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| | number = ML17264A677 | | | number = ML17264A677 |
| | issue date = 09/27/2017 | | | issue date = 09/27/2017 |
| | title = Audit Plan for the Nuscale SBO Transient Sensitivity Analysis November 2017 | | | title = Audit Plan for the NuScale SBO Transient Sensitivity Analysis November 2017 |
| | author name = Tabatabai O | | | author name = Tabatabai O |
| | author affiliation = NRC/NRO/DNRL/LB1 | | | author affiliation = NRC/NRO/DNRL/LB1 |
| | addressee name = Lee S S | | | addressee name = Lee S |
| | addressee affiliation = NRC/NRO/DNRL/LB1 | | | addressee affiliation = NRC/NRO/DNRL/LB1 |
| | docket = 05200048 | | | docket = 05200048 |
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| =Text= | | =Text= |
| {{#Wiki_filter: September 27, 2017 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Omid Tabatabai, Senior Project Manager /RA/ Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors | | {{#Wiki_filter:September 27, 2017 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Omid Tabatabai, Senior Project Manager /RA/ |
| | Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors |
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| ==SUBJECT:== | | ==SUBJECT:== |
| AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWER'S, LLC STATION BLACKOUT TRANSIENT SENSITIVITY ANALYSIS (CAC NO. RA9030) The purpose of this one-day regulatory audit is for the U.S. Nuclear Regulatory Commission (NRC) staff to (1) review NuScale Power's, LLC (NuScale) Station Blackout transient sensitivity case, and (2) hold discussions with NuScale staff related to specific areas of NuScale design certification application, Tier 2, Section 8.4, "Station Blackout," to determine whether NuScale design meets the applicable regulations. The NRC staff will conduct this audit in accordance with the guidance provided in Office of New Reactors-REG-108, "Regulatory Audits." | | AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWERS, LLC STATION BLACKOUT TRANSIENT SENSITIVITY ANALYSIS (CAC NO. RA9030) |
| The audit will take place at NuScale's Rockville Office and/or via NuScale Electronic Reading Room. The audit is currently scheduled for November 8, 2017. The audit plan is provided in . | | The purpose of this one-day regulatory audit is for the U.S. Nuclear Regulatory Commission (NRC) staff to (1) review NuScale Powers, LLC (NuScale) Station Blackout transient sensitivity case, and (2) hold discussions with NuScale staff related to specific areas of NuScale design certification application, Tier 2, Section 8.4, Station Blackout, to determine whether NuScale design meets the applicable regulations. The NRC staff will conduct this audit in accordance with the guidance provided in Office of New Reactors-REG-108, Regulatory Audits. |
| Docket No. 52-048 | | The audit will take place at NuScales Rockville Office and/or via NuScale Electronic Reading Room. The audit is currently scheduled for November 8, 2017. The audit plan is provided in . |
| | Docket No. 52-048 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Audit Plan cc w/encl.: DC NuScale Power LLC Listserv | | Audit Plan cc w/encl.: DC NuScale Power LLC Listserv CONTACT: Omid Tabatabai, NRO/DNRL 301-415-6616 |
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| CONTACT: Omid Tabatabai, NRO/DNRL 301-415-6616
| | ML17264A677 *via email NRO-002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRR/DE/EENB: BC* NRO/DNRL/LB1: PM Duc Nguyen (for NAME OTabatabai SGreen OTabatabai (sign) |
| | | TMartinez-Navedo) |
| ==SUBJECT:==
| | DATE 09/21/2017 09/22/2017 09/19/2017 09/27/2017 U.S. NUCLEAR REGULATORY COMMISSION AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWER, LLCS STATION BLACKOUT SENSITIVITY ANALYSIS (DOCKET NO. 52-048) |
| AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWER, LLC STATION BLACKOUT TRANSIENT SENSITIVITY ANALYSIS (CAC NO. RA9030) DATED: 9/27/2017 DISTRIBUTION: PUBLIC Reading File SLee, NRO FSacko, NRR GCranston, NRO OTabatabai, NRO TMartinezNavedo, NRR RidsOgcMailCenter RidsAcrsAcnwMailCenter
| | AUDIT PLAN Applicant: NuScale Power, LLC Location: U. S. Nuclear Regulatory Commission (NRC) Headquarters via NuScale Powers, LLC (NuScale) Electronic Reading Room and at NuScales Office in Rockville, Maryland, as necessary Reviewers: Fanta Sacko (Audit Team Leader) |
| | | Swagata Som, Senior Electrical Engineer Sheila Ray, Senior Electrical Engineer Project Manager: Omid Tabatabai NuScale Contacts: Darrell Gardner, Steve Mirsky Audit Dates/Times: November 8, 2017 8:30 a.m. - 4:00 p.m. |
| ADAMS Accession No.:ML17264A677 *via email NRO-002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRR/DE/EENB: BC* NRO/DNRL/LB1: PM NAME OTabatabai SGreen Duc Nguyen (for TMartinez-Navedo) OTabatabai (sign)
