ML24262A230
| ML24262A230 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 06/06/2025 |
| From: | Prosanta Chowdhury NRC/NRR/DNRL/NRLB |
| To: | Jardaneh M NRC/NRR/DNRL/NRLB |
| References | |
| TR-0516-49422, Rev 3 | |
| Download: ML24262A230 (7) | |
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 NUSCALES LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL TOPICAL REPORT, TR-0516-49422, REVISION 3 By memorandum dated March 22, 2023, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23067A300), the U.S. Nuclear Regulatory Commission (NRC) staff issued an initial audit plan for the review of Phase A of the NuScale Power, LLC (NuScale) US460 Standard Design Approval application (SDAA) and supporting topical reports (TRs) including the subject of this audit summary: TR-0516-49422, Loss-of-Coolant Accident (LOCA) Evaluation Model, Revision 3 (ML23008A002).
The NRC started the audit with a teleconference entrance meeting on March 27, 2023. 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. By memorandum dated July 29, 2024, (ML24211A089), the NRC staff updated the audit plan for Phase A of the SDAA review. The updated plan added a new phase to disposition audit issues not resolved by the planned audit end date of August 31, 2024.
CONTACT: Ricky Vivanco, NRR/DNRL Getachew Tesfaye, NRR/DNRL 301-415-0021 301-415-8013
M. Jardaneh 2
An audit exit meeting was held on September 3, 2024. An audit summary is provided as an enclosure to this memorandum.
Docket No. 05200050
Enclosure:
Audit summary cc: NuScale US460 Standard Design Approval GovDelivery
ML24262A230 via email*
NRR-106 OFFICE DNRL/NRLB: PM DNRL/NLIB: LA DNRL/NRLB: PM DNRL/NRLB: BC NAME RVivanco*
SGreen*
GTesfaye*
MJardaneh*
DATE 09/19/2024 09/19/2024 03/18/2025 03/14/2025 OFFICE DNRL/NRLB:PM NAME PChowdhury*
DATE 06/06/2025
Enclosure AUDIT
SUMMARY
FOR NUSCALES LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL TOPICAL REPORT, TR-0516-49422, REVISION 3
1.0 BACKGROUND
AND PURPOSE By memorandum dated March 22, 2023, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23067A300), the U.S. Nuclear Regulatory Commission (NRC) staff issued an initial audit plan for the review of Phase A of the NuScale Power, LLC (NuScale) US460 Standard Design Approval application (SDAA) and supporting topical reports (TRs) including the subject of this audit summary: TR-0516-49422, Loss-of-Coolant Accident (LOCA) Evaluation Model, Revision 3 (LOCA TR) (ML23008A002).
The NRC started the audit with a teleconference entrance meeting on March 27, 2023. The audit was primarily conducted remotely via NuScales eRR and video teleconferences. In addition, a few in-person meetings were held at NuScales offices in Rockville, Maryland and Corvallis, Oregon.
By memorandum dated July 29, 2024 (ML24211A089), the NRC staff issued an updated audit plan for Phase A of the US460 SDAA review. The updated plan added a new phase to disposition audit issues not resolved by the planned audit end date of August 31, 2024.
The purpose of the audit was for NRC staff to examine and evaluate information with the intent to gain understanding, verify information, and/or identify information that will require docketing to support the basis for the staff findings on the adequacy of the evaluation model presented in the LOCA TR.
NRC staff issued separate audit summaries for the following: (1) Phase A of the SDAA review -
audit summary (ML24264A049); (2) Phase A of the SDAA review - supplemental audit summary (ML25080A205); (3) TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 (ML23005A305) - audit summary (ML24262A257); and (4) TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ML23005A308) - audit summary (ML24263A009).
2.0 REGULATORY AUDIT BASIS The LOCA TR supports the NuScale SDAA which was submitted pursuant to the requirements of Title 10 of the Code of Federal Regulations, Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.
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
2 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 March 27, 2023, and ended with a teleconference exit meeting on September 3, 2024.
4.0 KEY AUDIT TEAM MEMBERS AUDIT TEAM (Project Management):
Mahmoud Jardaneh (Branch Chief)
Getachew Tesfaye (Project Lead)
Ricky Vivanco 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 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 electronic reading room (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
3 During the audit, the NRC staff reviewed the LOCA TR, and documents discussed therein. The NRC staff generated 54 audit questions. NuScale responded to the questions in the eRR. The NRC staff provided feedback on audit question responses. The NRC staff tracked the status of audit issues and provided that status on a bi-weekly basis to NuScale. NRC staff identified 10 audit question responses that required docketing. These audit responses are available as shown below:
Audit Question ADAMS ML#
Audit Question ADAMS ML#
A-LOCA.LTR-3 ML23205A233 A-LOCA.LTR-39 ML24326A338 A-LOCA.LTR-35 ML24326A329 A-LOCA.LTR-40 ML24326A340 A-LOCA.LTR-36 ML24326A331 A-LOCA.LTR-41 ML24326A343 A-LOCA.LTR-37 ML24326A334 A-LOCA.LTR-42 ML24326A345 A-LOCA.LTR-38 ML24326A336 A-LOCA.LTR-48 ML24326A347 8.0 EXIT BRIEFING The NRC staff conducted an audit exit meeting via teleconference on September 3, 2024.
The NRC staff summarized their observations.
9.0 OPEN ITEMS AND PROPOSED CLOSURE PATHS Most of these audit questions were resolved in the audit. At the end of the audit, the NRC staff issued Requests for Additional Information (RAIs) for those audit questions not resolved in the audit (ML24304B075). NuScale submitted responses to those RAIs on the docket generally within 30 days of issuance. NRC staff reviewed the responses and determined that the RAIs were satisfied. The responses to the RAIs are available as shown below:
RAI/Audit Question ADAMS ML#
RAI/Audit Question ADAMS ML#
LOCA.LTR-51, 52, 54 ML25021A153 LOCA.LTR-2 ML24353A252 LOCA.LTR-4, 45, 47 ML25017A391 LOCA.LTR-53 ML25045A252 10.0 DEVIATIONS FROM THE AUDIT PLAN Not applicable.
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 3 (ML23008A002)
- 3.
TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 (ML23005A305)
- 4.
TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ML23005A308)
4
- 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)