ML21019A462
| ML21019A462 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/2021 |
| From: | Jordan Hoellman NRC/NRR/DANU/UARP |
| To: | |
| Hoellman J,NRC/NRR/DANU/UARP | |
| References | |
| Download: ML21019A462 (112) | |
Text
Advanced Reactor Stakeholder Public Meeting January 21, 2021 Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 644 910 374#
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Time Agenda Speaker 10:00 - 10:15 am Opening Remarks NRC 10:15 - 10:30 am Regulatory Priorities for New and Advanced Reactors -
NRC Feedback on NEI Input M. Shams, NRC 10:30 - 11:00 am Pre-application Engagement White Paper - Incorporation of Feedback from November 5, 2020, Stakeholder Meeting A. Muniz, NRC 11:00 - 11:30 am Pre-application Engagement for Greater Enrichment of Fuels for Advanced Reactors M. Diaz, NRC 11:30 am - 12:00 pm Incorporation of HySplit Atmospheric Transport Dispersion (ATD) Model into MACCS to Advance ATD Capabilities D. Clayton, Sandia National Laboratories 12:00 - 12:15 pm Status of NRCs Endorsement Review of the Advanced Non-Light Water Reactor (ANLWR) Probabilistic Risk Assessment (PRA) Standard M. Gonzalez, NRC 12:15 - 1:00 pm BREAK All 1:00 - 1:45 pm U.S. Department of Energy (DOE) Gateway for Accelerated Innovation in Nuclear (GAIN) Initiatives C. King, DOE/GAIN 1:45 - 2:15 pm DOE Advanced Reactor Demonstration Program (ARDP)
Update T. Beville, DOE-NE 2:15 - 2:45 pm ASME Section III, Division 5 - Discussion of Contractor Reports Supporting NRC Endorsement J. Hoellman and J. Poehler, NRC 2:45 - 3:00 pm Concluding Remarks and Future Meeting Planning NRC/All 2 of 112
Advanced Reactor Integrated Schedule of Activities https://www.nrc.gov/reactors/new-reactors/advanced.html 3 of 112
NRC feedback on NEI Input on Regulatory Priorities for New and Advanced Reactors January 21, 2021 Mohamed Shams, Director Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU) 4 of 112
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Background===
- NEI letter dated December 18, 2020 (ML20353A393)
- NEI recommended establishing the following key regulatory objectives to inform NRC priorities:
1.
Streamlining of regulatory processes needed to support the timely and efficient review and oversight of new and advanced reactors.
2.
Resolution of key generic technical or policy topics needed to support the review and approval of new and advanced reactor applications.
3.
Changes to the regulations that are needed to achieve a more modern and efficient regulatory framework.
- Specific recommendations provided in an enclosure 5 of 112
Overview
- The staff appreciates NEIs input.
- The recommended key regulatory objectives are consistent with the NRCs vision and strategy for advanced reactor readiness.
- Our ongoing activities align with the NEIs specific recommendations
- Some differences in schedules 6 of 112
Several rulemakings are underway to modernize the regulatory framework Ongoing:
- Alternative Physical Security Requirements for Advanced Reactors (PR 4Q2021, FR 2Q2023)
- Advanced Nuclear Reactor Generic Environmental Impact Statement (GEIS)
- Emergency Preparedness Requirements for Small Modular Reactors and Other New Technologies (FR 4Q2021)
- Alignment of Licensing Processes and Lessons Learned from New Reactor Licensing (10 CFR Part 50 and 52)
Planned:
- Annual Fee Rule for Non-LWRs (FY2022)
- Part 51 PR = Proposed Rule FR = Final Rule 7 of 112
NEI Letter NRC Activities NRC generic environmental impact statements (GEISs) that minimizes the scope of site-specific environmental reviews GEIS rulemaking underway.
NRC guidance on the broader use of environmental assessments (EAs) and categorical exclusions Rulemaking for categorical exclusion is underway and staff will consider EAs for microreactors under rulemaking.
NRC allows existing environmental analyses to be incorporated into a projects EA or EIS NRC NEPA regulation already allows for environmental analyses to be incorporated into EAs and or EISs.
NRC clarity on an approach to use the applicants environmental report (ER) as the draft EA or EIS Not a planned activity NRC elimination of unnecessary burden in alternative site analysis ISG-029 provides guidance to the staff on focusing its review of the alternative site analysis.
NRC implementation of changes that increases efficiency of environmental reviews Ongoing activities: Issued ISG-029, developing a GEIS, and participates in FAST-41 and EO-13807 (one Federal Decision).
NRC elimination of duplicative adjudicatory hearings for NRC environmental reviews Not a planned activity: This requires Commission decision and possible rulemaking.
NRC is taking action to optimize the environmental reviews 8 of 112
Ongoing guidance development facilitates safety-focused reviews
- ISG for Construction Permit Applications
- Technology Inclusive Content of Applications Guidance (TICAP) (2021)
- Advanced Reactor Content of Applications Guidance (ARCAP)
(ISGs in 2021)
- Fuel Qualification
- Endorsement Non-LWR PRA standard
- Environmental ISG (Issued) 9 of 112
The staff has published generic licensing review schedules in accordance with Section 102(c) of NEIMA https://www.nrc.gov/about-nrc/generic-schedules.html.
The staff has developed a preapplication white paper to encourage robust preapplication interactions to facilitate shorter review schedules.
The staff has implemented strategies such as core review teams and the use of audits to facilitate timely and efficient reviews.
The staff is working on guidance to focus the level of detail in applications and to focus the staffs review on safety and risk significant areas.
The staff completed the NuScale DC, Clinch River ESP, and APR1400 DC reviews on or ahead of schedule.
In all cases, adequate time will be taken to provide reasonable assurance of adequate protection to the health and safety of the public.
NRCs actions and initiatives continue to improve review timeliness 10 of 112
Staff is working to timely resolve technical and policy topics Siting - awaiting Commission SRM Advanced Manufacturing Technologies (AMT)
- AMT Action plan was published in July 2020 (ML19333B980)
- Public workshop was held in December 2020
- Initial AMT application and review guidelines framework document (Subtask 2C in the Action Plan) published July 2020 (ML20203M254) (Revision under development).
