ML25080A205
| ML25080A205 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 06/06/2025 |
| From: | Prosanta Chowdhury NRC/NRR/DNRL/NRLB |
| To: | Jardaneh M NRC/NRR/DNRL/NRLB |
| References | |
| Download: ML25080A205 (8) | |
Text
June 6, 2025 MEMORANDUM TO:
Mahmoud Jardaneh, Chief New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation FROM:
Prosanta Chowdhury, Senior Project Manager
/RA/
New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
AUDIT
SUMMARY
FOR THE U.S. REGULATORY COMMISSION SUPPLEMENTAL AUDIT DURING PHASE A OF THE NUSCALE US460 STANDARD DESIGN APPROVAL APPLICATION REVIEW By memorandum dated November 7, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24311A005), the U.S. Nuclear Regulatory Commission (NRC) staff issued an audit plan to review documents that support confirmatory evaluations and request for additional information responses for Phase A of the US460 Standard Design Approval application (SDAA) review. The following topical reports (TRs) were reviewed with the SDAA: TR-0516-49422, Loss of Coolant Accident (LOCA) Evaluation Model, Revision 3 (ML23008A002); TR-0516-49416, Non-LOCA Transient Analysis Methodology, Revision 4 (ML23005A305); and TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ML23005A308).
The NRC started the audit on September 18, 2024. The audit was primarily conducted remotely via NuScales electronic reading room (eRR) and video teleconferences. In addition, a few in-person meetings were held at NuScales offices in Rockville, Maryland and Corvallis, Oregon.
CONTACT: Prosanta Chowdhury, NRR/DNRL Getachew Tesfaye, NRR/DNRL 301-415-1647 301-415-8013
M. Jardaneh 2
An audit exit meeting was held on March 6, 2025. An audit summary is provided as an enclosure to this memorandum.
Docket No. 05200050
Enclosure:
Audit summary Cc: NuScale US460 Standard Design Approval GovDelivery
ML25080A205 via email*
NRR-106 OFFICE DNRL/NRLB: PM DNRL/NLIB: LA DNRL/NRLB: PM DNRL/NRLB: BC NAME DDrucker*
SGreen*
GTesfaye*
MJardaneh*
DATE 03/12/2024 06/03/2024 06/04/2025 03/14/2025 OFFICE DNRL/NRLB:PM NAME PChowdhury*
DATE 06/06/2025
Enclosure AUDIT
SUMMARY
FOR THE U.S. REGULATORY COMMISSION SUPPLEMENTAL AUDIT DURING PHASE A OF THE NUSCALE US460 STANDARD DESIGN APPROVAL APPLICATION REVIEW
1.0 BACKGROUND
AND PURPOSE By memorandum dated November 7, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24311A005), the U.S. Nuclear Regulatory Commission (NRC) staff issued an audit plan for Phase A of the US460 Standard Design Approval application (SDAA) review. The following topical reports (TRs) were reviewed with the SDAA:
TR-0516-49422, Loss of Coolant Accident (LOCA) Evaluation Model, Revision 3 (ML23008A002); TR-0516-49416, Non-LOCA Transient Analysis Methodology, Revision 4 (ML23005A305); and TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ML23005A308).
The NRC started the audit on September 18, 2024. The audit was primarily conducted remotely via NuScales electronic reading room (eRR) and video teleconferences. In addition, a few in-person meetings were held at NuScales offices in Rockville, Maryland and Corvallis, Oregon.
An audit exit meeting was held on March 6, 2025.
The purpose of the audit was for NRC staff to review documents that support confirmatory evaluations and request for additional information (RAI) responses. The NRC staff requested that some of the audit responses be submitted on the docket. Section 12 of this document provides a list of the docketed responses and their ADAMS accession nos.
NRC staff issued separate audit summaries for the following: (1) Phase A of the SDAA review -
audit summary (ML24264A049); (2) TR-0516-49422, Loss-of-Coolant Accident [LOCA]
Evaluation Model, Revision 3 - audit summary (ML24262A230); (3) TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 - audit summary (ML24262A257);
and (4) TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 - audit summary (ML24263A009).
2.0 REGULATORY AUDIT BASIS This regulatory audit is based on the submittal of Revision 1 of the NuScale SDA application (ML23306A033). The bases for the submittal follow the regulations in Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, as outlined below:
10 CFR Part 52, Subpart E - Standard Design Approvals
§ 52.131 Scope of subpart.
2
§ 52.133 Relationship to other subparts.
§ 52.135 Filing of applications.
§ 52.136 Contents of applications; general information.
§ 52.137 Contents of applications; technical information.
§ 52.139 Standards for review of applications.
§ 52.141 Referral to the Advisory Committee on Reactor Safeguards.
§ 52.143 Staff approval of design.
§ 52.145 Finality of standard design approvals; information requests.
§ 52.147 Duration of design approval.
3.0 AUDIT LOCATION AND DATES The audit was primarily conducted remotely via NuScales eRR and video teleconferences and in the following locations:
NRC Headquarters One White Flint North 11545 Rockville Pike Rockville, Maryland 20852-2738 NuScale 11333 Woodglen Drive, Suite 205 Rockville, Maryland 20852 1100 NE Circle Blvd Corvallis, OR 97330 The audit started with a teleconference entrance meeting on September 18, 2024, and ended with a teleconference exit meeting on March 6, 2025.
