Browse wiki

CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.49 +, 10 CFR 50.62 +  and 10 CFR 50.63#c31 +

SECY 86-97 +, SECY 88-772 +, SECY 88-269 +, NLS-89-290 +  and NLS-89-308 +

05000324  +, 05000325  +, 00325  +  and 00324  +

Loflin L +  and Carolina Power & Light Co. +

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 84-04, 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 85-11, 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) +  and NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +

ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +, ML19332D647 +  and ML19332D647 +

ML20112F641 +, IR 05000324/1988035 +  and BSEP-89-0785, Supplemental Response to NRC Re Violations Noted in Insp Repts 50-324/89-01 & 50-325/89-01.Corrective Actions:Special Procedure OSP-89-018 Developed for Testing of RHR & Core Spray Pump Motors +

NLS-89-290 +  and NLS-89-308 +

NUREG-1269 +, NUREG-09 +, NUREG/CR-0054 +, NUREG-4776 +, NUREG/CR-5347 +, NUREG-0644 +, NUREG/CR-4761 +, NUREG-057 +, NUREG-08108 +, 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-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-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-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-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-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +, NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

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

SECY 86-97 +, SECY 88-772 +  and SECY 88-269 +

Steam Generator +, Feedwater +  and Residual Heat Removal +

Control of Heavy Loads +  and Water hammer +