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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

ASME Section III +, ASME Section I +  and ASME Section II +

Oxygen +, Hydrogen +, Xenon +, Zirconium +  and Lead +

Emergency Preparedness +  and Initiating Events +

SECY 80-325 +, NRC 1979 +  and CY 80-325 +

ML19350C875 +, ML19350C875 +, ML19350C875 +, ML19350C875 +, ML19350C875 +, ML19350C875 +  and ML19350C875 +

Westinghouse +  and General Electric +

NUREG-0623 +, NUREG-0705 +, NUREG-0691 +, 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-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, 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-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, 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-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG/CR-1280, Forwards Draft Fr Notice of Issuance of NUREG/CR-1280, Power Plant Staffing, for Public Comment +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-0572, Response in Support of Jf Doherty Contention 46 Re Control Rods Leading to Fuel Damage.Contention Involves New Info Appearing in ACRS Review of LERs 1976-78 rept,NUREG-0572. Certificate of Svc Encl +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-705 +, NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Washington +  and Tennessee +

Steam Generator +, Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Ultimate heat sink +, Anticipated operational occurrence +, Coatings +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Fuel cladding +, Generic Issues Program +, Backfit +, Thermal fatigue +  and Water hammer +