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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML15244A224  + (Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Reevaluation of RT (PTS) & Comparison to Predicted Value W/Future Submittals Requested)
• ML17251A870  + (Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Reevaluation of Resistor Temp PTS & Comparison to Pressure Temp Operating Limits Required by 10CFR50,App G)
• ML17219A352  + (Safety Evaluation Re Projected Values on Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Values Acceptable)
• ML17219A353  + (Safety Evaluation Re Projected Values on Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Values Acceptable)
• ML17202G580  + (Safety Evaluation Re Proposed Amends to Licenses DPR-19 & DPR-25,revising Testing Requirements of ECCS & Standby Gas Treatment Sys)
• ML17053D667  + (Safety Evaluation Re Proposed Changes to Revetment Ditch Sys.Use of Proposed Graded Granular Sys Acceptable Alternate to Filter Fabric)
• ML20024G410  + (Safety Evaluation Re Proposed Changes to Facility Tech Spec to Incorporate New Guidelines to Ensure Operability of Licensee Fire Protection Equipment)
• ML19249C390  + (Safety Evaluation Re Proposed Changes to Tech Specs Concerning Dc Electrical Power Sys Surveillance Requirements)
• ML18024B212  + (Safety Evaluation Re Proposed Changes to Tech Specs LPCI Sys.Technical Evaluation Rept Re Tech Specs Change Encl)
• ML17264A146  + (Safety Evaluation Re Proposed Criticality Analysis of Ginna New & Sf Racks/Consolidated Rod Storage Canisters for Ginna Npp.Finds Proposed Criticality Analysis Acceptable)
• ML20054H889  + (Safety Evaluation Re Proposed Facility Mods to Increase Capacity of Spent Fuel Storage Pool.Mods Acceptable Subj to Resolution of Open Items)
• IR 05000341/1985050  + (Safety Evaluation Re Proposed Fire Protection Mod to Independent Alternative Safe Shutdown Capability to Satisfy Open Items in Insp 50-341/85-50)
• ML20237D528  + (Safety Evaluation Re Proposed Increase in Sf Pool Heat Loads for Plant)
• ML20198S684  + (Safety Evaluation Re Proposed Merger of Calenergy Co,Inc & Midamarican Energy Holdings Co.Nrc Should Approve Application with Listed Condition)
• ML19256D698  + (Safety Evaluation Re Proposed Mods to Spent Fuel Pool Storage Capacity.Mods in Accordance W/Acceptable Criteria. Pool Structural Integrity & Leak Tightness Adequate for New Loading Conditions)
• ML19260C350  + (Safety Evaluation Re Proposed Mods to Triga Reactor Console Electronics)
• ML20235D243  + (Safety Evaluation Re Proposed Onsite Storage of Liquid Oxygen & Hydrogen for Implementation of Hydrogen Water Chemistry.Permanent Hydrogen Water Installation Acceptable)
• ML17180B487  + (Safety Evaluation Re Proposed Repair for Core Shroud at Dresden Nuclear Power Station,Units 2 & 3)
• ML20206F365  + (Safety Evaluation Re Proposed Repair of Core Spray safe- Ends,During Current Refueling Outage.Plant Can Be Safely Returned to Power Operation After Satisfactory Completion of Core Spray safe-end Repairs)
• ML20154F889  + (Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R.Licensee Request for Exemptions in Listed Areas Should Be Granted.Concept for Providing post-fire Shutdown Acceptable)
• ML18032A253  + (Safety Evaluation Re Proposed Tech Spec Rev Concerning Fire Detector Surveillance)
• ML19262C503  + (Safety Evaluation Re Proposed Tech Specs Change for High Pressurizer Pressure Trip Setpoint)
• ML19256D300  + (Safety Evaluation Re Protection,Control & Emergency Power Systems.Systems Acceptable)
• ML19261F070  + (Safety Evaluation Re Protection,Control & Emergency Power Sys.Approves General Design.Deficiency Noted:Lighting Fixtures of Unknown Seismic Integrity Suspended Directly Over Both Batteries.Referred to Div of Licensing for Review)
• ML14192A729  + (Safety Evaluation Re Pump & Valve Inservice Testing Program. NRC Positions Re Valves Discussed in Evaluation Should Be Reviewed.Valves Should Be Included in Program or Justification Provided)

