Revision as of 19:12, 8 July 2018

Text

M151215: Scheduling Note and Slides - Hearing on Construction Permit for Shine Medical Isotope Production Facility: Section 189A of the Atomic Energy Act Proceeding
	ML15350A289
Person / Time
Site:	SHINE Medical Technologies
Issue date:	12/16/2015
From:	; NRC/SECY
To:	;
References
	M151215
	Download: ML15350A289 (58)
	v • d • e

SCHEDULING NOTE Title: HEARING ON CONSTRUCTION PERMIT FOR SHINE MEDICAL ISOTOPE PRODUCTION FACILITY:

SECTION 189A OF THE ATOMIC ENERGY ACT PROCEEDING (Public Meeting)Scheduled:

Purpose: Duration: Location: December 15, 2015 9:00 am To receive testimony and exhibits regarding the application of SHINE Medical Technologies, Inc. for a medical radioisotope irradiation and processing facility construction permit. The testimony will focus on unique features of the facility or novel issues that arose as part of the review process and other significant technical or policy issues associated with aspects of the staff's review that are important for the Commission to make its final decision.

The Commission will determine whether the staff's review has been adequate to support the findings in 10 C.F.R. §§ 50.35(a)and 51 .105(a).1 day Commissioners' Conference Room, 1st Floor OWEN NOTE: Chairman to provide opening remarks, admit exhibits, and swear in witnesses.

20 mins.Participants:

Presentation (Note: Presenters seated at the table are listed, other staff available to answer questions will be seated in the well and reser'ved rows.)Overview (SHINE Medical Technologies.

Inc.)At the table: Greg Piefer, Chief Executive Officer, SHINE Jim Costedio, Manager, Licensing, SHINE Bill Hennessy, Manager, Engineering, SHINE Eric Van Abel, Supervisor, Engineering, SHINE Toi:Overview Commission 0 & A (round of questions; 6 minutes each)30 mins.*24 mins.**1 30 mins.*At the table: William Dean, Director, Office of Nuclear Reactor Regulation (NRR)Mirela Gavrilas, Deputy Director, Division of Policy and Rulemaking, NRR Jane Marshall, Deputy Director, Division of License Renewal, NRR Marissa Bailey, Director, Division of Fuel Cycle Safety, Safeguards and Environmental Review, Office of Nuclear Material Safety and Safeguards (NMSS)Toi:Overview of SHINE construction permit application and contents, summary of key safety and environmental information associated with the SHINE construction permit application, and summary of regulatory findings.

The staff will also discuss its review methodology and how it applied the Commission's regulations.

Commission 0 & A (round of questions; 6 minutes each) 24 mins.**BREAK 5 mins.NOTE: For the remaininq panels, the applicant is expected to discuss the contents of the construction permit application while the staff is expected to discuss its review process and requlatory conclusions.

Each panel should include a discussion of any permit conditions associated with the subject matter of the panel.Safety- Panel 1 (11:15 am)Applicant 5 mins.*At the table: Bill Hennessy, Manager, Engineering, SHINE Eric Van Abel, Supervisor, Engineering, SHINE Catherine Kolb, Supervisor, Engineering, SHINE Staff 10 mins.*At the table: Alexander Adams, Jr., Chief, Research and Test Reactors Licensing Branch, NRR Steven Lynch, Project Manager, Research and Test Reactors Licensing Branch, NRR Mary Adams, Senior Environmental Engineer, Enrichment and Conversion Branch, Office of Nuclear Materials Safety and Safeguards (NMSS)Toi:Sections of the application and the following chapters from the Safety Evaluation Report: Chapter 1, "The Facility," and Chapter 4, "Irradiation Unit and Radioisotope Production Facility Description," including discussion of the unique licensing considerations for SHINE's subcritical utilization facilities and production facility.2 Note that the panel will not have specific topics to discuss for the following chapters.

If the Commission wishes to ask questions on these chapters, this panel would be the appropriate time.o Chapter 2, "Site Characteristics" o Chapter 3, "Design of Structures, Systems, and Components" o Chapter 5, "Cooling Systems" o Chapter 6, "Engineered Safety Features," including proposed permit conditions o Chapter 7, "Instrumentation and Control Systems" Commission 0 & A (round of questions; 6 minutes each) 24 mains.**BREAK (Lunch Break-A pprox. 12:00-1:30 pmo)Safety -Panel 2 (1:30 pm)Applicant 5 mins.*At the table: Bill Hennessy, Manager, Engineering, SHINE Eric Van Abel, Supervisor, Engineering, SHINE Catherine Koib, Supervisor, Engineering, SHINE Staff 10 mains.*At the table: Steven Lynch, Project Manager, Research and Test Reactors Licensing Branch, NRR Joseph Staudenmeier, Senior Reactor Systems Engineer, Reactor Systems Code Development Branch, Office of Nuclear Regulatory Research Kevin Morrissey, Project Manager, Fuel Manufacturing Branch, NMSS I~~iSections of the application and the following chapters from the Safety Evaluation Report: Chapter 13, "Accident Analyses," including discussion of novel application of 10 CFR Part 50 and 70 accident analysis methodologies for radiological and chemical exposure accidents.

