Text

LLC Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Open Session) US460 Standard Design Approval Application Chapters 7, 9, 12, and 18, PM-172558, Revision 0
	ML24232A228
Person / Time
Site:	05200050
Issue date:	08/19/2024
From:	Griffith T; NuScale
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	LO-172559 PM-172558, Rev 0
	Download: ML24232A228 (1)
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LO-172559 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com August 19, 2024 Docket No. 052-050 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

NuScale Power, LLC Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Open Session) US460 Standard Design Approval Application Chapters 7, 9, 12, and 18, PM-172558, Revision 0 The purpose of this submittal is to provide presentation materials for use during the upcoming Advisory Committee on Reactor Safeguards (ACRS) NuScale Subcommittee Meeting on August 22, 2024. The materials support NuScales presentation of the subject chapters of the US460 Standard Design Approval Application.

The enclosure to this letter is the nonproprietary presentation entitled ACRS Subcommittee Meeting (Open Session) US460 Standard Design Approval Application Chapters 7, 9, 12, and 18, PM-172558, Revision 0.

This letter makes no regulatory commitments and no revisions to any existing regulatory commitments.

If you have any questions, please contact Chelsea Lockwood at 541-452-7171 or at clockwood@nuscalepower.com.

Sincerely, Thomas Griffith Manager, Licensing NuScale Power, LLC Distribution:

Mahmoud Jardaneh, Chief New Reactor Licensing Branch, NRC Getachew Tesfaye, Senior Project Manager, NRC Michael Snodderly, Senior Staff Engineer, Advisory Committee on Reactor Safeguards, NRC : ACRS Subcommittee Meeting (Open Session) US460 Standard Design Approval Application Chapters 7, 9, 12, and 18, PM-172558, Revision 0

LO-172559 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com ACRS Subcommittee Meeting (Open Session) US460 Standard Design Approval Application Chapters 7, 9, 12, and 18, PM-172558, Revision 0

NuScale Nonproprietary Template #: 0000-21727-F01 R10 ACRS Subcommittee Meeting (Open Session)

August 22, 2024 US460 Standard Design Approval Application Chapters 7, 9, 12, and 18

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Acknowledgement and Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0008928.

This presentation was prepared as an account of work sponsored by an agency of the United States (U.S.)

Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Chapter 7 August 22, 2024 Presenter: Thomas Case Instrumentation and Controls

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Instrumentation and Controls Section 7.0: Instrumentation and Controls - Introduction and Overview Section 7.1: Fundamental Design Principles Section 7.2: System Features

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 7.0: Instrumentation and Controls - Introduction and Overview Changes from DCA o Elimination of the remote shutdown station (across all of Chapter 7)

Alternate operator workstations allow for plant monitoring outside the main control room Results from audit and RAI review o No audit items or RAIs specific to Section 7.0 1 1 One audit item in Chapter 15 related to COL Item 7.0-1

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 7.1: Fundamental Design Principles Changes from DCA o Module protection system (MPS) setpoint changes due to changes in operating pressure and temperature, and updated safety analysis o Emergency core cooling system (ECCS) actuation changes due to updated safety analysis o Additional decay heat removal system (DHRS) and reactor trip system (RTS) actuations due to updated safety analysis o Addition of an 8-hour timer for ECCS actuation to add supplemental boron if needed to maintain subcriticality o Adoption of Institute of Electrical and Electronics Engineers (IEEE) Standard 497-2016 as endorsed by Regulatory Guide 1.97, Revision 5, and the addition of Type F post-accident monitoring variables Results from audit and RAI review o Removal of a note from Figure 7.1-1aa regarding inadvertent actuation block (A-7.1-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 7.2: System Features Changes from DCA o Information from the Advanced Sensor Technical Report cited in the DCA is incorporated into SDAA Section 7.2.16 o Change from digital to analog sensors

Reactor pressure vessel riser level, containment vessel water level, reactor coolant system pressure, pressurizer pressure

Diversity and defense-in-depth (D3) and coping analyses updated in Section 7.1 o Reduction in quantity of reactor coolant system temperature sensors based on updated engineering evaluation

