JFoster & Associates, LLC Zachry Nuclear Engineering, Inc. · hydraulic behavior of reactor and...

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Zachry Nuclear Engineering, Inc. JFoster & Associates, LLC

JFA-Zachry provides robust engineering, design and project management services to support safe and efficient operation of nuclear facilities. JFA-Zachry maintains traditional engineering disciplines which include mechanical, nuclear, civil, electrical and instrumentation and controls. Focus areas include cyber security, digital instrumentation and controls, mechanical/structural analyses of systems and components, transient and accident analysis, core design/physics, containment/compartment analysis, radiological analysis, thermal hydraulics analysis, spent fuel management analysis, new plant analyses including alternative coolants and fuel designs, outage planning, inspection support, plant modification evaluation, efficiency improvements, nuclear fuel cycle management, probabilistic risk assessment/risk-informed engineering, severe accident analysis, fire modeling, engineering studies and plant design changes.

JFA-Zachry has been providing engineering services and software products (including GOTHIC, RETRAN, VIPRE, RADTRAD-NAI, PROTO-FLO, PROTO-HX, PROTO-HVAC and PROTO-SPRINKLER) to the nuclear industry since 1984. We are internationally recognized for our expertise in thermal hydraulics analysis, radiological analysis, safety analysis and code development.

JFA-Zachry (Mentor-Protégé) Capability Statement www.jfaidaho.com www.zachrynuclear.com www.numerical.com

Nuclear Software, Analysis, Engineering, Design and Project Management ZNE: DUNS: 077312973 CAGE: Code 3M490 EIN: 06-1067568

JFA-Zachry provides trusted, best-in-class so ware tools, analysis, engineering and project management for design, tesng and safe operaon of nuclear facilies worldwide, with focus on responsive, innovave, effecve soluons, customer relaonships and long-term value.

Contacts

Julie Foster, PMP Jim Harrell, PE President & CEO Senior Director [email protected] [email protected] 208-709-0508 919-349-9038

425 N. Capital Avenue, Idaho Falls, ID 83402 1109 W. Main Street, Boise, ID 83702 14 Lords Hill Road, Stonington, CT 06378 410 Memorial Drive, Suite 205, Idaho Falls, ID 83402 2810 Coliseum Centre Drive, Bldg. 5, Suite 200, Charlotte, NC 28217 200 Regency Forest Drive, Suite 330, Cary, NC 27518

Idaho Cleanup Project Fire Protection Engineering, Environmental Engineering, Chemical Process Engineering and IWTU

Idaho National Laboratory ATR Reactor & Nuclear Safety Engineering, HVAC Design, TREAT Project Startup Support, ATR Re-actor Digital Controls Systems Engineering, ATR Experiments Engineering Support and ATR Warm Waste System Analysis & Recommendations

TerraPower Analysis of Sodium-Cooled Reactor Designs, Molten Chloride Analysis Demonstration NuScale Support for System & Subchannel Analyses and RELAP Code Development

Idaho National Laboratory Advanced Test Reactor Analysis with RELAP & RETRAN Hanford Site Developed GOTH for Non-Newtonian Thixotropic Fluid Analysis TVA Compartment/Containment Pressure-Temperature Evaluation and Fluid Transient Analysis Hanford Site Evaluated Hydrogen Generation & Venting for a Waste Tank Idaho National Laboratory ATR PDQ Analyses & software modification for multi-Dimensional Neutron Diffusion-Depletion

REPRESENTATIVE PAST PERFORMANCE

ARPA-E Project Development of a Nearly Autonomous Management and Control System for Advanced Reactors

541330 Engineering Services 541990 Profession, Scientific and Technical Services 541511 Custom Computer Programming Services 541620 Environmental Consulting Services 541690 Other Scientific and Technical Consulting 561320 Temporary Help Services 541715 Research and Development in the Physical,

Engineering and Life Sciences 541618 Other Management Consulting Services

541613 Marketing Consulting Services 561990 All Other Support Services; Inventory Computing

NAICS Codes

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JFA-Zachry Mentor-Protégé Profile The JFA-Zachry Mentor-Protégé relationship was established in accordance with the United States Small Business Administration (SBA) All Small Mentor-Protégé Program (ASMPP) pursuant to 13 CFR §125.9. The purpose of the relationship is for Zachry Nuclear Engineering to utilize our 30+ years of nuclear experience and expansive nuclear capabilities to provide technical, management and business development assistance and mentoring to JFA. The JFA-Zachry Mentor-Protégé provides the following professional services: engineering and project management, environmental consulting, remediation services to federal, state, and local agencies, and private-sector clients, cyber security, digital instrumentation and control, civil/structural analyses, electrical analyses, mechanical analyses, transient and loss of coolant analyses, criticality analyses, reload and core design, fuel reliability, fuel mechanical and performance analysis, containment/environmental qualification analysis, radiological and shielding analysis, thermal hydraulics analysis, spent fuel management analysis, advanced plant and SMR analyses, outage planning flexibility and length reduction, regulator inspection support, plant modification evaluation, efficiency improvements, operability assessment, regulatory finding mitigation, nuclear fuel cycle management, probabilistic risk assessment/risk-informed engineering, severe accident analysis, fire modeling, engineering studies, and plant design changes. Zachry’s staff is comprised of some of the industry’s most highly trained experts, who have completed thousands of projects fundamental to and in alignment with the planned growth areas of JFA’s professional services, making the relationship beneficial to both parties and to our customers. Systems Analysis and Software Development

