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Letter  and Inspection Report

Lead +, Zinc +, Tin +  and Tungsten +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50.54 +, 10 CFR 50.65a#4 +, 10 CFR 50.55a +, 10 CFR 50.65#a4 +, 10 CFR 50.65#a +  and 10 CFR 50.75#g +

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

NL-95-001 +, PLA-6720, Radiological Environmental Operating Report for the Calendar Year 2010 +, PLA-5768, Response to Request for Additional Information from NRC on Proposed Relief Request No. 3RR-01 to the Third 10-Year Inservice Inspection Program +  and PLA-4996 +

H.7 +  and P.2 +

05000387  +, 05000388  +, 00387  +  and 00388  +

IR 05000387/2011002 +, IR 05000387/2011008 +, ML060950382 +, ML050690239 +, IR 05000387/2010003 +  and IR 05000387/2010001 +

SE-183-006 +, FP-213-291 +, FP-213-271 +, FP-013-189 +, FP-113-119 +, FP-013-204 +, FP-213-100 +, SE-283-006 +, SE-204-202 +, SE-259-027 +, SE-224-1O7 +, SE-259-029 +  and SE-249-002 +

EC-1390749 +  and EC-644573 +

Darrell Roberts +  and Division Reactor Projects I +

NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 06-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +, IR 05000387/2011003 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609 Appendix H +, NRC Inspection Manual 0612 Appendix K +, NRC Inspection Manual 0612, Appendix K +, NRC Inspection Manual 0619 Appendix C +, NRC Inspection Manual 1182 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, IMC 0305, Operating Reactor Assessment Program +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71111.08 +, IP 71114.06 +, IP 71111.19 +, IP 95002 +, 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 71111.04S +, IP 71111.05Q +, IP 71111.04Q +, IP 71124.07, Radiological Environmental Monitoring Program +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NEI 99-02, Regulatory Assessment Performance Indicator Guideline +  and NEI 04-05 +

4kV +  and 4.16kV +

SP +, RT +, Emergency Operating Procedure +, Emergency Plan +, PSP-29 +, TP-215-008 +, TP-235-011 +, SP-DCA-219-1 +, TP-248-010 +, EP-DS-001 +, EP-DS-002 +, EP-DS-003 +, EP-DS-004 +, EP-DS-005 +  and EP-DS-006 +

Regulatory Guide 1.33 +, Regulatory Guide 1.101 +  and Regulatory Guide 1.23 +

NEDC-33645P +  and NEDC-32264 +

SR-3.6.4 +, SR-3.6.1.3.1 +  and SR-3.6.4.2.1 +

1E-6 +, 1E-7 +  and 5Q-3871201 +

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 +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Control Rod +, Main Steam +, Low Pressure Coolant Injection +  and Extraction steam +

TS-3.6.4.1 +, TS-3.6.1.3 +, TS-3.8.2 +, TS-3.6.4.2 +, TS-3.5 +, TS-5.4.1 +  and TS-5.7.1 +

Susquehanna +  and Rausch T +

Packing leak +, High Radiation Area +, Half scram +, Non-Destructive Examination +, Mission time +, Offsite Dose Calculation Manual +, Fire Barrier +, Weld Overlay +, Enforcement Discretion +, Met Tower +, Anchor Darling +, Nondestructive Examination +, Functionality Assessment +, Condition Adverse to Quality +, High Energy Line Break +, Significance Determination Process +, Local Leak Rate Testing +, Feedwater Heater +, Shift Technical Advisor +, Process Control Program +, Large early release frequency +, Stress corrosion cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Operability Determination +, Severe Accident Management Guideline +, Maintenance Rule Program +, Liquid penetrant +, Fire Protection Program +, Dissimilar Metal Weld +...