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ASME Section XI +, ASME Section III +  and ASME Section IX +

Iron +, Copper +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Chloride +, Lead +  and Aluminum +

10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 54.4#a1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +  and 10 CFR 54.21#c1iii +

05000305  +  and 00305  +

ML091600216 +, RIS 2008-30, Fatigue Analysis of Nuclear Power Plant Components +, ML072420437 +, ML070580498 +, ML062480050 +, ML0611700208 +, ML061700091 +  and ML061720131 +

MA-AA-102 +, PI-AA-100-1007 +  and AD-AA-10 +

Dominion Energy Kewaunee +  and Scace S +

NRC Generic Letter 04-02 +, NRC Generic Letter 06-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-09, Pilot Testing of Fundamentals Examination +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +, ML092320093 +...

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

LRA B.2.1.10 +  and LRA B.2.1.9 +

Information Notice 87-67 +, Information Notice 87-28 +, Information Notice 2009-02, Biodiesel in Fuel Oil Could Adversely Impact Diesel Engine Performance +  and Information Notice 81-38 +

NUREG-1431 +, NUREG/CR-6260 +, NUREG-1920 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

SP-55-085 +  and SP-36-084 +

TAC:MD9408 +  and TAC:MA0921 +

Regulatory Guide 1.121 +, Regulatory Guide 1.160 +  and Regulatory Guide 1.127 +

Washington +  and Wisconsin +

Steam Generator +, Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Shield Building +, Circulating Water System +, Emergency Core Cooling System +, Main Steam +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Packing leak +, Coatings +, VT-2 +, Zebra Mussel +, Aging Management +, Foreign Material Exclusion +, Feedwater Heater +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Biofouling +, Fire Protection Program +  and Operational leakage +