Pages that link to "05000348/LER-2016-007"
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The following pages link to 05000348/LER-2016-007:
Displayed 50 items.
- 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 05000364/LER-2015-001 (← links)
- 05000364/LER-2016-001 (← links)
- 05000348/LER-2016-008 (← links)
- 05000348/LER-2016-006 (← links)
- 05000348/LER-2016-005 (← links)
- 05000348/LER-2016-004 (← links)
- 05000348/LER-2016-003 (← links)
- 05000348/LER-2016-002 (← links)
- 05000348/LER-2016-001 (← links)
- 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown (← links)
- 05000348/LER-2016-009 (← links)
- ML17216A057 (← links)
- IR 05000348/2017002 (← links)
- ML17013A394 (redirect page) (← links)
- NL-18-0733, Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information (← links)
- NL-17-0611, Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow (← links)
- ML17158B319 (redirect page) (← links)
- TS-3.0.3 (← links)
- IR 05000348/2017004 (← links)
- ML18018B038 (← links)
- ML17324B307 (redirect page) (← links)
- 05000364/LER-2017-005 (← links)
- 05000364/LER-2017-004 (← links)
- 05000364/LER-2017-003 (← links)
- 05000364/LER-2017-002 (← links)
- 05000364/LER-2017-001 (← links)
- EPID:L-2017-LLA-0428 (← links)
- ML18087A146 (← links)
- NL-17-1952, LER 16-007-02 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters (redirect page) (← links)
- NL-17-1952 (redirect page) (← links)
- NL-17-0543, LER 16-007-01 for Joseph M. Farley, Unit 1, Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters (redirect page) (← links)
- NL-17-0543 (redirect page) (← links)
- NL-17-0004, LER 16-007-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters (redirect page) (← links)
- NL-17-0004 (redirect page) (← links)
- NL-13-1525, Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B (← links)
- NL-11-2445, LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems (← links)
- ML18271A207 (← links)
- L-16-308, Request for an Amendment to Revise Technical Specification 3.3.1. Reactor Protection System ≪Rps) Instrumentation. (← links)
- RS-16-172, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪Sse with High Frequency Exceedances (← links)
- NRC 2017-0040, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Section H.4.4, Path 4: GMRS ≪ 2X SSE (← links)
- NL-17-1262, NEI 12-06, Rev. 4, Appendix H, H.4.4 Path 4: GMRS ≪ 2xSSE Mitigating Strategies Assessment (MSA) Report (← links)
- NL-18-0733, Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information (← links)
- NL-08-0756, Special Report 2008-002-00, Inoperable Radiation Monitor R-60B (← links)
- NL-08-0659, Special Report 2008-001-00, Inoperable Radiation Monitor R-29B (← links)
- NEI 12-06, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS ≫ 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information (← links)
- NL-17-0611, Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow (← links)
- RS-16-170, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE (Partial Submittal - High Frequency Work Scope) (← links)
- NL-05-2234, Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B (← links)
- LR-N05-0003, Request for Change to Technical Specifications Emergency Core Cooling Systems Tavg <335 Degrees F, (← links)
- 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel (← links)
- 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift (← links)
- 05000364/LER-2023-003, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits (← links)
- 05000348/LER-2023-003, Emergency Diesel Generator (Eog) Lube Oil Pwnp Outlet Coupling Leak (← links)
- 05000348/LER-2023-001, Automatic Reactor Trip Due to DC Ground on Turbine Trip Solenoid (← links)