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Boron +, Iodine +, Cesium +, Nitrogen +, Hydrogen +, Chlorine +, Chloride +  and Lead +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.54#m +

Emergency Preparedness +  and Initiating Events +

ACEM-85-0059 +, ACEM-86-0042 +, ACEM-85-0219 +, ACEM-83-0232 +, ACEM-80-0026 +, ACEM-81-0044 +, ACEM-82-0299 +, ACEM-85-0099 +, ACEM-81-0078 +, ACEM-81-0154 +, ACEM-81-0449 +, ACEM-82-0129 +, ACEM-84-0521 +, ACEM-83-0225 +, ACEM-81-0083 +, ACEM-81-0103 +, ACEM-89-0007 +, ACEM-88-0059 +, ACEM-86-0030 +, ACEM-85-0110 +, ACEM-86-0208 +, ACEM-81-0025 +, ACEM-81-0052 +, ACEM-83-0222 +  and ACEM-83-0347 +

Emergency Operations Facility +  and Technical Support Center +

GDC 54 +, GDC 13 +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +  and NRC Generic Letter 83-24, TMI Task Action Plan Item I.G.1, "Special Low Power Testing and Training," Recommendations for BWRS +

ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +, ML21039A273 +  and ML21039A273 +

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)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 323-1974 +  and IEEE 344-1975 +

Co-60 +  and Cs-137 +

05000416/LER-1982-063, Forwards LER 82-063/99X-1 +, ML20128H737 +, AECM-84-0521, Responds to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs. No Mods Necessary.License Condition 2.c.(33)(e) Resolved Based on Response +, AECM-80-316, Forwards Essex Corp Human Factors Design Engineering Evaluation of Control Room Per NUREG-0660,Task I.D.1.Review Conducted from 800617-1001,using Criteria from NUREG-1580, Human Engineering Guide to Control Room Evaluation +, AECM-81-428, Forwards Public Version of Executed Agreement Between State of La & Util Re Implementation of Protective Actions on Behalf of Public in Event of Radiological Emergency,In Response to NRC Question 810.3(c) +, AECM-81-351, Forwards Proposed FSAR Changes & Responses to NRC Requests for Addl Info.Proposed Changes Will Be Incorporated in Forthcoming Amend to FSAR +, AECM-80-260, Completes Review & Evaluation of IE Bulletin 80-19,Revision 1.Station Has Not Utilized mercury-wetted Relays in Logic Matrix of Reactor Protection Sys.No Further Action Required. Approx 20 Manhours Expended on Bulletin +, ML19341D180 +  and AECM-80-138, Forwards Structural Drawings Supplementing Technical Info Submitted on 800529 & 0606 +

NRC Bulletin 80-06 +  and NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +

NUREG-0835 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Emergency Operating Procedure +  and Emergency Plan +

Regulatory Guide 1.97 +, Regulatory Guide 1.3 +, Regulatory Guide 1.33 +, Regulatory Guide 1.101 +  and Regulatory Guide 1.23 +

NEDO-24708A +  and NEDE-24988 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Reactor Vessel Water Level +, Post Accident Monitoring +, Local Leak Rate Testing +, Shift Technical Advisor +, Loss of Offsite Power +, Integrated leak rate test +, Power-Operated Valves +, Potassium iodide +, Control Room Habitability +  and Basic Component +