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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

• ML20128L149  + (Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Items 3.1.1 & 2,3.2.1 & 2,4.1 & 4.5.1 Re post- Maint Testing & Reactor Trip Sys Reliability)
• ML20035G059  + (Safety Evaluation Supporting Licensee Request for Relief from Requirements of ASME Section XI)
• ML19325D418  + (Safety Evaluation Supporting Licensee Request for Relief from ASME Boiler & Pressure Vessel Code Requirements Re Weld Repair)
• ML18107A393  + (Safety Evaluation Supporting Licensee Response to GL 95-07)
• ML17342B325  + (Safety Evaluation Supporting Licensee Use of Retran Computer Code for Sys Transient Analyses & Approving Licensee Topical Rept on PWR Lattice Physics Methodology)
• ML20128J152  + (Safety Evaluation Supporting Licensee post-trip Review Data & Info Capabilities,Per Generic Ltr 83-28,Item 1.2)
• ML20154M656  + (Safety Evaluation Supporting Licensee post-trip Review Program & Procedures Per Generic Ltr 83-28,Item 1.1 Re Generic Implications for Salem ATWS Events)
• ML20052A773  + (Safety Evaluation Supporting Licensing of GE Test Reactor)
• ML20002C569  + (Safety Evaluation Supporting Limited ECCS Exemption for 1978 Operating Cycle)
• ML20141C815  + (Safety Evaluation Supporting Limited Use of Cable Splices in Low Energy Circuits within Control Panels)
• ML20204C100  + (Safety Evaluation Supporting Listed Util Responses & Actions Reviewed During Insp on 840913-19 Re Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1)
• ML19350B179  + (Safety Evaluation Supporting Low Head Safety Injection & Outside Recirculation Spray Pump Operability)
• ML19340F141  + (Safety Evaluation Supporting Mechanical Operability of Purge & Vent Valves.Containment Isolation Capability of Valves in Closed Position Acceptable)
• ML20148P461  + (Safety Evaluation Supporting Microbiologically Induced Corrosion (MIC) Program in ERCW Sys)
• ML20203D760  + (Safety Evaluation Supporting Millstone 1 Certified Fuel Handler Training & Retraining Program)
• ML18130A619  + (Safety Evaluation Supporting Mod of 480-volt Emergency Power Sys)
• ML19345B049  + (Safety Evaluation Supporting Mod of 800211 Order by Providing for Use of Mini Decay Heat Removal Sys)
• ML19263E770  + (Safety Evaluation Supporting Mod of Design of Redundant Instrument Sensing Lines for Reactor Coolant Flow)
• ML20031A887  + (Safety Evaluation Supporting Mod of Ofc of Nuclear Reactor Regulation 800211 Order.Certificate of Svc Encl)
• ML20052A959  + (Safety Evaluation Supporting Mod of Spent Fuel Storage Pool)
• ML19270H193  + (Safety Evaluation Supporting Mod of Zr-water Correction to ECCS Analysis)
• ML13330B199  + (Safety Evaluation Supporting Mod to Enhance Availability of Second Source of Offsite Power at Facility)
• ML18029A676  + (Safety Evaluation Supporting Mod to Reactor Protection Sys/ Power Monitoring Sys Design)
• ML19273B658  + (Safety Evaluation Supporting Mod to Safety Injection Actuation Sys)
• ML14190A316  + (Safety Evaluation Supporting Mod to Safety Injection Actuation Sys)

• ML13309B313  + (Safety Evaluation Supporting Mod to Startup Test Program)

• ML17278A670  + (Safety Evaluation Supporting Mod to Tech Specs Re Operation W/One Recirculation Loop Out of Svc)
• ML20214X180  + (Safety Evaluation Supporting Modified Design Basis Documented in Amend 61)
• ML20212F158  + (Safety Evaluation Supporting Mods Re Axial Power Shape Issue,Large Break LOCA ECCS Evaluation Model,Phase I,For Cycle 10 Operation)
• ML17320A781  + (Safety Evaluation Supporting Mods Re IE Bulletin 80-11, Masonry Wall Design)
• ML19347C533  + (Safety Evaluation Supporting Mods Re Potential of Facility to Withstand Rupture of High Energy Lines Outside of Containment)
• ML19329A177  + (Safety Evaluation Supporting Mods to 230 Kv Switchyard)
• ML20246F277  + (Safety Evaluation Supporting Mods to ECCS Evaluation Model, Including Changes to FLECHT-based Reflood Heat Transfer Correlation,Steam Cooling Model & post-critical Heat Flux Heat Transfer Model)
• ML13322A976  + (Safety Evaluation Supporting Mods to ESF & Radiation Protection Sys Single Failure Analysis)
• ML20005A939  + (Safety Evaluation Supporting Mods to Large Break LOCA Model)
• ML19323F924  + (Safety Evaluation Supporting Mods to Power Supplies Providing Addl Assurance That Loss of Offsite Power Would Not Cause Diesel Generator Overload)
• ML19260A275  + (Safety Evaluation Supporting Mods to Tech Specs Re Local Power Range Monitor Requirements & Reduction of Pressure at Which Scram Time Surveillance Tests Are Conducted)
• ML17339A702  + (Safety Evaluation Supporting Mods to Tech Specs Re low-low Generator Water Level Reactor Trip Setpoint Change.Mod Will Increase Min Setpoint from 5 to 15% of Narrow Range Instrument Scale)
• ML20058N818  + (Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Jm Farley Nuclear Plant Units 1 & 2)
• ML20155D428  + (Safety Evaluation Supporting More Negative End-of-Life Moderator Temp Coefficient Tech Spec for Millstone Unit 3)
• ML20082T355  + (Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Aw Vogtle Nuclear Plant Units 1 & 2)
• ML20011F749  + (Safety Evaluation Supporting More Negative End-of-Life Moderator Temp Coefficient Tech Spec for Salem Units 1 & 2)
• ML19340E366  + (Safety Evaluation Supporting Movement & Insertion of Single Fuel Assembly Into Different Locations of Core for Indexing Purposes.License Amend Recommended)
• ML17059C570  + (Safety Evaluation Supporting NMPC Responses to NRC Bulletin 95-002, Unexpected Clogging of Rhrp Strainer While Operating in Suppression Pool Cooling Mode)
• ML17353A244  + (Safety Evaluation Supporting NRC Independent Flaw Calculations to Evaluate Licensee LBB Analysis of Large Diameter Reactor Coolant Piping for Plant,Units 3 & 4)
• ML19319A660  + (Safety Evaluation Supporting NRC Review of Fuel Rod Removal from Assembly 1D40)
• ML20198D075  + (Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding)
• ML20197C477  + (Safety Evaluation Supporting Nine Mile Point Unit 1 Reactor & Turbine Building Blowout Panels)
• ML20147H929  + (Safety Evaluation Supporting Nuclear Safety Review Staff Recommendations Requiring Resolution Before Restart of Facility)
• ML18033A736  + (Safety Evaluation Supporting Operatiion After Restoration & Mod of Facilities Following 750322 Fire)
• ML20117C656  + (Safety Evaluation Supporting Operation W/Missing Pipe Restraints for High Energy Lines Outside Containment)