Applicability of Regulations to Non-LWRs
- Staff response to NEI input planned in early 2021
- Revision to staff white paper planned in 2021 11 of 112
Conclusion
- Staff will continue to seek input from stakeholders on ongoing and planned activities
- Staff priorities are focused on ongoing license application reviews, preapplication engagement reviews, NEIMA required activities, Commission directed rulemakings, and activities to prepare for new applications.
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Finalization of Draft White Paper -
Preapplication Engagement to Optimize Application Reviews Adrian Muniz, Project Manager Advanced Reactor Licensing Branch January 21, 2021 13 of 112
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Background===
Draft White Paper was discussed during the 11/05/2020 advanced reactor meeting Stakeholders provided feedback for staffs consideration NRC staff considered the comments and is revising the document, as appropriate See ADAMS Accession No. ML21014A267 for current version 2
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Summary of Key Changes Probabilistic Risk Assessment (PRA)
Clarified the need for pre-application engagement to support efficient application reviews. Key areas include:
Preliminary PRA and/or peer review results for audit PRA acceptability for its use in the application Deviations from endorsed standards and staff guidance Early availability of risk insights Level of detail and degree of realism of PRAs for different licensing applications including construction permit Regulatory Exemptions Regulatory gap analysis should be informed by staffs draft white paper titled Analysis of Applicability of NRC Regulations for Non-LWRs Environmental Sections Updated the list of guidance documents that should be considered in developing an environmental report in preparation for pre-application interactions Revised and clarified examples of issues that have been challenging for previous combined license and early site permit application reviews Clarified the timeframe to begin pre-application interactions 3
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NEXT STEPS
- Review and concurrence of Revised Draft White Paper for final issuance
- Final White Paper will be posted on NRCs advanced reactors website 4
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Questions?
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NMSS/DFM Pre-application Engagement for Advanced Reactor Fuels January 21, 2021 Marilyn Diaz Office of Nuclear Material Safety and Safeguards (NMSS)
Division of Fuel Management (DFM)
Fuel Cycle Facilities, Transportation &
Storage 18 of 112
Support NRR Advanced Reactor (AR) program.
Readiness to license and certify fuel facilities, transportation packages, and spent fuel storage installations.
Enrichment (10 CFR Part 70),
Fuel fabrication (10 CFR Part 70),
Transportation package certification (10 CFR Part 71),
Spent fuel storage installations (10 CFR Part 72),
Material Control & Accounting (MC&A) (10 CFR Part 74) 2 NMSS/DFM Advanced Reactor Fuel Activities 19 of 112
Regulations (10 CFR Part 70) are adequate for the review of fuel enrichment and fabrication for technologies being developed at higher enrichments.
We continue to assess our regulatory framework to identify any challenges and/or data needs.
We are conducting technical evaluations to assess necessary updates for the guidance to account for AR designs Finalized report on possible material control and accounting approaches for a pebble bed reactor (ML20112F355).
Updating NRC guidance for material control and accounting for Category II fuel cycle facilities.
3 Readiness Activities - Fuel Cycle Facilities 20 of 112
We have experience in the approval of transportation packages and storage systems for TRISO and metallic fuels.
We are completing technical evaluations on transport and storage activities of ARF designs to identify potential information needs and determine whether additional updates to safety review guidance may be warranted.
Review of Operating Experience for Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types Potential Challenges with Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types Storage Experience with Spent (Irradiated) Advanced Reactor Fuel Types Potential Challenges with Storage of Spent (Irradiated) Advanced Reactor Fuel Types Transportation Experience and Potential Challenges with Transportation of Spent (Irradiated) Advanced Reactor Fuel Types Disposal Options and Potential Challenges to Waste Packages and Waste Forms in Disposal of Spent (Irradiated)
Advanced Reactor Fuel Types 4
Readiness Activities - Storage, Transportation & Disposal 21 of 112
Meetings between AR vendors will help staff gain knowledge on specific designs and technologies.
Training sessions will provide staff with insights into significant safety features of specific designs and technologies.
Technical reports addressing potential challenges will help staff risk inform their reviews.
5 How are we preparing?
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We encourage pre-application engagements to support an efficient review of new applications and amendments.
NMSS/DFM Letters to Advanced Reactors Stakeholders to encourage potential applicants to engage in early communication and interactions.
Pre-application engagements provide benefits for NRC staff and applicants.
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NMSS/DFM is proactively identifying potential technical challenges and information needs associated with the safe use of AR fuels in the areas of enrichment, fabrication, transport and storage.
NRC expects some of the efforts related to accident tolerant fuel to benefit the licensing and certification of ARFs.
Applicants are encouraged to engage early to ensure a common understanding of the regulatory issues associated with new AR fuel technologies.
We have experience with advanced technologies with regards to fuel cycle and transportation licensing, and we have the regulatory infrastructure in place. We continue to gather information to ensure our readiness.
7 Conclusions 24 of 112
Marilyn Diaz U. S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards Division of Fuel Management Marilyn.Diaz@nrc.gov 301-415-7110 25 of 112
P R E S E N T E D B Y Sandia National Laboratories is a multimission laboratory managed and operated by National Technology & Engineering Solutions of Sandia, LLC, a wholly owned subsidiary of Honeywell International Inc., for the U.S. Department of Energys National Nuclear Security Administration under contract DE-NA0003525.
SAND2021-0549 PE Incorporation of HYSPLIT Atmospheric Transport and Dispersion (ATD) Model into MACCS to Advance ATD Capabilities Dan Clayton Sandia National Laboratories Presented at the Advanced Reactor Stakeholder Meeting, January 21, 2021 26 of 112
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Background===
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Purpose for MACCS Created by Sandia to support NRC research and regulatory requirements
- Origins go back to the mid-1970s Typically used for prospective analyses, e.g.,
- Probabilistic risk assessments (NUREG-1150 and Level 3 PRA)
- Probabilistic consequence assessments (SOARCA)
- Cost/benefit analyses (commonly used for environmental analyses in licensing)
Very versatile with a large set of user inputs
- Intended to run rapidly for PRA applications
- Large set of weather trials (hundreds or thousands)
- Significant set of release categories (ten or twenty)
A release category is a group of similar source terms that can be represented by one or a few source terms.
