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Official Exhibit - NRC-006D-MA-CM01 - Northwest Medical Isotopes, LLC, Construction Permit Application - PSAR, NWMI-2013-021, Rev. 3, Chapter 4 (Sep. 2017)
	ML18025B160
Person / Time
Site:	Northwest Medical Isotopes
Issue date:	09/30/2017
From:	; NRC/OGC
To:	; NRC/OCM
	SECY RAS
References
	50-609-CP, Construction Permit Mndtry Hrg, RAS 54182
	Download: ML18025B160 (274)
	v • d • e

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Chapter 4.0 -Radioisotope Production Facility Description Prepared by: Construction Permit Application for Radioisotope Production Facility NWMl-2015-021, Rev. 3 September 2017 Northwest Medical Isotopes, LLC 815 NW g t h Ave , Suite 256 Corvallis , Oregon 97330 This page intentionally left blank.

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NORTMWUTM£01CALISOTOft£S NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Chapter 4.0 -Radioisotope Production Facility Description Construction Permit Application for Radioisotope Production Facility NWMl-2013-021, Rev. 3 Date Published:

September 5 , 2017 Document Number. NWMl-2013-021 Revision Number. 3 Title: Chapter 4.0 -Radioisotope Production Facility Description Construction Permit Application for Radioisotope Production Facility Approved by: Carolyn Haass Si nature: C w.J"rfv<-- (__ .... ;. NWMI ...... .. .. .*.* .. *.*. ' !* * . NOkTWWUT WOICAl ISOTOf'U This page intentionally left blank. NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description

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NORTtrWHT MEotCAt. tscnwu Rev Date 0 6/29/2015 1 5/19/2017 2 N/A 3 9/5/2017 REVI S ION HI S TORY Reason for Revision Initial Application NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Revised By Not required Incorporate changes based on responses to NRC C. Haass Requests for Additional Information Incorporate final comments from NRC Staff and ACRS; C. Haass fu ll document rev i sion T hi s p age int e n t ion a ll y l eft bl a nk. NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description

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NORTHWUT MEDICAL tSOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description CONTENTS 4.0 RADIOISOTOPE PRODUCTION FACILITY DESCRIPTION

........................... ...................... .4-1 4.1 Facility and Proc ess Description .................................................. ..................................... .4-2 4.1.1 Radioi sotope Production Facility Summary ................ .................................. ..... .4-2 4 .1.2 Process Summary ................................................................................ ................. 4-7 4.1.2.1 Process De sign Basis ........................................................ .................. .4-8 4.1.2.2 Summary of Reagent , Product and Wa ste Streams .................. ........ .4-10 4.1.2.3 Radioisotope Production Facility Spent Nuclear Mater ial Inventory ......................... ................................................ .................. 4-11 4.1.2.4 Radioisotope Production Facility Anticipated Maximum Radionuclid e Inventory ................ ..................................................... 4-13 4.1.3 Proces s Overview .................... ............ ........................................ ....................... 4-15 4.1.3.1 Target Fabrication ............................................................................. 4-15 4. 1.3.2 Target Receipt a nd Di sassemb l y ............................... ........................ 4-19 4.1.3.3 Target Dissolution ............................................................................ .4-21 4.1.3.4 Molybdenum Recovery and Purification ..................................... .... .4-23 4.1.3.5 U ranium Reco very and Rec yc l e ....................................................... .4-25 4.1.3.6 Waste Handling ............ ............................... ............. ......................... 4-27 4.1.4 Facility D esc ription ................ ............................................................................ 4-31 4.1.4.1 General Construction ................................................................ ....... .4-32 4.1.4.2 Site and Facility Access ............ ........................ ......................... ...... .4-34 4.1.4.3 Fac ility Ventilation ........................................................................... .4-34 4.1.4.4 Target Fabrication Area ................................................................... .4-35 4.1.4.5 Irradiated Target Rec ei pt Area ................... ...................................... .4-37 4.1.4.6 Hot Cell Area ...................... .......................................... .................... 4-38 4.1.4.7 Waste Mana ge ment Are a ............. ....................... ....................... ...... .4-42 4.1.4.8 La boratory Area ........................... ..................................................... 4-46 4.1.4.9 C hemical Makeup Room ................................... ................................ 4-47 4.1.4.10 Utility Area ........... ............... ...................................................... ........ 4-47 4.1.4.11 Administration and Support Area ............... ....................... .............. .4-51 4.2 Radioisotope Production Facility Biolo g ical S hi e ld .......................................... ............. .4-53 4.2.1 Introduction ......................... ............... ......................................................... ....... 4-53 4.2.1.1 Biological Shield Functions .............................................................. 4-53 4.2.1.2 Physical Layout of Biologic a l Shield ............................................... .4-5 3 4.2.2 Shielding Design ............................................. ....................... ............ ................ 4-55 4.2.2.1 Shielding Materials of Construction ................... .................... .......... 4-56 4.2.2.2 St ructural Int egrity ofShielding ........................................................ 4-56 4.2.2.3 Design of Pen etra tions ................. ..................................................... 4-57 4.2.2.4 Design of Material Entry and Exi t Ports ........................................... 4-57 4.2.2.5 Design of Operator Interfaces ................................................ .......... .4-59 4.2.2.6 Design of Oth e r Interface s ................................. .............................. .4-59 4-i .... **..... ... ;. NWMI .... .... .. ;e NOllTHWUT M£DJCAl ISOTOf'U NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description 4.2.3 4.2.4 4.2.5 Method s an d Assumptions for Shielding Calculations .............................. ........ 4-60 4.2.3.1 Initial Source Term ............. ............................ ............................. ..... 4-60 4.2.3.2 Shield Wall Material Composition .................................................... 4-62 4.2.3.3 Methods of Calculating Do se Rates .................... .............................. 4-63 4.2.3.4 Geometries ..................................... ................................................ ... 4-64 4.2.3.5 Es timated Hot Ce ll Wall Thickness ................. ................................ .4-70 4.2.3.6 Estima ted Minimum Hot Cell Window Thickness .......................... .4-73 Calculated Dose E quivalent Rate s and Shield Thickness Requirem ents ........... 4-73 Ventilation Systems for the Biolo g ical Shield Structure .................. ................ .4-73 4.3 Radioisotope Extraction System ............... ..................................................................... ... 4-74 4.3.1 Extrac tion Time Cycle ............ ..................... .................... ...................... ............ 4-74 4.3.2 Irradiated Target Receipt. ..................................................................... .............. 4-75 4.3.2.1 Desi g n Basi s .................................................. .................................... 4-75 4.3.2.2 System Description ........................................................................... 4-75 4.3.3 Target Disassembly ..................................................... ....................................... 4-86 4.3.3.1 Process Description .......................................... ................................. 4-86 4.3.3.2 Proce ss Equipment Arrangement .................................... ........... ....... 4-88 4.3.3.3 Process E quipment Design ........................ ........................................ 4-89 4.3.3.4 Special Nucle ar Material Description .......................... .................... .4-89 4.3.3.5 Radiological Hazards ................................. ..................... .................. 4-91 4.3.3.6 Chemical Hazards .................... .................. ....................................... 4-96 4.3.4 Irradiated Target Dissolution System ............................................... .................. 4-96 4.3.4.1 Process Description ......................................................... .................. 4-97 4.3 .4.2 Process Equipment Arrangement .................. .................................. 4-102 4.3.4.3 Process E quipment De s ign ............................ .................................. 4-105 4.3.4.4 Special Nuclear Materi a l Description ............................................. 4-107 4.3.4.5 Radiological Hazards ................................................... .............. .... .4-110 4.3.4.6 Chemical Hazards ............................................... ............................ 4-121 4.3.5 Molybdenum Recovery and Purification System ............ ................................ .4-122 4.3.5.1 Process Description .................... ..................... ................................ 4-122 4.3.5.2 Process Equipment Arrangement ............ ....................................... .4-127 4.3.5.3 Process Equipment Design .......................................... .................... 4-131 4.3.5.4 Special Nuclear Material De sc ription ............................................ .4-133 4.3.5.5 Radiological Hazards .............. ......................................... ............... 4-136 4.3.5.6 Chemical Haz ar ds ............................................................. .............. 4-141 4.4 Special Nuclear Material Proces s ing and Storage ..................... ................................. .... 4-143 4.4.1 Processing of Irradiated Special Nuclear Material. ......................................... .4-143 4.4.1.1 Process Description ...................... .................................................. .4-144 4.4.1.2 Process Equipment Arrangement ................................................... .4-156 4.4.1.3 Process Equipment De s ign ................ ............... ...................... ........ .4-157 4.4.1.4 Special Nuclear Material Description ................ .................... ........ .4-160 4.4.1.5 Radiological Hazards ........................................ .............................. 4-165 4.4.1.6 Chemical Hazards .......................... ................................................ .4-175 4-ii 4.4.2 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Processin g of Un irradiated Special Nuclear Material ........... .......................... .4-176 4.4.2.1 Target Fabrication Design Basis ............... ........... .......................... .4-177 4.4.2.2 Fresh Uranium Receipt and Dissolution ........................................ .4-182 4.4.2.3 Nitrate Extraction Subsystem ................ ..................................... ..... 4-190 4.4.2.4 Acid-Deficient Uranyl Nitrate Concentration Subsystem .............. .4-200 4.4.2.5 [Proprietary Information] ................................................................ 4-207 4.4.2.6 [Proprietary Information] Subsystem .................. .................... ....... .4-214 4.4.2. 7 [Proprietary Information] Subsystem .................................... ......... .4-220 4.4.2.8 Target Fabrication Wa ste Subsystem ............................................. .4-232 4.4.2.9 Target Assembly Subsystem ................. ........................ .......... ....... .4-238 4.4.2.10 Low-Enriched Uranium Storage Subsystem .................................. .4-246 4.5 References ...................................... ................................................................................ 4-251 4-iii Figure 4-1. Figure 4-2. Figure 4-3. Figure 4-4. Figure 4-5. Figure 4-6. Figure 4-7. Figure 4-8. Figure 4-9. Figure 4-10. Figure 4-11. Figure 4-12. Figure 4-13. Figure 4-14. Figure 4-15. Figure 4-16. Figure 4-17. Figure 4-18. Figure 4-19. Figure 4-20. Figure 4-21. Figure 4-22. Figure 4-23. Figure 4-24. Figure 4-25. Figure 4-26. Figure 4-27. Figure 4-28. Figure 4-29. Figure 4-30. Figure 4-31. Figure 4-32. Figure 4-33. Figure 4-34. Figure 4-35. Figure 4-36. Figure 4-37. Figure 4-38. FIGURES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Radioisotope Production Facility Site Layout ........................................................ ........ .4-2 Building Model of the Radioisotope Production Facility ............................. ................... 4-3 General Layout of the Radioisotope Production Facility ................................................. 4-4 Preliminary Layout of the Radioisotope Production Facility First Level Floor Plan and Associated Dimensions ..................................................................................... 4-5 Preliminary La yo ut of the Radioisotope Production Facility Second Level Floor Plan .............. ................................................ ................................ ............. ....................... 4-6 Radioisotope Production Facility Hot Cell Details ............................ .................. ............ 4-6 Radioisotope Production Facility Block Flow Diagram .................................................. 4-7 Reagents, Product, and Waste Summary Flow Diagram .............. ................................. 4-10 Radioisotope Processing Facility at 0 to 40 Hours End oflrradiation ............ .............. .4-14 Radioisotope Processing Facility at Greater than 40 Hours End oflrradiation ............ .4-14 Target Fabrication Block Flow Diagram ...................................................................... .4-16 Target Assembly Diagram .................................. ...................................... ..................... 4-17 Target Fabrication Location ........................................................................................... 4-I 8 Target Receipt and Disas sembly System Flow Diagram ........................ ....................... 4-19 Target Receipt and Disassembly System Facility Location ............................... ............ 4-2 0 Simplified Target Dissolution Process Flow Diagram .................................................. 4-21 Target Dissolution System Facility Location ............................ .................................... 4-22 Simplified Molybdenum Recovery and Purification Process Flow Diagram ................ 4-23 Molybdenum Recovery and Purification System Facility Location .............................. 4-24 Simplified Uranium Recovery and Recycle Process Flow Diagram ............................. 4-25 Uranium Recovery and Recycle System Location .................... ........................... ........ .4-26 Hi g h-Dose Liquid Waste Dispo s ition Process ......................................... ...................... 4-28 Low-Dose Liquid Waste Disposition Process .............................. ............. .................... 4-28 Waste Handling Locations ................................... ..................... ..................................... 4-29 Low-Dose Liquid Waste Evaporation Facility Location ............................................... 4-30 Radioisotope Production Facility Areas ........................................ ......................... ...... .4-31 Target Fabrication Area Layout ........................ ............................................................. 4-35 Irradiated Target Receipt Area Layout .................. .................... ................... ................. 4-37 Hot Cell Area Layout. ........................................ ........................... ...................... ........... 4-39 High-Integrity Contai ner Storage and Decay Ce ll s Layout.. ..................................... .... 4-42 Waste Management Loading Bay and Area Layout.. .................................................... 4-43 Waste Management Area -Ground Floor ............................ ............................... .......... 4-43 Waste Management Area -Low-Dose Waste Solidification Location ......................... 4-44 Laboratory Area Layout. ........... ............................. ................................................... ..... 4-46 First Floor Utility Area ........................................................... ....................................... 4-48 Second Floor Mechanical and Electrica l Room .......................... .............. .................... .4-48 Second Floor Mechanical Area ............... ....................................................................... 4-48 Administration and Support Area Layout ........................................ .............................. 4-5 I 4-iv

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NOtn'HWEST MEOK:Al ISOTOPES NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-39. Figure 4-40. Figure 4-41. Figure 4-42. Figure 4-43. Figure 4-44. Figure 4-45. Figure 4-46. Figure 4-47. Figure 4-48. Figure 4-49. Figure 4-50. Figure 4-51. Figure 4-52. Figure 4-53. Figure 4-54. Figure 4-55. Figure 4-56. Figure 4-57. Figure 4-58. Figure 4-59. Figure 4-60. Figure 4-61. Figure 4-62. Figure 4-63. Figure 4-64. Figure 4-65. Figure 4-66. Figure 4-67. Figure 4-68. Figure 4-69. Figure 4-70. Figure 4-71. Figure 4-72. Figure 4-73. Figure 4-74. Figure 4-75. Figure 4-76. Figure 4-77. Facility Location of Biological Shie ld ................................................................

........... 4-54 Hot Cell Arrangement ................. ............. ................. .................. ................................... 4-5 5 Hot Cell Target Transfer Port ...................... ........................................ .......................... 4-57 Waste S hippin g Transfer Port ........... ...................... ............................... ........................ 4-58 Manipulators and Shield Windows ........................................................ ..................... ... 4-59 Cover Block Configuration .................................... ....................... ................................. 4-60 Dose Equivalent Rate from an Irradiated Target as a Function of Time ...................... .4-68 Dose Eq uival ent Rate Variation through Base Case 120 Centimeter (4-Foot) Composite Wall .......... ............................................ ....................... ................................ 4-71 Extraction Time Cyc le ...................................... ............. ........................................... ..... 4-7 4 Cask Receipt Subsystem Flow Diagram .......... .................................. ...................... ...... 4-76 Irradiated Target Handling Equipme nt Arrangement Plan View .................................. 4-76 Irradiated Target Handling Equipment Arrangement Isometric View .......................... 4-77 Cask Preparation Airlock ........... ................. ..................... .............................................. 4-79 Cask Preparation Airlock Equipment Arrangement ............................................ .......... 4-79 Target Receipt Hot Cell Equipment Arrangement.. ............................... ...................... .. 4-80 Target Receipt In-Process Radionuclide Inventory Streams .............. .......................... .4-83 Target Disassembly Hot Cells Equipment Arrangement.. ............................................ .4-88 Target Disassembly In-Process Radionuclide Inventory Streams ................................ .4-91 Simplified Target Dissolution Flow Diagram ................................................................ 4-97 Dissolver Hot Cell Locations ....................................................................................... 4-102 Dissolver Hot Cell Equipment Arrangement (Typica l of Dissolver 1 Hot Cell and Dissolver 2 Hot Cell) .............................. ................. .................................. .................. 4-103 Target Dissolution System Tank Hot Cell Equipment Arrangement ......................... .4-104 Target Dissolution System Mezzanine Equipment Arrangement.. .............................. 4-105 Target Dissolution In-Process Radionuclide Inventory Streams .................. .............. .4-110 Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory Streams .................... .4-115 Fission Gas Treatment In-Process Radionuclide Inventory Streams .................... ...... .4-118 Simplified Molybdenum Recovery and Purification Process Flow Diagram .............. 4-123 Molybdenum Product Hot Cell Equ ipm ent Arrangement ........................ ................... 4-127 Molybdenum Recovery Hot Cell Equipment Arrangement ........... ............................. 4-128 Molybdenum Purification Hot Cell Equipment Arrangement.. ............................ ...... .4-129 Product and Sample Hot Cell Equipment Arrangement .............. ............................ .... 4-130 Molybdenum Feed Tank Hot Ce ll Eq uipment Arrangement.. ..................................... 4-131 Molybdenum Recovery and Purification In-Process Radionuclide Inventory Streams .................. ............... ............. ................... ................................ ........................ 4-136 Uranium Recovery and Recycle Process Functions .................................................... 4-143 Uranium Recovery and Recycle Overview .................................................................. 4-144 Simplified Uranium Recovery and Recycle Process Flow Diagram .......................... .4-146 Condensate Tank # 1 Config uration Concept ............................................................... 4-150 Tank Hot Cell Equipment Arrangement ................................................................ ...... 4-156 Alternative Pencil Tank Diameters for Equipment Sizing .................. ........................ .4-157 4-v NWMI ...... ' * * ! . NORTHWEST MEDICAL ISOTOPES NWMl-2015-021 , Rev. 3 Cha p ter 4.0 -RPF Description Figure 4-78. Figure 4-79. Figure 4-80. Figure 4-81. Figure 4-82. Figure 4-83. Figure 4-84. Figure 4-85. Figure 4-86. Figure 4-87. Figure 4-88. Figure 4-89. Figure 4-90. Figure 4-91. Figure 4-92. Figure 4-93. Figure 4-94. Figure 4-95. Figure 4-96. Figure 4-97. Figure 4-98. Figure 4-99. Figure 4-100. Figure 4-101. Figure 4-102. Figure 4-103. Figure 4-104. Figure 4-105. Figure 4-106. Figure 4-107. Figure 4-108. Figure 4-109. Figure 4-110. Figure 4-111. Figure 4-112. Figure 4-113. Figure 4-114. Figure 4-115. Figure 4-116. Figure 4-117. Conceptua l Ion Exchange Column for Uranium Purification ...................................... 4-158 Conceptua l Uranium Concentrator Vessel ................ ................................................... 4-158 Impure Uranium Collection Tanks In-Process Radionuclide Inventory Streams ........ 4-166 Uranium Recovery and Recycle In-Process Radionuclide Inventory Streams ............ 4-170 Key Subsystem Interfaces within Target Fabrication .............................................. .... 4-176 New Target Handling Flow Diagram .......................................................................... 4-181 ES-3100 S hippin g Container ............ ............................ ................................... ............ 4-182 Fresh Low-Enriched Uranium Handling and New Target Hand lin g Equipment Arrangement ................................................................................................................ 4-183 Fresh Uranium Dissolution Process Flow Diagram ................................................. .... 4-184 Fresh Uranium Dissolution Equipme nt Arrangement .............................................. ... 4-185 Dissolution Equipment Layout ........................................ ................... ......................... 4-186 Nitrate Extraction Process Flow Diagram ............... ................................................... .4-191 Nitrate Extraction Equipment Layout .......................................................................... 4-194 Uranyl Nitrate Storage Tank Arrangement .................................... .............................. 4-195 Nitrate Extraction Equipment Arrangement ................................................................ 4-196 Acid-Deficient Urany l Nitrate Concentration Process Flow Diagram ........................ 4-201 Acid-Deficient Uranyl Nitrate Concentration Eq uipment Layout.. ............................ .4-202 Acid-Deficient Urany l Nitrate Concentration Feed Equipment Arrangement ............ 4-203 Acid-Deficient Urany l Nitrate Concentration Equipment Arrangement ..................... 4-203 Sol-Gel Column Feed Process Flow Diagram .......................... ................... ................ 4-208 Sol-Gel Column Fee d Eq uipm ent Layout.. ................................ .................. ............... .4-209 Concentrated Acid-Deficient Urany l Nitrate Storage Equipme n t Arrangement ........ .4-210 Sol-Gel Co lumn Feed Equipment Arrangement.. ........................................................ 4-210 [Proprietary Information] ...................................... ...................... ........................... ...... 4-215 [Proprietary Information] Layout .............................. ................ .................................. 4-216 [Proprietary Information] Arrangement.. .................................. ................................... 4-217 [Proprietary Information] Flow Diagram ................................... .................................. 4-221 [Proprietary Information] Layout ................................................... ............................. 4-225 [Proprietary Information] Arrangement ........... ................. ......................... .................. 4-225 [Proprietary Information] Arrangement ........... .................................................. .......... 4-226 [Proprietary Information] Layout ................................... ............... .............................. 4-226 [Proprietary Information] Arrangement ....................... .................... ............................ 4-227 Target Fabrication Waste Process Flow Diagram .............................................. ......... .4-233 Target Fabrication Waste Equipment Layout ...................................................... ........ 4-234 Aqueous Waste Holding Tank ............... ............. .................................................. ....... 4-235 Trichloroethylene Recovery Skid Arrangement ..................... .......................... ........... 4-235 Target Loading Preparation and Target Loading Workstation .................................... 4-239 Target Welding Enclosure .............. ...................... ....................................................... 4-240 Target Weld Finishing Workstation ........................................................... .................. 4-240 Target Weld Inspection Station and Target Weight Inspection Equipment .......... ...... 4-241 4-vi

.. ;. NWMI *: :**:*; ...... ' * * ! . NOflllfWtST MEOfCAL ISOTOPES NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-118. Figure 4-119. F i g ure 4-1 2 0. Figure 4-121. Figure 4-122. Figure 4-123. Table 4-1. Table 4-2. Table 4-3. Table 4-4. Table 4-5. Table 4-6. Table 4-7. Table 4-8. Tab le 4-9. Table 4-10. Tab l e 4-11. Table 4-12. Tab le 4-1 3. Table 4-14. Table 4-15 Table 4-16 Tab l e 4-17. Ta ble 4-1 8. Table 4-1 9. Table 4-20. Table 4-21. Tab le 4-22. Table 4-23. Table 4-24. Table 4-25. Table 4-26. Table 4-27. Table 4-28. Table 4-29. Tab l e 4-30. Target Disassembly Workstation

................................................................................. 4-242 Target Assembly Equipment Layo ut .................................. ........................................ .4-242 Target Assembly Diagram (Doc-No 50-243) ............................................................. .4-243 Low-Enr iched Uranium Storage Equ ipm ent La y o ut ................................................... 4-247 Low-Enric hed Uraniu m Can Rack ..................................................... .......................... 4-248 12-Position Target Cart ................................................................................................ 4-248 TABLES Specia l Nuclear Material In ventory of Target Fabr ication Area ................................... 4-11 Special Nuclear Materia l Inventory of Irradiated Material Areas ................................ .4-12 Radionuclide Inventory for Radioisotope Production Facility Process Streams .......... .4-13 Radioisotope Production Facility Area Crosswalk ........................................................ 4-32 Facility Areas and Respective Confinement Zones ...................................................... .4-34 Target Fa bri cation Area Room Descriptions and F un ctions (2 pages) .......................... 4-35 Irradiate d Target Receipt Area Room Descriptions an d Functions .............................. .4-37 Hot Ce ll Area Room Descriptions a nd Functions (2 pages) ......................................... .4-39 Waste Management Ro o m Descriptions and Functio ns ............................................... .4-44 Laboratory Area Room Descriptions and Functions ..................................................... .4-46 Utility Area Room D escri pti ons and Functions ............................................................ .4-49 Administrat ion and Support Area Room Descriptions and Functio n s .......................... .4-52 Master Material List. ........................ .............................................................................. 4-62 Target Mo del Materials .................................... ............................. ......................... ....... 4-64 Pencil Tank Model Data ................................................................................................ 4-65 Carbon Bed Model Geometric Para m e t ers ................................................................... .4-65 Waste Container Geo m e tric Data .................................................................................. 4-65 Materia l Assignment for Stee l/Concrete Composite Wall Model ................................. 4-66 Dose Equiva l ent Rate fro m an Irradiated Target as a Function of T im e at Vario u s Distances in Air ...................... ........................ ............................................................... 4-67 Target Fabr i cation Incoming Process Stream Dose Rates ............................................. 4-69 Carbon Bed Model Dose Rate Results ........................................................................... 4-69 High-Dose Waste Contai n er Bounding Dose Equiva l ent Rates ................................... .4-70 Estimat ion of Coeffic i ent ..l2 .............................................................................. ........... 4-72 Required Steel Thickness in Composite Wall for Va riou s Total Wall Thicknesses ..... .4-72 Exterior Do se Rates for 1 20 Centi meter (4-Feet) Tota l Wall Thickness and Various Stee l Thicknesses ............................................................................................. 4-72 Estimate d Dose Equiva l e n t Rates on the Outside of the Hot Cell Window .................. 4-73 Radioisotope Extract i on Systems .................................................................................. 4-74 Irradiated Target Receipt Auxiliary E quipm ent... .................... ..................................... .4-80 Irradiated Target Receipt In-Process Spec i al N ucl ear M aterial Inventory ................... .4-81 Irradiated Target Receipt Radionuclide In-Process Inventory (3 pages) ...................... .4-83 4-vii ...*.. ... ;. NWMI .. *.. NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

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NOfmrwnr MEOtCAl ISOTOflltl Table 4-31. Table 4-3 2. Table 4-33. Table 4-34. T a ble 4-35. Table 4-36. Table 4-37. Table 4-38. Table 4-39. Table 4-40. Table 4-41. Table 4-42. Table 4-43. Table 4-44. Table 4-45. Table 4-46. Table 4-47. Table 4-48. Table 4-49. Table 4-50. Table 4-51. Table 4-52. Table 4-53. Table 4-54. Table 4-55. Table 4-56. Table 4-57. Table 4-58. Table 4-59. Table 4-60. Table 4-61. Table 4-62. Table 4-63. Table 4-64. Table 4-65. Table 4-66. Target Disassembly Auxiliary Equipment

........... .......................................................... 4-89 Individual Irradiated Target Disassembly Hot Cell In-Process Special Nuclear Material Inventory ......................................................................................................... 4-8 9 Target Disassembly In-Process Radionuclide Inventory (4 pages) .............................. .4-92 Irradiated Target Dissolution Process Equipment ...................................................... .4-106 Tar g et Dissolution Auxiliary Equipment ..................................................................... 4-107 Individual Targ e t Dissolution Hot Cell In-Process Special Nuclear Materi a l Inventory ....................... ............................................................................................... 4-108 Target Dissolution In-Process Radionuclide Inventory (4 pages) .............................. .4-111 Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory ( 4 pages) .................. .4-115 Fission Gas Treatment In-Process Radionuclid e Inventory (3 pa g es) ......................... 4-119 Chemical Inventory for the Target Dissolution Area .................................................. .4-121 Typical Ion Exchange Column Cycle .......................................................................... 4-124 Strong Basic Anion Exchange Column C y cle ............................................................ .4-125 Purified Molybdenum Product Specification .......................................................... ..... 4-126 Molybdenum Recovery and Purification Process E quipm e nt .................................... .4-1 3 2 Molybdenum Recovery and Purification Auxiliary Equipment ................................. .4-132 Mol y bdenum Recovery and Purification S y stem In-Proces s Sp e cial Nuclear Material Inventory ....................................................................................................... 4-134 Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages) ................................. ............. ......................................................................... 4-13 7 Chemical Inventory for the Molybdenum Recovery and Purification Area ............... .4-142 Fir s t-Cycle Uranium Recovery Ion Exchange Column Cycle Summary ................... .4-148 Uranium Reco v ery and Recycle Process Equipment (2 pages) ................................... 4-159 Uranium Reco v ery and Recycle In-Process Special Nuclear M a terial Inventory (2 pages) ................ ....................................................................................................... 4-161 Impure Uranium Collection Tanks In-Process Radionuclide In v entory (4 pages) ...... 4-166 Uranium Recovery and Recycle In-Proces s Radionuclide Inventory (4 p ag es) ......... .4-170 Uranium Recovery and Recycle Chemical Inventory ...................................... ........... .4-175 Target Fabrication Subs y stems .................................................................................... 4-176 Fresh Uranium Metal Specification (3 pages) ............................................................ .4-177 Low-Enriched Uranium Target Physical Properties ................................................... .4-180 Fresh Uranium Dissolution Process Equipment .......................................................... 4-186 Fresh Uranium Dissolution Design Basis Special Nuclear Material Inventory .......... .4-187 Fresh Uranium Dissolution Chemical Inventory ........................................................ .4-190 Recycled Uranium Specification (2 pages) ................................................................. .4-192 Nitrate Extraction Process Equipment ......................................................................... 4-197 Nitrate Extraction Special Nuclear Material Inventory .............................................. .4-198 Nitrate Extraction Chemical Inventory ........................................................................ 4-200 Acid Deficient Uranyl Nitrate Concentration Process Equipment .............................. 4-204 Acid-Deficient Uranyl Nitrate Concentration Maximum Special Nuclear Material Inventory ...................................................... ............... ................................................. 4-205 4-viii ..... NWMI ...... .. ... .. .. ...*.. '

NORTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description T a ble 4-67. T abl e 4-6 8. T abl e 4-69. Ta ble 4-70. T a ble4-71. T a ble 4-72. T a ble 4-73. T a ble 4-74. T a ble 4-7 5. T a ble 4-76. T a ble 4-77. T a ble 4-78. T a ble 4-79. T a ble 4-8 0. T a ble 4-8 1. [Proprietary In fo rmation] Proc ess E quipment .............................................................

4-2 11 [Proprietary Information] Spe cia l Nucl e ar M a t e rial In ve nt ory ................................... 4-2 1 2 C h e mic a l In v ent ory for the Sol-G el Column F ee d S ub sys t e m ................................... .4-2 1 3 [Proprietary Information] ............ ............................ ..................................................... 4-2 1 8 [Proprietary In fo rmation] Sub sys t e m ................ .......................................................... 4-22 0 [Proprietary Inf o rmation] ................................................................. ............ ................ 4-224 [Proprietary In fo rmation] ................................ ............................................................. 4-228 [Proprietary Information] ...................................... ....................................................... 4-2 29 C h e mical In v ent ory for the [P ro pri e ta ry Inform a tion] Sub sys t e m ................ ............. .4-23 1 Tar ge t F abricati o n Waste Proc e ss E quipm e nt ............................................................. 4-23 6 Tar ge t Fabricati on Wa s te Ch e mic a l Invento ry .......... ............................................ ..... .4-238 Ta r get A s sembl y Au x iliary Equipment .......... ............................................................. 4-2 4 3 Targ et Design Par a m e t e r s ................................. ......................................... .................. 4-2 44 Target A ss embl y S p e cial Nucle ar Material In ve ntory ................................................ .4-2 45 Low-E nriched U r a nium Stora g e M a ximum Spe c ial Nucle a r Material Inventory ....... 4-2 49 4-ix ..... NWMI :::**::* ...... . * * ! . NORTHWEST MEDttAl tsOTDflES TERMS Acronyms and Abbreviations 89 Sr strontium-89 90 Sr strontium-90 99 Mo molybdenum-99 99 mTc technetium-99m 1 3 1 1 iodine-131 133 Xe 23 4 U m u 23 6 u m u 23g u 23 9Np 239 pu AC ACI ADUN AEF AHS ALARA As ASME Ba BHMA Br BRR CFR C0 2 CSE DBE Discovery Ridge DOE DOT EBC EOI EPDM FDA Fe(S0 3 NH 2)2 H 2 H 2 0 H 3 P04 HEPA HIC HMTA HN0 3 HS0 3 NH 2 HVAC I JCP-MS xenon-133 uranium-234 uranium-235 uranium-236 uranium-237 uranium-238 neptunium-239 plutonium-239 administrative control American Concrete Institute acid-deficient uran y l nitrate active engineered feature ammonium hydroxide solution as low as reasonabl y achievable arsemc American Society of Mechanical Engineers barium Builders Hardware Manufacturers Association bromine BEA Research Reactor Code of Federal Regulations carbon dioxide criticality safety evaluation design basis event Discovery Ridge Re s earch Park U.S. Department of Energy U.S. Department of Transportation equivalent boron content end of irradiation ethylene propylene diene monomer U.S. Food and Drug Administration ferrous sulfamate hydrogen gas water phosphoric acid high-efficiency particulate air high-integrity container hexamethylenetetramine nitric acid sulfamic acid heating , ventilation , and air conditioning iodine inductively coupled plasma mass spectrometry 4-x NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description ICRP IROFS IRU IX Kr LEU MC&A MCNP Mo MOC MURR Na 2 S0 3 NaH 2 P0 4 NaN0 2 NaOCl NaOH Nb NESHAP NH40H NO NO x N0 2 NRC NWMI ORNL OSTR osu Pb PDF QC QRA R&D RCT Rh RPF Ru Sb Se Sn SNM SS SSC TBP TCE Tc Te [Proprietary Information] TMI TRU u U.S. NWM l-2015-021 , Re v. 3 C hapter 4.0 -RPF Desc r ipt i on Internatio n a l Commiss i on o n Radiation P rotection items relie d on for safety i odine removal unit i on exc h ange krypton low-enriched uranium materia l co n tro l and accountability Monte Car l o N-Particle molybdenum materials of constructio n University of Missouri R esearch Reactor sodium su l fite sodium di h ydrogen phosp h ate sodium nitr i te sodium hypoch l orite sodium hydroxide niobium Nationa l E m ission Stan d ards for Hazardo u s Air Pollutants ammonium h ydroxide nitric oxide nitroge n ox i de nitrogen dioxi d e U.S. Nuc l ear Regu l atory Commissio n Northwest Me di cal Isotopes , LLC Oak Ridge Nat i onal Laboratory Oregon State University TRIGA Reactor Oregon State University lead passive design feature quality contro l q u alitative risk ana l ysis research and development radiologica l control technician rhodium Radioisotope Production Fac il ity ruthenium antimony se l enium tin special nu c l ear material stainless stee l structures, systems and components tributyl ph osp h ate trichloroet h y l ene technetium te ll urium [Proprietary Informatio n] total meta lli c impurities transura n ic uranium United States 4-xi UN UNH [Proprietary Information] [Proprietary Information] USP Xe Units o c o p µ µCi µg µm atm Bq BY Ci cm cm 2 cm 3 CV ft ft2 g gal GBq gmol ha hr m. in.2 kg km kW L lb m M m 2 mCi MBq MeV mg m1 min mL mm mo! mR mrem uranyl nitrate uranyl nitrate hexahydrate [Proprietary Information] [Proprietary Information] U.S. Pharmacopeial Convention xenon degrees Celsius degrees Fahrenheit micron . . m1crocune microgram micrometer atmospheres becquerel bed volume cune centimeter square centimeter cubic centimeter column volume feet square feet gram gallon gigabecquerel gram-mo! hectare hour inch square inch kilogram kilometer kilowatt liter pound meter molar square meter millicurie megabecquerel

megaelectron volt milligram mile minute milliliter millimeter mole milliroentgen millirem 4-xii NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description NWMI ...... MT M W nCi r e m ppm pp mpU sec vo l% w wk wt% m etric to n megawatt n a n ocurie roe n tge n e qui va l e nt in m a n p arts per m i ll io n p arts per m i lli o n parts u ra niu m by mass secon d t onne vo l ume p e r cent watt week weight p e r ce nt 4-xiii NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description NWMI ...... ..* ... ..... .. .. .. * !*.* ! ' NOllTHWUT MlOICAl tsOTOIU This page intentionally left blank. 4-xiv NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

4.0 RADIOISOTOPE

PRODUCTION FACILITY DESCRIPTION This chapter describes the Northwest Medical Isotopes, LLC (NWMI) Radioisotope Production Facility (RPF) and the processes within the RPF involving special nuclear material (SNM). The RPF will produce molybdenum-99 (99 Mo) from low-enriched uranium (LEU) irradiated by a network of university research reactor s. The primary RPF operations will include the following:

* * *
Receiving LEU from the U.S. Department of Energ y (DOE) Producing LEU target materials and fabrication of targets Packaging and shipping LEU targets to the university reactor network for irradiation Returning irradiated LEU targets for dissolution , recovery , and purification of 99 Mo Recovering and recycling LEU to minimize radioactive , mixed , and hazardous w a ste generation Treatin g/packagin g wastes generated b y RPF process steps to enable transport to a disposal site This chapter provides an overview of the following:
* *
RPF description Detailed RPF design descriptions Biological shield Processes involving SNM The design description includes the design basis , equipment design , process control strate gy, hazards identification, and items relied on for safety (IROFS) to prevent or mitigate facility accidents.

In addition , the overview provides the name, amount, and specifications (including chemical and physical forms) of the SNM that is part of the RPF process , a list of byproduct materials (e.g., identity , amounts) in the process solutions, extracted and purified products, and associated generated wastes. A detailed description of the equipment design and construction used when processing SNM outside the RPF is also provided. Sufficient detail is provided of the identified materials to under s tand the associ a ted moderatin g, reflecting , or other nuclear-reactive properties. 4-1 NWM I .*.**... * * *

lrlOITHWEST llEDM:Al &SOTOPU 4.1 FACILITY AND PROCESS DESCRIPTION

4.1.1 Radioisotope

Production Facility Summary NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The proposed RPF site is situated within Discovery Ridge Research Park (Discovery Ridge). Discovery Ridge is located in the City of Columbia, Boone County, Missouri. The site is situated in central Missouri, approximately 201 kilometer (km) (125 miles [mi]) east of Kansas City and 201 km (125 mi) west of St. Louis. The site is 7.2 km (4.5 mi) south of U.S. Interstate 70 , just north of U.S. Highway 63 (see Chapter 19.0 , "E nvironmental Review , Figure 19-4). The Missouri River lies 15.3 km (9.5 mi) west of the site. The site is located 5.6 km (3.5 mi) southeast of the main University of Missouri campus. The RPF will support target fabrication, recovery and purification of the 99 Mo product from irradiated LEU targets that would be generated by irradiation in multiple university research reactor s , and uranium recovery and recycle to produce 99 Mo. The RPF site is 3.0 hectare (ha) (7.4-acre) and i s located on property owned by University of Missouri. Figure 4-1 shows the layout of the NWMI site including the RPF. Three adjacent, separate buildings will be located on the site: an Administrative Buildin g (outside of the protected area), a Wast e Staging and Shipping Buildin g for additional Class A waste storage (inside the protected area), and a Diesel Generator Buildin g. These major facilities also receive , sto re/hold , or process chemicals , oil, diesel fuel, and other hazardous and radioactive materials. DISCOVERY RIDGE LOT IS PROPERTY UNE 7.4ACRES P.LCURVE L-584.43' R-JOSS.42' SPACH RESERVED FOR FIRE WA"IBR STORAGE TANK. AND RECEIVER TANK. BERM PARK.ING LOT 32 TOTAL PARK.ING SPACES FllONT SETBACK-J S FEET STEP VAN GUARDHOUSE ADMIN BUilDING FOOTPIUNI" P.LCURVE I..-117.7 R-7 4.30' FllONT SETBACK. -JS FEET BBRM P.L. CURVE I..-3 S9.84' R-IS42.83' flRE WATER PUMP SlClD WASTE MANAGEMENT Bun.DING WASTE MANAGEMENT CANOPY AREA FOR MECHANICAL CHILLER SIDE SETBACK-IS FEET SIDE SET BACK-JS FBET STEP VAN GUARD HOUSE AND VEH!CLB TRAPARl!A GATE(TYPICAL) PARKING LOT 24 TOTAL PARK.ING SPACES SITE PLAN 0 100' 200' Figure 4-1. Radioisotope Production Facility Site Layout 4-2 N

NWM I ...*.. * *.* NORTi fWUT M£otCAl lSOTOl'U NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The building will be divided into material accountability areas that are regulated by Title I 0, Code of Fed e ral R e gulation s, Part 50 (10 CFR 50), "Domestic Licensing of Production and Utilization Facilities ," and 10 CFR 70 , " Domestic Licensing of Special Nuclear Material," as shown in Figure 4-2. The target fabrication area will be governed by 10 CFR 70 , and the remainder of the production areas (irradiated target receipt bay , hot cells , waste management, laboratory, and utilities) will be governed by 10 CFR 50. The administration and support area will provide the main per s onnel access to the RPF and include personnel support areas such as access control , change room s, and office spaces. Figure 4-2 provides a building model view of the RPF. Figure 4-2. Building Model of the Radioisotope Production Facility The first level (excluding the tank pit area) and second levels of the RPF are currently estimated to contain approximately 4,282 square meter (m 2) (46 , 088 square feet [ft2]) and 1 , 569 m 2 (16,884 ft2) of floor space, respectively. The processing hot cell and waste management temporary storage floor space area is approximately 544 m 2 (5 , 857 ft2). The maximum height of the building is 19.8 m (65 ft) with a maximum stack height of22.9 m (75 ft). The depth of the processing hot cell below-grade , without footers , is 4.6 m ( 15 ft) of enclosure height in rooms containing process equipment. The site will be enclosed by perimeter fencing to satisfy safeguards and security and other regulatory requirements. Figure 4-3 is first level general layout of the RPF and presents the seven major areas , including the target fabrication area, irradiated target receipt area, tank hot ce ll area , laboratory area, waste management area , utility area, and administrative support area. Figure 4-4 provides a ground-floor layout of the fac ili ty , including processing , laboratory, and operating personnel support areas and also provides the general dimension of the RPF. Figure 4-5 is a preliminary layout of the second level of the RPF. A mezzanine area above a portion of the process area will be for utility , ventilation and offgas equipment. Figure 4-6 illustrates the hot cell details for target disassembly dissolution , Mo recovery and purification , uranium reco v ery and recycle , and waste management. 4-3 waste management area Irradiated target receipt area , Administration and support area : NW Ml-040132101 10 CFR 70 10 CFR 50 .; .. ; .. NWMI ...... ..* *... ........... . * *.*

NORTlfWEST MEOICAL ISOTOPH [Proprietary Informat io n] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-4. Preliminary Layout of the Radioisotope Production Facility First Level Floor Plan and Associated Dimensions 4-5

.. NWMI ::.**.*.*.* .*.* .. *.* . . * *. * ! .' NOATlfWlST MEOICAL ISOTOl"ES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Fig ur e i s not drawn t o sca l e. Figure 4-5. Preliminary Layout of the Radioisotope Production Facility Second Level Floor Plan [Proprietary Information] Fig ur e is not drawn t o sca l e. Figure 4-6. Radioisotope Production Facility Hot Cell Details 4-6 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

4.1.2 Process

Summary A flow diagram of the primary process to be performed at the RPF is provided in Figure 4-7. The primary purpose of these RPF operations will be to provide 99 Mo product in a safe, economic, and environmentally protective manner. Fresh Blended Uranium Irradiate Targets in Reactor Irrad i ated Target D i sassembly and D i ssolution Target Fabrication

------Leeend

R ea ctor Operations
RPF Op e rations Unorad iated Target Shipping to U niversny Reactors
FiSSK>n Produc t SolutK>n to Liqu id Waste H and'ing ,---------------

0 ' ----: I rradiated Target Shipping arul Receiv i ng ---------------------------.

' ' lmpu(eU Mo Recovery and Purification Puri1ied "Mo Mo Product Packaging Product Gas Shipmen ts 10 Customer 99 Mo Production

Offgas Treatment and Re lease 10 Stack via Pnmary V en iauon Figure 4-7. Radioisotope Production Facility Block Flow Diagram Ta1ge 1 Claddlng to SOiid Waste Handing Facility operation will include the following general process steps (which correspond with Figure 4-7). Target Fabrication 0 LEU tar get material is fabricated using a combination of fresh LEU and recycled uranium. @ Target material is encapsulated using metal cladding to contain the LEU and fission products produced during irradiation. C> Fabricated targets are packa ge d and shipped to university reactors for irradiation. Target Receipt, Disassembly, and Dissolution 0 After irradiation , targets are shipped back to the RPF. 0 Irradiated targets are disassembled and metal cladding is removed. 0 Targets are then dissolved into a solution for proces sing. Molybdenum Recovery and Purification

@ Dissolved LEU solution is processed to recover and purify 99 Mo. *) Purified 99 Mo is packaged in certified shipping containers and shipped to a radiopharmaceutical distributor. 4-7 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Uranium Recovery and Recycle 0 LEU solution is treated to recover uranium and remove trace contamin a nts and is recycled back to Step I to be made into new targets via the target fabrication system. 4.1.2.1 Process Design Basis The process design requirements are identified in NMWI-2013-049 , Pro cess S y st e m Fun c tional Sp ec ifi c ation. The RPF is designed to have a nominal operational processing capability of [Proprietary Information]. The following summarizes key requirements for the RPF and the primary process systems: * * * *

Decay targets more than [Proprietary Information]

end of irradiation (EOI) prior processing Process a tar g et batch within [Proprietary Information] Receive MURR targets nominally [Proprietary Information] EOI Control/prevent flammable gas from reaching lo wer flammability limit conditions of 5 percent hydrogen g as (H 2); design for 25 percent of lower flammability limit Ensure that uranium-235 (235 U) processing and storage meet security and criticality safety requirements The target fabrication function will receive and store fresh LEU from DOE , produce [Proprietary Information] as tar g et material , assemble LEU targets and packages , and ship LEU targets. The overall process functional requirements include: *

Fabricating a [Proprietary Information]

Considerin g target fabrication as a material balance accountability area requiring measurements for SNM The process irradiated LEU targets function will receive , disassemble, and d issolve irradiated targets. The overall process functional requirements include: * * * * * * *

Accepting weekly irradiated targets in [Proprietary Information]

Disassembling irradiated targets to remove the irradiated LEU target material , and containin g fission gases released during target disassembly Dissolving irradiated LEU target material in nitric acid (HN0 3) Providing the capability to transfer dissolved solution to the molybdenum (Mo) recovery and purification system Removin g nitrogen oxides (NO x), as needed , to ensure proper operation of downstream process steps Providing the capability to collect scrubber liquid waste generated during dissolut i on Providing the capability to treat fission gases generated during dissolution Removing radioiodine sufficiently to allow discharge to the stack 4-8

NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Retaining fission product noble gases for a period of time until the gases hav e decayed sufficiently to allow dischar ge to the stack [Propri etary Information]

[Propri etary Information] The Mo recovery and purification function will produce 99 Mo product from the acidified target solution stream. The overall process functional requirem ents include: * * * * * * * *

Providing the capa bility to recovery 9 9 Mo from dissolver solutions at nominally

[Proprietary Information] Providing the capability to stage and transfer dissolver solution to the ion exchange (IX) resin beds Providing the capability to transfer LEU effluent to the U recovery and recycle system Providing the capa bility for 9 9 Mo product packaging and shipping Recovering more than [Proprietary Information] of 99 Mo from the target so lution Removin g radioiodine sufficiently from vessel ventilation to allow discharge to the stack Providing hot cell capability to transfer 99 Mo so lution to a "c lean cell" for an appropriate level of purification per U.S. Food and Dru g Administration requirements Confirming that the 99 Mo product meets the product specifications Shipping the 99 Mo product per 49 CFR 173, "S hipper s -General Requirements for Shipments and Packages" The U recovery and recycle function will recei ve , purify , and recycle U from the Mo r ecovery and purification system. The overall process functional requirements include: * * *

Providing the capability to recover U from the Mo waste so lution Providing the capability to [Proprietary Information]

Providing the capability to dilute the [Proprietary Information] Recovering the U-bearing solution usin g [Proprietary Information] Providin g the ca pabilit y for first-stage IX [Proprietary Information] Ensuring that each concentrator has [Propri etary Inform atio n] Providing [Proprietary Information] The handle waste function will process the waste streams generate d by the fabricate LEU targets, process irradiated LEU targets, Mo recovery and purification , and U recovery and recycle functions. The overall process functional requirements include:

Providing the capability to handle waste generated from processing up to [Propri etary Information]

4-9

* * * * *
4.1.2.2 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Providing the capability to treat, package , and transfer Class A waste t o the separa t e waste storage building prior to disposal Providin g the capability to package waste st reams from all RPF systems Measuring SNM (material accountability) prior to transfer to the waste handlin g syste m Accumulating and segregating waste based on waste type (e.g., Class A, Class C, hazardous waste, chemical compatibility) and/or dose level Providin g the capability to shield the waste storage area in the RPF to deca y waste -to meet shipping and disposal requirement Treating waste to compl y with the disposal facility's waste acceptance c riteria Assaying waste to verify compliance with shipping and disposal limits Summary of Reagent, Product and Waste Streams This section present s a summary of the reagents , byproducts , wastes, and finished product s of the RPF. Figure 4-8 provides a s ummary flow diagram of the reagents , product , and wastes. Trace impurities are identified later in this chapter in Table 4-43 and Table 4-56. [Proprietary Information]

Figure 4-8. Reagents, Product, and Waste Summary Flow Diagram The amount, concentration, and impurities of the rea ge nt, product, byproduct , and waste streams are provided in later sections of this chapter. 4-10 NWMI ...... ' * * ' NORTHWEST MEDICAL l$0TOPCS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.1.2.3 Radioisotope Production Facility Spent Nuclear Material Inventory The SNM invento ry of the RPF is summarized below ba se d on material accountability areas. The target fabrication area i s gove rned by 10 CFR 70 and described by Table 4-1. [Proprietary Information] The dissol ve r proce ss enclos ure will include uranium metal that i s being di sso l ve d to produc e uranyl nitrat e (UN) so lution. Co mposition ranges indicate the va riat io n of so lution compositions pre sent in different vessels at a particular location. Table 4-1. Special Nuclear Material Inventory of Target Fabrication Area Location 8 [Proprietary Information] Dissolver proc ess enc l os ur e Recycled uranium proces s enclosures ADUN co ncentrati on a nd storage process e n c l osures Wash column and drying tray enclosures [P ropr i etary Inform ation] ' ' Form Solid U-metal pieces/LEU target material in sealed containers U-m etal/UNH UNH ADUN [Proprietary Information] L EU target m a t erial in sea l e d targets Concentration [Proprietary Information] [Proprietary Inform a ti on] [Propri e tary Information] [Propri etary Inform ation] [Proprietary Information] [P rop ri etary In fo rm ation] .. [Proprietary Lnforrnation] [Proprietary In fo rm a ti on] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [P roprietary Inform at i on] SNM massh Boundingc , d [Proprietary Information] [Proprietary In fo rmati on] [Proprietary Information] [Propri e t ary In fo rm at i on] [Proprietary Information] [Proprietary Information] l@ffliffbi.f [Proprietary Information] [Propri etary Inform a ti on] [Proprietary Information] [Propri e t ary Inform a ti on] [Proprietary Information] [P ro pri e t ary In fo rm a ti on]

A ll proc ess e n closu r e s and s t orage s yste ms a r e l ocated in th e target fab ric a ti o n proce ss area. b SNM co n ce n tr a tion and m ass repre s e nt t ota l amo un t of LEU (comb in ed 235U a nd 23 8 U at :S I 9.95 wt% 235 U). c [Proprietary In formatio n] d T h e indi ca t ed masse s a r e n o t additive t o d e s c rib e the tota l I 0 CFR 70 area inv e nt ory beca u se m a t erial is transferred from one l ocation t o another durin g a pro cessin g week. [Proprietary In format i on). ADUN LEU N I A SNM ac id deficient uran y l nitrate so l uti o n. l ow-enriched ur a nium. n ot app li ca bl e. s p ecial nu clea r mat er i a l. U uranium. UNH uran y l nitrate h exahy drat e. [P rop ri etary Info rm at i on] = [Proprietary I nformat i on] Bounding and nomin a l SNM inventories are indi ca ted on Ta bl e 4-1 and s h ow n in terms of the equivalent m ass of uranium , independent of the phy s ical form. The boundin g invento ry in each loc at ion is ba se d on the full vesse l capacity and composition of in-process solution.

T he nomin al in ve ntor y is b ase d on the ass umption that storage areas a r e ge nera ll y operated at ha l f capacity to provide a buffer for potential variations in proce ss throughput during normal operation. Summation of the location inventories does not neces sar ily pro v id e an accurate d esc ription of th e total target fa bri ca tion area inventory due to the batch proce ssing operation. Material from one proc ess location is used as input to a s ub se quent loca tion so th at material cannot b e pre se nt in all loc a tion s at the indicated in ven tories under normal operatin g condition s. Irr a diated materi a l a r eas a re governed b y 10 CFR 5 0 and de scri b ed b y T a bl e 4-2. E quipm ent and vesse l s containing SNM will be located in a variety of hot cells within the RPF. Multiple forms are shown for the tar get di ss olution hot ce ll becau se material entering [Proprieta ry Information] to produce UN solution. 4-1 1 .; .. ;. NWMI ...... ..* .... ........... ' *.*

NOllllfWEST MlDtCAl tsOTOPU NWM l-20 1 5-0 21, R ev. 3 Chapter 4.0 -RP F D e s cription Tab l e 4-2. Special Nuclear Material Inventory of Irradiated Material Areas Location Target receipt hot cell Tar get disassembly hot cells* Target dissolution hot ce ll s* Mo recovery and purification hot cells Tank hot cell Mo recovery tank s Impure U co ll ection tanks IX columns and s upport tanks Uranium concentrator

I Uranium concentrator
2 U decay tanks U IX waste tank s High dose liquid accumulationg Solid waste vesselsh .. (Proprietary Information J [Propr i etary In forma ti on] [Proprietary Information J [Proprietary I nformation

] [Proprietary In forma tion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary I nforma tion] [Prop r ietary Information] [Proprietary Information] Concentration [Proprietary Information] [Propr i e t ary Information] (Proprietary Information] [Propr iet ary Information] [Proprietary Information] [Proprietary Information] [Proprietary In fo rm a ti o n] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary In fo rmati o n] [Proprietary Information] [Proprietary Information] SNM massa .. Nominalc , d Boundingb , c [Proprietary [Proprietary [Proprietary Information] Information] Information] [Prop ri e t ary [Propri etary [Propr i etary Information] Information] Information] (Proprietary [Proprietary [Proprietary Information] Information] Information] [Propr i etary [Proprietary [Proprietary In forma ti on] Information] In fo rm a tion] [Proprietary [Proprie ta ry [Proprietary Inform a tion] In forma tion] Information] [Proprietary [Proprietary (Proprietary ln formation] Information] Information] [Proprietary [Propri e t ary [Proprietary In format ion] In formation] Inform a ti on] [Proprietary [P ro prietary [Proprietary Information] In fo rmation] Information] [Proprietary [Propr i etary [Propri etary Inform a tion] Information] Information] [Proprietary [P r oprietary [Proprietary Information] Information J Information] [Prop ri e t ary [Proprietary [Propr i etary In fo rm at ion] In fo rmati o n] Inform a tion] (Proprietary [P ro prietary (Proprietary Information] Information] Information] [Proprietary [Proprietary [Propri etary Information] Information] In format i on]

SNM concentration and mas s r e pre se nt total a mount of LEU (combined 235 U and 238 U 19.95 wt% 235 U). b [Proprietary Informati o n] ' Th e indicated masses are not a dditi ve to describe th e total I 0 CF R 50 area invent ory , as the materi al is transferred from o ne lo ca tion to anoth er durin g a proc essi n g week. d [Proprietary Information].

e [Proprietary In for mation]. r [Proprietary Inform at ion]. g [Proprietary I nform a tion]. h [Proprietary Inform at ion]. IX LEU Mo MURR N I A ion exc han ge. l ow-enriched uranium. mol ybde num. University of Missouri Research R eacto r. not ap plicable. OSTR Oregon State U niver s ity TRI GA R eac tor. SNM s peci a l nuclear m a terial. U uranium UNH uran y l nitrate hexahydrat e so lution [Propriet ary Information] = [Proprietary Information] [Proprietary Information]. A more detailed description of the vesse l volume and composition ranges is described in Section 4.4.1.4. 4-12 .... ;. NWMI ...*.. .. .... ........ *. *.* NOmfW($T M(DM:Al tsOTDl'U NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Summation of the location inventories does not necessarily provide an accurate description of the total irradiated material area inventory due to the bat c h processing operation. Material from one proces s location is used as input to a subsequent location such that material cannot be present in all locations at the indicated inventories under normal operating conditions. 4.1.2.4 Radioisotope Production Facility Anticipated Maximum Radionuclide Inventory The anticipated radionuclide inventory in the RPF is based on [Proprietary Information]. The maximum radionuclide inventory is based on the accumulation in the various systems dependent on the process material decay times , as noted in Table 4-3. Table 4-3 provides the calculated radionuclide inventory (curies [Ci]) for the different process streams in the RPF. The radionuclide inventory values are discussed further in the Radiological Hazards (Sections 4.3.x.5) subsections of each RPF process area. Table 4-3. Radio nu clide Inventory for Radioisotope Prod u ction Facility Process Streams System Target disso l ution Mo feed tanks U syste m Mo system Mo waste tank Offgas system* Hi g h-dose waste tank sc Uranium recycled [Proprietary Inform ation] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] Time (hr EOI) [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

Offgas system radionuclide inventory is ba se d on NWMl-2013-CALC-O 11 b to account for accumu l ation of isotope buildup in th e offgas system [Proprietary Lnform atio n]. b Material deca y time is ba se d on the total equilibrium in-process in ventory , as des cr ib ed in NWM I-2013-CALC-O 11 , Source T e rm Ca l cu lati ons, Rev. A , Northwest Medical Isotopes, LLC , Corva lli s, Oregon , 2015. EO I HIC IX c [Proprietary Information].

d [Proprietary Inform atio n]. end of irradiation. high-int eg rity container. ion exchange. Mo u 4-13 mol y bdenum. uranium. .. ;.:; .. NWMI ..... ........ *. *

MOllntWlST
DK:AL tSOTOl'lS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-9 shows the anticipated radionuclide inventory and provides a color key indicating the amount of curies for the different process areas depending on the EOI. [Proprietary Information]

Figure 4-9. Radioisotope Processing Facility at 0 to 40 Hours End of Irradiation Figure 4-10 shows the anticipated maximum radionuclide inventory in the RPF at the completion of processing [Proprietary Information]at an operation time greater than 40 hr EOI. [Proprietary Information] Figure 4-10. Radioisotope Processing Facility at Greater than 40 Hours End oflrradiation 4-14 NWM I ...... ' *.*

NORTHWEST MEDICAL ISOTOl"ES

4.1.3 Process

Overview 4.1.3.1 Target Fabrication 4.1.3.1.1 Target Fabrication Process Overview NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF D escription The target fabrication process centers on the production of LEU target mat e rial that will be ge nerated through an [Proprietary Information], which will s ubsequently b e loaded into aluminum target elements. The LEU feed for the [Propriet ary Information] will be chilled uranyl nitrat e and consist of a combination o f fresh LEU, reco vere d recycled LEU, and LEU recovered from the proces si ng of irradiated tar gets. The [Proprietary Information]. The aluminum target components will be cleaned, and then a target subassembly will b e welded and loaded with LEU target material. This target subassembly will subsequently be filled with a helium or air cover gas and sea led by welding on the remainin g hardware end cap. The completed tar gets will be inspected and quality checked usin g a process sim ilar to that performed for commercial nuclear fuel. The targets will then be shipped back to the reactor si tes for irradiation. The target fabrication process will begin with the receipt of fresh uranium from DOE , tar get hardware , and chemica l s associated with microsphere production and target assembly. [Proprietary Information] The target hardware components wi ll be cleaned, a nd a target subassembly wi ll be welded an d loaded with [Proprietary Information] LEU target material by means of a vibratory target loadin g asse mbly. This target subassembly will subsequently be filled with helium or air cover gas an d sealed b y welding on the remaining hardw are end cap. The completed targets wi ll then be inspected and qua l ity checked. A simplified tar get fabrication di agra m is shown in Figure 4-11. The figure shows the fresh and rec y cled L EU feeds and the chemical reagents that will be used to produce the target material. The target assembly steps are summarized in the flow diagram and shown in more detail in Figure 4-12. Target fabrication subsystems will include the following:

Fresh uranium dis s olution
Nitrate extraction
ADUN concentration
[Proprietary Information]
[Proprietary Information]
[Proprietary Information]
Target fabrication waste
Target assembly
LEU storage Section 4.4.2 provides further detail on the target fabrication system. 4-1 5

[Propri etary In formatio n] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-11. Target Fabrication Block Flow Diagram 4-16 [Proprietary Information] Figure 4-12. Target Assembly Diagram 4-17 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.1.3.1.2 Target Fabrication Physical Location The target fabrication area will be located as shown in the area outlined in ye llow in Figure 4-13. Additional information on the la yo ut of the equipment and s ubs ys tems for the target fabrication system i s provided in Section 4.1.4.4. [Proprietary Information] Figure 4-13. Target Fabrication Location 4.1.3.1.3 Target Fabrication Process Functions The primary system functions of the target fabrication system include: * * *

Storing fresh LEU, LEU target material , and new LEU targets Producin g LEU target material from fresh and recycled LEU material Assembling, loading , and fabricating LEU targets Minimizin g uranium lo sses through the target fabrication system 4.1.3.l.4 Target Fabrication Safety Functions The target fabrication syste m wi ll perform safety functions that provide protect i on of on-site and off-site per sonne l from radiological and other industrial related hazard s b y: * *
Preventin g criticality within the target fabrication system Preventin g flammable gas composition within the target fabrication system Limiting personnel exposure to hazardous chemicals and offgases 4-18

.. NWM I ... ' * *. *

NOllTKWEST ME.OiCA l ISOTOPU 4.1.3.2 Target Receipt and Disassembly 4.1.3.2.1 Target Receipt and Disassembly Overview NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The target receipt and disassembly process will be operated in a batch mode, s tarting with receipt of a batch of targets inside a shipping cask. The targets wi ll be disassembled one at a time, and the irradiated LEU target material will be transferred to a dissolver.

A simplified target receipt and disassembly flow diagram is shown in Figure 4-14. *

Empty ** Target transfer to hot cell shipping cask -------------------'

return Le ge n d: -I nputs O u tput -Process -W a ste ma n agement Figure 4-14. Target Receipt and Disassembly System Flow Diagram The target receipt and disassembl y subsystems will include the following:

*
Cask receipt Target receipt Target disassembly 1 Target disassembly 2 Target material dissolution 1 or2 N W M l*04115r02 Target hardware waste The trailer containing the shipping cask will be positioned in the receipt bay , and the truck will be d is connected from the trailer and exit the facility via the high bay doors in which it entered. The shipping cask will first be checked for radiological contamination prior to further cask unloading activities.

