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 Issue dateTitleTopic
NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)4 December 2023Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)Weld Overlay
Nondestructive Examination
VT-2
Liquid penetrant
Through-Wall Leakage
Dissimilar Metal Weld
DM weld
ML23235A17223 August 2023Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .4 August 2023Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .Safe Shutdown
High winds
Reactor Vessel Water Level
Mission time
Tornado Missile
Internal Flooding
Probabilistic Risk Assessment
Operator Manual Action
FLEX
Tornado Missile Protection
Surveillance Frequency Control Program
Scram Discharge Volume
Large early release frequency
Tornado Missile Risk Evaluator
Flooding Focused Evaluation
Maintenance Rule Program
Offsite Circuit
Continuous fire watch
Scaffolding
NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)27 March 2023Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)Weld Overlay
Dissimilar Metal Weld
ML23055A28424 February 2023Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried PipingFitness for Duty
Ultimate heat sink
Non-Destructive Examination
Safe Shutdown Earthquake
Coatings
Operating Basis Earthquake
Finite Element Analysis
Aging Management
Foreign Material Exclusion
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits30 June 2022Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air SuitsMururoa
ML22178A17227 June 2022Long Term Coupon Surveillance ProgramAging Management
ML22147A17827 May 2022Owner'S Activity Report (Form OAR-1) for the Calvert Cliffs Nuclear Power Plant Unit 1 Spring 2022 Refueling OutageBoric Acid
Moisture barrier
ML21350A11416 December 2021Annual Commitment Change Notification
ML21316A05112 November 2021Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational ProjectionsEVT-1
ML21263A18620 September 2021Proposed Alternative Concerning Pressure Testing of ASME Section XI Class 2 Portions of the Auxiliary Feedwater SystemSafe Shutdown
VT-2
Through-Wall Leakage
RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections1 September 2021R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius SectionsFinite Element Analysis
Aging Management
ML21210A32530 July 2021Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report
RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld12 May 2021Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel WeldHydrostatic
VT-2
Finite Element Analysis
ML21077A18018 March 202110 CFR 50.46 Annual Report and 30-day Report for Framatome'S Protect Enhanced Accident Tolerant Fuel (Eatf) Lead Test Assembly (LTA)
ML21013A53013 January 2021Reactor Vessel Level Monitoring System Special Report
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping4 January 2021Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel PipingNondestructive Examination
ML20303A17523 October 2020Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
ML20280A5086 October 2020Submittal of Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection RequirementsIncorporated by reference
Fuel cladding
ML20265A19821 September 2020R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications for Steam Generator Tube Inspection FrequencyAnticipated operational occurrence
Weld Overlay
Locked High Radiation Area
Pandemic
COVID-19
ML20190A1488 July 2020FAQ 20-01 NMP Scram Final ApprovedUltimate heat sink
ML20100F6829 April 2020Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld IndicationWeld Overlay
Dissimilar Metal Weld
ML20034E3467 February 2020Review of the Spring 2019 Steam Generator Tube Inspection Report
ML19347A77912 December 2019License Amendment Request to Utilize Accident Tolerant Fuel Lead Test AssembliesShutdown Margin
Anticipated operational occurrence
Fuel cladding
ML19228A02315 August 2019Proposed Alternative to Utilize Code Case N-879
ML19072A09611 March 2019Information Regarding Dissimilar Metal Weld 2-CV-2005-30 Flaw Characteristic and Repair Weld OverlayWeld Overlay
Hydrostatic
Design basis earthquake
Earthquake
Dissimilar Metal Weld
NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.7 December 2018Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.Water Inventory Control
Surveillance Frequency Control Program
MELLLA
NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...20 August 2018Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...Ultimate heat sink
Tornado Missile
FLEX
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Battery sizing
Hardened vent
ML18018A96518 January 2018Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action PlanEarthquake
ML18018B01218 January 2018Semi-Annual Radioactive Effluent Release Report July-December 1999Grab sample
Offsite Dose Calculation Manual
Process Control Program
Tritium
ML18018B29118 January 2018Pipe Crack Task Force ReportNon-Destructive Examination
Grab sample
Hydrostatic
Liquid penetrant
Through-Wall Leak
ML18018B29218 January 2018Appendix a, Justification for Continued Operation, Component Review Summary SheetSafe Shutdown
Reactor Vessel Water Level
Scram Discharge Volume
ML17345A99021 December 2017R. E. Ginna Nuclear Power Plant Flood Hazard Mitigation Strategies AssessmentHigh winds
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Flood Hazard Mitigation Strategies Assessment
ML17324B36920 December 2017Flood Hazard Mitigation Strategies AssessmentInternal Flooding
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Flood Hazard Mitigation Strategies Assessment
ML17251A04520 September 2017- Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088)Safe Shutdown
Internal Flooding
Hydrostatic
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
ML17214A11827 July 2017Transmittal of 2017 Owner'S Activity Report for the Plant
ML17109A36513 April 2017Pressure and Temperature Limits ReportHydrostatic
Pressure and Temperature Limits Report
ML17079A38424 March 2017Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections
ML17037A6866 February 2017Table 7.2-1
ML17037A7036 February 2017Table 7.2-1 (Cont'D)
ML17027A01627 January 201710 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors
RS-16-181, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal9 November 2016Mitigating Strategies Flood Hazard Assessment (Msfha) SubmittalBoric Acid
Shutdown Margin
Ultimate heat sink
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2 November 2016High Frequency Supplement to Seismic Hazard Screening ReportSafe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Earthquake
ML16231A45230 August 2016Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events)FLEX
Fukushima Dai-Ichi
Earthquake
Power Operated Valves
Hardened vent
ML16223A85325 August 2016Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents)Ultimate heat sink
FLEX
Fukushima Dai-Ichi
Earthquake
Hardened vent
RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)14 June 2016Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)Spent Fuel Pool Instrumentation
ML16160A0948 June 2016ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004)
ML16061A01626 February 2016ISFSI - Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72-48Tornado Missile
ML16057A00225 February 2016Report Concerning Dissimilar Metal Weld Flaw in Pressurizer Safety Relief Nozzle-to-Safe-End WeldWeld Overlay
Finite Element Analysis
Dissimilar Metal Weld
DM weld
ML16076A35224 February 2016Plants, Units 1 and 2 - E-mail Re. Draft Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzel to Safe End WeldFinite Element Analysis
Dissimilar Metal Weld
DM weld