Analysis of the reactor coolant flow determined that streaming effects do not require the use of multiple sensors per quadrant Results from audit and RAI review o No audit items or RAIs specific to Section 7.2

NuScale Nonproprietary Template #: 0000-21727-F01 R10 SDAA Topical Report - Design of the Highly Integrated Protection System Platform TR-1015-18653-P-A Revision 2 NRC approved Topical Report (June 2017)

No changes since ACRS engagement in 2023

NuScale Nonproprietary Template #: 0000-21727-F01 R10 SDAA Technical Report - NuScale Instrument Setpoint Methodology Technical Report TR-122844 Revision 0 NRC reviewed as part of Chapter 7 No changes since ACRS engagement in 2023

NuScale Nonproprietary Template #: 0000-21727-F01 R10 COL items No change to COL Items in Chapter 7 1 1 One audit item in Chapter 15 related to COL Item 7.0-1

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Acronyms ACRS Advisory Committee on Reactor Safeguards COL Combined License D3 Diversity and Defense-in-depth DCA Design Certification Application DHRS Decay Heat Removal System ECCS Emergency Core Cooling System IEEE Institute of Electrical and Electronics Engineers MPS Module Protection System NRC Nuclear Regulatory Commission RAI Request for Additional Information RTS Reactor Trip System

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Chapter 9 August 22, 2024 Presenters: Sarah Turmero, Freeda Ahmed, and Jordan Green Auxiliary Systems

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Chapter 9: Auxiliary Systems Section 9.1 Fuel Storage and Handling Section 9.2 Water Systems Section 9.3 Process Auxiliaries Section 9.4 Air Conditioning, Heating, Cooling, and Ventilation Systems Section 9.5 Other Auxiliary Systems (Lighting, Communication, and Fire Protection)

Section 9A Fire Hazards Analysis

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1: Fuel Storage and Handling Section 9.1.1 Criticality Safety of Fresh and Spent Fuel Storage and Handling Section 9.1.2 New and Spent Fuel Storage Section 9.1.3 Pool Cooling and Cleanup System Section 9.1.4 Fuel Handling Equipment Section 9.1.5 Overhead Heavy Load Handling Systems

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1.1 Criticality Safety of Fresh and Spent Fuel Storage and Handling Criticality safety of fuel storage is addressed by COL Item 9.1-1.

COL Item 9.1-1 o An applicant that references the NuScale Power Plant US460 standard design will develop plant programs and procedures for safe operations during handling and storage of new and spent fuel assemblies, including criticality control.

Audit and RAI Results:

o Design of reactor flange tool is responsibility of COL applicant. Fuel remains in the lower reactor pressure vessel (RPV). Criticality of fuel while in the RPV is discussed in Section 4.3.2.6. (A-9.1.1-1) o COL Item 9.1-2 requires applicants to perform criticality analysis of fuel racks (A-9.1.1-2) o Criticality safety design for refueling pool is described in Section 9.2.5 (A-9.1.1-3)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1.2 New and Spent Fuel Storage Fuel storage is addressed by COL Item 9.1-2.

COL Item 9.1-2 o An applicant that references the NuScale Power Plant US460 standard design will provide the design of the spent fuel pool storage racks, including the structural dynamic and stress analyses, thermal hydraulic cooling analyses, criticality safety analysis, and material compatibility evaluation.

Audit and RAI Results:

o Demonstrated that the spent fuel pool (SFP) has >30 days of water above the top of fuel. (RAI 9.1.2-1.1) o Clarified the seismic classification between dry dock gate and the dry dock gate support in Section 9.1.2 and Section 9.1.3 (RAI 9.1.2-1.2)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1.3 Pool Cooling and Cleanup System Design changes from DCA:

o Combined the spent fuel pool cooling system, the reactor pool cooling system, the pool cleanup system, and the pool surge control system into a single pool cooling and cleanup system.

Major components remain the same (filters, demineralizers, surge control tank) with the exception of the pumps and heat exchangers, which have been reduced from five trains to three.

o Pool leakage detection system wall leak channels attach to the steel-plate composite walls.

