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Report, Technical Specifications, Technical  and Letter type:ULNRC

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50.59#c2 +, 10 CFR 50.59#c +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

AmerenUE +  and Keith Young +

ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +, ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0830, Advises That Condition 2.c.(3)(a) of License NPF-30 Fulfilled,Based on & 860117 Rept Re Environ Qualification Program for Electrical Equipment.Program Previously Accepted Per NUREG-0830,Section 3.11 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +

Regulatory Guide 1.45 +  and Regulatory Guide 1.43 +

Washington +  and Missouri +

Reactor Coolant System +  and Service water +

TS-3.4.13 +, TS-3.0.4 +, TS-3.4 +, TS-3.4.1 +, TS-3.4.15 +  and TS-5.5.14 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Unidentified leakage +, Operational leakage +, Leak-Before-Break +  and Leak Before Break +