ML23255A079
| ML23255A079 | |
| Person / Time | |
|---|---|
| Issue date: | 09/14/2023 |
| From: | Subbaratnam R NRC/NRR/DANU/UARP |
| To: | |
| References | |
| Download: ML23255A079 (1) | |
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Advanced Reactor Stakeholder Public Meeting September 14, 2023 Microsoft Teams Meeting Bridge line: 301-576-2978 Conference ID: 791 911 650#
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Time Agenda Speaker 10:00 - 10:10 am Opening Remarks NRC 10:10 - 10:15 am Advanced Rx. Integrated Schedule NRC 10:15 - 10:45 am Computer Code Readiness for Advanced Reactor Applications NRC 10:45 - 11:15 am Quality Assurance Program Reviews for Advanced Reactor NRC Applications 11:15 - 11:25 am Public Comments Public 11:25 - 11:30 am Planning for the Next Meeting and Closing Remarks Adjourn 2
Advanced Reactor Integrated Schedule of Activities The updated Advanced Reactor Integrated Schedule is publicly available on NRC Advanced Reactors website at:
https://www.nrc.gov/reactors/new-reactors/advanced/integrated-review-schedule.html 3
Advanced Reactor Integrated Schedule of Activities 4
https://www.nrc.gov/reactors/new-reactors/advanced/integrated-review-schedule.html
NRC Readiness for Advanced Reactor Systems Analysis Stephen M. Bajorek, Ph.D.
Senior Technical Advisor for Thermal-Hydraulics Office of Nuclear Regulatory Research United States Nuclear Regulatory Commission Advanced Reactor Stakeholder Meeting September 14, 2023 5
Exciting Times for Nuclear Many designs under development.
Multiple technologies.
Key mission for NRC is to be prepared
. . . for any & all.
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7 NRCs Integrated Action Plan (IAP) for Advanced Reactors Near-Term Implementation Action Plan Strategy 1 Strategy 4 Knowledge, Skills, Industry Codes and and Capacity Standards Strategy 2 Strategy 5 Technology Inclusive Computer Codes Issues Strategy 3 Strategy 6 Flexible Review Communication Process 7
Independent Analysis Capability 8
Volume 1: Systems Analysis and Design Basis Event Simulation
- Volume 1 activities are designed to:
- 1. Identify analysis codes and code development needs for non-LWRs. Address known deficiencies.
- 2. Develop a set of reference plant models that :
A. Test the capability of analysis codes (i.e. find flaws now)
B. Generate models that can be quickly modified to represent the real design.
- 3. Perform a range of design basis simulations.
- Unprotected Loss of Flow (ULOF)
- Unprotected Loss of Heat Sink
- Design specific (i.e. Heat Pipe Failure) 9
Comprehensive Reactor Analysis Bundle BlueCRAB SCALE SERPENT Cross-sections Cross-sections PARCS GRIFFIN PRONGHORN Nek5000 Neutronics Neutronics Core T/H CFD TRACE MOOSE System and Core T/H Coupling, Tensor Mechanics FAST BISON SAM SOCKEYE Fuel Performance Fuel Performance System and Core T/H Heat Pipe Performance Planned Completed Coupling Coupling Input/BC Data NRC Code Intl Code DOE Code 10 Current View; Sept 2023
Multiphysics Coupling SAM: System Level Thermo-Fluids Griffin: Reactor Kinetics Temperatures & Densities Power Temperatures Displacements Tensor Mechanics Module 11
Reference Model Development Reference Models - Generic HTR-10 representation of a design type, based on publicly available information. ABTR MSRE Scenarios of interest are selected (loss-of-flow, loss-of-heat sink, rapid reactivity insertion).
Simulations performed to MCFR demonstrate code capabilities and identify deficiencies before licensing reviews begin.
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13 Reference Plant Models: Quick Status Design Type Reference Model Comment Gas-Cooled Pebble Bed HTR-PM Coupled Neutronics/Thermal-Fluid Sodium Fast ABTR Coupled Neutronics/Thermal-Fluid/Structural Molten Salt Cooled PB-FHR Coupled Neutronics/Thermal-Fluid Molten Fuel Salt (Thermal) MSRE Coupled Neutronics/Thermal-Fluid Molten Fuel Salt (Fast) EVOL 2D Slice Coupled Neutronics/Thermal-Fluid Microreactor (Vertical) SPR Design A Neutronics/Thermal-Fluid/Structural Microreactor (Horizontal) eVinci - like Coupled Neutronics/Thermal-Fluid 14
Reference Plant Models: Example 15
Reference Plant Models: Example 16
Reference Plant Models: Example 17
Reference Plant Models: Example 18
Improvements & Capabilities Exercise of BlueCRAB codes and simulation of events has helped develop several important capabilities.
