IEC 63147:2017

IEC 63147 ®
Edition 1.0 2017-12
™
IEEE Std 497
INTERNATIONAL
STANDARD
Criteria for accident monitoring instrumentation for nuclear power generating
stations
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IEC 63147 ®
Edition 1.0 2017-12
IEEE Std 497™
INTERNATIONAL
STANDARD
Criteria for accident monitoring instrumentation for nuclear power generating

stations
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
ICS 27.120.20 ISBN 978-2-8322-5031-0

IEEE Std 497-2016
Contents
1. Overview . 1
1.1 Scope . 1
1.2 Purpose . 1
1.3 Application . 1
2. Normative references . 2
2.1 Normative references for IEEE domain . 2
2.2 Normative references for IEC domain . 3
3. Definitions . 3
4. Selection criteria . 6
4.1 Type A variables . 6
4.2 Type B variables . 6
4.3 Type C variables . 7
4.4 Type D variables . 7
4.5 Type E variables . 7
4.6 Type F variables . 8
4.7 Documentation of selection criteria . 8
5. Performance criteria . 9
5.1 Range . 9
5.2 Accuracy . 9
5.3 Response time .10
5.4 Required operating time .10
5.5 Reliability .10
5.6 Documentation of performance criteria .10
6. Design criteria .11
6.1 Single failure.11
6.2 Common cause failure .11
6.3 Independence and physical separation .11
6.4 Isolation .12
6.5 Information ambiguity .12
6.6 Power supply .13
6.7 Calibration .13
6.8 Testability .13
6.9 Direct measurement .14
6.10 Control of access .14
6.11 Maintenance and repair .14
6.12 Minimizing measurements .14
6.13 Auxiliary supporting features .14
6.14 Portable instruments .15
6.15 Documentation of design criteria .15
7. Qualification criteria .15
7.1 Type A variables .15
7.2 Type B variables .15
7.3 Type C variables .16
7.4 Type D variables .16
7.5 Type E variables .16
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– ii – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
7.6 Type F variables .16
7.7 Portable instruments .17
7.8 Operating time .17
7.9 Documentation of qualification criteria .17
8. Display criteria .17
8.1 Display characteristics .17
8.2 Trend or rate information .18
8.3 Display identification.18
8.4 Type of monitoring channel display .18
8.5 Display location .18
8.6 Information ambiguity .19
8.7 Recording .19
8.8 Digital display signal validation .19
8.9 Documentation of display criteria .19
9. Quality assurance.19
Annex A (informative) Accident monitoring instrument channel accuracy .20
A.1 Introduction .20
A.2 Accuracy requirement groupings according to usage .20
A.3 Typical accuracy requirements .20
Annex B (informative) Examples of monitoring channel displays.21
Annex C (informative) Operational state diagram .23
Annex D (informative) Bibliography .24
Annex E (informative) IEEE list of participants .25

Published by IEC under license from IEEE. © 2016 IEEE. All rights reserved.

IEEE Std 497-2016
CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION
FOR NUCLEAR POWER GENERATING STATIONS

FOREWORD
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– iv – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
International Standard IEC 61347/IEEE Std 497™-2016 has been processed through IEC
subcommittee 45A: Instrumentation, control and electrical power systems of nuclear
facilities, under the IEC/IEEE Dual Logo Agreement.
The text of this standard is based on the following documents:
IEEE Std FDIS Report on voting
IEEE Std 497™-2016 45A/1167/FDIS 45A/1170/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.
When applied in an IEC / IAEA environment this standard is to be used in conjunction
with IEC TR 63123:2017, Nuclear power plants – Instrumentation, control and electrical
power systems – Guidance for the application of IEC 63147:2017 / IEEE 497-2016 in the
IEC / IAEA framework.
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.
Published by IEC under license from IEEE. © 2016 IEEE. All rights reserved.

IEEE Std 497-2016
IEEE Standard Criteria for Accident
Monitoring Instrumentation for Nuclear
Power Generating Stations
Sponsor
Nuclear Power Engineering Committee
of the
IEEE Power and Energy Society
Approved 15 May 2016
IEEE-SA Standards Board
Published by IEC under license from IEEE. © 2016 IEEE. All rights reserved.

