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TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT

ANSI 14.6 +, ANSI N16.1 +, ANSI 57.2 +  and ANSl-14.6 +

AP-9.03 +, AP-10.41 +  and AP-7.00 +

Boron +, Iodine +, Uranium +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Lead +, Helium +, Calcium +  and Zinc +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 72.48 +, 10 CFR 72.106 +, 10 CFR 72.210, General License Issued +, 10 CFR 72.212 +  and 10 CFR 12.48 +

DBD-1 +  and DBD-5 +

05000255  +, 00255  +  and 00403  +

FC-944 +, FC-864 +, FC-951 +, FC-946 +, FC-934 +, FC-940 +, FC-947 +, FC-949 +, FC-950-02 +, FC-LID +, FC-925 +, FC-950-01 +  and FC-Lid +

Turbine Trip +  and Reactor Trip +

SC-93-087 +, SC-92-128 +, SC-92-124 +, SC-91-167 +, SC-92-050 +, SC-92-127 +, SC-92-169 +, SC-92-171 +, SC-92-177 +, SC-92-191 +, SC-92-199 +, SC-92-220 +, SC-92-227 +, SC-93-006 +, SC-93-007 +, SC-93-019 +, SC-93-026 +, SC-93-027 +, SC-93-032 +, SC-93-038 +, SC-93-044 +, SC-93-050 +, SC-93-054 +, SC-87-384 +, SC-92-1 +, SC-92-223 +  and SC-92-224 +

GDC 60 +  and GDC 62 +

NRC Generic Letter 85-14, Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated by The Utility +, NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications +, NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +, NRC Generic Letter 90-02, Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications +  and NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites +

ML18059B126 +, ML18059B126 +, ML18059B126 +, ML18059B126 +, ML18059B126 +, ML18059B126 +, ML18059B126 +, ML18059B126 +, ML18059B126 +  and ML18059B126 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +

IEEE 384 +, IEEE 344 +, IEEE 387 +, IEEE 387-1984 +  and IEEE 387-1974 +

Information Notice 90-09 +  and Information Notice 88-75 +

NUREG/CR-5250 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +

ES +, CH +, MP +, RT +, TOP +, Emergency Operating Procedure +  and ES-DC-1 +

Regulatory Guide 1.97 +, Regulatory Guide 1.25 +, Regulatory Guide 1.9 +, Regulatory Guide 1.155 +  and Regulatory Guide 1.26 +

5P-3 +, 5R-1 +, 5P-7 +, 5P-5 +, 5P-1 +, 43ft-lbs +, 8C4-10 +  and 1o-1x +

Steam Generator +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, HVAC +, Reactor Building Ventilation +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Containment Spray +  and Extraction steam +

TS-3.03 +, TS-3.8 +, TS-3.2.1 +, TS-3.3 +, TS-3.3.2.d +, TS-3.21.2.a +, TS-3.21.2.b +  and TS-3.3.2.g +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Grab sample +, Stroke time +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Temporary Modification +, Zebra Mussel +, Tornado Generated Missile +, Design basis earthquake +, Foreign Material Exclusion +, Feedwater Heater +, Eddy Current Testing +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Eddy Current Test +, Water rod +  and Spent fuel rack +

Cooling Tower +  and Lake Michigan +