ML20198M393
From kanterella
Jump to navigation
Jump to search
| ML20198M393 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 07/02/2020 |
| From: | Rad Z NuScale |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20198M390 | List: |
| References | |
| LO-0720-70830 | |
| Download: ML20198M393 (1) | |
Similar Documents at NuScale | |
|---|---|
Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
[Table view]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 Category:License-Application for Design Certification MONTHYEARML20224A5212020-07-29029 July 2020
[Table view]Part 07 - Exemptions - Chapters 01 - 17 (Rev. 5) - Part 07 - Exemptions - Chapters 01 - 17 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 ML20197A4142020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 20 - Mitigation of Beyond-Design-Basis Events - Sections 20.01 - 20.04 (Rev. 4.1) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20197A4322020-06-19019 June 2020 Part 10 - Quality Assurance Program Description (Rev. 4.1) - Part 10 - Quality Assurance Program Description (Rev. 4.1) ML20197A4302020-06-19019 June 2020 Part 09 - Withheld Information (Rev. 4.1) - Part 09 - Withheld Information (Rev. 4.1) ML20197A4282020-06-19019 June 2020 Part 08 - License Conditions, Inspections, Tests, Analyses and Acceptance Criteria (Rev. 4.1) - Part 08 - License Conditions, Inspections, Tests, Analyses and Acceptance Criteria (Rev. 4.1) ML20197A4262020-06-19019 June 2020 Part 07 - Exemptions - Chapters 01 - 17 (Rev. 4.1) - Part 07 - Exemptions - Chapters 01 - 17 (Rev. 4.1) ML20197A4242020-06-19019 June 2020 Part 06 - Security Plans (Rev. 4.1) - Part 06 - Security Plans (Rev. 4.1) ML20197A4222020-06-19019 June 2020 Part 05 - Emergency Plans (Rev. 4.1) - Part 05 - Emergency Plans (Rev. 4.1) ML20197A4202020-06-19019 June 2020 Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants (Rev. 4.1) - Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants - Volume 2 - Bases - Chapters 02 - 03 (Rev. 4.1) ML20197A4192020-06-19019 June 2020 Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants (Rev. 4.1) - Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants - Volume 1 - Specifications - Chapters 01 - 05 (Rev. 4.1) ML20197A4172020-06-19019 June 2020 Part 03 - Applicants Environmental Report - Standard Design Certification (Rev. 4.1) - Part 03 - Applicants Environmental Report - Standard Design Certification - Section 1.0 - Appendix B (Rev. 4.1) ML20197A4152020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 21 - Multi-Module Design Considerations - Sections 21.01 - 21.04 (Rev. 4.1) ML20197A4132020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation - Sections 19.00 - 19.05 (Rev. 4.1) ML20197A4122020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 18 - Human Factors Engineering - Sections 18.00 - 18.12 (Rev. 4.1) ML20197A4112020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 17 - Quality Assurance and Reliability Assurance - Sections 17.01 - 17.06 (Rev. 4.1) ML20197A4102020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 16 - Technical Specifications - Section 16.01 - Technical Specifications (Rev. 4.1) ML20197A4092020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 15 - Transient and Accident Analyses - Sections 15.00 - 15.10 (Rev. 4.1) ML20197A4082020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 14 - Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria - Sections 14.00 - 14.03 (Rev. 4.1) ML20197A4072020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 13 - Conduct of Operations - Sections 13.01 - 13.07 (Rev. 4.1) ML20197A4062020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 12 - Radiation Protection - Sections 12.01 - 12.05 (Rev. 4.1) ML20197A4042020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 10 - Steam and Power Conversion System - Sections 10.01 - 10.04 (Rev. 4.1) ML20197A3842020-06-19019 June 2020 Part 01 - General and Financial Information - Sections 01.01 - 01.04 (Rev. 4.1) - Part 01 - General and Financial Information - Sections 01.01 - 01.04 (Rev. 4.1) ML20197A3862020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 01 - Certified Design Descriptions and Inspections, Tests, Analyses, and Acceptance Criteria - Chapters 01 - 05 (Rev. 4.1) ML20197A3872020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 01 - Introduction and General Description of the Plant - Sections 01.01 - 01.10 (Rev. 4.1) ML20197A3882020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 02 - Site Characteristics and Site Parameters - Sections 02.00 - 02.05 (Rev. 4.1) ML20197A3892020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.01 - 03.06 (Rev. 4.1) ML20197A3902020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 1 - 265 (Rev. 4.1) ML20197A3912020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 266 - 307 (Rev. 4.1) ML20197A3922020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 308 - 345 (Rev. 4.1) ML20197A3932020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 346 - 482 (Rev. 4.1) ML20197A3942020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Des. Cat I Str. - Pgs 1 - 140 (Rev. 4.1) ML20197A3962020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 (Rev. 4.1) ML20197A3952020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Des. Cat I Str. - Pgs 141 - 271 (Rev. 4.1) ML20197A3972020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Appendices 3A - 3C (Rev. 4.1) ML20197A3982020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 04 - Reactor - Sections 04.01 - 04.06 (Rev. 4.1) ML20197A3992020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 05 - Reactor Coolant System and Connecting Systems - Sections 05.01 - 05.04 (Rev. 4.1) ML20197A4002020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 06 - Engineered Safety Features - Sections 06.01 - 06.07 (Rev. 4.1) ML20197A4012020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 07 - Instrumentation and Controls - Sections 07.00 - 07.02 (Rev. 4.1) ML20197A4022020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 08 - Electric Power - Sections 08.01 - 08.04 (Rev. 4.1) ML20197A4032020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 09 - Auxiliary Systems - Section 09.01 - Appendix 9A (Rev. 4.1) ML20197A4052020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 11 - Radioactive Waste Management - Sections 11.01 - 11.06 (Rev. 4.1) ML20036D4442020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 08 - Electric Power - Sections 08.01 - 08.04 ML20036D4422020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 07 - Instrumentation and Controls - Sections 07.00 - 07.02 ML20036D4402020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 06 - Engineered Safety Features - Sections 06.01 - 06.07 ML20036D4392020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 05 - Reactor Coolant System and Connecting Systems - Sections 05.01 - 05.04 ML20036D4382020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 04 - Reactor - Sections 04.01 - 04.06 ML20036D4372020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Appendices 3A - 3C ML20036D4332020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 2020-07-29 |
Text
LO-0720-70830 July 2, 2020 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, dated June 19, 2020
REFERENCE:
Letter from NuScale to NRG, "NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1," dated June 19,2020 On June 30, 2020, the NRC notified NuScale Power, LLC (NuScale) that a revised packing slip is required for NRG Document Control to process the NuScale Standard Plant Design Certification Application (DCA), Revision 4.1 (Reference) into the Agencywide Documents Access and Management System (ADAMS).
This letter responds to the NRC request to resubmit a revised packing slip for the DCA.
NuScale understands that the Submittal Document number is an internal NRC number used by ADAMS to track documents submitted and not the official DCA revision number.
This letter makes no regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions, please contact Liz English at (505) 310-4321 or at eenglish@nuscalepower.com.
Sincerely,
~~
~;;;;Rad Director, Regulatory Affairs NuScale Power, LLC : DVD 1, NuScale Standard Plant Design Certification Application Revision 4.1, Non-Public Version-Withhold under 1 O CFR 2.390 : DVD 2, NuScale Standard Plant Design Certification Application Revision 4.1, Public Version-NuScale Nonproprietary NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
Retrieved from "https://kanterella.com/w/index.php?title=ML20198M393&oldid=4096014"