Nuclear power plants - Instrumentation systems - Measurements for monitoring adequate cooling within the core of pressurized light water reactors

IEC 60911:2025 applies to pressurized water reactors (PWRs) and presents requirements for the monitoring of adequate cooling within the core in all operations, including normal and abnormal operations. Requirements for core cooling monitoring during conditions beyond a design basis accident, i.e. a design extension condition of type A or type B, are also covered in this document.
This document defines requirements for instrumentation to measure coolant parameters, which are of interest when abnormal conditions arise with either one or two phases of coolant or with gas included in the reactor pressure vessel (RPV).
This second edition cancels and replaces the first edition published in 1987. This edition includes the following significant technical changes with respect to the previous edition:
a) Modification of the title.
b) Integration and merging with the content of IEC 62117:1999 relative to the monitoring of core cooling during cold shutdown.
c) Integration of feedback following the 2011 Fukushima accident.

Centrales nucléaires de puissance - Système d'instrumentation - Mesures de surveillance du refroidissement du coeur des réacteurs à eau légère pressurisée

General Information

Status
Published
Publication Date
11-Jun-2025
Current Stage
PPUB - Publication issued
Start Date
12-Jun-2025
Completion Date
16-May-2025
Ref Project
Standard
IEC 60911:2025 - Nuclear power plants - Instrumentation systems - Measurements for monitoring adequate cooling within the core of pressurized light water reactors Released:12. 06. 2025 Isbn:9782832703977
English language
45 pages
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Standards Content (Sample)


IEC 60911 ®
Edition 2.0 2025-06
INTERNATIONAL
STANDARD
Nuclear power plants – Instrumentation systems – Measurements for monitoring
adequate cooling within the core of pressurized light water reactors

ICS 27.120.20  ISBN 978-2-8327-0397-7

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– 2 – IEC 60911:2025 © IEC 2025
CONTENTS
FOREWORD . 5
INTRODUCTION . 7
1 Scope . 9
2 Normative references . 9
3 Terms and definitions . 10
4 Abbreviated terms. 13
5 Operational conditions . 13
5.1 General . 13
5.2 Cooling state with steam generator . 14
5.2.1 General. 14
5.2.2 Coolant subcooled state . 14
5.2.3 Coolant saturated state . 14
5.2.4 Coolant superheated state . 15
5.3 Cooling state with RHRS . 15
5.3.1 General situation under RHRS operation . 15
5.3.2 Cold shutdown maintenance operations . 16
5.3.3 Cold shutdown refuelling operation . 16
5.3.4 PRHRS operation. 16
5.4 Cooling state with primary loop feed and bleed . 17
5.5 Cooling state with CIS . 17
6 Measurement methods . 17
6.1 General . 17
6.2 Water level measuring devices . 17
6.2.1 General. 17
6.2.2 RPV water level measuring devices . 17
6.2.3 RPV outlet pipe water level measuring devices . 19
6.2.4 Differential pressure measurement . 19
6.2.5 Ultrasonic liquid level monitoring . 19
6.2.6 Pressurizer level . 19
6.2.7 Reactor cavity level . 19
6.2.8 Containment flood-up level . 19
6.3 Temperature measuring devices. 19
6.3.1 General. 19
6.3.2 Core exit temperature . 20
6.3.3 RPV outlet and inlet pipe temperature . 20
6.3.4 RHRS temperature . 20
6.3.5 PRHRS temperature . 20
6.3.6 RPV and cavity temperature . 20
6.4 Flow measuring device . 20
6.4.1 RPV outlet pipe flow . 20
6.4.2 RHRS flow . 20
6.4.3 RSIS flow . 20
6.4.4 CIS flow . 21
6.5 Pressure measuring device . 21
7 Instrumentation requirements . 21
7.1 General requirements. 21

7.1.1 Overview . 21
7.1.2 Safety classification . 21
7.1.3 Accuracy and response time . 21
7.1.4 Reliability . 21
7.1.5 Single failure considerations . 21
7.2 Differential pressure measurement . 22
7.2.1 Differential pressure transmitters . 22
7.2.2 Reference columns . 22
7.2.3 Differential pressure tap locations . 22
7.2.4 Hydraulic instrument line installations . 23
7.2.5 Hydraulic instrument line temperature . 23
7.2.6 Type and quality of the fluid in the instrument lines . 24
7.3 Heated sensor measurement . 24
7.4 Ultrasonic liquid level measurement. 24
7.4.1 Application . 24
7.4.2 Accuracy and response time . 24
7.4.3 Installation considerations. 24
7.4.4 Special human machine considerations . 24
7.5 Temperature sensing devices . 24
7.6 Magnetic float sensing devices . 25
8 Operator displays . 25
9 Calibration . 26
10 In-service testing and maintenance . 26
11 Qualification . 26
12 Documentation . 26
Annex A (informative) Thermodynamic analysis of the reactor coolant system . 39
A.1 General . 39
A.2 Assessment of thermodynamic conditions . 39
A.2.1 General. 39
A.2.2 Momentum and mass behaviour . 39
A.2.3 Energy behaviour . 40
A.3 Display parameters . 40
A.4 Example of displays . 41
A.4.1 General. 41
A.4.2 Pressure-temperature deviation display . 41
A.4.3 Subcooling history display . 44
A.4.4 Temperature-pressure display . 44
Bibliography . 45

Figure 1 – Different void distributions with equivalent liquid levels . 11
Figure 2 – PWR configuration 1: Cooling state with steam generator . 27
Figure 3 – PWR configuration 2: Cooling state with RHRS . 28
Figure 4 – PWR configuration 3: Cooling state with PRHRS (primary side) . 29
Figure 5 – PWR configuration 4: Cooling state with PRHRS (secondary side) . 30
Figure 6 – PWR configuration 5: Cooling state with primary loop feed and bleed (RSIS) . 31
Figure 7 – PWR configuration 6: Cooling state with primary loop feed and bleed
(recirculated in containment) . 32

– 4 – IEC 60911:2025 © IEC 2025
Figure 8 – PWR configuration 7: Cooling state after core melting . 33
Figure 9 – Water level measurement by differential pressure method . 34
Figure 10 – Heated temperature sensor measurement. 35
Figure 11 – Magnetic float actuated reed switches for water level measurements . 36
Figure 12 – Flow measurement by differential pressure method . 37
Figure 13 – Thermal-hydraulic considerations affecting water level measurements . 38
Figure A.1 – Pressure-temperature deviation display . 42
Figure A.2 – Subcooling history display . 43
Figure A.3 – Temperature-pressure display . 43

Table A.1 – Thirteen different cases of changing pressure, temperature and subcooling . 41

INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS – INSTRUMENTATION SYSTEMS –
MEASUREMENTS FOR MONITORING ADEQUATE COOLING WITHIN
THE CORE OF PRESSURIZED LIGHT WATER REACTORS

FOREWORD
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all national electrotechnical committees (IEC National Committees). The object of IEC is to promote in
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