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ASME Section III +  and ASME Section IX +

Boron +, Uranium +, Iron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Lead +, Helium +, Aluminum +, Chromium +  and Hafnium +

GO2-13-174, Final Safety Analysis Report, Amendment 62, Appendix J - Shielding Evaluation Report +, GO2-90-162, Provides Final Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow +  and GO2-90-075, Application for Amend to License NPF-21,supporting Cycle 6 Reload & Operation of Lead Fuel Assemblies During Feedwater Temp Reduction Anticipated & Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow +

GO2-13-174, Final Safety Analysis Report, Amendment 62, Appendix J - Shielding Evaluation Report +, GO2-90-162, Provides Final Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow +  and GO2-90-075, Application for Amend to License NPF-21,supporting Cycle 6 Reload & Operation of Lead Fuel Assemblies During Feedwater Temp Reduction Anticipated & Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow +

ML14010A299 +, ML14010A299 +, ML14010A299 +, ML14010A299 +, ML14010A299 +, ML14010A299 +, ML14010A299 +, ML14010A299 +  and ML14010A299 +

Westinghouse +, Honeywell +  and General Electric +

NRC Bulletin 90-02 +  and NRC Bulletin 90-92 +

NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0892, Forwards Suppl to SER Chapter 9 Conditionally Accepting Applicant 830719 Request to Delay Relocation of HPCS Diesel Generator Control Panel & Installation of Air Dryers in Emergency Diesel Generator Air Starting Sys +

TP +  and TOP +

Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.31 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +, Regulatory Guide 1.36 +, Regulatory Guide 1.71 +, Regulatory Guide 1.66 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

NEDC-32694P +, NEDC-32601P +, NEDC-32868P +, NEDE-31152P +, NEDE-21354 +, NEDO-24226 +, NEDE-31758P +, NEDC-32851P +, NEDE-31096 +, NEDE-30931 +, NEDC-33144 +, NEDC-33419P +  and NEDO-20566P +

07-07-011 +, 07-02-022 +, 07-03-003 +, 07-12-027 +  and 02C12-04 +

Ohio +, Washington +  and California +

Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Reactor Pressure Vessel +, Core Spray +, Standby Liquid Control +, Main Steam Line +, Control rod blade +  and Control Rod +

Shutdown Margin +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Hydrostatic +, Nondestructive Examination +, Finite Element Analysis +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Fuel cladding +, Power change +, Power Uprate +, Water rod +  and Basic Component +