Nuclear power plants - Control rooms - Requirements for emergency response facilities

IEC 62954:2019 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).
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.

Centrales nucléaires de puissance - Salles de commande - Exigences pour les moyens de réaction d'urgence

l'IEC 62954:2019 expose les exigences pour les moyens de réaction d'urgence (ci-après dénommés "ERF") utilisées en cas d'incidents ou d'accidents qui surviennent sur la centrale nucléaire associée. L'ERF comprend l'ERC (Emergency Response Centre, centre de réaction d'urgence), le TSC (Technical Support Centre, centre de soutien technique) et l'OSC (Operational Support Centre, centre de soutien opérationnel).
Il établit les exigences pour les fonctionnalités de l'ERF ainsi que pour les équipements I&C de l'ERF pour:
· coordonner les efforts opérationnels sur site pour ce qui concerne la sûreté et la radioprotection;
· optimiser la conception en termes de contrôle environnemental, d'éclairages, d'alimentations électriques et de contrôle d'accès de l'ERF;
· améliorer l'identification et la résolution de conflits potentiels entre les moyens opérationnels traditionnels et les moyens d'urgence (MCR/SCR et ERF, personnel d'exploitation et équipes d'urgence, procédures opérationnelles et procédures d'urgence);
· faciliter l'identification et l'amélioration des synergies potentielles entre les moyens opérationnels traditionnels et les moyens d'urgence.

General Information

Status
Published
Publication Date
23-Jan-2019
Current Stage
PPUB - Publication issued
Completion Date
24-Jan-2019
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IEC 62954
Edition 1.0 2019-01
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
colour
inside
Nuclear power plants – Control rooms – Requirements for emergency response
facilities
Centrales nucléaires de puissance – Salles de commande – Exigences pour les
moyens de réaction d'urgence
IEC 62954:2019-01(en-fr)
---------------------- Page: 1 ----------------------
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IEC 62954
Edition 1.0 2019-01
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
colour
inside
Nuclear power plants – Control rooms – Requirements for emergency response
facilities
Centrales nucléaires de puissance – Salles de commande – Exigences pour les
moyens de réaction d'urgence
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
INTERNATIONALE
ICS 27.120.20 ISBN 978-2-8322-6384-6

Warning! Make sure that you obtained this publication from an authorized distributor.

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® Registered trademark of the International Electrotechnical Commission
Marque déposée de la Commission Electrotechnique Internationale
---------------------- Page: 3 ----------------------
– 2 – IEC 62954:2019 © IEC 2019
CONTENTS

FOREWORD ........................................................................................................................... 4

INTRODUCTION ..................................................................................................................... 6

1 Scope .............................................................................................................................. 9

2 Normative references ...................................................................................................... 9

3 Terms and definitions .................................................................................................... 10

4 Symbols and abbreviated terms ..................................................................................... 12

5 ERF basis for design ..................................................................................................... 12

5.1 General ................................................................................................................. 12

5.2 Role and main features ......................................................................................... 12

5.2.1 General ......................................................................................................... 12

5.2.2 Emergency Response Centre (ERC) .............................................................. 13

5.2.3 Technical Support Centre (TSC) .................................................................... 13

5.2.4 Operational Support Centre (OSC) ................................................................ 14

5.3 Availability and hazard withstand .......................................................................... 14

5.4 Information to be available in ERF ........................................................................ 15

6 ERF location and physical features ................................................................................ 15

6.1 Location ................................................................................................................ 15

6.2 Access routes ....................................................................................................... 16

6.3 Access control ...................................................................................................... 16

6.4 Environmental design............................................................................................ 16

6.5 Other habitability aspects ...................................................................................... 16

6.6 Power supplies ..................................................................................................... 17

6.7 Documentation ...................................................................................................... 17

7 Principles of operation ................................................................................................... 18

7.1 Organisational aspects ......................................................................................... 18

7.2 Staffing ................................................................................................................. 18

