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ACI-318 +  and ACI-349 +

ANSI N45.2-1977 +, ANSI N45.2.6 +, ANSI N45.2.11 +, ANSI B30.2.0 +, ANSI N45.2.1 +, ANSI N45.2.8 +, ANSI B31.1.0 +, ANSI N45.2.10 +, ANSI N45.2.13 +, ANSI N45.2.23 +, ANSI N42.7-1972 +, ANSI N101.6-1972 +, ANSI 101.4 +, ANSI N15.8 +, ANSI/ANS 8.3-1986 +, ANSI N45.2.2-1972 +, ANSI N45.2.3-1973 +, ANSI N45.2.6-1978 +, ANSI N45.2.10-1973 +, ANSI N45.2.5-1974 +, ANSI N45.2.23-1978 +, ANSI N45.2.6-1973 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

ASME Section IX +  and ASME Section III +

Iodine +, Nitrogen +, Carbon +, Hydrogen +, Chlorine +, Lead +, Aluminum +, Zinc +  and Tungsten +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 73 +, 10 CFR 74 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 73 Appendix B +, 10 CFR 50 Appendix B Criterion XIV, Inspection, Test, and Operating Status +, 10 CFR 70.24 +, 10 CFR 50.55#a +, 10 CFR 50.71#e +  and 10 CFR 73.1#b5 +

Emergency Preparedness +, Barrier Integrity +  and Physical Protection +

NRC-90-0095, Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request +, NRC-91-0098, Provides Explanation & Justification of QA Level Assigned to 11 Recorders Used for Category 1 Instrumentation,Per Evaluation of Plant Compliance W/Reg Guide 1.97 by NRC Insp Team During Wk of 910624 +, NRC-89-0201, Provides Addl Clarification & Replaces Repts to NRC on Compliance of Plant Design to Reg Guide 1.97,Rev 2.Design of Instrumentation Required to Assess Plant & Environ Condition During & Following Accident,Meets Reg Guide 1.97,Rev 2 +, NRC-98-0063, Forwards non-proprietary & Proprietary Versions of Criticality Safety Analysis, Re Request for Exemption from Requirements of 10CFR70.24.Proprietary Version Withheld +, 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-93-0105 +  and NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +

05000341  +  and 07200071  +

GDC 44 +, GDC 55 +, GDC 60 +, GDC 62 +, GDC 63 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +

NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +, NRC Generic Letter 83-13, Clarification of Survell. Req's for HEPA Filters and Charcoal Absorber Units In STD. Tech Specs on ESF Cleanup Systems +  and NRC Generic Letter 2003-01, Control Room Habitability +

ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +, ML16165A448 +  and ML16165A448 +

IEEE 384 +, IEEE 344 +, IEEE 382 +, IEEE 279-1971 +, IEEE-450 +, IEEE 323-1971 +, IEEE 387-1977 +, IEEE 382-1972 +, IEEE 338-1971 +  and IEEE 338-1977 +

NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +, NEI 03-12 +, NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NRC-90-0095, Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request +, NRC-91-0098, Provides Explanation & Justification of QA Level Assigned to 11 Recorders Used for Category 1 Instrumentation,Per Evaluation of Plant Compliance W/Reg Guide 1.97 by NRC Insp Team During Wk of 910624 +, NRC-89-0201, Provides Addl Clarification & Replaces Repts to NRC on Compliance of Plant Design to Reg Guide 1.97,Rev 2.Design of Instrumentation Required to Assess Plant & Environ Condition During & Following Accident,Meets Reg Guide 1.97,Rev 2 +, NRC-98-0063, Forwards non-proprietary & Proprietary Versions of Criticality Safety Analysis, Re Request for Exemption from Requirements of 10CFR70.24.Proprietary Version Withheld +, 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-93-0105 +  and NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +

NUMARC 87-00 +  and NUMARC 93-01 +

NUREG-0314 +, NUREG-0908, Ack Receipt of 961030 Amend 41 to Physical Security Plan. Eleven Changes Did Not Meet Criteria of 10CFR50.54(p),two Changes Did Not Follow Acceptance Criteria of NUREG-0908 & 37 Changes Require Clarification +, NUREG/CR-5009, Forwards NUREG/CR-5009, Assessment of Use of Extended Burnup Fuel in Lwrs. Rept Concludes That Environmentally, Burnup Increase Would Have No Significant Impact Over That of Normal Burnup.W/O Encl +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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-0389, Forwards NUREG-0389 Re Cost Benefit Analysis Requirements & 10CFR50,App 1,concerning Application of Analysis to Certain Plants Docketed Before 710102.W/o Encl +

TAC:MA1645 +, TAC:59620 +  and TAC:M59620 +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.25 +, Regulatory Guide 1.196 +, Regulatory Guide 1.27 +, Regulatory Guide 1.1 +, Regulatory Guide 1.163 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.137 +, Regulatory Guide 1.63 +, Regulatory Guide 1.74 +, Regulatory Guide 1.9 +, Regulatory Guide 1.155 +, Regulatory Guide 1.3 +, Regulatory Guide 1.52 +, Regulatory Guide 1.76 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.33 +, Regulatory Guide 1.49 +, Regulatory Guide 1.121 +, Regulatory Guide 1.143 +, Regulatory Guide 1.160 +, Regulatory Guide 1.84 +, Regulatory Guide 1.100 +, Regulatory Guide 1.105 +, Regulatory Guide 1.181 +, Regulatory Guide 1.106 +...

NEDO-32686 +, NEDO-10029 +, NEDC-12431 +, NEDO-32721P +, NEDC-32975 +  and NEDO-31558A +

Fermi +  and 07200071 +

Steam Generator +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Remote shutdown +, Spray Pond +, Emergency Core Cooling System +, Control Room Envelope +, Control Rod +  and Low Pressure Coolant Injection +

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Ultimate heat sink +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Coatings +, Cyber Security +, Condition Adverse to Quality +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Safeguards Contingency Plan +, Earthquake +, Commercial Grade +, Turbine Missile +, Pressure Boundary Leakage +, Grace period +, Unidentified leakage +, Overspeed trip +, Overspeed +  and Control Room Habitability +

Cooling Tower +  and Lake Erie +