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LEGAL TRANSCRIPTS & ORDERS & PLEADINGS  and PLEADINGS

Hydrogen +, Lead +  and Tin +

10 CFR 2.206 +  and 10 CFR 50.46 +

NRC 400 +, NRC 707 +  and NRC 351 +

05000000  +, 05000269  +, 05000270  +, 05000287  +, 05000289  +, 05000302  +, 05000312  +, 05000313  +, 05000346  +, 05000438  +, 05000439  +, 00333  +, 00280  +, 00281  +, 00334  +  and 00309  +

Turbine Trip +  and Reactor Trip +

UNION OF CONCERNED SCIENTISTS +, Weiss E +  and Pollard R +

ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +, ML20215D674 +  and ML20215D674 +

NRC 400 +, NRC 707 +  and NRC 351 +

NRC Bulletin 79-27 +  and NRC Bulletin 19-27 +

CLI-78-06 +, CLI-80-26 +  and CLI-80-21, Response in Opposition to Tx Association of Community Organizations for Reform Now 800804 Motion Seeking Briefs on CLI-80-21 & Admission of Contention 11.Rulemaking on Environ Qualification Addresses Issue.W/Certificate of Svc +

NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, 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 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Davis Besse +, Oconee +, Arkansas Nuclear +, Crystal River +, Rancho Seco +, Bellefonte +, 05000000 +  and Crane +

Georgia +, North Carolina +, Washington +, California +, Virginia +, New York +, Florida +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Main Turbine +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Emergency Feedwater System +

Loop seal +, Fire Barrier +, Nondestructive Examination +, Design basis earthquake +, Loss of Offsite Power +, Earthquake +  and Fuel cladding +