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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
US600 DC and SDA 50.46 Exemption - Letter
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LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3)
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OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor
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Final Safety Evaluation Report for the NuScale Standard Plant Design
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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
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Area of Focus - Boron Redistribution
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LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application
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LLC, Submittal of Environmental Report: Revision Status
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LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020
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OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance
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LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0
ML20181A2702020-06-22022 June 2020
Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
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Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter)
ML20198M3922020-06-19019 June 2020
LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1
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Letter to NuScale Requesting -A for TR-0716-50350
ML20150C5172020-05-29029 May 2020
LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0
ML20150E1772020-05-29029 May 2020
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, Revision 0
ML20150C8812020-05-29029 May 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0
ML20149M1192020-05-28028 May 2020
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ML20141L8082020-05-20020 May 2020
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ML20141N0122020-05-20020 May 2020
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ML20141L8162020-05-20020 May 2020
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ML20141M7642020-05-20020 May 2020
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ML20141L7872020-05-20020 May 2020
LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4
ML20141M1142020-05-20020 May 2020
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ML20141L8042020-05-20020 May 2020
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ML20128J3162020-05-18018 May 2020
OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring
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LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0
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OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology
ML20099H0802020-04-0808 April 2020
LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to NuScales EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0
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Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items
ML20097F1922020-04-0606 April 2020
Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0
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LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0
ML20092L8992020-04-0101 April 2020
LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4
ML20072M6682020-03-30030 March 2020
Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content
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LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0
ML20057D9002020-03-0606 March 2020
Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant
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
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0
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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February 28, 2019 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC.
1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
LETTER TO NUSCALE POWER, LLC, REGARDING REQUEST TO LOCATE SAFEGUARDS INFORMATION AT STRUCTURAL INTEGRITY ASSOCIATES AND TO REMOVE SAFEGUARDS INFORMATION FROM ANATECH, INC.
Dear Mr. Bergman:
On June 2, 2010, the U.S. Nuclear Regulatory Commission (NRC) issued Order Imposing Safeguards Information (SGI) Protection Requirements and Fingerprinting and Criminal History Records Check Requirements for Access to Safeguards Information (EA-10-073) (AgencyWide Documents and Access Management System (ADAMS) ML101600588). EA-10-073 included restrictions on the storage and sharing of the information designated SGI by the Order.
Specifically, Section lll.A.2 of EA-10-073 requires written NRC approval of any additional facilities in which NuScale Power, LLC., (NuScale) intends to store the information designated SGI by the Order listed above.
The NRC staff received NuScales letter dated February 22, 2019, entitled, NuScale Power, LLC, Request to Locate Safeguards Information at Structural Integrity Associates and to Remove SGI from ANATECH, Inc., (ML19010A401) requesting approval to store SGI, including Aircraft Impact Analysis (AIA), at the Structural Integrity Associates (SIA) facility located at 9710 Scranton Road, Suite 300, San Diego, CA 92121.
In the request, it was stated that the previously approved facility, located at 5435 Oberlin Drive, San Diego, CA 92121, would no longer be used, and should be removed from the list of NRC approved SGI storage facilities that are under the purview of NuScale Power, LLC. Additionally, the request stated that on November 14, 2018, the NuScale Power, LLC, Reviewing Official had inspected the SIA physical security infrastructure and associated procedural documents of the SIA SGI program. The outcome of that inspection, as stated in NuScales letter, concluded that the day-to-day protection procedures for SGI and security infrastructure, provided by SIA, were equal to those provided by NuScale.
Based on the information provided by NuScale, the staff has determined that the SIA facility, listed above, meets the requirements for storage of SGI thats governed by EA-10-073.
Accordingly, the request to store SGI at the SIA facility is approved.
In keeping with NuScales previous request to store SGI at an alternate location, NuScale must modify its NRC-approved security procedures for the protection of SGI, NP-QP-0602-211, to reflect the added storage location. Additionally, NuScale must ensure that its contractor, SIA,
T. Bergman follows and adheres to information security procedures that are consistent with or comparable to NP-QP-0602-211.
NuScale is reminded that the terms of Order EA-10-073 require NRC approval if NuScale intends to provide that SGI to individuals for whom fingerprinting and a Federal Bureau of Investigation criminal history records check was not reasonably expected to yield sufficient criminal history information to form the basis of an informed decision on granting access to SGI.
Should you have any questions, comments or concerns regarding this issue, please contact, Mr. Gregory V. Cranston, Project Manager via email at Gregory.Cranston@nrc.gov or via telephone at (301) 415-0546.
Sincerely,
/RA/
Robert M. Taylor, Director Division of Licensing, Siting, and Environmental Analysis Docket No.: 52-0048 cc: DC NuScale Power, LLC Listserv
ML19056A363 *via email NRO-002 OFFICE NRO/DLSE/LB1:PM NRO/DLSE/LB1:LA NRO/NSIR/ISB:BC NRO/DLSE/LB1:BC NRO/DLSE:D NAME GCranston CSmith DParsons SLee RTaylor (RNorman for)
DATE 02/27/2019 02/26/2019 02/27/2019 02/27/2019 02/28/2019