Audit and RAI Results:

o None specific to Section 9.1.3.

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1.4 Fuel Handling System Design changes from DCA:

o New fuel elevator capable of handling irradiated fuel for inspection purposes o New fuel jib crane classification changed from ASME NUM-1 Type 2 to ASME NUM-1 Type 1A, single failure proof Audit and RAI Results:

o None specific to Section 9.1.4

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1.5 Overhead Heavy Load Handling Systems Design Changes from DCA:

o Reactor Building crane (RBC) capacity increased from 850 tons to 950 tons o Module lifting adapter in DCA design was removed and is now integral to the RBC o RBC auxiliary hoist capacity increased from 15 tons to 40 tons o Changes to automated control system software reduces probability of operator error o Added additional jib cranes designed to ASME NUM-1 Type 1A o Removal of heavy load exclusion zone above the SFP Change to COL Item 9.1-5 o An applicant that references the NuScale Power Plant US460 standard design will provide a description of the program governing heavy loads handling. The program should address

operating and maintenance procedures.

inspection and test plans.

personnel qualification and operator training.

detailed description of the safe load paths for movement of heavy loads.

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.1.5 Overhead Heavy Load Handling Systems, continued Audit and RAI Results:

o Clarifies use of ASME NUM-1 within Section 9.1.5 including demonstrating compliance with Regulatory Guide 1.244 Position C.1 (A-9.1.5-1, A-9.1.5-2, A-9.1.5-8) o Justifies deviation of ASME NOG-1 design factor for plate buckling and the methodology for determining spacing of transverse stiffeners (RAI 9.1.5-3) o Eliminates heavy load exclusion zone terminology in 9.1.5, 15.7.5, and 17.4 (RAI 9.1.5-6)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.2: Water Systems Section 9.2.1 Station Service Water System - Not applicable to US460 Section 9.2.2 Reactor Component Cooling Water System Section 9.2.3 Demineralized Water System Section 9.2.4 Potable and Sanitary Water Systems Section 9.2.5 Ultimate Heat Sink Section 9.2.6 Condensate Storage Facilities Section 9.2.7 Site Cooling Water System Section 9.2.8 Chilled Water System Section 9.2.9 Utility Water Systems 9.2.9 Utility Water Systems

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.2.4 Potable and Sanitary Water Systems Changes from DCA o

Potable and Sanitary Water System piping (including loop seals) penetrating the control room envelope changed from Seismic Category II (SC-II) to Seismic Category I (SC-I).

Audit and RAI Results:

o Removal of COL Item 9.2-2 concerning source and pre-treatment methods of potable water o

Removal of COL Item 9.2-3 concerning sanitary waste storage and disposal o

The potable and sanitary water systems serve no safety-related functions, are not credited for mitigation of design-basis accidents, and have no safe shutdown functions. Site-specific characteristics do not impact ability to meet the identified requirements (A-9.2.4-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.2.5 Ultimate Heat Sink (UHS)

Changes from DCA o The number of modules was reduced from 12 to six, reducing the inventory of the UHS due to a smaller footprint.

o UHS level lowered from 68 ft to 53 ft from bottom of module.

No Audit questions or RAIs specific to Section 9.2.5

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.2.7 Site Cooling Water System Changes from DCA o

Changed from one-loop open system to a two-loop system in SDAA to better maintain water quality for plant users

The two-loop system consists of a closed loop that removes heat from plant loads and an open cooling tower loop that rejects heat to the environment.

o Removed COL Item 9.2-4 concerning long-term corrosion and fouling

The site cooling water system serves no safety-related functions, is not credited for mitigation of design-basis accidents and has no safe shutdown functions. Site-specific characteristics do not impact ability to meet the identified requirements.

Audit and RAI Results:

o Discussed that utility water provides makeup to the tower basin and demineralized water provides makeup to the closed loop (A-9.2.7-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.2.9 Utility Water Systems (UWS)

Changes from DCA o

Removed COL Item 9.2-5 concerning identification of a site-specific water source and water treatment system o

This item was written for a previous revision of Regulatory Guide 1.206, which does not apply to the SDAA. The UWS meets GDCs 5, 60, 64 and 10 CFR 20.1406.

