Published 1996 | Version v1
Report Restricted

Reactor coolant pump testing using motor current signatures analysis

Description

This paper describes reactor coolant pump motor testing carried out at Florida Power Corporation's Crystal River plant using Framatome Technologies' new EMPATH (Electric Motor Performance Analysis and Trending Hardware) system. EMPATH trademark uses an improved form of Motor Current Signature Analysis (MCSA), technology, originally developed at Oak Ridge National Laboratories, for detecting deterioration in the rotors of AC induction motors. Motor Current Signature Analysis (MCSA) is a monitoring tool for motor driven equipment that provides a non-intrusive means for detecting the presence of mechanical and electrical abnormalities in the motor and the driven equipment. The base technology was developed at the Oak Ridge National Laboratory as a means for determining the affects of aging and service wear specifically on motor-operated valves used in nuclear power plant safety systems, but it is applicable to a broad range of electric machinery. MCSA is based on the recognition that an electric motor (ac or dc) driving a mechanical load acts as an efficient and permanently available transducer by sensing mechanical load variations, large and small, long-term and rapid, and converting them into variations in the induced current generated in the motor windings. The motor current variations, resulting from changes in load caused by gears, pulleys, friction, bearings, and other conditions that may change over the life of the motor, are carried by the electrical cables powering the motor and are extracted at any convenient location along the motor lead. These variations modulate the 60 Hz carrier frequency and appear as sidebands in the spectral plot

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Title
Proceedings of the 4th NRC/ASME symposium on valve and pump testing
Imprint Pagination
719 p.
Journal Page Range
p. 2A.63-2A.74.
Report number
NUREG/CP--0152

Conference

Title
4. NRC/ASME symposium on valve and pump testing in nuclear power plants.
Dates
15-18 Jul 1996.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28013965
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ELECTRIC CURRENTS; ELECTRIC MOTORS; IN-SERVICE INSPECTION; MONITORING; NUCLEAR POWER PLANTS; PRIMARY COOLANT CIRCUITS; WATER PUMPS
Descriptors DEC
COOLING SYSTEMS; CURRENTS; ELECTRICAL EQUIPMENT; EQUIPMENT; INSPECTION; MOTORS; NUCLEAR FACILITIES; POWER PLANTS; PUMPS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-9607103--.