Notable are:
- 1. Coupled pre-cursor tracking (molten fuel salts)
- 2. Equilibrium core calculation (Pebble tracking and depletion)
- 3. Coolant solidification
- 4. Multiple computation platforms (GovCloud, INL HPC, MacBooks) Stream Tube
- 5. Demonstration of coupled neutronic / tensor mechanics (fast spectrums)
- 6. MOOSE - Mesh for common geometries to speed input prep.
- 7. Heat Pipe Models (Superconductor - - SAM Component - - Sockeye)
- 8. Improvements in Multiphysics code coupling.
Mixing at outlet Discard 19 B > Bmax
Still Under Consideration . . .
- Phenomena that are significant and new with increased importance for non-LWRs relative to conventional LWRs include but are not limited to:
- Thermal stratification and thermal striping
- Thermo-mechanical expansion and effect on reactivity
- Large neutron mean-free path length in fast reactors
- Transport of neutron pre-cursors (in fuel salt MSRs)
- Solidification and plate-out (LMRs and MSRs)
- 3D conduction / radiation (passive decay heat removal)
- Molten salt thermophysical properties
- Secondary / tertiary loop modeling
- Modeling of RCCS and DHRS
- Heat Pipe performance and transient behavior 20
Evaluation Model Regulatory Guide 1.203 defines the Evaluation Model concept & process (EMDAP).
An evaluation model (EM) is the calculational framework for evaluating the behavior of the reactor system during a postulated transient or design-basis accident. As such, the EM may include one or more computer programs, special models, and all other information needed to apply the calculational framework to a specific event Elements of EMDAP include:
- 1. Determine requirements for the evaluation model.
- 2. Develop an assessment base consistent with the determined requirements.
- 3. Develop the evaluation model.
- 4. Assess the adequacy of the evaluation model.
- 5. Follow an appropriate quality assurance protocol during the EMDAP.
- 6. Provide comprehensive, accurate, up-to-date documentation.
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Reg Guide 1.203 Code Development Identify Plant & Scenario Establish Assessment PIRT Matrix (Phenomena Identification & Ranking Tables)
Experimental Model Analysis Testing & Data Development Code Evaluation Model Acceptable ?
Yes Deficiency Code Assessment Compare Code vs. IET and SET Application Uncertainty Methods Slide 22
BlueCRAB V&V Report Contents
- Introduction and Code Summary
- Verification
- Regression Testing and Coverage
- Verification of Code Coupling
- Evaluation Model Development
- Expected Scenarios
- Design Types Considered
- PIRTs
- Validation
- Gas-Cooled
- Liquid Metal Cooled
- Molten Salt Reactors
- Microreactors
- General Neutronics
- Components
- Appendix: Brief Description of Tests 23
BlueCRAB V&V Report
- BlueCRAB V&V Report Objectives:
- 1. Provide documentation that verification and validation exists and is being performed for codes that are part of BlueCRAB.
- 2. Summarize validation that is applicable (and probably necessary) for common design types.
- 3. Identify gaps in either the assessment base or available experimental database - to the extent possible prior to applicant submittals.
Assessment of individual codes does not necessarily satisfy EMDAP requirements. But it is an important first step.
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SMRs (LWRs with Passive Cooling)
Independent analysis of SMRs performed with conventional codes (TRACE, FAST, PARCS, MELCOR).
Previous work for AP600, AP1000, ESBWR provided initial validation and data.
Additional validation performed as needed, with experimental data provided by applicant, from international collaboration (ATLAS, PKL, PANDA, PERSEO) or by NRC (RBHT).
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Summary There remain several physical processes that need to be understood better for non-LWR analysis.
Reference Models for most designs are now available and are being used & improved.
For non-LWR system analysis and design basis type accident scenarios . . . We Are (cautiously) Ready.
Design specific information is necessary to develop independent analysis models.
Validation must be identified and shown sufficient and scaled to a particular design.
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27 Quality Assurance Program Reviews for Advanced Reactor Applications SEPTEMBER 14, 2023 FRANKIE VEGA R E A C T O R O P E R AT I O N S E N G I N E E R NRR/DRO/IQVB 28
Purpose/Outcome Present NRC staff expectations for advanced reactor developer quality assurance programs to support high-quality topical reports and applications.
Present issues encountered during staffs reviews and cover lessons-learned from these reviews.
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Outline Regulatory Framework Pre-application Activities Regulatory Requirements Regulatory Guidance Staff review approach/guidance - Standard Review Plan Issues encountered QAPD Reviews Lessons learned Staffs recommendations 30
Quality Assurance Program Description The QAPD is the top-level document that establishes the manner in which quality is to be achieved and presents overall philosophy regarding achievement and assurance of quality.
The QAPD provides for control of activities that affect the quality of safety-related nuclear plant structures, systems, and components (SSCs) and include all planned and systematic activities necessary to provide adequate confidence that such SSCs will perform satisfactorily in service.
The QAPD describes the methods and establishes quality assurance (QA) and administrative control requirements that meet 10 CFR 50.34, Appendix B to 10 CFR Part 50 and 10 CFR Part 52, as applicable.
