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NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

Boron +, Iodine +, Cesium +, Hydrogen +, Chloride +, Lead +  and Aluminum +

10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +  and 10 CFR 50.44 +

00327  +, 00328  +, 05000327  +  and 05000328  +

Technical Support Center +  and Emergency Operations Facility +

Reactor Trip +  and Turbine Trip +

GDC 57 +, GDC 20 +, GDC 13 +, GDC 4, Environmental and dynamic effects design bases +  and GDC 3, Fire protection +

ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +, ML20030B720 +...

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

ML19341D736 +, ML19340D167 +, ML19331B559 +, ML19254E764 +, ML19294B150 +, ML19347E518 +, ML19331C668 +, 05000327/LER-1981-147, Forwards LER 81-147/03L-0 +, 05000327/LER-1981-035, Forwards LER 81-035/03L-0 +, 05000327/LER-1981-045, Forwards LER 81-045/03L-0 +, 05000327/LER-1981-041, Forwards LER 81-041/03X-1 +, IR 05000327/1980048 +, ML19343D486 +, IR 05000327/1980027 +, 05000327/LER-1980-104, Forwards LER 80-104/03L-0 +, 05000327/LER-1980-121, Forwards LER 80-121/03L-0 +, 05000327/LER-1980-103, Forwards LER 80-103/03L-0 +  and 05000327/LER-1980-070, Forwards LER 80-070/03L-0 +

Westinghouse +  and Target Rock +

NUREG-0623 +, NUREG-0761, Certified Minutes of ACRS Subcommittees on Site Evaluation & on Reactor Radiological Effects 810430 & 0501 Joint Meeting in Washington,Dc Re 10CFR100,10CFR20,radiation Protection Plan (NUREG-0761) & Health Physics Appraisal Plan +, NUREG-11 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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/CR-1659, Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0011, Notice of Availability of SER (NUREG-0011) +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.75 +, Regulatory Guide 1.3 +, Regulatory Guide 1.100 +  and Regulatory Guide 1.89 +

SR-4.6.1.3.a +  and SR-4.6.1.3.b +

Tennessee +, Georgia +, Washington +  and Alabama +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Primary containment +, Auxiliary Building Gas Treatment System +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Containment Spray +

TS-3.3.2.1 +, TS-3.6.1.9 +, TS-6.2.2 +  and TS-3.6.1.4 +

Safe Shutdown +, Reactor Vessel Water Level +, Tornado Missile +, Tornado-Generated Missile +, Tornado Generated Missile +, Shift Technical Advisor +, Process Control Program +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Integrated leak rate test +, Earthquake +, Control of Heavy Loads +, Continuous fire watch +, Fire Protection Program +, Fire Watch +, Core Exit Thermocouple +, Control Room Habitability +  and Spill +