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Issue date | Title | Topic | |
---|---|---|---|
05000220/LER-2017-001 | 8 February 2017 | Manual Reactor Scram Due to Hiah Turbine Vibration LER 17-01-00 for Nine Mile Point Unit 1 RE: Manual Reactor Scram Due to High Turbine Vibration | |
CAC:MF9046 | 3 January 2017 | ||
CAC:MF9357 | 28 February 2017 | ||
CAC:MF9381 | 7 March 2017 | ||
CAC:MF9470 | 28 March 2017 | ||
IR 05000220/2016004 | 1 February 2017 | Integrated Inspection Report 05000220/2016004 and 05000410/2016004 and NRC Office of Investigations Report 1-2016-007 | Safe Shutdown Half scram Fire Barrier Commercial Grade Dedication Functionality Assessment Significance Determination Process Job Performance Measure Surveillance Frequency Control Program Open Phase Condition Operability Determination Fire Protection Program Downpower Coast down |
IR 05000220/2016006 | 1 March 2017 | Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2016006 and 05000410/2016006) | Spent Fuel Pool Instrumentation |
ML17009A141 | 31 January 2017 | Se Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 (CAC Nos. MF1129, MF1130, MF1131, and MF1132) | Safe Shutdown High winds Shutdown Margin Ultimate heat sink Mission time Tornado Missile Safe Shutdown Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake Pressure Boundary Leakage Fire Protection Program GOTHIC |
ML17010A077 | 19 January 2017 | Submittal of Annual Report of the Nuclear Advisory Committee | Cyber Security |
ML17017A109 | 24 January 2017 | Acceptance of Requested Licensing Action Partial Length Fuel Rod Burnup | |
ML17018A282 | 17 January 2017 | Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2017 | Generic Fundamentals Examination |
ML17019A053 | 31 January 2017 | Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Reduce Steam Dome Pressure in Reactor Core Safety Limits | |
ML17026A414 | 20 January 2017 | C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling | |
ML17027A016 | 27 January 2017 | 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors | |
ML17031A156 | 6 February 2017 | Staff Review of High Frequency Confirmation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi |
ML17033B018 | 2 February 2017 | Professional Qualifications Jan A. Norris Directorate of Licensing U.S. Atomic Energy Commission | |
ML17033B021 | 2 February 2017 | Qualifications of Robert Nilsen Senior Power Engineer Nine Mile Point Nuclear Station, Unit 2 Stone and Webster Engineering Corporation | |
ML17033B024 | 2 February 2017 | Qualifications P. Allister Burt General Superintendent - Nuclear Generation Niagara Mohawk Power Corporation | |
ML17033B056 | 2 February 2017 | Direct Testimony of John M. Haynes, Vice President and Treasurer, Niagara Mohawk Power Corporation, Before the Public Service Commission | |
ML17033B063 | 2 February 2017 | Supplemental Testimony of Herman G. Roseman | |
ML17033B209 | 2 February 2017 | Certificate of Service for Updated Copies of the Application for Licenses, as Amended, Eliminating All Superseded Information | |
ML17033B437 | 2 February 2017 | Professional Qualifications of Barton M. Hoglund | |
ML17033B453 | 2 February 2017 | Professional Qualifications Dennis Rathbun U.S. Atomic Energy Commission | |
ML17034A109 | 2 February 2017 | December 7, 2016, NRC Generic Fundamentals Examination Results for Nine Mile Point Nuclear Station Unit 2 (Cover Letter Publicly Available, Enclosures Withheld from Public | Generic Fundamentals Examination |
ML17037A265 | 6 February 2017 | Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant | Anticipated operational occurrence |
ML17037A461 | 6 February 2017 | Drawing 807E154TY, Revision 3, Leak Detection System Elementary Diagram. Sheet 3 | |
ML17037A462 | 6 February 2017 | Drawing 807E154TY, Revision 3, Leak Detection System Elementary Diagram. Sheet 4 | |
ML17037A652 | 6 February 2017 | Cross Section PT-1, West Wall Pit 1, Plate 4-8 | |
ML17037A653 | 6 February 2017 | Cross Section PT-2, East Wall Pit 1, Plate 4-7 | |
ML17037A654 | 6 February 2017 | Cross Section CT-1, West Wall Cooling Tower Piping Trench, Plate 4-11 | |
ML17037A655 | 6 February 2017 | Cross Section 4-1A, West Wall Trench 4, Plate 4-35 | |
ML17037A656 | 6 February 2017 | Cross Section 5-1, East Wall Trench 5, Plate 4-48 | |
ML17037A657 | 6 February 2017 | Cross Section 5-2, West Wall Trench 5, Plate 4-49 | |
ML17037A658 | 6 February 2017 | Stratigraphic Correlation Chart Borings T-3-1 Through T-3-10, Plate 5-2 | |
ML17037A659 | 6 February 2017 | Stratigraphic Correlation Chart Borings T-4-1 Through T-4-12, Plate 5-3 | |
ML17037A662 | 6 February 2017 | Structural Comparison of Fault Zone in Boring Series T-3, Plate 5-11 | |
ML17037A663 | 6 February 2017 | Structural Comparison of Fault Zone in Boring Series T-4, Plate 6-12 | |
ML17037A666 | 6 February 2017 | Relative Pollen Percentages, Spores and Miscellaneous Microfossil Abundance, Plate 1-3 | |
ML17037A682 | 6 February 2017 | Figure SI-23, Morristown Site Area | |
ML17037A683 | 6 February 2017 | Figure SI-24, Waddington Site Area | |
ML17037A686 | 6 February 2017 | Table 7.2-1 | |
ML17037A689 | 6 February 2017 | Figure 12.1-1, General Arrangement Reactor Building - Plans | |
ML17037A690 | 6 February 2017 | Figure 7.9 - 1A, Feedwater Control System. | |
ML17037A692 | 6 February 2017 | Figure 7.6-7, Rod Block Interlocks from Neutron Monitoring System | |
ML17037A694 | 6 February 2017 | Figure 7.4-10, Power Range Neutron Monitoring System Instrument Electrical Diagram | |
ML17037A696 | 6 February 2017 | Figure 7.4-2, Source Range Monitor/Intermediate Range Monitor Neutron Monitoring Unit | |
ML17037A697 | 6 February 2017 | Figure 7.3-10a, Residual Heat Removal System Piping and Instrumentation Diagram | |
ML17037A698 | 6 February 2017 | Figure 7.2-1a, Nuclear Boiler System Piping and Instrumentation Diagram | |
ML17037A701 | 6 February 2017 | Table 7.2-1 (Continued) | |
ML17037A702 | 6 February 2017 | Figure 7.1-1, Reactor Protection System (Schematic) |