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IEEE DRAFT 1205 : D3 99

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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DRAFT GUIDE FOR ASSESSING, MONITORING AND MITIGATING AGING EFFECTS ON CLASS 1E EQUIPMENT USED IN NUCLEAR POWER GENERATING STATIONS

Superseded date

30-03-2000

Superseded by

IEEE 1205-2014

Published date

12-01-2013

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1 Overview
    1.1 Scope
    1.2 Purpose
    1.3 Application
2 References
3 Definitions
4 Stressors, aging mechanisms, and aging effects
    4.1 Stressors
    4.2 Aging mechanisms and effects
5 Discussion
    5.1 Need for an aging assessment
    5.2 Desired objective and benefits
    5.3 Aging assessment elements
6 Aging assessment
    6.1 Define evaluation boundaries
    6.2 Identify equipment safety functions
    6.3 Identify plant locations where the equipment
          is installed
    6.4 Identify the electrical equipment service
          conditions
    6.5 Identify the materials of construction
    6.6 Identify and assess aging effects
7 Monitoring and mitigating aging degradation
    7.1 Maintenance
    7.2 Replacement
    7.3 Refurbishment
    7.4 Redesign of equipment
    7.5 Adjustments in operating environments and
          practices that reduce stresses
    7.6 Environmental and operational stress monitoring
    7.7 Inspection
    7.8 Surveillance
    7.9 Trending
8 Data
    8.1 Baseline data (original capability)
    8.2 Historical data (operating history)
    8.3 Diagnostic testing data
Annex A - Aging Effects Tables
A.1 - Introduction
A.2 - Use of the equipment aging tables
Annex B - Monitoring of Environments
B.1 - Introduction
B.2 - Environmental stressors
B.2.1 - Temperature
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
B.3.2 - Plant survey
B.3.3 - Compilation of available data
B.3.4 - Developing the monitoring program
B.3.5 - Monitoring period
B.3.6 - Review of results and storage of data
Annex C - Condition Monitoring
C.1 - Introduction
C.2 - Conditon monitoring considerations and characteristics
C.3 - Available condition monitoring techniques
C.4 - Conditioning monitoring bibliography
C.4.1 - Reports
Annex D - Equipment and System Examples
D.1 - Reactor protection system
D.1.1 - Evaluation boundaries
D.1.2 - Identify safety functions
D.1.3 - Equipment locations
D.1.4 - Sevice conditions
D.1.5 - Materials of construction
D.1.6 - Identify and assess significant aging effects
D.2 - Emergency Diesel Generator
D.3 - Motor Control Centers
D.4 - Insulated Cables
D.4.1 - Define the evaluation boudaries
D.4.2 - Identify safety functions
D.4.3 - Identify plant locations where the cables are
          installed
D.4.4 - Identify the cable service conditions
D.4.4.1 - Environmental conditions
D.4.4.1.4 - Summary of environmental service conditions
D.4.4.2 - Operational conditions
D.4.4.3 - Results - service conditions
D.4.5 - Identify the cable materials of construction
D.4.6 - Aging effects assessment
D.4.6.1 - Medium-voltage cable insulation - moisture and
          voltage stress
D.4.6.2 - Low-voltage & medium-voltage cable insulation -
          radiation, oxygen
D.4.6.3 - Low-voltage & medium-voltage cable insulation -
          heat, oxygen
D.5 - Electrical Penetration Assemblies (EPAS)
Annex E
Aging Management Program Attributes
Annex F
Bibliography

Gives guidelines for assessing, monitoring and mitigating aging degradation effects on Class 1E equipment for use in nuclear power generating stations.

DocumentType
Draft
PublisherName
Institute of Electrical & Electronics Engineers
Status
Superseded
SupersededBy

IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations

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