Each source term can be complex, multi-isotope, and time-dependent.
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Challenges to Gaussian Plume Model Use of Gaussian model questioned
- Adequacy at locations that experience lake or sea breezes
- Suitability for river valleys that strongly influence local winds
- Adequacy for areas with significant surface relief
- Distance to which a Gaussian plume model is reliable Challenges motivated a detailed benchmark study (NUREG-6853, 2004)
- Four ATD models Lagrangian model (LODI)
Two Gaussian puff models (RASCAL and RATCHET)
Gaussian plume segment model (MACCS)
- Showed differences in the annual average exposure and deposition results were nearly within a factor of two out to 100 miles
- Did not address sea breezes, river valleys, or other terrain variations 4
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HYSPLIT Selection 30 of 112
Selection of Advanced ATD Model Essential features
- Treats Lagrangian particles
- Executable can be distributed to users (either by Sandia or directly from developer)
- Source code available in case modifications are required for integration
- Code meets QA requirements
- Treats 3D wind field (gridded data)
Desirable features
- Can model both puffs and particles
- Supports a variety of gridded weather data formats
- Facilitates graphical post processing 6
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Evaluation of Advanced ATD Model HYSPLIT FLEXPART LODI CALPUFF RASCAL SCIPUFF Includes Essential Feature Distributable Yes Yes No Yes Yes Yes Source Code Yes Yes No No Yes No QA Yes Yes Yes Yes Yes Yes Treats 3D Wind Yes Yes Yes Yes No Yes Meets All Requirements Yes Yes No No No No Score on Desirable Feature Puffs & Particles 5
3 Not scored Not scored Not scored Not scored Weather Formats 5
4 Not scored Not scored Not scored Not scored Graphics 5
1 Not scored Not scored Not scored Not scored Supports Linux &
PC 5
5 Not scored Not scored Not scored Not scored Total Score 20 13 Not scored Not scored Not scored Not scored 7
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Interface Requirements Multiple aerosol diameters (typically 10) plus inert gases Variable emission rates Multiple release elevations Transient air and ground concentrations (to work with evacuation model)
Option to choose particles or puffs One year of weather data to support weather sampling Mapping native concentration grid to MACCS grid 8
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Implementation 34 of 112
MACCS Modules ATMOS
- Source term definition
- Weather sampling algorithms
- Atmospheric transport, dispersion, and deposition Option for either HYSPLIT or Gaussian model EARLY (1 to 40 days)
- Doses as modified by emergency-phase countermeasures such as sheltering, evacuation, relocation, and KI ingestion
- Multiple population cohorts
- Acute and latent health effects from early acute exposure CHRONC (1 week to >50 years)
- Doses as modified by intermediate and recovery-phase protective actions such as relocation, interdiction, decontamination, and condemnation
- Latent health effects from chronic exposure to deposited materal
- Economic impact from early and late phase protective actions 10 35 of 112
Implementation Choices Unit releases without radioactive decay and ingrowth in HYSPLIT (MACCS treats these aspects) for each hour of a calendar year MACCS then scales and sums unit releases to account for variable emission rates Releases at several fixed elevations or buoyancy fluxes (MACCS determines which to use)
Multiple aerosol diameters with possibilities for dry deposition, wet deposition, both, or neither
- 2*N+2 possibilities for N aerosol diameters Air and ground concentrations tracked at time interval
- 60 min, 15 min, 5 min, 1 min 11 36 of 112
Overall Process 12 37 of 112
Generating HYSPLIT Files 13 38 of 112
Normalized Release Release one-Bq of a tracer species for each aerosol size over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and then track during transport
- Generating /Q and D/Q values for each period and aerosol size
- One year equates to 8,760 simulations
- Provides enough data to effectively model any source term over every hour for the entire year Expanded to account for buoyancy effects
- Requires additional sets (8,760 more runs per year) for each additional release level
- Specify sets of release heights or power levels
- Release heights utilize MACCS calculated rise heights
- Powel levels determine rise heights from HYSPLIT buoyancy calculations
- Appropriate file set determined based on weather conditions and plume segment sensible heat 14 39 of 112
GenHysplit Code Used to generate and organize the HYSPLIT output concentration files Configured to run on a Linux system to be able to access large computer resources at Sandia National Laboratories
- Has also been run in a Windows environment
- Preliminary testing on a cloud-based machine Designed to be flexible
- Many options controlled by input file 15 40 of 112
Converting HYSPLIT Output to MACCS Input 16 41 of 112
HyGridConvert Code MACCS utilizes a non-uniform polar grid Converts the HYSPLIT output concentrations to defined MACCS polar grid Configured to run on a Windows machine Can be run separately or called by WinMACCS (preferred).
