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A list of all pages that have property "Title" with value "Evaluation". 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

  • ML20147E455  + (Evaluates TRAC,RELAP5 & Thor Codes for LOCA Analysis. Recommends Trac Code)
  • ML19322D001  + (Evaluates Three Pump Operation Effects on Safety Concerns & Potential Unreviewed Safety Items)
  • ML19261C207  + (Evaluates Unresolved Issues Re Methods to Obtain 1/4T Fluence Used in Proposed pressure-temp Limits.Recommends Specific Issues Be Resolved Before Operation W/Proposed Limits Beyond Four Effective Full Power Years)
  • ML19319C055  + (Evaluates Util Proposed Corrective Action Re Shipping Damage to Facility Primary Pump Casing.Corrective Action Satisfactory,Providing Distortion or Surface Discontinuity Not Shown in Dimensional & Liquid Penetration Insp)
  • ML20093G106  + (Evaluates Util Response to ASLB Jul 1982 Partial Initial Decision on Qualifications of Training Instructors.Util Should Develop Guidelines & Criteria to Support Alternate Evaluations of Technical Qualifications of Instructors)
  • ML19224C503  + (Evaluates Util Response to IE Bulletin 79-06B.Items Which Have Not Been Adequately Addressed Include Containment Isolation & Continued Operation of Radiological Control Program)
  • ML19241B364  + (Evaluates Util Responses to IE Bulletin 79-06A.Forwards Memo Reviewing Westinghouse Rept, Qualification Testing of Barton Pressure & Differential Pressure Transmitters)
  • ML20054A328  + (Evaluates Waste Burial Area at VA Hosp,Los Angeles.Less than One Tenth of Allowable Quantities Were Buried.Most Wastes Can Now Be Disposed of W/O Controls.No Reason Exists to Restrict Property Use)
  • ML19259B305  + (Evaluates YAEC-1160 Re Model for LOCA Analyses.Rept Acceptable)
  • ML20010D272  + (Evaluating Flaw Detectability Under Limited Coverage Conditions)
  • ML19329G146  + (Evaluating Hazards of Disposing of Wastes from Energy Production, Bureau of Radiation Protection,Harrisburg,Pa. Presented as Part of ANS 800227-29 Topical Meeting Re Technical Assessment of Nuclear Power & Alternative)
  • ML20137J800  + (Evaluating Leak Behavior Through DG Obrien Electrical Penetration Assemblies Under Severe Accident Conditions, Quick Look Rept.Viewgraphs & Supporting Documentation Encl)
  • ML20081J481  + (Evaluating Prediction Uncertainty)
  • ML19323G541  + (Evaluating Strength & Ductility of Irradiated Zircaloy Task 5, Quarterly Progress rept,Apr-June 1979)
  • ML19309F624  + (Evaluating Strength & Ductility of Irradiated Zircaloy, Task 5, Progress Rept for Jul-Dec 1978)
  • ML19289C874  + (Evaluating Strength & Ductility of Irradiated Zircaloy,Task 5, Quarterly Rept Apr-June l978)
  • ML19253D078  + (Evaluating Strength & Ductility of Irradiated Zircaloy: Task 5, Quarterly Progress Rept Jan-Mar 1979)
  • ML19256F806  + (Evaluating Strength & Ductility of Irradiated Zircaloy, Task 5.Quarterly Progress Rept Oct-Dec 1977)
  • ML20032C373  + (Evaluating Strength and Ductility of Irradiated Zircaloy Task 5.Quarterly Progress Report,January-March 1978)
  • ML19340C524  + (Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5.Quarterly Progress Report,July-September 1979)
  • ML19345H528  + (Evaluating Strength and Ductility of Irradiated Zircaloy Task 5)
  • ML19345H526  + (Evaluating Strength and Ductility of Irradiated Zircaloy Task 5)
  • Regulatory Guide 1.78  + (Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release)
  • ML25059A010  + (Evaluating the High Temperature Design Rules and Design Space of Section III, Division 5 and Section Viii of the ASME Boiler & Pressure Vessel Code)
  • ML24177A278  + (Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants)
  • ML20215B676  + (Evaluation & Analysis of Point Beach Nuclear Plant Unit 1, Reactor Vessel Safety Injection Nozzle-to-Shell Weld Indication)
  • ML19308D706  + (Evaluation & Comparison of Calculated Steam Head Losses & Reactor Bldg Sump Test Sys Head Losses)
  • ML19242B917  + (Evaluation & Comparison of Nuclear Power Plant Siting Methodologies)
  • ML18139A558  + (Evaluation & Critique of NUREG/CR-1580)
  • ML19275A629  + (Evaluation & Development of Ecosystem Models Assessing Environ Impact, Third Annual Rept)
  • ML20237A639  + (Evaluation & Disposition of Flaws at Quad Cities Nuclear Power Plant Unit 1 (1987 Outage))
  • ML19294B021  + (Evaluation & Performance of Open Circuit Breathing Apparatus,Respirator Studies for NRC, Oct 1977-Sept 1978)
  • ML18139A397  + (Evaluation & Proposed Changes to Tech Specs Sections 3.3, 3.4,3.6,3.8,4.1,4.5 & 4.11 Re Containment Spray Sys Performance)
  • ML19291B899  + (Evaluation & Recommendations for Ultrasonic Examinations of ASME Nuclear Class 1 & 2 Piping Welds,Code Assessment & Applications Program, Evaluation Rept)
  • ML20064K429  + (Evaluation & Screening Criteria for Peach Bottom Unit 3 Shroud Indications)
  • ML20059G090  + (Evaluation & Screening Criteria for Peach Bottom Unit-3 Shroud Indications)
  • ML20072L963  + (Evaluation & Screening Criteria for Peach Bottom Unit-2 Shroud)
  • ML19198A196  + (Evaluation - Big Rock Point Exemption Request, Decrease Decommissioning Funding)
  • ML18158A130  + (Evaluation - Memorandum Regarding Licensee Event Report Safety Significance Review in Response to Findings Associated with Inspection Procedure 95003; Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station)
  • ML20141P218  + (Evaluation Approving Use of ASME Code Cases N-397 & N-411. Applicant Must Investigate Root Cause by Considering Physical Mods Made to Piping Sys & Indicate Extent to Which Issues Resolved as Result of Revised Analyses Using Cases)
  • ML19318B823  + (Evaluation Behavior of Waterlogged Fuel Rod Failures in Lwrs)
  • ML050960303  + (Evaluation Biennial Summary Report for 2003 / 2004)
  • ML20206M556  + (Evaluation Concluding That Basis Provided by Licensee for Justifying Relief Requests for Replacement Parts Sufficient & Relief Requests 5003 & 5044 Acceptable.Licensee Should Certify Compliance W/Commitments When Replacements Complete)
  • ML20135E813  + (Evaluation Criteria for COMMUNICATIONS-RELATED Corrective Action Plans)
  • ML20038A813  + (Evaluation Criteria for Detailed Control Room Design Review)
  • ML20090E585  + (Evaluation Criteria for Detailed Control Room Design Reviews)
  • ML091460391  + (Evaluation Documenting Assessment of Oyster Creeks Response to the Condition Document in IR 00842333)
  • DCL-18-050, Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 2  + (Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 2)
  • ML14029A064  + (Evaluation ETE-NAF-20130072, Revision 0, Kewaunee Spent Fuel Pool Zirconium Fire Parameter Comparison)
  • ML25078A364  + (Evaluation Example - Pcc Cross Regional Panel Form - MAR 2025 - Redacted)
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