Note that the panel will not have specific topics to discuss for the following chapters.

If the Commission wishes to ask questions on these chapters, this panel would be the appropriate time.o Chapter 8, "Electrical Power Systems" o Chapter 9, "Auxiliary Systems" o Chapter 11, "Radiation Protection Program and Waste Management," including proposed permit condition o Chapter 12, "Conduct of Operations"~***

o Chapter 14, "Technical Specifications" o Chapter 15, "Financial Qualification" 3 Commission 0 & A (round of questions; 6 minutes each) 2 is*24 mins.**Environmental

-Panel (2:10 pm)Applicant At the table: Katrina Pitas, Vice President, Business Development, SHINE Bill Hennessy, Manager, Engineering, SHINE Catherine Kolb, Supervisor, Engineering, SHINE Tim Krause, Environmental Specialist, Sargent and Lundy 10 mins.*Staff 25 mins.*At the table: Jane Marshall, Deputy Director, Division of License Renewal, NRR David Wrona, Chief, Environmental Review and Guidance Update Branch, NRR Michelle Moser, Project Manager and Biologist, NRR Topic: Final Environmental Impact Statement* Provide a summary of the process for developing the Final Environmental Impact Statement (EIS) including:

o The decision to prepare an EIS o The scoping process o Consultations with other Federal, State, and local agencies and Tribes/DOE as a cooperating agency o The staff's independent review and analysis o Issuance of the Draft EIS, public meetings on the Draft EIS, and solicitation of stakeholder comments on the Draft EIS o The environmental impacts from the proposed action on the following resource areas: land use, visual resources, air quality and noise, water resources, ecological resources, historic and cultural resources, socioeconomics, human health, transportation, waste management, and environmental justice* Discuss the analysis of alternatives including:

o Range of reasonable alternatives o Alternative sites o Alternative technology o No-action alternative

Summarize conclusions and recommendation including a summary of the benefits and costs of the proposed action Commission 0 & A (round of questions; 6 minutes each)24 mins.**BREA K 5 mins.4 Closing (3:15) 5 is 54 mins.Closing Statement by Applicant 15 rmins.*Greg Piefer, Chief Executive Officer Closing Statement by Staff 15 rains.*William Dean, Director, NRR Commission Q & A and Closing Statements 24 rmins.***For presentation only and does not include time for Commission 0 & A's.**AII Commissioners will have an opportunity to ask questions after each panel.Commissioners will start the Q&A with their total time allotted to allocate as they see fit among the panels.**Chapter 12, "Conduct of Operations," of the staff's SER includes evaluations of SHINE's quality assurance program description and preliminary emergency plan.5 HEARING ON CONSTRUCTION PERMIT FOR SHINE MEDICAL ISOTOPE PRODUCTION FACILITY:

SECTION 189A OF THE ATOMIC ENERGY ACT PROCEEDING (Public Meeting)December 15, 2015 Slides/Handouts Overview-SHINE Medical Technologies, Inc.-NRC Staff Safety -Panel 1-SHINE Medical Technologies, Inc.-NRC Staff Safety -Panel 2-SHINE Medical Technologies, Inc.-NRC Staff Environmental

-Panel-SHINE Medical Technologies, Inc.-NRC Staff N RC-010 United Nuclear Regulatory C~, mmtnslon Protecting People andt¢ the Environnwnt Construction Permit Application Review SHINE Medical Technologies Panelists* William Dean* Mirela Gavrilas* Jane Marshall* Marissa Bailey-Director, NRR-Deputy Director, NRR/DPR-Deputy Director, NRR/DLR-Director, NMSS/FCSE Introduction to Molybdenum-99

Molybdenum-99 (9 9 M0) Mc 0.90 decays to -Effective diagnosis o-Minimal exposureV* 50,000 procedures daily Tc009* No domestically-produced supply ooo.o Establishing a Domestic Supply* National policy objectives support domestic production capabilities

Cost-sharing agreements encourage commercial partners* SHINE proposes to produce 9 9 M0 through uranium fission Preparing for SHINE Review* Interoffice working group contributed diverse expertise* Public meetings engaged stakeholders

Review coordinated with Federal, State, and local governments Allowing Construction

SHINE application only seeks construction authorization

Design details may be left for operating license application

Review assessed preliminary design and analysis Conducting the Safety Review cn~~itW Tailoring Review Methodology

Review accommodated unique technology

Staff used existing guidance* Staff determined whether reasonable assurance that final design will conform to design bases Additional Information

Review supported by additional information

In some cases, permit conditions necessary* Regulatory commitments track items for resolution in final safety analysis report (FSAR)Environmental Regulations

National Environmental Policy Act-Informs Federal decision making-Public disclosure

NRC's environmental regulations

-Title 10 of the Code of Federal Regulations (10 CFR) Part 51 Environmental Review Process* Opportunity for Public Involvement Proposed Janesville Site..... Agricultural fields....

