Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core

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Hardcopy , PDF , PDF 3 Users , PDF 5 Users , PDF 9 Users

Language(s)

English - French, Russian

Published date

03-20-1996

Publisher

International Electrotechnical Committee

FOREWORD
Clause
1 Scope and object
2 Normative references
3 Definitions
4 Operational conditions
   4.1 Normal operation
   4.2 Abnormal operation
5 Measurement methods
   5.1 Water-level measuring devices
   5.2 Temperature sensing devices
6 Instrumentation requirements
   6.1 Differential pressure measurement
   6.2 Float switches
   6.3 Ultrasonic liquid level monitoring
   6.4 Temperature sensing devices
7 Data processing
8 Presentation of information
9 Requirements for redundancy and diversity
10 Verification and calibration
11 In-service testing and maintenance
12 Qualification
13 Documentation
Figures
Annexes
A Verification and qualification
B Testing and maintenance
C Bibliography

Gives requirements for core cooling monitoring instrumentation to ensure safe operation of BWRs during normal operation and during and after design basis accidents.

Committee	TC 45/SC 45A
DevelopmentNote	Stability Date: 2017. (09/2017)
DocumentType	Standard
Pages	50
PublisherName	International Electrotechnical Committee
Status	Current

BS IEC 62118:2000	Nuclear reactor instrumentation. Pressurized water reactor (PWR) of VVER design. Monitoring adequate cooling within the core during cold shutdown
IEC 61505:1998	Nuclear reactor instrumentation - Boiling water reactors (BWR) - Stability monitoring
BS IEC 62117:1999	Nuclear reactor instrumentation. Pressurized light water reactors (PWR). Monitoring adequate cooling within the core during cold shutdown.
VDE 0491-4 : 2001	NUCLEAR POWER PLANTS - PRESSURIZED LIGHT WATER REACTORS - MONITORING ADEQUATE COOLING WITHIN THE CORE DURING COLD SHUTDOWN
BS IEC 61505:1998	Nuclear reactor instrumentation. Boiling water reactors (BWR). Stability monitoring
IEC 62118:2000	Nuclear reactor instrumentation - Pressurized water reactor (PWR) of VVER design - Monitoring adequate cooling within the core during shutdown
IEC 62117:1999	Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown

IEC 61226:2009	Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions
IEC 60770-2:2010	Transmitters for use in industrial-process control systems - Part 2: Methods for inspection and routine testing
IEC 60980:1989	Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations
IEC 60987:2007+AMD1:2013 CSV	Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems
IEC 61227:2008	Nuclear power plants - Control rooms - Operator controls
IEC 60770:1984	Methods of evaluating the performance of transmitters for use in industrial-process control systems
IEC 60911:1987	Measurements for monitoring adequate cooling within the core of pressurized light water reactors
IEC 60737:2010	Nuclear power plants - Instrumentation important to safety - Temperature sensors (in-core and primary coolant circuit) - Characteristics and test methods
IEC 60880:2006	Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
IEC 60780:1998	Nuclear power plants - Electrical equipment of the safety system - Qualification
IEC 61225:2005	Nuclear power plants - Instrumentation and control systems important to safety - Requirements for electrical supplies
IEC 60964:2009	Nuclear power plants - Control rooms - Design
IEC 60050-393:2003	International Electrotechnical Vocabulary (IEV) - Part 393: Nuclear instrumentation - Physical phenomena and basic concepts

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IEC 61343:1996

Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core

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