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A list of all pages that have property "Title" with value "Safety Safeguards Status". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20246E732  + (Safety Research Programs Sponsored by Office of Nuclear Regulatory Research.Progress Report,January-March 1989)
  • ML20206A940  + (Safety Research Programs Sponsored by Office of Nuclear Regulatory Research.Quarterly Progress Report,April-June 1986)
  • ML20207H406  + (Safety Research Programs Sponsored by Office of Nuclear Regulatory Research.Quarterly Progress Report, October-December 1985)
  • ML20066D018  + (Safety Research Programs Sponsored by Office of Nuclear Regulatory RESEARCH.January-March 1982)
  • ML20039F810  + (Safety Research Programs Sponsored by Office of Nuclear Regulatory Research.Quarterly Progress Report,April 1-June 30,1981)
  • ML20093E335  + (Safety Research Programs Sponsored by the Office of Nuclear Regulatory Research.Quarterly Progress Report,October 1 - December 31,1983)
  • ML20087M802  + (Safety Research Programs Sponsored by the Office of Nuclear Regulatory Research.Quarterly Progress Report,April-June 1983)
  • ML20083D402  + (Safety Research Programs Sponsored by the Office of Nuclear Regulatory Research.Quarterly Progress Report,January 1- March 31,1983)
  • ML20203L858  + (Safety Research in Next Decade, Presented at Halden Meeting in Lillehammer,Norway on 980316)
  • ML20031C216  + (Safety Review Approving Proposed Tech Spec Change 92, Allowing Replacement of Reactor Vessel Closure Studs)
  • ML13316B886  + (Safety Review Rept for Nuclear Instrumentation Sys)
  • ML20205E795  + (Safety Review Training Program Description. Related Info Encl)
  • ML20135E688  + (Safety Review for LaSalle County Station Units 1 & 2 Safety Relief Valves Reduction & Setpoint Tolerance Relaxation Analyses)
  • ML20148L035  + (Safety Review of Amend Appl of 780928 Re Storage of Fuel Assemblies at Subj Facil.Amend Is Concerned Soley W/Nuc Criticality Safety in Partial Dismantling of of Fuel Assemblies.Approval of Amend Is Recommended)
  • ML20148N530  + (Safety Review of Amend to Delete Requirements for Separate Training Prog for Each Worker Category Pc 77070A.Recommends Approval of Amend)
  • ML20028G368  + (Safety Review of Browns Ferry Nuclear Plant Unit 1 at Core Flow Conditions Above Rated Flow During Cycle 5)
  • ML20091J905  + (Safety Review of Peach Bottom Unit 3 at Core Flow Conditions Above Rated Flow Throughout Cycle 6)
  • ML20087L093  + (Safety Review of Pilgrim Nuclear Power Station,Unit 1 at Core Flow Conditions Above Rated Flow Throughout Cycle 6)
  • ML20127N856  + (Safety Review of Trojan Plant Restart:Steam Generator Deterioration & Interim Plugging Criteria)
  • ML17278A805  + (Safety Review of WPPSS Nuclear Project 2 at Core Flow Conditions Above Rated Flow Throughout Cycle 1 & Final Feedwater Temp Reduction)
  • ML20009B841  + (Safety Review of the Design,Operation and Radiation Sections of the General Electric Morris Operation Consolidated Safety Analysis Report)
  • ML18009A522  + (Safety Review on Aircraft Hazards Study of Facility. Operation of Facility in Vicinity of Proposed Airport Would Be Acceptable on Condition That Operational Level of Airport Would Not Exceed Licensee 10-yr Projection)
  • ML20310A277  + (Safety Risk Metrics for Light Water Reactors and Advanced Light Water Reactors Presented at Institute of Nuclear Material Management Conference on Risk-Informing Security Using Safety Risk Information)
  • ML19312C972  + (Safety Role of Regulatory,Corporate & Personal Initiatives in the 1980s)
  • ML23242A153  + (Safety Safeguards Gantt)
  • ML20246E935  + (Safety Series Document on Regulating Use of Consumer Products Containing Radioactive Substances, Draft for Comments)
