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BS IEC/TR 61838:2001

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

Nuclear power plants. Use of probabilistic safety asessment for the classification of instrumentation and control functions

Available format(s)

Hardcopy , PDF

Superseded date

02-28-2010

Language(s)

English

Published date

05-15-2001

FOREWORD
INTRODUCTION
Clause
1 Scope
2 Reference documents
3 Definitions and abbreviations
   3.1 Definitions
4 Limitations regarding the use of PSA
5 The use of PSA: methods and results
   5.1 Introduction
   5.2 Use of PSA in the design of future NPPs
       5.2.1 Overall scope
       5.2.2 Methods
       5.2.3 Plant analysis and modelling I&C in PSA
   5.3 Benefits of the use of PSA for existing NPPs
6 The use of PSA for classification
   6.1 General
   6.2 Approach 1: time and reactor states based approach
       6.2.1 Use of PSA in conjunction with a functional
             deterministic method
       6.2.2 Classification of functions, systems and
             equipment
       6.2.3 Associated technical requirements
       6.2.4 Complementary use of PSA alongside the
             iterative design process
   6.3 Approach 2: quantitative importance based approach
       6.3.1 Quantitative assignment criteria
       6.3.2 Quantitative criteria
       6.3.3 Category assignment
       6.3.4 Classification procedure
       6.3.5 Determination of requirements
Annex A (informative) Proposal for modelling I&C in PSA
        A.1 Scope
            A.1.1 Background
            A.1.2 I&C modelling in PSA
        A.2 Modelling description
            A.2.1 Global description
            A.2.2 Sensor part
            A.2.3 Logic part
            A.2.4 Actuator part
        A.3 Quantitative analysis: unavailability values
            A.3.1 Use of less classified systems for
                  safety functions and modelling in PSA
            A.3.2 Sensor part
            A.3.3 Specific logic part
            A.3.4 Non-specific logic part
            A.3.5 Actuator part
        A.4 Use of modelling in the event trees of PSA
            A.4.1 Taking account of different I&C configurations
            A.4.2 Importance of the actuators
            A.4.3 Integration in PSA event trees
Annex B (informative) Bibliography

Gives a survey of some of the methods by which probabilistic risk assessment results can be used to establish "risk based" classification criteria, so as to allow FSEs to be placed within the four categories established within IEC 61226.

Provides a survey of some of the methods by which probabilistic risk assessment results can be used to establish \'risk based\' classification criteria, so as to allow FSEs to be placed within the four categories established within IEC 61226.

Committee
NCE/8
DevelopmentNote
Supersedes 99/713794 DC. (06/2005)
DocumentType
Standard
Pages
0
PublisherName
British Standards Institution
Status
Superseded
SupersededBy
Supersedes

Standards Relationship
IEC TR 61838:2009 Identical

IEC 60863:1986 Presentation of reliability, maintainability and availability predictions
IEC 61226:2009 Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions
IEC 60812:2006 Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA)
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 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 60964:2009 Nuclear power plants - Control rooms - Design
IEC 61508-1:2010 Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 1: General requirements (see Functional Safety and IEC 61508)

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