IEEE 352 2016:2017 Edition

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IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Othere Nuclear Facilities

Published By	Publication Date	Number of Pages
IEEE	2017	155

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Description

Revision Standard – Active. General reliability and availability analysis methods that can be applied to structures, systems, and components (SSCs) in nuclear power generating stations and otherre nuclear facilities are contained in this guide.

PDF Catalog

PDF Pages	PDF Title
1	IEEE Std 352-2016 Front cover
2	Title page
4	Important Notices and Disclaimers Concerning IEEE Standards Document
7	Participants
9	Introduction
10	Contents
13	1. Overview 1.1 General 1.2 Scope
14	1.3 Purpose 2. Normative references 3. Definitions, acronyms, and abbreviations 3.1 Definitions
16	3.2 Acronyms and abbreviations 4. Objectives and methods 4.1 Overview 4.2 Consideration of the human factor
17	4.3 Qualitative analysis 4.3.1 Objectives of a qualitative analysis 4.3.2 Steps in a qualitative analysis
18	4.4 Quantitative analysis 4.5 Applications of reliability methodology 4.5.1 Overview 4.5.2 Failure modes and effects analysis (FMEA)
19	4.5.3 Logic trees 4.5.4 System modeling
20	4.5.5 Reliability testing 4.5.5.1 Confirmation testing 4.5.5.2 Operational test intervals
21	5. Qualitative analysis principles 5.1 Overview 5.2 Failure modes and effects analysis (FMEA) 5.2.1 Purposes of failure modes and effects analysis (FMEA)
24	5.2.2 Timing of a failure mode and effects analysis (FMEA) 5.2.3 Issues addressed in a failure mode and effects analysis (FMEA)
25	5.2.4 Preparatory steps for a failure mode and effects analysis (FMEA) 5.2.5 Procedure for a failure mode and effects analysis (FMEA)
26	5.3 Fault tree analysis
28	5.3.1 Functions and benefits of fault tree analysis
29	5.3.2 Representation of events and operations in a fault tree
31	5.3.3 Procedure for constructing a fault tree
32	5.4 Reliability block diagram (RBD)
33	5.4.1 Reliability block diagram (RBD) construction 5.4.2 Reliability block diagram (RBD) reduction 5.4.3 Comparison of fault tree and reliability block diagrams (RBDs)
34	5.5 Example 5.5.1 Description of a typical reactor trip function 5.5.2 Failure mode and effects analysis (FMEA) 5.5.3 Fault tree analysis 5.5.4 Reliability block diagram (RBD)
35	5.6 Extended qualitative analysis for common-cause failures
39	5.6.1 Extended failure mode and effect analysis (FMEA)
40	5.6.2 Extended fault tree analysis 5.6.3 Termination of the analyses
41	6. Quantitative analysis principles 6.1 Overview 6.2 Mission definition 6.2.1 Reliability
43	6.2.2 Availability (steady-state)
44	6.3 Mathematical modeling
45	6.3.1 Manual calculation
55	6.3.1.1 Numerical substitution—Reliability calculations 6.3.1.2 Numerical substitution—Availability calculations
56	6.3.1.3 Common-cause failures
58	6.3.1.4 Other dependent failures 6.3.2 For computer calculation 6.3.2.1 Markov models
60	6.3.2.2 Monte Carlo methods
61	6.4 Tabular reference to popular logic configurations
62	6.5 Trial calculations 6.5.1 Manual calculations 6.5.2 Computer calculations 6.6 Credibility check of results 6.6.1 Comparison with prior analysis 6.6.2 Sensitivity analysis
63	6.6.2.1 Variable-parameter—wide range method
64	6.6.2.2 Variable-parameter—narrow range method 7. Guides for data acquisition and use 7.1 Overview
65	7.2 Input parameters 7.2.1 Failure rates 7.2.2 Mean time to repair (MTTR)
66	7.2.3 Mission time 7.2.4 Test interval 7.2.5 Test schedule 7.3 Probability distributions, parameters, and estimation
68	7.3.1 Exponential distribution
71	7.3.2 Poisson distribution
72	7.3.3 Binomial distribution
73	7.3.4 Weibull distribution
74	7.3.5 Combining and updating data 7.4 Established data programs
