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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
- ML25043A223 + (Real Id Act - NRC Frequently Asked Questions)
- ML25043A216 + (Real Id Act Information Notice for Nuclear Power Plants)
- ML093350783 + (Real Id Act of 2005 - Title II (Public Law 109-13) - Letter)
- ML25101A213 + (Real Id Act of 2005 U.S. NRC Phased Enforcement Plan)
- ML20214Q861 + (Real Time Mass Spectrometric Evaluation of Fission Product Transport at Temp & Pressure)
- ML19347D576 + (Real Time Simulation of Thermal Conduction in Nuclear Fuel Elements, Interim Rept)
- ML060170306 + (Realignment of Intermediate Subsidiaries)
- B18994, Realignment of Intermediate Subsidiaries + (Realignment of Intermediate Subsidiaries)
- ML20155C020 + (Realism/Best Efforts Discovery.* Forwards Lilco Third Set of Interrogatories & Requests for Production of Documents Re Contentions 1-2,4-8 & 10 to Suffolk County,State of Ny & Town of Southampton.Related Correspondence)
- Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting from Nuclear Fuel Thermal Conductivity Degradation + (Realistic Emergency Core Cooling System Evaluation Model Effects Resulting from Nuclear Fuel Thermal Conductivity Degradation)
- Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting From Nuclear Fuel Thermal Conductivity Degradation + (Realistic Emergency Core Cooling System Evaluation Model Effects Resulting From Nuclear Fuel Thermal Conductivity Degradation)
- ML19345B706 + (Realistic Estimates of Consequences of Nuclear Accidents)
- HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028 + (Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028)
- ML012400019 + (Realistic Large Break LOCA Methodology for Pressurized Water Reactors, EMF-2103(NP) Revision 0)
- ML031360417 + (Realistic Large Break Loss of Coolant Accident (Rlbloca) Analysis Results for Proposed Technical Specifications Changes & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel)
- ML032110465 + (Realistic Large Break Loss of Coolant Accident Analysis Results for Proposed TS Changes & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel)
- ML20005B371 + (Realistic Seismic Design Margins of Pumps,Valve and Piping)
- ML20090H891 + (Realistic Simulation of Severe Accidents in BWRS-COMPUTER Modeling Requirements)
- ML19165A161 + (Realizing Innovation in Advanced Reactors - Presentation to GAIN-EPRI-NEI-US Nic Micro-Reactor Workshop - June 2019)
- ML19305D459 + (Reamended Contentions Re Renewal of License SNM-1265. Relies on Heidelberg Rept Re False Calculations Upon Which NRC Has Based Assessment of Radiation Absorbed by Population)
- ML19305D003 + (Reamended Contentions of Intervenors That Under Present GE License No Account Is Taken of Possibility of Accident to Storage Pools Which Might Result in Large Release of Radioactive Gases)
- ML20095G763 + (Reanalysis Against 10CFR50,App R,Sections Iii.G,J & O)
- ML20155G666 + (Reanalysis of 1984 Eddy Current Data for Steam Generators 3 & 4, Supplemental Rept)
- ML20205H423 + (Reanalysis of HPCI Steam Supply Line W/Energy Absorbers as Replacements for Hydraulic Snubbers,Peach Bottom)
- ML20064D262 + (Reanalysis of LaSalle Wetwell to Drywell Vacuum Breakers Under Pool Swell Loading Conditions, Rev 0)
- NL-05-058, Reanalysis of Large Break Loss of Coolant Accident Using ASTRUM + (Reanalysis of Large Break Loss of Coolant Accident Using ASTRUM)
- ML20197H565 + (Reanalysis of Main Steam Line Outside Containment W/Energy Absorbers as Replacements for Hydraulic Snubbers for Point Beach Nuclear Plant)
- ML20030D074 + (Reanalysis of Matl Models for Envelope Spectra)
- ML20214E040 + (Reanalysis of Min Required Auxiliary Feedwater Flow Rate)
- ML20132C706 + (Reanalysis of RHR Line W/Energy Absorbers as Replacements for Hydraulic Snubbers)
- ML19309B105 + (Reanalysis of Safety-Related Piping Sys, Corrected Pages)
- GNRO-2012/00144, Reanalysis of Severe Accident Mitigation Alternatives + (Reanalysis of Severe Accident Mitigation Alternatives)
- ML19350D159 + (Reapplication by Nj Monson for Operator License)
- ML19350D160 + (Reapplication by Re Boyer for Senior Operator License)
- ML19350D161 + (Reapplication by Wa Fraser for Operator License)
- ML20214G401 + (Reapplication for Subpoena on Behalf of Seacost Anti- Pollution League.* D Laughton Requested to Appear for Deposition Re Availability of Teamsters Bus Drivers to Transport Evacuees in Emergency.W/Certificate of Svc)
- ML20247K949 + (Reappraisal of Nuclear Activities Re Fort Calhoun Station)
- ML19330C756 + (Reapprises NRC of Withdrawal of CP Application for Facilities)
- ML20266C959 + (Rear Sight. Sheet 1 of 1)
- ML24183A169 + (Reasonable Accommodation (RA) Pia)
- ML23030B873 + (Reasonable Accommodation Procedures)
- ML20303A215 + (Reasonable Accommodation Tracking Tool Privacy Impact Assessment (Pia))
- ML102800114 + (Reasonable Assurance Justification Template)
- ML18065A211 + (Reasonable Assurance for Pilgram Station (March 2, 2018 Severe Weather Event))
- ML20003F042 + (Reasons for Delay in Power Plant Licensing & Const:Initial Review of Data Available on Power Plants Brought on Line from 1967-1976)
- ML052630060 + (Reasons for Hope, Q3 Assessment Deltas)
- ML19329D411 + (Reasons for Late Filing of Petition to Intervene in OL Hearing.Aec Failed to Notify Coalition for Safe Electric Power of OL Hearing.Coalition First Heard About Hearing from Newspaper Reporter on 730504)
- ML22020A380 + (Reassertion of Certain Regulatory Authority in the State of Idaho FRN Doc 91_9021 Filed April 16 1991)
- ML20153H206 + (Reassesses 850711 & 0913 Commitments to Review DOE HTGR & Advanced Liquid Metal Reactor Conceptual Designs,Due to FY86-87 Budget Reductions.Meeting Requested to Discuss Plans,Schedules & Priorities)
- ML13304A288 + (Reassesses Fees for Listed Applications Re Safety Valves, Natural Circulation Tests & Offsite Dose Calculation Manual,In Response to Taking Exception to Class III Determination)
- ML19317E845 + (Reassesses Steam Generator Tube Leakage at Facility. Defective Tubes Plugged.Potential for Circumferential Cracks Exists During Operation within Tech Spec Limits. Re-evaluation of Bases for Continued Operation Warranted)