Audit and RAI Results:

o The UWS provides raw water to the demineralized water system, site cooling water and fire protection for general washdown use. The system function determines the system chemistry controls. The selected source of raw water has no impact on the safety-related structures systems and components (SSC) (A-9.2.9-1) o Discussed UWS piping in the vicinity of safety-related or SC-I SSC; and protective measures to avoid impact on system from flooding (A-9.2.9-2)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.3: Process Auxiliaries Section 9.3.1 Compressed Air Systems Section 9.3.2 Process Sampling System Section 9.3.3 Equipment and Floor Drain Systems Section 9.3.4 Chemical and Volume Control System Section 9.3.5 Standby Liquid Control System Section 9.3.6 Containment Evacuation System Section 9.3.7 Containment Flooding and Drain System 9.3.7 Containment Flooding and Drain System 9.2.9 Utility Water Systems

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.3.4 Chemical and Volume Control System (CVCS)

Design changes from DCA:

o Module heatup system modified to use an electric heater in lieu of an auxiliary boiler Audit and RAI Results:

o Clarified how CVCS complies with General Design Criterion (GDC) 4 (A-9.3.4-1) o Revised demineralized water system isolation valves to Quality Group C (RAI 9.3.4-1) o Added the maximum boron concentration for the boron addition system to prevent boric acid precipitation (RAI 9.3.4-2) o Provided additional design information regarding flow-restricting venturis to support probabilistic risk assessment (RAI 9.3.4-3)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.3.6 Containment Evacuation System (CES)

Design changes from DCA:

o The CES inlet pressure instrumentation and connecting piping, up to and including isolation valves, are designed to SC-I standards (SC-III in DCA), which ensures these components maintain capability to perform their function during and after a safe shutdown earthquake.

o The same section of piping was increased to containment design pressure (Table 19.1-3) to act as a diverse independent backup to the CIVs in support of probabilistic risk assessment. (RAI 19.1-52)

Audit and RAI Results:

o Containment pressure correlates to a reactor coolant system leak rate (A-9.3.6-1) o Correction factor to account for water vapor bypass is calculated (A-9.3.6-2) o Vacuum pump removal of water vapor resulting from leaks inside containment (A-9.3.6-3)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.4: Air Conditioning, Heating, Cooling, and Ventilation Systems Section 9.4.1 Control Room Area Ventilation System Section 9.4.2 Reactor Building and Spent Fuel Pool Area Ventilation System Section 9.4.3 Radioactive Waste Building Ventilation System Section 9.4.4 Turbine Building Ventilation System Section 9.4.5 Engineered Safety Feature Ventilation System 9.2.9 Utility Water Systems

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.5: Other Auxiliary Systems Section 9.5.3 Lighting Systems Section 9.5.2 Communication Systems Section 9.5.1 Fire Protection Program 9.2.9 Utility Water Systems

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.5.3 Lighting Systems Changes from the DCA o Main control room (MCR) has dedicated emergency lighting that is continuously on Audit and RAI Results:

o Clarified illumination levels for normal and emergency lighting (RAI 9.5.3-1) o Explained how manual fire suppression would be handled with emergency lighting (A-9.5.1-2) o Clarified illumination levels outside MCR (RAI 9.5.3-3)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.5.2 Communication System Changes from the DCA o Sound-powered telephone system was removed o Health physics network added to the communication system o Removed COL Item 9.5-2 concerning the location of security power equipment within a vital area

Now part of the standard plant design No Audit items or RAIs specific to Section 9.5.2

