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

ACI-318 +, ACI-359 +  and ACI-443 +

Uranium +, Hydrogen +, Lead +  and Tin +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50 Appendix E +, 10 CFR 50.47#b +, 10 CFR 5#j +  and 10 CFR 50#0 +

00466  +  and 05000466  +

Technical Support Center +  and Emergency Operations Facility +

ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +, ML20033A934 +  and ML20033A934 +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 9.259259e-4 d (0.0222 hours, 1.322751e-4 weeks, 3.044e-5 months)  +  and 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +

IEEE 308 +, IEEE 344-1975 +  and IEEE 208 +

ML20263R382 +, ML20010B154 +, ML20030B917 +, ML20032B004 +, ML20031A358 +  and ML19347G044 +

NUREG/CR-1677 +, NUREG-0705 +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves +, NUREG-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents 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-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0718, Forwards Final Rule on Licensing Requirements for Pending CP & Mfg License Applications & NUREG-0718,Revision 2.SER Comparison to New Requirements Revealed Util Commitments & CP Conditions Conform to Nureg.W/O NUREG +, NUREG-515 +, 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-0515, Second Errata Suppl to NUREG-0515,Suppl 2 to SER +, NUREG-0576, Forwards NUREG-0576, Nuclear Power Reactor Security Personnel Training & Qualification Plan Reviewer Workbook +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +  and NUREG-0460 +

CP +  and ST +

Regulatory Guide 1.7 +, Regulatory Guide 1.100 +  and Regulatory Guide 1.91 +

Texas +, Colorado +, Maryland +, Washington +  and New Hampshire +

Feedwater +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +  and Control Rod +

Safe Shutdown +, Ultimate heat sink +, Anticipated operational occurrence +, Coatings +, Abnormal operational transient +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Commercial Grade +, Control of Heavy Loads +, Fuel cladding +, Generic Issues Program +, Siren +, Failure to Scram +  and Water rod +