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Category:Legal-Affidavit
MONTHYEARML25027A3932025-01-27027 January 2025 LLC, Submittal of Sgfiv Flow Testing Report Summary ML25023A2142025-01-23023 January 2025 LLC, Submittal of NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-121353, Revision 2 ML25021A1532025-01-21021 January 2025 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML25021A2172025-01-21021 January 2025 Nuscale Power, LLC - Response to NRC Response to Request for Additional Information No. 037 (RAI-10357-R1) on the Nuscale Standard Design Approval Application ML25017A3912025-01-17017 January 2025 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML25016A3002025-01-16016 January 2025 LLC, Response to NRC Request for Additional Information No. 008 (RAI-10081 R1) on the NuScale Standard Design Approval Application ML25016A1522025-01-16016 January 2025 LLC, Response to NRC Request for Additional Information No. 018 (RAI-10142 R1) on the NuScale Standard Design Approval Application ML25014A1562025-01-14014 January 2025 LLC, Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML25009A0022025-01-0909 January 2025 LLC - Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML25009A0192025-01-0909 January 2025 LLC, Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Closed Session) Loss-of-Coolant Accident Topical Report and High Impact Technical Issue Status PM-177841, Revision 0 ML25009A0062025-01-0909 January 2025 LLC, Responses to NRC Request for Additional Information No. 039 (RAI-10359 R1) on the NuScale Standard Design Approval Application ML24354A1602024-12-19019 December 2024 LLC, Response to NRC Request for Additional Information No. 027 (RAI-10189 R1) on the NuScale Standard Design Approval Application ML24354A1312024-12-19019 December 2024 LLC, Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML24353A2182024-12-18018 December 2024 LLC, Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24353A2522024-12-18018 December 2024 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML24348A1302024-12-13013 December 2024 LLC, Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24348A1132024-12-13013 December 2024 Nuscale Power, LLC - Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24346A1312024-12-11011 December 2024 LLC Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24344A0892024-12-0202 December 2024 Nuscale Power, LLC - Submittal of Supplemental Information in Support of NRC Review of Nuscale Topical Reports Associated with the Standard Design Approval Application ML24327A0362024-11-22022 November 2024 LLC Submittal of US460 NuScale Power Module Seismic Analysis, TR-121515, Revision 1 ML24327A1492024-11-22022 November 2024 LLC, Responses to NRC Request for Additional Information No. 024 (RAI-10185 R1) on the NuScale Standard Design Approval Application ML24326A3282024-11-21021 November 2024 LLC, Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24325A5932024-11-20020 November 2024 LLC, Response to NRC Request for Additional Information No. 036 (RAI-10350 R1) on the NuScale Standard Design Approval Application ML24313A0662024-11-0808 November 2024 LLC - Response to NRC Request for Additional Information No. 015 (RAI-10133 R1) on the NuScale Standard Design Approval Application ML24313A1212024-11-0808 November 2024 LLC - Response to NRC Request for Additional Information No. 020 (RAI-10150 R1) on the NuScale Standard Design Approval Application ML24312A4012024-11-0707 November 2024 LLC, Submittal of Pipe Rupture Hazards Analysis, TR-121507, Revision 1 ML24303A2482024-10-29029 October 2024 LLC Submittal of Pressure and Temperature Limits Methodology, TR-130877, Revision 1 ML24296A4702024-10-22022 October 2024 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-121353, Revision 1 ML24281A0202024-10-0707 October 2024 LLC, Response to NRC Request for Additional Information No. 023 (RAI-10177 R1) on the NuScale Standard Design Approval Application ML24274A1532024-09-30030 September 2024 LLC Submittal of NuScale Containment Leakage Integrity Assurance, TR-123952, Revision 1 ML24243A0092024-08-30030 August 2024 LLC, Submittal of NuScale Power Module Short-Term Transient Analysis, TR-121517, Revision 1 ML24240A1412024-08-27027 August 2024 LLC - Response to NRC Request for Additional Information No. 16 (RAI-10134 R1) on the NuScale Standard Design Approval Application ML24239A8452024-08-26026 August 2024 LLC, Submittal of NuScale Technical Report, Fluence Calculation Methodology and Results, TR-118976, Revision 1 ML24233A2392024-08-20020 August 