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ML24018A20118 January 2024Attachment 2 (Non-Proprietary): HI-2200343-A, Topical Report for Allowance of Heat Load Patterns in HI-Storm 100 and HI-Storm FW Systems
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update15 December 2023Quality Assurance Topical Report (FPL-1) Revision 30 UpdateFitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Post Accident Monitoring
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Aging Management
Process Control Program
Operability Determination
Safeguards Contingency Plan
License Renewal
Maintenance Rule Program
Fire Protection Program
Grace period
Power Uprate
ML23334A19230 November 2023HI-2210161-A, Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage SystemsFuel cladding
ML23310A1226 November 2023LLC, Submittal of Supplemental Topical Report Entitled Statistical Subchannel Analysis Methodology, Supplement 1 to TR-0915-17564-P-A, Revision 2, Subchannel Analysis Methodology, TR-108601-P, Revision 4Affidavit
ML23285A34112 October 2023LLC Submittal of Supplemental Topical Report Entitled Statistical Subchannel Analysis Methodology, Supplement 1 to TR-0915-17564-P-A, Revision 2, Subchannel Analysis Methodology, TR-108601-P, Revision 3
ML23283A3369 October 2023LLC Submittal of Topical Report Entitled NuScale US460 Fuel Storage Rack Design Topical Report, TR-145417-P, Revision 0
ML23265A00422 September 2023NRC 898 Revised Completeness Determination for NuScale Topical Report TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0
ML23265A14522 September 2023LOCA Revised NRC Form 898 for Resource Estimate
RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals21 September 2023Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel InternalsSafe Shutdown
Unanalyzed Condition
Non-Destructive Examination
Nondestructive Examination
Functionality Assessment
Aging Management
Stress corrosion cracking
Eddy Current Testing
License Renewal
Subsequent License Renewal
EVT-1
Power change
Power Uprate
Measurement Uncertainty Recapture
Thermal fatigue
ML23198A24417 July 2023LLC Submittal of Topical Report Methodology for the Determination of the Onset of Density Wave Oscillations (Dwo), TR-131981, Revision 1
L-MT-23-030, Subsequent License Renewal Application Supplement 34 July 2023Subsequent License Renewal Application Supplement 3Hydrostatic
Fire Protection Program
ML23159A2308 June 2023Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019)EVT-1
CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out1 June 2023Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal22 May 2023NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual SubmittalFitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Post Accident Monitoring
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Aging Management
Process Control Program
Operability Determination
Safeguards Contingency Plan
License Renewal
Maintenance Rule Program
Fire Protection Program
Grace period
Power Uprate
ML23104A37913 April 2023HI-2210161, Revision 4, Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage SystemsFuel cladding
L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)28 March 2023Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)Hydrostatic
Pressure and Temperature Limits Report
ML23058A01217 March 2023Topical Report TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Rev. 0
ML23069A01010 March 2023Withholding Determination - NRC Form 897 - for NuScale Topical Report TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0
ML23181A15328 February 2023Attachment 3 - LAS-FLU-001-R-005, Revision 1, LaSalle County Generating Station Unit 1 Reactor Pressure Vessel Fluence Evaluation - End of Cycle 18Hydrostatic
ML23181A15428 February 2023Attachment 4 - LAS-FLU-001-R-002, Revision 1, LaSalle County Generating Station Unit 2 Reactor Pressure Vessel Fluence Evaluation - End of Cycle 18Hydrostatic
ML23058A22627 February 2023NRR E-mail Capture - (External_Sender) Re Transmittal of NRC Staff Draft Safety Evaluation Regarding Kairos Power Graphite Materials Qualification Topical Report
ML23032A4521 February 2023Attachment 2: HI-2210161, Revision 3, Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage SystemsFuel cladding
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-1031 January 2023Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10Safe Shutdown
Fitness for Duty
Shutdown Margin
Non-Destructive Examination
Offsite Dose Calculation Manual
Commercial Grade Dedication
Safe Shutdown Earthquake
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Aging Management
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Operability Determination
License Renewal
Maintenance Rule Program
Fire Protection Program
CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A30 January 2023Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-AFire Protection Program
