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Letter, Inspection Report  and Non-Cited Violation

AR 01866469 +, AR 01986898 +, AR 01874026 +, AR 01908490 +, AR 01957411 +, AR 02022864 +, AR 01855682 +, AR 01871088 +, AR 01873948 +, AR 02022758 +  and AR 02024359 +

Boron +, Iodine +, Carbon +, Hydrogen +, Lead +  and Aluminum +

10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 71 +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.55a +, 10 CFR 50.73#a2v +, 10 CFR 50.72#b3v +, 10 CFR 50.65#a4 +, 10 CFR 50.55a#b2 +, 10 CFR 50.55a#g6iiD +, 10 CFR 50.55a#ai +, 10 CFR 50.48#c +  and 10 CFR 50.75#g +

E. Crowe +, P. Downing +, T. Thulien +, M. Hatley +, M. Ginn +, A. Wells +, K. Ellis +, E. Burchfield +, C. Wasik +, A. Best +, K. Adomako +, D. Berkshire +, A. Ginn +, E. Lampe +, P. Metler +, L. D. Robinson +, A. Wallach +, Natasha Childs +  and Teresa Ray +

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

S.2(o) +  and S.2(a) +

05000269  +, 05000270  +, 05000287  +, 00269  +, 00270  +  and 00287  +

05000287/FIN-2016002-04 +, 05000287/FIN-2016002-01 +  and 05000287/FIN-2016002-03 +

Frank Ehrhardt +  and NRC/RGN-II/DRP/RPB1 +

IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +, IR 05000269/2016002 +...

0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71111.08 +, IP 71111.19 +, IP 71151 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71124.06, Radioactive Gaseous and Liquid Effluent Treatment +, IP 71111.05AQ +, IP 71124.07, Radiological Environmental Monitoring Program +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609 Appendix F +, NRC Inspection Manual 609 Appendix A +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71124.08 +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71124.06, Radioactive Gaseous and Liquid Effluent Treatment +  and IP 71124.07, Radiological Environmental Monitoring Program +

NCR 01733811 +, NCR 01981762 +, NCR 02027086 +, NCR 01904926 +, NCR 02018719 +, NCR 02018247 +, NCR 02035887 +, NCR 02019828 +, NCR 02031359 +, NCR 02023700 +, NCR 02016327 +  and NCR 02018602 +

NUREG-1608 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +

Regulatory Guide 1.33 +, Regulatory Guide 1.21 +, Regulatory Guide 8.38 +, Regulatory Guide 1.109 +  and Regulatory Guide 4.15 +

3E-7 +, 3MS-1 +, 1PSW-22 +, 1CC-C1 +, 3CC-C1 +, 3LPSW-563 +, 3LP-22 +, 3HP-36 +, 3LWD-1137 +, 3LP-42 +, 3HP-974 +, 3HP-18 +, 3A-R22C81 +, 3A-R79C72 +, 3A-R87C124 +, 3A-R140C68 +, 3B-R22C20 +, 3TD-14 +, 3HP-254 +, 2FWD-315 +  and 4RIA-45 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Turbine +, Decay Heat Removal +, Main Steam Line +  and Main Steam +

TS-3.8.1 +, TS-5.0 +, TS-5.5 +  and TS-5.4 +

Duke Energy +  and Batson S +

Hot Short +, Safe Shutdown +, Boric Acid +, Time of Discovery +, High Radiation Area +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Internal Flooding +, Enforcement Discretion +, Functionality Assessment +, Incorporated by reference +, Locked High Radiation Area +, Aging Management +, Significance Determination Process +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program +, Loss of Offsite Power +, Integrated leak rate test +, Eddy Current Testing +, Operability Determination +, Moisture barrier +, Liquid penetrant +, Fire Protection Program +, Eddy-Current Testing +  and Operational leakage +