Modification of the control rod drives from electromechanical-hydraulic to completely hydraulic system, revisions to the reactor safety system, refinements in the reactor physics data, and effects of these changes on the safety analyses are discussed. Answers on specific safety questions pesed by the AEC are given. (W.D.M.)
U.S. Atomic Energy Commission depository collection.
Note
NSA number: NSA-14-025055 OSTI Identifier 4149544 Research organization: Commonwealth Edison Co., Chicago. Research organization: General Electric Co. Atomic Power Equipment Dept., Schenectady, N.Y..