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MACCS Meteorological Preprocessor 18 43 of 112
MacMetGen Description MACCS-formatted meteorological file needed for MACCS calculations
- Weather sampling
- Calculating plume rise height (if binned release heights used)
- Precipitation effects on evacuation speed Can be time consuming to collect site data and compile into file MacMetGen developed to automate MACCS formatted meteorological file generation Makes use of same meteorological files used to drive HYSPLIT
- Ensure consistency
- Can be any data set if in similar format 19 44 of 112
MacMetGen Information Flow 20 45 of 112
MACCS Use of HYSPLIT Data 21 46 of 112
Combination with Source Term Break each plume into one-hour segments and associate each one hour segment with a single HYSPLIT converted file (mcd file)
For each segment, multiply the normalized concentrations for each aerosol bin by the actual hourly release amounts for each different radionuclide/aerosol size Account for the radioactive decay and ingrowth at the time in the calculation Results in an air and a ground concentration array as a function of radionuclide, grid cell and time in MACCS These concentrations are then used by MACCS to determine consequences using the EARLY and CHRONC modules 22 47 of 112
Verification 48 of 112
Verification Test Cases Test cases were created to verify the implementation of the HYSPLIT/MACCS coupling Compared results from HYSPLIT/MACCS with HYSPLIT standalone Modified Inputs
- Single plume segment -> Multiple plume segments
- Single, fixed deposition velocity -> Ten aerosol sizes, each with own deposition velocity calculated from internal HYSPLIT model
- Constant weather -> Spatially and temporally varying weather
- Insignificant radioactive decay -> Significant radioactive decay
- No evacuation -> With evacuation 24 49 of 112
Compared Results Atmospheric Model Outputs
- Peak (around the compass) time-integrated air concentration (/Q, s/m3) over the region
- Peak (around the compass) ground concentration (D/Q, 1/m2) over the region
- Land areas (km2) that exceed various levels of contamination Consequence Output
- Peak (around the compass) ionizing radiation dose (Sv) over the region 25 50 of 112
Test Case 1 comparison of land areas that exceed 1,000 Ci/m2 Test Case 1 comparison of peak air concentration Test Result Summary All quantities for all six text cases match at all distances 26 51 of 112
Wrap-up 52 of 112
Summary MACCS coupled with HYSPLIT has been implemented and verified
- Supplements Gaussian plume segment model in MACCS with an alternative The ability to incorporate HYSPLIT model results in MACCS is a major improvement in the capabilities of MACCS simulations and provides a state-of-the-art alternative to the use of the Gaussian plume segment model Need to balance the need for higher fidelity models with associated higher computational costs 28 53 of 112
Status and Plans to Develop Regulatory Guide Endorsing the Advanced Non-LWR PRA Standard Michelle Gonzalez, RES Advanced Reactor Stakeholder Meeting January 21, 2021 1
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Agenda
- Update of Staff Endorsement of the ASME/ANS Advanced Non-LWR PRA Standard
- Development of Staff White Paper on PRA Acceptability for ANLWRs
- Schedule 2
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Update on Staff Endorsement
- JCNRM ballot of the ANLWR PRA Standard ASME/ANS RA-S-1.4-2021
- Initial ballot-May 2020
- Recirculation ballot-August, 2020
- Final issuance by ANSI anticipated February 2021 (tentative)
- Initially submitted May 2020. Public meetings held July, October and December 2020.
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Staff Activities
- Development of the staff position for an acceptable ANLWR PRA
- Identify and resolve technical and policy issues
- Early communication of staff views and perspectives - draft white paper
- Development of trial use regulatory guide
- Engagement with internal stakeholders (management, OGC, ACRS). Engagement with external stakeholders (public, potential applicants)
- Update the action plan for ANLWR PRA Standard Endorsement 4
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Development of Regulatory Guidance on PRA Acceptability for ANLWRs 5
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Considerations Consistency with current regulatory principles for LWR PRA acceptability Support LMP implementation (RG 1.233, NEI 18-04, Rev. 1)
Endorsements:
- ANLWR PRA standard, ASME/ANS RA-S-1.4-2021
- Peer review guidance, NEI 20-09
- Based on NEI 17-07, Rev. 2 which has been endorsed Approach for providing staff views:
- Draft white paper: provides staff views and perspectives, not formal staff positions
- Trial-use regulatory guide: provides formal staff position and endorsement Timing:
- Support near-term applicants
- Promote long-term regulatory stability 6
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Draft White Paper
- NRC Staff Draft White Paper: Demonstrating the Acceptability of Probabilistic Risk Assessment Results Used to Support Advanced Non-Light Water Reactor Plant Licensing
- Issued January 15, 2021 - ML21015A434
- Meeting planned for February 2021 to discuss in detail 7
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Schedule Milestone Activity 1/15/2021 Issue staff draft white paper 1/21/2021 Present staff draft white paper at Advanced Reactors Stakeholders meeting Late February 2021 JCNRM publishes ASME/ANS RA-S-1.4-2021 NRC begins review of latest available version of NEI 20-09 February/March 2021 Tentative public meeting on draft white paper and NEI 20-09 June 2021 RG technically complete; start RG publication process December 2021 RG issued for trial use TBD Revise trial-use RG to incorporate lessons learned and revision to ASME/ANS RA-S-1.4 (anticipated in 2023-2024) 8 61 of 112
Break Meeting will resume at 1pm EST Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 644 910 374#
Advanced Reactor Stakeholder Public Meeting 62 of 112
GAIN Overview Christine King, GAIN Director January 21, 2021 NRC Advanced Reactor Stakeholder Meeting
@GAINnuclear gain.inl.gov 63 of 112
Mission and Vision Vision (2030)
The U.S. nuclear industry is equipped to lead the world in deployment of innovative nuclear technologies to supply urgently needed abundant clean energy, both domestically and globally.
Mission Provide the nuclear energy industry with access to cutting-edge R&D, along with the technical, regulatory, and financial support necessary to move innovative nuclear energy technologies toward commercialization in an accelerated and cost-effective fashion.
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NRIC and GAIN are Complementary and Coordinated Efforts to Support the Nuclear Energy Industry
- Established in 2015 as a resource for accelerated development of nuclear innovations with lab partners
- Comprehensive resource to entire nuclear innovation ecosystem at all development stages
- Provides streamlined access to testing, MASL, experimental facilities, lab expertise, and legacy data
- Regulatory expertise (e.g. NRC advanced reactor licensing strategy support)
- Manages NE Vouchers Provides a capability for building and demonstrating reactor concepts
- Focused program to enable innovators nearing demonstration stage
- Provides access to sites, required upgrades, site services, fuel material/fabrication facilities, and demonstration process support
- Provides regulatory assistance related to demonstration
- Facilitates NRC observation/ learning 66 of 112
Goal #1. Provide nuclear industry entities access to financial support opportunities and national laboratory capabilities (facilities, expertise, and tools) to accelerate commercialization of innovations through research, development, demonstration, and deployment.
Goal #2. Work with industry to identify gaps, gather needs, and develop viable paths forward to inform DOE research programs and remove barriers for industry.
