ML18114A318

M180424: Scheduling Note and Slides - Briefing on Advanced Reactors (Public Meeting)

ML18114A318
Person / Time
Issue date:	04/24/2018
From:	NRC/SECY
To:
References
M180424
Download: ML18114A318 (72)

Text

SCHEDULING NOTE

Title:

BRIEFING ON ADVANCED REACTORS (Public Meeting)

Purpose:

To provide the Commission with an update on the staffs activities to prepare for effective and efficient reviews of advanced reactor applications and to provide stakeholder perspectives on advanced reactor development activities, including projected policy and program issues that need to be resolved.

Scheduled: April 24, 2018 9:00 am Duration: Approx. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Location: Commissioners' Conference Room, 1st Fl. OWFN

Participants:

Presentation Panel1 36 mins.*

Dr. John Herczeg, Deputy Assistant Secretary, for Nuclear Technology 6 mins.*

Research and Development, Department of Energy (DOE)

Topic:

• DOE perspectives on advanced reactors, including DOE's vision/strategy for deployment Dr. Rita Baranwal, Idaho National Laboratory, Director of the Gateway 6 mins.*

for Accelerated Innovation in Nuclear Topic:

• Advanced nuclear technologies developmental efforts Dr. Farshid Shahrokhi , Framatome Inc., Chair of the NEI High 6 mins.*

Temperature Gas-Cooled Reactor Technology Working Group Topic:

• Activities of the NEI High Temperature Gas-Cooled Reactor Technology Working Group Dr. Jacob DeWitte, Okla Inc., Chair*of the NEI Fast Reactor 6 mins.*

Working Group Topics:

• Activities of the NEI Fast Reactor Working Group Nick Irvin, Southern Company Services, NEI Molten Salt Reactor 6 mins.*

Technology Working Group Topic:

• Activities of the NEI Molten Salt Reactor Technology Working Group

Dr. Edwin Lyman, Union of Concerned Scientists 6 mins.*

Topic:

• Perspectives on advanced reactor regulatory and policy issues Commission Q & A 30 mins.

Break 5mins.

Panel2 40 mins.*

Victor McCree, Executive Director for Operations Fred Brown, Acting Director, Office of New Reactors (NRO)

Topic:

• Overview of staff accomplishments and challenges to prepare for efficient and effective review of advanced reactor applications John Monninger, Director, Division of Safety Systems, Risk Assessment, and Advanced Reactors, NRO Topic:

An update on ongoing and planned activities to ensure readiness to efficiently and effectively review advanced reactor applications Stephen Bajorek, Senior Level Advisor for Thermal Hydraulic Code Development and Analysis, Division of Systems Analysis, Office of Nuclear Regulatory Research Topic:

• Identification, assessment, and enhancement of analytical computer codes, tools, and industry codes and standards for confirming advanced reactor safety Brian Smith, Deputy Director, Division of Fuel Cycle Safety, Safeguards And Environmental Review, Office of Nuclear Material Safety and Safeguards Topic:

• Fuel cycle considerations for advanced reactor applications, including fuel development Commission Q & A 30 mins.

Discussion - Wrap-Up 5mins.

• For presentation only and does not include time for Commission Q & As 2

, .

. ' .

Presidential and Departmental Nuclear Energy Priorities 2

DOE-NE MISSION AND PRIORITIES DOE-NE MISSION MISSION PRIORITIES

• Advance nuclear power as a resource capable of making major contributions in meeting our Nation's energy supply, environmental and energy security needs

• Seek to resolve technical, cost, safety security, and regulatory issues through RD&D Advanced Reactor Pipeline

• By focusing on the development of advanced nuclear technologies, support the goals of providing domestic sources of secure energy, reducing greenhouse gases, and enhancing national security.

RD&D INFRASTRUCTURE 3

' .._ .

DOE-NE ADVANCED REACTORS PIPELINE REACTOR TYPES 12 X 50 MWe Inside a NuScale Small Modular Reactor Building Light-Water Based SMRs e.g. NuScale High-Temperature Reactors

• Prismatic & pebble bed designs

• Helium Cooled

• Molten Salt Cooled Emphasis: TRISO fuel and Graphite qualification Liquid Fueled Reactor (Molten Salt)

• Fast-, thermal- and hybrid-spectrum designs

---u.c Xe-100 Pebble-Bed Reactor (200 MWth)

Metal-cooled Fast Spectrum Reactors 1-Micro Reactors Pressure vessel 1

Graphite reflector I Pebble bed s

f £

.

