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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 Commissions Report of the Regulatory Audit Performed Between March 4, 2019, Through September 10, 2019, for Nuscale Power, LLC, Regarding NuScales 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 Nuscale’S 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 NuScales 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 Commissions Report of the Regulatory Audit Performed Between March 4, 2019, Through September 10, 2019, for Nuscale Power, LLC, Regarding NuScales 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
February 16, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Prosanta Chowdhury, Project Manager /RA/
Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors
SUBJECT:
AUDIT
SUMMARY
REPORT FOR THE NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION AUDIT OF PHYSICAL SECURITY UNDER CHAPTER 13, CONDUCT OF OPERATIONS (DOCKET NO.52-048)
On December 5 and 6, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an audit of the physical security elements of NuScale Power, LLC (NuScale) design certification application. The audit was conducted at the NuScale offices located at 1100 NE Circle Blvd.,
Suite 200, Corvallis, Oregon 97330. The purpose of the audit was to examine the supporting documentation for the design of physical security systems described for the NuScale Standard Plant.
The detailed information related to the subject contains safeguards, security-related, and/or proprietary information and the details are protected in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 73.21, Protection of Safeguards Information:
Performance Requirements, and 10 CFR 2.390, Public inspections, exemptions, requests for withholding. The audit plan can be found in the Agencywide Documents Access and Management System under Accession No. ML17318A512 dated November 29, 2017. The results of the audit are summarized in Enclosure 1. The List of Attendees and the List of Documents Made Available to the NRC Staff are documented in Enclosures 2 and 3, respectively.
Docket No.52-048
Enclosure:
- 1. Audit Summary Report
- 2. List of Attendees
- 3. List of Documents Made Available to the NRC Staff cc w/
Enclosures:
NuScale DC Listserv CONTACT: Prosanta Chowdhury, NRO/DNRL 301-415-1647
ML18031A454 *via email NRO-002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NSIR/DPCP/RSB: BC NRO/DNRL/LB1: PM NAME PChowdhury* Maria Moore* Alison Rivera* PChowdhury DATE 1/31/2018 2/01/2018 2/08/2018 2/16/2018 U.S. NUCLEAR REGULATORY COMMISSION NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION AUDIT OF PHYSICAL SECURITY UNDER CHAPTER 13, CONDUCT OF OPERATIONS DECEMBER 5 - 6, 2017
SUMMARY
REPORT NRC Audit Team:
Pete Lee (NSIR, Technical Lead)
Gregory Cranston (NRO, Project Manager) (joined remotely)
Andrew Nelson (U.S. Army Corps of Engineers, NRC Contractor) 1.0
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) staff conducted an audit of the physical security elements of the NuScale Power, LLC (NuScale or the applicant) Design Certification Application (DCA), which included safeguards and security-related information supporting the Tier 1 and Tier 2 of the Final Safety Analysis Report (FSAR). The audit was conducted on December 5 - 6, 2017, at the NuScale offices located at 1100 NE Circle Blvd., Suite 200, Corvallis, Oregon 97330. The staff conducted the audit in accordance with the NRCs Office of New Reactors (NRO) Office Instruction NRO-REG-108, Regulatory Audits (Agencywide Document Access and Management System (ADAMS) Accession No. ML081910260, April 2, 2009). The audit plan, dated November 29, 2017, can be found under ADAMS Accession No. ML17318A512.
2.0 BASIS This audit was conducted in order for the NRC staff to gain an understanding of NuScale designs and design bases for physical security systems within the scope of the NuScale design certification. The supporting information on how an applicant designs physical security systems to meet performance and/or prescriptive regulatory requirements allows for the NRC staff to arrive at informed security findings. In addition, the descriptions of design bases for engineered physical protection systems are required for the inspections, tests, and/or analyses for verifying physical security Inspections, Tests, Analyses, and Acceptance Criteria, and the supporting documents (e.g., analyses, evaluations, engineering calculations, etc.) provide direct evidence for the designs of physical security systems and hardware within the scope of the design certification.
The selected subjects of the audit included the review of: (1) NuScales methods and assumptions for determining bounding minimum safe standoff distances for protecting against the design basis threat vehicle bombs; and (2) design drawings and specification documents, engineering reports, analyses, assessments, and referenced standards for the designs of physical security systems.
Enclosure 1 1
3.0 OBSERVATIONS AND RESULTS
- a. The audit provided an understanding of the methods or approaches applied to support the design bases and descriptions for physical security systems in NuScale Technical Report (TR) 0416-48949, NuScale Design of Physical Security Systems, which is incorporated by reference in Tier 2 of the FSAR.
- b. The audit provided an understanding of the technical bases and assumptions for how NuScale determined bounding minimum safe standoff distances (MSSD) to protect against the design basis threat vehicle bombs. NuScale methods or documents applied for this audit included security engineering methods acceptable for use in the design of physical systems referenced in NUREG/CR-7145, Nuclear Power Plant Security Assessment Guide, for determining blast effects, such as U.S. Department of Defense (DoD) Single Degree of Freedom Blast Design Spreadsheet (SBEDS) and Convention Weapons Effect (CONWEP) Software and Manual.
- c. NuScale also applied other DoD methods and guidance for predicting blast effects and structural responses. These included DoD UFC 3-040-01, Design and Analysis of Hardened Structures to Conventional Weapons Effects, PDC-TR 06-08, Single Degree Freedom Structural Response Limits for Antiterrorism Design, BlastX - Fast Running Model for Airblast Prediction Involving Internal and External Detonations, In Structure Shock (ISS) 3D, and LS-Dyna Finite Element Analysis Software.
