ML18201A161

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7/09/19 - Letter from R. Franovich to T. Bergman Preliminary Safety Evaluation with Open Items for NuScale DCA Chapter 15, Transient and Accident Analyses
ML18201A161
Person / Time
Site: NuScale
Issue date: 07/09/2019
From: Rani Franovich
NRC/NRO/DLSE
To: Bergman T
NuScale
Franovich R / 415-7443
Shared Package
ML18201A159 List:
References
Download: ML18201A161 (3)


Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION July 9, 2019 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330

SUBJECT:

NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION -

PRELIMINARY SAFETY EVALUATION WITH OPEN ITEMS FOR CHAPTER 15, TRANSIENT AND ACCIDENT ANALYSES

Dear Mr. Bergman:

The U.S. Nuclear Regulatory Commission (NRC) staff is preparing a safety evaluation (SE) with open items (OIs) for each chapter of the NuScale Power, LLC (NuScale) Design Certification Application (DCA) submitted by NuScale on January 6, 20171.

The NRC staffs preliminary SE with OIs for Chapter 15, Transient and Accident Analyses, is based on Chapter 15 of the NuScale DCA, Revision 2. This preliminary SE chapter includes numerous items characterized for the purpose of this SE chapter as OIs. However, many of these issues are unresolved without a clearly defined path toward resolution identified at this time and may involve potential legal issues. For this reason, the staff anticipates that NuScale will make revisions throughout this chapter of the application. Accordingly, this preliminary SE chapter, while useful for illuminating the issues unique to the review of transient and accident analysis for the NuScale design, may not reflect the NuScale revised approach and associated NRC review of that revised approach. The staff provided a version of this preliminary SE chapter to support a meeting with the ACRS held on June 19-20, 2019, to discuss key issues related to this chapter and its associated topical reports. It should be noted that this preliminary SE reflects the staff evaluation as of June 18, 2019.

The enclosed preliminary SE with OIs is being provided to NuScale for review of proprietary information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 2.390, Public Inspections, Exemptions, Requests for Withholding. The NRC will withhold the enclosed preliminary SE from public disclosure for ten business days from the date of this letter to allow you the opportunity to identify any proprietary information or factual errors. If within that ten-day period, you do not request that all or portions of the preliminary SE be withheld from public disclosure, the enclosure will be made available for public viewing through the Publicly Available Records component of NRCs Agencywide Documents Access and Management System and placed on the NRCs public webpage for this application.

Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.

1 The Design Certification Application was submitted via a transmittal letter dated December 31, 2016.

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

OFFICIAL USE ONLY - PROPRIETARY INFORMATION T. Bergman 2 If you have any questions or comments concerning this matter, I can be reached at (301) 415-7334 or via e-mail address at Rani.Franovich@nrc.gov.

Sincerely,

/RA/ (Gregory Cranston for)

Rani Franovich, Senior Project Manager Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors Docket No.52-048

Enclosure:

1. Preliminary Safety Evaluation with Open Items for Chapter 15, Transient and Accident Analyses OFFICIAL USE ONLY - PROPRIETARY INFORMATION

Pkg: ML18201A159 Letter: ML18201A160 SER: ML19168A103 *via email NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DLSE/LB1: BC NRO/DLSE/LB1: PM NAME RFranovich MMoore SLee (GCranston for) RFranovich (GCranston for) (GCranston for)

DATE 7/9/2019 6/27/2019 7/9/2019 7/9/2019