EN IEC/IEEE 60980-344:2021

Nuclear facilities - Equipment important to safety - Seismic qualification

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

Kerntechnische Anlagen - Sicherheitstechnisch wichtige Geräte - Seismische Qualifizierung

Installations nucléaires - Equipements importants pour la sûreté - Qualification sismique

Jedrski objekti - Oprema, pomembna za varnost - Seizmična (potresna) kvalifikacija (IEC/IEEE 60980-344:2020)

General Information

• Status: Published
• Publication Date: 22-Apr-2021
• ICS: 27.120.10 - Reactor engineering
• 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: 23-Apr-2021
• Due Date: 13-May-2023
• Completion Date: 23-Apr-2021
• Ref Project: SIST EN IEC/IEEE 60980-344:2021 - Nuclear facilities - Equipment important to safety - Seismic qualification (IEC/IEEE 60980-344:2020)

Overview

EN IEC/IEEE 60980-344:2021 is the Slovene adoption of IEC/IEEE 60980-344:2020, titled "Nuclear facilities - Equipment important to safety - Seismic qualification." Endorsed as EN IEC/IEEE 60980-344:2021 and adopted by SIST without modification, the standard provides internationally harmonized guidance for demonstrating that safety‑important electrical, electronic and electromechanical equipment in nuclear facilities will perform under seismic loading.

What this standard covers

• Seismic qualification methods for equipment important to safety, including testing, analysis and combined test/analysis approaches.
• Treatment of earthquake environment and equipment response (response spectrum, time‑history, PSD functions).
• Consideration of damping, mounting, interfaces and adverse interactions between equipment and supporting structures.
• Ageing effects (thermal, radiation, vibration, corrosion) and their impact on seismic capability.
• Detailed testing guidance: proof/generic testing, fragility testing, component and assembly testing, multi‑axis and modal tests.
• Qualification by similarity, extrapolation and documentation requirements including the seismic qualification report.

Key technical topics and requirements

• Seismic input specification: use of response spectra, time histories and PSD to simulate earthquake motions appropriate for nuclear facilities.
• Test methods: single‑frequency, multiple‑frequency, multi‑axis shaker testing, shock testing and modal testing techniques for capturing realistic equipment response.
• Analysis methods: static, dynamic and nonlinear analysis approaches to predict seismic behaviour when testing is impractical.
• Acceptance criteria and monitoring: defining pass/fail criteria, instrumentation during tests, and post‑test inspections or refurbishment.
• Ageing and environmental considerations: specification of equipment ageing state during qualification to ensure representative performance under seismic events.
• Documentation: comprehensive seismic qualification reports and traceable records of test and analysis results.

Practical applications and users

This standard is intended for:

• Nuclear plant designers and safety engineers conducting seismic qualification of safety‑related equipment.
• Equipment manufacturers and test laboratories that perform seismic testing or supply qualified components.
• Regulatory bodies, plant operators and quality assurance personnel assessing compliance and safety demonstrations.
• Consultants performing seismic analyses, fragility studies or qualification by similarity.

Related standards

• IEC/IEEE 60780-323 (nuclear electrical equipment qualification)
• Relevant IEC 60068 environmental test series (EN IEC 60068‑2‑6, EN 60068‑2‑47, etc.) - referenced for harmonized environmental test methods.

Keywords: seismic qualification, nuclear facilities, equipment important to safety, IEC/IEEE 60980-344, seismic testing, response spectrum, modal testing, ageing, qualification by similarity.

Standards Content (Sample)

SLOVENSKI STANDARD
01-junij-2021
Jedrski objekti - Oprema, pomembna za varnost - Seizmična (potresna)
kvalifikacija (IEC/IEEE 60980-344:2020)
Nuclear facilities - Equipment important to safety - Seismic qualification (IEC/IEEE 60980
-344:2020)
Kerntechnische Anlagen - Gerät mit sicherheitstechnischer Bedeutung - Seismische
Qualifizierung (IEC/IEEE 60980-344:2020)
Installations nucléaires - Equipements importants pour la sûreté - Qualification sismique
(IEC/IEEE 60980-344:2020)
Ta slovenski standard je istoveten z: EN IEC/IEEE 60980-344:2021
ICS:
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
91.120.25 Zaščita pred potresi in Seismic and vibration
vibracijami protection
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EUROPEAN STANDARD EN IEC/IEEE 60980-344