JFA-Zachry has expertise in the development and application of nuclear software, including developing and maintaining BOATM, CentralStor, COBRA (various versions), CORALTM, GOTHICTM, PROTO-ChillerTM, PROTO-FLOTM, PROTO-HVACTM, PROTO-HXTM, PROTO-SPRINKLERTM, RADTRAD-NAITM, RELAP (various versions), RETRANTM and VIPRETM. BOA is a crud and boron deposition prediction tool for Pressurized Water Reactors. CentralStor is a data archival and retrieval system in a nuclear quality assurance environment that also supports automation and integration of computer software runs. COBRA is a thermal hydraulics code for transient analyses of nuclear reactor components. GOTHIC is a comprehensive software package for efficient analysis of thermal hydraulic transients involving water, steam and noncondensing gases, as well as alternative fluids (such as sodium or molten chloride) and radioisotopes. GOTHIC is a versatile, easy to use, accurate tool for modeling a wide range of systems and events. From simple “lumped” analysis to detailed three dimensional modeling, GOTHIC combines features that quickly provide effective solutions. It is used extensively in the

nuclear utility industry for safety related applications. PROTO-Chiller is a steady-state chiller performance analysis program. PROTO-FLO is a steady-state single phase fluid flow program, including many typical nuclear components. PROTO-HVAC is a steady-state HVAC flow design program. PROTO-SPRINKLER is a steady-state fire protection program. RADTRAD-NAI is designed to estimate radiological doses at offsite locations and in onsite buildings (such as the control room or control room envelope) of a nuclear facility resulting from certain postulated accidents. RELAP is used to analyze the thermal-hydraulic behavior of reactor and balance of plant systems. RETRAN-3D is a best-estimate light water reactor and reactor systems transient thermal hydraulic code used extensively by the commercial nuclear industry. It is the basis for many utility-specific licensing and safety analyses and for various industry generic safety analysis submittals to the US Nuclear Regulatory Commission (USNRC) and has also been utilized for analysis of test reactors such as the ATR. The USNRC completed an extensive review of RETRAN-3D and issued a Safety Evaluation Report (SER) that finds it “acceptable for referencing in licensing applications”. VIPRE-01 is a finite-volume sub-channel analysis code capable of three-dimensional modeling of reactor cores and other similar geometries in steady-state and transient conditions. VIPRE-01 calculates the detailed steady-state and operational transient core flow distributions, coolant conditions, fuel rod temperature and MDNBR.

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JFA-Zachry General Engineering Capabilities In addition to extensive analytical and software development experience, JFA-Zachry maintains expertise in all of the traditional engineering disciplines, including civil/structural, mechanical, electrical and instrumentation and controls. This discipline engineering experience includes developing calculations, engineering studies and reports, plant design change packages and safety evaluations. JFA-Zachry also employs both nuclear engineers and health physicists, as well as personnel with plant operations and systems experience.

Mechanical Examples of mechanical experience include: system design and analysis, component expertise (heat exchangers, chillers, compressors, etc.), system modification and upgrade, power uprate projects, HVAC design and upgrades, emergency equipment modifications, and ASME code support. Electrical Examples of electrical experience include: electrical system design, ETAP, SKM, PSCAD, voltage drop, load flow, short circuit analyses, transient motor starting analyses, transient stability analyses, break replacements, variable frequency drives, auxiliary power systems, protective schemes, coordination studies, security system design, and open phase detection support.

Civil/Structural Examples of civil/structural experience include: structural analysis, piping and support design and analysis, reinforced concrete design and analysis, equipment anchorage, foundations, geotechnical engineering applications, high energy line break program support, flooding evaluations, seismic analyses and walkdowns and instrument/conduit supports. Instrumentation and Controls Examples of I&C experience include: analog control system upgrades, digital component and system upgraders/PLC projects, security system upgrades, plant process/security computer upgrades, radiation monitoring, power uprate support, advanced reactor design support and cyber security.

Project Initiation, Project Management and Execution Examples of key projects experience include: Project management and assessment, construction project reviews, cost estimating, project controls, earned value management, trending & analysis, project scheduling, hazard analysis and safety management (evaluation and oversight), lessons learned implementation, quality assurance, and risk management.

