ML20059N687

Regulatory Audit Plan for NuScale DCA Chapters 6, 7, and 15

ML20059N687
Person / Time
Site:	NuScale
Issue date:	03/02/2020
From:	Getachew Tesfaye NRC/NRR/DNRL/NRLB
To:	Michael Dudek NRC/NRR/DNRL/NRLB
Tesfaye G / 415-8013
References
Download: ML20059N687 (6)

Text

March 02, 2020 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 THE REGULATORY AUDIT OF NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION, CHAPTERS 6, ENGINEERED SAFETY FEATURES, CHAPTER 7, INSTRUMENTATION AND CONTROLS, AND CHAPTER 15, TRANSIENT AND ACCIDENT ANALYSES, RELATED TO CHANGE IN INSTRUMENTATION AND CONTROLS SETPOINTS AND/OR LOGIC By letter dated December 31, 2016, NuScale Power, LLC (NuScale) submitted to the U.S. Nuclear Regulatory Commission (NRC) a Final Safety Analysis Report (FSAR) for its Design Certification (DC) application of the NuScale design (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17013A229). The NRC staff is aware that a change is being made to instrumentation and controls setpoints and/or logic to address an issue related to boron redistribution and the associated Return to Power analyses associated with Section 15.0.6 of the FSAR. The purpose of this regulatory audit is to: (1) better understand the impact of this design change on information related to Chapter 6, Engineered Safety Features, Chapter 7, Instrumentation and Controls, and Chapter 15, Transient and Accident Analyses, as well as associated technical and topical reports; (2) confirm information through examination of calculations and other information; (3) identify information that will require docketing to support a regulatory finding; and (4) ensure conformance with applicable NRC regulations.

The audit will take place via the Electronic Reading Room and/or at NuScales offices in either Rockville, Maryland or Corvallis, Oregon. The audit entrance date will be as soon as practical after March 2, 2020. The contents of the audit plan are provided as an enclosure.

Docket No.52-048

Enclosure:

Audit Plan cc w/encl.: DC NuScale Power, LLC Listserv CONTACT:

Getachew Tesfaye, NRR/DNRL 301-415-8013

ML20059N687

• via email NRR-106 OFFICE DNRL/NRLB:PM DNRL/NRLB:LA DNRL/NRLB:PM NAME GTesfaye SGreen*

GTesfaye DATE 02/28/2020 03/02/2020 03/02/2020 UNITED STATES NUCLEAR REGULATORY COMMISSION AUDIT PLAN FOR THE REGULATORY AUDIT OF OF NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION, CHAPTERS 6, 7 and 15 DOCKET NO.52-048 AUDIT PLAN APPLICANT: NuScale Power, LLC (NuScale)

CONTACTS: Rebecca Norris Gregory Myers Mike Melton Marty Bryan Paul Infanger Matthew Presson DURATION:

1 month Phase 4: March 2, 2020 through April 3, 2020 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:

1. Jeff Schmidt, Office of Nuclear Reactor Regulation (NRR), Audit Team Lead

2. Rebecca Patton, NRR

3. Ryan Nolan, NRR

4. Shanlai Lu, NRR

5. Alex Siwy, NRR

6. Carl Thurston, NRR

7. Josh Borromeo, NRR

8. Robert Beaton, NRR

9. Syed Haider, NRR

10. Jeanne Johnston, NRR

11. Dinesh Taneja, NRR

12. Peter Lien, Office of Nuclear Regulatory Research (RES)

13. Andrew Ireland, RES

14. Joseph Staudenmeier, RES

15. Andrew Bielen, RES

16. Peter Yarsky, RES

17. Joseph Ashcraft, NRR

18. Dawnmathews Kalathiveettil, NRR

2 I.

BACKGROUND AND OBJECTIVES By letter dated December 31, 2016, NuScale submitted to the U.S. Nuclear Regulatory Commission (NRC) an FSAR for its Design Certification (DC) application of the NuScale design (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17013A229). The NRC staff is aware that a change is being made to instrumentation and controls setpoints and/or logic to address an issue related to boron redistribution and the associated Return to Power analyses associated with Section 15.0.6 of the FSAR. This design change affects, at minimum, information in Chapter 6, Engineered Safety Features, Chapter 7, Instrumentation and Controls, and Chapter 15, Transient and Accident Analyses, of the FSAR, as well as associated technical and topical reports. The purpose of this regulatory audit is to understand the impact of the revised instrumentation and controls setpoints and/or logic on figures of merit used to make regulatory findings.

II.

REGULATORY AUDIT BASIS This regulatory audit is based on the following:

General Design Criteria (GDC) 4, Environmental and Dynamic Effects Design Bases, of Appendix A to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, which requires in part that the applicant take provisions to accommodate and appropriately protect structures, systems and components (SSC) important to safety against the environmental conditions, including dynamic effects, that may result from normal operation, maintenance, testing, equipment failures and postulated accidents.