NORME EUROPÉENNE
EUROPÄISCHE NORM
April 2021
ICS 27.120.10; 27.120.20
English Version
Nuclear facilities - Equipment important to safety - Seismic
qualification
(IEC/IEEE 60980-344:2020)
Installations nucléaires - Equipements importants pour la Kerntechnische Anlagen - Gerät mit sicherheitstechnischer
sûreté - Qualification sismique Bedeutung - Seismische Qualifizierung
(IEC/IEEE 60980-344:2020) (IEC/IEEE 60980-344:2020)
This European Standard was approved by CENELEC on 2021-04-19. 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
© 2021 CENELEC All rights of exploitation in any form and by any means reserved worldwide for CENELEC Members.
Ref. No. EN IEC/IEEE 60980-344:2021 E

European foreword
The text of document 45A/1323/FDIS, future edition 1 of IEC/IEEE 60980-344, prepared by SC 45A
"Instrumentation, control and electrical power systems of nuclear facilities" of IEC/TC 45 "Nuclear
instrumentation" was submitted to the IEC-CENELEC parallel vote and approved by CENELEC as
The following dates are fixed:
•
latest date by which the document has to be implemented at national (dop) 2022-01-19
level by publication of an identical national standard or by endorsement
• latest date by which the national standards conflicting with the (dow) 2024-04-19
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 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/IEEE 60980-344:2020 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 60068-3-3 NOTE Harmonized as EN IEC 60068-3-3
IEC 60068-2-81 NOTE Harmonized as EN 60068-2-81
IEC 60068-2-47 NOTE Harmonized as EN 60068-2-47
IEC 60068-2-57 NOTE Harmonized as EN 60068-2-57
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 Where 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
- Environmental testing - Part 2-6: Tests - -
IEC 60068-2-6 EN 60068-2-6
Test Fc: Vibration (sinusoidal)
- Nuclear facilities - Electrical equipment -
IEC/IEEE 60780- EN 60780-323
important to safety - Qualification
IEC/IEEE 60980-344 ®
Edition 1.0 2020-10
INTERNATIONAL
STANDARD
Nuclear facilities – Equipment important to safety – Seismic qualification

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
ICS 27.120.10; 27.120.20 ISBN 978-2-8322-8482-7

– 2 – IEC/IEEE 60980-344:2020
 IEC/IEEE 2020
CONTENTS
FOREWORD . 6
INTRODUCTION . 8
1 Scope . 11
2 Normative references . 11
3 Terms and definitions . 11
4 Abbreviated terms . 19
5 General discussion of earthquake environment and equipment response. 20
5.1 General . 20
5.2 Earthquake environment . 20
5.3 Equipment on foundations . 20
5.4 Equipment on structures . 20
5.5 Interfaces and adverse interactions. 21
5.6 Simulating vibration induced by an earthquake . 21
5.6.1 General . 21
5.6.2 Response spectrum . 21
5.6.3 Time history . 22
5.6.4 PSD function . 22
5.7 Damping . 22
5.7.1 General . 22
5.7.2 Measurement of damping . 23
5.8 Application of damping . 23
5.8.1 General . 23
5.8.2 Application of damping in testing . 23
5.8.3 Application of damping in analysis . 24
6 Seismic qualification requirements . 24
6.1 General . 24
6.2 Specification of equipment to be qualified . 25
6.3 Specification of ageing condition . 25
6.4 Specification of seismic requirements . 25
6.5 Specification of acceptance criteria . 25
7 Seismic qualification approach . 26
7.1 Safety function . 26
7.2 Seismic qualification methods . 26
8 Ageing . 27
8.1 General . 27
8.2 Thermal ageing . 28
8.3 Radiation ageing . 28
8.4 Material degradation and corrosion . 28
8.5 Mechanical or electrical cycle ageing . 28
8.6 Vibration ageing . 28
8.6.1 General . 28
8.6.2 Ageing from non-seismic vibration conditions . 29
8.6.3 Hydrodynamic loads . 29
8.6.4 Seismic ageing (OBE/S1) . 29
9 Testing . 29
9.1 General . 29

