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Responds to AEC 700806 ltr re sensitive stainless steel components in RCS.Complete engineering rept will be submitted by 700930.
Accession Number: ML20090C760
Date Released: Saturday, October 26, 2024
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- ML20090C756 - Responds to AEC 700806 ltr re sensitive stainless steel components in RCS.Complete engineering rept will be submitted by 700930. (1 page(s), 8/28/1970)
- ML20090C770 - Forwards Westinghouse field rept "Repair & Insp of CT-Yankee Steam Generator Primary Nozzle Safe-Ends,May-June 1970," per 700526 meeting in Washington,DC. (1 page(s), 7/29/1970)
- ML20090C783 - "Repair & Insp of CT-Yankee Steam Generator Primary Nozzle Safe-Ends,May-June 1970." (11 page(s), 7/15/1970)
- ML20090C792 - Forwards ltr & rept "Metallurgical Review & Analysis of Reactor Component Failures at CT Yankee Atomic Power Station." Rept supports previous recommendations re component failures discussed in 700605 memo. (1 page(s), 7/10/1970)
- ML20090C812 - Forward "Metallurgical Review & Analysis of Reactor Component Failures at CT Yankee Atomic Power Station." (1 page(s), 6/30/1970)
- ML20090C820 - "Metallurgical Review & Analysis of Reactor Component Failures at CT Yankee Atomic Power Station." (14 page(s), 6/11/1970)
- ML20090C826 - Requests that encl proposed ltr re inservice failure of stainless steel in primary reactor coolant sys be sent to listed licensees. (2 page(s), 5/28/1970)
- ML20090C835 - Forwards SWRI 700520 ltr rept re investigation of furnace sensitive safe-ends.Rept will be discussed at 700526 meeting w/AEC. (8 page(s), 5/22/1970)
- ML20090C849 - Submits info re steam generator safe-end cracks found on steam generator 2.Cause of cracks unknown. (2 page(s), 5/15/1970)
- ML20090C862 - Inquiry Memorandum 50-213/70-D re surface indication on steam generator nozzle shop weld. (2 page(s), 5/15/1970)
- ML20090C873 - Informs that preliminary exam of safe-end on one steam generator revealed indication of cracks on outside surface of shop weld between steam generator nozzle & safe-end. (1 page(s), 5/13/1970)
