Home > NRC Library > ADAMS Public Documents

Advises that specific & generic aspects of RO 77-52 re unresolved safety question involving moderator dilution are under review by Div of Operating Reactors.Transfer of lead responsibility not needed.

Accession Number: ML19329D697

Date Released: Saturday, November 7, 2020

Package Contents

The following links on this page are to Adobe Portable Document Format (PDF) files. To obtain a free viewer for displaying this format, see our Plugins, Viewers, and Other Tools.

• ML19329D696 - Advises that specific & generic aspects of RO 77-52 re unresolved safety question involving moderator dilution are under review by Div of Operating Reactors.Transfer of lead responsibility not needed. (1 page(s), 8/1/1977)
• ML19329D698 - Forwards util 770620 ltr & RO 77-52 re unresolved safety question involving moderator dilution.Transfer of lead responsibility should be transferred to Ofc of Nuclear Reactor Regulation. (1 page(s), 6/29/1977)
• ML19329D699 - Forwards RO 77-52. (1 page(s), 6/20/1977)
• ML19329D700 - RO 77-52:on 770614,B&W evaluation of RO 77-17 indicated possible unreviewed safety question re moderator dilution. Possibly caused by unterminated injection of sodium hydroxide tank contents into RCS causing core criticality. (3 page(s), 6/20/1977)
• ML19329D701 - Confirms possibility of unreviewed safety question re moderator dilution due to unterminated injection of sodium hydroxide tank contents into RCS.Administrative & physical controls provided to preclude occurrence. (2 page(s), 6/15/1977)