2024 LLC, Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Closed Session) High Impact Technical Issues Discussion, PM-172561, Revision 0 ML24222A5282024-08-0909 August 2024 LLC, Submittal of NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-121354, Revision 1 ML24228A2422024-08-0606 August 2024 LLC, Submittal of Supplemental Information in Support of Review of TR-131981-P, Methodology for the Determination of the Onset of Density Wave Oscillations (Dwo), Revision 1, Audit Question A-DWO.LTR-127 ML24215A0012024-08-0202 August 2024 LLC, Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24213A3162024-07-31031 July 2024 LLC, Submittal of NuScale Technical Report, NuScale US460 Statistical Subchannel Critical Heat Flux Analysis Probabilistic Uncertainties, TR-169856, Revision 0 ML24205A1562024-07-23023 July 2024 LLC, Response to NRC Request for Additional Information No. 14 (RAI-10131 R1, Question 3.9.4-8) on the NuScale Standard Design Approval Application ML24205A2112024-07-23023 July 2024 LLC, Response to NRC Request for Additional Information No. 022 (RAI-10157 R1) on the NuScale Standard Design Approval Application ML24135A2942024-04-25025 April 2024 LLC Resubmittal of Supplemental Information in Support of NRC Review of Topical Report TR-124587-P, Extended Passive Cooling and Reactivity Control Methodology, Revision O (A-XPC.LTR-8 Resubmittal) ML24067A0622024-03-0707 March 2024 LLC, Submittal of Supplemental Information for NuScale Letter LO-130201 ML24047A2522024-02-16016 February 2024 LLC, Response to NRC Request for Additional Information No. 10115 (RAI No. 10115) on the NuScale Standard Design Approval Application ML24024A0552024-01-19019 January 2024 LLC Submittal of Information in Support of NRC Review of Sdaa Chapter 3 ML23361A0992023-12-27027 December 2023 LLC, Response to NRC Request for Additional Information (RAI 10083) on the NuScale Standard Design Approval Application ML23310A1222023-11-0606 November 2023 LLC, 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 4 ML23306A2742023-11-0202 November 2023 LLC, Submittal of Additional Information with the NuScale Standard Design Approval Application, Revision 1 ML23304A3162023-10-31031 October 2023 LLC, Submittal of Revision 1 to Standard Design Approval Application ML23285A3412023-10-12012 October 2023 LLC 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 ML23283A3362023-10-0909 October 2023 LLC Submittal of Topical Report Entitled NuScale US460 Fuel Storage Rack Design Topical Report, TR-145417-P, Revision 0 2025-01-09
[Table view] Category:Letter
MONTHYEARML25027A3932025-01-27027 January 2025 LLC, Submittal of Sgfiv Flow Testing Report Summary ML25023A2142025-01-23023 January 2025 LLC, Submittal of NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-121353, Revision 2 ML25021A1532025-01-21021 January 2025 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML25021A2172025-01-21021 January 2025 Nuscale Power, LLC - Response to NRC Response to Request for Additional Information No. 037 (RAI-10357-R1) on the Nuscale Standard Design Approval Application ML25017A3912025-01-17017 January 2025 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML25016A3002025-01-16016 January 2025 LLC, Response to NRC Request for Additional Information No. 008 (RAI-10081 R1) on the NuScale Standard Design Approval Application ML25016A1522025-01-16016 January 2025 LLC, Response to NRC Request for Additional Information No. 018 (RAI-10142 R1) on the NuScale Standard Design Approval Application ML25014A1562025-01-14014 January 2025 LLC, Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML25009A0022025-01-0909 January 2025 LLC - Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML25009A0062025-01-0909 January 2025 LLC, Responses to NRC Request for Additional Information No. 039 (RAI-10359 R1) on the NuScale Standard Design Approval Application ML25009A0122025-01-0909 January 2025 LLC, Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Open Session) Chapter 16, Part 4, LOCA LTR, and Hiti Status, PM-177830, Revision 0 ML25009A0192025-01-0909 January 2025 LLC, Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Closed Session) Loss-of-Coolant Accident Topical Report and High Impact Technical Issue Status PM-177841, Revision 0 ML24354A1312024-12-19019 December 2024 LLC, Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML24354A1602024-12-19019 December 2024 LLC, Response to NRC Request for Additional Information No. 027 (RAI-10189 R1) on the NuScale Standard Design Approval Application ML24354A2522024-12-19019 December 