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Steam generator tube inspection in Japan [electronic resource].

Published
Richland, Wash. : CH2M Hill, inc., 1997.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
pages 321-328 : digital, PDF file
Additional Creators
CH2M HILL (Firm) and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Steam generator tube inspection was first carried out in 1971 at Mihama Unit-1 that is first PWR plant in Japan, when the plant was brought into the first annual inspection. At that time, inspection was made on sampling basis, and only bobbin coil probe was used. After experiencing various kinds of tube degradations, inspection method was changed from sampling to all number of tubes, and various kinds of probes were used to get higher detectability of flaw. At present, it is required that all the tubes shall be inspected in their full length at each annual inspection using standard bobbin coil probe, and some special probes for certain plants that have susceptibility of occurrence of flaw. Sleeve repaired portion is included in this inspection. As a result of analyses of eddy current testing data, all indications that have been evaluated to be 20% wall thickness or deeper shall be repaired by either plugging or sleeving, where flaw morphology is to be a wastage or wear. Other types of flaw such as IGA/SCC are not allowed to be left inservice when those indications are detected. These inspections are performed according to inspection procedures that are approved by regulatory authority. Actual inspections are witnessed by the Japan Power engineering and inspection corporation (JAPEIC)`s inspectors during data acquisition and analysis, and they issue inspection report to authority for review and approval. It is achieved high safety performance of steam generator through this method of inspections, however. some tube leakage problems were experienced in the past. To prevent recurrence of such events, government is conducting development and verification test program for new eddy current testing technology.
Report Numbers
E 1.99:nureg/cp--0154
E 1.99: anl--96/14
E 1.99:nea/cnra/r--(96)1
E 1.99:conf-9510423--
conf-9510423--
nea/cnra/r--(96)1
anl--96/14
nureg/cp--0154
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
02/01/1997.
"nureg/cp--0154"
" anl--96/14"
"nea/cnra/r--(96)1"
"conf-9510423--"
"TI97004312"
CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995.
Fukui, Shigetaka.
View MARC record | catkey: 14800794