Published 1990 | Version v1
Report Restricted

10 Years of operating experience of the valves in the safety systems on Caorso plant

  • 1. ENEA, Rome, (Italy)

Description

The Operating Experience (O.E.) of the valves in the safety related systems on Caorso plant has been analysed. The valves have been grouped according to system, type and manufacturer. All the data on the failures have been respectively drawn out by the O.E. data bank and, in some cases, they have been integrated by informations collected directly on the plant. The events and the relevant causes have been analysed, particularly taking into account the repetitive events. Most of the failures were discovered during the surveillance tests, giving a positive indication of the effectiveness of the periodic test program. It was also that concluded hardware problems caused more failures than human errors both during operation and maintenance. Abnormal distributions of failures on the valves and on their components have been found out. Weak components both mechanical and electrical and pertinent corrective measures have been identified, aimed to eliminate the recurring failure modes

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Part of:
Trend and pattern analyses of operational data from nuclear power plants

Additional details

Publishing Information

Imprint Title
Trend and pattern analyses of operational data from nuclear power plants
Imprint Pagination
695 p.
Journal Page Range
p. 475-490.
Report number
EUR--12578

Conference

Title
OECD/CSNI-CEC Specialist meeting on trend and pattern analyses of operational data from nuclear power plants.
Dates
3-7 Apr 1989.
Place
Rome (Italy).

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
22012582
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DATA BASE MANAGEMENT; ENEL-4 REACTOR; FAILURE MODE ANALYSIS; FAILURES; FEEDBACK; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; VALVES
Descriptors DEC
BWR TYPE REACTORS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; MANAGEMENT; OPERATION; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CSNI--159.