Published March 1990 | Version v1
Report Metadata-only

Aging assessment of auxiliary feedwater systems

Creators

  • 1. Oak Ridge National Lab., TN (USA)

Description

A study of pressurized water reactor auxiliary feedwater (AFW) systems has been conducted by Oak Ridge National Laboratory (ORNL) under the auspices of the Nuclear Regulatory Commission's Nuclear Plant Aging Research Program. The study has reviewed historical failure experience and current monitoring practices for the AFW System. This paper provides an overview of the study approach and results with respect to the following topics: AFW system design and functions, specifically, pump suction sources, pumps, pump discharge and flow distribution; failure data analysis results; and plant monitoring practices reviews

Additional details

Publishing Information

Imprint Title
Seventeenth water reactor safety information meeting: Proceedings. Volume 3, Primary systems integrity; plant performance, testing and analysis; piping and NDE [nondestructive examination]; plant aging
Imprint Pagination
529 p.
Journal Page Range
p. 439-451.
Report number
NUREG/CP--0105-Vol.3

Conference

Title
17. water reactor safety information meeting.
Dates
23-25 Oct 1989.
Place
Rockville, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22091335
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; AGING; CONTROL SYSTEMS; DATA PROCESSING; ECCS; FAILURES; FEEDWATER; HISTORICAL ASPECTS; ORNL; PUMPS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; REACTOR SHUTDOWN; REACTOR START-UP; RESEARCH PROGRAMS; SAFETY ENGINEERING; SECONDARY COOLANT CIRCUITS; SPECIFICATIONS; US NRC
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; HYDROGEN COMPOUNDS; NATIONAL ORGANIZATIONS; OPERATION; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL; SHUTDOWN; START-UP; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Secondary number(s)
CONF-8910222--Vol.3.