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A list of all pages that have property "Title" with value "Submits Info Re NRC Document Control Sys,Per 800909 Memo". Since there have been only a few results, also nearby values are displayed.

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List of results

  • 0CAN129504, Submits Info Re Manner in Which Basic Emergency Planning Info Disseminated to Public within ANO Plume Exposure Pathway Emergency Planning Zone During 1995  + (Submits Info Re Manner in Which Basic Emergency Planning Info Disseminated to Public within ANO Plume Exposure Pathway Emergency Planning Zone During 1995)
  • ML20091A648  + (Submits Info Re Mark I Containment,Per 760707 & 0819 Meetings with NRC)
  • ML18030A313  + (Submits Info Re Meteorological Sys,In Response to NRC Informal Questions.Dual Source Power Supplies Will Be Provided to Both Primary & Backup Towers.Fsar Will Be Revised in mid-Sept.Diagram of Primary Tower Encl)
  • ML20086S912  + (Submits Info Re Methodology & Schedule for Responding to Suppl 4 to Generic Ltr 88-20, Individual Plant Exam of External Events for Severe Accident Vulnerabilities. Exam Results Expected to Be Submitted by 961218)
  • BVY-92-111, Submits Info Re Methodology/Plans to Address Suppl 4 to GL 88-20 Re IPE of External Events for Severe Accident Vulnerabilities.Internal Fires & Internal Floods Will Be Analyzed W/Level 1 Pra.Results Will Be Sent by 950630  + (Submits Info Re Methodology/Plans to Address Suppl 4 to GL 88-20 Re IPE of External Events for Severe Accident Vulnerabilities.Internal Fires & Internal Floods Will Be Analyzed W/Level 1 Pra.Results Will Be Sent by 950630)
  • ML18037A187  + (Submits Info Re Mgt & Technical Resources Available to Respond to Unusual Event,In Response to NRC 790629 Request)
  • ML20056A348  + (Submits Info Re Mgt Changes at Facility & Changes in Addresees for NRC Correspondence)
  • ML20202B960  + (Submits Info Re Mgt Structure,Per Request,Including Names of Summa Medical Corp Board of Directors,Corporate Officers & President.Response Should Be Held in Confidence Due to Competitive Nature of License Venture)
  • ML19345F160  + (Submits Info Re Minor Changes Made to Facility During CY80.Filtered Exhaust Sys Installed to Exhaust Air from Reactor Bay During Emergency.Monitor Meter Installed in Reactor Control Room to Provide Status Indication)
  • ML19345F161  + (Submits Info Re Minor Changes Made to Facility During CY80.Filtered Exhaust Sys Installed to Exhaust Air from Reactor Bay During Emergency.Monitor Meter Installed in Reactor Control Room to Provide Status Indication)
  • ML19289D804  + (Submits Info Re Missing Parts of AC & DC Solenoid Operated Valves:Name & Address of Reporting Individual Facility, Activity,Component Affected,Firm Constructing or Supplying Facility,Description of Defect & Report Date)
  • ML20096G470  + (Submits Info Re Mns,Unit 1 SGs Dec 1995 EOC-10 Refueling Outage F*,15-day & 12-month Insp Rept.Results Encl)
  • ML19340B134  + (Submits Info Re Mod Containment Purging.Mod Complete on Unit 1.Mod Scheduled to Be Completed on Unit 2 During Snubber Insp Outage 810228)
  • ML19323A624  + (Submits Info Re Mod Performed on Reactor Coolant Pumps,Fire Protection Item 3.15.Seventeen Photographs Encl.Drawings Available in Central Files Only)
  • TXX-9070, Submits Info Re Mod to Insp Program for Connecting Rods on Facility Train a Diesel Generator  + (Submits Info Re Mod to Insp Program for Connecting Rods on Facility Train a Diesel Generator)
