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

ASME Section II +  and ASME Section III +

Iodine +, Uranium +, Iron +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +  and Lead +

10 CFR 21 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 30 +, 10 CFR 2.206 +, 10 CFR 50.44 +, 10 CFR 50.62 +, 10 CFR 50.75 +, 10 CFR 73.21 +, 10 CFR 50.54 +, 10 CFR 2.790 +, 10 CFR 50.33#k +, 10 CFR 50.33#k1 +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#g2 +, 10 CFR 50.44#c3iiB +, 10 CFR 50.12#a +  and 10 CFR 50.12#a2v +

00352  +, 00353  +, 05000352  +  and 05000353  +

GDC 57 +, GDC 54 +, GDC 56 +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-09, ASME Section III Component Replacements +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 89-05, Pilot Testing of the Fundamentals Examination +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 89-03, Operator Licensing Examination Schedule +  and NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products +

ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +, ML20246A397 +...

ML20141N148 +, ML20195J915 +, ML20206C410 +, ML20205K824 +, ML20207C548 +, ML20244A661 +, ML20246H238 +, ML20245D601 +, ML20236J193 +, ML20235R960 +, ML20235E078 +, IR 05000352/1986015 +, 05000352/LER-1989-017, :on 890302,drywell H Mixing Sys Low Air Flow Elements Not in Compliance W/Environ Qualification Requirements.Caused by Failure of Architect/Engineer to Transfer Info Re Revised Environ Qualification +  and 05000352/LER-1985-056, :on 850529,primary Containment Instrument Gas Sys Isolation Valves Isolated to Closed Position.Caused by Loose Connections in Panel.Connections Tightened to Prevent Further Inadvertent Isolations +

NRC Bulletin 88-10 +, NRC Bulletin 88-05 +, NRC Bulletin 83-10 +  and NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors +

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-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG-0991, Advises That Rev 1 to Plant Preservice Insp Program for Reactor Coolant Pressure Boundary & for ASME Code Class 2 & 3 Sys & Components Acceptable & in Compliance W/ 10CFR50.55a(g)(2).Evaluation Included in NUREG-0991,Suppl 7 +, NUREG-991 +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, 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-1221, Summary, Analysis and Response to Public Comments on Proposed Amendments to 10 CFR Parts 30, 40, 50, 51, 70, and 72 Decommissioning Criteria for Nuclear Facilities +

Regulatory Guide 1.147 +, Regulatory Guide 1.3 +, Regulatory Guide 1.52 +, Regulatory Guide 1.99 +, Regulatory Guide 1.68 +  and Regulatory Guide 1.115 +

NEDE-24011 +, NEDE-30284 +  and NEDC-31629P +

Limerick +  and NPF-27 +

Ohio +, Pennsylvania +, Maryland +, Washington +, California +, New Jersey +  and New York +

Feedwater +, Secondary containment +, Main Steam Isolation Valve +, Primary containment +, Safety Parameter Display System +, HVAC +, Standby Liquid Control +, Reactor Enclosure Recirculation System +, Remote shutdown +, Spray Pond +, Rod Worth Minimizer +, Rod Sequence Control System +  and Control Rod +

Safe Shutdown +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Systematic Assessment of Licensee Performance +, Chernobyl +, Turbine Missile +, Fuel cladding +  and Pressure Boundary Leakage +