Previously disturbed..... No surface water* features I No threatened or endangeredspce

o historical or cultural resources Regulatory Basis* Commission authorized by Atomic Energy Act, Section 103* Review primarily based on 10 CFR Parts 20, 50, and 51* Review also considered 10 CFR Part 70 performance requirements Construction Permit Issuance* Preliminary design described* Further technical or design information may be left for FSAR* Ongoing research and development has been identified

Facility can be constructed and operated without undue risk Permit Considerations

Construction will not endanger public health and safety* SHINE technically and financially qualified* Environmental requirements satisfied Introducing Review Panels Safety Panel 1 Safety Panel 2 Environmental Panel Licensing Considerations Accident Analysis* Final Environmental Impact Statement Process* Analysis of Alternatives

Summary of Conclusions and Recommendations Safe...Evaluation.Repor Chapters 1 and 4 Safety Evaluation Re port Chapter 13 Final Environmental Impact Statement Acronyms* FCSE -Division of Fuel Cycle Safety, Safeguards, and Environmental Review* DLR -Division of License Renewal* DPR -Division of Policy and Rulemaking Acronyms* NMSS- Office of Nuclear Material Safety and Safeguards

NRR -Office of Nuclear Reactor Regulation Exhibit SHN-026 Medical Technologies Commission Mandatory Hearing SHINE Construction Permit Application Overview December 15, 2015 SHINE Medical Technologies, Inc. Mission* SHINE is dedicated to being the world leader in safe, clean, affordable production of medical tracers and cancer treatment elements a Highest priority is safely delivering a highly reliable, high-quality supply of the medical ingredients required by nearly 100,000 patients globally each day, while maintaining a minimal environmental impact a Will fill gap in supply chain caused by exiting foreign reactors, and ensure continuity of essential treatments for U.S. patients for decades to come Medical Isotopes* Molybdenum-99 (Mo-99), the most widely-used medical isotope, decays into technetium-99m, which is used in more than 40 million doses annually* Stress tests and bone scans most common of dozens of uses MedicalProchyedursUig"T7 M72rn M~&7 A44~ 7717r ~ A7p17 7*? 1717 A7,7~, ~1717<nn{*fll t1717 krr. 7*7* *4747 77 7 W ?77x7777 7ft.1777, Nr~ 777477*774 771~ '777 7,777* 1777 4, J Supply Situation with No New Capacity*Canada will stop operating the NRU reactor in March 2018* Following Canadian exit, there will be no North American producer Highl relvantNEA Demand Growth (+35% ORC) vs, ig hl relvantcurrent processing capacity, 2015-202 because Mo-99 °decays ~1% per hour z0=Domestic supply o is necessary to j o ensure US patient '°health 717077 77477 470777 4 4 7-J* 471-077 4*4* 471077 4*177 417077 4777.477 77-077 7*477 77077 2014 2011 2014 2017 2011 2019 2020-.-NEAD.77772g177*

'40% WC, CU7071 ~71*$772 C8277777 U 4 SHINE Medical Technologies, Inc. Core Values=SHINE mission driven by our core values-Ensure health and safety of the public and our workforce* Minimize environmental impacts of medical isotope production

Ensure minimal or no disruption to patient supply chain* Ensure cost effectiveness and therefore patient access* Eliminate need for highly enriched uranium (HEU) reactors or targets in medical isotope supply chain* SHINE believes each of these points are essential to fulfill our mission Technological Approach Reflects Core Values* Small systems: Hundreds of times less power than isotope production reactors being used SLow source term--helps ensure safety of public and workforce ,Decay heat per system < 1 kW within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months oMinimizes waste nuclide generation compared to reactors* Low enriched uranium (LEU) reusable target* Reduces waste and cost Product compatible with current supply chain* Eliminates need for HEU* Driven by low-energy electrostatic accelerator

