Browse wiki

Letter  and Inspection Report

Boron +, Nickel +, Carbon +  and Tin +

10 CFR 20 +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#q2 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b9 +  and 10 CFR 50.55a#g6iiD +

G. Hopper +, B. Waldrep +, B. McCabe +, G. Simmons +, D. Griffith +, T. Thulien +, L. Faulk +, J. Keltner +, I. Nordby +, S. OConnor +, M. Parker +, D. Corlett +, R. Chezem +, A. Staller +, S. Volk +, A. Zimandy +, J. Caves +, J. Dufner +, E. Fonteneau +, C. Hartweg +, J. Jankens +  and J. Warner +

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

05000400  +  and 00400  +

05000400/FIN-2015002-01 +, 05000400/FIN-2015002-02 +  and 05000400/FIN-2015002-03 +

Hopper G +  and NRC/RGN-II/DRP/RPB4 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +, IR 05000400/2015002 +...

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, 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 71111.05Q +, 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 0612 Appendix B +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609, Appendix B +, NRC Inspection Manual 0609 Appendix G +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix A +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71124.05 +, IP 71124.04 +, IP 71124.02 +  and IP 71124.01, Radiological Hazard Assessment and Exposure Controls +

IR 05000400/2015002 +  and IR 05000400/2014005 +

05000400/LER-2014-003, Regarding Diesel Fuel Oil Storage Building Moderate Energy Line Break Design Deficiency +, 05000400/LER-2015-002, Regarding Breakers to the a and B Train Control Room Normal Intake Isolation Damper Motor Actuators Tripped Open +  and 05000400/LER-2015-003, Regarding Reactor Vessel Head Nozzle Repairs +

NUREG-1738, Yellow Ticket 020010064 - Nuclear Energy Institute Comments on NUREG-1738, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants +, 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 +

MST-I0189 +, SP-952 +, MST-I0145 +, MST-I0031 +, MST-I0322 +  and MST-M0006 +

Regulatory Guide 1.33 +, Regulatory Guide 8.40 +, Regulatory Guide 8.38 +  and Regulatory Guide 8.15 +

1CZ-1 +, 1CZ-2 +, 1A-SA +, 1RC-903 +, 3SF-E004 +, 1CS-347 +, 13R-15 +, 1CT-99 +, 1SI-333 +, 1SP-1756 +, 1CS-230 +, 1CS-424 +, 1CS-427 +, 1CT-33 +, 1CS-499 +, 1B31-SB-11B +, 1CS-423 +, 1SW-39 +, 1A21-5A-12C +  and 1CS-7 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Remote shutdown +, Decay Heat Removal +, Control Room Envelope +  and Control Rod +

TS-6.8.1 +  and TS-6.8 +

Duke Energy +  and Waldrep B +

Boric Acid +, Time of Discovery +, Shutdown Margin +, High Radiation Area +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Internal Flooding +, Met Tower +, Functionality Assessment +, Incorporated by reference +, Locked High Radiation Area +, Significance Determination Process +, Stress corrosion cracking +, Eddy Current Testing +, Operability Determination +, Fire Protection Program +, Operational leakage +, Control Room Habitability +  and Seal weld +

WO 13344486 +, WO 13352682 +, WO 2199334 +, WO 856563#09 +, WO 2107301#01 +, WO 1846416#01 +, WO 13513467 +, WO 13468424 +, WO 13314231 +, WO 02228277 +, WO 02224607 +  and WO 13534885 +