C

(!)

.~

E 4

AREVA- HTGR

. . .

ADVANCED REACTOR TECHNOLOGIES FOCUS AREAS

• Advanced Light Water Reactors

• Fast Reactor Technologies

• Demonstrate feasibility of advanced systems and component technologies

• Methods and code validation to support design and licensing

• Advanced alloy materials qualification for metal-cooled systems Terra Power

• Gas Reactor Technologies MCFR

• Advanced alloy and graphite materials qualification for high temperature gas-cooled systems

• Scaled integral experiments to support design and licensing

• TR ISO-coated particle fuel development and qualification

• Molten Salt Reactor Technologies

• Investigate fundamental salt properties GA Gas-cooled

• Materials, models, fuels and technologies for salt-cooled and salt-fueled Fast Reactor reactors

• Cross-Cutting technologies

• Advanced energy conversion

• Supercritical Carbon Dioxide (sC02) Brayton Cycle

• Micro reactors for remote defense and commercial applications NuScale PWR GE Hitachi PRISM 5

VERSATILE TEST REACTOR (VTR)

IN SUPPORT OF ADVANCED REACTOR TECHNOLOGIES NEAC Advice:

• The need for a VTR was established through a series of independent surveys of the potential U.S. user community (industry, DOE programs) and support from international partners resulting in a NEAC report ("Assessment of Missions and Requirements for a new U.S. Test Reactor" 2/2017): it states that "The Ad Hoc NEAC subcommittee recommends that DOE-NE proceed immediately with pre-conceptual planning activities to support a new test reactor (including cost and schedule estimates)."

Goals:

• 3 year R&D effort, along with appropriate reviews and planning, leading to an operational VTR by 2026

• VTR would support accelerated development of advanced fuels and materials for U.S.

advanced reactor vendors, as well as to provide the capability for testing those fuels and materials to support licensing by the Nuclear Regulatory Commission.

• VTR with a high fast neutron flux would revitalize our research infrastructure and remove a critical impediment for U.S. developers of advanced nuclear energy technologies.

• Constructed and operated under DOE authority, in close collaborations with NRC.

• $35 million in 2017 Omnibus Bill for versatile fast test reactor's R&D activities to achieve CD-0 in January 2019. 6

SUMMARY

• The demand for domestically-generated, reliable, and clean sources of base-load electricity will continue to drive many countries toward nuclear energy as part of their "energy security" and national economic and environmental calculus.

• Profound opportunity for new nuclear growth:

• Strong global market interest

• Growing need for increased global access to electricity

• Support energy security, economic and environmental goals

• U.S. leadership to ensure safety & nonproliferation are as important as ever

• The Administration is committed to advancing nuclear energy in the United States and abroad.

"Nuclear energy is a critical component of America's energy future, and entrepreneurs are developing promising new technologies that could truly spur a renaissance in the United States and around the world."

7

• DRAFT REQUIREMENTS/ASSUMPIIONS OF VERSATILE TEST REACTOR (VTR)

1. Approach to Design: Conducting a 3 year research & development effort on core design.

VTR draft core map

2. Reach fast flux of approximately 4.E15 n/ cm 2 -s, with prototypica I spectrum

3. Load factor: as large as possible (maximize dpa/year to > 30 dpa/year)

4. Provide flexibility for novel experimental techniques

.

5. Be capable of running loops representative of typical fast reactors (Candidate Coolants: Na, Lead, LBE, Gas, Molten Salt)

- May be a single location with replaceable loops.

6. Effective testing height < 1 m

7. Ability to perform large number of experiments simultaneously

8. Metallic driver fuel (possible options: LEU, Pu, LEU+Pu) 9

AIN nnovalton rn Nuclear What is GAIN?