2024 Nuscale Power, LLC - Response to Request for Additional Information No. 032 (RAI-10297 Ri) on the Nuscale Standard Design Approval Application ML24353A2522024-12-18018 December 2024 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML24353A3332024-12-18018 December 2024 Nuscale Power, LLC - Response to NRC Request for Additional Information No. 037 (RAI-10357 Ri) on the Newscale Standard Design Approval Application ML24353A0292024-12-18018 December 2024 Nuscale Power LLC - Responses to NRC Request for Additional Information No. 011 (RAI-10111 Ri) on the Nuscale Standard Design Approval Application ML24353A2182024-12-18018 December 2024 LLC, Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24348A1302024-12-13013 December 2024 LLC, Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24348A1132024-12-13013 December 2024 Nuscale Power, LLC - Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24346A1312024-12-11011 December 2024 LLC Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24344A0892024-12-0202 December 2024 Nuscale Power, LLC - Submittal of Supplemental Information in Support of NRC Review of Nuscale Topical Reports Associated with the Standard Design Approval Application ML24327A1832024-11-23023 November 2024 Sdaa Aia Inspection Announcement Letter ML24327A0362024-11-22022 November 2024 LLC Submittal of US460 NuScale Power Module Seismic Analysis, TR-121515, Revision 1 ML24327A1492024-11-22022 November 2024 LLC, Responses to NRC Request for Additional Information No. 024 (RAI-10185 R1) on the NuScale Standard Design Approval Application ML24326A0932024-11-21021 November 2024 LLC Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24326A3282024-11-21021 November 2024 LLC, Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24325A5932024-11-20020 November 2024 LLC, Response to NRC Request for Additional Information No. 036 (RAI-10350 R1) on the NuScale Standard Design Approval Application ML24312A3882024-11-12012 November 2024 NRCs 2nd Acknowledgement Letter NuScale Sdaa QAP Implementation Inspection NOV ML24313A0522024-11-0808 November 2024 LLC Response to NRC Request for Additional Information No. 14 (RAI-10131 R1) on the NuScale Standard Design Approval Application ML24313A0662024-11-0808 November 2024 LLC - Response to NRC Request for Additional Information No. 015 (RAI-10133 R1) on the NuScale Standard Design Approval Application ML24313A1212024-11-0808 November 2024 LLC - Response to NRC Request for Additional Information No. 020 (RAI-10150 R1) on the NuScale Standard Design Approval Application ML24312A4012024-11-0707 November 2024 LLC, Submittal of Pipe Rupture Hazards Analysis, TR-121507, Revision 1 ML24304B0462024-10-30030 October 2024 LLC, Reply to a Notice of Violation, EA-24-057 ML24304B0572024-10-30030 October 2024 LLC, Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Open Session) Chapters 3, 8, and 14 (Including Part 8), PM-175101, Revision 0 ML24303A2482024-10-29029 October 2024 LLC Submittal of Pressure and Temperature Limits Methodology, TR-130877, Revision 1 ML24269A0082024-10-24024 October 2024 Audit Status - the Staff Review of the NuScale Power, LLC Standard Design Approval (SDA) Application - NuScale US460 ML24296A4702024-10-22022 October 2024 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-121353, Revision 1 ML24281A0202024-10-0707 October 2024 LLC, Response to NRC Request for Additional Information No. 023 (RAI-10177 R1) on the NuScale Standard Design Approval Application ML24281A0182024-10-0707 October 2024 LLC, Response to NRC Request for Additional Information No. 017 (RAI-10135 R1) on the NuScale Standard Design Approval Application ML24274A1532024-09-30030 September 2024 LLC Submittal of NuScale Containment Leakage Integrity Assurance, TR-123952, Revision 1 ML24214A1272024-09-30030 September 2024 Nuscale Power, LLC – Disputed Cited Violation Revised 05200050/2024201-01 ML24271A2822024-09-27027 September 2024 LLC - Response to NRC Request for Additional Information No.026 (RAI-10199 R1) on the NuScale Standard Design Approval Application ML24269A0242024-09-25025 September 2024 LLC, Submittal of Presentation Materials Entitled Sdaa Review Presentation on RPV Connections, PM-174304, Revision 0 ML24256A1452024-09-12012 September 2024 LLC, Submittal of Oath or Affirmation ML24243A0092024-08-30030 August 2024 LLC, Submittal of NuScale Power Module Short-Term Transient Analysis, TR-121517, Revision 1 ML24242A2132024-08-29029 August 2024 LLC Submittal of the Nrc’S Request for Docketing of Resolved Audit Response ML24240A1412024-08-27027 