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Letter  and Inspection Report

AR 01082316 +, AR 01097273 +  and AR 01138049 +

10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 20.1501 +, 10 CFR 20.1704 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix I +, 10 CFR 20.1101 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.73#a2vii +, 10 CFR 50.54#q +, 10 CFR 50.54#t +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b2 +, 10 CFR 50.47#b5 +, 10 CFR 50.55a#f4 +  and 10 CFR 20.1101#c +

C. Gannon +, J. Welsh +, B. Payne +, D. Coffin +, KROHN P, RI/DRP/PB4/610-337-5120 +, R. Healey +, R. Bogar +, C. Manges +, S. Sienkiewicz +, T. Iliadis +, R. Linden +, R. Collier +, R. Kessler +, R. Pagodin +, N. Coddington +, M. Adelizzi +, J. Folta +, D. DAngelo +, H. Riley +, P. Capotosto +, R. Doty +, M. Jaworsky +, M. Micca +, R. Paley +, R. Wehry +  and Patrick Brady +

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

H.1(u) +, P.2 +  and P.2(b) +

05000387  +, 05000388  +, 00387  +  and 00388  +

ML090280115 +, IR 05000387/2008005 +, ML091800460 +, PLA-6489, Work Environment Issues at the Susquehanna Steam Electric Station Supplement - Reply to Chilling Effect Letter from W. H. Spence, Dated 3/13/09 +  and PLA-6486, NRC Request to Address Work Environment Issues at Susquehanna Steam Electric Station, Dated 02/27/09 +

FP-213-282 +, FP-013-321 +, FP-013-313 +  and FP-013-312 +

EC-674911 +, EC-881351 +, EC-674914 +  and EC-6902720 +

Paul Krohn +  and Reactor Projects Region 1 Branch 4 +

IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +, IR 05000387/2009003 +...

2.199074e-4 d (0.00528 hours, 3.141534e-5 weeks, 7.2295e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 9.259259e-4 d (0.0222 hours, 1.322751e-4 weeks, 3.044e-5 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 9.953704e-4 d (0.0239 hours, 1.421958e-4 weeks, 3.2723e-5 months)  +

NRC Inspection Manual 0609 +, IMC 0305, Operating Reactor Assessment Program +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.17 +, IP 71111.13 +, IP 71114.03 +, IP 71111.08 +, IP 71114.02 +, IP 71111.19 +, IP 71151 +, IP 71114.05 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71114, Reactor Safety Emergency Preparedness +, IP 71121.02 +, IP 71121.01 +, IP 71111.05Q +, IP 71111.07A +, IP 71004 +, IP 71121.03 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000387/2009003 +, IR 05000387/2008005 +  and IR 05000387/2009006 +

Information Notice 2006-24, Recent Operating Experience Associated with Pressurizer and Main Steam Safety/Relief Valve Lift Setpoints +  and Information Notice 85-92 +

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 +

115kV +  and 4kV +

Emergency Plan +, TP-249-087 +, TP-242-003 +, TP-244-042 +, TP-262-033 +  and TP-293-041 +

Pennsylvania +  and Washington +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, HVAC +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Electrohydraulic Control +, Control rod blade +, Main Condenser +, Control Rod +, Main Steam +  and Electro-Hydraulic Control +

TS-5.5.6 +, TS-5.7 +  and TS-6.9.1.7 +

Susquehanna +  and Rausch T +

High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Time to boil +, Hydrostatic +, Nondestructive Examination +, Significance Determination Process +, Feedwater Heater +, Operability Determination +, Fire Protection Program +, Dissimilar Metal Weld +, DM weld +, Operability Assessment +, Power Uprate +, Simmer margin +, Eddy Current Test +  and ANS Design Report +