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| DATE 09/21/2017 09/22/2017 09/19/2017 09/27/2017 OFFICIAL RECORD COPY Enclosure U.S. NUCLEAR REGULATORY COMMISSION AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWER, LLC'S STATION BLACKOUT SENSITIVITY ANALYSIS (DOCKET NO. 52-048) AUDIT PLAN Applicant: NuScale Power, LLC Location: U. S. Nuclear Regulatory Commission (NRC) Headquarters via NuScale Power's, LLC (NuScale) Electronic Reading Room and at NuScale's Office in Rockville, Maryland, as necessary Reviewers: Fanta Sacko (Audit Team Leader) Swagata Som, Senior Electrical Engineer Sheila Ray, Senior Electrical Engineer Project Manager: Omid Tabatabai NuScale Contacts: Darrell Gardner, Steve Mirsky Audit Dates/Times: November 8, 2017 8:30 a.m. - 4:00 p.m. | |
| BACKGROUND AND REGULATORY BASIS: | | BACKGROUND AND REGULATORY BASIS: |
| In the design certification application (DCA), Final Safety Analysis Report (FSAR) Tier 2, Section 8.4.3, the applicant states that a Station Blackout (SBO) transient sensitivity case that considered a simultaneous loss of all alternating current and direct current (DC) power was evaluated and demonstrates that the NuScale Power Plant design does not rely on DC power from the highly reliable DC Power System (EDSS) to meet the requirements of Title10 Code of Federal Regulations (CFR) 50.63, "Loss of all alternating current power." In Request for Additional Information (RAI)-8824, Question 08.04-1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML17146B298), the staff requested additional information regarding the assumptions and a summary of the SBO transient sensitivity evaluation that NuScale performed to show compliance with 10 CFR 50.63. In response to RAI-8824, Question 08.04-1 (ADAMS Accession No. ML17179A979), dated June 28, 2017, the applicant stated: "Consistent with the definition of a Station Blackout in 10 CFR 50.2, "Definitions" the SBO transient analysis identified in FSAR Section 8.4 assumes operation of the EDSS during the event, which in part forms the basis for compliance with 10 CFR 50.63. FSAR Section 8.4 includes the assumptions and a summary for the analysis of record. The model and assumptions for the sensitivity case are the same as the base case except the sensitivity case includes a simultaneous failure of the EDSS at the outset of the event, which represents an additional failure that is precluded by the SBO definition. Consequently, the sensitivity evaluation is not used to show compliance with 10 CFR 50.63, and NuScale does not believe that the results of the sensitivity study should be included in the FSAR. The analysis that documents the assumptions and results of the sensitivity case can be made available for NRC audit upon request." | | In the design certification application (DCA), Final Safety Analysis Report (FSAR) Tier 2, Section 8.4.3, the applicant states that a Station Blackout (SBO) transient sensitivity case that considered a simultaneous loss of all alternating current and direct current (DC) power was evaluated and demonstrates that the NuScale Power Plant design does not rely on DC power from the highly reliable DC Power System (EDSS) to meet the requirements of Title10 Code of Federal Regulations (CFR) 50.63, Loss of all alternating current power. |
| AUDIT PURPOSE: The purpose of this one-day regulatory audit is for the NRC staff to (1) review NuScale's SBO transient sensitivity case and (2) hold discussions with NuScale staff related to specific areas of NuScale FSAR, Section 8.4, "Station Blackout," and the applicant's methodology, to determine whether NuScale design DCA meets the applicable regulations, i.e. 10 CFR 50.63. Specifically, 1. The NRC staff seeks clarification of NuScale's assumptions and methodology on the SBO transient analysis. 2. The NRC staff seeks clarification on the SBO sensitivity case which demonstrates that the NuScale design does not rely on DC power from the EDSS to meet the requirements of 10 CFR 50.63. The information to be reviewed is intended to provide direct support for the safety conclusions that apply to the NuScale DCA under 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants". Specifically, the information to be reviewed will provide support to the staff's review regarding NuScale's assertion that the design does not rely on DC power from the EDSS to meet 10 CFR 50.63. The information to be assessed is intended to augment the NRC staff's understanding and verification. Furthermore, this information will be referenced in the NRC staff's final safety evaluation report (FSER) on the methodology and assumptions of the NuScale DCA, regarding how the electrical systems meet the applicable regulations.
