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 Issue dateTitleTopic
ML23180A15129 June 2023LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3)Incorporated by reference
Exemption Request
ML21102A30715 April 2021OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor
ML21084A1232 April 2021Review Schedule for the NuScale Power, LLC, Topical Report Methodology for Establishing the Technical Basis for Plume Exposure Emergency Planning Zones, TR-0915-17772, Revision 2 (PROJ0769)
ML21050A43119 February 2021LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular ReactorProbabilistic Risk Assessment
Design basis earthquake
Exemption Request
Earthquake
Backfit
Fatality
ML20247J56411 September 2020Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application
ML20231A80428 August 2020Final Safety Evaluation Report for the NuScale Standard Plant Design
ML20224A46025 August 2020OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular ReactorProbabilistic Risk Assessment
ML20231A59825 August 2020OEDO-20-00285_NuScale Area of Focus - Boron RedistributionProbabilistic Risk Assessment
ML20210M89029 July 2020Area of Focus - Boron RedistributionAnticipated operational occurrence
Probabilistic Risk Assessment
ML20195A58713 July 2020LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular ReactorsFitness for Duty
Job Performance Measure
Operability Determination
Generic Fundamentals Examination
Earthquake
Power change
ML20195C76613 July 2020LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application
ML20192A32610 July 2020LLC, Submittal of Environmental Report: Revision Status
ML20198M3932 July 2020LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020
ML20174A3471 July 2020OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve PerformanceProbabilistic Risk Assessment
ML20184A2871 July 2020LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0
ML20181A43222 June 2020Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter)
ML20181A27022 June 2020Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
ML20171A73119 June 2020LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use
ML20198M39219 June 2020LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1Exemption Request
ML20157A2233 June 2020Letter to NuScale Requesting -A for TR-0716-50350
ML20150C51729 May 2020LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0Shutdown Margin
Anticipated operational occurrence
Probabilistic Risk Assessment
Flow Induced Vibration
ML20150C88129 May 2020LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0Shutdown Margin
Anticipated operational occurrence
Probabilistic Risk Assessment
Flow Induced Vibration
ML20150E17729 May 2020LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, Revision 0
ML20149M11928 May 2020LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33Exemption Request
ML20141L80420 May 2020LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4Safe Shutdown
Boric Acid
Shutdown Margin
High Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Water Inventory Control
Post Accident Monitoring
Probabilistic Risk Assessment
Surveillance Frequency Control Program
Open Phase Condition
Fuel cladding
ML20141L80820 May 2020LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3Anticipated operational occurrence
Hydrostatic
Incorporated by reference
Fuel cladding
ML20141L81620 May 2020LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3
ML20141M11420 May 2020LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3Anticipated operational occurrence
ML20141N01220 May 2020LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report
ML20141M76420 May 2020LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3
ML20141L78720 May 2020LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4Hot Short
Safe Shutdown
Unanalyzed Condition
Boric Acid
Time of Discovery
Shutdown Margin
High Radiation Area
Ultimate heat sink
Non-Destructive Examination
Mission time
Offsite Dose Calculation Manual
Fire Barrier
Stroke time
Anticipated operational occurrence
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Nondestructive Examination
Incorporated by reference
Missed surveillance
Pressure and Temperature Limits Report
Surveillance Frequency Control Program
Annual Radiological Environmental Operating Report
Process Control Program
Excess Flow Check Valve
Operability Determination
Earthquake
Power-Operated Valves
Power Operated Valves
Turbine Missile
Fuel cladding
Biofouling
Pressure Boundary Leakage
Fire Protection Program
Power change
Flow Induced Vibration
Unidentified leakage
Failure to Scram
ML20128J31618 May 2020OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring
ML20133K08812 May 2020LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0
ML20133J91411 May 2020LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0
ML20107F8491 May 2020OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design
ML20112F4551 May 2020LLC, Design Certification Application Phases 5 and 6 Review Status
ML20104A07927 April 2020OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology
ML20099H0808 April 2020LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0Safe Shutdown
Earthquake
Fatality
ML20098G2377 April 2020Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items
ML20097F1926 April 2020Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0
ML20094H6743 April 2020LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0Probabilistic Risk Assessment
ML20092L8991 April 2020LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4Safe Shutdown
Unanalyzed Condition
Boric Acid
Time of Discovery
Shutdown Margin
High Radiation Area
Ultimate heat sink
Non-Destructive Examination
Offsite Dose Calculation Manual
Fire Barrier
Stroke time
Anticipated operational occurrence
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Nondestructive Examination
Incorporated by reference
Finite Element Analysis
Missed surveillance
Pressure and Temperature Limits Report
Surveillance Frequency Control Program
Foreign Material Exclusion
Annual Radiological Environmental Operating Report
Process Control Program
Operability Determination
Spent Fuel Pool Instrumentation
Earthquake
Power-Operated Valves
Turbine Missile
Fuel cladding
Pressure Boundary Leakage
Pressure boundary leak
Fire Protection Program
Power change
Flow Induced Vibration
Unidentified leakage
Failure to Scram
ML20072M66830 March 2020Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content
ML20072H3339 March 2020LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0
ML20057D9006 March 2020Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant
ML20062F7265 March 2020Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter PublicTurbine Missile
ML20069A9634 March 2020LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0
ML20069A1774 March 2020LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0
ML20069A1574 March 2020LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0
ML20066G2803 March 2020LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0Severe Accident Management Guideline
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