Operators will remove the shipping cask's upper impact limiter. The operators will then use the facility overhead crane (TD-L-100) to lift and locate the shipping cask onto the transfer cart. The powered transfer cart will transfer the shipping cask into the cask preparation airlock. The cask air space will be sampled and the cask lid removal. Operators will raise the cask using the [Proprietary Information] shipping cask lift to the transfer port sealing surface of the target receipt hot cell. The port will be opened and the shielding plug removed. The target basket will be retrieved and placed in one of two basket storage location in the target receipt hot cell. Two target disassembly stations will be provided. Individual targets will be transferred from the target receipt hot cell into either of the target disassembly hot cell for processing. The targets will be disassembled, and the irradiated target material collected. The target material container will be filled with the contents of the targets and then physically transferred to the dissolver hot cell. Sections 4.3.2 and 4.3.3 provide further detail on the target receipt and disassembly process. 4.1.3.2.2 Target Receipt and Disassembly Physical Location The target receipt and disassembly hot cells will be loc ated along the rows of the processing hot cells within the RPF. The target receipt , target disassembly 1 , and target disassembly 2 subsystems will be lo cated in the tank hot cell. The subsystem locations are shown in Figure 4-15. 4-19 .;.-.;. NWMI ...... ..* .. .*.* .. *.*. NOflTHWt:STMEDICALISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-15. Target Receipt and Disassembly System Facili ty Location 4.1.3.2.3 Target Receipt and Disassembly Process Functions The functions of the target receipt and disassembly system include: * * *

Handling the irradiated target shipping cask, including all opening , clo s ing, and lifting operations Retrieving irradiated targets from a shipping cask Disassembling targets and retrieving irradiated target material from tar g ets Reducing or eliminating the buildup of static electricity wherever targe t material i s handled 4.1.3.2.4 Target Receipt and Disassembly Safety Functions The target receipt and disassembl y system will perform safety functions that provide protection of on-site and off-site personnel from radiological and other industrial related hazards by: * * * *
Providing radiological shielding during target handling Preventing inadvertent criticality through inherently safe design of the target receipt and disassembly equipment Preventing radiological release during shipping cask and target handlin g Maintaining positive control of radiological materials (irradiated target ma t erial and ta r get hardware)

Protecting personnel and equipment from industrial hazards associated with the system equipment, such as moving parts, high temperatures, and e l ectric shock 4-20 4.1.3.3 Target Dissolution 4.1.3.3.1 Target Dissolution Process Overview NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The target dissolution hot cell operations will begin with transfer of the collection containers holding irradiated LEU target material from the target disassembly hot cells. A dissolver basket will be filled with the LEU target material and then be lowered into place in the dissolver assembly via the open valve. After loading the dissolver basket into the dissolver assembly, the valves will be closed in preparation for the start of dissolution. The LEU target material will be dissolved in hot nitric acid. The off gas containing the fission product gases will go throu gh a series of cleanup columns. The NO x will be removed by a reflux condenser and several NO x scrubbers, the fission product gases (noble and iodine) captured, and the remaining gas filtered and discharged into the process ventilation header. The dissolver solution will be diluted , cooled, filtered, and pumped to the 9 9 Mo system feed tank. Only one of the two dissolvers is planned to be actively dissolving LEU target material at a time. A simplified target dissolution diagram is shown in Figure 4-16. The target dissolution subsystems will include the following:

* *
Target dissolution 1 Target dissolution 2 NO x treatment 1 NO x treatment 2 * * *
Pressure relief Primary fission gas treatment Secondary fission gas treatment Waste collection

[Proprietary Information] Figure 4-16. Simplified Target Dissolution Process Flow Diagram Section 4.3.4 provides further detail on the target dissolution system. 4-21 .; ... ;. NWMI ..**.. .. *.. .......... . *.*

NOlllfWUT MEotCAL ISOTOPH 4.1.3.3.2 Target Dissolution Physical Location NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The target dissolution I and target dissolution 2 subsystems will be located alo n g the rows of the processing hot cells within the RPF. The NO x treatment I, NO x treatment 2, pressure relie f , primary fission gas treatment, and waste collection subsystems will be located in the tank hot cell. The subsystem locations are shown in Figure 4-17. [Proprietary Information]

Figure 4-17. Target Dissolution System Facility Location 4.1.3.3.3 Target Dissolution Process Functions The target dissolution system functions will provide a means to: * * * *

Receive the collection containers holding recovered LEU target material Fill the dissolver basket with the LEU target material Dissolve the LEU target material within the dissolver basket Treat the offgas from the target dissolution system Handle and package solid waste created by normal operational activities 4.1.3.3.4 Target Dissolution Safety Functions The target dissolution system will perform safety functions that provide protection of on-site and off-site personnel from radiological and other industrial related hazards by:
Providing radiological shielding during target dissolution activities 4-22 NWM I ..**.. * *
NOATHWHT MEDICAL ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description
* *
4.1.3.4 Preventing inadvertent criticality through inherently safe design of the target dissolution equipment Preventing radiological materials from being released during target dissolution operations to limit the exposure of workers, the public, and environment to radioactive material Maintaining positive control ofradiological materials (LEU target material and radiological waste) Protecting personnel and equipment from industrial hazards associated with the system equipment such as moving parts, high temperatures , and electric shock Molybdenum Recovery and Purification 4.1.3.4.1 Molybdenum Recovery and Purification Process Overview Acidified dissolver solution from the target dissolution operation will be processed by the Mo recovery and purification system to recover the 99 Mo. The Mo recovery and purification process will primarily consist of a series of chemical adjustments and IX columns to remove unwanted isotopes from the Mo product solution.

Product solution will be sampled to verify compliance with acceptance criteria after a final chemical adjustment. The product solution will then be placed into shipping containers that are sequentially loaded into shipping casks for transfer to the customer. Waste solutions from the IX columns will contain the LEU present in the incoming dissolver solution and transferred to the LEU recovery system. The remaining waste solutions will be sent to low-or high-dose waste storage tanks. A simplified Mo recovery and purification diagram is shown in Figure 4-18. [Proprietary Information] Figure 4-18. Simplified Molybdenum Recovery and Purification Process Flow Diagram Mo recovery and purification subsystems will include the following:

Primary ion exchange Secondary ion exchange *
Tertiary ion exchange Molybdenum product Section 4.3.5 provides further detail on the Mo recovery and purification process system. 4.1.3.4.2 Molybdenum Recovery and Purification Physical Location The primary IX , secondary IX , tertiary IX , and Mo product subsystems will be located in the tank hot cell within the RPF. The subsystem locations are shown in Figure 4-19. 4-23 l

NWM I ......

NOITMWHT MmlCAl tS01WU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

[Proprietary Information] Figure 4-19. Molybdenum Recovery and Purification System Facility Location 4.1.3.4.3 Molybdenum Recovery and Purification Process Function The Mo recovery and purification system will provide programmatic system functions , including the fo ll owing two main functions:

Recovery of Mo product from a nitric acid so luti on created from dissolved irradiated uranium targets Purification of the recovered Mo product to reach specified purity requ i rements, fo llowed by s hipment of the Mo product The high-dose nitri c acid so lu tion create d from dissolved irradiated uranium targets, a lon g with the dose Mo product solution, will require that all functions be carried out in a remote environme nt that includes the containment and confinement of the material.

4.1.3.4.4 Molybdenum Recovery and Purification Safety Functions The Mo recovery and purification system will perform safety functions that provide protection of on-site and off-site personnel from radiological and other industrial related h azards by: *

Preventing inadvertent critica lity through inherently safe design of components that could handle high-uranium content fluid Preventing radiological materials from being released by containing the fluids in appropriate tubing, valves , and other compo nents 4-24

..... NWMI "!:**:*:* ...... ' *

NOIT H WEST MEDICAL llOTOPH NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description
4.1.3.5 Maintaining positive control of radiological material s (99 Mo product , intermediate st reams , and radiological waste) Providin g appropriate containers and handling systems to protect personnel from industrial h aza rd s such as chemical exposure (e.g., nitric acid , caustic, etc.) Uranium Recovery and Recycle 4.1.3.5.1 Uranium Recovery and Recycle Process Overview The U recovery and recycle system will proces s aqueous LEU so lutions genera ted in the Mo recovery and purification system to separate unwanted radioisotopes from uranium. Uranium will be separate d from the unw a nted radioisotopes usin g two IX cycles. A concentrator will be provided for the uranium-bearing so lution as part of each IX cycle to adjust the LEU solution uranium concentration.

Vent gases from proce ss vessels will be treated by the process vessel vent system prior to merging with the main facility ventilation system and release to the environment. Recycled uranium product is an aqueous LEU solution that wi ll be tran sferre d to the tar get fabrication system for use as a source to fabricate new reactor targets. Waste ge nerated b y the U reco very and recycle system operation will be transferred to the waste handlin g system for solidification, packaging , and shipping to a disposal s ite. A s implified U recovery and rec ycle di agra m is s hown in F igure 4-20. The U recovery and recycle s ubsystems will include the following:

* *
Impure uranium collection Primary ion exchange Primar y concentration Secondary ion exchange Secondary concentration
*
Ura nium recycle Uranium decay and accountability Spent ion exchange resin Waste collection

[Propr ietary Information] Figure 4-20. Simplified Uranium Recovery and Recycle Process Flow Diagram 4-25 ..... ;. NWMI ...... ..* ... .......... ' NOtnHWUT MEOfCAl ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.1.3.5.2 Uranium Recovery and Recycle Physical Layout The U recovery an d recycle system equipment will be located in the tank hot cell, as shown in Figure 4-21. [Proprietary Information] Figure 4-21. Uranium Recovery and Recycle System Location 4.1.3.5.3 Uranium Recovery and Recycle Process Functions The U recovery and recycle structures, systems and components (SSC) will be housed within the RPF process facility, and rely on shielding and confinement features of that facility for confinement of radioactive materials , shielding, worker safety, a nd protection of public safety. The U recovery and recycle system will provide the following programmatic system functions: *

Receive and decay impure LEU solution -This sub-function will collect the aqueous solutions containing U and other radioisotopes from the Mo recovery and purific a tion system and provide a [Proprietary Information]

in preparation for the purification proce ss (NWMI-2013-049, Section 3 .6.1 ). Recover and purify impure LEU solution -This sub-function will separate uranium from unwanted radioisotopes present as other elements in the decayed impur e uranium so lution (NWMI-2013-049, Section 3.6.2). 4-26

NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Decay and recycle LEU solution -[Proprietary Information] (NWMI-2013

-04 9, Section 3.6.3) . Transfer process waste -This sub-fun ction will provide storage and monitoring of process wastes prior to transfer to the waste handling system. 4.1.3.5.4 Uranium Recovery and Recycle Safety Functions The U recovery and recycle system will perform safety functions that provide protection of on-site and off-site personnel from radiological and other industrial related hazards by: * * * * *

4.1.3.6 Providing radiological shielding during U recovery and recycle system activities Preventing inadvertent critica lity through inherently safe design of the U recovery and recycle equipment Preventing radio lo g ical release during U recovery and recycle system activities Controlling and preventing flammab le gas from reaching lower flammability limit cond ition s Maintainin g positive control of radiological materials Protecting personnel and equipment from industrial hazards associated wit h the system equipment , such as moving parts, high temperatures, and electric s hock Waste Handling 4.1.3.6.1 Waste Handling System Process Overview The waste handling system will consist of three subsystems:

(1) liquid waste system, (2) solid waste system , and (3) specialty waste system. The liquid waste system will consist of a group of storage tanks for accumulating waste liquids and adjusting the waste composition. Liquid waste wi ll be split into dose and low-dose streams by concentration. The high-dose fraction composition will be adjusted and mixed wit h adsorbent material in high-integrity conta in ers (HIC), stored, and loaded into a shipping cask for disposal. A portion of the lo w-dose fraction is expected to be suitab l e for recycle to selecte d hot cell systems as process water. Water that is not rec yc led wi ll be adjusted and then mixed with a n adsorbent material in 55-gallon (ga l) drum s. The so lid waste disposal system will consist of an area for collect ion , size-redu ction, and staging of solid wastes. The solids will be placed in a 208 L (55-gal) waste drum a nd encapsulated by adding a cement material to fill voids remaining within the drum. Encaps ula ted waste will be stored until the drums are lo aded into a shipping cask and transported to a disposal site. A s pecialty waste disposal system wi ll deal with the small quantities of unique wastes ge nerated by other processes. The following are examples of these processes: * *

A reclamation process to recycle organic solvent [Proprietary Information]

Operation of a trichloroethylene (TCE) reclamation unit All waste streams will be containerized, sta bili zed as appropriate , and s hipp ed offsite for treatment and disposal. 4-27 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The high-dose and low-dose liquid waste operations are shown in Figure 4-22 and Figure 4-23. Chapter 9 , "Auxiliary Systems," Section 9.7 provides details on the waste handling system processes. [Proprietary Information] Figure 4-22. High-Dose Liquid Waste Disposition Process [Proprietary Information] Figure 4-23. Low-Dose Liquid Waste Disposition Process 4-28 4.1.3.6.2 Waste Handling System Physical Layout NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The location of the waste handling systems is shown in Figure 4-24 and Figure 4-25. The liquid waste tanks will be located in the tank hot cell, and the waste solidification and container handling activities will take place in the waste management area. This area will include the waste management loading bay , the low-dose waste area , and the HIC storage area in the basement (Chapter 9.0 , "Auxiliary S y stems," provides additional details). [Proprietary Information] Figure 4-24. Waste Handling Locations 4-29

";" NWM I ........ ** NOmrWEST MUMC.Al tsOTIWU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The low-dose liquid waste evaporation equipment arrangement located on the mezzanine level is shown in Figure 4-25. [Proprietary Information]

Figure 4-25. Low-Dose L i quid Waste Evaporation Facility Location 4.1.3.6.3 Waste Handling System Process Functions The waste handling system will provide the capability for: * * * * *

Transferring liquid waste that is divided into high-dose source terms and low-dose source terms to lag storage Transferring remotely loaded drums with high-activity solid waste via a solid waste drum transit system to a waste encapsulation area Loading drums with low-dose liquid waste Loading HI Cs with high-dose liquid waste Solidifying high-dose and low-dose liquid waste drums or containers Encapsulating solid waste drums Handling and loading a waste shipping cask with radiological waste drums/containers 4-3 0 NWM I ..*... ' * * ! ' NORTHWEST MfOltAl ISOTOPES NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description 4.1.3.6.4 Waste Handling Safety Functions The waste handling system will perform safety functions that provide protection of on-site and off-site personnel from radiological and other industrial related hazards by: * *
4.1.4 Maintaining uranium solids and solutions in a non-critical inventory or composition to eliminate the possibility of a criticality Preventing spread of contamination to manned areas of the facility that could result in personnel exposure to radioactive materials or toxic chemicals Providing shielding , distance , or other means to minimize personnel exposure to penetrating radiation Facility Description This subsection describes the RPF construction and functions, beginning with discussions of the general construction and facility ventilation , followed by descriptions of the RPF areas. The RPF will be divided into seven areas with generally different functions, as shown in Figure 4-26. area t Irradiated target receipt area Administration and support area Figure 4-26. Radioisotope Production Facility Areas 10 CFR 70 10 CFR 50 Table 4-4 provides a crosswalk of the seven different areas with the primary functions and primary systems. 4-31

.; .. ;. NWMI ...... .. ... .......... *.* ! ' NOllTifWEST MfDtCAL ISOTOPE I N WMl-2015-0 21 , Rev. 3 Chapte r 4.0 -RPF Description Table 4-4. Radioisotope Prod u ction Facility Area Crosswalk Area (room designator) Target fab ri ca ti on (T) Ir r a d iate d t a rget rece ip t bay (R) Hot cell (H o r G<) Waste management (W) Lab o rat o ry (L) Utility (U) Administrati o n a nd s u p port (S) Primary functions Fabricate LEU targets Process irradiated LEU targets Proce ss irradi ate d L EU targets Recover and purify 99 Mo product Recover and rec y cle L E U solution Hand l e waste Handle waste Support systems Support sys tem s Support systems Primary systems -..

Tar ge t fabrication (TF) 10 CFR 70*
Mat e rial handling (MH)
Material hand l ing (MH) 10 CFR SOb
Target receipt and disassembly (TD)
Tar ge t receipt and di sasse mbl y (TD) 10 CFR SO b
T arge t di sso lution (OS)
Molybdenum recover and purification (MR) 10 CFR SOb
Uranium recov e r y and recycle (UR) 10 CFR SOb
Waste handling 10 CFR SOb
Waste h a ndlin g (WH) 10 CFR SO b
Mat er ial handlin g (MH)
Chemical supply (CS) 10 CFR SOb
Gas supply (GS)
Material handling (MH)
Normal facility electrical power 1 0 CFR SOb
Proce ss uti li ty sys tem s
Facility ventilation systems
Facility process control and communications (FPC) N I A
Fire protection (FP)
Radiation protection
Safeguards and security
I 0 CF R 7 0 , " D o m es tic Licensing of Special N ucl ea r Material," Code of Federal R egu l atio n s, Office of the Federa l Re giste r , as amended. b I 0 CFR 50 , "Do m es tic Licensing of Produ c tion and U tiliz a tion Facilities

," Code of Federal R egu l at i ons, Office of th e Federal Re g ister , as amended. c H indicates a h ot cell , G indi ca tes a hot ce ll oper ator ga llery , or other room that may be occ upi e d. 99 Mo mo l y bdenum-99 N I A = not applicable. L EU = low-enric h e d uranium. 4. 1.4.1 General Construction This section describes the facility construction that is not part of the force-resisting systems (described in Chapter 3.0, "Design of Structures, Systems, and Components," Section 3.2) or the fire-rated wall construction (described in Chapter 9.0 , Section 9.3). 4.1.4.1.1 B u ilding Envelope Roofing -The low-slope roofing will be single-ply EPDM (ethylene propylene diene monomer) rubber over a cover board with two layers of polyisocyanurate insulation. This material will provide continuous insulation with an R-value of25. The entire assembly wi ll be fu ll y adhered to meet design wind-uplift loads. The metal building portion of the roof over the truck receiving bays will be metal standing-seam roofing with Rl 9 batt insulation between purlins , and Rl 1 batt insulation on a vapor barrie r liner under the purlins on a linear support system. The insulation liner will be a white, rein fo rced pol y propylene material with a less than 75 flame-s pread rating and less than 450 smoke-devel o ped ratin g. 4-32 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Wall cladding -The wall cladding system will be insulated metal wall panels attached over sub-girts to the structural backup wall system. The cladding will provide a primary weather barrier and insulation. The backup wall will be treated with a liquid-applied membrane product to provide an air, vapor, and water barrier. The cavity at the top of the wall will be sealed to the roofing system through a transition membrane that will maintain the continuity of the air barrier. Subgrade walls and slab will be treated with continuous waterproofing that will also provide a vapor barrier. The walls will be covered with a drainage medium to relieve hydrostatic pressure and closed-cell insulation to minimize heat loss and protect the waterproofing and drainage medium during placement of backfill. Windows -Windows will be limited to the administration and support area and the outer walls of the stair towers. Windows will be fixed (non-operable) and designed to resist design wind loads and driven missiles in ASCE 7 Minimum Design Loads for Buildings and Oth e r Structur e s , requirements. A heavy aluminum curtain wall system with thermal break will support the glass. Glass will be insulating units , each comprising a transparent , laminated inner pane, airspace, and outer pane of tinted, lo w-e coated , heat strengthened , or fully tempered glass. 4.1.4.l.2 Interior Construction Ceilings -The ceilings in the office , conference , break rooms, locker room, and corridors in the administration and support area will be suspended acoustical panels on a prefinished grid system. Restroom ceilings will be painted gypsum wallboard. Shower ceilings will be ceramic tile on gypsum tile backer. Ceilings in the production areas (e.g., target fabrication , utility , laboratory , waste management , and irradiated target receipt areas) requiring radiation control , decontamination , or cleaning and disinfecting will be gypsum board wit h a scrubbable resinous finish. Ceilings in the production areas without radiation contro l or disinfection concerns will be exposed structure with a paint finish. Partitions -Partitions in the administration and support area will generally be steel stud framing with gypsum wallboard cladding and a commercial-grade paint finish. Partitions in the production areas will be cast-in-place concrete for structural wa ll s and either concrete masonry unit or metal stud walls for internal partitions. Where radiation control or cleaning and disinfecting are required, the finish will consist of gypsum board c l adding with resinous paint finish over the backup wall on furring. In wet areas , a high-build resinous finish will be applied directly to the walls. Floors -In production areas where cleanliness is required , the floor finish will be a trowel-grade, chemical-resistant resinous system with integral cove and wall base. The floor finish in the truck bays and material transport areas will be an industrial, concrete hardener, densifier, sea l er system to provide durability against wear and impact , prevent contamination penetration , and provide long-term appearance retention. The floor finish in corridors, utility rooms , and rooms not subject to water or radiological contamination will be sealed concrete. Doors in high-traffic areas such as restrooms , locker rooms , stairs , and airlock will be fiberglass doors for maximum durability. Other doors exposed to light traffic in the administration and support area will be Level 2 (I 8-gauge) hollow metal with a durable paint finish. Doors exposed to light traffic in the production area will be Level 3 (I 6-gauge) galvanized hollow metal with an industrial paint finish. All high-traffic doors to work areas will have vision lights for safety. Door hardware will be Builders Hardware Manufacturers Association (BHMA) Grade I. Where avai l able , hardware will have a brushed stainless-steel finish for durability and resistance to chemical exposure. Otherwise , the finish wi ll be brushed chrome plate , except closer covers , which wi ll have an alum inum paint finish. High-frequency and security doors will have full-height, continuous geared hinges. Other doors will have mortised, friction hinges , with mortise locksets and rim exit devices. Closers will be adjustable for closing force and size. 4-33 4.1.4.2 Site and Facility Access NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Vehicular and personnel access to the site and personnel access within the facil i ty will be contro ll ed as part of the physical security requirements. Additional information on the site and facility a ccess is provided in the NWMI RPF Physical Security Plan (Chapter 12.0 , "Conduct of Operations ," Appendix B). 4.1.4.3 Facility Ventilation The facility ventilation system will maintain a series of cascading pressure zones to draw air from the cleanest areas of the facility to the most contaminated areas. Zone IV will be a c l ean zone that is independent of the other ventilation zones. Zone III will be the cleanest of the potentially contaminated areas , with each subsequent zone being more contaminated and having lower pressures. Table 4-5 defines the venti l ation zone applicable to major spaces. A common supply air system will provide 100 percent outdoor air to all Zone III areas and some Zone II areas that require makeup air in addition to that cascaded from Zone III. Three separate exhaust systems will maintain zone pressure differentials and containment:

*
Zone I exhaust system will service the hot cell, waste loading areas, target fabrication enc losur es, and process offgas subsystems in Zone I Zone II/III exhaust system will service exhaust flow needs from Zone II and Zone III in excess of the flow cascaded to interior zones A laboratory exhaust system will service fume hoods in the laboratory area. The supply air will be conditioned using filters , heater coils, and cooling coils to meet the requirements of each space. Abatement technologies (primarily high-efficiency particulate air [HEPA] filtration and activated carbon) will be used to ensure that air exhausted to the atmosphere meets 40 CFR 61, "National Emission Standards for Hazardous Air Pollutants" (NESHAP) and applicable State law. A stack sampling system will be employed to demonstrate compliance with the stated regulatory requirements for exhaust. Table 4-5. Facility Areas and Respective Confinement Zones Area Hot cells (production)

Tank hot cell Solid waste treatment hot cell High-dose waste solidification hot cell Uranium decay and accountabi lit y hot cell HlC vault Analytical laboratory gloveboxes R&D hot cell laboratory hot cells Target fabrication room and enc l osures Utility room Ana l ytical laboratory room and hoods R&D hot cell laboratory room and hoods Waste loading hot cell Maintenance ga ller y Manipulator maintenance room Exhaust filter room Air lock s* Irradiated target basket receipt bay Waste l oading truck bay Operating gallery and corridor E l ectrical/mechanical supply room Chemical supply room Corridors Decontamination room Loading docks Waste management loading bay Irradiated target receipt truck bay Maintenance room Support staff areas *+!.!* I II II II II II II II , Ill III Ill III Ill Ill Ill III IV IV IV IV JV

Confinement zone of airlocks will be dependent on th e two adjacent zones bein g connected.

HIC high-integrity container. R&D = research and development. The systems and components of the facility ventilation system are described in Section 9.0, Section 9.1. 4-34 ... .. NWMI ..... .......... * * ' NOllTHWHT M£DtcAl JSOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The process offgas subsystem will be connected directly to the process vessels and will maintain a negative pressure within the vessels. Process vessel ventilation systems will include a set of subsystems that are specialized to the equipment that the subsystems support. These systems will merge together at the process offgas filter train prior to merging with the Zone I exhaust system. Each process offgas subsystem will treat the process offgas components separately to prevent mixing of waste constituents. The process offgas systems are described in Section 4.2.5. 4.1.4.4 Target Fabrication Area Target fabrication rooms will contain target fabrication equipment and support the target fabrication system. Material processed by the system will be unirradiated LEU obtained as feed from DOE and rec ycle d LEU from processing irradiated targets. Recycled LEU will be purified in the remote hot cell and transferred as a solution to the target fabrication tanks. Verification measurements on the recycled LEU so lutions will confirm that the LEU material can be handled without shie lding. Figure 4-27 illu strates the la yo ut of the target fabrication rooms. The function of each room in the target fabrication area is sum marized in Table 4-6. [Proprietary Information] Figure 4-27. Target Fabrication Area Layout Table 4-6. Target Fabrication Area Room Descriptions and Functions (2 pages) Room name ... TIO! Fresh L EU and 14 7 unirr adiated s hippin g and rec eiv in g Tl03 Target fabrication airlock 139 TI 04A Target fab rication room 1445 Tl04B Target fabrication room 920 IV III II II 4-35 Room functions/features

Shipping bay an d truck lo ading dock for unirradiated target s hippin g Receiving ba y and truck unloadin g dock for fresh LEU receipt
Separates the Zone IV ventilation of Room Tl 01 and Zone II ventilation of Room TI04A
Shipping and receiving area within the target fabrication room
Staging area for incoming and outgoing s hippin g containers
Target assembly activities from [Proprietary Information]

through welded LEU target quality checks .. NWM I ..... .... .... .. * *

HOllTHWEST MEotW rsonwu NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-6. Target Fabrication Area Room Descriptions and Functions (2 pages) -Room name ... Room functions/features TI 04C Target fabrication room 1748 65 225 II IV II * [Proprietary Information]

Tl05 Water entry #2

Fire riser room [Proprietary

[Propri eta r y Information] Information]

[Proprietary Information]
[Proprietary Inform atio n] * [Proprietar y Information]

LEU = low-enriche d uranium. = uranium trioxide. The target fabrication rooms will include the following.

* *
Room Tl 01 (Fresh LEU and unirradiated shipping and receiving)

-Room TI 0 I is the truck loading and unloading dock that will support target fabrication shipping and receiving. The exterior wall material is undefined. The interior walls will be 1-and 2-hr fire-rated partition walls. Fresh uranium will be unloaded in ES-3100 shipping containers by pallet jacks and transported immediately through Room Tl03 to [Proprietary Information]. Sealed t argets will enter the loading dock from Room Tl 03 in ES-3100 shipping containers and immediately be loaded onto the truck. Room Tl03 (Target fabrication airlock) -Room Tl 03 is the airlock that will separate the Zone II ventilation of Room Tl04C from the Zone IV ventilation of Room TIOI. The walls will consist of concrete shear wall and 1-and 2-hr fire-rated partition walls. Fresh uranium in ES-3100 shipping containers will be transported through the airlock on pallet jacks from Room TlOl to Room Tl04A. Sealed targets in ES-3100 shipping containers will be transported through the airlock on pallet jacks from Room Tl04A to Room TlOl. Room T104A (Target fabrication room) -Room Tl 04A is part of Room Tl 04 , and no dividing wa ll s will separate the room from Room Tl 04B. The north wall will be an exterior concrete wall. The west wall and parts of the so uth wall wi ll be 2-hr fire-rated interior partition walls; the remaining south wall will be an interior partition wall. This room will support shipping and receiving activities, and staging for incoming and outgoing shipping containers. [Proprietary Information]. Room Tl04C will provide the main personnel access point. Room T104B (Target fabrication room)-Room Tl04B is part of Room Tl04, and no dividing walls will separate the room from Rooms Tl 04A and Tl 04C. The north wall will be an exterior concrete wall, and the south wall will be an interior concrete wall. This room will support target assembly activities from [Proprietary Information] through tar ge t quality checks. Other activities within this room will include receipt and disassembly of off-specification targets. Room Tl 04B will open to Rooms Tl04A and Tl04C on either side. Room Tl04C w i ll provide the main personnel access point, and Room Tl04A wi ll provide the main material access point. [Proprietary Information] will be transferred manually in containers from Room Tl04C. Finished targets will be transferred to [Proprietary Information] for storage, or Room Tl04A for packagin g in shipping containers. Room TlOS (Water entry #2) -Room Tl05 is one of two rooms where fire-protection water will enter the RPF. The wa ll s will consist of 1-hr and 2-hr fire-rated interior partit i ons. The only access to Room Tl05 will be from the exterior. 4-36

4.1.4.5 [Proprietary Information]

Irradiated Target Receipt Area NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The irradiated target receipt area will receive irradiated targets and associated shipping casks loaded on semi-truck trailers. The bay will be designed to operate as a Zone II airspace durin g tar get unloading procedures and when the hot cell cover block is removed for maintenance. The 67 .8 metric ton (MT) (75-ton) traveling bridge crane [Proprietary Information] will service the target basket receipt bay and the hot cells. The crane will Figure 4-28. Irradiated Target Receipt Area Layout span 15.24 m (50 ft) and a run of 36.58 m (120 ft). The crane will be serviced in this area from a crane platform. Figure 4-28 illustrates the layout for the irradiated target receipt truck bay area. The function of each room in the irradi ate d target receipt area is summarized in Table 4-7. Table 4-7. Irradiated Target Receipt Area Room Descriptions and Functions Room name RO I I Cask transfer tunnel RO 12 Cask preparation airlock RO 13 Irradiat e d target ba y stairwe ll R 10 I AIB Irradiated target receipt truck bay A and B RI 02A/B Irradiat ed target receipt bay A and B R201 Irradiated target receipt mezzanine ... 323 314 314 3 ,2 06 3 , 150 TBD Ill II Ill IV III III 4-37 Room functions/ features

Transport of cask from truck trailer to RO 1 2
Ventilation confinement from Zone III RO 11 to Zone I H 105/H I 06
Cask de-lidding and cask gas sampling
Personn e l access/eg res s
Truck entry port and truck wash down
Cask impact limiter remo val
Cask imp act limiter remov a l
Move cask to transfer tunn el
Crane access space

.; .. ;. NWMI ...... .. *.. .......... *.*

NO<<THWEST MEOICAl ISOTOf'U NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description The irradiated target receipt rooms will include the following.
* * *
4.1.4.6 Room R011 (Cask transfer tunnel) -Room ROl l is the transfer tunnel that will transport casks to the cask preparation airlock. The walls will consist of concrete shielding and concrete shear wall. Casks will be lowered by crane onto a powered transfer cart , which will tran s fer the cask to Room R012. Room R012 (Cask preparation airlock) -Room R012 is the airlock where the cask gas is sampled and the cask lid is removed. The shielding plug will remain in place. The walls will consist of concrete shielding and concrete shear wall. Casks will enter from Room RO 11 on a powered transfer cart and will be lifted to mate with Rooms HO 15/HO 16 in the hot cell area. Room R013 (Irradiated target bay stairwell)

-Room R013 is the stairwell connecting the irradiated target receipt bay (Rl02A) with the cask transfer tunnel (ROI I). Room R013 will be open to Rooms ROl land Rl02A. Room RlOlA/B (Irradiated target receipt truck bay A and B)-Rooms RlOlA and RlOlB are the truck bays where trucks will enter the facility. The irradiated target receipt truck bays may be in a pre-engineered metal building attached to the concrete shear wa l l. This truck bay will provide a place to wash down the truck, trailer , or cask as required. Trucks will enter the facility through high bay doors and transport the trailers to Rooms Rl 02A/B through the high bay doors. Room Rl02A/B (Irradiated target receipt bay A and B)-Rooms Rl02A and Rl02B are the truck ba y s where casks will be removed from the trailers. The walls in the irradiated target receipt bays will consist of a concrete shear wall , 2-hr fire-rated interio r partitions , and a rated interior partition to the hot cell operating gallery. The tractor-trailer will enter from Rooms Rl OlA/B , the trailer will be disconnected , and the tractor will t h en exit to RlOlA/B during cask unloading operations. The cask impact limiters will be removed , and an overhead crane will transfer the cask to a cart in Room RO 11. Room R201 (Irradiated target receipt mezzan i ne)-Room R201 is the high ba y above the hot cell operating gallery. The high bay will provide crane access to the irradiated target receipt bay , maintenance space for the crane , and personnel egress. Room R201 will be open to H201. The walls will consist of concrete shear wall. Hot Cell Area Irradiated target processing will be performed using equipment that is located i n heavily shielded hot cells to protect operating personnel from doses generated by radioactive materials. T he hot cells will provide the capabi l ity for remote operation and maintenance of the process equipment by features t hat include shielding windows and in-cell and through-wall manipu l ators for operation and maintenance of equipment , access via cover blocks and bridge crane to support remote maintenance activi t ies , and equipment (e.g., pumps and valves) that will be remotely operated from outside the hot cell. The hot cells and associated ventilation equipment will also provide containment and confinement for the potential release of radioactive materials from a process vessel during maintenance activities or off-normal operating conditions. The hot cell will have a geometry-favorable sump configuration and HEPA filters on the ventilation inlets and outlets. The hot cell and its galleries will include the following:

Target receipt, target disassembly, and target
Parts of the waste handlin g process dissolution cells
Operating gallery
Mo recovery and purification cells
Maintenance gallery
LEU recovery and recycle area
Remote support systems 4-38 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF D escription Figure 4-29 shows the layout of the hot cell area rooms. The function of each room in the hot cell area is summarized in Table 4-8. [Proprietary Information]

Figure 4-29. Hot Cell Area Layo u t Table 4-8. Hot Cell Area Room Descriptions and Functions (2 pages)

Room name HO 13 Uranium d ecay and acco untabilit y vau lt H014B Waste collection tanks GIOIA Operating ga ll ery -B GIOIB Operating gallery -A GIOIC Operating ga ller y -C G102 Maintenance gallery 0103 Maintenanc e ga ll e r y airlock HIOJ Disso l ver 2 hot ce ll HI02 Target di sasse mbl y 2 hot cell H103 Target receipt hot cell ... 240 769 1 , 564 278 1 , 200 339 92 77 81 Ill III III II II 4-39 Room functions/features
Uranium l ag storage
Bermed area on the floor to contain waste collection tanks within the hot cell area
M a nipulators a nd window -access for hot cells HIOI , H102 a nd H10 3
Manipulators and window -access for hot cells H104 , HIOS , H106 , HI07 and H108
Access to truck ba y and maint e nance rooms-* Manipulators and window access to HO 14A, solid waste ports and solid waste hot cells
A irlock betw een maintenance ga llery a nd corridor LI 06A
Target disso l ution activities
Target disas sem bl y ac tivitie s
Transfer of targets from the target transfer port docked to the shipping cask into the target staging rack hot cell

.; .. ;. NWMI ...... ..* ... .......... ' *.* NORTtfWCST lllEDtcAL tSOTOl'lS NWMl-20 15-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-8. Hot Cell Area Room Descriptions and Functions (2 pages)

Room name * .. Room functions/features HI 04 Target disassembly I hot cell 77 93 6 1 79 IOI
Target disassembl y activities HI 05 Dissolver I hot cell
Target dis so lution activities HI 06 Mo recovery hot ce ll
Mo recovery activities Hl07 Mo purification hot cell I
Mo purification activities HI 08 Product and samp l e hot cell
Mo packagin g and l oad in g the product s hipping containe r
Samp lin g and samp l e l oad out act i vit i es G201 Hot cell cover block access III III
Cover block access and high bay G202 Ex it p assageway 209
Personnel egress Mo = molybd e num. The hot cell rooms wi ll include the fo llowin g. * * * * *
Room H013 (Uranium decay and accountability vault) -The urani u m decay and accountability va ult will be for decay storage of uranyl nitrate. The walls will consist of concrete with a steel l ine r , as de scribe d in Section 4.2. Purified uranyl nitr ate will be pip ed from the south wa ll , and once decayed , will be piped to the target fabrication room through the north wall. Room H014B (Waste collection tank hot cell) -The waste collection tank hot cell will be open to Room Hl04A , but a berm will divide the two cells. The walls and berm will consist of concrete with stee l lin ers. Room H014B wi ll contain process equipme n t associated wi th liquid waste in the waste handling system. Room G lOlA/B/C (Operating gallery -A/B/C) -Room G 101 will be the opera t ing gallery for hot cells H 101 through Hl 11. The south wall will be a concrete shear wall , and walls dividing the ga lle ry from the hot cells will serve as biological shie ldin g, as described in Section 4.2. Local co ntrol stations will be provided in the operating gallery to physically operate remote mounted manipulators and s upport system operation.

Personnel access will be through the access corr idor , Ll 08. Room G102 (Maintenance Gallery)-Room GI02 on the back side of the hot cells (H!Ol to Hl05) and tank hot cell (H014). The north , south, east , and west wall m aterial will be concrete. The maintenance ga ll eries wi ll include enclosures for repair of contam i nated equipment, areas for tool storage , and spare parts storage. G 103 will provide the main personnel access point. Room G103 (Maintenance gallery airlock) -The north and south wa ll material will be concrete. Corridor L 108B will provid e the main personnel access poi n t to Room G 103. Room HlOl (Dissolver 2 hot cell)-Room HlOl wall material will be concrete required for sh ieldin g. Rooms GlOIB and Gl02A wi ll be adjacent to Room HlOl. Room H102 will be the hot cell next to Room Hl02. The Room HlOl hot cell area will support the tar get dissolution process and wi ll house the dissolver. 4-40 ... ;. NWMI *:*****:* ........ ' * *

NORTHWEST MEDH:Al ISOTOPES NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description
* * * * * * *
Room H102 (Target disassembly 2 hot cell) -Room HI 02 wall material will be concrete required for shielding.

Rooms GIOIB and GI02B wi ll be adjacent to Room HI02. This hot cell area will support the target disassembly process. The target disassembly station wi ll pick one target at a time from the sh ippin g basket, de-lid the target , and pour target material into a transfer container or funnel and then into the dissolver. The spent target wi ll be inspected to ensure that it is empty, passed through to the waste management area , and disposed of as solid waste. The disassembly stat ion s will be supported with le aded windows and/or cameras and master-slave manipulators. Room H103 (Target receipt hot cell)-Room HI06 wall material will be concrete required for s hieldin g. Rooms GIOIA and GI02B w ill be adjacent to Room Hl03. Rooms Hl02 and Hl04 wi ll b e the hot cells next to Room Hl03. The Room HI03 hot cell area will support target r eceipt and include a feature that mates with the s hielded transfer cask to lower the target basket into the hot cell. Room H104 (Target disassembly 1 hot cell)-Room Hl04 wall material will be concrete required for shie ldin g. Rooms Gl02 and Gl02B will be adjacent to Room Hl07. Th is hot cell area will support the target disassembly process. The disassembly station will pick one target at a time from the shipp in g basket, de-lid the target , a nd pour target material into a transfer container or funnel and then into the dissolver. The spent target will be inspected to ensure that it is empty , passed through to the waste management area, and disposed of as solid waste. The disassembly stations will be supported with l eaded windows and/or cameras and master-slave manipulators. Room HlOS (Dissolver 1 hot cell) -Room HI 05 wall material will be concrete required for shie ldin g. Rooms GIOIA and Gl02B will be adjacent to Room Hl05. Rooms Hl04 and Hl06 will b e the hot cells ne xt to Room Hl05. The Hl05 hot ce ll area will support the target dissolution process and house the diss olver. Room H106 (Mo recovery hot cell) -Room HI 06 wall material will be concrete required for shie ldin g. Room Gl02B wi ll be adjacent to Room Hl06. Hot cells Hl05 and Hl07 will be next to Room Hl06. The hot cell will include the primary and seco nd ary sma ll IX columns with containers, peristaltic pumps, and collection tanks. Operation of the process will be performed using the hot ce ll r emote manipulators. Room H107 (Mo purification hot cell) -Room Hl07 wa ll material wi ll be concrete required for shielding. Room Gl02B w ill b e adjacent to Room Hl07. Hot cells Hl06 and Hl08 will b e next to Room Hl 07. The cell will include tertiary IX column wit h containers, peristaltic pumps, and collection tanks. Operation of the process will be performed using the hot ce ll remote manipulators from Room Gl02. This area of the hot cell will h ave design features that support U.S. Food and Drug Administration (FDA) cleanroom requirement

s. Room H108 (Product and sample hot cell) -Room HI 08 wall material will be concrete required for shie ldin g. Room G 10 2B will be adjacent to Room H 108 , with hot cell H 107 ne xt to Room HI 11. An access point will be included for load-in and lo ad-out of the 99 Mo s hippin g cask. Room G201 (Hot cell cover block access)-Room G201 will provide crane access to the hot cells and hot cell cover blocks for maintenance.

Room G201 will be open to the irradiated target receipt mezzanine (R201 ). The walls wi ll consist of concrete shear wa ll. Room G202 (Exit passageway) -Room G202 will provide personnel egress from the maintenance ga llery (G 102). 4-41 .; .. ;. NWMI ...*.. ..* **. .......... ' *. * !' . NORTifWlST M£DK:Al ISOTOflt:S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.1.4.7 Waste Management Area The waste management area will include shielded enclosures for tanks collecting liquid waste and containers used to stage solid wastes generated by the other process systems. Parts of the waste management system that are dedicated for high-dose liquid waste will be included in the remote hot cell. There will be three shielded areas in the waste management area, including:

*
HIC vault, where filled waste containers will be held for several months to allow s h ort-lived radioisotopes to decay to lower doses Hot cell solid waste export area, where equipment and empty targets w i ll pass out of the hot cell Solidification cell , where liquid waste will be processed or mixed with materials to prepare a low-level waste package for disposal Solid waste will be moved to the waste loading area where the waste will be loaded into a shipping cask (already on a trailer) to be transported to a disposal site. The waste management area will be serviced by a second bridge crane. The HIC storage and decay cell zones that are located in the basement of the RPF are shown in Figure 4-30. Figure 4-3 I and Figure 4-32 show the waste management loading bay and the ground floor of the waste management area, respectively.

Figure 4-33 shows the low-dose liquid solidification rooms within the waste management area. [Proprietary Information] Figure 4-30. High-Integrity Container Storage and Decay Cells Layout 4-42 [Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-31. Waste Management Loading Bay and Area Layout [Proprietary Information] Figure 4-32. Waste Management Area -Ground Floor 4-43 .; ... ;. NWMI ...... ..* *.. ..... .... .. ' " "NOfllTHWUT MCtMCAl ISOTOPlS [Propri e t ary In fo rm a ti o n] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-33. Waste Management Area -Low-Dose Waste Solidification Location Th e fun c tion of eac h room in th e was te m a n age m e nt a r ea is s umm a ri z ed i n T abl e 4-9. Table 4-9. Waste Management Room Description s and Functions Room name Room functions/features WOl I A/B

D ecay storage fo r HI Cs HI C vau l t 1 , 865 I V W IO I
Truck e ntr y port for wa s te s hipment Waste manag e ment 1 , 64 7 IV loadin g ba y W l 02 Waste l oa d i n g area WI03A/B High-do se wast e hand l in g hot c e ll Wl04 Hi gh d ose was t e tr ea tm ent h o t ce ll WI05 Stair #3 W l 06 W as t e manage m e n t a i r l ock Wl0 7 Lo w-do s e liquid s o l idification W20 1 S t a ir #3 HI C = hi g h-integrity co nt a in e r. 1 , 086 5 3 4 2 09 1 6 1 550 209 lll II III
Remove upper impact limiter
Loadi ng a r ea , w h e r e drum s of hi g h-a n d l ow-d ose was t e are l oa d e d in to cask
Movem e nt of high-do se w as t e contain e r s by c ran e
A dd e n ca p s ul a t io n age nt to drum s
A dd hi gh d ose liquid an d s o l idi ficat i on age n t to HI C
St a irwell in the tar g et fabr i ca tion ar e a pro v id es acce ss between th e airlock or outdoors and th e mechanical

/ el e ctrical room in the utilit y area on th e se cond floor llI

Se p arates t h e Zo n e I V ve ntil a ti o n of sta ir we ll a nd Zo n e TI ve ntil a ti o n of roo m WI 0 7 II
Hou s e s equipment for the low-dose so l id ifi cation process
Control s t a tion for was te handling op era tion s III
Access b etwee n fi r st an d seco nd fl oor 4-44 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The waste management area rooms will include the followin g. * * * * * * * *
Room WOll (HIC vault) -The HIC vault will provide decay storage of high-dose waste. The waste will be packaged in HICs, and a conveyor system will provide for first-in , first-out inventory management.

The HIC vault will be below the hot cells , operating gallery, and maintenance gallery. The walls, floor , and ceiling will be shielding concrete, as described in Section 4.2. A single lift will transfer HICs into and out of Room Wl03. Room WlOl (Waste management loading bay)-Room WlOl will provide truck access from outside the RPF to the sub-grade waste loading area. The walls have not been defined and ma y be part of a pre-engineered metal building. The wall to Room W 102 will be a concrete shear wall with a high bay door. Room Wl02 (Waste loading area) -Room WI 02 will house the trailer during cask loading operations. Room Wl02 will be beneath a portion of Room Wl03. The loading operations will consist of a crane transporting the HIC into the cask through a telescoping port , which will connect Room Wl03 to the cask. The walls will consist of concrete shear wall , shielding concrete , and 2-hr fire-rated interior partitions. Bollards or other means will be used to prevent the trailer from contacting the shielding walls. Room W103 (High-dose waste handling hot cell) -Room W 103 will house equipment for the transport of sealed HI Cs and drums from Room WI 04. A crane will lift the HIC from the waste transfer drawer and lower the container into the shipping cask. A telescoping port will create a confinement boundary between the hot cell and the shipping cask to minimize radiation exposure. The walls, floor , and ceiling will be shielding concrete, as described in Section 4.2. Room Wl 04 (High dose waste treatment hot cell) -Room W 104 will house the equipment to solidify the high-dose liquid waste in HICs and encapsulate the solid waste in drums. Room WlOS (Stair #3)-Room Wl05 will be the stairwell connecting Room WI 06 with Room U201. Walls will consist of concrete shear wall and 2-hr fire-rated interior partitions. Room WI 05 will provide personnel acc e ss to t he second floor and egress from the second floor. Room W106 (Waste management airlock)-Room WI06 is the airlock that will separate the Zone II ventilation of the low dose liquid solidification room (WI07) from the Zone IV ventilation of the waste management loading bay (W 10 I). The walls will consist of concrete shear wall and 1-hr fire-rated interior partitions. Low-dose waste containers will be transported from Room TlOl to Room Tl04C by pallet jack. Room W107 (Low-dose liquid solidification) -Room Wl07 will house equipment for the dose waste solidification process. Low-dose waste will be piped in from the holding tanks in the utility area above Room W 107 , and drums of solidified waste will be transported out by pallet jack. Room W107 will also serve as a control room for the high-dose and solid waste hot cell operations. The walls will consist of concrete shear wall and 1-and 2-hr fire-rated interior partitions. Room W201 (Stair #3) -Room W201 is the second floor of the stairwell that will connect Room W106 with Room U201. Walls will consist of concrete shear wall and 2-hr fire-rated interior partitions. Room Wl05 will provide personnel access to the second floor and egress from the second floor. 4-45 ...... ;. NWMI ...... ..* *.. ........ *. ' *.* HORTHWUT MEDICAL tSOTOPU 4.1.4.8 Laboratory Area NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description An on-site analytical laboratory will support production of the 99 Mo product and fabricatio n of targets for irradiation. The target fabrication area will have tools and systems installed to perform local analyses like radiography, helium leak detection , and dimensional analyses. Samples from each batch o f purified 99 Mo product will be collected , transported to the laboratory, and prepared in the laboratory hot cell space. Other laboratory features will include the following:

Hoods and/or gloveboxes to complete sample preparation, waste handling, and standards preparations
Rooms with specialty instruments, [Proprietary Information]

Chemical and laboratory supplies storage

Bench-top systems like balances, pH meters, ion-chromatography, etc. Figure 4-34 shows the layout of the laboratory area rooms. The function of each room in the laboratory area is presented in Table 4-10. [Proprietary Information]

Figure 4-34. Laboratory Area Layout Table 4-10. Laboratory Area Room Descriptions and Functions -Room name ... Room functions/features L 101 Receiving 424 I Allow s the flow of materia l supplies into the facility L 102NB Chemical supply 932 rn Storage of chemicals Ll03 99 Mo product shipping 265 IV Preparation of 99 Mo product for shipping LI 04 Shipping airlock 264 III Separate confinement zones L 105 Ana l ytical laboratory 1694 II Area for laboratory activities (e.g., sample analysis) with glovebox ventilation I LI 06 R&D hot cell laboratory 724 II Containment area for R&D with glovebox ventilation Zone I L 107 Laboratory corridor 694 III Personnel access/egress Ll08 Access corridor 1289 III Personnel access/egress 99 Mo = molybdenum-99. R&D = research and deve l opment. 4-46

- "*h*NWMI ..... ........ *. ' * *
NORTHWEST MEDtc:Al ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The laboratory rooms will include the following. * * * * * * *
Room LlOl (Receiving)

-Room LIOI will be adjacent to Room s LI02 , Ll03 , and LI04. The north and west walls will be interior concrete walls. The east wall will be an exterior concrete wall with a rollup door access. The south wall will be an exterior concrete wall. Room L 10 I will s upport receipt of chemical supplies and materials for the laborato ry. Room L102 (Chemical supply) -The chemical makeup room will include tanks s upplying aqueous chemicals to the process systems , flammable material storage cabinets used to segregate incompatible materials , and storage of chemical solids used in the process system s. Room Ll03 (99 Mo product shipping) -Room LI 03 will support shipping and receiving activities , and the stagin g of outgoing s hipping containers Room Ll04 (Shipping airlock) -Room L 104 will have a I-hr fire-rated partition wall adjacent to Rooms LI 05 and LI 07. Room LlOS (Analytical laboratory) -Room LI 05 will have a 1-hr fire-rated partition wall adjacent to Room Ll 07. The analytical laboratory will support production of th e 99 Mo product and fabrication of targets. Room L106 (R&D hot cell) -Room LI 06 will have a 1-hr fire-rated partition wall adjacent to Rooms Ll05 and Ll07. Room Ll07 (Laboratory corridor) -Room Ll 07 will be adjacent to Rooms Ll 04 , Ll 05 , and Ll06. The interior wall will be a 2-hr fire-rated partition wall adjacent to operating gallery A (G102). The interior wall will be a 1-hr fire-rated partition wall adjacent to Rooms Ll04 and LI 0 5. Room Ll 07 will provide a main personnel access point. Room L108 (Access corridor) -Room Ll 08 will provide access from the administration and support a rea to the production areas. The walls will consist of concrete shear wall a nd fire-rated interior partitions. 4.1.4.9 Chemical Makeup Room The chemical makeup room will include tanks supplying aqueous chemicals to the process systems, flammable material storage cabinet s used to segr e gate incompatible materials , and storage of chemical solids used in the process systems. The g as distribution room (not shown) will serve as a location for storage of small quantity gases (s tored in gas cylinders) and distribution manifolds. Large quantities of gases will be stored outside the RPF in appropriate storage tanks or trailers. These areas will be designed to segregate incompatible chemicals. Figure 4-34 s hows the layout of the chemical makeup room. Further detail for chemical suppl y system is provided in Chapter 9.0 , Section 9.7.4. 4. 1.4.10 Utility Area A mechanical /electrical room will be located on the second floor over a corridor and portion of the target fabrication and waste management area rooms. The mechanical /electrical room will be the location of electrical systems , motor control centers , pumps , boilers , air compressors , and venti l ation supply equipment. The utili ty area will provide support functions and include space for maintenance , parts storage , mechanical and electrical utility equipment , and ventilation handling equipment. The utility area will include parts of the ground floor and second floor. The heating , ventilation , and air-conditioning (HV AC) chillers will be located outside the facility, in the same area as the process chilled water chillers. 4-47 NWMl-2015-021 , Rev. 3 Cha p ter 4.0 -RPF Description Figure 4-35 , Figure 4-36 , and Figure 4-37 s how the layout of the utility area , se c ond floor mechanical /electrical room , and mechanical area , respectivel

y. [Proprietary Information]

Figure 4-35. First Floor Utility Area [Proprietary Information] Figure 4-36. Second Floor Mechanical and Electrical R oom [Proprietary Information] Figure 4-37. Second Floor Mechanical Area The function of each room in the utility area is s ummarized in Table 4-11. 4-48

' I NWMl-2015-0 2 1, Rev. 3 Chapter 4.0 -RPF D escription Tab l e 4-11. Utility Area Room Descriptions and Functions Room name * .. I Room functions/features U I 0 I Electrical 698 IV
Facility pow e r s uppl y U I 02 Manipulator maintenance 473 II
Perform maintenance on manipulators U 103 Maintenance shop 567 Ill
Perform maintenance on equip ment U I 04 Stair #2 297 IV
Personnel access/egress U I 05 Corridor 227 IV
Personnel access/eg r ess U 106 Janitor 111 IV
Storage U 107 Elevator machine room 60 IV
House s eq uipm e nt for elevator operation Ul08 Freight elevator 96 IV
Moves equipment and supplies to/from Ul09 Utility area loading UllO Men's restroom Ulll Women's restroom U112 Water entry # I UI 13 Communications room Ull4 Process equipment and parts storage U201 Electrical and m ec hanical su pply U202 Corridor U203 Ventilation exhaust 1 , 487 350 314 158 15 7 342 6,320 566 8,616 IV IV IV IV IV I V 111 III II second floor
Eq uipm ent receipt
Per so nnel access/egress
Personal hygiene
Personal h ygiene
Fire-protection water
Houses communication equipment
Storage area for spa r e process eq u ipment
Housing for elect ri ca l and mechanical utilit y e quipm e nt
Housing for supp l y air handlin g unit s
Personnel access/egress
Housin g for Zo n e I and Zone Tl/III Ex hau st filter hou sings
Housing for process offgas final treatment The utility area rooms will include the followin g. * *
Room UlOl (Electrical)-

Room UlOI will be the electrical service entrance room. The south wall will be a concrete exterior wall, and the other walls will be interior partition walls. The main electrical supply will enter the RPF at this room. Equipment within the room will include transformers, switchgear, and the automatic transfer switch for the diesel ge nerator. Room U 102 will provide the main personnel access point. Room U 102 (Ma ni p ul ator ma in tena n ce s h op) -Room U 102 will be a manipulator maintenance shop. The walls will be 1-hr fire-rated and non-fire-rated interior partitions. This room will provide space for manipulator maintenance activities. Personnel access will be from the building exterior. Roo m Ul03 (Mai n te n ance shop) -Room U103 will be a maintenance shop. The north wall will be a 1-hr fire-rated interior partition, and the other walls will be non-fire-rated interior partition walls. This room will provide general space for maintenance activities, including maintenance of process equipment. Per sonne l access will be provided through corridor LI 07. 4-49

.-:;.:: NWM I ........ *
NORTHWHT MEDK:Al I SOTIWH NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description
* * * * * * * * * * *
Room U104 (Stair #2) -Room U 104 will be a stairwell providing access to the second floor ventilation exhaust room (U203). Interior walls will be 2-hr fire-rated interior partitions.

This room will have an exterior door for emergency egress. Personnel access will be through Corridor Ul05. Room Ul 05 (Corridor) -Corridor U 105 will provide personnel access to and egress from rooms. Walls will consist of concrete shear wall and 1-hr fire-rated interior partitions. Personnel access will be through corridor Ll 07. Room U106 (Janitor)-Room U106 will be a janitor storage area. W a lls will consist rated and non-fire-rated interior partitions and a concrete shear wall. Personnel access will be through Corridor Ul05. Room U107 (Elevator machine room) -Room Ul 07 will provide space for elevator machinery . Walls will consist of concrete shear wall and 1-hr fire-rated interior partitions. Personnel access will be through Corridor Ul 05. Room U108 (Freight elevator) -Room Ul08 will be the freight elevator. Walls will consist of concrete shear wall and 1-hr fire-rated interior partitions. Personnel access will be through Corridor Ul05. Room U109 (Utility area loading)-Room Ul09 will be a loading area for general shipping and receiving , including utility and process equipment. The room will also provide pe r sonnel access and egress to utility area and hot cell area rooms. Equipment will be brought in through a roll-up door at the loading dock. Walls will consist of concrete shear walls and 1-and 2-hr fire-rated walls. Room U110 (Men's restroom)-Room Ul 10 will be the men's restro o m. Walls will mainly be non-fire-rated interior partitions. Room U111 (Women's restroom) -Room Ul 11 will be the women's restroom. Walls will mainly be non-fire-rated interior partitions. Room U112 (Water entry #1) -Room UI 12 will be one of two rooms where fire-protection water enters the RPF. The walls will consist of 1-and 2-hr fire-rated interior partitions. The onl y access to Room Ul 12 will be from the exterior. Room U113 (Communications room)-Room Ul 13 will house communications equipment. Walls will mainly be non-fire-rated interior partitions. Room U114 (Process equipment storage) -Room Ul 14 will provide space for process equipment storage. Walls will mainly be non-fire-rated interior partitions. Room U201 (Mechanical/electrical supply)-Room U201 will provide space fo r the majority of the utility supply equipment. The room will be located on the second floor above the target fabrication area. The equipment in Room U201 will include supply air handling units, process boilers, air compressors , low-dose waste tanks , a demineralized water supply tank , heat exchangers, and motor control centers. Walls surrounding Room U20 1 will be concrete shear walls. Room U202 (Corridor) -Corridor U202 will provide personnel acce s s and egress to Rooms U201 and U203. Room U202 will be above access corridor Ll08. Walls surrounding Room U202 will be 2-hr fire-rated interior partitions and 3-hr fire-r a ted concrete shear walls. 4-50

.. ;. NWMI *: :**:*:* ...*.. *. *

NORTHWEST MEDtCIJ. ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description
Room U203 (Ventilation exhaust) -Room U203 will provide space for the Zone I, Zone II/III , laboratory and process offgas exhaust systems. The room will be located on the second floor above the utility and laboratory areas. The equipment in Room U203 will include blowers, filter housings , shielded offgas carbon beds, and high-efficiency gas adsorbers for the final process offgas treatment.

Walls surrounding this room will be concrete shear walls. Utilities External to Radioisotope Prod u ction Facility The process and HV AC chillers will be located in a mechanical yard on the southwest side of the RPF , as shown in Figure 4-4. The chillers will be adjacent to the facility in an area enclosed by screen wall. 4.1.4.11 Administration and Support Area The administration and support area will be an annex to the RPF and include various rooms supporting production. The general construction of the administration and support [Proprietary Information] Figure 4-38. Administration and Support Area Layout area will be gypsum wallboard mounted on metal studs for interior walls , and curtain or storefront walls on the exterior. The wall separating the administration area from the production areas will be a 3-hr rated interior partition. The function of each room in the administration and support area is summarized in Table 4-12. Figure 4-38 shows the layout of the administration and support area rooms. Control Room The control room will provide the majority of interfaces for the overall basic process control system , monitoring , and process alarms and acknowledgement for the facility. The control room will consist ofa control console with two or three operator interface stations or human-machine interfaces (one being a dedicated engineering interface), a master programmable logic controller or distributed controller , and all related and necessary cabinetry and subcomponents (e.g., input/output boards , gateways, E thernet switches , power supplies, uninterruptable power supply). This control system will be supported by a dat a highway of sensing instrument signals in the facility process areas that will be gathered onto the highwa y throughout the facility by an Ethernet communication-based interface backbone and brought into the control room and onto the console displays. Details of the control room are provided in Chapter 7.0, "Instrumentation and Control Systems." The control room door into the facility will be equipped with controlled access , as described in the NWMI RPF Physical Security Plan (Chapter 12, Appendix B). 4-51 .; ... ;.*NWMI ...... ..* *.. ........... ' *.*

NOITHWEST MEDtcAL ISOTOPl:S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-12. Administration and Support Area Room Descriptions and Functions
Room name SIOI Vestibule Sl02 Entry SI 03 Entry hall S I 04 Corridor SI05 Women's change room SI 05A Vestibule SI 06 Women's restroom SI06A Vestibule SI07 Men's re stroo m Sl08 Men's change room hall SI09 Men's change room SllO Men's shower SI 12 Decont a mination room SI l3 Hall SI 14 Airlock SI 15 RCT office Sl 16 Shift manager office Sll7 Stair #I SI 18 Closet SJ 18A Server room SI 19 Control room Sl20 Corridor Sl20A Vestibule Sl21 Break room Sl22 Communications

/electrical Sl23 Office #4 Sl24 Janitor Sl25 Office #3 Sl26 Office #I SI27 Office #2 Sl28 Restroom Sl29 Hall Sl30 Conference room RCT = radiological control technician. * .. Room functions/ features 225 637 1 , 033 1,033 284 46 281 38 426 49 199 164 253 94 193 119 148 200 30 267 366 275 36 858 134 121 70 126 124 127 72 192 598 IV IV IV IV IV IV IV IV IV IV IV TV IV IV JV IV IV IV IV IV IV IV Personnel access/egress Personnel access/egress Per so nnel access/egress Personnel access/egress Per so nnel area for changing clothes Personnel access/egress Personnel h ygie ne Personnel access/egress Personne l h ygie ne Personnel access/egress Personne l area for changing clothes Shower enclosure Area to remove contamination Personnel access/egress Personnel access/egress Functional RCT workspace Functional workspace Personnel access/egress Storage Space devoted to computer servers Provides the majority of interfaces for the RPF process control system Personnel access/egress IV Per so nnel access/egress IV Personnel lunch room IV Housing for electrical utilit y equipment IV Functional workspace IV Storage IV Functional workspace JV Functional workspace IV Functional workspace IV Personnel hy g iene IV Personnel access/egress IV Workspace area for meetin gs RPF = Radioi soto pe Production Facility. 4-52 .. ;.;: .. NWMI ..... .*.* .. *.*. ' e * ' NOllTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

4.2 RADIOISOTOPE

PRODUCTION FACILITY BIOLOGICAL SHIELD 4.2.1 Introduction 4.2.1. I Biological Shie ld Functions The RPF biolo gical shield will provide an integr ate d system of features that protect workers from the high-dose radiation generated during the radioi soto pe processin g to recover 99 Mo. The primary function of the biological shie ld will be to reduce the radiation dose rates and accumulated doses in occupied areas to not exceed the limit s of 10 CFR 20, "S tandard s for Protection Against Radiation," and the guidelines of the facility ALARA (as low as reasonably achievable) program. The shielding and its components will withstand se i smic and other concurrent l oads, while maintainin g containment and s hieldin g during a design basis event (D BE). Functions of the biological shield , as related to the RPF pro cess systems, are described in Sect ion 4.2.3.4. 4.2.1.2 Physical Layout of Biological Shield The biological shield, located in the hot cell area, is shown in Figure 4-39. Hot ce ll arrangement within the biological s hield is s hown in Fig ure 4-40. 4-53 .. ; ... ; .. NWMI ...*.. ..* ... .......... ' *,* NOllTHWHT MCOtCAL. ISOTOPlS [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-39. Facility Location of Biological Shield 4-54 ... ;. NWMI .... ** ..... .......... * *

NOtn"HWEST MfOtCAl. ISOTOPES [Proprietary Information]

Figure 4-40. Hot Cell Arrangement 4.2.1.2.1 Location of Hot Cell Appurtenances NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The number and location of hot cell appurtenances (e.g., windows, manipulators , a nd optics) wi ll be developed for the Operating License App licati on. The hot cell app urt e nan ces are described in Sections 4.2.2.3 through 4.2.2.6. 4.2.2 Shielding Design The radiation shield is designed consistent with standards found acceptable for co n struction of radiation s hi elding st ru ctures specified in U.S. Nuclear Regulatory Commissio n (NRC) Regulatory Gu ide 1.69 , Concrete Radiati on Shie l ds and Generic Shield Testing for Nuclea r Pow er Plants, to the exte nt that the recommended standards a ppl y to a compos it e (concrete a nd stee l) shie ld. The desi g n of the concrete for shielding structures, including materials se l ection, durability requirements , quality control (QC), mixing, placement, formwork, embedded pipes, construction joints, reinforcement, analysis, and design, conforms to the provisions out lined in Chapters 3 through 8 of American Concrete Institute (ACI) 349, Code R equirements for Nuclear Safety-Related Concrete Structures. The final minimum thickness of a concrete s hi eld structure is the greate r of the: ( 1) thickness determined based on radiation shie ldin g requirements , and (2) thickness determined based on structural requirement

s. 4-55

.. ;.;;**NWMI ...... .*.* .. *.*. * *. *

NOflJTifWEST MEDICAL tsOTOPES NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description 4.2.2.1 Shielding Materials of Construction The RPF biological shield will be constructed primarily of s teel-reinforced normal (2.2 to 2.4 g/c ubic centimeter

[cm 3]) and high-density (2.5 to 4.5 g/c m 3) concrete walls. In areas where shielding requirements are hi g her than the nominal average, steel cladding will be us ed to increas e the radiation shielding. 4.2.2.1.1 Nuclear Properties of Shielding Materials The nuclear properties of shielding materials are dictated by the fundamental cross-sections measured or otherwise established for a given nuclide. These cross-sections are used b y co mputer codes to calculate interaction probabilities for both neutrons and photons. When u se d , the cross-section libraries used will be specifically identified. 4.2.2.2 Structural Integrity of Shielding 4.2.2.2.1 Evaluation of Shielding Structural Integrity The bioshield will be designed and constructed u s ing applicable structural and construction standards. 4.2.2.2.2 Effects of Radiation on Structural Materials The effects of radiation on s tructural materials in the RPF were not quantified during preliminary design. ANS 6.4-2006, Nuclear A nal ysis and D esign of Co n crete Radiation Shielding for N ucl ear Power Plants , provides the following guidance that will be used to evaluate the effects of radiat i on on structural materials: * *

Section 5.4 -" Jn the design of a concrete radiation shie ld , it is necessary that the temperature and t emperature distribution throughout the shield be ca l cu lat ed prior to co nstru ctio n. Jn addition to radiation heating sources, these ca l cu lati ons must include detailed consideration of other h eat so ur ces and sinks. A lthough structura l considerations are outside the scope of this sta ndard , the shield designer should be aware that thermal c han ges resulting from the radiati on e nvironm ent may affect the ability of concrete to meet its structura l requirements. " Section 8.1.1-"T h e op e rating t emperature of th e concrete s hould be co nsid ered in the se l ection of co n crete mixtures and in the prediction of the attenuation characteristics. " " When neutrons and gamma rays int eract with concrete, e ner gy is deposited in the co n crete. The resultant increase in temperature i s the primary radiation effect that ha s b ee n found. For incident energy fluxes < 10 10 megaelectron volt (Me V)/square centimeter (cm 2)/sec ond (sec), a n eg ligibl e te mp erat ur e rise takes place in concrete.

