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CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS

Hydrogen +  and Lead +

10 CFR 50 +, 10 CFR 52 +, 10 CFR 50.34 +, 10 CFR 55.4 +, 10 CFR 50.54 +, 10 CFR 50.54#f +, 10 CFR 50.34#f1i +, 10 CFR 50.34#f3i +, 10 CFR 52.47#a1ii +  and 10 CFR 52#U +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

Brookhaven National Laboratory +, Higgins J +, Ohara J +  and Stubler W +

NRC Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54 +, NRC Generic Letter 91-07, GI-23, "Reactor Coolant Pump Seal Failures" and Its Possible Effect on Station Blackout +  and NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f) +

ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +, ML20063D912 +  and ML20063D912 +

Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators +  and Information Notice 1993-81, Implementation of Engineering Expertise on Shift +

NUREG/CR-2300 +, NUREG/CR-5228 +, NUREG/CR-6146 +, NUREG/CR-3331 +, NUREG/CR-3371 +, NUREG/CR-5908 +, NUREG/CR-5439 +, NUREG/CR-2623 +, 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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, NUREG/CR-6105, Forwards Preliminary Draft Version of NUREG/CR-6105, Human Factors Engineering Guidelines for Review of Advanced Alarm Sys & Draft of NUREG/CR-5908, Advanced Human Sys Interface Design Review Guideline +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG/CR-3485 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0899, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, NUREG-1358, Forwards NRC Info Notice 92-076, Issuance of Suppl 1 to NUREG-1358, Lessions Learned from Special Insp Program for EOPs (Conducted Oct 1988-Sept 1991). W/O Encl +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

PSP +, TOP +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.47 +, Regulatory Guide 1.108 +, Regulatory Guide 1.33 +, Regulatory Guide 1.81 +, Regulatory Guide 1.22 +, Regulatory Guide 1.62 +  and Regulatory Guide 1.114 +

E2CDO-T4-1-1 +  and 1AEA-TECDOC-668 +

Washington +  and New York +

Reactor Coolant System +, Feedwater +, Service water +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Low Pressure Coolant Injection +

Probabilistic Risk Assessment +, Loss of Offsite Power +, Backfit +  and Control Room Habitability +