih oprem (tj. okvare s skupnim vzrokom zaradi programske opreme). Ta dokument ne naslavlja izrecno zaščite programske opreme pred grožnjami, ki izhajajo iz zlonamernih napadov, tj. kibernetske varnosti, za računalniške sisteme. Zahteve za varnostne programe za računalniške sisteme določa standard IEC 62645.

General Information

Status
Published
Publication Date
26-Sep-2019
Withdrawal Date
08-Sep-2022
ICS
27.120.20 - Nuclear power plants. Safety
Technical Committee
CLC/TC 45AX - Nuclear power plants
Drafting Committee
CLC/TC 45AX - Nuclear power plants
Current Stage
6060 - Document made available - Publishing
Start Date
27-Sep-2019
Due Date
13-Apr-2021
Completion Date
27-Sep-2019
Ref Project
SIST EN IEC 62138:2019 - Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category B or C functions (IEC 62138:2018)

Relations

Replaces
EN 62138:2009 - Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions
Effective Date
23-Jan-2023

Buy Standard

EN IEC 62138:2019EN IEC 62138:2019
PreviousNext
Standard
EN IEC 62138:2019
English language
55 pages
sale 10% off
Preview
sale 10% off
Preview
e-Library read for
1 day

Standards Content (Sample)


SLOVENSKI STANDARD
01-december-2019
Nadomešča:
SIST EN 62138:2009
Nuklearne elektrarne - Instrumenti in nadzorni sistemi za zagotavljanje varnosti -
Značilnosti programske opreme računalniških sistemov, ki izvajajo funkcije
kategorij B ali C (IEC 62138:2018)
Nuclear power plants - Instrumentation and control systems important to safety -
Software aspects for computer-based systems performing category B or C functions (IEC
62138:2018)
Kernkraftwerke - Leittechnische Systeme mit sicherheitstechnischer Bedeutung -
Softwareaspekte für rechnerbasierte Systeme zur Realisierung von Funktionen der
Kategorien B oder C (IEC 62138:2018)
Centrales nucléaires de puissance - Systèmes d’instrumentation et de contrôle-
commande importants pour la sûreté - Aspects logiciels des systèmes informatisés
réalisant des fonctions de catégorie B ou C (IEC 62138:2018)
Ta slovenski standard je istoveten z: EN IEC 62138:2019
ICS:
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EUROPEAN STANDARD EN IEC 62138

NORME EUROPÉENNE
EUROPÄISCHE NORM
September 2019
ICS 27.120.20 Supersedes EN 62138:2009 and all of its amendments
and corrigenda (if any)
English Version
Nuclear power plants - Instrumentation and control systems
important to safety - Software aspects for computer-based
systems performing category B or C functions
(IEC 62138:2018)
Centrales nucléaires de puissance - Systèmes Kernkraftwerke - Leittechnische Systeme mit
d'instrumentation et de contrôle-commande importants pour sicherheitstechnischer Bedeutung - Softwareaspekte für
la sûreté - Aspects logiciels des systèmes informatisés rechnerbasierte Systeme zur Realisierung von Funktionen
réalisant des fonctions de catégorie B ou C der Kategorien B oder C
(IEC 62138:2018) (IEC 62138:2018)
This European Standard was approved by CENELEC on 2019-09-09. CENELEC members are bound to comply with the CEN/CENELEC
Internal Regulations which stipulate the conditions for giving this European Standard the status of a national standard without any alteration.
Up-to-date lists and bibliographical references concerning such national standards may be obtained on application to the CEN-CENELEC
Management Centre or to any CENELEC member.
This European Standard exists in three official versions (English, French, German). A version in any other language made by translation
under the responsibility of a CENELEC member into its own language and notified to the CEN-CENELEC Management Centre has the
same status as the official versions.
CENELEC members are the national electrotechnical committees of Austria, Belgium, Bulgaria, Croatia, Cyprus, the Czech Republic,
Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, the
Netherlands, Norway, Poland, Portugal, Republic of North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,
Turkey and the United Kingdom.