IEC/IEEE 60980-344:2020 – 3 –
 IEC/IEEE 2020
9.1.1 Test programme . 29
9.1.2 Mounting . 31
9.1.3 Monitoring . 31
9.1.4 Loading . 31
9.1.5 Refurbishment . 32
9.1.6 Exploratory tests . 32
9.1.7 Seismic ageing (OBE/S1) . 34
9.2 Proof and generic testing . 34
9.3 Fragility testing . 35
9.4 Component testing . 35
9.5 Assembly testing . 35
9.5.1 General . 35
9.6 Test methods . 36
9.6.1 General . 36
9.6.2 Single-frequency test . 37
9.6.3 Multiple-frequency tests . 40
9.6.4 Other tests . 45
9.6.5 Test duration and low-cycle fatigue potential . 45
9.6.6 Multi-axis tests . 45
9.6.7 Line-mounted equipment . 47
9.6.8 Additional tests . 48
9.7 Test documentation . 48
10 Qualification by similarity . 48
10.1 General . 48
10.2 Excitation . 48
10.3 Physical systems . 48
10.4 Safety function . 49
11 Analysis . 49
11.1 General . 49
11.2 Seismic analysis methods . 50
11.2.1 General . 50
11.2.2 Static analysis . 51
11.2.3 Static coefficient analysis . 51
11.2.4 Dynamic analysis . 51
11.3 Nonlinear equipment response . 52
11.4 Other dynamic loads . 52
11.5 Seismic analysis results . 52
11.6 Documentation of analysis . 53
12 Combined analysis and testing . 53
12.1 General . 53
12.2 Modal testing . 53
12.2.1 General . 53
12.2.2 Normal-mode method . 53
12.2.3 Transfer-function method . 54
12.2.4 Analytical methods utilizing test data . 54
12.2.5 Qualification . 54
12.3 Extrapolation for similar equipment . 54
12.3.1 General . 54
12.3.2 Test method . 54

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 IEC/IEEE 2020
12.3.3 Analysis . 55
12.4 Shock testing . 55
12.5 Extrapolation for multi-cabinet assemblies . 55
12.6 Other test/analysis . 55
13 Documentation . 56
13.1 General . 56
13.2 Seismic qualification report . 56
13.2.1 General . 56
13.2.2 Analysis . 56
13.2.3 Testing . 56
13.2.4 Combined analysis and testing or similarity . 57
Annex A (normative) Experience-based seismic qualification . 58
A.1 General . 58
A.2 Earthquake experience data . 58
A.2.1 General . 58
A.2.2 Characterization of the earthquake experience motions . 58
A.2.3 Earthquake experience spectrum (EES). 59
A.2.4 Characterization of reference equipment class . 59
A.2.5 Qualification of candidate equipment . 61
A.3 Test experience data . 62
A.3.1 General . 62
A.3.2 Characterization of test experience input motions . 62
A.3.3 Test experience spectra (TES) . 62
A.3.4 Characterization of reference equipment class . 63
A.3.5 Qualification of candidate equipment . 64
A.4 Special considerations . 64
A.4.1 Inherently rugged equipment . 64
A.4.2 Limitations . 65
A.5 Experience-based documentation . 65
A.5.1 General . 65
A.5.2 Reference data . 66
A.5.3 Candidate equipment qualification . 66
Annex B (informative) Measurement of zero period acceleration . 67
Annex C (informative) Frequency content and stationarity . 68
Annex D (informative) Fragility testing . 69
D.1 General . 69
D.2 Excitation motion . 69
D.3 Application of results. 70
D.4 Other considerations . 70
Annex E (informative) Test duration and number of cycles . 72
Annex F (informative) Statistically independent motions . 76
Annex G (informative) Seismic qualification illustrative flowcharts . 77
G.1 General . 77
G.2 Establishment of seismic conditions and acceptance criteria . 77
G.3 Qualification by testing . 77
G.4 Qualification by analysis . 77
G.5 Qualification by combination of analysis and testing . 77
Bibliography . 82