TRISO Fuel Particle IJt] @GAINnuclear gain.inl.gov

~AIN GAIN Initiative: Simultaneous Achievement of Three Strategic Goals STRATEGIC GOALS Suppliers Utilities Lead Enable Optimize Global Global Domestic Technology Industrial Energy Commercialization Leadership Portfolio IJCJ @GAINnuclear gain .inl.gov

GAIN: Connecting nuclear innovators to DOE laboratory capabilities and RD&D programs Base Reactor Modeling & Crosscutting NRC Interface and Fuel Cycle Experimentation Simulation Design Support R&D Programs HPC Infrastructure Nuclear Licensing Advanced Nuclear Fuels Hybrid Energy Framework Fuel Cycles Verification and Instrumentation Validation Nuclear Gradual Advanced and Sensors Cyber Security Risk Reduction Reactors M&S Expertise Materials Science Digital l&C Licensing LW-based Reactor physics Test Reactors Human Factors Support Expertise Reactors Modeling and Simulation Expertise Unique Facilities Knowledge Management & Integration

-GAIN-Industry and investor access to DOE capabilities and expertise IJCl @GAINnuclear gain.inl.gov

~AIN Development & Regulatory Framework Su'pj,Oif"-

Radiol og i cal Release ensor s & Contra.ls SuirveUlanoo & T oct"llnl cal Baa.as f"or Inst . and D i agnost i c.s Ana l ytical Tools Struct:ural Control A natysis Human Fa.c itors Coolant lrradia1ion & Dovol op R .c qu i rcd Property Testi ng Boundary Methods & Data A na ytlcal M alberia s Code* & S - n d a rda Valida.t o Codo9 & Codes &

A nal y sis Dcvotop<<nont Model* Methods Oomonatrati on ,o *f C<>do-3 for Physics Fue* Perlor mance- a nd Thermal Fllui d""

Fuel Co r e H ,eat Qua l ification F l - l o n Produc t Hoat Romoval Re*moval Transport System Testing

-'

Probabilistic R isk Asscs-9mont A c c ident:

S equences &

Init i ators

GAIN NE Voucher Recipient Title AMS Corp.

Radiation Aging of Nuclear Power Plant Components ORNL Knoxville, TN Methodology for Meeting Containment System Columbia Basin Consulting Group LLC Principal Design Criteria for Heavy Metal Fast Reactor PNNL Kennewick, WA Systems DVNAC Systems LLC Dynamic Natural Convection System INL Del Mar, CA Synthesis of Molten Chloride Salt Fast Reactor Fuel INL/ ANL Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-uman ac ors ngineenng for the Move to Digital INL Control Systems- Improved Strategies for Operations NEAMS [Nuclear Energy Advanced Modeling and Kairos Power LLC Simulation] Thermal -Fluids Test Stand for Fluoride- ANL/ INL Oakland, CA Salt-Cooled, High-Temperature Reactor Development MicroNuclear LLC Development of the Microscale Nuclear Battery INL Franklin, TN Reactor System Conversion of Light Water Reactor Spent Nuclear fuel ORNL Evaluation of Powe r Fluidic Pumping Technology for ORNL Molten Salt Reactor Applications SNL/ANL for a Compact Fast Reactor SMR lnventec LLC Small Modular Reactor-160 Primary Flow Stability ORNL Camden, NJ IMSR [Integral Molten Salt Reactor] Fuel Salt Property Confirmation: Thermal conductivity and ANL Fuel Salt Characterization ANL

~AIN Innovator Access to DOE Facilities and Expertise

• Accident-Tolerant Fuels (ATF)

• New ATF cladding conceived, developed, manufactured and tested at ORNL has been manufactured by Global Nuclear Fuels (GNF) into lead test assemblies, and shipped to Southern Nuclear Operating Company for trials in Edwin I Hatch plant.

• FeCrAI cladding (Ironclad) will be the first developed through US Department of Energy's (DOE) Enhanced Accident-tolerant Fuel program to be installed in a commercial nuclear reactor

• Molten Salt Reactor (MSR) development

• Training on MSR technology and MSRE experience has been provided to NRC via series of training courses

• Continue to support the ARC-15 FOA with TerraPower on MSR technology development, including material development, corrosion expertise, salt properties, modeling & simulation, safeguards

• Legacy reports from MSRE and MSBR have been released for developer community

• Database development

• Legacy fast reactor information, including EBR-11 reactor physics and fuel performance data, and TREAT data on fuel transient testing and post-test examination. GAIN supported completion and activation of TREAT database (TREXR) for benefit of industry users.