ML23008A0028 January 2023LLC, Submittal of Topical Report Loss-of-Coolant Accident Evaluation Model, TR-0516-49422, Revision 3
ML23005A3085 January 2023LLC, Submittal of Topical Report Extended Passive Cooling and Reactivity Control Methodology, TR-124587, Revision 0Safe Shutdown
Boric Acid
Ultimate heat sink
Anticipated operational occurrence
ML23005A3055 January 2023LLC Submittal of Topical Report Non-Loss-of-Coolant Accident Analysis Methodology, TR-0516-49416, Revision 4Anticipated operational occurrence
ML23058A22523 December 2022NRR E-mail Capture - (External_Sender) Re Transmittal of NRC Staff Draft Safety Evaluation Regarding Kairos Power Metallic Material Qualification Topical Report
ML22349A65814 December 2022NEI Responses to NRC Comments on Draft NEI 99-01, Revision 7, Developments of EALs for Non-Passive Reactors
ML22347A2848 December 2022GE-Hitachi Nuclear Energy Americas, LLC, Accepted Version of NEDO-11209-A Revision 17, GE Hitachi Nuclear Energy Quality Assurance Program DescriptionCoatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Pandemic
COVID-19
Liquid penetrant
Grace period
ML22238A10125 August 2022Clinch River, Topical Report Quality Assurance Program Description for New Nuclear ProgramShutdown Margin
Commercial Grade Dedication
Safe Shutdown Earthquake
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
License Renewal
Fire Protection Program
Grace period
L-2022-082, NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC, Quality Assurance Topical Report FPL-1, Revision 2823 May 2022NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC, Quality Assurance Topical Report FPL-1, Revision 28Fitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Post Accident Monitoring
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Aging Management
Process Control Program
Operability Determination
Safeguards Contingency Plan
License Renewal
Maintenance Rule Program
Fire Protection Program
Grace period
Power Uprate
L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 225 April 2022NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2Fitness for Duty
Offsite Dose Calculation Manual
Commercial Grade Dedication
Post Accident Monitoring
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Annual Radiological Environmental Operating Report
Process Control Program
Fire Protection Program
Grace period
ML22038A9437 February 2022International, HI-2210161, Revision 2, Radiological Fuel Qualification Methodology for Dry Storage SystemsFuel cladding
ML22021B56219 January 2022Enclosure 1 - HI-2210161-R2-Draft-0-01-18-2022 Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage SystemsFuel cladding
ML21336A45017 December 2021Transmittal Email of NRC 896 Form for U.S. Nuclear Regulatory Commission Staff -A Verification of the HI-2200343, Rev 2, Topical Report for Allowance of Heat Load Patterns in HI-STORM 100 and Hi STORM FW (Flood Wind) Systems
L-2021-234, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 Update15 December 2021NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 UpdateFitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Post Accident Monitoring
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Aging Management
Process Control Program
Operability Determination
Safeguards Contingency Plan
License Renewal
Maintenance Rule Program
Fire Protection Program
Grace period
Power Uprate
ML22067A15130 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 1
L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D30 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D
ML22067A14930 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Cover Through Section 5
ML22067A15030 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Section 6 Through Appendix B
ML22067A15430 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 4
ML22067A15230 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 2
ML22067A15330 November 2021WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 3
ML21312A4785 November 2021NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis DevelopmentProbabilistic Risk Assessment
Turbine Missile
ML23059A2652 November 2021NRR E-mail Capture - Preliminary Questions on Revision 1 of Kairos Graphite Materials Qualification Topical Report
ML21292A32731 October 2021Oklo Inc., Performance-Based Licensing Methodology Topical, Revision 1Probabilistic Risk Assessment
ML21302A14729 October 2021Attachment 2: HI-2200343-A Topical Report for Allowance of Heat Load Patterns in HI-STORM and HI-STORM FW Systems (Non-Proprietary Version)Unanalyzed Condition
Time to boil
Fuel cladding
Environment Report
ML22332A45612 October 2021Attachment 8 - LaSalle County Generating Station Unit 1 Fluence Methodology Report, LAS-FLU-001-R010, Rev. 0 (Non-Proprietary Version)Hydrostatic
ML21278B0985 October 2021Oklo, Inc. - Maximum Credible Accident MethodologyProbabilistic Risk Assessment
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