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- W346979043 abstract "Probabilistic risk assessment (PRA) methods are used to evaluate alternatives to existing requirements for three operationally burdensome technical specifications at La Salle Nuclear Station. The study employs a decision logic to minimize the detailed analysis necessary to show compliance with given acceptance criteria; in this case, no risk increase resulting from a proposed change. The analyses provide insights to choose from among alternative options. The SOCRATES computer code was used for the probabilistic analysis. Results support a change to less frequent diesel generator testing, eliminations of one reactor scram setpoint, and establishing an allowed out-of-service time for valves in a reactor scram system. In each case, the change would result in a safety improvement." @default.
- W346979043 created "2016-06-24" @default.
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- W346979043 date "1987-06-01" @default.
- W346979043 modified "2023-09-27" @default.
- W346979043 title "Risk-based evaluation of technical specification problems at the La Salle County Nuclear Station: Final report" @default.
- W346979043 hasPublicationYear "1987" @default.
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