Jn additio n , if concrete temperatures are to be maintain ed below 65 C, no special consideration needs to be given t o temperature effects in conc r ete shie ld s. " Section 8.1.2 -"A major conside ration of h ea tin g of concrete shi e lds is the impa ct on the structura l characteristics. Laboratory experiments clearly indicate that the mechanical properties of concrete are related to temperature. Compress iv e strengt h is reduced as th e temperature of co ncr ete is increased, and eve n greater relative losses in t e nsil e st r engt h , modulus of e la sticity, and bond strengt h hav e been not ed. The thermal properties of concr e te are also known to be influenced by the type of aggregate emp lo yed. Jn the design of a concrete radiation s hi e ld , structural considerations are paramount in those cases where the shield also serves a necessary and vita l structural role. Thi s would be the case, for examp l e, if the shie ld wall also provided a conta inment barrier in addition to forming an integral part of the building structure. Jn some instances , the struc tural c hara cteristics of a concre t e shield might not be important; co ncr ete's dual rol e as shield and structure, ho wever, is usually an important feature. " 4-56 NWM I ..*... e * ! . NOmfW'EST MU>fCAl ISOTOPlS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information]. This heat load is comparable to the heat generated by the lighting within the hot cells. Therefore , excessive heat to the level at which concrete is affected by temperature is not considered a credible situation and will not affect the structural integrity. 4.2.2.3 Design of Penetrations The penetrations provided for ventilation, piping , construction detail , shield plugs , personnel entryways, and viewports in biological shield structures will reduce the shielding effectiveness. The magnitude of the reduced effectiveness will depend on geometry, material composition, and source characteristics. Each penetration in a shield will be evaluated for its impact on the effectiveness of the shield in which it is located. Penetrations are designed with offsets and steps to prevent direct streaming of radiation through the penetration. 4.2.2.4 Design of Material Entry and Exit Ports Material entry and exit ports are designed to [Proprietary Information] provide safe and efficient transfer of process and routine maintenance materials into and out of the hot cell confinement boundary without breaking confinement. Material entry and exit ports are designed to maintain radiation shielding to protect the worker from high-dose radiation at all times during the transfer process. Workers will be Figure 4-41. Hot Cell Target Transfer Port stationed behind secondary shield walls or otherwise in a radiologically safe position during entry or exit port opening activities to prevent accidental exposure. Radiation monitoring devices will be placed near the entry and exit ports to alarm workers of a radiation leak within the entry or exit port cold side area.

The target transfer port (TD-TP-210, TD-TP-220) in the target receipt hot cell (H103) is an adaptation of a double-door transfer system typically used with 55-gal drums. The system will use a double-door-type sealing concept. The BRR shipping cask lift (TD-L-110, TD-L-120) will position the cask in proper alignment with the port using the sensors and control syste m. A powered drive will operate the port door after the cask is properly positioned.

Once the port is opened, the cask shield plug may be removed to access and retrieve the irradiated targets. Figure 4-41 provides details of the target transfer port in the target receipt hot cell. 4-57 .; ... ;. NWMI .... ** ...... .*.* .. *.*.* ' ! * *

NOflTHW£ST MEDtcAL tSOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description
* *
Cell-to-cell transfer doors will be provided for the movement of small items from a hot cell workstation to an adjacent hot cell workstation as required by process and maintenance activities. Doors may be interlocked as required by administrative safety controls and operating procedures. Waste drum transfer ports will be provided in some hot cell workstations.

The wa s te drum transfer port will be a double-door transfer system that enables safe and efficient transfer of waste items out of the hot cell without breaking containment. The drum transfer cart will position the drum in proper alignment with the port using the sen s ors and control s ystem. A powered-drive system will engage the port door with the drum's containment lid and open the port. The product transfer port (MR-TP-400) and sample transfer port (MR-T P-410) in the product and sample hot cell (H 108) are an adaptation of a double-door transfer system typically used with 55-ga l drums. The system will use a double-door-type sealing concept that will enab l e safe and efficient tran s fer of packaged product and process samples out of the hot cell. The Mo product container lift will position the cask in proper alignment with the port using sensors and a control system. A powered-drive will operate the port door after the cask is properly positioned. Once the port is opened , the cask can be de-lidded for package loading. The waste shipping transfer port, shown in Figure 4-42, will be located in the high-dose waste handling hot cell and include a port door (cover) that will be removed by crane during waste shipping cask loading and unloading activities. A telescoping shield sleeve (curtain) wi ll provide radiation shielding between the shield wall of the hot cell and the ca s k. [Proprietary Information] Figure 4-42. Waste S h i p ping Transfer Port 4-58 NWM I ...**... NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description

* *
NORTHWEST MlDICAl ISOTOPES 4.2.2.5 Design of Operator Interfaces Operator interfaces will include the following.
4.2.2.6 Through-wall manipulators will be provided throughout the biological shield where activities requirin g high dexterity are performed , includin g normal operation and periodic maintenance. Manipulator type and position will be determined through analysis of the reach envelopes, capacity , and interface requirements at each workstation, and operator er g onomic s. A typical through-wall manipulator workstation is s hown in Fi g ure 4-43. [Propri e tary Information]

Figure 4-43. Manipulators and Shield Windows The biological shield will be fitted with windows at workstations to provide operators with direct visibility of the activities being performed. Each radiation shjeJding window will provide adequate radiation shielding for the radiation source in the respective cel l. The attenuat i on of the window will be matched to the attenuation of the hot cell wall. Design of Other Interfaces Cover blocks , shown in Figure 4-44, will be positioned throughout the biological shield and provide access to the hot cells and vaults to facilitate major maintenance activities and facility decommissioning. 4-59 .. ;.:; .. NWMI ..... .*.* .. *.*. !**!': NOATHWHTMfDtcAL.ISOTOPU [Proprietary Information] Figure 4-44. Cover Block Configuration

4.2.3 Methods

and Assumptions for Shielding Calculations NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description The shielding analysis demonstrates that the production facility will comply with the regulatory requirements of 10 CFR 20. The intent of the shielding design is to limit the dose rate for the highest source term to 5 millirem (mrem)/hr at 30 centimeters (cm) from the most accessible the surface. Assuming an individual is working at this location for 200 hr/year, this will limit the total dose equivalent received to 1 roentgen equivalent in man (rem), which is half of the preliminary NWMI ALARA annual dose equivalent limit of2 rem. To evaluate the necessary shielding required to maintain these limits, a series o f photon-sp ectr um source terms were generated for the following primary locations or process streams: * * *

Hot cell (dissolution) wall and window Target fabrication incoming material Offgas treatment High-dose waste container Each of these process streams represents the expected maximum inventory for a given location requirin g a bioshield within the RPF. A source term was estimated for each system based on the highest estimated radioactive material content entering the RPF and moving through each system, as designed at the minimum expected time from the end of irradiation. This source term was used to generate a photon energy spectrum indicative of the radioactive material inventory at a given time, which was then used by the particle transport code to estimate the thickness of the shielding material needed. 4.2.3.1 Initial Source Term [Proprietary Information].

The NWMI LEU targets, described in Section 4.4.2.9.3, will be used regardless of the reactor at which the irradiation occurs. Because MURR has the [Proprietary Information] reactors providing irradiation services for NWMI [Proprietary Information]. 4-60

...*.. lllORTHWHT MEDK:Al 1$0l'Ol'U NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] The SCALE package ofneutronics and depletio n codes was used to perform the calculation. Specifica ll y, a two-dime n sional model of the OSTR was created in SCALE u s in g TRITON, the depl etion was calculated with NEWT, and the output was formatted with OPUS. The OSTR core was modeled in a configuration similar to the existing core config uration. [Proprietary Information]. The TRITON model consists of an x-y s li ce of the active core at approximately mid-hei ght. The model only included the core, the graphite reflector assembly, and s urroundin g water. While composed of several different materials , the graphite assembly was simplified in the model to only be an aluminum-clad structured filled with graphite. Smear densities were created for each fuel element by smearing the fuel meat together with a central zirco nium pin. Smear den sities were created for each target by smearing [Proprietary Information] with the inner and outer cladding. [Proprietary Information]. Dim ens ions , loc ations, and numb er densitie s for the fuel elements were taken from the OSTR safety analysis report. Dimensional values of the tar gets were taken from the target drawings. The calculations u si n g this model were run with the ENDF/B-V 44 gro up libra ry (vS-44). The TRITON model was used to calcu lat e the relative distribution of fuel and target pow er for a designated irradiation (ca lled "bum" in SCALE) [Proprietary Information] in the OSTR. Knowing the reactor power for the fuel , the power results were normalized. Based on the 89 fuel elements in the core an d a reacto r power of 980 kilowatt (kW) (reduction of 2 percent from lic ensed power to account for uncertainty in measured power [Proprietary Information]. Calculations were performed to predict the m ass (g), activity (Ci), and d ecay heat power (W) before irradiation, at EOI , and at s pecifi c points in time following irradiation for the targets. The top 400 isotopes in order of importance at each requested decay (cooling) inter val were provided. Because this code package was originally intended to p erfo rm depl etion calculations for commercial power reactor fuel and a two-dimensional model was used to model the OSTR core, output of OPUS produces units of gram (or curies or watts) MT he avy metal/cm. To convert this to more u seful units, the output was multiplied by [Proprietary Information] (unit conversion) by [Proprietary Information] (the height of the fuel meat in each fuel element), and then b y [Propri etary Inform ation] (SCALE normalizing factor) and further divided by [Proprietary Information] (the number of targets in the model) to produce average target va lues in units of grams , curies, or watts , as a pplicable. F inall y , a power correction was app lied. The output of the calculation do es not represent a core that could be configured to meet the technical s pecification s of the OSTR because the total power exceeds the license limit. However , becau se the production of i so top es is largely go in g to be a function of the target power , this calculation was useful to predict the quantity of isotopes ba sed on the distribution of isotop es identifi ed by SCALE at the identifi e d power. The average po wer per tar get predicted b y the SCALE modeling was estimated to be [Proprietary Information]. Other wor k usin g the Monte Carlo N-Particle (MCNP) simulation on the OSTR an d MURR reactors estimated prototypical target po wers to be [Proprietary Information]. 4-61 .... :: .. NWMI ...... .......... ' *.* NOmfWEIT MEDICAL tsOTOPH NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The photon source strength for the NWMI shielding analysis was determin e d based on the ac tivity associated with [Proprietary Information] for different process strea ms and initial decay times because the MURR irradiated targets will present the highest so urce term. Photon source spectra are computed based on the associated radioisotope inventories for each process stream. The ORIGEN-S code was then used to evaluate the source photon spectra at the indicated minimum deca y time an d a t subsequent decay time s for each process stream. Photon spectra were evaluated using a 19 energy group structure t hat was based on the SCALE V7 27NI9G gamma library. A suitable bremsstrahlung ma ster photon library was employed to capture the effects of bremsstrahlun g radiation production associat e d with bet a deca y processes in the process streams. For the preliminary safety analysis phase of the NWMI project, photon source terms were ge nerated for the proces ses associated with the targets, penci l tanks, carbon bed absorber, waste containers, and hot cell walls. The generated photon source terms were then incorporated into the Monte Carlo transport models for analysis. 4.2.3.2 Shield Wall Material Composition Except as noted below , material compositions for shielding walls were obtained from the SCALE Standard Composition Library. The SCALE Re g-Concrete composition at 2.3 g/c m 3 was used for the concrete material description. This represented density is conservatively lower than those l isted for ordinary concretes in Table I of ANSl/ANS-6.4 , Nuclea r Anal y sis and Design of Co n crete Radiation S hi eldi n g/o r Nuclear Power Plants. The lead-glass composition is based on the composition for glass code R WB46 offered by Radiation Protection Products, Inc. Relevant models employing leaded glass report results in both thickness and areal density. The areal density results are not sensitive to the particular leaded glass composition and were used to determine the required thickness for alternative leaded glass compositions. The compositions and number densities of [Proprietary Information] were obtained using the SCALE Material Information Processor solution model. The solidified hi g h-do se waste stream is represented based on ma sses for water, solidifying agent, and so dium nitrite. No other constituents are credited. Table 4-13 lists materials used in the analysis, along with nominal densities. Number densities are provided in NWMI-2015-SHIELD-OO I , Radi oisoto p e Produ ctio n Facility Shielding Analysis. Table 4-13. Master Material List Material Description A ir Dry a ir l.2929E-0 3 Po l y Polyethylene 9.2 000E-01 Water H 2 0 1.0000 E+OO SS304 Scale SCL SS304 7.9400E+OO Co ncret e Scale SCL Reg-Concrete 2.3000E+OO Target material Target material [Proprietary [Proprietary Information] Information] Car bon Steel Sca le SCL carbo n s t ee l 7.82 12 E+OO Aluminum Scale SCL aluminum 2.7020E+OO Lead Glass Leaded g l ass ( 48% Pb , 15% Ba) 4.8000E+OO UNSol150 (Proprietary Information] (Proprietary Information] GAC G ranular activated carbon [Propri etary In for m a tion] Hdsolid So l idified high-dose waste [Proprietary Information] Ldsolid So lidifi ed low-dose waste [Proprietary Information] So urc e: NWMI-20 15-SHI ELD-OO I , Radioisotop e Produ c ti on Fa c ility Shi e lding A n a l ys i s, Rev. A, Northwest Medical I so topes , LLC, Co r va lli s , Oregon , 2015. Ba Pb u 4-62 barium. l ea d. uranium. UN uran y l nitrate. [Proprietary Information]

.-

;.:. NWM I **.**:** * * *
NOftTHWUl MEDICAL ISOTOPU 4.2.3.3 Methods of Calculating Dose Rates NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description A number of methods have been developed to calculate the penetration of neutrons and photons through material.

For the RPF, a Monte Carlo simulation is used to track particles through the shielding. The Monte Carlo calculation simulates the penetration ofradiation by compiling the life histories of individual particles that move about from the point where they enter the shield to the point where they are either absorbed in the shield or pass through it. The shielding methodology used for ana l ysis of the RPF is consistent with standard industry practice and consists of source term generation, Monte Carlo transport model development, variance reduction technique application , and tally setup. The Monte Carlo transport code MCNP6 version 1.0, developed by Los Alamos National Laboratory, was used to transport photons through the shield material and to determine a subsequent dose rate to the worker and the public. MCNP is a general-purpose Monte Carlo N-Particle code that can be used for neutron , photon, electron, or coupled neutron , photon, and electron transport. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first-and second-degree surfaces and fourth-degree elliptical tori. Pointwise cross-section data typically are used, although wise data are also available. For photons, the code accounts for incoherent and coherent scattering , the possibility of fluorescent emission after photoelectric absorption, absorption in pair production with local emission of annihilation radiation, and bremsstrahlung. Important standard features that make MCNP very versatile and easy to use include a powerful general source, critica l ity source, and surface source; both geometry and output tally plotters; a rich collection of variance reduction techniques; a flexible tally structure; and an extensive collection of cross-section data. MCNP contains numerous flexible tallies: surface current and flux, volume flux (track length), point or ring detectors , particle heating, fission heating, pulse height tally for energy or charge deposition, mesh tallies, and radiography tallies. The number of particles that successfully penetrate the shield divided by the total number of histories is an estimate of the probability that a particle will not be stopped by the shield. For complicated geometries or excessively thick shields, the probability that a partic l e will not be stopped by the shield is so low that statistically meaningful results for such events would require large numbers of particle histories such that the computer run times would for all practical purposes approach infinity. Variance reduction techniques are used in Monte Carlo analysis to reduce the excessively long run times for simulation of such rare events to practical magnitudes. Variance reduction techniques include geometry splitting and Russian roulette, energy splitting and Russian roulette , exponential transform , implicit capture and weight cutoff , energy weight windows, and next event estimator. The next event estimator was used for the simpler geometries modeled for the RPF , including the targets , pencil tanks, carbon bed absorber, high-dose waste container, and low-dose waste container. For the hot cell walls , the deep penetration through the thick concrete requires a bit more sophisticated variance reduction technique. Therefore, energy-dependent, mesh-based weight windows were used to accelerate the simulation of particle transport through the hot cell walls. Tallies were used to score particles when they emerge from the shield material and form the basis for the results reported in any shie l d i ng or dose assessment. For the RPF, the tally was recorded as dependent particle flux. To obtain meaningful results, the energy-dependent particle flux was convolved with a response function of interest. The response function used for the NWMI calcu l ations was the In t ernationa l Commission on Radiation Protection (ICRP) 1974 photon flux-to-dose conversion factors. 4-63 NW Ml-2015-0 21, Re v. 3 Cha pter 4.0 -R PF Desc ripti on For the NWMI target a n a l ysis, ring detector tallies are placed at the surface, 1 m, 2 m, 3 m , and 4 m from the target material axial midpoint [Propr i etary Information]. For the NWMI pe n cil tank analysis, and-ring detector tallies were placed at the tank content axial midpoint, at the surface, and at 1 m , 2 m, 3 m, and 4 m. The response functions for the penci l tank were normalized to the number of batches represented in the model. [Proprietary Information]. For the carbon bed absorber analysis, point detector and ring detector tallies were placed n ea r the surface and at 1 m, 2 m, 3 m, and 4 m from the tank at the axia l mid-plane [Proprietary Informatio n]. For the waste container analysis, point detector tallies were placed at the surface and 1 m, 2 m, 3 m , and 4 m from the container content axia l midpoint [Proprietary Information]. For the hot cell wall analysis, detector tallies were placed at the source location and distributed along the -X direction at the exterior surface and at distances 1 m, 2 m, 3 m, and 4 m away. In addition, detector tallies were included through t h e wall at the inside position, the materia l interface, and at the midpoints of each composite material. Due to the variations in wall thickness, the hot cell wall analysis did not emp l oy dose rate res ponse functions. Instead, direct calculations were made for each case. 4.2.3.4 Geometries The geometries for each of the five process streams modeled using MCNP. 4.2.3.4.1 Target Geo m etry The NWMI target model dimensions are based on reference drawing OSTR-M0-1 00, " Molybdenum Production Project." Materials employed in the mode l are shown Table 4-14. Number densities for each material are provided in NWMl-2015-SHIELD-001. Table 4-14. Target Mo d e l Ma t er i a l s Void Model material Target Claddin g End fitting Bottom washer Top washer Ambient Master material [Propri e tary In fo rm a tion J [Propri e tary Information] [Propri e t a ry In fo rm a tion] [Propri etary Inform a t i on] [P ropri e t ary In fo rm a tion J [Proprietary Inform a tion] [P ropri e t a ry I n form a tion] Density (g/cm 3) [Proprietary Information] [Proprietary Information] [Propriet ary Inform a ti o n] [Proprietary Information] [Propri e t ary inform a tion] [Proprietary Information] [Prop r i e tary Information] Source: NWMI-20 l 5-SHI E LD-00 I , Radi o i so t o p e Produ c ti o n Fa c ili ty Shi e lding A nal ys i s, R e v. A , Northwest M e dical I s otopes , LLC , Corvallis , Oregon , 2015. [Proprietary Information] 4-64

.;. NWMI

::**:*:* ..**.. ' * * ! . NOlffHWlST MEDtcAl ISOTOPH 4.2.3.4.2 Pencil Tank Geometry The models for a 5-inch (in.) Schedule 40S pencil tank were developed based on the data shown in Table 4-15. The tank diameter and wall thickness were taken from standard industry American Society of Mechanical E ngineers (ASME) references.

Other dimensions were assume d ba se d on engineering judgement. The tank contents were represented [Proprietary Information]. Tank walls are modeled as SS304. Number den sities for eac h material are provided in NWMI-2015-SHIELD-001. 4.2.3.4.3 Off gas Carbon Bed Geometry The geometry for the offgas carbon bed was similar to the pencil tank model , but a nominal [Proprietary Information] Schedule 40S pipe was used instead , and the tank content was granular activated carbon at [Proprietary Information]. The dimensions used for the model are s h own in Table 4-16. Number densities for each materia l are provided in NWMI-2015-SHIELD-001. 4.2.3.4.4 Waste Container Geometries Waste container models a re dev e l ope d based on the geometric and materia l data shown in Table 4-17. The high-dose waste container contents are bas e d on streams WOO 15 (Hdsolid, high-dose solidified waste). N umb er densities for each material are provided in NWMI-2015-SHIELD-001. The soli difying agent is ass um ed to be sodium montmorillonite. For the high-dose waste, the sorbent, wa ter , and so dium nitrite were considered. ' ' NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-15 Pencil Tank Model Data Description Outer di ameter Tank wall thickness Tank h e i g ht F loor thickness Roof thickness Floor offset Roof offset Reference ANSI/ ASME 36. I 9M8 Schedule 40S ANSl/ASME 36.19M* Schedule 40S Assumed Assumed Assumed Assumed Assumed .. [Propri e t ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [P roprietary Inform at i on] [Proprietary Information] [P ropr i e t ary Inform a tion] So urc e: NWMI-2015-SHIELD-001 , Radi o i so top e Produ c ti o n Facility Shielding A nalysis , Rev. A , Northwest Medical I soto p es , LLC, Co rv a lli s, Orego n , 20 I 5.

ANSI/ ASME 36. I 9M , Stainless Stee l Pip e, A m e ri can Society of Mechanical E n g in ee r s, 4*h Edition, New York , New York, 2015. Table 4-16 Carbon Bed Model Geometric Parameters Description Reference

.. Outer diameter ANSl/ASME 36.19M* [Propr i etary Schedule 40S I nforma ti on] Tank wa ll thickness ANSl/ASME 36.19M* [Proprietary Schedule 40S Information] Tank h e i g ht Assumed [P roprietary In for m a ti on] Tank separa ti on Assumed [Proprietary ln formation] Sh ield wa ll thickness Assumed [Pr oprie t ary In fo rm at i on]

ANSI/ ASME 36.19M , Stainless Stee l Pip e, Ameri c an So ciety of Mechani c al Eng in ee rs , 4*h Edition , New York , New York, 20 1 5. Table 4-17. Waste Container Geometric Data Container Reference 111111*1111 H i gh-d ose waste C-003-00 1 456-007 ,3 Note 8 5.4583 6.2292 5.89 1 4 0.5 Poly 3785 a C-003-001456-00 7, " Po l y HJ C CRM Flat Bottom Liner ," Re v. 3 , Energy Solutions , Columb i a , South Caro lina. 4-65

.. "NWM I ..... .......... ' *.* NOITHWEST ME.OICAL ISOTOl"E I 4.2.3.4.5 Hot Cell Wall Geometry NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The RPF shield wall model was based on the layout of the dissolution hot cell. The results are not sensitive to the precise hot cell configuration since tallies are taken through the wa ll at a location directl y adjacent to a point source representation of the irradiated target source. The primary bioshield walls of the dissolution hot cell were modeled as a composite of an i nner steel wall and an outer concrete wall. For the composite wall analysis, windows were not represented in the model , and the tally locations were conservatively placed directly adjacent the source. To evaluate the hot cell window , the primary bioshield wall was replaced with a composite of leaded glass window and air. Table 4-18. Material Assignment for S teel/Concrete Composite Wall Model The composite wall materials and thicknesses were parameterized in the model, with values varied to determine the required wall composition to meet an external surface dose rate limit of0.5 mrem/hr. Materials used in the model are shown in Table 4-18 for the steel/concrete composite wall analysis. For the window analysis, model material "Comp W alll" was set to LeadG lass and "CompWall2" was set to Air. Number .. Void Ambient Wall Window Ce ll Wall Ground Outside WindowWell C omp Wall I CompWa112 Floor Master material Void Air Concr e t e LeadGlass SS304 Concrete Air Air Carbon Steel Co n crete Concrete densities for each material are provided in NWMI-2015-SHIELD-OO

1. 4.2.3.4.6 Expected Dose Equivalent Rate s in Air Density (g/cm 3) [Pr o pr ietary Information]

[Proprietary Information] [Propri e t a ry Information] [Proprietary Information] [Propri e t a ry Information] [Proprietary Information) [Propri etary Information] [Proprietary Information] [Propri etary Inform a ti o n] [Proprietary Information] (Prop r i e t ary Informa t i o n] To understand the hazards associated with the radioactive materia l inventory, an estimate of the dose equivalent rate was calcu l ated with MCNP, based on the source spectrums generated from ORIGEN-S for each of the five configurations. 4.2.3.4. 7 Irradiated Target Esti mated Dose Eq uivalent Rate in Air Using the initial target source term from MURR and the methodology described above , the dose equivalent rate for a target in air was calculated as a function of time and distance from the target. Table 4-19 and Figure 4-45 present the results of this calculation for a single target. The earliest time after the EOI was chosen to be [Proprietary Information], which is considered the earliest conservable time after EOI that a target shipment cou ld be received by the RPF from a shipment originating from MURR. Substantial shielding will be required to handle the irradiated targets. 4-66 .. ;.-::***NWMI ..... ........... ' * * ' NORTHWEST MEDtCAl lSOTIWES NWMl-2015-0 21, Rev. 3 Chapter 4.0 -RPF Description Table 4-19. Dose Equivalent Rate from an Irradiated Target as a Function of Time at Various Distances in Air * [Proprietary lnfonnation] [Proprie t ary lnfonnation] [Proprietary lnfonnation] [Propri etary lnfonn ation] [Proprietary Information] [Proprie t ary lnfonnation] [Proprietary lnfonnation] [Proprietary lnfonnat i o n] [Proprietary lnfonnation] [Proprietary ln fonnat ion] [Proprietary Information] (Proprie t ary lnfonn ation] [Proprietary lnfonnation] [Proprietary lnfonnation] [Proprietary Information] [Proprie t ary Inform at i o n] [Proprietary lnformation] [Prop rie t ary In format i on) [Propri etary Information] [P roprietary In forma ti o n] Dose equivalent rate at surface (rem/hr) [Proprietary Tnfonnation] [Proprietary lnfonnation] [Proprietary Information] [Proprie t ary lnfonnation] [Proprietary Informat i on] (Proprietary Infonnation] [Proprietary lnfonnation] [Prop ri etary Infonnation] [Proprietary lnfonnation] [Proprietary lnfonnation] [Proprietary Information] (Propr i etary lnfonnation] [Proprietary Information] (Proprie t ary Information] [Proprietary Information] [Propr i e t ary Information] [Proprietary Information] (Propr i etary Information] (Proprietary lnfonnation] [Prop ri etary Information] Dose equivalent rate at 1 m (rem/hr) [Proprietary lnfonnation] [Prop ri etary lnfonnat i on] [Proprietary Information] [Proprietary lnfonnation] [Proprietary lnfonnation] [Proprie t ary In fonnation] [Proprietary lnfonnation] [P r opr i e t ary lnfonnation J (Proprietary lnfonnation] [Proprietary lnfonn a tion] [Proprietary lnfonnation] [Proprietary lnfonnation] [Proprietary lnfonnation] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [P ropr i e ta ry Information] [Proprietary Information] [Proprietary Information] Dose equivalent rate at 2 m (rem/hr) [Proprietary Information] (Proprietary Infonnat ion] [Proprietary lnfonnation] [Proprietary Infonnation J [Proprietary Jnfonnation] [Proprietary lnfonn ation] [Proprietary lnfonnation] [Proprietary Infonnation] [Proprietary lnfonnation] [Propri etary ln fonnation] [Proprietary lnfonnation] [P ropr i etary lnfonnation] [Proprietary lnfonnation] [Pr oprietary Information) [Proprietary Information] [Pr oprietary Information] [Proprietary Information] (Pr opr i etary In formation] [Proprietary Information] [P roprietary In formation] 4-67 Dose equivalent rate at 3 m (rem/hr) [Proprietary Infonnation] (Propr i etary Infonnation] [Proprietary Information] [Propr i e ta ry lnfonnation] [Proprietary Infonnation] (Proprietary lnfonnation] [Proprietary lnfonnation] [Proprie t ary Infonnation] [Proprietary lnfonnation] [Propr i etary Infonnation] [Proprietary Information] [Proprietary ln fonnation] [Proprietary lnfonnation] [Proprietary Information) [Proprietary Information] [Proprietary In forma ti on] [Proprietary Information] (Proprietary Informat i on] [Proprietary Information] [Proprietary Information] Dose equivalent rate at 4m (rem/hr) [Proprietary lnfonnation] [Propr i etary Inform at ion] [Proprietary Information] [Proprietary lnfonnati on] [Propr i etary Jnfonnation] [Proprietary lnfonnation] [Proprietary lnfonnation] [Proprietary Infonn a ti on] [Proprietary lnfonnation] [Propri etary Infonnati o n] [Proprietary Information] [Proprietary lnfonnation] [Propr i etary lnfonnation] [Proprietary Information] [Proprietary Information] [Propr i etary Information] [Propriet ary Information] (Proprietary Information) [Proprietary Information] [Proprietary Information] .. ;.;; .. NWMI ...... ........ *. ' ; *,* NOfl'THWUT MfDICAl ISOTOPlS [Proprietary lnfonnation] NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description Figure 4-45. Dose Equivalent Rate from an Irradiated Target as a Function of Time 4.2.3.4.8 Recycled Uranium to Target Fabrication Estimated Dose Equivalent Rate in Air The material recei v ed into the target fabrication area will be a purified uranium solution with a concentration of [Proprietary Infonnation]. This time period will allow sufficient time for the [Proprietary Infonnation]. This material will be fed into a 5-in. diameter pencil tank descr i bed pre v iously. Results of the estimated dose equivalent rate as a function of time post-EOI and distance in air are given in Table 4-20. There are two primary observations from the results [Propriet a ry Infonnation]. 4-68 l __ _ NWMI .:.: .. :.:. *.*

NORTHWEST MEDtcAl lSOTOPH NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-20. Target Fabrication Incoming Process Stream Dose Rates Time after irradiation (week) [Propriet a r y Informati o n] [Proprietary In forma t ion] [P ro pr ie t a r y In fo rmat i o n] [Proprietary In formation] (Pr o pr ie t a r y Informati o n] [Proprietary ln forma t K>n] [Pr o pri e tar y In fo r mati o n] [Proprietary ln fo rmatton] (P ro pri e tary In fo rm at i on] [Pr op r ietary In Format io n] (P ro pri e tar y Information]

[Proprietary In fo rmat ion] [Proprieta ry In fo rmat i o n] [Proprietary In formation] [Propri e tar y Informat i o n] [Propr ietary In fo rmation] [P r o pri e tar y Information] [Propr ietary Information] [P ropri e tar y Information) [Propr ietary Information] Dose equivalent rate at surface (mrem/hr) [Propri e t a r y In formati o n] f Proprtetary In fo rmat ion] [P ro pri e t a r y In fo rmati o n] [Proprietary In forma t ion] [P ro pri e t a r y I n fo rmati o n] [Proprietary ln formatton] [P ro priet a r y Informati o n] [Proprietary Informat io n} (Propri e tar y In fo rm ati o n] [Pro pr ietary I n formatio n] [Propri e t a r y I n fo rmati o n] [Propdetary In formation] [Propri e t a r y I n fo r ma t io n] [Proprietary In fo rmat ion J (Pr o pri e tar y In fo r mati o n] [Proprietary In formatio n] [Pr o pri e tar y I n fo rmati o n] [P rop rietar y Informati o n] [Pr o prietar y In format i o n] [Proprietary Information) Dose equivalent rate at 1 m (mrem/hr) [Proprieta r y In fo r mati o n] [Proprietary In fo rmat ion] [Proprletar y I nfor ma ti o n] [Prop r ietary Inf o r mation) (Propriet a r y I n fo rmat io n} [Pro priet ary ln formatKm] [Prop ri etar y Informati o n] [Proprietary Informat ion] [Proprietar y Informat io n] [Proprie t ary In fo rmat ion] [P ro pri e tar y In format io n] [Proprietary Informa tion] (P ro pri e tar y In forma t i o n] [Proprietary In formation] [Prop r ieta r y In fo rmati o n] [Proprietary In fo rmati on] [Propr i eta r y In fo r mati o n] [Proprietary In fo rmat ion] [Propr i etar y Informati o n] [Prop r ietary Information] 4.2.3.4.9 Secondary Carbon Adsorbers Estimated Dose Equivalent Rate in Air The dose equivalent rate off of the dissolver offgas secondary carbon bed is of interest because its function is to delay (i.e., create decay time) the release of the halogen and noble gases by collecting the offgas effluent over time. Table 4-21 shows the weekly average and cumulative dose equivalent rates for the carbon bed assuming a weekly deposition of off gas. Due to rapid decay of the retained radioisotopes , the cumulative dose rate from the carbon bed soon reaches a limiting value after approximately [Proprietary Information]. Dose equivalent rate at 2 m (mrem/hr) (P ro pri e tar y I nformat io n] (Propdetary In formation] [P ro pri e tar y ln fo rmat to n] (Prop r ietar y In formation] [P ro pri e t a r y Informati o n] [Pro pr ietary In formation] [P r o prietar y In fo rmation] [Proprietary In format i on] [Proprietar y I nformation ] [Pro pri etary Information] [Proprietar y I n fo rmati o n] [Proprietary In fo r ma ti on] (P ro p r i e ta ry In fo rmati o n] [P roprietary Information] (Pr o pri e t a r y In fo rmati o n] [Proprietary In fo rmat io n] [P ro pri e tar y I n fo rmati o n] [P ro pri e t ary In fo rmat ion] [Pr o pri e tar y I n fo rmati o n] [Proprietary In formation] Dose equivalent rate at 3 m (mrem/hr) [Proprietar y Informati o n] [Proprietary Information] {P ro pri e t a r y In for m a t krn] [Propdetary In formation] [P ro pri e t ary I n fo rm a ti o n] [Proprietary In fo rmati o n] [Propr ie tar y In fo r mation] [Propriet ary In fo rmati o n] [P ropri e tar y In fo r mation] [Pr oprietary In fo rmati on] (Pr o pri e tar y I n fo rmati o n] [Proprietary lnF ormation] [P ro pr ie tar y In fo rmati o n] [Proprietary Information] [P ro pri e t a r y In fo rmati o n] (P roprietary Informati o n] [Proprietar y Informati o n] [Proprietary Information] [Propri e t a r y Informati o n] [Proprietary Information] Dose equivalent rate at 4m (mrem/hr) (Propri e ta r y In formati o n] [Proprietary Informat ion] [P ro priet a r y In formati o n] [Proprietary In formation) (Proprietar y Informati o n] [Proprietary In formation] [Proprietar y Informati o n] [Proprietary In fo rmat io n] [Pr o prietar y Information] [Proprietary Info rmation] (P ro prietar y I nformati o n] [Proprietary In fo rmatio n] f Propri e tar y I n fo r mat io n] [Proprietary In formation] [Propri e tar y In fo r mat io n] [P r op r te tary I nformati on] [Pr o prietar y In format i o n] [Propr ietary Informat io n] [Pr o prietar y Informati o n] [Proprietary Informat ion] Table 4-21. Carbon Bed Model Dose Rate Results * . Average weekly dose equivalent rate (rem/hr) [Pr oprietary [Propri etary Information) In formation] [Propri etary [Propri etary Information] Inform ation] [Proprietary [Proprietary In fo rmation] In form a ti o n] [Proprietary [Propri etary Information] Informati o n) [Proprietary [Proprietary Information] In formation J [Proprieta ry [Proprietary Information) Inform atio n] [Proprietar y In forma ti o n] [Proprieta ry Information] Cumulative dose equivalent rate (rem/hr) [Proprietary In formation] [Propri etary Information) [Pr o prietary In formation] [Proprietary Informati on] [Proprietary In formation) [Proprietary Informati on) [Propr i etary In formation] 4-6 9 ..... ;.*NWMI .... ** ..*... .......... ' !*.* ' . NORTHWEST MfotCAL ISOTOl'ES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.2.3.4.10 High-Dose Waste Container Estimated Dose Equivalent Rate in Air Each high-dose waste container will hold high-activity waste generated [Proprietary Information]. Results of the bounding estimated dose equivalent rate from a high-dose waste c ontainer as a function of time post-EOI and the distance in air are listed in Table 4-22. Table 4-22. High-Dose Waste Container Bounding Dose Equivalent Rates -. [Proprietary Information) [Propri etary Information] [Proprietary Information] [Proprietary Information J [Proprietary In fo rm ation] [Proprietary Information) [P roprietary In forma ti on] [Proprietary Information] [Proprietary In formation] [Proprietary Information) [Proprietary Information) [Proprietary Information] [Proprie t ary Information) [Proprietary In forma tion] [Prop ri e t ary Information] [Proprietary Information) [Proprietary In forma ti o n] [Proprietary Information) [P rop ri e t ary In format i o n] [Proprietary Information) Dose equivalent rate at surface (rem/hr) (Proprietary Inform a ti o n) [Proprietary Information) (Pro prietary In for mati on) (Proprietary Information] [P roprietary Informati on] [Proprietary Information) [P roprietary In format i on] [Proprietary Information] [Proprietary In for m a ti o n] [Proprietary Information) [Prop rietary Informati on] [Proprietary Information) [Propri etary Inform a ti o n) [Propri etary Information) [Propri etar y In forma ti on) [Proprietary Information] [Propri etary Inform at i on] [Proprietary Information) [Proprietary Inform at ion] [Proprietary Information] Dose equivalent rate at 1 m (rem/hr) [Propr i etary In fo rm ation] [Proprietary Information] [Propr i e ta ry In fo rm ation] [Proprietary Information] [Proprietary Information) [Proprietary Information] [Proprietary In fo rm ation] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information) [Prop ri etary I nformation] [Proprietary Information) [Prop r i e t ary Inform a ti on] [Proprietary Information) [P r op ri e t ary Inform ation] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information) [Proprietary Inform ation] [Proprietary Information] 4.2.3.5 Estimated Hot Cell Wall Thickness Dose equivalent rate at 2 m (rem/hr) [Propr i eta r y In format i o n] [Proprietary In fo rmation] [Propri etary I nfo rmati on) [Proprietary Information] [Propr iet ary In formatio n] [Proprietary Information] [Propri e t ary I nformatio n] [Proprietary Information] [Propri etary In formatio n] [Proprietary Information] [P rop rietar y Information) [Proprietary Information] [Propr i etary In format i on] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary In forma ti o n] [Proprietary Information] [Propri e t a r y In forma ti on) [Proprietary Information] Dose equivalent rate at 3 m (rem/hr) [P roprietary I n format i o n] [Propr ietary I n formation] [P rop ri etary I n formation] [Proprietary I n formation] [Proprietary I n formation) [Proprietary I n formation] [Proprietary I n fo rm at i o n] (Proprietary I n formation] [Proprietary I n for mation] [Proprietary I n formation] [Proprietary I n formation) [Proprietary I n formation) [Prop r i etary I nfo rmation] [Proprietary Information] [Proprietary I nfo rmation] [Proprie tary I n formation) [Propri etary I n forma tion] [Proprietary Information] [Pr op ri etary I n formation] [Proprietary Information J Dose equivalent rate at 4 m (rem/hr) [Propr i etary Informati on] [Proprietary Information] [Proprietary Info rmation] [Proprietary Information] [Proprietary In format i on] [Proprietary Information] [Proprietary Informati on] (Proprietary Information) (Proprietary Information] [Proprietary Information] [Proprietary Information) [Proprietary Information] [P roprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Inform ation) [Proprietary Information] [Proprietary Inform at i on) [Proprietary Information] Based on the source terms identified above, the most important shield i ng consideration will be the thickness of the primary bioshield wall surrounding the hot cells. While not yet determined, the final composition of the hot cell wall will likely be a combination (composite) of both steel and concrete. For the composite wall analysis, a base case was defined as a [Proprietary Information]. MCNP was then used to estimate the dose equivalent rate on the other side of the wall. 4-7 0 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The calcu lated dose equiva lent rate through the composite wall is s hown in Figure 4-46. [Propri etary Information] Figure 4-46. Dose Equivalent Rate Variation through Base Case 120 Centimeter (4-Foot) Composite Wall The linearity of the logarithmic transform of dose eq uival ent rate with thickness ex hibit ed in Figure 4-46 s u ggests that the dose rate variation can be characterized by determining the exponentia l coefficients il 1 and il 2 describing the dose rate decay through the stee l and concrete walls , respectively. For each region i = 1,2 , the dose rate variation through region i is modeled as: Where di-l = d (xi_1) = Dose rate at source-side boundary of region i x 0 = 0 is the inside s urface of the composite wall Eq uation 4-1 To determine the exponent ial coefficients il 1 and il 2 , a series of three cases was executed with a fixed total wall thickness of [Proprietary Information]. The exponentia l coefficient il 1 was then determined by an exponential fit to the calculated dose rate at the extent of the stee l wall d(x 1). The fitted val ue for il 1 was estimated to be [Proprietary Information]. To determine il 2 , Equation 4-1 is first rearranged as follows: 1 _ ln(d 0)-ln(d 2)-il 1 x 1 /l2 -X2-X1 4-71 Equation 4-2 .... ;. NWMI ...... .. *.. .......... ' *

NOtllllfWE.ST Mf.OK:Al ISOTOPH NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description An estimate of il 2 is obtained for each of the three cases, as shown in Table 4-23 , and the average of the three i s taken as the best estimate.

Table 4-23. Estimation of Coefficient ..1.2 [Pr o p r i e t a r y Information) [P ro pri e t a ry Inform a ti o n] (Pr o p r i e t ary Inform a ti o n] [Propri e t a r y In fo rm a ti o n] [P ro pri e t ary Inform a ti o n] [Proprietary Inform a ti o n] [Prop r ietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Informati o n] [Pr oprietary Informati o n] [Prop r ietary In fo rm a ti o n] [Pr opr i e t ary In fo r ma t io n] [P ro pr ietary I nforma ti o n] [P rop ri e t ary In fo rm a ti o n] [P r o pri e t ary In for m a ti on] Average [Proprietary Informati o n) Solving Equation 4-2 for x 1 and setting the through-wall dose rate d 2 to 0.5 rnrem/hr , an expression for the required steel wall thickness as a function of the total wall thickness x 2 is obtained: ln(d 0)-ln(d 2)-il 2 x2 il1 -il 2 Using Equation 4-3 , the required s teel thickness to s hield the design basis source term for various tot a l wall thicknesses is shown in Table 4-24. Table 4-24. Required Steel Thickness in Composite Wall for Various Total Wall T hicknesses Total shield thickness Steel Concrete (cm) (in.) (cm) (in.) [Propri e tary Information] [Proprietary Information] [Propr i etary Information] [Proprietary Information J [Proprietary Information] [Proprietary Information] [Proprietary I n form a ti o n] [Prop ri etary Inform a ti on) [P ropr i e t ary I nfo rm a ti on] [P ro pri etary In fo rm atio n] [P rop ri e t ary In fo rm a ti o n) [P r opr i e t ary In for m ation] [Proprietary Information] [Proprietary Informati o n] [Proprietary Information) [Proprietary In fo rmati o n] [Proprietary Informati o n] [Proprietary Informati o n) [Pro p r ietary Info r m a ti o n] [Pro p r i e t a r y In fo rm at i on] [P ro pri e t a r y In fo rm a t io n) [Pr o prie ta r y I nfo rm a ti o n] [P ro p rietary In fo rm a ti o n] [Pro pri e ta ry In fo rm a ti on] [Propri e tary Information] [Proprietary Information] [Proprietary Information) [Proprietary Information] [Proprietary Information) [Proprietary Information] For the base case [Proprietary Information], the exterior dose equivalent rates are shown in Table 4-25 for various steel wall thicknesses. Table 4-25. Exterior Dose Rates for 120 Centimeter (4-Feet) Total Wall Thickness and Various Steel Thicknesses

- ** I. . [P roprieta r y [Pro pr i e t ary In fo r ma ti o n) In fo rm a ti o n) [Pr o prietary [Proprietary Information]

Informati o n] [P rop ri e t ary [Propri e t ary In for m at i o n) Inform a ti o n) Dose equivalent rate at surface (mrem/hr) [P ro pr ietary In fo rm a ti on] [Proprietary Information] [Propri e t ary Inform a t ion) Dose equivalent rate at 1 m (mrem/hr) [P ro pr ietary In fo r mat i on] [Proprietary Information] [P ro pri etary In fo rm a ti o n] 4-72 Dose equivalent rate at2 m (mrem/hr) [P rop ri e t ary I nfo rm a ti o n] [Proprietary Information] [Pro pr ie t ary In fo rm a ti o n) Dose equivalent rate at3 m (mrem/hr) [Pr o pri e t ary In fo rm a t io n] [Proprietary Information) [P ro pr ie t ary I nfo rm a ti o n] Dose equivalent rate at4 m (mrem/hr) [P ro pri etary In for m a ti o n] [Proprietary Information] [P ro p r i e t ary Inform a ti o n] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description While the final hot cell wall thickness and composition has not yet been determined, the results in Table 4-25 indicate that a wall thickness of [Proprietary Information] can accomp li sh the goal of minimizing the external wall dose rates to 0.5 mrem/hr , significant l y below the 5 rnrem/hr goal. This also represents the thickness required for the lar gest source term. Using the same methodology , the shield wall thickness surrounding the smaller source terms described above is anticipated to be proportionally smaller for the final facility design. 4.2.3.6 Estimated Minimum Hot Cell Window Thickness To analyze the hot cell window thickness needed, the entire hot cell wall was assumed to be made entirel y from leaded glass. The wall thickness was varied to determine the required thickness to meet an exterior surface dose rate of 0.5 rnrem/hr. Table 4-26 lists the dose rate results for a series of four cases with varying window thicknesses. The results suggest that th e required window thickness is [Proprietary Information] with an associated areal density of [Proprietary Information]. If the lead glass composition varies from the composition analyzed here , the same s hi elding effectiveness can be achieved by ensuring that the window has the same required areal density. Table 4-26. Estimated Dose Equivalent Rates on the Outside of the Hot Cell Window ** ** I* I [Propri e tary [Propri e t ary In form a tion] In formation] [Proprietary [Prop rietary Information] lnformation] [P ro pr ie t ary [Propr ietary In fo rm a t io n] ln forma t ion] [Proprietary [Proprietary lnformation] Information] Dose equivalent rate at surface (mrem/hr) [Propriet ary In form a ti o n] [Proprietary lnformation] [P ro pri etary In fo rm a t ion] [Proprietary lnformation] Dose equivalent rate at 1 m (mrem/hr) [Propr ie t a ry In form a ti o n] [Proprietary lnformation] (Propri e t ary lnform a t ion] [Proprietary lnfonnation] Dose equivalent rate at2 m (mrem/hr) [Pr o priet a ry In form a tion] [Proprietary lnformation] [P ropr i e t ary In fo rm a ti on] [Proprietary lnformation] Dose equivalent rate at3 m (mrem/hr) [Propri e t ary lnformation] [Proprietary Information] [Pr o pri e t ary I nfo rm a ti o n] [Proprietary Information]

4.2.4 Calculated

Dose Equivalent Rates and Shield Thickness Requirements Dose equivalent rate at4 m (mrem/hr) (Propri e t ary lnformati o n] [Proprietary lnformation] [P ro pri e t ary ln fo rm a ti o n] [Proprietary Information] The shielding boundary provides shielding for workers and the public during normal operations to reduce worker exposure to an average of 0.5 mrem/hr , or less , in all normally accessible workstations and occupied areas outside of the hot cell. All penetrations will be designed with offset bends or with a labyrinth configuration such that streaming will not occur. In all cases, the shielding thickness required to create a work environment within the limits and parameters found in 10 CFR 20 can be achieved.

4.2.5 Ventilation

Systems for the Biological Shield Structure Summary of Ventilation Systems for the Biological Shield Structure The ventilation around the biological shield structure will be Zone IJ/III supply and the Zone I exhaust. The biological shielding will be subjected to ambient temperature conditions. The Zone I exhaust will provide venti lati on of the hot cell and confinement of the hot cell atmosphere , and maintain the hot cell at negative pressure. The supply air will maintain the temperature for personnel comfort. The process off gas treatment system will provide confinement of the chemical vapors from the process equipment within the hot cell and treat the radioactive offgases through retention , adsorption , and filtration. The facility ventilation system , including the Zone I exhaust and the process v essel ventilation , is described in Chapter 9.0 , Section 9.1. 4-73

4.3 RADIOISOTOPE

EXTRACTION SYSTEM This section describes the radioisotope extraction process from the time irradiated targets enter the RPF through the 99 Mo product shipment. The radioisotope extraction processes will include the major systems listed in Table 4-27, which are described in this section. 4.3.1 Extraction Time Cycle NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description Table 4-27. Radioisotope Extraction Systems System name 1m11.1.1 Irradiated target receipt and disassembly 4.3.2 (irradiated target receipt subsystem) Irradiated target receipt and disassembly 4.3.3 (target disassembly subsystem) Target dissolution Molybdenum recovery and purification 4.3.4 4.3.5 NWMI-2015-RPT-007, Process Time-Cycle Analysi s Report (Part 50 Licens e), was developed to evaluate the time-cycle of the radioisotope extraction process. Results of the evaluation are based on the operating logic and activity durations used as inputs. The time-cycle evaluation presented is based on the current inputs for receiving MURR targets. The sequence is described below and summarized in Figure 4-4 7. Irradiated target receipt -Irradiated targets are transported between the reactor and RPF in a cask and received at the RPF no sooner than [Proprietary Information]. The weekly receipt of irradiated targets from a reactor is assumed to be transported [Proprietary Information]. The receipt activities from cask receipt to transfer to target disassembly, which are described in detail in Section 4.3.2, [Proprietary Information] of the first transfer cask to avoid delaying target disassembly and dissolution activities. Target disassembly -Once the targets are transferred to the disassembly hot cells, the targets will be disassembled and the target material collected. The time for disassembly activities, described in Section 4.3.3, will be [Proprietary Information]. Target dissolution -The target dissolution sequence , described in Section 4.3.4, will begin with preparation activities lasting [Proprietary Information] of the target dissolution process will last [Proprietary Information], from the end of target disassembly to the time the so l ution is transferred to the Mo recovery and purification system. [Proprietary Information]. Mo recovery and purification -The Mo recovery and purification sequence will begin with three exchange separation steps , lasting [Proprietary Information]. A samp le of the r e covered and purified 99 Mo solution will be transferred to a sample container, and the container then transferred to the analytical laboratory for testing , which lasts [Proprietary Information] including transfer time. The transfer of product solution to the product containers is [Proprietary Information]. Loading the product container into the shipping cask and preparing for shipment takes [Proprietary Information]. The activities of the [Proprietary Information]. The relationship and overlap of activities from irradiated target receipt through product shipment is shown in Figure 4-47. [Proprietary Information]. 4-74 [Proprietary Information] Figure 4-47. Extraction Time Cycle NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

4.3.2 Irradiated

Target Receipt Irradiated target receipt will include movement of the cask from the truck , receipt inspection activities, and introduction of the irradiated targets into the target receipt hot cell (H103). The system description also includes content required in NUREG-1537, Guidelines for Pr epa rin g and R eviewing Applications for the Licensing of Non-Power R eacto rs -Format and Content, Chapter 4. 4.3.2.1 Design Basis The irradiated target receipt subsystem will receive irradiated target shipping casks and transfer the irradiated targets to the hot cell for disassembl

y. The design basis for this subsystem is to: * *

*
4.3.2.2 Receive irradiated tar gets in casks per the cask certificate of compliance Provide the capabi lity to complete gas samp lin g of the cask Provide a bridge crane for irradiated target cask handling Provide appropriate space for removal of the impact limiters, etc . Provide a transfer system to move the cask and/or target s from the truck port to a hot cell Meet ALARA principles during target transfer activities System Description The irradiated target receipt system description provides information regarding the proces s, process equipment, SNM and radioactive inventories, and the hazardous chemicals used in the system. The process descriptions (Sections 0 and 4.3.2.2.2) provide a detailed account of the SNM in process during normal operations and provide the basis for equipment design. The arrangement and design of the processing equipment , including norma l operating conditions, are described in Sections 4.3.2.2.3 and 4.3.2.2.4.

These sections describe the equipment in sufficient detail to provide confidence that the SNM and byproduct material can be controlled throughout the process. A description of the SNM in terms of ph ys ical and chemical form, volume in process , required criticality control features, and radioactive in ve ntory in process is provided in Sections 4.3.2.2.5 and 4.3.2.2.6. The ha za rdous chemicals that are used or may evolve during the process, a lon g with the provisions to protect workers and the public from exposure, are described in Section 4.3.2.2.7. These descriptions provide a detailed account of the SNM in process during the cask receipt activ iti es. The SNM, along with any included fission-product radioactivity , is described in Sections 4.3.2.2.5 and 4.3.2.2.6. Based on this description , these operations can be conducted safely in the NWMI RPF. 4-75 .; .. ;. NWMI ..*... ..* .... . *.******** ' *.* NOflTHW£ST M£DtcAt. ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.3.2.2.1 Cask Receipt Process Description A simp lified operational flow di agram for the cask receipt s ub system i s shown in Figure 4-48. [Propri etary Information] Figure 4-48. Cask Receipt Subsystem Flow Diagram The subsystem activities will be gin with the arrival of the truck and lowbo y trailer with the s hippin g cask containing the irradiated targets. The truck , trailer, and shipping cask will ente r the NWMI RPF via an exterior facility hi g h bay door. The truck , trailer , and shipping cask will e nter the facility i n one of the irradiated target receipt ba ys (Figure 4-49 and Figure 4-50). The s hippin g cask will then be documented for material trackin g and accountability requirements. Operators will use the truck bay overhead spray wand for any nece ssary wash-down of the truck, trailer , or shipping cask while located in t h e irradiated t arget receipt truck bays. The truck, trailer, and s hippin g cask w ill then enter the irradiated target receipt ba y via a high ba y door. [Proprietary Information] Figure 4-49. Irradiated Target Handling Equipment Arrangement Plan View 4-76 [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-50. Irradiated Target Handling Equipment Arrangement Isometric View The trailer containing the shipping cask will be positioned between impact limiter removal platform IA (TD-MP-100) and impact limiter removal platform 1B (TD-MP-110), ifentering from the irradiated target receipt truck bay A. The trailer containing the shipping cask will be positioned between impact limiter removal platform 2A (TD-MP-120) and impact limiter removal platform 2B (TD-MP-130), if entering from the irradiated tar get receipt truck bay B. The truck will be disconnected from the trailer and exit the facility via the high ba y doors in which it entered. All high bay doors will be verified to be closed before proceeding with the cask unloading activities. The shipping cask will first be checked for radiological contamination prior to further cask unloading activities. Operators will remove the shipping cask's upper impact limiter using the impact limiter removal platform s (T D-MP-JOO , TD-MP-110 , TD-MP-120 , and TD-MP-130) and facility overhead crane (MH-L-100). The upper impact limiter will then be located in the designated impact limiter landing zone and secured. The facility process control and communications system will be used to noti fy operators in the operating gallery that the BRR shipping cask transfer cart (TD-MC-100) is in position an d ready for shipping cask loading. The operators will then use the facility overhead crane (TD-L-100) to lift and locate the shipping cask onto the transfer cart. The powered transfer cart will transfer the sh ipping cask to the cask preparation airlock. Before the cask enters the cask preparation airlock, operators will be in position , having entered the airlock through the main entry door. The material transfer cart rail switch will be positioned to direct the cart to the desired BRR shipping cask lift (TD-L-110, TD-L-120) located beneath a tar get transfer port (TD-TP-210, TD-TP-220). Once the area is prepared , operators will open the airlock entry door. The powered BRR shipping cask transfer cart will move along the cart rails to the park position on the [Proprietary Information] lift. The airlock entry door will then be closed, with the cask in position and read y for preparation for hot cell transfer. 4-77 ..-----------------

.. NWM I ..... .......... ' * * ! ' NOllTHWUT MEDK:Al ISOTOPf.S NWMl-2015-0 21, Rev. 3 Chapter 4.0 -RPF Description A gas sampling device connected to the cask vent port will analyze the headspace in the cask. Following verification that there is no contamination in the gas sample, the cavity will be vented to the atmosphere to equalize pressure. The cask de-lidding backdraft hood (TD-EN-100) will be used for added protection and remain on throughout the cask lid removal and hot cell docking steps. Hoist rings will be installed in the closure lid , and the lid-retaining screws removed while monitoring for any release of radiation.

The closure lid will be removed using the lid hoist (TD-L-130) and placed on the closure lid stand. The cask sealing surface protector , shield plug restraint, and remote handling adapter will then be installed. Once the cask is prepared , operators will use a human-machine interface to raise the cask using the BRR shipping cask lift (TD-L-110, TD-L-120) to the transfer port sealing surface. Position indicators will signal when the cask's face is at the determined seal compression height. Following the target receipt activities (described in Section 4.3.2.2.2), the transfer cart will move the empty shipping cask to the loadin g/unloading area. The operators will then use the facility overhead crane (TD-L-100) to lift and locate the shipping cask onto the trailer and replace the cask's upper impact limiter. The truck will enter the RPF via an exterior facility high bay door in either irradiated targe t receipt truck bay A or irradiated target receipt truck bay B, depending on which station the trailer and shipping cask are in. Operators will use the truck bay overhead spray wand for any necessary wash-down of the truck while located in the irradiated target receipt truck ba ys. The truck will then enter the irradiated target receipt bay via a high bay door , connect to the trailer, and exit to the irradiated target receipt truck bay. The shipping cask will then be documented for material tracking and accountability requirements. The truck , trailer , and shipping cask will exit the facility via the high bay doors in which it entered. 4.3.2.2.2 Target Receipt Process Descri p tion When the cask is in position and ready for target transfer into the target receipt hot cell (TD-EN-200), the target transfer port (TD-TP-210 , TD-TP-220) will be opened to access the cask shield plug. Using the target receipt hoist (TD-L-200) and the remote hand l ing adapter , the shield plug will be removed and placed on a shield plug stand. Using the target receipt hoist (TD-L-200), the targets will be removed from the cask and placed in the target staging rack. When all tar gets are removed from the cask and placed in the target staging rack , the cask shield plug will be repositioned in the cask by the target receipt hoist (TD-L-200) and the target transfer port (TD-TP-210, TD-TP-220) will be closed. When the cask is ready for removal , the BRR shipping cask lift (TD-L-110 , TD-L-120) will be lowered. The cask de-l idding backdraft hood (TD-EN-100) will provide added protection while operators survey and decontaminate the cask lid area. The shield plug remote handling adapter, restraint , and sealing surface protector will be removed and decontaminated for reuse. The lid hoist (TD-L-130) will be used to install the cask closure lid, the retaining screws installed and torqued, and the vent port plug insta ll ed. The lid area will again be surveyed and decontaminated , as required. The powered [Propr i etary Information] transfer cart will move the empty cask out of the airlock to its par k po s ition in the cask transfer tunnel , and the airlock door closed. The above description provides a detailed account of the SNM in process during the target receipt activities. The SNM, a l ong with any included fission-product radioactivity, is described in Sections 4.3.2.2.5 and 4.3.2.2.6. Based on this description , these operations can be conducted safely in this facility. 4.3.2.2.3 Process Eq ui p m ent Arra n gement The cask preparation air l ock , shown in Figure 4-51 , will be located under the operating ga llery between the shipping cask truck bay and the hot cell. The [Proprietary Information] transfer cart will move the casks into a n d out of the cask preparation airlock. 4-7 8 [Proprietary Information] Figure 4-51. Cask Preparation Airlock NWMl-20 15-021 , Rev. 3 Chapter 4.0 -RPF Description The equipment arrangement within the cask preparation airlock is shown in Figure 4-52. [Proprietary In formation] Figure 4-52. Cask Preparation Airlock Equipment Arrangement 4-79 The equipment arrangement within the target receipt hot cell (Hl02) is shown in Figure 4-53. Casks will be lifted to mate with the target transfer port (TD-TP-210 and TE-TP-220), where the lid hoist (TD-L-310) opens the port. The target receipt hoist (TD-L-200) will remove the irradiated targets from the casks , and targets will be moved by manipulators through the transfer doors to target disassembly hot cells. 4.3.2.2.4 Process Equipment Design During irradiated target receipt activities, the irradiated target material will remain within the targets, and the targets will remain within the shielded shipping cask. Section 4.4.2.9.3 provides a description of the target. The shipping container license describes the shipping cask. Auxiliary equipment will be used to remove the cask impact limiters , move the cask, and mate the cask to the port on the hot cell. This equipment is listed in Table 4-28. NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-53. Target Receipt Hot Cell Equipment Arrangement Table 4-28. Irradiated Target Receipt Auxiliary Equipment Equipment name Impact limiter removal platfonn I A Impact limiter removal platform lB Impact limiter removal platform 2A Impact limiter removal platform 28 Facility overhead crane [Proprietary Information] transfer cart Cask de-lidding backdraft hood [Proprietary Information] lift [Proprietary Information] lift Lid hoist Target receipt hoist Target transfer port Target transfer port [Proprietary Information] Equipment no. TD-MP-JOO TD-MP-110 TD-MP-120 TD-MP-130 TD-L-100 TD-MC-100 TD-EN-110 TD-L-110 TD-L-120 TD-L-130 TD-L-200 TD-TP-210 TD-TP-220 4-80 .; .. ;.NWMI ********** .*.* .. ' * *

NOATHWEST MEDK:Al ISOTOPES 4.3.2.2.5 Special Nuclear Material Description Special Nuclear Material Inventory NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The SNM inventory within the irradiated target receipt system will be determined by the number of targets received by cask shipments in each operating week. The total SNM inventory within the target receipt system will be bounded by the number of targets in the maximum weekly cask shipments.

