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ASME Section II +  and ASME Section XI +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 21 +, 10 CFR 26 +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 19 +, 10 CFR 25 +, 10 CFR 73 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50.91 +, 10 CFR 50 Appendix I +, 10 CFR 73.1 +, 10 CFR 73.55 +, 10 CFR 73.58 +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 73.22 +  and 10 CFR 50.54#x +

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

ML052520204 +, ML062890456 +, ML073510727 +, ML091590710 +, ML12290A180 +, ML20112F347 +, ML031200261 +, ML042450266 +, ML052580058 +, ML062400471 +, ML073530647 +, ML090360621 +, ML11175A317 +, ML11322A093 +, ML12248A361 +, ML15177A309 +, ML15195A155 +, ML15075A079 +, ML15068A066 +, ML16301A167 +, ML16301A342 +, ML16301A076 +  and ML20112F452 +

Technical Support Center +  and Emergency Operations Facility +

Kenneth Kolaczyk +  and NRC/NRR/DRO/IRSB +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +  and NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +

ML20112F347 +, ML20112F347 +, ML20112F347 +, ML20112F347 +, ML20112F347 +  and ML20112F347 +

4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 3.935185e-4 d (0.00944 hours, 5.621693e-5 weeks, 1.2937e-5 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)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 3.703704e-4 d (0.00889 hours, 5.291005e-5 weeks, 1.2176e-5 months)  +

ML20112F346 +  and ML20314A37 +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0308 +, NRC Inspection Manual 0326, Operability Determinations & Functionality Assessments for Conditions Adverse to Quality of Safety +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 2515 Appendix D +, NRC Inspection Manual 1245 Appendix A +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 1245 +, NRC Inspection Manual 1245, Appendix A +  and NRC Inspection Manual 2201, Appendix D +

IP 71111.12 +, IP 71111.04 +, IP 71111.22 +, IP 71111.13 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71124, Radiation Safety-Public and Occupational +, IP 73756 +, IP 71715 +  and IP 71111.20, Refueling and Other Outage Activities +

NEI 18-03 +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

Information Notice 93-72 +, Information Notice 95-57 +  and Information Notice 1997-78, Crediting of Operator Actions in Place of Automatic Actions & Modifications of Operator Actions, Including Response Times +

NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, 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 +, NUREG-0728, Responds to Re Offsite Emergency Organization Agreements.Rev 1 to NUREG-0728 Assures That NRC Responds to Incidents Having Potential to Threaten Health & Safety of Public or Environ.Summary of NRC Role in Emergency Encl +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Regulatory Guide 1.189 +, Regulatory Guide 1.147 +, Regulatory Guide 1.33 +, Regulatory Guide 1.160 +, Regulatory Guide 1.84 +, Regulatory Guide 1.26 +  and Regulatory Guide 8.38 +

RIS 2005-01, Changes to Notice of Enforcement Discretion (NOED) Process and Staff Guidance +  and RIS 2006-10, NRC Regulatory Issue Summary NRC Regulatory Issue Summary 2006-010 - Regulatory Expectations with Appendix R Paragraph III.G.2 Operator Manual Actions +

Steam Generator +, Reactor Coolant System +, Auxiliary Feedwater +, HVAC +, Decay Heat Removal +, Main Steam Line +  and Control Rod +

Safe Shutdown +, Fitness for Duty +, High Radiation Area +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Enforcement Discretion +, Operator Manual Action +, Temporary Modification +, Functionality Assessment +, Locked High Radiation Area +, B.5.b +, Significance Determination Process +, Notice of Violation +, Operability Determination +, Pressure Boundary Leakage +, Fire Protection Program +, Inattentive +  and Eddy Current Test +