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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
US600 DC and SDA 50.46 Exemption - Letter
ML23180A1512023-06-29029 June 2023
LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3)
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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
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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
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Area of Focus - Boron Redistribution
ML20195A5872020-07-13013 July 2020
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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
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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
ML20181A2702020-06-22022 June 2020
Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
ML20181A4322020-06-22022 June 2020
Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (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
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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
ML20141L8162020-05-20020 May 2020
LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3
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
ML20141M1142020-05-20020 May 2020
LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3
ML20141L8042020-05-20020 May 2020
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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
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OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design
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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 NuScales 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
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
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
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
ML20066G2802020-03-0303 March 2020
LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0
2024-03-28
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June 5, 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-0129-64509 Human Factors Engineering Task Analysis ML19119A394 AF-0219-54510 April 29, 2019 Results Summary Report, RP-0316-17616-P, Revision 2 LO-0219-64511 "Human Factors Engineering Program ML19119A343 AF-0219-54512 April 29, 2019 Management Plan, RP-0914-8534-NP, Revision 5 LO-0219-64513 Human Factors Engineering Verification ML19119A372 AF-0219-54514 April 29, 2019 and Validation Implementation Plan, RP-0914-8543-P, Revision 5 LO-02190-64505 Human-System Interface Design Results ML19119A398 AF-0219-64506 April 24, 2019 Summary Report, RP-0316-17619-P, Revision 2, Proprietary Version RAIO-0419-65386 NuScale Supplemental Response to NRC ML19121A600 AF-0419-65387 May 1, 2019 Request for Additional Information eRAI No.
8911, Proprietary LO-0519-65510 Changes to NuScale Final Safety Analysis ML19129A278 AF-0519-65613 May 8, 2019 Report Tier 2 Section 6.2, Containment Systems, and Technical Report TR-0516-49084, Containment Response Analysis Methodology, Proprietary Version LO-0219-64504 Human-System Interface Style Guide, ES- ML19133A296 AF-0219-64503 May 2, 2019 0304-1381-P, Revision 3, Proprietary Version LO-0219-64507 Concept of Operations, RP-0215-10815- ML19133A293 AF-0219-64508 May 9, 2019 P, Revision 3, Proprietary Version LO-0519-65575 NuScale Instrument Setpoint Methodology ML19136A411 AF-0519-65576 May 16, 2019 Technical Report, TR-0616-49121-P, Revision 2, Proprietary Version
T. Bergman 2 LO-0519-65561 Nuclear Steam Supply System Advanced ML19137A361 AF-0519-65562 May 16, 2019 Sensor Technical Report, TR-0316-22048, Revision 2, Proprietary Version RAIO-0519-65656 "Methodology for Establishing the Technical ML19142A460 AF-0519-65678 May 22, 2019 Basis for Plume Exposure Emergency Planning Zones at NuScale Small Modular Reactor Plant Sites," TR-0915-17772, Revision 1 RAIO-0519-65643 NuScale Power, LLC Supplemental ML19143A206 AF-0519-65644 May 22, 2019 Response to NRC Request for Additional Information No. 466 (eRAI No. 9482) on the NuScale Design Certification Application The affidavits state that the submitted information should be considered exempt:
(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.
T. Bergman 3 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 Prosanta Chowdhury for/
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
ML19154A575 *via email NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA* NRO/DLSE/LB1: PM NAME GCranston MMoore GCranston (PChowdhury for)
DATE 5/31/2019 5/28/2019 6/5/2019