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 Issue dateFromTitleProject stage
ML20148T00720 January 1988SACRAMENTO MUNICIPAL UTILITY DISTRICTRev 1 to STP.961, Loss of Offsite PowerOther
ML20153A85229 June 1988Office of Nuclear Reactor Regulation
Fairtile M
Forwards Safety Evaluation Accepting Util Proposed Steam Cooling Model for Large Break LOCA AnalysisApproval
ML20236C73314 March 1989Office of Nuclear Reactor Regulation
Fairtile M
Summary of 890307 Meeting W/Util in Rockville,Md Re Proposed Mods to Fletch Correlation for Use in LOCA Analysis. Attendance List EnclMeeting
ML20246F26611 July 1989Office of Nuclear Reactor Regulation
Fairtile M
Forwards Safety Evaluation Supporting Licensee 880105 & 890502 Proposed Revs to ECCS Evaluation Model.Revs Made to FLECHT-based Reflood Heat Transfer Model,Steam Cooling Model & post-critical Heat Flux Heat Transfer ModelApproval