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CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE

ANSI 831.1 +  and ANSI N45.2 +

Copper +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Aluminum +, Calcium +, Titanium +, Mercury +  and Tin +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +  and 10 CFR 50.61 +

SECY-84-458 +, SECY 83-465 +, L 66 +  and L 230 +

S.6(o) +  and H.6(t) +

05000498  +, 05000499  +, 00498  +  and 00499  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

Novak T +  and Office of Nuclear Reactor Regulation +

GDC 12 +, GDC 21 +, GDC 45 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 5, Sharing of structures, systems, and components +

ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +, ML20137Q107 +  and ML20137Q107 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

L 66 +  and L 230 +

Westinghouse +  and General Electric +

NUREG-0623 +, NUREG-0705 +, NUREG-1014, Forwards Generic Evaluation (NUREG-1014) of Mod to Westinghouse Steam Generators D4/D5/E.Mod Acceptable. Modified Steam Generators Can Be Operated at 100% Design Capacity,Pending plant-specific Verification.W/O Encl +, NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, 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-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, 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-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, 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-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, 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-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +, 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 +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, 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-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

ES +, ST +, CH +, SAP +, RT +, TOP +  and CH.CL +

Regulatory Guide 1.97 +, Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.108 +, Regulatory Guide 1.70 +, Regulatory Guide 1.26 +, Regulatory Guide 1.29 +, Regulatory Guide 1.59 +  and Regulatory Guide 1.68 +

SECY-84-458 +  and SECY 83-465 +

10A-6Al +, 8H-87 +  and 8H-33 +

Texas +, Colorado +, Maryland +, Washington +, California +, Virginia +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +, Electrohydraulic Control +, Moisture Separator Reheater +, Main Condenser +, Control Rod +, Main Steam +  and Extraction steam +

Goldberg J +  and Creating Houston Lighting and Power Company +

Safe Shutdown +, Boric Acid +, High winds +, Ultimate heat sink +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Nondestructive Examination +, Emergency Lighting +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Generic Issues Program +, Overspeed trip +, Overspeed +  and Water hammer +