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List of results

• ML20134K477  + (Rev 0 to Fermi 2 Colr,Cycle 6)
• ML20072T303  + (Rev 0 to Field Administrative Constructors Rept 2, Handling of Contractor Incident Interface Repts. DE Mcgarrigan 820429 Memo to Am Ebner Re QA Trend Rept for Jan-Mar 1982 & Handwritten Notes Concerning Entrance Interviews Encl)
• ML20086E847  + (Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds)
• ML17059A888  + (Rev 0 to Field Disposition Instruction 0245-90800, Shroud)
• ML20072T400  + (Rev 0 to Field Instruction FI-126, Use of Automatic Welding Machines)
• ML20198R592  + (Rev 0 to Field Instrument Terminal/Junction Box Separation Sampling Criteria for Millstone Unit 2 Independent Corrective Action Verification Program)
• ML20154D459  + (Rev 0 to Final Draft of NEI 98-03, Guidelines for Updating Fsars)
• ML17264A105  + (Rev 0 to Final Exam Rept for 1995 SG Eddy Current Insp at Ginna Nuclear Power Station,)
• ML20247L295  + (Rev 0 to Final Rept CE NPSD-1103, Evaluation of Degraded Secondary Internals Susceptibility Assessment)
• ML20199L918  + (Rev 0 to Final Rept CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Tech Specs)
• ML20211C064  + (Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson Spent Fuel Storage Racks (Unpoisoned,Low Density) W/4.2% Enriched 15x15 Fuel Assemblies)
• ML20211C049  + (Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson New Fuel Storage Vault W/4.2% Enriched 15x15 Fuel Assemblies)
• ML20034B494  + (Rev 0 to Final Rept Criticality Safety Analysis Millstone-2 New Fuel Storage Vault & Transfer Carriage W/5 % Enriched 14x14 Fuel Assemblies)
• ML20207F998  + (Rev 0 to Final Rept Criticality Safety Analysis,Dc Cook New Fuel Storage Vault W/5.0% Enriched 17 X 17 Fuel)
• ML20113E297  + (Rev 0 to Final Rept Fsar/Sys Vertical Slice Review,Project Rept for Northeast Nuclear Energy Co)
• ML20116M423  + (Rev 0 to Final Rept Point Beach Refueling Water Storage Tank Seismic Capacity)
• ML17348A320  + (Rev 0 to Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant Unit 3)
• ML20034J058  + (Rev 0 to Final Site Decontamination Rept)
• ML20196K362  + (Rev 0 to Final Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments & RAI Responses)
• ML20154H149  + (Rev 0 to Final Verification & Validation Rept on TMI-1 Spds)
• ML20098B044  + (Rev 0 to Finite Element Analysis of Pipe Whip Restraints SI3R-640A,FWR-35 & FWR-16)
• ML20135E434  + (Rev 0 to Fire & Hose Stream Test of 8-Inch Thick Specimen of TCO-002 Medium Density Silicone Elastomer Used in Electrical Sleeve Opening Penetrated by Extended Steel Conduit)
• ML20135E423  + (Rev 0 to Fire & Hose Stream Test of 8-Inch Thick Specimen of TCO-002 Medium Density Silicone Elastomer Used in Electrical Sleeve Opening Penetrated by Extended Aluminum Conduit)
• ML17229A178  + (Rev 0 to Fire Barrier Ampacity Correction Factors Extrapolation of Test Results for 3 Hour Barrier)
• ML20215D884  + (Rev 0 to Fire Protection/Prevention)
• ML20203G427  + (Rev 0 to First Ten-Year Interval Containment Insp Program for Cns)

• ML20151J496  + (Rev 0 to Floor Response Spectrum Generation)
• ML20151J464  + (Rev 0 to Floor Response Spectrum Generation)

• ML20067A987  + (Rev 0 to Flow Evaluation - RHR Valve to Recirculation Tee)
• ML20116G658  + (Rev 0 to Form NIS-1 Owners Data for Inservice Insps)
• ML20113A977  + (Rev 0 to Form NIS-1, Owners Data Rept for ISI for 940820- 960312)
• ML20211N741  + (Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program)
• ML20112J923  + (Rev 0 to Fort Calhoun Station Reg Guide 1.97,Rev 2 Response)
• ML20211N759  + (Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check)
• ML20099J326  + (Rev 0 to Fort St Vrain SPDS Sar)
• ML20213F473  + (Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One-1 a Pump Case Indication)
• ML20214K395  + (Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `A Pump Case - Supplementary Topics)
• ML20214K364  + (Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B Pump Case-Surface Flaw)
• ML20214K316  + (Rev 0 to Fracture Mechanics Analysis of Arkansas Nuclear One,Unit 1 `B Pump Case Indication)
• ML20134P218  + (Rev 0 to Fracture Mechanics Evaluation & Weld Overlay Design for Recirculation Sys Piping in Ja Fitzpatrick Nuclear Power Plant)
• ML20154Q132  + (Rev 0 to Fracture Mechanics Evaluation of Recirculation Sys Piping Welds in Browns Ferry Unit 2 Nuclear Power Plant)
• ML17256A648  + (Rev 0 to Fracture Mechanics Evaluation of High Energy Piping Lines at Re Ginna Nuclear Power Plant)
• ML20136E737  + (Rev 0 to Framatome Mark-B Fuel Assembly Spacer Grid Deformation in B&W Designed 177 Fuel Assembly Plants)
• ML111820083  + (Rev 0 to Fratility Analysis of Circulating Water Intake & Discharging Piping)
• ML20059A499  + (Rev 0 to Frequency of Chlorine Concentration in Control Room in Excess of Toxicity Limit Due to Barge Accident)
• ML20129A462  + (Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway)
• ML20080U094  + (Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Rept for Repower Area)
• ML20063M155  + (Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release)
• ML20116C684  + (Rev 0 to Fuel Consolidation & Storage Rept)
• ML20140E144  + (Rev 0 to Fuel Receiving & Storage Facility. Figures Inadvertently Not Distributed Provided)
• ML20237H602  + (Rev 0 to Function Restoration Guidelines FR-C.2, Response to Saturated Core Cooling)
• ML20237H689  + (Rev 0 to Function Restoration Guidelines FR-Z.2, Response to Containment Flooding)