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Cyber Security Experience JFA-Zachry has been extensively involved with the nuclear industry’s efforts to implement Cyber Security Programs which comply with the requirements of 10CFR73.54 “Protection of Digital Computer and Communication Systems and Networks” as well as the industry guidance documents NEI 08-09, “Cyber Security Plan for Nuclear Power Reactors” and NEI 13-10 “Cyber Security Control Assessments”. JFA-Zachry is also fluent with several industry standards and best-practices, such as the ISA/IEC 62443 series, the ISO/IEC 2700x series, the NIST Cybersecurity Framework, the NISTSP800-53/82 guidelines, and other Network Security Monitoring (NSM) recommendations. While significant efforts have been made to date by each nuclear site to establish a foundation of cyber security that complies with their respective Cyber Security Plans, there will be a need for continuing cyber security activities. With this comes a new cyber security landscape for the nuclear industry to ensure that the cyber security controls for Critical Digital Assets (CDAs) are properly updated and maintained and that the facilities are prepared to support response/recovery. JFA-Zachry recognizes the importance of being able to assist with and respond to the cyber security needs of our industry and is capable of providing the following skills. Cyber Security Process/Program Skills JFA-Zachry’s key skills in the Cyber Security process include identifying a facility’s CDAs, and performing risk assessments of identified CDAs. Key observations, analyses, and findings of the risk assessments are documented using automated tools and manual forms. Beyond the analysis of individual CDA components, JFA-Zachry analyzes the applicability and rigor of controls that protect each CDA. Such an analysis involves tabletop reviews of vendor and technical documentation supporting the digital components under assessment. Additionally, performing walkdowns or electronic validation of CDAs to confirm and/or expand on information ensures the most thorough analysis. Beyond meeting the basic requirements for protecting CDAs, JFA-Zachry provides added value to its customers by establishing a basis for a fleet approach to Cyber Security CDA assessments and Cyber Security program management. JFA-Zachry considers the whole picture when it comes to Cyber Security. These skills ensure that JFA-Zachry’s Cyber Security analyses develop network solutions and program strategies that will minimize internal and external threats on digital computers, communication systems, and networks. Cyber Security IT Network/Industrial Control System (ICS) Skills

In addition to assessments of individual CDAs, JFA-Zachry has hands on experience with Network Components (Firewalls, Data Diodes, Switches, VMware, etc.), device deployment (Hostname, user credentials, IP address, default gateway, subnet assignment etc.), and network configuration (VLAN setup, logical port assignment, static routing, trunk port setup, configuring cisco discovery protocol, portfast, spanningtree, etc.). Combining these skills ensures JFA-Zachry delivers a robust Cyber Security network. JFA-Zachry’s experience in ICS and network management include device hardening (Access control list configuration, remote syslog, etc.), ICS Network Assessment

(passive data collection, network traffic analysis, etc.), and ICS Cyber Vulnerability Testing (Passive / Active Device Scanning, Service Enumeration, Active Vulnerability Scanning, Penetration Testing, Exploitation, Social Engineering, Vulnerability Assessment, etc.). JFA-Zachry’s cyber security experts comprise a highly capable team with deep understanding of utility processes, plant operations, networking, digital plant process systems/components, interconnection protocols, regulatory requirements and information security guidance/regulation. Our experience allows us to provide the optimum solutions and mitigation strategies to safeguard critical digital infrastructure at any nuclear utility site. Client recognition and trust in JFA-Zachry has led to assignments in qualified roles of CSAT Coordinator, CSAT Engineering, CSAT Maintenance/I&C, CSAT Operations, and Cyber Security Analyst.

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Zachry Nuclear Engineering, Inc. JFoster & Associates, LLC Idaho National Laboratory JFA-Zachry consistently provides responsive, quality technical and professional support across a broad and diverse project portfolio. JFA-Zachry’s proven experience in DOE nuclear facilities makes us best-in-class for understanding project scope, resource qualifications, and successful project execution. Idaho Cleanup Project JFA-Zachry’s resources supporting Fluor-ID and the Idaho Cleanup Project have ranged from subject matter experts (SMEs) in environmental and spent fuel processing systems, nuclear facility operations and startup/testing, troubleshooting the IWTU chemical process system (currently) with the local area’s most respected PhD in chemical engineering to project and outage scheduling (with an individual who has been a nuclear reactor operator, nuclear system engineer, and P6 scheduler in the most critical environments) to a construction coordinator and two work planners. INL Advanced Test Reactor (Individual Experience) While employed by Battelle Energy Alliance, the owner, Julie Foster, reactivated the center pressurized water loop 2A that was out of service for almost 20 years, enabling INL to perform more complex tests for commercial entities like EPRI. Another JFA-Zachry staff member, while employed by INL, worked as a qualified ATR Safety Analyst who performed safety analyses, USQ determinations, maintained the safety basis documentation, supported modifications, and helped with design basis reconstitution, while maintaining a DOE “L” security clearance. INL Advanced Test Reactor (JFA-Zachry Operation and Outage Support) JFA-Zachry’s operation and outage work at ATR includes providing services with their SMEs in ATR’s software and digital controls systems, writing nuclear safety packages for experiments, refurbishing the warm waste system, writing corrective actions and work packages to help extend the life of the reactor to 2085. We also helped to review and prepare the safety analysis for the hydraulic shuttle irradiation facility (HSIS) to provide suggestions that could enable INL/customers to irradiate fuels for short periods of time.

