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IWB-3600 +, IWB-3500 +, IWC-3500 +  and IWA-5250 +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 2 +, 10 CFR 50.9 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.71 +, 10 CFR 50.90 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.55a +, 10 CFR 50.49#b1 +, 10 CFR 50.54#f +, 10 CFR 5#O +, 10 CFR 50.55a#g +, 10 CFR 50.109#a5 +  and 10 CFR 50.55#a +

05000003  +, 05000010  +, 05000029  +, 05000133  +, 05000155  +, 05000171  +, 05000206  +, 05000213  +, 05000219  +, 05000220  +, 05000237  +, 05000244  +, 05000245  +, 05000247  +, 05000249  +, 05000250  +, 05000251  +, 05000254  +, 05000255  +, 05000259  +, 05000260  +, 05000261  +, 05000263  +, 05000265  +, 05000266  +, 05000267  +, 05000269  +, 05000270  +, 05000271  +, 05000272  +...

Partlow J +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 88-07, Modified Enforcement Policy Relating to 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety" +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +  and NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +

ML031140549 +, ML031140549 +, ML031140549 +, ML031140549 +, ML031140549 +, ML031140549 +, ML031140549 +, ML031140549 +  and ML031140549 +

NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +  and NRC Bulletin 79-14 +

ML031140549 +  and ML031140549 +

Beaver Valley +, Millstone +, Hatch +, Monticello +, Calvert Cliffs +, Dresden +, Davis Besse +, Peach Bottom +, Browns Ferry +, Salem +, Oconee +, Mcguire +, Nine Mile Point +, Palisades +, Palo Verde +, Perry +, Indian Point +, Fermi +, Kewaunee +, Catawba +, Harris +, Wolf Creek +, Saint Lucie +, Point Beach +, Oyster Creek +, Watts Bar +, Hope Creek +, Grand Gulf +, Cooper +, Sequoyah +...

Steam Generator +, Reactor Coolant System +  and Service water +

Safe Shutdown +, Unanalyzed Condition +, Fitness for Duty +, Probabilistic Risk Assessment +, Condition Adverse to Quality +, Missed surveillance +, Operability Determination +, Exemption Request +, Pressure Boundary Leakage +, Backfit +  and Operational leakage +