European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung
CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels
© 2019 CENELEC All rights of exploitation in any form and by any means reserved worldwide for CENELEC Members.
Ref. No. EN IEC 62138:2019 E
European foreword
This document (EN IEC 62138:2019) consists of the text of IEC 62138:2018 prepared by SC 45A
"Instrumentation, control and electrical power systems of nuclear facilities" of IEC/TC 45 "Nuclear
instrumentation".
The following dates are fixed:
• latest date by which this document has to be (dop) 2020-09-09
implemented at national level by publication of an
identical national standard or by endorsement
• latest date by which the national standards (dow) 2022-09-09
conflicting with this document have to be
withdrawn
This document supersedes EN 62138:2009 and all of its amendments and corrigenda (if any).
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CENELEC shall not be held responsible for identifying any or all such patent rights.
As stated in the nuclear safety directive 2009/71/EURATOM, Chapter 1, Article 2, item 2, Member
States are not prevented from taking more stringent safety measures in the subject-matter covered by
the Directive, in compliance with Community law. In a similar manner, this European standard does
not prevent Member States from taking more stringent nuclear safety and/or security measures in the
subject-matter covered by this standard.
Endorsement notice
The text of the International Standard IEC 62138:2018 was approved by CENELEC as a European
Standard without any modification.
In the official version, for Bibliography, the following notes have to be added for the standards
indicated:
IEC 61508-3:2010 NOTE  Harmonized as EN 61508-3:2010 (not modified)
IEC 61508-4:2010 NOTE  Harmonized as EN 61508-3:2010 (not modified)
IEC 61511-1:2016
NOTE  Harmonized as EN 61511-1:2016 (not modified)
ISO 9001:2015
NOTE  Harmonized as EN ISO 9001:2015 (not modified)
Annex ZA
(normative)
Normative references to international publications
with their corresponding European publications
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements of this document. For dated references, only the edition cited applies. For
undated references, the latest edition of the referenced document (including any amendments)
applies.
NOTE 1 When an International Publication has been modified by common modifications, indicated by (mod), the relevant

EN/HD applies.
NOTE 2 Up-to-date information on the latest versions of the European Standards listed in this annex is available here:
www.cenelec.eu.
Publication Year Title EN/HD Year
IEC 60880 2006 Nuclear power plants - Instrumentation EN 60880 2009
and control systems important to safety -
Software aspects for computer-based
systems performing category A functions
IEC 61226 -  Nuclear power plants - Instrumentation EN 61226 -
and control important to safety -
Classification of instrumentation and
control functions
IEC 61513 2011 Nuclear power plants - Instrumentation EN 61513 2013
and control important to safety - General
requirements for systems
IEC 62671 2013 Nuclear power plants - Instrumentation - -
and control important to safety - Selection
and use of industrial digital devices of
limited functionality
IEC 62138 ®
Edition 2.0 2018-07
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Instrumentation and control systems important to

safety – Software aspects for computer-based systems performing category

B or C functions
Centrales nucléaires de puissance – Systèmes d’instrumentation et de contrôle-

commande importants pour la sûreté – Aspects logiciels des systèmes

informatisés réalisant des fonctions de catégorie B ou C

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
INTERNATIONALE
ICS 27.120.20 ISBN 978-2-8322-5830-9

– 2 – IEC 62138:2018 © IEC 2018
CONTENTS
FOREWORD . 4
INTRODUCTION . 6
1 Scope . 8
2 Normative references. 8
3 Terms and definitions . 9
4 Symbols and abbreviated terms . 17
5 Key concepts and assumptions . 17
5.1 General . 17
5.2 Types of software . 17
5.3 Types of configuration data . 18
5.4 Software and system safety lifecycles . 19
5.5 Gradation principles . 21
6 Requirements for the software of class 2 and class 3 I&C systems . 22
6.1 Applicability of the requirements . 22
6.2 General requirements . 22
6.2.1 Software safety lifecycle – Software quality assurance . 22
6.2.2 Verification . 23
6.2.3 Configuration management . 24
6.2.4 Selection and use of software tools . 25
6.2.5 Selection of languages . 26
6.3 Selection of pre-developed software . 27
6.3.1 General . 27
6.3.2 Documentation for safety. 27
6.3.3 Evidence of correctness . 28
6.3.4 Functional suitability . 35
6.3.5 Selection and use of digital devices of limited functionality . 35
6.4 Software requirements specification . 35
6.4.1 General . 35
6.4.2 Objectives . 35
6.4.3 Inputs . 36
6.4.4 Contents . 36
6.4.5 Properties . 37
6.5 Software design . 38
6.5.1 Objectives . 38
6.5.2 Inputs . 38
6.5.3 Contents . 39
6.5.4 Properties . 40
6.6 Implementation of software . 40
6.6.1 General requirements . 40
6.6.2 Configuration of software and of devices containing software . 40
6.6.3 Implementation with application-oriented languages . 41
6.6.4 Implementation with general-purpose languages . 41
6.7 Software aspects of system integration . 43
6.7.1 General . 43
6.8 Software aspects of system validation . 43
6.8.1 General . 43