8 Human Machine Interface (HMI) .................................................................................... 18

8.1 Room layout and workspace design ...................................................................... 18

8.2 Hardware and software HMI design ....................................................................... 18

9 Human Factors Engineering (HFE) ................................................................................ 19

9.1 General ................................................................................................................. 19

9.2 Operational experience ......................................................................................... 19

9.3 Functional analysis and assignment ...................................................................... 19

9.4 Task analysis ........................................................................................................ 19

9.5 Style guide ............................................................................................................ 20

9.6 HFE verification and validation .............................................................................. 20

10 Instrumentation and control equipment .......................................................................... 20

10.1 Safety classification .............................................................................................. 20

10.2 Design of I&C equipment for ERF ......................................................................... 20

10.3 I&C functions of the ERF ....................................................................................... 21

10.4 Testability ............................................................................................................. 21

11 Equipment qualification ................................................................................................. 21

12 Communications ............................................................................................................ 21

12.1 Communication principles ..................................................................................... 21

12.2 Nature of communications ..................................................................................... 21

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IEC 62954:2019 © IEC 2019 – 3 –

12.3 Data communications ............................................................................................ 22

12.4 Verbal communications ......................................................................................... 22

12.5 Non-verbal communications .................................................................................. 22

12.6 Communication confidentiality ............................................................................... 22

13 Maintenance and training .............................................................................................. 23

13.1 Maintainability ....................................................................................................... 23

13.2 Repairs ................................................................................................................. 23

13.3 Periodic verification of equipment and perishable goods ....................................... 23

13.4 Training and exercises .......................................................................................... 23

Annex A (informative) Extracts from IAEA Safety Guides relevant to ERF ............................ 24

Bibliography .......................................................................................................................... 26

Figure 1 – On-site and off-site ERFs and communicating entities ............................................ 6

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– 4 – IEC 62954:2019 © IEC 2019
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS – CONTROL ROOMS –
REQUIREMENTS FOR EMERGENCY RESPONSE FACILITIES
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

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International Standard IEC 62954 has been prepared by subcommittee 45A: Instrumentation,

control and electrical power systems of nuclear facilities, of IEC technical committee 45:

Nuclear instrumentation.
The text of this International Standard is based on the following documents:
FDIS Report on voting
45A/1236/FDIS 45A/1251/RVD

Full information on the voting for the approval of this International Standard can be found in

the report on voting indicated in the above table.

This document has been drafted in accordance with the ISO/IEC Directives, Part 2.

---------------------- Page: 6 ----------------------
IEC 62954:2019 © IEC 2019 – 5 –

The committee has decided that the contents of this document will remain unchanged until the

stability date indicated on the IEC website under "http://webstore.iec.ch" in the data related to

the specific document. At this date, the document will be
• reconfirmed,
• withdrawn,
• replaced by a revised edition, or
• amended.

IMPORTANT – The 'colour inside' logo on the cover page of this publication indicates

that it contains colours which are considered to be useful for the correct

understanding of its contents. Users should therefore print this document using a

colour printer.
---------------------- Page: 7 ----------------------
– 6 – IEC 62954:2019 © IEC 2019
INTRODUCTION
a) Technical background, main issues and organisation of the Standard

The Fukushima-Daiichi accident has shown that extremely severe hazards can occur for

which a nuclear power plant has not been designed to resist. In such situations, the plant has

possibly to cope with one or several damaged reactors, and associated radioactive releases,

but also has to cope with the loss of a major part of the electrical sources, cooling functions

and I&C, possibly including the Main Control Room (MCR), as well as with difficulties in

accessing the site. Providing safe on-site facilities for managing such an emergency is hence

a major issue.

An international consensus has emerged to promote the design and installation of a specific

set of facilities aiming at coordinating the efforts of personnel charged with controlling the

emergency activities and those of authorities external to the site charged with protecting the

population and the environment. These facilities are called the Emergency Response

Facilities (ERF).

Different countries, utilities and nuclear power plants have different geographical and

infrastructure characteristics and different requirements under emergency situations.

However, the same fundamentals apply in terms of both on-site and off-site requirements.

