IEEE 1205 1993

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IEEE Guide for Assessing, Monitoring and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations

Published By	Publication Date	Number of Pages
IEEE	1993	61

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Description

New IEEE Standard – Inactive – Superseded. The guidelines are provided for assessing, monitoring, and mitigating degradation of Class 1E equipment used in nuclear power generating stations due to aging. The methods described can be used to identify the performance capability of Class 1E equipment beyond its qualified life. A discussion of stressors and aging mechanisms is included. If aging considerations have been satisfactorily addressed through other means (e.g., equipment qualification), then use of this guide may not be warranted. For some equipment, only partial application of this guide may be warranted.

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PDF Pages	PDF Title
1	Title Page
3	Introduction
6	CONTENTS
8	1. Overview 1.1 Scope 1.2 Purpose 1.3 Application 2. References
9	3. Definitions 4. Discussion 4.1 Need for an aging assessment 4.2 Desired objective and benefits
10	4.3 Aging assessment elements
11	5. Stressors and aging mechanisms 5.1 Stressors 5.2 Aging mechanisms and effects
12	6. Aging assessment
13	6.1 Describing the equipment 6.2 Identifying the aging components 6.3 Screening for obsolescence or replacement
14	6.4 Identifying significant aging mechanisms 6.5 Determining significant age-related failure modes 6.6 Determining limiting age-related critical characteristics 6.7 Determining parameters to be observed
15	6.8 Establishing residual life
16	7. Methods for monitoring and mitigating aging degradation 7.1 Monitoring methods
18	7.2 Mitigation methods
19	8. Data
20	8.1 Baseline data (original capability)
21	8.2 Historical data (operating history)
22	8.3 Diagnostic testing data
23	Annex A—Aging effects tables A.1 Introduction A.2 Use of the equipment aging tables
32	Annex B—Monitoring of environments B.1 Introduction B.2 Environmental stressors B.2.1 Temperature
33	B.2.2 Radiation B.2.3 Humidity B.2.4 Chemical exposure B 2.5 Dust/dirt B.3 Environmental monitoring program B.3.1 Plant areas to be monitored
34	B.3.2 Plant survey B.3.3 Compilation of available data B.3.4 Developing the monitoring program
35	B.3.5 Monitoring period B.3.6 Review of results and storage of data
36	Annex C—Equipment and system examples C.1 Reactor protection system C.1.1 Description of system
37	C.1.2 Identification of components C.1.3 Screen for obsolescence C.1.4 Identification of aging mechanisms
38	C.1.5 Determination of significant age-related failure modes C.1.6 Determination of limiting age-related critical characteristic C.1.7 Determination of parameters to be observed
39	C.1.8 Estimation of residual life
40	C.1.9 Data requirements
42	C.2 Emergency diesel generator C.2.1 Description of equipment
43	C.2.2 Identification of aging components C.2.3 Screen for obsolescence C.2.4 Identification of aging mechanisms
45	C.2.5 Determination of significant failure modes
47	C.2.6 Determination of limiting age-related critical characteristics
48	C.2.7 Determination of parameters to be observed C.2.8 Estimation of remaining service life
49	C.2.9 Data requirements C.3 Motor control centers C.3.1 Description of equipment C.3.2 Identification of aging components
50	C.3.3 Screen for obsolescence C.3.4 Identification of aging mechanisms
56	C.3.5 Identification of significant age-related failure modes C.3.6 Determination of limiting age-related critical characteristic C.3.7 Determination of parameters to be observed
57	C.3.8 Estimation of residual life
58	C.3.9 Data requirements
59	Annex D—Bibliography

Additional information

Standard Title	IEEE Guide for Assessing, Monitoring and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations
Published Code	IEEE
Publication Date	1993
Pages Count	61

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IEEE 1205 1993

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