  • ML19351F691  + (Submits Info Re Model 4kV Magne-Blast Breakers Ref Partially Omitted from Bulletin 74-09)
  • ML19323B344  + (Submits Info Re Model 6400 Overpack,In Response to NRC .No Model 6400 Packaging Owned)
  • ML20198R220  + (Submits Info Re Model 7062B,serial Numbers 22874 & 21615)
  • ML20197B646  + (Submits Info Re Moderator Temp Coefficient (Mtc) Prior to Unit 1 Cycle 10,per 861001 Meeting.Generic ATWS Assumptions Will Be Addressed.Unit 1 Cycle 9 & Unit 2 Cycle 8 Mtc Will Be Negative at 100% Power)
  • ML17306B028  + (Submits Info Re Modification of Current Periodic Testing Performed on App R dual-life Fixtures,To Supplement 900801 Response to Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25 Re Safe Shutdown Emergency Lighting)
  • ML19253C842  + (Submits Info Re Modified Amended Security Plan.Info Withheld (Ref 10CFR2.790))
  • ML19338C827  + (Submits Info Re Mods to Reactor Operator Training Program in Response to NRC .Course Summaries for Thermodynamics,Fluid Flow & Heat Transfer Training & for Mitigating Core Damage Encl)
  • ML20244E422  + (Submits Info Re NDE of Feedwater Nozzles & safe-end Welds During 1988 Maint/Refueling Outage.No Significant Indications or Evidence of Cracking Noted)
  • ML19257A199  + (Submits Info Re NRC 791109 Interim Position for Containment Purge & Vent Valve Operation.Normal Online Purging of Containment Not Routine Operation.Isolation for Purge & Vent Sys Provided by Butterfly Valves)
  • ML18010A967  + (Submits Info Re NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification. CP&L Modified Design of Supports During Refueling Outage RFP 4,which Completed Actions Re Bulletin)
  • ML19284C409  + (Submits Info Re NRC Document Control Sys,Per 800909 Memo)
  • ML19340E549  + (Submits Info Re NRC Program Plans to Assure That safety- Related Equipment in Nuclear Facilities Is Qualified to Perform Function Under Accident Conditions.Forwards SECY-80-319 Outlining New Qualification Program.W/O Encl)
  • ML19340E554  + (Submits Info Re NRC Program Plans to Assure That safety- Related Equipment in Nuclear Facilities Is Qualified to Perform Function Under Accident Conditions.Forwards SECY-80-319 Outlining New Qualification Program.W/O Encl)
  • ML19340E546  + (Submits Info Re NRC Program Plans to Assure That safety- Related Equipment in Nuclear Facilities Is Qualified to Perform Function Under Accident Conditions.Forwards SECY-80-319 Outlining New Qualification Program.W/O Encl)
  • ML19340E553  + (Submits Info Re NRC Program Plans to Assure That safety- Related Equipment in Nuclear Facilities Is Qualified to Perform Function Under Accident Conditions.Forwards SECY-80-319 Outlining New Qualification Program.W/O Encl)
  • ML19340E557  + (Submits Info Re NRC Program Plans to Assure That safety- Related Equipment in Nuclear Facilities Is Qualified to Perform Function Under Accident Conditions.Forwards SECY-80-319 Outlining New Qualification Program.W/O Encl)
  • ML19340E559  + (Submits Info Re NRC Program Plans to Assure That safety- Related Equipment in Nuclear Facilities Is Qualified to Perform Function Under Accident Conditions.Forwards SECY-80-319 Outlining New Qualification Program)
  • ML20042C033  + (Submits Info Re NRC Review of Radiation Control Program in Response to)
  • ML20003H302  + (Submits Info Re NUREG-0737 Item II.K.3.30 for Small Break LOCA Methods.Justification of Present Model Provided by Comparison to Existing Data,Per NUREG-0565.Review & Approval Requested by 810601.Unit 2 Results by 820101)