The IAEA requirements for emergency response are addressed in SSR-2/1 and GSR Part 7.

Informative Annex A provides the more relevant extracts from these two IAEA publications.

Figure 1 below illustrates the most important control locations, emergency response facilities

and other associated facilities on-site and off-site. Some of the on-site facilities could be

combined to support close-communication or their functions could be dispersed across other

on-site facilities. The level of hardening and autonomy of the individual on-site facilities could

vary considerably.
Figure 1 – On-site and off-site ERFs and communicating entities

NOTE 1 No internationally standardized terminology has been established for the various on-site and off-site

emergency response facilities. The terms used in Figure 1 indicate the ones that have been adopted in this

document.

NOTE 2 Depending on local contexts, the “on-site” ERFs could be implemented close to the NPP and not inside it.

NOTE 3 The role and composition of the off-site civil authorities and emergency infrastructure are known to vary

widely. These entries in Figure 1 are therefore considered as illustrative only.

As indicated in Figure 1 some functional services are already dealt with in IEC standards.

---------------------- Page: 8 ----------------------
IEC 62954:2019 © IEC 2019 – 7 –

This standard was proposed after the Fukushima-Daiichi accident to take into account the

lessons learned from those dramatic events. Several reports prepared after the accident, at

national level (Japanese Government report) as well as at international level (IAEA fact

finding mission) highlighted the role played by the Emergency Response Centre (ERC) during

those events and identified the need to take into account the experience gained to strengthen

the requirements for such a facility.
This led to the development of this standard, with the following principles:

• The scope should align with that of the relevant IAEA guidance, as given in SSR-2/1,

Rev. 1 and GSR Part 7;

• The scope should address the three functional facilities related to Emergency Response

that are addressed by the IAEA guidance (i.e. the ERC, TSC and OSC);

• The scope should be limited to such facilities that are on or near the NPP site. The scope

should exclude activities in the scope of local response authorities;

• The requirements should be defined in terms of the functions that are to be performed;

• The standard should address the way in which the functions are invoked in response to

different severities of incident / accident and any responsibilities that would be transferred

from the MCR to the Emergency Response Facilities (ERFs);

• The scope should include consideration of the requirements for environment control,

lighting, power supplies, access control of the ERFs, etc., as needed to enable the

Emergency Response functions to be performed;

• The only “controls” that should be provided are those that relate to the services that

provide the above mentioned environment control, lighting, power supplies, access control

of the ERFs, etc.;

• The standard should recognize that a wide range of national or regional situations exist

regarding the structure and arrangements for the off-site Emergency Response support.

This IEC standard specifically focuses on the issue of requirements relevant for the

Emergency Response Facilities (ERFs).

It is intended that the Standard be used by designers and operators of NPPs (utilities),

systems evaluators, vendors and subcontractors, and by licensors.

b) Situation of the current Standard in the structure of the IEC SC 45A standard series

IEC 62954 is at the third level of the IEC SC 45A standard series. It is to be considered as

affiliated to IEC 60964, the top document on control rooms in the SC 45A standard series.

For a generic description of the structure of the IEC SC 45A standard series, see item d) of

this introduction.
c) Recommendations and limitations regarding the application of the Standard

This standard establishes functional requirements for Emergency Response Facilities and

clarifies the design and operation of the ERF systems to be used in case of incidents or

accidents occurring on nuclear power plants (NPPs) and/or nuclear facilities.

It is recognized that this is an evolving area of regulatory requirements, due to ongoing

analysis of the Fukushima lessons learned. Therefore, the goal of this project is to provide a

standard, which defines the framework within which the evolving country or plant specific

requirements may be developed and applied.
---------------------- Page: 9 ----------------------
– 8 – IEC 62954:2019 © IEC 2019

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

NSS17 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.

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 GSR 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.
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IEC 62954:2019 © IEC 2019 – 9 –
NUCLEAR POWER PLANTS – CONTROL ROOMS –
REQUIREMENTS FOR EMERGENCY RESPONSE FACILITIES
1 Scope

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 identificat
...

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