IEC 62138:2018 © IEC 2018 – 3 –
6.9 Installation of software on site . 45
6.9.1 General . 45
6.10 Anomaly reports . 45
6.11 Software modification . 46
6.11.1 General . 46
6.12 Defences against common cause failure due to software . 47
Annex A (informative) Typical list of software documentation . 48
Annex B (informative) Correspondence between IEC 61513:2011 and this document . 49
Annex C (informative) Relations of this document with IEC 61508 .
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.

This May Also Interest You

CLC
EN IEC 62988:2022(Main)
Nuclear power plants - Instrumentation and control systems important to safety - Selection and use of wireless devices
SIST EN IEC 62988:2022

See the scope of IEC 62988:2018. Adoption of IEC 62988:2018 is to be done without modification.

  • Standard
    21 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 60987:2021(Main)
Nuclear power plants - Instrumentation and control important to safety - Hardware requirements
SIST EN IEC 60987:2021

IEC 60987:2021 provides requirements and recommendations for the hardware aspects of I&C systems whatever the technology and applies for all safety classes in a graded manner (as defined by IEC 61513). The requirements defined within this document guide, in particular, the selection of pre-existing components, hardware aspects of system detailed design and implementation and equipment manufacturing. This third edition cancels and replaces the second edition published in 2007. This edition includes the following significant technical changes with respect to the previous edition: a) Title modified; b) Take account of the fact that hardware requirements apply to all I&C technologies, including conventional hardwired equipment, programmable digital equipment or by using a combination of both types of equipment; c) Align the standard with the new revisions of IAEA documents SSR-2/1, which include as far as possible an adaptation of the definitions; d) Replace, as far as possible, the requirements associated with standards published since the edition 2.1, especially IEC 61513, IEC 60880, IEC 62138, IEC 62566 and IEC 62566‑2; e) Review the existing requirements and update the terminology and definitions; f) Extend the scope of the standard to all hardware (computerized and non-computerized) and to all safety classes 1, 2 and 3; g) Complete, update the IEC and IAEA references and vocabulary; h) Check possible impact of other IAEA requirements and recommendations considering extension of the scope of SC 45A; i) Highlight the use of IEC 62566 and IEC 62566-2 for HPD development; j) Introduce specific activities for pre-existing items (selection, acceptability and/or mitigation); k) Introduce clearer requirements for electronic module-level design, manufacturing and control; l) Complete reliability assessment methods; m) Introduce requirements when using automated tests or control activities; n) Complete description of manufacturing control activities (control process, assessment of manufactured equipment, preservation of products); o) Define and ensure the inclusion of a graded approach for dealing with the 3 different classes of equipment and related requirements.

  • Standard
    53 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 62855:2021(Main)
Nuclear power plants - Electrical power systems - Electrical power systems analysis
SIST EN IEC 62855:2021

