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Report  and Miscellaneous

ANSI N14.6 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

IWC-5000 +  and IWA-5000 +

ASME Section III +  and ASME Section XI +

Iodine +, Carbon +, Oxygen +, Hydrogen +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50.59 +, 10 CFR 19 +, 10 CFR 73.55 +, 10 CFR 50.55a +, 10 CFR 5#O +, 10 CFR 50.36#a +, 10 CFR 50.55a#a3 +  and 10 CFR 50#O +

05000220  +  and 00220  +

FE-01-98 +  and FE-01-101 +

EC-309 +  and EC-310 +

NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +  and NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +

ML061930385 +, ML061930385 +, ML061930385 +, ML061930385 +, ML061930385 +, ML061930385 +, ML061930385 +, ML061930385 +, ML061930385 +  and ML061930385 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

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-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

SAP +, Emergency Operating Procedure +  and Emergency Plan +

10A-7 +, 10A-11 +, 10A-50 +, 1OA-1 +, 10A-112 +, 10A-101 +, 10B-26 +, 10B-28 +, 10B-32 +, 10B-33 +, 10B-43 +, 10B-44 +, 10B-45 +, 10B-46 +, 10B-47 +, 10B-48 +, 10B-11 +, 10B-21 +, 10B-22 +, 10B-23 +, 10B-24 +, 10B-78 +, 10B-198 +, 07-99-007 +, 07-99-010 +, 07-99-026 +, 07-99-032 +, 07-98-025 +, 07-96-019 +, 07-94-022 +...

Illinois +  and New York +

Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Control Room Emergency Ventilation +, Remote shutdown +, Reactor Building Closed Loop Cooling +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.2.7 +, TS-3.2.5.a +, TS-6.5.2 +, TS-6.5.1 +, TS-6.5.3 +, TS-6.0 +, TS-6.2.3 +, TS-6.2.1 +, TS-6.8.2 +, TS-6.8.3 +, TS-6.6.b +  and TS-6.10 +

Hot Short +, Safe Shutdown +, Reactor Vessel Water Level +, High Radiation Area +, Fire Barrier +, Stroke time +, Hydrostatic +, Coatings +, Temporary Modification +, Local Leak Rate Testing +, Feedwater Heater +, Scram Discharge Volume +, Sewage Treatment Plant +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Loss of Offsite Power +, Turbine Missile +, Fuel cladding +, Fire Protection Program +, Unidentified leakage +, Failure to Scram +, Water hammer +, Control Room Habitability +  and Spent fuel rack +