IEC/IEEE 60980-344:2020 – 5 –
 IEC/IEEE 2020
Figure 1 – Sine beat . 39
Figure 2 – Decaying sine . 39
Figure 3 – Random spectrum with superimposed sine beats . 43
Figure 4 – Resonant amplification versus cycles per beat . 44
Figure E.1 – Fractional cycles to obtain one equipment maximum peak cycle . 73
Figure E.2 – Equivalent peak-stress cycles induced by stationary random motion . 74
Figure E.3 – Equivalent peak-stress cycles induced by stationary random motion to 20 Hz . 74
Figure G.1 – Seismic qualification flowchart . 78
Figure G.2 – Seismic qualification test flowchart . 79
Figure G.3 – Seismic qualification analysis flowchart . 80
Figure G.4 – Seismic qualification analysis and test flowchart . 81

Table A.1 – EES reduction factor based on number of independent items . 60

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INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR FACILITIES –
EQUIPMENT IMPORTANT TO SAFETY –
SEISMIC QUALIFICATION
FOREWORD
1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising
all national electrotechnical committees (IEC National Committees). The object of IEC is to promote international
co-operation on all questions concerning standardization in the electrical and electronic fields. To this end and
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IEEE Standards documents are developed within IEEE Societies and Standards Coordinating Committees of the
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Use of IEEE Standards documents is wholly voluntary. IEEE documents are made available for use subject to
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9) Attention is drawn to the possibility that implementation of this IEC/IEEE Publication may require use of material
covered by patent rights. By publication of this standard, no position is taken with respect to the existence or
validity of any patent rights in connection therewith. IEC or IEEE shall not be held responsible for identifying
Essential Patent Claims for which a license may be required, for conducting inquiries into the legal validity or
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Users of this standard are expressly advised that determination of the validity of any patent rights, and the risk
of infringement of such rights, is entirely their own responsibility.

