EN 61513:2013
(Main)Nuclear power plants - Instrumentation and control important to safety - General requirements for systems
Nuclear power plants - Instrumentation and control important to safety - General requirements for systems
Instrumentation and control (I&C) systems important to safety may be implemented using conventional hard-wired equipment, computer-based (CB) equipment or by using a combination of both types of equipment (see Note 1). IEC 61513:2011 provides requirements and recommendations for the overall I&C architecture which may contain either or both technologies. The main technical changes with regard to the previous edition are as follows: - alignment with the latest revisions of IAEA documents; - alignment with new editions of IEC 60880, IEC 61226, IEC 62138, IEC 62340 and IEC 60987; - alignment with significant advances of software engineering techniques; - integration of requirements for staff training.
Kernkraftwerke - Leittechnik für Systeme mit sicherheitstechnischer Bedeutung - Allgemeine Systemanforderungen
Centrales nucléaires de puissance - Instrumentation et contrôle-commande importants pour la sûreté - Exigences générales pour les systèmes
Les systèmes d'I&C importants pour la sûreté peuvent être réalisés à l'aide de composants traditionnels câblés, de composants informatiques ou d'une combinaison des deux. La CEI 61513:2011 fait état des exigences et des recommandations relatives à l'architecture d'ensemble de l'I&C incluant l'une ou l'autre de ces technologies ou les deux. Les principaux changements techniques par rapport à l'édition précédente sont les suivants: - mise en cohérence avec les nouvelles éditions des documents de l'AIEA; - prise en compte des dernières éditions des normes CEI 60880, CEI 61226, CEI 62138, CEI 62340 et CEI 60987; - prise en compte de progrès significatifs des techniques de génie logiciel; - intégration des exigences relatives à la formation du personnel.
Jedrske elektrarne - Instrumenti in krmilje, pomembni za varnost - Splošne zahteve za sisteme
Merilna in nadzorna oprema za zagotavljanje varnosti se lahko načrtuje z uporabo konvencionalne fiksno pritrjene opreme, računalniške opreme (CB) ali kombinacije obeh vrst opreme (glej opombo 1). Ta mednarodni standard zagotavlja zahteve in priporočila (glej opombo 2) za celotno arhitekturo merilne in nadzorne opreme, ki lahko vključuje eno ali obe tehnologiji. Ta standard poudarja tudi potrebo po celovitih in natančnih zahtevah, izpeljanih iz varnostnih ciljev elektrarne, kot predpogoj za določitev celovitih zahtev za celotno arhitekturo merilne in nadzorne opreme in tako tudi posameznih delov merilne in nadzorne opreme za zagotavljanje varnosti. Ta standard vpeljuje koncept življenjskega cikla glede varnosti za celotno arhitekturo merilne in nadzorne opreme ter življenjski cikel glede varnosti za njene posamezne dele. Tako poudari razmerja med varnostnimi cilji jedrske elektrarne in zahtevami za celotno arhitekturo merilne in nadzorne opreme za zagotavljanje varnosti ter razmerja med celotno arhitekturo merilne in nadzorne opreme in zahtevami njenih posameznih delov za zagotavljanje varnosti. Življenjski cikli, predstavljeni in upoštevani v tem standardu, niso edini možni; drugi življenjski cikli so možni, če so izpolnjeni cilji, navedeni v tem standardu.
OPOMBA 1: Merilna in nadzorna oprema lahko uporablja tudi elektronske module, ki temeljijo na kompleksnih elektronskih komponentah, kot so integrirana vezja za določen namen (ASIC) in programirljivo polje vrat (FPGA). Glede na področje uporabe in delovanje teh komponent jih je mogoče obravnavati v skladu s smernicami za konvencionalno elektronsko opremo ali podobno kot računalniško opremo. Večina smernic za računalniško opremo se uporablja tudi za načrtovanje opreme s kompleksnimi elektronskimi komponentami, vključno npr. s koncepti ponovne uporabe predhodnih načrtov, in za ugotavljanje napak v načrtovanju programske ali kompleksne strojne opreme.
OPOMBA 2: Izraz »zahteva« je uporabljen kot skupen izraz za oboje – zahteve in priporočila. Do razlikovanja pride pri specifičnih določilih, kjer so zahteve izražene s strukturo »je treba«, priporočila pa z »naj bi«.