| | In Request for Additional Information (RAI)-8824, Question 08.04-1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML17146B298), the staff requested additional information regarding the assumptions and a summary of the SBO transient sensitivity evaluation that NuScale performed to show compliance with 10 CFR 50.63. In response to RAI-8824, Question 08.04-1 (ADAMS Accession No. ML17179A979), dated June 28, 2017, the applicant stated: |
| | Consistent with the definition of a Station Blackout in 10 CFR 50.2, Definitions the SBO transient analysis identified in FSAR Section 8.4 assumes operation of the EDSS during the event, which in part forms the basis for compliance with 10 CFR 50.63. FSAR Section 8.4 includes the assumptions and a summary for the analysis of record. The model and assumptions for the sensitivity case are the same as the base case except the sensitivity case includes a simultaneous failure of the EDSS at the outset of the event, which represents an additional Enclosure |
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| The NRC staff will conduct this audit in accordance with the guidance provided in Office of New Reactors Office (NRO) Instruction, NRO-REG-108, "Regulatory Audits." | | failure that is precluded by the SBO definition. Consequently, the sensitivity evaluation is not used to show compliance with 10 CFR 50.63, and NuScale does not believe that the results of the sensitivity study should be included in the FSAR. The analysis that documents the assumptions and results of the sensitivity case can be made available for NRC audit upon request. |
| INFORMATION AND DOCUMENTS NECESSARY FOR THE AUDIT: 1. SBO transient sensitivity case 2. An overview presentation of the document(s) to the NRC staff by NuScale subject matter experts. AUDIT TEAM ASSIGNMENTS: The audit team is comprised of the following NRC staff. These individuals will review the relevant documents that are related to the audit and will be available at the time of the audit: | | AUDIT PURPOSE: |
| | The purpose of this one-day regulatory audit is for the NRC staff to (1) review NuScales SBO transient sensitivity case and (2) hold discussions with NuScale staff related to specific areas of NuScale FSAR, Section 8.4, Station Blackout, and the applicants methodology, to determine whether NuScale design DCA meets the applicable regulations, i.e. 10 CFR 50.63. Specifically, |
| | : 1. The NRC staff seeks clarification of NuScales assumptions and methodology on the SBO transient analysis. |
| | : 2. The NRC staff seeks clarification on the SBO sensitivity case which demonstrates that the NuScale design does not rely on DC power from the EDSS to meet the requirements of 10 CFR 50.63. |
| | The information to be reviewed is intended to provide direct support for the safety conclusions that apply to the NuScale DCA under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. Specifically, the information to be reviewed will provide support to the staffs review regarding NuScales assertion that the design does not rely on DC power from the EDSS to meet 10 CFR 50.63. The information to be assessed is intended to augment the NRC staffs understanding and verification. Furthermore, this information will be referenced in the NRC staffs final safety evaluation report (FSER) on the methodology and assumptions of the NuScale DCA, regarding how the electrical systems meet the applicable regulations. |
| | The NRC staff will conduct this audit in accordance with the guidance provided in Office of New Reactors Office (NRO) Instruction, NRO-REG-108, Regulatory Audits. |
| | INFORMATION AND DOCUMENTS NECESSARY FOR THE AUDIT: |
| | : 1. SBO transient sensitivity case |
| | : 2. An overview presentation of the document(s) to the NRC staff by NuScale subject matter experts. |
| | AUDIT TEAM ASSIGNMENTS: |
| | The audit team is comprised of the following NRC staff. These individuals will review the relevant documents that are related to the audit and will be available at the time of the audit: |
| * Tania Martinez Navedo, Electrical Engineering Branch, Acting Chief | | * Tania Martinez Navedo, Electrical Engineering Branch, Acting Chief |
