ML15090A710

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Presentation for the Public Meeting on April 2, 2015 with Northwest Medical Isotopes Corporation, LLC, Regarding Medical Isotope Production Facility
ML15090A710
Person / Time
Site: Northwest Medical Isotopes, PROJ0803
Issue date: 04/02/2015
From:
Northwest Medical Isotopes
To:
Office of Nuclear Reactor Regulation
Balazik, Michael 415-2856
References
Download: ML15090A710 (13)


Text

1 1 U.S. Nuclear Regulatory Commission Pre Construction Permit Application Meeting Public Presentation April 2, 2015 11:00am - 12:00pm 2 Agenda April 2, 2015 Public Session

11:00am Opening Remarks (5 minutes)

NRC 11:05am NWMI Introductions and Project Status (10 minutes) NWMI Facility Description (10 minutes)

Facility Licensing Approach (10 minutes)

Process Functions & Requirements and Facility Design Criteria (10 minutes)

Public Question and Answer Period (15 minutes) NRC 3 NWMI INTRODUCTION AND PROJECT STATUS April 2, 2015

4 NWMI Introductions and Organization Irradiation Services - University Reactors Radioisotope Production Facility Partners Technology Demonstration Partners Carolyn Haass, Vice President Steve Reese, Irradiations Logistics Manager Marcus Voth, Technical Adviser John Andrzejczak, Chief Engineer Gary Dunford, Hot Cell Process Lead David Smith, Target Fabrication Lead Michael Corum, ISA/Shielding/Criticality Lead Engineering Design Licensing and Environmental Permitting Criticality, Shielding, and Safety Analysis Transportation

5 NWMI Project Status Construction Permit Application

-Received Exemption to Submit CP Application in 2 Parts (Oct 2013)

-Part 1 complete and submitted

-Part 2 will be submitted in 2 nd Q 2015 Facility preliminary design completed; initiating final design in

2 nd Q 2015 Proof of concept tests have/are continuing to be performed Prototypic target production initiated/OSU license amendment submitted and awaiting NRC approval Siting Decision Taken; Option formalized Network of irradiation suppliers complete Strategic Partnerships and Major Subcontractor development complete

6 FACILITY DESCRIPTION April 2, 2015

7 Process Block Flow Diagram LEU target material is fabricated (both fresh LEU and recycled U) LEU target material encapsulated using metal cladding LEU Target LEU targets are packaged and shipped to university reactors for irradiation After irradiation, targets are shipped back to RPF Irradiated LEU targets disassembled

Irradiated LEU targets dissolved into a solution for processing

Dissolved LEU solution is processed to recover and purify 99 Mo Purified 99Mo is packaged/shipped to a radiopharmaceutical distributor LEU solution is treated to recover U and is recycled back to Step 1 8 Facility Description 1 st Level footprint ~52,000 ft 2 -Target Fabrication Area

-Hot Cell Processing areas (e.g., Dissolution, 99Mo recovery, 235U recovery)

-Waste Management, Laboratory and Utility Areas 2 nd Level foot print ~17,000 ft 2 (e.g., Utility, Ventilation, and Off-Gas Equipment)

WM Out Building (~1,200 ft

2) High bay roof - 65 ft Mach area roof - 46 ft Top of exhaust stack - 75 ft Loading dock (back) roof - 20 ft Support & Admin (front) roof - 12 ft Depth below grade for tank farm/HIC storage - 15 ft Administration Building (outside of secured RPF area) ~10,000 ft2 9 FACILITY LICENSING APPROACH April 2, 2015

10 Licensing Approach NWMI will combine several license activities and submit one application that covers all applicable regulations for construction and operation of an RPF under 10 CFR 50

-Process 99Mo and recycle LEU under 10 CFR 50, Domestic Licensing of Production and Utilization Facilities

-Target fabrication (ability to receive, possess, use, and transfer of SNM) under 10 CFR 70, Domestic Licensing of SNM

-Ability to handle by

-product material under 10 CFR 30, Rules of General Applicability to Domestic Licensing of Byproduct Material NWMI's understanding

-NRC will approve and issue one license under 10 CFR 50; Activities under 10 CFR 70 and 10 CFR 30 will be part of 10 CFR 50 license (10 CFR 50.31, Combining Applications) -NRC will complete a single review process (10 CFR 50.32, Elimination of Repetition) -Only interact with one group within NRC (e.g., administrative, license reviews and approvals, inspections) (10 CFR 50.32, Elimination of Repetition) -Fees will only be assessed under 10 CFR 50 Other Integrated License Activities to support NWMI's RPF

-University Reactor(s) will amend their current operating license's to support production of 99 Mo -Required transportation casks will be amended by NWMI (if necessary)

11 Facility Licensing Layout 10 CFR 50 Activities

-Irradiated Target receipt

-Irradiated target disassembly

-Target dissolution

-99Mo separations, purification and packaging

-LEU reclamation and purification

-Waste management

-Associated laboratory and support 10 CFR 70 Activities

-Receipt of LEU (from DOE)

-Production of LEU target material

-Target fabrication and testing

-Shipping/loading of fabricated targets

-Associated laboratory and support areas 10 CFR 30 Activities

-Handling of byproduct material

12 FACILITY ASSUMPTIONS AND CRITERIA April 2, 2015

13 RPF Primary Assumptions and Criteria Single RPF using LEU Irradiated targets generated by multiple reactors; Utilize same target design Individual target batch processing time from EOB 32 hr Uranium losses during process < 3 % Recycling processed LEU for reuse as target material Fission product releases will comply with environmental release criteria Uranium processing and storage will meet all required Safeguards & Security Requirements Each unit process/function and sub process/function requirements have been identified Facility Design Criteria Document Complete Facility Process Functions & Requirements Document Complete Radioisotope Production Facility ProcessFabricateTargetsHandle WasteRecover MolybdenumProcess IrradiatedTargetsRecoverUraniumSupport SystemsNWMI-001r1Receive New UraniumProduce Target MaterialAssemble TargetsHandle Scrap UraniumPackage and Ship TargetsAccumulate WasteTreat WastePackage and Assay WasteShip WasteSeparate MolybdenumPurify Molybdenum Package and Ship MolybdenumReceive Irradiated TargetsDisassemble TargetsDissolve Target MaterialFission Product Gas CaptureReceive Impure UraniumPurify UraniumRecycleUraniumOffgasTreatmentUtilities and ConsumablesLaboratory