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Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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
Hardcopy , PDF
02-28-2010
English
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
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