ML23067A298
| ML23067A298 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 03/22/2023 |
| From: | Getachew Tesfaye NRC/NRR/DNRL/NRLB |
| To: | Michael Dudek NRC/NRR/DNRL/NRLB |
| References | |
| Download: ML23067A298 (7) | |
Text
March 22, 2023
MEMORANDUM TO: Michael I. Dudek, 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 U.S. NUCLEAR REGULATORY COMMISSION REQUESTS FOR SUPPLEMENTAL INFORMATION IDENTIFICATION OF SPECIFIC INFORMATION REQUIREMENTS - NUSACLE S TANDARD DESIGN APPROVAL APPLICATION
By letter dated December 31, 2022 (electronically submitted on January 1, 2023), NuScale Power, LLC (NuScale) transmitted the last part of the required staged submittal of the Standard Design Approval (SDA) application. The submitted documents can be found at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 22339A066. The staff completed the acceptance review of the SDA application an d issued the acceptance review letter on March 17, 2023 (ML23058A160).
Based on its review, the U.S. Nuclear Regulatory Commission (NR C) staff has identified technical sufficiency issues in the SDA application related to density wave oscillation (DWO),
with impacts on some parts of the SDA application Part 2, Final Safety Analysis Report (FSAR)
Chapters 3, 5, 6, 15 and 19, and the following associated licen sing topical reports (LTRs): (1)
TR-0516-49422, Loss-of-Coolant Accident [LOCA] Evaluation Mode l, Revision 3 (ML23008A002); (2) TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 (ML23005A305); (3) TR-124587, Extended Passive Cool ing and Reactivity Control Methodology, Revision 0 (ML23005A308); and (4) TR-131981, Met hodology for the Determination of the Onset of Density Wave Oscillations (DWO), Revision 0 (ML22364A332).
As a result, the NRC staff has concluded that supplemental info rmation on this topic is required before the NRC staff can accept the SDA application for docketi ng and conduct a detailed technical review of all aspects of the application.
of the March 17, 2023, NRC letter outlined, at a hi gh-level, the missing DWO-related information. As stated in that letter, the purpose of t his audit is to resolve and close-out the staffs identified questions about DWO so that the applicat ion can be adequately remedied and then found acceptable for docketing.
CONTACT: Getachew Tesfaye, NRR/DNRL (301-415-8013)
M. Dudek
The audit will start on March 27, 2023, and will exit on or abo ut August 22, 2023; or earlier if the staff completes its review and all of the needed undocketed SDA application supporting documents associated with DWO, identified in Enclosure 1 of the March 17, 2023, NRC letter, have been provided. The audit will be conducted primarily via NuScale Electronic Reading Room and/or at NuScales offices in either Rockville, Maryland or Corvallis, Oregon. The contents of the audit plan are provided as an enclosure.
Docket No. 05200050
Enclosure:
Audit Plan
cc w/enclosure: NuScale Power, LLC Listserv
ML23067A298 *via email NRR-106 OFFICE DNRL/NRLB:PM DNRL/NLIB:LA DNRL/NRLB:BC DNRL/NRLB:PM NAME GTesfaye SGreen* MDudek* GTesfaye DATE 03/16 /2023 03/16/2023 03/22/2023 03/22/2023 UNITED STATES NUCLEAR REGULATORY COMMISSION AUDIT PLAN FOR THE STAFF ACCEPTANCE REVIEW OF THE NUSCALE POWER, LLC STANDARD DESIGN APPROVAL AND REQUESTS FOR SUPPLEMENTAL INFORMATION
DOCKET NO. 05200050
AUDIT PLAN
APPLICANT:
NuScale Power, LLC (NuScale)
CONTACTS:
Manager: Thomas Griffith
Supervisors: Thomas Griffith, Jim Osborn, Stephanie Terwillige r, Shane Scanlon, Wren Fowler
DURATION:
Audit Entrance - March 27, 2023
Audit Exit - August 22, 2023
LOCATION:
U.S. Nuclear Regulatory Commission (NRC) Headquarters (via NuScales Electronic Reading Room (eRR))
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, OR 97330
AUDIT TEAM (Project Managers):
Getachew Tesfaye (Project Lead) Thomas Hayden David Drucker Bruce Bavol Stacy Joseph Joseph Colaccino (Technical Advisor)
Ricky Vivanco
Enclosure AUDIT TEAM (Technical Branch):
NuScale Requests for Email Address Division/Branch Supplemental Information Team Rebecca Patton (BC) rebecca.karas@nrc.gov DSS/SNRB Antonio Barrett antonio.barrett@nrc.gov DSS/SNRB John Budzynski John.Budzynski@nrc.gov DSS/SNRB Joshua Miller joshua.miller@nrc.gov DSS/SNRB Rosie Sugrue rosemary.sugrue@nrc.gov DSS/SNRB Adam Rau adam.rau@nrc.gov DSS/SNRB Dr. Dong Zheng Dong.Zheng@nrc.gov DSS/SNRB Ryan Nolan ryan.nolan@nrc.gov DSS/SNRB Shanlai Lu shanlai.lu@nrc.gov DSS/SNRB
I. BACKGROUND AND OBJECTIVES
By letter dated December 31, 2022 (electronically submitted on January 1, 2023), NuScale Power, LLC (NuScale) transmitted the last part of the required staged submittal of the Standard Design Approval (SDA) application. The submitted documents can be found at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 22339A066. The staff completed the acceptance review of the SDA application an d issued the acceptance review letter on March 17, 2023 (ML23058A160).
