Search by property

Jump to navigation Jump to search

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

Search by property

A list of all pages that have property "Title" with value "Evaluation of 24 Element Graphite Reflected Core". Since there have been only a few results, also nearby values are displayed.

⧼showingresults⧽

View (previous 50 | next 50) (20 | 50 | 100 | 250 | 500)

    

List of results

  • ML20154R330  + (Evaluation for Tube Vibration Induced Fatigue)
  • ML20151K686  + (Evaluation for Tube Vibration Induced Fatigue)
  • ML20248E893  + (Evaluation for Tube Vibration Induced Fatigue)
  • ML12215A337  + (Evaluation for Tube Vibration-Induced Fatigue)
  • ML18222A216  + (Evaluation from NYSERDA Re Proposed Solar Photovoltaic Facility on a Portion of Western Ny Nuclear Service Center)
  • ML19309G564  + (Evaluation in Support of Extension of Const Completion Date Until 851230.Action Involves No Significant Hazards Consideration)
  • ML20171A704  + (Evaluation in Support of the Pennsylvania State University Radiation Facilities, 2019 Financial Test for a Self Guarantee for Decommissioning Funding)
  • ML15134A097  + (Evaluation of 10 CFR 50.54(p)(2) Changes to Security Plans)
  • ML16008B103  + (Evaluation of 10CFR 50.54(p)(2) Changes to the Security Plans)
  • ML20247Q977  + (Evaluation of 12 H/Day Shift Schedule, Presented at 1986 Annual Meeting of Human Factors Society in Dayton,Oh)
  • ML19344E483  + (Evaluation of 18-Inch Containment Isolation Valves for Dresden Station,Units 2 & 3 & Quad Cities Station,Units 1 & 2)
  • ML080230485  + (Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report)
  • ML080230484  + (Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report)
  • ML070510609  + (Evaluation of 2005 Mid-Cycle (14MCO) Steam Generator Tube Inspections)
  • ML070950503  + (Evaluation of 2005 Steam Generator Tube Inspections at Crystal River Unit 3)
  • ML071860655  + (Evaluation of 2006 (Cycle 14) Steam Generator Tube Inspection Report Summaries)
  • ML080780217  + (Evaluation of 2006 Steam Generator Tube Inspections)
  • ML091030490  + (Evaluation of 2007 (Cycle 15) Steam Generator Tube Inspections)
  • ML092080073  + (Evaluation of 2008 (Cycle 24) Steam Generator Tube Inspections))
  • ML100540042  + (Evaluation of 2008 (Cycle 28) Steam Generator Tube Inspections)
  • ML101820184  + (Evaluation of 2009 (Cycle 24) Steam Generator Tube Inspections)
  • ML110480057  + (Evaluation of 2009 (Cycle 25) Steam Generator Tube Inspections)
  • ML103050461  + (Evaluation of 2009 Steam Generator Tube Inservice Inspection Report, Performed During Refueling Outage 20 Which Began September 2009)
  • ML110820865  + (Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections)
  • ML11201A273  + (Evaluation of 2010 (Cycle 25) Steam Generator Tube Inspections)
  • ML20030D418  + (Evaluation of 24 Element Graphite Reflected Core)
  • ML043060591  + (Evaluation of 2EOC13 ISI Flaw in SG2C to Hot Leg Weld)
  • ML19331C672  + (Evaluation of 42-Inch Containment Isolation Valves for Zion Station 1 & 2, Revision 1)
  • ML20058M149  + (Evaluation of 460-Volt Diesel Generator Cooling Pump Min Starting Voltage)
  • ML19253C005  + (Evaluation of 720215 BAW-10013, Study of Intergangular Separations in Low Alloy Steel Heat Affected Zones Under Austenitic Stainless Steel Weld Cladding. Rept Acceptable)
  • ML19210C968  + (Evaluation of 790925 Cooldown Incident.Low Pressure Feedwater Heater Drain Cooler Dump Valve Began to Cycle, Causing Reactor Trip.Caused by Tube Leakage Inside Drain Cooler.Problem Generic in Nature)
  • ML20031F492  + (Evaluation of 791221 Application & 801117 & 810601 Suppls for Amend to License SNM-1097 Authorizing Operation of Two New Conversion Lines in Bldg D.Amend Recommended)
  • ML20031F544  + (Evaluation of 810415 Application for Renewal of License SNM-107 Extending Expiration Date to 860930.Renewal Recommended)
  • ML20031D676  + (Evaluation of 810806 Application for Amend to License SNM- 1879 Adding 810806 Date to Identify New co-holders of Matls License & Permitting Storage of New Fuel Assemblies Prior to Installation of Fire Detection & Alarm Sys.Amend Approved)
  • ML20031D668  + (Evaluation of 810806 Application for Amend to License SNM- 1852 Adding 810806 Date to Identify New co-holders of Matls License & Permits Storage of New Fuel Assemblies Prior to Installation of Fire Detection & Alarm Sys.Amend Approved)
  • ML20031F461  + (Evaluation of 810817 Application for License SNM-1887 Authorizing Receipt,Possession & Use of 12 Excore Detectors Containing Less than 6 G U-235.Approval Recommended)
  • IR 05000440/1982013  + (Evaluation of 821012-13 Insp (IE Insp Repts 50-440/82-13 & 50-441/82-12))
  • ML20127A148  + (Evaluation of 840911 Application to Amend License SNM-1168 Re Authorization to Modify Plant Activities & Functions Due to Removal of Pelletizing Operation.Issuance of Amend Recommended)
  • ML20127D485  + (Evaluation of 841130 License Amend Application Re Addition of 1,000 G of Contained U-235 in Residue Enriched to Greater than or Equal to 20 Weight Percent U-235.Issuance of Amend Recommended)
  • ML20082Q827  + (Evaluation of 9 by 9 Fuel Impact on Stability of Susquehanna-2 at End of Cycle 4)
  • ML20205B304  + (Evaluation of AC-Independent Containment Spray Sys)
  • ML060260035  + (Evaluation of ANO-1 Response to GL 2004-01, Requirements for Steam Generator Tube Inspection)
  • ML20011A813  + (Evaluation of ANO-2 HPSI Pump Operability W/O Svc Water Cooling, Revision 1)
  • ML062620115  + (Evaluation of ANOs Response to Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations (TAC No. 1546))
  • ML20236S968  + (Evaluation of AP600 Containment THERMAL-HYDRAULIC Performance)
  • ML20008G005  + (Evaluation of ASME Section XI Reference Level Sensitivity for Initiation of Ultrasonic Inspection Examination)
  • ML19256F093  + (Evaluation of Ability of Electrical Rods to Simulate Nuclear Rod Behavior During LOCA, Interim Rept for Oct 1979)
  • ML20078S335  + (Evaluation of Abnormal Wear at Limerick)
  • ML20083L531  + (Evaluation of Acceptability of Fddr 1E6AR-FDDR-001 for Shroud Repair Program at Quad Cities Unit 2)
  • ML20094G961  + (Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internal Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612)
  • ML20069C377  + (Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell,Load Cell Linkage & Reactor Coolant Pump Motor Lift Sling to Requirements of NUREG-0612)
Retrieved from "https://kanterella.com/Special:SearchByProperty/:Title/Evaluation-20of-2024-20Element-20Graphite-20Reflected-20Core"