QAPDs should be developed considering the intended application of the QAPD (e.g., ESP, COL, construction phase, operations, or all).
For CP application the QAPD should address design and construction QA activities For DC applications the QAPD should address design QA activities in support of a DC For COL applications the QAPD should address all phases of a facilitys life, including design, construction, and operation 31
Regulatory Framework (QA Reviews) 10 CFR Part 50 10 CFR Part 52 Process Processes Construction Early Site Permit -
Permit - 50.34 52.17 Design Operating License Certification &
- 50.34 SDAs - 52.47 and 52.137 Combined License
- 52.79 Manufacturing Licenses (52.157) 32
Applicable regulatory guidance associated with QAPDs (power reactors)
NUREG-0800, Standard Review Plan (SRP) for the RG 1.231, Acceptance of Review of Safety Analysis CommercialGrade Design RG 1.234, Evaluating Reports for Nuclear Power NRC Regulatory Guide (RG) NRC Regulatory Guide 1.33, RG 1.164, Dedication of and Analysis Computer Deviations and Reporting Plants, Section 17.5, 1.28, Quality Assurance Quality Assurance Program Commercial-Grade Items for Programs Used in Defects and Noncompliance Quality Assurance Program Program Criteria (Design and Requirements (Operation), Use in Nuclear Power SafetyRelated Applications Under 10 CFR Part 21, Description - Design Construction), Rev 5 Revision 3 Plants, Revision 0 for Nuclear Power Plants, Revision 0.
Certification, Early Site Revision 0.
Permit and New License Applicant 33
Applicable regulatory guidance associated with QAPDs (non-power reactors)
NUREG-1537, Part 1, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Format and Content, dated February 1996 NUREG-1537, Part 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Standard Review Plan and Acceptance Criteria, dated February Regulatory Guide 2.5, Quality Assurance Requirements for Research and Test Reactors, Revision 1, dated June 2010 ANSI/ANS-15.8-1995, American National Standard for Quality Assurance Program Requirements for Research Reactors, dated May 10, 2013.
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Issues encountered during staffs QAPD reviews
- 1. QAPDs are often generic and are applied to multiple applications
- 2. Scope/Applicability section of the QAPD does not clearly specify the application the QAPD will be supporting
- 3. QAPDs dont clearly state that an evaluation was performed against the SRP NUREG-0800 SRP 17.5
- 4. QAPDs lack statements with commitment to compliance with specific NQA-1 Quality Assurance Requirements for Nuclear Facility Applications, requirements
- 5. Applicants (non-licensees) must submit changes to an approved QAPD in accordance with 10 CFR 50.4(b)(7(ii) (vs 10 CFR 50.54(a) for licensees)
- 6. Regulatory Commitments are often vague and do not address specific RGs and its exceptions or clarifications 35
Issues encountered during staffs review (cont.)
- 7. QAPDs, when referencing NEI 14-05-A, Guidelines for the Use of Accreditation in Lieu of Commercial Grade Surveys for Procurement of Laboratory Calibration and Testing Services, often dont include all the conditions approved by the staff in the SE (ADAMS ML20322A019) (RG 1.28 Rev. 5)
- 8. QAPDs often dont include commitments to the most recent revision of RGs and generic letters (SRP 17.5 Section V)
- 9. Training and qualification requirements for inspection and test personnel typically are not included in QAPDs (SRP Section 17.5, Subsection II.T; Criterion II, NQA-1 Requirement 2 Section 302)
- 10. QAPDs referencing COL activities lack specific QA requirements for operation phases (SRP 17.5) and often dont include commitments to RG 1.33.
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Issues encountered during staffs review (cont.)
- 11. Relying on industry programs such as ASME and NUPIC as input or the basis for supplier qualification is not appropriate for most applicants
- 12. Roles and Responsibilities for quality related activities during each of the phases (i.e., design, construction and operation) should be clearly described 37
Lessons Learned
- Engage with NRC staff during pre-application phase
- Clearly state what applicants want to achieve with the Applicants QAPD are
- Submit a complete, accurate, and comprehensive submittal encourage
- Reference documents that reflect latest revision issued or endorsed
- Be familiar with issues identified with previous QAPDs reviews 38
Questions or Comments?
Contact Information Frankie Vega Kerri Kavanagh Quality Assurance and Vendor Branch Chief, Quality Assurance and Inspection Branch Vendor Inspection Branch Frankie.Vega@nrc.gov Kerri.Kavanagh@nrc.gov
Future Meeting Planning
- The next periodic stakeholder meetings in 2023 are scheduled for October 25, and December 7.
- Potential topics for our next meeting include seismic design, use of standard design approvals for construction permit and operating license applications, and metallic fuel qualification.
- If you have suggested topics, please reach out to Ramachandran Subbaratnam at Ramachandran.Subbaratnam@nrc.gov.
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How Did We Do?
- Click link to NRC public meeting information:
https://www.nrc.gov/pmns/mtg?do=details&Code=20230271
- Then, click link to NRC public feedback form:
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