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9.5.1 Fire Protection Program Changes from DCA o Building layout change Audit and RAI Results:

o Confirmed containment cable design attributes (A-9.5.1.2.4-1) o Explained that fixed emergency lighting is not required for post-fire safe shutdown functions or alternative safe shutdown functions (A-9.5.1-2 & A-9.5.3-1) o Discussed structural and electrical raceway fire barrier requirements (A-9.5.1-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 9A: Fire Hazards Analysis Design changes from DCA o Building layout change Audit and RAI Results:

o Clarified safe shutdown requirements vs capabilities concerning MCR evacuation (A-9A.6.4.1-1 & -2) o Clarified the fire hazards analysis to state which rooms did not contain safe shutdown equipment and discussed how propagation is mitigated (RAI 9A.5-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Acronyms ASME American Society of Mechanical Engineers CES Containment Evacuation System CIV Containment Isolation Valve COL Combined License CVCS Chemical and Volume Control System DCA Design Certification Application GDC General Design Criterion MCR Main Control Room RAI Request for Additional Information RPV Reactor Pressure Vessel RBC Reactor Building Crane SFP Spent Fuel Pool SC-I Seismic Category I SC-II Seismic Category II SSC Structures, Systems, and Components SDAA Standard Design Approval Application UHS Ultimate Heat Sink UWS Utility Water System

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Chapter 12 August 22, 2024 Presenter: Erik Slobe Radiation Protection

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Chapter 12: Radiation Protection Section 12.1 Ensuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable Section 12.2 Radiation Sources Section 12.3 Radiation Protection Design Features Section 12.4 Dose Assessment Section 12.5 Operational Radiation Protection Program

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 12.1 Ensuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable Same methodology as the Design Certification Application (DCA)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 12.2 Radiation Sources Same methodology as DCA Updated source term information in Tables 12.2-1 through Table 12.2-31 o Updated for change in cycle length, increase in burnup rate, change in thermal power, and change in number of NuScale Power Modules o Design basis failed fuel fraction is applied to one reactor for shared system source terms (11.1).

Audit results o Dose rate for workers on the fuel handling machine (A-12.2.1.8-1) o Decay of N-16 to insignificant levels in the chemical volume control system flow path (A-12.2-5) o Source terms for components of the low conductivity waste (LCW) processing skid, including LCW filters, ion exchanger, accumulators, and LCW polishers (A-12.2-3)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 12.3 Radiation Protection Design Features Same methodology as DCA Differences from DCA o No very high radiation areas o Reduction in number of reactor building and radwaste building shield doors o Reduction in fixed radiation monitors o Removal of COL Item 12.3-5 on additional area radiation monitors

Design criteria for area radiation monitors are included in Section 12.3.4.2 o Removal of COL Item 12.3-8 on radiation shielding for shield wall penetrations

Completion of more detailed shielding analyses Audit Results o Break pot tanks in phase separator tank and spent resin storage tank vent lines replaced with hooded vents (A-12.3.1.1-2)

RAI Results o Shielding based on nominal concrete equivalent gamma attenuation (RAI 12.3-1) o Radiation monitors under the bioshield are post accident monitoring system B, C, and F variables (RAI 12.3.4.2-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 12.4 Dose Assessment Same methodology as DCA Changes from DCA o Updated for change in cycle length, increase in burnup rate, change in thermal power, change in number of Nuscale Power Modules, building layout changes, and operational optimizations o Vital areas for post-accident actions do not include areas for initiating combustible gas monitoring Audit Results o An update to COL Item 12.4-1 includes changing the dose to construction workers from co-located existing operating NuScale Power Plants to a responsibility of the applicant. (A-12.4.1.9-1)

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 12.5 Operational Radiation Protection Program No changes from DCA

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Acronyms COL Combined License DCA Design Certification Application LCW Low Conductivity Waste NRC Nuclear Regulatory Commission RAI Request for Additional Information

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Chapter 18 August 22, 2024 Presenter: Doug Bowman Human Factors Engineering

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Introduction Chapter 18 Overview o Section 18.1 - Human Factor Engineering (HFE) Program Management o Section 18.2 - Operating Experience Review (OER) o Section 18.3 - Functional Requirements Analysis and Function Allocation (FRA/FA) o Section 18.4 - Task Analysis (TA) o Section 18.5 - Staffing and Qualifications (S&Q) o Section 18.6 - Treatment of Important Human Actions (TIHAs) o Section 18.7 - Human-System Interface (HSI) Design o Section 18.8 - Procedure Development o Section 18.9 - Training Program Development o Section 18.10 - Human Factors Verification and Validation (V&V) o Section 18.11 - Design Implementation (DI) o Section 18.12 - Human Performance Monitoring There are not slides for the areas that have not changed Other Items

