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• PMNS20190032, Technical Meeting to Discuss Cimarron Facility Decommissioning Plan-Rev.1  + (Technical Meeting to Discuss Cimarron Facility Decommissioning Plan-Rev.1)
• PMNS20190871, Technical Meeting to Discuss NRC Staff Review of the Cimarron Facility Decommissioning Plan  + (Technical Meeting to Discuss NRC Staff Review of the Cimarron Facility Decommissioning Plan)
• PMNS20230927, Technical Meeting with NRC on Probabilistic Fracture Mechanics (Pfm) and Nondestructive Examination (NDE) of Cast Austenitic Stainless Steel (CASS)  + (Technical Meeting with NRC on Probabilistic Fracture Mechanics (Pfm) and Nondestructive Examination (NDE) of Cast Austenitic Stainless Steel (CASS))
• ML20126D078  + (Technical Memorandum 8-79:Isotope User Manual)
• ML17321A098  + (Technical Note 80581, Thermo-Lag 330 Conformable Stress Skin 3 H Fire Wall Sys Application Procedures)
• ML071560385  + (Technical Note on Critical Flaw Size Evaluation for Circumferential Cracks in Dissimilar Metal Welds)
• ML24276A050  + (Technical Notice of Deficiency with Updated Closure Plan)
• ML20205S164  + (Technical Operating Procedure Change Notice 2 to Technical Operating Procedure TOP-001-02)
• ML021050498  + (Technical Pages for Seabrook Unit 1 6.15 Containment Leakage Rate Testing Program)
• ML23318A217  + (Technical Paper Entitled Development and Testing of Coarse-Grained Models for Ultrasonic Simulations of Cast Austenitic Stainless Steel)
• ML16092A029  + (Technical Paper on Loss of AC Bus Initiator for RBS)
• ML20245K148  + (Technical Paper, Safety Experience in Operation of BWR Station in India, Presented at Iama Seminar on Reactor Safety in Spring of 1973)
• ML20137L268  + (Technical Position & Rulemaking on Low-Level Waste Shipment Manifest Info & Reporting, to Advisory Committee on Nuclear Waste)
• ML20245H504  + (Technical Position Paper,Environ Monitoring of Low Level Radwaste Disposal Facilities)
• ULNRC-06166, Technical Position TP-06 Position Indication Testing of EMHV8924  + (Technical Position TP-06 Position Indication Testing of EMHV8924)
• ML20062G384  + (Technical Position on Borehole & Shaft Sealing)
• ML20154D874  + (Technical Position on Items and Activities in the HIGH-LEVEL Waste Geologic Repository Program Subject to Quality Assurance Requirements)
• ML24304A855  + (Technical Presentation at the Fall 2024 IEEE Pes ICC Subcommittee D Technical Session, Electrical Cable Damage and Ignition Characteristics Under Severe Thermal Exposure)
• ML20198A291  + (Technical Procedure CP-206,rev 4,PCR 98-034, Specifications & Surveillance Component Cooling/Service Waster System)
• ML20198A298  + (Technical Procedure CP-217,rev 7,PCR 98-034, Specifications & Surveillance,Secondary Chemistry)
• ML20198A313  + (Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated)
• ML082680052  + (Technical Procedure, Fuel Handling Procedure 305 (FH-305), Core Alterations, Revision 12)
• ML20040H503  + (Technical Proposal PR-5792, Program Plan - Independent Design Review. Book 1 of 2)
• ML20079F154  + (Technical Proposal PR-6194, Independent Design Review of Zimmer Nuclear Power Station)
• ML20044D453  + (Technical Proposal for Deluge Valve. W/One Oversize Drawing)

• ML20044D459  + (Technical Proposal for Squib Valves)

• ML20205C366  + (Technical Proposal. Portions Deleted)
• ML20030A515  + (Technical Qualifications:Big Rock Nuclear Point Nuclear Plant)
• ML22357A066  + (Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan)
• ML061660437  + (Technical Report (TAC MC7897) on Third 10-Year Inservice Inspection Interval Request for Relief for Nuclear Management Company, LLC)
• ML23251A046  + (Technical Report - Review of Documents Related to Tank 12H Grout Formulations)
• ML073240759  + (Technical Report 1415, Addendum Report: Intensive Archaeological Survey of the Proposed Expansion Areas at the Vogtle Electric Generating Plant, Borrow Pit Area)
• ML20206K701  + (Technical Report 16.1A,Review of Modular Accident Analysis Program PWR & BWR Codes. W/870407 Release Memo)
• ML110120053  + (Technical Report MUAP-10023, Initial Type Test Result of Class 1E Gas Turbine Generator System)
• ML052220506  + (Technical Report NE-1454, Rev. 0, Surry Unit 2, Cycle 20 Startup Physics Tests Report)
• ML24008A039  + (Technical Report NEI 20-07, Draft Revision E, Request for Withholding Information from Public Disclosure)
• ML103210496  + (Technical Report No. EE-0116 Revision 8, Allowable Values for North Anna Improved Technical Specifications Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications, Section 2.3 and 3.7 and Allowable Values for Ke)
• ML103210495  + (Technical Report No. EE-0116, Rev. 8, Allowable Values for North Anna Improved Technical Specifications (ITS) Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications (Cts), Sections 2.3 and 3.7, and Allowable)
• ML093070164  + (Technical Report No. EE-0116, Revision 5)
• ML11116A211  + (Technical Report No. SQN2-SGR-TR3, Revision 0 Sequoyah Unit 2 Steam Generator Replacement Alternate Rebar Splice - Bar-Lock Mechanical Splices Technical Report, Attachment 2)
• ML040280040  + (Technical Report No. YA-REPT-00-010-03 Evaluation of the Dose Integration Parameter in RESRAD-BUILD)
• ML18096B275  + (Technical Report PNNL 26399 Analysis of Parent Techniques Data)
• ML18096B293  + (Technical Report PNNL 26993 Blind Testing of Parent Open Techniques)
• ML20349A012  + (Technical Report PNNL-30759, Survey of Nondestructive Evaluation Techniques of AMT-Fabricated Components)
• ML17006A059  + (Technical Report Revision, License Amendment Request 15-03, Application of Alternative Source Term)
• ML20049H977  + (Technical Report on D.C. Power Supplies in Nuclear Power Plants)
• ML20148S843  + (Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping.Final Report)
• ML20207H581  + (Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping)
• DCL-16-061, Technical Report, Implementation of Alternative Source Terms Summary of Dose Analysis and Results, Revision 3  + (Technical Report, Implementation of Alternative Source Terms Summary of Dose Analysis and Results, Revision 3)
• ML12114A061  + (Technical Report, SQN2-SGR-TRI, Revision 3, Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling)
• ML20207S900  + (Technical Rept 1.1 Safety Goal Evaluation:Implications for Idcor. W/870313 Release Ltr)