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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023
LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3)
ML21102A3072021-04-15015 April 2021
OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor
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Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application
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Final Safety Evaluation Report for the NuScale Standard Plant Design
ML20224A4602020-08-25025 August 2020
OEDO-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 Reactor
ML20231A5982020-08-25025 August 2020
OEDO-20-00285_NuScale Area of Focus - Boron Redistribution
ML20210M8902020-07-29029 July 2020
Area of Focus - Boron Redistribution
ML20195A5872020-07-13013 July 2020
LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors
ML20195C7662020-07-13013 July 2020
LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application
ML20192A3262020-07-10010 July 2020
LLC, Submittal of Environmental Report: Revision Status
ML20198M3932020-07-0202 July 2020
LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020
ML20174A3472020-07-0101 July 2020
OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance
ML20184A2872020-07-0101 July 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0
ML20181A4322020-06-22022 June 2020
Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter)
ML20181A2702020-06-22022 June 2020
Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
ML20198M3922020-06-19019 June 2020
LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1
ML20171A7312020-06-19019 June 2020
LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use
ML20157A2232020-06-0303 June 2020
Letter to NuScale Requesting -A for TR-0716-50350
ML20150C5172020-05-29029 May 2020
LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0
ML20150E1772020-05-29029 May 2020
LLC - 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
ML20150C8812020-05-29029 May 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0
ML20149M1192020-05-28028 May 2020
LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33
ML20141L8082020-05-20020 May 2020
LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3
ML20141N0122020-05-20020 May 2020
LLC 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
ML20141M7642020-05-20020 May 2020
LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3
ML20141L7872020-05-20020 May 2020
LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4
ML20141L8162020-05-20020 May 2020
LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3
ML20141M1142020-05-20020 May 2020
LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3
ML20141L8042020-05-20020 May 2020
LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4
ML20128J3162020-05-18018 May 2020
OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring
ML20133K0882020-05-12012 May 2020
LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0
ML20133J9142020-05-11011 May 2020
LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0
ML20112F4552020-05-0101 May 2020
LLC, Design Certification Application Phases 5 and 6 Review Status
ML20107F8492020-05-0101 May 2020
OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design
ML20104A0792020-04-27027 April 2020
OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology
ML20099H0802020-04-0808 April 2020
LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0
ML20098G2372020-04-0707 April 2020
Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items
ML20097F1922020-04-0606 April 2020
Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0
ML20094H6742020-04-0303 April 2020
LLC 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 0
ML20092L8992020-04-0101 April 2020
LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4
ML20072M6682020-03-30030 March 2020
Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content
ML20072H3332020-03-0909 March 2020
LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0
ML20057D9002020-03-0606 March 2020
Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant
ML20062F7262020-03-0505 March 2020
Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public
ML20069A1572020-03-0404 March 2020
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0
ML20069A1772020-03-0404 March 2020
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0
ML20069A9632020-03-0404 March 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0
ML20066G2802020-03-0303 March 2020
LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0
ML20066G2882020-02-28028 February 2020
LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0
2023-06-29
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August 14, 2019 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE FOR NUSCALE POWER, LLC
Dear Mr. Bergman:
By letters to the U.S. Nuclear Regulatory Commission (NRC) included in the list below, NuScale Power, LLC (NuScale) requested that the information included within the letters, or as an enclosure to the letters, be withheld from public disclosure pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 2, Section 2.390.
Letter Number Subject Accession Affidavit and Date Number LO-0419-65333 NuScale Containment Leakage Integrity ML19149A298 AF-0419-65334 May 28, 2019 Assurance, TR-1116-51962-P, Revision 1 RAIO-0519-65732 Response to NRC Request for Additional ML19149A653 AF-0519-65734 May 29, 2019 Information No. 9466 (eRAI No. 9466) on the NuScale Topical Report, "Non-Loss of Coolant Accident Analysis Methodology,"
TR-0516-49416, Revision 1 LO-0519- 65737 NuScale Power, LLC Submittal of Turbine ML19151A834 AF-0519-65738 May 31, 2019 Missile Barrier Design Closure Plan Actions (Final Safety Analysis Report, Tier 2, Section 3.5.1.3)
RAIO-0519-65801 NuScale Power, LLC Supplemental ML19151A837 AF-0519-65802 May 31, 2019 Response to NRC Request for Additional Information No. 377 (eRAI No. 9380) on the NuScale Design Certification Application RAIO-0519-65799 NuScale Power, LLC Response to NRC ML19154A605 AF-0519-65800 June 03, 2019 Request for Additional Information No.
