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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

• ML15246A126  + (To STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSI)-191 and Respond to Generic Letter (GL) 2004-02)
• ML19338E992  + (To Safe Shutdown Analysis for Fires in Control Room,Relay Room or Cable Spreading Rooms)
• ML20217J805  + (To Safety Evaluation of EPRI Topical Rept TR-105747, BWR Vessel & Internals Project,Guidelines for Reinspection of BWR Core Shrouds (BWRVIP-07))
• ML20062M666  + (To Safety Relief Valve In-Plant Test Plan)
• ML050470048  + (To Safety and Mission Assurance Directorate, Plum Brook Reactor Facility Supplemental Characterization Report for the Plum Brook Reactor Facility)
• ML050690310  + (To Safety and Mission Assurance Directorate, Plum Brook Reactor Facility Final Status Survey Plan for the Plum Brook Reactor Facility. Attachment B: Approach & Basis for Development of Site-Specific Derived Concentration Guideline Levels)
• ML050690309  + (To Safety and Mission Assurance Directorate, Plum Brook Reactor Facility Final Status Survey Plan for the Plum Brook Reactor Facility)
• ML050900164  + (To Sandy Buchanan of Ohio Citizen Action Re Davis-Besse Mid-Cycle Outage Scope)
• ML20003H644  + (To Sar,Including Revision C to Drawing X-60-200D Re Model N-55 Type B Overpack)
• ML040900350  + (To Saxton Nuclear Experimental Corporation Facility License Termination Plan)
• ML20245A689  + (To Scenario 16, Gpu Oyster Creek Nuclear Generating Station Emergency Preparedness Exercise Scenario)
• L-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source  + (To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source)
• L-2024-037, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source  + (To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source)
• ML040770079  + (To Section 1 of Core Operating Limits Report for LaSalle, Unit 1, Cycle 11)
• ML19309F023  + (To Section 3.0 of WCAP-9402, Verification Testing & Analyses of Westinghouse 17x17 Optimized Fuel Assembly, Nonproprietary Version)
• ML20003H745  + (To Seismic Analysis of Waterford Ses Spent Fuel Storage Racks)
• ML20052D866  + (To Seismic Evaluation of Wolf Creek Generating Station Structures Using Lll Spectrum)
• ML20052B189  + (To Seismic Qualification Analysis for Series 20K Instrument & Control Switch)
• ML20038A593  + (To Settlement Update for Midland Plant Units 1 & 2)
• SBK-L-12185, To Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal Application  + (To Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal Application)
• SBK-L-12053, To Severe Accident Mitigation Alternatives Analysis, License Renewal Application  + (To Severe Accident Mitigation Alternatives Analysis, License Renewal Application)
• ML20052A664  + (To Shutdown from Outside Control Room)
• ML20054H638  + (To Single Rod Scram Insertion Times Test, Periodic Test)
• ML20053B514  + (To Site-Specific Response Spectra for Clinton Power Station Unit 1)
• ML20039F408  + (To Small Break ECCS Evaluation of B&W 205 FA NSS Using Dec 1976 ECCS Evaluation Model)

• ML20054H644  + (To Software Changes to Process Computer)

• ML20062J361  + (To Spec for Earthquake Resistance Design of Equipment Located in Reactor Bldg for Midland Unit 1 & 2)
• ML19347D013  + (To Special Low Power Tests:Safety Evaluation)
• ML20133J183  + (To Special Nuclear Material License SNM-33,for Mallinckrodt Chemical Works)
• ML19350E200  + (To Special Rept 80-3:on 801016,during Normal Operation,Fuse in Channel RB2 Failed,Giving 2 Out of 3 Condition Required for Actuation of Es Channel B.Caused by Failed Relay in Safeguards Cabinet 5B.Relay Replaced)
• ML20148K372  + (To Special Rept 96-04:on 961011,groundwater Level Was Above 731 Feet for 7 Days.Caused by Precipitation During Previous Week.Verified That No Other Groundwater Monitoring Instruments Were in Alarm)
• ML040550271  + (To Specification ME-326, Control Room Emergency Air Treatment System (Creats) and Emergency Cooling System Design, Fabrication, & Installation Specification)
• ML20054E124  + (To Spent Fuel Pool Mod)
• ML20005A992  + (To Spent Fuel Pool Mod for Increased Storage Capacity Re Licensing Rept on High Density Spent Fuel Racks)
• ML20244B633  + (To Spent Fuel Pool Storage Rack Design Rept)
• ML20041G432  + (To Spent Fuel Storage Expansion Rept. One Oversize Figure Encl.Aperture Card Is Available in PDR)
• ML20003H787  + (To Spent Fuel Svcs Operation QA Plan)
• BVY 06-031, To Steam Dryer Monitoring Plan  + (To Steam Dryer Monitoring Plan)
• ML18043A918  + (To Steam Generator Repair Rept.Contains Responses to Requests for Addl Info)
• ML20027E468  + (To Steam Generator Water Chemistry Monitoring - Unit 1)
• ML031110304  + (To Steve from Mark)
• ML20040B728  + (To Structural Engineering Branch Interim Criteria for Safety-Related Masonry Wall Evaluation)
• ML16034A325  + (To Summary of Methodology Used for Seismic Capacity Evaluation of GMRS Mitigation Components)
• ML20003C816  + (To Suppl 2 of Seismic Re-evaluation. Rept Reflects Revisions to Analysis Re Emergency Diesel Generator & Cooling Water Heat Exchanger)
• ML19256A786  + (To Suppl Info Sheet for LER NP-33-78-120 on 781005.Other Svc Water Valves Associated W/Component Cooling Water Heat Exchangers Were Inspected for Similar Inoperable Conditions.No Problems Noted)
• ML20054M080  + (To Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3,Reload 4)
• ML090830334  + (To Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML13357A218  + (To Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML20154N217  + (To Supporting Info for Vectra Calculation Package,Rev 1,NUH004.0409,Questions 7.1,7.2 & 7.3)
• ML20039E776  + (To Suppression Pool Leakage Return. Response to NUREG-0737,Item II.B.3 Re post-accident Sampling Encl)
• ML20066A335  + (To Surveillance Instruction SQN SI-114.1, Inservice Insp Program for TVA Sequoyah Nuclear Plant)