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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 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 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 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 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 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 ML24304B0462024-10-30030 October 2024 LLC, Reply to a Notice of Violation, EA-24-057 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 ML24214A1272024-09-30030 September 2024 Nuscale Power, LLC – Disputed Cited Violation Revised 05200050/2024201-01 ML24274A1532024-09-30030 September 2024 LLC Submittal of NuScale Containment Leakage Integrity Assurance, TR-123952, Revision 1 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-173492 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com August 27, 2024 Docket No.52-050 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. 16 (RAI-10134 R1) on the NuScale Standard Design Approval Application
REFERENCE:
- 1. NRC Letter to NuScale, Request for Additional Information No. 16 (RAI-10134 R1), dated March 2, 2024 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The enclosure to this letter contains NuScale's response to the following RAI question from NRC RAI-10134 R1:
x 3.6.3-1 is the proprietary version of the NuScale response to NRC RAI No. 16 (RAI-10134 R1). 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 Elisa Fairbanks at 541-452-7872 or at efairbanks@nuscalepower.com.
I declare under penalty of perjury that the foregoing is true and correct. Executed on August 27, 2024.
Sincerely, Mark W. Shaver Director, Regulatory Affairs NuScale Power, LLC
RAIO-173492 Page 2 of 2 08/27/2024 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com Distribution:
Mahmoud Jardaneh, Chief New Reactor Licensing Branch, NRC Getachew Tesfaye, Senior Project Manager, NRC Prosanta Chowdhury, Senior Project Manager, NRC
- NuScale Response to NRC Request for Additional Information RAI-10134 R1, proprietary : NuScale Response to NRC Request for Additional Information RAI-10134 R1, nonproprietary : Affidavit of Mark W. Shaver, AF-173493
RAIO-173492 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-10134 R1, proprietary
RAIO-173492 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-10134 R1, nonproprietary
Response to Request for Additional Information Docket: 052000050 RAI No.: 10134 Date of RAI Issue: 03/02/2024 NRC Question No.: 3.6.3-1 Regulatory Basis 10 CFR Part 50 Appendix-A GDC 4 states that structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit. However, dynamic effects associated with postulated pipe ruptures in nuclear power units may be excluded from the design basis when analyses reviewed and approved by the Commission demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping.
Issue FSAR Section 3.6.3 states that Leak-Before-Break (LBB) is not used for SDAA. This is a change from the DCA approach where LBB methodology was used. Specifically, for DCA, Pipe Rupture Hazards Analysis Technical Report, TR-0818-61384-P, Revision 2, utilized LBB methodology while the SDAA Pipe Rupture Hazards Analysis TR-121507-P, Revision 0, does not.
In the DCA, LBB methodology was credited to justify exclusion of high energy line breaks in large-diameter secondary piping, namely main steam system (MSS) and feedwater system (FWS) piping. This was noted in section 2.2.2.1.1 of the DCA Technical Report TR-0818-61384-P, Revision 2. NuScale analyzed MSS and FWS piping for LBB and showed them to meet the criteria in the Section 2.2.5 discussion related to SRP 3.6.3. This was also reflected in Section 3.6.3.2 of the DCA Safety Evaluation. However, in the SDAA NuScale does not use LBB methodology for MSS and FWS piping inside containment. This is a significant change in NuScales approach.
Information Requested Provide the basis for break exclusion for the high energy piping (and particularly the MSS and FWS piping) inside containment that account for the change in methodology from DCA to NuScale Nonproprietary NuScale Nonproprietary
SDAA. Discuss changes in design parameters such as pressure, temperature, and flow rate as a result of the power increase from DCA to SDAA, and whether there are any changes in MSS and FWS piping routing inside containment, and how the above are considered in the justification for break exclusion. Provide a summary of maximum stress and its location for MSS and FWS systems for BTP 3-4 stress combination as well as for ASME service levels A, B, C, and D. Discuss whether the leak detection system based on previous LBB approach from DCA remains due to a change in methodology in SDAA.