IEC 62855 provides the electrotechnical engineering guidelines for analysis of AC and DC electrical power systems in nuclear power plants (NPPs) in order to demonstrate that the power sources and the distribution systems have the capability for safe operation and shut down of the NPP, bringing it to a controlled state after an anticipated operational occurrence or accident conditions and finally reaching a safe state. The analytical studies discussed in this document provide assurance that the design bases are satisfied to meet their functional requirements under the conditions produced by the applicable design basis events. The studies provide assurance that the electrical power system is capable of supporting safety functions during all required plant conditions. NOTE The safety functions are described in IAEA Specific Safety Requirements SSR-2/1 related to the design of the nuclear power plants.. Analytical studies validate the robustness and adequacy of design margins and demonstrate the capability of electrical power systems to support plant operation for normal, abnormal, degraded and accident conditions. The analyses are used to verify that the electrical power system can withstand minor disturbances and that the consequences of major disturbances or failures do not degrade the capability of the electrical power systems to support safe shutdown of the plant and maintain the plant in shutdown condition. The analyses are performed with one or more of • simulation tools (software and hardware) that have been verified and validated, • hand calculations, and • tests. This document provides guidance on the types of analyses required to demonstrate that the plant's auxiliary power system can perform the required safety functions. This document does not provide specific details on how the analysis should be conducted. This document does not cover digital controllers (such as controllers for rectifiers, inverters, sequencers and electrical protection devices) used in electrical power systems. IEC 61513 gives recommendations that apply to the electronic controls and protective elements of the electrical power systems. This document does not include environmental conditions (i.e. temperature, humidity, etc.) or external events (seismic, flooding, fire, high energy electromagnetic pulse, etc.) that may impact equipment sizing or protection requirements. The external events lightning and geomagnetic storms are included. This document does not cover additional or unique requirements for stand-alone power system, such as power supplies for security measures in NPPs. Pertinent clauses of this document may be used as a guideline for such systems. Redundancy in the power system design can increase the availability of electrical power to critical plant equipment. Performing a probabilistic risk assessment (PRA) is a method of assessing system availability and optimizing design for high reliability. This document does not cover improving the reliability of NPP electrical power systems using statistical or diverse and redundant schemes. Requirements for safeguards of personnel involved with installation, maintenance and operation of electrical systems and general personal safety are outside the scope of this document. General guidance for lightning protection of equipment is provided in relevant clauses of this document. This document is intended to be used: • for verification of the design of new nuclear power plants, • for demonstrating the adequacy and impact of major modifications of electrical power systems in operating nuclear power plants, and • where there is a requirement to assess and establish operating limits and constraints for existing plants. Pertinent parts of this document can be used as guidance for decommissioning stages.

  • Standard
    60 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 62954:2021(Main)
Nuclear power plants - Control rooms - Requirements for emergency response facilities
SIST EN IEC 62954:2021

This document presents the requirements for the on-site emergency response facilities (referred to hereinafter as the “ERF”) which are to be used in case of incidents or accidents occurring on the associated Nuclear Power Plant (NPP). The ERF consists of the Emergency Response Centre (ERC), the Technical Support Centre (TSC) and the Operational Support Centre (OSC), as shown in Figure 1. It establishes requirements for the ERF features and ERF I&C equipment to: • coordinate on-site operational efforts with respect to safety and radioprotection; • optimize the design in terms of environment control, lighting, power supplies and access control of the ERF; • enhance the identification and resolution of potential conflicts between the traditional operational means and emergency means (MCR/SCR and ERF, operating staff and emergency teams, operational procedures and emergency procedures); • aid the identification and the enhancement of the potential synergies between the traditional operational means and emergency means. This document is intended for application to new nuclear power plants whose conceptual design is initiated after the publication of this document, but it may also be used for designing and implementing ERF in existing nuclear power plants or in any other nuclear facility. Detailed equipment design is outside the scope of this document. This document does not define the situations (reactor plant conditions, hazards and magnitudes of hazards) leading to mobilisation of emergency response teams and activation / use of the ERF. These aspects are usually addressed in the NPP Emergency Plan. However, the need for consistency of the ERF design and operation with the NPP Emergency Plan is within scope.

  • Standard
    29 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC/IEEE 62582-6:2021(Main)
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 6: Insulation resistance
SIST EN IEC/IEEE 62582-6:2021

This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control cables using insulation resistance measurements in the detail necessary to produce accurate and reproducible results during simulated accident conditions. It includes the requirements for the measurement system and measurement procedure, and the reporting of the measurement results. NOTE Measurement of insulation resistance during simulated accident conditions with the aim of determining the lowest value during the accident in order to assess cable performance involves special requirements given in this document. Methods for measurement under stable (non-accident) conditions are available in other international standards, e.g. IEC 62631-3-3. The different parts of the IEC/IEEE 62582 series are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582- 1 includes requirements for the application of the other parts of the IEC/IEEE 62582 series and some elements which are common to all methods. Information on the role of condition monitoring in qualification of equipment important to safety is found in IEC/IEEE 60780-323.

