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

Iodine +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +  and 10 CFR 50.34 +

Emergency Preparedness +  and Initiating Events +

00322  +  and 05000322  +

Turbine Trip +  and Reactor Trip +

GDC 3, Fire protection +  and GDC 10 +

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +

ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +, ML20041G031 +  and ML20041G031 +

9.259259e-4 d (0.0222 hours, 1.322751e-4 weeks, 3.044e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

ML20011A009 +  and ML17275A672 +

NUREG-420 +, NUREG-0420, Forwards Sser 9 (NUREG-0420).W/o Encl +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, 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 +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Maryland +, Washington +, Massachusetts +  and New York +

Reactor Coolant System +, Feedwater +, Secondary containment +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Remote shutdown +, Emergency Core Cooling System +, Safety Relief Valve +  and Control Rod +

Tornado Missile +, Hydrostatic +, Probabilistic Risk Assessment +, High Energy Line Break +, Shift Technical Advisor +, Control of Heavy Loads +, Fire Protection Program +  and Control Room Habitability +