Goal #3. Work with industry stakeholders and NRC as means of communicating and resolving common (industry-wide) issues through regulatory interactions.
Goal #4. Facilitate the advanced nuclear industrys access to information to support their technology commercialization efforts.
Goal #5. Contribute tailored, factual information to key stakeholders to motivate the integration of clean nuclear energy for long-term success.
GAIN Goals for FY 2020-2025:
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How to do Business with GAIN Provides Contract Mechanisms on one side and Funding Opportunities on the other Information applies to all the DOE national labs in their contracting discussions with industry 68 of 112
GAIN NE Voucher Awards for Round 1, FY2021 The TerraPower voucher represents the first voucher to be awarded for work at LANL and involves characterization of the properties of plutonium chloride salt using neutron beam imaging in the LANSCE facility.
The two vouchers to be completed at ORNL involve utilization of modeling and simulation capability in support of innovations in additive manufacturing.
Date to Remember:
NE Vouchers Round 2 2021: Close on Feb 1, 2021 iFOA Round 1 2021: Close on Feb 28, 2021 69 of 112
GAIN FY2020 Voucher Awards 8
FY 2020 Voucher Recipient Proposal Lab Round 1 Hydromine, Inc.
On-Line Lead/Water Heat Exchanger Sensor/System Feasibility PNNL Round 1 Lightbridge Cor Advanced Test Reactor experiment design for measurement of Lightbridge Fuel'thermophysical properties INL Round 2 Neutroelectric Combined effects testing of high-temperature and neutron fluence to support qualification of NE-300, a high-temp Neutron shielding Material ORNL Round 2 Oklo, Inc.
Address gaps in legacy data on fuel steel interactions INL Round 3 SMR, LLC Coupled neutronic and thermal hydraulic analysis of a natural circulation based small modular reactor using VERA-CS ORNL Round 3 Ultra Safe Nuclear Corp Graphite finite element model verification ORNL Round 4 Kairos Power Pebble Bed Large Eddy Simulations for Lower Order Methods Benchmarking and Uncertainty Quantification Development ANL Round 4 Natura Resources, LLC RELAP5-3D Development and Assessment for Liquid-fuels Molten Salt Reactor Licensure INL Round 4 TerraPower, LLC Thermophysical Properties Measurements of NaCl-PuCl3 ANL 70 of 112
GAIN Voucher Impact - 2020 9
Voucher Summary 54 Awarded 27 Completed
$18.8 M to National Labs Total Project Costs $23.6 M 16Nov20 71 of 112
GAIN Assistance on Process Improvement NE Advance Class Patent Waiver DOE forgoes taking title to patentable inventions conceived using DOE funding Advance: Available when contract negotiations begin Class: large domestic businesses in DOE-NE related funding opportunities.(note: small business have this with Bayh-Doyle legislation)
This waiver will speed up negotiations for iFOA and ARD awards and reduce uncertainty in negotiations More info on gain.inl.gov 10 GAIN Access CRADA (in process)
Enable an industry partner to sign an agreement with a single lab that grants them simultaneous access to other labs in the complex.
Conceptually how this works:
- Industry partner with workscope that crosses multiple labs
- Identify the lead lab and negotiate CRADA
- Partner Labs review CRADA and sign on to agreement.
Allows us single agreements across DOE Offices of NE and Science 72 of 112
Legacy Documents / Industry Access Initial Fast Reactor (FR) Technology List provides access to 4250 openly published FR documents available from OSTI (December 2018)
Initial Molten Salt Reactor (MSR) Technology List provides access to 210 cataloged MSR documents available on OSTI (February 2017)
OSTI Spreadsheet of 12,000 Applied Technology (AT) Documents with abstracts provided to GAIN. List released with abstracts on February 28, 2019. Provided to TWG Chairs on March 8, 2019.
Clinch River Breeder Reactor (CRBR) Project documents. Contract initiated in Feb 2020. Scanning on hold (COVID-19). Iron Mountain will proceed as soon as possible (235 boxes + 75 reels of microfilm).
LOFT and other LWR Experiments. Fauske and Associates developed a pilot knowledge preservation activity in March 2019.
Phase II contract will proceed in FY2021.
New Production Reactor (NPR) documents at INL Storage (125 boxes-Idaho Falls). Working with Red Ink to scan and organize files for Export/Classification Reviews. Effort is underway.
Loft Experiment Data for code validation (Box of data -INL - to be scanned & reviewed.
PBF Documents (3 boxes at INL) will be scanned and reviewed.
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Databases of Experimental Information Database Lab Status (18Jan21)
TREXR TREAT Experiment Relational Database ANL https://www.trexr.anl.gov/
External access available by application NaSCoRD Sodium System & Component Reliability Database SNL https://www.sandia.gov/nascord/
Phase II Complete - FY20.
ETTD EBR-II Transient Testing Database ANL https://ettd.ne.anl.gov/
External access available by application FIPD EBR-II Metallic Fuel Irradiation Database ANL https://fipd.ne.anl.gov/
External access available by application. Data for U-Zr fuel type employed in commercial designs being qualified in accordance with NRC approved QAPP.
FFTF Passive Safety Testing & Metal Fuel Irradiation Database PNNL https://pnnl.gov/projects/fftf/
External Access Plan Complete; will be implemented FY21.
OPTD Out of Pile Transient Testing Database ANL https://optd.ne.anl.gov/
External access available by application EBR-II and FFTF Metal Fuel Experiment PIE Data INL/ANL Organized effort to supplement the FIPD and FFTF Databases. Complete in 2021.
MSRE Molten Salt Reactor Component Reliability Database ORNL/EPRI Available FY-2021-under export control review https://newton.ornl.gov/test/msre/app/
All databases will have links available at gain.inl.gov 74 of 112
Whats New? GAIN Workshops and Webinars - 2021 GAIN Webinar Series Focused on Multi-Industry Stakeholders January 27, 2021: Paving the Way - A Historic Journey to Deployment February 2021: Understanding and Navigating Within the Existing Regulatory Framework March 2021: Identifying and Managing Regulatory Risk on the Paths to Successful Deployment GAIN Net Zero Carbon Webinar Series February-March 2021: First Webinar in the Series Stay tuned for more information !!!