System must be driven to operate, no criticality

Hundreds of times less waste than reactors* Electrostatic technology simple, demonstrated and cost effective SHINE Medical Technologies, Inc., The SHINE facility is located on a previously undeveloped 91 acre parcel in the southern boundaries of the City of Janesville in Rock County, Wisconsin 7 SHINE Facility Layout* The SHINE facility consists of an irradiation facility (IF)and a radioisotope production facility (RPF)ldiation acility idioisotope roduction Facility 8 SHINE Irradiation Facility='The SHINEF IF consists of eight subcritical irradiation units (IUs), which are comparable in thermal power level and safety considerations to existing non-power reactors licensed under 10 CFR Part 50=However, due to subcriticality, the IUs did not meet the existing definition of utilization facility in 10 CFR 50.2' To align the licensing process with potential hazards, the NRC issued a direct final rule modifying 10 CFR 50.2 definition of utilization facility to include SHINE lUs* An IU consists of a subcritical assembly, a neutron driver, and supporting systems SHINE Radioisotope Production Facility ,The RPF is the portion of the SHINE facility used for preparing target solution; extracting, purifying, and packaging Mo-99; and the recycling and cleaning of target solution* Based on batch size (i.e., greater than 100 grams), the RPF meets the definition of a production facility as defined in 10 CFR 50.2 ,1° SHINE Construction Permit Application SSHINE submitted the CP Application in two parts, pursuant to an exemption to 10 CFR 2.101 (a)(5)SPart I of the Application submitted March 26, 2013*PSAR Chapter 2 (Site Characteristics)

=PSAR Chapter 19 (Environmental Review),General and Financial Information SPart 2 of the Application submitted May 31, 2013 SRemaining PSAR Chapters SA discussion of the preliminary plans for coping with emergencies, in accordance with 10 CFR 50.34(a)(10), provided September 25, 2013=The SHINE facility will be licensed under 10 CFR Part 50,"Domestic Licensing of Production and Utilization Facilities" Regulatory Guidance and Acceptance Criteria* NUREG-1 537, "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors"* Interim Staff Guidance augmenting NUREG-1 537* Incorporates relevant guidance from NUREG-1 520, "Standard Review Plan for the Review of a License Application for a Fuel cycle Facility" , Additional guidance (e.g., Regulatory Guides, ANSI Standards) used 12 SHINE Facility Layout* Production, processing, and packaging operations located within one controlled, confined area 13 SHINE Process Overview SSupercell Recycle Loop Product Recycle tank TSV and Irradiation Unit Cell A~Hold Periodic Cleanup Loop associated cleanup* processes 4....-w Target Solution 14 paato SHINE Irradiation Facility* An IU consists of a subcritical assembly, a neutron driver, and supporting systems* Major supporting systems include:* Light water pool system (LWPS)* Target solution vessel (TSV) off-gas system (TOGS).Primary closed loop cooling system (PCLS)* Tritium purification system (TPS)* Primary system at near-atmospheric pressure* Target solution is drained to dump tank via gravity* Dump tank is criticality-safe by geometry and passively-cooled

Redundant, fail-open dump valves* TSV is an annular vessel to be constructed of Zircaloy-4

Natural convection within TSV SHINE's Fusion- FIssion Coupling V N'4 14 11 Neutron Oriver Neutron Multiplier Target Solution Vessel N'4> N Radioisotopes in solution 15 Subcritical Assembly Subcritical Assembly Support Structure (SASS)TSV Dump Tank -,.TSV and Neutron S Multiplier (Internal to SASS)TSV Dump and Overflow Lines~(2 each)16 Neutron Driver and Tritium Purification System* One Neutron Driver per IU cell* Electrostatic accelerator with a gas target* D-T fusion reaction generates 14 MeV neutrons that drive the fission process* Tritium purification system* Isotopically separates gases, and supplies clean tritium to neutron drivers* Tritium lines and processing equipment in gloveboxes and q double-walled pipe 1 TSV Off-Gas and Primary Cooling Systems*TSV off-gas system (TOGS)* Contains the fission product1 TOGS gases i*of-aRemoves iodine from the* Recombines hydrogen and oxygen to maintain hydrogen gas below the lower flammability limit (LFL)* Subcritical assembly submersed in light water pool °-,* Provides shielding and heat s-,..,8AS8) removal ......18 Subcritical Assembly Irradiation Process* Uranium concentration of solution and any other necessary parameters are measured* Operators use a 1/M startup methodology to monitor the reactivity increase in the TSV* TSV is filled in discrete increments

Final fill level is approximately 5% by volume below critical* Automatic safety systems will be designed to protect the primary system boundary (PSB) and ensure the TSV remains subcritical