75	7.4.1 Failure Rate Data Program (FARADA) 7.4.2 Government-Industry Data Exchange Program (GIDEP) 7.4.3 Nonelectric parts reliability data (NPRD-1)
76	7.4.4 Energy Technology Engineering Center (ETEC) 7.4.5 United Kingdom Atomic Energy Authority Data Program (UKAEA), National Center of Systems Reliability (SYREL) 7.4.6 Nuclear Plant Reliability Data System (NPRDS) 7.4.6.1 Nuclear Plant Reliability Data System (NPRDS) inputs
77	7.4.6.2 Nuclear Plant Reliability Data System (NPRDS) outputs 7.4.7 Generating Availability Data System (GADS) 7.4.8 Licensee event reports
78	7.4.9 Operating Units Status Report (NUREG-0020) 7.4.10 Reactor Safety Study, WASH-1400 (NUREG-75/01 4) 7.4.11 Failure Incident Report Review (FIRR) 7.4.12 IEEE Survey of Industrial and Commercial Power Systems 7.4.13 Nuclear power experience reports
79	7.4.14 IEEE Nuclear Reliability Data Manual—IEEE Std 500™ [B22] 7.5 Developing field data programs
80	7.5.1 Failure analysis 7.5.1.1 Failure reporting forms
81	7.5.1.2 Failure cause categories
82	7.5.2 Failure data analysis
85	8. Application of reliability methods 8.1 Introduction 8.2 Numerical goals 8.2.1 Basis for establishing numerical goals 8.2.1.1 Frequency of demand
86	8.2.1.2 Consequence of failure 8.2.1.3 Risk 8.2.2 Specific goals 8.2.2.1 Reactor protective action 8.2.2.2 Engineered safety features
87	8.2.3 Procedures 8.3 Selection of the modeling technique 8.3.1 Model requirements 8.3.2 Model limitations
88	8.4 Fault tree techniques 8.4.1 Characteristics
89	8.4.2 Recommended uses 8.5 The Markov process as a reliability model
92	8.5.1 Constant failure and repair rate components 8.5.2 Constant repair or switching time components
93	8.5.3 Constant success/failure on demand 8.6 Monte Carlo techniques 8.6.1 Characteristics
94	8.6.2 Recommended uses 8.7 Equipment and system testing 8.7.1 Acceptance sampling
99	8.7.2 Initial test intervals
101	8.7.3 In-service adjustment of test intervals
102	Annex A (informative) Bibliography
105	Annex B (informative) Illustration of concepts and methods of reliability and availability analyses B.1 Introduction B.2 Procedure B.2.1 System definition
106	B.2.2 Failure mode and effects analysis (FMEA) (qualitative analysis) B.2.3 Common-cause-failure analysis B.2.4 Reliability/Availability prediction (quantitative) B.2.4.1 Determination of test interval B.2.4.2 Reconciliation of system goals B.3 Illustrative examples B.3.1 System definition
108	B.3.2 Qualitative analysis—failure modes and effects analysis (FMEA) B.3.2.1 Uses of the failure modes and effects analysis (FMEA)
109	B.3.2.2 Mechanics of the failure modes and effects analysis (FMEA)
125	B.3.2.3 Results of failure modes and effects analysis (FMEA)
128	B.3.3 Common-cause-failure analysis B.3.3.1 Failure combinations
129	B.3.3.2 Causative factors B.3.3.3 Preventive measures
130	B.3.3.4 Evaluation of system susceptibility to common-cause failure
132	B.3.4 Quantitative analysis B.3.4.1 Fault tree analysis
136	B.3.4.2 Monte Carlo analysis
141	B.3.4.3 System goals and test intervals
149	Annex C (informative) Mean time to repair (MTTR) process C.1 Introduction C.1.1 Call-out C.1.2 Briefing C.1.3 Access control C.1.4 Establishing prerequisite conditions
150	C.1.5 Troubleshooting C.1.6 Spare parts acquisition C.1.7 Pre-configuration C.1.8 Disassembly C.1.9 Re-assembly C.1.10 Inspections
151	C.1.11 Post-configuration C.1.12 Test C.2 Systematic mean time to repair (MTTR) estimation method
153	C.3 A sample mean time to repair (MTTR) estimation
155	Back cover

Additional information

Standard Title	IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Othere Nuclear Facilities
Published Code	IEEE
Publication Date	2017
Pages Count	155

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