[Proprietary Information]. Table 4-29 summarizes the irradiated target rec eipt in-process SNM inventory. The target receipt SNM inventory is planned to be [Proprietary Information] (Section 4.3.1). As cask receipt through target disassembly activities are performed, the irradiated target receipt system SNM inventory will be bounded by [Proprietary Information]. Table 4-29. Irradiated Target Receipt In-Process Special Nuclear Material Inventory Stream Form Concentration a SNM mass a Irr adiated targets [Propr i etary lnfonn a tion] [Propri e tary ln fonnation] [Propri etary lnfonn a tion]

SNM concentr a tion and mass repre se nt total amount of LEU (combined m u and 238 U at S 1 9.95 wt% m u). L EU N I A low-enriched uranium. = not a pplicable. SNM = spec ial nucl ear material. (Proprietary In formation]

NWMI-2015-CSE-001, NWMI Pr e liminary Criti c ality Saf ety Eva luati on: Irradiat e d Tar get Handling and Disass e mbl y, describes criticality safety evaluations (CSE) of the irradiated target receipt system performed during preliminary design. Normal operations in the irradiated target receipt cell are intended to be unmoderated. Single param ete r limits for uranium containing 20 wt% 235 U indicate that an unmoderated, but [Proprietary Information] at theoretical density remains subcritica

l. Licensing documentation for the [Proprietary Information]

indicates that a si ngle shipping basket with all positions filled [Proprietary Information]. However, the current double-contingenc y ana l ysis in NWMI-2015-CSE-001 imposes a limit of[Proprietary Information]. Further evaluation of the irradiated target receipt area criticality controls will be performed and included in the Operating License Application. Criticality Control Features Criticality control features are required in this syste m , as defined in NWMI-2015-CSE-OO

l. This evaluation covers handling of the targets beginnin g with their removal from their shipping casks. The criticality control features, includin g passive de sign features and administrative co ntrols , allow for adherence to the double-contingency principle.

This section applies the criticality control features that are described in Chapter 6.0 , "E ngineered Safety Features," Section 6.3. The administrative contro ls and technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0, "Technica l Specifications ." The criticality control features for this subsystem , including passive design features and admi ni s trative controls with desi gnators of PDF and AC, respectively, are listed below. Chapter 6.0 pro vides detailed descriptions of the criticality control features. 4-81 .; ... ;. NWMI ..**.. .. *.. ..... NOfn'HWUTMEOfCAl ISOTOl'lS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The passive design features will include:

Exclusion of liquid lines (CSE-01-PDFl)
Geometry requirements of the basket holding wells within the hot cell (CSE-0 l -PDF2) The administrative controls will include: *
Limited movement to one irradiated target basket at a time (CSE-01-AC4)

Limited number of targets that may be in the target receipt hot cell (CS E-01-AC4) Some or all of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13 .0 , "Accident Analysis ," Section 13 .2. Section 13 .2 provides a description of the IROFS. The following IROFS will be applicable to the irradiated target receipt activities. * * * *

IROFS CS-02 , "Mass and Batch Handling Limits for Uranium Metal , [Proprietary Information], Targets, and Laboratory Samples outside Process Systems ," sets batch limits on samples. IROFS CS-03 , " Interaction Control Spacing Provided by Administrative Control ," defines spacing requirements between irradiated target baskets. IROFS CS-04, " Interaction Control Spacing Provided by Passively Designed Fixtures and Workstation Placement ," affects the location, spacing, and design of workstations.

IROFS CS-05 , "Container Batch Volume Limit ," restricts the volume of the [Proprietary Information]. IROFS CS-08 , "Floor and Sump Geometry Control on Slab Depth , Sump Diameter or Depth for Floor Dikes ," controls the geometry of the floor to prevent criticality in the event of spills. In addition to the features that apply the double-contingency principle, several fe atures will provide defense-in-depth in criticality control. These features will include the followin g. * *

The batch limits in the receipt hot cell are set conservatively low such that the administrative control on spacing can sustain multiple upsets. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed , or stored, as described in Chapter 6.0. The effects of a criticality accident are mitigated by the shielding described in Section 4.2 . The criticality control features provided throughout the irradiated target receipt process will be in accordance with the double-contingency principle, and the RPF will provide suitable defense-in-depth for the contained processes. 4.3.2.2.6 Radiological Hazards This section provides details of the radioactive inventory in process. This section also identifies the essential physical and operational features of the irradiated SNM processing system that are required to prevent the release of radioactive material and to maintain radiation levels below applicab l e radiation exposure limits prescribed in 10 CFR 20 for the protection of workers and public. The analysis in this section is based on information developed during preliminary design. Additional detailed information , including definition of technical specifications , will be developed for the Operating License Application and included in Chapter 14.0. 4-82 Radionuclide Inventory NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes.

NWMI-2014-CALC-O 14 , S e l ec tion of Dominant Targ et I s otop e s for NWMJ Mat e rial Balan ces , identifies the 123 dominant radioisotopes included in the MURR material balance (NWMI-2013-CALC-006). NWMI-2014-CALC-O 14 provides the basis for using the 123 radioisotope s from the total list of 660 radioisotopes potentially present in irradiated targets. The majority of omitted radioisotopes exist in trace quantities and/or decay swiftly to stable nuclides. The reduced set of 123 radioisotopes consists of those that dominate the radioactivity and deca y heat of irradiated targets. Activities during an operating week that proces s targets irradiated in the MURR represent the radionuclide inventory as described in Section 4.1. Targets a rri v i ng in sh i pping casks Targe t s trans f ers to d i sassemb l y hot ce ll s The radionuclide inventory will be based on a [Proprietary Information]. The targets will be received in the target receipt system and staged for transfer to the target disassembly hot cells. Figure 4-54. Target Receipt In-Process Ra d i onu clide Inventory Streams Figure 4-54 provides a simp l ified description of the process streams used to describe the in-process radionuclide inventory. The in-process radionuclide inventory of the irradiated targets is listed in Table 4-30 , assuming all [Proprietary Information] could be stored in the target receipt hot cell and neglecting deca y that occurs during the time to perform receipt activities. Ta bl e 4-30. Irradiated Target Rece i pt Radion u c li de I n-P r ocess Inventory (3 pages) Item MURR target processing Unit operat i on Target r ece ipt Decay Ti m e after EOI" [Propri e tary I nformation] 241 Am [Proprietary lnformation] I 3 6m Ba [Proprietary Information] I37mBa [Proprietary lnformation] 1 3 9 Ba [Propri e t ary Information) 140 83 [Proprietary Information] 14 1 ce [Propri etary Information] 143Ce [Proprietary Information] 144 Ce [Propri e tary Information] 242cm [Proprietary lnformation] 2 4 3 Cm [Proprietary Information] 244Cm [Proprietary Information] 134 Cs [Proprietary Information] I34mcs [Proprietary Information] 1 3 6 Cs [P ro pr i e tary In fo rm a ti o n] 137 Cs [Proprietary Information] 4-83 Item 103 mRh 105 Rh 106 Rh 10 6 mRh 1 0 3 Ru 1o s Ru 1 06 Ru 122sb 1 2 4 Sb 125 Sb 126 Sb 127 Sb MURR target processing Tar g et receipt [Propri e tary Information] ---[Proprietary Information] (Propri e tary Information] [Proprietary Information] [Propri e t a ry Information) [Proprietary Information] (Propri e t a ry Informati o n] [Proprietary Information] (Propri e tary Information] [Proprietary Information] [Proprietary Information] [Proprietary In formation] [Proprietary Information] (Proprietary Information] [P ro pri e t a ry In fo rm a ti o n] [Proprietary Information]

.-.;. NWMI ...*.. .. ... .......... ' *. * ' NOITHWEST MEDtcAL ISOTOP'U NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-30. Irradiated Target Receipt Radionuclide In-Process Inventory (3 pages) Item Unit operation Decay Time after E013 1 ss Eu 1 s 6Eu 1 s1 Eu 1 2 91 13 01 1 3 11 1 32 1 1 3 2m] 133 1 133ml 1 34 1 rnr 83m Kr 8 5 Kr 85m Kr 87Kr 8 8Kr 140La 1 4 1La 142La 99 Mo 9 5 Nb 95m Nb 96Nb 97 Nb 97mNb 141 Nd 2 36mNp 231 Np 238Np 23 9Np 2 3 3 pa MURR target processing Target rec e ipt [Propri e t ary Inform a tion] [Proprietary Information]

[Propri e ta ry Information] [Proprietary Information] [Prop rietary In fo rm a tion] [Proprietary Information] [Propr ie t ary Inform a tion] [Proprietary Information] [Propri etary In fo rmati o n] [Proprietary Information] [Prop r i e t ary In for m a ti o n] [Proprietary Information] [P ro p r i e t ary In fo rm a tion] [Proprietary Information] [P ro p rie t ary In fo rmati o n] [Proprietary Jn formation] [Propri e t ary In fo rmati o n] [Proprietary Information] [P rop ri etary In fo rm a t ion] [Proprietary Information] [Propri e t ary Inform a tion] [Proprietary Information] [P ro pri etary Inform a t io n] [Proprietary Information] [Propri e t ary Inform a ti o n] [Proprietary Information] [P ro pr ietary In fo rmati o n] [Proprietary Information] [Propri e t ary Inform a tion] [Proprietary Information] [Propri etary In fo rm a t i on] (Proprietary Information] Item MURR target process i ng I Unit operation: Target rec e ipt I Decay Time after EOl3 [P roprietary Information] ..._ 128 Sb [P ro pri e t ary Inform a ti o n] 1 2 smsb [Proprietary Information] 129 Sb [Propri e t ary Inform a tion] 1 s 1sm [Proprietary Information] 153 Sm [Pro p ri e t ary Informati o n] i s 6sm [Propri e tary Information] s9 sr [Propri e t ary Informati o n] 90 Sr [Proprietary Information] 9 1sr [Propri e t ary Inform a ti o n] 92 Sr [Proprietary Information] 99 Tc [Propr ietary Inform a tion] 99mTc [Proprietary Information] 125m Te [Propr ie t ary Inform a ti o n) 12 1 Te [Proprietary Information] 127 mTe [Propri etary In fo rm a ti o n] 1 29 Te [Proprietary Information] 129 mTe [Pr o pri e t ary Inform a ti o n] l31Te [Proprietary Information] 131m Te [Propr ie t ary Inform a t io n] 132 Te [Proprietary Information] 1 33 Te [Propri e t ary Inform a ti o n] !33 mTe [Proprietary Information] 134 T e [Propri etary In fo rm a tion] 2 31 Th [Proprietary Information] 234 Th [Propri e t ary Information] 232 u [Proprietary Information] 234 u [Propri etary In fo rm a ti o n] 23s u [Proprietary Information] 236 u (Propri etary Inform a ti o n] 23 1 u (Proprietary Information] 238 u [P ro pri e t ary In fo rm a ti o n] 1 31 mxe [Proprietary Information] 4-84 ... ;. NWMI ::*****; .. ........ NORTHWUTMEDICAltSOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-30. Irradiated Target Receipt Radionuclide In-Process Inventory (3 pages) Item ' MURR target processing Item MURR target processing Unit operation Target receipt I Unit operation: Target receipt [Proprietary Information] Decay Time after EOI" [Propri e tary Inform at ion] I Decay Time after EOP tionb ---234 pa 234m pa 11 2p d 147pm J48pm 148mpm J49 pm I SO pffi I Sl pm J42pr J43 pr 144pr 144mpr 14sPr 2Js pu [Proprietary lnformation] [Proprietary ln fo rmation] [Proprietary ln for mati on] [Proprietary lnformation] [Proprietary lnformation] (Proprietary lnformation] (Propri etary lnformation] [Propri etary lnformation] [Propri etary In format i on] [Propri etary lnformation] [Propri etary lnformation ] [Proprietary lnformation] [P roprietary lnform a tion] [Proprietary lnformation] [P roprietary lnformation ] 133 Xe 1JJmxe 135 Xe nsmxe 89m y 90m y 91y 9Jm y 92 y 93 y 93z r 9 s z r 91z r Total C i [Propri etary lnformation] [Proprietary Inform at ion] [Propri e t ary Information] [Proprie tary Information] [P roprietary lnformation] [Propri etary lnformation] (Propri etary lnform a tion] [Propri etary Information] (Propri etary lnform a tion] [Propri etary lnformation] [P roprietary lnformation] [Proprietary Information] (Prop r ietary lnformation] [Propriet ary Information] [Proprietary Information]

In-process inventory based on a [Proprietary Inform atio n], n eg l ecting the time r eq u ired to receive targets in [Proprietary In formatio n]. b Fig ur e 4-54 provide s a s implifi ed de s cription of the process streams indicat e d. c In-proc ess in ventory based on total of [Propri etary Information], repre se nting the weekly process thr oug hput. Normal operation ex pect ed to begin target transfers to target disas se mbly when the tar ge ts become avai l a bl e after receipt from the first s hippin g cask. EO I = e nd of irradiation.

MURR U ni ve r s it y of Mis s ouri R esearch Reactor. Radiologica l Protection Features Radiolo gica l protection features are designed to prevent the release of radioactive materi al and to maintain radiation levels below applicable radiation exposure limits prescribed in I 0 CFR 20 for the protection of workers and the public. These features include defense-in-depth and engineered safety features. The engineered safety features identified in this section are described in Chapter 6.0, Section 6.2. The following defense-in-depth features will provide radiological protection to workers and the public. *

Shipment a nd receipt of radiological material will requir e approved procedures that implement U.S. Department of Transportation (DOT) requirements. The cask lifts and dockin g ports will be equipped with mechanical or electrical interlock s to e nsure cask mating. The cask lifts will have lockin g bar s that prevent lowering of the lift until the bars are removed. 4-85

.. ;. NWMI .... ** ..... .......... * *

NOITHWHT MEDtCAl ISOTOPES NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Descr i ption *
Alarming radiation monitors will provide continuous monitoring of the dose rate in occupied areas and alarm at an appropriate setpoint above background.

Temporary shielding may be used to reduce radiation exposure when i rradiated target baskets are removed from casks. Chapter 13.0, Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the target receipt activities and will provide radiological protection to workers and the public: * *

Cranes and lifts involved in irradiated target receipt will have enhanced procedures (IROFS FS-01) and additional design and testing requirements (IROFS FS-02). The irradiated target cask lifting fixture (IROFS FS-04) design prevents cask tipping or toppling during a seismic event. The high-dose material will be processed inside shielded areas. The hot cell shiel d ing boundary (IROFS RS-04) will provide shielding for workers and the public at all workstations and occupied areas outside of the hot cell. The hot cell liquid confinement boundary (IROFS RS-01 ), which is credited to prevent releases ofliquid , will also prevent the release of the solid target material.

The cask atmosphere will be sampled before the lid is removed (IROFS RS-12), and a local hood will provide ventilation during the lid removal (IROFS RS-13). 4.3.2.2. 7 Chemical Hazards No chemical reagents will be used for irradiated target receipt , and the chemicals hazards of the irradiated target material will be bounded by the radiological hazards. The features preventing relea s e of radioactive material and limiting radiation exposure will also protect workers and the publ i c from exposure to hazardous chemicals.

4.3.3 Target

Disassembly Target disassembl y will include the disassembly of the targets and the retrieva l and transfer of the irradiated target material for processing. This system will be fed by irradiated target receipt, as described in Section 4.3.2. This system will feed the target dissolution system by the transfer of recovered irradiated target material through the dissolver 1 hot cell (H105) and dissolver 2 hot cell (HlOl) isolation door interfaces. The target disassembly system description provides information regarding the process, process equipment , SNM and radioactive inventories , and the hazardous chemicals used in the s y s t em. The process description (Section 4.3.3.1) provides a detailed account of the SNM i n process d u ring normal operation and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions , are described in Sections 4.3.3.2 and 0. These sections describe the equipment in sufficient detail to provide confidence that SNM and b y product material can be controlled throughout the process. A description of the SNM in terms of physical and chemical form , volume in process , required critica l ity control features , and radioactive inventory in process is provided in Sections 4.3.3.4 and 4.3.3.5. The hazardous chemicals that are use d or may evolve during the process, along with the provisions to protect workers and the public from exposure, are described in Section 4.3.4.6. 4.3.3.1 Process Description Two target disassembly stations will be provided , each one dedicated to a single dissolver. A maximum of [Proprietary Information] will be disassembled for each dissolver batch. The target materia l container will be filled with the contents of the targets and then physically transferred to the dissolver and inserted at the start of the dissolution cycle. Individua l targets will be transferred from the target receipt hot cell (H103) into either the target disassembl y 1 hot cell (H 104) or target disassembly 2 hot ce ll (H 102) for processing. 4-86 NWM I ' * *

NOATifWHT MEIHCAL ISOTOf>lS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The targets will be disassembled , and the irradiated target material collected and transferred to either dissolver 1 hot cell (H105) or dissolver 2 hot cell (HlOl). Using hot cell manipulators, a single target will be passed through the transfer door from the target receipt hot cell (H102) into the target disassembly hot cell (H102 , Hl04). The target and the collection container will be scanned and weighed to meet material control and accountability (MC&A) tracking and verification requirements. The target will be fastened into the target cutting assembly spindle, and the collection container will be moved into position beneath the collection hopper. The target disassembly subsystem will disassemble targets and collect irradiated target material.

The following conditions will be required prior to disassembly.

* *
Ventilation inside the hot cell is operable . The fission gas capture hood is on and functional.

The irradiated target material collection container is in position under the target cutting assembly collection bin. The waste drum transfer port is open, and there is physical space to receive the waste target hardware after disassembly and irradiated target material recovery. The operator will activate the fission gas capture hood (TD-Z-310 , TD-Z-410) and the collection hopper vibrator. Using hot cell manipulators, the target cutting tool will be manually advanced by a hand wheel until the tool pierces the target outer wall. The target spindle will be manually rotated by a hand wheel to complete the outer wall cut. The cutting tool will then be manually advanced until the tool pierces the target inner wall , and the spindle manually rotated to complete the inner wall cut. The target disassembly station will open the target. Gases released during opening and removal of the target material will flow to the airspace of the target disassembly station enclosure. The vent gas from the enclosure will discharge at a controlled rate in a separate line to the dissolver offgas system equipment. The target disassembly station will be sealed to minimize leakage. This station will be maintained at a lower pressure than the hot cell to ensure that the fission product gases from any leaks do not flow into the hot cell airspace. The empty target hardware will be retained inside the disassembl y enclosure until outgassing of fission product gases is sufficiently comp l ete. The empty target hardware will then be transferred through an airlock into a waste receptacle. The hot cell manipulators will be used to release each target piece from the spindle, upend it with the open end in the collection hopper , and tap it against the side of the hopper a number of times until it appears that no more irradiated target material remains inside. The hardware pieces will then be placed on the scale for verification that all irradiated target material has been recovered. The collection container will be placed on the sca l e for verification that all irradiated target material has been collected in the container. The waste drum transfer port (TD-TP-300, TD-TP-400) will be opened, and the empty target hardware pieces will be placed in the waste drum for transfer to the waste handling system. The collection container lid will be installed, and the container placed in the target dissolution system transfer drawer. The following equipment will be used in target disassembly 1 or 2: * * *

Target disassembly hoist (TD-L-300) or target disassembly hoist (TD-L-400)

Waste drum transfer port (TD-TP-300) or waste drum transfer port (TD-TP-400) Target cutting assembly (TD-Z-300) or target cutting assemb l y (TD-Z-400) Fission gas capture hood (TD-Z-310) or fission gas capture hood (TD-Z-410) 4-87 NWM I ...... ' ! e

NOfllTHW(Sl MEDtcAL JSOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The need for MC&A equipment has been identified, but has not been defined. Additional detailed information will be provided in the Operating License Application.

The above description provides a detailed account of the SNM in process during the target disassembly activities. The SNM, along with any included fission-product radioactivity , is desc ribed in Section 4.3.3.4. Based on this description, these operations can be conducted safely in this facility. 4.3.3.2 Process Equipment Arrangement The equipment arrangement within the target disassembly hot cell (Hl02 , Hl04) is shown in Figure 4-55. Irradiated targets will be received through the transfer door by manipulator. One-by-one, targets will be loaded into the target cutting assembly (TD-Z-300 , TD-Z-400) under the fission gas capture hood (TD-Z-310, TD-Z-410). [Proprietary Information] Figure 4-55. Target Disassembly Hot Cells Equipment Arr a ngement The targets will be cut, and the target material collected in a container. container will then be transferred to the target dissolution hot cells. The target material collection 4-88

, 4.3.3.3 Process Equipment Design During target disassembly activities , the irradiated target material will be transferred from the target to the target material collection container.

Section 4.4.2.9.3 provides a description of the target. Auxiliary equipment supporting target disassembly , including the cutting assembly , fission gas capture hood , and handling equipment , is listed in Table 4-31. Process Monitoring and Control Equipment Process monitoring and control equipment was not defined during preliminary design. The process description identifies the control strategy for normal NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-31. Target Disassembly Auxiliary Equipment Equipment name Tar g et cutting assembl y fission gas capture hood Target disassembl y hoist Waste drum transfer port Tar g et cutting assembl y Fission gas capture hood Tar g et di s assembl y hoi s t Waste drum transfer port Equipment no. TD-Z-300 TD-Z-310 TD-L-300 TD-TP-300 TD-Z-400 TD-Z-410 TD-L-400 TD-TP-400 operations, which sets requirements for the process monitoring and control equipment, and the associated instrumentation. Other information on instrumentation and controls is provided in Chapter 7.0. Additional detailed information of the process monitoring and control equipment will be developed for the Operating License Application. 4.3.3.4 Special Nuclear Material Description Special Nuclear Material Inventory The SNM inventory within the irradiated target disassembly system will be determined by the number o f targets transferred from the target receipt hot cell for disassembly to prepare a dissolver basket. Targets will be transferred [Proprietary Information] between the receipt and disassembly hot cells. The total SNM inventory within the target disassembly system will be bounded by the number of targets in the maximum dissolver charge. [Proprietary Information]. Each irradiated target is designed to [Proprietary Information]. Table 4-32 summarizes the in-process SNM inventory for an individual tar g et disassembly cell. The target disassembl y SNM inventory is planned to be zero during a majority of the RPF operating week (Section 4.3.1). Two disassembl y hot cells will be available in the RPF and both hot cells could contain an in-process inventory at the same time. During disassembly activities , the maximum disassembly cell in-process SNM in v entory will vary from [Proprietary Information], depending on the target reactor source in a particular operating week. Table 4-32. Individual Irradiated Target Disassembly Hot Cell In-Process Special Nuclear Material Inventory Stream Form Concentration

SNM mass* Irradiated target s [Proprie t ary ln fonn a ti o n] (Propr i etary ln fonna t ion] (Propr ietary ln fo nn a ti on]
S NM concentration a nd mass r e pr e sent total a mount of LEU (c o mbined m u and 238 U at :S 19.9 5 wt% m u). b SNM in-pro cess inv e ntory of an individual di s a ss embl y hot c ell. Tw o di s assembl y h o t c ell s are available and both cell s m ay co nt a in S M inv e ntory at the sam e time. m u uranium-235. SNM = special nu c lear material.

m u uranium-2 3 8. U = uranium L EU low-e nri c h e d uranium. [Proprieta ry Information] N I A not applicable. 4-89 .; ... ;. NWMI ...... .. *.. .......... *.* HOWTHWlST MlrMCAl tSOTOl'll NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description NWMI-2015-CSE-001 describes CSEs of the target disassembly system performed during preliminary design. Normal operations in the target disassembly cell are intended to be unmoderated. Single parameter limits for uranium containing 20 wt% 235 U indicate that an unmoderated, but ideally shaped and reflected [Proprietary Information] remains subcritical. However, the current double contingency analysis in NWMI-2015-CSE-001 imposes a limit of [Proprietary Information] on the disassembly hot cell inventory , combined with ensuring that no liquid lines exist in the disassembly hot cell as a criticality safety control. Current criticality safety controls are based on single parameter limits under flooded condi t ions. The single parameter limit for an ideally reflected and moderated sphere [Proprietary Information]. The single parameter vo lu me limit for a homogeneous [Proprietary Information]. Further e valuation of the target disassembly hot cell criticality controls will be performed and included in the Operating License Application. Criticality Control Features Criticality control features are required in this system , as defined in NWMI-2015-CSE-OO

1. This evaluation covers handling of the targets , beginning with removal from the shipping casks. These features , including passive design features and administrative controls , allow for adherence to the contingency principle. This section applies the criticality control features that a re described in Chapter 6.0, Section 6.3. Technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0. The criticality control features for this subsystem will include the passive design features and administrative controls with designators of PDF and AC, respectively, listed below. Chap t er 6.0 provides detailed descriptions of the criticality control features. The passive design features will include: * *

Exclusion of liquid lines (CSE-01-PDFl)

Geometry requirements of the basket holding wells within the hot cell (CSE-0 l -PDF2) In line HEPA filter installed in the gas capture hood (CSE-0 l-PDF3) The administrative controls will include: *

Limited number of targets that may be in the target disassembly hot cells (CSE-0 l-AC3) Volume limit of the container that collects [Proprietary Information]

during disassembly (CSE-01-AC4) Some or all of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0, Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the irradiated target receipt activit i es. * *

IROFS CS-02 sets batch limits on samples . IROFS CS-04 affects location , spacing , and design of workstations . IROFS CS-05 restricts the volume of the [Proprietary Information]

collection container. IROFS CS-08 controls the geometry of the floor to prevent criticality i n the event of spills . 4-90 NWM I ...... * * ! ' NOWTHWEST MEDICAl ISOTOPl S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description In addition to the features that apply the double-contingency principle, several features will provide defense-in-depth in criticality control. These features include:

The batch limits in the disassembly hot cell will be set conservatively low such that the administrative control on spacing can sustain multiple upsets.
The criticality alarm system will provide criticality monitoring and alarm in all areas where SNM is handled , processed , or stored , as described in Chapter 6.0.
The effects of a criticality accident will be mitigated b y the shielding described in Section 4.2 . The criticality control features provided throughout the irradiated target receipt process will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes.

4.3.3.5 Radiological Hazards This section provides details of the radioactive inventory in process and identifies the essential physical and operational features of the irradiated SNM processing system that are required to prevent the release of radioactive material and to maintain radiation levels below applicable radiation expo s ure limits prescribed in 10 CFR 20 for the protection of workers and the public. The analysis in this section is based on information developed during preliminary design. Additional detailed information, including definition of technical specifications , will be developed for the Operating L i cense Application and included in Chapter 14.0. Radionuclide Inventory A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes. NWMI-2014-CALC-014 identifies the 123 dominant radioisotopes included in the MURR material balance (NWMl-2013-CALC-006). NWMI-2014-CALC-014 provides the basis for using the 123 radioisotopes from the 660 radioisotopes potentially present in irradiated targets. The majority of omitted radioisotopes exist in trace quantities and/or decay swiftly to stable nuclides. The reduced set of 123 radioisotopes consists of those that dominate the radioactivity and decay heat of irradiated targets. Activities during an operating week that proces s targets irradiated in the MURR represent the radionuclide inventory as described in Section 4.1. The radionuclide inventory will be based on a weekly throughput of [Proprietary Information]. Targets will be [Proprietary Information] receipt to the target disassembly hot cells. During MURR [Proprietary Information] Figure 4-56. Target Disassembly In-Process Radionuclide Inventory Streams target processing , four LEU targets will be collected as a dissolver charge in a disassembly hot cell and transferred to one of the dissolver hot cells for processing. Figure 4-56 provides a simplified description of process streams used to describe the in-process radionuclide inventory. The radionuclide inventory will be split among the three streams (disassembly offgas, target cladding, and dissolver charge) in the target disassembly hot cell. 4-91 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF D escription A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 u sing the reduced se t of 123 radioi soto pes. The in-proces s radionuclide invento ry passing through target di sass embl y activities during an operating week is listed in Table 4-33 based on a total of eight MURR targets, neglecting decay that will occur during the time to perform tar ge t receipt and disassembl y ac tivities. Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages) Item Unit operation Deca y t i me after EOI8 Stream desc r ipt i onh Isotopes 24 1Am 1 3 6 mBa 137 mBa 139 B a 140 Ba 14 1ce 1 43 Ce 1 44Ce 2 4 2 Cm 243 C m 244 Cm 1 3 4Cs 134m cs 136 Cs 137 Cs 1 ss E u 1s6Eu 1 s 1E u 129 1 1 3 0 1 131 1 1 3 2 J 132m I 133J 133ml 1 3 4 I 1351 83 mKr 85Kr [Propri etary Informati o n] [Proprietary Information] [Propr ietary Inform ation] [Proprietary lnformation] [Propri etary In fo rm atio n] [Proprietary Information] [P roprietary Inform ation] [Proprietary Information] [Propri etary I nform at i o n] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [P roprietary In fo rm at i o n] [Proprietary Information] [Propri eta r y I nformati o n] [Proprietary I n formation] [Propri e tar y I nformati o n] [Proprietary Information] [Pr op ri et ar y I nformati o n] [Proprietary Information] [Propri etary I nform a ti o n] [Proprietary Information] [Propri e tar y Inform a tion] [Proprietary I n formation] [Propri et ar y Inform at i o n] [Proprietary Information] [P rop ri etary In fo rm ation] [Proprietary Information] MURR target processing Target di sassemb l y [Propri etary Inform ation] Di sassem bl y offgas [Propri etary Informati o n] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Propri e t ary Inform ation] [Proprietary I nformation] [Proprietary Inform ation] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Propri etary Inform at i on] [Proprietary I n formation] [Propri eta r y Inform a ti on] [Proprietary Information] [Propri etary Inform at i o n] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Pr o pri e tar y I nform at i o n] [Proprietary Information] [Propriet ary Inform a ti o n] [Proprietary Information] [Propri etary In fo rm ation] [Proprietary Information] 4-9 2 Di sso l ve r charge Cic [Proprietary Information] [Propri etary Inform a tion] [Proprietary Information] [Propri etary Inform a tion] [Proprietary Information] [Propr ietary Jn formation] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Inform a tion] [Proprietary Information] [Propr ietary Inform ation] [Proprietary Information] [Propr ietary Inform ation] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Propri eta r y Inform a tion] [Proprietary Information] [Propri etary Inform a tion] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri eta r y Information] [Propriet a ry Information] [Propri eta r y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information]

.. NWMI ...... .*.* .. *.*. ' *.*

NOITHWf:ST W:DICAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Descr i ption Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOl3 Stream descriptionb Isotopes 8 5 m Kr 87Kr 88Kr t4oLa 141 La 142La 99Mo 95Nb 95 mNb 96 Nb 9 7 Nb 97m Nb t4 7N d 2 36 mNp 2 3 1 Np 23 8Np 239N p 233 pa 23 4 p a 234 mpa 11 2 pd t47pm t 4&pm t48mpm t49pm 1 s opm 1 s 1 pm t4 2 pr J43pr t44pr 1 44m pr t4 s pr Targets cladding Ci 0 [Propri etary Information]

[Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri eta r y Information] [Proprietary I nformation] [Proprietar y Information] [Proprietary Information] [Propri etary Informati on] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Propri e tar y Information] [Proprietary Information] [Propri eta r y Inform atio n] [Proprietary Information] j [Propri etary Informati o n] I [Proprietary Information] j [Propri etary Informati o n] I [Proprietary Information] I [Propri eta r y Informati o n] I [Proprietary Information] I [Propri etary Information] I [Proprietary Information] I [Propri etary Informati on] I [Proprietary Information] I [Proprietar y Information] I [Proprietary Information] I MURR target process i ng Target disassembl y [Proprietary Information] Di sasse mbly offgas Ci 0 [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propriet a r y Inform a tion] [Proprietary Information] [Proprietary Inform at ion] [Proprietary Information] [Propriet ary Informati on] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Inform a tion] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propriet a r y Inform at ion] [Proprietary Information] [Propriet a r y Inform atio n] [Proprietary Information] [Propri eta r y Inform a tion] [Prop r ietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Informati on] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprieta ry Information] [Proprietary Information] 4-93 Dis so l ve r charge Ci 0 [Proprietar y Information] [Proprietary Information] [Proprietary Inform at ion] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Propri e tar y Information] [Proprietary Information] [Proprietary Inform a tion] [Proprietary Information] [Propri e tar y Information] [Proprietary Information] [Propri etary lnfonnation] [Proprietary Information] [Propri e tar y Infonnation] [Proprietary Information] [Propri e t a r y Information] [Proprietary Information] [Propri etary Inform at ion] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Proprietary Inform a tion] [Proprietary Information] [Propriet ary Information] [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOP Stream descriptionb Isotopes 23 8 pu 23 9pu 240 pu 2 4lpU !03m Rh 105Rh 106 Rh 106mRh 103 Ru I OS Ru 10 6 Ru 122 sb 1 24 Sb 125 Sb 126 Sb 127 Sb 128 Sb 12smsb 129 Sb 1 s 1sm 153 Sm i s 6sm s9s r 90 Sr 91 sr 92 Sr 99 Tc 99m Tc 1 25m T e 121Te 1 27m T e 129Te J 29m T e 131Te Targets cladding Ci 0 [Proprietar y Information] I [Proprietary Information] I [Propri e tar y Information] I [Proprietary Information] I [Proprietary Information] I [Proprietary Information] I [Propri etary Information] I [Proprietary Information] I [Propri etary Inform atio n] I [Proprietary Information] I [Proprietar y Information] I [Proprietary Information] I [Proprietary Information] I [Proprietary Information] I [Propri eta r y Informati o n] I [Proprietary Information] I [Propri etary Inform atio n] I [Proprietary Information] I [Propri e tary Inform atio n] I [Proprietary lnformation] I [Proprietar y Information] I [Proprietary Information] I [Proprietar y Inform atio n] [Proprietary Information] [Propri e tar y Inform at i o n] [Proprietary Information] [Propri eta ry Information] [Proprietary Information] [Propri e tar y Inform at ion] [Proprietary Information] [Propri e tar y Informati o n] [Proprietary Information] [Propri etary Informati o n] [Proprietary Information] MURR target processing Target di sasse mbly [Propriet a r y Inform at ion] Di sasse mbly off gas [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Inform at ion] [Proprietary Information] [Propri etary Inform at i on] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprieta ry Informati on] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] 4-94 Di sso l ver charge [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propriet a r y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Descript ion Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOI" Stream descriptionh Isotopes 131m Te 132 Te 133Te 133mTe 134Te 231 Th 234Th 232u 234 LJ mu 236 LJ 231u 238 LJ 1 J 1mxe 133 Xe J33mxe 135 Xe 1Jsmxe 89my 90y 90my 9Jy 91my 92y 93 y 93 zr 9 s zr 91zr Total C i MURR target processing Target di sasse mbl y [Proprietary Inform ation] Targets claddin g Di sasse mbly offgas Cic Cic [Proprietary Information] I [Proprietary Informati on] [Proprietary Information] I [Proprietary Information] [Proprietary Informati on] I [Propri etary Information] [Proprietary Information] I [Proprietary Information] [Propri etary Informati o n] I [Proprietar y Inform ation] [Proprietary Information] I [Proprietary Information] [Propri etary Informa tion] I [Proprietary Inform ation] [Proprietary Information] I [Proprietary Information] [Proprietary Information] I [Proprietary Inform ation] [Proprietary Information] I [Proprietary Information] [Propri etary Information] I [Propri etary Information] [Proprietary Information] I [Proprietary Information] [Propri etary Information] I [Propriet a ry Inform at ion] [Proprietary Information] I [Proprietary Information] [Propri etary Informati on] I [Propri etary Inform ation] [Proprietary Information] I [Proprietary Information] [Propr ietary Informati on] I [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information] I [Proprietary Inform ation] [Proprietary Information] I [Proprietary Information] [Proprietary Information] I [Propriet ary Inform a tion] [Proprietary Information] I [Proprietary Information] [Proprietary Information] I [Proprietar y Inform at ion] [Proprietary Information] I [Proprietary Information] [Proprietary Informati o n] I [Propri etary Inform a tion] [Proprietary Information] I [Proprietary Information] [Propri etary Information] I [Proprietar y Information] [Proprietary Information] I [Proprietary Information] [Propri etary Information] I [Proprietary Information] Dis so lver charge CiC [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information]

In-process invent ory b ase d [Proprietary Informati o n], n eg l ecting tim e required to r ece ive and di sassemble tar ge t s. b Figure 4-56 p rovides a s implifi ed description of th e process s tr eams. c In-process in ve ntory based [Proprietary Informati o n], repre se ntin g the weekly pro cess throughput.

Normal o peration expected to prepare a dissolver charge [Proprietary Inform atio n] such that the in-process inventory of an individual tar get di sasse mbly cell is described by one-half the listed radionuclide in ve nt ory. EOI = end of irradiation. MURR = Un iv e r sity of Missouri R esearch R eac tor. 4-95 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The radionuclide inventory of target transfers from target receipt is listed in Table 4-30 , recognizing that a target enters a disassembly hot cell one at a time. Based on preparing a dissolver charge containing [Proprietary Information], the in-process inventory of an individual target disassembly hot cell is described by one-half the radionuclide inventory listed in Table 4-33. Radiological Protection Features Radiological protection features are designed to prevent the release of radioactive material and to maintain radiation le v els below applicable radiation exposure limits prescribed in 10 CFR 2 0 for the protection of workers and the public. These features include defense-in-depth and engineered safety features. The engineered safety features identified in this section are described in Chapter 6.0, Section 6.2. The following defense-in-depth features will provide radiological protection to workers and the public: *

The workspaces within the target disassembly hot cells are designed to contain spilled material.

Alarmin g radiation monitors will provide continuous monitoring of the dose rate in occupied areas and alarm at an appropriate setpoint above background. Chapter 13.0 , Section 13.2 , provides a description of the IROFS. The followin g IROFS w i ll be applicable to the target disassembly activities and will provide radiological protection to workers and the public: *

4.3.3.6 The high-dose material will be processed inside shielded areas. The hot cell shielding boundary (IROFS RS-04) will provide shielding for workers and the public at workstations and occupied areas outside of the hot cell. The hot cell liquid confinement boundary (IROFS RS-01), which is credited to prevent releases of liquid , will also prevent the release of the solid target material.

Radioactive gases will flow to target dissolution offgas treatment , which is part of the hot cell secondary confinement boundary (IROFS RS-03). Chemical Hazards No chemical reagents will be used for target disassembly, and the chemicals hazards of the target disassembly process will be bounded by the radiological hazards. The features preventing release of radioactive material and limiting radiation exposure will also protect workers and the public from exposure to hazardous chemicals.

4.3.4 Irradiated

Target Dissolution System The target dissolution system description provides information regarding the process , process equipment, SNM and radioactive inventories , and the hazardous chemicals used in the system. The process description (Section 4.3 .4.1) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions, are described in Sections 4.3.4.2 and 4.3.4.3. These sections describe the equipment in sufficient detail to provide confidence that the SNM and byproduct material can be controlled throughout the process. A description of the SNM in terms of physical and chemica l form , volume in process , required criticality contro l features, and radioactive inventory in process is provided in Sections 4.3.4.4 and 4.3.4.5. The hazardous chemicals that are used or may evolve during the process, along with the provisions to protect workers and the public from exposure, are described in Section 4.3.4.6. 4-96 NWMI ...... *

NOITHWHT MEIHCA&. tSiOTOflH 4.3.4.1 Process Description NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The target dissolution system will begin with the receipt of irradiated target material from disassembled targets that is passed to one of the target dissolution hot cells. The target dissolution system wi ll then dissolve the target materia l , treat the offgas , and transfer the concentrated uranyl nitrate solution from the dissolver hot cells to feed tank IA and feed tank lB (MR-TK-100 and MR-TK-200) in the Mo recovery and purification system. Any solid waste generated in the target dissolution system will feed the waste handling system through the dissolver waste drum ports (DS-TP-100 and DS-TP-200) where the solid waste drums are transferred. The target dissolution process will be operated in a batch mode. The targets will be disassembled one at a time , and the irradiated LEU target material will be transferred to a collection container.

The collection container will move throug h the pass-through to a dissolver basket positioned over a dissolver, the target material dissolved, and the resulting so luti on transferred to the separations step. Dissolution Process Description The function of the dissolution process is to dissolve the irradiated target materia l to uranyl nitrate so the 99 Mo can be extracted from the solution. Figure 4-57 provides a summary of the major process flows for the target dissolution process steps. The irradiated targets will be opened , and the contained LEU target material removed and placed in collection containers. Using hot ce ll manipulators, a single container will be passed through the transfer door from one of the target disassembly hot cells into the corresponding dissolver hot cell. The dissolver basket will be positioned and fastened into the dissolver basket filler (DS-Z-100). The target material container will then be manipulated to transfer the irradiated target material from the container into the dissolver basket. [Proprietary Information] Figure 4-57. Simplified Target Dissolution Flow Diagram 4-97 .; ... ;. NWMI ...... .. .. .......... ' ; * * ! ' NOllTHWEST M£OICAL ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The container will then be scanned and weighed to verify that all irradiated target material has been transferred per the MC&A requirements. The hot cell manipulator will be u s ed to return the empty collection container into the dissol v er 1 hot cell isolation door for transfer back to the target disassembly 1 hot cell (H 104 ). The LEU collection container transfer activities and dissolver basket filling operations will be repeated as required for the quantity of collection containers in the specified dissolver batch. Detailed design of the dissolver baskets and associated handling mechanisms is yet to be developed. Preliminary analysis indicates that the dissolver baskets will have an [Proprietary Information]. When handling the fixture and bottom support plate, the overall height of a dissolver basket is expected to be between [Proprietary Information]. The dissolver baskets will be made of a screen material that is open on top. Stainless steel or other corrosion-resistant metal is assumed to be the primary material of construction for the dissolver baskets. Each dissolver basket will hold the irradiated LEU t arget material for a full dissolver batch. The dissolver design includes a valve arrangement allowing placement and remova l of a dissolver basket. To initiate dissolution , the operator will open the valve assembl y, and the dissolver hoist will lift a dissol v er basket from the filling station and lower it into the dissolver (DS-D-100/DS-D-200). Markings on the hoist cable will indicate when the basket is at the proper position, and the hoist hook wi ll be disengaged from the basket and raised out of the dissolver and valve assembly. Concentrated nitric acid will be added to submerge the irradiated target material and heated to near-boil i ng temperatures (about 100 to 120 degrees Celsius [°C]). The heat-up rate will be controlled to prevent excessive foaming. The [Proprietary Information]: [Proprietary Information] The mass balance calculations in NWMI-2013-CALC-002 , O ve rall Summa ry Mat e rial Balanc e -OS U Tar ge t Bat c h , and NWMI-2013-CALC-006 provide detailed descriptions of the feed and product streams. The initial concentration of the nitric acid for the dissolution batch is [Proprietary Information] (NWMI-2013-CALC-013 , Irradiat e d Targ e t Di sso lution S y st e m Equipm e nt Si z ing). Based on these concentrations and a [Proprietary Information]. Dissolution with nitric acid will produce nitrogen oxide gases (NO x) and evolve gaseous fission products. The offgas treatment is described in the following section. In addition to the g a seous fiss i on products , the intense radiation field in the dissol v er will generate hydrogen and oxygen gas in the dissol v er due to radiolysis of water. A sweep gas during dissolution will limit the concentration of flammable gases to less than 25 percent of the lower flammabi li ty limit. When dissolution i s complete , the uranyl nitrate solution will be cooled enough to allow pumping and will then be transferred to the Mo recovery and purification system. The solution will be passed through a strainer during the transfer to remove residual suspended solids. After the uranyl nitrate system is transferred to the Mo recovery and purification system , the dissolver valve assemb l y will be opened for dissolver basket removal. The dissolver hoist hook will be lowered down through the v alve assembl y and into the dissolver until markings on the h oist cable indicate that the hook is at the proper position. The hoist hook will be engaged with the basket and raised out of the dissolver and valve assemb l y , and the basket will be placed in the drying area within the hot cell. 4-98 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Nitrogen or air will be used to purge the dissolver at the end of dissolution. This proces s will reduce the concentration of radioactive gases in the dissolver to minimize the risk ofrelease into the cell airspace when the dissolver entry valves are opened to allow fresh target material to be added for the ne xt batch. Between dissolver batches , the dissolver and offgas sys t em will be filled with nitrogen or air to prevent buildup of flammable hydrogen gas mixtures. Contin uou s sweep gas flow is not expected to be required for hydrogen mitigation during these periods. Dissolver Offgas Process Description The dissolver offgas wi ll consist ofNO x, nitric acid vapors , water vapor , and gaseo u s fission products (iodine [I], Xe, and Kr). The first step in offgas treatment will be removing the NO x and nitric acid vapors , followed by treatment of the gaseo u s fission products. The gaseous fissio n products from the offgas treat ment will be mixed with the offgas from the target disassembly activities. Iodine will be absorbed from the offgas stream by the iodine remova l unit (IRU). The release of other gaseo u s fission products will be delayed by adsorption beds to allow sufficient decay. The followi n g sub s ystems will comprise the dissolver offgas treatment process: * * *

NO x treatment 1 NOx treatment 2 Primary fission gas treatment Secondary fissio n gas treatment Waste collection NOx Treatment De scrip tion The NO x treatment subsystem will remove NO, nitrogen dioxide (N0 2), HN0 3 , water vapor, and a portion of the iodine from the dissolver offgas. Removal of these components will substantially reduce the total volume of the gas stream and provide a composition suitable for u se in the downstream fission gas retention eq uipm ent. The NO x treatment design is based on minimizing total net gas flow from the dissolver a nd offgas system to minimize impacts to the required fission gas retention equipment size. Two trains w ill be provided for NO x treatment, one d edicated to eac h dissolver (DS-D-1 OO/DS-D-200) where the condensers (DS-E-1 30/DS-E-230) are mounted above the dissolvers.

The downstream equipment for control of fission product gases will be s hared between the two dissolver syste m s. Gas components removed by this system wi ll includ e nitrogen oxides (NO and N0 2), and carbon dioxide (C0 2) gases plus water (H 2 0) and HN0 3 vapors. To facilitate the dissolution and offgas treatment processes , a sma ll amount of air or oxygen wi ll be added to the dissolver. A portion of the oxygen will react with the dissolver so luti on to reduce acid consumption and reduce NO x generation. The balance of the oxygen will mix wit h the evolved gases and continue to react with nitric oxide (NO) in the downstream process steps. Secondary reaction s between NO x gas species , water, nitric and nitrous acids, and oxygen will take place b y the reactions shown in Equation 4-4 and Equatio n 4-5. The production of nitric acid will reduce the amount of nitric acid initially required. The N0 2 produced will be more readily reacted and absorbed b y scrubbing so lution s. Eq uation 4-4 Equation 4-5 4-99 .; ... : NWMI ...*.. ..* .. * * * *

NOITlfWEIT MlotCAl ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description From the dissolver, the offgas will flow to the dissolver offgas condenser (DS-E-130 or DS-E-230).

In the condenser, the stream will be cooled, condensing water and nitric acid vapors. N0 2 will be absorbed into the condensate, producing additional HN0 3 and NO , while oxygen will react with NO present in the off gas producing additional N0 2. The condensed nitric acid stream from the condenser will drain back to the dissolver. The recycled acid will reduce the amount of acid needed in the initial dissolver charge. Vent gas from the dissolver offgas condenser will flow to a primary caustic scrubber (DS-C-310 or DS-C-410), which will remove most of the remaining NO x by reaction with a sodium hydroxide (NaOH) solution to produce a sodium nitrate/nitrite solution. [Proprietary Information] may be added to the scrubber solution ifneeded to improve NO x removal. Any C0 2 in the condenser vent stream will also be removed by reaction with NaOH , producing sodium carbonate. Reaction of ox y gen and NO will continue in the primary caustic scrubber, further reducing the NO concentration. The primary caustic scrubber will also be expected to remove a substantial fraction of radioiodine present in the off gas stream. In the primary caustic scrubber , the gas/liquid contact will be performed in a vertical column. As an initial step, scrubbing solution will be injected into the gas stream via a venturi scrubber or spray nozzle. The mixture will then flow into the bottom of the column, where the gas and liquid separate. The gas will flow upward through the column packing, and the liquid will collect in a reservoir at the bottom of the column. Cooling water flowing through a coolin g coi l or jacket wil l remove the heat generated by the reactions. Additional scrubbing solution will be added at the top of the column and flow downward through the packing , where it will contact the up-flowing gas stream to remove additional NO x. At the bottom of the column , the liquid will collect in a reservoir. The gas will exit through a pipe at the top of the column. From the primary caustic scrubber (DS-C-31O/DS-C-410), the gas will flow to a NO x oxid i zer (DS-C-340 or DS-C-440), where it will be contacted with a liquid oxidant solution to convert the rem a ining NO to N0 2. A number of reagents ma y be considered for the liquid oxidant , including sodium h y pochlorite , hydrogen peroxide , potassium permanganate , sodium percarbonate, and sodium persulfate. Sodium hypochlorite is used commercially for this purpose , but is undesirable for this application due to potential corrosion problems related to the added chloride. In the current analysis , [Proprietary Information] will be the assumed oxidation agent. The g as will flow from the NO x oxidizer to a NO x absorber (DS-C-370 or DS-C-470), where it will be contacted with a solution of [Proprietary Information to remove the remaining N0 2. Treated gas from the NO x absorber will flow to the fission gas retention equipment. During upset conditions when the offgas treatment loses vacuum, a pressure relief confinement tank (DS-TK-500) will contain the offgas until the gas treatment equipment is operational. A pressure relief valve connected to the NO x absorber will evacuate the dis s olver offgas during loss of vacuum. The pressure relief confinement tank will normally be maintained under vacuum. Further detail on the pressure relief confinement tank is provided in Chapter 6.0. Fission Gas Retention Process Description Irradiated target material will have a high content of short-lived radioisotopes of iodine and noble gases (Xe and Kr). These isotopes will be released as gases during the dissolution process. The high radioactivity and mobility of these isotopes will require stringent measures be taken to control their movement and release. The primary functions of the fission gas retention equipment will be to remove radio iodine from the gas stream and to delay release of the noble gases (Xe and Kr) sufficiently to allow release to the stack. The fission gas retention equipment will also provide primary confinement of the gases to prevent their release within the facility. 4-100 .. ..... .......... ' *.

NOflTHWEST MEOICAl ISOTOf'f S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Emissions modeling has not been finalized; however, preliminary estimates suggest that the required overall decontamination factor for iodine could be on the order of [Proprietary Information].

Several sequential iodine removal steps will be included in the overall dissolver offgas treatment process to achieve the required iodine removal. Each step is an important component of the overall approach but is not required to perform the full iodine control function. The dissolver and NO x treatment systems are expected to retain [Proprietary Information of the iodine from the target material. Each IRU (DS-SB-600NB /C) is expected to retain [Proprietary Information] of the iodine in its inlet gas stream, and the primary adsorbers (DS-SB-620NB /C) and iodine guard beds (DS-SB-640NB /C) are expected to retain [Proprietary Information] of the iodine in their inlet gas streams. The combined iodine decontamination factor of these units is expected to well exceed [Proprietary Information]. As part of the overall approach, a key function of the IRUs will be to reduce the iodine content sufficiently so that the radiation dose rate and heat generation from absorbed iodine does not significantly reduce the performance or life expectanc y of the downstream primary adsorbers. The primary adsorbers and iodine guard beds will then remove the remaining traces of iodine that are not removed by the IRUs. A radiation detector will be placed on or downstream of each iodine guard bed to verify that the iodine has been adequate l y removed. To increase sensitivity , the radiation detector may use a solid iodine sorbent to collect residual iodine in the vent gas , coupled with a radiation detector that will monitor for any significant buildup of radiation dose rate on the sorbent material. Within the offgas treatment systems, the IRUs and the secondary adsorbers will be the primary unit operations responsible for retaining the iodine and fission product noble gases. The configuration of this offgas equipment will be three trains operating in parallel. Vent gas from the NO x absorbers will flow t o IRUs (DS-SB-600NB /C). The IRUs wi ll absorb iodine [Proprietary Information]. Remaining traces of iodine in the IRU vent gas will be removed in the downstream primary adsorber and iodine guard beds (DS-SB-640NB/C). Buildup of radiation dose rates in the iodine guard beds may be used as an indication that the IRU sorbent bed needs to be replaced. From the IR Us , the gas stream will flow to gas dryers (DS-E-61 ONB/C) and primary adsorbers (DS-SB-620NB /C). The gas dryers will reduce water vapor content of the gas to improve performance of the downstream sorbent beds. For radioactive noble gases, the overall process concept is to delay the gas release so that decay wi ll reduce the radioisotope content sufficient l y to allow the decayed noble gases to be safely discharged to the stack. Preliminary information suggests that xenon-1 33 (1 33 Xe) is the isotope that will drive the required delay time , and that a delay time for 133 Xe of about [Proprietary Information] is expected to be sufficient. Two sequentia l noble gas retention s teps wi ll be included in the overall dissolver offgas treatment process. The primary adsorbers are expected to provide a moderate delay for xenon, on the [Proprietary Information]. From the primary adsorbers, the gas will flow through an iodine guard bed , particu l ate filter , vacuum receiver tank , vacuum pump , and then to secondary adsorbers. The secondary adsorbers (DS-SB-730NB /C) will provide an extended delay ofxenon, on the order of[Proprietary Information]. The primary and secondary adsorbers wi ll also adsorb and delay release of krypton. However , the delay time for krypton is much shorter, only [Proprietary Information] of that for xenon. The secondary adsorbers will provide some additional iodine retention but are not credited as part of the iodine control approach. Vacuum receiver tanks (DS-TK-700NB), located between the primary and secondary adsorbers, w ill act as buffer tanks for the vacuum system to reduce the cycling and peak capacity requirement for the vacuum pumps. 4-101 .... ;. NWMI ...... .. *.. .*.* .. *.*. ' *.* NDmfWEST MEOICAUSOTOPU Waste Collection NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Description During normal process operations, liquid wastes will be ge nerated b y the primary caustic sc rubber s, NO x oxidizers and absorbers , and gas dryers. Liquid wastes will be collected in waste collection and sampling tanks (DS-TK-800 /DS-TK-820). Additional liquid wastes will be ge nerated b y maintenan ce operations , such as tank and line flushes. Waste volume estimates have not ye t been developed. The above description provides a detailed account of the SNM in process durin g the tar get dissolution activities. The SNM , along with any included fission-product radioactivity , is d escribed in Sections 4.3.4.4 and 4.3.4.5. Ba se d on this description , these operations can be conducted safe ly in the RPF. 4.3.4.2 Process Equipment Arrangement The target dissolution 1 and tar get dissolution 2 s ubsystems will be located along the rows of the proces si ng hot cells w ithin the RPF. The NO x treatment 1 , No x treatment 2, pressure relie f, primary fission gas treatment , and waste collection subsystems will be loc ate d in the tank hot cell. The subsystem locations are shown in Figure 4-17. The dissolver I hot cell (H104) and dissolver 2 hot cell (HIOl) location within t he rows of the proce ssi n g hot cells is shown in Figure 4-58. Irradiated tar ge t material will be transferred from the target disassembly hot cells to the dis so l ver hot cells via manipulators. Followin g dissolution , the uran y l nitr ate solution will be transferred from the dissolver hot cells to the Mo recovery hot cell. [Proprietary Information] Figure 4-58. Dissolver Hot Cell Locations 4-102 NWM I ...*.. * *

HOll11fWErT MEDM:Al 1$0TOP'f.S NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The equipment arrangement within the di ssolver I hot cell (HJ04) i s shown in Figure 4-59. Irradiated target material in containe r s will be brought in through the dissolver hot cell isolation door an d loaded into dissolver baskets at the filler (DS-Z-100). The basket will be lifted by the hoist (DS-L-100) and lowered through the va lve assembly into the dissolver (DS-D-100).

Durin g dissolution, the reflux condenser (DS-E-130) wi ll cool the offgas and return water and nitric acid to the dissolvers. The primary caustic scru bber (DS-C-3 l 0) wi II be the first step of the off gas treatment. [Proprietary Information] Figure 4-59. Dissolver Hot Cell Equipment Arrangement (Typical of Dissolver 1 Hot Cell and Dissolver 2 Hot Cell) 4-103 .; ... ;. NWMI .... ** ...... ........ *.* '

NOWTHWUT MEDltAl tSOTOPU NWMl-2 0 15-021 , Rev. 3 Chapter 4.0 -RPF Description The remainder of the off gas treatment eq uipm ent w ill be l ocated in the tank hot ce ll , as shown in Figure 4-60. The gas from the primary caustic scrubbers will flow to NO x treatment 1 or NO x treatment 2 and then to the primary fission gas treatment equipment.

Liquid waste from the offgas treatment equipment will be pumpe d to the waste co ll ection eq uipm ent. [Proprietary Information] Figure 4-60. Target Dissolution System Tank Hot Cell Equipment Arrangement 4-104 NWM I ..*... * *.*

NOtmfWlST MEDICAl ISOTOf'U NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The secondary fission gas treatment equipment will be located on the second floor with local shielding , as shown in Figure 4-61. [Proprietary Information]

Figure 4-61. Target Dissolution System Mezzanine Equipment Arrangement 4.3.4.3 Process Equipment Design A common vessel geometry has been assumed for vessels that may contain significant quantities of fissile material. This approach provides a geometricall y favorable configuration for criticality control when process solutions may contain significant quantities of uranium with enrichments up to 20 wt% 235 U. The assumed geometry is based on use of vessel elements ("risers") with [Proprietary Information] apart from other solution-containing vessel risers (center-to-center). The actual diameter and spacing requirements will be better defined by vessel sizing analysis. Multiple interconnected risers will be used to provide the overall capacity required for a specific vessel. 4-105 NWM I ...... *

NOmfW(Sf MEDtCM. JSOTOf'll NWMl-2015-0 21, Rev. 3 Chapter 4.0 -RPF De s c ription The assumed geometry requirement influences the configuration of the dissolvers and off gas treatment columns and liquid was te tanks. For each dissol ver, there will be two vertical risers with the required spacing between riser s. Each dissolver will include a vertically oriented condenser that sits on top of one of the risers. Circulation will be induced by an agitator.

Offgas from each disso l ver condenser will flow directl y to dedicated offgas treatment equipment that will include a primary caustic scrubber, NO x o x idizer, and NO x a bsorber. IRU s, gas dryers , a nd adsorber sys tems will be s hared between the two dissol ve r systems and treat gases from the dissolution and target evacuation s teps. Pendin g formal analysis, the geometrically favorable configuration requirements are assumed to apply to the dissolvers , condensers , prima ry caustic scrubbers, NO x oxidizers , NO x absorbers, and waste collection and sampling tanks. The geometrically favorable configuration requirements are assumed to not appl y to the IRUs , gas dryer s, and downstream offgas treatment equipment. Details for design parameters of the processing equipment, including normal operating conditions, are summarized in Table 4-34. Tab le 4-34. Ir r a d iate d Ta r get Di sso lu tio n Process Eq u i pm e n t Equipment name Equipment no. Di sso l ver DS-D-100/20 0 D i ssolver reflux DS-E-130/230 condense r NO x treatment (primary DS-C-3 10/340/37 0 caustic scrubber, NO x DS-C-410/440/470 oxidizer, a nd NO x a b so rb e r Iodine removal unit DS-SB-600A/B /C Gas dryer DS-E-61 OA/B/C Primary absorber DS-SB-620A/B /C Iodine g uard bed DS-SB-640 A/B/C Secondary a b sorber OS-SB-730A/B/C Vacuum receiver tank DS-TK-700A/B Waste collection and DS-TK-800/820 sampling tanks Pre ss ure relief DS-TK-500 confinement tank N I A not applicable. NO x = nitro gen ox id e. Operating range [Pr oprietary [Proprietary 304L SS In fo rm at ion] In formation] [Pr op rietary [Pr opr iet ary 3 04 L SS Jnformat i on] Informati o n] [Propri eta r y [Propri etary 3 04 L SS In format i o n] In fo rm a tion] [Pr oprietary [Proprietary 304L SS Informal ion] Information] [Proprietary [Proprietary 304L SS In formation] In fo rm ation] [Pr opr ietar y [Proprietary 304L SS Information] In forma ti on] [Proprietary [P roprietary 304L SS Inform at ion] In formation] [Proprietary [Propri eta ry 304L SS In format i o n] Inform ation] [Proprietary [Propri etary 304L SS In format i on] In formation] [Proprietary [Proprietary 304L SS Information] Information] [Proprietary [Proprietary 304L SS In fo rm at i o n] In formation] Temperature °C (°F)3 [P r op ri e t ary I nformati o n] [Proprietary I nformat i on] [P r o pri e t ary In for m at i o n] [Proprietary Informati o n] [Proprietary Informati on] [Propri etary Informati on] [Proprietary In fo rm ation] [Proprietary I nform a tion] [Proprietary In formation] [Proprietary Information] [Proprietary In formation] SS s tainle ss stee l. TBD to be d eter min e d. Pressure [Proprietary Informa t ion] [Proprietary Information] [Pr o priet ary I n forma ti o n] [Proprietary Information] [Proprietary I nformation] [Proprietary Information] [Propri e t ary In format i o n J [Proprietary Informati on] [Propri e t ary In formation] [Proprietary Information] [Proprietary In formation] The primary caustic scrubber, NO x oxidizer, and NO x absorber will each be nomina l [Proprietary Information] vertical columns with internal packing, baffles , and/or trays to facilitate contact of offgas with the scrubbing and oxidation solutions. The solutions will be recirculated through each column using a mechanica l pump to maintain adequate liquid downflow. The bottom of each column will be a liquid reservoir that holds accumulated scrubber solution. 4-1 06 .; .. ;. NWMI ...... ..* .. .......... * *.*

NOltTlfWEST MEDICAL ISOTOPES The IRUs will consist of a sorption bed that uses a [Proprietary Information].