– vi – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
Abstract: Established in this standard are criteria for variable selection, performance, design,
and qualification of accident monitoring instrumentation for anticipated operational, design basis
events and severe accidents.
Keywords: accident monitoring, design criteria, display criteria, IEEE 497™, performance
criteria, selection criteria, severe accidents, type variables

Published by IEC under license from IEEE. © 2016 IEEE. All rights reserved.

IEEE Std 497-2016
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– viii – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
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IEEE Std 497-2016
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– x – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
IEEE Introduction
This introduction is not part of IEEE Std 497™-2016, IEEE Standard Criteria for Accident Monitoring Instrumentation
for Nuclear Power Generating Stations.
History
This standard evolved from IEEE Std 497™-2010 [B4] . It represents a continued effort by IEEE to
support the specification, design, and implementation of accident monitoring instrumentation of nuclear
power generating stations.
IEEE Std 497-2010 [B4] was developed to provide criteria for advanced instrumentation system designs
and design modifications based on modern digital technology. It marked a clear path forward for the
application of new technology. Though still maintaining applicability to existing systems, this version of
IEEE Std 497 provides more current guidance based on historically related standards and guidance.
It was the working group’s intention that the criteria of this standard address the variety of possible
accident monitoring channel configurations that current technology affords. It was also the working group’s
intention to address the display of information using computer generated displays and calculated values.
The criteria presented in this standard provide guidance in this area without limiting the types of displays
that can be made available to accident management personnel.
Although written primarily for new plant designs, existing plants may also use the guidance and applicable
criteria in this standard. The use of applicable plant procedures to determine the requirements of the
accident monitoring instrumentation provides the necessary flexibility for useful design criteria. This
standard can be used to help address the necessary changes to the plant configuration that occur over the
operating life of any plant.
Historically the standard addressed accident monitoring instrumentation used for anticipated operating
occurrences (AOOs) and design basis events (DBEs). To address lessons learned from various industry
events, the scope of this standard has evolved to now include severe accidents. This evolution was intended
to provide a broader applicability to cover both preventative and mitigative phases of potential plant events.
A broader applicability of the standard was also achieved by moving to a more international, technology
neutral approach to the standard. This approach was achieved by changing to International Atomic Energy
Agency (IAEA) definitions of terms, where applicable; the removal, where appropriate, of U.S. specific
references; and involvement in the working group of members of other standards organizations.
Furthermore, the corresponding International Electrotechnical Commission (IEC) counterparts to the IEEE
standards referenced were investigated and introduced as a second set of normative references. This opens
the possibility to apply this standard in the IEC domain. The individual IEEE and IEC reference sets in
whole are individually appropriate for use in the application of the standard, but inclusion of the IEEE and
IEC references does not imply equivalency between the individual references of the two sets.
Intended use
The standard applies to instrumentation intended for use during anticipated operational occurrences (AOO),
design basis events (DBE), and design extension conditions (DEC) including severe accidents.
This standard defines severe accidents as a subset of design extension conditions during which fuel damage
has occurred. Operationally, severe accidents and design extension conditions without fuel damage are
___________
The numbers in brackets correspond to those of the bibliography in Annex D.
Published by IEC under license from IEEE. © 2016 IEEE. All rights reserved.

IEEE Std 497-2016
distinguished by the procedures and guidelines used to manage the event, with emergency operating
procedures (EOP) used for design extension conditions without fuel damage and severe accident mitigation
guidelines (SAMG) used for severe accidents (see Annex C).
The standard is to be applied to instruments designated for severe accidents (Type F variables); however,
use of non-designated instruments during a severe accident is not precluded if these instruments are
available and can aid in the accident mitigation. Design extension conditions that are not severe accidents
are not covered by this standard.
This standard is intended to be used for both new plant designs and major modifications or upgrades of
existing nuclear power generating stations. The standard can be applied to various reactor types used for
power generation; however, development of the standard focused on light water reactors and application of
the standard to reactor technologies beyond light water reactors should be evaluated prior to initial use.
Revision summary
Since IEEE Std 497 was approved in 2010, industry events have occurred that highlighted the need for the
standard to address not just design basis events but severe accidents as well. The working group has
considered and incorporated appropriate changes related to the following significant items:
 Lessons learned from industry events including Fukushima (earthquake and tsunami), Browns
Ferry (tornado), Salem (loss of RPS due to CCF), and North Anna (earthquake)
 Accident monitoring instrument requirements based on emergency procedures and guidelines
(EOPs and SAMGs)
 Reactor technology neutral approach
 International usability
 User feedback
 Requirements for severe accidents instrumentation
 IAEA definitions
Other minor editorial improvements throughout the standard were also incorporated.
Future work
As the use of digital technology in the nuclear plant is a dynamic area of design, the working group intends
to keep this area as an ongoing future task.
Since no counterpart to this standard exists in the IEC domain, this standard was identified as a potential
candidate for a dual-logo standard to be applied in both the IEEE and the IEC domain early in the course of
this revision. A joint group of both organizations identified topics and aspects to be harmonized and
recommended to proceed. Thus the recent revision was performed with the intent and the spirit to prepare
and facilitate the application for the IEC domain. Formal involvement of the IEC was delayed. This
revision of the standard is, therefore, still an IEEE standard, but may be further modified in the future after
closer investigation by and discussion with IEC experts on its potential as a dual-logo standard.
Another area that the working group believes should be considered in a future revision to the standard is
how to adopt risk-informed techniques into accident monitoring criteria.
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– xii – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
Additionally, user feedback related to the implementation of the standard on non-light water reactors and
implementation of Type F variables will be reviewed and considered for a future revision.