GDC 16, Containment design, which requires in part that a reactor containment and associated systems be provided to establish an essentially leak-tight barrier and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.

GDC 38, Containment heat removal, which requires that:

o The containment heat removal system be capable of rapidly reducing the containment pressure and temperature following a LOCA and to maintain these parameters at acceptably low levels.

o The containment heat removal system performs in a manner consistent with the function of other systems.

o The safety-grade design of the containment heat removal system provides suitable redundancy in components and features and suitable interconnections, leak detection, isolation, and containment capability to ensure that, for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available),

the system safety function can be accomplished in the event of a single failure.

3 GDC 50, Containment design basis, which requires in part that the reactor containment structure and its internal compartments to accommodate the calculated pressure and temperature conditions resulting from any LOCA.

10 CFR 52.47, Contents of applications; technical information in final safety analysis report.

10 CFR 50.43(e), concerning testing to qualify and assess the capability of submitted designs to meet safety criteria 10 CFR 50.46, Acceptance criteria for ECCS for Light-Water Nuclear Power Reactors GDC 35, Emergency core cooling system, as it pertains to transfer heat from the reactor core following any loss of reactor coolant at a rate such that (1) fuel and clad damage that could interfere with continued effective core cooling is prevented and (2) clad metal-water reaction is limited to negligible amounts.

GDC 10, Reactor Design, as it pertains to ensuring the specified acceptable fuel design limits are not exceeded during normal operation, including the effects of anticipated operational occurrences.

GDC 13, Instrumentation and Control, as it relates to instrumentation and controls provided to monitor variables over anticipated ranges for normal operations, for AOOs, and for accident conditions.

GDC 26, Reactivity Control System Redundancy and Capability, as it relates to the reliable control of reactivity changes to ensure that specified acceptable fuel design limits are not exceeded even during AOOs.

Principal design criteria (PDC) 27, Combined Reactivity Control Systems Capability, as it relates to having the capability of reliably controlling reactivity changes to assure that under postulated accident conditions and with appropriate margin for stuck rods the capability to cool the core is maintained.

III.

REGULATORY AUDIT SCOPE The audit team will view supporting calculations and documentation associated with Chapter 6, Engineered Safety Features, Chapter 7, Instrumentation and Controls, and Chapter 15, Transient and Accident Analyses which may be impacted by the revised instrumentation and controls setpoints and/or logic. The audit team may also request to meet with subject matter expert(s) to discuss details and to support the staffs understanding of any revised analyses.

4 IV.

INFORMATION AND OTHER MATERIAL NECCSSARY FOR THE REGULATORY AUDIT The staff requests access to any analysis or documentation which support revisions to FSAR Chapter 6, Engineered Safety Features, Chapter 7, Instrumentation and Controls, and Chapter 15, Transient and Accident Analyses, as well as associated technical and topical reports, or any evaluations as to why no revisions were deemed necessary, due to the revised instrumentation and controls setpoints and/or logic. Documentation made available should include revised FSAR, technical or topical report markups, if available.

V SPECIAL REQUESTS The NRC staff requests the applicant to make identified documents available to the NRC auditors in NuScales eRR to the extent possible. Use of the eRR allows multiple auditors in different geographic locations to examine the same document at the same time, which improves the efficiency and reduces the cost of the audit. Additional documents may be identified as the review progresses. When the staffs review of the documents associated with a specific issue is complete, the NRC staff will notify either the NRCs Division of New and Renewed Licenses or NuScale that these documents can be removed from eRR, thereby minimizing their residence time in eRR.

In addition, the NRC staff may request in-person or telephone audit meetings with NuScale personnel to facilitate the staffs understanding of material to be audited. Such meetings will be scheduled based on mutual availability. The staff requests that document titles identified by the NRC staff that are germane to an audit meeting be made available in the eRR prior to any scheduled audit meeting.

VI DELIVERABLES The NRC audit team is expected to consist of the above listed individuals who are or have been involved in reviewing FSAR Chapter 6, Engineered Safety Features, Chapter 7, Instrumentation and Controls, and Chapter 15, Transient and Accident Analyses, or the associated technical and topical reports. The NRC staff will conduct this audit in accordance with the guidance provided in LIC 111, Regulatory Audits (ADAMS Accession No. ML19226A274). The NRC staff acknowledges the proprietary nature of the information requested and will handle it appropriately 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 will initiate on March 2, 2020 and end April 3, 2020.

The staff will hold audit calls and/or meetings with NuScale as necessary to understand audit material. The NRC will inform NuScale of emerging information needs as well as documents that can be removed from eRR.

An audit report will be generated at the completion of the audit. If necessary, any circumstances related to the conductance of the audit will be communicated to, Getachew Tesfaye, at 301-415-8013 or Getachew.tesfaye@nrc.gov.