The gas dryers will each have a vertical pipe heat exchanger [Proprietary Information]. The heat exchanger will be cooled with chilled glycol solution. The primary and secondary adsorbers will consist of carbon-filled columns made from nominal [Proprietary Information] pipe segments. In addition to the process equipment, auxiliary equipment will be used for material handling , pumping , and waste handling. This equipment is listed in Table 4-35. Process Monitoring and Control Equipment NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-35. Target Dissolution Auxiliary Equipment Equipment name Dissolver agitator Dissolver offgas pipe cooler Dissolver hoist Dissolver basket filler Dissolver waste drum port Venturi eductor NO x treatment so lution pumps Pressure relief tank pump Fission gas treatment filters Vacuum pump Equipment no. DS-A-100 1 200 DS-E-140/240 DS-L-100/200 DS-Z-100/200 DS-TP-100 1 200 DS-ED-3 00/ 400 DS-P-330/360/390 (A/B) DS-P-430/460/490 (A/B) DS-P-510 DS-F-630A/B /C DS-P-710A/B Process monitoring and control equipment was not Waste collection and DS-TK-800/820 defined during preliminary desi gn. The process sampling tanks descriptions identify the control strategy for Waste tank pumps DS-P-810/830 normal operations, which will set requirements for the process monitoring and control equipment and NO x nitrog e n oxi d e. the associated instrumentation. Other information on instrumentation and controls is provided in Chapter 7.0. Additional detailed information of the process monitoring and control equipment will be developed for the Operating License Application. 4.3.4.4 Special Nuclear Material Description This section provides a summary of the maximum amounts of SNM and the chemical and physica l forms of SNM used in the process. Any required criticality control features that are designed into the process systems and components are also identified. Criticality control features provided will be in accordance with the double-contin ge ncy principle, and the RPF will pro vide suitable defense-in-depth for the contained proces ses. Special Nuclear Material Inventory The SNM inventory within the irradiated target dissolution system will be determined by the mass of uranium in a dissol ver charge that has been tran sfe rred into the di sso lver hot cell from the target disassembly hot cell. Irradiated LEU tar ge t material will be moved into the dissolver hot cells in a container. The transfer container contents will be poured into a dissolver basket or inserted directly into the dissolver. The dissolver basket contents will be dissolved in nitric acid , and the resulting aqueous solution of uranyl nitrate will be transferred to the Mo recovery and purification system for further processing. The total SNM inventory within the target dissolver system will be bounded by the number of targets in the maximum dissol ver charge. [Proprietary Information]. The target dissolution system SNM inventory will be reduced when targets from MURR are being processed [Proprietary Information]. 4-107

.. ;. NWMI ...... ..* .. .... .... .. ' *.* NOffTHWEll M£DtCAl ISOTDf'U NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-36 s umm arizes the in-process SNM inventory for an individual target dissolution cell. The target dissolution SNM inventory is [P roprietary Information] (Section 4.3.1). Two d i sso lution hot cells will be available in the RPF, and both hot cells could contain an in-process inventory a t the same time. During dissolution activities, the maximum dissolution ce ll in-process SNM inventory wi ll vary [Proprietary Information], depending on the target reactor source in a particular operating week. The dissolution system will produce uranium so lution in the dissolver with a maximum concentration of approximately

[Proprietary Information]. Dilution water will be added to a dissolver at the end of [Proprietary Information] such that initial solution transfers to the 99 Mo recovery feed tank ra nge from approx im ately [Propri etary Information]. Initial dissolver so lution transfers will be followed by a dissolver vessel and transfer line water flush volume ranging from [Proprietary Information]. The design i s based on producing [Proprietary Information] in the downstream tank 99 Mo recovery feed tank after dilution with flush water. Table 4-36. Individual Target Dissolution Hot Cell In-Process Special Nuclear Material Inventory Stream Form Concentration* SNM mass* Dissolver I or di ssolver 2 (DS-D-1 00 , DS-D-200) [Proprietary Inform at i on] [Proprietary In format i on] [Propr ie tary In formation)

SNM co n centration and ma ss r e pre se nt tota l amount of LEU (combined m u and m u at::=: 1 9.95 wt% m u). b Di sso lution r eac tion c h a n ges chemica l form from

[Proprietary Informati o n] to aqueous u r an y l nitrate so lution. c SNM in-pro cess inv e ntory of an individua l di sso l ver h o t ce ll. Two dissolver h ot ce ll s are avai l able , and both ce ll s co uld co nt a in SNM in ventory a t th e s ame tim e. m u m u LEU ur anium-235. uranium-2 38. low e nrich e d uranium. SNM = special nucl ear material. U = uranium. [Propriet ary In formation] Nuclear criticality evaluat ion s performed in NWMI-2015-CRJTCALC-002 , Irr ad iat ed T arget LoEnriched Uranium Mat e rial Di sso lution, indic ate that the target dissolution system vessels remain subcritica l under normal and abnormal conditions when all vesse l s contain solution at a conce ntration of 750 g U/L after dissolution. NWMI-2015-CSE-002 , NWMI Pr e limina ry C riti c a li ty Saf ety Eva lu ation: Irradiat e d Low-Enri c h e d Uranium Targ e t Mat e rial Dis so l ution , describes CSEs of the target di sso lution system. The current double-contingency analysis in NWMI-2015-CSE-002 im p oses [Propri etary Information] on the dissolution hot cell inventory as a criticality safety control. Current critica li ty safety controls are based on sing l e parameter limits und er fl o oded conditions. The single parameter limit for [Propri etary Information]. Further eval u ation of the t arget dissolution hot cell criticality controls will be performed and included in the Operating License Application. 4-108 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Descript ion Criticality Control Features Criticality control features are required in this system, as defined in NWMI-2015-CSE-002. These features, including passive design and active engineered features, allow for adherence to the contingency principle. This section applies the criticality control features that are discussed in Chapter 6.0, Section 6.3. The criticality control features for this subsystem will include the passive design and active engineered features with designators of PDF and AEF, respectivel y, listed below. The passive design features will include geometric constraints of the floor, proces s equipment, workstations, and ventilation system. Active engineered features will include the requirement of continuous ventilation. Chapter 6.0 provides detailed descriptions of the following criticality contro l features.

For the case of a liquid leak , the floor will be criticality-safe (CSE-02-PDF I), and the floor will have a minimum area to preclude collection of l eaked fissile solution at high concentration to an unfavorable depth (CSE-02-PDF4).

The geometry of the process equipment will be inherently criticality-safe (CSE-02-PDF2 and CSE-0 2-PDF3) and will maintain a subcritica l geometry during and after a facility DBE (CSE-02-PDF5 and CSE-02-PDF6). Dissolver design and operability of the ventilat ion system will preclude pressurization of the process vessels (CSE-02-AFE-I). For the case of liquid leaks to secondary sys tems , a safe-geometry secondary system barrier will be provided between the process vessels and the unfavorable-geometry supply systems (CSE-02-PDF7 and CSE-02-PDF8). Some or a ll of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the target dissolution activities.

* * *
IROFS CS-02 sets batch limits on samples . IROFS CS-04 affects location, spacing, and design of workstations . IROFS CS-05 restricts the volume of [Proprietary Information]

collection container . IROFS CS-07, "Pencil Tank Geometry Contro l on Fixed Interaction Spacing of Individual Tanks," defines maximum tank diameters and minimum spacing between proce ss equipment , which is applicab l e to the dissolvers, reflux condenser, and the primary caustic scrubber. IROFS CS-08 controls the geometry of the floor to prevent criticality in the event of sp ill s . In addition to the features that apply the double-contingency principle, several features will provide defense-in-depth in criticality control. These features wi ll include the following.

* *
Tanks are vented and unpressurized durin g normal operations, and corrosion re s i sta nce is a design requirement.

Level is monitored on all tanks and indicated to the operator to reduce the likelihood of overflow. The batch limits in the dissolution hot cell are set conservatively low such that the administrative control on spacing can sustain multiple upsets. The criticality a larm system provides criticality monitoring and alarm in a ll areas whe re SNM is handled, processed , or stored, as described in Chapter 6.0. The effects of a criticality acci dent are mitigated by the s hieldin g described in Section 4.2 . The criticality control features provided throughout the target dissolution process will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes. 4-109 NWMI .*.**... * * *

HOATifW(Sl MEDtCAl. tsOTOPf.S 4.3.4.5 Radiological Hazards NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description This section provides details of the radioactive inventory in process and identifies the essential physical and operational features of the irradiated SNM processing system that are requi r ed to prevent the release of radioactive material and to maintain radiation levels below applicable radiation exposure I imits prescribed in 10 CFR20 for the protection of workers and the public. The analysis in this section is based on information developed during preliminary design. Additional detailed information, including definition of technical specifications, will be developed for the Operating License Application and described in Chapter 14.0. Radionuclide Inventory A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes. NWMI-2014-CALC-014 identifies the 123 dominant radioisotopes included in the MURR material balance (NWMI-201 3-CALC-006).

NWMI-2014-CALC-014 provides the basis for using the 123 radioisotopes from the total list of 660 radioisotopes potentially present in irradiated targets. The majority of omitted radioisotopes exist in trace quantities and/or decay swiftly to stable nuclides. The reduced set of 123 radioisotopes consists of those that dominate the radioactivity and decay heat of irradiated targets. Activities during an operating week that process targets irradiated in the MURR represent the radionuclide inventory as described in Section 4.1. The radionuclide inventory will be based on a [Proprietary Information]. During MURR target processing , LEU from [Proprietary Information] will be collected as a dissolver charge in a disassembly hot cell and transferred to one of the dissolver hot cells for processing. Figure 4-62 provides a simplified description of process [Proprietary Information] Figure 4-62. Target Dissolution In-Process Radionuclide Inventory Streams streams used to describe the in-process radionuclide inventory. The radionuclide inventory will be split among three streams (dissolver offgas , filter solids , and dissolver solution) in the target dissolution hot cell. Dissolver offgas will be gases generated during the dissolution reaction that leave the dissolver condenser. Filter solids represent undissolved material that will be removed from the dissolver solution as it is transferred out of a dissolver hot cell. A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes. The in-process radionuclide inventory passing through target dissolution activities during an operating week is listed in Table 4-37 based on [Proprietary Information], neglecting decay that will occur during the time to perform target receipt , disassembly , and dissolution activities. The radionuclide inventory of dissolver charge transfers from target disassembl y is summa r ized in Table 4-33. Based on preparing a dissolver charge containing [Proprietary Information], the in-process inventory of an individual target dissolution hot cell is described by [Proprietary Information ]listed in Table 4-37. 4-110 Table 4-37. , Item Unit operation Deca y time after EOI" Stream description b Isotopes 241Am 136m Ba I37rn Ba 1 39 Ba 140Ba 141ce 143Ce 144Ce z4zcm z43 Cm z44cm 134 Cs I 34 mcs 136 Cs 137 Cs 1ssE u 1s6Eu 1 s1 Eu 129J 1 30 1 1 3 1J 132 1 1 32 mJ 133 1 133mJ 1341 13 5 1 8 3 mKr 85Kr 8 5m Kr 87Kr 88 Kr 140La NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Target Dissolution In-Process Radionuclide Inventory (4 pages) Dissolver offgas [Proprietary Information] I [Proprietary Information] I [Propri etary Information] I [Proprietary Information] I [Proprietar y Inform ation] I [Proprietary Information] I [Propri etary Inform ation] I [Proprietary Information] I [Proprietar y Informati on] I [Proprietary Information] I [Propri etary Inform atio n] I [Proprietary Information] I [Proprietary Inform ation] I [Proprietary Information] I [Propri etary Inform ation] I [Proprietary Information] I [Propri e tary Inform ation] [Proprietary Information] [Proprietary Informati on] [Proprietary Information] [Propr ietary Inform ation] [Proprietary Information] [Propri e tar y In formation] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Propri e tary Inform ation] [Proprietary Information] MURR target processing Target dissolution [Proprietary Inform ation] Dissolver so luti o n [Proprietary lnformation] [Proprietar y Information] [Proprietary Information] [Propri etary Informati on] [Proprietary lnformation] [Proprietary Inform ation] [Proprietary Information] [Proprietary Informati on] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Proprietary Informati o n] [Proprietary Information] [Propri etary Informati on] [Proprietary Information] [Proprietary In formation] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Propri etary Informati on] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Propr ietary Information] [Proprietary Information] [Propri e ta ry Inform ation] [Proprietary Information] [Proprietary Informati on] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Proprietary In fo rm ation] [Proprietary Information] 4-111 Filter so lid s [Proprietary Information] [Propr i etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Informati on] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Informati on] [Proprietary Information] [Proprietary Informati on] [Proprietary Information] [Proprietar y Inform ation] [Proprietary Information] [Proprietary Inform at i on] [Proprietary Information] [Proprietar y Informati on] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Inform at i on] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Proprietary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information]

.**.* ... .; ... ;. NWMI ........ *. * * *
NOmfWEST MEDICAl ISOTOPU Table 4-37. Item Unit operation Decay time after EOI" Stream descriptionh Isotopes 141La 142La 99 Mo 9sNb 95 mNb 96Nb 97 Nb 97mNb 147Nd 236mNp 231 Np 23sNp 239N p 233pa 234 pa 234mpa 1 1 2 pd I47pm I48pm I48mpm I49pm ISOpm IS I pm 142Pr I43 pr I44pr I44m pr I4Spr 2Js pu 239pu 240 pu 24Ipu NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Target Dissolution In-Process Radionuclide Inventory (4 pages) Di sso l ver offgas [Propri e tar y Information]

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Infonnation] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary I n formation] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] I [Proprietary Information] I [Proprietary Information] I MURR target processing Tar get dis so lution [Proprietary Information] Dissolver solution [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary I n formation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-112 Filter solids [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] Table 4-37. Item Unit operation Decay time after EOI" Stream description b Isotopes 1 0 3 mRh IO S Rh 1 0 6 Rh 106mRh 10 3 Ru 1o s Ru io 6 Ru 122 sb 1 2 4S b 125 Sb 1 2 6S b 127 Sb 128 S b 1 2 smsb 129 S b 1 s 1sm 153 S m 1 s6 sm s9sr 90 Sr 9 1 S r 92 sr 99 T c 99 mTc J25 m T e 1 21 Te 127 m T e 12 9 Te I 2 9 mT e 1 31 Te 1 3 I m T e 132 Te NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Target Dissolution In-Process Radionuclide Inventory (4 pages) ' MURR target processing Di ss ol ve r off g a s [Propri e t a r y Inform at i o n] I [Proprietary Information] I [P ro pri e tary Inform a ti o n] I [Proprietary Information] I [Prop r i e t ary Inform at i o n] I [Proprietary Information] I [Propri e t ary In fo rmati o n] I [Proprietary Information] I [P ro p r i e tar y In fo rm a ti o n] I [Proprietary Information] I [Propri e t a r y Inform at i o n] I [Proprietary Information] j [Propri eta r y In fo rm a ti o n] I [Proprietary Information] j [Propri e tar y Informati o n] I [Proprietary Information] I [Propri e t a r y Inform a ti o n] I [Proprietary Informat i on] I [P ro pri e t a r y In fo rm a ti o n] I [Proprietary Information] I [P ro pri e t a r y In fo rm a t io n] I [Proprietary Information] I [P ro pri e t ary In fo rm atio n] I [Proprietary Information] I [Propri e t ary In fo rmati o n] j [Proprietary Informatio n] j [Propr ie t ary In fo rm at i o n] I [Proprietary Information] j [Prop rie tar y Inform a ti o n] I [Proprietary information] j [Propr ie t ary Inform a ti o n] I [Proprietary Information] j T a r ge t di ss oluti o n [Propr ietary Inform at i o n] Di ss ol ve r s olution [Propri e t ary Inform at i o n] [Proprietary Information] [Propri etary Inform a ti o n] [Proprietary Information] [Propri e t a r y Inform a ti o n] [Proprietary Information] [Propri e t ary Inform a ti o n] [Proprietary Information] [Propri e t ary Inform a ti o n] [Proprietar y Information] [Propri e tar y Inform a ti o n] [Proprietary Information] [Propriet ary Inform a ti o n] [Proprietary Information] [Propriet ary Inform a ti o n] [Proprietary Information] [Propri e t a r y In fo rm a ti o n] [Proprietary Information] [Propri e t ary Inform a ti o n] [Proprietary Information] [Prop r i e t a r y Inform a ti o n] [Proprietary Information] [Propri etary In fo rm a ti o n] [Proprietary Information] [Propri e t a r y Inform a ti o n] [Proprietary information] [Propri e t ary In fo rm a ti o n] [P r oprietary Information] [Propri e t ary Informati o n] [Proprietary Information] [Propri e t ary Inform a ti o n] [Proprietary Information] 4-1 1 3 F ilt e r s olid s [Propr ie t ary Inform a tion] [Proprietary Information] [Propri eta r y In fo rm a ti o n] [Proprietary Information] [Propri e t ary Inform a ti o n] [Proprietary Information] [Propri e t ary Inform a tion] [Proprietary Information] [Propr ie t a r y Informati o n] [Proprietary Information] [Propri e t ary Informati o n] [Proprietary Information] [Propri e t a r y Information] [Proprietary Information] [Propri e t ary Inform a tion] [Proprietary Information] [Propri e t ary Informati o n] [Proprietary Information] [Propri e t ary Inform a tion] [Proprietary Information] [Propri e t a r y Inform a tion] [Proprietary Informat i on] [P ro pri etary In fo rmati o n] [Proprietary Information] [Propri e t a r y In fo rm a tion] [Proprietary Information] [Propri eta r y Inform a tion] [Proprietary Information] [Propri eta r y Informati o n] [Proprietary Information] [Propri etary Inform a tion] [Proprietary Information] .; ... ;. NWMI *********. ........ *. ' *

NOlfTHWUT MfDICAl. ISOTOPES NWMl-2015-021, Rev. 3 Cha p ter 4.0 -RPF Descr i ption Table 4-37. Target Dissolution In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOI" Stream desc r iptionb ' Isotopes 133 Te I 33m Te 1 3 4Te 23 1Th 23 4Th m u 23 4U 23s u 23 6u 231 u 23 su 1J1mxe 133 Xe I33mxe 135 Xe 1Jsmxe 89 my 90y 90 my 9Iy 9Imy ny 93 y 93zr 9 s zr 91zr Total Ci Dissolver offgas [Proprietary Information]

[Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta ry Informati o n] [Proprietary I n formation] [Proprietar y Information] MURR target processing Target disso l ution [Proprietary Information] Dissolver solution [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Inform ation] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Inform at ion] [Proprietary Information] [Proprietar y Information] Filter solids [Proprieta r y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propri etary Information]

In-process inv entory based on [Proprietary Information], ne g l ecting time requir e d to receive , disas semb le , and di sso lv e targets. b Figure 4-62 provides a si mplifi ed description of the process streams. c In-process inventory ba se d [Proprietary Information], representing the week l y pro cess throu g hput. No r mal operation expected to prepare a dissolver charge conta inin g [Propri etary Inform a tion] s uch that the in-process invento ry of an individu al target dissolution cell is de sc ribed b y [Proprietary Inform at ion] EOI = end of irradiation.

MURR = U n iversity of Missouri Research Reactor. 4-114 NWMI ...... ..* *.. ..........

NORTHWEST MEOICAl tSOTOr'ES Dissolver off gas will be treated by the dissolver offgas system to control radionuclide emissions. The dissolver off gas system includes two groups of unit operations:

NO x scrubbers a nd fission gas treatment. Radionuclides in the dissolver offgas stream listed in Table 4-37 will enter the NO x scrubbers , where NO x is removed and the radionuclide inventory is split into two st ream s (scrubbed gas, and waste), as shown in NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-63. The maximum in-process radionuclide inventory of the target dissolution offgas strea ms is listed in Table 4-38. Figure 4-63. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory Streams Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay Time after EOI" Stream descriptionb Isotopes 2 41Am 1 36m B a 1 37m Ba 1 39 Ba 140Ba 1 4 1ce 1 43 Ce 1 44 Ce 242 cm 243 Cm 244Cm 1 34 Cs 1 3 4mcs 1 36 Cs 137 Cs 1 ss Eu 1 s6 Eu 1 s1 Eu 1 29 I 130 1 131] 1 32] 1 32m l 1 33 J 13 3 m l 1 3 4 1 1 35 1 MURR target processing NO x scrubbers [Proprietary Information] Scrubbed gas Sc rubb er waste CiC [Proprietary Informat i on] [Propri etary In formation] [Proprietar y In format ion] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietar y In formatio n] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary In formatio n] [Proprietary Information] [Proprietary Information] [Propri etary In fo rmati on] [Proprietary In format ion] [Proprietary Information] [Proprietary Information] [Propri e tary Inform ation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary In fo rm ation] [Proprietary In formatio n] [Proprietary Information] [Proprietary Information] [Propr ietary Inform ation] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propr ietary Inform ation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propr ietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary In format ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary In formatio n] [Proprietary Information] [Proprietary Information] [Propri etary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Inform ation] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-115 ' NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Des c ription Tab l e 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay T i me after EOI" Stream descriptionb Isotopes 8 3 mKr 85Kr 8 5 mKr s1Kr 8 8 Kr 140La 1 4 1L a 142La 9 9 Mo 95 Nb 95m Nb 96 Nb 97 Nb 97mNb 14 1 Nd 2J6m Np 231 Np 238N p 23 9Np 233 pa 234 p a 234m pa 11 2 pct 14 7 pm 14spm 148mpm 149pm 1so pm 15l pm 142Pr 143 pr J44pr 1 4 4mp r 14 5 pr 23 8 pu 239 pu 2 40 pu 241 Pu MURR target processing NO x scrubbers [Proprietary lnfonnation] Scrubbed gas Scrubber waste CiC CiC [Propri etary Information] [Proprietary I nfonnation] [Proprietary lnfonnation] [Proprietary lnfonnation] [Propri etary Information] [Proprietary ln fonnat ion] [Proprietary Information] [Proprietary Information] [Propriet ary Information] [Proprietary In fo rmation] [Proprietary lnfonnation] [Proprietary lnfonnation] [Propri etary Information] [Proprietary Information] [Proprietary Infonnation] [Proprietary lnfonnation] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary In forma tion] [Proprietary Information] [Proprietary Information] [Proprietary Inform atio n] [Proprietary Information] [Proprietary lnfonnation] [Proprietary Infonnation] [Propri e tar y Inform at ion] [Proprietary Information] [Proprietary lnfonnation] [Proprietary lnfonnation] [Propri etary Inform atio n] [Proprietary Information] [Proprietary lnfonnation] [Proprietary Tnfonnation] [Proprietary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Inform ation] [Proprietary Informat i on] [Proprietary lnfonnation] [Proprietary lnfonnation] [Propri eta r y Inform atio n] [Proprietary Information] [Proprietary Infonnation] [Proprietary Information] [Propri eta r y Inform ation] [Proprietary ln fo nnation] [Proprietary Infonnation] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Inform atio n] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propriet a r y Inform a tion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Inform atio n] [Proprietary In fo rmation] [Proprietary Information] [Proprietary Information] [Propriet a r y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-1 16 .... ;. NWMI ...... .. **. .*.* .. *.* . * *

NOllTHW£ST MEDtcAl lSOTOn.$ NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay Time after EOP Stream descriptionh Isotopes 10 3 mRh IO S R.h 106 Rh 106mRh 1 0 3 Ru 1o s Ru 106 Ru 122 sb 1 24 Sb 1 2s sb 1 26 Sb 127 Sb 128 S b 12smsb 129 S b 1 s 1sm 153 Sm 1 s 6sm 89 Sr 9osr 91 sr 92 Sr 99 Tc 99 mTc I 2S mT e 1 21 Te I 27m T e 1 29 Te I 29m T e n1Te 1 3 I m T e 13 2 Te 1 33 T e I 3 3mre 1 34 T e 2 3 1Th 234Th 232 u MURR target processing NO x s crubber s [Proprietar y Information]

Scrubbed gas Scrubber waste CiC CiC [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propri e tar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y I nformation] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propri e ta ry Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri e tary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propri e tar y Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietar y Inform a tion] [Propri e tar y Information] [Proprietary information] [Propr i etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri e tar y Information] [Propri e tar y Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary I nformation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary I nformation] [Propri e tary Information] [Proprietary I nformation] [Proprietary Information] 4-1 17 NWM I ...... *

NOlllfWHT MEotc:Al ISOTOl'H NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages) Item MURR target processing Unit operation Decay Time after EOI" Stream descriptionb NO x sc rubb ers [Proprietar y Information]

Sc rubbed gas Scrubber waste Isotopes Cic CiC 234 u [Propri etary Inform at ion] [Proprietary Inform a tion] 23su [Proprietary Information] [Proprietary Information] 236 u [Propri eta ry Information] [Proprietary Information] 231 u [Proprietary Information] [Proprietary Information] 23 su [Propri etary Information] [Propri e tar y Information] 1 J 1mxe [Proprietary Information] [Proprietary Information] 133 Xe [Propri etary Information] [Proprietary In fo rmation] I33mxe [Proprietary Information] [Proprietary Information] 135 Xe [Propri e t a r y Information] [Propri e tar y Information] 1 Js mxe [Proprietary Information] [Proprietary Information] 8 9m y [Propri etary Information] [Proprietary In for mation] 90 y [Proprietary Information] [Proprietary Information] 90m y [Propri eta r y Inform a tion] [Proprietary In for mation] 9I y [Proprietary Information] [Proprietary Information] 9Jmy [Propri etary Information] [Proprietary In fo rm a tion] 92 y [Proprietary Information] [Proprietary Information] 9 3 y [Propri etary Inform a tion] [Proprietary Information] 93z r [Proprietary Information] [Proprietary Information] 9 s zr [Propri eta r y Inform a tion] [Propri eta r y Information] 91z r [Proprietary Information] [Proprietary Information] T ota l Ci [Propri eta r y Inform ation] [Proprietary Information]

In-process inventory ba se d on [Proprietary In formatio n), n eg l ec t i n g time r e qu red to rece i ve , di sassemb l e, a nd di sso l ve targets. b Figure 4-63 pro vides a s implifi ed description of the process streams. c In-process inv e nt ory based on [P roprie t ary I nform ation], r e pr esenting the weekly process t hr o u g hput. No rm a l o p eration expected to prepare a di sso lver c har ge co nt a inin g [Propri etary In forma ti on] suc h th a t th e in-process inv entory of an individual tar ge t di sso lution offgas sys tem i s d esc rib ed b y o n e-h a l f the li s ted ra di onucl id e in ve nt ory. EO I e nd of irradiation.

NO x = ni trogen oxide. MURR = U n iversity of Missouri Re se arch R eactor. Scrubbed gas from the NO x scrubbers a nd disa sse mbl y off gas wi ll be pass e d through the fission gas treatm e nt unit operation s prior to release via the proce ss vessel vent ilation sys tem. Figure 4-64 provide s a simplified description of process streams used to describe the in-process radionuclide in ventory. The in-proce ss [Propri etary Inform at ion] Fig u re 4-64. Fissio n Gas Treat m ent In-Process Rad i on u clide Inven t ory Streams radionuclide inven tory entering t h e fission gas treatment unit operations includes the di sasse mbl y off gas s tream in Table 4-33 and the scrubbed gas s tream in Table 4-38. 4-118 .. NWM I ..... . *.******* ' e * ! NOllTtfWUT llCDM:Al tsOTOPIS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The fission gas treatment system will remove iodine isotopes from gas passing through the sy stem and delay the release of Kr and Xe isotopes to reduce the activity in offgas emission by decay. Table 4-39 describes the radionuclides in treated target dissolution offgas. Isotopes of Kr will be reduced b y a holdup of [Proprietary Information] and Xe isotop es will be reduced by a [Propr ie tar y Information]. Iodine is captured on solid materi a ls in the IRU s. The total in-process inventory of captured radionuclides and i so topes delayed for decay vary as radionuclides from one processing week decay as additional material is captured during subsequent operating weeks. Bounding estimates for the in-process inventory of iodine , Kr , and Xe i so topes are estimated in NWMI-2013-CALC-O

11. The bounding estimates produce a total equilibrium in-proces s inventory on fi ss ion gas treatment equipment of [Proprietary Information]

for all iodine isotope s, [Proprietary Information] for all Kr i so top es, and [Propriet ary Information] for all Xe isotopes. Table 4-39. Fission Gas Treatment In-Process Radion u clide Inventory (3 pages) Item MURR target processing Item MURR target processing Unit operation: Fis s ion gas tr ea tm en t I Unit operation: F i ss ion gas tre a tm e nt Decay time after EOI" [Propriet ary Information] I Decay time after EOI: [Propri e tar y Information] tar et dis so lution offi as Stream tio n: Treated tar et di ss olution offi as 2 41Am [Proprietary Information] 239pu [Proprietary Information] 136 mBa [Propri etary Inform a tion] 240 pu [Propri e tar y Informati o n] 137m Ba [Proprietary Information] 241 pu [Proprietary Information] 139 Ba [Propri eta r y Information] 10 3m Rh [Proprietar y Information] 140Ba [Proprietary Information] IOSRh [Proprietary Information] 141ce [Propri etary Information ] 106 Rh [Propr i e tar y Information] 143Ce [Proprietary Information] 106m Rh [Proprietary Information] 144Ce [Propri e tar y Inform a tion] 10 3 Ru [Propri e tar y Information] 242 cm [Proprietary Information] 1 os Ru [Proprietary Information] 2 4 3 Cm [Proprietar y Information ] 106 Ru [Proprietar y Information] 244 Cm [Proprietary Information] 122 sb [Proprietary Information] 1 3 4Cs [Propri etary Information] 1 24 S b [Propri e tar y Information] 134 mcs [Proprietary Information] 125 Sb [Proprietar y Information] 136 Cs [Propri etary Information] 126 S b [Propri e tar y Information] 137 Cs [Proprietary Information] 127 Sb [Proprietary Information] 1 ss E u [Propri e t a r y Information] 128 S b [Propri e tar y Information] 156Eu [Proprietary Information] 12smsb [Proprietary Information] 1s1E u [Propri etary Information] i 29 s b [Propri e tar y Information] 1 29 1 [Proprietary Information] 1s1s m [Proprietary Information] 130 I [Propri etary Information] 153 S m [Proprietar y Information] 131 l [Proprietary Information] 1s6 sm [Proprietary Information] 132 I [Propri e tar y Information] s9sr [Proprietary Information] n2m I [Proprietary Information] 90 Sr [Proprietary Information] 133 1 [Propri etary Information] 91S r [Propri e tar y Information] 133mJ [Proprietary Information] 92 sr [Proprietary Information] 134 f [Propri etary Information] 99 Tc [Proprietar y Information] 1351 [Proprietary Information] 99mTc [Proprietary Information] 83 mKr d [Proprietar y Information] 1 2sm T e [Propri e tar y Information] 85Krd [Proprietary Information] 121Te [Proprietary Information] 8 5 mKrd [Propri etary Information] 1 27m T e [Propr i etary Information] 87Krd [Proprietary Information] 129Te [Proprietary Information] 4-119 .; ... ; NWMI : i****-:-........ * * *

NOlrTHWEn MEDICAL tSOTOPf.S NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-39. Fission Gas Treatment In-Process Radionuclide Inventory (3 pages) Item MURR target processing Item MURR target processing Unit operation:

Fission gas tr eat ment I Unit operation: Fission gas treatm e nt Decay time after EOI" [Propri etary Informati on] I Decay time after EOI: [Proprietar y Informati o n] ..... Treated tar et di sso l ution offi Tr ea ted tar e t dissolution oft: as 88 Kr d [Propri etary Information] 129 mTe [Proprietary Information] 140 La [Proprietary Information] 131 Te [Proprietary Information] 141 La [Propri etary Information] I 3 I m T e [Propri etary Jnform at ion] t4 2 La [Proprietary Information] 132 Te [Proprietary Information] 99 Mo [Propri eta r y Information] 1 33 T e [Proprietary Information] 95Nb [Proprietary Information] 133m Te [Proprietary Information] 9 5 mN b [Propri etary Informati on] 1 3 4Te [Propri etary Inform a tion] 96 Nb [Proprietary Information] 231 Th [Proprietary Information] 97N b [Propri etary Informati o n] 23 4T h [Propri e tar y Inform a tion] 97 mNb [Proprietary Information] 232 u [Proprietary Information] 1 4 1 Nd [Prop rietary Informati on] 234 LJ [Propri etary Jn formation] 236m Np [Proprietary Information] mu [Proprietary Information] 231 Np [Propri etary Informati on] 236 LJ [Propri etary Inform at i o n] 23s Np [Proprietary Information] 231u [Proprietary Information] 23 9Np [Propri etary Informati o n] mu [Propri e tar y Information] 233 pa [Proprietary Information] 1J1mxe d [Proprietary Information] 23 4 pa [Propri e t ary Inform ation] m xed [Propri e tar y Inform a ti o n] 234 mpa [Proprietary Information] 133mxed [Proprietary Information] 11 2 pd [Propr ietary Information] 135 Xe d [Proprietary Information] 14 7 pm [Proprietary Information] 1Jsmxed [Proprietary Information] 148 pm [Propr ietary Inform at ion] 89my [Propri etary Informat i on] 1 48m pm [Proprietary Information] 90 y [Proprietar y Information] I 4 9 pm [Propr ietary Inform a ti on] 9 0 m y [Proprietary Information] 1sopm [Proprietary Information] 9I y [Proprietary Information] 1 s 1 pm [Propri etary I nform a tion] 9lm y [Propri e tar y Information] 142Pr [Proprietary Information] n y [Proprietary Information] 14 3 pr [Propri etary Information] 93 y [Propri etary Information] I44 pr [Proprietary Information] 93 zr [Proprietar y Information] 144 mpr [Propri e t ary Informati o n] 9s z r [Propri etary Inform at i o n] I4 5 pr [Proprietary Information] 91 zr [Proprietary Information] 23 8 pu [Propri etary Inform atio n] T ota l C i [Propri etary Information]

I n-pro cess in ventory based on [Proprietary In fonnat i o n], eg l ecting ti m e to r eceive , disassemble , a nd dissolve targets. b Fig ur e 4-64 provides a s implifi e d description of th e process s tr eams. ' In-pro cess in ventory b ase d on [Proprietary ln fonnat i o n], r e pr esen ting t h e week l y process throughput.

No nna! o p eration expected t o prep are a dissolver charge co nt a inin g [Propri etary I nform at i o n] s u c h th a t th e in-process in ve nt ory of an individu a l t arget disso lu tion offgas sys t em i s d escr ib ed b y one-half t h e li sted r a dionuclid e inv e nto ry. d Fissio n gas treatment syste m based o n nobl e gas h o ldup for d ecay. Syste m provid es [Propri etary ln fonnat i o n] of Kr i sotopes a nd [Propri etary In fo rmation] fo r Xe i so t opes. EO I Kr end of irradiation. = kr y pt on. MU RR Xe 4-12 0 U ni versity of Missouri R esearch R eactor. xe n on. ...... ; NWMI *:*****:* ..*..*.. ' *.*

NORTHWEST MfOICAl ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Radiological Protection Features Radiological protection features are designed to prevent the release of radioactive material and to maintain radiation levels below the applicable radiation exposure limits prescribed in 10 CFR 20 for the protection of workers and the public. These features include defense-in-depth and engineered safety features.

The engineered safety features identified in this section are described in Chapter 6.0, Section 6.2. The following defense-in-depth features will provide radiological protection to workers and the public. * *

Target dissolution processes operate at or slightly below atmospheric pressure, or solutions are pumped between tanks that are at atmospheric pressure to reduce the like l ihood of a system breach at high pressure.

The process equipment is designed for high re l iability with materials that minimize corrosion rates associated with the processed solutions. Alarming radiation monitors provide continuous monitoring of dose rate in occupied areas and alarm at an appropriate setpoint above background. Chapter 13.0, Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the target dissolution activities and will provide radiological protection to workers and the public:

The high-dose material and solution is processed inside shie l ded areas. The hot cell shielding boundary (IROFS RS-04) provides shielding for workers and the public at workstations and occupied areas outside of the hot cell. The hot cell liquid confinement boundary (IROFS RS-01) prevents releases of l iquid.
Radioactive gases flow to target dissolution off gas treatment, which is part of the hot ce ll secondary confinement boundary (IROFS RS-03). 4.3.4.6 Chemical Hazards This sectio n provides a summary of the maximum amounts of chemicals used in the process and the associated chemical hazards. Any required chemical protection provisions designed into the process systems and components are also identified.

Chemica l Inventory Chemicals used for the dissolution and offgas treatment processes will include oxygen gas, nitric acid, NaOH, Na 2 S0 3 , and hydrogen peroxide so l utions. Estimated quantities are listed in Table 4-40. Table 4-40. Chemica l Inventory for the Target Dissolution Area Chemical OSU batch MURR batch Annual quantity 20% (6.1 M) NaOH [Proprietary Information] [Proprietary Information) [Proprietary Information) 5% NaOH + 5% Na2S03 so lu tion [Proprietary Information] [Proprietary Information] [Proprietary Information] Hydrogen peroxide (30%) [Proprietary Information) [Proprietary Information) [Propr i e tary Information] Nitric aci d (10 M) [Proprietary Information ] [Proprietary Information] [Proprietary Information] Nitrogen gas [Proprietary Information] [Proprietary Information) [Proprietary Information) Oxygen gas [Proprietary Information] [Prop ri etary Information] [Proprietary In formation] Note: This tab l e does not inc l ude the special nuclear material identified in Table 4-36. MURR University of Missouri Research Reactor. Na 2 S0 3 = sodium su l fite. Na OH osu 4-1 21 sodium hydroxide. = Oregon State University. ..... ;. NWMI .... ** ..... .......... ! *.* ! ' NotrrHWHT MEDK:Al. ISOTOPES Chemical Protection Provisions NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The chemical hazards for target dissolution system are described in Chapter 9.0. Chemica l s hazards within the system are bounded by the radiological hazards. The features preventing release of radioactive material and limiting radiation exposure will also protect workers and the publi c from exposure to hazardous chemicals.

4.3.5 Molybdenum

Recovery and Purification System The Mo recovery and purification system description provides information regarding the process , process equipment, SNM and radioactive inventories, and the hazardous chemicals used in the system. The process description (Section 4.3.5.l) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions , are described in Sections 4.3.5.2 and 4.3.5.3. These sections describe the equipment in sufficient detail to provide confidence that SNM and byproduct material can be controlled throughout the process. A description of the SNM in terms of physical and chemical form, volume in process, required criticality control features , and radioactive inventory in process is provided in Sections 4.3.5.4 and 4.3.5.5. The hazardous chemicals that are used or may evolve during the process , along with the provisions to protect workers and the public from expos u re , are described in Section 4.3.5.6. 4.3.5.1 Process Description The overall function of the Mo recovery and purification system is to extract 99 Mo from ur a nyl nitrate solution , remove impurities from the 99 Mo solution , and package the solution in shipping containers and casks. The target dissolution system will provide the uranyl nitrate solution with 9 9 Mo , and the U recovery and recycle system will receive the uranyl nitrate solution after the 9 9 Mo has been extracted. The Mo recovery and purification flow diagram , Figure 4-65 , illustrates the basic process s teps and diagrams the relationships between the five subsystems of the Mo recovery and purificatio n system: * * * *

Primary ion exchange Secondary ion exchange Tertiary ion exchange Molybdenum product Mo product handling 4-122

[Propri etary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-65. Simplified Molybdenum Recovery and Purification Process Flow Diagram Primary Ion Exchange The first set of IX co lumn s (MR-IX-125 and MR-IX-165) will [Proprietary Information], which will retain molybdenum from an acidic solution while allowing other s pecies to pass throu g h. Other species that will be retain ed to so me extent [Proprietary Information). The feed tanks (MR-TK-100 and MR-TK-140) for the primary IX subsystem w ill be loc ate d in the tank hot cell (H014), and the primary IX columns will be located in the Mo recovery hot cell (H106). 4-123 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The col umn operation w ill consist of pumping a seq u ence of solutio n s through t h e IX med i a (summarized in Table 4-41). Column effluents wi ll be routed to different vessels during a process cycle , depending on the processing step. The co lumn operatio n s will inc lud e the following. * * *

Loading cycle -Uranyl nitrate solution with 99 Mo will be pumped to the co l umns from the feed tanks to retain 99 Mo from the so lution. [Proprietary Information].

Col umn effluent during the loading c yc le wi ll be routed to the U r ecovery and recycle system. Table 4-41. Typical Ion Exc han ge Co lumn Cycle Cycle Loadin g Column feed solution [Proprietary In fo rm a ti o n] Pre-elution rinse [Proprietary Informa t ion] Pre-elution rinse cycle -To ensure that the 99 Mo in the so lution has had a chance to load onto the co lumn , a wate r rinse E luti on Regeneration so lution will be pumped from the chemical BY addition hood (MR-EN-I I 0) through the column after the loadin g cyc le. Effluent H 0 3 NaOH [Propr i etary Informa t i o n] [Proprietary Informa t i o n] b e d vo lum e nitric acid. so dium h y dro x id e. from the column will be routed to the waste handlin g system. --[Pr o prietary [Propri e t ary In fo rmation] In form a ti o n] [Proprietary [Propri etary In forma tion] In formation] [Proprietary (Pr oprietary I nformation] In fo rm ation] [Proprietary [Proprietary In fo rmation] Inform ation] E lution cyc l e -Once the pre-elution rinse cycle is complete, the column feed will be switched to a so lution containing [Proprietary Information]. This solution will be p umped from the chemical addition hood (MR-EN-110). Molybdenum w ill be elute d off the column, and the effluent from the column will be routed to the Mo purification feed tank #2 (MR-TK-2 00). Regeneration step cycle -Restoring the co lumn to a nitric acid condition will be done b y rinsing the column with a [Proprietary Information]. Co lumn effluent will be directed to the waste handling system. Secon dary Ion Exchange The eluate from the primary IX column will be adj u sted with [Proprietary Information] will be fed b y the operator via the chemical addition hood (MR-EN-110) to the feed tank 2 (MR-TK-200) located in the Mo recovery hot cell (H106). The [Proprietary Information] state so that it does not adsorb to the secondary IX column (MR-IX-225). 4-124 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The second product recovery and purification IX column will be a [Proprietary Information] form prior to use. The column operation will consist of pumping a sequence of solutions (listed in Table 4-42. Strong Basic Anion Exchange Column Cycle 11:111t*** Table 4-42) through the IX media. Column effluents will be routed to different vessels during a process cycle, depending on the processing step. The column operations will include the following. Cycle Loading Pre-elution rinse [P ro pri e t ary In fo rmati o n] [Proprietary Information] [Pro pri e t ary [Pro pr i e t a r y Information] Inform a ti o n] [Proprietary [Propriet a ry Information] Information]

* * *
Loading cycle -Mo solution will be fed to the column during the loading cycle to retain the Mo from the solution.

The material will adsorb [Proprietary Information] of the incoming Mo, along with only a trace of the [Proprietary Information] noted earlier. Column effluent during the loading cycle will be routed to the waste handling system. Elution [Propr i etary In fo rm at i o n] Regeneration (first) [Proprietary Information] Regeneration [P r op ri e t ary (s econd) I nfor m at i o n] Preconditioning [Proprietary Informat i on] BY = bed volum e [P rop ri e t a ry [P ro pri e t ary I nforma ti o n] In fo r mation] [Proprietary [Proprietary Information] Information] [Pr o pri e ta ry [Propri e t a r y In fo rm a tion] In fo rm atio n] [Proprietary [Pr o prietary Information] Informati o n] Pre-elution rinse cycle -To ensure that all the Mo in the solution has had a chance to load onto the column , a water rinse solution will be routed to the column after the loading cycle. Effluent from the column will be routed to the waste handling system. Elution cycle -Once the pre-elution rinse cycle is complete , the column feed will be switched to a solution containing [Proprietary Information]. The Mo will be eluted off the column, and the effluent from the column will be routed to the Mo purification feed tank #3 (MR-TK-300) located in the Mo purification hot cell (H 107). Regeneration first step -Restoring the column to a phosphate form will begin with [Proprietary Information]. This step will displace the nitrate ions in the column with nitrite ions. Column effluent will be directed to the waste handling system. Regeneration second step -The second step will displace nitrite ions by rinsing the column with a [Proprietary Information]. Column effluent will be directed to the waste handling system. Preconditioning step -To ensure the [Proprietary Information] will be pumped through the column. Column effluent will be directed to the waste handling system. The chemical rinses for the secondary IX column will be fed from the chemical addition hood (MR-E N-110). The waste streams from the IX columns will accumulate in the waste collection tank (MR-TK-340). Sampling will verify the absence of fissile material prior to being pumped to the large-geometry waste handling system. Tertiary Ion Exchange Beginning with the collection of the eluate from the secondary IX column, the tertiary IX activities will take place within the Mo purification hot cell (H107), where special considerations for the aseptic handling of the Mo product will be applied. Air purified to U.S. Pharmacopeial Convention (USP) standards , along with chemicals that have this level of purity, will be used to ensure the integrity of the Mo product. 4-125 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The eluate from the secondary IX media will require [Proprietary Information]. The third IX media will [Proprietary Information] a nd the co lumn (MR-IX-325) will be operated as des c ribed for the primary IX column. The exception is that during the loadin g cycle, the effluent will be directed to the waste handl ing subsystem. The volume of feed materia l to this co lumn will be much smaller than the liquid feed to the first or second column. The eluate from this column will be the molybdate product, which will flow to the product tank (MR-TK-400). Molybdenum Product Once the 99 Mo product solution is eluted, a small amount of bleach solution will be added and samp l es taken for ve rific ation of product specifications, whic h are listed in Table 4-43. The product from one [Proprietary Information] with a sma ll amount of [Proprietary Information] added. This product will have an instantaneous 99 Mo content as high as [Propriet ary Information], depending o n the time between the EOI an d the molybdenum recovery. Table 4-43. Purified Molybdenum Product Specifica t ion Item Lantheus requirement Mallinckrodt requirements Chemical form a [Proprietary Information] [Proprietary Information] Specific activity [Proprietary Information] [Proprietary Information] Concentrationb [Propr i etary Information] [Proprietary Information] Radiopurity c , d [Proprietary Information] [Proprietary Information] Gamma [Proprietary Information] [Proprietary Information] Other gammas [Proprietary Information] [Proprietary Information] (excluding 99 mTc) Beta [Propr i etary Information] [Proprietary Information] Alpha [Proprietary Information] [Proprietary Information] Source: NWM I-20 1 3-049 , Pro c ess Sy s t e m Fun c tional Sp ec ifi c ation , Rev. C , Nort hw est Medical I sotopes , LLC , Corvall i s, Oregon , 20 15.

Product i s normally s ta bili zed by additio n (Proprietary In formation]. b Activity and concentration spec i fications are at buyer's ca libr ation time. c Radiopurity specifications are at 72 hr afte r buyer's officia l receipt time. d Assay accuracy of material delivered wi ll be +/-5% of labeled va lu e. e Based on vendor's ca libration date. Na 2 Mo0 4 = sodium molybdate. Na OH = sodi um hydroxide. NaO C I = sodium hypochlorite. The operators will fill and weigh the 9 9 Mo product via the product holder/scale (MR-Z-420) from the product tank. Using hot cell manipulators, the operator will fill the de s ignated product vesse ls and transfer the product vesse l containing the 99 Mo product to the capping unit (MR-Z-430). The 99 Mo product vesse l will then be capped, sea led , and prepared for transfer to the pro d uct and samp le hot cell (H 108) v ia an isol at i on door. 4-126 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Using hot cell manipulators, a single container will be passed through the transfer door from the Mo purification hot cell (Hl 07) into the product and sample hot cell (Hl 08). Once the shipping cask is in position, the operator may safely open the product transfer port (MR-TP-400) entry door. Using hot cell manipulators, the operator will load the shipping cask with the packaged 99 Mo product. 4.3.5.2 Process Equipment Arrangement The Mo recovery hot cell, Mo purification hot cell , and product and sample hot cell location will be within the rows of the processing hot cells shown in Fi g ure 4-66. [Proprietary Information]

Figure 4-66. Molybdenum Product Hot Cell Equipment Arrangement 4-127 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The equipment arrangement within the Mo recovery hot cell is shown in Figure 4-67. The uranyl nitrate solution will be pumped into the hot cell to one of the IX columns (MR-IX-125 or MR-IX-165). The eluate from these columns will collect in the feed tank 2 (MR-TK-200) and will then be pumped to IX column 2 (MR-IX-225). The chiller (MR-Z-130) will maintain constant temperatures in the IX columns. The eluate from IX column 2 (MR-IX-225) will flow to feed tank 3 (MR-TK-300) in the Mo purification hot cell (H107). [Proprietary Information] Figure 4-67. Molybdenum Recovery Hot Cell Equipment A r rangement 4-128 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The equipment arrangement within the Mo purification exchange hot cell is shown in Figure 4-68. Molybdenum solution will be collected in feed tank 3 (MR-TK-300) and will then be pumped through IX column 3 (MR-IX-325). The product will collect in the product tank (MR-TK-400), where final adjustments will be made. The operator will fill and weigh product containers on the product holder/scale (MR-Z-420) and sea l the container with the capping unit (MR-Z-430). Product containers will be transferred by manipulators throu g h the isolation door to the product and sample hot cell (H 108). [Proprietary Information] Figure 4-68. Molybdenum Purification Hot Cell Equipment Arrangement 4-129 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The arrangement of the product and sample hot cell equipment is shown in Figure 4-69. Product and sample containers will be transferred by manipulator into the hot cell. These containers will be loaded into their respective transfer carts by the product and sample hoist (MR-L-400) through the transfer ports. [Proprietary Information] Figure 4-69. Product and Sample Hot Cell Equipment Arrangement 4-130 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The tanks feeding the uranyl nitrate solution (MR-TK-100 and MR-TK-140), the tank collecting the extraction uranyl nitrate solution (MR-TK-180), and the tank collecting the IX waste streams (MR-TK-340) will be located in the tank hot cell (HO l4A), as show n in Figure 4-70. [Proprietary Information] Figure 4-70. Molybdenum Feed Tank Hot Cell Equipment Arrangement 4.3.5.3 Process Equipment Design The process equipment basis is described in the process description (Section 4.3.5. I) and located in the equipment arrangement (Section 4.3.5.2). Details for design parameters of the processing equipment, including normal operating conditions, are listed in Table 4-44. The auxiliary equipment, whic h includes chemical feed equipment , chillers , and handling equipment, is listed in Table 4-45. 4-131 .... ** .... .*.* .. *.*. NWMI NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-44. Molybdenum Recovery and Purification Process Eq uipm ent Individual Criticality-Equipment tank safe by Tank Temperature Pressure Equipment name no. capacity geometry material °C atm Fee d ta nk IA MR-T K-100 [P rop ri e t a r y Y es 3 04L SS [Pro pri e t a r y I n fo r ma ti o n] [P ro pri e t a r y In fo rm at i o n] I n fo rmat io n] IX column I A feed pump MR-P-120 [Prop r ietary Ye s TBD [Pro pr ie t ary ln fo nnat io n] [Pro p rietary lnf o nnat io n] I nfo r ma t io n] I X co lu mn I A MR-IX-1 2S [Proprietary Ye s 304 L SS [Proprietar y I nfo r matio n] [Pro pr ietary Informat io n] I n fo r mation] Fe e d tank 1B MR-TK-140 [Proprietar y Yes 304L SS [Proprietar y I nformat io n] [Pro pr ietary I nf o r mat io n] In fo r ma t ion] I X co lumn I B fe e d pump MR-P-1 S O [P rop ri e t a r y Y es TBD (P ro p r i e t a r y In for m a t io n) (P ro pri e t a r y I n fo r ma ti o n] I n fo rm ati o n] IX column lB MR-IX-16S (P ro pr ietary Ye s 304L SS (P ro p rie t a r y ln fonnatio n] [Pro p rte t ary In formatio n] In fo rma t io n] U so lu t i o n co ll ec ti on tank MR-T K-1 8 0 [P rop r ieta r y Ye s 3 0 4L SS [P ro p de t a r y I nformatio n] [Proprietar y I nformation] In fo r ma t ion] U s olution tank pump MR-P-190 [P rop r ie ta r y Ye s TBD [Pro pd c tar y I nformat io n] [P ro pr iet ary I n fo rmat io n] In format io n] Fee d t a nk 2 MR-TK-2 00 [P rop ri eta r y Yes 3 04L SS [Pro pri etary I n fo r ma t io n) [P ro pri e t ary I n fo r matio n] I n fo r ma t io n] IX co lumn 2 feed pump MR-P-2!0 [Propr ie t a ry Ye s TBD [Pro pr ietar y I n fo r ma t io n] [Proprietary In fo rmat io n) Info r mat ion] I X co lumn 2 MR-I X-22S [Proprietar y Y e s 3 0 4L SS f P roprietary Informa t ion] [P rop r ietary I nfo r ma t ion) I n format i on) Fe e d tank 3 MR-TK-300 [Pro pr ietary Yes 304L SS [P ro p rie ta ry In formatio n] [ProJ)<ieta r y In formatio n] In fo rmat io n] I X co lumn 3 fee d pump MR-P-3 1 0 [Pr o p r i e ta r y Y es TBD [P ro pr i e t a r y In for m a ti o n] [P ro pri e t a r y In for m at i o n] I n fo rm a ti o n) rx c o lumn 3 MR-IX-32S [Prop r ie tary Ye s 304L SS [Pro p d e tar y I nforma tio n] [Pro pr ietary I nfo r mat io n] I nformat io n] Was t e co ll ec t ion t ank MR-T K-340 [Proprietar y Yes 3 0 4L SS [P roprie t ary In fo r mation] [Prop r ietary l nformat K>n] I nfo r mation] Waste collection tank pump MR-P-3SO [Proprietar y Yes TBD [P rop r ietary In fo r mat io n] [Pro pr ieta ry Jn fo r mat K>n] In fo r ma t io n] Pr o du c t ta nk MR-T K-4 00 [P ro pri e t ary Yes 3 0 4L SS {P ro p r i e t a r y Jn fo m uuio n] [P ro pri e t ary I nfo r mat i o n] I n fo rmat io n] Product tank pump MR-P-410 (Prop r ietary Ye s TBD [P ropriet a r y I n fo rmat io n] (Pro pr iet ary In formation] I nfo r mat io n] I X i o n ex c h a n ge. TB D to b e d e t e nnin e d. N I A n o t appli ca b l e. u ur an i um. SS s ta inl ess s t e e l. Table 4-45. Molybdenum Recovery and Purification A u xiliary Eq uipm ent Equipment name Equipment no. Equipment name Equipment no. C h emica l a dd i ti on h oo d MR-E -11 0 I X co lu mn 3 filt e r MR-F-320 IX c olumn 1 chemical pump MR-P-11 S/1 SS C hiller 3 MR-Z-330 I X co lumn I filt e r MR-F-1 2 0/1 60 P ro du ct h o ld e r/sca l e MR-Z-4 2 0 C hill e r 1 MR-Z-130/17 0 C apping unit MR-Z-4 3 0 I X co lumn 2 ch e mi ca l pump MR-P-2 1 S P ro du c t an d s ampl e h o t ce ll MR-EN-400 IX column 2 filter MR-F-220 Product tran s fer port MR-TP-400 C hill e r 2 MR-Z-23 0 S ampl e t ra n s f er p o rt MR-TP-410 Mo purification hot c e ll MR-EN-300 Product and s ample hoi s t MR-L-400 I X co lumn 3 c h e mi ca l p ump MR-P-3 1 S I X i o n exc h a n g e. Mo m o l y bd en u m. 4-132 Process Monitoring and Control Equipment NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Descript ion Process monitoring and control equipment was not defined during preliminary design. The process description identifies the control strategy for normal operations, which sets the requirements for the process monitoring and control equipment and the associated instrumentation. Other information on instrumentation and controls is provided in Chapter 7.0. Additiona l detailed information on the process monitoring and control equipment will be developed for the Operating License Application. 4.3.5.4 Special Nuclear Material Description This section provides a summary of the maximum amounts of SNM and the chemica l and physical forms of SNM used in the process. Any required criticality control features that are designed into the process systems and components are also identified. Critica li ty control features provided will be in accordance with the double-contingency princip l e, and the RPF will provide suitable defense-in-depth for the contained processes. Specia l N uclear Materia l Inventory The SNM inventory within the Mo recovery and purification system will be determined by the uranium in dissolver solution transfers into the IX co lumn !NIB feed tanks (MR-TK-100 and MR-TK-140). Dissolver solution in the feed tanks wi ll be passed through IX columns IA and 1B (MR-IX-125 and MR-IX-165). During the IX column lNlB loading cycles, essentially all uranium will remain in the column effluent that is transferred to the U solution collection tank (MR-TK-180) and on to the impure U collection tanks in the U recovery and recycle system. IX column lNlB eluate transferred to feed tank 2 (MR-TK-200) and other column effluents transferred to the Mo system waste collection tank (MR-TK-340) will contain only trace quantities of uranium. The IX product and waste streams from IX column 2 (MR-IX-225) and IX column 3 (MR-IX-325) will a l so contain only trace uranium quantities. Individual irradiated target dissolver solution transfers to the IX column I NIB feed tanks are described in Section 4.3.4.4 and are summarized as follows: *

During OSTR target processing:

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] During MURR target processing: [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] Tab l e 4-46 summarizes the in-process SNM inventory for Mo recovery and purification SNM vesse l s containing the dominant uranium inventory. The Mo recovery and purification system SNM inventory is planned to be [Proprietary Information] (Section 4.3.1 ). Based on the a l ternat ive transfer sequences from target dissolution , the solution concentration in [Proprietary Information], after the initial dissolver solution transfer. 4-133 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The uranium concentration will range from [Proprietary Information] (MR-TK-180) based on the solution concentration range after combination of dissolver solution and flush water. Waste collected in MR-TK-340 will contain only trace uranium quantities. All vesse ls associated with IX column 2 (MR-IX-225) and IX column 3 (MR-IX-325) operation will contain solutions with trace quantities of uranium and have been excluded from Table 4-46. Table 4-46. Molybdenum Recovery and Purification System In-Process Special Nuclear Material Inventory Stream Form Concentration SNM mass* Feed tank IA-(MR-TK-100) [Proprie ta ry Information] (Proprietary [Proprietary information] inform ation] Feed tank lB -(MR-TK-140) [Proprietary Information] [Proprietary [Propri etary Information] Information] U sol ution collection tank (M R-TK-1 80) [Proprietary information] [Proprietary (P rop ri etary information] in format i on] Mo system waste collection tank (MR-TK-340) [Proprietary information] (Proprietary [Proprietary Information] Information] Mo syste m ion exc han ge vessels (MR-IX-125/165) [Proprietary In forma tion] [Proprietary [Propri e t ary Info r mation] Inform ation]

SNM concentration and ma ss represent total amount of LEU (combined m u a nd 238 U at::; 1 9.95 wt% m u) b Aq u eo u s so luti on of uranyl nitrate. c Use d as a transfer tank for feed tank so lution s after ion exc han ge column processing.

The SNM in-pro ces s in ve nt ory is described by th e contents of a s ingle feed tank durin g n orma l o p erat ion. In ventory i s limit ed to so lution in two of the thr ee tanks MR-TK-100, MR-TK-14, a nd MR-TK-1 80. 23s u 2Js u d Aq u eo u s so luti on w ith trace quantities of uranium ions that ma y be present in a variety o f chemical forms. e Based on two i on exc han ge co lumn s, eac h with vo lum e of 0.15 L. molybdenum. LEU uranium-235. uranium-238. low-enric h e d uranium. Mo SNM u spec i al nuclear mat er i a l. ur a nium. Feed tank lA and feed tank lB were sized to contain solution from [Proprietary Information]. Therefore , the maximum in ventory of each feed tank is described b y so lution from di sso lution of [Proprietary Information]. Logistics to minimi ze the time for preparation of a 99 Mo product batch during MURR tar get processing may result in [Proprietary Information]. The U solution collection tank (MR-TK-180) will be used to support SNM-bearing solution transfers to the U recovery and recycle system impure U collection tanks and will be genera ted by pro c essing material from a feed tank through IX column I A or IX column 1 B. Therefore, the bounding in-process SNM 99 Mo sys tem inventory is described by the contents of the two feed tanks during normal operation. Nuclear criticality evaluations performed in NWMI-20 l 5-CRITCALC -006 , Tank Hot Cell, indicate that the Mo recovery and purification system vessels located in the tank hot cell (MR-TK-100, MR-TK-140 , MR-TK-180 , and MR-TK-340) remain s ubcritical under normal and abnormal conditions when all vessels contain solution at a [Propri e tary Information]. NWMI-2015-CSE-003, NWM J Preliminary Critica li ty Saf ety Eva luation: Molybdenum -99 Product R ecovery, describes CSEs of the Mo recovery and purification system. The current double-contingenc y analysis in NWMI-2015-CSE-003 imposes a limit of [Proprietary Information] IX feed tank (MR-TK-100 and MR-TK-140) as a criticality safety control. Current criticality safety controls are based on single parameter limits under flooded conditions. Further evaluation of the Mo recovery and purification syste m cr i ticality controls will be performed and inc l uded in the Operating License Application. 4-134 ..... ; NWMI ::-:**::*. ...... ' NO<<THW£Sl MlDICAl. llOTOPl S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Criticality Control Features Criticality control features are required in the Mo recovery and purification system, as defined in NWMI-2015-CSE-003. These features, including passive design and active engineered features, allow for adherence to the double-contingency principle. This section applies the crit icality control features that are discussed in Chapter 6.0, Section 6.3. The criticality control features for this subsystem will include the passive design and active engineered features with designators of PDF and AEF , respectively, listed below. The passive design features will include geometric cons traints of the floor, proce ss equipment , workstations , and ventilation system. The active engineered features will include the requirement of continuous ventilation. The passive design features affect the design of process equipment, ve ntilation piping , and the room floor. Chapter 6.0 provides detailed descriptions of the following criticality control features. * * * *

For the case of a liquid leak , the floor will be criticality-safe (CSE-03-PDF 1 ), and the floor will have a minimum area to preclude collection of leaked fissile solution at high concentration to an unfavorable depth (CSE-03-PDF2).

The geometry of the process equipment will be inherently criticality safe (CSE-03-PDF3 and CSE-03-PDF4) and will maintain a subcritical geometry during and after a facility DBE (CSE-03-PDFS and CSE-03-PDF9). The dissolver design and operability of the venti lation system will preclude pressurization of the process vessels (CSE-03-AFE-l). The mol ybde num IX column volume will be limited , and the installation of support vessels will provide a safe geometry for criticality safety (CSE-03-PDF6, CSE-03-PDF7, and CSE-03-PDF8). The internal vo lume for the molybdenum local chiller wi ll be limited (CSE-03-PDFlO) . For the case ofliquid leak s to secon dary systems, a safe-geometry seco ndary system barrier will be provided between the process vessels and the unfa vora ble-geom etry supply systems (CSE-03-PDFl l and CSE-03-PDF12). Some or all of the engi neered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0, Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS wi ll be applicable to the Mo recovery and purification activities.

*
IROFS CS-02 sets batch limits on samples . IROFS CS-04 affects loc ation, spacing, and design of workstations . IROFS CS-07 defin es maximum tank diameters and minimum spacing between process equipment, wh ich is applicable to the feed tanks, IX columns , and waste collection tanks. IROFS CS-08 controls the geo metry of the floor to prevent criticality in the event of spills . In addition to the features that apply the double-contingenc y principle, several features will provide defense-in-depth in criticality control. These features will include the following. * * *
Tanks are vente d and unpressurized during normal operations , and corrosion resistance is a design requirement.

