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ML14223A021 +
10 CFR 50.72 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50.73#a2ivA +, 10 CFR 50.73#a2vC +, 10 CFR 50.73#a2ivB +, 10 CFR 50.72#b3vC +, 10 CFR 50.72#b3vA +, 10 CFR 50.54#q +, 10 CFR 50.54#q3 +, 10 CFR 50.54#q5 + and 10 CFR 50.65#a4 +
John Stanley +, Daniel Schroeder +, J. Snyder +, E. Perkins +, C. Costanzo +, J. Holton +, K. Clark +, W. Trafton +, P. Orphanos +, M. Busch +, M. Kunzwiler +, T. Tanguay +, S. Homoki +, M. Shanbhag +, S. Dhar +, J. Leonard +, Jeremy Dean + and Jacqueline Thompson +
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IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +, IR 05000220/2014003 +...
IP 71111.18 +, IP 71111.01 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71114.06 +, IP 71124.03 +, IP 71111.19 +, IP 71124.04 +, IP 71151 +, IP 71124.02 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, 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 71111.05A +, IP 71111.05Q +, IP 71111.12Q +, IP 05000 +, IP 71111.07A +, IP 71111.08G +, IP 71111.20, Refueling and Other Outage Activities + and IP 71152, Problem Identification and Resolution (PI&R) +
NRC Inspection Manual 0609 +, IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +, NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues + and IMC 0310, Aspects within the Cross-Cutting Areas +
August 7, 2014 +
05000410/LER-2014-007, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors +, 05000410/LER-2014-005, Regarding Secondary Containment Inoperable Due to Sustained High Winds +, 05000220/LER-2014-001, Regarding Reportable Conditions Not Reported During the Previous 3 Years Involving Average Power Range Monitors Inoperability +, 05000410/LER-2013-005, Regarding Secondary Containment Inoperabilities Due to Differential Pressure Not Meeting Technical Specification Surveillance Requirement 3.6.4.1.1 + and 05000410/LER-2013-004, Regarding Manual Reactor Protection System Actuation Due to Loss of Reactor Recirculation Flow +
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22:29:06, 10 January 2025 +
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, 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 + and NUREG-0041, Request Addl Info Re Requested Clarifications/Exceptions to NUREG-0041,respiratory Protection Program.Nrc Comments Encl +
67 +
August 7, 2014 +
Washington + and New York +
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Intermediate Range Monitor +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Electrohydraulic Control +, Control Room Envelope + and Control Rod +
IR 05000220-14-003, 05000410-14-003; on 4/1/14 - 6/30/14; Nine Mile Point Nuclear Station Units 1 & 2; Operability Determinations & Functionality Assessments, Problem Identification & Resolution, and Follow-Up of Events & Notices of Enforce +
Exelon + and Costanzo C +
High winds +, Reactor Vessel Water Level +, High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Water Inventory Control +, Enforcement Discretion +, Nondestructive Examination +, Temporary Modification +, Functionality Assessment +, Condition Adverse to Quality +, Significance Determination Process +, Job Performance Measure +, Feedwater Heater +, Shift Technical Advisor +, Loss of Offsite Power +, Integrated leak rate test +, Operability Determination +, Power change +, Power Uprate +, Reactive Inspection + and Respirator fit test +
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