GAIN Interface with NRC The linked memorandum of understanding (MOU) between the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (DOE) describes the roles, responsibilities, and the processes related to the implementation of the DOE Gateway for Accelerated Innovation in Nuclear (GAIN) initiative. GAIN is an initiative that is intended to provide the nuclear energy community with increased access to the technical, regulatory, and financial support necessary to mover new or advanced nuclear reactor designs toward commercialization while ensuring the continued safe. reliable. and economic ooeration of the existino nuclear j

Future Activities 2018 IJC'J @GAINnuclear gain.inl.gov

Gateway for Accelerated Innovation in Nuclear firJ @GAINnuclear gain.inl.gov

HTGR Simple Safe Secure HTGR Technology Working Group HTGR TWG Members BWXT Framatome (previous AREVA)

Kairos Power StarCore Nuclear X-Energy DOE, Duke Energy, EPRI and NEI Farshid Shahrokhi (Chairman HTG R-TWG)

HTGR HTGR-TWG Simple SJfe Secure Developers

• Reactor Developers Framatome

• SC-HTGR - prismatic core modular high temperature gas-cooled reactor Star Core Nuclear

• StarCore - small core modular high temperature gas-cooled reactor X-Energy

• Xe-100 - pebble bed core modular high temperature gas cooled reactor Kairos Power

• KP-FHR - molten salt core high temperature reactor

• Fuel Manufacturers BWXT

• UCO based TRISO coated particle fuel X-Energy

• UCO based TRISO coated particle fuel framatome X nergy BWX rechnologies, In c .

April, 24, 2018 N STARC@RE lJ f I f r.. n te} Kairos Po w e r Page 2

-~

HTGR HTGR-TWG Sim~ SJr, Securt Activities

• Regulatory Guide 1.232 "Guidance for Developing Principal Design Criteria for Non-Light Water Reactors"

• Radionuclides retention - Functional Containment

• Limited Scope Topical Report (LSTR) for TRISO coated particle fuel -

- Complete the report

- Submit to the NRC

- Begin NRC review/comment

• ASME Section Ill, Div. 5

- Advocacy for NRC review and endorsement

- Technical support of the NRC review and comments resolution

• Engage in efforts to reduce licensing uncertainties for advanced reactors Advocacy for NRC endorsement of Licensing Moderniz~tion Project proposal and approach Support for development of technology-inclusive license application content guide for advanced non-LWRs April, 24, 2018 Page 3

FRWG Fast Reador Working Group Fast Reader Waking Qtq,Activities 2018 NU:atnissia1erMeeting April 24, 2018

@ Multiple developers working a, multiple technologies

@ Sprs variety of fast reactor technologies in developmert Elysunlndustries General Amics CE Hycmnine Oklo TenaPouuer Exelon Southem S1udsvik~

Highlighted Efforts

@ FLB5 @ LegLydala

> Vaielyoffuelsooirg > Fl.Bad cxnµ:rat cxn:tJaoo ~

> \/Vawga, infrasbucture ram @ Versatile test reactor

> D3la @ Strdads-

@ IVkrlrg ad simulatbn 111, DJ. 5

> Existirg ad reN tools @ R31.232

.

~-

Good Morning - My name is Farshid Shahrokhi. I am the director of HTGR technology at Framatome.

Today I represent the High Temperature Gas-cooled Reactor Technology Working Group. We are an independent industry group formed within the NEI Advanced Reactor Working Group. Our membership includes high temperature reactor developers, coated particle fuel manufacturers, and a utility. We also have representatives from EPRI, DOE and NEI. Our mission is to express and support our members' common technical and R&D needs.

• We have engaged and interacted with the DOE research co*m munities, the universities, the standards development communities, and the NRC.

Our reactor designs use Helium as the coolant or molten salt in the case of Kairos PoVli'er, graphite moderator, and Uranium Oxy-Carbide (UCO) kernel Tri-isotropic (TRISO) coated particles as our basic fuel form. Our designs produce high temperature steam ("'560 °C) for either high efficiency electricity production or industrial process steam. Our reactors are

• modular and small - ranging in power from 10 to 275 MWe.

NEXT SLIDE

. First, I would like to thank the NRC staff for working with us and the other advanced reactor communities in an effort to modernize and risk inform our regulatory infrastructure. Your work is important to us because we need guidance that applies to our reactor designs as opposed to the current guidance that has evolved over the past SO years through licensing mainly light water reactors.

Risk-Informed and Performance-Based guidance for non-light water reactor licensing basis development will provide a systematic process for 1

demonstrating satisfaction of existing regulations that we could use independent of any specific reactor technology. The work that the NRC is doing with support from the Licensing Modernization Project is a major step forward in the long term goal of technology inclusive regulatory structure.

