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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

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

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

05000312  +  and 00312  +

Keuter D +  and SACRAMENTO MUNICIPAL UTILITY DISTRICT +

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

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 81-03, Implementation of NUREG-0313,Technical Report on Material Selection & Processing GL for BWR Coolant Press Boundary Piping +, NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +, 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 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, 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 +  and NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +

ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +, ML19332E910 +  and ML19332E910 +

NUREG-0993 +, NUREG-6224 +, NUREG-09 +, NUREG/CR-0054 +, NUREG/CR-3480 +, NUREG-4776 +, NUREG/CR-5347 +, NUREG/CR-3922 +, NUREG-0644 +, NUREG/CR-4761 +, NUREG-0069 +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, 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/CR-3509, Summary of 880628 Meeting W/Util in Rockville,Md Re Removal of Temporary Wall Dividing Control Room.Attendee List & Draft NUREG/CR-3509 Encl +, 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-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-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-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-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-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 +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +...

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

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

8R-772 +  and 88W-PWP +

Steam Generator +  and Feedwater +

Control of Heavy Loads +, Water hammer +  and Leak-Before-Break +