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Letter  and Inspection Report

ANSI N13.1 - 1969 +  and ANSI/ANS-2.5-1984 +

Iodine +, Germanium +  and Hydrogen +

10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +  and 10 CFR 50.75#g +

R. Bernhard +, N. Thomas +, T. Cleary +, D. Bodine +, P. Simmons +, C. Church +, R. Thompson +, Z. Kitts +, S. Bowman +, T. Marshall +, B. Wetzel +, J. Proffitt +, K. Wilkes +, M. Kerwin +, J. Dvorak +, D. Clift +, N. Eggemeyer +, D. Boone +, L. Cross +, J. Whitaker +, T. Orf +  and Kenneth Jones +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

05000327  +, 05000328  +, 00327  +  and 00328  +

ENS 44627 +  and ENS 44649 +

Eugene Guthrie +  and Reactor Projects Region 2 Branch 6 +

IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +, IR 05000327/2009002 +...

TI 2515/176 +  and TI 2515/174 +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +  and IMC 0305, Operating Reactor Assessment Program +

IP 71122.01 +, IP 71121.03 +, IP 71122.03 +  and IP 71152, Problem Identification and Resolution (PI&R) +

05000328/LER-2008-002, Indications of a Dropped Control Rod During Startup +  and 05000328/LER-2008-001, Manual Reactor Trip Following Partial Loss of Main Feedwater Flow to Loop 4 Steam Generator +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG/CR-6427, Information Provided by Duke Corp Related to Severe Energy Accident Mitigation Alternatives in Its License Renewal Application for the McGuire Nuclear Station, Units 1 & 2 +

AOP +  and AOP-N.02 +

Regulatory Guide 1.33 +, Regulatory Guide 1.21 +, Regulatory Guide 4.15 +  and Regulatory Guide 8.15 +

1B-B +  and 1A-A +

Manual Scram +  and Automatic Scram +

Tennessee +, Georgia +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Shield Building +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Containment Spray +

TS-3.2.5 +, TS-5.0 +, TS-6.8.1 +  and TS-6.8.1.a +

Tennessee Valley Authority +  and Swafford P +

Offsite Dose Calculation Manual +, Fire Barrier +, Temporary Modification +, Significance Determination Process +, Loss of Offsite Power +, Open House +, Power change +, Unidentified leakage +, Radiological Environmental Operating Report +  and Spill +