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ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Sodium +, Hydrogen +  and Helium +

10 CFR 55 +, 10 CFR 50.46 +  and 10 CFR 50 +

SECY-82-111 +, SECY 82-111 +  and RA-20-0134, Amendment 63 to Updated Final Safety Analysis Report, Drawings (Redacted) Part 2 of 2 +

Turbine Trip +  and Reactor Trip +

GDC 18 +, GDC 64 +, GDC 51 +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 82-02, Nuclear Power Plant Staff Working Hours +  and NRC Generic Letter 83-35, Clarification of TMI Action Plan Item II.K.3.31 +

ML20147A036 +, ML20147A036 +, ML20147A036 +, ML20147A036 +, ML20147A036 +, ML20147A036 +, ML20147A036 +, ML20147A036 +, ML20147A036 +  and ML20147A036 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 279 +, IEEE 279-1971 +  and IEEE 323 1974 +

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-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, 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 +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.108 +, Regulatory Guide 1.26 +, Regulatory Guide 1.127 +, Regulatory Guide 4.15 +, Regulatory Guide 1.8 +, Regulatory Guide 1.140 +, Regulatory Guide 1.133 +, Regulatory Guide 1.34 +, Regulatory Guide 1.48 +, Regulatory Guide 1.67 +  and Regulatory Guide 1.95 +

SECY-82-111 +  and SECY 82-111 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Containment Spray +  and Extraction steam +

Safe Shutdown +, Boric Acid +, Loop seal +, Tornado Missile +, Emergency Lighting +, High Energy Line Break +, Shift Technical Advisor +, Process Control Program +, Loss of Offsite Power +, Safeguards Contingency Plan +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Fire Protection Program +, Overspeed +, Water hammer +  and Control Room Habitability +

WCAP-9584 +, WCAP-9804 +, WCAP-9292 +, WCAP-10019 +  and WCAP-9219 +

WCAP-9584 +, WCAP-9804 +, WCAP-9292 +, WCAP-10019 +  and WCAP-9219 +