INL Advanced Test Reactor (JFA-Zachry Thermal-Hydraulic Analysis Support) JFA-Zachry revised RELAP5 and RETRAN ATR input models and performed safety-related thermal-hydraulic analysis for several proposed test programs. Additional analyses included performing an allowable temperature analysis for the standard and large in-pile test loops, and independent reviews of an ATR RELAP5 standard in-pile tube model based on drawings and other data. Supported proposed experiments with thermal-hydraulic analyses, a pump trip transient, and miscellaneous safety analysis projects.

INL Advanced Test Reactor (JFA-Zachry Core Physics Support) JFA-Zachry’s core physics expertise was utilized to perform PDQ core loading pattern analyses and MCNP analyses for heat loading for a core internal change-out study. Additional support included performing PDQ calculations to study power distribution and core monitoring instrumentation for the updated FSAR, and helped reconstitute original design bases ATR PDQ calculations.

Outage Management at IWTU JFA-Zachry provides full time outage management planning, issue resolution facilitation, activity coordination, project controls functions, and critical sequence scheduling for the Integrated Waste Treatment Unit (IWTU) modification completion, systems testing, start-up preparations and operations readiness demonstrations. JFA-Zachry personnel work with ICP management, IWTU management and Fluor-ID Senior Management to plan remaining scope and develop critical path schedules for outage completion and IWTU startup. The outage management oversight and execution scope require coordination of technical issues with engineering, nuclear facility operations, maintenance work planning, and construction management to clearly define critical issues, develop solutions with timely resolution paths, identify alternative parallel paths, minimizing impacts that hinder startup, and provide logical recovery schedules when needed.

Office Proximities to DOE Sites JFA-Zachry has offices located each within 2 miles of INL in Idaho Falls:

425 N. Capital Avenue, Idaho Falls, ID 83402 410 Memorial Drive, Suite 205, Idaho Falls, ID 83402

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Zachry Nuclear Engineering, Inc. JFoster & Associates, LLC Small Modular Reactors (SMR) and Advanced Reactor Designs JFA-Zachry has supported numerous Small Modular Reactor (SMR) and advanced reactor designs including, GE-Hitachi PRISM/ARC-100, mPower, NuScale, Westinghouse AP600, Westinghouse AP1000, GE-Hitachi ESBWR, Areva EPR, Toshiba ABWR, Mitsubishi Heavy Industries (MHI) US-APWR, KEPCO’s APR1400 and TerraPower’s sodium-cooled TWR and molten chloride designs.

GE-Hitachi PRISM/ARC-100 Authored the ARC-100 sodium fast reactor (SFR) primary heat transfer system and metal fuel design descriptions, as well as a plan for methods development and code qualification, for submittal to Canadian Nuclear Safety Commission (CNSC). JFA-Zachry staff participated in the design, layout and cost evaluation of the fuel fabrication facility and reactor service system, for a potential UK-PRISM SFR.

mPower Experience Performed design transients to evaluate plant design, transient and accident analyses with RELAP to support the Design Control Document (DCD), containment analysis methodology, multi-dimensional containment modeling with GOTHIC, subcompartment analyses with GOTHIC, Emergency Planning Zone dose assessment approach and Integrated Test Facility (ITF) RELAP model development and cases.

NuScale Experience Developed GOTHIC software modifications for point kinetics models, GOTHIC general plant model, VIPRE Subchannel models, transient and accident software development (NRELAP5), transient and accident analyses with RETRAN and RELAP, High Energy Line Break (HELB) Program development support and development of HELB GOTHIC models and case runs to determine environmental conditions of equipment in support of the Design Certification Application, and development of passive cooling GOTHIC models to simulate a loss of AC power event.

Westinghouse AP600 and AP1000 Experience Completed support modifications to WGOTHIC, test facility benchmarks/comparisons and containment analyses for the DCD. The Westinghouse AP1000 support included: WGOTHIC modifications, development of portions of WCAP-15846, subcompartment analyses and associated WCAP-15965, hydrogen and recombiner evaluations and GOTHIC predictive analysis for passive core cooling start-up testing.

GE-Hitachi ESBWR Experience Developed a Passive Containment Cooling System (PCCS) benchmark with GOTHIC, completed I&C design and analysis to support the DCD, completed plant-specific Combined Operating License Application analyses and developed input for the following sections of the COLA: Chemical Hazards, Meteorology, Diffusion, Groundwater Transport, Flooding, Wind and Tornado Loading, Flood Design, Piping Breaks and Effects, Environmental Conditions, Fuel System Design, Nuclear Design, Thermal Hydraulic Design, RCS Overpressure Protection, Containment Design and Performance, ECCS Design and Performance, Habitability Systems, Fission Product Removal and Control Systems, MSIV Leakage Control System, Fuel Pool Cooling, Ultimate Heat Sink Analyses, Cooling Water Systems, HVAC, Fire Protection Systems, Source Terms, Liquid and Gaseous Waste Management Systems, Process and Effluent Radiation Monitoring, Radiation Sources and Magnitude, Radiation Protection Design Features, Emergency Operating Procedures, and Accident Analyses. In addition, JFA-Zachry developed and applied a multidimensional groundwater transport program to evaluate the impact of radioactive liquid tank failures.

