United States Nuclear Regulatory Commission - Protecting People and the Environment

Steam Generator Tube Integrity Program Semiannual Report: October 1998 – March 1999 (NUREG/CR-6511, Volume 7)

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Publication Information

Manuscript Completed: June 2000
Date Published: September 2000

Prepared by:
D. R. Diercks, S. Bakhtiari, K. E. Kasza, D. S. Kupperman,
S. Majumdar, J. Y. Park, W. J. Shack

Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439

J. Muscara, NRC Project Manager

Prepared for:
Division of Engineering Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC Job Code W6487

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Abstract

This report summarizes work performed by Argonne National Laboratory on the Steam Generator Tube Integrity Program during the period October 1998 through March 1999. The program is divided into five tasks: (1) Assessment of Inspection Reliability, (2) Research on In-Service-Inspection (ISI) Technology, (3) Research on Degradation Modes and Integrity, (4) Integration of Results, Methodology, and Technical Assessments for Current and Emerging Regulatory Issues, and (5) Program Management. Under Task 1, progress is reported on the status of the steam generator tube mock-up, the effect of a thin oxide corrosion product on the eddy current signal from stress corrosion cracks, and the effectiveness of +Point eddy current techniques for profiling cracks and establishing maximum flaw depths. Under Task 2, efforts focused on the multiparameter analysis of eddy current nondestructive evaluation (NDE) results, and estimated depth profiles are provided for a sA of 24 laser-notched specimens with single and multiple axial/circumferential notches. Under Task 3, pressurization and leak-rate test results are reported for tubes with electro-discharge machined (EDM) flaws as well as tubes with partthroughwall stress corrosion cracks. The design and construction of a new high-pressure test facility has also been initiated. Laboratory-induced cracking has been produced in hundreds of steam generator tubes that will subsequently be used for the evaluation of NDE equipment and techniques and for pressure and leak-rate testing. In addition, models for predicting the onset of crack growth and for calculating crack opening area and leak rate from a throughwall circumferential crack in a steam generator tube have been developed. Leak-rate models have been validated with tests on specimens with notched EDM slots, and simplified equations for calculating crack opening area have been verified with finiteelement calculations. Finally, under Task 4, results of EC and ultrasonic examinations of two cracked test sections Electrosleeved by Framatome Technologies, Inc. are presented.

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