IEC/IEEE 60980-344:2020 – 7 –
 IEC/IEEE 2020
International Standard IEC/IEEE 60980-344 has been prepared by subcommittee 45A:
Instrumentation, control and electrical power systems of nuclear facilities, of IEC technical
committee 45: Nuclear instrumentation, in cooperation with Nuclear Power Engineering
Committee of the IEEE, under the IEC/IEEE Dual Logo Agreement.
It is published as an IEC/IEEE dual logo standard.
This new edition cancels and replaces the first edition of IEC 60980, published in 1989, and
TM
constitutes a technical revision. It also supersedes IEEE Std 344 -2013.
The text of this standard is based on the following IEC documents:
FDIS Report on voting
45A/1323/FDIS 45A/1334/RVD
Full information on the voting for the approval of this standard can be found in the report on
voting indicated in the above table.
International standards are drafted in accordance with the rules given in the ISO/IEC Directives,
Part 2.
The IEC Technical Committee and IEEE Technical Committee have decided that the contents
of this publication will remain unchanged until the stability date indicated on the IEC web site
under "http://webstore.iec.ch" in the data related to the specific publication. At this date, the
publication will be
• reconfirmed,
• withdrawn,
• replaced by a revised edition, or
• amended.
– 8 – IEC/IEEE 60980-344:2020
 IEC/IEEE 2020
INTRODUCTION
a) Technical background, main issues and organisation of the Standard
This standard is applicable to electrical equipment important to safety and its interfaces that
are necessary to perform a safety function, or whose failure could adversely affect the safety
functions of other equipment.
Electrical equipment in nuclear facilities shall meet its safety function requirements throughout
its installed life. This is accomplished by a thorough programme of quality assurance, design
control, quality control, qualification, production, transportation, storage, installation,
maintenance, periodic testing, and surveillance. This IEC/IEEE standard specifically focuses
on seismic qualification. This standard shall be used in conjunction with IEC/IEEE 60780-323.
Other aspects, relating to quality assurance, reliability, selection and use of electronic devices,
design and modification of digital systems including Verification and Validation (V&V) activities
are not part of this standard.
Industry research in the area of equipment qualification and decades of its application have
greatly benefited this standard. Future activities of the working group to update this standard
will consider the following:
• Experience and knowledge gained by using condition monitoring techniques,
• Knowledge gained on ageing mechanisms and kinetics,
• Improvement in the use of methods (test and analysis) described throughout the standard,
• Improvement of computation tools and modalities of use.
It is intended that the Standard be used by operators of NPPs (utilities), systems evaluators,
equipment manufacturers, test facilities, qualification laboratories and by licensors.
b) Situation of the current standard in the structure of the IEC SC 45A standard series
IEC 61513 and IEC 63046 are first level IEC SC 45A documents that give guidance applicable
to Instrumentation and Control (I&C) system and electrical power systems (at system level).
They are completed by guidance relative to functional classification (IEC 61226).
These documents are supplemented by second level IEC SC 45A documents. Second level IEC
SC 45A documents give guidance on hardware design (IEC 60987), software (IEC 60880 and
IEC 62138), selection and use of HDL programmed integrated circuits (IEC 62566),
requirements in order to reduce the possibility and limit the impact of common cause failure of
category A functions (IEC 62340), qualification (IEC/IEEE 60780-323, IEC/IEEE 60980-344 and
IEC 62003), control room design (IEC 62342) and cybersecurity (IEC 62645).
IEC/IEEE 60980-344 is a second level IEC SC 45A document which focuses on seismic
qualification of electrical equipment important to safety.
For more details on the structure of the IEC SC 45A standard series, see item d) of this
introduction.
IEC/IEEE 60980-344:2020 – 9 –
 IEC/IEEE 2020
c) Recommendations and limitations regarding the application of this standard
This dual logo standard applies to all electrical equipment important to safety in accordance
with IAEA terminology. If using IEEE standards, this standard applies to systems, structures,
and components classified as safety or safety-related. If using the IEC 61226 and IEC 61513
classification guidance, this standard applies to all Class 1, 2 and 3 equipment. This document
shall only be applied in accordance with the single selected classification scheme, either IEC
or IEEE.
To ensure that the Standard will continue to be relevant in future years, the emphasis has been
placed on issues of principle, rather than specific technologies.
d) Description of the structure of the IEC SC 45A standard series and relationships with
other IEC documents and other bodies documents (IAEA, ISO)
The top-level documents of the IEC SC 45A standard series are IEC 61513 and IEC 63046.
IEC 61513 provides general requirements for I&C systems and equipment that are used to
perform functions important to safety in NPPs. IEC 63046 provides general requirements for
electrical power systems of NPPs; it covers power supply systems including the supply systems
of the I&C systems. IEC 61513 and IEC 63046 are to be considered in conjunction and at the
same level. IEC 61513 and IEC 63046 structure the IEC SC 45A standard series and shape a
complete framework establishing general requirements for instrumentation, control and
electrical systems for nuclear power plants.
IEC 61513 and IEC 63046 refer directly to other IEC SC 45A standards for general topics
related to categorization of functions and classification of systems, qualification, separation,
defence against common cause failure, control room design, electromagnetic compatibility,
cybersecurity, software and hardware aspects for programmable digital systems, coordination
of safety and security requirements and management of ageing. The standards referenced
directly at this second level should be considered together with IEC 61513 and IEC 63046 as a
consistent document set.
At a third level, IEC SC 45A standards not directly referenced by IEC 61513 or by IEC 63046
are standards related to specific equipment, technical methods, or specific activities. Usually
these documents, which make reference to second-level documents for general topics, can be
used on their own.
A fourth level extending the IEC SC 45 standard series, corresponds to the Technical Reports
which are not normative.
The IEC SC 45A standards series consistently implements and details the safety and security
principles and basic aspects provided in the relevant IAEA safety standards and in the relevant
documents of the IAEA nuclear security series (NSS). In particular this includes the IAEA
requirements SSR-2/1, establishing safety requirements related to the design of nuclear power
plants (NPPs), the IAEA safety guide SSG-30 dealing with the safety classification of structures,
systems and components in NPPs, the IAEA safety guide SSG-39 dealing with the design of
instrumentation and control systems for NPPs, the IAEA safety guide SSG-34 dealing with the
design of electrical power systems for NPPs and the implementing guide NSS 17 for computer
security at nuclear facilities. The safety and security terminology and definitions used by
SC 45A standards are consistent with those used by the IAEA.