Areva EPR Experience Completed numerous accident and transient analyses with S-RELAP to support the DCD, completed GOTHIC containment analyses to support the DCD, completed Emergency Core Cooling System performance analyses to support the DCD, completed radiological analyses for accidents and completing Emergency Operating Procedure analyses with S-RELAP and GOTHIC.

Toshiba ABWR Experience The Toshiba ABWR support included developing a GOTHIC containment model and evaluating pool swell and hydrodynamic loads.

Mitsubishi Heavy Industries APWR Experience The MHI US-APWR support included developing and applying GOTHIC containment models and associated mass and energy release models for breaks.

KEPCO APR1400 Experience The KEPCO APR1400 support included developing GOTHIC containment models to evaluate containment sprays (including multidimensional models), transition from Combustion Engineering analytical methods to RETRAN-3D analytical methods, containment hydrogen mixing analysis, and Passive Containment Cooling System modeling support (including adding new heat transfer correlations).

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Zachry Nuclear Engineering, Inc. JFoster & Associates, LLC TerraPower GOTHICTM Support JFA-Zachry has been supporting the design and analysis of TerraPower’s traveling wave reactor (TWR) designs (both TWR-P and more recently the TWR-300) since 2015. This has included an expansion of the GOTHIC™ code to include sodium and molten chloride fluid properties to model the primary system coolant, as well as the development of some additional tools to model the core and steam generator loop design. To date, the work has proven that GOTHIC is capable of analyzing the primary system and has produced quality results that would be difficult to obtain using other analysis tools.

TerraPower is working on the design of a Molten Chloride Fast Reactor (MCFR) to complement the TWR design. The design utilizes a liquid fuel salt and features an open core design. GOTHIC has been demonstrated to be well-suited to simulate the MCFR because it can accurately and efficiently capture many of the important phenomena. For example, traditional system level codes like RELAP are limited to confined geometries and wall-drag dominated flows. Meanwhile, GOTHIC includes a full treatment of the fluid-fluid shear as well as molecular and turbulent diffusion, which is consistent with what would be found in a CFD type code. This is one reason that GOTHIC can accurately simulate mixing, stratification and buoyancy-driven natural circulation. At the same time, GOTHIC still relies on wall functions (e.g., correlations for heat transfer coefficients and friction factors) rather than trying to resolve the boundary layer. As a result, GOTHIC can apply much larger computational cells than CFD type codes. The significant reduction in mesh density is one reason that GOTHIC is much more computationally efficient than CFD, while still providing equal accuracy in benchmark data comparisons. Additionally, the generic fluid property framework that was developed and implemented in GOTHIC to support sodium properties for the TWR designs can be extended to apply for molten salts as well. GOTHIC v8.3, released in early 2019, includes fluid property tables for six (6) generic molten salts; however, specific fluid property tables can be created as needed. Additionally, GOTHIC has been demonstrated as effective in tracking radioisotopes in various fluids and has the capability to support radiological source term determination for advanced reactor designs.

Liquid Sodium and Molten Salt Reactor Relevant Experience ◊ Completed preliminary investigation of sodium spray fires, including licensing criteria, literature review, data requirements, and

GOTHIC capability review. ◊ Developed GOTHIC models of the TerraPower TWR-P for the hot pool and full vessel. ◊ Performed natural circulation and loss of heat sink calculations, and heat exchanger placement studies for the TWR-P using

GOTHIC. ◊ Completed detailed GOTHIC model development to support TWR-P design with respect to potential sodium-water reaction due to

a Steam Generator Tube Rupture (SGTR), loss of heat sink with transition to natural circulation, and an alternate vessel design. Developed the sodium-filled Intermediate Heat Transfer System (IHTS) in GOTHIC, including steam generators and intermediate heat exchangers in configurations of stand-alone models as well as models coupled to the GOTHIC reactor vessel. Included the development of the Direct Reactor Auxiliary Cooling System (DRACS) model. The models successfully demonstrated Reactor Vessel steady-state and transient performance and the system pressure response due to the sodium-water reaction.

◊ Developed a simplified TWR-P model to evaluate flow patterns, determine loop transport time, and enhance model run time. ◊ Performed benchmarks to existing testing facilities and experiments. For example, developed a GOTHIC model of the

Experimental Breeder Reactor II (EBR-II) and performed a benchmark simulation of the Shutdown Heat Removal Test 17. This analysis was performed to validate GOTHIC for the TWR-P design.

◊ Developed a GOTHIC model of the TWR-300 and completed a reactor vessel pressure drop study at steady state, Loss of Heat Sink (LOHS) transient analysis, DRACS assessment of core overcooling and overheating events, and SGTR transient analysis.

◊ Developed an automated process to create a fully detailed TWR-300 reactor core GOTHIC model including all fuel assemblies, all heat structures, and with localized reactor power for each assembly. A DLL was also developed that automatically balances all assembly inlet orifice losses considering steady state flows.

