Published February 1997 | Version v1
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Alternate tube plugging criteria for steam generator tubes

  • 1. Tecnatom, S.A., Madrid (Spain)

Description

The tubing of the Steam Generators constitutes more than half of the reactor coolant pressure boundary. Specific requirements governing the maintenance of steam generator tubes integrity are set in Plant Technical Specifications and in Section XI of the ASME Boiler and Pressure Vessel Code. The operating experience of Steam Generator tubes of PWR plants has shown the existence of some types of degradatory processes. Every one of these has an specific cause and affects one or more zones of the tubes. In the case of Spanish Power Plants, and depending on the particular Plant considered, they should be mentioned the Primary Water Stress Corrosion Cracking (PWSCC) at the roll transition zone (RTZ), the Outside Diameter Stress Corrosion Cracking (ODSCC) at the Tube Support Plate (TSP) intersections and the fretting with the Anti-Vibration Bars (AVBs) or with the Support Plates in the preheater zone. The In-Service Inspections by Eddy Currents constitutes the standard method for assuring the SG tubes integrity and they permit the monitoring of the defects during the service life of the plant. When the degradation reaches a determined limit, called the plugging limit, the SG tube must be either repaired or retired from service by plugging. Customarily, the plugging limit is related to the depth of the defect. Such depth is typically 40% of the wall thickness of the tube and is applicable to any type of defect in the tube. In its origin, that limit was established for tubes thinned by wastage, which was the predominant degradation in the seventies. The application of this criterion for axial crack-like defects, as, for instance, those due to PWSCC in the roll transition zone, has lead to an excessive and unnecessary number of tubes being plugged. This has lead to the development of defect specific plugging criteria. Examples of the application of such criteria are discussed in the article

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Additional details

Publishing Information

Imprint Title
Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants
Imprint Pagination
621 p.
Journal Page Range
p. 359-370.
Report number
NUREG/CP--0154

Conference

Title
CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants.
Dates
30 Oct - 2 Nov 1995.
Place
Oak Brook, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28068495
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFECTS; EVALUATION; MAINTENANCE; PLUGGING; PWR TYPE REACTORS; REGULATIONS; STEAM GENERATORS; TUBES
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; LAWS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information