August 2024 LLC - Response to NRC Request for Additional Information No. 16 (RAI-10134 R1) on the NuScale Standard Design Approval Application ML24239A8452024-08-26026 August 2024 LLC, Submittal of NuScale Technical Report, Fluence Calculation Methodology and Results, TR-118976, Revision 1 2025-01-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML25027A3942025-01-27027 January 2025 LLC, Response to Sdaa Audit Question Number Sgfiv Flow Testing Report Summary ML25021A1532025-01-21021 January 2025 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML25021A2172025-01-21021 January 2025 Nuscale Power, LLC - Response to NRC Response to Request for Additional Information No. 037 (RAI-10357-R1) on the Nuscale Standard Design Approval Application ML25017A3912025-01-17017 January 2025 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML25016A3002025-01-16016 January 2025 LLC, Response to NRC Request for Additional Information No. 008 (RAI-10081 R1) on the NuScale Standard Design Approval Application ML25016A1522025-01-16016 January 2025 LLC, Response to NRC Request for Additional Information No. 018 (RAI-10142 R1) on the NuScale Standard Design Approval Application ML25014A1562025-01-14014 January 2025 LLC, Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML25014A2772025-01-13013 January 2025 LLC - Response to Topical Report Audit Question Number NA-NonLOCA.LTR-66 ML25014A2712025-01-13013 January 2025 LLC - Response to Topical Report Audit Question Number A-NonLOCA.LTR-46S ML25014A2732025-01-13013 January 2025 LLC - Response to Topical Report Audit Question Number A-NonLOCA.LTR-56 ML25014A2752025-01-13013 January 2025 LLC - Response to Topical Report Audit Question Number A-NonLOCA.LTR-63 ML25014A2692025-01-13013 January 2025 LLC - Response to Topical Report Audit Question Number A-NonLOCA.LTR-46 ML25009A0062025-01-0909 January 2025 LLC, Responses to NRC Request for Additional Information No. 039 (RAI-10359 R1) on the NuScale Standard Design Approval Application ML24354A1602024-12-19019 December 2024 LLC, Response to NRC Request for Additional Information No. 027 (RAI-10189 R1) on the NuScale Standard Design Approval Application ML24354A2522024-12-19019 December 2024 Nuscale Power, LLC - Response to Request for Additional Information No. 032 (RAI-10297 Ri) on the Nuscale Standard Design Approval Application ML24354A1312024-12-19019 December 2024 LLC, Response to NRC Request for Additional Information No. 032 (RAI-10297 R1) on the NuScale Standard Design Approval Application ML24353A0292024-12-18018 December 2024 Nuscale Power LLC - Responses to NRC Request for Additional Information No. 011 (RAI-10111 Ri) on the Nuscale Standard Design Approval Application ML24353A3332024-12-18018 December 2024 Nuscale Power, LLC - Response to NRC Request for Additional Information No. 037 (RAI-10357 Ri) on the Newscale Standard Design Approval Application ML24353A2522024-12-18018 December 2024 LLC, Response to NRC Request for Additional Information No. 031 (RAI-10296 R1) on the NuScale Standard Design Approval Application ML24353A2182024-12-18018 December 2024 LLC, Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24348A0722024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-54 ML24348A0702024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-49 ML24348A0452024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-33 ML24348A0622024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-43 ML24348A0242024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-22 ML24348A0772024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-59 ML24348A1132024-12-13013 December 2024 Nuscale Power, LLC - Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24348A0752024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-58 ML24348A0542024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-37 ML24348A0142024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-5S ML24348A0612024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-41 ML24348A0122024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-5 ML24348A0582024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-39 ML24348A0692024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-45 ML24348A0292024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-24 ML24348A0732024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-57 ML24348A0672024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-44S ML24348A0332024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-26 ML24348A0812024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-59S2 