◊ Performed a series of simulations to demonstrate the applicability of GOTHIC to the TerraPower Molten Chloride Fast Reactor (MCFR). Focused on physical processes and phenomena that are important in the MCFR design and operation, including thermodynamic and transport properties for a molten chloride, ability to represent relevant geometry and components, and simulating fission product transport, including radioactive decay.

◊ Modified GOTHIC in support of modeling the MCFR design, including an option to specify decay heat released to the system from decaying liquid fuel.

◊ Simulated source terms and fission product transport following a leakage event, with release to the environment, for a molten salt reactor design.

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Pacific Northwest National Laboratory and Hanford Site JFA-Zachry has completed a variety of analyses to support continued operations at the Hanford Site. JFA-Zachry’s work for Hanford also included development of a custom version of GOTHICTM, named “GOTH,” for Non-Newtonian Thixotropic Fluid Analysis, and included the addition of particle field modeling and implementation of a time-dependent laminar shear stress model. Thermal-Hydraulic Analysis of Underground Waste Tank C-106 JFA-Zachry developed an analysis model of the C-106 waste tank at the Hanford site using GOTH, an early version of GOTHICTM modified for non-Newtonian Thixotropic fluid analysis. The model was benchmarked to a 1994 test, termed “the Process Test,” for the purpose of observing temperature rise at thermocouple locations within the tank sludge under various environmental conditions. The controlled test was conducted in winter months so that the benchmarked model could reasonably predict scenarios in the summer months, when tank behaviors could be more volatile.

With the benchmarked model of the waste tank C-106, JFA-Zachry simulated the Process Test during hot summer months and made predictions about the sludge behavior such as a rise in sludge level of a few inches due to steam generation and gas retention in the sludge. Observations were also made regarding the temperature profile of the sludge and if temperatures approached saturation, or the effect of environmental conditions on the saturation zone. The detailed noding of the GOTH model combined with the thixotropic analysis capability allowed JFA-Zachry to confidently make recommendations as to how specific portions of the sludge should be mixed (or not mixed) together to ensure the overall contents of the tank remain stable.

Simulation of a Gas Release Event in Tank 101-SY (Hydrogen Generation and Sludge Mixing)

JFA-Zachry developed a GOTH model which simulates the behavior of the contents of Tank 101-SY during a gas release event (GRE). Having a model that simulates GREs not only helps to understand the phenomena, but also is critical in evaluating operational and safety implications of GREs especially those resulting from routine or experimental operations.

The GRE phenomena is the result of hydrogen (primarily) generation in the non-convective layer (thick bottom layer, or “sludge”) of the tank’s contents. Eventually the amount of entrapped gas becomes large enough that a localized mixture of gases, particles, and liquid within this thick layer become less dense than the supernatant mixture of liquid and particles above it. When a portion of the non-convective layer becomes less dense than the supernatant layer, instabilities develop between the layers and the contents of the tank roll over. This represents a sort of natural mixing of tank contents.

GOTH, and later versions of GOTHIC, are ideal tools to simulate the GRE because of its ability to simulate two-phase flow, laminar shear stress and conduction within the fluid, and turbulent shear stress and energy transport. These capabilities are believed to be essential to the simulation of the tank contents which consists of a mixture of liquid, solid particles and gas bubbles. GOTHIC features additional components such as fans, pumps and valves, and through-wall conduction heat transfer that are important to the simulation of tank safety, ventilation and mitigation systems. N-Reactor Thermal Hydraulic Analyses Two analyses were completed for the N-Reactor at PNNL showcasing some of the fundamental features of GOTHICTM. First was a compartment pressurization following a LOCA, from a break near the pressurizer (shown right). The second analysis was a demonstration of hydrogen (forced flow) mixing within the pressurizer penthouse. Additional Hanford/PNNL Projects Condensation Induced Water Hammer Fire Evaluation for the Plutonium Finishing Plant Tank Ventilation System Demonstration

Office Proximity to DOE Site JFA-Zachry has an office located within 5 miles of

PNNL and the Hanford Site in Washington: 1955 Jadwin Avenue, Suite 470, Richland, WA 99354

Break

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JFA-Zachry Additional DOE/Government Experience ARPA-E Project: Development of a Nearly Autonomous Management and Control System for Advanced Reactors (NAMAC)

The North Carolina State University led team, which includes JFA-Zachry, is currently working to develop a highly automated management and control system for advanced nuclear reactors. The system will provide recommendations to plant operators and will use artificial intelligence and continuous data monitoring to predict future plant status through machine learning. Ultimately, the team seeks to enable a significantly smaller operational staff to manage the plant, assisted by instrumentation, operator training, and smart procedures, reducing overall operational cost. The project is led by NC State University and includes JFA-Zachry. Other partners in the project include TerraPower, INL, ORNL, New Mexico State University, and Ohio State University. JFA-Zachry’s project scope includes the use of GOTHIC as a modeling and simulation tool to assist in the development of the NAMAC capability for a non-LWR design where a primary goal is to support reduction of the emergency planning zone radius. GOTHIC was selected because of its ability to model alternative fluids and track radioactive isotopes in a full system model in a computationally efficient manner. Thermal-Hydraulics for Tennessee Valley Authority (TVA)