NuScale Response:
Executive Summary Leak before break (LBB) methodology was applied to the main steam system (MSS) and feedwater system (FWS) in the US600 design certification (DCA). The US460 standard design approval application (SDAA) implements an alternate approach under Branch Technical Position (BTP) 3-4, and extends the break exclusion zone in certain instances as long as the additional design criteria of BTP 3-4 B.1.(ii) are satisfied. Criteria for break exclusion under BTP 3-4 B.1.(ii) include the following:
application of more conservative stress and fatigue limits than those required by ASME Code
100 percent volumetric inservice examination of all pipe welds during each inspection interval BTP 3-4 B.1.(ii) imposes conservative stress limits and inspection requirements to reduce the probability of flaw initiation and growth. In contrast, LBB relies on detecting leakage from a crack that has already propagated through the pressure boundary, allows higher operating stresses, and requires no additional inspections.
Basis for break exclusion for high energy piping inside containment The basis and methodologies for break exclusion are described in Pipe Rupture Hazards Analysis, TR-121507, Revision 0, Appendix A.
Inside containment, BTP 3-4 B.1.(ii) is applied to the following:
the steam generator system (SGS), main steam (MS), and feedwater (FW) piping
the terminal end welds between the decay heat removal system (DHRS) piping and the containment vessel (CNV) safe ends
the bolted connections between the emergency core cooling system (ECCS) valves and the reactor pressure vessel (RPV)
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Changes in design parameters as a result of the power increase from DCA to SDAA TR-121507 Table 3-3 defines the characteristics of the high energy piping (including temperature and pressure) inside the Reactor Building for the SDAA, and is comparable to the pipe rupture hazards analysis TR-0818-61384 Table 3-3 for the DCA. A comparison between these values is shown below in Table 1.
Table 1: SGS MS and FW Parameter Comparison System Parameter US600 DCA US460 SDAA SGS MS Operating Temperature 585 F 575 F Design Temperature 650 F 650 F Operating Pressure 500 psia 700 psia Design Pressure 2100 psia 2200 psia Full Power Steam Flow 5.321E5 lbm/hr 8.14E5 lbm/hr SGS FW Operating Temperature 300 F 250 F Design Temperature 650 F 650 F Operating Pressure 550 psia 701 psia Design Pressure 2100 psia 2200 psia The increase in secondary side operating pressures between the DCA and SDAA is due to operating conditions throughout an operating range of 20 percent to 102 percent power.
Changes to the SGS MS and FW pipe routing are addressed in the current SDAA design. TR-121507 Section A.1.1 describes the application of BTP 3-4 B.1.(ii) and includes considerations for pipe routing.
Summary of maximum stress for MSS and FWS systems Preliminary stress analyses are performed for the Class 1, 2, & 3 high-energy piping larger than nominal pipe size (NPS) 1 both inside and outside containment in order to confirm the adequacy of the piping layout and support locations, and to support high energy line break evaluations as described in SDAA Section 3.12. Current stress analysis results for the portions of SGS MS and FW lines inside containment are summarized in Table 2 and Table 3 below. High stress locations are shown in Figure 1 and Figure 2.
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Table 2: Steam Generator System Feedwater & Decay Heat Removal Piping Stress Analysis Results
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Figure 1: Steam Generator System Feedwater & Decay Heat Removal Piping Stress Analysis Result Locations
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Table 3: Steam Generator System Main Steam Piping Stress Analysis Results
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Figure 2: Steam Generator System Main Steam Piping Stress Analysis Result Locations
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Leakage detection system changes between DCA and SDAA The DCA leakage detection system sensitivity requirement is 0.001 gpm for the application of the LBB methodology. The SDAA leakage detection system sensitivity requirement is 0.05 gpm to meet the Leakage-Monitoring-Related Positions specified in RG 1.45. These requirement changes are discussed further in the response to RAI Question 3.6.2.7-2.
Conclusion The SDAA reflects the updated design and analysis of the US460 standard plant and applies the break exclusion methodologies described in Pipe Rupture Hazards Analysis, TR-121507, Revision 0, Appendix A, ensuring 10 CFR Part 50 Appendix-A GDC 4 is met.
Impact on US460 SDAA:
There are no impacts to US460 SDAA as a result of this response.
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RAIO-173492 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 Mark W. Shaver, AF-173493
AF-173493 Page 1 of 2
NuScale Power, LLC AFFIDAVIT of Mark W. Shaver I, Mark W. Shaver, state as follows:
(1)
I am the Director 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-10134 R1) 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-10134 R1 Chapter 3.6.3-1. 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-173493 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.
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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.
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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.
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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 August 27, 2024.
Mark W. Shaver M
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