| * Omid Tabatabai, Licensing Branch 1, Senior Project Manager | | * Omid Tabatabai, Licensing Branch 1, Senior Project Manager |
| * Fanta Sacko (Audit Team Leader) | | * Fanta Sacko (Audit Team Leader) |
| * Swagata Som, Senior Electrical Engineer | | * Swagata Som, Senior Electrical Engineer |
| * Sheila Ray, Senior Electrical Engineer AUDIT ACTIVITIES AND DELIVERABLES: The NRC audit team review will cover the technical areas identified previously in this audit plan. The NRC Project Manager will coordinate with NuScale in advance of audit activities to verify specific documents, identify any changes to the audit schedule and requested documents, and record the participants of the audit (NRC and NuScale staff). | | * Sheila Ray, Senior Electrical Engineer |
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| | AUDIT ACTIVITIES AND DELIVERABLES: |
| | The NRC audit team review will cover the technical areas identified previously in this audit plan. |
| | The NRC Project Manager will coordinate with NuScale in advance of audit activities to verify specific documents, identify any changes to the audit schedule and requested documents, and record the participants of the audit (NRC and NuScale staff). |
| The NRC staff acknowledges the proprietary and/or sensitive nature of the information requested and will handle appropriately throughout the audit. While the NRC staff will take notes, the NRC staff will not remove hard copies or electronic files from the audit site(s). | | The NRC staff acknowledges the proprietary and/or sensitive nature of the information requested and will handle appropriately throughout the audit. While the NRC staff will take notes, the NRC staff will not remove hard copies or electronic files from the audit site(s). |
| At the completion of the audit, the audit team will issue an audit summary within 90 days that will be declared and entered as an official agency record in the NRC's ADAMS records management system, in accordance with NRO-REG-108. The audit outcome may be used to assist the NRC staff in the issuance of request for additional information for the licensing review of the NuScale Design Certification Document and to identify any additional information to be submitted on the docket in support of the NRC staff's preparation of the FSER. | | At the completion of the audit, the audit team will issue an audit summary within 90 days that will be declared and entered as an official agency record in the NRCs ADAMS records management system, in accordance with NRO-REG-108. The audit outcome may be used to assist the NRC staff in the issuance of request for additional information for the licensing review of the NuScale Design Certification Document and to identify any additional information to be submitted on the docket in support of the NRC staffs preparation of the FSER.}} |
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MONTHYEARML17179A9792017-06-28028 June 2017 LLC Response to NRC Request for Additional Information No. 33 (Erai No. 8824) on the NuScale Design Certification Application Project stage: Response to RAI ML17264A6772017-09-27027 September 2017 Audit Plan for the NuScale SBO Transient Sensitivity Analysis November 2017 Project stage: Other 2017-06-28
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Category:Audit Plan
MONTHYEARML20059N6872020-03-0202 March 2020 Regulatory Audit Plan for NuScale DCA Chapters 6, 7, and 15 ML19270G6762019-11-22022 November 2019 Audit Summary for the Regulatory Audit of NuScale Power, LLC, Final Safety Analysis Report Chapter 15, Transient and Accident Analyses, (Memo) ML19284A5162019-11-22022 November 2019 Audit Summary for the Regulatory Audit of NuScale Power, LLC, Final Safety Analysis Report Chapter 15, Transient and Accident Analyses. (Encl. 1 Non-Proprietary Version) ML19255F0222019-09-12012 September 2019 Audit of NuScale Documents Related to Change in Iab Operating Range and Cram ML19225B5942019-08-22022 August 2019 Audit Plan for the Regulatory Audit of the NuScale Power, LLC, Seismic Category I Equipment and Environment Qualification of Electrical Equipment Specifications ML19207A2992019-07-30030 July 2019 Audit Plan for the Regulatory Audit of the NuScale Power, LLC, Containment Isolation Valves and Reactor Safety Valves ML19203A2492019-07-24024 