Reliability of Sampling Inspection Schemes Applied to Replacement Steam Generators

Author:

Roussel Guy1,Cizelj Leon2

Affiliation:

1. Association Vinçotte Nuclear, Rue Walcourt 148 Walcourtstraat, B-1070 Brussels, Belgium

2. Institut “Jožef Stefan,” Jamova 39, SI-1000 Ljubljana, Slovenia

Abstract

The basis for determining the size of the random sample of tubes to be inspected in replacement steam generators is revisited in this paper. A procedure to estimate the maximum number of defective tubes left in the steam generator after no defective tubes have been detected in the randomly selected inspection sample is proposed. A Bayesian estimation is used to obtain closed-form solutions for uniform, triangular, and binomial prior densities describing the number of failed tubes in steam generators. It is shown that the particular way of selecting the random inspection sample (e.g., one sample from both SG, one sample from each SG, etc.) does not affect the results of the inspection and also the information obtained about the state of the uninspected tubing, as long as the inspected steam generators belong to the same population. Numerical examples further demonstrate two possible states of the knowledge existing before the inspection of the tubing. First, virtually no knowledge about the state of the steam generator tubing before the inspection is modeled using uniform and triangular prior densities. It is shown that the knowledge about the uninspected part of the tubing strongly depends on the size of the sample inspected. Further, even small inspection samples may significantly improve our knowledge about the uninspected part. On the other hand, rather strong belief on the state of the tubing prior to the inspection is modeled using binomial prior density. In this case, the knowledge about the uninspected part of the tubing is virtually independent on the size of the sample. Furthermore, it is shown qualitatively and quantitatively that such inspection brings no additional knowledge on the uninspected part of the tubing.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference8 articles.

1. 1998, PWR Steam Generator Examination Guidelines: Revision 5, Volume 2: Technical Basis, EPRI Report No. TR-107569-V2R5.

2. Roussel, G., and Cizelj, L., 2005, Selection of Samples for Inservice Inspection of Steam Generator Tubes, ASME Pressure Vessels and Piping Conference, Denver, CO.

3. Banic, M. J. et al. , 1996, Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generator, IAEA Safety Series, International Atomic Energy Agency, Vienna.

4. Probabilistic Evaluation of Leak Rates Through Multiple Defects: The Case of Nuclear Steam Generators;Cizelj;Fatigue Fract. Eng. Mater. Struct.

5. Reliability of Steam Generator Tubes with Axial Cracks;Cizelj;J. Pressure Vessel Technol.

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