Workshops Focused on Advanced Nuclear Needs and Feedback April 13-15. 2021: GAIN-EPRI-NEI Safeguards Program Virtual Workshop May 12-13, 2021: GAIN-EPRI-NEI Microreactor Program Virtual Workshop August 24-26, 2021: GAIN-EPRI-NEI Advanced Methods for Manufacturing Qualification 75 of 112
GAIN Outreach Nuclear-focused Collaborators Nuclear Energy Institute Electric Power Research Institute Envoy Public Labs Third Way Clearpath Titans of Nuclear Generation Atomic American Nuclear Society Nuclear Innovation Alliance 76 of 112
Titans of Nuclear GAIN-NRIC Miniseries: Realizing the Nuclear Future https://www.titansofnuclear.com/
Connect with what excites you about nuclear today and imagine nuclear tomorrow.
Titans of Nuclear produces podcasts featuring interviews with experts across technology, industry, economics, policy and more.
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NE STRATEGIC VISION A thriving U.S. nuclear energy sector delivering clean energy and economic opportunities.
Advance nuclear energy science and technology to meet U.S. energy, environmental, and economic needs.
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STRATEGIC GOALS 79 of 112
Develop technologies that reduce operating costs.
Expand to markets beyond electricity.
Provide scientific basis for continued operation of existing plants.
By 2022, demonstrate a scalable hydrogen generation pilot plant.
By 2025, begin replacing existing fuel in U.S. commercial reactors with accident tolerant fuel.
By 2026, complete engineering and licensing activities needed to demonstrate successful deployment of a digital reactor safety system in an operating plant.
By 2030, achieve widespread implementation of accident tolerant fuel.
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Reduce risk and time needed to deploy advanced nuclear technology.
Develop reactors that expand market opportunities for nuclear energy.
Support a diversity of designs that improve resource utilization.
By 2024, demonstrate and test a fueled microreactor core fabricated by advanced manufacturing techniques.
By 2025, enable demonstration of a commercial U.S. microreactor.
By 2027, demonstrate operation of a nuclear-renewable hybrid energy system.
By 2028, demonstrate two U.S. advanced reactor designs through cost-shared partnerships with industry.
By 2029, enable operation of the first commercial U.S. small modular reactor.
By 2035, demonstrate at least two additional advanced reactor designs through partnerships with industry.
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Address gaps in the domestic nuclear fuel supply chain.
Address gaps in the domestic nuclear fuel cycle for advanced reactors.
Evaluate options to establish an integrated waste management system.
By 2021, begin procurement process for establishing a uranium reserve.
By 2022, demonstrate domestic HALEU enrichment.
By 2023, make available up to five metric tons of HALEU from non-defense DOE material.
By 2030, evaluate fuel cycles for advanced reactors.
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Gateway for Accelerated Innovation in Nuclear
- Accelerated must match advanced nuclear developer pace and reflect the market window (next 5-10 years).
- Innovation is not just about technology. Be creative in all spaces with a bias to taking risks.
- Focus on initiating and completing projects that support commercial deployment.
@GAINnuclear gain.inl.gov Questions? Reach out to gain@inl.gov (or one of our team members.)
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GAIN Organization 84 of 112
Tim Beville - Director, Advanced Reactor Demonstration Program Office of Nuclear Energy Overview of Advanced Reactor Demonstration Program January 21, 2021 85 of 112
energy.gov/ne 2
Advanced Reactor Demonstration Program (ARDP) Overview Advanced Reactor Demonstration Funding Opportunity Announcement (FOA) Overview Announced ARD FOA Awards Summary/Questions Topics to be Covered 86 of 112
energy.gov/ne 3
Dozens of U.S. companies are working on advanced nuclear projects for a wide array of capabilities to meet the energy needs of the future
- Light water-cooled advanced small modular reactors
- Advanced sodium-, gas-, lead-, molten salt-cooled reactors
- Significant levels of private sector investment Motivation for advanced reactor development
- Potential for improved safety and operational capability
- Various options for future commercial, limited-grid and remote applications
- Potential for improved nuclear resource utilization and reduced nuclear waste
- Flexible operation to support the national grid of the future containing many energy-source options Advanced Reactors: U.S. Landscape 87 of 112
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Established in fiscal year (FY) 2020 budget language ($230 million (M))
Focuses DOE and non-federal resources on actual construction of real demonstration reactors Establishes ambitious timeframe for demonstration reactors - five to seven years from award, including design, licensing, construction and start of operations Program also addresses technical risks for less mature designs Desired outcomes:
- Support diversity of advanced designs that offer significant improvements to current generation of operational reactors
- Enable a market environment for commercial products that are safe and affordable to both construct and operate in the near-and mid-term
- Stimulate commercial enterprises, including supply chains Overall FY21 budget for ARDP activities $250 M Advanced Reactor Demonstration Program 88 of 112
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Advanced Reactor Demonstrations (Demos)
- Cost-shared partnerships with industry (up to 50 percent (%) government, not less than 50% industry) to build two advanced demonstration reactors with significant improvements compared to current generation of operational reactors
- Demos to be constructed and operational in a 5-7 year window after award
- $160 M appropriated for fiscal year (FY) 2020 ($80 M per award)
- $160 M appropriated for FY 2021 ($80 M per award)
Risk Reduction (RR) for Future Demonstrations
- Cost-shared research and development (R&D) activities with industry (up to 80% government, not less than 20% industry) to address technical risks in advanced reactor designs to support potential future advanced reactor demonstrations
- $30 M appropriated for FY 2020 (up to 5 awards)
- $40 M appropriated for FY 2021 (To be distributed among awards based on agreed-upon cost requirements)
ARDP Program Elements 5
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National Reactor Innovation Center (NRIC)
Empower innovators with access to facilities, sites, materials, and expertise to enable demonstration of at least two advanced reactor technologies Support advanced reactor regulatory readiness for demonstrations Develop enduring demonstration support infrastructure Establish methods for efficient coordination among national laboratories ARDP Program Elements (cont.)
