Technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun Nuclear Power Plant

Technical Report · Tue Jan 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/5495224· OSTI ID:5495224

Hackett, D B

This report documents the technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun nuclear power plant. The review criteria are based on IEEE Std-279-1971 requirements for the safety signals to all purge and ventilation isolation valves. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory.

• Research Organization: EG and G, Inc., San Ramon, CA (USA). Energy Measurements Group
• DOE Contract Number: EY-76-C-08-1183
• OSTI ID: 5495224
• Report Number(s): UCRL-15172; TRN: 80-005634
• Country of Publication: United States
• Language: English

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