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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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August 22, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Sitting, and Environmental Assessment Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/
Licensing Branch 1 Division of Licensing, Sitting, and Environmental Assessment Office of New Reactors
SUBJECT:
AUDIT PLAN FOR REGULATORY AUDIT OF NUSCALE POWER, LLC; DESIGN DOCUMENTS FOR CONTAINMENT ISOLATION VALVES AND REACTOR SAFETY VALVES On January 6, 2017, NuScale Power, LLC (NuScale) submitted a design certification application (DCA) for a small modular reactor to the U.S. Nuclear Regulatory Commission (NRC)
(Agencywide Documents Access and Management System Accession No. ML17013A229).
The NRC staff started its detailed technical review of NuScales DC application on March 15, 2017.
The purpose of the subject audit to be conducted by the NRC staff is to: (1) gain a better understanding of the NuScale design of the containment isolation valves (CIVs) and reactor safety valves (RSVs); (2) verify information provided in the DCA; (3) identify information that may require docketing to support the basis of the licensing or regulatory decision; and (4) review related documentation and non-docketed information to evaluate conformance with regulatory guidance and compliance with NRC regulations.
The audit will take place at NuScales offices in Rockville, Maryland, and/or online via NuScales electronic reading room. The audit is currently scheduled to start on September 4, 2018, and end on October 17, 2018. The audit plan is enclosed.
Docket No.52-048
Enclosure:
- 1. Audit Plan cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Marieliz Vera, NRO/ DLSE 301-415-5861
ML18229A114 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DLSE/LB1: PM NAME MVera MMoore MVera DATE 08/17/2018 08/20/2018 08/22/2018 U.S. NUCLEAR REGULATORY COMMISSION REGULATORY AUDIT OF DESIGN DOCUMENTS FOR CONTAINMENT ISOLATION VALVES AND REACTOR SAFETY VALVES NUSCALE STANDARD PLANT DESIGN CERTIFICATION DOCKET NO.52-048 AUDIT PLAN APPLICANT: NuScale Power, LLC APPLICANT CONTACT: Marty Bryan, NuScale DURATION: September 4, 2018 to October 17, 2018 LOCATION: U.S. Nuclear Regulatory Commission (NRC)
Rockville Office 11545 Rockville Pike Rockville, MD 20852-2738 NuScale Rockville Office or NuScale Electronic Reading Room (eRR)
AUDIT TEAM: Thomas G. Scarbrough, Senior Mechanical Engineer, NRC, Audit Lead John Budzynski, Reactor Systems Engineer, NRC Clinton Ashley, Reactor Systems Engineer, NRC James Gilmer, Reactor Systems Engineer, NRC Marieliz Vera Amadiz, Project Manager, NRC I. BACKGROUND On March 15, 2017, the U.S. Nuclear Regulatory Commission (NRC or Commission) accepted the design certification application (DCA) for docketing for the NuScale Power, LLC (NuScale)
Standard DCA on for a small module reactor (SMR) design submitted by NuScale (Reference 1). NuScale submitted Revision 1 to its Standard Plant DCA on March 15, 2018 (Reference 2).
The NRC staff determined that efficiency gains would be realized by auditing the documents supporting the NuScale SMR design presented in the NuScale Final Safety Analysis Report (FSAR), in lieu of multiple requests for additional information (RAI) for the applicant to submit design documents. The purpose of this audit is to allow the NRC technical staff to gain an understanding of the design of the containment isolation valves (CIVs) and reactor safety valves (RSVs) in the NuScale reactor to better focus the staffs inquiries to the applicant. During the audit and interactions with the applicant, there may be detailed RAIs developed, which would be part of a future formal correspondence.
Enclosure 1
II. PURPOSE The purpose of the audit is to evaluate the detailed design of the CIVs and RSVs in support of the NuScale Standard Plant DCA.
III. REGULATORY AUDIT BASIS The audit basis is to confirm that the design of the NuScale CIVs and RSVs is consistent with the assumptions for the performance of those valves in the NuScale DCA.
Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, Section 47, Contents of Applications; Technical Information, states the following:
The application must contain a level of design information sufficient to enable the Commission to judge the applicants proposed means of assuring that construction conforms to the design and to reach a final conclusion on all safety questions associated with the design before the certification is granted. The information submitted for a design certification must include performance requirements and design information sufficiently detailed to permit the preparation of acceptance and inspection requirements by the NRC, and procurement specifications and construction and installation specifications by an applicant. The Commission will require, before design certification, that information normally contained in certain procurement specifications and construction and installation specifications be completed and available for audit if the information is necessary for the Commission to make its safety determination.
The NRC staff will review the design documents for the CIVs and RSVs described in the NuScale FSAR Tier 2:
- Section 3.9.6, Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints,
- Section 5.2.2, Overpressure Protection, and
- Section 6.2.4, Containment Isolation System.
The NRC staff will conduct this audit in accordance with the guidance provided in the Office of New Reactors (NRO)-REG-108, Regulatory Audits (Reference 3).
IV. REGULATORY AUDIT SCOPE The primary scope of this audit is the review of the design demonstration documentation, design drawings, design specifications, test plans, and qualification plans for the CIVs and RSVs to be used in the NuScale SMR to verify that the design and actuation of those valves is consistent with their performance assumed in the NuScale FSAR.
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V. DOCUMENTS/INFORMATION NECESSARY FOR THE AUDIT The design demonstration documentation, design drawings, design specifications, test plans, and qualification plans for the CIVs and RSVs are to be made available to the NRC staff in the NuScale eRR. Appropriate handling and protection of proprietary information shall be acknowledged and observed throughout the audit.
VI. SPECIAL REQUESTS The NRC staff requests that NuScale provide the technical staff with access to the audit documents. NuScale can upload the requested documents into the NuScale eRR for NRC staffs review. During the audit, the NRC staff will have questions and discussion items for the NuScale subject matter experts. When the NRC staffs review of the documents associated with a specific issue is complete, the staff will notify either the NRO, Division of Licensing, Sitting, and Environmental Assessment or NuScale that these documents can be removed from eRR; thereby minimizing their residence time in eRR.
VII. AUDIT ACTIVITIES AND DELIVERABLES The NRC audit team review will review the technical documents identified in Section V of this audit plan.
The regulatory audit will be scheduled from September 4, 2018 through October 17, 2018, from 7:00 AM to 3:00 PM, at the NRC Rockville Office, 11545 Rockville Pike, Rockville, MD 20852-2738. At the end of the audit, a technical audit summary will be provided by the technical reviewers to the NRC Project Manager (PM) for prompt issuance to the applicant as well as a public version of the same.
The NRC PM will coordinate with NuScale in advance of audit activities to verify specific documents and identify any changes to the audit schedule and requested documents.
The audit entrance/exit meetings and weekly audit meeting are to be scheduled as followings:
- Entrance Meeting - September 4, 2018.
- Exit Meeting: October 17, 2018.
- Weekly Audit Telephone Conference (as needed): Wednesday 11:00 AM - 12:00 PM Eastern Standard Time.
The NRC staff acknowledges the proprietary nature of the information requested. It will be handled 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.
During the weekly telephone conferences, the NRC will discuss with NuScale any issues identified during the audit, and their resolution either through audit activities or by another mechanism, such as RAIs or public meetings. During the weekly conferences, NRC will also identify any new emerging information needs as well as documents that can be removed from eRR.
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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 Agencywide Documents Access and Management System (ADAMS) records management system.
The audit outcome may be used to identify any additional information to be submitted for making regulatory decisions, and will assist the NRC staff in the issuance of RAIs (if necessary) to support the NRC review of the NuScale design certification application in preparation of the NRCs Safety Evaluation Report.
If necessary, any circumstances related to the performance of the audit will be communicated to Marieliz Vera Amadiz, NRC at 301-415-5861, or email: Marieliz.VeraAmadiz@nrc.gov.
VIII. REFERENCES
- 1. NRC Letter, NuScale Power, LLC. - Acceptance of an Application for Standard Design Certification of a Small Modular Reactor, ADAMS Accession No. ML17074A087, March 23, 2017.
- 2. NuScale Standard Plant DCA, Revision 1, ADAMS Accession No. ML18086A090, March 15, 2018.
- 3. NRO-REG-108, Regulatory Audits, ADAMS Accession No. ML081910260, April 2, 2009.
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