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

Environmental Protection Agency +  and Federal Emergency Management Agency +

Boron +, Iodine +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.47 +, 10 CFR 50.49 +, 10 CFR 50.57 +, 10 CFR 50.90 +, 10 CFR 50 Appendix E +, 10 CFR 73.55 +, 10 CFR 50.559 +, 10 CFR 50.55g +, 10 CFR 73.70 +, 10 CFR 50.54#q +, 10 CFR 50.47#b +, 10 CFR 50.47#c1 +, 10 CFR 50.47#c2 +, 10 CFR 50.47#c +, 10 CFR 73.70#d +, 10 CFR 50.47#c1iiiB +, 10 CFR 73.55#51 +, 10 CFR 73.55#d7iiB +, 10 CFR 73.55#d9 +, 10 CFR 50.47#C +  and 10 CFR 73.55#d7iA +

NRC 794-95 +, NRC 410 +, NRC 383 +, NRC 644 +, NRC 311 +, NRC 756 +  and NRC 705 +

00322  +, 05000322  +  and 00440  +

GDC 56 +  and GDC 2, Design bases for protection against natural phenomena +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, 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 +  and NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +

ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +, ML20246E602 +  and ML20246E602 +

LBP-88-24 +, LBP-85-12 +  and LBP-85-31 +

ML20154B569 +, ML20202F843 +, ML20207C634 +, IR 05000322/1987003 +, ML20245A935 +, IR 05000322/1989005 +, ML20248D873 +, ML20234B803 +  and 05000322/LER-1988-013, :on 880810,seismic Monitoring Instrumentation Inoperable for More than 30 Days Due to Calibr.Replacement Parts Unavailable During Calibr.New Parts Expected to Be Onsite by 880930 +

NRC 794-95 +, NRC 410 +, NRC 383 +, NRC 644 +, NRC 311 +, NRC 756 +  and NRC 705 +

NRC Bulletin 79-27 +, NRC Bulletin 79-15 +  and NRC Bulletin 79-26, Boron Loss From BWR Control Blades +

CLI-87-12, Forwards App to CLI-87-12 Omitted from Text of Order as Served +  and CLI-89-02, Order.* Since Commission Terminated Proceeding in CLI-89-02, Prehearing Conference Scheduled for 890313 & Hearing Scheduled to Commence on 890327 Cancelled.Certificate of Svc Encl.Served on 890308 +

NUREG-420 +, NUREG-0420, Forwards Sser 9 (NUREG-0420).W/o Encl +, NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs +, 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-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 +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

Maryland +, Washington +  and New York +

Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Safety Parameter Display System +, Core Spray +, Remote shutdown +, Safety Relief Valve +  and Control Rod +

Temporary Modification +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Exemption Request +, Earthquake +, Fire Protection Program +, Siren +  and Control Room Habitability +