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List of results

• ML17317A471  + (Evaluation of Proposed Change Regarding Revision to the Emergency Plan for Technical Support Center Relocation & Revised Pages to Emergency Plan)
• ML15091A661  + (Evaluation of Proposed Change Regarding Proposed License Amendment to Adopt Emergency Action Level Scheme)
• ML19322C099  + (Evaluation of Proposed Changes to Tech Specs for Facility Reload Cycle 2 & Supporting BAW-1409 Rept.Densification Analysis Acceptable,Provided Addl Info Submitted)
• ML093360321  + (Evaluation of Proposed Emergency Action Level Revision)
• ML092720671  + (Evaluation of Proposed Emergency Action Level Revision)
• ML090130047  + (Evaluation of Proposed Emergency Action Level Revision)
• ML082200367  + (Evaluation of Proposed Emergency Action Levels)
• ML040220124  + (Evaluation of Proposed Interim Staff Guidance (ISG)-11: Recommendations for Fatigue Environmental Effects in a License Renewal Application)
• ML072610510  + (Evaluation of Proposed Risk-Informed Request for an Inservice Inspection Program)
• ML20083J994  + (Evaluation of Proposed Special Test Exception for Diesel Generator & Essential Cooling Water Maintenance)
• ML20078N358  + (Evaluation of Proposed Wildlife Mgt Lake, Final Rept)
• ML20234E306  + (Evaluation of Protective Action Risks)
• ML20070D089  + (Evaluation of Quad Cities Nuclear Power Station - Commonwealth Edison Co,1982)
• ML20031F166  + (Evaluation of Quarterly Progress Rept 3,Research Program on Hydrogen Combustion & Control,)
• ML17355A458  + (Evaluation of Question Bank Only Generic Fundamentals Exam Final 12-20-17)
• Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters  + (Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters)
• ML16092A034  + (Evaluation of RBS Remote Shutdown Panel Rooms)
• 05000461/FIN-2017012-03  + (Evaluation of RCE 04082490, Reactor Scram from Trip of 1AP07EJ))
• 05000461/FIN-2014008-02  + (Evaluation of RCE 1594407 Against Inspection Procedure 95001 Objectives)
• ML20137E719  + (Evaluation of RCS Components & Component Supports for Optimized Reactor Coolant Pump Support Configuration Loadings)
• ML20134P031  + (Evaluation of RCS Loads & Component Support Margins Resulting from Optimized Reactor Coolant Pump Support Configuration)
• ML20214V192  + (Evaluation of RCS for Elimination of Primary Component Support Snubbers)
• ML20235A514  + (Evaluation of RCS for Steam Generator Upper Support Redesign)
• ML20077E548  + (Evaluation of RTV Coatings for Post Insulators, Interim Rept)
• ML13317A021  + (Evaluation of RWST for Buckling)

• ML20008F321  + (Evaluation of Radiation Protection Plan)

• ML19259C725  + (Evaluation of Radiation Streaming, Informal Progress Rept as of 790715)
• ML19209C247  + (Evaluation of Radiation Streaming.Monthly Progress Rept as of 790815)
• ML20140G645  + (Evaluation of Radioactive Liquid Effluent Releases from Rancho Seco Nuclear Power Plant)
• ML20150B630  + (Evaluation of Radioiodine Measurements at Pilgrim Nuclear Power Plant)
• ML19289F920  + (Evaluation of Radiolysis Associated W/TMI-2 Incident)
• ML20132B021  + (Evaluation of Radionuclide Geochemical Information Developed by DOE HIGH-LEVEL Nuclear Waste Repository Site Projects.Annual Progress Report for October 1983-September 1984)
• ML20083K578  + (Evaluation of Radionuclide Geochemical Information Developed by DOE HIGH-LEVEL Nuclear Waste Repository Site Projects)
• ML20050B779  + (Evaluation of Rancho Seco Nuclear Generating Station- Unit 1, Feb 1982)
• ML20132C668  + (Evaluation of Rcic,Turbine Exhaust Pressure Trip for LOCA Application)
• ML20010E943  + (Evaluation of Reactivity Response for Steam Line Break Event W/Unterminated Emergency Feedwater Flow)
• ML13323A456  + (Evaluation of Reactor Coolant Pump Restart Criteria for San Onofre Unit 1)
• ML17256A404  + (Evaluation of Reactor Coolant Pump Restart Requirements Following Steam Generator Tube Failure at Re Ginna Nuclear Power Plant)
• ML18078A942  + (Evaluation of Reactor Coolant Sys Considering Subcompartment Pressurization Following a Loca)
• ML18092A176  + (Evaluation of Reactor Pressure Vessel Head & Internals Lift Rigs for Salem Units 1 & 2)
• ML022770461  + (Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Figures 21 - 70)
• ML022760264  + (Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Memorandum Dated 09/27/02 - Figure 20)
• ML19326C701  + (Evaluation of Reactor Protection Sys Grounding Concern)
• ML19273B907  + (Evaluation of Reactor Vessel Brittle Failure Due to Injection of Cold HPI Water During Small LOCA Events)
• ML072530532  + (Evaluation of Reactor Vessel Head Inspection Data for Control Element Drive Mechanism (CEDM) 56)
• ML20056F294  + (Evaluation of Reactor Vessel OD Flaw (PIP 2-M93-0717))
• ML20009C775  + (Evaluation of Reattachment Welds for Loft Cladding Thermocouples, Interim Rept)
• ML20207Q715  + (Evaluation of Recirculation Sys Flow Anomaly in Pilgrim Nuclear Power Station, Informal Technical Evaluation Rept)
• ML20043C956  + (Evaluation of Reinforced Concrete Gamma Pit,Canal & Holdup Tank Cintichem Plant,Tuxedo,Ny)
• ML20031E066  + (Evaluation of Relative Surface Properties of Alternative Nuclear Waste Encapsulates, Quarterly rept,Jan-Mar 1981)
• ML20031E064  + (Evaluation of Relative Surface Properties of Alternative Nuclear Waste Encapsulates, Interim Progress Rept & Renewal Proposal)