High flux trips* Primary cooling system temperature trips Subcritical Assembly Irradiation Process' When irradiating the TSV:* Further solution addition is prevented* Tritium is supplied to the target, and neutron driver output is gradually increased* Reactivity decreases significantly in the assembly due to the strong negative feedback* Normal irradiation mode operations are approximately 5.5 days-'Following shutdown, light water pool provides decay heat removal* On a loss of off-site power, pool passively removes heat* Temperature rise of 12°F (7°(c) after 90 days without cooling Radioisotope Production Facility*Extracting, purifying and packaging Mo-99 in supercells-Laboratory scale purification process*Noble Gas Removal System (NGRS) stores TSV off-gas*Held for 40 days of decay prior to sampling for release* Released through the Process I Vessel Vent System (PWS)*Monitored and filtered discharge to ensure regulatory limits are met*Recycling and cleaning target solution* Uranium extraction (U REX)process separates uranium for ......................

reuse Pu~Packagoe Engineered Safety Features (ESFs)* SHINE protects public health and safety during postulated accidents via a confinement system ,Radionuclide inventory in any one confinement area is approximately 10,000 times less than a power reactor-Low dispersion forces in processes byConfinement functions provided ,,,F, RPF;Biological shielding (IU cells, hot cells, trenches, tank vaults)Isolation valves on piping systems* Ventilation systems* Instrument and control systems: Engineered Safety Features Actuation System (ESFAS)Radiological Integrated control System (RIcS)Zo,,e 2 Zen. 3 Ventilation Zones in Production Facility 22 Summary , Preliminary design described in the PSAR shows the SHINE facility can be constructed such that it meets the applicable regulatory requirements

Robust engineered and administrative controls have been identified to ensure protection of the public, the environment, and our workers , The plant is being designed with safety as the primary criterion 23 NRC-01l' U.S.NRC United Stats Nuileair Regulatory Comnisslio Protecting People and the Emwironment Construction Permit Application Review SHINE Medical Technologies Safety Panel I December 1 5o 201 5 Panelists* Alexander Adams, Jr.-Chief, Research and Test Reactors Licensing Branch, NRR* Steven Lynch-Project Manager, NRR* Mary Adams-Project Manager, NMSS Licensing Considerations

SHINE seeks to construct commercial non-power utilization and production facilities

Licensing process similar to that of research and test reactors* Developed technology-specific guidance for application review Advisory Committee on Reactor Safeguards (ACRS) Review* Staff presented at subcommittee and full committee meetings* ACRS recommended issuance of construction permit* Staff adequately addressed questions regarding aircraft impact and facility layup Irradiation Unit Licensing* Irradiation units represent first subcritical utilization facilities

Staff considered licensing under 10 CFR Part 70* Given similarities to non-power reactors, ultimately reviewed under 10 CFR Part 50 Irradiation Unit Design Features* Thermal power level similar to non-power reactors* Safety considerations include:-Fission heat removal-Decay heat generation

-Fission gas release-Accident scenarios Production Facility Licensing* Production facility will process irradiated materials containing special nuclear material* Similar to processes at existing fuel cycle facilities

Staff used NUREG-1537 and Interim Staff Guidance Proposed Permit Conditions

Criticality accident alarm system* Criticality events "not credible"* Criticality safety analyses* Reactivity contributions from fissile isotopes* Radiation shielding and occupancy times Acronyms*NMSS- Office of Nuclear Material Safety and Safeguards

NRR -Office of Nuclear Reactor Regulation Exhibit SIIN-027 qSHINE'T Medical Technologies Commission Mandatory Hearing SHINE Construction Permit Application Safety -Panel 1 Facility December 15, 2015 SHINE Process Overview Recycle Loopq IB12i~A Recycle tank Product TSV and Irradiation Unit Cell Hl e Periodic Cleanup Loop* associated cleanup* processes.4. *Target Solution~Preparation Design of Structures, Systems, and Cornponents a Certain structures, systems, and components (SSCs)are designated safety-related because they are relied upon to perform safety functions during normal operation or design basis events a SSCs must be able to perform their design basis functions during normal operation and under required accident conditions a SSCs that are determined to have safety significance are designed, fabricated, and tested commensurate with the criteria set forth in ANSI/ANS-1 5.8 ("Quality Assurance Program Requirements for Research Reactors")

Safety-Related SSC Definition a Safety-related SSCs are those SSCs that are relied upon to remain functional during normal conditions and during and following design basis events to assure: 1. The integrity of the primary system boundary;2. The capability to shutdown the target solution vessel (TSV) and maintain the target solution in a safe shutdown (SSD) condition;

3. The capability to prevent or mitigate the consequences of accidents which could result in potential exposures comparable to the applicable guideline exposures set forth in 10 CFR 20;4. That all nuclear processes are subcritical, including use of an approved margin of subcriticality;

