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Pages with broken file links, TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

Iodine +, Iron +, Copper +, Nitrogen +, Carbon +, Hydrogen +, Lead +  and Aluminum +

10 CFR 50.73 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.44#c3 +  and 10 CFR 50.44#c3i +

00322  +  and 05000322  +

NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +, NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 81-08, Odyn Code +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +  and NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants +

ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +, ML20141D865 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00294 d (0.0706 hours, 4.199735e-4 weeks, 9.6647e-5 months)  +, 2.199074e-4 d (0.00528 hours, 3.141534e-5 weeks, 7.2295e-6 months)  +, 0.00856 d (0.206 hours, 0.00122 weeks, 2.8157e-4 months)  +, 0.00608 d (0.146 hours, 8.680556e-4 weeks, 1.997625e-4 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.00127 d (0.0306 hours, 1.818783e-4 weeks, 4.1855e-5 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 0.00863 d (0.207 hours, 0.00123 weeks, 2.83853e-4 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 0.00694 d (0.167 hours, 9.920635e-4 weeks, 2.283e-4 months)  +, 0.00347 d (0.0833 hours, 4.960317e-4 weeks, 1.1415e-4 months)  +, 0.0926 d (2.222 hours, 0.0132 weeks, 0.00304 months)  +, 0.0072 d (0.173 hours, 0.00103 weeks, 2.36671e-4 months)  +, 0.0174 d (0.417 hours, 0.00248 weeks, 5.7075e-4 months)  +, 0.00388 d (0.0931 hours, 5.539021e-4 weeks, 1.274675e-4 months)  +, 3.587963e-4 d (0.00861 hours, 5.125661e-5 weeks, 1.17955e-5 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +

ML031150585 +, ML20101R414 +, ML20101E402 +, ML20100N585 +, ML20100K110 +, ML20093M480 +, ML20106E440 +, ML20117A411 +, ML20111C540 +, ML20108D653 +, ML20132D001 +, ML20128Q840 +, IA-84-942, Forwards Rev to Proposed Draft Order in SECY-84-393A Based Upon Commissioner Comments.Additions to Draft Order Underlined,Deletions Lined Out.W/O Encl +, 05000322/LER-1985-010, :on 850310,while Pressurizing Reactor Vessel for Backflushing Crds,Inadvertent Isolation of RHR Sys Occurred.Caused by Exceeding High Suction Pressure Setpoint. Procedures Being Revised +  and ML19276C773 +

General Electric +  and Target Rock +

NRC Bulletin 79-27 +  and NRC Bulletin 79-15 +

NUREG-04 +, NUREG-420 +, NUREG-0420, Forwards Sser 9 (NUREG-0420).W/o Encl +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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 +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

Regulatory Guide 1.9 +  and Regulatory Guide 1.108 +

07-03-359 +  and 1C-cycle +

McGuire +, NPF-19 +  and Shoreham +

Maryland +, Washington +, California +, New York +, Wisconsin +, Florida +  and Mississippi +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, HVAC +, Core Spray +, Automatic Depressurization System +, Remote shutdown +, Reactor Building Closed Loop Cooling +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +  and Low Pressure Coolant Injection +

Fire Barrier +, Weld Overlay +, Nondestructive Examination +, Finite Element Analysis +, Shift Technical Advisor +, Process Control Program +, Loss of Offsite Power +, Breakaway torque +, Control of Heavy Loads +, Liquid penetrant +, Fire Protection Program +, Hourly Fire Watch +, Overspeed +, Eddy-Current Testing +  and Control Room Habitability +