General Information
Standards Content (Sample)
SLOVENSKI STANDARD
01-junij-2013
Jedrske elektrarne - Instrumenti in krmilje, pomembni za varnost - Splošne zahteve
za sisteme
Nuclear power plants - Instrumentation and control important to safety - General
requirement for systems
Kernkraftwerke - Leittechnik für Systeme mit sicherheitstechnischer Bedeutung -
Allgemeine Systemanforderungen
Centrales nucléaires de puissance - Instrumentation et contrôle commande importants
pour la sûreté - Exigences générales pour les systèmes
Ta slovenski standard je istoveten z: EN 61513:2013
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 61513
NORME EUROPÉENNE
February 2013
EUROPÄISCHE NORM
ICS 27.120.20
English version
Nuclear power plants -
Instrumentation and control important to safety -
General requirements for systems
(IEC 61513:2011)
Centrales nucléaires de puissance - Kernkraftwerke -
Instrumentation et contrôle-commande Leittechnik für Systeme mit
importants pour la sûreté - sicherheitstechnischer Bedeutung -
Exigences générales pour les systèmes Allgemeine Systemanforderungen
(CEI 61513:2011) (IEC 61513:2011)
This European Standard was approved by CENELEC on 2013-01-14. 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, Former Yugoslav Republic of Macedonia, France, Germany,
Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, Norway, Poland,
Portugal, Romania, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the United Kingdom.
CENELEC
European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung
Management Centre: Avenue Marnix 17, B - 1000 Brussels
© 2013 CENELEC - All rights of exploitation in any form and by any means reserved worldwide for CENELEC members.
Ref. No. EN 61513:2013 E
Foreword
This document (EN 61513:2013) consists of the text of IEC 61513:2011 prepared by SC 45A
"Instrumentation and control of nuclear facilities" of IEC/TC 45 "Nuclear instrumentation".
The following dates are fixed:
(dop) 2014-01-14
• latest date by which this document has to be
implemented
at national level by publication of an identical
national standard or by endorsement
(dow) 2016-01-14
• latest date by which the national standards conflicting
with this document have to be withdrawn
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CENELEC [and/or CEN] 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 measures in the subject-matter
covered by this standard.
Endorsement notice
The text of the International Standard IEC 61513:2011 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 61508-1:2010 NOTE Harmonized as EN 61508-1:2010 (not modified).
IEC 61508-3:2010 NOTE Harmonized as EN 61508-3:2010 (not modified).
IEC 61069-1:1991 NOTE Harmonized as EN 61069-1:1993 (not modified).
IEC 62381 NOTE Harmonized as EN 62381.
IEC 61000-6-2 NOTE Harmonized as EN 61000-6-2.
IEC 61000-6-4 NOTE Harmonized as EN 61000-6-4.
ISO 9000:2005 NOTE Harmonized as EN ISO 9000:2005 (not modified).
ISO 8402:1994 NOTE Harmonized as EN ISO 8402:1995 (not modified).
- 3 - EN 61513:2013
Annex ZA
(normative)
Normative references to international publications
with their corresponding European publications
The following documents, in whole or in part, are normatively referenced in this document and are
indispensable for its application. For dated references, only the edition cited applies. For undated
references, the latest edition of the referenced document (including any amendments) applies.
NOTE When an international publication has been modified by common modifications, indicated by (mod), the relevant EN/HD
applies.