- d. The NRC staff noted that some of the MSSDs indicated in the NuScale TR 0416-48949 were mistakenly smaller than the worst case shown in supporting calculations. In addition, the design basis for the MSSD for doors calculated with SBEDS assumed very specific doors and configurations that must be installed. With the exception of the noted discrepancy, the overall determinations of required MSSDs of the structures within the scope of the NuScale Power Plant standard design applied accepted methods, software, and/or guidance to provide results (with corrected mistakes) that are reasonable.
- e. During the audit, the applicant informed and provided insights to the NRC staff regarding the designs and bases for physical security structures, systems, and components within the scope of the NuScale Power Plant standard design. The NRC staff noted that the information presented and discussed during the audit, addressed subjects included in NRC request for additional information (RAI) No. 8998. The NRC staff did not identify any additional subject areas that are not already included in RAI No. 8998.
- f. The documents the NRC staff examined included information that are outside of the scope of the design certification and are not subject of the ongoing DCA application review. For example, the NuScale application of ConWep cratering calculations, in lieu of the U.S. Department of the Army TM 3-34.82, Explosive and Demolition, to establish breach radius for a wall and the breaching calculations addressed a specific method, but not necessarily bounding of a worst-case within the DBT, are outside of the scope of the design certification and would be addressed during the review of the application for an operating license.
2
4.0 CONCLUSION
The summary of observations, as documented above, was communicated to NuScale during the audit and reiterated at the exit briefing. The audit did not identify a need for additional questions to supplement the subjects already addressed in RAI No. 8998. The NRC staff emphasized that the DCA and the technical report that is incorporated by reference, must contain sufficient and necessary details on designs of physical security systems to provide the basis for the NRC staffs adequate regulatory findings.
U.S. NUCLEAR REGULATORY COMMISSION NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION AUDIT OF PHYSICAL SECURITY UNDER CHAPTER 13, CONDUCT OF OPERATIONS DECEMBER 5 - 6, 2017 LIST OF ATTENDEES NAME REPRESENTING Pete Lee U.S. Nuclear Regulatory Commission (NRC)
Gregory Cranston NRC Project Manager (joined remotely)
Andrew Nelson U.S. Army Corps of Engineers (NRC Contractor)
Cyrus Arshar NuScale Power, LLC (NuScale)
Dale Atkinson NuScale Tom Bergman NuScale Kevin Deyette NuScale Liz English NuScale Carrie Fosaaen NuScale Dustin Greenwood NuScale GL Plumlee III NuScale Enclosure 2 2
U.S. NUCLEAR REGULATORY COMMISSION NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION AUDIT OF PHYSICAL SECURITY UNDER CHAPTER 13, CONDUCT OF OPERATIONS DECEMBER 5 - 6, 2017 LIST OF DOCUMENTS MADE AVAILABLE TO THE NRC STAFF The U.S Nuclear Regulatory Commission staff reviewed the following documents during the audit:
ER-P000-3954 Generation of Location Cutsets for Target Set and Vital Areas Identification, Revision 9, April 29, 2016 ER-0000-4589 Report on Tactical Blast Assessment of Targets in the NuScale Design RXB, Revision 2, August 30, 2016, ER-0000-4972 Blast Analysis and Minimum Safe Standoff Distance Evaluation for Critical Assets and Function, Revision 0, August 30, 2016 ED-F010-4355 Reactor Building Vital Areas and Equipment Plan View ED-F010-4356 Reactor Building Physical Security System Plan View ED-F010-4357 Control Building Vital Areas and Equipment CRB-Plan ED-F010-4358 Control Building Physical Security Systems CRB-Plan ED-F010-4359 RWB Physical Security Systems RWB-Plan ED-F010-4361 Central Alarm Station Layout ED-F170-4756 Central Alarm Station Section View Report 15000925-402 Aircraft Impact Assessment for NuScale NP-12 Plant Design Structural Response Analysis, Revision 0, January 2016 NSWC-66-TR 2012/023 Simulation of Explosive Effects in Water Confined in Large Structures, Revision A, August 2012 TR 0315-48929, NuScale Design of Physical Security Systems, Revision 0, November 16, 2016 EC-FO10-2429 Flooding Analysis, Revision 1, May 25, 2016 EC-B175-3253 Ultimate Heat Sink Boil Off Calculations, Revision 1, July 27, 2017 Enclosure 3
SD-G040-2804 Communication Systems (COM) System Design Description, Revision 0, June 16, 2016 SD-D070-3609 Plant Lighting System (PLS) System Design Description, Revision 0, March 28, 2016 SD-D070-2750 Plant Lighting System Function Specification, Revision 1, March 28, 2016 EC-D070-3047 Plant Lighting System (PLS) Scoping Calculation, Revision 1, February 3, 2016 EC-D070-5605 through 5607, Lighting Illumination at MCR and RSS.
FS-D100-2070 Security power System Functional Specification, Revision 2, May 25, 2016 Security Assessment Report Using (intentionally not identified), July 7, 2016 ED-F010-1697 RX Concrete ED-F107-2330 Control Building Structural Concrete ED-F090-1136 NuScale Module Plant Site Plan ED-F012-3661 Bio-Shield General Arrangement and Details ED-G020-4890 Security System Interconnection Diagram