For near term we support and applaud the DOE and the NRC efforts for developing and publishing earlier this month the Regulatory Guide 1.232 "Guidance for Developing Principal Design Criteria for Non-Light Water Reactors". This guide provides acceptable ways for developing Principal Design Criteria for a range of advanced reactor, designs including our modular HTGRs.

Next - within our developer communit\l::-the -interfm results from the DOE TRISO particle fuel qualification and characterization program (DOE AGR Program) show that reactors that use a combination of TRISO fuel, graphite core, and a single-phase chemically inert coolant could have an extraordinarily low radiologica~ source term . This.enables enhanced operational capacity and accident tolerance whi.c h-is the foundation for an alternative radionuclides retention strategy and perform<:!nce criteria definition.

The so called "Functional Containment" is an independent set of systems, structures and components working together to retain fission products and limit the site dose at the boundary to less than 1 REM (EPA PAG limit -

which is a design goal for us) for all anticipated, design bases, and beyond design bases accident scenarios without relying on a pressure retaining reactor building.

2

We have worked with the NEI and the NRC staff in establishing a radionuclides retention strategy using the concept of "Functional Containment" for non-light water reactors. A draft Commission paper titled "Functional Containment Performance Criteria" is working its way through the NRC regulatory review and approval chain. Acceptance of functional containment for radionuclides retention is essential to our reactor concepts development and commercialization.

Meanwhile - Our TWG is collaborating with the DOE, Idaho National Lab, and the Electric Power Research-Institute in preparation of a Limited Scope Topical Report (LSTR) to be submitted to the NRC early next year for "off-fee" review and approval. This report will be a generic Topical Report documenting the completed TRISO fuel test.ing results at Idaho National

. .. . '.

Lab. Once reviewed and app.roved, ~ach developer that wishes to use UCO based TRISO fuel can reference this topical in its design specific fuel qualification report.

The HTGR TWG also recognizesthat further advanced reactor regulatory framework development, with .a goal of reduction of regulatory uncertainty, wilJ continue to require close collaboration, coordination, and interaction with the industry. This is evident by our past and on-going engagement with the consensus standards communities such as ANS and ASME. We have proposed and encourage the NRC review and endorsement of one of our key standards - the ASME Section Ill, Div. 5 "High Temperature Reactors".

We will continue our engagement with the NRC staff to further develop cross-cutting improvements such as a) safety-focused regulatory reviews, b) emergency planning, c) staffing, and d) security requirements for 3

J -

advanced reactors to further reduce regulatory uncertainties and encourage early deployments of advanced reactors .

Thank you

....... ' ....-.

"

.... .

( .

r.

• I

• "1* '

• t * ** * *

• .1 4

FRWG Fast Reador Working Group Fast Reactor Waking GnpActivities 2018 ~ M e e t i n g April 24, 2018

~

• ~!W!

@ Multiple developers waking on multiple technologies

@ 5IBls variety of fast reactor technologies in development

~ 8ysiunlndustries General Atancs CE Hycmnine Oklo TerraPOJVer

[Ue Exelon Southern I LIDI Studsvik~

2

Highlighted Efforts

@ Fl.BS @ l..BJLYdata

> Variety of fuels ooirg > FLeadanµra,t

~ dat:mses

> Wakrga, infrastructure rarls @ Versa1iletest reactor

> D3la @ Siardads-

@ rvtrl:frg ad simularon 111, Dv. 5

> Exislirg ad reN tools @ R31.232 3

Molten Salt Reactor Technology Working Group (MSR TWG)

Nick Irvin Director - Advanced Energy Systems, Southern Company Services 4.24.18

ONE TWO THREE FOUR Terra Thorcon Terrestrial Flibe Molten Salt Power Thermal Energy Energy Reactor Fast Breeder Burner Liquid Fuel Thermal Burner Thermal Breeder TWG ~ Liquid Fuel SaltCooled SaltCooled Thorium Liquid Fuel SaltCooled Liquid Fuel SaltCooled Uranium Uranium Thorium (Could use Th) (Could use Th)

FIVE SIX SEVEN EIGHT Transatomic Elysium Alpha Tech Muons Power Industries Research Corp Inc.

Hybrid Fast Thermal Thermal Burner Breeder Breeder Burner Liquid Fuel Liquid Fuel Liquid Fuel Liquid Fuel SaltCooled SaltCooled SaltCooled SaltCooled Uranium Uranium Thorium Uranium

-

~ Exelon,, tffe1 EF'l21

C.

