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RAIO-0118-57981, LLC Response to NRC Request for Additional Information No. 278 (Erai No. 9123) on the NuScale Design Certification Application
PMNS20180545, Design Certification Review Discussions
PMNS20180524, Design Certification Review Discussions
PMNS20180523, Design Certification Review Discussions - Response to RAI 9092, 9196 and 9128
PMNS20180496, Design Certification Review Discussions
PMNS20180543, Design Certification Review Discussions
PMNS20180542, Design Certification Review Discussions
PMNS20180548, Design Certification Review Discussions
PMNS20180547, Design Certification Review Discussions
PMNS20180541, Design Certification Review Discussions
PMNS20180196, Design Certification Review Discussions
PMNS20180497, Design Certification Review Discussions
PMNS20180498, Design Certification Review Discussions - Response to RAI 9335 Chapter 5
PMNS20180194, Public Meeting Conference Call - to Discuss Application of ASME Code Requirements to the NuScale Design
PMNS20180191, Design Certification Review Discussions
PMNS20180188, Design Certification Review Discussions
PMNS20180187, Design Certification Review Discussions - Steam Generator
PMNS20180182, Design Certification Review Discussions
PMNS20180183, Design Certification Review Discussions
PMNS20180180, Design Certification Review Discussion Response to RAI 8858 (Steel Containment) and RAI 8934 (Seismic System Analysis)
PMNS20180181, Design Certification Review Discussions
PMNS20180139, Design Certification Review Discussions
PMNS20171500, Design Certification Review Discussions
PMNS20171499, Design Certification Review Discussions
PMNS20180052, Design Certification Review Discussions
PMNS20180012, Design Certification Review Discussions
PMNS20180008, Design Certification Review Discussions
PMNS20171498, Design Certification Review Discussions
PMNS20180055, Design Certification Review Discussions
PMNS20171497, Design Certification Review Discussions
PMNS20180031, Design Certification Review Discussions
PMNS20180013, Design Certification Review Discussions
PMNS20171503, Design Certification Review Discussions
PMNS20180007, Design Certification Review Discussions
RAIO-0418-59703, LLC - Response to NRC Request for Additional Information No. 388 (Erai No. 9220) on the NuScale Design Certification Application
RAIO-0418-59692, LLC - Response to NRC Request for Additional Information No. 379 (Erai No. 9381) on the NuScale Design Certification Application
RAIO-0418-59635, LLC Response to NRC Request for Additional Information No. 382 (Erai No. 9402) on the NuScale Design Certification Application
RAIO-0518-59812, LLC - Submittal of Response to NRC Request for Additional Information No. 380 (Erai No. 9394) on the NuScale Design Certification Application
RAIO-0518-59779, LLC Response to NRC Request for Additional Information No. 389 (Erai No. 9414) on the NuScale Design Certification Application
RAIO-0418-59516, LLC Response to NRC Request for Additional Information No. 390 (Erai No. 9371) on the NuScale Design Certification Application
RAIO-0418-59505, LLC Response to NRC Request for Additional Information No. 381 (Erai No. 9397) on the NuScale Design Certification Application
RAIO-0917-55893, LLC Response to NRC Request for Additional Information No. 97 (Erai No. 8878) on the NuScale Design Certification Application
RAIO-0917-56027, LLC Response to NRC Request for Additional Information No. 99 (Erai No. 8905) on the NuScale Design Certification Application
RAIO-0418-59751, LLC - Response to NRC Request for Additional Information No. 387 (Erai No. 9398) on the NuScale Design Certification Application
RAIO-0418-59636, LLC Response to NRC Request for Additional Information No. 372 (Erai No. 9364) on the NuScale Design Certification Application
RAIO-0318-59129, LLC Supplemental Response to NRC Request for Additional Information No. 239 (Erai No. 9075) on the NuScale Design Certification Application
RAIO-0418-59509, LLC Response to NRC Request for Additional Information No. 369 (Erai No. 9329) on Design Certification Application
RAIO-0418-59696, LLC - Response to NRC Request for Additional Information No. 308 (Erai No. 9261) on the NuScale Design Certification Application
RAIO-0518-59982, LLC Response to NRC Request for Additional Information No. 467 (Erai No. 9382) on the NuScale Design Certification Application
PMNS20180015, Design Certification Review Discussions on NuScales Response to RAI 8963 (Foundations), 8901 (Reactor Pressure Vessel Internals)
RAIO-1217-57684, LLC Response to NRC Request for Additional Information No. 277 (Erai No. 8747) on the NuScale Design Certification Application
RAIO-1217-57723, LLC Response to NRC Request for Additional Information No. 240 (Erai No. 8817) on the NuScale Design Certification Application
RAIO-1217-57654, LLC Response to NRC Request for Additional Information No. 262 (Erai No. 8847) on the NuScale Design Certification Application
