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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

ANSI N14.6.6 +  and ANSI B30.9 +

Nitrogen +, Hydrogen +  and Lead +

SECY 89-122 +, SECY 86-97 +, SECY 88-272 +, SECY 88-260 +, SECY-89-122 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY-84-119 +, L-85-11 +  and L 01 +

05000220  +  and 00220  +

Terry C +  and Niagara Mohawk +

GDC 50 +, GDC 16 +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 79-57, Acceptance Criteria for the Mark I Containment Long Term Program +, 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 81-04, Emergency Procedures And Training for Station Blackout Events +, 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 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +, 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 84-11, Inspections of BWR Stainless Steel Piping +, 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) +  and NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +

ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +, ML18038A771 +...

L-85-11 +  and L 01 +

ML17055E055 +, NRC Generic Letter 1989-12 +, ML17037C094 +, ML17037B593 +, ML17037B535 +, ML17037A773 +, ML20009E437 +, ML20050D485 +, 05000410/LER-1986-009, :on 861124,reactor Bldg Ventilation Exhaust Damper 2HVR*AOD9B Closed Initiating Standby Gas Treatment Train A.Caused by Jumper Which Fell & Shorted to Ground. Alternate Installation Methods Under Review +, ML20072M755 +, 05000220/LER-1982-017-03, /03L-0:on 821206,during Maint Outage,Leakage from Valves 68-06 & 68-09 Found Exceeding Tech Specs.Caused by Poor Seal Design.Mods Will Be Completed During Current Outage & Followed by Retest +, ML18038A418 +, IR 05000220/1989003 +, 05000220/LER-1980-028, Forwards LER 80-028/04T-0 +, ML17053C251 +, ML17055E133 +, ML17055E666 +, ML17056A192 +, ML17053C239 +, ML17054A772 +, ML17053A290 +, ML17056A318 +  and ML17053C923 +

Westinghouse +  and General Electric +

NUREG-0993 +, NUREG/CR-1161 +, NUREG/CR-0054 +, NUREG/CR-3480 +, NUREG/CR-3805 +, NUREG/CR-4261 +, NUREG/CR-3922 +, NUREG/CR-4470 +, 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-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-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-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-1211, Informs of CRGR Meeting 98 Agenda Mod +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, 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 +, NUREG-1217, Forwards NRC Resolution of USI A-47, Safety Implications of Control Sys, for Info.Resolution Consists of NUREG-1217, Evaluation of Safety Implications...Technical Findings Re USI A-47 & NUREG-1218, Regulatory Analysis.... W/O Encls +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +...

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

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

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

Safe Shutdown +, Intergranular Stress Corrosion Cracking +, Control of Heavy Loads +, Backfit +  and Water hammer +