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LEGAL TRANSCRIPTS & ORDERS & PLEADINGS  and PLEADINGS

10 CFR 2.206 +  and 10 CFR 50.109 +

NRC 400 +, NRC 707 +, NRC 814 +  and PM-137-82 +

05000000  +, 05000269  +, 05000270  +, 05000287  +, 05000289  +, 05000302  +, 05000312  +, 05000313  +, 05000346  +, 05000438  +, 05000439  +, 00269  +, 00329  +  and 00330  +

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

ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +, ML20210N486 +  and ML20210N486 +

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

Westinghouse +  and General Electric +

NRC 400 +, NRC 707 +  and NRC 814 +

NUREG-0705 +, NUREG-0963, Forwards Comments on NRC Safety Research Program Budget for FY86-87, NUREG-0963, Review & Evaluation of NRC Safety Research Program for FY84-85, NUREG-1039, Review For... FY85 & NUREG-1080, Long Range Research Plan.... W/O Encl +, 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-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, 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-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +  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 +

Ohio +, Maryland +, Washington +, California +, Oklahoma +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Main Turbine +, Reactor Pressure Vessel +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +

Safe Shutdown +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Earthquake +, Backfit +  and Manual Operator Action +