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Letter  and Inspection Report

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 55.53 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.73#a2iB +, 10 CFR 50.54#q +, 10 CFR 50.54#q3 +, 10 CFR 50.54#t +, 10 CFR 50.54#q5 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b4 +  and 10 CFR 50.47#b5 +

David Jones +, T. Terryah +, K. Cimorelli +, P. Scanlan +, Schroeder, dl +, H. Strahley +, J. Gorman +, B. Bridge +, B. Franssen +, J. Jennings +, C. Manges +, N. Giusto +, J. Franke +, J. Barnhardt +, T. Creasy +, E. OTruba +, R. Rodrigues-Gilroy +, M. Dziedzic +, B. Hyduk +, T. French +, A. Kuklis +, A. May-Allen +, T. Mogavero +, S. Muntzenberger +, B. ORourke +, T. Roth +, J. Waclawski +  and Darrell Adams +

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

05000387  +, 05000388  +, 00387  +  and 00388  +

Technical Support Center +  and Emergency Operations Facility +

05000388/FIN-2015004-01 +, 05000387/FIN-2015004-02 +  and 05000387/FIN-2015004-04 +

Daniel Schroeder +  and Reactor Projects Region 1 Branch 4 +

IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +, IR 05000387/2015004 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71111.19 +, IP 71151 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.05A +, IP 71111.04S +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609, Appendix B +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71114.03 +, IP 71114.02 +, IP 71151 +, IP 71114.05 +, IP 71111.11B +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.11Q +  and IP 71152, Problem Identification and Resolution (PI&R) +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +  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 +

Emergency Plan +  and EP-115 +

Pennsylvania +  and Washington +

Reactor Coolant System +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Steam +  and Low Pressure Coolant Injection +

TS-3.6.4.1 +, TS-3.0.3 +, TS-3.7.3 +, TS-3.3.6.1 +, TS-3.6.1.3 +, TS-3.3.6.2 +, TS-5.5.11 +, TS-3.0.6 +, TS-3.3.7.1 +, TS-5.4.1 +  and TS-5.4.1.a +

Susquehanna +  and Rausch T +

Ultimate heat sink +, Fire Barrier +, Stroke time +, Water Inventory Control +, Internal Flooding +, Enforcement Discretion +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Job Performance Measure +, Loss of Offsite Power +, Operability Determination +, Operability Assessment +, Siren +, ANS Design Report +  and Reactive Inspection +