5. That acute chemical exposures to an individual from licensed material or hazardous chemicals produced from licensed material could not lead to irreversible or other serious, long-lasting health effects to a worker or cause mild transient health effects to any individual located outside the owner controlled area; or 6. That an intake of 30 mg or greater of uranium in soluble form by any individual located outside the owner controlled area does not occur Seismic Design and Quality Levels* Plant SSCs are designed to withstand the effects of the design basis earthquake (DBE) if they perform a safety-related function or if necessary to ensure they do not degrade the function and performance of a safety-related SSC* SHINE Quality Levels (QLs): SQL-I: Safety-related SSCs are designated as QL-1 in the Quality Assurance Program Description (QAPD), and the full measure of the QAPD is applied to these SSCs-QL-2: Selected SSCs that support or protect the safety function of safety-related equipment are designated QL-2, and quality elements are applied commensurate with the importance to safety*QL-3: Nonsafety SSCs that do not support or protect the safety function of safety-related SSCs are designated QL-3 Design of Structures, Systems, and Components

Single failure criterion is applied to safety systems-Sufficient redundancy and independence that a single failure of an active component does not result in loss of capability to perform its safety function-A single failure, in conjunction with initiating event, does not result in the loss of the system's ability to perform its safety function* SHINE system designs based on defense-in-depth practices, with preference for engineered and passive controls over administrative controls 6 NRC-012-R SU.S.NRC United States Nuclear Regulatory Comni~ssion Protecting PrcopLt and the Enzmnment Construction Permit Application Review SHINE Medical Technologies Safety Panel 2 Decermber 1 5 201 5 Panelists* Steven Lynch-Project Manager, NRR* Joseph Staudenmeier

-Senior Reactor Systems Engineer, RES* Kevin Morrissey-Project Manager, NMSS Review Methodology

Two methodologies applied to SHINE accident analyses-Maximum hypothetical accident-Integrated safety analysis* Radiological and chemical hazards evaluated against 10 CFR Parts 20 and 70, respectively Irradiation Facility Accident Analysis* Irradiation facility characteristics:

-Operates at low power, pressure, and temperature

-Large heat sink for passive decay heat removal-Radiological sources Event Identification

Delineation of possible accident categories

Identification of limiting accident for the category* Strategy to mitigate accident and limit consequences

Analysis of dose consequences Safety Concept* Detection of high radiation levels* Confinement of radiation source* Evacuate workers* Filter releases to environment

Emergency planning zone could be the operational boundary Limiting Accident* Release of irradiated target solution from one TSV* Consequences bounded by RPF maximum hypothetical accident* Meets 10 CFR Part 20 limits-5 rem for workers-100 mrem for public Production Facility Accident Analysis* Radiological and chemical accident analysis performed* Defines facility hazards and controls that support establishment of design basis Production Facility Accident Analysis* Multiple event types:-Radiological accidents-Chemical accidents-Criticality accidents-Fires-External events Exhibit SHN-028 Medical Technologies Commission Mandatory Hearing SHINE Construction Permit Application Safety -Panel 2 Accident Analysis December 15, 2015 Accident Initiating Events and Scenarios*Bases for identification of accidents:.Hazard and Operability Study (HAZOPS)SPreliminary Hazard Analysis (PHA)*List of events from NUREG-1 537 and the Interim Staff Guidance (ISG)augmenting NUREG-1537 ,Experience of the hazards analysis team*Current preliminary design information SQualitative evaluations within categories ,Quantitative evaluations to determine consequences

Postulated an irradiation facility (IF) and radioisotope production facility (RPF) Maximum Hypothetical Accident (MHA)°Establishes an outer limit consequence, bounds other accidents SMost limiting MHA was in the RPF ("Facility MHA")

IF Postulated Maximum Hypothetical Accident Target solution vessel (TSV) and subcritical assembly support structure (SASS) integrity lost, target solution spills into irradiation unit (IU) cell ,Maximum inventories assumed in TSV SPool presence ignored SHigh radiation detected, initiates alarms and confinement

°High efficiency particulate air (HEPA) filters and charcoal adsorbers credited SDose consequences-Worker TEDE: 3.1 rem ..-Public (site boundary)

TEDE: TSV Q ........0 0017 rem RPF Maximum Hypothetical Accident (Facility MHA)°The five noble gas storage tanks rupture simultaneously

° With the maximum inventory*Contents are instantly released SHigh radiation levels initiate alarm and cell isolation , Redundant isolation dampers close' 10% of the activity bypasses the isolation dampers' 10% of the activity leaks* through penetrations TSV Oft G.~P~.rge NORS Nobk G.~Stosg. Ts,,k~Conden~ot~

Knock Oft Pro~es, Ves~eI Thnk v~,,t Syften, R~dIo.ctWn LIqnId Wnte RPF Maximum Hypothetical Accident (Facility MHA)=Dose consequences

