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Environmental Protection Agency +, Occupational Safety and Health Administration +, Federal Aviation Administration +, Federal Communications Commission +  and American Society of Civil Engineers +

Boron +, Iodine +, Uranium +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Xenon +, Chlorine +, Thorium +, Chloride +, Lead +, Aluminum +, Silicon +, Mercury +, Tin +, Hafnium +, Plutonium +  and Curium +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 2.390 +, 10 CFR 50.44 +, 10 CFR 72.210, General License Issued +, 10 CFR 72.214 +, 10 CFR 72.212 +  and 10 CFR 50.71#e +

05000498  +  and 05000499  +

Drawing 1.7-1 +, Drawing 1.7-2 +, FV-0012 +, FV-0013 +, FV-0011 +, FV-7189 +, FV-7190 +, FV-7191 +, FV-7192 +, FV-9594 +, FV-9776 +, FV-9549D +, FV-9549C +, Drawing 1.2-22 +, Drawing 1.7-39 +  and Drawing 1.7-64 +

Technical Support Center +  and Emergency Operations Facility +

Reactor Trip +  and Turbine Trip +

ML22140A077 +, ML22140A077 +, ML22140A077 +, ML22140A077 +, ML22140A077 +, ML22140A077 +, ML22140A077 +, ML22140A077 +, ML22140A077 +  and ML22140A077 +

Westinghouse +  and General Electric +

NUREG-0085 +, NUREG-0143 +, NUREG/CR-1741 +, NUREG-0818 +, NUREG-0004 +, NUREG-0291 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0570, Toxic Vapor Concentrations in the Control Room Following a Postulated Accidental Release Potential Error in Equation 2.2-1 +, NUREG/CR-5009, Forwards NUREG/CR-5009, Assessment of Use of Extended Burnup Fuel in Lwrs. Rept Concludes That Environmentally, Burnup Increase Would Have No Significant Impact Over That of Normal Burnup.W/O Encl +, NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +, NUREG-0814, Advises That Due to Issuance of NUREG-0737,Suppl 1, Evaluation of Design Plan for Emergency Response Facilities Using NUREG-0814 Not Applicable to Plant +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

345kV +  and 4.16kV +

AM +, SP +, RT +, EAP +, CP +, Emergency Operating Procedure +, ST-170 +, ST-190 +, ST-140 +, ST-160 +, ST-130 +, ST-180 +  and ST-150 +

6G01-9-M-000 +, 6D01-9-M-000 +, 9P07-0-M-000 +, 6C18-9-N-050 +, 6C01-9-M-000 +, 6M18-9-N-050 +, 6F18-9-N-050 +, 6Y01-0-M-000 +, 6P20-0-M-000 +, 6P22-0-M-000 +, 9Q27-0-M-000 +, 7T23-0-M-000 +, 9V01-0-M-000 +, 9Q16-0-M-000 +, 9Q13-0-M-000 +, 9P26-0-C016 +, 3B-MOD +, 9A31-O-F-000 +, 9Y10-0-M-000 +  and 9Y22-0-M-000 +

Texas +, Tennessee +, Pennsylvania +  and Colorado +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Main Turbine +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Emergency Core Cooling System +, Main Steam Line +, Electrohydraulic Control +, Control Room Envelope +, Moisture Separator Reheater +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Turbine Gland Sealing System +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Ultimate heat sink +, Anticipated operational occurrence +, Water Inventory Control +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Nondestructive Examination +, Incorporated by reference +, High Energy Line Break +, Design basis earthquake +, Shift Technical Advisor +, Loss of Offsite Power +, Integrated leak rate test +, Earthquake +, Fuel cladding +, Pressure boundary leak +, Flow Induced Vibration +, Water hammer +  and Control Room Habitability +

WCAP-15063-P-A +, WCAP-9601 +, WCAP-7817 +, WCAP-8373 +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-9600 +, WCAP-10444-P-A +, WCAP-6065 +, WCAP-8183 +, WCAP-8768 +, WCAP-8377 +, WCAP-8381 +, WCAP-8236 +, WCAP-8288 +, WCAP-8278 +, WCAP-8279 +, WCAP-8446 +, WCAP-8449 +, WCAP-7941-P-A +, WCAP-7959-A +, WCAP-8622 +, WCAP-8623 +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-16676-NP +, WCAP-8305 +, WCAP-8218-P-A +, WCAP-8219-A +...

WCAP-15063-P-A +, WCAP-9601 +, WCAP-7817 +, WCAP-8373 +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-9600 +, WCAP-10444-P-A +, WCAP-6065 +, WCAP-8183 +, WCAP-8768 +, WCAP-8377 +, WCAP-8381 +, WCAP-8236 +, WCAP-8288 +, WCAP-8278 +, WCAP-8279 +, WCAP-8446 +, WCAP-8449 +, WCAP-7941-P-A +, WCAP-7959-A +, WCAP-8622 +, WCAP-8623 +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-16676-NP +, WCAP-8305 +, WCAP-8218-P-A +, WCAP-8219-A +...