ML24348A0432024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-30 ML24348A0202024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-8 ML24348A0872024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-68 ML24348A0272024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-23 ML24348A0522024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-36 ML24348A0072024-12-13013 December 2024 LLC Submittal of the NRCs Request for Docketing of Resolved Audit Responses ML24348A0632024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-44 ML24348A0102024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-2 ML24348A0402024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-28S ML24348A1302024-12-13013 December 2024 LLC, Response to NRC Request for Additional Information No. 037 (RAI-10357 R1) on the NuScale Standard Design Approval Application ML24348A0312024-12-13013 December 2024 Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-25 2025-01-09
[Table view] |
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RAIO-157114 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com Docket No. 052-050 February 16, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Response to NRC Request for Additional Information No. 10115 (RAI No. 10115) on the NuScale Standard Design Approval Application
REFERENCES:
- 1. U.S. Nuclear Regulatory Commission, "Request for Additional Information No. 10115 (RAI No. 10115)," dated December 6, 2023 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosures to this letter contain NuScale's response to the following RAI Question from NRC RAI No. 10115:
19.1.5-1 is the proprietary version of the NuScale Response to NRC RAI No. 10115 (RAI No. 10115). NuScale requests that the proprietary version be withheld from public disclosure in accordance with the requirements of 10 CFR § 2.390. The enclosed affidavit (Enclosure 3) supports this request. Enclosure 2 is the nonproprietary version of the NuScale response.
This letter makes no regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions, please contact Wren Fowler at 541-452-7183 or at sfowler@nuscalepower.com.
Sincerely, Thomas Griffith Manager, Licensing NuScale Power, LLC Distribution:
Mahmoud Jardaneh, NRC Getachew Tesfaye, NRC Alina Schiller, NRC
RAIO-157114 Page 2 of 2 02/16/2024 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com : NuScale Response to NRC Request for Additional Information RAI No. 10115, proprietary : NuScale Response to NRC Request for Additional Information RAI No. 10115, nonproprietary : Affidavit of Carrie Fosaaen, AF-157115
RAIO-157114 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com :
NuScale Response to NRC Request for Additional Information RAI No. 10115, proprietary
RAIO-157114 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com :
NuScale Response to NRC Request for Additional Information RAI No. 10115, nonproprietary
Response to Request for Additional Information Docket: 052000050 RAI No.: 10115 Date of RAI Issue:12/06/2023 NRC Question No.: 19.1.5-1 Regulatory Basis 10 CFR 52.137(a)(25) states that an SDAA must contain an FSAR that includes a description of the design-specific probabilistic risk assessment (PRA) and its results. The Statement of Considerations (SOC) for Part 52 (72FR49352) states, [t]he Commission has decided that the contents of applications for design approvals should contain essentially the same technical information that is required of design certification applications (e.g., demonstration of compliance with technically relevant Three Mile Island requirements, proposed technical resolutions of unresolved safety issues and medium and high-priority generic safety issues, and design-specific probabilistic risk assessment information) and many of the public comments on contents of applications for design certification apply to the requirements for design approvals.
Issue In SECY-93-087, the Commission approved the use of a PRA-based seismic margins analysis (SMA) for a design certification application (DCA) in lieu of a seismic PRA.
NUREG-0800, Standard Review Plan (SRP), Chapter 19.0, Revision 3, provides guidance on the methods acceptable to the staff to demonstrate low seismic risk, including the acceptance criteria for PRA-based SMA. The guidance includes the seismic fragility calculations based on design-specific information and the consideration of the accident sequences that require seismic fragility evaluation for determining sequence-level high confidence of low probability of failure (HCLPF) capacities.