JFA-Zachry is currently building on its working relationship with TVA through several recent projects. JFA-Zachry performed room heat-up calculation conversions from MAYA TMG models to GOTHIC models for Watts Bar, Sequoyah, and Browns Ferry. Another similar conversion was completed for a high energy line break (HELB) calculation, from the MONSTER code to GOTHIC for the West Valve Vault at Sequoyah. JFA-Zachry is using GOTHIC to evaluate axial loads along a portion of feedwater piping at Watts Bar. JFA-Zachry supported initial PRA efforts of screening equipment for reclassification under 10CFR 50.69. One project considered the 6.9kV and 480V board rooms at Watts Bar for a 24 hour mission time. The evaluation developed six approaches/options for mitigating peak temperatures in these room without crediting the associated chiller that provides room cooling. The second project considered the removal of a RHR Pump Room Cooler at Browns Ferry for a 24 hour mission time. A GOTHIC model of the 3-Unit Reactor Building demonstrated the potential for cooling the RHR Pump Room simply through bouyancy-driven airflow. JFA-Zachry’s responsiveness was highlighted by completing a time-sensitive third party review of the WBN Units 1 and 2 Past Operability Evaluation (POE) document packages addressing ECCS gas issues (CR1407257), including support for meetings/phone calls as required. Fire Modeling

JFA-Zachry personnel have both code development and applications experience with FIRAC and CFAST. JFA-Zachry personnel have utilized GOTHIC for limited fire/temperature and smoke transport modeling, particularly modeling of a pool fire and associated temperature effects.

Safety Evaluations, Analyses, and Unreviewed Safety Question Determinations

JFA-Zachry personnel have experience in performing safety evaluations, analyses and USQ determinations for both commercial nuclear facilities and government nuclear facilities.

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Alternative Fluid, Non-Newtonian Fluid and Groundwater Modeling and Software As described previously, JFA-Zachry has significant experience in both software development and analysis of alternative fluids/coolants, non-Newtonian fluids and groundwater transport.

Alternative Fluids

GOTHIC’s ability to model any reactor coolant system cooling fluid has been instrumental in the design of some advanced reactors. GOTHIC’s ability to model sodium, molten chlorides and gases as reactor coolants allows it to readily support these non-water-cooled reactor designs. GOTHIC has been benchmarked against facilities such as EBR-II further demonstrating its fidelity and allowing it to be used as a design tool for new reactor designs. GOTHIC additionally is capable of modeling radioisotopes, including removal and decay mechanisms, such that it can be used for tracking and establishing a source term for alternative reactor design radiological analyses. A demonstration model for molten chloride with circulating fuel has been created.

Non-Newtonian Fluids

A derivative of GOTHIC was developed (GOTH) to support modeling sludge and other non-Newtonian fluids, such as those in some waste tanks. The models implemented in GOTH cover both yield-pseudoplastic and thixotropic fluids/materials. GOTH allows for: non-zero yield stress, non-zero shear strength, non-linear relationship between the shear stress and strain rate, temperature dependence, particle concentration dependence and time dependence (thixotropic).

Groundwater Modeling

JFA-Zachry developed a multidimensional groundwater transport model to assess the impact of radioactive liquid tank failure on nearby bodies of water, rivers and wells. The USNRC approved the software as part of the ESBWR licensing effort. GOTHIC may also be utilized to model groundwater transport.

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Radiological Consequences and Shielding Experience JFA-Zachry has extensive experience in the application of various dose and shielding software packages to creatively solve utility and vendor challenges. JFA-Zachry also has extensive experience in performing shielding and equipment modifications to resolve utility and vendor issues. RADTRAD and RADTRAD-NAI JFA-Zachry has completed numerous radiological analyses utilizing the RADTRAD and RADTRAD-NAI software packages, including Alternative Source Term (AST) and support for RADTRAD-NAI models in licensing submittals. MCNP, MICROSHEILD, and MICROSKYSHINE Zachry developed extensive shielding and dose calculations for Robinson’s and Brunswick’s Independent Spent Fuel Storage Installations (ISFSIs). This effort included completing point source hand calculations, as well as MCNP, MICROSHIELD and MICROSKYSHINE calculations. Zachry personnel have utilized MCNP for a wide range of radiological analyses, including criticality analyses, PWR spent fuel storage, criticality alarm system design, and medical isotope production.

PAVAN, ARCON96 JFA-Zachry staff utilize PAVAN and ARCON96 to calculate atmospheric dispersion coefficients and atmospheric concentrations from a radiological release, for input into radiological dose analyses. ORIGEN, QADMOD-GP JFA-Zachry staff are experienced at using ORIGEN to develop isotope generation, depletion, and decay heat data for input into other radiological codes and analyses. Data from ORIGEN is typically key information in characterizing the source term.

