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NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

National Environmental Policy Act of 1969 +  and Atomic Energy Act of 1954 +

Nitrogen +, Oxygen +  and Hydrogen +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 2.109 +, 10 CFR 50.44 +, 10 CFR 50.47 +, 10 CFR 50.49 +, 10 CFR 50.109 +, 10 CFR 51.21 +, 10 CFR 50.54#f +, 10 CFR 50.44#c3ii +  and 10 CFR 50.44#g +

SECY 83-19 +  and SECY-83-19 +

00237  +, 05000237  +, 00249  +, 00254  +  and 00265  +

Emergency Operations Facility +  and Technical Support Center +

GDC 1, Quality standards and records +  and GDC 41 +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-36, NUREG-0737 Technical Specifications +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +, NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +

ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +, ML17202U847 +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

ML17252B012 +, ML20247D301 +, 05000237/LER-1984-008-04, :on 840530,Cardox Sys Master Valve Not Tested in Automatic Mode.Caused by Lack of Documentation to Verify That Cardox Sys electro-mechanical Master Pilot Valve Operable in Automatic Mode.Procedure Revised +, ML20033E061 +, 05000237/LER-1982-058, Forwards LER 82-058/03L-0 +, ML20033G825 +, ML20042E048 +, IR 05000237/1987030 +, IR 05000010/1982022 +, IR 05000237/1989019 +, ML17201Q439 +, ML17202G788 +, ML17201Q405 +, ML17201M874 +, ML17202G549 +, ML17199G544 +, ML17202L245 +, ML17202L265 +, ML17202L198 +, ML20043B147 +  and ML17202L274 +

General Electric +  and Bliss +

NRC Bulletin 82-03 +  and NRC Bulletin 83-02 +

NUREG-0823, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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-0531, Forwards NUREG-0531, Investigation & Evaluation of Stress Corrosion Cracking in Piping of LWR Plants & Notice of Issuance.W/O Rept.Fr Notice Encl +, NUREG-1403, Forwards NUREG-1403, SER Re Full-Term OL for Dresden Nuclear Power Station,Unit 2 +, NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +  and NUREG-0600 +

TAC:49398 +, TAC:68539 +, TAC:55148 +, TAC:65176 +, TAC:69366 +  and TAC:56118 +

Regulatory Guide 1.97 +  and Regulatory Guide 1.108 +

SECY 83-19 +  and SECY-83-19 +

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

Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +  and Main Steam +

Safe Shutdown +, Reactor Vessel Water Level +, Weld Overlay +, Probabilistic Risk Assessment +, Nondestructive Examination +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Control of Heavy Loads +, Hardened vent +, Backfit +, Water hammer +  and Control Room Habitability +