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TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST/INSPECTION/OPERATING PROCEDURES  and NUREG REPORTS

IWB-3640 +  and IWB-3650 +

Carbon +, Oxygen +, Hydrogen +, Lead +, Sulfur +  and Chromium +

10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50 Appendix A +

ASME Code Case N-411 +, ASME Code Case N-462 +  and ASME Code Case N-451 +

ML20155A239 +, ML20155A239 +, ML20155A239 +, ML20155A239 +, ML20155A239 +, ML20155A239 +, ML20155A239 +, ML20155A239 +  and ML20155A239 +

General Electric +  and Westinghouse +

NUREG-12 +, NUREG-0823, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program +, NUREG/CR-4667 +, NUREG/CR-1576 +, NUREG/CR-4826 +, NUREG/CR-4813 +, NUREG/CR-4263 +, NUREG/CR-5073 +, NUREG/CR-2406 +, NUREG/CR-3022 +, NUREG/CR-3722 +, NUREG/CR-3942 +, NUREG/CR-4859 +, NUREG/CR-5023 +, NUREG/CR-4529 +, NUREG/CR-4562 +, NUREG/CR-5105 +, NUREG/CR-4998 +, NUREG-0825, Requests Addl Info within 30 Days Re Analysis of Wind & Tornado Events,Per SEP Topic III-2 & NUREG-0825.Questions Generated by Audits of Block Wall Analyses & Review of 860905 Submittal in Response to 860314,0417 & 0606 Concerns +, NUREG-1222, Requests Listed Marked Documents Re Rev 1 to NUREG-1147, Seismic Safety Research Program Plan, Be Placed in PDR +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0827, Accepts 851114 Request for Deferral of Remaining Mod to Reactor Protection Sys,Including Installation of Isolation Devices & Separation of Power Supplies,Until 1987 Refueling Outage +, NUREG-0826, Discusses NRC 811230-820128 Investigation of Activities Associated W/Preparation & Submittal of Drafts of Preliminary Rept & Seismic Reverfication Program for Review & Comment +, NUREG-0822, Safety Evaluation Documenting Findings of Staff Review of Util Responses to Drywell Penetration & Reinforcement of Openings & SEP Topic III-7B, Design Codes,Design Criteria, Load Combinations & Reactor Cavity Design Criteria +, NUREG-0824, Evaluation Concluding Info & Proposed Corrective Action Re Integrated Plan SAR Section 4.20, Containment Isolation Sys Acceptable +, NUREG-1061, Informs That ME101 & Superpipe Computer Codes Reviewed by NRC & Found Acceptable for Independent Support Motion Response Spectrum Analysis,Per NUREG-1061 +, NUREG-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +, NUREG-0933, Discusses Prioritization of GI 161 Re Associated Circuits +, NUREG-0313, Safety Evaluation Re IGSCC in RCPB Sys +...

Regulatory Guide 1.45 +, Regulatory Guide 1.84 +, Regulatory Guide 1.92 +, Regulatory Guide 1.61 +  and Regulatory Guide 1.122 +

Maryland +, Washington +, Idaho +, New York +, Michigan +  and Maine +

Steam Generator +  and Feedwater +

Weld Overlay +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Flow Induced Vibration +, Unidentified leakage +  and Water hammer +