Based on its review, the NRC staff has identified technical sufficiency issues in the SDA application related to density wav e oscillation (DWO), with impacts on some parts of the SDA application Part 2, Final Safety Analysis Report (FSAR) Chapter s 3, 5, 6, 15 and 19, and the following associated licensing topical reports (LTRs): (1) TR-0 516-49422, 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, Revision 0 (ML23005A308);
and (4) TR-131981, Methodology for the Determination of the On set of Density Wave Oscillations (DWO), Revision 0 (ML22364A332). As a result, the NRC staff has concluded that supplemental information on this topic is required before the N RC staff can accept the SDA application for docketing and conduct a detailed technical revi ew of all aspects of the application.
of the March 17, 2023, NRC letter outlined, at a hi gh-level, the missing DWO-related information. As stated in that letter, the purpose of t his audit is to resolve and close-out the staffs identified questions for DWO so that the applicatio n can be adequately remedied and then found acceptable for docketing.
The audit will start on March 27, 2023, and will exit on or abo ut August 22, 2023, or earlier if the staff completes its review of all undocketed SDA application su pporting documents and identifies the specific information required by the requests fo r supplemental information (RSI).
The audit will be conducted primarily via NuScale eRR and/or at NuScales offices in either Rockville, Maryland or Corvallis, Oregon. The contents of the a udit plan are provided as an enclosure.
2 II. REGULATORY AUDIT BASIS
This regulatory audit is based on the submittal of the FSAR doc uments for its SDA application of the NuScale design (ML22339A066). The bases for the submittal f ollow the regulations in 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 Safegua rds (ACRS).
o § 52.143 Staff approval of design.
o § 52.145 Finality of standard design approvals; information re quests.
o § 52.147 Duration of design approval.
III. REGULATORY AUDIT SCOPE
The audit covers parts of the NuScale SDA application (ML22339A 066) impacted by technical sufficiency issues related to density wave oscillation (DWO). T his include parts of SDA application Part 2, Final Safety Analysis Report (FSAR) Chapter s 3, 5, 6, 15 and 19, and parts of the following associated licensing topical reports (LTRs): ( 1) TR-0516-49422, Loss-of-Coolant Accident [LOCA] Evaluation Model, Revision 3 (ML23008A 002); (2) TR-0516-49416, Non-Loss-of-Coolant Accident Analys is Methodology, Revision 4 (ML23005A305); (3)
TR-124587, Extended Passive Cooling and Reactivity Control Met hodology, Revision 0 (ML23005A308); and (4) TR-131981, Methodology for the Determin ation of the Onset of Density Wave Oscillations (DWO), Revision 0 (ML22364A332).
In particular, the audit scope covers the following missing inf ormation needed for technical sufficiency for the NuScale SDA application and applicable LTRs :
- Scope of the methodology for calculating DWO and the full appl icability range, conditions, and figures of merit;
- Testing that was performed including test results and test dat a;
- Comparisons of test data to the analysis models and justificat ion for the applicability of the models for evaluation of the SDA application design; and
- Evaluations for the effect of DWO or other flow instability ph enomena on steam generator and decay heat removal system performance SDA applica tion Section 5.4.3 and 6.3) during all operating conditions including normal opera tion, LOCAs, Non-LOCAs, and extended passive cooling.
3 IV. INFORMATION AND OTHER MATERIAL NECCSSARY FOR THE REGULATORY AUDIT
NuScale should be prepared to provide documents, reports, calcu lations, computer code verification, and other material, as applicable, supporting the identification and resolution of RSIs. The NRC staff may request that NuScale make these materia ls available in the eRR and/or as a computer disc for review.
V SPECIAL REQUESTS
NuScale and NRC have discussed and agreed upon the following au dit logistics:
- NuScale creates Certrec eRR locations for document viewing.
o NuScale to set up access for NRC participants once Staff emails are communicated.
- Weekly schedule for audit activities o Friday - NRC PMs submits audit RSI items (via email) o Monday - NuScale addresses RSI items o Tuesday/Wednesday/Thursday - standing audit meetings o Thursday/Friday - NuScale posts RSI items feedback in eRR
- During the standing audit meetings NuScale and NRC staff will :
o Clarify audit RSI items o Discuss audit potential RSI items resolutions o Discuss additional document needs
- NRC to track status of audit RSI items (internal spreadsheet).
o NRC to provide NuScale a copy of the current tracker on Friday s.
o Ensure mutual alignment during weekly standing meetings
- NRC PMs will be notified via email when new material is poste d in eRR
VI DELIVERABLES
The NRC audit team will identify and communicate to NuScale the specific RSI items that are required to be submitted as soon as practicable, but no later t han September 15, 2023; which is 6-months after the issuance of the acceptance review letter (Ma rch 17, 2023). Receiving this information in a timely manner will ensure that the SDA applica tion can and will be accepted for detailed technical review. The NRC staff acknowledges the propr ietary nature of the information reviewed in eRR and will handle it appropriately throughout the audit. While the NRC staff will take notes, the NRC staff will not remove hard copies or electr onic files from the audit site(s).
The NRC will inform NuScale of emerging information needs as we ll as documents that can be removed from eRR following completion of staff review.
An audit report will be generated at the completion of the audit. If necessary, any circumstances related to the conduct of the audit will be commu nicated to Getachew Tesfaye, at 301-415-8013 or Getachew.tesfaye@nrc.gov.
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