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ACI-318 +  and ACI-531 +

ANSI B31.1.0 +, ANSI B96.1 +  and ANSI A58.1 +

Boron +, Iodine +, Uranium +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chlorine +, Lead +, Titanium +, Neptunium +  and Plutonium +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +  and 10 CFR 50.44 +

Barrier Integrity +  and Initiating Events +

05000341  +  and 07200071  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

GDC 20 +, GDC 41 +, GDC 10 +, GDC 12 +, GDC 18 +, GDC 24 +, GDC 13 +, GDC 30 +, GDC 29 +, GDC 19, Control room +, GDC 1, Quality standards and records +  and GDC 26, Reactivity control system redundancy and capability +

NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 93-08, Relocation of Technical Specification Tables of Instrument Response Time Limits +  and NRC Generic Letter 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation +

NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +, NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +  and NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +

IEEE 344 +, IEEE 323 +, IEEE 323-1974 +, IEEE 279 +, IEEE 279-1971 +, IEEE 379 +, IEEE 279-1968 +, IEEE 308 +, IEEE 344-1975 +, IEEE 379-1972 +, IEEE 336 +, IEEE 336-1971 +, IEEE 323-1971 +, IEEE 344-1971 +, IEEE 317 +, IEEE 338-1971 +, IEEE 338 +  and IEEE 34 +

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-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 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

ES +, CH +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.52 +, Regulatory Guide 1.70 +, Regulatory Guide 1.7 +, Regulatory Guide 1.53 +, Regulatory Guide 1.21 +, Regulatory Guide 1.23 +, Regulatory Guide 1.118 +  and Regulatory Guide 1.22 +

NEDO-24708A +, NEDO-10139 +, NEDC-32410P +, NEDO-31146 +, NEDO-10678 +, NEDO-31558A +, NEDC-31843P +, NEDO-10698 +, NEDO-21617 +, NEDO-32291A +, NEDO-l0678 +  and NEDO-l0698 +

72C-F +, 4l60-V +, 3D-Monicor +, 72E-5B +, 72B-2A +, 72C-3A +, 72B-4C +, 72B-3A +, 72F-4A +, 72M-3B +, 72S-2A +  and 211A-74 +

Manual Scram +  and Automatic Scram +

Fermi +  and 07200071 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Emergency Response Data System +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Emergency Equipment Cooling Water +...

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

Hot Short +, Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Squib +, Emergency Lighting +, Incorporated by reference +, Test box +, Abnormal operational transient +, Feedwater Heater +, Scram Discharge Volume +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Overtravel +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Pressure boundary leak +, Unidentified leakage +, Overspeed trip +, Overspeed +, Manual Operator Action +, Water hammer +, Control Room Habitability +  and Operational convenience +