• UCS Perspectives on Advanced Reactor Regulatory and Policy Issues April 24, 2018 Dr. Edwin Lyman Senior Scientist Union of Concerned Scientists

Advanced reactors

• All non-light water reactor (LWR) reactor concepts have both advantages and disadvantages compared to LWRs

• All non-LWRs have novel features whose behavior will require significant testing and analysis to quantify margins and uncertainties for licensing purposes

• At this stage of development, there is no technical basis to support the assertion that non-LWRs will be inherently safer or more secure than LWRs

• In fact, there is reason to believe that characteristics of non-LWRs could render them less safe and secure overall than LWRs, requiring compensatory measures 2

Advanced reactor licensing

• The NRC's regulatory processes are being unfairly maligned as significant obstacles to advanced reactor deployment

• In fact, the main barriers are the huge investments in cost and time required for non-LWR vendors to develop their concepts to the level of maturity needed to support high-quality applications

• Weakening NRC licensing standards to expedite advanced reactor licensing is unnecessary and potentially dangerous

• Congress should ensure that the NRC has licensing authority over any advanced reactor built in the U.S., even when the Atomic Energy Act does not require it 3

Expectation versus reality

• "The new designs typically have lower probabilities of severe accidents because of their smaller size or innovative safety features, which would also likely lower impacts to public health and safety from any radiological emergency." - NRC, Final Regulatory Basis, Rulemaking for Emergency Preparedness for Small Modular Reactors and Other New Technologies," Sept. 2017

• For non-LWRs of any size, this is an unverified and likely false assertion

• The Advanced Reactor Policy Statement "expects," but does not require, that advanced reactors "will provide enhanced margins of safety and/or use simplified, inherent, passive, or other innovative means to accomplish their safety and security functions."

- This non-mandatory expectation must be extensively validated before it can be used as a basis for regulatory decisions 4

A self-defeating prophecy

• Even for designs that can be shown to have additional inherent safety, overall safety will depend on NRC policy decisions on

- siting

- functional containment and other changes to the General Design Criteria

- emergency preparedness

- security

- use of probabilistic risk assessment (PRA)

- testing requirements/acceptance of advanced modeling and simulations

- special treatment requirements

• Excessive reductions in safety margin and defense-in-depth could undermine, rather than enhance, safety

• Rather than reduce margin, the NRC should treat any first-of-a-kind (FOAK) demonstration reactor as a "prototype" and require additional safety features to compensate for uncertainties 5

Non-LWR safety and security vulnerabilities

• Gas-cooled reactors can be seriously damaged by air or water ingress

• Liquid sodium-cooled fast reactors have reactivity instabilities and flammable coolant

• Molten-salt reactors must be kept within a narrow temperature range to prevent freezing of the coolant or rapid destruction of the reactor (within ten minutes)

• Must consider implications for the entire fuel cycle

- Any reactor with co-located reprocessing facilities will raise many novel safety and security issues 6

"Risk-informing" advanced reactor licensing

• PRAs for non-LWR designs are largely academic exercises and lack data for validation

- Uncertainties in defining design-basis accident spectrum

- Uncertainties in evaluating severe accident progression and consequences

• Thus the risk information from such models has little utility for FOAK reactor licensing

• Over time, use of PRA may be increased as operating reactor information becomes available 7

Non-LWR security rulemaking

• The Nuclear Energy Institute (NEI) has proposed that the NRC weaken its security requirements for advanced reactors that meet certain conditions:

- No need to protect against the design basis threat (DST)

- No need for security performance evaluations

• The NRC's position is that the current regulatory framework for security is already flexible enough to accommodate different design features that may impact security

• However, the staff is scheduled to submit a paper to the Commission later this year that may include a rulemaking option

• In our view, this would be an unnecessary effort

- there is no conceivable circumstance under which the fundamental requirements for protection against radiological sabotage could be safely waived for advanced reactors 8

Excessive secrecy

• It appears that vendors are withholding far more basic information about their designs during pre-application reviews than in the past

- Toshiba 4S fast reactor: detailed design and safety basis information were presented in several public meetings (e.g. ML072950026)

• There is virtually no comparable information about the Okla or Terrestrial Energy design or safety basis on ADAMS

• It is unclear why the standard for proprietary information protection would be different today

- UCS may need to test the standard by challenging the NRC's proprietary information determinations

• Much more information will have to be eventually released if vendors pursue design certifications or construction/operating licenses

- Why shouldn't early engagement with the public be as important to the vendors as early engagement with the regulator?

