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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 - Boron Redistribution
ML20195A5872020-07-13013 July 2020
LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors
ML20195C7662020-07-13013 July 2020
LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application
ML20192A3262020-07-10010 July 2020
LLC, Submittal of Environmental Report: Revision Status
ML20198M3932020-07-0202 July 2020
LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020
ML20174A3472020-07-0101 July 2020
OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance
ML20184A2872020-07-0101 July 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0
ML20181A4322020-06-22022 June 2020
Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter)
ML20181A2702020-06-22022 June 2020
Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
ML20198M3922020-06-19019 June 2020
LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1
ML20171A7312020-06-19019 June 2020
LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use
ML20157A2232020-06-0303 June 2020
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
LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33
ML20141L8082020-05-20020 May 2020
LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3
ML20141N0122020-05-20020 May 2020
LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report
ML20141M7642020-05-20020 May 2020
LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3
ML20141L7872020-05-20020 May 2020
LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4
ML20141L8162020-05-20020 May 2020
LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3
ML20141M1142020-05-20020 May 2020
LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3
ML20141L8042020-05-20020 May 2020
LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4
ML20128J3162020-05-18018 May 2020
OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring
ML20133K0882020-05-12012 May 2020
LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0
ML20133J9142020-05-11011 May 2020
LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0
ML20112F4552020-05-0101 May 2020
LLC, Design Certification Application Phases 5 and 6 Review Status
ML20107F8492020-05-0101 May 2020
OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design
ML20104A0792020-04-27027 April 2020
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 Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0
ML20098G2372020-04-0707 April 2020
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
ML20094H6742020-04-0303 April 2020
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
ML20072H3332020-03-0909 March 2020
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
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
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
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
ML20066G2802020-03-0303 March 2020
LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0
ML20066G2882020-02-28028 February 2020
LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0
2023-06-29
[Table view]
Category:Safety Evaluation Report
MONTHYEARML21012A3632021-02-11011 February 2021
Safety Evaluation for NuScale Power, LLC, Control Room Staffing Topical Report TR-0420-69456 Public
ML20199M4082020-07-20020 July 2020
Final SER for NuScale Chapter 15, Transient and Accident Analyses (Public Version)
ML20181A4312020-06-22022 June 2020
Final SER for NuScale TR-0516-49416, Rev 3 (Encl. 1_PUBLIC Version)
ML20181A2682020-06-22022 June 2020
Final SER for NuScale TR-0516-49422, Rev 2 (Encl. 1_PUBLIC Version)
ML20157A2212020-06-0505 June 2020
Final SER for NuScale TR-0716-50350-P, Rod Ejection Accident Methodology, Revision 1 (Letter) & (Encl.1 Public Version)
ML20056C9082020-02-27027 February 2020
Final SER for NuScale Power LLC TR-0716-50351, Areva Method for Evaluation of Fuel Assembly Structural Response to External Applied Forces, Revison 1 (Letter) & (Encl. 1 - Public Version)
ML20049H5442020-02-18018 February 2020
Letter to NuScale NON-LOCA TR SER
ML20049H5422020-02-18018 February 2020
NON-LOCA TR SE Final Redacted (Public)
ML20044E3492020-02-18018 February 2020
Rod Ejection Accident Methodology SER
ML20027A1082020-01-30030 January 2020
Accident Source Term TR Final SER Public
ML20022A1782020-01-22022 January 2020
Design Certification Application - Chapter 9 Phase 4 SER Public
ML19352E7782020-01-21021 January 2020
SER NuScale TR_0516_49417 Stability_Public_Encl 1
ML19336B5932020-01-16016 January 2020
Chapter 4 Phase 4 SER with No Ols
ML19284A3722020-01-13013 January 2020
Chapter P4 SER, Reactor Coolant System and Connecting Systems
ML20013D4372020-01-13013 January 2020
DCA - Safety Evaluation Report with No Open Items for Chapter 1, Introduction and General Discussion.
