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| {{#Wiki_filter:}} | | {{#Wiki_filter:January 30, 2020 Mr. Zackary W. Rad Director, Regulatory Affairs 1100 Circle Boulevard, Suite 200 Corvallis, OR 97330 |
| | |
| | ==SUBJECT:== |
| | FINAL SAFETY EVALUATION FOR NUSCALE POWER, LLC, LICENSING TOPICAL REPORT: TR-0915-17565, REVISION 3, ACCIDENT SOURCE TERM METHODOLOGY By letter dated April 23, 2019, NuScale Power, LLC (NuScale) submitted licensing topical report (TR) TR-0915-17565, Revision 3, Accident Source Term Methodology, dated April 21, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19112A172nonproprietary version), for review and approval by the U.S. Nuclear Regulatory Commission (NRC) in support of the application for the design certification of NuScales small modular reactor (SMR). By letter dated July 31, 2019 (ADAMS Accession No. ML19212A801), NuScale submitted changes to Revision 3 of the TR in response to the staff request for additional information. |
| | The NRC staff has found that TR-0915-17565, Revision 3, as updated by the July 31, 2019, letter acceptable for referencing in licensing applications for the NuScale SMR design to the extent specified and under the conditions and limitations delineated in the enclosed safety evaluation report (SER). The SER defines the basis for acceptance of the TR. |
| | In accordance with the guidance provided on the NRCs TR Web site (http://www.nrc.gov/about-nrc/regulatory/licensing/topical-reports.html), we request that NuScale publish an accepted version of this TR within three months of receipt of this letter. The accepted version shall incorporate this letter and the enclosed safety evaluation between the title page and the abstract. It must be well indexed such that information is readily located. Also, it must contain in its appendices historical review information, such as questions and accepted responses, and original report pages that were replaced. The accepted version shall include an "-A" (designated accepted) following the report identification symbol. |
| | |
| | Z. Rad 2 If the NRCs criteria or regulations change so that its conclusion in this letter (that the TR is acceptable) is invalidated, NuScale and/or the applicant referencing the TR will be expected to revise and resubmit its respective documentation or submit justification for the continued applicability of the TR without revision of the respective documentation. |
| | If you have any questions or comments concerning this matter, I can be reached at (301) 415-8013 or via e-mail address at Getachew.Tesfaye@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Getachew Tesfaye, Senior Project Manager New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No. 52-048 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc: w/o encl.: DC NuScale Power, LLC Listserv |
| | |
| | ML20027A105 *via email NRR-043 OFFICE DNRL/NRLB:PM DNRL/NRLB:LA DNRL/NRLB: BC DNRL/NRLB:PM NAME GTesfaye SGreen* MDudek GTesfaye DATE 01/27/2020 01/28/2020 01/28/2020 01/30/2020}} |
Latest revision as of 00:05, 16 February 2020
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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023 LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3) ML21102A3072021-04-15015 April 2021 OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - 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January 30, 2020 Mr. Zackary W. Rad Director, Regulatory Affairs 1100 Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
FINAL SAFETY EVALUATION FOR NUSCALE POWER, LLC, LICENSING TOPICAL REPORT: TR-0915-17565, REVISION 3, ACCIDENT SOURCE TERM METHODOLOGY By letter dated April 23, 2019, NuScale Power, LLC (NuScale) submitted licensing topical report (TR) TR-0915-17565, Revision 3, Accident Source Term Methodology, dated April 21, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19112A172nonproprietary version), for review and approval by the U.S. Nuclear Regulatory Commission (NRC) in support of the application for the design certification of NuScales small modular reactor (SMR). By letter dated July 31, 2019 (ADAMS Accession No. ML19212A801), NuScale submitted changes to Revision 3 of the TR in response to the staff request for additional information.
The NRC staff has found that TR-0915-17565, Revision 3, as updated by the July 31, 2019, letter acceptable for referencing in licensing applications for the NuScale SMR design to the extent specified and under the conditions and limitations delineated in the enclosed safety evaluation report (SER). The SER defines the basis for acceptance of the TR.
In accordance with the guidance provided on the NRCs TR Web site (http://www.nrc.gov/about-nrc/regulatory/licensing/topical-reports.html), we request that NuScale publish an accepted version of this TR within three months of receipt of this letter. The accepted version shall incorporate this letter and the enclosed safety evaluation between the title page and the abstract. It must be well indexed such that information is readily located. Also, it must contain in its appendices historical review information, such as questions and accepted responses, and original report pages that were replaced. The accepted version shall include an "-A" (designated accepted) following the report identification symbol.
Z. Rad 2 If the NRCs criteria or regulations change so that its conclusion in this letter (that the TR is acceptable) is invalidated, NuScale and/or the applicant referencing the TR will be expected to revise and resubmit its respective documentation or submit justification for the continued applicability of the TR without revision of the respective documentation.
If you have any questions or comments concerning this matter, I can be reached at (301) 415-8013 or via e-mail address at Getachew.Tesfaye@nrc.gov.
Sincerely,
/RA/
Getachew Tesfaye, Senior Project Manager New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No.52-048
Enclosure:
As stated cc: w/o encl.: DC NuScale Power, LLC Listserv
ML20027A105 *via email NRR-043 OFFICE DNRL/NRLB:PM DNRL/NRLB:LA DNRL/NRLB: BC DNRL/NRLB:PM NAME GTesfaye SGreen* MDudek GTesfaye DATE 01/27/2020 01/28/2020 01/28/2020 01/30/2020