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Pages 18-21

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From page 18...
... a reduced margin of safety as defined in the licensing basis for any technical specification. USNRC regulatory treatment of upgrades or modifications to nuclear power plants may be summarized as follows: If there is a change in technical specifications, the licensee must seek prior USNRC approval via 10 CFR 50.90.
From page 19...
... Hence, in addition to coping with uncertainties arising from digital technology itself, its use may require changes or additions to the underlying technical infrastructure and regulatory framework. Technical Problems Identifiedfrom Some Applications of Digital I&C in Nuclear Power Plants.
From page 20...
... , common-mode failure, configuration management,8 and systems integration the need for an overarching strategy to guide regulatory developments and the certification process for the new technology the rapid pace of technological changes that affect I&C systems, including developments in the areas of artificial intelligence, expert systems, neural networks, fuzzy logic, genetic algorithms, and chaos theory To address technical concerns, and in hopes of developing a wide consensus across the USNRC and the nuclear industry for a regulatory program, the USNRC held a workshop on digital systems reliability and nuclear safety, cosponsored by the National Institute of Standards and Technology, in September 1993 (USNRC, 1993a)
From page 21...
... The six technical issues are: systems aspects of digital I&C technology; software quality assurance; common-mode software failure potential; safety and reliability assessment methods; human factors and human-machine interfaces; and dedication of commercial off-the-shelf hardware and software. The two strategic issues are the case-by-case licensing procedure and adequacy of the technical infrastructure.


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