Recent Activities:
Establishing NRIC through planning and engagement with industry, NRC, national laboratories, and other key stakeholders Performed gap assessment for demonstration capabilities Developing a demonstration resource network, such as experimental facilities, test beds, and demonstration site identification and preparation
$20 M appropriated for FY 2020; $30 M for FY 2021 90 of 112
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Advanced Reactor Regulatory Development
- National laboratory-led R&D to resolve technical challenges with licensing advanced reactors
- Supporting efforts with NRC and industry stakeholders to develop cross-cutting advanced reactor licensing frameworks
- Licensing Modernization Project (LMP)
- Technology-Inclusive Content of Application Project (TICAP)
- Focused R&D to address technology-specific regulatory challenges for NE advanced reactor campaigns
- $15 M appropriated for FY 2020; $15 M for FY 2021 Advanced Reactor Safeguards
- Applies laboratory R&D to address near term challenges that advanced reactor vendors face in meeting domestic requirements for U.S. builds.
- Project focus areas - Materials Accountancy, Physical Protection, Gen-IV &
IAEA Interface
- $5 M appropriated for FY 2020; $5 M for FY 2021 ARDP Program Elements (cont.)
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energy.gov/ne 8
Advanced Reactor Demonstration FOA solicited applications under 3 funding pathways aligned with different technology maturity levels:
- Advanced Reactor Demonstration (Demos) awards
- Cost-shared demonstration of two reactor designs that have potential to be operational in five to seven years following award finalization
- Risk Reduction for Future Demonstration (Risk Reduction) awards
- Support for 2-5 additional, diverse advanced reactor designs that have potential to be operational in ten to twelve years following award finalization
- Advanced Reactor Concepts-20 (ARC-20) awards
- A new solicitation (to be known as ARC-20) for at least 2 new public-private partnerships focused on advancing reactor designs moving toward demonstration phase
- Not formally part of ARDP; funded under separate budget line. Included in ARD FOA to allow developers to select best pathway.
Advanced Reactor Demonstration FOA 92 of 112
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Two sets of reviewers: non-federal subject matter experts (SMEs) and federal merit review panel (MRP).
Congressional language that established the Advanced Reactor Demonstration Program directed the selection of projects be advised by subject matter experts:
- Electric utility that operates a nuclear power plant
- High-temperature process heat users (e.g., hydrogen production, industrial processing)
- Design, manufacturing and operation of nuclear reactors
- Finance industry with background in nuclear field Non-federal SMEs independently reviewed applications and provided individual feedback.
Federal MRP members individually reviewed applications and then developed consensus recommendations, taking SME input into account.
Coordinated with NRC on applicant proposed licensing strategies and schedules Advanced Reactor Demonstration and Risk Reduction Pathway Merit Review Competition and Source Selection Information - Not for Public Release 93 of 112
energy.gov/ne 10 TerraPower LLC - Natrium Reactor
- Sodiumcooled fast reactor that leverages of decades of development, including fuel
- High temperature reactor coupled with thermal energy storage for flexible electricity output
- New metal fuel fabrication facility
- Visit: https://natriumpower.com/
X-energy - Xe-100 reactor
- High temperature gas-cooled reactor that leverages decades of development and robust fuel form
- Provides flexible electricity output and process heat for a wide range of industrial heat applications
- Commercial scale TRISO fuel fabrication facility
- Visit: https://x-energy.com/
Demonstration Pathway Selected Technologies 94 of 112
energy.gov/ne 11 Risk Reduction Pathway Selected Technologies Prime Applicant Commercial Target Reactor Type and Fuel Risk Reduction Project Key Deliverables Kairos Power.
LLC KP-FHR - 140 Mwe thermal spectrum fluoride salt-cooled MSR, TRISO annular pebble fuel Design, construction and operation of Hermes reduced-scale test reactor (precursor to commercial-scale KP-FHR)
Westing-house eVinci - 4.5 MWe heat pipe-cooled microreactor, TRISO UCO compact HALEU fuel Technical risk reduction for moderator design, wick manufacturing, refueling and licensing.
BWXT BANR - 50 MWt transportable microreactor HTGR with UN TRISO Maturation of technology, including the development of UN TRISO fuel, to improve the commercial viability of BANR Holtec SMR-160 - 160 MWe LW-cooled natural circulation PWR Early stage design, engineering, and licensing activities for the SMR-160.
Southern Company Molten Chloride Fast Reactor -180 MWt pool-type MSR fast reactor with liquid salt fuel Design, construction and operation of Molten Chloride Reactor Experiment (MCRE)
Kairos KP-FHR WEC eVinci BWXT BANR Holtec SMR-160 TerraPower MCFR 95 of 112
energy.gov/ne 12 ARC-20 Pathway Selected Technologies Prime Applicant Commercial Target Reactor Type ARC-20 Project Key Deliverables Advanced Reactor Concepts ARC-100 100 MWe pool type sodium-cooled fast reactor Conceptual and preliminary design of a seismically isolated advanced sodium-cooled reactor facility General Atomics GA-EMS 50 MWe gas-cooled fast modular reactor Conceptual design of the GA-EMS 50 MWe FMR, increase TRL on systems and components, develop prelim. cost estimates MIT Modular Integrated Gas-cooled High Temperature Reactor (MIGHTR)
Conceptual design for MIGHTR and support for future commercialization as a safe and cost-competitive HTGR concept Advanced Reactor Concepts MIT General Atomics 96 of 112
energy.gov/ne 13 The Advanced Reactor Demonstration Program:
- Supports a diversity of U.S. advanced reactor designs for near-term or mid-term commercial demonstration
- Employs innovative technologies and fuel cycles to improve economic competitiveness, safety, and resiliency of nuclear energy systems
- Ensures nuclear energy continues to serve as a resource capable of meeting the Nation's energy, environmental and energy security goals
- Will require continued coordination with NRC to meet aggressive deployment schedules Summary 97 of 112
energy.gov/ne 14 Questions?
