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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

ASME Section XI +  and ASME Section III +

Occupational Safety and Health Administration +  and American Society of Civil Engineers +

Iodine +, Uranium +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Chlorine +  and Zinc +

10 CFR 21 +, 10 CFR 50 +, 10 CFR 52 +, 10 CFR 73 +, 10 CFR 50.34#f +, 10 CFR 73.55#h +  and 10 CFR 100#5 +

ASME Code Case N-411 +, ASME Code Case N-397 +, ASME Code Case N-420 +, ASME Code Case N-462 +  and ASME Code Case N-451 +

Advisory Committee on Reactor Safeguards +  and Committee To Review Generic Requirements +

SECY-77-439 +, SECY-90-377 +, SECY-90-016 +, SECY-92-053 +, SECY-90-241 +, SECY-91-178 +, SECY-91-210 +, SECY-92-214 +, SECY-88-147 +, SECY-91-229 +, SECY-91-273 +, SECY-92-127 +, SECY-92-172 +, SECY-92-219 +, SECY-92-037 +  and SECY-91-262 +

P.1(t) +  and S.0(l) +

Technical Support Center +  and Emergency Operations Facility +

NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +  and NRC Generic Letter 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" +

ML20105C984 +, ML20105C984 +, ML20105C984 +, ML20105C984 +, ML20105C984 +, ML20105C984 +  and ML20105C984 +

IEEE 323 +, IEEE 1050-1989 +, IEEE P1025 +  and IEEE P10 +

Westinghouse +, General Electric +, Worthington +  and Target Rock +

NUREG-1197 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-1242, Provides Background Info That May Be Useful for 920903 Commission Meeting W/Epri +, 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-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 +  and 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 +

RAP +  and Emergency Plan +

Regulatory Guide 1.76 +  and Regulatory Guide 1.29 +

SECY-77-439 +, SECY-90-377 +, SECY-90-016 +, SECY-92-053 +, SECY-90-241 +, SECY-91-178 +, SECY-91-210 +, SECY-92-214 +, SECY-88-147 +, SECY-91-229 +, SECY-91-273 +, SECY-92-127 +, SECY-92-172 +, SECY-92-219 +, SECY-92-037 +  and SECY-91-262 +

N0G-1 +, 4f-1 +, N0G-1-1983 +, 90A-1989 +, D0D-MIL-HDBK-217 +  and D0D-Mll-HDBK-263 +

Illinois +, Maryland +, Washington +, California +, Idaho +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +  and Fuel Pool Cooling and Cleanup +

Safe Shutdown +, Ultimate heat sink +, Mission time +, Offsite Dose Calculation Manual +, Fire Barrier +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Coatings +, Emergency Lighting +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +  and Integrated leak rate test +