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ANSI B31.7 +, ANSI B-31.7 +, ANSI-B16.34 +  and ANSI-5.5-37 +

IWB-2500 +, IWC-2500 +, IWB-5000 +, IWB-1220 +, IWB-2600 +, IWC-2411 +, IWA-5000 +  and IWA-2420 +

ASME Section III +  and ASME Section XI +

Iodine +, Cobalt +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Helium +, Aluminum +, Mercury +  and Zinc +

BWRVIP-86 +, BWRVIP-135 +, BWRVIP-78 +  and BWRVIP-86-A +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.55 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.55a#g5iii +, 10 CFR 50.55a#g4 +  and 10 CFR 50.55#a +

NRC-08-0064, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +, WM 12 +, ND-3512 +  and NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +

05000341  +  and 07200071  +

Turbine Trip +  and Reactor Trip +

GDC 34 +  and GDC 55 +

NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +

NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +  and NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems +

1.967593e-4 d (0.00472 hours, 2.810847e-5 weeks, 6.4685e-6 months)  +  and 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +

General Electric +  and Target Rock +

NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System +  and NRC-08-0064, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +

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-0798, Advises That NRC Review of Sys Leakage Reduction Test Results Cannot Be Completed Until Final Test Procedures & Acceptance Criteria Upon Which Sys Test Results Based Submitted & Reviewed +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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 +

RT +, ISP +  and TP +

Regulatory Guide 1.45 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.31 +  and Regulatory Guide 1.56 +

NEDC-33178P +, NEDO-10899 +, NEDE-21821 +, NEDE-32906P +, NEDO-24154 +, NEDO-24951 +, NEDC-33133P +, NEDC-33785P +  and NEDO-l0677 +

E308L-15 +, 15-308A-D +, 6M721-2083 +, 6M721-2034 +, 6M721-2035 +  and 6M721-2044 +

Fermi +  and 07200071 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Core Standby Cooling System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +...

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Reactor Vessel Water Level +, Grab sample +, Anticipated operational occurrence +, Weld Overlay +, Hydrostatic +, Operating Basis Earthquake +, Multiple Spurious Operation +, Abnormal operational transient +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Liquid penetrant +, Pressure boundary leak +, Dissimilar Metal Weld +, Unidentified leakage +, Unidentified leak +, Power Uprate +, Overspeed trip +, Overspeed +, Subsequent actuation +, Loss of condenser vacuum +, Water hammer +, Gas accumulation +  and Pressure Temperature Limits Report +