Robotic inspection confirms steam generator modification plan
Journal Article
·
· Power Engineering (Barrington)
OSTI ID:113288
In March 1993, Palo Verde Nuclear Generating Station`s Unit 2 sustained a tube rupture within steam generator 2-2. A search for the root cause of failure identified intergranular stress corrosion cracking (IGSCC) in the hot leg upper bundle. Subsequent eddy current inspections and tube pull evaluations supported this conclusion. An Electric Power Research Institute (EPRI) computer code, ATHOS, was used to analyze the generators secondary thermal-hydraulics to reveal what led to the axial cracking. The thermal-hydraulic output from ATHOS depicted the high bundle region and those data were correlated with eddy current results to determine the boundary of the affected area. This ``dryout`` region indicated conditions that were conducive, but not necessarily sufficient, to cause intergranular attack and IGSCC. Remote inspections preceded planned secondary side modifications at the three-unit power plant. The modification project required an annular sealing system to reduce roentgen equivalent man exposure.
- OSTI ID:
- 113288
- Journal Information:
- Power Engineering (Barrington), Journal Name: Power Engineering (Barrington) Journal Issue: 9 Vol. 99; ISSN POENAI; ISSN 0032-5961
- Country of Publication:
- United States
- Language:
- English
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