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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

SECY 86-97 +, SECY 88-272 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY 88-772 +, SECY 89-172 +, SECY 85-97 +, SECY 86-250 +  and RS-260 +

05000000  +, 05000454  +, 05000455  +, 05000456  +  and 05000457  +

Exelon +  and Hunsader S +

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 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +

ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +, ML19332E656 +  and ML19332E656 +

NUREG-0944, Notice of Availability of SER for full-term OL (NUREG-0944) +, NUREG-0993 +, NUREG/CR-1161 +, NUREG-0044 +, NUREG/CR-0054 +, NUREG-4776 +, NUREG/CR-5347 +, NUREG/CR-5230 +, NUREG-0987 +, NUREG/CR-3400 +, NUREG/CR-3900 +, NUREG-4371 +, 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-1109, Recommends That Final Station Blackout Rule,As Contained in Encl Fr Notice & Reg Guide,Providing Method Acceptable to Comply W/Rule,Be Issued in Order to Implement Final Resolution of USI A-44 +, 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-1211, Informs of CRGR Meeting 98 Agenda Mod +, NUREG-0859, Responds to 820407 Questions Re NUREG-0859, Compliance Determination Procedures for Environ Radiation Protection Stds for U Recovery Facilities 40CFR190. W/O Encl Reg Guide 3.51 +, 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 +, NUREG-0598, Responds to 790713 Request for Info Re Release of Radioactive Matls to Environ from 790328-0407.Iodine & Noble Gases Were Only Radioactive Matls of Any Consequence That Were Released +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o 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-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 +...

Regulatory Guide 1.155 +  and Regulatory Guide 1.139 +

SECY 86-97 +, SECY 88-272 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY 88-772 +, SECY 89-172 +, SECY 85-97 +  and SECY 86-250 +

01shan-NRR +, 8mi-PNP +  and 60C-4 +

Byron +, Braidwood +  and 05000000 +

Murley T +  and Office of Nuclear Reactor Regulation +