  • ML021160410  + (Safety Significance Assessment of the Davis-Besse Nuclear Power Station, Unit 1 Reactor Pressure Vessel Head Degradation - Non-Proprietary Version)
  • ML050540254  + (Safety Significance Evaluation of ECCS Containment Sump Voided Piping)
  • ML053610092  + (Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 1, Revision 1)
  • ML053610100  + (Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 2, Revision 1)
  • Information Notice 1980-14, Safety Suggestions from Employees  + (Safety Suggestions from Employees)
  • ML20046A260  + (Safety Sys Functional Assessment, Low Pressure Core Spray & RCIC Sys)
  • ML20151B287  + (Safety Sys Functional Insp Plan)
  • IR 05000255/1986029  + (Safety Sys Functional Insp Rept 50-255/86-29 on 860922-1024. Potential Enforcement Findings:Lack of seal-in Feature for Recirculation Actuation signal,air-operated Valve Design Deficiencies & Misleading Info to Control Room Operators)
  • ML14175B480  + (Safety Sys Functional Insp Rept 50-261/87-06 on 870309-0415. Violations Noted:Inadequate Implementation of App R Dedicated Shutdown,Emergency Diesel Generator Failures & Inadequate Electrical Switchgear Coordination)
  • IR 05000333/1989080  + (Safety Sys Functional Insp Rept 50-333/89-80 on 890501-26. Violations,Deficiencies & Unresolved Items Noted.Major Areas Inspected:Electrical Power Sys,Including Emergency Diesel Generators & Support Sys)
  • ML17346B149  + (Safety Sys Functional Insp Repts 50-250/85-32 & 50-251/85-32 on 850826-0913.Ten Potential Enforcement Findings Noted During Auxiliary Feedwater Sys Insp in Areas of Maint, Operations,Surveillance,Qa,Training & Design Changes & Mod)
  • IR 05000338/1989200  + (Safety Sys Outage Mod & Maint Team Insp Repts 50-338/89-200 & 50-339/89-201 on 890508-12 & 22-26.No Violations Noted. Major Areas Inspected:Implementation of Matl & Work Control Sys to Ensure Mod Conformed to Installation Requirements)
  • ML20212M485  + (Safety Sys Outage Mod Insp Rept 50-285/85-22 on 850916-1008. Deficiencies Noted:Engineering Input Into post-mod Testing Procedures Inadequate,Seismic Requirements Not Properly Addressed & Incorrect or Inappropriate Documents Used)
  • IR 05000286/1987013  + (Safety Sys Outage Mod Insp Rept 50-286/87-13 on 870422-0714. Rept Describes Activities & Findings Associated W/First Portion of Team Insp Re Outage Design Insp)
  • IR 05000295/1988003  + (Safety Sys Outage Mod Insp Rept 50-295/88-03 on 880329-0602. Violations Noted.Major Areas Inspected:Design,Installation & Testing of Several Mods to Be Performed During Outage & Util Corrective Action Program)
  • IR 05000482/1987032  + (Safety Sys Outage Mods Insp Rept 50-482/87-32 on 871102-20. Major Areas Inspected:Verification That Detailed Design, Engineering Support & Procurement Activities Adequate to Support safety-related Mods Performed During Outage)
  • ML20214M994  + (Safety Sys in Atomic Power Stations W/Std Reactor VVER-1000, NRC Translation 849)
  • ENS 55436  + (Safety System Actuation)
  • ENS 43303  + (Safety System Actuation - Autoclave High Condensate Level Alarm Received During Heatup)
  • ENS 43787  + (Safety System Actuation Due to Incidental Uf6 Release)
  • ENS 40599  + (Safety System Actuation at Portsmouth Gdp)
  • ML021020555  + (Safety System Design & Performance Capability Inspection NRC Inspection Report Nos. 50-269/2002-09, 50-270/2002-09 & 50-287/2002-09)
  • ML051170013  + (Safety System Design and Performance Capability Inspection - NRC Inspection Report 05000413/2005009 and 05000414/2005009 - Notification Letter)
  • ML022190508  + (Safety System Design and Performance Capability Inspection Report Nos. 50-250/2002-05, 50-251/2002-06)
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