Published 1989 | Version v1
Journal article

Development of a heat exchanger root-cause analysis methodology

Creators

Description

The objective of this work is to determine a generic methodology for approaching the accurate identification of the root cause of component failure. Root-cause determinations are an everyday challenge to plant personnel, but they are handled with widely differing degrees of success due to the approaches, levels of diagnostic expertise, and documentation. The criterion for success is simple: If the root cause of the failure has truly been determined and corrected, the same causal failure relationship will not be demonstrated again in the future. The approach to root-cause analysis (RCA) element definition was to first selectively choose and constrain a functionally significant component (in this case a component cooling water to service water heat exchanger) that has demonstrated prevalent failures. Then a root cause of failure analysis was performed by a systems engineer on a large number of actual failure scenarios. The analytical process used by the engineer was documented and evaluated to abstract the logic model used to arrive at the root cause. For the case of the heat exchanger, the actual root-cause diagnostic approach is described. A generic methodology for the solution of the root cause of component failure is demonstrable for this general heat exchanger sample

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society, Supplement
Journal Volume
59
Series
Trans. Am. Nucl. Soc., Suppl.
Journal Page Range
43-44
CODEN
TANSB

Conference

Title
plant operations - the human element.
Acronym
14. biennial conference on reactor operating experience
Dates
6-9 Aug 1989.
Place
Charlotte, NC (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21028569
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; HEAT EXCHANGERS; HEAT TRANSFER; HYDRAULICS; IMPLEMENTATION; NUCLEAR POWER PLANTS; RESEARCH PROGRAMS; SAFETY ENGINEERING; SYSTEM FAILURE ANALYSIS; TESTING; US NRC; VERIFICATION
Descriptors DEC
ENERGY TRANSFER; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; US ORGANIZATIONS

Optional Information

Secondary number(s)
CONF-890833--.