514 (eRAI No. 9645) on the NuScale Design Certification Application RAIO-0619-65808 NuScale Power, LLC Supplemental ML19154A622 AF-0619-65809 June 03, 2019 Response to NRC Request for Additional Information No. 202 (eRAI No. 8911) on the NuScale Design Certification Application L0-0519- 65780 NuScale Power, LLC Submittal of ML19156A055 AF-0519-65781 May 31, 2019 Presentation Materials Entitled "ACRS Full Committee Presentation, NuScale FSAR Chapter 19, Passive Safety System Reliability," PM-0619-65779-P, Revision 0
T. Bergman 2 Letter Number Subject Accession Affidavit and Date Number RAIO-0619-65847 NuScale Power, LLC Supplemental ML19157A326 AF-0619-65848 June 06, 2019 Response to NRC Request for Additional Information No. 232 (eRAI No. 9113) on the NuScale Design Certification Application LO-0419-65357 NuScale Power, LLC Submittal of ML19158A382 AF-0419-65356 June 7, 2019 Containment Vessel Ultimate Pressure Integrity, TR-0917-56119, Revision 1 L0-0619-65815 NuScale Power, LLC Supplemental ML19162A086 AF-0619-65816 June 05, 2019 Information in Support of the NRC Review of Topical Report "Loss-of-Coolant Accident Evaluation Model," TR-0516-49422 LO-0619-65912 NuScale Power, LLC Submittal of ML19164A145 AF-0619-65913 June 13, 2019 Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 1 RAIO-0619-65953 NuScale Power, LLC Response to NRC ML19168A249 AF-0619-65954 June 17, 2019 Request for Additional Information No.
9676 (eRAI No. 9676) on the NuScale Topical Report, "Improvements in Frequency Domain Soil-Structure-Fluid Interaction Analysis," TR-0118-58005, Revision 0 L0-0619-65987 NuScale Power, LLC Submittal of ML19172A097 AF-0619-65986 June 17, 2019 Presentation Materials Entitled "ACRS Subcommittee Presentation: NuScale Topical Report - Evaluation Methodology for Stability Analysis of the NuScale Power Module," PM-0619-65961-P, Revision 0 L0-0619-65993 NuScale Power, LLC Submittal of ML19172A101 AF-0619-65994 June 17, 2019 Presentation Materials Entitled "ACRS Subcommittee Presentation, NuScale FSAR Chapter 15, Transient and Accident Analyses," and Chapter 6.2.1, Containment Functional Design," PM-0619-65992-P, Revision 0 L0-0619-65930 NuScale Power, LLC Submittal of ML19172A099 AF-0619-65929 June 17, 2019 Presentation Materials Entitled "ACRS Subcommittee Presentation, NuScale FSAR Chapter 6, Emergency Core Cooling System Valve Figure Supplement for Closed Session," PM-0619-65927-P, Revision 0 RAIO-0619-66063 NuScale Power, LLC Supplemental ML19176A580 AF-0619-66064 June 25, 2019 Response to NRC Request for Additional Information No. 232 (eRAI No. 9113) on the NuScale Design Certification Application L0-0619-66059 NuScale Power, LLC Submittal of ML19182A046 AF-0619-66060 June 27, 2019 Presentation Materials titled "TF-3 Modal Demonstration Testing and SIET Tour,"
PM-0619-66058-P, Revision 0 The affidavits state that the submitted information should be considered exempt:
T. Bergman 3 (a) The information sought to be withheld from public disclosure is owned by NuScale and has been held in confidence by NuScale; (b) The information sought to be protected is not available to the public to the best of your knowledge and belief; and (c) The information is of the type that would customarily be held in confidence by NuScale. Public disclosure of this information is likely to cause harm to NuScale because it would allow contractors, vendors, and competitors to understand the competitive position of NuScale.
The NRC staff reviewed your application and the material in accordance with the requirements of 10 CFR 2.390. Based upon the statements in the affidavit, we have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure. Therefore, the version of the submitted information marked as proprietary will be withheld from public disclosure pursuant to 10 CFR 2.390(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, the NRC staff may send copies of this information to our consultants working in this area. The NRC staff will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future, such that the information could then be made available for public inspection, you should promptly notify the NRC staff. You also should understand that the NRC staff may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC staff makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions regarding this matter, I may be reached at (301) 415-0546 or via e-mail at Gregory.Cranston@nrc.gov.
Sincerely,
/RA/
Gregory Cranston, Senior Project Manager Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors Docket No.52-048 cc: NuScale Power LLC Listserv
ML19226A234 *via email NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DLSE/LB1: PM NAME GCranston MMoore* GCranston (signed)
DATE 08/14/2019 8/14/2019 08/14/2019