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A list of all pages that have property "Title" with value "Review & Evaluation of NRC Safety Research Program for FY81". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML19261A743  + (Reverses 781219 Denial of Intervention,Finding Sufficient Interest in the Proceeding in Petitioners Geographical Proximity to & Recreational Activity in the Vicinity of Facility)
  • ML19305A223  + (Reverses 790109 Decision & Allows NRDC to Intervene in Proceeding on Discretionary Basis,Per 790212 Stipulation of Parties)
  • ML20217B271  + (Reverses 980304 Statement Which Offered No Objection to Making Public Draft Secy Paper Attached to COMSECY-98-04. Advises That Commissioner Dicus Approach to Duration of Combined License Would Be Preferrable)
  • ML19220B761  + (Reverses ASLB 770214 Order & Remands W/Instructions to Deny Untimely Intervention Petition of Environ Coalition on Nuclear Power.Certificate of Svc Encl)
  • ML19326A787  + (Review & Acceptance of Spent Fuel Storage & Handling Applications)
  • ML19319D946  + (Review & Acceptance of Spent Fuel Storage & Handling Applications)
  • ML20209J471  + (Review & Analysis of Hydraulic & Tracer Testing at C-Holes Complex Near Yucca Mountain,Nv)
  • ML20151D383  + (Review & Analysis of Radium Incidents)
  • ML18057A966  + (Review & Analysis of SRP Chapter 15 Events for Palisades W/ 15% Variable High Power Trip Reset)
  • ML19290F407  + (Review & Assessment of Package Requirements (Yellowcake) & Emergency Response to Transportation Accidents, Final Rept)
  • ML19242C979  + (Review & Assessment of Package Requirements (Yellowcake) & Emergency Response to Transportation Accidents, Draft Rept)
  • ML19318B583  + (Review & Assessment of Research Relevant to Design Aspects of Nuclear Power Plant Piping Sys, Final Rept)
  • ML20207A715  + (Review & Assessment of Water Hammer Occurrences,CY81-CY85)
  • ML20147D393  + (Review & Comment of Rept by Dr Sternglass Re Radioactivity & Health Statistics Around Nuc Facil in Ct.Finds No Support for Contention That CT Nuc Plants Have Released Sufficient Radionuclides to Cause Significant Radiat Exposure)
  • ML20136D045  + (Review & Comment on Regulatory Analysis for USI A-46, Seismic Qualification of Equipment in Operating Plants)
  • ML19343A137  + (Review & Comments on 800707 Statement Prepared for Util Nuclear Waste Mgt Group & EEI Re Capability for Safe Interim Storage of Spent Fuel)
  • ML20049J366  + (Review & Comments on Feb 1982 Rept by Weston Geophysical Corp on Description & Evaluation of Bedrock Surface Structures in Vicinity of Midland Plant - Units 1 & 2 Midland,Mi)
  • ML19206B125  + (Review & Comments on Suppl 7 Re First stress-steel Prestressing Tendon Anchorage Sys for Nuclear Containments Will Be Completed by 710312)
  • ML19340A346  + (Review & Evaluation of Dames & Moore Verification Study of Hurricane Storm Surge Model)
  • ML20204F187  + (Review & Evaluation of Emergency Preparedness at Research & Test Reactors, to Be Presented at 830401-03 Reactor Operations Div of ANS Topical Meeting in Scottsdale,Az)
  • ML20236V830  + (Review & Evaluation of Historical Fire Protection Licensing Basis Related to Fire Areas Ix,X,Xi,Xv,Xvii & Xviii at Ja FitzPatrick Nuclear Power Plant)
  • ML20202E254  + (Review & Evaluation of Industry Proposed Safety Factors for Steam Generator Tube)
  • ML20008F409  + (Review & Evaluation of Licensing Actions for Operating Reactors, Monthly Progress Rept for Period Ending 810228)
  • ML19340C103  + (Review & Evaluation of Licensing Actions for Operating Reactors, Monthly Progress Rept for Oct 1980)
