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CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE

Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +

Boron +, Uranium +, Gadolinium +, Nitrogen +, Oxygen +, Zirconium +, Lead +, Calcium +  and Plutonium +

10 CFR 50.72 +, 10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 2.202 +, 10 CFR 2.206 +, 10 CFR 50.44 +, 10 CFR 50.62 +, 10 CFR 2.206#c +  and 10 CFR 50.55#e +

05000259  +, 05000260  +, 05000296  +, 00296  +, 00259  +, 00293  +, 00324  +, 00325  +, 00440  +, 00237  +, 00249  +, 00254  +, 00265  +, 00373  +, 00155  +, 00341  +, 00219  +, 00321  +, 00366  +, 00458  +, 00461  +, 00331  +, 00322  +, 00416  +, 00298  +, 00245  +, 00263  +, 00387  +, 00388  +, 00277  +...

Black S +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +  and NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +

ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +, ML20005E051 +  and ML20005E051 +

NRC Bulletin 79-26, Boron Loss From BWR Control Blades +  and NRC Bulletin 80-07 +

NUREG-128 +, NUREG/CR-2836 +, NUREG/CR-4594 +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, NUREG-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, NUREG-1169, Notification of 870902 Meeting W/Util in Bethesda,Md to Discuss MSIV Leakage Control Sys & NUREG-1169 Applicability. Proposed Agenda Encl +, NUREG-0798, Advises That NRC Review of Sys Leakage Reduction Test Results Cannot Be Completed Until Final Test Procedures & Acceptance Criteria Upon Which Sys Test Results Based Submitted & Reviewed +, NUREG-0474, Forwards NUREG-0474 Re Safety of Pressure Suppression Containment Sys,Per 780615 Request.Rept Covers All Pressure Suppression Containment Designs in Use in Us.W/O 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-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1285, Responds to Expressing Concerns About Family Safety Due to Nearby Location of Nuclear Plant.Nrc Does Not Consider BWR W/Mark I Containments to Be Unsafe & Will Strive to Ensure That All Plants Made Even More Safe +, NUREG-0312, Advises That Util 1979 Mod & Insp Program Is Acceptable & Satisfies NUREG-0312 requirements.NUREG-0619 Will Address BWR Nozzle & Control Rod Drive Return Line Cracking Problem +, 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 +, 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 +  and 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 +

Harold Denton +  and Robert Pettis +

NEDC-31336 +, NEDE-21821 +  and NEDE-31096 +

Ohio +, Tennessee +, Pennsylvania +, Georgia +, Illinois +, Maryland +, Washington +, California +, Alabama +, New York +, Mississippi +, Nebraska +, Vermont +  and Iowa +

Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Shield Building +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control rod blade +, Control Rod +, Main Steam +  and Containment Spray +

Kingsley O +  and Tennessee Valley Authority +

Safe Shutdown +, Shutdown Margin +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, Feedwater Heater +, Stress corrosion cracking +, Earthquake +, Hardened vent +, Backfit +  and Leak-Before-Break +