4.0 KEY AUDIT TEAM MEMBERS AUDIT TEAM (Project Managers):
Mahmoud Jardaneh (Branch Chief)
Ricky Vivanco David Drucker Getachew Tesfaye (Project Lead)
Thomas Hayden Dennis Galvin Stacy Joseph Prosanta Chowdhury Alina Schiller River Rohrman AUDIT TEAM (Technical Branch Chiefs):
Branch Chief Branch Branch Chief Branch Wendell Morton DEX/EEEB Milton Valentin DSS/SCPB Stewart Bailey DEX/EMIB Shivani Mehta DSS/STSB Jason Paige DEX/ELTB Angie Buford DNRL/NVIB Fanta Sacko DEX/EICB Matthew Mitchell DNRL/NPHP Ian Tseng DEX/ESEB Steven Bloom DNRL/NCSG Barbara Hayes DEX/EXHB James Anderson DRO/IOLB Evan Davidson DRA/APLB Kerri Kavanagh DRO/IQVB
3 Shilp Vasavada DRA/APLC Kenneth Erwin NMSS/REFS/ERNRB Kevin Hsueh DRA/ARCB Jessie Quichocho NSIR/DPR/RLB Rebecca Patton DSS/SNRB Mario Fernandez NSIR/DPCP/CSB Phillip Sahd DSS/SNSB Amanda Marshall NSIR/DPCP/RSB Scott Krepel DSS/SFNB 5.0 KEY APPLICANT PARTICIPANTS Thomas Griffith, Licensing Manager Wren Fowler, Licensing Supervisor Jim Osborn, Licensing Supervisor Elisa Fairbanks, Licensing Supervisor Amanda Bode, Licensing Supervisor Erin Blumsack, Licensing Engineer 6.0 AUDIT DOCUMENTS Primarily, the staff audited documents via NuScales eRR. On a few occasions, the staff reviewed hardcopy documents and or files on a NuScale-owned computer during an in-person meeting.
7.0 DESCRIPTION
OF AUDIT ACTIVITIES AND
SUMMARY
OF OBSERVATIONS During the audit, the NRC staff reviewed responses to the audit questions and then provided feedback to NuScale. NuScale provided revised responses in the eRR based on the NRC feedback. NRC staff reviewed the revised responses and provided feedback as appropriate.
The NRC staff tracked the status of audit questions and provided to NuScale on a weekly basis.
A list of the docketed audit question responses and their ADAMS Accession Nos. are provided in Section 12 below.
8.0 EXIT BRIEFING The NRC staff conducted an audit exit meeting via teleconference on March 6, 2025. The NRC staff summarized their observations.
9.0 OPEN ITEMS AND PROPOSED CLOSURE PATHS During the audit, the NRC staff and NuScale discussed the audit questions generated by the staff and the responses provided by NuScale. The NRC staff issued RAIs for some of the audit questions that remained unresolved. Appendix E of the Final Safety Evaluation Report will provide a list of RAI responses and links to those RAI responses. All audit items and RAIs were resolved on or before the issuance of this audit summary.
10.0 DEVIATIONS FROM THE AUDIT PLAN Not applicable.
4
11.0 REFERENCES
- 1.
NuScale Power, LLC, US460 Standard Design Approval application, Revision 1, October 31, 2023, (ML23306A033).
- 2.
TR-0516-49422, Loss-of-Coolant Accident [LOCA] Evaluation Model, Revision 5 (ML25086A182).
- 3.
TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 5 (ML25085A357).
- 4.
TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ML23005A308).
- 5.
Audit Plan for the Staff Review of the NuScale Power, LLC Standard Design Approval Application - NuScale US460, March 22, 2023 (ML23067A300).
- 6.
Updated - Audit Plan for the Staff Review of the NuScale Power, LLC Standard Design Approval Application - NuScale US460 Design, July 29, 2024 (ML24211A089).
12.0 DOCKETED RESPONSES TO AUDIT QUESTIONS Question ADAMS ML#
Chapter 3 A-3.9.2-26 ML24346A147 Chapter 5 A-5.4.3-4 ML25071A178 Chapter 6 A-6.2-4 ML25022A195 A-6.3-10 ML25022A196 Chapter 9 A-9.1.5-3 ML25063A183 Chapter 15 A-15.6.5-1 ML24348A008 A-15.9-1 ML25065A161 Non-LOCA NonLOCA.LTR-3, 9, 18, 19, 20, 21, 69 ML25042A062 A-NonLOCA-20 ML25035A245 A-NonLOCA-46 ML25014A269 A-NonLOCA-46S ML25014A271 NonLOCA-50 ML25058A423 NonLOCA-55 ML25045A237 A-NonLOCA-56 ML25014A273 A-NonLOCA-63 ML25014A275 A-NonLOCA-66 ML25014A277
5 XPC XPC-2 ML25030A364 XPC-6 ML25051A166 XPC-21 ML25058A229 XPC-23 ML25056A126 XPC-24 ML25045A158