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Control Rod Trip Failures; Salem 1, the Cause, Response, and Potential Fixes

  • Robert E. Hall
  • John L. Boccio
  • William J. Luckas

Abstract

The objective of this paper is to address the systems and reliability analysis of recent nuclear reactor control rod failure-to-trip (or scram) events that have been experienced in the U.S. commercial nuclear industry. This viewpoint will introduce the operational factors of hardware, procedures, and the human into the analysis of transients without scram.

Keywords

Fault Tree Pressurize Water Reactor Boiling Water Reactor Trip Device Reactor Coolant Pump 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    Examination of Breaker Testing Frequency for the Westinghouse RTS-NRC Internal Document.Google Scholar
  2. 2.
    The Salem Case: A Failure of Nuclear Logic, News and Comments, Science, Vol. 220.Google Scholar
  3. 3.
    Salem Breaker Incident, P. 540, Nuclear Safety, Volume 24, No. 4, July-August, 1983.Google Scholar
  4. 4.
    W. Vesely, F. Goldberg, R. Powers, J. Dickey, J. Smith, and R. Hall, FRANTIC II-A Computer Code for Time Dependent Unavailability Analysis, NUREG/CR-1924, April 1981.Google Scholar
  5. 5.
    T. Ginzburg, J. Dickey, and R. Hall, Sensitivity Study Using the FRANTIC Code for the Unavailability of a System to the Failure Characteristics of the Components and the Operating Conditions, NUREG/CR-2542, February 1982.Google Scholar

Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • Robert E. Hall
    • 1
  • John L. Boccio
    • 1
  • William J. Luckas
    • 1
  1. 1.Department of Nuclear EnergyBrookhaven National LaboratoryUptonUSA

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