• ML20197D296  + (Safety Evaluation Re Pump & Valve Inservice Testing Program)

• ML20027E277  + (Safety Evaluation Re Purge & Vent Operability.Forty 8-inch Butterfly Purge Valve Operability Not Demonstrated in Event of LOCA)
• ML19256E593  + (Safety Evaluation Re Qualifications of Reactor Physics Methods for Application to Kewaunee. Reliability of Each Physics Parameter Acceptable)
• ML19343B742  + (Safety Evaluation Re RCS Pressure Safety Limit Mods.Mod Does Not Authorize Change in Effluent Types or Total Amounts Nor Increase in Power Level)
• ML20035C277  + (Safety Evaluation Re RG 1.97 Concerning BWR Neutron Flux Monitoring)
• ML20035D167  + (Safety Evaluation Re RG 1.97 post-accident Neutron Flux Monitoring Instrumentation for BWRs)
• ML19327A037  + (Safety Evaluation Re RHR Pump Suction Line Insp.Crack Is Not Generic.Weld Repair Was Effective)
• ML20129E172  + (Safety Evaluation Re Radiological Consequences of Hypothetical LOCA While Purging Containment at Power. Radiological Consequences Acceptable)
• ML20028F043  + (Safety Evaluation Re Radiological Field Operations Training Program.Program Acceptable Subj to Incorporation of Certain Experience Requirements for Radiological Control Foreman & Technicians)
• ML17054A378  + (Safety Evaluation Re Reactor Bldg Wall Crack.Facility Can Safely Operate Until long-term Corrective Decoupling of Reactor Bldg & Screenhouse Wall Completed in Spring 1984 Refueling Outage)
• ML20236D911  + (Safety Evaluation Re Reactor Coolant Pump Flywheel Integrity.Matl,Fabrication,Design & Insp Aspects of Flywheels Acceptable)
• ML20207K072  + (Safety Evaluation Re Reactor Coolant Pump Shaft Integrity Issue at Facility.Licensee Adequately Informed & Trained Operators as to Symptons & Actions to Be Taken Re Reactor Coolant Pump Sheared Shaft Event.Responses Acceptable)
• ML20235K924  + (Safety Evaluation Re Reactor Pressure Vessel Flaw.Flaw Conditionally Acceptable Per Subarticle IWB-3123 of Section XI of ASME Code & Therefore Requires Augmented Inservice Insps Based on 10CFR50.55(g)(4))
• ML20012E502  + (Safety Evaluation Re Reactor Protection Sys Upgrade Phase 1. Sys & Hardware Design Provides Reasonable Assurance to Perform Safety Functions Per Updated FSAR & Tech Specs)
• ML20137B578  + (Safety Evaluation Re Reactor Trip Sys Reliability (vendor- Related Mods),Item 4.1 of Generic Ltr 83-28.Licensee Response to Vendor Recommended Mods for Reactor Trip Sys Acceptable)
• ML20235F624  + (Safety Evaluation Re Reactor Trip Sys Reliability,Items 4.2.3 & 4.2.4 of Generic Ltr 83-28.Licensee Response Acceptable)
• ML17055E175  + (Safety Evaluation Re Reactor Vessel Pressure Temp Limits & Surveillance Program)
• ML17345A212  + (Safety Evaluation Re Reactor Vessel Toughness.Addl Analysis & Matl Test Data Needed to Confirm That Reactor Vessels Will Meet Safety Margins of App G of ASME Code & 10CFR50 for 40 EFPY)
• ML17219A464  + (Safety Evaluation Re Reanalysis of Postulated Loss of Nonemergency Ac Power & Seized Rotor Events.Analysis Acceptable)
• ML19221A717  + (Safety Evaluation Re Reanalysis of Small Break LOCA W/O Charging Pump Injection)
• ML19327A029  + (Safety Evaluation Re Recirculation Inlet Nozzle Safe End Insp Program.Safe Ends Are Acceptable for Continued Operation.Licensee Should Implement Insp Program)
• ML17054B608  + (Safety Evaluation Re Recombiner Capability Requirements of 10CFR50.44 in Response to Generic Ltr 84-09.Recombiner Capability Not Required)
• ML20148L164  + (Safety Evaluation Re Recommended Mod to Reg Guide 1.76, Tornado Design Basis for Advanced Light Water Reactor. Tornado Design Criteria in Table 2 Acceptable on Interim Basis for Advanced LWRs Until Reg Guide Revised)
• ML20137D837  + (Safety Evaluation Re Refueling Procedures to Licenses DPR-67 & NPF-16)
• ML20029A721  + (Safety Evaluation Re Refueling Water Storage Tank at Plant)
• ML20035E417  + (Safety Evaluation Re Reg Guide 1.97 Involving post-accident Neutron Flux Monitoring Instrumentation for BWRs)