BS IEC/TR 61838:2001
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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Nuclear power plants. Use of probabilistic safety asessment for the classification of instrumentation and control functions
Hardcopy , PDF
28-02-2010
English
15-05-2001
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.
Committee |
NCE/8
|
DevelopmentNote |
Supersedes 99/713794 DC. (06/2005)
|
DocumentType |
Standard
|
Pages |
0
|
PublisherName |
British Standards Institution
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
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.
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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