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A list of all pages that have property "Title" with value "Technical Issues Biographies". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20084H681  + (Technical Guide TG-OP-902-008 for Rev 0 to OP-902-008, Safety Function Recovery Procedure)
  • ML20070D566  + (Technical Guidelines for Aseismic Design of Nuclear Power Plants.Translation of Jeag 4601-1987)
  • ML20207L744  + (Technical Guidelines. Basis for Guidelines & Description of Plant Encl)
  • ML20207A502  + (Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,Oct 1985 - Jan 1986)
  • ML20207A260  + (Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,June-Jul 1985)
  • ML20211G130  + (Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,Apr-May 1986)
  • ML20211F838  + (Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program,Feb-Mar 1986)
  • ML20127F176  + (Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program, June-Jul 1984)
  • ML20127F137  + (Technical Highlights/Administrative Rept for NRC Reactor Safety Research Program, Apr-May 1984)
  • ML20206H367  + (Technical Info Memo, 170 Providencia Street,Burbank Property Response to Comments of 981216 & Meeting of 990126)
  • ML20247R963  + (Technical Info Memo, Low Level Radwaste Source Term for Texas Disposal Facility)
  • ML20215C760  + (Technical Info Relating to Alternate for Matls for BWR- Control Rod-B4C-Tube Cladding)
  • ML19340A533  + (Technical Info for Amend to License DPR-2 as Amended,First Reload Fuel for Dresden Nuclear Power Station)
  • ML20137P042  + (Technical Info for Prioritization of Generic Safety Issues)
  • NUREG-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France  + (Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France)
  • ML061740010  + (Technical Information Meeting)
  • ML19284D693  + (Technical Information Request for the Old Rifle Processing Site Revised Gcap)
  • ML19170A232  + (Technical Information Sheet - 50/50 Tin Lead Solder)
  • ML23059A428  + (Technical Information from the NRC February 1, 2023 Onsite Observation Visit to the Saltstone Disposal Facility at the Savannah River Site)
  • RIS 2000-10, Technical Information to Facilitate Public Access to the U.S. Nuclear Regulatory Commission'S Agencywide Documents Access and Management System ( Adams) Firewall Access  + (Technical Information to Facilitate Public Access to the U.S. Nuclear Regulatory Commission'S Agencywide Documents Access and Management System ( Adams) Firewall Access)
  • ML003682046  + (Technical Information to Facilitate Public Access to the U.S. Nuclear Regulatory Commissions Agencywide Documents Access and Management System ADAMS) Firewall Access)
  • ML20081J171  + (Technical Instruction 47, Offsite Dose Calculation Manual)
  • ML110960447  + (Technical Instruction TI-137, Revision 0, Control of Portable Two-Way Radios)
  • ML20137Y722  + (Technical Issue Summary RI-94-04, Pressurizer Safety Valves & Solid Plant Operation)
  • ML19327A924  + (Technical Issue Summary Re High Level Radiation/ Contamination Area at Facility.Licensee Hired Contractor to Clean Up Contaminated Areas & Work Continues.Augmented Insp Team Dispatched to Review Use of sub-basement for Storage)
  • ML20137E558  + (Technical Issues Summary from Special Review Team Rept of 840731)
  • NL-08-0373, Technical Justification Regarding Scope Expansion for Dissimilar Metal Weld Examination  + (Technical Justification Regarding Scope Expansion for Dissimilar Metal Weld Examination)
  • NL-08-0316, Technical Justification Regarding Scope Expansion for Dissimilar Metal Weld Examination  + (Technical Justification Regarding Scope Expansion for Dissimilar Metal Weld Examination)
  • ML080601269  + (Technical Justification Regarding Scope Expansion for Dissimilar Metal Weld Examination)
  • ML20215L741  + (Technical Justification for Changing Rosemount Analog Trip Unit Sys Tech Spec Test Interval)
  • DCL-09-002, Technical Justification for Deviation from EPRI MRP Bare Metal Visual Examination Schedule - NEI 03-08 Mandatory Work Product Element - for Information Only  + (Technical Justification for Deviation from EPRI MRP Bare Metal Visual Examination Schedule - NEI 03-08 Mandatory Work Product Element - for Information Only)
  • ML20214V237  + (Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Beaver Valley Unit 1)
  • ML19310D145  + (Technical Justification for Eliminating Pressurizer Surge Line Rupture as Structrual Design Basis for Byron Units 1 & 2 & Braidwood Units 1 & 2)
  • ML20091C539  + (Technical Justification for Eliminating Mid-Cycle Insp of Feedwater Nozzle (N4A) to Safe-End Weld Indication at River Bend Plant)
  • ML20206G432  + (Technical Justification for Elimination of Post-Accident Sampling Sys from Plant Design & Licensing Bases for CEOG Utils)
  • ML20269A331  + (Technical Letter Report (TLR-RES/DE/CIB-2020-08) Survey of Modeling and Simulation Techniques for Predicting Initial Microstructures for Advanced Manufacturing Technologies, Volume 1: Predicting Initial Microstructures)
  • ML23058A084  + (Technical Letter Report (TLR-RES/DE/REB-2023-02) State-Of-Technology and Technical Challenges in Advanced Sensors, Instrumentation, and Communication to Support Digital Twin for Nuclear Energy Application)
  • ML18178A431  + (Technical Letter Report - Important Aspects of Probabilistic Fracture Mechanics Analyses - Final)
  • ML092530168  + (Technical Letter Report - Request for Additional Information on the Third 10-Year Inservice Inspection Interval Requests for Relief 09-001-II, 09-002-II and 09-003-II for Florida Power Corporation)
  • ML20325A002  + (Technical Letter Report - TLR-RES/DE/CIB-2020-07, Benchmark Solutions for Xfem Analysis Comparisons)
  • ML20100E299  + (Technical Letter Report - TLR-RES/DE/CIB-2020-03, Final Report on Support for Xfem Component Integrity Analysis: Task 1 Literature Survey)
  • ML20311A262  + (Technical Letter Report - TLR-RES/DE/CIB-2020-06, Evaluation of PWSCC Subcritical Crack Growth in Complex Geometries Using Abaqus Xfem)
  • ML21133A485  + (Technical Letter Report - TLR-RES/DE/CIB-2021-11, Sensitivity Studies and Analyses Involving the Extremely Low Probability of Rapture Code)
  • ML19016A056  + (Technical Letter Report ANL-13/08, Leak Rate, Ligament Rupture, and Burst Pressure Model Updates for Allow 690 Thermally-Treated Steam Generator Tubes)
  • ML21174A167  + (Technical Letter Report Anl)
  • ML24309A090  + (Technical Letter Report Global GS24 Ground Motion Models for Active Crustal Regions Based on Non-Traditional Modeling Approach)
  • ML111050268  + (Technical Letter Report PNNL-19362, Evaluation of Ultrasonic Time-of-Flight Diffraction Data for Selected Control Rod Drive Nozzles from Davis Besse Nuclear Power Plant)
  • ML23101A170  + (Technical Letter Report Predicting Rupture Pressure and Leak Rate of Alloy 600 U-bend Tubes with PWSCC and Comparing with Test Results -ANL-22/21)
  • ML23264A148  + (Technical Letter Report TLR-RES-DE-2024-005 - Analyzing the Impact of Using Wireless Technologies for Monitoring Safety-Related Critical Digital Assets (2-16-2024))
  • ML20017A171  + (Technical Letter Report TLR-RES/DE/CIB-2020-01, Compilation of Software Quality Assurance and Verification and Validation Documentation for the Fracture Analysis of Vessels - Oak Ridge (Favor) Software Product)
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