Worker TEDE: rem*Public (site boundary)

TEDE: 0.082 rem oThe MHA consequences are conservative ,Simultaneous, instantaneous rupture* Entirety of noble gas is transferred and released SThe five tanks are filled to capacity°Additional ventilation isolation dampers would close, but are not credited-Actual doses would be lower Doses to the Public From Analyzed Accidents Radiological consequences to workers and the public are within the limits of 10 CFR 20.1101, 20.1201, and 20.1301 I EuU _______5 NRC-01 3<U.S.NRC United Stjres Nuclear Re~ul~tory Comtml$slon Protecting People and the Environment Construction Permit Application Review SHINE Medical Technologies Panelists* Jane Marshall-Deputy Director, Division of License Renewal, NRR* David Wrona-Branch Chief, NRR* Michelle Moser-Project Manager, NRR Environmental Review* National Environmental Policy Act* Environmental review process-Title 10 of Code of Federal Regulations (10 CFR) Part 51-Environmental Standard Review Plan (NUREG-1 537)-Interim Staff Guidance Environmental Impact Statement (EIS)* 10 CFR 51.20* Project-specific decision-Potential significant impacts-First-of-a-kind facility with a unique application of technologies

-Public involvement maximized Scoping* 2 public meetings in Janesville, Wisconsin* 5 oral comments* 6 written comments Department of Energy (DOE)* National Environmental Policy Act-Lead agency: Nuclear Regulatory Commission

-Cooperating agency: DOE* American Medical Isotopes Production Act-Complementary environmental reviews Environmental Review Areas Socioeconomics and Environmental Justice Terrestrial Resources Environmental Impacts Resource Area Impact Land Use and Visual Resources SMALL Air Quality and Noise SMALL Geologic Environment SMALL Ecological and Water Resources SMALL Historic and Cultural Resources SMALL Socioeconomics SMALL Human Health and Waste SMALL Transportation SMALL to MODERATE Reasonable Alternatives

No-action alternative

Alternative sites-Chippewa Falls-Stevens Point* Alternative technologies Alternative Technologies

Neutron capture* Aqueous homogenous reactor* Linear-accelerator-based

-Analyzed in depth Costs and Benefits* Purpose-Inform recommendation to the Commission

Costs-Environmental and financial* Benefits-Societal, medical, and economic Environmental Costs Proposed Janesville Site Chippewa Falls Alternative Stevens Point Alternative Alternative Technology No-action Alternative Traffic Traffic, Noise Traffic 1 Noise, Visual Traffic None* SMALL impacts for all other resource areas Benefits* Support United States (U.S.)policy* Support U.S. public health needs* Economic benefits-Increased tax revenue-New employment opportunities Consultations

0 0 6 .~ 3--

0 Endangered Species Act, Section 7 National Historic Preservation Act, Section 106 No Effect No Adverse Effect Draft Environmental Impact Statement* 2 public meetings in Janesville, Wisconsin* 1 oral comment* 8 written comments NRC Staff's Recommendation Staff recommends issuance of the construction permit.

Future NEPA Analyses* 10 CFR 51 .95(b) requires the staff to supplement the Final EIS-Matters that differ from the Final EIS-New significant information Acronyms* NRR -Office of Nuclear Reactor Regulation Exhibit SHN-029 Medical Technologies Commission Mandatory Hearing SHINE Construction Permit Application Environmental Overview December 15, 2015 Development of the Environmental Report* Began work October 2011* SHINE production facility will be located in Janesville, Rock County, Wisconsin* Environmental Report follows the Final Interim Staff Guidance Augmenting NUREG-1 537 ii 2 Structure and Content of the Environmental Report 19.1 -Introduction 19.2 -Proposed Action 19.3- Descrption of the Affected Environment 19.4- Impacts of the Proposed Construction, Operations, and Decommissioning 19.5 -Alternatives 19.6 -Conclusions Purpose and need for the proposed action, Regulatory provisions, permits and required consultations Site location and layout, Radioisotope facility description, Water consumption and treatment.

Cooling and heating dissipation systems, Waste systems, Storage, treatment and transportation of radioactive and nonradioactive materials, including LEU, waste, radioisotopes and any other materials Land use and visual resources, Air quality and noise, Geooic environment, Water resources, Ecological resources, Historic and cultural resources, Socioeconomics,s Human health Land use and visual resources, Air quality and noise, Geologic environment, Water resources, Ecological resources, Historic and cultural resources, Socioeconomics, Human health, Waste management, Transportation, Postulated accidents, Environmental justice, Cumulative effects NO-action alternative.

