ML19322B610

Responds to NRC 751015 Ltr.Discusses Review of Design Basis for Reactor Vessel Support Sys & Concludes That Further Analysis Not Required to Assure Public Health & Safety. Forwards Model Used to Calculate Support Sys Loads

Date released: 12/02/2019	Download: ML19322B610

Reactor Vessel Support Evaluation for LOCA Loadings.

ML19322B612
Person / Time
Site:	Oconee
Issue date:	11/14/1975
From:	DUKE POWER CO.
To:
References
Download: ML19322B612 (3)

Responds to NRC 751015 Ltr.Discusses Review of Design Basis for Reactor Vessel Support Sys & Concludes That Further Analysis Not Required to Assure Public Health & Safety. Forwards Model Used to Calculate Support Sys Loads

ML19322B609
Person / Time
Site:	Oconee
Issue date:	11/14/1975
From:	Parker W DUKE POWER CO.
To:	RUSCHE B C Office of Nuclear Reactor Regulation
References
Download: ML19322B609 (1)