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Letter  and Inspection Report

AR 01398404 +  and AR 01398163 +

ASME Section IV +  and ASME Section XI +

Carbon +  and Helium +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 72.12 +, 10 CFR 72.48 +, 10 CFR 72.104 +, 10 CFR 72.212 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.73#a2iB +, 10 CFR 50.73#a2v +, 10 CFR 50.73#a2vC +, 10 CFR 50.73#a2vii +, 10 CFR 50.73#a2iiA +, 10 CFR 50.54#q2 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +  and 10 CFR 50.47#b14 +

ASME Code Case N-513-3 +  and ASME Code Case N-513 +

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

05000387  +, 05000388  +, 00387  +  and 00388  +

IR 05000387/2014003 +, IR 05000387/2012005 +, IR 05000387/2013004 +  and IR 05000387/2013001 +

FP-013-138 +, FP-013-142 +, FP-013-148 +, FP-013-150 +, FP-213-242 +, FP-213-241 +, FP-213-247 +, FP-213-254 +  and SE-159-031 +

Technical Support Center +  and Emergency Operations Facility +

Fred Bower +  and Reactor Projects Region 1 Branch 4 +

IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +, IR 05000387/2014005 +...

7.175926e-4 d (0.0172 hours, 1.025132e-4 weeks, 2.3591e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609, Appendix B +, NRC Inspection Manual 0612 Appendix K +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71124.08 +, IP 71111.13 +, IP 71114.06 +, IP 71124.03 +, IP 71111.19 +, IP 71124.04 +, IP 71124.02 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11Q +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.05Q +, IP 71111.11A +, IP 71111.04Q +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000387/2014005 +, IR 05000387/2014003 +, IR 05000387/2012005 +, IR 05000387/2013008 +  and IR 05000387/2013001 +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

Emergency Plan +, EP-RM-004 +, EP-PS-001 +, PSP-26 +, TP-024-149 +, TP-164-045 +, TP-252-006 +, PSP-29 +  and EP-AD-000-511 +

3E-8 +  and 3E-10 +

Pennsylvania +  and Washington +

Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Remote shutdown +, Residual Heat Removal Service Water +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

TS-3.6.4.1 +, TS-3.4.3 +, TS-3.3.8.2 +, TS-5.4 +  and TS-1.2.12 +

Susquehanna +  and Rausch T +

Safe Shutdown +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Water Inventory Control +, Enforcement Discretion +, Fire impairment +, Functionality Assessment +, Locked High Radiation Area +, FLEX +, Significance Determination Process +, Job Performance Measure +, Notice of Violation +, Foreign Material Exclusion +, Shift Technical Advisor +, Process Control Program +, Loss of Offsite Power +, Operability Determination +, Reasonable doubt of operability +, Liquid penetrant +, Pressure boundary leak +, Fire Protection Program +, Fire Watch +, Hourly Fire Watch +, Unidentified leak +, Overexposure +, Overspeed trip +  and Water hammer +