July 2019 Audit Plan for the Regulatory Audit of the NuScale Power, LLC, Component Design Specifications ML19158A4442019-06-12012 June 2019 Audit Plan for the Audit of Nuscale Power, Llc., Helical Steam Generator Tube Modal Testing ML19150A3212019-06-0505 June 2019 Audit Plan for the Regulatory Audit of NuScale Power, LLC Human Factors Engineering Verification and Validation Results Summary Report Supporting Analyses and Confirmatory Item Closure Verification ML19150A2842019-05-31031 May 2019 Regulatory Audit Plant for the Audit of NuScale Documents Associated with Accident Source Term and Pass Exemption Request ML19116A2152019-04-29029 April 2019 Plan for Regulatory Audit of NuScale Power, LLC, Component Design ML19108A4002019-04-26026 April 2019 Hfe ITAAC and Di Implementation Review Audit Plan ML19067A1432019-03-20020 March 2019 Plan for Regulatory Audit of Nuscale Power, LLC, Emergency Core Cooling System Valve Design Demonstration Testing and Follow-Up Items ML19060A2712019-03-0404 March 2019 Phase 4 Audit Plan for the Audit of NuScale Power, Llc., Documents Related to Reactor Internals Comprehensive Vibration Assessment Program ML19018A1122019-01-28028 January 2019 Regulatory Audit of Nuscale Design Certification Application, Final Safety Analysis Report, Tier 1 and Tier 2, Section 3.5.3 Barrier Design Procedures. ML19058A5232019-01-27027 January 2019 Audit Plan - Neutron Fluence Bioshield-Containment Final Rev 1 ML18348A9862019-01-0808 January 2019 Regulatory Audit Plan for the Audit of Nuscale Documents Associated with EQ and Radiation Protection Neutron Source Term ML18348B0762019-01-0707 January 2019 Audit Plan - Nuscale Chapter 20 - RAI 9486 ML19008A3552018-12-28028 December 2018 Audit Plan for the Regulatory Audit of Nuscale Power, LLC, Topical Report Loss of Coolant Accident Evaluation Model. ML19004A0982018-12-20020 December 2018 Audit Plan for the Regulatory Audit of Nuscale Power, LLC Design Certification Application, Chapter 15, Transient and Accident Analyses ML18344A1512018-12-13013 December 2018 Phase 2 Audit Plan for the Audit of NuScale Power, LLC Documents Related to Reactor Internals Seismic Analysis ML18324A5512018-11-26026 November 2018 Audit Plan for Regulatory Audit of Nuscale Design Certification Application, Final Safety Analysis Report, Tier 2, Section 3.7 Seismic Design and Section 3.8 Design of Category I Structures ML18323A4452018-11-20020 November 2018 Audit Plan for the Regulatory Audit of NuScale Power, LLC Topical Report TR-0516-49416, Non-Loss-Of-Coolant Accident Analysis Methodology, Revision 1 - Memo ML18284A2592018-10-12012 October 2018 Audit Plan for the Second Regulatory Audit of Environmental Report for NuScale Power LLC Regarding the Severe Accident Mitigation Design Alternative Analysis ML18243A2962018-09-0606 September 2018 Audit Plan for the Phase II Regulatory Audit of the Design Basis Failed Fuel Fraction for NuScale Power, LLC Design Certification Application ML18236A5332018-08-28028 August 2018 Phase 2 Audit Plan for the Audit of Nuscale Power, LLC Documents Related to Reactor Internals Comprehensive Vibration Assessment Program ML18235A5092018-08-28028 August 2018 Audit Plan for the Follow-Up Regulatory Audit of Nuscale Power, LLC; Sections 3.9.4, Control Rod Drive System, and 4.6, Functional Design of Control Rod Drive System ML18114A0552018-08-25025 August 2018 Phase 2 Audit Plan for Design Specifications Meb May - June 2018 ML18229A1142018-08-22022 August 2018 Audit Plan for Regulatory Audit of Nuscale Power, LLC Design Documents for Containment Isolation Valves and Reactor Safety Valves ML18177A0872018-06-28028 June 2018 Addenda to the NuScale Containment and Ventilation System Audit Plan ML18158A1642018-06-12012 June 2018 Audit Plan for the Phase II Regulatory Audit of the Pool Leakage Detection System for the Ultimate Heat Sink for Nuclear Power, LLC ML18144A7582018-06-0404 June 2018 June 26-28 2018 NuScale Hfe Audit Plan ML18074A0792018-03-14014 March 2018 Audit Plan for NuScale Computer Codes Section 3.9.1 March - April 2018 ML18067A1292018-03-0808 March 2018 Audit Plan NuScale Chapter 4 ML18053A2162018-03-0505 March 2018 2018 SPRA-NuScale Audit Plan ML18060A0682018-03-0505 March 2018 Audit Plan for the Regulatory Audit of ECCS Valves Design and FMEA Analysis, March - May 2018 ML17356A1202017-12-27027 December 2017 Audit Plan for Nuscale Power, LLC, Final Safety Aanalysis Report - Chapter 20, Mitigation of Beyond Design-Basis Events ML17264A6772017-09-27027 September 2017 Audit Plan for the NuScale SBO Transient Sensitivity Analysis November 2017 ML17255A8992017-09-26026 September 2017 June 2017 Chapter 8 Audit Report 2020-03-02
