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A list of all pages that have property "Title" with value "Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML100130366  + (Fr Notice--Beaver Valley Power Station, Unit No. 2 - Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing, and Order Imposing Procedures for Access to Sensitive Unclassified N)
  • NRC-2010-0086, Fr Notice--Beaver Valley Power Station, Unit No. 2 - Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing, and Order Imposing Procedures for Access to Sensitive Unclassif  + (Fr Notice--Beaver Valley Power Station, Unit No. 2 - Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing, and Order Imposing Procedures for Access to Sensitive Unclassified N)
  • ML101620031  + (Fr Notice--Peach Bottom, Units 2 and 3 - Withdrawal of an Amendment Request)
  • NRC-2010-0160, Fr Notice--Peach Bottom, Units 2 and 3 - Withdrawal of an Amendment Request  + (Fr Notice--Peach Bottom, Units 2 and 3 - Withdrawal of an Amendment Request)
  • ML20207D326  + (Fr Notices 51FR27872,51FR27921,51FR40438 & Draft Policy Statement, Nuclear Power Plant Access Authorization Program & Draft Industry Guidelines for Nuclear Power Plant Access Authorization Programs)
  • ML070310436  + (Fr Notices, Transfer of Renewed Facility)
  • ML20006E205  + (Fr,Page 42,953,notifying of Receipt of Antitrust Info from Util.Nrr Will Issue Initial Finding as to Whether Significant Changes Occurred Since 800915 Antitrust Settlement)
  • ML20051T243  + (Frac (Failure Rate Analysis Code): a Computer Program for Analysis of Variance of Failure Rates.An Application Users Guide)
  • ENS 41763  + (Fractional Dose Delivered Differed from the Prescribed Dose)
  • ML19290E841  + (Fractographic & Microstructural Analysis of Stress Corrosion Cracking of A533 Grade B Class 1 Plate & A508 Class 2 Forging in Pressurized Reactor-Grade Water at 93 C, Memo Rept 4121)
  • ML20062H353  + (Fractographic & Microstructural Analysis of Fatigue Specimens of A302 Grade B Steel Tested in Air at Room Temp)
  • ML20092G896  + (Fracture & NDE Evaluations for Closure Flange Regions of Comanche Peak Units 1 & 2)
  • ML21175A301  + (Fracture Analysis of Vessels - Oak Ridge (Favor) User Guide v20.1.12)
  • ML21175A300  + (Fracture Analysis of Vessels - Oak Ridge (Favor) Theory Manual v20.1.12, Theory and Implementation of Algorithms, Methods, and Correlations)
  • ML20199A927  + (Fracture Analysis of Welded Type 304 Stainless Steel Pipe. J-R Curve Characterization and Limit Load Analysis)
  • ML20133G798  + (Fracture Behavior of Circumferentially SURFACE-CRACKED Elbows)
  • ML20094R212  + (Fracture Behavior of Short Circumferentially SURFACE-CRACKED Pipe)
  • ML20040D205  + (Fracture Deformation of the Higganum DIKE,SOUTH-CENTRAL Connecticut)
  • ML19343D344  + (Fracture Evaluation of Reactor Coolant Pump Motor Seismic Snubber Lugs)
  • ML20248D113  + (Fracture Evaluation of Surface Cracks Embedded in Reactor Vessel Cladding)
  • ML20214A866  + (Fracture Evaluation of Surface Cracks Embedded in Reactor Vessel Cladding.Unirradiated Bend Specimen Results)
  • ML20155D549  + (Fracture Evaluation of Surface Cracks Embedded in Reactor Vessel Cladding.Material Property Evaluations)
  • ML20082T334  + (Fracture Evaluations of Fusion Line Cracks in Nuclear Pipe Bimetallic Welds)
  • ML20053B461  + (Fracture Mechanics Analysis of Oyster Creek Nuclear Generating Station Emergency Cooling Sys)
  • ML20147D580  + (Fracture Mechanics Analysis of Postulated Underclad Cracks in B&W Designed Reactor Vessels for Period of Extended Operation)
  • L-94-074, Fracture Mechanics Analysis of Pressurizer Instrument Nozzle Flaws  + (Fracture Mechanics Analysis of Pressurizer Instrument Nozzle Flaws)
  • ML18098A088  + (Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability)
  • EPID:L-2018-LLR-0050  + (Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability)
  • ML20072M047  + (Fracture Mechanics Evaluation of Circumferential Indications at Weld 10-0-06 in Peach Bottom 2 RHR Supply Line)
  • ML20024E165  + (Fracture Mechanics Evaluation of Core Spray Sparger Indications, Final Rept)
  • ML20034H964  + (Fracture Mechanics Evaluation of Indication in Weld NG-D-18 in Recirculation Sys in Oyster Creek Nuclear Plant)
  • ML19338B827  + (Fracture Mechanics Evaluation of Reactor Vessel of Smud Unit at Rancho Seco for Unanticipated Transient on 780320)
  • ML20095G200  + (Fracture Mechanics Evaluation of UT Indications Found During 1995 Reexam of FW Nozzle to Shell Welds at Cns)
  • ML20086S881  + (Fracture Mechanics Evaluation of UT Indications Found in Cooper Feedwater-Nozzle-to Shell Weld)
  • ML20086B548  + (Fracture Mechanics Evaluation,Braidwood,Unit 2 Residual Heat Exchanger Tube Side Inlet & Outlet Nozzles)
  • ML20055D893  + (Fracture Mechanics Evaluation:Haddam Neck Pressurizer)
  • ML20054H378  + (Fracture Mechanics Models Developed for Piping Reliability Assessment in Light Water Reactors)
  • ML19347D272  + (Fracture Mechanics Procedures for Primary Component Support Toughness Evaluations:Recommendations for Inclusion in NUREG-0577)
  • ML19343D349  + (Fracture Mechanics Procedures for Primary Component Support Toughness Evaluations)
  • ML20010A552  + (Fracture Prevention of Containment Pressure Boundary. Eighteen Oversize Drawings Encl.Aperture Cards Are Available in PDR)
  • ML20112H471  + (Fracture Prevention of Containment Pressure Boundary (GDC 51))
  • ML20151N782  + (Fracture Sensitivity Study of Girth Weld 6 Repaired Configuration,Indian Point Unit 2)
  • ML20248J408  + (Fracture Toughness Analysis Per 10CFR50 App G)
  • ML19332F115  + (Fracture Toughness Characterization of Nuclear Piping Steels)
  • ML20057E686  + (Fracture Toughness Characterization of WF-70 Weld Metal)
  • ML20057D712  + (Fracture Toughness Characterization of WF-70 Weld Metal)
  • Regulatory Guide 7.11  + (Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with Maximum Wall Thickness of 4 Inches (0.1 M))
  • ML20135E822  + (Fracture Toughness Evaluations of TP304 Stainless Steel Pipes)
  • ML19294C120  + (Fracture Toughness of Nuclear Containment Pressure Boundary, Bimonthly Mgt Status Rept)
  • ML20069B462  + (Fracture Toughness of PWR Component Supports)
  • ML17326A751  + (Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Donald C. Cook Units 1 & 2, Technical Evaluation Rept)
  • ML19337A846  + (Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Inidian Point Unit 2, Interim Technical Evaluation Rept)
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