Evaluating the seismic fragility is a key element of a PRA-based SMA and provides key insights to understand plant risk. A PRA-based SMA considers all sequences leading to core damage or containment failure. The results of the PRA-based SMA include characterization of the HCLPF capacities for select structures, systems, and components (SSCs) and sequence-level and NuScale Nonproprietary NuScale Nonproprietary
plant-level HCLPF capacities. Focusing on only those SSCs that contribute to the plant-level HCLPF capacity does not provide adequate information to support the staffs review of the development of and risk insights from the PRA-based SMA. Further, only providing HCLPF capacities does not provide adequate information for the staffs review of the fragility evaluation performed for the PRA-based SMA and the resulting uncertainties. Section 5.4, Position on Documentation of DC/COL-ISG-020 (ML100491233) specifies that fragilities for the SSCs in the seismic equipment list (SEL) as well as the sequence-level and plant-level HCLPF capacities, among others, be provided in Chapter 19 of the FSAR.
Due to the above reasons, NuScale SDAA FSAR Section 19.1.5.1, Seismic Risk Evaluation, does not provide sufficient information in Table 19.1-32 for the staff to effectively review the description and results of the PRA-based SMA, including the SSC fragility parameters and the corresponding uncertainty. The level of information necessary for the staff to make it finding on PRA-based SMA is consistent with that provided in the NuScale DCA FSAR Table 19.1-38.
Consequently, there is insufficient information in the SDAA FSAR to support the staffs finding on the PRA-based SMA per the regulatory basis identified above and the guidance in SRP Section 19.0, specifically under Design-Specific PRA (PRA-Based SMA) and the acceptance criteria in Section II of that guidance. The information requested hereunder is necessary for the staff to evaluate the PRA-based SMA, including its results, and make corresponding safety findings.
Information Requested To support the staffs finding on the PRA-based SMA against 10 CFR 52.137(a)(25), NuScale is requested to update the FSAR to include the following information in either an expanded Table 19.1-32 or in separate tables:
- 1. Key SSCs on the SEL that are considered important to understanding seismic risk insights, with their respective failure modes, fragility parameters (HCLPF, median capacity (Am)),
logarithmic standard deviation for randomness (beta_r), logarithmic standard deviation for uncertainty (beta_u), fragility evaluation method, and seismic correlation information.
- 2. Sequence-level HCLPF capacities for each seismically initiated accident sequence.
NuScale Nonproprietary NuScale Nonproprietary
NuScale Response:
- 1. NuScale proposes the following additional columns in FSAR Table 19.1-32, Seismic Margin Assessment Fragility: seismic correlation class, median seismic capacity (Am), randomness of the fragility evaluation (r), and uncertainty in the median seismic capacity (u). As described in FSAR Section 19.1.5.1.1.1, all structures, systems, and components (SSC) reported in Table 19.1-32 are design-specific and evaluated with the separation of variables fragility method. In addition to adding columns, NuScale has reorganized the controlling failure mode and assumed consequence information for valve fragilities included in the table and corrected errors in the HCLPF capacity values for the two bioshield entries and the controlling mode failure for the containment isolation valves. Lastly, NuScale has made several style and formatting improvements.
- 2. NuScale uses the MIN-MAX method to determine the plant-level HCLPF capacity for the US460 design. Per the MIN-MAX method, the plant-level HCLPF capacity is the minimum sequence-level HCLPF capacity. Each sequence-level HCLPF capacity is the minimum cutset HCLPF capacity. Each cutset HCLPF capacity is the maximum HCLPF capacity of the collection of SSC within the cutset (i.e., the controlling SSC). Table 1 below identifies the sequence-level HCLPF capacity for each seismically-induced sequence and the controlling SSC. Table 19.1-32 includes more information on the fragility analysis of these SSC. As described above, the plant-level HCLPF capacity is equal to the SSC associated with the minimum sequence-level HCLPF capacity. For the US460 design, the plant-level HCLPF capacity is 0.92g peak ground acceleration, which is associated with failure of the Reactor Building crane support.
