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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

ASME Section XX +  and ASME Section I +

Boron +, Copper +, Sodium +, Hydrogen +, Chlorine +, Aluminum +  and Zinc +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.62 +, 10 CFR 50 Appendix E +, 10 CFR 70.14 +, 10 CFR 70.24 +  and 10 CFR 55.31#e +

00461  +  and 05000461  +

GDC 60 +  and GDC 1, Quality standards and records +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 85-03, Clarification of Equivalent Control Capacity for Standby Liquid Control Systems +, NRC Generic Letter 86-14, Operator Licensing Examinations +  and NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +

ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +, ML20210M465 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

IEEE 384 +, IEEE 383 +, IEEE 384-1974 +  and IEEE 383-1974 +

Standby Liquid Control +, ML20042C557 +, ML20069F419 +, ML20100N186 +, ML20106C321 +, ML20137L291 +, IR 05000461/1985030 +, IR 05000461/1986004 +, IR 05000461/1986003 +, ML20138N891 +, IR 05000461/1985044 +, ML20155K384 +, IR 05000461/1986020 +, ML20199E887 +, ML20203N030 +, ML20203M858 +, IR 05000461/1986055 +, ML20203G496 +, ML20202D452 +, ML20209B684 +, ML20212P012 +, ML20212B852 +, ML20212A570 +, IA-86-278, Partial Response to FOIA Request.Documents Listed in Apps D & E Available in PDR +, U-600672, Advises That Control Logic for Operation of Four 36-inch Isolation Valves Does Not Meet NUREG-0737,Item II.E.4.2 Requirement That Reopening of Containment Isolation Valves Require Deliberate Operator Action.Plant Mod Pending +, U-600696, Forwards Info Re Temporary Use of Component Unqualified to Required Environ Stds Prior to Fuel Load Due to Unavailability of Qualified Components,Per SER Section 3.10.1.3.Components Not Needed for Safe Operation of Plant +, U-600700, Forwards Technical Justification of Deferral of Addl Initial Test Program Item Re Area Temp Surveys to Be Completed After Fuel Load.Deferral Will Not Affect Safe Operation of Plant or Put Excess Burden on Operators or Startup Personnel +, U-600636, Forwards Responses to Questions Re Amends to FSAR Chapter 8, Electric Power. FSAR Will Be Updated in Future Amend. Response Closes Out Sser 6 Issues +, U-600593, Forwards Addl Info to Satisfy Requirements of TMI Action Item II.F.1 Re Accident Monitoring Instrumentation,Per Sser 5 (NUREG-0854).Correction Factor Curves for Stack Monitors & Standby Gas Treatment Sys Sample Cooler Capacity Info Encl +, U-600573, Submits Results of Investigation Into Concerns in NRC .Qualifications of Supervisor in Question Verified.Concernee Had No Knowledge of Quality or Hardware Problems at Plant +...

Westinghouse +  and General Electric +

NRC Bulletin 79-27 +, NRC Bulletin 80-06 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-853 +, NUREG-1212, Informs That Papers from Apr 1986 NEA Symposium in Japan Re Reduction of Scram Frequency Available for Public Insp at Pdr.Recently Published NUREG-1212 Presents NRC Findings Re Initial Phase of Maint & Surveillance Program +, 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 +  and NUREG-0776, Safety Evaluation on Followup Allegation Re Chugging Loads at Facility,Per Sser 3 (NUREG-0776) +

ML20210M465 +  and ML20210M465 +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +  and Regulatory Guide 1.139 +

1H13-601 +  and F402D-5BS +

Illinois +, Maryland +, Washington +  and New York +

Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Standby Gas Treatment System +, Standby Liquid Control +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Ultimate heat sink +, Anticipated operational occurrence +, Hydrostatic +, Operating Basis Earthquake +, Emergency Lighting +, Feedwater Heater +, Shift Technical Advisor +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +  and Control Room Habitability +