9

4 '

Acronyms

• DBT: Design Basis Threat

• EP: Emergency Preparedness

• FOAK: First of a Kind

• NEI: Nuclear Energy Institute

• PRA: Probabilistic Risk Assessment

• UCS: Union of Concerned Scientists 10

U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment NRC's Advanced Reactors Program "Enabling the Safe and Secure Use of Nuclear Materials

• Commission Meeting

• April 24, 2018

Agenda

• N RC' s Advanced Reactors Program -

. Fred Brown

• Licensing Readiness and Potential Policy Issues - John Monninger

• Analytical Codes, Tools, and Industrial Standards - Stephen Bajorek

• Fuel Cycle Considerations - Brian Smith

-

U.S.NRC United States N ucl ear Regu latory C om mission Protecting People and the Environment NRC's Advanced Reactors Program Fred Brown, Acting Director Office of New Reactors

Dynamic and Evolving Landscape LMFR HTGR MSR

,,,,..----------- ......

'-----------------------------~

]~ a

/

( GE-H Framatome ] Kairos  :

( ARC ]: : X-ener ~- - - - - - - - - - - -

1 ~~~~~~~5 1 Oklo 1.

1(

StarCore

]

, - ,

I II ~[ !!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!~] II I  ;

11--------

, - - - - - - - - - - -

.'[

TerraPower

\ ' - - _SDdilJDL - - - - - ;

___ ..COoJ.ed - - - - - - ,

Westinghouse n I

• - ____ u<<SDE~L - - -'

I---------=

1 1

~ [~ ~ ~T Terrestria 1 Transatomic

! !h

! !o

!!!r!c!!!

o!!

- -........

n~~~~

• • [. Columbia Basin .1*.  : [_ _ _ _ _ Fl_ib_e_ _ __

( Hydromine J: Thermal Neutron Spectrum I I I I

I I

l

' - - - J..Ji.aJJ - - - - - - - / Terra Power Cooled [ General Atomics I Fast Neutron Spectrum lI Elysium J;

\ I RIS Responses , ____LLq!:!.icJJ:.u~_I ___ ;

Assuring Readiness

• Developed the Vision and Strategy

• Executing the Implementation Action Plans

• Building capabilities

- Incremental progress

- Identifying key policy issues

- Focused "Core" team concept

Potential Early Applications

.

• Individual developer's timelines

• Recognizing relative maturity

• Further transformation

- Leveraging advancements from recent light water reactors licensing

- Optimizing the regulatory structure

U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment Licensing Readiness and Potential Policy Issues John Monninger, Director Division of Safety Systems, Risk Assessment, and Advanced Reactors Office of New Reactors

Making Progress in the Near-Term Advanced Reactor Strategies

- ---- I -

i i i i i i lt!Jl!m!1 &ic*taalt 2 §kll!sllf ~ §lratea3t4 Strataav ~ ltmtaavl Knowledge, Computer Flexible Review Industry Codes Technology- Communication Skills and Codes Processes and Standards Inclusive Policy Capacity Issues I .

1aenuncat1orv -,,ung near ORNL Molten Assessment Regulatory ASMEBPVC densely Salt Reactor Training of available Roadmap

...

Sect. Ill Div. 5 populated NRCDOE Workshops I toalA Ar1U1111

- -

AN~

Knowledge Prototype Standards Insurance and Periodic Management Guidance 20.1, 20.2, Uablllty Stakeholder 30.2. 54.1 Meetings Non-LWR Consequence

... Competency Design Non-LWR ... Based NRCDOE Modeling Criteria PRA Standard Security GAi MOU

.

1 i--1ng Modernization ... EPforSMRs International Project andONTs ... Coordination

• • .,..

.,._In L8E 81111:tlan F*

,_ .

• SSC.._

• PRAApplOICh Qaullcalfon Containment Performance Criteria EnYlrunmental

Modernizing the Licensing Approach

• Flexible, staged, and predictable processes

• Advanced Reactors Design Criteria

• Developing a risk-informed, and performance-based approach

- Identification of licensing-basis events

- Probabilistic risk assessment approach

- Classification of structures, systems, and components

- Defense-in-depth

Pursuing Resolution of Policy Issues

• Emergency preparedness for small modular reactors and other nuclear tech_n ologies

• Consequence based physical security

• Functional containment performance criteria

Evaluating Other Potential Issues

• Engaging with stakeholders to identify and prioritize potential policy

• issues

- Siting

- Insurance

• Technology-specific policy issues

U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment Analytical Codes, Tools, and Industrial Standards Stephen M. Bajorek, Ph.D.