RAIO-0118-58142, LLC Response to NRC Request for Additional Information No. 313 (Erai No. 9312) on the NuScale Design Certification Application
RAIO-0817-55698, LLC Response to NRC Request for Additional Information No. 82 (Erai No. 8879) on the NuScale Design Certification Application
RAIO-1117-57265, LLC Supplemental Response to NRC Request for Additional Information No. 90 (Erai No. 8758) on the NuScale Design Certification Application
RAIO-1217-57779, LLC Response to NRC Request for Additional Information No. 225 (Erai No. 9058) on the NuScale Design Certification Application
RAIO-1217-57889, LLC Response to NRC Request for Additional Information No. 279 (Erai No. 9131) on the NuScale Design Certification Application
RAIO-0917-56030, LLC Response to NRC Request for Additional Information No. 100 (Erai No. 8906) on the NuScale Design Certification Application
RAIO-0418-59693, LLC - Response to NRC Request for Additional Information No. 378 (Erai No. 9372) on the NuScale Design Certification Application
RAIO-1017-56884, LLC Response to NRC Request for Additional Information No. 220 (Erai No. 8805) on the NuScale Design Certification Application
RAIO-1217-57887, LLC Response to NRC Request for Additional Information No. 237 (Erai No. 9002) on the NuScale Design Certification Application
RAIO-0418-59511, LLC - Response to NRC Request for Additional Information No. 391 (Erai No. 9370) on the NuScale Design Certification Application
RAIO-0917-55953, LLC Response to NRC Request for Additional Information No. 127 (Erai No. 8909) on the NuScale Design Certification Application
PMNS20241183, Virtual - 2024 Nuclear Regulatory Commission (NRC) and Boiling Water Reactor Owners Group (BWROG) Executive Oversight Meeting
PMNS20240936, Clarification Call on Electric Power Research Institute Responses to Requests for Additional Information 8 & 9 to BWRVIP-100, Revision 2: Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internals Compo
PMNS20221127, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding the Passive Core Cooling System (Pccs) to Support the Construction Permit for the Holtec SMR-160 Design
PMNS20221077, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding Technical Specifications to Support the Construction Permit for the SMR-160 Design
PMNS20220967, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding a Potential Loss-of-Coolant Accident Exemption to Support the Construction Permit for the SMR-160 Design
PMNS20220862, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding a Potential Exemption Related to Closed System Isolation Valves to Support the Construction Permit for the SMR-160 Design
PMNS20220861, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding a Potential Exemption to Containment Heat Removal Testing to Support the Construction Permit for the SMR-160 Design
PMNS20220966, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding Reactivity Control Aspects of the Control Rod Drive System to Support the Construction Permit for the SMR-160 Design
PMNS20220859, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding Spent Fuel Makeup Compliance to Support the Construction Permit for the SMR-160 Design
PMNS20220961, Preapplication Meeting with SMR, LLC (a Holtec International Company) Regarding Its White Paper on Instrumentation and Control Architecture to Support the Construction Permit for the Holtec SMR-160 Design
PMNS20220860, Preapplication Meeting with Holtec International, LLC, to Discuss a White Paper on Potential Exemptions to the Regulations Related to the Loss-of-Coolant Accident Analyses to Support the Construction Permit for the Holtec SMR-160 Design
PMNS20220856, Preapplication Meeting with Holtec International, LLC, Regarding Loss-of-Coolant Analyses to Support the Construction Permit for the Holtec SMR-160 Design
PMNS20220476, Preapplication Meeting with NuScale Power, LLC, Regarding the NuScale Cybersecurity Methodology to Support the Carbon Free Power Project (CFPP) Combined License (COL) Application
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
RS-19-019, Response to Request for Additional Information Regarding Relief Request 13R-15
RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RS-20-011, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
RS-20-012, Response to Request for Additional Information Regarding Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval
RS-19-052, Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High
RS-19-053, Response to NRC Regulatory Issue Summary 2019-02, Preparation and Scheduling of Operator Licensing Examinations
RS-19-051, Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies
RS-19-066, Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency
RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
RS-19-082, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS)
RS-19-087, License Amendment Request and 10 CFR 50.12 Exemption Request for Alternate Material Properties Bases
RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-19-094, Supplemental Response to Reqeust for Additional Information Regarding Application to Revise Plants Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Rev. 2
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions
TSTF-19-13, Technical Specifications Task Force - Updated TSTF Membership and Distribution
RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
TSTF-19-14, Technical Specifications Task Force - TSTF Response to NRC Questions on TSTF-582, RPV WIC Enhancements
RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)
RS-20-024, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections
RS-20-041, Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations
RS-20-057, Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections
RS-20-056, Re. Ginna, Withdrawal of Relief Request for Alternative Frequency to Supplemental Indication
TSTF-20-01, Transmittal of TSTF-IG-20-02, Guidance on Evaluating One-Time Surveillance Frequency Changes Under the Surveillance Frequency Control Program (TSTF-425M SFCP)
RS-20-043, 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-20-022, Response to Request for Additional Information Regarding License Amendment Request to Revise Braidwood Station Technical Specifications 3.7.9, Ultimate Heat Sink (Uhs)
TSTF-20-04, Technical Specifications Task Force - Transmittal of TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections
RS-20-087, Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink
RS-20-080, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2)
RS-20-089, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-20-079, Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections
RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating
RS-20-104, Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink
RS-20-133, Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69
RS-20-135, Supplement Regarding Request to Withhold Information Related to License Amendment Request to Revise Technical Specification 3.7.3, Ultimate Heat Sink
RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)
RS-20-150, Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements
RS-20-148, Subsequent Request for Exemption from Part 26 Work Hours Requirements
RS-20-144, Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, IV.F.2.b
RS-20-146, Request to Withhold Previously Submitted Exercise Scenario from Public Release
RS-20-147, Response to Request for Additional Information Related to Exemption from Part 26 Requirements
RS-20-143, Response to Request for Additional Information Regarding Application to Revise Technical Specifications 3.8.1, AC Sources- Operating
RS-20-152, Supplemental Information Regarding Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, IV.F.2.b
RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18
RS-21-019, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections
RS-21-008, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2)
TSTF-21-01, Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
RS-21-011, Subsequent Request for Exemption from Part 26 Work Hours Requirements
RS-21-027, Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.65
RS-21-026, Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.65
RS-21-020, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RS-21-028, Fitness for Duty Performance Data Reports - Annual 2020
RS-21-035, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs
RS-21-034, Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair
RS-21-043, Supplemental Information Regarding Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
RS-21-042, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)
RS-21-046, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-21-045, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)
RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations
RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.
RS-21-057, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections
RS-20-085, Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements
RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology
RS-19-100, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended
RS-16-239, Supplement to RS-16-239: Revision to Exelon Generation Company, LLC Commitment Relating to Large Break Loss of Coolant Accident (LBLOCA) Analysis with an NRC Approved Emergency.
RS-19-084, Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval
RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections
TSTF-21-04, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
TSTF-21-02, Submittal for Information of TSTF-GG-21-01, Technical Requirements Manual and Operational References (TRM) Format and Content Guideline
TSTF-20-07, TSTF Response to NRC Questions on TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections, and Submittal of Revision 1
TSTF-20-08, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirement