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Category:Audit Report
MONTHYEARML20160A2502020-07-28028 July 2020
Enclosure 1 - ECCS Boron Redistribution Issue Audit Summary Public Version
ML20176A1572020-07-10010 July 2020
Enclosure 1 - Chapter 15 Audit Summary Public Version
ML20076D8852020-03-16016 March 2020
Summary Report for the January 2019 Regulatory Audit of NuScale Chapter 20
ML20054A0602020-02-28028 February 2020
Regulatory Audit Report for NuScale DCA Inadvertent Actuation Block (Iab) Operating Range Change
ML20042E0392020-02-12012 February 2020
NON-LOCA Topical Report Phases 3 and 4 Audit Report
ML20042E0242020-02-12012 February 2020
LOCA Topical Report Phase IV Audit Report - Public
ML20010D1332020-01-28028 January 2020
Enclosure 1 - LOCA Audit Summary Public Version
ML20010D1312020-01-16016 January 2020
Audit Summary Memo NuScale LOCA TR
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)
ML19343C7562020-01-0808 January 2020
Generator Tube - Siet Audit Report (Public)
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
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
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
ML19308A0612019-11-0101 November 2019
Summary of NRC Staff Audit of NuScale Power'S Containment and Ventilation Systems
ML19291A8872019-10-21021 October 2019
U.S. Nuclear Regulatory Commission Summary Report of Regulatory Close-out Audit of NuScale Power, LLC, Component Design Specification
ML19220B6752019-09-0909 September 2019
Hfe Vv Rsr Audit Summary Report
ML19203A0432019-07-25025 July 2019
Phase IV Regulatory Audit of NuScale Neutron Radiation Source Term
ML19175A0672019-07-18018 July 2019
Audit Summary Report for the Regulatory Audit of NuScale Power, LLC Proposed Inspections, Tests, Analyses, and Acceptance Criteria and Revised Design Implementation Implementation Plan
ML19151A6582019-06-14014 June 2019
Audit Report for the Regulatory Audit of Nuscale Power, LLC FSAR Chapter 20, Mitigation of Beyond-Design-Basis Events
ML19037A4892019-03-15015 March 2019
Memo - Summary Report for the Environmental Audit of Part 3 of the NuScale Design Certification Application
ML19018A1402019-02-11011 February 2019
U.S. Nuclear Regulatory Commission Staff Report of Regulatory Audit for Nuscale Power, LLC; Follow-Up Audit of Component Design Specifications
ML18333A2212018-12-13013 December 2018
Phase 2 Audit Nuscale Reactor Internals Comprehensive Vibration Assessment Program
ML18331A0422018-12-0707 December 2018
U.S. Nuclear Regulator Commission Staff Report of Regulatory Audit of Nuscale Power, LLC; Design Documents for Containment Isolation Valves and Reactor Safety Valves
ML18325A1532018-12-0606 December 2018
U.S. Nuclear Regulatory Commission Staff Report of Follow-Up Regulatory Audit for Nuscale Power, LLC Design Certification Application Final Safety Analysis Report Sections 3.9.4 and 4.6
ML18324A5622018-11-29029 November 2018
U.S. Nuclear Regulatory Commission NuScale Power, LLC; Summary Report of Regulatory Audit of Computer Program Codes as Part of the NuScale Design Control Document
ML18298A1902018-11-14014 November 2018
July-August 2018 NuScale Isv Audit Summary Report for the Regulatory Audit of NuScale Power, LLC, Design Certification Application Human Factors Engineering
ML18317A2772018-11-14014 November 2018
Audit Summary for Nuscale Topical Report TR-0915-17564, Revision 1, Subchannel Analysis Methodology.
ML18291B2282018-11-0909 November 2018
Interim Audit Summary Report - Containment and Ventilation Systems
ML18173A2912018-10-25025 October 2018
U.S. Nuclear Regulatory Commission Report of Regulatory Audit for Nuscale Power, LLC Seismic Category 1 Equipment and Environment Qualification of Electrical Equipment Specifications
ML18219B6342018-08-14014 August 2018
U.S. Nuclear Regulatory Commission Staff Report of Regulatory Audit of Failure Modes and Effects Analysis and Other Supporting Documents for Emergency Core Cooling System Valves in the NuScale Power, LLC, Design Certification Application
ML18208A3712018-08-0101 August 2018
June 26-28 2018 NuScale Hfe Audit Summary Report
ML18172A0762018-06-13013 June 2018
Nonproprietary - Regulatory Audit of Nuscale Draft Rev 3 of the Accident Source Term Methodology Topical Report TR-0915-17565
ML18143B6672018-06-13013 June 2018
Summary Report for the Environmental Audit of Part 3 of the NuScale Design Certification Application
ML18135A0502018-05-24024 May 2018
Hfe Audit Report (Jul 25-2017 - Feb 14-2018)
ML18103A1982018-04-30030 April 2018
Chapter 11 Audit Report - June Through November 2017
ML18051A7222018-03-26026 March 2018
Audit Summary for NuScale Steam Generators_Non_Prop Version
ML18051A7302018-03-26026 March 2018
Audit Summary Memo NuScale Steam Generators
ML18052A0792018-02-26026 February 2018
U.S. Nuclear Regulatory Commission Staff Report of Initial Regulatory Audit for Emergency Core Cooling System Valves in Nuscale Power, LLC, Design Certification Application
ML18031A4542018-02-16016 February 2018
Physical Seurity Audit Report
ML18023A0912018-02-0505 February 2018
Public - Audit Report NuScale 3.9.2
ML18018A2342018-01-25025 January 2018
Summary Audit Report of Phase 1 NuScale Design Specfication Rev
ML18004A0462018-01-0505 January 2018
Audit Report - Nuscale'S EC-0000-3070, Station Blackout Transient Analysis, Revision 1 (Docket No. 52-048)
2020-07-28
[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
[Table view] |
Text
May 24, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Demetrius Murray, Project Manager /RA Prosanta Chowdhury for:/
Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors
SUBJECT:
AUDIT REPORT
SUMMARY
FOR THE REGULATORY AUDIT OF NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION HUMAN FACTOR ENGINEERING From July 25, 2017, through February 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a regulatory audit of NuScale Power, LLC (NuScale) Design Certification Application (DCA) Human Factors Engineering (HFE) Topics.
The purpose of the audit was to: (1) review non-docketed information related to verification and validation methods to evaluate conformance with regulatory guidance and (2) identify information that will require docketing to support the basis of the licensing or regulatory decision. The NRC staff conducted the audit at NuScales offices in Rockville, Maryland and also reviewed documents in the NuScale electronic reading room.
The NRC staffs audit plan, dated July 25, 2017, can be accessed via the NRCs Agencywide Documents Access and Management System under Accession No. ML17205A465. The NRC staff conducted the audit in accordance with the Office of New Reactors (NRO) Office Instruction NRO-REG-108, Regulatory Audits.
The objectives of the audit, based upon the purpose stated above, were met during or shortly after the audit. The enclosed report summarizes the NRC staffs activities and conclusions involving the audit.
Docket No.52-048
Enclosure:
- 1. Audit Summary Report CONTACT: Prosanta Chowdhury, NRO/DNRL 301-415-1947
ML18135A049 - Pkg *via Email NRO- 002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRO/DCIP/HOIB: BC NRO/DNRL/LB1: PM NAME DMurray* MMoore* LKent* PChowdhury*
DATE 05/10/2018 05/16/2018 05/14/2018 05/24/2018 U.S. NUCLEAR REGULATORY COMMISSION NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION - HUMAN FACTORS ENGINEERING AUDIT
SUMMARY
REPORT Audit Team Members
- Brian Green Background and Audit Bases By letter dated December 31, 2016, NuScale submitted a design certification application (DCA) for review (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17013A229). The DCA includes Final Safety Analysis Report (FSAR) Tier 2, Chapter 18, Human Factors Engineering, which describes the human factors engineering (HFE) program for the NuScale Standard Design Power Plant (ADAMS Accession No. ML17013A289).
