Aging assessment of reactor instrumentation and protection system components, Phase 1

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:5667419

Gehl, A C; Hagen, E W ^[1]; Farmer, W S ^[2]

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1. Oak Ridge National Lab., TN (United States)
2. Nuclear Regulatory Commission, Washington, DC (United States)

A study of the aging-related operating experiences throughout a five year period (1984--1988) of six generic instrumentation modules (indicators, sensors, controllers, transmitters, annunciators, and recorders) was performed as a part of the USNRC Nuclear Plant Aging Research (NPAR) Program. The effects of aging from operational and environmental stressors were characterized from results depicted in Licensee Event Reports (LERs). The data are graphically displayed as frequency of events per plant year for operating plant ages from 1 to 28 years to determine aging-related failure trend patterns. This document describes the results and conclusions from this study.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5667419
• Report Number(s): CONF-920375-2; ON: DE92009387
• Resource Relation: Conference: Aging research information conference, Rockville, MD (United States), 24-27 Mar 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
AGING
ALARM SYSTEMS
CORROSION
ELECTROMAGNETIC PULSES
ENGINEERED SAFETY SYSTEMS
FAILURE MODE ANALYSIS
FAILURES
FATIGUE
HUMAN FACTORS
INSPECTION
MECHANICAL VIBRATIONS
MOISTURE
RADIATION EFFECTS
REACTOR OPERATION
TEMPERATURE EFFECTS
WEAR
CHEMICAL REACTIONS
CONTROL SYSTEMS
ELECTROMAGNETIC RADIATION
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
OPERATION
POWER PLANTS
PULSES
RADIATIONS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
220400* - Nuclear Reactor Technology- Control Systems
220900 - Nuclear Reactor Technology- Reactor Safety