[Table view] Category:Memoranda
MONTHYEARML24004A0472024-01-31031 January 2024 U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss NuScales Us600 Exemption Request ML20274A1082020-09-30030 September 2020 Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics ML20199M1492020-08-19019 August 2020 Memo Transmitting Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System ML20219A4112020-08-10010 August 2020 Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851 ML20210M0772020-07-28028 July 2020 Memo - Category 1 Public Meeting - Audit Exit NuScale Emergency Core Cooling System Boron Redistribution Issue and Applicable Design Changes ML20160A2472020-07-28028 July 2020 Audit Summary Memo NuScale ECCS Boron Redistribution Issue ML20176A1582020-07-10010 July 2020 Audit Summary 2019 Memo NuScale Chapter 15 ML20108F5082020-05-27027 May 2020 Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR ML20140A1892020-05-19019 May 2020 Public Meeting Summary May 14, 2020, NuScale Boron Redistribution Issue ML20114E2162020-05-0404 May 2020 Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0192020-04-27027 April 2020 Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0392020-04-23023 April 2020 Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process ML20097C2292020-04-0707 April 2020 Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution ML20072M7982020-03-19019 March 2020 Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan ML20076D8852020-03-16016 March 2020 Summary Report for the January 2019 Regulatory Audit of NuScale Chapter 20 ML20072K5232020-03-11011 March 2020 Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048) ML20059N6872020-03-0202 March 2020 Regulatory Audit Plan for NuScale DCA Chapters 6, 7, and 15 ML20054A0602020-02-28028 February 2020 Regulatory Audit Report for NuScale DCA Inadvertent Actuation Block (Iab) Operating Range Change ML20044E3522020-02-18018 February 2020 Memo to ACRS Rod Ejection Accident Methodology SER ML20049H1872020-02-18018 February 2020 Memo to ACRS Rea NON-LOCA TR SE ML20049H5442020-02-18018 February 2020 Letter to NuScale NON-LOCA TR SER ML20042E0242020-02-12012 February 2020 LOCA Topical Report Phase IV Audit Report - Public ML20042E0392020-02-12012 February 2020 NON-LOCA Topical Report Phases 3 and 4 Audit Report ML20010D1312020-01-16016 January 2020 Audit Summary Memo NuScale LOCA TR ML19345E9362020-01-13013 January 2020 Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference ML19340A9712020-01-13013 January 2020 U.S. Nuclear Regulatory Commission Report of the Regulatory Follow-Up Audit Performed Between May 1, 2019, Through September 19, 2019, Regarding the Nuscale Stress and Fatigue Analysis of Major Design Components (Public) ML20006G4202020-01-0808 January 2020 ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapters 2, 8 and 12 ML19343C7562020-01-0808 January 2020 Generator Tube - Siet Audit Report (Public) ML20006G5752019-12-20020 December 2019 Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 8, Electric Power ML19331A3972019-12-20020 December 2019 U.S. Nuclear Regulatory Commission Report of the Regulatory follow-up Audit Performed Between 8/22/19 - 9/24/19, Regarding NuScale Power, Seismic Category I Equipment and Environment Qualification of Electrical Equipment Specifications ML19340A0152019-12-20020 December 2019 U.S. Nuclear Regulatory Commission'S Report of the Regulatory Audit Performed Between March 4, 2019, Through September 10, 2019, for Nuscale Power, LLC, Regarding Nuscale'S Power Module Leakage Flow Instability Analysis - Public Memo ML20006G4892019-12-19019 December 2019 Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters ML19340A0192019-12-19019 December 2019 U.S. Nuclear Regulatory Commission Report - Regulatory Audit Between 03/20/19 - 10/09/19 - Emergency Core Cooling System Valve Design Demonstration Testing and Follow-Up Items NuScale Power, LLC, Standard Plant Design Certification ML20006G7002019-12-19019 December 2019 Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 12, Radiation Protection ML19143A1042019-12-12012 December 2019 DCA - Safety Evaluation with No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors - Memo ML19168A1382019-12-12012 December 2019 LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 3, Design of Structures, Systems, Components and Equipment ML19169A2992019-12-11011 December 2019 Memo to ACRS Transmitting SER - Chapter 15 ML19169A1322019-12-10010 December 2019 Memo to ACRS Transmitting SER ML19165A2792019-12-0909 December 2019 Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 1, Introduction and General Discussion ML19168A1682019-12-0909 December 2019 Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 4, Reactor - Memo ML19168A2002019-12-0909 December 2019 Memo to ACRS Transmitting SER - Chapter 6 ML19169A3142019-12-0404 December 2019 LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 16, Technical Specifications - Memo ML19169A3322019-12-0404 December 2019 LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events - Memo ML19169A2952019-11-26026 November 2019 Memo to ACRS Transmitting SER ML19319C2322019-11-26026 November 2019 U.S. Nuclear Regulatory Commission Summary Report of Regulatory follow-up Audit of Design Documents for NuScale Containment Isolation Valves and Reactor Safety Valves ML19270G6762019-11-22022 November 2019 Audit Summary for the Regulatory Audit of NuScale Power, LLC, Final Safety Analysis Report Chapter 15, Transient and Accident Analyses, (Memo) ML19169A2912019-11-22022 November 2019 Memo to ACRS Transmitting SER ML19169A1192019-11-22022 November 2019 Memo to ACRS Transmitting Phase 4 SER for Chapter 8 ML19162A2732019-11-15015 November 2019 LLC, Design Certification Application Memo - Safety Evaluation with No Open Items for Chapter 18, Human Factors Engineering ML19162A0962019-11-13013 November 2019 Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters 2024-01-31
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September 27, 2017 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Omid Tabatabai, Senior Project Manager /RA/
Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors
SUBJECT:
AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWERS, LLC STATION BLACKOUT TRANSIENT SENSITIVITY ANALYSIS (CAC NO. RA9030)
The purpose of this one-day regulatory audit is for the U.S. Nuclear Regulatory Commission (NRC) staff to (1) review NuScale Powers, LLC (NuScale) Station Blackout transient sensitivity case, and (2) hold discussions with NuScale staff related to specific areas of NuScale design certification application, Tier 2, Section 8.4, Station Blackout, to determine whether NuScale design meets the applicable regulations. The NRC staff will conduct this audit in accordance with the guidance provided in Office of New Reactors-REG-108, Regulatory Audits.
The audit will take place at NuScales Rockville Office and/or via NuScale Electronic Reading Room. The audit is currently scheduled for November 8, 2017. The audit plan is provided in .
Docket No.52-048
Enclosure:
Audit Plan cc w/encl.: DC NuScale Power LLC Listserv CONTACT: Omid Tabatabai, NRO/DNRL 301-415-6616
ML17264A677 *via email NRO-002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRR/DE/EENB: BC* NRO/DNRL/LB1: PM Duc Nguyen (for NAME OTabatabai SGreen OTabatabai (sign)
TMartinez-Navedo)
DATE 09/21/2017 09/22/2017 09/19/2017 09/27/2017 U.S. NUCLEAR REGULATORY COMMISSION AUDIT PLAN FOR THE REGULATORY AUDIT OF NUSCALE POWER, LLCS STATION BLACKOUT SENSITIVITY ANALYSIS (DOCKET NO.52-048)
AUDIT PLAN Applicant: NuScale Power, LLC Location: U. S. Nuclear Regulatory Commission (NRC) Headquarters via NuScale Powers, LLC (NuScale) Electronic Reading Room and at NuScales Office in Rockville, Maryland, as necessary Reviewers: Fanta Sacko (Audit Team Leader)
Swagata Som, Senior Electrical Engineer Sheila Ray, Senior Electrical Engineer Project Manager: Omid Tabatabai NuScale Contacts: Darrell Gardner, Steve Mirsky Audit Dates/Times: November 8, 2017 8:30 a.m. - 4:00 p.m.
BACKGROUND AND REGULATORY BASIS:
In the design certification application (DCA), Final Safety Analysis Report (FSAR) Tier 2, Section 8.4.3, the applicant states that a Station Blackout (SBO) transient sensitivity case that considered a simultaneous loss of all alternating current and direct current (DC) power was evaluated and demonstrates that the NuScale Power Plant design does not rely on DC power from the highly reliable DC Power System (EDSS) to meet the requirements of Title10 Code of Federal Regulations (CFR) 50.63, Loss of all alternating current power.
In Request for Additional Information (RAI)-8824, Question 08.04-1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML17146B298), the staff requested additional information regarding the assumptions and a summary of the SBO transient sensitivity evaluation that NuScale performed to show compliance with 10 CFR 50.63. In response to RAI-8824, Question 08.04-1 (ADAMS Accession No. ML17179A979), dated June 28, 2017, the applicant stated:
Consistent with the definition of a Station Blackout in 10 CFR 50.2, Definitions the SBO transient analysis identified in FSAR Section 8.4 assumes operation of the EDSS during the event, which in part forms the basis for compliance with 10 CFR 50.63. FSAR Section 8.4 includes the assumptions and a summary for the analysis of record. The model and assumptions for the sensitivity case are the same as the base case except the sensitivity case includes a simultaneous failure of the EDSS at the outset of the event, which represents an additional Enclosure
failure that is precluded by the SBO definition. Consequently, the sensitivity evaluation is not used to show compliance with 10 CFR 50.63, and NuScale does not believe that the results of the sensitivity study should be included in the FSAR. The analysis that documents the assumptions and results of the sensitivity case can be made available for NRC audit upon request.
AUDIT PURPOSE:
The purpose of this one-day regulatory audit is for the NRC staff to (1) review NuScales SBO transient sensitivity case and (2) hold discussions with NuScale staff related to specific areas of NuScale FSAR, Section 8.4, Station Blackout, and the applicants methodology, to determine whether NuScale design DCA meets the applicable regulations, i.e. 10 CFR 50.63. Specifically,
- 1. The NRC staff seeks clarification of NuScales assumptions and methodology on the SBO transient analysis.
- 2. The NRC staff seeks clarification on the SBO sensitivity case which demonstrates that the NuScale design does not rely on DC power from the EDSS to meet the requirements of 10 CFR 50.63.
The information to be reviewed is intended to provide direct support for the safety conclusions that apply to the NuScale DCA under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. Specifically, the information to be reviewed will provide support to the staffs review regarding NuScales assertion that the design does not rely on DC power from the EDSS to meet 10 CFR 50.63. The information to be assessed is intended to augment the NRC staffs understanding and verification. Furthermore, this information will be referenced in the NRC staffs final safety evaluation report (FSER) on the methodology and assumptions of the NuScale DCA, regarding how the electrical systems meet the applicable regulations.
The NRC staff will conduct this audit in accordance with the guidance provided in Office of New Reactors Office (NRO) Instruction, NRO-REG-108, Regulatory Audits.
INFORMATION AND DOCUMENTS NECESSARY FOR THE AUDIT:
- 1. SBO transient sensitivity case
- 2. An overview presentation of the document(s) to the NRC staff by NuScale subject matter experts.
AUDIT TEAM ASSIGNMENTS:
The audit team is comprised of the following NRC staff. These individuals will review the relevant documents that are related to the audit and will be available at the time of the audit:
- Tania Martinez Navedo, Electrical Engineering Branch, Acting Chief
- Swagata Som, Senior Electrical Engineer
AUDIT ACTIVITIES AND DELIVERABLES:
The NRC audit team review will cover the technical areas identified previously in this audit plan.
The NRC Project Manager will coordinate with NuScale in advance of audit activities to verify specific documents, identify any changes to the audit schedule and requested documents, and record the participants of the audit (NRC and NuScale staff).
The NRC staff acknowledges the proprietary and/or sensitive nature of the information requested and will handle appropriately throughout the audit. While the NRC staff will take notes, the NRC staff will not remove hard copies or electronic files from the audit site(s).
At the completion of the audit, the audit team will issue an audit summary within 90 days that will be declared and entered as an official agency record in the NRCs ADAMS records management system, in accordance with NRO-REG-108. The audit outcome may be used to assist the NRC staff in the issuance of request for additional information for the licensing review of the NuScale Design Certification Document and to identify any additional information to be submitted on the docket in support of the NRC staffs preparation of the FSER.