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

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List of results

  • ML050450423  + (Technical Audit of Vermont Yankee Steam Dryer Analysis in Support of Extended Power Uprate)
  • ML21141A006  + (Technical Bases Memo for Re-Evaluated Aeb 98-03 Multi-Group and Numerical Integration)
  • ML17347A521  + (Technical Bases Revisions Updated Through November 2017)
  • ML20127E771  + (Technical Bases and Users Manual for the Prototype of Sparc - a Suppression Pool Aerosol Removal Code)
  • ML20236B412  + (Technical Bases for Eliminating Accumulator Line Rupture as Structural Design Basis for Vogtle Unit 2)
  • ML20097J252  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Byron Units 1 & 2 & Braidwood Units 1 & 2)
  • ML20205G710  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Prairie Island Unit 2)
  • ML20106J526  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Prairie Island Unit 1)
  • ML20093G907  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Beaver Valley Unit 2)
  • ML20213E055  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for North Anna Units 1 & 2)
  • ML20135E269  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases for McGuire Units 1 & 2)
  • ML20112H524  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Shearon Harris Unit 1)
  • ML20106F636  + (Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Callaway & Wolf Creek Plants)
  • ML20140A465  + (Technical Bases for Eliminating Pressurizer Surge Line Ruptures as Structural Design Basis for South Texas Project. Addl Info Encl)
  • ML20207D743  + (Technical Bases for Eliminating RHR Line Rupture from Structural Design Basis for South Texas Project Units 1 & 2)
  • ML20246K178  + (Technical Bases for Eliminating Rupture of Accumulator Injection Nozzles as Structural Design Basis for Comanche Peak Unit 1)
  • ML20235F354  + (Technical Bases for Eliminating Rupture of Accumulator Line & Attached RHR Piping from Structural Design Basis for South Texas Project Units 1 & 2)
  • ML19351A182  + (Technical Bases for Estimating Fission Product Behavior During LWR Accidents)
  • ML20009B673  + (Technical Bases for Estimating Fission Product Behavior During LWR Accidents)
  • ML21021A271  + (Technical Bases for Inspection Requirements for PWR Pressurization Shell-To-Head, and Nozzle-to-Vessel Welds)
  • ML20113E049  + (Technical Basis & Description of Approach for Review Method Selection)
  • ML19343C198  + (Technical Basis - Evaluation of Potential Dose to Members of the Public from Treatment of Dogs with Synovetin Oa Containing Sn-117m)
  • ML20142A295  + (Technical Basis - Evaluation of Potential Dose to Members of the Public from Treatment of Dogs with Synovetin Oa)
  • ML25345A097  + (Technical Basis Document No. 20-6002-1362, Rev. 1, Radionuclide Selection for Dcgl Development Site Characterization Project)
  • RA-05-003, Technical Basis Document for NRC Review: Exploranium GR-130 Minimum Detectable Concentration (MDC) of Cs-137 and Co-60 in Surface Soil - 30 Day Notice Per LTP Requirement  + (Technical Basis Document for NRC Review: Exploranium GR-130 Minimum Detectable Concentration (MDC) of Cs-137 and Co-60 in Surface Soil - 30 Day Notice Per LTP Requirement)
  • ML12194A581  + (Technical Basis Document, TBD-12-002, Rev. 0, Dose Assessment for Miscellaneous and Buried Piping for the Plum Brook Reactor Facility, Licenses)
  • ML20248H768  + (Technical Basis and Implementation Guidelines for a Technique for Human Event Analysis (Atheana).Draft Report for Comment)
  • ML16190A294  + (Technical Basis for 2000 G Pube Sealed Neutron Sources Mass Limit)
  • ML20056G797  + (Technical Basis for Crystal River Unit 3 Plant Specific Procedure to Resolve NRC Generic Ltr 87-02)
  • ML21209A524  + (Technical Basis for Draf RG 1.183 Revision 1 (2021) Non-LOCA Fission Product Release Fractions)
  • ML20154G683  + (Technical Basis for EPRI Advanced LWR Requirements Document Assuption on Delayed Fission Product Release (Task 8.3.5.2), Advanced Reactor Severe Accident Program)
  • ML20092H691  + (Technical Basis for Eliminating Class 1 Accumulator Line Rupture as Structural Design Basis for Catawba Units 1 & 2)
  • ML18152A281  + (Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619)
  • ML20216E345  + (Technical Basis for Environmental Qualification of MICROPROCESSOR-BASED SAFETY-RELATED Equipment in Nuclear Power Plants)
  • ML20069B889  + (Technical Basis for Evaluating Electromagnetic and RADIO-FREQUENCY Interference in SAFETY-RELATED I&C Systems)
  • ML20245H515  + (Technical Basis for Granting Test Frequency Relief)
  • ML20246B440  + (Technical Basis for Offsite Emergency Planning in Us)
  • L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair  + (Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair)
  • ML13330A593  + (Technical Basis for Piping Strain & Stress Limits,Long-Term Svc Seismic Program)
  • ML032340513  + (Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2. Table of Contents Through Figure 8-12)
  • RNP-RA/03-0075, Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6  + (Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6)
  • ML20032B197  + (Technical Basis for Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants)
  • ML20012F219  + (Technical Basis for Review of HIGH-LEVEL Waste Repository Modeling)
  • ML20147H568  + (Technical Basis for Srss Method of Combining Dynamic Responses. Executive Summary Rept & Suppl)
  • ML20147H570  + (Technical Basis for Srss Method of Combining Dynamic Responses. Executive Summary Rept & Suppl)
  • ML18306A479  + (Technical Basis for Updating Fcse Seismic Hazard Analysis Guidance)
  • ML18306A499  + (Technical Basis for Updating Fcse Seismic Hazard Analysis Guidance Final)
  • RC-12-0173, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles  + (Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles)
  • ML050460281  + (Technical Basis for the Effectiveness of Current Inservice Inspection Methods in Sleeved Steam Generator Tubes)
  • ML20095F751  + (Technical Basis of LaSalle County Station Fire Damper Surveillance Program)
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