Digital Instrumentation and Control Systems in Nuclear Power Plants Safety and Reliability Issues (1997) / Chapter Skim
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Pages 51-55
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From page 51... ...
The USNRC should maintain its basic position regarding the need for diversity in digital instrumentation and control (I&C) systems as stated in the draft branch technical position, Digital Instrumentation and Control Systems in Advanced Plants, and its counterpart for existing plants.
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From page 52... ...
These methods must be sufficiently robust, justified, and understandable to be useful in assuring the public that using digital I&C technology in fact enhances public safety. Statement of the Issue Effective, efficient methods are needed to assess the safety and reliability of digital I&C systems in nuclear power plants.
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From page 53... ...
event, but at the same time defines how the probability of the end event is calculated as a function of the probabilities of the basic events. Thus the fault tree model can evolve as the system evolves and can at any time evaluate the effect of proposed changes on the reliability and safety of the nuclear power plant.
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From page 54... ...
Applicability to Digital Systems Deterministic analysis techniques for digital systems are a generalization of the design basis accident methodology used in the nuclear industry and include such techniques as hazard analysis and formal methods (Leveson, 1995; Rushby,1995~. The use of deterministic analysis techniques for the analysis of digital systems is not controversial, as long as they are applied with care to consider the failure modes attributable to digital systems.
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From page 55... ...
The fault tree analysis included such failure modes as inadvertent operator actions, software failures, physical damage from external events, lack of coverage, and hardware component and communication failures.
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