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ASME Section XI +, ASME Section III +  and ASME Section X +

Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +

Carbon +  and Oxygen +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 54.4 +, 10 CFR 54.29 +, 10 CFR 54.30 +, 10 CFR 140.92 Appendix B +, 10 CFR 50.61a +, 10 CFR 65 +, 10 CFR 54.4#a +, 10 CFR 54.4#a3 +, 10 CFR 54.3#a +, 10 CFR 50.49#b +, 10 CFR 50.49#b1 +, 10 CFR 50.49#d +, 10 CFR 50.33#a +, 10 CFR 50.33#j +, 10 CFR 54.37#b +, 10 CFR 51.53#c +, 10 CFR 54.21#a3 +, 10 CFR 54.21#c1 +...

ML17228A684 +, ML17228A684 +, ML17228A684 +, ML17228A684 +, ML17228A684 +, ML17228A684 +, ML17228A684 +, ML17228A684 +  and ML17228A684 +

IP 71003 +  and IP 71002, License Renewal Inspection +

NEI 96-07 +, NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +, NEI 17-01 +, NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +, NEI 14-12 +, NEI 14-13 +  and NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +

NUREG-1850 +, NUREG-1950, Official Exhibit - ENT000528-00-BD01 - NUREG-1950, Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800 (Apr. 2011) (Excerpted) +, NUREG-1412, Forwards NUREG-1412, Foundation for Adequacy of Licensing Bases, & Screening of Generic Safety Issues for License Renewal Considerations, (NUREG/CR-5382) +, 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-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

ES +, ST +  and Emergency Operating Procedure +

TAC:MB3406 +  and TAC:M92972 +

Regulatory Guide 1.188 +  and Regulatory Guide 4.2 +

Illinois +  and Florida +

Steam Generator +, Reactor Coolant System +, Service water +, Reactor Pressure Vessel +  and Control Rod +

Safe Shutdown +, Fire Barrier +, Probabilistic Risk Assessment +, Coatings +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Severe Accident Management Guideline +, License Renewal +, Exemption Request +, Subsequent License Renewal +, Subsequent License Renewal Application +  and Leak-Before-Break +