Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants (NUREG/CR-6715)
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Manuscript Completed: March 2001
Date Published: April 2001
J. I Braverman, C. A.
Miller B. R. Ellingwooda
D. J. Nausb
C. H. Hofinayer, S. Shteyngart, P. Bezler
Brookhaven National Laboratory
Upton, NY 11973-5000
aSchool of Civil and Environmental Engineering
Georgia Institute of Technology
Atlanta, GA 30332
bOak Ridge National Laboratory
Oak Ridge, TN 37831
T. Y. Chang, NRC Project Manager
Division of Engineering Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code W6245
This report describes the research performed to address concerns related to aging degradation of reinforced concrete structures at nuclear power plants (NPPs). The aging effects due to reinforced concrete degradation mechanisms are studied in order to develop analytical methods and degradation acceptance limits for concrete flexural and shear wall members. The focus of this phase of the research program is to perform a probability-based evaluation of degraded reinforced concrete members. The research effort develops fragility modeling procedures for undegraded and degraded reinforced concrete structural components subjected to earthquake ground motions. These quantitative methods provide a basis for evaluating reinforced concrete structures in nuclear plants for continued service and for developing guidelines for in-service inspection and repair. The probability-based degradation acceptance limits that are developed can be used as a tool for making risk-informed decisions regarding degradation of reinforced concrete members.
This study is being conducted under Phase II of a multi-year research program sponsored by the Nuclear Regulatory Commission (NRC) to assess age-related degradation of structures and passive components for U.S. nuclear power plants. A full description of the Phase I effort, which has identified reinforced concrete members and other components for further research in Phase HI, is presented in NUREG/CR-6679.