ML15090A710
| 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
U.S. Nuclear Regulatory Commission Pre Construction Permit Application Meeting Public Presentation April 2, 2015 11:00am - 12:00pm 1
1
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 2
NWMI INTRODUCTION AND PROJECT STATUS April 2, 2015 3
NWMI Introductions and Organization 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 Irradiation Services - University Reactors Radioisotope Production Facility Partners Technology Demonstration Partners Engineering Design Criticality, Shielding, and Safety Analysis Licensing and Environmental Permitting Transportation 4
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 2nd Q 2015 Facility preliminary design completed; initiating final design in 2nd 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 5
FACILITY DESCRIPTION April 2, 2015 6
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 99Mo Purified 99Mo is packaged/shipped to a radiopharmaceutical distributor LEU solution is treated to recover U and is recycled back to Step 1 7
Facility Description 1st Level footprint ~52,000 ft2 High bay roof - 65 ft
- Target Fabrication Area Mach area roof - 46 ft
- Hot Cell Processing areas (e.g., Dissolution, 99Mo recovery, 235U recovery) Top of exhaust stack - 75 ft
- Waste Management, Laboratory and Utility Areas Loading dock (back) roof - 20 ft 2nd Level foot print ~17,000 ft2 (e.g., Utility, Ventilation, and Support & Admin (front) roof - 12 ft Off-Gas Equipment)
Depth below grade for tank farm/HIC storage - 15 ft WM Out Building (~1,200 ft2)
Administration Building (outside of secured RPF area) ~10,000 ft2 8
FACILITY LICENSING APPROACH April 2, 2015 9
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 NWMIs 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 NWMIs RPF
- University Reactor(s) will amend their current operating licenses to support production of 99Mo
- Required transportation casks will be amended by NWMI (if necessary) 10
Facility Licensing Layout 10 CFR 50 Activities 10 CFR 70 Activities 10 CFR 30 Activities
- Irradiated Target receipt
- Receipt of LEU (from DOE) - Handling of byproduct material
- Irradiated target disassembly
- Target dissolution - Production of LEU target material
- 99Mo separations, purification and packaging - Target fabrication and testing
- LEU reclamation and purification - Shipping/loading of fabricated targets
- Waste management - Associated laboratory and support areas
- Associated laboratory and support 11
FACILITY ASSUMPTIONS AND CRITERIA April 2, 2015 12
RPF Primary Assumptions and Criteria Single RPF using LEU Recycling processed LEU for reuse as Irradiated targets generated by multiple target material reactors; Utilize same target design Fission product releases will comply with Individual target batch processing time environmental release criteria from EOB 32 hr Uranium processing and storage will meet Uranium losses during process < 3 % all required Safeguards & Security Requirements Radioisotope Each unit process/function and sub process/function requirements have been Production Facility Process Fabricate Targets Process Irradiated Recover Molybdenum Recover Uranium Handle Waste Support Systems identified Targets Receive New Receive Separate Receive Accumulate Offgas Facility Design Criteria Document Complete Irradiated Impure Uranium Molybdenum Waste Treatment Targets Uranium Produce Facility Process Functions & Requirements Disassemble Purify Purify Utilities and Target Molybdenum Treat Waste Consumables Targets Uranium Material Assemble Targets Dissolve Target Material Package and Ship Molybdenum Recycle Uranium Package and Assay Waste Laboratory Document Complete NWMI-001r1 Fission Handle Scrap Product Gas Ship Waste Uranium Capture Package and Ship Targets 13