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Forwards safety evaluation re induced neutron flux error for B&W reactors.Limits on DNB & ctr fuel melt not exceeded due to errors & no changes required for present operating parameters.

Accession Number: ML20052D033

Date Released: Friday, November 6, 2020

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• ML20052D032 - Forwards safety evaluation re induced neutron flux error for B&W reactors.Limits on DNB & ctr fuel melt not exceeded due to errors & no changes required for present operating parameters. (2 page(s), 4/21/1982)
• ML20052D037 - Safety evaluation re induced neutron flux errors for B&W reactors. (7 page(s), 4/21/1982)