Alternate tube plugging criteria for steam generator tubes
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
Files
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
- Secondary number(s)
- ANL--96/14; NEA/CNRA/R--(96)1; CONF-9510423--.