  • ML20135F363  + (Submits Info Re NUREG-0737,Item II.B.3,concerning post-accident Sampling Sys,Per 850507 Request.Ornl Chloride Analysis Methods Should Meet NRC Guidelines for Chloride Analysis)
  • A03616, Submits Info Re NUREG-0737,Items II.E.1.2, Safety Grade Auxiliary Feedwater Sys Initiation & Flow Indication & II.K.3.3, Reporting of Safety & Relief Valve Failures & Challenges, Per Util & Generic Ltr 82-16  + (Submits Info Re NUREG-0737,Items II.E.1.2, Safety Grade Auxiliary Feedwater Sys Initiation & Flow Indication & II.K.3.3, Reporting of Safety & Relief Valve Failures & Challenges, Per Util & Generic Ltr 82-16)
  • ML20136A536  + (Submits Info Re Natl Academy for Nuclear Training.Charter for Academy,Brochure Describing Various Activities & Ltrs to Moynihan & Herrington Encl)
  • ML19340E310  + (Submits Info Re New Applications to Be Submitted,Per NRC 801205 Request)
  • ML18136A449  + (Submits Info Re New Steam Generator Nozzle Design.Design Issued Prior to Present Concerns About Feedwater Pipe Cracking.Possible Conclusion Concerning Advantages of Welded Nozzle in Preventing Nozzle Cracks Is Premature)
  • ML20239A000  + (Submits Info Re Nonconformance Rept 4490,per Request at 840927 Meeting.Numbers of safety-related Welds Reinspected & & Rejected Noted & Company Providing Bulk of Rexaminers Stated.Related Info Including Partially Deleted Info Encl)
  • ML20062D898  + (Submits Info Re Noninvasive Vessel Level Sys Results. Neutron Detector Assemblies Do Not Meet Stds & Are Not Compatible w/NUREG-0737,Item II.F.2.Review of Available Sys Initiated.Status Rept Expected by 830201)
  • ML20210J564  + (Submits Info Re Notification of Upcomming Shipment of 8x20 Containers of Enriched UF6,contained in 31 Type AF Packages IAW Convention on Physical Protection of Nuclear Matl & NRC Final Rule of 870326)
  • ML19290E741  + (Submits Info Re Nuclear Package,Under 20CFR71.Will Comply W/All Certificates QA Programs & Documents Re Use & Maint of Packaging.Forwards New England Nuclear Re Application for Certificate of Competent Authority)
  • ML20148B916  + (Submits Info Re Nuclear Property Insurance,In Compliance W/ 10CFR50.54(w))
  • ML20148B952  + (Submits Info Re Nuclear Property Insurance Coverage for Plant in Compliance w/10CFR50.54(w))
  • ML20077E130  + (Submits Info Re Nuclear Property Insurance in Effect at Facilities Per 10CFR50.54(W) by Primary/Excess Property & Liability Limits)
  • ML18030A262  + (Submits Info Re Number & Types of Respiratory Equipment for Facility)
  • ML19332G062  + (Submits Info Re Number of Tubes Plugged in Steam Generator 12 During Current Outage.Two Tubes Had Indications Which Exceeded Tech Spec Plugging Limit of 40% Penetration)
  • ULNRC-03488, Submits Info Re Number of Tubes Plugged During Ninth Steam Generator Tube Inservice Insp  + (Submits Info Re Number of Tubes Plugged During Ninth Steam Generator Tube Inservice Insp)
  • ML19317G514  + (Submits Info Re OL Application Status.Fsar Submitted as Amend 11 to OL Application.Projected Fuel Loading Date Is July 1973,commercial Operation Planned for Sept 1973 & Presentation to ACRS Planned for Sept 1972)
  • ML20052E837  + (Submits Info Re Odyn Code Reanalysis Requirements,In Response to Generic Ltr 81-37.Code Will Be Used for Pressurization Transient Calculations Beginning W/Cycle 10 Reload Design & Safety Analysis.Results Expected by 820630)
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