NRCDOSE The NRCDOSE suite combines LADTAP, GASPAR, and XOQDOQ, which predict routine radioactive effluents from nuclear power plants through liquid pathways, gaseous pathways, and atmospheric dispersion. JFA-Zachry staff successfully used NRCDOSE to support a utility’s COL Appendix I evaluation. HABIT JFA-Zachry has experience with the HABIT suite for addressing Control Room Habitability during accidental releases of toxic chemicals or radioactive materials. Recently JFA-Zachry used HABIT to estimate the toxic chemical release impact on Control Room habitability for a utility’s COL evaluation. Radiological Analysis Impact JFA-Zachry’s diverse and extensive experience with industry radiological analysis software ensures that all aspects of plant systems, operations and maintenance are considered in the analyses, as well as the appropriate theory. JFA-Zachry has delivered outstanding radiological products to its customers through applications of the above mentioned software. Key radiological applications experience among the staff includes Off-site/On-site dose analyses, source term and shielding analyses, criticality analyses, source term, and X/Q analyses.

In many cases, there is data validation or analysis required to generate inputs or process outputs from the radiological analysis. As part of delivering a complete and useful product to our customers JFA-Zachry is well equipped to handle these peripheral aspects of the radiological analyses. Some examples include meteorological data validation, equipment qualification, chemical/pH analyses, vital area access analyses for EOPs, and groundwater transport analyses.

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Nuclear Fuel Analysis and Core Physics/Criticality In order to be responsive to customer needs and to support safe and efficient operation and modification of nuclear plants, JFA-Zachry supports: operations evolution assessments, regulatory finding evaluations, generic regulatory issue resolution, reduction of dependence on external suppliers (fuel vendors, Architect Engineers, etc.), efficiency improvements and assurance that plant modifications are both technically feasible and economical. For many of these situations, time is of the essence. Possessing the appropriate skills, experience and analytical tools is critical to success. JFA-Zachry has the required skills, experience and tools to solve these problems as can be seen by the depth and breadth of our described expertise.

In addition, JFA-Zachry personnel have provided significant reload analysis and review support. JFA-Zachry staff have supported performance of reload analyses for BWRs and PWRs, as well as independent detailed technical reviews of fuel vendor thermal hydraulic and neutronic analyses. The JFA-Zachry has the reload analysis experience to support either fuel vendors or utilities, including prior qualification in General Electric and Westinghouse methods. With respect to fuel vendors, JFA-Zachry has the capability to complete analysis preparation and review work for reloads to support schedule constraints. With respect to utilities, JFA-Zachry has the capability to support owner's reload reviews of the work performed by fuel vendors and core design optimization.

JFA-Zachry’s staff members also have extensive analytical methodology development experience, including Regulatory Guide 1.203 (Transient and Accident Analysis) implementation and defense to the regulator.

Transient and LOCA Analysis As the developer and maintainer of RETRAN and VIPRE, JFA-Zachry has unsurpassed NSSS and subchannel code methods, modification and applications experience. This support began with the original NRC submittals and subsequent Safety Evaluation Reports and continues today. JFA-Zachry personnel have extensive RELAP development experience, having supported fuel and new plant vendors and Naval Reactors. JFA-Zachry personnel have COBRA subchannel thermal hydraulics code development and applications experience.

Examples of our JFA-Zachry personnel world-wide transient and LOCA experience: • Built RETRAN models for 42 PWRs and 8 BWRs • Built VIPRE models for 46 PWRs and 6 BWRs • Built RELAP models for 62 PWRs and 8 BWRs • Built COBRA models for 12 PWRs and 2 BWRs

Fuel Reliability Experience and Support JFA-Zachry personnel supported the development and analyses of BWR crud deposition models and a risk assessment tool (CORAL) to predict tenacious crud deposition and assess the risk for crud-induced fuel cladding corrosion issues. JFA-Zachry personnel also supported the development and application of a Boron-induced Offset Anomaly (BOA) risk assessment tool to evaluate corrosion, physical chemistry, and thermal hydraulic effects for the prediction of corrosion product release. JFA-Zachry is the current maintainer of CORAL and BOA.

Fuel Mechanical Performance JFA-Zachry personnel have experience with fuel mechanical and performance analyses including FRAPCON analyses, fuel performance code development, review of fuel vendor (COPERNIC and TACO) fuel mechanical analyses, and verification of BWR fuel mechanical evaluation software.

Core Physics and Criticality JFA-Zachry personnel have extensive experience with several core physics software packages, including several versions of CASMO/SIMULATE. JFA-Zachry personnel have completed design depletion analyses, cycle specific loading patterns, cross-section development, axial shape analyses, verification of radial falloff curves, evaluation of burnable poisons, pin layout optimization and fuel pattern optimization. JFA-Zachry has also partnered with the developer of CASMO/SIMULATE, Studsvik. JFA-Zachry personnel have criticality and shielding modeling experience with MCNP and have created automation and parallel processing modifications/additions for the software.

JFoster & Associates, LLC Zachry Nuclear Engineering, Inc. · hydraulic behavior of reactor and...

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