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ANSI 13.1 +  and ANSI N13.1 +

Boron +, Iodine +, Cesium +, Germanium +, Krypton +, Nitrogen +, Oxygen +, Hydrogen +, Xenon +, Chlorine +, Chloride +, Lead +, Helium +, Argon +  and Silver +

10 CFR 50 Appendix A +, 10 CFR 26 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.44 +, 10 CFR 50 Appendix E +  and 10 CFR 73.2 +

05000352  +  and 05000353  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

GDC 57 +, GDC 54 +, GDC 10 +  and GDC 19, Control room +

ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +, ML21133A054 +  and ML21133A054 +

1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

IEEE 344 +  and IEEE 279 +

I-131 +  and Sr-90 +

ML19256F034 +, ML20263Q211 +, IR 05000352/1981014 +, ML19340C219 +, ML20009A613 +  and ML19294B935 +

NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +  and NRC Bulletin 80-10 +

NUREG/CR-1474 +, 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 +, NUREG/CR-1580, Notice of Availability of Draft NUREG/CR-1580, Human Engineering Guide to Control Room Evaluation +, 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 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.3 +, Regulatory Guide 1.70 +, Regulatory Guide 1.7 +, Regulatory Guide 1.100 +, Regulatory Guide 1.101 +, Regulatory Guide 1.92 +, Regulatory Guide 1.141 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.95 +

NEDO-24708A +, NEDE-24988 +  and NEDO-24951 +

7x10-4 +, 1x10-2 +, 5x10-4 +, 5x10-3 +, 4x10-3 +, 3x10-3 +, 1x10-3 +, 7x10-3 +, 6x10-3 +, 2x10-2 +, 8x10-4 +, 3x10-2 +  and 2x10-1 +

Manual Scram +  and Automatic Scram +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, High Pressure Core Spray +, Core Spray +, Reactor Water Cleanup +, Control Room Emergency Filtration System +, Main Steam Safety Valve +, Remote shutdown +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Fitness for Duty +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Grab sample +, Anticipated operational occurrence +, Hydrostatic +, Coatings +, Shift Technical Advisor +, Loss of Offsite Power +, Containment high range radiation monitor +, Fuel cladding +, Subsequent actuation +, Potassium iodide +, Control Room Habitability +  and Gas accumulation +