– 10 – IEC/IEEE 60980-344:2020
 IEC/IEEE 2020
IEC 61513 and IEC 63046 have adopted a presentation format similar to the basic safety
publication IEC 61508 with an overall life-cycle framework and a system life-cycle framework.
Regarding nuclear safety, IEC 61513 and IEC 63046 provide the interpretation of the general
requirements of IEC 61508-1, IEC 61508-2 and IEC 61508-4, for the nuclear application sector.
In this framework IEC 60880, IEC 62138 and IEC 62566 correspond to IEC 61508-3 for the
nuclear application sector. IEC 61513 and IEC 63046 refer to ISO as well as to IAEA GS-R part
2 and IAEA GS-G-3.1 and IAEA GS-G-3.5 for topics related to quality assurance (QA). At level
2, regarding nuclear security, IEC 62645 is the entry document for the IEC/SC 45A security
standards. It builds upon the valid high level principles and main concepts of the generic
security standards, in particular ISO/IEC 27001 and ISO/IEC 27002; it adapts them and
completes them to fit the nuclear context and coordinates with the IEC 62443 series. At level
2, IEC 60964 is the entry document for the IEC/SC 45A control rooms standards and IEC 62342
is the entry document for the ageing management standards.
NOTE 1 It is assumed that for the design of I&C systems in NPPs that implement conventional safety functions (e.g.
to address worker safety, asset protection, chemical hazards, process energy hazards) international or national
standards would be applied.
NOTE 2 IEC/SC 45A domain was extended in 2013 to cover electrical systems. In 2014 and 2015 discussions were
held in IEC/SC 45A to decide how and where general requirements for the design of electrical systems were to be
considered. IEC/SC 45A experts recommended that an independent standard be developed at the same level as
IEC 61513 to establish general requirements for electrical systems. Project IEC 63046 is now launched to cover this
objective. When IEC 63046 is published, this Note 2 of the introduction of IEC/SC 45A standards will be suppressed.

IEC/IEEE 60980-344:2020 – 11 –
 IEC/IEEE 2020
NUCLEAR FACILITIES –
EQUIPMENT IMPORTANT TO SAFETY –
SEISMIC QUALIFICATION
1 Scope
This International Standard describes methods for establishing seismic qualification procedures
that will yield quantitative data to demonstrate that the equipment can meet its performance
requirements. This document is applicable to electrical, mechanical, instrumentation and control
equipment/components that are used in nuclear facilities. This document provides methods and
documentation requirements for seismic qualification of equipment to verify the equipment’s
ability to perform its specified performance requirements during and/or after specified seismic
demands. This document does not specify seismic demand or performance requirements. Other
aspects, relating to quality assurance, selection of equipment, and design and modification of
systems, are not part of this document. As seismic qualification is only a part of equipment
qualification, this document is used in conjunction with IEC/IEEE 60780-323.
The seismic qualification demonstrates equipment’s ability to perform its safety function(s)
during and/or after the time it is subjected to the forces resulting from at least one safe shutdown
earthquake (SSE/S2). This ability is demonstrated by taking into account, prior to the SSE/S2,
the ageing of equipment and the postulated occurrences of a given number of lower intensity
operating basis earthquake (OBE/S1). Ageing phenomena to be considered, if specified in the
design specification, are those which could increase the vulnerability of equipment to vibrations
caused by an SSE/S2.
2 Normative references
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.
IEC 60068-2-6, Environmental testing – Part 2-6: Tests – Test Fc: Vibration (sinusoidal)
IEC/IEEE 60780-323, Nuclear facilities – Electrical equipment important to safety –
1 2
Qualification ,
TM
IEEE Std 382 , IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power
Generating Stations
3 Terms and definitions
The terminology and definitions used in this document are consistent with IAEA Safety
Glossary .
____________
IEEE publications are available from The Institute of Electrical and Electronics Engineers
(http://standards.ieee.org/).
The IEEE standards or products referred to in this clause are trademarks of The Institute of Electrical and
Electronics Engineers, Inc.
IAEA safety glossary is available at https://www.iaea.org/publications/11098/iaea-safety-glossary-2018-edition

– 12 – IEC/IEEE 60980-344:2020
 IEC/IEEE 2020
For the purposes of this document, the following terms and definitions apply.
ISO, IEC, and IEEE maintain terminological databases for us
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