Table 1: Sequence-Level High Confidence of Low Probability of Failure Capacities
((2(a),(c)
NuScale Nonproprietary NuScale Nonproprietary
Impact on US460 SDA:
FSAR Section 19.1 FSAR Table 19.1-32 has been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary NuScale Nonproprietary
NuScale Final Safety Analysis Report Probabilistic Risk Assessment NuScale US460 SDAA 19.1-147 Draft Revision 2 Audit Issue A-19.1-41 RAI 19.1.5-1 Table 19.1-32: Seismic Margin Assessment Fragility SSC HCLPF (g)
Controlling Failure Mode Assumed Consequence Reactor Building Crane Supports 0.92g Weld failure Core damage/Large Release Bioshield - normal operation (single stack) 0.93g Bolt shear failure Core damage/Large Release Bioshield - refueling of adjacent NPM (double stack) 0.93g Bolt shear failure Core damage/Large Release when configuration present Reactor Building 0.97g Roof in-plane shear failure Core damage/Large Release Reactor Building Crane 1.11g Plate bending failure Core damage/Large Release NPM Supports 1.14g Weld failure Core damage/Large Release Reactor Recirculation Valves 1.38g Valve body deformation Valve failure to open Reactor Vent Valves 2.69g Valve body deformation Valve failure to open Containment Isolation Valves 3.92g Valve body deformation Valve failure to open Reactor Safety Valves 6.00g Valve body deformation Valve failure to open Trip Valves for Reactor Recirculation Valves 7.14g Valve body deformation Valve failure to open Trip Valves for Reactor Vent Valve 8.44g Valve body deformation Valve failure to open Note:
- HCLPF = High-Confidence (95%) of a Low Probability (5%) of Failure (EPRI 103959)
NuScale Final Safety Analysis Report Probabilistic Risk Assessment NuScale US460 SDAA 19.1-148 Draft Revision 2 RAI 19.1.5-1 Table 19.1-33: Seismic Margin Assessment Fragility Seismic Correlation Class SSC Am (g) r u
HCLPF (g)
Controlling Failure Mode Assumed Consequence RBCS-145-RXB--WCL-SEIS Reactor Building Crane Supports 2.67 0.26 0.39 0.92 Weld failure Core damage/Large release BION-125-RXB--BSF-SEIS Bioshield - normal operation (single stack) 1.99 0.10 0.35 0.95 Bolt shear failure Core damage/Large release BIOR-125-RXB--BSF-SEIS Bioshield - refueling of adjacent NPM (double stack) 1.99 0.10 0.35 0.95 Bolt shear failure Core damage/Large release when configuration present RXB-----------IPS-SEIS Reactor Building 2.91 0.19 0.48 0.97 Roof in-plane shear failure Core damage/Large release RBC--145-RXB--PBL-SEIS Reactor Building Crane 3.45 0.24 0.45 1.11 Plate bending failure Core damage/Large release NPMS-80--RXB--WCF-SEIS NPM Supports 3.12 0.23 0.38 1.14 Weld failure Core damage/Large release POV--40--NPM--FTO-SEIS Reactor Recirculation Valves 3.83 0.26 0.36 1.38 Valve failure to open Note 1 POV--80--NPM--FTO-SEIS Reactor Vent Valves 7.09 0.25 0.34 2.69 Valve failure to open Note 1 HOV--100-NPM--FTC-SEIS Containment Isolation Valves 10.53 0.24 0.36 3.92 Valve failure to close Note 1 RSV--80--NPM--FTO-SEIS Reactor Safety Valves 15.58 0.26 0.32 6.00 Valve failure to open Note 1 SOV--60--NPM--FTO-SEIS Trip Valves for Reactor Recirculation Valves 20.85 0.24 0.31 8.44 Valve failure to open Note 1 SOV--70--NPM--FTO-SEIS Trip Valves for Reactor Vent Valves 18.84 0.25 0.34 7.14 Valve failure to open Note 1 Notes:
- Am = median seismic capacity
- r = randomness of the fragility evaluation
- u = uncertainty in the median seismic capacity
- HCLPF = high confidence (95%) of low probability (5%) of failure (EPRI 103959)
- 1. Component failures are contributors to plant response (e.g., failure of the RRVs to open results in ECCS failure)
RAIO-157114 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com :
Affidavit of Carrie Fosaaen, AF-157115
AF-157115 Page 1 of 2 NuScale Power, LLC AFFIDAVIT of Carrie Fosaaen I, Carrie Fosaaen, state as follows:
(1)
I am the Vice President of Regulatory Affairs of NuScale Power, LLC (NuScale), and as such, I have been specifically delegated the function of reviewing the information described in this Affidavit that NuScale seeks to have withheld from public disclosure, and am authorized to apply for its withholding on behalf of NuScale.