Senior Level Advisor for Thermal Hydraulics Division of Systems Analysis Office of Nuclear Regulatory Research

Progress in Technical Readiness

• Familiarization with advanced reactor technologies and technical issues

• Access and training with DOE analysis codes and evaluation of existing NRC code capabilities

• Identification of technical "gaps"

- Code capabilities and limitations

- Experimental data and code verification and validation

- Industrial standards for materials

Methodical Approach to Selection of Codes

• Does a code contain the correct physics and modeling features?

• Is it more economical to develop an NRC code, or adopt use of a code developed elsewhere?

• If a non-NRC code is used, how does the NRC maintain its independence?

• Can a code be developed for application to more than one reactor design type?

• What applicable verification and validation exists for a particular code?

~omprehensive ,Reactor Analysis fundle (CRAB)

SCALE Cross-sections I

Nek5000 CFO PARCS

• AGREE Neutronics Core T/H TRACE t +

I I

I I

BISON MELCOR Fuel Performance Containment I FP I

L---------- FAST SAM Fuel Performance System and Core T/H NRCCode DOE Code

Resolving Technical Challenges

• Numerous advanced reactor designs

• Some (vital) data is non-existent

- Molten salt thermophysical properties

- High temperature material behavior

• DOE and NRC codes have been developed for different purposes

- DOE: Normal operation, very high detail

- NRC: Accident scenarios, peak power regions

• DOE codes designed for high performance computing systems

Leveraging Industrial Standards

• N RC Objectives

- Obtain performance needs and identify issues for structural materials and component integrity

- Support consensus standards

• Staff participation on Industrial Standards activities

- ASME Section Ill, Division 5 - High Temperature Materials

- ANS Committees and Working Groups

- ASME/ ANS Joint Committee on Nuclear Risk Management

Path Forward

• Efforts in 2018 will be primarily generic and focus on identification of gaps in knowledge, data, and code modeling requirements

• DOE codes will continue to be tested and cooperative efforts expanded

• Support for Industrial Standards activities will continue with emphasis on high temperature materials

U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment Fuel Cycle Considerations Brian Smith, Deputy Director Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Material Safety and Safeguards

Engagement on Fuel Cycle Considerations

• Participant in meetings with developers, industry, and DOE

• Participant in advanced reactors training

• Reviewed draft NEI white paper on challenges for front end fuel cycle

Evaluation of Fuel Cycle Regulatory Framework

• Existing framework has sufficient flexibility for solid-fueled reactors using once through fuel cycle

- May require new regulatory guidance for new design characteristics

• Potential for regulatory challenges for fluid-fueled reactors or reactors with closed fuel cycles

Engaging on Issues that Need to be Addressed by Industry

• Obtaining uranium enriched greater than 5% and subsequent fuel fabrication

• New transportation packages

• Criticality benchmark experiments

Proactively Identifying Regulatory Issues

• Material control and accounting requirements for Category II facilities

• Physical security requirements for Category II facilities

• Material control and accounting requirements for fluid-fueled reactors

Continue Active Participation

• Maintain involvement in advanced reactors activities

• Encourage industry development of fuel cycle technology and designs in parallel with reactors design

• Encourage industry development and implementation of regulatory engagement plan

Acronyms

• ANS - American Nuclear Society

• ASME - American Society of Mechanical Engineers

• BPVC - Boiler and pressure vessel code

• DOE - Department of Energy

• EP - Emergency preparedness

• GAIN - Gateway for Accelerated Innovation in Nuclear

• HTGR - High temperature gas reactor

• LBE - Licensing basis events

• LMFR - Liquid metal fast reactor

• MOU - Memorandum of Understanding

• MSR - Molten salt reactor

• NEI - Nuclear Energy Institute

• Non-LWR - Non light-water-reactor

• ONT - Other nuclear technologies

• ORNL - Oak Ridge National Laboratory

• PRA - Probabilistic Risk Assessment

• RIS - NRC Regulatory Information Summary

• SMR - Small modular reactor

• SSC - Structures, systems, and components