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Letter  and Inspection Report

AR 02063783 +  and AR 02047870 +

Cobalt +, Carbon +  and Zinc +

10 CFR 20 +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 55.59 +, 10 CFR 50 Appendix B Criterion XVI +  and 10 CFR 50.55a#g6iiD +

T. Hamilton +, T. Stephens +, D. Griffith +, J. Robertson +, L. Faulk +, P. Fisk +, J. Keltner +, S. OConnor +, T. Toler +, M. Parker +, R. Chezem +, E. Fronteneau +, K. Rochelle +, A. Staller +, S. Volk +, C. Yarley +, A. Zimandy +  and Steven Rose +

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

05000400  +  and 00400  +

Turbine Trip +  and Reactor Trip +

05000400/FIN-2016003-01 +, 05000400/FIN-2016007-00 +, 05000400/FIN-2016003-00 +, 05000400/FIN-2016004-00 +, 05000400/FIN-2016005-00 +  and 05000400/FIN-2016006-00 +

NRC/RGN-II/DRP/RPB4 +  and Steven Rose +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +, IR 05000400/2016004 +...

0.0152 d (0.364 hours, 0.00217 weeks, 4.98455e-4 months)  +, 0.0237 d (0.569 hours, 0.00339 weeks, 7.796445e-4 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 0.0154 d (0.369 hours, 0.0022 weeks, 5.05304e-4 months)  +  and 0.0249 d (0.598 hours, 0.00356 weeks, 8.19597e-4 months)  +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.08 +, IP 71124.05 +, IP 71124.03 +, IP 71111.19 +, IP 71124.04 +, IP 71151 +, IP 71124.02 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.07, Heat Sink Performance +, 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 B +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +  and IP 71124.01, Radiological Hazard Assessment and Exposure Controls +

IR 05000400/2016004 +  and IR 05000400/2016003 +

05000400/LER-2016-004, Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power +, 05000400/LER-2016-003, Regarding Containment High-Range Radiation Monitors Declared Inoperable Due to Potential for Temperature Induced Current +, 05000400/LER-2016-007, Regarding Containment Spray System Valve Actuation +, 05000400/LER-2016-006, For Shearon Harris Nuclear Plant, Unit 1 Regarding Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void +  and 05000400/LER-2016-005, Regarding Offsite Power Undervoltage Caused Actuation of Several Systems +

NCR 02081048 +, NCR 02077459 +, NCR 02072469 +, NCR 02073741 +  and NCR 02067609 +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Emergency Operating Procedure +  and ISP-1138 +

1A-SA +, 1CT-102 +, 1CT-105 +, 1CT-71 +, 1CT-26 +, 1RC-124 +, 13R-16 +, 1IC-J-5 +, 1SP-952 +, 3SF-E004 +, 1NI-109 +, 1RC-1016 +, 1ED-145 +  and 1B35-SB-13C +

Steam Generator +, Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

TS-6.11 +  and TS-3.3.3.6 +

Progress Energy Carolinas +  and Hamilton T +

Boric Acid +, Fitness for Duty +, Packing leak +, High Radiation Area +, Non-Destructive Examination +, Commercial Grade Dedication +, Nondestructive Examination +, VT-2 +, Functionality Assessment +, Incorporated by reference +, Locked High Radiation Area +, Significance Determination Process +, Flow Accelerated Corrosion +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Liquid penetrant +, Fire Protection Program +, Downpower +  and Overspeed trip +

WO 13506167 +, WO 12230406#03 +  and WO 20091262#01 +