  • Standard
    27 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 61226:2021(Main)
Nuclear power plants - Instrumentation, control and electrical power systems important to safety - Categorization of functions and classification of systems
SIST EN IEC 61226:2021

This document establishes, for nuclear power plants2, a method of assignment of the functions specified for the plant into categories according to their importance to safety. Subsequent classification of the I&C and electrical power systems performing or supporting these functions, based on the assigned category, then determines relevant design criteria. The design criteria, when applied, ensure the achievement of each function in accordance to its importance to safety. In this document, the criteria are those of functionality, reliability, performance, environmental qualification (e.g. seismic) and quality assurance (QA). This document is applicable to: - the functions important to safety that are performed by I&C systems and supported by electrical power systems (categorization of I&C functions), - the I&C systems that enable those functions to be implemented (classification of I&C systems), - the electrical power systems that support those functions (classification of electrical power systems). The systems under consideration provide automated protection, closed or open loop control, information to the operating staff, and electrical power supply to systems. These systems keep the NPP conditions inside the safe operating envelope and provide automatic actions, or enable manual actions, that prevent or mitigate accidents, or that prevent or minimize radioactive releases to the site or wider environment. The I&C and electrical power systems that fulfil these roles safeguard the health and safety of the NPP operators and the public. This document follows the general principles given in IAEA Safety Requirement SSR-2/1 and Safety Guides SSG-30, SSG-34 and SSG-39, and it defines a structured method of applying the guidance contained in those codes and standards to the I&C and electrical power systems that perform functions important to safety in a NPP. This document is read in association with the IAEA guides together with IEC 61513 and IEC 63046 in implementing the requirements of the IEC 61508 series. The overall classification scheme of structures, systems and components for NPPs can be summarized as follows by Figure 1.

  • Standard
    43 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 63046:2021(Main)
Nuclear power plants - Electrical power system - General requirements
SIST EN IEC 63046:2021

See the scope of IEC 63046:2020. Adoption of IEC 63046:2020 is to be done without modification.

  • Standard
    91 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC/IEEE 60980-344:2021(Main)
Nuclear facilities - Equipment important to safety - Seismic qualification
SIST EN IEC/IEEE 60980-344:2021

See the scope of IEC/IEEE 60980-344:2020. Adoption of IEC/IEEE 60980-344:2020is to be done without modification.

  • Standard
    85 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 62566-2:2020(Main)
Nuclear power plants - Instrumentation and control systems important to safety - Development of HDL-programmed integrated circuits - Part 2: HDL-programmed integrated circuits for systems performing category B or C functions
SIST EN IEC 62566-2:2021

See the scope of IEC 62566-2:2020. Adoption of IEC 62566-2:2020 is to be done without modification.

  • Standard
    61 pages
    English language
    sale 10% off
    e-Library read for
    1 day
CLC
EN IEC 62003:2020(Main)
Nuclear power plants - Instrumentation, control and electrical power systems - Requirements for electromagnetic compatibility testing
SIST EN IEC 62003:2020

IEC 62003:2020 establishes requirements for electromagnetic compatibility testing of instrumentation, control, and electrical equipment supplied for use in systems important to safety at nuclear power plants and other nuclear facilities. The document lists the applicable IEC standards (principally the IEC 61000 series) which define the general test methods, and provides the necessary application-specific parameters and criteria to ensure that nuclear safety requirements are met. This second edition cancels and replaces the first edition published in 2009. This edition includes the following significant technical changes with respect to the previous edition: a) title modified. b) expand the scope to encompass Electromagnetic Magnetic Compatibility (EMC) considerations for electrical equipment. c) provide guidance for addressing the use of wireless technology. d) enhance the description of the electromagnetic environment to provide clarification when selecting custom test levels or for test exemptions. e) include example information to be contained within an EMC test plan. f) provide guidance for characterization of the electromagnetic environment at the point of installation within a nuclear facility.

  • Standard
    42 pages
    English language
    sale 10% off
    e-Library read for
    1 day