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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

ANSI B30.2 +, ANSI N14.6.6 +  and ANSI B30.9 +

Hydrogen +  and Copper +

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 50.49#48 +

SECY 89-122 +, SECY 86-97 +, SECY 88-272 +, SECY 83-288 +, SECY 88-260 +, SECY 82-465 +, SECY 81-687 +, L-83-146, Forwards Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell,Load Cell Linkage & Reactor Coolant Pump Motor Lift Sling to Requirements of NUREG-0612, in Response to +, L-85-398, Forwards Addl Info Re Category C-2 Steam Generator Tube Insps,Completing Response to Generic Ltr 85-02.Addl Tubes Will Be Inspected on case-by-case Basis +, L-89-144, Forwards Assessment of Amended Station Blackout Rule 10CFR50.63,description of Procedures in Place That Will Be Modified & Proposed Mods & Implementation Schedule +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +  and L-89-190, Forwards Addl Info Re Reactor Vessel Fracture Toughness,Per NRC 880531 SER Request.Extension of 30-day Submittal Date Granted by NRC +

05000250  +, 05000251  +, 00250  +  and 00251  +

Harris K +  and NextEra Energy +

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

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, 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 81-03, 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 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 85-11, 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 88-19, Use of Deadly Force by Licensee Guards to Prevent Theft of Special Nuclear Material +, 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 +

L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +  and L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +

L-83-146, Forwards Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell,Load Cell Linkage & Reactor Coolant Pump Motor Lift Sling to Requirements of NUREG-0612, in Response to +, L-85-398, Forwards Addl Info Re Category C-2 Steam Generator Tube Insps,Completing Response to Generic Ltr 85-02.Addl Tubes Will Be Inspected on case-by-case Basis +, L-89-144, Forwards Assessment of Amended Station Blackout Rule 10CFR50.63,description of Procedures in Place That Will Be Modified & Proposed Mods & Implementation Schedule +, L-89-415, Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Request for Implementation of USI Requirements +  and L-89-190, Forwards Addl Info Re Reactor Vessel Fracture Toughness,Per NRC 880531 SER Request.Extension of 30-day Submittal Date Granted by NRC +

NUREG-0993 +, NUREG/CR-1161 +, NUREG/CR-0054 +, NUREG/CR-3480 +, NUREG-4776 +, NUREG/CR-5347 +, NUREG/CR-4261 +, NUREG/CR-5230 +, 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-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 +...

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 83-288 +, SECY 88-260 +, SECY 82-465 +  and SECY 81-687 +

Washington +  and Florida +

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

Safe Shutdown +, Boric Acid +, Internal Flooding +, Notice of Violation +, Earthquake +, Control of Heavy Loads +, Backfit +, Leak-Before-Break +  and Leak Before Break +

WCAP-10858 +  and WCAP-10858-P-A +

WCAP-10858 +  and WCAP-10858-P-A +