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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

ANSI B30.9 7 +  and ANSI B30.2 +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +  and 10 CFR 50.54#f +

SECY 89-122 +, SECY 86-97 +, SECY 88-272 +, SECY-85-349 +, SECY 88-260 +, SECY-88-260 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY-84-119 +  and SECY-86-97 +

05000237  +, 05000456  +, 05000457  +, 00456  +, 00457  +  and 00454  +

Sands S +  and Office of Nuclear Reactor Regulation +

GDC 4, Environmental and dynamic effects design bases +  and GDC 16 +

NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 83-42, Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" +, NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +, NRC Generic Letter 87-03, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 89-12, Operator Licensing Examination +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 29-19 +, NRC Generic Letter 83-47 +  and NRC Generic Letter 39-19 +

ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +, ML20033F189 +  and ML20033F189 +

NUREG-0993 +, NUREG/CR-1161 +, NUREG/CR-0054 +, NUREG/CR-3480 +, NUREG/CR-5347 +, NUREG/CR-4261 +, NUREG/CR-5230 +, NUREG/CR-3922 +, NUREG/CR-4470 +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-1289, Submits Revised Agenda for CRGR Meeting 141 on 880714 in Bethesda,Md.Items for Review Include Proposed Generic Ltr on Instrument Air Problems & Proposed Draft Rule to Require College Degrees for Senior Reactor Operators +, NUREG/CR-3509, Summary of 880628 Meeting W/Util in Rockville,Md Re Removal of Temporary Wall Dividing Control Room.Attendee List & Draft NUREG/CR-3509 Encl +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-1233, Informs of NRC Plans to Visit Tokyo on 890920-28.Requests Meeting W/Ministry of Intl Trade & Industry on 890921 to Discuss Advanced BWR Licensing Issues & Review Status.Srp, NUREG-1233 & Questions & Discussion Topics Encl.W/O SRP +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-1174, Summary of CRGR Meeting 163 on 890524 Re Proposed Generic Ltr on Emergency Response Data Sys,Usi A-17 on Sys Interactions,Generic Issue A-30 on safety-related Dc Power Sys & USI A-47 on Control Sys +, NUREG-1229, Forwards Revised Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Package Requested to Be Revised to State More Explicitly Proposed Actions Taken by Licensees & by Nrc.Issue Identified as Category 2 Action +, NUREG-1002, Forwards Sser 4 (NUREG-1002) Re Operation of Facility,For Use.Rept Being Placed in Pdr.W/O Encl +, NUREG-0876, Advises That Preservice Insp Program,Described in Util 860723,0902,30 & 1016 Ltrs,Acceptable & in Compliance W/ 10CFR50.55a(g)(3).Safety Evaluation Will Be Included in Sser 7 (NUREG-0876) +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0902, Forwards Listed Reg Guides & NUREGs in Response to Interest Expressed at Blue Ribbon Commission on Siting 921116 Meeting.W/O Encls +, NUREG/CR-1582, Forwards Aug 1980 NUREG/CR-1582,Vols 2 & 3, Seismic Hazard Analysis,Solicitation of Expert Opinion, Prepared by Tera Corp.W/O Encl +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +...

CP +  and RT +

TAC:64035 +, TAC:68515 +  and TAC:64030 +

Regulatory Guide 1.155 +, Regulatory Guide 1.139 +, Regulatory Guide 1.113 +  and Regulatory Guide 1.154 +

SECY 89-122 +, SECY 86-97 +, SECY 88-272 +, SECY-85-349 +, SECY 88-260 +, SECY-88-260 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY-84-119 +  and SECY-86-97 +

01shan-NRR +, 48FR-2730-2733 +, 1SHORT-TERMPR0 +  and M8RFG-1233 +

Dresden +  and Braidwood +

Steam Generator +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +  and Containment Spray +

Earthquake +, Control of Heavy Loads +, Backfit +, Water hammer +  and Leak Before Break +