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Comparison of HFE Program for US600 DCA and US460 SDAA Program Element US600 DCA US460 SDAA Operating Experience Review RSR Submitted IP Submitted Functional Requirements Analysis and Function Allocation RSR Submitted IP Submitted Task Analysis RSR Submitted IP Submitted Staffing and Qualifications RSR Submitted RSR Submitted Treatment of Important Human Actions RSR Submitted RSR Submitted Human-System Interface Design RSR Submitted IP Submitted Procedure Development COL Activity COL Activity Training Program Development COL Activity COL Activity Verification and Validation IP Submitted/RSR Submitted IP Submitted Design Implementation COL Activity IP Submitted Human Performance Monitoring COL Activity COL Activity Implementation plan (IP) describes methodology Results summary report (RSR) describes methodology and results NUREG-0711 allows for submittal of an IP or RSR DCA: submitted RSRs for all HFE elements that are predecessors to V&V SDAA: NuScale is following the traditional model for HFE

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 18.3 - Functional Requirements Analysis and Function Allocation The purpose of this element is to verify those functions needed to satisfy the plant's safety and commercial goals, and the assignment of those functions to personnel and automation, takes advantage of human and machine strengths and avoids human and machine limitations As the FRA/FA process has matured, a single, combined and interlinked database has been developed that aligns the HFE task analysis, FRA/FA database, the Operator Training Task Analysis and the Plant Operating Procedure set

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 18.4 - Task Analysis TA identifies specific tasks (human actions) required to satisfy the functions from the FRA/FA element Similar process to US600 DCA o Now combined in a single, interlinked database as described in Section 18.3

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 18.5 - Staffing and Qualifications S&Q determines the number and qualification of licensed operators required for safe and reliable plant operation o Minimum staffing requirement is one licensed reactor operator and two licensed senior reactor operators Changes from the DCA:

o For the DCA: Minimum staffing requirements are located in the DC rule (Part 52 App. G) o For the SDAA: Technical basis and approach for minimum staffing requirements is approved topical report NuScale Control Room Staffing Plan, TR-0420-69456-NP-A o Previously reviewed by ACRS (ML21139A226 and ML21139A232 [April 2021])

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 18.6 - Treatment of Important Human Actions Identification of IHAs within the scope of Chapters 7,15, and 19 Probabilistic Risk Assessment (Chapter 19) determines risk-important human actions Deterministic human actions are those credited in Chapter 15 and D3 (diversity and defense-in-depth) coping analyses of Chapter 7 (e.g., those required for long-term decay heat removal or reactivity control)

US460 Standard Design does not have IHAs Changes from the DCA:

o DCA included two IHAs No longer RIHAs in the SDAA (see Chapter 19) o The DCA IHAs are still addressed and mitigating strategies accounted for in the current SDAA generic technical guidelines, HSI design, HFE and training task analysis

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Section 18.7 - HSI Design HSI design element establishes the HSI design Substantially similar main control room and HSI as the US600 o US460 changes are in response to ISV and design changes from the US600

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Other Items New HFE-related ITAAC:

NuScale Nonproprietary Template #: 0000-21727-F01 R10 SDAA Audit 20 audit items successfully resolved Included virtual demonstration of simulator and staff review of databases

NuScale Nonproprietary Template #: 0000-21727-F01 R10 Acronyms ACRS Advisory Committee on Reactor Safeguards COL Combined License D3 Diversity and Defense-in-depth DCA Design Certification Application DI Design Implementation FRA/FA Functional Requirements Analysis and Function Allocation HSI Human-System Interface IHA Important Human Action IP Implementation Plan ISV Integrated System Validation MCR Main Control Room OER Operating Experience Review RIHA Risk Important Human Action RSR Results Summary Report S&Q Staffing and Qualifications SDAA Standard Design Approval Application TA Task Analysis TIHA Treatment of Important Human Actions V&V Verification and Validation

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