Level is monitored on all tanks and indicated to t he operator to reduce the likelihood of overflow. Under normal conditions , the product samp les have no fissile material , and therefore criticality is not feasible. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled, processed , or store d , as described in Chapter 6.0. The effects of a criticality accident are mitigated by the shielding described in Section 4.2 . 4-135 .... ;. NWMI ...*.. ..* ... .*.* .. *.*. " "NORTHWESTMEOICAl tsOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The criticality control features provided throughout the Mo recovery and purification system will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes. 4.3.5.5 Radiological Hazards Radionuclide Inventory A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes. NWMI-2014-CALC-014 identifies the 123 dominant radioisotopes included in the MURR material balance (NWMI-2013-CALC-006). NWMI-2014-CALC-014 provides the basis for using the 123 radioisotopes from the total list of 660 radioisotopes potentially present in irradiated targets. The majority of omitted radioisotopes exist in trace quantities and/or decay swiftly to stable nuclides. The reduced set of 123 radioisotopes consists of those that dominate the radioactivity and decay heat of irradiated targets. Activities during an operating week that process targets irradiated in the MURR represent t he radionuclide inventory as described in Section 4.1. The radionuclide inventory will be based on a weekly throughput of [Proprietary Information] will be produced as dissolver solution in a dissolution hot cell and transferred to one of the two Mo recovery and purification system IX feed tanks located in the tank hot cell. Figure 4-71 provides a simplified description of process streams used to describe the in-process radionuclide inventory. The radionuclide inventory will be split among the three streams (Mo product , impure U , and Mo IX waste) in the Mo recovery and purification system hot cells. A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes. The in-process radionuclide inventory passing through Mo recovery and purification activities during an operating week is listed in Table 4-46 based on a total of [Proprietary Information]. Normal operation will store large solution volumes in the tank hot cell. Therefore , the in-process inventory of the Mo recovery and purification hot cells [Proprietary Information] Figure 4-71. Molybdenum Recovery and Purification In-Process Radionuclide Inventory Streams includes a small fraction of the impure U and Mo IX waste streams, combined with the total Mo product stream. The in-process inventory is based on [Proprietary Information] to receive , disassemble , and dissolve targets for transfer to the first stage Mo IX feed tank and describes the generation of impure U. [Proprietary Information] of process time is required to complete recovery and purification activities for the Mo product. The allocations produce decay times ranging from [Proprietary Information] when combined with a minimum receipt target decay of [Proprietary Information] after EOI. The radionuclide inventory of dissolver solution transfers into the IX feed tanks is listed in Table 4-37. 4-136 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOI" Stream descriptionb Isotopes 24 1Am 1 3 6 m Ba 137 mBa 1 3 9Ba 140Ba 1 4 1ce t43Ce t44Ce 242 cm 243 Cm 244 Cm 134Cs 134mcs 136 Cs 137 Cs 1 ss E u 1 s6E u 1 s1 E u 1 29 J 1 3 0 I 131 1 1 32 1 132ml 133 1 133m J 1 34 1 1351 8 3 m Kr 85Kr 8 5 mKr 87Kr 88 Kr 140La MURR target processing Mo r ecove ry a nd purifi cat ion [Proprietar y Inform atio n] Impur e U [Proprietar y Inform a tion] [Propri eta r y Information] Mo IX waste Ci 0 [Proprietary Information] [Propri etary Informati o n] [Propri etary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietar y Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Prop rietary Informati o n] [Propriet ary Inform a ti on] [Proprietary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Inform a tion] [Propri e t ary Information] [Propri e tary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Propriet ary Inform ation] [Propri etary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Inform a tion] [Propri etary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Informati o n] [Propriet ary Inform at i o n] [Proprietary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Informat io n] [Propriet ary Information] [Propri etary Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Propriet ary Informati on] [Propri etary Inform at i on] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Inform at i on] [Propri etary Informati o n] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Information] [Propriet ary Inform a tion] [Propri e t ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Informati o n] [Propriet ary Inform ation] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Inform a tion] [Propriet ary Inform a tion] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Inform atio n] [Propriet ary Inform a tion] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Propri etary Information] [Propri e t ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-137 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOI" Stream descriptionb Isotopes 14 1La 142La 99Mo 95Nb 95 mNb 96Nb 97 Nb 97mNb 14 1 Nd 236m Np 231 Np 23sNp 23 9Np 233pa 23 4pa 234m pa 112pd 147pm I4 8 pm !48mpm I4 9 pm 1sopm !Sl pm 142Pr I 43 pr I44pr I44mpr 14 s pr 2Js pu 239pu 2 40pu 241pu 10 3m Rh 105Rh MURR target processing Mo recovery and purification [Proprietary Information] [Proprietary Information] [Proprietary Information] Impure U Mo product Mo IX waste Ci 0 Ci 0 Ci 0 [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Inform at ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary I nformation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Info r mation] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary T nformation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-13 8 I NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages) Item Unit operation Decay time after EOP Stream description h Isotopes 1 0 6 Rh 106m Rh 10 3 Ru 1o s Ru 1 06 Ru 122 sb 1 2 4Sb 125 Sb 126 Sb 127 Sb 128 S b 1 2 smsb 1 2 9S b 151 Sm 1s3 s m i s6 sm s9 sr 90 Sr 91 s r 92 Sr 9 9 T c 9 9 m Tc 1 2s m T e 1 21 T e J 27 m T e 129 Te J 2 9 mT e 131 Te 13 Im T e 1 32 Te 1 33 Te I 33 mTe 1 34 T e 2 3 1 Th MURR target processing Mo r e co very a nd purifi ca tion [Propri e tar y Information] [Proprietary Informati o n] [Propri e t a r y Inform a tion] Impure U Mo product M o IX wa s t e Cic CiC Cic [Propri e t a r y Inform a ti o n] [Propri e t a r y Inform a ti o n] [Propri e t a r y Inform a ti o n] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri e tar y Inform a ti o n] [Propri e t a r y Information] [Propri e t a r y Informati o n] [Propri e tary Information] [Propr i etary Information] [Proprietary Information] [Prop r i e t a r y Inform a ti o n] [Propri e t a r y Inform a ti o n] [Propri e t ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri e tar y Informati o n] [Propri e t ary Inform a ti o n] [Propri e t a r y Inform a ti o n] [Propri e tary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Inform a ti o n] [Propri e t a r y Informati o n] [P ro pri e t ary Informati o n] [Propri e tary Information] [Proprietary Information] [Proprietary Information] [Propri e t ary Inform a ti o n] [Propriet a r y Inform a ti o n] [Propri e t ary Informati o n] [Propri e tary Information] [Proprietary Information] [Proprietary Information] [Propri e t ary Informati o n] [Propri e t a r y In fo rm a t io n] [Propr ie t ary Informati o n] [Propri e tary Information] [Proprietary Information] [Proprietary Information] [Propri e t a r y Inform a ti o n] [P ro pri e t ary In fo rm a ti o n] [Propri e t ary Inform a tion] [Propri e tary Information] [Proprietary Information] [Propri e tary Information] [Propri e t ary Inform a tion] [Propri e tar y Inform a t io n] [Propri e tar y Infonnation] [Propri e tary Information] [Proprietary Information] [Propri e tary Information] [Pro pr i e t ary Inform a ti o n] [Propri eta r y In fo rmati o n] [Prop r i etary In fo rm a ti o n] [Propri e tary Information] [Proprietary Inform a tion] [Propri e t ary Information] [Propri etary Inform a ti o n] [Propri e t a r y Inform a t io n] [Propri et ar y Information] [Proprietary Inform a tion] [Proprietary Information] [Proprietary Information] [Propr ietary Inform a ti o n] [Propri e t ary In fo rm a ti o n] [Pr o pri etary Informati o n] [Propri e tar y Information] [Proprietary Information] [Propr ie t ary Information] [Prop r i eta r y Informati o n] [Propri e t a r y In fo rm a ti o n] [Prop r i e t ary Info r mati o n] [Proprietary Information] [Proprietary Information] [Proprieta ry Information] [Propri e t a r y Inform a ti o n] [Proprie ta r y Inform a tion] [Propri e t ary Inform a tion] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propr ie t a r y Inform a ti o n] [Propriet a r y Inform a t io n] [Propri e t ary Inform a ti o n] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Propri e t a r y I nformation] [Propri e t a r y Inform a ti o n] [Propri e tar y Information] [Proprietary I n formation] [Proprietary Information] [Proprietary Information] [Propr ieta r y Inform a ti o n] [Propri e t a r y Informati o n] [Propri e t ary Inform a tion] [Proprietary Information] [Proprietary Information] [Propriet ary Information] 4-1 3 9 NWMl-2015-021, Rev. 3 Chapt e r 4.0 -RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide I nventory (4 pages) : Item Unit operation Decay time after EOI" Stream description b Isotopes 23 4Th 232u 2 34u m u 236 u 231u 23 su 13tmxe t 33 Xe t 33m xe 135 Xe 1Jsmxe 89 my 90y 9 0my 9 ty 9 t m y 92y 93 y 93 zr 9s zr 91zr Total Ci MURR target processing Mo r ecovery a nd purificatio n [Proprietar y Information] [Proprietary Inform at ion] [Propriet ary Information] Impur e U Mo product Mo IX waste Cic Cic Cic [Proprietary Informati o n] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Propriet ary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet ary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta ry Information] [Proprietar y Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietar y Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Propriet a r y Inform at ion] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y I nformation] [Propriet ary Inform at ion] [Proprietar y Informati o n] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta ry Information] [Proprietary Information] [Proprietary Inform a tion]

In-pro cess inventory b ase d on decay time ranging from [Propri etary lnform a tion], di sasse mb l e, and di sso lve tar ge t s fo r transfer to the first stage Mo IX fee d tank and d escr ib e the ge n era tion of impure U. An [Proprie t ary In fo rm ation] of pro ces s time is a ll owed t o comp l ete r ecovery and purification activities t o d esc rib e the Mo produ ct and Mo IX waste ge ner ate d. T h e a ll ocatio n s produ ce decay tim es ran gi n g fro m [Proprietary Inform a ti o n] w h e n co mbin ed with a min i mum receipt t a r get d ecay of [P roprietary Inform a ti on]. b F i g ure 4-71 p rovi d es a s implifi ed d esc ription of th e p rocess s tre a m s. c In-process inventory b ase d [Propri etary I nformati on], r e pr ese ntin g the [Propri e t ary Information]

throu gh put. Normal operation s tore s lar ge so luti o n vo l um es in the ta nk h o t ce ll. Therefore , th e in-process in ve nt ory of Mo r ecovery and pur i fication h ot cells is describ ed by a s m a ll fraction of th e impure U and Mo I X waste strea m s , combined with th e t o t a l Mo produ c t stream. EO I I X Mo e nd of irra di at i o n. ion exc han ge. mol y bd en um. MURR u 4-14 0 Un iv ers it y of Missouri R esearch R eac t or. = uranium. NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Radiological Protection Measures Radiological protection features are designed to prevent the release of radioactive material and to maintain radiation levels below the applicable radiation exposure limits prescribed in 10 CFR 20 for the protection of workers and the public. These features include defense-in-depth and engineered safety features. The engineering safety features are identified in this section and described in Chapter 6.0, Section 6.2. The following defense-in-depth features will provide radiological protection to workers and the public. * *

Most solution process equipment operates at or slightly below atmospheric pressure or solutions are pumped between tanks that are at atmospheric pressure to reduce the likelihood of system breach at high pressure. The process equipment is designed for high reliability with materials that minimize corrosion rates associated with the processed solutions. Alarming radiation monitors provide continuous monitoring of the dose rate in occupied areas and alarm at an appropriate setpoint above background.

Chapter 13.0, Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the Mo recovery and purification activities and will provide radiological protection to workers and the public: *

4.3.5.6 The high-dose material and solution is processed inside shielded areas. The hot cell shielding boundary (IROFS RS-04) provides shielding for workers and the public at workstations and occupied areas outside of the hot cell. The hot cell liquid confinement boundary (IROFS RS-01) prevents releases of liquid. Radioactive gases flow to the target dissolution offgas treatment , which is part of the hot cell secondary confinement boundary (IROFS RS-03). Chemical Hazards This section provides a summary of the maximum amounts of chemicals used in the process and the associated chemical hazards. Any required chemical protection provisions that are designed into the process systems and components are also identified.

Chemical Inventory Table 4-48 provides a summary of the supply chemicals required for Mo recovery and purification system unit operations based on the material balances. These chemicals will be managed through the laboratory chemical supply rather than bulk supply. Most of the additions will be in small batch bottles pumped into the Mo recovery hot cell and Mo purification hot cell via a glovebox with a high-purity air supply. Higher purity chemicals will be needed, including USP-grade for some of the caustic and wash water used with the final IX column, plus the [Proprietary Information] added to the final product. 4-141 .; .. ;. NWMI ...... ... .. .*.* .. *.*. ' !*.* ' NOmfW[ST MEDICAL ISOTOPE.I NWMl-20 1 5-021 , Re v. 3 Ch apter 4.0 -RPF Desc r ip ti o n Ta bl e 4-48. C h e mic a l Inve nto ry for t he M ol y bd e num R e co very a nd Purifi cat ion A r ea Chemical [Propri etary Inform a t ion] [Proprietary Information] [Proprietary Inform at i on] [Proprietary Information] [Propri e t ary Inform a ti on] [Proprietary Info rm ation) [P ropr i e t a ry Inform at i on] [Proprie t ary In formation] [P roprietary Inform a ti on) OSU cycle (L) [Proprietary Informati o n] [Proprietary Information] [Proprietary Information] [Proprie t ary Informat i on] [Propriet ary I nfo rm a ti o n] [Proprietary Informatio n] (Prop ri etary Information] [Proprietary Informa t io n] [Proprietary Information] MURR cycle (L) [Proprietary I nformation] [Pro pr ietary Informat i on] [Proprietary In format ion] [Pro p rietary Information] (Propriet ary Inform a ti o n] [Proprietary Informatio n) [P rop r ietary Information] [Proprietary Informatio n] [Proprietary In fo rm a ti o n] Note: This tab l e do es n o t inc l ude th e spec i a l n u c l ear mat er ia l id e n tifi e d in Table 4-46.

Co mputed a s eight OSU campaigns o f 3 0 targets , and 44 MURR campaigns of e i g ht targets per year. [Propri e tary I n formation]

[Propri e tary Informati o n] IX ion exc han ge. Mo mo l y bd e num. MURR University of Missouri R esearc h React or. [Proprietary I n form a ti o n] C h e mic a l P rot e c tio n P ro vis i o n s [Propri e tary I nformation] [Proprietary I nformation] [Propri etary Information] OSU = Oregon State U niver s ity. [Proprietary Inform a tion] Annual (L)" [Propri e t ary Inform a ti on] [Proprietary Information] [Propri etary Inform a ti on] [Proprietary Information] [Proprietary Inform a ti o n) [Proprietary In formation] [Propri etary In fo rm a tion] [Pro p rietary Information] [Propri e t ary Inform a ti on] The chemica l hazards for t h e Mo recovery and pur i ficatio n system are de scr ibed in Chapter 9.0. Chemica l s h azards within the system are bounded by the radiological h azards. The features preventing release of radioactive material and limiting radiatio n exposure wi ll also protect worke r s and the public from expos ur e to hazardo u s chemica l s. 4-142 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

4.4 SPECIAL

NUCLEAR MATERIAL PROCESSING AND STORAGE This section describes the processing components and procedures involved in handling, processing and storing SNM beyond the radioisotope extraction process. Section 4.4.1 describes the processing of irradiated LEU, which comprises the U recovery and recycle system. The product of the U recovery and recycle system will be recycled LEU with doses low enough to be directly handled without shielding. Section 4.4.2 describes the processing of the fresh and recycled LEU, which comprises the target fabrication system. The product of the target fabrication system will be new targets. 4.4.1 Processing oflrradiated Specia l Nuclear Material The U recovery and recycle system description provides information regarding the SNM processing time cycle, process, process equipment, SNM and radioactive inventories, and the hazardous chemicals used in the system. The SNM processing time-cycle identifies the functions for lag storage for feed storage and product solutions described in Section 4.3.1. The process description (Section 4.4.1.1) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions, are described in Sections 0 and 4.4.1.3. These sections describe the equipment in sufficient detail to provide confidence that the SNM and byproduct material can be controlled throughout the process. The description ofSNM in terms of physical and chemical form, volume in process , required criticality control features , and radioactive inventory in process is provided in Sections 4.4.1.4 and 4.4.1.5. The hazardous chemicals that are used or may evolve during the process, along with the provisions to protect workers and the public from exposure, are described in Section 4.4.1.6. Figure 4-72 provides an overview of the U recovery and recycle process. Uranium-bearing raffinate from the Mo recovery and purification system is processed by the U recovery and recycle system. [Proprietary Information] Fig ure 4-72. Uranium Recovery and Recycle Process Functions 4-143 NWM I ...*.. *

NOmfWEST MEDtcAL ISOTOP'll NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The U recovery and recycle process will include three weeks of lag storage for feed soluti o n and 13 weeks of lag storage for product solutions.

The lag storage will have three main functions:

*
Minimize the potential for uranium processing to delay Mo recovery and purification operations

[Proprietary Information] Control the content of 237 U in solutions transferred between the uranium recycle and target fabrication systems Depending on the source reactor of a target batch , the uranium processing will be performed in as many as [Proprietary Information]. For example, if OSU is the source reactor [Proprietary Information]. In contrast, if MURR is the source [Proprietary Information]. Two cycles of uranium purification will be included to separate uranium from unwanted fission products via ion exchange. The first cycle will separate the bulk of the fission product contaminant mass from the uranium product. Product will exit the IX column as a dilute uranium stream that is conce n trated to control the stored volume of process solutions. Uranium from the first cycle w i ll be purified by a nearly identical second-cycle system to reduce fission product contaminants to satisfy product cri t eria. Each IX system feed tank will include the capability of adding a reductant and modifying the feed chemical composition such that adequate separations are achieved , while minimizing uranium losses. Supporting systems will include interface tanks between the uranium process and waste handling vessels. These interface vessels will be required to monitor solutions that are transferred between process systems using different criticality control philosophies. The support systems will also include a uranium rework vessel for returning solutions to the second uranium cycle feed tank. Rework material will primarily originate from out-of-specification product when processing uranium from irradiated targets , but a l so could be obtained periodically from solution generated in the target fabrication system. 4.4.1.1 Process Description Figure 4-73 provides an overview of the U recovery and recycle process. [Proprietary Information] Figure 4-73. Uranium Recovery and Recycle Overview 4-144 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The process was divided into the following five major subsystems for de sign development:

* * *
Impure U lag storage -An important feature of the RPF is to minimize the time that solutions containing 99 Mo are held up in the system equipment due to the short half-life of the primary product. The impure U lag storage process will consist of a group of solution storage vessels used to minimize the potential for the U recovery and recycle process to delay upstream processing activities in the target dissolution and Mo purification systems. First-cycle uranium recovery-This subsystem represents a group of unit operations that separate the bulk of the fission product contaminant mass from the uranium product. IX columns will be used as the primary contaminant separation unit operation.

The IX column operation will be supported by tanks for storage of intermediate process solutions and a concentrator or condenser to control the volume of uranium product solutions. Second-cycle uranium recycle -This subsystem represents a group of unit operations that provide the fina l separation of fission product contaminants from the uranium product and is similar to the first-cycle uranium recovery system. Fission product separation will be performed using an IX column as the separation unit operation. The IX column operation will be supported by tanks for storage of intermediate proce ss solutions and a concentrator or condenser to control the volume of uranium product solutions. Product uranium lag storage -This subsystem consists of a group of solution storage vessels included to minimize the potential for the U recovery and recycle process to dela y upstream processing activities in the target dissolution and Mo purification systems. Delays will be minimized by providing storage for uranium product such that target fabrication delays have minimal impact on operating the U recovery and recycle system, with the impure U lag storage tanks available to receive so lutions from the Mo purification system. Other support -This subsystem consists of a group of storage vessels that interface with other facility systems. The capabilities will include vessels to interface between the IX columns and liquid waste handling system supporting routine process waste transfers , and between the IX columns and solid waste handling system supporting periodic resin bed replacement. The system is sized to purify [Proprietary Information] for rec ycle to the target fabrication system. The goal operating time is to complete the weekly proce ss load in [Proprietary Information]. E quipment sizing is based on processing feed so lution from [Proprietary Information]. Throughput tum-down associated with [Proprietary Information] from the MURR reactor will be accomplished by processing fewer sub-bat ches [Proprietary Information] in the U recovery and recycle system equipment during a particular operatin g week. A s implified proces s flow diagram for the U recovery a nd rec ycle system, indicating the major proces s equipment, is shown in Figure 4-74. The material balances are presented for two uranium processing cases [Proprietary Information]. During operations , the system is designed to process uranium from a maximum of[Proprietary Information]. Uranium lag storage capacity has been included at the front and back end of the system to support a batch operating concept. 4-145 [Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-74. Simplified Uranium Recovery and Recycle Process Flow Diagram Impure Uranium Collection (UR-TK-100/120/140/160) Feed to the U recovery a nd recycle system will consist of uranium-bearing solutions generated b y the first cycle of the Mo purification system , which wi ll be acc umul ated in the impure U co ll ection tanks. These vessels will provide a lag storage capability between the Mo purification and the uranium system equipment. The uranium-bearing sol ution has a nominal composition of approximate l y [Proprietary Information] when processing targets from MURR based on the material balance described in NWMI-2013-CALC-006. The uranium-bearing solut ion concentration is increased to approximately [Proprietary Information] when processing targets from the OSU reactor to reduce the solution volume stored by the impure U co ll ection tanks. So lu tion wi ll b e pumped from the Mo purification system feed tank through the IX beds to the impure U co ll ection tanks. Tank capacity, whe n combined with the first-cycle uranium recovery IX fee d tank , will be sized to contain feed so luti on lag storage such t h at u ran ium processed has been d ecayed at least [Proprietary Information]. The v esse l contents w i ll be maintained at a nominal temperature of [Proprietary Information] by cooling jackets w hile residin g in the l ag s torage tanks. Radiolytic decay is considered the primary heat so ur ce of solutions store d in these vesse l s , a nd t h e so luti on wi ll be maintained at the IX media operating temperature to reduce evaporation during the decay storage time. Storage temperature contro l w ill a l so minimize the time required for temperature adjustment when preparing a feed batch for the IX system. No s ys tem-specific off gas treatment wi ll be provided for this vesse l. However , the potential exists for iodine-131 (1 3 1 1) to evo l ve in offgas from this vesse l, a nd the vent system supporting the vessel i s assumed to requir e treatment to contro l the iodine em i ss i ons. 4-146 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Primary Ion Exchange The primary IX subsystem will separate the bulk of the fission product contaminant mass from the uranium product. IX Feed Tank #1 (UR-TK-200) The IX feed tank will be used to prepare feed batches for the first-cycle uranium recovery system by adjusting the composition of solution fed in batches to IX column # 1 to initiate separation of uranium from fission products. Solution from the impure U collection tanks will be adjusted to a composition of [Proprietary Information]. In addition, reductant will be added to each feed batch , converting fission [Proprietary Information]. The valence state adjustment will reduce the affinity of the IX media for plutonium by addition of a combination of [Proprietary Information]. Evaluation of the kinetics indicate s that the reduction reaction is essentially complete in [Proprietary Information]. Holding reductant is added at a ratio of [Proprietary Information]. No system-specific offgas treatment will be provided for this vesse l. Howe ver, the potential exists for 1 3 1 1 to evolve in offgas from this vessel, and the vent system supporting the vessel is assumed to require treatment to control iodine emissions. IX Column #1 (UR-IX-2401260) The [Proprietary Information] was used in the preliminary design to describe the characteristics of a uranium purification media. [Proprietary Information]. The vendor information indicates that the material is generally produced to support analytica l chemistry samp le preparation. An industrial-scale material , with equivalent properties , is expected to be identified for the IX material used within the RPF. Discussion with the vendor indicates that [Proprietary Information]. A working capacity [Proprietary Information] has been used as the basis for column s izing (NWMI-2013-CALC-009 , Uraniu m Purifi c ation S ys t e m Equipment Sizing). The uranium recovery column operation will consist of processing a sequence of so lution s through the IX media. Co lumn effluents will be routed to different vessels during a process cycle , depending on the ions present in the effluent. The column cycle operations are summarized as follows: *

Loading cycle -Adjusted solution from the IX feed tanks will be fed to the uranium recovery column durin g the loading cyc l e to capture uranium in the liquid phase on the IX media , a llo wing contaminants (e.g., fission products and plutonium) to pass through the column. [Proprietary Information].

Column effluent during the loading cycle wi ll contain a small fraction of the feed uranium and most of the contaminants. The column effluent will be routed to the IX waste collection tanks during the loading cycle , and the composition is projected to [Proprietary Information]. Pre-elution rinse cycle -Once the loading cycle is complete, the uranium recovery column feed will be switched to a solution containing [Proprietary Information] to flush residual loading cycle feed solution from the column liquid holdup. Effluent from the uranium recovery column will be routed to the IX waste collection tanks during the pre-elution rinse cycle because liquid holdup in the column is co n sidered a solution with potential contaminants at the end of the loading cycle. The effluent composition is projected to be [Proprietary Information]. 4-147

NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF De scr i ption Elution cycle -Once the pre-elution rinse cycle is complete, the uranium recovery column feed will be switched to a solution [Proprietary Information]

from the media to the liquid phase passing through the column. Effluent from the uranium recovery column will be routed to the uranium concentrator feed tank# I durin g the elution cycle. The selected eluent volume will be sufficient to flush any desorbed [Proprietary Information] from the column liquid holdup by the time the elution cycle is complete. The effluent solution (eluate) has a nominal composition of [Proprietary Information]. Regeneration cycle -The regeneration cycle will prepare the uranium recovery media to perform a new loading cycle by replacin g the liquid phase with a solution composition similar to the adjusted impure uranium feed solution. The column feed will be switched to a so lution containing [Proprietary Information], which will be used to displace any residual liquid holdup that may be present at approximately [Proprietary Information]. Effluent from the uranium recovery column will be routed to the IX waste collection tanks during this cycle, and the effluent composition can be characterized as a solution that is on the order of [Proprietary I nformation]. Separation of the uranium system from the other major processes will provide the flexibility to select a column size to support the operation. NWMI-20 I 3-CALC-009 performed a sensitivity study of column s ize versus the number of uranium batches purified in a week of operation. Therefore, column sizing could be viewed as a tradeoff between the complexity of processing more IX feed batche s with the cost of maintaining a lar ger resin inventory in the facility. While not formally optimized, the sizing comparison selected a column size ba se d on processing the uranium throughput in [Proprietary Information]. This allows a total [Proprietary Information] for processing each feed batch to co mplete the uranium processing in a total operating period of [Proprietary Information]. Table 4-49 provides a summary of the uranium recovery column cycles, including the volume processed , liquid phase flow rate, and time r eq uired to complete each cycle. The flow s and volumes are based on a two-column system, operating in parallel, with a [Proprietary Information]. The two-column system was selecte d to achieve the required throughput usin g columns that satisfy geometrically favorable dimension s for criticality control. Pressure drop across a resin bed at the indicated flow rates is currently predicted to range from approximatel y [Proprietary Information]. Table 4-49. First-Cycle Uranium Recovery Ion Exchange Co l umn Cycle Summary Cycle Fluid Loading f Propri e tar y I nformati o n] Pre-elution rinse [Proprietary Informat io n] E lution [Proprietar y I n fo r mat i o n] Regeneration [Pro prietary Informat io n] [Pr o pri etar y In formati o n] L Proprietary In formation] [Proprietar y In formati o n] [Proprietary In fo r mation] Dimensionless volume f Propri etary In forma ti o n] [Proprietary In formation] [P roprie t a r y I nformation] [Proprietary Information] [Proprietary I Pr o priet ary [Prop ri etar y I nformation] In format io n] In forma t ion) [Proprtetary [Proprietary [Prop r ieiary In fo r mation] Inf o rmat ion] Information] (Proprietar y [Proprietar y [P ro pr ietary In format io n] In format io n] Information) [Proprietary [Proprietary [Proprietary lnformatton] In formation) Information] Note: Volumes and flow rates for a sing l e pro cess bat ch use two co lumn s operating in parallel w ith a [Proprietary Informati on] in each co lumn. This information is provided for a s in gle col umn in the two parallel column sys tem. The r ecyc led uranium is processed in [Propri etary Information] during an individu a l week of operation. BY CV b ed volume. = co lumn vo lum e. [Proprietary Information] [Proprietary Information] Resin performance data provided by the vendor is at [Proprietary Information] which is u se d for the column operating conditions. Temperature control is pro v ided for column feed streams and not on the IX column itself (no cooling jacket on column). Decay heat was evaluated as the primary he at load in the column during operation, and an adiabatic heat balance included in NWMI-2013-CALC-009 indicated that column cooling would not be required under normal operating conditions. 4-148 .; ... ; NWMI :::**::* ...... ' * *

NOATHWlST MEDICAL ISOTOl'ES Primary Concentration NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The primary concentration subs y stem will receive solution fr om the primar y IX subsystem during the elution cycle and concentrate the uranium such that is suitable for adjustment to the feed composition required as input to the secondary IX subsystem. U Concentrator Feed Tank #1 (UR-TK-300)

Uranium-bearing solutions in column effluents during the elution cycle will be concentrated when generated to control the stored volume of process solutions. Eluant from IX column# 1 will be routed to the U concentrator feed tank # 1. This vessel will provide an interface between the column and concentrator that allows control of the concentrator feed rate. The capability to add water to the concentrator feed tank will be provided for control of the concentrate acid concentration. No specific off gas treatment will be provided for this vessel. Uranium Concentrator/Condenser

1 (UR-Z-320)

The uranium concentrator /condenser

1 will be included in the first-cycle uranium system to reduce the volume of uranium-bearing solution that must be stored within the hot cell vessels. Uranium-bearing solution for purification will originate from elution of IX column# 1 , and the solution composition will be approximately

[Proprietary Information]. The dilute solution will be concentrated using a thermosiphon concentrator that operates in a near-continuous operating mode based on natural convection for agitation during operation. The concentrator will be operated at approximately [Proprietary Information]. Under these operating conditions , nitric acid in the concentrate is predicted to be at [Proprietary Information]. The concentrate will be transferred to the uranium IX feed adjustment tanks in the second-cycle uranium recycle system. Overhead vapors from the concentrator will be routed to a condenser that is currently modeled as a simple total condenser operating [Proprietary Information]. Condensate from the condenser is predicted to be characterized as a nitric acid solution with concentration of approximately [Proprietary Information]. No system-specific offgas treatment will be provided for this vess e l. Typical concentrator designs include a de-entrainment section to minimize carryover of uranium-bearing concentrate droplets to the overheads. A nominal superficial velocity of [Proprietary Information] at the concentrator operating conditions , assuming a [Proprietary Information] vessel for criticality control, is used to define the maximum eluent concentration rate. The selected column batch size was found to not be constrained by the de-entrainment section diameter. Condensate Tanks #1 (UR-TK-34013601370) Condensate will consist of solutions that are approximately [Proprietary Information] and will enter the condensate tanks at approximately [Proprietary Information]. No system-specific offgas treatment will be provided for these vessels. Condensate tank #1 will provide an interface point for monitoring condensate generated by uranium concentrator /condenser

1 prior to transfer to the liquid waste handling system. Equipment in the uranium system will be of geometrically favorable design for criticality control , while it is anticipated that the waste handling system equipment will use an alternate criticality control philosophy (e.g., mass control).

The condensate tanks will provide a location for verifying that solutions comply with waste handling criticality control requirements using detectors , as shown in Figure 4-75. 4-149

- - .. NWMI ...... ........... "NomtWESTMEOICAl.ISOTOPU

[Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Sour ce: F i g ure 7-7 o f N WMl-201 3-CA L C-009 , U ranium Purifi c ation S ys t e m Equ i pm e nt Siz in g , Rev. A , Northwest Medi ca l Isotop e s , LLC , C orvallis , Or eg on , 201 3. Figure 4-75. Condensate Tank #1 Configuration Concept Condensate generated by eluate concentration represents a relatively large solution volume that would require an extensive commitment of process floor space if monitoring was performed by a collection , sampling , and transfer control approach. Therefore , an online monitoring concept is proposed for condensate transfers to the liquid waste handling system. Uranium in condensate (from concentrator foaming, or other off-normal conditions) was considered the component of i nterest for crit i cality control. Continuous monitoring of the uranium concentration in condensate sample tank #IA will be provided b y a sample loop to a uranium concentration detector (e.g., fluorimeter). Circulation to the detector will be operated at flow rates that allow samp l e tanks to approximate a continuous, s tirred tank flow pattern. The detector on Tank# I A will control the routing of transfers out of condensate sample tank # IB. Solution transfers out of condensate sample tank# IB will be routed to wa s te handling, as long as condensate uranium concentrations comply with criticality control requirements. A plug flow delay vessel was included between condensate sample tanks IA and IB to provide a minimum time of 10 min between detecting an upset uranium concentration and the observed uranium concentration reaching the diversion point. Diversion is expected to be accomplished by operation of a three-way valve such that the 10-min delay time could be considered conservative. The plug flow dela y vessel will provide a response time for the control system to divert solution away from transfers to waste handling prior to uranium reaching the waste handling transfer l ine. A high uranium co n centration reading will result in diverting the condensate back to the concentrator feed tank and will stop the column elution. Operation in thi s recycle mode will continue until the off-norma l conditions causing the high uranium condensate concentrations are corrected. Condensate sample tank# 1 B will support recovery from an off-normal event , and the uranium monitor at this vesse l will not be used during routine concentrator operation. The condensate sample tank # 1 B monitor will be used to determine that an upset has cleared from the delay vessel system , and condensate is allowed to be rerouted back to the waste system tanks after an upset. 4-150 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Descript ion Secondary Ion Exchange The secondary IX subsystem will provide the final separation of fission product contaminants such that uranium-bearing solution complies with requirements for acceptance by the target fabrication system. Uranium IX Feed Adjustment Tanks (UR-TK-4001420) Concentrate from uranium concentrator /condenser

1 will be collected in one of two tanks that are used to alternate between collecting concentrate and feeding to IX column #2. After collecting a batch of concentrate, the solution will be prepared for feeding the IX column by adding a reductant to modify the valence state of plutonium remaining in the solution.

The reductant is based on addition [Proprietary Information]. No system-specific offgas treatment will provided for these vessels. A majority of radionuclides will be separated from the uranium-bearing solution by IX column # 1. Radiolytic decay heat will not be significant in this vesse l; however, a cooling jacket will be required to control temperature at the IX media operating temperature of [Proprietary Information] as chemical adjustments are performed. IX Column #2 (UR-IX-4601480) The dominant component composition of feed to IX co lumn #2 wi ll be similar to the feed composition of IX column# 1 and has been assumed to be similar for the preliminary design description. The [Proprietary Information] will also be used for IX co lumn #2 , with a uranium loading of approximately [Proprietary Information] during the loading cycle. The column operation wi ll be similar to IX column# 1 and will consist of a sequence of solutions that passes through the IX media. Column effluents will be routed to different vessels during a process cycle , depending on the ions present in the effluent. The column cycle operations are summarized as follows. *

Loading cycle -Adjusted solution from the uranium IX feed adjustment tanks will be fed to the uranium recycle co lumn during the loading cyc l e to capture uranium in the liquid phase on the IX media, allowing contaminants (fission products and plutonium) to pass through the column. Column effluent during the loading cycle will contain a small fraction the feed uranium and most of the feed contaminants. The column effluent will be routed to the IX waste collection tanks during the loading cycle , and the composition is projected to contain [Proprietary Information].

Pre-elution rinse cycle -Once the loading cyc l e is complete, the uranium recycle co lumn feed wi ll be switched to a solution containing [Proprietary Information] to flush residual loading cycle feed solution from the column liquid holdup. Effluent from the uranium recycle column will be routed to the IX waste collection tanks during the pre-elution rinse c y cle , as liquid holdup in the column is considered a solution with potential contaminants at the end of the loading cycle. The effluent composition is projected to be [Proprietary Information]. 4-151

NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Elution cycle -Once the pre-elution rinse cycle is complete, the uranium recycle column feed will be switched to a solution containing

[Proprietary Information] passing through the column. Effluent from the uranium recycle column will be routed to the uranium concentrator feed tank #2 during the elution cycle. The selected eluent volume will be sufficient to flush any [Proprietary Information] from the column liquid holdup by the time the elution cycle is complete. The effluent solution (eluate) will have a nominal composition of [Proprietary Informa t ion]. Regeneration cycle -The regeneration cycle will prepare the uranium media for performin g a new loadin g cycle by replacing the liquid phase with a solution composition similar to the adjusted impure uranium feed solution. The column feed will be sw itched to a solution containing [Proprietary Information], which will be used to displace any residual liquid holdup that may be present at [Proprietary Information]. Effluent from the uranium rec yc le column will be routed to the IX waste collection tanks during this cycle, and the effluent composition can be characterized as a solution that is on the order of [Proprietar y Information]. Column sizing for IX column #2 was assumed to be identical to IX column #1 , based on processing [Proprietary Inform at ion]. This sizi n g was considered appropriate for preliminary de s ign because the dominant component feed composition is similar to the IX column # l feed composition. Therefore, Table 4-49 also provid es a summary of the uranium recycle column cycles , including the volume proce sse d , liquid phase flow rate , a nd time required to complete each cycle. The flows and volumes are based on a two-column sys tem , operating in parallel , with a resin bed volume [P roprietary Information]. The column operatin g temperature will be [Proprietary Information]. Temperature control will be provided for column feed streams and not on the IX column itself(no cooling jacket on column). Secondary Concentration The seco ndary concentration subsystem will receive solution from the secondary IX subsystem durin g the elution cycle and concentrate the uranium such that is suitable for transfer to the uranium recycle subsystem. U Concentrator Feed Tank #2 (UR-TK-500) Uranium-bearing solutions in column effluents during the elution cycle will be concentrat e d , as the solutions are generated to control the stored volume of process so lutions. Eluant from IX column #2 will be routed to the U concentrator feed tank #2. This vessel will provide an interface between the column and concentrator that will allow control of the concentrator feed rate. The capability to add water to the concentrator feed tank will be provided for control of the concentrate acid concentration. No specific offgas treatment will be provided for this vessel. 4-152 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Uranium Concentrator/Condenser

2 (UR-Z-530)

Uranium concentrator /condenser

2 will be similar to uranium concentrator

/condenser# I and will be included in the second-cycle uranium system to reduce the volume of uranium-bearing solution that must be stored within the hot cell vessels. Uranium-bearing solution for purification will originate from elution of IX column #2, and the solution composition will be [Proprietary information]. The dilute solution will be concentrated using a thermosiphon concentrator that operates in a near-continuous operating mode based on natural convection for agitation during operation. The concentrator will be operated at approximately [Proprietary information]. The concentrate will be transferred to the rec y cled uranium collection and adjustment tanks. Overhead vapors from the concentrator will be routed to a condenser that is currently modeled as a simple total condenser operating at [Proprietary Information]. Condensate from the condenser is predicted to be characterized as a nitric acid solution with concentration of [Proprietary Information]. No system-specific offgas treatment will be provided for this vessel. Typical concentrator designs include a de-entrainment section to minimize carryover of uranium-bearing concentrate droplets to the overheads. A nominal superficial velocity of [Proprietary information] at the concentrator operating conditions , assuming a [Proprietary information] diameter vessel for criticality control, is used to define the maximum eluent concentration rate. The selected column batch size was found to not be constrained b y de-entrainment section diameter. Condensate Tanks #2 (UR-TK-54015601570) Condensate tanks #2 will provide an interface point for monitoring condensate generated by uranium concentrator /condenser

2 prior to transfer to the liquid waste handling system. The function of these vessels is identical to that of condensate tanks# I. No system-specific offgas treatment will be provided for these vessels. Recycled Uranium Collection Tanks (UR-TK-600 and UR-TK-620)

The recycled uranium collection tanks will provide a lag storage capability between the uranium recycle and target fabrication system equipment. The solution entering the vessels will originate as concentrate from uranium concentrator /condenser

2. The solution will have a nominal composition ranging from [Proprietary information].

Two individual tanks will be provided for recycled uranium product collection. The recycled uranium collection tanks will perform the following functions. *

Concentrate receiver tank -This receiver tank will accumulate recycled uranium batches generated by uranium concentrator

2. The tank will provide holdup of the uranium solution as it is generated by the concentrator to create solution batches that can be periodically transferred to a vessel that can be sampled to confirm compliance with product specifications. Product sample tank -This sample tank will be used to verify that the recycled uranium complies with product specifications.

The tank will provide a vessel for sampling an accumulated batch of concentrate from uranium concentrator

2. The sample vessel will provide a location for the sampler installation and holdup time for the uranium product batch sample to be analyzed. The vessel will also enable the diversion of the sampled solution to a rework tank if sample analysis indicates that the product batch does not comply with product specifications.

4-153 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description A nominal temperature of [Proprietary Information] is currently specified for solution stored in the recycled uranium collection tanks , and coolingjackets are included to cool concentrate stored in the product sample and recycle uranium transfer send tanks. No system-specific offgas treatment will be provided for this vessel. Uranium Rework Tank (UR-TK-660) The uranium rework tank will provide the capability to divert out-of-specification recycled uranium, detected in the product sample tank , to be accumulated and returned to one of the two uranium feed batch adjustment tanks. The solution will then be processed by transfer to the uranium IX adjustment tanks in the second-cycle uranium system and prepared to be feed to IX column #2. No system-specific offgas treatment will be provided for this vessel. Uranium Decay and Accountability Tanks (UR-TK-700 and UR-TK-720) NWMI-2014-RPT-005 , Uranium R ec overy and R ecy cl e Process Evaluation D ec isions, recommends that transfers of uranium product from the uranium system be delayed to allow for decay of [Proprietary Information] to transfer to the target fabrication system. The recycled uranium should be greater than or equal to an [Proprietary Information] for radiation exposure to be reduced to a level that allows contact operation and maintenance in the target fabrication systems. The uranium decay holdup tanks will provide storage [Proprietary Information]. The uranium decay holdup tanks will consist of [Proprietary Information] that are supported by a manifold system that will allow filling and emptying of individual tanks. The tank group capacity is estimated to provide the required holdup time for a system that processes the uranium thro ug hput of [Proprietary Information]. The uranium decay holdup tanks will be co-located with a recycled uranium transfer send tank, which will provide the capability to perform accountability measurements of uranium crossing a facility licensing boundary. The transfer send tank will provide a vessel for performing measurement of the uranium mass that is transferred between the uranium and target fabrication systems. The uranium mass measurement will need to emphasize techniques that provide an uncertainty conforming to accountability requirements. Sample analyses will focus only on the uranium and nitric acid concentration of product solution. Multiple samples and tank level instruments may be needed to reduce measurement uncertainty. In addition, the temperature of process solutions during sampling , tank level measurements , and sample analysis may need to be controlled. Spent Ion Exchange Resin Resin Replacement Vessels (UR-TK-8201850) Resin beds are anticipated to periodically require replacement, as most resins gradually degrade due to exposure to both chemicals and radiation. The degradation reduces the resin uranium capacity and reduces the loading cycle volume (decreasing the process throughput rate) or decreases the effectiveness of uranium separation from unwanted fission products. The frequency of resin bed replacement must be determined based on testing. Resin replacement will likely be required after experiencing an absorbed dose on the order of [Proprietary Information]. The resin replacement vessels will support removal of spent resin from an IX column and addition of fresh resin to a column after spent resin has been removed. The resin replacement vessels have been evaluated as a combination of tanks located inside and outside the hot cell to clarify the flow of material during the resin replacement activity. The current concept for resin replacement vessels includes spent resin collection tanks and a transfer liquid storage tank located inside the hot cell. Fresh resin makeup tanks will be located outside the hot cell. 4-154 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description There wi ll be a total of [Proprietary Information] in the RPF: [Proprietary Information]. Resin replacement activities wi ll be performed during time periods when the uranium system is not attempting to process uranium solutions. The frequency of resin replacement is not yet established. The higher dose rates to resin beds in the first uranium cyc le are anticipated to require more frequent replacement than the second uranium cycle resin beds. The spent resin collection tanks will be provided to s upport removal of spent resin from the IX columns and samp ling resin prior to transfer ofresin to the waste handling system for disposal. The spent resin collection tanks are designed with geometrically favorab l e dimensions to control the potential for criticality. Sampling or monitoring of the spent resin uranium content will be required prior to transfer to the waste handlin g system, where vesse l s are not expected to be designed to dimensions that control criticality by geometry. Two spent resin co llecti on tanks will be provided so that the two IX columns in a uranium cycle can be replaced to allow resumption of uranium processing without waiting to complete spent resin sampling or monitoring and then transfer to the waste handling system. The spent resin collection tank operation w ill be s upported by a resin transfer liquid tank to manage liqu ids in the resin slurry during transfers. The fresh resin makeup tanks will be provided to support preparation of fresh resin for addition to an IX co lumn after spent re s in has been removed. The fresh resin makeup tanks will be locat ed outsi de the hot cell and will not contain materials that have been contacted with uranium or fission products. Therefore , the vessels are not designed using dimensions to contro l the potential for criticality. One fresh resin makeup tank per column is currently identified as a method for minimizing the potential for batching resin in a sing le column. The above de scription provides a detailed account of the SNM in process during the target disassembly activities. The SNM , a long with any included fission-product radioact i vity, is described in Section 4.4.1.3. Based on this description , these operations can be conducted safely in this facility. 4-155 NWM I ...... * * ' NORTHWEST MEDICA&. ISOTOPll NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description 4.4.1.2 Proce ss E quipment Arrangement The U recovery an d recyc l e system e quip me n t arra n ge m ent w i t hin t h e tank hot ce ll is s h own in F i gure 4-7 6. [P roprietary I n formation] Figure 4-76. Tank Hot C e ll Equipment Arrang e ment 4-156 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description 4.4.1.3 Process Equipment Design A common vesse l geometry h as been assumed for eac h vessel in the U recovery and recycle sys tem based on dimensions that provide geometrica ll y favorable d esigns for criticality control when process so lution s contain uranium at 20 wt% 235 U. The assumed geometry is ba se d on a [Proprietary Information]. Detailed design calcu lations were not developed for equipment as part of the preliminary design. However , a de scription of the following major uranium proces s ing equipment pieces can be developed from past experience with s imil ar types of facilities. The major equipment for the uranium processin g system will consist of tanks , IX columns, and concentrators. Tanks will r epresent a dominant vessel used as equipment in the uranium system. Two differ e nt tank types hav e been assumed as equipment in the preliminary d esign: ( 1) un cooled tank configuration, and (2) coo l ed tank configuration. An example o f an individual pencil tank for the altern at ive configurations is shown on Figure 4-77. Both tank alternatives are int ended to satisfy [Proprietary In formatio n] No t e: P e n c il tank h e i g ht varied based on tan k capacity r e quir ements. Figure 4-77. Alternative Pencil Tank Diameters for Equipment Sizing criticality requirem ents for a geometrica lly favorable desi gn. The uncooled tank will b e constructed from [Propri etary Information] Schedule 40 pipe len gths as the primary tank wall. A coo l ed tank will be constructed from [Proprietary Information] Schedule 40 pipe lengths as the primar y tank wall, combined with a coo lin gjacket fabricated from [Proprietary lnformation] Sc hedule 40 pipe. The cooled tank configuration will provide ge ometry control for the uranium-bearing solutions under une x pected accident conditions , where process liquid le a ks into the cooling jacket due to corrosion or other vessel failure mechanism. A major difference between the two tank configurations i s the capacity of the a lt e rn atives to store process liquid. The uncooled tank configuration will have a capacity of [Propriet ary Information] of primary vessel length, while the cooled tank configuration will have a ca pacity of[Proprietary Information]. 4-157 Figure 4-78 is a conceptual sketch of an IX column for uranium purification. The vesse l is currently envisioned as based on a [Proprietary Inform atio n] diam eter cylindrical geometry for criticality control , with the IX media s upport ed on a screen to form a resin bed. An upper screen will be included in the column to restrain the resin within a fixed portion of the column. Inlet and outlet piping connections will commun icat e with the resin section of the column to allow periodic bed replacement using s lurry transfer of the resin. The current NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-78. Conceptual Ion Exchange Column for Uranium Purification concept is based on providing a config uration with two of the co lumn s shown i n Figure 4-78 that operate in parallel for each of the IX cycles. Liquid phase will pass through the co lumn in a down-flow such that feed for a p articular colu mn cycle will enter at the top of the column and cycle effluents wi ll l eave the column fro m the bottom. The column is anticipated to include a rupture di sk-t ype safety pressure relief assembly as part of the column design. Pressure-relief capabilities wi ll typically be required when using organic resins in a nitric acid system. Figure 4-79 is a conceptua l sketch of a typical concentrator for uranium-bearing solutions where uranium must be controlled by a geomet rically favorable design. The configuration shown in Figure 4-79 is based on a natural convection thermosiphon arrangement, but cou ld be confi g ured as a forced co nvection equi pm ent piece. Dilute feed will enter the concentrator near the bottom and circulate through the reboiler. The reboiler will he at the so lution and partially evaporate the feed liquid. Vapor wi ll migrate up the concentrator vesse l , through a demister , and will then be condense d. Feed liquid will [Proprietary Information] Sou r ce: F i g ure 2 [modified] ofO R N L/T M-55 I 8 , D es i g n and T es t of a Th e rm os iphon Evapo rat or for Ac id-D efic i e nt U ran y l N itrat e, Oak Rid ge a ti o nal Laboratory , Oak Rid ge , Tenne ssee , November , 1 976. Figure 4-79. Conceptual Uranium Concentrator Vessel continue to circulate thro u g h the reboiler until the so lution reaches a goa l density. For the conce ptual sketch, co ncentrat e overflows from a mid-point position of the co ncentr ator to a receiver vesse l. Table 4-50 pro vides a summary description of the U recovery and recycle proces s equipment. 4-158

i:.-:;.: .. : NWM I ........ ' *,* NORTHWEST Mt:DtCAl ISOTOl'fS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-50. Uranium Recovery and Recycle Process Equipment (2 pages) Nominal tank Individual diameter tank Tank Temperature Pressure Equipment name Equipment no. (in.) capacity material °C (°F)* atm (lb/in2a)b Impure U collection tanks UR-TK-[Prop r ietary [Proprietary 304L SS [Pr opr i etary [Proprietary I 00/ 120/ 140/160 In formation] In formation]

Inform at i on] In fo rm ation] IX feed tank # 1 UR-TK-200 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information ] IX column IA a nd UR-IX-240/260 [Proprietary [P roprietary 304L SS [Propr i e t ary [Proprietary IX column lB In format i on] Information] In for m ation] In fo rm ation] Concentrator l feed tank UR-TK-300 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Inform atio n] Information] Inform a tion] Information] Concentrator I UR-Z-320 [Proprietary [Proprietary 304L SS [Proprietary [Propri e t ar y Information] Inform at i o n] In fo rm a ti on] Informati on] Condenser I UR-Z-320 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information] Concentrate cooler I UR-Z-320 [Proprie t ary [Propri etary 304L SS [Propri etary [Propri e t ary Information] In for m ation] In fo rm a tion] Informati on] Sample tank# I A UR-TK-340 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Informa tion] Information] Information] Plug flow delay vessel UR-TK-360 [Propr i etary [Propri etary 304L SS [Propr i etary [Propri etary In format ion] Information] In fo rm a ti on] Inform at i on] Sample tank #lB UR-TK-370 [Pr oprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Informati o n] Info r mation] Uranium feed batch UR-TK-400/420 [Proprietary [Propriet ary 304L SS [Proprie tary [Propriet ary adjustment tanks In format ion] Inform ation] In fo rm ation] In for mati on] Uranium recycle exchange UR-IX-460/480 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary column #2 Information] Information] Information] Information] Concentrator 2 feed tank UR-TK-500 [Proprietary [Pr op ri eta ry 304L SS [P ropr i etary [P rop ri e t ary In format i o n] In formation] In format i on] Informati on] Concentrator 2 UR-Z-520 [Proprietary [Proprietary 304L SS [Prop r ietary [Proprietary Information] Information] Information] I nformation] Condenser

2 UR-Z-520 [Prop ri etary [P ropr i etary 304L SS [Propri etary [P ropr ieta r y In forma ti on] In formation]

Inform at i on] Informati on] Concentrate cooler #2 UR-Z-520 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Informati o n] Information] Sample tank #2A UR-TK-540 [Proprietary [Propri e t a ry 304L SS [Propriet ary [Propr i etary In formation] In formatio n] Information] Informati on] Plug flow de l ay vessel UR-TK-560 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information] Sample tank #2 B UR-TK-570 [Proprietar y [Propriet a ry 304L SS [Pro pr i etary [Propr i e tar y Info rmation] Inform ation] Inform at i on] I nformati on] Concentrate receiver tank UR-TK-600 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Informa t ion] Information] Information] Product sa mple tank UR-TK-620 [Proprietar y [Proprietary 304L SS [Proprieta ry [Propriet ar y Inform ation] In format i on] In fo rm at i on] Information] Uranium rework tank UR-TK-660 [Proprietary [Proprietary 304L SS [Proprietary [Prop r ietary Information] Information] Information] Information] Uranium decay holdup UR-TK-7oo c [Propr i etar y [Propri etary 304L SS [Propriet ary [Proprietary tank s c Informat i on] In formation] Inform at i on] Inform a ti o n] Uranium product transfer UR-TK-720 [Proprietary (Proprietary 304L SS [Proprietary [Proprietary send tank Information) lnfonnation) Information] Information] 4-1 59 ...... ;. NWMI .... ** ...... ........ *.* ' *.* ' NORTHWEST MEOICAl ISOTOPfS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-50. Uranium Recovery and Recycle Process Equipment (2 pages) Nominal tank Individual diameter tank Tank Temperature Pressure Equipment name Equipment no. (in.) capacity material °C (°F)* atm (lb/in 2 a)b Sp e nt r es in collection tank s UR-TK-820 [P rop ri e t ar y [P ropr i etary 304L S S [P ro p r i e t ary [P ro pri e t ary In forma ti o n] I nformat i o n] In fo rm a ti o n] In fo rmati o n] Resin transfer liquid tank UR-TK-850 [Propri e t a r y [Proprietary 304L SS [Propri e t ary [Propri e t ary In fo rmation] Informati o n] Information ] Info r mation] Uranium IX wa s t e UR-TK-900/920 [Pro pr ieta r y [P ropr i e t ary 3 04L SS [P ro pri etary [P ro pr ie t a r y coll e ction tank s In form a ti on] In forma t io n] In for m a ti o n] In fo rm atio n]

T e mp e ratur e ran ge es timat e d fo r proce s s so luti o n s. Th e nominal o p era tin g t e mp e ratur e o fIX sy st e m-re lat e d s o l ution s is [Propr i et ary Inform a tion] ba se d on c o n t rollin g re s in op e rating c ondition s. T h e n o mina l op era tin g t e mp e ratur e of th e c onc e ntr a to r sy st e m s in c lude s tran s iti o n to an op e ratin g t e mp e rature o f [Propri e t a ry Inform a ti o n], operatin g t h e c o n ce ntrator a t [Propr ie ta ry Inform a ti o n], and oper a tin g the c ond e n se r a t [P ro prietar y Inform a tion]. C ond e n se r c oolin g wat e r s uppl y is a s sum e d to be a t [Propri e tary In fo rm a tion]. b A tm os pheri c p ress ur e , as c o nt ro ll ed b y the vesse l v entilati o n sy st em t o maint a in a n ega ti ve v es sel pr ess ur e r e lativ e to th e v ess el e n c l os ur e (norm a ll y hot ce ll e n c l os ur e fo r th ese v esse l s). c U ranium d ecay h o ldup tank s [Propri e tary Inform a tion], l ab e l e d U R-T K-7 00A throu g h UR-TK-7 00R. IX SS ion exc h a n ge. = s t ai nl ess s t ee l. Process Monitoring and Control Equipment u = uranium. Process monitoring and control equipment was not defined durin g preliminary design. Th e process description in Section 4.4.1.1 identifies the control strategy for normal operations, which set s requirements for the process monitorin g and control equipment and the associated instrumentation. Othe r information on instrumentation and controls i s provided in Chapter 7.0. Additiona l detail s of the process monitoring and control equipment wi ll be developed for the Operating License Applicatio

n. 4.4.1.4 Special Nuclear Material Description This s ection provides a summar y o f the maximum amounts of SNM and the ch e mica l and physical form s of SNM used in the process. Th is s ection also describes required criticality control fe a tur e s that are designed into the process system s and components. The criticality control features will be in accordance with the doub l e-contingenc y principle, and the RPF wi ll provide suitab l e de fe n s e-in-depth for the cont a ined processes. All SNM discussed in this section is not be considered waste and wi ll be returned to the U recovery and re c ycle system , purified , and reused. Specia l N u clear Materia l Inventory The U recovery and rec y c le s y stem SNM in v entory will be dominated by [Proprietary Information].

After holdup in the impure U collection tanks , the stored uranium solution wi ll be processed by the IX system in multiple s mall batches that are collected in the U deca y tanks. The U decay tanks will provide an additional [Proprietary Information] prior to transfer to the target fabricatio n system. [Proprietary Information] will control worker ex posure during target fabrication operation s. Table 4-51 summ a rizes the U recovery and recycle SNM design ba s is invento ry. Uranium solution concentrations vary from less than [Proprietary Information], depending on the process ac t i v ities supported by a particular vessel and the reactor source for tar g ets in a particula r operating week. Nuclear criticality evaluations performed in Atkins-NS-DAC -NMI-14-006 indicate that the U recovery and rec y cle s y stem ves s els remain subcritical under norma l and abnormal conditio n s when all vessels contain solution at a concentr a tion of [Proprietary Information]. 4-16 0 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-51. Uranium Recovery and Recycle In-Process S p ecia l N u clear Materia l Inventory (2 pages) Stream Form Concentration

Volume SNM mass* Impur e U collection tank s -Liquid uranyl nitrat e (Proprietary

[Pro priet ary (Proprietary UR-TK-1 OOA/B , I 20A/8 , In forma ti o n) In fo rm a tion] Inform a tion] 140A/8 , 160 A/8 TX feed tank I -UR-TK-200 b Liquid uranyl nitrate (Proprietary [Proprietary (Proprietary Inform atio n] Information] Inform ation) Co nc e ntrator I feed tank -Liquid uranyl nitrat e (Proprietary [Propr i e t ary [Propri etary UR-TK-300b In formation) Information] I nformation) Concentrator I holdup -UR-Z-Liquid uranyl nitrate [Proprietary (Proprietary [Proprietary 320b ln formation) Information) Information] Co nd e n sate sample tank I A -Liquid ur a n y l nitra te (Propri e t ary (Propr i etary [Propri e t ary UR-TK-340 b In formation] In fo rm a ti o n) I nformation) Condensate delay tank I -Liquid uranyl nitrate [Propri etary [Proprietary [Proprietary UR-TK-360b Inform ation) Information) Information) Condensate sample tank I 8 -Liquid uran y l nitrat e (Propr ie t ary [Proprie t ary [Propri e t ary UR-TK-3 7 0b In formation] Information] In fo rm at i o n) IX feed tank 2A-UR-TK-400b Liquid uranyl nitrate (Proprietary (Prop ri etary [Proprietary Inform atio n] Information] Inform ation] I X feed tank 2 8 -U R-TK-4 2 0 b Liquid uran y l nitrat e (Proprietary (Propr i etary (Proprietary I n formation] Informatio n) In forma ti o n] Concentrator 2 feed tank -Liquid urany l nitrate (Proprietary (Proprietary (Proprietary UR-TK-500b Information) Information] Information) Concentra t o r 2 h o ldup -U R-Z-Liquid uranyl nitrat e (Proprietary (Pro pri e t ary [Propr ietary 520b In format i o n] Information] I nformation] Condensate sample tank 2A -Liquid uranyl nitrate (Proprietary (Proprietary [Propri e t ary UR-TK-540b Information) Information) Information) Co nd ensate del ay t a nk 2 -Liquid uranyl nitrat e [P roprietary [Propr i etary [Propri etary U R-TK-560b In formation] Inform a tion] In fo rm a ti o n] Condensate sample tank 2B -Liquid uranyl nitrate (Proprietary [Proprietary [Proprie tary UR-TK-570b ln formation] Information] Inform a ti on] Co n centrate re ce i ve r tank -Liquid uran y l nitrat e [Propr ietary [Proprie t ary [Proprietary U R-TK-6 00 b ln formation) In fo rm a ti o n] In forma ti o n] Product samp l e tank -UR-TK-Liquid uranyl nitrate [Proprietary (Proprietary [Proprietary 620b Inform a tion] Information] Information] U r ewo rk tank -UR-TK-66 0 b Liquid uran y l nitrat e [P roprietary [Prop ri etary [Proprietary I nformation] Information] I nforma ti on] U de ca y tanks ([Proprietary Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary Information]) UR-TK-700A to R Inform ation] Information] Inform ation] U product transfer send tank -Liquid uran y l nitrat e (Propriet ary [Proprietary [Propri e t ary U R-TK-720 I n fo rmation] In fo rm a t ion) In format i on] Spent resin collection tank A -Spent resin in water [Proprietary [Propri etary (Proprietary UR-TK-820A Information J Information] Information] S p e nt resin collection ta n k 8 -Spent r es in in water [Proprietary [Prop r ie t ary [P ro p r i etary U R-TK-82 08 In formation) Inform a ti on] In fo rm a tion] Resin transfer liqu i d tank -Resin transfer water (Proprietary [Proprietary (Proprietary UR-TK-850 I nformat io n) Information] Information) 4-161 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF D esc r iption Table 4-51. Uranium Recovery and Recycle In-Process Specia l N u clear Materia l Inventory (2 pages) Stream Form Concentration a Volume SNM mass a IX waste collection tank I -Liquid uran y l nitr ate [Proprietary [Proprie t ary [P roprietary UR-TK-900 In formation) Information] in formation J lX waste collection tank 2 -Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-920 lnfonnation J information J Information]

S M concentration an d mass represent total amount of LEU (combined m u and 238 U at::::; 19.95 wt% m u). b So lution m oves from impure uranium co ll ection tanks , through the uranium process vesse l s , to the U decay tank s during a processing week. c Co ncentrator equip m ent not currently de s i g ned. Holdup volume ap proxim a ted [Proprietary I n fo rm a t io n]. d Co nd e nsate c urr en tl y es timat ed to co nt a in trace qu a ntiti es of uranium [Propri e t ary In forma ti o n). c U ranium co n centrat i o n varies depending o n targets being pro cesse d [Proprietary In fo rm a ti o n]. r R esi n is e lut ed prior to di s p osa l as spe nt resin. Di sposa l strea m s lur ry projected to contain [Propri etary Informati on]. No data are c urrentl y avai l ab l e to predict elute d resin o r transfer liquid ur anium co nt e nt , but expected to contain trace uranium quantities.

s I X waste c urr ent l y est imat ed to conta in tra ce quantiti es of ur a nium at an ave r age [P roprietary I n formation]. I X LEU MURR ion exchange. l ow-enriched uranium. University of Missouri Research R eactor. [Proprietary Inform a tion] osu SNM u O r egon State Un iv e r s i ty. special nuclear material. uranium. Uranium solution collected for decay storage in the impure U co l lection tanks wi ll be processed as multiple smaller batche s throu gh the IX separation sys tem. The nominal weekly process throughput will range from [Propri etary Information]. The IX system is s ized to proce ss so lution in batches containing approximately [Proprietary Information], which w ill be prepared from impure U collection tank transfer s in UR-TK-200. The U recove ry a nd recycle system e quipment design is based [Proprietary Information]. Uranium from the feed tank batch will be collected on the first-cyc l e IX columns and e luted to UR-TK-300 for feed to concentrator UR-Z-320 , while alternating concentrate collection between UR-TK-400 and UR-TK-420. Uranium-bearing eluate will pass through the concentrator feed tank (UR-TK-300) to concentrator UR-Z-32 0 , which i s not intended as a major uran i um collect i on point durin g norma l operation , but can hold up to [Proprietary Information]. While not finali ze d , the current concentrator design (UR-Z-320) is based on a n a tura l convection thermosiphon configuration with the potential to hold up to approximately [Propriet ary Information] under normal operating conditions. Condensate vessels (UR-TK-340 , UR-TK-360, and UR-TK-370) are expected to contain trace quantitie s o f uranium durin g normal operati o n. 4-162 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Uranium concentrate from UR-Z-320 will be collected in the second-cyc l e IX feed tanks (UR-TK-400 or UR-TK-420) using a batch size of approxi matel y [Proprietary Information], collected on the second-cyc l e IX columns, and eluted to UR-TK-500 for feed to concentrator UR-Z-520. As wit h the first uranium cycle , UR-TK-500 is not intended as a major uranium collection point during normal operation, but can hold up [Proprietary Information]. Based on the current concentrator design, UR-Z-520 ha s the potential to hold between [Proprietary Information], dep end in g on the planned normal operating conditions. Concentrate from UR-Z-520 will be collecte d in the concentra te receiver UR-TK-600 from multiple IX batches for transfer to the product sample tank (UR-TK-620). The conce ntr ate rec eiver a nd product samp l e tanks wi ll be capable of holding up to [Proprietary Information]. During normal operation , one transfer per week of [Propr ietary Information] is projected to occur between UR-TK-600, UR-TK-620, and the U decay tanks (UR-TK-700A to R) [Proprietary Information]. The uranium rework tank (UR-TK-660) will be empty during normal operation, but has the capacity to contain [Proprietary Information]. [Proprietary Inform ation] The uranium product transfer send tank (UR-TK-720) will s upport accountability measurements betw een the U recovery and recycle system a nd target fabricat ion system. The tank wi ll norm a ll y be e mpty w h en not supporti n g transfers betwe en the two systems, but will have the capa bili ty to contain approximate l y [Proprietary Inform atio n]. The spent re s in collection tanks (UR-TK-820NB) and resin transfer liquid tank (UR-TK-850) will be us ed to sup port replacement of the IX r esi n columns in the U recovery and recycle system. The IX columns will be elute d to remov e uranium from the media prior to replacement. However, trace ur an ium quantiti es are anticipated to rem ain after column elution. Estimates of residual uranium in spent resin and transfer liquid will be co mpleted for inclusion in the Operating License Application. Waste so lution generate d by the U recovery and recycle system is esti mated to contain small quantities of uranium , which is charac terized as a concentration of [Propriet ary Information]. Multiple was te batche s will be generated during IX column operation. The uranium inventory of each waste batch is estimated to average [Proprietar y Information]. Criticality Control Features Criticality control features are required in this system, as defined in NWMI-2015-CSE-008, NWM I Pr e liminary Criti ca li ty Safety Evaluation: Hot Ce ll Uranium Purification. These features , including passive design and act ive engineered features, allow for ad herenc e to the double-contingency principl e. This sectio n applies the criticality contro l features that are discussed in Chapter 6.0, Section 6.3. The criticality control features for this s ubsy stem will include passive de sign and active engineered features , which are listed below. The passive d esign features wi ll include geometr ic constraints of the floor , process equipment , wo rk stat ions , and ventilatio n system. The active engineered features will include the requir ement of continuous ventilation. C hapter 6.0 provides detailed de scriptions of the criticality control features. 4-163 NWM I ...... !*

N<*THW£ST MEDiCAl ISOTOPfS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The following passive design features affect the design of process equipment, ventilation piping, and the room floor. * * * * * *
For the case of a liquid leak , the floor will be criticality-safe (CSE-08-PDFl), the floor of the hot cell will be sealed against chemical penetration (CSE-08-PDF2), and the floor sumps will have a favorable geometry of shallow depth or small diameter (CSE-08-PDF8).