  • ML20212H741  + (Review & Evaluation of NRC Safety Research Program for FY88, Rept to Congress)
  • ML19284A882  + (Review & Evaluation of NRC Safety Research Program for FY81)
  • ML19221A331  + (Review & Evaluation of Personnel Dosimetry Data from 790328-0405)
  • ML20059F422  + (Review & Evaluation of Recent Publications Bearing on Fuels Sections of the Draft Mhtgr Pser)
  • ML20214E480  + (Review & Evaluation of Tdi Diesel Engine Reliability & Operability - San Onofre Nuclear Generating Station Unit 1, Technical Evaluation Rept)
  • ML20127B927  + (Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Grand Gulf Nuclear Station,Unit 1)
  • ML20097H616  + (Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Comanche Peak Steam Electric Station Unit 1, Technical Evaluation Rept)
  • ML20133B068  + (Review & Evaluation of Tdi Diesel Engine Reliability & Operability - River Bend Station Unit 1)
  • ML20111A655  + (Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Shoreham Nuclear Power Station Unit 1)
  • ML19330B249  + (Review & Integration of Existing Literature Concerning Potential Social Impacts of Transportation of Radioactive Matls in Urban Areas)
  • ML13317B229  + (Review & Reassessment of SONGS 1 Lower Reactor Internals & Vessel Insp)
  • ML19261D065  + (Review & Recommendations of Dose Conversion Factors & Environ Transport Parameters for Pb-210 & Ra-226, Final Rept)
  • 05000482/FIN-2012008-06  + (Review Actions to Correct Water Hammer Events in the ESW System)
  • 05000324/FIN-2007003-02  + (Review Adequacy of Licensee Monitoring and Control of SDSP Releases to Ensure Doses to Members of the Public Are Maintained ALARA.)
  • 05000361/FIN-2007008-01  + (Review Adequacy of Manual Action Completion Times for Control Room Evacuation.)
  • 05000324/FIN-2008002-01  + (Review Adequacy of Suppression Pool Temperature Monitoring System Calibration Relative to Technical Specification SR 3.3.3.1.3 Channel Calibration)
  • ML18074A124  + (Review Approach and Expectations for the NuScale Power LLC Initial Test Program)
  • ML040360415  + (Review Backfit Rule Handwritten Notes)
  • ML20237K219  + (Review Comments & Responses to Spook Preliminary Final Cadsar)
  • ML20133P250  + (Review Comments on ESF Alcove Ground Support Analysis & ESF Ground Support - Structural Steel Analysis)
  • L-2012-115, Review Comments on Safety Evaluation Report and Technical Specifications for Amendments 247 and 243, Relocation of Cycle Specific Parameters to the Core Operating Limits Report (Colr)  + (Review Comments on Safety Evaluation Report and Technical Specifications for Amendments 247 and 243, Relocation of Cycle Specific Parameters to the Core Operating Limits Report (Colr))
  • ML20207T407  + (Review Comments on Seabrook Station Steam Generator Tube Response During Severe Accidents & Related Section of Technical Evaluation of EPZ Sensitivity Study for Seabrook)
  • ML071070027  + (Review Complete, Response to GL 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power)
  • ML19319C454  + (Review Completed of Licensee Proposed Procedure for Stuck Rod Measurement & High Reactivity for Ejected Rod Accident. Proposed Test Considered to Exceed Bounds of Safety Analysis & Is Unacceptable)
  • ML20073L814  + (Review Criteria for the Physical Fitness Training Requirements in 10 CFR Part 73)
  • ML073170640  + (Review Date Change for Proposed Revision to Technical Specification Pressurizer Power Operated Relief Valves Testing)
  • ML20148P094  + (Review Draft of Chapter 10 to Oper Specs Containing Additions to Oper Specs Originally Submitted as Proposed Specs in June 1977)
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