ML19267A0862020-01-0808 January 2020
Phase 4 Chapter 14 SER
ML19337A7872020-01-0808 January 2020
Phase 4 SE Input for Chapter 3 (Public)
ML19330E0202019-12-27027 December 2019
LLC, Design Certification Application - Phase 4 Chapter 16 Safety Evaluation
ML19352E7752019-12-19019 December 2019
Letter to NuScale Transmitting Final SER TR-0516-49417 Rev 1 Stability
ML19343A0272019-12-18018 December 2019
Phase 4 SER - Chapter 6
ML19182A2412019-12-16016 December 2019
DCA - Chapter 13.6 SE with No Open Items
ML19340A0652019-12-16016 December 2019
DCA - Chapter 18 SER with No Open Items
ML19338B7832019-12-11011 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events - Public SER
ML19169A1312019-12-10010 December 2019
Letter to NuScale Transmitting SER
ML19169A1322019-12-10010 December 2019
Memo to ACRS Transmitting SER
ML19169A3122019-12-0404 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 16, Technical Specifications - Letter
ML19318E3032019-12-0404 December 2019
Chapter 12 Phase 4 SE - Clean Version OGC Reviewed NLO
ML19319A6842019-12-0303 December 2019
Phase 4 SER - Chapter 8
ML19165A2822019-11-27027 November 2019
DCA - Chapter 2 SER with No Open Items
ML19169A2952019-11-26026 November 2019
Memo to ACRS Transmitting SER
ML19169A2902019-11-22022 November 2019
Letter to NuScale Transmitting SER
ML19169A1182019-11-22022 November 2019
Letter to NuScale Transmitting Phase 4 SER for Chapter 8
ML19169A2912019-11-22022 November 2019
Memo to ACRS Transmitting SER
ML19169A2722019-10-23023 October 2019
DCA - Chapter 21 SER with No Open Items
ML19289C1592019-10-18018 October 2019
Dnrl Memo to ACRS - Safety Evaluation for Topical Report, TR-0915-17565
ML19165A2862019-10-17017 October 2019
DCA - Chapter 13 SER with No Open Items
ML19270F2782019-09-27027 September 2019
Public Version of Phase 4 SER for Chapter 7
ML19218A0372019-09-12012 September 2019
Phase 4 SER - Chapter 10
ML19254C8582019-09-11011 September 2019
Non-Proprietary Version - SER for NuScale TR-0516-49417 Evaluation Methodology for Stability Analysis of the NuScale Power Module, Rev 0
ML19169A1412019-09-0909 September 2019
Memo to ACRS Transmitting Chapter 10 (Phase 4) SER
ML19169A1392019-09-0909 September 2019
Letter to NuScale Transmitting Chapter 10 (Phase 4) SER
ML19169A1492019-08-29029 August 2019
Letter to NuScale Transmitting SER with No Open Items for Chapter 11, Radioactive Waste Management.
ML19169A1502019-08-29029 August 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 11, Radioactive Waste Management
ML19240A4422019-08-29029 August 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 11, Radioactive Waste Management - SER
ML19238A0172019-08-23023 August 2019
Preliminary P2 SER NuScale Ch 15 Redacted Version - Clean
ML19233A0712019-08-21021 August 2019
Ser_Areva Seismic Methodology TR-0716-50351_Non_Proprietary
ML19207A3712019-08-0808 August 2019
Chapter 17 Phase 4 SER
ML19224B3762019-08-0808 August 2019
Chapter 17 Phase 4 SER (Public)
ML18220B3132019-04-24024 April 2019
DCA - Chapter 21 - Multi-Module Design Considerations - SE with Open Items
ML19073A0712019-04-19019 April 2019
DCA - Safety Evaluation Report with Open Items - Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors
2021-02-11
[Table view] |
Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION December 19, 2019 Mr. Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
FINAL SAFETY EVALUATION FOR NUSCALE POWER, LLC TOPICAL REPORT TR-0516-49417, REVISION 1, EVALUATION METHODOLOGY FOR STABILITY ANALYSIS OF THE NUSCALE POWER MODULE
Dear Mr. Rad:
By letter dated July 31, 2016, NuScale Power, LLC (NuScale), submitted Topical Report (TR)
TR-0516-49417, Evaluation Methodology for Stability Analysis of the NuScale Power Module, Revision 0, to the U.S. Nuclear Regulatory Commission (NRC) staff for review and approval in support of the application for the design certification of NuScales small modular reactor (SMR).
By letters dated September 17, 2019, and November 22, 2019, NuScale submitted TR-0915-17564, Revision 1, which incorporated changes from requests for additional information responses and corrects a minor error to the TR, respectively.
The NRC staff has found that TR-0516-49417, Revision 1, is 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.
The NRC staff requests that NuScale publish the applicable version(s) of the SER listed above within three months of receipt of this letter. The accepted version of the TR shall incorporate this letter and the enclosed SER and add -A (designated accepted) following the report identification number.
Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.
CONTACT: Bruce M. Bavol, NRR/DNRL 301-415-6715 OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION Z. Rad 2 If the NRC staffs criteria or regulations change, such that the conclusion that the SER is acceptable is invalidated, NuScale and/or the applicant referencing the SER will be expected to revise and resubmit its respective documentation, or submit justification for continued applicability of the SER without revision of the respective documentation.
Prior to placing the public version of this document in the publicly available records component of NRCs Agencywide Documents and Access Management System (ADAMS), the NRC staff requests that NuScale perform a final review of the SER for proprietary or security related information not previously identified. If you believe that any additional information meets the criteria, please identify such information line by line and define the basis pursuant to the criteria established in Title 10 of the Code of Federal Regulations, Part 2, Section 3.90, Public inspections, exemptions, requests for withholding.
If after a ten-day period, if you do not request that all or portions of the SER be withheld from public disclosure, the SER will be made available for public inspection through the publicly available records component of NRCs ADAMS.
If you have any questions or comments concerning this matter, please contact Bruce Bavol at 301-415-6715 or via e-mail address at Bruce.Bavol@nrc.gov.
Sincerely,
/RA/ Bob Caldwell for Anna Bradford, Director Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No.52-048
Enclosures:
- 1. TR-0516-49417 SER (Non-Proprietary)
- 2. TR-0516-49417 SER (Proprietary) cc: DC NuScale Power, LLC Listserv (w/o Enclosure 2)
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
Pkg: ML19352E752 Letter: ML19352E775 Enclosure No. 1: ML19352E778 Enclosure No. 2: ML19352E777 *via email NRR-106 OFFICE DNRL/NRLB: PM DNRL/NRLB: LA DNRL/NRLB: BC DNRL: D NAME BBavol CSmith* MDudek ABradford DATE 12/09/2019 12/05/2019 12/19/2019 12/19/2019