Published by IEC under license from IEEE. © 2016 IEEE. All rights reserved.

IEEE Std 497-2016
Standard Criteria for Accident
Monitoring Instrumentation for Nuclear
Power Generating Stations
IMPORTANT NOTICE: IEEE Standards documents are not intended to ensure safety, security, health,
or environmental protection, or ensure against interference with or from other devices or networks.
Implementers of IEEE Standards documents are responsible for determining and complying with all
appropriate safety, security, environmental, health, and interference protection practices and all
applicable laws and regulations.
This IEEE document is made available for use subject to important notices and legal disclaimers.
These notices and disclaimers appear in all publications containing this document and may
be found under the heading “Important Notice” or “Important Notices and Disclaimers
Concerning IEEE Documents.” They can also be obtained on request from IEEE or viewed at
http://standards.ieee.org/IPR/disclaimers.html.
1. Overview
1.1 Scope
This standard contains the functional and design criteria for accident monitoring instrumentation for new
plant designs and nuclear power generating stations desiring to perform design modifications.
1.2 Purpose
The purpose of this standard is to establish selection, design, performance, qualification, and display
criteria for accident monitoring instrumentation for anticipated operational occurrences, design basis
events, and severe accidents.
1.3 Application
This standard applies to accident monitoring instrumentation intended for use during the following
operations:
 As required for planned operator action related to accident mitigation
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– 2 – IEC 63147:2017 © IEC 2017
IEEE Std 497-2016
 For assessing plant conditions, safety system performance, and making decisions related to plant
response to abnormal events
 For achieving and maintaining safe shutdown following an accident
This standard does not apply to the following:
 Accident monitoring instrumentation that is intended solely for historical recording or solely for
maintenance purposes
 Other instrumentation that may be available during accident conditions
2. Normative references
The following referenced documents are indispensable for the application of this document (i.e., they must
be understood and used, so each referenced document is cited in text and its relationship to this document is
explained). For dated references, only the edition cited applies. For undated references, the latest edition of
the referenced document (including any amendments or corrigenda) applies.
2.1 Normative references for IEEE domain
ASME NQA-1-2008, Quality Assurance Requirements for Nuclear Facility Applications.
IEEE Std 7-4.3.2™-2016, IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of
3,4
Nuclear Power Generating Stations.
IEEE Std 308™-2012, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating
Stations.
IEEE Std 323™-2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating
Stations.
IEEE Std 344™-2013, IEEE Standard for Seismic Qualification of Class 1E Equipment for Nuclear Power
Generating Stations.
IEEE Std 352™-1987, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power
Stations.
IEEE Std 379™-2014, IEEE Standard Application of the Single-Failure Criterion to Nuclear Power
Generating Station Safety Systems.
IEEE Std 384™-2008, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits.
IEEE Std 577™-2012, IEEE Standard Requirements for Reliability Analysis in the Design and Operation
of Safety Systems for Nuclear Power Generating Stations.
IEEE Std 603™-2009, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.
___________
ASME publications are available from the American Society of Mechanical Engineers, 22 Law Drive, Fairfield, NJ 07007, USA.
The IEEE standards or products referenced in Clause 2 are trademarks owned by The I
...