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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
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ML20141N0122020-05-20020 May 2020
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ML20072M6682020-03-30030 March 2020
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ML20062F7262020-03-0505 March 2020
Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public
ML20069A9632020-03-0404 March 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0
ML20069A1772020-03-0404 March 2020
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ML20069A1572020-03-0404 March 2020
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0
ML20066G2802020-03-0303 March 2020
LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0
2024-03-28
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Text
April 27, 2020 Matthew W. Sunseri, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
SAFETY EVALUATION REPORT FOR TOPICAL REPORT TR-0516-49416, REVISION 2, NON-LOSS-OF-COOLANT ACCIDENT ANALYSIS METHODOLOGY
Dear Mr. Sunseri:
In your letter dated March 25, 2020 (Agencywide Documents Access and Management System Accession No. ML20085K048), the Advisory Committee on Reactor Safeguards (ACRS or the Committee) reported on the Committees review of the U.S. Nuclear Regulatory Commission (NRC) staffs safety evaluation (SE) of the NuScale Power, LLC (NuScale), Topical Report TR-0516-49416, Revision 2, Non-Loss-Of-Coolant Accident Analysis Methodology, issued November 30, 2019. I appreciate the time and effort that the ACRS has devoted to this review, as reflected in meetings with the ACRS Subcommittee on February 19-20, 2020, and the ACRS Full Committee on March 5, 2020.
Your letter offered the following conclusions and recommendations:
- 1. The Non-Loss-Of-Coolant Accident (non-LOCA) Analysis Methodology topical report, with the limitations and conditions imposed by the staff SE report, provides an acceptable methodology to analyze anticipated occurrences, infrequent events, and postulated accidents for the NuScale Power Module (NPM).
- 2. The staff should include an additional condition that allows application of this topical report with any critical heat flux (CHF) correlation approved for use in NPM applications.
- 3. The staffs SE report should be issued with this additional condition.
With regard to these conclusions and recommendations, the NRC staffs review of the prescreening CHF correlation employed in the non-LOCA methodology includes an examination of various references1,2,3. The NRC staff has concluded that the behavior of the prescreening CHF correlation noted by the ACRS is expected, and the references support, the validity of the 1 Todreas, Neil E., and Mujid Kazimi, Nuclear Systems, Volume 1, 2nd Edition, Boca Raton, FL: CRC Press (2011).
2 RELAP5-3D© Code Manual, Volume IV: Models and Correlations, Revision 4.3, The RELAP5-3D© Code Development Team, Idaho National Laboratory (October 2015).
3 Hejzlar, Pavel, and Neil E. Todreas, Consideration of critical heat flux margin prediction by subcooled or low quality critical heat flux correlations, Nuclear Engineering and Design, Volume 163, Issues 1-2, pp. 215-223 (June 1996).
M. Sunseri correlation for comparing relative minimum CHF ratio values (e.g., for identifying limiting CHF cases) but not for calculating absolute values (e.g., for quantifying thermal margins).
The prescreening CHF correlation described in the non-LOCA topical report and the NSP correlations, implemented in the VIPRE-01 subchannel code, produce similar trends given variations in the input parameters as shown in the non-LOCA topical report. This information was confirmed by the NRC staffs audit (ADAMS Accession No. ML19039A090). The NRC staff, therefore, finds the prescreening CHF correlation to be acceptable because it can be reasonably expected to identify the limiting CHF cases to be further analyzed using VIPRE-01.
The NRC staff emphasizes that the non-LOCA prescreening CHF correlation is used for relative comparisons only and is not used to determine thermal margins.
While the NRC staff understands the ACRSs desire for flexibility in the prescreening CHF correlation, reflected in Conclusions and Recommendations 2 and 3, the NRC staff notes that the applicant has not requested NRC approval of other CHF correlations for prescreening. As such, the NRC staff has not reviewed other CHF correlations for this purpose. The condition and limitation proposed by ACRS would necessitate additional justification from the applicant, and review findings by the NRC staff, that other CHF correlations approved for NPM applications can reliably identify the limiting CHF cases relative to the NSP correlations in VIPRE-01. The NRC staff does not believe that that the proposed condition and limitation is needed given that a methodology acceptable to the NRC staff already exists. Should an applicant or licensee wish to use a different approach as part of its non-LOCA CHF prescreening process in the future, it should submit a change to the topical report for the NRC staffs review and approval.
The NRC staff appreciates the ACRSs review and will issue the SE with no additional conditions and limitations by June 2020.
Sincerely, Robert Digitally signed by Robert M. Taylor M. Taylor Date: 2020.04.27 08:40:46 -04'00' Ho Nieh, Director Office of Nuclear Reactor Regulation Docket No.: 52-048 cc: Chairman Svinicki Commissioner Baran Commissioner Caputo Commissioner Wright SECY
Pkg: ML20091K561 Ltr: ML20104A079 *via e-mail NRR-106 OFFICE DNRL/NRLB: PM DNRL/NRLB: LA QTE DSS/SNRB: BC NAME MJohnson* CSmith* QTE* RPatton*
DATE 04/09/2020 04/13/2020 04/15/2020 04/15/2020 OFFICE DNRL/NRLB: BC DSS:D DNRL: D NRR: D*
NAME MDudek* JDonoghue* ABradford* HNieh (RTaylor for)
DATE 04/15/2020 04/17/2020 04/17/2020 4/27/2020