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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

Boron +, Iodine +, Cesium +, Oxygen +, Hydrogen +, Chlorine +, Chloride +, Lead +  and Sulfur +

10 CFR 21 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.54 +, 10 CFR 50.54#m +, 10 CFR 50.54#m2 +, 10 CFR 50.44#c3iii +  and 10 CFR 50.44#c +

SECY-82-407 +, SECY-82-384 +, L 90 +, L 00 +, L 36 +, L 160 +, L 122 +  and SECY-83-259 +

Technical Support Center +  and Emergency Operations Facility +

Office of Nuclear Reactor Regulation +, Hernan R +, Miner S +, Kadambi N +, Thoma J +, Van Vliet J +, Vanvlict J +, Vanvliet J +  and Vissing S +

GDC 54 +  and GDC 19, Control room +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +  and NRC Generic Letter 83-31, Safety Evaluation of "Abnormal Transient Operating Guidelines" +

ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +, ML20091F761 +  and ML20091F761 +

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

L 90 +, L 00 +, L 36 +, L 160 +  and L 122 +

NUREG-737 +, NUREG-0752, Notice of Issuance & Availability of Suppl 1 to NUREG-0752, Control Room Design Review Rept for TMI-1 +, NUREG-106 +, 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-0680, Applicant Exhibit A-7,consisting of NUREG-0680,Section 4.0, TMI-1 Leak Rate Falsification +, 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-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-1066, Forwards Table of B&W Plants Comparing Selected TMI Actions from NUREG-1066.Incomplete TMI Items for Facility Listed Per NUREG-0737.NUREG-0737 & Suppl 1 Active Items Re post-implementation Reviews Also Listed +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

ES +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.3 +  and Regulatory Guide 1.23 +

SECY-82-407 +, SECY-82-384 +  and SECY-83-259 +

Ohio +, Maryland +, Washington +, New York +, Florida +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Safety Parameter Display System +, HVAC +, Remote shutdown +, Emergency Feedwater Initiation and Control +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

Loop seal +, Grab sample +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Main Steam Line Radiation Monitor +, Exemption Request +, Core Exit Thermocouple +  and Control Room Habitability +