Publication Year Title EN/HD Year
IEC 60671 - Nuclear power plants - Instrumentation EN 60671 -
and control systems important to safety -
Surveillance testing
IEC 60709 - Nuclear power plants - Instrumentation EN 60709 -
and control systems important to safety -
Separation
IEC 60780 - Nuclear power plants - Electrical equipment EN 60780 -
of the safety system - Qualification
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 60964 2009 Nuclear power plants - Control rooms - EN 60964 2010
Design
IEC 60965 - Nuclear power plants - Control rooms - EN 60965 -
Supplementary control points for reactor
shutdown without access to the main control
room
IEC 60980 - Recommended practices for seismic - -
qualification of electrical equipment of the
safety system for nuclear generating stations
IEC 60987 2007 Nuclear power plants - Instrumentation EN 60987 2009
(mod) and control important to safety -
Hardware design requirements
for computer-based systems
IEC 61000-4-1 - Electromagnetic compatibility (EMC) - EN 61000-4-1 -
Part 4-1: Testing and measurement
techniques - Overview
of IEC 61000-4 series
IEC 61000-4-2 - Electromagnetic compatibility (EMC) - EN 61000-4-2 -
Part 4-2: Testing and measurement
techniques - Electrostatic discharge
immunity test
IEC 61000-4-3 - Electromagnetic compatibility (EMC) - EN 61000-4-3 -
Part 4-3: Testing and measurement
techniques - Radiated, radio-frequency,
electromagnetic field immunity test
IEC 61000-4-4 - Electromagnetic compatibility (EMC) - EN 61000-4-4 -
Part 4-4: Testing and measurement
techniques - Electrical fast transient/burst
immunity test
Publication Year Title EN/HD Year
IEC 61000-4-5 - Electromagnetic compatibility (EMC) - EN 61000-4-5 -
Part 4-5: Testing and measurement
techniques - Surge immunity test
IEC 61000-4-6 - Electromagnetic compatibility (EMC) - EN 61000-4-6 -
Part 4-6: Testing and measurement
techniques - Immunity to conducted
disturbances, induced by radio-frequency
fields
IEC 61226 2009 Nuclear power plants - Instrumentation EN 61226 2010
and control important to safety -
Classification of instrumentation
and control functions
IEC 61500 - Nuclear power plants - Instrumentation EN 61500 -
and control important to safety - Data
communication in systems performing
category A functions
IEC 61508-2 2010 Functional safety of EN 61508-2 2010
electrical/electronic/programmable
electronic safety-related systems -
Part 2: Requirements for
electrical/electronic/programmable electronic
safety-related systems
IEC 61508-4 2010 Functional safety of EN 61508-4 2010
electrical/electronic/programmable electronic
safety-related systems -
Part 4: Definitions and abbreviations
IEC 62138 2004 Nuclear power plants - Instrumentation EN 62138 2009
and control important for safety - Software
aspects for computer-based systems
performing category B or C functions
IEC 62340 - Nuclear power plants - Instrumentation EN 62340 -
and control systems important to safety -
Requirements for coping with common
cause failure (CCF)
ISO 9001 2008 Quality management systems - EN ISO 9001 2008
Requirements
IAEA INSAG-10 1996 Defence in depth in nuclear safety - -
IAEA NS-R-1 2000 Safety of nuclear power plants: Design - -
IAEA GS-R-3 2006 The management system for facilities - -
and activities - Safety requirements
IAEA GS-G-3.1 2006 Application for the management system - -
for facilities and activities - Safety Guide
IAEA NS-G-1.3 2002 Instrumentation and control systems - -
important to safety in nuclear power plants
IAEA 75-INSAG-3 1999 Basic safety principles for nuclear power - -
Rev.1 - INSAG 12 plants
IEC 61513 ®
Edition 2.0 2011-08
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Instrumentation and control important to safety –
General requirements for systems
Centrales nucléaires de puissance – Instrumentation et contrôle-commande
importants pour la sûreté – Exigences générales pour les systèmes
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
CODE PRIX XD
ICS 27.120.20 ISBN 978-2-88912-663-7
– 2 – 61513 IEC:2011
CONTENTS
FOREWORD . 5
INTRODUCTION . 7
1 Scope . 9
1.1 General . 9
1.2 Application: new and pre-existing plants . 9
1.3 Framework . 9
2 Normative references . 12
3 Terms and definitions . 13
4 Symbols and abbreviations . 26
5 Overall I&C safety life cycle . 26
5.1 General . 26
5.2 Deriving the I&C requirements from the plant safety design base . 29
5.2.1 General . 29
5.2.2 Review of the functional, performance and independence
requirements . 29
5.2.3 Review of the categorisation requirements . 30
5.2.4 Review of plant constraints . 31
5.3 Output documentation . 32
5.4 Design of the overall I&C architecture and assignment of the I&C functions . 32
5.4.1 General . 32
5.4.2 Design of the I&C architecture . 33
5.4.3 Assignment of functions to systems . 36
5.4.4 Required analysis . 37
5.5 Overall planning . 38
5.5.1 General . 38
5.5.2 Overall quality assurance programs . 38
5.5.3 Overall security plan . 38
5.5.4 Overall I&C integration and commissioning . 39
5.5.5 Overall operation plan . 41
5.5.6 Overall maintenance plan . 42
5.5.7 Planning of training. 42
5.6 Output documentation . 43
5.6.1 General . 43
5.6.2 Architectural design documentation . 43
5.6.3 Functional assignment documentation . 43
6 System safety life cycle . 44
6.1 General . 44
6.2 Requirements .
...
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