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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

ANSI B30.9 +  and ANSI B30.2 +

Copper +, Nitrogen +, Hydrogen +  and Lead +

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 83-288 +, SECY-85-349 +, SECY 88-260 +, SECY-88-260 +, SECY-89-122 +, SECY 84-119 +, U-601563, Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl +, U-601427, Forwards Response to Station Blackout rule,10CFR50.63, Satisfying Requirement That Proposed Station Blackout Coping Duration,Description of Procedures to Be Implemented & List of Mods,As Required,Be Submitted +, U-600733, Interim Deficiency Rept 55-86-10 Re Plant Mods Performed W/O Adequate Spec & Required Testing & Test Criteria. Initially Reported on 860919.Mods Affecting Structures,Sys or Components Reviewed +, U-601317 +, SECY-84 119 +  and SECY-86 97 +

05000461  +  and 00461  +

40 FR 2730 +  and 50 FR 32130 +

John Hickman +  and Office of Nuclear Reactor Regulation +

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

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 81-03, Implementation of NUREG-0313,Technical Report on Material Selection & Processing GL for BWR Coolant Press Boundary Piping +, 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 84-24, Certification of Compliance to 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for 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 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +, 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 87-02, 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" +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +, ML20012E937 +  and ML20012E937 +

Westinghouse +  and General Electric +

NUREG-0993 +, NUREG/CR-1161 +, NUREG/CR-0054 +, NUREG/CR-3480 +, NUREG/CR-5347 +, NUREG/CR-5230 +, NUREG/CR-3922 +, NUREG-0019 +, NUREG-0653 +, NUREG/CR-4776 +, NUREG-0061 +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, 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-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, NUREG-1032, Draft Reg Guide,Task SI 501-4, Station Blackout. Draft NUREG-1109 & NUREG-1032 Re Regulatory/Backfit Analysis for Resolution of USI A-44 & Evaluation of Station Blackout Accidents at Nuclear Power Plants,Respectively,Encl +, NUREG-1109, Recommends That Final Station Blackout Rule,As Contained in Encl Fr Notice & Reg Guide,Providing Method Acceptable to Comply W/Rule,Be Issued in Order to Implement Final Resolution of USI A-44 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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-0400, Ack Clarifying 861119 Inquiry Re Validity of Docket 99900318.Docket Reassigned to New Company Name & White Book Vendor Info Changed Accordingly +, 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.. +...

ST +  and CP +

TAC:69130 +  and TAC:74396 +

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

SECY 89-122 +, SECY 86-97 +, SECY 88-272 +, SECY 83-288 +, SECY-85-349 +, SECY 88-260 +, SECY-88-260 +, SECY-89-122 +, SECY 84-119 +, SECY-84 119 +  and SECY-86 97 +

10w-tempera +, M1A-FORINFU +  and 1LONS-TERMFR0 +

Washington +  and Illinois +

Steam Generator +, Feedwater +, Reactor Protection System +, Reactor Pressure Vessel +, Core Spray +, Standby Liquid Control +, Decay Heat Removal +, Safety Relief Valve +  and Control Rod +

Safe Shutdown +, Hydrostatic +, Intergranular Stress Corrosion Cracking +, Earthquake +, Control of Heavy Loads +, Backfit +, Water hammer +  and Leak Before Break +