Reasonable altemnatives, Cost-beneflt of the alternatives, Comparison of potential environmental impacts Unavoidable adverse environmental impacts, Relationship between short-term uses and long-term productivity of the environment, Irreversible and irretrievable commitments of resources 3 6 Scope of Field Investigations

=Phase I Environmental Site Assessment

°General Reconnaissance

+Soil Borings/Geotechnical Investigation ,Well Installation

°Phase I Archaeological Investigation

°Baseline Visual Assessment

Wetland Delineation

°Quarterly Ecological Investigations

=Aquatic Ecology ,Terrestrial Ecology oMonthly Water Resources+Water Quality=Water Levels U Context for Data Acquisition ,Site* 91.27 acre parcel located on the south side of the City of Janesville in Rock County, WI* Project Area*Circular area with a radius approximately 1 mile from the site center point' Region' Circular area with a radius of 5 miles from the site center point' Larger context as appropriate (e.g., geology, air quality)' Region of Influence , ,Rock County 5 Consultations

' City of Janesville

' Rock County-Wisconsin Department of Natural Resources-Wisconsin State Historic Preservation Office (SHPO)-Wisconsin Department of Transportation-U.S. Fish and Wildlife Service o ,E,' Federal Aviation Administration

' Bureau of Indian Affairs' Native American Tribes (13): ' Wisconsin Tribes: ,Forest County Potawatomi Community, Wisconsin°Ho-Chunk Nation of Wisconsin* Non-Wisconsin Tribes:-' 11 Tribal Entities 0~1 6 Alternative Sites Construction SMALL impacts to all Impacts resource categories Construction 420 jobs; $635,000 Benefits annual property tax payments Operation SMALL impacts to all Impacts resource categories Operation 150 jobs: reliable Benefits source of diagnostic isotopes:

Mo-99, 1-131. Xe-1 33;$680.000 annual property tax payments MODERATE impacts to Visual Resources, Noise and Transportation 420 jobs; $635,000 annual property tax payments SMALL impacts to all resource categories 150 jobs; reliable source of diagnostic isotopes:

Mo-99, 1-131. Xe-i133:$680,000 annual property tax payments MODERATE impacts to Land use, Visual Resources, Noise, Ground Water, and Transportation 420 jobs: $635,000 annual property tax payments SMALL impacts to all resource categories 150 jobs; reliable source of diagnostic isotopes:

Mo-99, 1-131, Xe-i133;$680,000 annual property tax payments SMALL impacts to all resource categories None SMALL impat to all resource categories None 7 Alternative Technologies Eu."l Construction SMAL impat to all Impat resource categories Construction 420 jobs, $635,000 Benefits annual property tax payments Operation SMLL impact to all Impat reorce caeories Operation 150 jobs; reliable Benefits source of diagnostic isotopes:

Mo-99, 1-131. Xe-i133;$680,000 annual property tax payments SMALL impacts to all resource cateories 420 jobs; $635,000 annual property tax payments SMALL impacts to all resource categorie 150 jobs; reliable source of Mo-99;$660,000 annual property tax payments SMALL impacts to all SMALL impatsto all resource categories resource categorie 420 jobs; $635,000 None annual property tax payments SMALL impacts to all SMALL impacts to all resource categorie resourc categories 150 jobs; reliable source of diagnostic isotopes:

Mo-99, 1-131, Xe-133;$660,000 annual property tax payments None 11 8 NRC Environmental Site Audit July 30- August 1, 2013* SHINE presentations on the production process and alternative site selection process-Janesville site visit°Walk down of proposed site SDriving tour SRock River visit SSampling sites 1 and 2 along the unnamed tributary to the Rock River* Tour of the Janesville Wastewater Treatment Facility ,Alternative site visits:-Stevens Point ,Chippewa FallsI SResponded to NRC Site Audit Information Needs SHINE and The Community* SHINE believes the relationships between the company, Janesville, and Wisconsin are important* SHINE favors a policy of transparency with our community , SHINE's actions support these principles a Participation in four public meetings per year (two SHINE hosted, two for city council)* SHINE management involvement in community activities a Regular discussions with city leadership to coordinate plans a Regular updates provided to State of Wisconsin* These activities have fostered a relationship of trust and enthusiasm for the project 10 Conclusions o The SHINE environmental review was conducted pursuant to 10 CFR Part 51 and is adequate=The requirements of Sections 102(2) (A), (C), and (E) of the National Environmental Policy Act (NEPA) have been satisfied°SHINE's weighing and balancing of the environmental, technical, and other costs and benefits of the SHINE facility supports issuance of the construction permit 11 SCHEDULING NOTE Title: HEARING ON CONSTRUCTION PERMIT FOR SHINE MEDICAL ISOTOPE PRODUCTION FACILITY: