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Letter  and Updated Final Safety Analysis Report (UFSAR)

Boron +, Iodine +, Nitrogen +, Oxygen +, Sodium +, Xenon +  and Lead +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 2.390 +, 10 CFR 72.48 +, 10 CFR 100.11 +, 10 CFR 50.7l#e +, 10 CFR 50.36#c2ii +, 10 CFR 50.4#b6 +, 10 CFR 72.48#d2 +, 10 CFR 50.71#e +  and 10 CFR 71.106, Changes to quality assurance program +

Emergency Preparedness +  and Mitigating Systems +

NRC-87-0156 +, NRC-90-0161 +, NRC-99-0112 +, NRC-89-201 +, NRC-15-0081, License Renewal Application Update for the Boraflex Monitoring Program +, NRC-15-0020, Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Sets 19, 20, and 21 +, NRC-14-0028, License Renewal Application, Appendix E, Page 10-1 Through End +, NRC-14-0007, Response to NRC Request for Additional Information Regarding Bulletin 2012-01, Design Vulnerability in Electric Power System. +, NRC-95-0052, Responds to Insp Rept 50-341/95-06.Corrective Actions: Procedure for Initial Training,Requalification & Firearms Policy That Defines Security Training Requirements Revised +, NRC-89-0148, Submits Addl Clarification Re Compliance W/Rev 2 to Reg Guide 1.97, Instrumentation for Water-Cooled Nuclear Power Plants to Assess Plant & Environ Conditions During & Following Accident +, NRC-89-0046, Forwards Response to NRC Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipments. Encl Also Includes Discussion of Program for Maintaining Proper Instrument Air Quality +  and NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +

05000341  +, 07200071  +  and 00341  +

DTE Energy +  and Colonnello W A +

GDC 33 +, GDC 18 +, GDC 30 +, GDC 28 +, GDC 29 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 26, Reactivity control system redundancy and capability +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +  and NRC Generic Letter 91-09, Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies for the Reactor Protection System +

NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +, NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +  and NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

IEEE 485 +, IEEE 308 +  and IEEE-450 +

NEI 99-03 +, NEI 96-07 +, NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

NRC-87-0156 +, NRC-90-0161 +, NRC-99-0112 +, NRC-89-201 +, NRC-15-0081, License Renewal Application Update for the Boraflex Monitoring Program +, NRC-15-0020, Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Sets 19, 20, and 21 +, NRC-14-0028, License Renewal Application, Appendix E, Page 10-1 Through End +, NRC-14-0007, Response to NRC Request for Additional Information Regarding Bulletin 2012-01, Design Vulnerability in Electric Power System. +, NRC-95-0052, Responds to Insp Rept 50-341/95-06.Corrective Actions: Procedure for Initial Training,Requalification & Firearms Policy That Defines Security Training Requirements Revised +, NRC-89-0148, Submits Addl Clarification Re Compliance W/Rev 2 to Reg Guide 1.97, Instrumentation for Water-Cooled Nuclear Power Plants to Assess Plant & Environ Conditions During & Following Accident +, NRC-89-0046, Forwards Response to NRC Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipments. Encl Also Includes Discussion of Program for Maintaining Proper Instrument Air Quality +  and NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +

NUREG-0979, Forwards Sser 5,(NUREG-0979).W/o Encl +, NUREG-0562, Advises That NUREG-0562 Fuel Failure Criteria Not Approved as Basis for Licensing.Use of Criteria Should Be Discontinued to Eliminate Licensing Delays.List of Plants Applying Criteria Requested +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

Regulatory Guide 1.183 +, Regulatory Guide 1.25 +, Regulatory Guide 1.196 +, Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.45 +, Regulatory Guide 1.52 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.181 +, Regulatory Guide 1.6 +  and Regulatory Guide 1.32 +

NEDC-32988 +  and NEDC-31982 +

SR-3.6.4.1.2 +, SR-3.5.1.4 +, SR-3.5.1.1 +, SR-3.8.1.3 +, SR-3.4.4.1 +, SR-3.5.1.9 +, SR-3.5.1 +, SR-3.8.1 +, SR-3.3.1.1.2 +, SR-3.5.1.6 +, SR-3.7.5.2 +, SR-3.8.1.7 +, SR-3.6.4.1.3 +, SR-3.8.7.1 +, SR-3.6.4.1.5 +, SR-3.0.3 +, SR-3.6.4.3.2 +, SR-3.7.5.1 +, SR-3.5.1.8 +, SR-3.8.3.2 +, SR-3.3.3.2.1 +, SR-3.7.1.1 +, SR-3.4.10.1 +, SR-3.2.3.1 +, SR-3.3.8.2.2 +, SR-3.7.2.2 +, SR-3.8.3.4 +, SR-3.6.4.3.1 +, SR-3.6.1.3.8 +, SR-3.8.4.6 +...

Fermi +  and 07200071 +

Washington +  and Michigan +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Remote shutdown +, Emergency Equipment Cooling Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Moisture Separator Reheater +, Main Condenser +, Control Rod +  and Main Turbine Bypass System +

TS-3.0.3 +, TS-3.5.1 +, TS-3.8.1 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.7.3 +, TS-3.5.2 +, TS-3.8.7 +, TS-3.5.3 +, TS-3.3.6.1 +, TS-3.8.5 +, TS-3.6.1.6 +, TS-3.8.4 +, TS-3.6.1.3 +, TS-3.8.2 +, TS-3.4.4 +, TS-3.1.6 +, TS-3.4.1 +, TS-3.1.3 +, TS-3.6.4.2 +, TS-3.6.4.3 +, TS-3.4.6 +, TS-3.1.1 +, TS-3.1.4 +, TS-3.9.5 +, TS-3.0.6 +, TS-3.1.8 +, TS-3.6.1.8 +  and TS-5.5.10 +

Office of Nuclear Material Safety and Safeguards +, Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Stroke time +, Hydrostatic +, Squib +, Incorporated by reference +, Surveillance Frequency Control Program +, Open Phase Condition +, Scram Discharge Volume +, Loss of Offsite Power +, Excess Flow Check Valve +, Battery sizing +, License Renewal +, Fuel cladding +, Pressure Boundary Leakage +, Recently irradiated fuel +, Offsite Circuit +, Unidentified leakage +, Power Uprate +, Measurement Uncertainty Recapture +, Overspeed trip +, Overspeed +, Operational leakage +  and Water hammer +