Consistent with NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Chapter 18, Human Factors Engineering, the NRC staff is using the review criteria in NUREG-0711, Human Factors Engineering Program Review Model, Revision 3, to determine whether the NuScale design complies with HFE-related NRC regulatory requirements. The HFE Program Review Model described in NUREG-0711 consists of 12 elements (refer to Figure 1-1, Elements of the HFE programs review model, of NUREG-0711 for additional information).
The FSAR Tier 2, Section 18.0, Human Factors Engineering - Overview, states the NuScale HFE program incorporates accepted HFE standards and guidelines including the applicable guidance provided in NUREG-0711. NuScale submitted two types of technical reports to address the 12 elements in NUREG-0711, Implementation Plans and Results Summary Reports. NUREG-0711, Section 1.2.2, Review Elements, explains that implementation plans describe processes and methods for performing HFE activities and results summary reports describe the results of performing those activities.
NuScale submitted, Human Factors Verification and Validation Implementation Plan (V&V IP),
Revision 2, with the DCA. In a letter dated April 8, 2016, from Mr. Thomas Bergman, NuScale, Vice-President, Regulatory Affairs to Mr. Frank Akstulewicz, Director, Division of New Reactor Licensing, NRC (ADAMS Accession No. ML16099A270), NuScale stated that NuScale would submit the V&V Results Summary Report (RSR) prior to Phase 4 of the NRCs review of the NuScale DCA.
As described in NUREG-0711, Section 11.1, Background, a significant V&V activity is the integrated system validation (ISV) test. The V&V IP, Section 4.6, Test Design, says, Upon approval, the ISV scenarios and test plan will be available for review or audit by the NRC Enclosure
sufficiently before the conduct of ISV so that comments or concerns can be adequately addressed prior to commencing ISV.
In May 2017, the NRC staff conducted an audit consistent with the audit plan dated April 25, 2017 (ADAMS Accession No. ML17110A254). The audit included a review of the ISV Test Plan and scenario bases documents to verify the V&V scenarios and ISV test methods conform to selected review criteria in NUREG-0711, Section 11.4, Review Criteria. The results of the audit are documented in the audit summary report dated July 17, 2017 (ADAMS Accession No. ML17181A415).
Audit Activities The NRC staff commenced a follow-up audit on July 24, 2017 as discussed in the audit plan dated July 25, 2017 (ADAMS Accession No. ML17205A465). The objective of the audit was to verify the V&V methodology conforms to the review criteria in NUREG-0711, Section 11.4, that was not assessed as part of the previous audit and to identify information that will require docketing to support the basis of the licensing or regulatory decision. This objective is identified as Objective 1 in the audit plan. The audit plan includes Objectives 2, 3, 4, and 5, which were not assessed during this audit because the NRC staff determined they could be verified during subsequent audit(s) that will be more appropriately timed to coincide with the activities discussed in the response from NuScale to the NRC staffs request for additional information (RAI) 9123, Question 18-12 (ADAMS Accession No. ML18002A554).
The NRC staff reviewed the following documents in NuScales Electronic Reading Room (ERR):
- Integrated Systems Validation Test Plan, Revision 0,
- ISV Scenario Basis Documents, Original Revision,
- Human System Interface Design and Validation Process, Revision 1, and
- Design verification test plan, Original Revision.
Additionally, the NRC staff held discussions with the NuScale staff1 about the proposed V&V methods and the scope of information to be included in the application.
Audit Results The NRC staff began reviewing non-docketed information on July 24, 2017, via NuScales ERR and concluded the audit on February 14, 2018. The NRC staff issued the following RAIs as a result of this audit: RAI Nos. 8805, 9394, 9371, 9395, 9396, 9397, 9398, 9399, and 9414.
Conclusion The NRC staff conducted an audit exit call with NuScale staff on February 14, 2018. The NRC 1
The NuScale staff members who participated in substantive conversations include Timothy Tovar, Manager, Plant Operations; Doug Bowman, Supervisor, Plant Operations; and Ryan Flamand, Operations Engineer.
2
staff stated they were able to accomplish the audit objective, and was able to identify areas where RAIs were warranted.
3