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10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 2.348, Separation of Functions +, 10 CFR 50.71 +, 10 CFR 50.82 +, 10 CFR 50.90 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50 Appendix B Criterion VII, Control of Purchased Material, Equipment, and Services +, 10 CFR 50.5921 +, 10 CFR 50.55a +, 10 CFR 50.65#a4 +, 10 CFR 50.59#a2 +, 10 CFR 50.59#d +, 10 CFR 50.59#c2 +, 10 CFR 50.59#a +, 10 CFR 50.59#d2 +, 10 CFR 50.59#c2viii +, 10 CFR 50.59#a2i +, 10 CFR 50.59#a2ii +  and 10 CFR 50.71#e +

NRC 315 +, NRC 307 +  and NRC 551 +

05000247  +, 05000286  +, 00361  +  and 00362  +

MD 8.3, NRC Incident Investigation Program +, ML111801157 +, 05000362/LER-2012-001, (Songs), Unit 3 Regarding Unit 3 Manual Reactor Trip Due to Steam Generator Tube Leak +, 05000362/LER-2012-002, Regarding Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing +, Regulatory Guide 1.187 +, IR 05000361/2012010 +, ML003771157 +, ML13261A116 +, IR 05000361/2009004 +, IR 05000362/2010009 +, ML102630150 +, IR 05000361/2012007 +, ML070810350 +, ML131640201 +, ML14353A114 +, ML12087A323 +, ML070260376 +, ML031220043 +, ML13357A058 +, ML13263A271 +, ML13246A435 +, IR 05000361/2013801 +, ML12242A518 +, IR 05000361/2012006 +, Information Notice 2012-07, Tube-to-Tube Contact Resulting in Wear in Once-Through Steam Generators +, ML14028A028 +, ML14276A478 +, ML15062A125 +, ML15062A132 +, ML12086A182 +...

64 FR 53582 +, 67 FR 36920 +, 64 FR 53613 +, 64 FR 53583 +  and 78 FR 22576 +

New York +  and Office of the Attorney General +

ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +, ML15160A419 +  and ML15160A419 +

IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0350 +, NRC Inspection Manual 0351 +  and IMC 0305, Operating Reactor Assessment Program +

IP 71111.18 +, IP 71111.21 +, IP 71111.08 +, IP 50001 +, IP 37805 +  and IP 71111.17T, Evaluations of Changes, Tests, and Experiments +

IR 05000361/2013801 +, IR 05000361/2012006 +, IR 05000361/2013006 +  and IR 05000362/2013006 +

05000362/LER-2012-001, (Songs), Unit 3 Regarding Unit 3 Manual Reactor Trip Due to Steam Generator Tube Leak +  and 05000362/LER-2012-002, Regarding Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +, NEI 96-07 +  and NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting +

NRC 315 +, NRC 307 +  and NRC 551 +

Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) +  and Information Notice 2012-07, Tube-to-Tube Contact Resulting in Wear in Once-Through Steam Generators +

CLI-96-13 +, CLI-13-09 +  and CLI-14-11 +

Regulatory Guide 1.187 +  and Regulatory Guide 1.20 +

California +, New York +  and Florida +

Steam Generator +  and Reactor Coolant System +

Notice of Violation +, Stress corrosion cracking +, Open House +, Power Uprate +  and Reactive Inspection +