The geometry of the process equipment will be inherently criticality sa f e (CSE-08-PDF3 and CSE-08-PDFS) and maintain a subcritical geometry during and after a fa cility DB E (CSE-08-PDF4). For the case of liquid leaks to secondary systems, a safe-geometry secondary system barrier will be provided between the process vessels and the unfavorable-geometry supply sys t ems (CSE-08-PDF6 and CSE-08-PDF7). The uranium IX column volume will provide for safe geometry and incorporate a pressure-relief mechanism (CSE-08-PDF9). Local vent headers will incorporate design features for a criticality-safe geometry (CSE-08-PDFl

0) . Back.flow of tank solution into the gas system will be prevented (CSE-08-PDFl

1) . Back.flow of uranium solution to the unfavorable geometry vessels of the chemica l makeup systems will be prevented (CSE-08-PDF12).

Overpressurization of the uranium process vessels will be prevented (CSE-08-AFE 1 ) . Some or all of the engineered safety features and administrative controls are cl a ssified as IROFS according to the accident analyses in Chapter 13.0, Section 13.2. Section 13.2 p rovides a description of the IROFS. The following IROFS will be applicable to the U recovery and rec y cle system activities.

* * * * *
The process equipment is designed to be inherently safe by geometry to prevent criticality.

This approach applies limitations on the configuration , including: (1) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equ i pment with fissile solution (IROFS CS-07). The floor geometry and use of floor dikes are controlled to prevent crit i cality in the event of spills (IROFS CS-08). Chemical and water supplies are potential sources for back.flow of fissile solution t o the large geometry of the chemical supply system or demineralized water system. To prevent back.flow , solutions are provided through an anti-siphon device that separates the supply from the process equipment (IROFS CS-18). Fissile solution that may overflow into the ventilation header is discharged to the floor local overflow drains (IROFS CS-13) or by condensing pots on the ventilation lines (IROFS CS-12). In the event of a heat exchanger internal failure, where fissile solution enters the heating or cooling loop, the secondary chilled water and steam loops are inherently criticality-safe by geometry with detection to notify operators of the upset (IROFS CS-10). Condensate from the uranium concentrators is monitored actively with isolation t o prevent condensate from entering the large-geometry waste handling system (IROFS CS-14). Independent monitoring and isolation provides redundant accident prevention (IROFS CS-15). Batch limits are applied, by means of container sizes, to samples taken for analysis (IROFS CS-02). Where fissile material is piped through facility walls, double-wall piping that drains to safe geometry prevents fissile leakage from accumulating in an unfavorable geometry (IROFS CS-09). 4-164 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Descript ion In addition to the features that apply the double-contingency principle, several features will provide defense-in-depth in criticality control. These features will include the following.

* *
Tanks are vented and unpressurized during normal operations , and corrosion resistance is a design requirement. Level is monitored on all tanks and indicated to the operator to reduce the likelihood of overflow. Criticality calculations analyzed concentrations , mass limits, and volumes that are not anticipated under normal conditions , so the controls can sustain multiple upset s. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled, processed , or stored , as described in Chapter 6.0. The effects of a criticality accident are mitigated by the shie ldin g described in Section 4.2 . The criticality control features provided throughout the U recovery and rec y cle system will be in accordance with the double-contin g ency principle , and the RPF will provide suitable defense-in-depth for the contained processes. 4.4.1.5 Radiological Hazards Radionuclide Inventory A breakdown of the radionuclide inventory is e x tracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes. NWMI-2014-CALC-014 identifies the 123 dominant radioisotopes included in the MURR material balance (NWMI-2013-CALC-006). NWMI-2014-CALC-014 provides the basis for using the 123 radioisotopes from the total list of 660 radioisotopes potentially present in irradiated targets. The majority of omitted radioisotopes exist in trace quantities and/or decay swiftly to stable nuclides.

The reduced set of 123 radioisotopes consists of those that dominate the radioactivity and decay heat of irradiated targets. Activities during an operating week that process targets irradiated in the MURR represent the radionuclide inventory as described in Section 4.1. The radionuclide inventory wi ll be based on a weekly throughput of [Proprietary Information]. The in-process radionuclide inventory of the U recovery and recycle system will be dominated by so luti on Ja g storage in the impure U collection tanks. During MURR target proce s sing , [Proprietary Information] will be stored after the 99 Mo has been extracted by the Mo recovery and purification sy stem. The solution will be stored in an impure U collection tank such that all feed will be at a decay time [Proprietary Information] after EOI when processed b y the U recovery and recycle IX equipment. Figure 4-80 is a simplified flow diagram illustrating the impure U collection tanks in-process radionuclide inventory. Four separate tanks will be provided to obtain the required decay time period. One tank will receive solution transfer from the Mo recovery and purification system and provide stora g e for a decay period of [Proprietary Information]. A second tank will provide storage of material from the prior operating week for a decay period of [Proprietary Information], while a third tank wi ll provide stora g e for a decay period of [Proprietary Information]. A fourth tank will store material that has been decayed to [Proprietary Information], from which feed batches will be drawn for the uranium IX system. 4-165 .. *.-:; .. NWMI ...... ........ *. ' * * ' NOITifWEST MEDtCAl ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-80. Impure Uranium Collection Tanks In-Process Radionuclide Inventory Streams A breakdown of the radionuclide inventory is extracted from NWMI-2013-CALC-006 using the reduced set of 123 radioisotopes as recommended in NWMI-2014-CALC-014. The impure U collection tank in-process inventory is described b y Table 4-52. Table 4-52. Impure Uranium Collection Tanks In-Process Radionuclide Inventory (4 pages) Item MURR target processing Unit operation Impure U collection tank s Decay time after EOI" [Proprietary In format i o n] [Pr op ri e t ary In for m a ti o n] [Pr o pri e t ary In formation] [Proprieta ry In format i o n] [Proprieta ry Informa t i o n] Stream descriptionh [Prop ri etary In formation] [Proprietary In fo rm a ti o n] [Pr o priet ary In for m atio n] [P roprietary In fo rm a ti o n] [Proprietary In formation] Isotopes Ci C Cic Ci C Total Ci 241Am [Proprietary Informal ion J [Proprietary Information J [Proprietary Information] 1 J6 mBa [Propri e ta ry I nformatio n] [Proprieta ry In formation] I [Propri etary In fo rm a ti o n] [Proprietary In formation] [P roprietary In fo rm a ti o n J 1 37 mBa [Proprietary Information J [Proprietary Informati o n] I [Proprietary Information] [Proprietary Informati o n] [Proprietary Inform at ion] 1 39 Ba [Propr i e tary In fo rm a ti o n] [P r o pri e tary I nforma ti o n] I [Propri e tary Inform a ti o n] [Proprieta r y In formation] [P rop ri etary In fo rm at i o n] 140Ba [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Pr o prieta ry Information] [P roprietary Information] 1 4 1ce [Pr o pri etary In formation] [Proprietar y In formation] I [Pr oprietary In formation] [P roprietary In for m a tion] [P roprietary I nform atio n] 14 3C e [Proprietary Information] [Proprietary Information 1 I [Proprietary Information] [Pr o prietary Information] [Proprietary Information] 144Ce [Proprie tary I nformation] [Propriet ary In fo rm a ti o n] I [Propriet ary In for mati o n] [P ro priet ary In fo rm a ti o n] [P r o prietary In formation] 242 cm [Proprietary Information J [Proprietary Information] I [Proprietary Information] [Pr o prietary Information] [Pro prietary Information] z43 Cm [Propr i e t ary In formation] [P r opr i etary Information] I [P roprietary Information] [Proprietary In formation] [P rop ri e ta ry In formation] 244C m [Proprietary Information] [Proprietary I nformation] I [Proprietary Information] [Proprietary Information] [Proprietary Information] n4 cs [Proprie tary I nforma t ion] [Proprietar y In for mati o n] I [Pr opr iet ary In formation] [P ro prieta ry In formation] [P roprietary In formation] 1 J 4mcs [Proprietary Information] [Proprietary In fo rmation] I [Proprietary Information] [Proprieta ry Inform a tion] [P roprietary Information] 1 J6 Cs [Propri etary In fo rm a ti o n] [Proprietary In fo rmati o n] I [P r opr i etary In formation] [Proprietary In formation] [P ropr i etary In formation] 137 Cs [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprieta ry Information] [Pro prietary Information] 1 ssE u [Pro prie ta ry In for mation] [Proprietary Informati o n] I [Propri etary In format i o n] [P roprietary Inform a ti o n] [P r op ri e t a ry I nformati o n] 1 s6E u [Proprietary Information] [Proprietary Information] j [Proprietary Information] [Proprietary Information] [Pro pri e tary Inform at ion] 1 s1 Eu [Proprie t ary In for m a ti o n] [Proprieta ry Inform atio n] I [P roprietary In fo rmation] [P ro prieta r y Inform a ti o n] [P ropr i e t ary In formation] 1291 [Proprietary Information] [Proprietary Information] I [Proprietary Informat i on] [Pr o prietary Information] [Pro prietary Information] nor [Proprietary In fo rm atio n] [P rop ri e tar y Informati o n] I [Proprietary In formation] [P roprietary Inform a tion] [P ro pri etary In fo rm ation] 1311 [Proprietary Information] [P r oprietary Information] I [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-166

.**.* ... ...... NWMI .......... * "NOATlfWUT MflHCAL tsOTOPE S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-52. Impure Uranium Collection Tanks In-Process Radionuclide Inventory (4 pages) Item MURR target processing U nit operation Impure U co ll ectio n tanks Decay time after EOI" [Propr i etary In formation)

[Proprietary Information] [Proprietary Information) [Proprietary In formation] [Proprietary Information] Stream de s criptionb [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary In forma ti on] [Proprietary In forma t ion] Isotopes Total Ci 1 3 2] [Proprietary I nformation] [Proprietary Information 1 I [Proprietary Information] [Proprietary In formation] [Proprietary Information] 132m r [Proprietary Informa tion] [Proprietary Informat ion] J [Proprietary Information] [Proprietary Information] [Proprietary Information] 1 3 3] [Propr i etary Information] [Proprietary Information] I [Proprietary Information] [Proprietary In format i on J [Proprietary Information] 133m] [Proprietary Information J [Proprietary Information] J [Proprietary Information J [Proprietary Inform ation] [Proprietary Information] 1 3 4 1 [Proprietary Information] [Propr i etary Information] I [Proprietary Information] [Proprietary In formation] [Proprietary Information] 135 1 [Proprietary Information] [Proprietary In format i on] J [Propri e t ary Information] [Propri etary Inform at ion] [Proprietary Information] 8 3 mKr [Proprietary Information] [Proprietary Information] I [P roprietar y Informat i on] [Proprietary I nformation] [Proprietary Information] 85K.r [Proprietary Information] [Proprietary Information] J [Proprietary Information] [Propri etary Inform at ion] [Proprietary Information] 85mKr [Prop ri etary Information] [Proprietary Information] I [Proprietary Information J [Proprietary Information] [Proprietary Information] 87K.r [Proprietary Information] [Propr i e tary Information] I [Propri etary Informati on] [P roprietary Information] [Proprietary Informat ion] ssKr [Prop ri etary Information] [Proprietary Information] I [P roprietar y Information] [Proprietar y In formation] [Proprietary Information] 140La [Propr i etary Information J [Proprietary Information] I [Pr oprietary Information] [Proprietary Information) [Proprietary Information] 141La [Proprietary In formation] [Proprietar y Information] I [Proprietary Information] [Propr i etary In formation] [Proprietary Information] 142La [Proprietary Information] [Propriet ary Information] I [Proprietary Information] [Propri etary Inform ation] [Proprietary Informat ion] 99Mo [Prop ri etary In formation J [Proprietary Information] I [Proprietary Information] [Proprietary In formation] [Propr i e ta ry Information] 95 Nb [Proprietary Information] [Proprietary Information] I [Propri etary Info rmation] [Pr oprietary Inform at ion] [Proprietary Inform ation] 95mN b [Proprietary Information J (Proprietary Information] I [Proprietary Information] [Proprieta r y In formation] [Proprietary Information] 96N b [Proprietary Information) [Proprietary Information] I [Propriet ary Information] [Proprietary Information] [Proprietary Information] 97Nb [Proprietary In format i on] [Proprie t ary Information] I [Proprietary Information] [Proprietary In formation] [Proprietary Information] 97mNb [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Prop rietary Inform ation) [Proprietary Informat ion] 141N d [P r op ri etary In formation] [Propr i etary Information] I [Proprietary Information] [Proprietary In format i on] [Proprietary In formation] 236mN p [Prop rietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information] [Proprietary In formation] 2 3 1N p [Prop ri etary I nformat i on] [Proprietary Informa ti o n] I [Proprietar y Information) [Proprietary I nformation] [Proprietary In formation] 238N p [Proprietary Informati on] [Proprietary Information] I [Proprietary Informat i on] [Proprietary Information] [Proprietary Information] 239N p [Proprietary Information] (Propriet a ry Information] I [P roprietar y Information] [Proprietary I nfo rmati on] [Prop ri etary Information] 233 p 3 [Proprietary Information] [Proprieta ry Information] I [Propri e t ary Info r mation] [Proprietary Informati on] [Proprietary Informati on] 2 3 4pa [Prop ri etary Information] [Proprietary Information] I [P roprietar y Information] [Proprietar y I nformat i on] (Prop ri etary Information] 234m p 3 [Propr iet ary Information] [Proprietary Informat i on] I [Proprietary Information] [Propri etary Information] [Proprietary Informati on] 1 1 2p d [Proprietary Information] [Proprietary Information] I [P rop ri etary Information] [Proprietar y I nformation] [Proprietary Information] 147pm [Proprietary Information J [Proprietary Informat i o n] I [Proprietary Information] [Proprietary Information] [Proprietary Informati on J 148 pm [Prop ri etary In formation] [Proprietary In fo rm ation] I [Proprietary Information] [Proprietary Information] [Proprietary Information] 148mpm [Proprietary Information] [Proprietary Inform at ion] I [Proprietary Information] [Proprietary Information] [Proprietary Information] 149pm [Proprietary Information] [Proprietary Information] I [Pr oprietary Information] [Proprietary Inform at i on J [Propr i etary Information] 1 sopm [Proprietary Information] [Proprietary Information 1 J [Proprietary Informat i on] [Proprietary Information] [Proprietary Inform a tion] 1 s1p m [Propr i e t ary I nformation] [Proprietary Information] I [P roprietary In fo rm at i on] [P roprietar y I nformat i on] [Proprietary I nformation] 1 42Pr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Propr ietary In formation J [Proprietary Information] 4-167 ... .-.**=-***NWMI ...... ........ *. ' *.* NORTHWEST MEDICAUSOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-52. Impure Uranium Collection Tanks In-Process Radionuclide Inventory (4 pages) Item MURR target processing Unit operation Impure U collection tanks Decay time after EOI" [Proprietary In format i o n] [Proprietary Inform at ion] [Propriet ary Information] [P roprietary Informati on] [P r oprietary Inform at i on] Stream descriptionb [Proprietary In formatio n] [Proprietary Inform ation] [P roprietary Information) [Propriet a r y Informati o n) [P roprietary Inform ation) Isotopes Ci c Cic Ci c CiC Total Ci 1 4 3 pr [Proprietary Inform ation] [Propri etary Information) I [Pr op ri etary Information) [Proprieta r y Informati on] [P roprietary Inform ation] 1<<pr [Propriet ary Information] [Proprietary Information) I [Proprietary Information] [Proprietary Information] [P roprietary Informati o n] 144mpr [Proprietary Inform atio n) [Propriet ary In fo rmati o n] I [Pr oprietary Information] [Prop rietary Informati on] [P rop ri etary Inform a tion] J45pr [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information] [P roprietary Information] 238 pu [Proprietary Inform ation) [Proprieta ry Inform a tion] I [Propriet ary Inform atio n] [P roprie t a r y Informati on] [P roprietar y I nformation] 239pu [Proprietary Information] [Proprietary Information 1 I [Proprietary Information J [Proprietary Information] [P roprietary Information] 2 4Dpu [Pr o pri etary Inform atio n] [Propriet a r y In formatio n] I [Prop rietary Information] [P roprie t a r y Informati on] [P roprietary Inform ation] 241pu [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information) [P roprietary Information J I03mRh [Proprietary In format i on] [Propriet ary Inform a ti o n) I [Proprietar y In format ion] [P ropr i eta r y I nformati o n] [P roprietary Inform ation] 105Rh [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information] [P roprietary Information] 10 6 Rh [Proprietary In formation] [Propri e t ary In fo rm atio n] I [Prop r i etary Information] [Pr oprie t a r y I nformation) [P roprietary Informa tion] I06mRh [Proprietary Information] [Proprietary Information 1 j [Proprietary Information) [Proprietary Information] [P roprietary Information) 1 03 Ru [Propri e t ary In formation) [Propri e t ary Inform a tion] I [Propri e t a r y In fo rm a ti o n] [Proprie t a r y Informati on] [P roprietary Information] 1o s Ru [Proprietary Information) [Proprietary Information] I [Proprietary Information] [Proprietary Information] [P roprietary Information] 1 06 Ru [Propri etary In format ion] [Propri e t ary Information] I [Propri etary In forma ti on] [P roprieta r y I nformati on] [P roprietary Information) 122 sb [Proprietary Information] [Proprietary Information] I [Proprietary Information) [Proprietary Information) [P roprietary Information] 1 24 sb [Proprietary Information] [Pr o pri etary Information] ![Propri etary Information] [Proprieta r y I nformati on] [P roprietary Inform ation] 125 Sb [Proprietary Information] [Proprietary Information] j [Proprietary Information] [Propri etary I nformation] [P roprietary Information] 126Sb [Pro pri etary Information) [Propri e t ary In forma tion) I [Propri etary Information] [P roprieta r y I nform a tion] [P roprie t ary Inform ation] 127 Sb [Proprietary Information) [Propri e tary Information] j [Proprietary Information] [Proprietary Information] [P roprietary Information) 1 2s sb [Pr op r i etary In format i on] [Propri etary In forma tion] I [P ro pri etary Inform a tion] [Proprieta r y I nform a tion] [P roprie t ary Inform ation] 1 2 smsb [Proprietary Information) [Proprietary Information) I [Proprietary Information) [Proprietary Information] [P roprietary Information) 1 29 Sb [Proprietary Information) [Propriet ary In for mati o n) I [Pr opr i etary Information] [Propri eta r y I nform a ti on) [P roprieta ry Informati on] 1s1sm [Proprietary Information J [Proprietary Information) I [Proprietary Information) [Proprietary Information] [P roprietary Information) i sJ sm [Propr i etary In formatio n) [Propriet ary Information) I [Pr oprietary Information] [Proprieta ry Inform ation] [P ropr i etary Inform ation] 1s6sm [Proprietary Information] [Prop r ie t ary Information) I [Proprietary Info r mation] [Proprietary Information] [P roprietary Information) 89S r [Proprieta ry In formation) [Propriet ary Information) I [Proprietary Information) [Propriet a r y Inform ation) [P r o prietary In for mati on) 9osr [Proprietary Information) [Proprietary Information] I [Proprietary Information] [Proprietary Information] [P roprietary Information] 9 1sr [Proprie tary In forma tion] [Propri etary Information 1 j [Propri etary Information) [Propri etary Information) [P r op ri e ta ry Informa tion] 92 Sr [Proprietary Information J [Proprietary Informat i on] I [Proprietary Information ] [Proprietary Information] [P roprietary Information) 99Tc [Proprietary Information] [Proprietary Informat i o n) I [Propriet ary In fo rm at i o n) [Proprietary I nform at ion] [P r op rieta ry Inform ation) 99mTc [Proprietary Information) [Proprietary Informat i on] I [Proprietary Information) [Proprietary Information) [Proprietary Information) 1 2sm Te [Pr op ri etary Informati on] [Proprietar y Information] I [Propriet ary Informati on] [Proprietar y Information] [P roprietary Inform at i o n] 1 21Te [Proprietary Information) [Proprietary Informat i on] I [Proprietary Information] [Proprietary Information] [P roprietary Information] 1 27 mTe [Proprietary Information) [Proprietar y Information) I [Propriet ary In fo rmati o n] [Proprietary Inform at i on] [P roprietary Informa tion] 129Te [Proprietary Information] [Proprietary Information J j [P r oprietary Information] [Proprietary Information] [P roprietary Information] 4-168 ...... .. .. .*.******* NWMI NORTHWEn M£DICAL ISOTWU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-52. Impure Uranium Collection Tanks In-Process Radionuclide Inventory (4 pages) Item MURR target processing Unit operation Impur e U co ll ect ion tanks Decay time after EOI" [Propriet a ry Information] [Proprietary In formation] [Propriet a ry Information] [Propri e tary Information] [Proprietary Informati o n] Stream description b [Proprietary Information] [Proprietar y Information] [Propri e tary Information] [Propri e tary In formati o n] [Proprietary Informati o n] Isotopes Cic Cic Cic Ci c 1 29 mTe [Proprietary Informati o n] [Proprietary Informati o n 1 I [Proprietary Information] [Pr o pri e tary Inform a tion] 1J1Te [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary In formation] 1 3 JmTe [Propr i etary Inform a tion] [Proprietary Informati o n] I [Proprietar y Information] [Propri e t a r y Information] 1J2Te [Proprietary Information] [Proprieta ry Information] I [Proprietary Information] [Proprietary Inform ation] 1 3 3Te [Propr i etary In formation] [Proprietar y Information] I [Proprietar y Information] [Propriet a r y I nformation] 1 33mTe [Proprietary In forma tion] [Proprietary Information] I [Proprietary Information] [Proprietary Informati on] !3 4Te [Pr o prietary I nform a ti o n] [Proprietary Informati o n] I [Propriet a ry Information] [Propri e tary In formation] 231T h [Proprietary In formation] [Proprietary Information] I [Proprietary Information] [Proprietary Inform ation] 23 4T h [Proprietary In fo rm a ti o n] [Proprietary Information] I [Propriet a ry I nformation] [Propri e t a r y Informati o n] 232u [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary In forma ti on] 234 U [Propri e ta ry In fo rmation] [Propriet a r y Informati o n] I [Pr o priet a ry Information] [Propriet a ry Inform a ti o n] 23su [Proprietary Information] [Proprietary Informat i on] I [Proprietary Information] [Proprietary Inform ation] 23 6U [Proprietary Inform a tion] [Propri e tary Information] I [Pr o prietar y Information] [Proprietar y I nformati o n] 231u [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Inform a ti o n] 2 3 su [Proprie t ary Information] [Proprietar y Information] I [Propriet a r y In formation] [Propri e t a r y In format i on] 1J1mxe [Proprietary Information] [Proprietary Information 1 I [Proprietary Information] [Proprietary Inform at i on] 133 Xe [Propri e tary Inform a tion] [Propr i etary I nformation] I [Propriet a r y Information] [Propri e t a r y I nformati o n] JJJmxe [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information ] 135 Xe [Propri e ta ry Inform a tion] [Proprieta ry In fo rm a ti o n 1 I [Propriet a r y Information] [Prop r ieta ry Informati o n] 1Jsmxe [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Inform ation] 89my [Proprieta ry Inform a ti o n] [Propr i etar y In fo rmation] ![Proprieta ry Information] [Pro p ri e tar y Informati o n] 90y [Proprietary In formation] [Proprietary Information] I [Proprietary Informati o n] [Proprietary In formation] 90my [Propr i e tary Information] [Proprietar y Information] I [Propriet a r y Information] [Propriet a r y In formati o n] 9J y [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Pr oprietary Inform ation] 9 J my [Propr i etary Inform a tion] [Proprietar y Information] I [Proprietar y Information] [Propri e t a r y In fo rm ation] ny [Proprietary Information] [Proprietary Information 1 I [Proprietary Information] [Proprietary Information] 93 y [Propr i etary Information] [Proprietar y Informati o n] I [Propri e t ary Information] [Pr o pri e t a r y Information] 93z r [Proprietary Information] [Proprietary Information] I [Proprietary Information] [Proprietary Information] 9s zr [Proprietary Information] [Proprietary In fo rm a ti o n] I [Propri etary Inform a ti o n] [Pr o pri e t ary Information ] 91z r [Proprietary Information] [Proprietary In formation] I [Proprietary Information] [Proprietary Information] Tota l Ci [Proprietary In fo rm a ti o n] [Propri e tar y Information] [Propri e tary In formation] [Propri e tar y Informati o n]

l n-process inventory of each s t orage tank based on indicated decay times. Figure 4-80 provides a simplified description of the process streams. c Jn-process inv entory based o n processing of [Propri etary I nform at i on] per operating week. EO I MURR en d of irradiation.

u uranium. University of Missouri Research R eactor. 4-16 9 Total Ci [Proprietary Informati o n] [Proprietary Information] [Propriet a ry Informati o n] [Proprietary Inform at i on] [Proprietary Informati o n] [Proprietary Inform ation] [Proprietary Information] [Proprietary Information] [Propriet a ry Inform a ti o n] [Proprietary Information] [Proprietary Informati o n] [Proprietary Information] [P ro prietary I nformati o n] [Proprietary Inform ation] [Proprietary Information] [Proprietary Information] [Proprietary In formati o n] [Proprietary Information] [Proprietary Informati o n] [Proprietary Information] [Propr i etary Inform a ti o n] [Proprietary Information] [Proprietary In form a tion] [Proprietary Information] [Proprie t ary Information] [Proprietary In format i on] [Proprietary Information] [Proprietary Information] [Proprietary Informati o n] [Proprietary Information] [Proprietary In formation] Solution designated as decayed impure U in Table 4-52 will be withdrawn in multiple batches for processing through the U recovery and recycle separation systems. Figure 4-81 is a simplified flow diagram illustrating the in-process radionuclide inventory of separations provided b y IX and concentrator equipment as feed solution passe s through the system. The radionuclide inventory will be split among the three streams (U condensate , rec yc led U, and U IX waste) by the separation system. All material in-process will be [Proprietary Information] by storage in the impure NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-81. Uranium Recovery and Recycle In-Process Ra d ionuclide Inventory Streams U collection tanks. The maximum radioactive inventory will be based on a weekly throughput of [Proprietary Information]. The separation system in-process inventory is shown in Table 4-53. Table 4-53. Uranium Recovery and Recycle I n-Process Radionuclide Inventory (4 pages) Item Unit operation: Decay time after EOP Stream descriptionb Isotopes 241Am 1 36 mBa l 37 mBa 139Ba 140Ba 141ce 143Ce 144Ce 242cm 243C m 244Cm 134 Cs l34mcs 136 Cs 137 Cs 1 ss Eu 1 s6 Eu 1 s1 Eu 1291 1 3 01 l31I U condensate Ci 0 [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] I [Proprietar y Information] I [Proprietary Information] I [Proprietary Informat i on] I [Proprietary Information] I [Proprietary Information] I [Proprietary Information] I MURR target processing U recover y and rec yc l e [Propri e tar y Information] R ecy cled U Ci 0 [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-1 70 U I X waste Ci 0 [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] NWM I ...... '

NOITHWHT MCotcAl ISOTOl'E.S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-53. Uranium Recovery and Recycle In-Process Radionuclide Inventory (4 pages) Item Unit operation:

Decay time after EOI" Stream descriptionb Isotopes 1 32 1 13 2 mI 1331 133mI 1 3 41 1351 8 3 mJ<r 85Kr 85 mJ<r 87Kr 88Kr 140La 141La 142La 99Mo 9sNb 9 5 mNb 96 Nb 97 Nb 97mNb 1 41 Nd 236mNp 2 31 Np 23sNp 23 9Np 233pa 234 pa 234mpa 1 1 2 pd 147prn 148pm 148mpm 149pm ISOpm I Si pm 142Pr 14 3 pr 144pr U condensate [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information) [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary I n formation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary I n formation] MURR target processing U recovery and recycle [Proprietary Information] Recycled U [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-1 71 U IX waste [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] ......... *.* .. ; ... ; ... NWMI ........... ' *.*

NORTHWEST MEDICAl ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-53. Uranium Recovery and Recycle In-Process Radionuclide Inventory (4 pages) Item Unit operation:

Decay time after EOP Stream descriptionh Isotopes 144mpr 14 5 pr 23 sPu 239 Pu 24 0pu 24 1Pu 10 3 mRh 105Rh 106Rh 106mRh 103Ru 1osRu 106Ru 1 22 sb 1 2 4Sb 125 Sb 1 26 sb 127 Sb 128 Sb 12smsb 129 S b 1s1sm 1s3s m 156 Sm &9s r 9osr 9 1sr 92 Sr 99 Tc 99mTc 1 25 mTe 121Te I 27 mTe 129Te 1 29 mTe 131Te 1 3 1 m Te 132Te U condensate CiC [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta ry Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information ] [Proprietary Information] [Proprietary Information] [Proprietary Information) MURR target processing U recov e r y and rec ycle [Proprietary Information] Recycled U CiC [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-1 72 U I X waste Cic [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propr ietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Propriet a ry Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry I nformation] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] [Propriet a ry Information] [Proprietary Information] NWM I ...... ' e * ' NO<<THWEST MEDttAl tSOTOl'fS NWMl-2015-02 1 , Rev. 3 Chapter 4.0 -RPF Description Table 4-53. Urani u m Recovery and Recycle In-Process Radionuclide Inventory (4 pages) Item Unit operation: Decay time after EOI" Stream descriptionh Isotopes 133 T e 133m Te 1 3 4 Te 231Th 23 4Th 232u 234 LJ m u 2 3 6u 231 u 23 su 1 J1m xe 133 Xe IJJmxe 135 Xe 13smxe 89m y 90y 90m y 9I y 9I my 92 y 93 y 93z r 9s zr 97zr Tota l Ci U condensate CiC [Propri etary Inform atio n] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri e tary I nformation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri eta r y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri e tar y Inform atio n] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri e tar y Information] [Proprietary Information] [Proprietar y Information] MURR target processing U r ecovery and rec ycle [Propri etary Information] R ecycle d U CiC [Proprieta ry Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri e tar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietar y Inform at ion] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Informati on]

In-proces s in ventory based on deca y time [Propri etary Informati on). b Figure 4-8 1 pro vi de s a s implifi e d description of th e proc ess s tr eams. U IX waste CiC [Proprietar y Information]

[Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri e tary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri e t ary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propriet a r y Information] [Proprietary Information] [Propriet ary Information] c In-proces s in ventory based on total [Proprietary Inform a tion], r e pr ese ntin g the weekl y process throu g hpu t. E OI MURR end of irra di a tion. = Univer s it y of Miss o uri R esearc h Reactor. u = uranium. The weekly proce ss throughput described by recycled U in Table 4-53 will be stored in U decay tank s prior to transfer to the target fabrication system. The U deca y tanks will function similar to the impure U collection tanks described above, [Proprietary Information]. Simi l ar to the impure U collection system, the U decay storage system will provide 13 positions for solution storage plu s a position to support transfers to target fabrication [Proprietary Information]. The total activity of uranium solution produced during an operatin g wee k will decrease from [Proprietary Information]. 4-1 7 3 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Radioisotope inventory changes will be dominated b y the [Proprietary Informa t ion]. The total activity of weekly solution transfers to target fabrication at the end of the decay period wi ll be domin ate d by uranium isotopes and includes:

*
* * [Proprietary Information]

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] A simplified bounding estimate of the radionuclide in-process inventory of U decay tanks can be obtained from [Proprietary Information] the radionuclide listing for the recycled U stream shown in Table 4-53 , recognizing that the recycled U composition does not reflect the radionuclide inventory transferred into the target fabrication system. Radiological Protection Features Radiological protection features are designed to prevent the release of radioactive material and to maintain radiation levels below applicable radiation exposure limits prescribed in I 0 CFR 20 for the protection of workers and the public. These features include defense-in-depth and engineered safety features. The engineered safety features identified in this section are described in Chapter 6.0, Section 6.2. The following defense-in-depth features will provide radiological protection to workers and the public. * *

Most U recovery and rec yc le process equipment operates at or slightly below atmospheric pressure or solutions are pumped between tanks that are at atmospheri c pressure to reduce the likelihood of system breach at high pre ss ure. The proce ss equipment is designed for high reliability with materials that minimize corrosion rates associated with the processed solutions. Alarming radiation monitors provide continuous monitoring of the dos e rate in occupied areas and alarm at an appropriate setpoint above background.

The following engineered safety features, listed below as IROFS and described in Chapter 13.0 , will provide radiological protection to workers and the public. * * *

The hi g h-dose material and solution is processed inside shielded areas. The hot cell shielding boundary (IROFS RS-04) provides shielding for workers and the publi c at workstations and occupied areas outside of the hot cell. The hot cell liquid confinement boundary (IROFS RS-01) prevents releases of liquid. Radioactive gases flow to the target di sso lution off gas treatment, which is part of the hot cell secondary confinement boundary (IROFS RS-03). Before the uranyl nitrate solution is rec yc led to the target fabrication system, samples are analyzed to verify sufficient decay and extraction of fission products (IROFS RS-08). Certain high-activity tanks may require a backup purge ifthe normal purge is lost (IROFS FS-03). Additional detailed information about which tanks require backup purge will be developed for the Operating License Application.

4-174 4.4.1.6 Chemical Hazards NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description This section provides a summary of the maximum amounts of chemicals used in the proce ss and the associated chemical hazards. This section also identifies any required chemical protection provisions that are designed into the process systems and components. Chemical Inventory The chemical reagents for the uranium recovery and recycle are listed in Table 4-54. In addition to the chemical reagents , offgases will include NO, N0 2 , and nitric acid fumes. Table 4-54. Uranium Recovery and Recycle Chemical Inventory Chemical OSU batch" MURR batchb Annual quantity" [Proprietar y Information] [Proprietar y Inform at ion] [Propri etary Inform atio n] [Propri etary Informati o n] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Inform a tion] [Propri etary Inform atio n] [Propri etary Inform a ti o n] Demineralized waterd 24,320 L 6,450 L 480,000 L

Represents s um of c h e mic a l a dditi o n s to uranium syste m s calculated by NWMl-20 I 3-CALC-002 , Ov e ra ll Sum m a ry Mat e rial Balanc e -OS U Targ e t B at c h , material b a lan ces for pro cessi ng a n irradiated target batc h (Propri etary Information). b R e pr ese nts s um of c h e mical additions t o uranium systems ca lculat ed by NWMJ-20 1 3-CALC-00 6, Ov e rall Summary Mat e rial Balan ce -M U RR Targ e t Bat c h , m ate rial b a lanc es fo r proc ess in g an irradiated target [Pro pri e t ary Information].

c Annual quantity based on [Propri etary Information]. d R e presents a combination of rec yc l e d water a nd fresh d e mi n era li ze d water. [Pr oprietary Inform atio n] M U RR U niv ers it y of Missouri Re s earch R eactor. [P roprie tary Informati on] OSU = Oregon State U ni vers i ty. [Pro pri etary Inform ati o n] Chemical Protection Provisions The chemical hazards for the U recovery and recycle system are described in Chapter 9.0. Chemicals hazards of the system will be bounded by the radiolo g ical ha za rds. The features will pr event release of radioactive materi a l a nd limit radiation exposure to protect workers and th e public from h aza rdou s chemicals. 4-175 ... ;. NWMI .... ** ...... .......... ' * * ' NOllTHWEST MEDtCAt ISOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

4.4.2 Processing

of Unirradiated Special Nuclear Material This section describes the target fabrication system , which will produce LEU targets from fresh LEU metal and recycled uranyl nitrate. The system begins with the receipt of LEU from the DOE supplier, and ends with packaging new targets for shipment to the irradiation facilities. The uranium received in the target fabrication will be both fresh LEU metal and purified recycled uranyl nitrate; therefore , the uranium within target fabrication may be handled directly without shielding. Table 4-55. Target Fabrication Subsystems lfl.M 4i§i!!.!,i I 00 Fresh uranium receipt and dissolution 4.4.2.1.5 200 Nitrate extraction 300 ADUN concentration 400 [Proprietary Information] 500 [Proprietar y Information] 600 [Proprietary Information] 700 Target fabrication waste 800 Target assembly Due to the variety of activities performed 900 LEU storage 4.4.2.3 4.4.2.4 4.4.2.5 4.4.2.6 4.4.2.7 4.4.2.8 4.4.2.9 4.4.2.10 during target fabrication, the system _A_D_UN ____ a_c-id--d-e-fi-,c-ie_n_t u-r-an_y_l_n-itr-a-te-. --------description is divided into the nine subsystems L E U low enriched uranium. listed in Table 4-55. The key interfaces between subsystems, including uranium flows, are shown in Figure 4-82. [Proprietary Information] Figure 4-82. Key Subsystem Interfaces within Target Fabrication 4-176 4.4.2.1 Target Fabrication Design Basis NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF D escription The target fabrication system will produce and ship targets for irradiation. The overall design basis includes: * * [Proprietary Information] [Proprietary Information]

Ensuring LEU processing and storage meet security and criticality safety requirements Designating target fabrication as a material balance accountability area requiring measurements for SNM
Controlling/preventing flammable gas from reaching lower flammability limit conditions of 5 percent H 2 , designing for 25 percent oflower flammability limit In addition to the overall design basis, more specific requirement s of the design basis are divided into the sub-functions:

receive fresh and recycled LEU, produce LEU target material , assemble LEU targets, and package and ship LEU targets. There is no significant radiological dose hazard associated with target fabrication activitie s. Additional information on the design basis is provided in Chapter 3.0. 4.4.2.1.1 Receive Fresh and Recycled LEU The receive fresh and recycled LEU sub-function will receive and store fresh LEU from DOE for producing targets , and recycled LEU from the U recovery and recycle system. The design basis for this sub-function is to: * * * [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Inform ation] Fresh LEU impurities (based on draft DOE input s) will be as specified in Table 4-56. Table 4-56. Fresh Uranium Meta l Specification (3 pages) Specified item Symbol Units Specification limits EBC factor Uranium purity u gU/g (Proprietary Informati on) (Proprietary In formation] 232 LJ U-232 µgig u [Pr o pri e t ary In fo rm at ion] [Pr o prietary In form a ti o n] 2 3 4U U-234 µglgU [Proprietary Inform atio n] [Proprietary Inform a ti on] m u U-235 wt% [P ropr i et ary Information] [Proprietary Inform ati o n] (+/-0.2%) [Proprietary Information) [Proprietary Informati on] 236 u U-236 µgig u [P ro pri e t ary In fo rm a ti o n] [Pr o prietary In form a ti o n] *re+ 90 S r Tc-99 Bq/gU [Pr o priet ary Information] [Proprietary Informati on) TRU (a lpha) TRU Bq/g U [Pr o pri e tary Information) [Proprietary In form a t i o n] Beta Beta Bq/gU [Proprietary Inform a tion] [Proprietary Inform a ti o n J Activation product s ActProd Bq/gU [P ro pri e t ary Information] [P ro prieta ry In form a ti o n) Fission pro d ucts FissProd Bq/g U [Proprietary Information] [Proprietary Inform atio n) 4-177 "NWMI ...... .t: ** :.:. *

NORTHW'EST MEDtcAl. tsOTOl'lS NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-56. Fres h Uranium Metal Specification (3 pages) Specified item Symbol Units Specif i cation limits EBC factor Moisture H 2 0 ppm or µgig [Pr o priet ary In fo rm a ti o n] [Proprietary In fo rm a ti o n] oxide sa mple Density Density glcm 3 [Pr op rietary Information]

[Proprietary Informati on] S ur face area m 2/g [Propriet ary Informati o n] [P r opr ieta ry In forma t ion] Aluminum Al µglgU [Proprietary Information] [Proprietary Information] Antimo n y Sb µgig u [Propriet ary I nfo rm a ti o n] [Prop ri etary In formation] Arsenic As µglgU [Proprietary Information] [Proprietary Inform ation] Barium Ba µgig u [Prop r i e t ary Inform a ti o n] [Prop ri e t ary In fo rm a ti on] Beryllium Be µgig u [Propriet ary Information] [Proprietary Informati on] Boron B µgig u [Propriet ary In fo rm a ti on] [Propr i e t ary In fo r mation] Cadmium Cd µglgU [Proprietary In for mati o n] [Proprietary In formation] Calc ium Ca µgig u [Pr opr i e t ary In formation] [Proprietary In formation] Carbon c µgig u [Proprietary Information] [Proprietary In forma ti o n] Cesi um Cs µgig u [Propri etary Informati o n] [Propr iet ary In fo rm a ti on] Chromium Cr µglgU [Proprietary Informati o n] [Proprietary Inf orma ti o n] Coba lt Co µgig u [P ropr i e t ary In fo rm a ti o n] [Propr i e tary In form a ti o n] Copper Cu µglgU [Proprietary Inform a tion] [Proprietary Inform a ti on] D ys pro s ium D y µgig u [Propr i etary Informati o n] [Propr i etary In fo r ma t ion] E uropium Eu µglgU [Proprietary In formation] [Proprietary In formation] Gadoli nium Gd µgig u [Propriet ary I nformation] [Propr i etary In fo r mation] Hafnium Hf µglgU [Proprietary Informati o n] [Proprietary Inform atio n] Ir o n Fe µgig u [Propriet ary In forma ti o n] [P r op r i etary In fo rm at i on] Lead Pb µglg U [Proprietary Information] [Proprietary In formation] Lithium Li µgig u [Propr i etary Information] [Propr i etary In fo rm a ti o n] Magnesium Mg µglgU [Propri etary Informati on] [Proprietary Informati o n] Manganese Mn µgig u [P r opr i e t ary In fo rm a ti on] [Propr i e t ary I nformati o n] Mercury Hg µglgU [Proprietary I nformatio n] [Propr ietary Information] Mol y bdenum Mo µgig u [P roprietary In forma ti on] [Propr i etary Inform a ti o n] Nickel Ni µglgU [Proprieta ry Inf o rmati o n] [Proprietary I n formation] Niobium Nb µgig u [Prop r i e t ary I nformation] [P r opr i etary In forma ti on] Nitrogen N µglgU [Proprietary Information] [Proprietary Information] Pho s phorus p µgig u [Prop r ietary Inform a ti o n] [Proprietary In for mati o n] Potassium K µglgU [Proprietary Informati o n] [Proprietary Informati on] Samarium S m µgig u [Propri e t ary I nforma ti o n] [Prop ri etary In fo r ma ti on] Silicon Si µglgU [Proprietary Information] [Proprietary Informati on] Si l ver Ag µgig u [P roprietary Informati o n] [Propr i etary In formation] Sodium Na µglgU [Proprietary Inf ormation] [Proprietary Informati o n] 4-178 NWMI ...... ' * * . NOITHWEST M£ote:Al NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-56. Fresh Uranium Metal Specification (3 pages) Specified item Symbol Units Strontium Sr µgig u Tantalum Ta µgig u Thorium Th µgig u Tin Sn µgig u Titanium Ti µgl gU Tungsten w µglgU Vanadium v µgig u Zinc Zn µgig u Zirconium Zr µgig u TMl (total impurities) µglgU Equivalent boron content EBC µg EB/g U

The values shown reflect the sum of the listed nuclide s: (Proprietary Information]

[Proprietary Information] [Proprietary Information] [Proprietary Information] Specification limits EBC factor [Proprietary In fo rm a ti o n] [P ro prietary Inform a ti o n] [Proprietary Information] [Proprietary Information] [Propriet ary In fo rm a ti o n] [P ro p r ieta ry Inform a ti o n] [Proprietary Information] [Proprietary Information J [Propri e t ary In fo rm a ti o n] [P ro prieta ry Informati o n] [Proprietary Information] [Proprietary Information] [Propri e t ary In fo rm a ti o n] [Propriet a ry Inform a ti o n] [Proprietary Information] [Proprietary Information] [Propri e t a r y In fo rmation] [Pr o pri e t ary Inform a ti o n] [Proprietary Information] [Proprietary Information] [Pr o pri e t ary I nfor m a ti o n] [Pro pri e t ary Inform a ti o n] b EBC factors are taken from ASTM C I233-09 , Standard Pra c ti ce f or D e t e rmining EBC o f Nucl e ar Mat e rial s. EBC calculations will include boron , cadmium , dysprosium , europium , gadolinium , lithium , and samarium. Other E BC factors are provided for information only. The limit on EBC may re s trict some elements to lower value s than those shown in the table. ' The limit on EB C ma y r e strict s ome elements to lower value s than s hown in the table. EBC NM TBR 4.4.2.1.2 equivalent boron content. not me as ured. to be reported. Produce LEU target Material TMI TRU u total metallic impuritie s transuranic. uranium. The produce target sub-function will produce LEU target material. The design basis for this sub-function is to: * [Proprietary Information]

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.**.*.*. ..... ;. NWMI .*.* .. *.*. ' ! *.* ' NOffTHWEST MEDICAL ISOTOP'U * [Proprietary Information]

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[Proprietary Information]
[Proprietary Information]
[Proprietary Information]

N W Ml-2015-021 , Rev. 3 Chapter 4.0 -RPF Description 4.4.2.1.3 Assemble Low-Enriched Uranium Targets The assemble LEU targets sub-function fills , seal welds, and examines targets. The design basis for this sub-function is to: Table 4-57. Low-Enriched Uranium Target Physical P roperties

* *
Clean target hardware components prior to filling with LEU target material Provide capability to collect LEU target material spilled during target filling Provide capability to fill LEU targets to specifications in Table 4-57 Target parameter

[Pr opr i etary Information] [Propri etary Information] [Propr i etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [P ro pri etary Information] [Proprietary Information] a [Proprietary Information] b [Proprietary Information]. Value [Proprietary In forma ti on] [Proprietary Information] [Proprietary Inform ation] [P r oprietary Information] [Proprietary In forma ti on] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] Perform qualification and verification examinations on assembled targets (e.g., helium leak check, weld inspection) 235 U uranium-235. U uranium. to meet licensing requirements TBD = to be determined. [Proprietary Information]

Process out-of-specification targets that fail quality assurance standard(s) 4.4.2.1.4 Package and Ship Low-Enriched Uranium Targets The package and ship LEU targets sub-function stores, packages for shipment, a nd ships unirradiated targets to the university reactors.

The design basis for this sub-function is to: * * * [Proprietary Information] Package targets per certificate of compliance for shipping cask Ship targets per 49 CFR 173 4.4.2.1.5 New Target Handling New target handling is generally addressed in Chapter 9.0. The discussion is l oc ated in this chapter to maintain the continuity of discussion of all operations with SNM in the RPF. For that reason, the new target handling description is organized based on content required in NUREG-1537 , Chapter 9. The system description also includes content required in NUREG-153 7, Chapter 4. The new target handling subsystem is designed to provide a means to handle and ship unirradiated targets via ES-3100 shipping casks from the RPF. The new target handling subsystem is between the target assembly or LEU storage subsystems and the transporter. The operational flow diagram for the new target handling subsystem is shown in Figure 4-83. 4-180

NWM I ...... ' * * ! . NOmfWEST MEOICAl ISOTOPU [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-83. New Target Handling Flow Diagram New targets will be stored in the [Proprietary Information] (described in Section 4.4.2. l 0.3) at the end of target assembly. The [Proprietary Information] will provide inherent physical protection of the new targets during storage. The [Proprietary Information]. Prior to shipment , targets will be loaded into ES-3100 shipping containers. Detailed information on the internal configuration within the ES-3100 shipping container will be developed for the Operating License Application. The new target handling subsystem function begins with the arrival of the truck transporting the empty ES-3100 shipping casks to the fresh and unirradiated shipping and receiving area. The receiving area door will be opened , and the truck docked to the receiving bay for transfer of the shipping casks into the RPF. Single-loaded shipping casks will be unloaded from the truck onto the ES-3100 shipping cask transfer cart (TF-MC-900) using the ES-3100 shipping cask floor crane (TF-L-900) (Figure 4-85, Section 4.4.2.2.1). Pallet-loaded shipping casks will be unloaded from the truck using the ES-3100 shipping cask pallet jack (TF-PH-900). The unloaded ES-3100 shipping casks will then be documented for material tracking and accountability per the safeguards and security system requirements. The transfer cart carrying a single ES-3100 shipping cask and/or the pallet jack carrying multiple ES-3100 shipping casks will then be transferred to the shipping and receiving airlock door where the empty ES-3100 shipping casks will enter the target fabrication system. After the ES-3100 shipping casks have been loaded with unirradiated targets in the target fabrication system, a shipping pallet loaded with multiple ES-3100 shipping casks will arrive from the shipping and receiving airlock door. The shipping pallet will be transported by the pallet jack from the shipping and receiving airlock to the fresh and unirradiated shipping and receiving area. The ES-3100 shipping casks containing unirradia ted targets will then be documented for material tracking and accountability per the safeguards and security system requirements. The ES-3100 shipping cask pallet will be loaded to the truck via the ES-3100 shipping cask pallet jack (TF-PH-200). The shipping area door will be closed, and the truck and shipping cask will exit the RPF. A more detailed description the new target physical control will be provided in the NWMI RPF Physical Security Plan (Chapter 12.0, Appendix B). 4-181 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description 4.4.2.2 Fresh Uranium Receipt and Dissolution The fresh uranium dissolution subsystem description provides information regarding the process, process equipment, SNM inventory, and the hazardou s chemicals used in the subsystem. The process description (Section 4.4.2.2.1) provides a detailed account of the SNM in process du ring normal operations a nd provides the b asis for eq uipment design. The arrangement and design of the processing equipment, including norm al operating conditions, are des cribed in Sections 4.4.2.2.2 and 4.4.2.2.3. A description of the SNM in terms of physical an d chemica l form, vo lum e in process, and criticality co ntrol features is provided in Section 4.4.2.2.4. The hazardous chemicals that are used or may evo l ve during the proce ss , along wi th the provisions to protect workers and the public from exposure, are described in Section 4.4.2.2.5. 4.4.2.2.1 Process Description Fresh Uranium Receipt Fresh uranium will be received as uranium metal with an enrichment of 19.75 wt% +/-0.20 wt% 235 U. The fresh uranium metal will be received in ES-3100 shipping containers. The ES-310 0 shipping container design is shown in Figure 4-84. [Proprietary Information] Figure 4-84. ES-3100 Shipping Container Fresh uranium receipt handling -The fresh LEU handling s ub sys tem function will b egin with the arrival of the truck transporting the ES-3100 shipping casks containing the fresh LEU material to the fresh and unirradiated shipp ing a nd receiving area. The receiving area door will be o pened , and the truck docked to the receiving ba y , allowing for transfer of the s hippin g casks into the RPF. Single-loaded s hippin g casks will be unloaded from the truck onto the ES-310 0 shipping cask transfer cart (TF-MC-900) using the ES-3100 shipping cask floor crane (TF-L-900) (Fig ure 4-85). Pallet-loaded shipping casks will be unloaded from the truck using the ES-3 100 shipping cas k pallet jack (TF-PH-900). T he unloaded ES-3100 s hippin g casks will be documented for material trackin g and accountability per the safegua rds and security sys tem requirements. The transfer cart carrying a sing le ES-3100 s hipping cask and/or the pallet jack carrying multiple ES-3100 s hippin g casks will then be transferred through the s hippin g and receiving ai rlock (T103) to the target fabrication room (T104). 4-182 NWM I .*.**... * *.*

NOlmfWES1 MEDICAL ISOTOf'f.S [Proprietary Information]

NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Fresh uranium verification -On receipt, a review of the supplier's certificate of conformance, included with the shipment, will verify that the impurities and enrichment meet the specification requirements listed in Table 4-56. The container of uranium will be opened, and the SNM weighed along with other MC&A requirements. The uranium will be repackaged in criticality-safe containers and placed into secured storage in the LEU can rack until needed for dissolution. The LEU can rack is within the LEU storage subsystem , which is described in Section 4.4.2.10. Preparation of fresh uranium for use -Fresh LEU metal may be coated in oil by the supplier for shipment, which would require a uranium washing step. Additional information on fresh LEU metal washing will be developed for the Operating License Application. [Proprietary Information] Figure 4-85. Fresh Low-Enriched Uranium Handling and New Target Handling Equipment Arrangement Fresh Uranium Dissolution Figure 4-86 provides the stream numbers corresponding to the fresh uranium dissolution process description. Fresh uranium metal (Stream Fl03) will be loaded into a basket within the dissolver (TF-D-100) for dissolution along with any rejected LEU target material (Stream Fl 02) or recovered uranium (Stream Fl04). Note that the fresh uranium metal may need to be cleaned prior to loading into the basket. [Proprietary Information]. During initial startup for the facility , or as needed , the dissolver may be operated daily. During steady-state operations, the dissolver will be operated with a frequency of [Proprietary Information]. 4-183 .. ... ;. NWMI ..**.. ..* *.. ........... . '. NOATHWUTMfDICAllSOTOPES [Proprietary Inform atio n] NWMl-2015-021, Rev. 3 Ch a pter 4.0 -RPF Description Figure 4-86. Fresh Uranium Dissolution Process Flow Diagram 4-184 .. ;.:; .. NWMI ..... ........ *. ' *.* NORTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The uranium will be dissolved with 6 M nitric acid. The uranium dissolution reactions are given as: U + 4 HN0 3----+ U0 2 (N0 3)2 + 2 NO+ 2 H 2 0 U0 2 + 4 HN0 3 ----+ U0 2 (N0 3)2 + 2 N02 + 2 HzO Equation 4-6 Equation 4-7 The nitric acid will be added and the dissolver heated to [Proprietary Information]. Since the uranium dissolution reaction is exothermic, the dissolver will be cooled in a pipe-in-pipe heat exchanger (TF-E-120) as the reaction proceeds to maintain the temperature [Proprietary Information]. Although not shown in the reaction equations above , uranium metal dissolution with water can produce hydrogen. A sweep gas of air will continuously dilute any hydrogen gas generated to prevent the off gas (Stream Fl 05B) from exceeding 25 percent of the lower flammability limit. The off gas will be vented to the vessel ventilation system. A pump (TF-P-1 10) will be used to circulate the liquid for mixing. The uranium will be dissolved to produce a final solution around [Proprietary Information] and washed to ensure complete dissolution. Excess nitric acid will be acceptable in the product, as the product is fed to the nitrate extraction subsystem. Following dissolution , the uranyl nitrate product will be cooled before transfer to the uranyl nitrate blending subsystem. The use of a reflux condenser to limit NO x emissions , along with an excessi v e loss of water , will be considered for the Operating License Application. 4.4.2.2.2 Process Equipment Arrangement Fresh Uranium Receipt The equipment arrangement associated with the fresh uranium receipt activities is described in Section 4.4.2.2.1. Fresh Urani um Dissolution The fresh uranium dissolution process equipment will be mounted on a single skid within room T104C , the wet side of the target fabrication room. Figure 4-87 shows the equipment arrangement , and Fi g ure 4-88 shows the location of the process equipment. [Proprietary Information] Figure 4-87. Fresh Urani um Dissolution Equipment Arrangement 4-185 .. .. NWMI ..... .......... *. *

NOllTHWEST MEDtCAl lSOTOPU NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description

[Propri etary Information] Figure 4-88. Dissolution Equipment La yo ut 4.4.2.2.3 Process Eq uipm ent Design Fresh Uranium Receipt Fresh uranium receipt activ itie s will involve handling s hippin g casks and repackaging fresh LEU metal into critica lity-sa fe containers. The design of the shippi n g containers is described in Section 4.4.2.2.1 , and the design of the criticality -safe containers will be de veloped for the Operating License Application. The auxiliary equipment that will be used to move sea led containers includes: * *

TF-L-900 , ES-3100 shipping cask floor crane TF-MC-900 , ES-3100 s hipping cask transfer cart TF-PH-900 , ES-3100 shipping cask pallet jack Fresh Uranium Dissolution This sectio n identifies the processing apparatus and auxi li ary equip ment supporting the fresh uranium dissolution s ub system. This equipment is li sted in Table 4-58 with de sign data developed during prelimin ary design. Because dimensions ha ve not yet been defined, two fie ld s are provided to identify the basis for equipment dim ensions; capacity and whether the equipment is designed to be criticality-safe b y geometry.

Additional detailed information (e.g., dimensions) wi ll b e de ve loped for the Operating License Application. Table 4-58. Fresh Uranium Dissolution Process Equipment Criticality-safe by geometry Operating conditions

- H**1*Mf iii Equipment name Uranium dis so lv er TF-D-100 Uranium dissolution filter TF-F-100 Uranium di sso lution pump T F-P-110 Uranium dissolution cooler TF-E-120 [Prop ri etary In fo rm atio n] Ye s [Proprietary Yes Informati o n] [Pr oprietary In formation]

Ye s [Proprietary Yes Inform ation] 304L SS [Propri e t ary In format i on] TBD* [Proprietary TBD* 304L SS In formation] [Pr op r ietary In format i o n] [Proprietary Information]

Information will b e provided in the Operatin g Li ce n se Application s ubmi ss ion. MO C N I A material s of con s tructi o n. = not a ppli ca ble. SS TBD 4-186 stain l ess s t ee l. = to be det e rmin e d. Pressure [Pr op ri e t ary In fo rm a ti on] [Proprietary Informati o n J [Proprietary In format i on] [Proprietary Information]

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NORTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Process Monitoring and Control Equipment Process monitoring and control equipment was not defined during preliminary design. Preliminary process sequences are provided in this section to identify the control strategy for normal operations, which sets requirements for the process monitoring and control equipment and the associated instrumentation. Other information on instrumentation and controls is provided in Chapter 7.0. Additional detailed information on the process monitoring and control equipment will be de ve loped for the Operating License Application.

Fresh uranium dissolution will be a batch process. T here are three normal modes of operation: loading , dissolution , product cooling and transfer.

*
During loading operations , the operator will weigh [Proprietary Information]

and load the LEU into the dissolver basket (in the dissolver , TF-D-100). The operator will close the dissolver , open the inlet air damper valve (TF-V-1002), and initiate the nitric acid addition. The nitric acid addition will be an automated process , adding a predetermined volume of [Proprietary Information]. The operator will initiate the dissolution mode , which will start the dissolver heatin g and recirculation pump (TF-P-110). The dissolution will proceed at [Proprietary Information]. Density instrumentation w ill indicate that the uranium has dissolved. Once dissolution is complete, the operator will initiate the product cooling mode. The recirculation pump will continue to recirculate solution, and the heater will be deenergized. Chilled water will cool the product to ambient temperature by the uranium dissolution heat exchanger (TF-E-120). When the uranyl nitrate solution is cooled, the chilled water loop will be closed. The operator will open TF-V-1105 and close TF-V-1104 to transfer the uranyl nitrate solution to the uranyl nitrate storage tank (TF-TK-200). 4.4.2.2.4 Special Nuclear Material Description Special Nuclear Material Inventory Uranium within the fresh uranium receipt activities will be transient and bounded by the uranium inventory in the LEU storage SNM description (Section 4.4.2.10.4). Likewise , the criticality control features are discussed in the LEU storage SNM description. The SNM inventory in the fresh uranium dissolution subsystem will consist of dissolving fresh LEU metal to uranyl nitrate. Table 4-59 lists the SNM inventory , accounting for both forms even though the maximum mass of both forms will not be present at the same time. Table 4-59. Fresh Uranium Dissolution Design Basis Special Nuclear Material Inventory Location Form Uranium dissolver (TF-D-100) [P r o prietary In formation] Uranium dissolver (TF-D-100) [Proprietary Information] Concentratio na 1@!11,,!j [Proprietary In formation] [Pr op ri etary In format i on] [Proprietary Information] [Proprietary Information] SNM mass a [Pr op ri etary Information] [Proprietary Information] a SNM concentration and mas s r eprese nt total amount of LEU (combined m u and 238 U at wt% m u). b Total uranium in the dis so lver will not exceed this va lue. Th e form w ill change from uranium metal to uran y l nitrate durin g dissolution, so the SNM mas s in the dissolver will r ema in constant. m u 238u L EU uranium-235. uranium-2 38. low-enri c hed uranium. N I A SNM u 4-187 not appli cab l e. special nucl ear material. uranium. NWM I ...... ' *

NOKllfWUT MEDICAi. ISOTOl'ES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Criticality Control Features Criticality control features are required in this subsystem , as defined in NWMI-2015-CSE-005 , NWMI Pr elimi nary Criticality Safety Evaluation:

Targ et Fabrication Uranium Solution Proc esses. These features, including passive design features, active engineered features, and administrative contro l s, allow for adherence to the double-contingency principle. This section applies the criticality control features that are described in Chapter 6.0, Section 6.3. The technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0. The criticality accident sequences are identified in Chapter 13 .0, Section 13 .2, where accident prevention measures and features are identified. The criticality control features for this subsystem include the passive design features, active engineered features , and administrative controls with designators of PDF, AEF, and AC, respectively , listed below. Chapter 6.0 provides detailed descriptions of the critica li ty control features. The passive design features affect the design of process equipment, ventilation piping , and the room floor , and will include the following.

* * *
The geometry of the process equipment is inherently criticality-safe (CSE-05-PDF3) and maintains a subcritical geometry during and after a facility DBE (CSE-05-PD F4). To prevent inadvertent interaction with mobile containers or carts, sidewalls surround the process skids (CSE-05-PDF5).

Liquid systems vessels and piping are designed for chemical operating conditions such that corrosion and leaking of tank walls and seals are prevented or minimized (CSE-05-PDF6). Workstations where fresh LEU metal is handled do not have spill-prevention lips higher than 2.5 cm (I in.) (CSE-05-PDF7). The ventilation system connected to process equipment containing fiss i le material is inherently criticality-safe by geometry, and overflow drains prevent liquid accumulation beyond the criticality-safe geometry (CSE-05-PDF8). For the case of a liquid leak, the floor is critica li ty-safe (CSE-05-PDFl), and a barrier or seal prevents penetration of fissile material into the floor (CSE-05-PDF2). The active design features will include: *

The geometry of the closed-loop chilled water system is inherently criticality-safe (CSE-05-AEFl), which prevents criticality in case of an internal failure of the heat exchanger.

