|
---|
Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024 US600 DC and SDA 50.46 Exemption - Letter ML23180A1512023-06-29029 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 ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20181A4322020-06-22022 June 2020 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 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 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 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 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 NuScales 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 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
[Table view] Category:License-Application for Combined License (COL) (Amend/Renewal) DKT 52
MONTHYEARML19241A3152019-08-22022 August 2019 LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 3 2019-08-22
[Table view] |
Text
L0-0819-66414 August 22, 2019 Docket No 52-048 U S Nuclear Regulatory Comm1ss1on ATTN Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 SUBJECT NuScale Power, LLC Submittal of the NuScale Standard Plant Design Cert1f1cat1on Apphcat1on, Rev1s1on 3 REFERENCES 1 Letter from NuScale Power, LLC to U S Nuclear Regulatory Comm1ss1on, "NuScale Power, LLC Submittal of the NuScale Standard Plant Design Cert1f1cat1on Application (NRC ProJect No 0769)," dated December 31, 2016 (ML17013A229) 2 Letter from NuScale Power, LLC to U S Nuclear Regulatory Comm1ss1on, "NuScale Power, LLC Submittal of the NuScale Standard Plant Design Cert1f1cat1on Apphcat1on, Rev1s1on 1," dated December 31, 2018 (ML18086A090) 3 Letter from NuScale Power, LLC to U S Nuclear Regulatory Comm1ss1on, "NuScale Power, LLC Submittal of the NuScale Standard Plant Design Cert1f1cat1on Apphcat1on, Rev1s1on 2," dated October 30, 2018 (ML18311A006)
NuScale Power, LLC (NuScale) 1s pleased to submit to the U S Nuclear Regulatory Comm1ss1on (NRC) Rev1s1on 3 of the NuScale Standard Plant Design Cert1f1cat1on Application (DCA) in accordance with the requirements of 10 CFR 52, Subpart B, Standard Design Cert1f1cat1ons NuScale requests NRC review, approval, and granting of standard design cert1f1cat1on for the NuScale Standard Plant Design Rev1s1on 3 of the NuScale DCA includes the following parts Part 1, "General and Financial Information" - Part 1 provides general and financial information in accordance with the requirements of 10 CFR 52 46 and pursuant to 10 CFR 50 33(a) through (c) and (J)
Part 2, Tier 1 and 2, "Final Safety Analysis Report" - Part 2, Tier 1 and 2 provide the NuScale Final Safety Analysis Report in accordance with 10 CFR 52 47(a)
Part 3, "Applicant's Environmental Report - Standard Design Cert1f1cation" - Part 3 provides the NuScale Environmental Report in accordance with 10 CFR 52 47(b)(2) as required by 10 CFR 51 55 Part 4, "Technical Spec1f1cat1ons" - Part 4 provides the NuScale Technical Spec1f1cat1ons and Bases in accordance with 10 CFR 52 47(a)(11), the Technical Spec1f1cat1ons and Bases are referenced in Part 2, Tier 2, Chapter 16 Part 5, "Emergency Plans" - Emergency plans are not applicable to design cert1f1cat1on appl1cat1ons and, therefore, not provided in this application Part 6, "Security Plans" - Security plans are not applicable to design cert1f1cat1on applications and, therefore, are not provided in this application Part 7, "Exemptions" - Part 7 provides exemption requests necessary to accommodate the unique safety features of the NuScale Power Plant
)
NuScale Power, LLC 1100 NE Circle Blvd , Suite 200 Corvalhs, Oregon 97330 Office 541 ~60 0500 Fax 541 207 3928 www nuscalepower com '
L0-0819-66414 Page 2 of 2 08/22/2019 Part 8, "License Cond1t1ons, Inspections, Tests, Analyses & Acceptance Criteria" (ITAAC) have been developed in accordance with 10 CFR 52 47(b)(1) The ITAAC are located in Chapters 2 and 3 of Part 2, Tier 1 and are based on information found in Part 2, Tier 2 The description of the process used to develop the ITAAC 1s provided in Part 2, Tier 2, FSAR Section 14 3 License cond1t1ons are not applicable to the design cert1f1catlon applications Part 9, "Withheld Information" - Part 9 1dent1f1es the location of security-related information within the FSAR that 1s to be withheld from public disclosure in accordance with 10 CFR 2 390 Part 10, "Quality Assurance Program Description" - In accordance with 10 CFR 52 47(a)(19), NuScale Topical Report NP-TR-1010-859-A, Rev1s1on 4, 1s referenced in Part 2, Tier 2, Section 17 5 The DCA Rev1s1on 3 1s being submitted electronically as Enclosures 1 and 2 on two d1g1tal versatile discs (DVDs)
- Enclosure 1 (DVD 1) includes certain information, designated in accordance with NRC guidance as sens1t1ve unclass1f1ed nonsafeguards information (SUNSI) and referred to as security-related information (SRI), that 1s to be withheld from public disclosure under 10 CFR 2 390
- Enclosure 2 (DVD 2) omits the SUNSI/SRI mentioned above and 1s suitable for pubhc disclosure Please contact Thomas A Bergman, Vice President, Regulatory Affairs at 541-360-0740 1f you have any questions This letter makes no regulatory commitments and no rev1s1ons to any existing regulatory commitments
\
Sincerely, 21=:-s~:n§fj-..
Vice President, Regulatory Affairs NuScale Power, LLC Enclosure 1 DVD 1, NuScale Standard Plant Design Cert1f1cat1on Application Rev1s1on 3, Non-Public Vers1on-W1thhold Under 10 CFR 2 390 Enclosure 2 DVD 2, NuScale Standard Plant Design Cert1f1cat1on Application Rev1s1on 3, Public Vers1on-N uScale Non proprietary NuScale Power, LLC 1100 NE Circle Blvd, Suite 200 Coivalhs, Oregon 97330 Office 5413600500 Fax 5412073928 www nuscalepower com