IEC 60965:2009

Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room

IEC 60965:2009 establishes requirements for the supplementary control points provided to enable the operating staff of nuclear power plants to shut down the reactor and maintain the plant in a safe shut-down state in the event that control of the safety functions can no longer be exercised from the main control room, due to unavailability of the main control room or its facilities. The main technical changes with regard to the previous edition are as follows:
- to clarify the definitions and review the requirements;
- to update the references to new IEC standards published since the first issue;
- to align the standard with new editions of the relevant IAEA documents.

Centrales nucléaires de puissance - Salles de commande - Points de commande supplémentaires pour l'arrêt des réacteurs sans accès à la salle de commande principale (salle de commande de repli)

La CEI 60965:2009 établit des exigences applicables aux points de commande supplémentaires permettant au personnel d'exploitation des centrales nucléaires d'arrêter le réacteur et de maintenir l'installation dans un état d'arrêt sûr, pour le cas où les fonctions de sûreté ne pourraient plus être commandées de la salle de commande principale, en cas d'indisponibilité de celle-ci ou de ses équipements. Les modifications techniques majeures par rapport à l'édition précédente sont les suivantes:
- clarification des définitions et revue technique des exigences;
- mise à jour des références avec celles des nouvelles normes CEI publiées depuis la première édition;
- mise en cohérence de la norme avec les nouvelles éditions des documents de l'AIEA pertinents.

General Information

• Status: Published
• Publication Date: 15-Jul-2009
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: SC 45A - Instrumentation, control and electrical power systems of nuclear facilities
• Current Stage: DELPUB - Deleted Publication
• Completion Date: 23-Feb-2016

Relations

• Revised: IEC 60965:2016 - Nuclear power plants - Control rooms - Supplementary control room for reactor shutdown without access to the main control room
• Effective Date: 05-Sep-2023

Standards Content (Sample)

IEC 60965 ®
Edition 2.0 2009-07
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Control rooms – Supplementary control points for
reactor shutdown without access to the main control room

Centrales nucléaires de puissance – Salles de commande – Points de
commande supplémentaires pour l’arrêt des réacteurs sans accès à la salle de
commande principale (salle de commande de repli)

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IEC 60965 ®
Edition 2.0 2009-07
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Control rooms – Supplementary control points for
reactor shutdown without access to the main control room

Centrales nucléaires de puissance – Salles de commande – Points de
commande supplémentaires pour l’arrêt des réacteurs sans accès à la salle de
commande principale (salle de commande de repli)
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
Q
CODE PRIX
ICS 27.120.20 ISBN 978-2-88910-354-6
– 2 – 60965 © IEC:2009
CONTENTS
FOREWORD.3
INTRODUCTION.5
1 Scope.7
2 Normative references .7
3 Terms and definitions .8
4 Abbreviations .9
5 Design principles.9
5.1 General .9
5.2 Main objectives .9
5.3 Safety principles.10
5.4 Human factors engineering principles.12
6 Design process.12
7 Functional design .13
7.1 General .13
7.2 Human factors.13
7.3 Location and access route.13
7.4 SCP environment .14
7.5 Space and configuration.14
7.6 Information and control equipment .14
7.7 Communication systems.15
7.8 Other equipment.15
8 System verification and validation.15
Bibliography.16

60965 © IEC:2009 – 3 –
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS –
CONTROL ROOMS –
SUPPLEMENTARY CONTROL POINTS FOR REACTOR SHUTDOWN
WITHOUT ACCESS TO THE MAIN CONTROL ROOM

FOREWORD
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International Standard IEC 60965 has been prepared by subcommittee 45A: Instrumentation
and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation.
The text of this standard is based on the following documents:
FDIS Report on voting
45A/749/FDIS 45A/769/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.
This second edition cancels and replaces the first edition published in 1989. This edition
constitutes a technical revision.

– 4 – 60965 © IEC:2009
The main technical changes with regard to the previous edition are as follows:
• to clarify the definitions and review the requirements.
• to update the reference to new standards published since the first issue, including
IEC 61227, IEC 61771, IEC 61772, IEC 61839, and IEC 62241.
• to align the Standard with the new revisions of IAEA documents NS-R-1 and NS-G-1.3.
This publication has been drafted in accordance with the ISO/IEC Directives, Part 2.
The committee has decided that the contents of this publication will remain unchanged until
the maintenance result 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.
60965 © IEC:2009 – 5 –
INTRODUCTION
a) Technical background, main issues and organization of the standard
IEC 60965:1989 was developed to provide requirements relevant to the design of NPP
supplementary control points for reactor shutdown without access to the main control room.
The first edition of IEC 60965 has been used extensively within the nuclear industry. It was
however recognized that recent technical developments especially those which are based on
software technology should be incorporated. It was also recognized that the relationships with
the standard for the main control room (i.e. IEC 60964) and the derivative standards to that
standard (i.e. IEC 61227, IEC 61771, IEC 61772, IEC 61839, and IEC 62241) should be
clarified and conditioned.
This IEC standard specifically focuses on the functional design process of the supplementary
control points of an NPP. It is intended that the standard is used by NPP designers, design
authorities, vendors, utilities, and by licensors.
At the end of the current revision, at the FDIS stage, two further points were identified. These
are: (a) requirements should be included associated with regular testing of the SCP, and (b) a
theoretical assessment is needed of the time available during which the reactor will be safe
but unattended, in order to move from the MCR to the SCP and for the SCP to become
operational. Howev
...