(2)
I am knowledgeable of the criteria and procedures used by NuScale in designating information as a trade secret, privileged, or as confidential commercial or financial information. This request to withhold information from public disclosure is driven by one or more of the following:
(a)
The information requested to be withheld reveals distinguishing aspects of a process (or component, structure, tool, method, etc.) whose use by NuScale competitors, without a license from NuScale, would constitute a competitive economic disadvantage to NuScale.
(b)
The information requested to be withheld consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), and the application of the data secures a competitive economic advantage, as described more fully in paragraph 3 of this Affidavit.
(c)
Use by a competitor of the information requested to be withheld would reduce the competitors expenditure of resources, or improve its competitive position, in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
(d)
The information requested to be withheld reveals cost or price information, production capabilities, budget levels, or commercial strategies of NuScale.
(e)
The information requested to be withheld consists of patentable ideas.
(3)
Public disclosure of the information sought to be withheld is likely to cause substantial harm to NuScales competitive position and foreclose or reduce the availability of profit-making opportunities. The accompanying Request for Additional Information response reveals distinguishing aspects about the response by which NuScale develops its NuScale Power, LLC Response to NRC Request for Additional Information (RAI No. 10115) on the NuScale Standard Design Approval Application.
NuScale has performed significant research and evaluation to develop a basis for this response and has invested significant resources, including the expenditure of a considerable sum of money.
The precise financial value of the information is difficult to quantify, but it is a key element of the design basis for a NuScale plant and, therefore, has substantial value to NuScale.
If the information were disclosed to the public, NuScales competitors would have access to the information without purchasing the right to use it or having been required to undertake a similar expenditure of resources. Such disclosure would constitute a misappropriation of NuScales intellectual property, and would deprive NuScale of the opportunity to exercise its competitive advantage to seek an adequate return on its investment.
(4)
The information sought to be withheld is in the enclosed response to NRC Request for Additional Information RAI 10115 Chapter 19.1.5-1. The enclosure contains the designation Proprietary at the top of each page containing proprietary information. The information considered by NuScale to be proprietary is identified within double braces, (( }} in the document.
AF-157115 Page 2 of 2 (5)
The basis for proposing that the information be withheld is that NuScale treats the information as a trade secret, privileged, or as confidential commercial or financial information. NuScale relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC § 552(b)(4), as well as exemptions applicable to the NRC under 10 CFR §§ 2.390(a)(4) and 9.17(a)(4).
(6)
Pursuant to the provisions set forth in 10 CFR § 2.390(b)(4), the following is provided for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld:
(a)
The information sought to be withheld is owned and has been held in confidence by NuScale.
(b)
The information is of a sort customarily held in confidence by NuScale and, to the best of my knowledge and belief, consistently has been held in confidence by NuScale. The procedure for approval of external release of such information typically requires review by the staff manager, project manager, chief technology officer or other equivalent authority, or the manager of the cognizant marketing function (or his delegate), for technical content, competitive effect, and determination of the accuracy of the proprietary designation.
Disclosures outside NuScale are limited to regulatory bodies, customers and potential customers and their agents, suppliers, licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or contractual agreements to maintain confidentiality.
(c)
The information is being transmitted to and received by the NRC in confidence.
(d)
No public disclosure of the information has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or contractual agreements that provide for maintenance of the information in confidence.
(e)
Public disclosure of the information is likely to cause substantial harm to the competitive position of NuScale, taking into account the value of the information to NuScale, the amount of effort and money expended by NuScale in developing the information, and the difficulty others would have in acquiring or duplicating the information. The information sought to be withheld is part of NuScales technology that provides NuScale with a competitive advantage over other firms in the industry. NuScale has invested significant human and financial capital in developing this technology and NuScale believes it would be difficult for others to duplicate the technology without access to the information sought to be withheld.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 16, 2024.
Carrie Fosaaen}}