ML24262A016
| ML24262A016 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 09/18/2024 |
| From: | Getachew Tesfaye NRC/NRR/DNRL/NRLB |
| To: | Jardaneh M NRC/NRR/DNRL/NRLB |
| References | |
| Download: ML24262A016 (7) | |
Text
September 18, 2024
MEMORANDUM TO: Mahmoud Jardaneh, Chief New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
FROM: Getachew Tesfaye, Senior Project Manager /RA/
New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
AUDIT PLAN FOR THE STAFF REVIEW OF THE NUSCALE POWER, LLC STANDARD DESIGN APPROVAL APPLICATION -
NUSCALE US460 DESIGN - RELATED TO DOCUMENTS THAT SUPPORT CONFIRMATORY REVIEWS AND REQUEST FOR ADDITIONAL INFORMATION RESPONSES
By letter dated October 31, 2023, NuSc ale Power, LLC (NuScale) submitted Standard Design Approval Application (SDAA), Revision 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23306A033). The associated topical reports (TRs) that are being reviewed with the SDAA are: TR-0516-49422, Loss of Coolant Accident (LOCA)
Evaluation Model, Revision 3 (ML23008A002); TR- 0516-49416, Non-LOCA Transient Analysis Methodology, Revision 4 (ML23005A305); TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revis ion 0 (ML23005A308); and TR-131981, Methodology for the Determination of the Onset of Density Wave Oscillations (DWO), Revision 1 (ML23212B224). The purpose of this audit is to review documents that support confirmatory evaluations and request for additional information responses.
The audit will begin on September 18, 2024, with an Entrance meeting. The audit is being conducted primarily via the established NuSc ale Electronic Reading Room and at NuScale s offices in Rockville, Maryland and Corvallis, Oregon. The NRC headquarters offices can also be used for hybrid (virtual/in-person) audit meet ings, as appropriate. The contents of the audit plan are provided as an enclosure to this memorandum.
Docket No. 05200050
Enclosure:
Audit Plan
cc w/encl: NuScale Power, LLC Listserv
CONTACT: Getachew Tesfaye, NRR/DNRL 301-415-8013
ML24262A016 *via email NRR-106 OFFICE DNRL/NRLB: PM DNRL/NLIB: LA DNRL/NRLB: BC DNRL/NRLB: PM NAME GTesfaye SGreen* MJardaneh
- GTesfaye DATE 09/17/2024 09/18/2024 09/18/2024 09/18/2024 UNITED STATES NUCLEAR REGULATORY COMMISSION AUDIT PLAN FOR THE STAFF REVIEW OF THE NUSCALE POWER, LLC STANDARD DESIGN APPROVAL APPLICATION - NUSCALE US460 DESIGN - RELATED TO DOCUMENTS THAT SUPPORT CONFIRMATORY REVIEWS AND REQUEST FOR ADDITIONAL INFORMATION RESPONSES DOCKET NO. 05200050
AUDIT PLAN
APPLICANT:
NuScale Power, LLC (NuScale)
CONTACTS:
Licensing Manager: Thomas Griffith
Licensing Supervisors: Jim Osborn, Wren Fowler, Elisa Fairbanks, Amanda Bode
DURATION:
September 18, 2024 - October 31, 2024
LOCATION:
U.S. Nuclear Regulatory Commission (NRC) Headquarters (via NuScale Electronic Reading Room (eRR) and hybrid (virtual/in-person))
One White Flint North 11545 Rockville Pike Rockville, Maryland 20852-2738 NuScale 11333 Woodglen Drive, Suite 205 Rockville, Maryland 20852 NuScale 1100 NE Circle Blvd Corvallis, Oregon 97330
Enclosure 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 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
2 I. BACKGROUND AND OBJECTIVES
By letter dated October 31, 2023, NuScale Power, LLC (NuScale) submitted Standard Design Approval Application (SDAA), Revision 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23306A033). The a ssociated topical reports (TRs) that are being reviewed with the SDAA are: TR-0516-49422, Loss of Coolant Accident (LOCA)
Evaluation Model, Revision 3 (ML23008A002); TR -0516-49416, Non-LOCA Transient Analysis Methodology, Revision 4 (ML23005A305); TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revisi on 0 (ML23005A308); and TR-131981, Methodology for the Determination of the Onset of Density Wave Oscillations (DWO), Revision 1 (ML23212B224). The purpose of this audit is to review documents that support confirmatory evaluations and request for additional information responses. The staff audits material that may be needed to make a reasonable assurance finding that the design protects public health and safety. If the NRC staff identifies information that is needed to support a finding, NuScale submits that information on the application docket.
II. REGULATORY AUDIT BASIS
This regulatory audit is primarily based on Title 10 of the Code of Federal Regulations (10 CFR)
Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.
- 10 CFR Subpart E - Standard Design Approvals o § 52.131 Scope of subpart.
o § 52.133 Relationship to other subparts.
o § 52.135 Filing of applications.
o § 52.136 Contents of applications; general information.
o § 52.137 Contents of applications; technical information.
o § 52.139 Standards for review of applications.
o § 52.141 Referral to the Advisory Committee on Reactor Safeguards.
o § 52.143 Staff approval of design.
o § 52.145 Finality of standard design approvals; information requests.
o § 52.147 Duration of design approval.
III. REGULATORY AUDIT SCOPE
The audit covers all parts of the NuScale SDA application (ML23306A033) and all parts of the following four TRs: (1) TR-0516-49422, Loss-of-Coolant Accident [LOCA] Evaluation Model, Revision 3 (ML23008A002); (2) TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 (ML23005A305); (3) TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revisi on 0 (ML23005A308); and (4) TR-131981, Methodology for the Determination of the Onset of Density Wave Oscillations (DWO), Revision 1 (ML23212B224).
IV. INFORMATION AND OTHER MATERIAL NECCSSARY FOR THE REGULATORY AUDIT
NuScale should be prepared to provide documents, reports, calculations, computer code verification, and other material, as applicable, supporting the analyses documented in the respective chapters of NuScale SDAA Final Safe ty Analysis Report, and technical and topical reports. The NRC staff may request that NuScale make these additional materials available in the eRR and/or as a computer disc to be submitted on the docket.
3 V SPECIAL REQUESTS
NuScale and NRC have discussed and agr eed upon the following audit logistics:
- NuScale creates Certrec eRR portal for document viewing.
o NuScale to set up access for NRC participants once the staff emails are communicated.
- Weekly schedule for audit activities o Tuesday/Wednesday/Thursday - standing audit meetings
- During the standing audit meetings NuScale and NRC staff will:
o Clarify audit issues o Discuss audit issue resolutions o Discuss additional document needs o Determine if a docketed response is required.
- The RAI process will be used when:
o NRC requires formal docketing of a response o completion of the response will extend past the audit close date o requested by NuScale or NRC
- NRC will send formal RAI to NuScale via email
- RAI clock starts on the day the question is sent
- NuScale will respond to RAI questions:
o Does the RAI contain proprietary, export control, or security related information?
o Is clarification needed?
o Is the 30-day response timeline achievable?
NuScale responses to RAIs will be submitted electronically to the NRC docket.
VI DELIVERABLES
The NRC audit team is expected to be compos ed of the above listed project managers along with a multi-faceted group of NRC technical reviewers and contractors. The NRC staff acknowledges the proprietary nature of the information requested and will handle it in accordance with agency policies and procedures throughout the audit. While the NRC staff will take notes, the NRC staff will not remove hard copies or electronic files from the audit site(s).
The audit started on September 18, 2024, and will end on October 31, 2024.
The NRC will inform NuScale of emerging information needs as well as documents that can be removed from eRR.
The NRC will generate an audit report at the completion of the audit. The audit report will include a link for all docketed materials requested by the staff during the audit.
4 The NRC point of contact for communicating questi ons or comments related to the conduct of the audit is Mr. Getachew Tesfaye, who can be reached at 301-415-8013 or via email at Getachew.tesfaye@nrc.gov.
5