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NRC Review and Endorsement of ASME BPVC Section III, Division 5 -
Update Advanced Reactor Policy Branch Office of Nuclear Reactor Regulation Jordan Hoellman, Project Manager Jeff Poehler, Sr. Materials Engineer Component Integrity Branch Office of Nuclear Regulatory Research 99 of 112
Purpose
- Provide status of NRCs review and endorsement of 2017 ASME BPVC Section III, Division 5, High Temperature Materials
- Provide status of contractor reports supporting NRCs review 2
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=
Background===
- NRC Staff is developing two guidance documents related to review/endorsement of ASME Section III-Division 5 and associated code cases.
- NUREG - Technical Review of the 2017 Edition of ASME Section III, Division 5, High Temperature Reactors
- Document the staffs technical evaluation of the 2017 Edition of Section III, Division 5 and associated Code Cases for acceptability and endorsement.
- Regulatory Guide (RG) - Acceptability of ASME Section III, Division 5, High Temperature Reactors (DG-1380)
- Describes an approach that is acceptable to the NRC staff to meet regulatory requirements for components constructed in elevated temperature environments that are subject to time-dependent material properties and failure modes.
- Will contain any conditions arising from staffs review.
- The regulatory guide will update the guidance of RG 1.87.
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Overview
- Staff is finalizing the draft NUREG and draft regulatory guide.
- Conditions are likely in the areas of general requirements, mechanical design, metallic materials properties, and graphite design and materials.
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Status of Contractor Reports
- See NRCs Advanced Reactor Public Website: https://www.nrc.gov/reactors/new-reactors/advanced.html#endorev
- All reports are final and publicly available (except ANL)
- PNNL - (ML20269A145)
- ORNL - (ML20269A125)
- NUMARK/EMC2 -
o Metallic Appendices HBB-T, HBB-II, HCB-I, HCB-II, and HCB-III (ML20349A003) o Graphite Materials (ML20358A145) o Code Cases N-861 and N-862 (ML20349A002)
- ANL - ANL input is being finalized.
o Input provides historical context and perspective on materials properties.
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Contractor Assignments
- Elevated Temperature Metallic Components
- Design, Fabrication, Examination, Testing (HBB; HCB; HGB-3000, -4000, -5000, -6000),
- Rules for Strain, Deformation, and Fatigue Limits (Mandatory Appendix HGB-I)
- Rules for Construction of Core Support Structures Without Explicit Consideration of Creep and Stress-Rupture (Mandatory Appendix HGB-II)
- Rules for Buckling and Instability (Mandatory Appendix HGB-III)
- Rules for Time-Temperature Limits (Mandatory Appendix HGB-IV)
- Materials (HBB; HCB; & HGB-2000)
- Tables and Figures (Mandatory Appendix HBB-I)
- Guidelines for Restricted Material Specifications (Non-Mandatory Appendix HBB-U) 6 104 of 112
Contractor Assignments
- Elevated Temperature Metallic Components (continued)
- NUMARK/EMC2
- Rules for use of SA-533 Type B (Mandatory Appendix HBB-II)
- Rules for Strain, Deformation, and Fatigue Limits (Nonmandatory Appendix HBB-T)
- Rules for Stress Range Reduction Factors (Mandatory Appendix HCB-I)
- Rules for Allowable Stress Values for Class B Components (Mandatory Appendix HCB-II)
- Rules for Time-Temperature Limits (Mandatory Appendix HCB-III)
- Graphite
- NRC Staff (General Requirements)
- NUMARK/EMC2 (Technical Requirements)
- Code Cases N-861 and N-862
- NUMARK/EMC2 (All aspects) 7 105 of 112
General Requirements
- HAA & HAB (General Requirements) will contain several conditions to ensure consistency with the 2017 Edition of NCA, Division 1 and address oversights that were corrected in the 2019 Edition of Division 5 8
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Mechanical Design
- Staff has reviewed portions of PNNL and NUMARK reports related to the design of mechanical SSCs, as well as related Division 5 Articles.
- The staff is considering some conditions and recommendations on design, some of which are already included in 10CFR50.55a and in Section III Mandatory Appendix XII, and some from RG 1.87 Rev. 1 9
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Metallic Materials
- Independent analysis of materials allowable stresses and other materials properties by ORNL and NUMARK implied some Division 5 values are nonconservative.
- NRC staff is considering these findings in a holistic manner, including how these properties are used, inherent conservatism of the Division 5 design rules, and historical context.
- Some conditions on allowable stresses are likely for reasonable assurance of safe designs.
- Input from ANL provides historical context and perspective on materials properties.
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Graphite Materials and Design
- Numark Associates Inc. provided a technical assessment of Subsection HH, Class A Nonmetallic Core Support Structures, Subpart A, Graphite Materials.
- Staff has completed the review of the above report and all applicable sections of ASME Section III, Division 5 and obtained clarifications and feedback from NRC contractors (Numark and INL) in order to come up with the conclusions identified in the NUREG.
- The staff's deliberations and independent review of the code requirements will take into account the holistic design of graphite core support structures.
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INL Expert Assistance
- INL is providing on-call technical expertise related to NRCs endorsement of ASME BPVC Section III, Division 5.
- Providing the review team with the technical basis and historical perspective on ASME BPVC Section III, Division 5.
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Current Status - Next Steps
- The NRC has shared NRC contractor comments with the ASME Code committees
- At the current time, we have not found any issues that would be show stoppers
- Incorporate SSC classification guidance for high temperature reactors (similar to RG 1.26) into draft RG 13 111 of 112
Future Meeting Planning 2021 Tentative Schedule for Periodic Stakeholder Meetings January 26, 2021 (Part 53 - Options for Fusion)
February 2, 2021 (ACRS - Advanced Reactor Fuel Qualification)
February 4, 2021 (Part 53)
February 18, 2021 (ACRS - Part 53)
February 25, 2021 (Periodic (AM), TICAP/ARCAP (PM))
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