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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

ASME Section III +  and ASME Section XI +

Iodine +, Carbon +, Hydrogen +, Chlorine +, Zirconium +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 52 +, 10 CFR 61 +, 10 CFR 50.34 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 73.55 +, 10 CFR 50.49#f +, 10 CFR 50.34#f +, 10 CFR 50.34#0 +  and 10 CFR 52.47#aiv +

Initiating Events +  and Physical Protection +

SECY-93-087 +, SECY 89-122 +  and SECY-90-016 +

Fox J +  and GENERAL ELECTRIC CO. +

GDC 41 +, GDC 18 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +, ML20036A066 +  and ML20036A066 +

4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 384 +, IEEE 344 +, IEEE 323 +, IEEE 279 +, IEEE 603 +, IEEE 308 +, IEEE 741 +  and IEEE 741-1986 +

Target Rock +  and General Electric +

Information Notice 83-41 +  and Information Notice 87-12 +

NUREG/CR-1161 +, NUREG-0311 +, NUREG-037 +, NUREG/CR-1924 +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, 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-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-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-9033 +, 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/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +, NUREG-1469, Submits Advanced Comments for Meeting of ABWR GE & ACRS Re NUREG-1469 +, 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-4171 +, NUREG-0305, Forwards NUREG-0305,technical Rept on Dc Power Supplies in Nuclear Power Plants.W/O Encl +, 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-0193, Research Info Ltr 18:transmits Results of Completed Research on Development of Frantic Computer Code to Calculate Sys Unavailabilities.Forwards Users Manual (NUREG-0193) & Descriptive Rept.W/O Encl +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0978, Informs That CRGR Meeting 44 on 830803 Rescheduled for 830810 in Bethesda,Md.Proposed NUREG-0978 Re Generic Issue B-10, Behavior of BWR Mark III Containments, Will Be Discussed +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +, 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 +  and NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +

AM +  and CP +

Regulatory Guide 1.97 +, Regulatory Guide 1.27 +, Regulatory Guide 1.75 +, Regulatory Guide 1.9 +, Regulatory Guide 1.155 +, Regulatory Guide 1.52 +, Regulatory Guide 1.100 +, Regulatory Guide 1.142 +, Regulatory Guide 1.140 +, Regulatory Guide 1.13 +, Regulatory Guide 1.89 +, Regulatory Guide 1.57 +  and Regulatory Guide 1.151 +

SECY-93-087 +, SECY 89-122 +  and SECY-90-016 +

07-52-001 +, R1IR-m +  and R11R-LPFL +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Poslusny C +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Ultimate heat sink +, Post Accident Monitoring +, Hydrostatic +, High Energy Line Break +, Feedwater Heater +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, License Renewal +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Biofouling +, Failure to Scram +, Loss of condenser vacuum +, Water hammer +  and Control Room Habitability +