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Letter  and Inspection Report

AR 01793148 +, AR 01740921 +, AR 01727385 +, AR 01781325 +, AR 01784613 +, AR 00469691 +, AR 01796777 +, AR 01795296 +, AR 01793964 +, AR 01804496 +, AR 01628106 +, AR 01785554 +, AR 01785553 +, AR 01785833 +, AR 01625160 +, AR 01607198 +, AR 01673747 +, AR 01634142 +, AR 01634167 +, AR 01650532 +, AR 01676169 +, AR 01788839 +, AR 01788838 +, AR 01788836 +, AR 01788842 +, AR 01788841 +, AR 01788852 +, AR 01674887 +, AR 01787655 +...

Carbon +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50.59 +, 10 CFR 19 +, 10 CFR 2.390 +, 10 CFR 20.1003 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 71.5 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.65#a4 +, 10 CFR 20.1501#a2 +  and 10 CFR 71.5#a +

H. 29-21 +, H. 29-28 +, H. 1 +, H. MS-60 +, H. MS-62 +, H. 7 +, H. 312 +, H. 315 +, A. 4-1 +  and L. 89-10 MOV Cable Voltage Drop +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

H.7 +  and H.14 +

05000335  +, 05000389  +, 00335  +  and 00389  +

ML12053A340 +, ML12188A031 +, ML12173A215 +, ML1030901420 +, ML110700122 +, ML12056A050 +, IR 05000335/2010005 +  and Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping +

EC-246559 +, EC-246543 +, EC-249980 +, EC-246564 +, EC-246556 +, EC-249981 +, EC-246560 +  and EC-272468 +

Turbine Trip +  and Reactor Trip +

EN-AA-203-1001 +, ER-AA-102 +, PI-AA-205 +, EN-AA-205 +, OP-AA-108 +, WM-AA-1000 +, OP-AA-104-1007 +, OP-AA-102-1002 +, ER-AA-102-1000 +, RP-AA-108-1002 +, RP-AA-108-1004 +  and RP-AA-108-1003 +

NRC/RGN-II/DRP/RPB3 +  and Rich D +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +  and NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +

IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +, IR 05000335/2012004 +...

TI 2515/187 +, TI 2515/177 +  and TI 2515/188 +

NRC Inspection Manual 0609 +, NRC Inspection Manual 310 +  and NRC Inspection Manual 0612, Appendix F +

IP 71124.08 +, IP 60855.1 +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.08P +, IP 71004 +  and IP 71152, Problem Identification and Resolution (PI&R) +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +, NEI 99-06, Response to Request for Additional Information Regarding License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor +, NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 09-14, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000168, Guideline for the Management of Underground Piping and Tank Integrity, NEI 09-14 (Rev.1) (December 2010) (NEI 09-14 Rev. 1) +

Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping +  and Information Notice 2011-07, Specific License Required When Exporting To Embargoed Destinations Listed In 10 CFR 110.28 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1608 +

ST +, Emergency Operating Procedure +  and OSP +

NPF-16 +  and DPR-67 +

Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Steam Bypass Control System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Auxiliary Feed Water +, Main Steam +, Containment Spray +  and Extraction steam +

TS-6.8.1 +, TS-6.8 +, TS-2.02.c +  and TS-2.02.d +

NextEra Energy +  and Nazar M +

Safe Shutdown +, Boric Acid +, High Radiation Area +, Fire Barrier +, Fire impairment +, Functionality Assessment +, Locked High Radiation Area +, Fukushima Dai-Ichi +, Significance Determination Process +, Foreign Material Exclusion +, Flow Accelerated Corrosion +, Feedwater Heater +, Process Control Program +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, License Renewal +, Maintenance Rule Program +, Liquid penetrant +, GOTHIC +, Unidentified leakage +, Power Uprate +, Eddy Current Test +  and Gas accumulation +

WO 40145261 +, WO 40095052 +, WO 40048843 +, WO 40129677 +, WO 40117724 +, WO 40083063 +  and WO 40044935 +