Monitoring of the chilled water loop provides indication of the failure . The administrative contro l s will include: * *

Minimum spacing between movable containers and process equipment (CSE-05-ACl)

Carrying limit of one fissile-bearing container per operator (CSE-05-AC2) [Proprietary Information] (CSE-05-A C3) 4-188 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Some or all of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the fresh uranium dissolution activities.

* *
Fresh LEU metal for dissolution is handled in approved containers and within the mass and batch handling limits (IROFS CS-02). While moving the LEU metal, minimum spacing between the fresh LEU container and other fissile material is managed administratively (IROFS CS-03). These measures:

(1) limit the operator to handle one container at a time , (2) require use of approved workstations with interaction control spacing from other fissile material , and (3) provide interaction guards at normally accessible fissile solution process equipment. The dissolver , heat exchanger, and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality. This approach applies limitations on the configuration, including the outside diameter of the process equipment and piping (IROFS CS-06), and fixed spacing between the process equipment with fissile solution (IROFS CS-07). The supply of nitric acid is a potential source for backflow of fissile solution to the large geometry of the chemical supply system. To prevent backflow, nitric acid is provided through an anti-siphon air break that separates the supply from the process equipment (IROFS CS-1 8). The anti-siphon air break is a pipe discharging to a funnel with a vertical offset so that siphoning is impossible. The dissolver receives nitric acid from the chemical supply system. Anti-siphon breaks (IROFS CS-1 8) on the nitric acid supply prevent backflow of fissile material to the chemical supply system. In addition to the features that apply the double-contingency principle, several features will provide defense-in-depth in criticality control. These features include: * * *

Administrative batch limits are set based on worst-case moderation , even though uranium is dry during normal conditions. Administrative interaction controls are based on man y evenly spaced units contributing to the return of neutrons.

Administrative failures during handling between workstations generally involve onl y two containers. Critica li ty calcu l ations analyzed concentrations , mass limits, and volumes that are not anticipated under normal conditions, so the controls can sustain multip l e up sets. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed , or stored , as described in Chapter 6.0. The critica li ty control features provided throughout the irradiated target receipt process will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes. 4-189

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NDllTHWIST ME DICAl ISOTOPES 4.4.2.2.5 Chemical Hazards Chemical Inventory NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The chemica l reagents for the fresh uranium dissolution are li sted in Table 4-60. In addition to the chemical reagents, offgases will include NO , N0 2 , and nitric acid fumes. Table 4-60. Fresh Uranium Dissolution Chemical Inventory Chemical Quantity Physical form Nitric acid (HN0 3) [Proprietary Inform a tion] [P roprietary Information]

Note: This table does not include the SNM identified in Tab l e 4-59. SNM = special nuclear material. Chemical Protection Provisions Concentration (if applicable) (Propr i etary Information The primary chemical hazard s in the fresh uranium dissolution s ub system wi ll be a chemical spray of nitric acid or uran yl nitrate, and personnel exposure to offgases. A spray shield installed on the skid will protect the operator from chemical bums in the event of a spray leak from the d issolver or associa ted piping. The headspace above the dissolver will be purged by a sweep gas and maintained at a negative pres sure to prevent personnel exposure to offgases. 4.4.2.3 Nitrate Extraction Subsystem The nitrate extraction subsystem description provides information regardin g the process , process equipment, SNM inventory, and the ha zar dous chemicals used in the subsystem. The process description (Section 4.4.2.3.1) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and d esign of the processing e q uipment , includin g normal operating conditions, are described in Sections 4.4.2.3.2 and 4.4.2.3.3. A description of the SNM in terms of phy sica l and chemical form , volume in p ro cess , and crit ical ity control features is provided in Section 4.4.2.3.4. A description of ha zar dou s chemicals that are u sed or may evo lve durin g the process , along with the provisions to protect workers and the public from exposure, are presented in Section 4.4.2.3.5. 4.4.2.3.1 Process Description Figure 4-89 provides the stream numbers corresponding t o the nitrate extraction proce ss descript i on. 4-190 .; ... ; .. NWMI ...... ..* .. ........ *.* ' NORTHWEST MEDICAUSOTOPU [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-89. Nitrate Extraction Process Flow Diagram 4-191 .... ... NWMI ...*.. ..* .... .*.* .. *.*. , * "NORTHMST MIDICAUSOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Fresh uranyl nitrate will be received from the [Proprietary Information]. The specifications of the recycled uranium are summarized in Table 4-61. Table 4-61. Recycled Uranium Specification (2 pages) Chemical or physical property* Specification Comment Form [Proprietary Information] [Proprietary Information] Total uranium, [Proprietary Information] [Proprietary Information] nitric acid Uranium Isotopes 232u [Proprietary Information] [Proprietary Information] m u [Proprietary Information] [Proprietary Information] 234U [Proprietary Information] [Proprietary Information] 23s u [Proprietary Information] [Proprietary Information] 236u [Proprietary Information] [Proprietary Information] Other Actinides 238pu [Proprietary Information] [Proprietary Information] 239 pu [Proprietary Information] [Proprietary Information] 240pu [Proprietary Information] [Proprietary Information] 2 4 2 pu [Proprietary Information] [Proprietary Information] 241Am [Proprietary Information] [Proprietary Information] 231 Np [Proprietary Information] [Proprietary Information] 231pa [Proprietary Information] [Proprietary Information] 233 pa [Proprietary Information] [Proprietary Information] 230Th [Proprietary Information] [Proprietary Information] Fission Products 9szr [Proprietary Information] [Proprietary Information] 9 5 Nb [Proprietary Information] [Proprietary Information] 103Ru [Proprietary Information] [Proprietary Information] All others total [Proprietary Information] [Proprietary Information] O ther Imp urities Iron [Proprietary Information] [Proprietary Information] Chromium [Proprietary Information] [Proprietary Information] 4-192 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-61. Recycled Uranium Specification (2 pages) Chemical or physical property* Specification Comment Nickel Sodium [Proprietar y Information] [Proprietary Information] [Proprietar y Inform ation] [Proprietary Information] Source: NWMI-2013-049 , Process S y st e m Functional Sp ec ifi c ation , R ev. C , Northwest Medical I soto p es, LLC , Corva lli s , Oregon , 20 1 5.

No constraint is imposed o n the recycled uranium for c h e mi cal o r physical properti es that are not li sted in this table. b (a, n) source limit= These i sotopes r e pr ese nt p otentia l so ur ces of worke r ex po s ur e due to int eraction of a lpha particl es with light elements (e.g., oxyge n) that generate n e utr ons and co uld influ ence s hieldin g requirements for target fa brication a nd h a ndlin g sys tem s. The specifica tion is based on limitin g the n e utron ge n eratio n rat e inc rease of an individu a l isotope to (Propriet ary Inform ation]. Es timat e simp lification s are described in NWMJ-2013-049.

c The facility will process LEU; p rocessi ng hi g her uranium e nri c hm ents is not includ ed in t h e proc ess sco p e. A ma x imum product specification for 235 U i s ass umed to st ill b e d oc um e nt e d as part of the c riticality safety co ntrol s. A minimum 235 U co nt ent is ex p ected t o be identified in the future ba sed on target eco n o m ics and i s not in c lud ed in the pr econceptua l de s i gn scope. d y source limit= T h ese i so top es represent pot e nti al ga mm a em itt er sources of worker ex p os ure a nd co uld influen ce s hi e ldin g requir e m ents fo r target fab ri cation and handlin g syste m s. T h e specifica tion is based o n limi ting the unshielded d ose (Proprietary Inform ation]. Est im ate simplifica tion s are d esc rib ed in NWMI-20 1 3-049. L EU ppmpU TBD low-enriched uranium. parts per million part s uranium b y m ass. to b e d eterm in e d. U uraniu m. (P rop ri etary Informati on] The urany l nitrate so lution will be stored in a tank (TF-TK-200) and blended and diluted with demineralized water to create [Proprietary Information] uran y l nitrate solution with consistent 235 U enrichment and impurities. The nitrate extraction subsystem w ill use a so lv ent extraction process to remove nitrate from the solution to convert uran yl nitrate with excess nitric acid to ADUN with a ratio of [Proprietary Inform a tion]. The nitrate extraction process w ill last less than 4 hr/bat ch of uran yl nitrate rece ive d. The nit rate extraction reactions are given as: Equation 4-8 E quation 4-9 The solvent ex tra ction process will be accompli she d with a [Proprietary In fo rmation]. R e d oil formation i s not a concern in this process be ca use tributyl phosphate (TBP) is not pr esent. The temp era ture for th e solvent extraction process will be maintained at [Proprietary Information] by inline heater s for all feeds (TF-E-220, TF-E-223, TF-E-226, and TF-E-255). To avoid uranium losse s due to unde sirable reactions , the uranium concent ratio n will be controlled [Propriet ary In forma tion]. I. The nitrate extraction contactor (TF-Z-23 0) will mix the uranyl nitrate solution with [Proprietary Information] in so l vent to e x tract nitrate s (ORNL-5300, R es in-Ba sed Preparation of HGTR Fuels: Op eratio n of an Engineering-Scale Uranium Loading System). The inlet flow of uranyl nitrate will be [Proprietary Information]. An inline pH meter and tran s mitter on the uranyl nitrate stream will control the speed of the nitrate extraction s olvent pump (TF-P-250). The aqueous product from the nitrate extraction contactor (TF-Z-230) will flow to the phase separator (TF-SP-270). The solvent w ill flow to the uranium reco very contactor s (TF-Z-23 I A/B). 4-193 .. NWM I ...... .......... * *.*

NORTHWEST MEDtGAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

2. The two uranium recovery contactors, configured in series (TF-Z-231 A/B), will wash the solvent stream with demineralized water to minimize uranium losses. The demineralized water will be fed at a combined ratio of [Proprietary Information].

The aqueous products from the uranium recovery contactors (TF-Z-231A/B) will flow to the phase separator (TF-SP-270), and the solvent will flow to the organic regeneration contactor (TF-Z-232). 3. The organic regeneration contactor (TF-Z-232) will regenerate the amine using [Proprietary Information]. An inline pH meter and transmitter on the solvent stream will control the flow of the sodium hydroxide solution. The aqueous effluent (sodium nitrate solution) will drain to a surge tank that pumps the solution to the aqueous waste holding subsystem, and the solvent will flow to the wash contactor (TF-Z-233).

4. The wash contactor (TF-Z-233) will wash the solvent with demineralized water to scrub entrained aqueous waste from the solvent. The demineralized water will be fed at a ratio of [Proprietary Information].

The aqueous effluent (sodium nitrate solution) will drain to a surge tank that pumps the s olution to the aqueous waste holding subsystem , and the solvent will d rain to the nitrate extraction solvent feed tank (TF-TK-240).

5. The aqueous product from the nitrate extraction contactor (TF-Z-230) and the uranium recovery contactors (TF-Z-23 lA/B) may have entrained solvents or excess solvent due to process upsets. The phase separator (TF-SP-270) will separate solvent from the aqueous product. Solvent recovered from the phase separator will flow to the nitrate extraction solvent feed tank (TF-TK-240). The aqueous product will drain to an ADUN surge tank (TF-TK-280) and will be pumped to the recycled uranyl nitrate concentration subsystem.

The nitrate extraction solvent will be purged at a rate of [Proprietary Information], and fresh solvent will be added at the same frequency. The purged solvent will be discharged to [Proprietary Information] containers and anal y zed for uranium concentration in the analytical laboratory b efore disposal. 4.4.2.3.2 Process Equipment Arrangement The nitrate extraction process equipment will be mounted on one skid and one workstation within room Tl04C, the wet side of the target fabrication room. Figure 4-90 shows the location of the p rocess equipment. [Proprietary Information] Figure 4-90. Nitrate Extraction Equipment Layout 4-194 ..... ; NWMI ::****:* . ........ * *.*

NOAllfW£S1 MEDfCAL ISOlOPE S Figure 4-91 shows the arrangement of the uran yl nitrate storage tank, which will receive the recycled uranyl nitrate from the U recovery and recycle system and feed the nitrate extraction process. Figure 4-92 shows the arrangement of the n itrate extraction process. The solvent extraction will occur in bench-mounted contactors.

Uranyl nitrate will enter at the nitrate extraction contactor (TF-Z-230), and the ADUN product will flow to the phase NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-91. Uranyl Nitrate Storage Tank Arrangement separator (TF-SP-270). The product from the phase separator will drain to the ADUN surge tank (TF-TK-240) and will be pumped to the ADUN concentration subsystem. Aqueous waste from the contactors will drain to the aqueous waste surge tank (TF-TK-260) and will be pumped to the target fabrication waste subsystem. The solvent will be fed to the nitrate extraction contactor and to the subsequent contactors (TF-Z-23 lA through TF-Z-233) before draining back to the nitrate extraction solvent feed tank (TF-TK-240) for recycle. 4-195

.**.* .... .; ... ;. NWMI ........ *. * *. * ! . . NOtmlWEST MEOfCAl ISOTOPU Figure 4-92. [[Proprietary Information]

NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Nitrate Extraction Equipment Arrangement 4.4.2.3.3 Process Equipment Design This section identifies the processing apparatus and auxiliary equipment supporting the nitrate extraction subsystem. This equipment is listed in Table 4-62 with design data developed during preliminary design. Because dimensions have not yet been defined, two fields are provided to ident i fy the basis for equipment dimensions

capacity and whether the equipment is designed to be criticality-s a fe by geometry.

Additional detailed information (e.g., dimensions) will be developed for the Operating License Application. 4-196 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-62. Nitrate Extraction Process Equipment I Equipment name ---i& .. 1.;;;;1111;;14111; Operating range Uranyl nitrate storage tank TF-TK-200 [Pr o pr i e tar y Inform a tion] Yes 304L SS [Proprietary [Propriet a ry Inform a tion] In form a ti o n] Uranyl nitrate storage pump TF-P-210 [Propr i etary Yes TBD [Proprietary [Proprietary Information] In formation] Information] Uranyl nitrate feed pump TF-P-215 [Pr o pri e t a r y In for m a ti o n] Yes TBD [P ro p rie t ary [P ro pri e t ary In fo rm a ti o n] Inform at i o n] Uranyl nitrate heater TF-E-220 [Proprietary Information] N I A TBD [Proprietary [Proprietary Information] Information] Water heater TF-E-223 [Propri e tar y N I A TBD [Propri e tary [P ropri e t a r y In fo rm a ti o n] I n fo rm a ti o n] In form a ti o n] Caustic heater TF-E-226 [Proprietary In formation] N I A TBD [Proprietary [Proprietary In formation] In formation] Nitrate extraction contactor TF-Z-230 [Propr ie tar y Yes 304L SS (Pr o pri e t ary [Pro p ri e t ary In fo rm a ti o n] I nfo r m a ti o n] In fo rm a ti o n] Uranium recovery contacto r TF-Z-231A [Proprietary Information] Yes 304L SS [Proprietary [Proprietary In fo rm ation] Informati on] Uranium recovery contacto r TF-Z-2318 [Propri e t a r y I n fo rm a ti o n] Yes 304L SS [Propri e t ary [Propri e t ary I n fo rm a ti o n] I n fo r m a ti o n] Organic regeneration contactor TF-Z-232 [Proprietary Yes 304L SS [Proprietary [Proprietary Informat i on] In formation] information] Wash co ntactor TF-Z-233 [Propri e t a r y Yes 304L SS [Propri e t a ry [Propri e t ary In fo rmation] Inform a ti o n] Inform a ti o n] Nitrate extraction solvent feed TF-TK-240 [Proprietary Yes 304L SS [Proprietary [Proprietary tank Information] In formation] Information] Nitrate extraction solvent pump TF-P-250 [Pr opr i e t a r y Yes TBD (Pr o pri e t ary [Pro p ri e t ary In fo rm at i o n] In form a ti o n] In fo rm at i on] Solvent heater TF-E-255 [Proprietary In format i o n] N I A TBD [Proprietary [Proprietary Information] Information] Aqueous waste s ur ge tank TF-TK-260 [P ro pr i e t a r y Yes 304L SS [Propri e t ary [Propri e t ary Information ] In form a ti o n] I nform a ti o n] Aqueous waste surge pump TF-P-265 [Proprietary Yes TBD (Proprietary [Propriet a ry Information] In formation] In formation] Phase separator TF-SP-270 [P ro pri e t ary I nfo rmati o n] Yes TBD [P ro pri e t ary [Pr o pri e t ary In fo rm a t io n] In form atio n] ADUN surge tank TF-TK-280 [Proprietary Yes 304L SS [Proprietary [Proprietary Inform ation] Inform ation] Inform ation] ADUN surge tank pump TF-P-285 [P ro pri e t a r y Yes TBD [Propri e t ary [Propri e t ary In fo rm a ti o n] In form a ti o n] In fo rm a ti o n] ADUN ac id-d eficient uranyl nitrate. SS s tainle s s s teel. N I A n ot a pplic a ble. TBD to be determined. Process Monitoring and Control Eq uipm ent Process monitoring and control equipment was not defined during pre l iminary design. Preliminary process sequences are provided in this section to identify the control strategy for normal operat i ons, which sets requirements for the process monitorin g and control equipment and the associated instrumentation. Other information on instrumentation and controls is provided in C hapt er 7.0. Additional detailed information on the process monitoring and control equipment will be developed for the Operating License App li cation. 4-19 7 NWM I ...... * *

0 NOmfWEST MfDM:Al tSOTOl'll NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Nitrate extraction will be a semi-batch process. There are four normal modes of operation: sta ndb y, extraction preparation , nitrate extraction, and end of extraction.
*
During standby mode , the uranyl nitrate storage tank (TF-TK-200) ma y receive recycled uranyl nitrate , fresh uranyl nitrate , and/or water for dilution. Pumps , heaters , and contactors wi ll a ll be deenergized. The surge tank pumps will remain energized. During extraction preparation mode , the uranyl nitrate storage pump (TF-P-210) will mix uranyl nitrate wit hin TF-TK-200 by recirculation.

The contactors (TF-Z-230 -TF-Z-233), solvent pump (TF-P-250), and so l vent heater (TF-E-255) wi ll be energ i zed to preheat the contactors. To initiat e nitrate extraction , a ll feed strea m s (uranyl nitrate , demineralized water, and 1.5 M ca u stic) will be o pen ed, and their respective h eaters energ i zed. The first three contactors (TF-Z-230, TF-Z-23 l A/B) will recover ADUN as their aqueo u s product. The product wi ll flow through the phase separator (TF-SP-270) to the ADUN surge tank (TF-TK-280), where produ ct wi ll be pumped to th e ADUN evaporator fee d tank (TF-TK-300). The end of extraction operations has not b een d efined. 4.4.2.3.4 Special Nuclear Material Description Special Nuclear Material Inventory The SNM inventory in the nitrate extraction subsystem will consist of the recycled ur anyl nitrate. Table 4-63 li sts the SNM inv entory, w hich includ es the recycled uranyl nitrate storage tank. Table 4-63. Nitrate Extraction Special Nuclear Material Inventory Location Uranyl nitrate storage tank (TF-TK-200) Form (Proprietary In formation] Concentration* [Proprie t ary In for m a t ion] Q!il,,!W SNM mass* [Propri etary (Propriet ary ln formation] lnform a ti on]

SNM co nc e ntrati on and ma ss r eprese nt th e total amount of LEU (combined m u and 238 U a t :s; 1 9. 95 wt% mu). m u rn u LEU uranium-235 ur anium-238 l ow-enriched uranium. Criticality Control Features SNM u s p ec i a l nu c l ear mat er i a l. = ur a nium. Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-00 5. These features, including passive de sign features, active engineered features, and admin i strative contro l s, allow for adherence to the double-contingency principle. T hi s section applies the cri tic a lity control features that are described in Chapter 6.0, Section 6.3. The technical specificat ion s required for criticality control will be developed for the Operating License A ppli cation a nd d escribed in C h apter 14.0. The critica li ty accident seq uen ces are de scri b ed and analyzed in C h apter 13 .0, Sect ion 1 3 .2, w here accide nt prevention measures an d features are identified. The critica lity contro l features for this subsystem include the passive design fe a tures , active engineered features, and adm in is trative controls with design ato r s of PDF , AEF, a nd AC, respectively, listed below. Chapter 6.0 provides detailed de script ion s of the cri ticality control features.

4-198 ..... ;. NWMI ::.**.*.* .*.* .. *.*.* ' *.* ' NORTHWEST MEDICAL ISOTOM S NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The passive design features affect the design of process equipment , ventilation piping , and the room floor , and will include the following. * * *

The geometry of the process equipment is inherently criticality-safe (CSE-05-PDF3) and maintains subcritical geometry during and after a facility DBE (CSE-05-PDF4).

To prevent inadvertent interaction with mobile containers or carts , sidewalls surround the process skids (CSE-05-PDF5). Liquid systems vessels and piping are designed for chemical operating conditions such that corrosion and leaking of tank walls and seals are prevented or minimized (CSE-05-PDF6). The ventilation system connected to storage tanks , or other equipment with fissile material, is inherently criticality-safe by geometry, and overflow drains prevent liquid accumulation beyond the criticality-safe geometry (CSE-05-PDF8). For the case of a liquid leak , the floor is criticality-safe (CSE-05-PDFl ), and a barrier or seal prevents penetration of fissile material into the floor (CSE-05-PDF2). The administrative controls will include:

Minimum spacing between movable containers and process equipment (CSE-05-ACl)

Chapter 13.0, Section 13.2 provide s a description of the IROFS. The following IROFS will be applicable to the nitrate extraction activities. * *

The tanks, contactors , heat exchangers and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality. This approach applies limitations on the configuration , including:(!)

outside diameter of process equipment and piping (IROFS CS-06) and (2) fixed spacing between process equipment with fissile solution (IROFS CS-07). The supplies of sodium hydroxide solution and demineralized water are potential sources for backflow of fissile solution to the large geometry of the chemical supply system or the demineralized water system. To prevent backflow, reagents are provided through an anti-siphon air break that separates the supply from the process equipment (IROFS CS-18). The anti-siphon air break is a pipe discharging to a funnel with a vertical offset so that s iphoning is impossible. Instrument air supplied for level measurement is a potential source for backflow of fissile solution to the large geometry of the instrument air system. To prevent backflow, the instrument air supply piping has a high point above the maximum liquid level before connecting to the vented tank (IROFS CS-20). If instrument air supply pressure is lost, the highest liquid level is below the supply piping high point, so backflow is impossible. In addition to the features that apply the double-contingency principle, several features provide in-depth in criticality control. These features will include the following.

Criticality calculations analyzed concentrations , mass limits , and volumes that are not anticipated under normal conditions, so the controls can sustain multiple upsets. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed, or stored , as described in Chapter 6.0. The criticality control features provided throughout the irradiated target receipt process will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes.

4-199 .

- - - - . ......... * . . ' ! ' NORTHWEST M£DKAL ISOTDP£S 4.4.2.3.5 Chemical Hazards Chemical Inventory NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The nitrate extraction chemical inventory is summarized in Table 4-64. Table 4-64. Nitrate Extraction Chemical Inventory Chemical Quantity Physical form Concentration (if applicable)

[Proprietary In formation) [Proprietary Information] [Proprietary Inform ation] (Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] (Proprietary Information] Note: This table does not includ e the SNM identified in Table 4-63. SNM = special nuclear material. Chemical Protection Provisions The primary chemical hazards in the nitrate extraction subsystem will be a chemical spray of uranyl nitrate or solvent, and personnel exposure to offgases. A spray shield installed on the skids will protect the operator from chemical burns in the event of a s pray leak from the proc ess e quipment or associated piping. The headspace above the process equipment will be maintained at a negative pressure and vented to the vessel ventilation system to prevent personnel exposure to offgases. 4.4.2.4 Acid-Deficient Uranyl Nitrate Concentration Subsystem The ADUN concentration subsystem description provides information regarding the process, process equipment, SNM inventory, and the hazardous c hemicals us ed in the subsystem. The process description (Section 4.4.2.4.1) provides a detailed account of the SNM in process durin g normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions, are described in Sections 0 and 4.4.2.4.3. A description of the SNM in terms of physical and chemical form, vo lume in proce ss, and criticality control features is provided in Section 4.4.2.4.4. A description of hazardous chemicals that are u s ed or may evolve durin g the process, along with the provisions t o protect workers and the public from exposure, are presented in Section 4.4.2.4.5. 4.4.2.4.1 Process Description Figure 4-93 [Proprietary Information] Figure 4-93 provides the stream numbers corresponding to the ADUN concentration process description. ADUN solution from the nitrate extraction subsystem will be fed to the ADUN concentration subsystem at less than [Proprietary Information]. The dilute ADUN solution will be stored in the ADUN evaporator feed tank (TF-TK-300) and then fed into the steam-heated evaporator (TF-V-340 and TF-E-330), where it will be [Proprietary Information]. 4-200 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The evaporator level will be monitored by a bubbler that compensates for density. When the level is too low , additional ADUN will be fed from the ADUN evaporator feed tank (TF-TK-300). The concentrated ADUN will be cooled to [Proprietary Information] and stored in the ADUN storage tanks (TF-TK-400, TF-TK-405, TF-TK-410, and TF-TK-415). The overheads from the evaporator will be condensed in the ADUN evaporator condenser (TF-E-350) and drained to the aqueous waste pencil tanks (TF-TK-700, 705). Non-condensable vapors from the condenser will vent to the vessel ven tilation system. [Proprietary Information] Figure 4-93. Acid-Deficient Uranyl Nitrate Concentration Process Flow Diagram 4-201 .... ;. NWMI ...... .. ... .*.******* ' *.*

NOllTNWEST MEDtCAUSOTOPH 4.4.2.4.2 Process Equipment Arrangement NWMl-2015-021 , Rev. 3 Ch a pter 4.0 -RPF Description The ADUN concentration process equipment will be mounted on two skids within room Tl04C, the wet side of the target fabrication room. Figure 4-94 shows the location of the process equipment.

[Proprietary Information] Figure 4-94. Acid-Deficient Uranyl Nitrate Concentration Equipment Layout 4-202

NWM I ...**... * * *

NOallfWEST MfDtCAt. ISOTOPH NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-95 shows the arrangement of the ADUN concentration feed tank where ADUN will be received from the nitrate extraction subsystem.

Figure 4-96 shows the arrangement of the concentration equipment, including the evaporator column (TF-V-340), the reboiler (TF-E-330), and the condenser (TF-E-350). Concentrated ADUN from the evaporator will be cooled to near-ambient temperature by the ADUN product heat exchanger (TF-E-360). [Proprietary Information] Figure 4-95. Acid-Deficient Uranyl Nitrate Concentration Feed Equipment Arrangement 4.4.2.4.3 Process Equipment Design Figure 4-96. Acid-Deficient Uranyl Nitrate Concentration Equipment Arrangement This section identifies the processing apparatus and auxiliary equipment supporting the ADUN concentration subsystem. This equipment is listed in Table 4-65 with design data developed during preliminary design. Because dimensions have not yet been defined, two fields are provided to identify the basis for equipment dimensions: capacity and whether the equipment is designed to be criticality-safe by geometry. Additional detailed information (e.g., dimensions) will be developed for the Operating License Application. 4-203 ..... ;. NWMI ..*... ..* .... ........ *.* , ' *, *

NORTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 3 Ch a pter 4.0 -RPF Descr i ption Table 4-65. Acid Deficient Uranyl Nitrate Concentration Process Equipment Operating range Equipment name Temperature

.. AD UN e vaporator f ee d tank TF-TK-300 (P ro p r i etary In fo rm a ti o n] Ye s 3 04L S S (Propri etary In fo rm a ti o n] (P ro pri etary Inform a ti o n] ADUN evaporator feed pump TF-P-310 [Proprietary Information] Yes TBD [Proprietary Information] [Proprietary Information] A DUN evaporator pump TF-P-320 [P rop ri etary ln fo rm a ti o n] Y es TBD [P ro pri etary lnform a t io n] (P ro pri e t ary ln fo rm at i on] ADUN evaporator reboiler TF-E-330 [Proprietary In fo rmation] Yes 304L SS [Proprietary Informat i on] [Proprie tary Informat i on] ADUN evaporator TF-V-340 [Pro p r i e ta ry In fo rm a ti o n] Y es 304L SS [Propri etary In fo rmati on] (Propri e t ary lnformati o n] ADUN evaporator condenser TF-E-350 [Proprietary Information ] Yes 304L SS [Propri e tary Information] [Proprietary Information] AD UN product heat ex chan g er T F-E-360 (P rop ri e t ary In fo rm a ti o n] Y es 304L SS (Propri etary Inform a ti o n] [Propri e t ary Inform at i o n] AD UN acid-d e fi c i e nt uran y l nitr a t e. SS s t ai nl ess s teel. N I A = n o t a pplicabl e. TBD to b e d e t e r min e d. Process Monitoring and Control Equipment Process monitoring and control equipment w a s not defined during prelimin a ry de s ign. Preliminary process sequences are provided in this section to identify the control strateg y for normal operations , which sets requirements for the process monitoring and control equipment a nd the associ a t ed instrumentation. Other inform a tion on instrumentation and c o ntrols is provided in Chapt er 7.0. Additiona l detailed information of the proces s monitoring and control equipment wi ll be developed for the Operating Licens e Application. ADUN concentration is a semi-batch process. There will be t hree normal modes of operation: s t andb y, concentration , and end of concentration. * *

During standby mode , the ADUN evaporator feed tank (TF-TK-300) may receiv e dilute ADUN from the nitrate extraction subsystem.

Steam and chilled water s uppl y valves will b e closed , and pumps de-energi z ed. T F-P-310 may be energized to mi x contents. The evaporator will concentrate the ADUN [Proprietary Information]. Level mea s urement will control the dilute ADUN inlet valve , a nd density measurement will control the product dischar g e va l ve. The product will be coo l ed to ambient temperatures in TF-E-36 0. The operator will initiate concentration mode by: Feedin g dilute ADUN to the ADUN evaporator (TF-V-340) Beginning forced recir c ulation by energizing TF-P-320 Opening s team and chilled water supply valves to TF-E-330 , TF-E-350 , and TF-E-360 The e n d of conce n tration mode will begin when feed from TF-TK-30 0 is exhaus t ed and the ADUN within the evaporator has reached a [Proprietary Inform a tion]. The steam s upply val v e will be closed , and the concentrated ADUN wi ll be pumped by TF-P-320 to TF-T K-400. TF-P-320 will be deenergi z ed, and the chilled water supply valves will be closed. After the end of concentration mode , the ADUN concentrat i on sub sy stem will return to standb y mode. 4-2 0 4 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.4.2.4.4 Special Nuclear Material Description Special N u clear Materia l Inventory The SNM inventory in the ADUN concentration subsystem will consist of dilute and concentrated ADUN. Table 4-66 lists the SNM inventory , including the feed tank and evaporator. Table 4-66. Acid-Deficient Urany l Nitrate Concentration Maximum Specia l Nuclear Material Inventory Location Form Concentration* Volume SNM mass* ADUN evaporator fee d tank [P roprietary In fo rm a ti o n] [Prop r ietary [Pr o pr ie t ary (Pro p ri e t ary ln fo rm a tion] Inform a tion] Inform a ti o n] (TF-TK-300) ADUN evaporator [Proprietary Information] [Proprietary [Proprietary [Proprietary lnformation] Information] Information]

SNM concentr a ti o n a nd ma ss r e pr ese nt tot a l a m o unt o f LEU (co mbin e d 235 U and 238 U a t ::S l 9.9 5 wt% m u). b AD UN ev a p o r a t o r c annot r e c e i ve m o re SNM m ass than i s in th e AD UN e v a por a t o r fee d tank due t o th e nature o f the b a tch pro ces sin g, so th e ev aporator fe ed t a nk provid es a b o undin g es timat e fo r the s ub sys t e m. m u 2Js u A D UN uranium-235. uranium-238. acid-d e fi c i e nt uran y l nitr a t e. L EU S M u low-enri c h e d uranium. s pe c i a l nu c l ear m a t e ri a l. uranium. Criticality Control Featu r es Criticality control features are required in this subsystem , as defined in NWMI-2015-CSE-005. These features , includin g passive design features, active engineered features and administrative contro l s , allow for adherence to the double-contingency principle.

This section applies the criticality control features that are described in Chapter 6.0 , Section 6.3. The technical specifications required for criticality control will be de v eloped for the Operating License Application and described in Chapt e r 14.0. The cr i ticality accident sequences are described and analyzed in Chapter 1 3.0 , Section 13.2 , where accid e nt prevention measures and features are identified. The criticality control features for this subsystem include the passive design features , active engineered features , and administrative controls with designators of PDF , AEF , and AC , respectively , li s ted be l ow. Chapter 6.0 provides detai l ed descriptions of the criticality control features. The passive design features affect the design of process equipment, ventilation piping , and the room floor , which will include the followin g. * * *

The geometry of the process equipment is inherently criticality-safe (CSE-05-PDF3) and maintains subcritical geometry during and after a facility DBE (CS E-05-PDF4). To prevent inadvertent interaction with mobile containers or carts, s idewall s surround the process skids (CSE-05-PDF5). Liquid s ys tems vessels and piping are de s igned for chemical operating conditions s uch that corrosion and leaking of tank walls and sea l s are prevented or minimized (CSE-05-PDF6).

The ventilation system connected to the evaporator feed tanks and the evaporator i s inherentl y criticality-safe by geometry, and overflow drains prevent liquid accumulation be y ond the criticality-safe g eometr y (CSE-05-PDF8). For the case of a liquid leak , the floor is criticality-safe (CSE-05-PDFl ), and a barrier or seal prevents penetration of fissile material into the floor (CSE-05-PDF2). 4-2 0 5 .. ;. NWMI *::**::* ..*... *

NORTifWHT Mfl>tCA&.

ISOTGn.S NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The active design featu r es wi ll include: *

The geometry of the closed-loop c hill ed water system is inherently critica li ty safe (CSE-05-AEFl), which prevents criticality in case of an internal failure of the heat exchanger.

Monitoring of the chilled water loop provides indi cation of the fai lur e. The condensate return from the ADUN reboiler is monitored for uranium. If uranium is detected, an isolation va l ve prevents the condensate from r eturning to the process steam system (CSE-05-AEF2). The admin i strative controls wi ll include:

Minimum spacing between movable containers and process equipment (CSE-05-ACl)

Some or all of the engineered safety features and administrative controls are classifie d as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 1 3.2 p rovides a description of the IROFS. The following IROFS will be applicable to the ADUN concentration activities.

*
The tanks , evaporator , heat exchangers , and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality.

This approach applies limit ations on the configuration , includin g the outside diameter of the process equipment a nd pipin g (IROFS CS-06), and fixed spacing between the process equipmen t with fissile solution (IROFS CS-07). The ADUN evaporator reboi ler (TF-E-330) is an interface between the l arge-geometry steam system and fissile material. In the case of a he at exchanger failure simu ltaneou s with a change in pressure differential , the con den sate return piping could contain fissile material. A conductivity swi tch and interlock would close an isolation valve on the condensate r eturn to prevent fissile material from proceedin g to the process steam system (IROFS CS-10). Instrument air piping for level mea sureme nt is a potential source for ba c kflow of fissi le solution to the l a r ge geometry of the instrument air system. To prevent back.flow , the instrument air sup pl y piping has a high point a bo ve the maximum liquid le ve l before connecting to the vented tank (IROFS CS-20). If instrument air supp l y pressure is lost , the highest liquid level is below the suppl y piping hi gh point , so backflow is impossible. In addition to the features that app l y the doubl e-co ntin ge nc y principle , several features provide d efense-in depth in criticality co ntrol. These fea tures will inc lude the following

C riticality calc ulations analyze d concentrations, m ass limits, and volumes that are not anticipated under normal conditions , so the controls ca n s u stain multiple upsets. The criticality a larm system provides criticality monitoring and alarm in a ll areas where SNM is handled , processed , or stored, as describ ed in Chapter 6.0. The critica lity contro l features provided throughout the irradiated target receipt process will be in accorda nce with the double-contingency principle , and the RP F wi ll pro vide suitab le de fense-in-depth for the contained pro cesses. 4-206 NWM I ...... ' *
NOmfWlST M£DICAl l$0TOflU 4.4.2.4.5 Chemical Hazards Chemical Inventory NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The chemical inventory in the ADUN concentration subsystem is represented in the SNM inventory in Table 4-66. Chemical Protection Provisions The primary chemical hazard in the ADUN concentration subsystem will be a chemical spray of ADUN. A spray shield installed on the skids will protect the operator from chemical bums in the event of a spra y leak from the process equipment or associated piping. 4.4.2.5 [Proprietary Information]

The [Proprietary Information] subsystem description provides information regarding the process, process equipment, SNM inventory, and the hazardous chemicals used in the subsystem. The process description (Section 4.4.2.5.1) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions, are described in Sections 0 and 4.4.2.5.3. A description of the SNM in terms of physical and chemical form , volume in process , and criticality control features is provided in Section 4.4.2.5.4. A description of hazardous chemicals that are used or may evolve during the process, along with the provisions to protect workers and the public from exposure , are presented in Section 4.4.2.5.5. 4.4.2.5.1 Process Desc r iption Figure 4-97 provides the stream numbers corre s ponding to the [Proprietar y Information]. [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-2 0 7 .. NWM I ...... ' e

NOllTHWHT MEDICAL tsOTOl'H [Proprietary Information]

NWMl-2015-021 , Rev. 3 Ch a pter 4.0 -RPF Description Figure 4-97. Sol-Gel Column Feed Process Flow Diagram 4-208 .... ; NWMI ...... .. *.. .*.******* * * *

NOmfWEST MEDtcAl ISOTOHS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.4.2.5.2 Process Equipment Arrangement

[Proprietary Information]. Figure 4-98 shows the location of the process equipment. [Proprietary Information] Figure 4-98. Sol-Gel Column Feed Equipment Layout 4-209 [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Propri etary Information] Figure 4-99. Concentrated Acid-Deficient Uranyl Nitrate Storage Equipment Arrangement 4.4.2.5.3 Process Equipment Design Figure 4-100. Sol-Gel Column Feed Equipment Arrangement This section identifies the processing apparatus and auxiliary equi pment supporting the [Proprietary Information] subsystem. This equipment is li sted in Table 4-67 with de sign data developed during preliminary design. Because dimensions have not ye t been defined , two fields are provided to identify the basis for equipment dimensions: capacity and whet her the equipment is designed to be criticality-safe by geometry. Additional detailed information (e.g., dimensions) will be developed for the Operating License Application. 4-210 ..... ; .. NWMI .......... *. ........ *. ' *.*

NOflTHW[ST MEDICAL ISOTOPES NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-67. [Proprietary Information]

Process Equipment Equipment name [Proprietary Information) [Proprietary Informati o n] [Proprietary Informati o n) [Propri etary In formation) [Proprietary Information] [Propri etary In fo rm a ti on) [Proprietary Information) [Propriet ary In fo rm ation) [Proprietary Information] [Pr o prieta ry Information] [Proprietary Information) [Propri etary In format i on) * [Proprietary Information] [Proprietary Information) [Proprietary Information] [Propr i e t ary Inform a tion] [Proprietary Information J [Proprietary In fo rm a tion] [Proprietary Information] [Proprietary Inform a tion] [Proprietary Information] [Proprietary In forma ti o n] [Proprietary Information] [Prop ri e tary Information J ADUN N I A acid-deficient uranyl nitrate. not applicab l e. I Individual tank capacity [Proprietary Information] [Proprietary I nformat i on] [Proprietary Information J [P ropri e tar y I nformat ion] [Proprietary Information) [Propr ieta ry Inform a tion] [Proprietary Information J [Prop rietary Information) [Proprietary Information) [Propr i e ta ry Inform at ion] [Proprietary Information J [P roprietar y In for m a ti on] SS TBD Process Monitoring and Control Equipment Operating range *----[Proprie tary [Proprietary [Propri etary [Proprietary Information) Information) Information] Information] [Proprietary [Pr o pri e t ary [Propri etary [Proprietary I nformation) Inform atio n) In formation] Info rmation) [Proprietary [Proprietary [Proprietary [Proprietary Information] Inform ation] Information] Informati on] [Propr i e t a r y [Propri etary [Propri etary [Prop ri etary In forma tion] In formation] I nformati o n) In formation] [Proprietary [Proprietary [Proprieta ry [Proprieta ry Information J Inform atio n J Information) Information] [Proprietary [Propri etary [Propri etary [Propri etary Inform a ti o n) In formation) Information] Information ] [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] Informati on] Informati on] [Propr i e t a r y [Prop rietary [Propri etary [Propri e t ary In for m at ion] In formation) In formation] Informati on] [Proprietary [Proprietary [Proprietary [Proprietary Information) Inform ation] Information] Informati on] [Propr i e t a r y [Pr oprie t ary [Propriet ary [Proprieta ry I nforma ti o n) I nform at i o n) Informati o n] In formation] [Proprietary [Proprietary [Propri etary [Proprietary Information J Information J Inform ation] Informati on) [Proprietary [Prop rietary [Propri etary [Propri etary In for mation] Inform at i on] Informati on] Inform at i o n] s tainl ess steel. to b e determined. Process monitoring and control equipment was not defined during prelimina ry design. Preliminary process sequences are provided in this section to identify the control s trate gy for normal operations , which sets requirements for the process monitoring and control equipment and the associated instrumentation. Other information on instrumentation and controls is provided in Chapter 7.0. Additional detailed information of the process monitoring and control equipment will be developed for the Operating License Application. [Proprietary Information]

[Proprietary Information]

4-211 ...... ;: NWMI ...... ..* **.* ........ * . * *. * ' NOATHW£ST MEDICAL I SOfOl"ES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

[Proprietary Information]

4.4.2.5.4 Special Nuclear Material Description Subsystem Special Nuclear Material Inventory [Proprietary Information] Table 4-68. [Proprietary Information] Special Nuclear Material Inventory Location Form Concentration* g111 .. 1;11m1 . .g?{* [Propri e tary In formation) [Proprietary Information) [Proprieta ry In formation) [P roprietary [Proprietary In formation) In format i on)

SNM concen t ration and m ass repre se nt total amount of LEU (combined mu and 238 U at S I 9.95 wt% m u). m u 23 su ADUN uranium-235. uranium-238. acid-defic ient uranyl nitrate. LEU SNM u low-enriched uranium. specia l nuclear material.

uranium. Criticality Control Features Criticality control fea tures are required in this s ubsystem , as defined in NWMI-2015-CSE-004 , NWMI Pr e liminary Criticality Safety Evaluation: Low-Enriched Uranium Targ e t Materia l Produ c tion. These features, includin g passive design features, active engineered features , and administrative co ntrols , allow for adherence to the double-contingency principle. This section applies the criticality control features that are described in Chapter 6.0 , Section 6.3. The technical s pecifications required for criticality control will be developed for the Operating License Application and de scribe d in Chapter 14.0. The critica lity accident sequences are described and analyzed in Chapter 13 .0, Section 13 .2. The criticality control features for this s ubsystem include the passive design features , active engineered features, and administrative controls with designators of PDF, AEF, and AC, respectively, listed below. Chapter 6.0 provide s detailed descriptions of the critica lity control features. The passive design features will include: * *

The geometry of the process equipment is inherently critica lity safe (CSE-0 4-PD F3, CSE-04-PDF7) and maintains subcritical geometry during and after a facility DBE (CSE-04-PDF4).

To prevent inadvertent interaction w ith mobile containers or carts, sidewalls surround the process skids (CSE-04-PDF5). Proce ss equipment and piping are designed for the normal process fluids and operating temperatures to minimize leakage (CSE-04-PDF6). At interfaces between lar ge-geo metry equipment and criticality-geometry equipment , anti-siphon air breaks prevent backflow (CSE-04-PDF12). The ventilation system connected to process equipment containing fiss i le material is inherently criticality-safe by geometry, and overflow drains prevent liquid accumulation be yon d the criticality-safe geometry (CSE-04-PDF 16). For the case of a liquid leak , the floor is criticality-safe (CSE-04-PDFl), and a barrier or seal prevents penetration of fissile material into the floor (CSE-04-PDF2). 4-212 ...... ;. NWMI ...*.. ..* .. .*.******* ' *.* NORTHWEST MEOK:Al tSOTOPH NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The active engineered features will include:

Continuous venti lation of tanks containing fissile material (CSE-04-AEFl)

The administrative features will include:

Minimum spacing between movable containers and process equipment (CSE-04-AC3)

Some or all of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 13.2 provides a description of the IROFS. [Proprietary Information].

*
The tanks , heat exchangers and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality.

This approach applies limitations on the configuration , including: (1) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equipment with fissile solution (IROFS CS-07). The supply of HMTA-urea solution is a potential source for backflow of fissile solution to the large geometry tanks. To prevent backflow, reagents are provided through an anti-siphon air break that separates the supp ly from the process equipment (IROFS CS-18). The anti-s iphon air break i s a pipe discharging to a funnel with a vertical offset so that siphoning is impossible. Instrument air piping for level measurement is a potential source for backflow of fissile solution to the large geo metry of the instrument air system. To prevent backflow , the instrument air s uppl y piping has a high point above the maximum liquid level before connecting to the vented tank (IROFS CS-20). If instrument air supply pressure is lost , the highest liquid le ve l is below the supply piping high point, so backflow is impossible. In addition to the features that apply the double-contingenc y principle, several features will provide defense-in-depth in criticality control. These features will include the following.

Criticality calculations analyzed concentrations, mass limits, and volumes that*are not anticipated under normal co nditions , so the controls can sustain multiple upsets.
The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed, or store d , as describ ed in Chapter 6.0. The criticality control features pro vi ded throughout the irradiated target receipt process will be in accordance with the double-contingency principle, and the RPF will provid e su itable defense-in-depth for the contained processes. 4.4.2.5.5 Chemical Hazards Chemical Inventory The chemical inventory for the [Proprietary Information]

subsystem is summarized in Table 4-69. Table 4-69. Chemical Inventory for the Sol-Gel Column Feed Subsystem Chemical Quantity Physical form [Propri etary Information J [Prop ri etary Information) [Propri etary Inform a ti on) [Proprietary Information) [Proprietary Information) [Proprietary Informa t ion) Note: This tabl e do es not include th e SNM identified in Tab l e 4-68. SNM = specia l nuclear materi al. 4-213 Concentration (if applicable) [Proprietary Information) [Proprietary Information) NWMI ...... * * ' NORTHWEST MEDICAl lSOTOPES Chemical Protection Provisions NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information]. A spray shield installed on the skids will protect the operator from chemical bums in the event of a spray leak from the process equipment or associated piping. The headspace above the process equipment will be maintained at a negative pressure and vented to the vessel vent system to prevent personnel exposure to offgases. 4.4.2.6 [Proprietary Information] Subsystem [Proprietary Information]. The process description (Section 4.4.2.6.1) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions, are descri be d in Sections 4.4.2.6.2 and 4.4.2.6.3. A description of the SNM in terms of physical and chemical form , volume in process, and criticality control features is provided in Section 4.4.2.6.4. The hazardous chemicals that are used or may evolve during the process , along with the provisions to protect workers and the public from exposure, are described in Section 4.4.2.6.5. 4.4.2.6.1 Process Description Figure 4-101 provides the stream numbers corresponding to [Proprietary Information]. [Proprietary Information [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-214 [P ro p r i etary In fo rm atio n] Figure 4-101. [Proprietary Information] 4-215 NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Descript i on [Proprietary Information] [Proprietary Information] [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.4.2.6.2 Process Equipment Arrangement [Proprietary Information] [Proprietary Information] Figure 4-102. [Proprietary Information] Layout 4-216 .; ... ;. NWMI ..*... .. .... ........ *.* NOATKWESTMEDtCAllSOTOPlS [Proprietary Information] 4.4.2.6.3 Process Equipment Design This section identifies the processing apparatus and [Proprietary Information] column subsystem. This equipment is listed in Table 4-70 with design data developed during preliminary design. Because dimensions have not yet been defined, two fields are provided to identify the basis for equipment dimensions

capacity and whether the equipment is designed to be criticality-safe by geometry.

Additional detailed information NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-103. [Proprietary Information] Arrangement (e.g., dimensions) will be developed for the Operating License Application. 4-217

.**.*.* .. ..... ;. NWMI ........... ' * * .' N0'"1fW£ST MEDICAL ISOTOPES N WMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Tab l e 4-70. [Proprietary Information]

Equipment name [Proprietary Information J [Proprietary Information] [P ropr i etary Inform at ion] [Propri etary Inform ation] [Proprietary Information] [Proprietary Information J [Prop rietary Informati on] [Propri etary Inform ation] [Proprietary Information] [Proprietary Informati o n] [Proprietary Inform at i on] [Proprietary Inform ation] [Proprietary Information] [Proprietary Information) [Propri etary Information] N I A SS not applicab l e. stainless stee l. [Proprietary Inform ation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietar y Inform at i on] [Proprietary Information] [Propriet ary Informati on] [Proprietary Information J [Proprietary Inform ation] Process Monitoring and Control Equipment Criticality-safe by geometry [Proprietary Information J [Proprietary Inform ation] [Proprietary Information] [Propriet ary In fo rm at i on] [Proprietary Information] [Propri etary Info rmation] [Proprietary Information] [Proprietary In for mati on] TBD .. Operating range [Proprietary Information J [Propri etary Inform at i on] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Propri etary In fo rm ation] [Proprietary Information J [Propriet ary Informati on) Temperature [Proprietary Information] [Propri etary Inform a ti on] [Proprietary Information] [Proprietar y Informati on J [Proprietary Information] [Proprietary Inform at ion] [Proprietary Information] [Propri etary Informati on] to be determin e d. Pressure [Proprietary Information] [Propri etary Informati on] [Proprietary Information] [Propri etary Inform at i on] [Proprietary Information] [Propri etary Information J [Proprietary Information] [Propri etary Inform at i on] Process monitoring and control equipment was not defined during preliminary design. Preliminary process sequences are provided in this section to identify the control strategy for normal operations, which set requirements for the process monitoring and control equipment and the associated instrumentation. Other information on instrumentation and controls is provided in Chapte r 7.0. Additional detailed information of the process monitoring and control equipment will be developed for the Operating License Application. [Proprietary Information].

* [Proprietary Information]

[Proprietary Information] 4.4.2.6.4 Special Nuclear Material Description Special Nuclear Material Inventory [Proprietary Information] Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-006, NWMI Preliminary Criticality Safety Evaluation: Targ et Finishing. These features, including passive design features , active engineered features, and administrat i ve controls, allow for adherence to the contingency principle. 4-218 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description This section applies the criticality control features that are described in Chapter 6.0 , Section 6.3. The technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0. The criticality accident sequences are described and analyzed in Chapter 13.0, Section 13.2 , where accident prevention measures and features are identified. The criticality control features for this subsystem include the passive design features , active engineered features, and administrative controls with designators of PDF, AEF, and AC, respectively , listed below. The passive design features include requirements for the floor , process equipment , workstations , and ventilation system. Active engineered features include the requirement of continuous ventilation. Chapter 6.0 provides detailed descriptions of the criticality control features. The passive design features will include the following.

* *
The geometry of the process equipment is inherently criticality-safe (CSE-04-PDF3 , CSE-04-PDF7 , CSE-04-PDF8 , CSE-04-PDF9, CSE-04-PDFlO , CSE-04-PDF15) and maintains subcritical geometry during and after a facility DBE (CSE-04-PDF4).

To prevent inadvertent interaction with mobile containers or carts , sidewalls surround the process skids (CSE-04-PDFS , CSE-04-PDFl 3). Process equipment and piping are designed for the normal process fluids and operating temperatures to minimize leakage (CSE-04-PDF6). At interfaces between large-geometry equipment and criticality-geometry equipment , anti-siphon air breaks prevent backflow (CSE-04-PDF 12). Workstations where LEU target material is handled do not have spill-prevention lips higher than 2.54 cm (1 in.) (CSE-04-PDFl I , CSE-04-PDF14). The ventilation system connected to process equipment containing fissile material is inherently criticality-safe by geometry , and overflow drains prevent liquid accumulation beyond the criticality-safe geometry (CSE-04-PDF16). For the case of a liquid leak , the floor is criticality-safe (CSE-04-PDFl), and a barrier or seal prevents penetration of fi s sile material into the floor (CSE-04-PDF2). The active engineered features will include:

Continuous ventilation of tanks containing fissile material (CSE-04-AEFl)

The administrative features will include:

Minimum spacing between movable containers and process equipment (CSE-04-AC3)

Some or all of the en g ineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0, Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the [Proprietary Information]. *

The tanks , heat exchangers , and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality.

This approach applies limitations on the configuration, including: (1) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equipment with fissile solution (IROFS CS-07). Instrument air piping for level measurement is a potential source for backflow of fissile solution to the large geometry of the instrument air system. To prevent backflow, the instrument air supply piping has a high point above the maximum liquid level before connecting to the vented tank (IROFS CS-20). If instrument air supply pressure is lost, the highest liquid level is below the supply piping high point , so backflow is impossible. 4-219 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description In addition to the features that apply the double-contingency principle, several fe atures will prov i de defense-in-depth in criticality control. These features will include the followin g.

Criticality calculations ana lyzed concentrations, mass limits , and volumes that are not anticipated under normal conditions, so the controls can sustain multiple up se ts.
The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed, or stored, as described in Chapter 6.0. The criticality control features provided in the irradiated target receipt proce ss will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in

-depth for the contained proce sses. 4.4.2.6.5 Chemical Hazards Chemical Inventory [Proprietary Information] Table 4-71. [Proprietary Information] Subsystem Chemical [Propri e tary Information] Quantity [Proprietary In forma ti on] Note: This ta bl e does not include the SNM id e ntifi ed in Tab l e 4-68. SNM = s peci al nuclear material. Chemical Protection Provisions [Proprietary Information]. 4.4.2.7 [Proprietary Information] Subsystem Physical form [P roprietary Information] Concentration (if applicable) [Proprietary Information] The [Proprietary Information] subsystem description provides information rega r ding the process , process equipment, SNM inventory, and the hazardous chemicals used in the subsystem. The process description (Section 4.4.2.7.1) provides a detailed account of the SNM in process during normal operations and pro vi des the basis for equipment de s ign. The arrangement and design of the processing equipment, including normal operating conditions, are described in Sections 4.4.2.7.2 and 4.4.2.7.3. A description of the SNM in terms of physical and chemical form, volume in process, and critic a lity control features is provided in Section 4.4.2. 7.4. The hazardous chemicals that are used or may evolve durin g the proces s, along with the provi sio ns to prot ect workers and the public from exposure, a re described in Section 4.4.2.7.5. 4.4.2.7.1 Process Description Figure 4-104 provide s the stream numbers corresponding to the [Proprietary Information] descriptions. 4-220 [Propri etary In fo rm atio n] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-104. [Proprietary Information] Flow Diagram 4-221 NWM I ...... * *

NOATIIWEIT MEOtcAL ISOTDl'U [Proprietary Information]

[Proprietary Information]

* * * [Propriet ary Information]

[Proprietary Information] [Propriet ary Information] [Proprieta ry Information] . [Proprietary Information] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Proprietary Inform ation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

* * [Proprietary Information]

[Proprietary Information] [Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Descript i on [Propr ietary Information]

* * [Proprietary Information]

[Proprietary Information] [Proprietary Information] 4-222 [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

* * [Proprietary Information]

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] 4-223 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description .... ;. NWMI ...... .. .. .......... ' *. *

NOflTHWEST MfotcAl 1$0TOPlS [Proprietary Information]

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Inform atio n] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-72. [Proprietary Information] Process operation [Propriet ary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] Probable recycle material [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Propri etary Information] LEU = low-enrich ed u r anium. [Proprietary Information] [Proprietary Information] 4-224 4.4.2. 7.2 Process Equipment Arrangement [Proprietary Information] [Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] [Proprietary Information] Figure 4-105. (Proprietary Information] Layout 4-225 [Proprietary Information] Figure 4-106. [Proprietary Information] Arrangement .; ... ; NWMI ..*... ..* .. .*.* .. *.*. ' *.*

NOITifWErT MEDIC.Al lSOTOl"U [Proprietary Information]

[Proprietary Information] [Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-107. [Prop r ietary Information] Arrangement [Proprietary Information] Figure 4-108. [Proprietary Information] Layout 4-226

.. ;. NWMI 'f: **::* ...... ' * *

NORllfWUT MEDICAL ISOTOPES Figure 4-109 shows the arrangement of the [Proprietary Information].

[Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Figure 4-109. [Proprietary Information] Arrangement 4.4.2.7.3 Process Equipment Design [Proprietary Information]. Equipment is li sted in Tab l e 4-73 with the design data developed during preliminary design. Because dimensions have not yet been defined , two fields are provided to id entify the basis for equipment dimensions: capacity and whether the equipment is designed to be critica li ty-safe by geometry. Additional detailed information (e.g., dimensions) will be developed for the Operat in g License Application. 4-227 .. ;.-:;**NWMI ..... .......... ' *.* . NOmfWEtT MlDK:AL tsOTOPU Equipment name [Proprietary Info rm ation] [Proprietary Information] [Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary In format i on] [Propri etary Information] [Proprietary Inform at i on] [Proprietary Information] [Proprietary Inform at i on] [Propri etary Information] [Proprietary Information J [Proprietary Informat i on] [Proprietary Information] [Proprietary Informa ti on] [P roprietary I nformation] [Proprietary Information] [Proprietary Information] [Proprietary I nform at i on] LEU l ow-enriched uranium. N I A not a ppli cab l e. [P rop ri e tary I n formation]. NWMl-20 1 5-021 , Rev. 3 Chapte r 4.0 -RPF Descript i on Ta bl e 4-7 3. [P r o p r i e ta ry I n fo rm a tion] Equipment no. [Propr i etary Info rm atio n J [Propr i etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Informat i on] [Prop r ie t ary Information ] [Proprietary Informa t io n] [Proprietary Information] [Proprietary Information] [Prop ri e t ary lnformation] [Propr i etary Inform at io n J [Propr i etary Information] [Prop r ietary Information] [Propr i e t ary Information] [Propr i etary Informat i o n] [Prop ri etary Information] [Propr i etary Information J [Proprietary Information]

_-___ _ Operating range [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Informat i o n] I nformation] I nformation] I nformat i on] In fo rm ation] [Proprietary [Proprietary [P roprietary [Proprietary [Proprietary In format i on] Information] Information] In format i on] In formation] [Proprietary [Prop r ietary [Proprietary [Proprietary [Propri e tary Information] Information] Information] Inform a t i on] Informat ion] [Propr i etary [Proprietary [P roprietary [Proprietary [Propri e t ary lnformation J In formatio n] ln format ion] I nformat i on] In formation] [Proprietary [Propri e tary [Proprietary [Proprietary [Proprietary Informat i on] Information] Inform at ion] Informat i on J Informat i on] [Proprie t ary [P roprietary [Proprietary [Pr oprietary [P roprietary In formation] ln formation] I n formation] ln format i on] I nformation] [Propri e tary [Proprietary [Proprietary [Propri etary [Proprietary Informa t io n] Informatio n] In formation] Informat i on] In formation J [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] In format i on] Information] I n format i on] ln formation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] Informatio n] Inform at i on] Information] [Proprie t ary [Proprie t ary [Proprietary [Proprietary [Proprietary lnformation] lnform ation] I nformation] In format i on] l nformation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Informat i o n] Informat i on] Informatio n] Informat i on J Informati on] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] In formatio n] I nformation] I nformat i on] Information] [Prop r ietary [Proprietary [Proprietary [Proprietary [Proprietary Informatio n J Information ] Information] Informat i on] Inform at ion] [Pro pri e t ary [Propr ietary [P roprietary [Propri etary [Propri etary lnformation] ln formation] ln formation] Informat i on] Information] [Prop r ietary [Proprietary [Proprietary [Proprietary [Propri etary Inform a tion] Information] Information ] Informat i o n] In formation] [Proprietary [P roprietary [Proprietary [P roprietary [P ro pr ietary Information] I nformation] I nformation ] ln format i on] In formation] [Proprietary [Prop r ietary [Proprietary [Proprietary [Proprietary Inform a t i o n] Informatio n] I nformation] Inform at i on J Informati o n] [Propr i etary [Proprietary [P roprietary [Proprietary [Proprietary I nforma ti o n] I nformatio n] l nformation] I nformat i on] In format i on] SS s tain l ess stee l. TBD to b e determined. TCE trich l oroe thy l e n e. 4-2 2 8 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Process Monitoring and Control Equipment Proce ss monitoring and control equipment was not defined during preliminary design. Preliminary process sequences are provided in this section to identify the control strategy for normal operations, which sets requirem e nts for the process monitorin g and control equipment and the associated instrumentation. Other information on instrumentation and controls is provided in Chapter 7.0. Additional detailed information of the process monitoring and control equipment will be developed for the Operating License Application. [Proprietary Information]

* [Proprietary Information]

[Proprietary Information] [Propriet ary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] 4.4.2. 7.4 Special Nuclear Material Description Spent Nuclear Material Inventory [Proprietary Inform atio n] Table 4-74. [Proprietary Information] Location Form [P roprie t ary Inform a ti o n] [Proprietary I nformation) [Proprietary Infonnation] [Proprietary Inform a tion) [Propri e t ary Inform a ti on] [P roprietary Inform a ti on] Concentration* [Propri etary In formation] [Proprietary Information] [Propri etary In format i on] i@!l!,,!W [Propri etary In formation] [Proprietary Inform a tion) [Propri e t ary In forma ti on] SNM mass* [Propriet ary Information) [Proprietary Information J [Propri e t ary Inform ation]

SNM concentrati o n an d ma ss r eprese nt tota l amount of LEU (combined m u and 238 U at:<:; 1 9.95 wt% 235 U). m u 238 u LEU N I A uranium-235. uranium-238. lo w-enriche d uranium. not applicab le. SNM = s pecial nuclear material.

U = ur anium. [Proprietary Information] (Propri etary Informati on] 4-229 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Criticality Control Features Criticality control features are required in this subsystem , as defined in NWMI-20 l 5-CSE-004. These features , including passive design features, active engineered features , and administrative controls, allow for adherence to the double-contingency principle. This section applies the crit i cality control features that are described in Chapter 6.0, Section 6.3. The technical specifications required for critical i ty control will be developed for the Operating License Application and described in Chapter 14.0. The criticality accident sequences are described and analyzed in Chapter 13 .0 , Section 13 .2, where accident prevention measures and features are identified. The criticality control features for this subsystem include the passive design features, active engineered features, and administrative controls with designators of PDF , AEF , and AC , respectively , listed below. The passive design features include requirements of the floor, process equipment , workstations, and ventilation system. Active engineered features include the requirement of continuous ventilation. Chapter 6.0 provides detailed descriptions of the criticality control features. The passive design features will include the following.

* *
The geometry of the process equipment is inherently criticality-safe (CSE-04-PDF3, CSE-04-PDF8 , CSE-04-PDF9 , CSE-04-PDFlO) and maintains subcritical geometry during and after a facility DBE (CSE-04-PDF4). To prevent inadvertent interaction with mobile containers or carts, sidewalls surround the process skids (CSE-04-PDF5 , CSE-04-PDFl 3). Process equipment and piping are designed for the normal process fluids and operating temperatu r es to minimize leakage (CSE-04-PDF6).

Workstations where LEU target material is handled do not have spill-prevention li ps higher than 2.54 cm (1 in.) (CSE-04-PDFl 1 , CSE-04-PDF14). The ventilation system connected to process equipment containing fissile material is inherently criticality-safe by geometry, and overflow drains prevent liquid accumulation be y ond the criticality-safe geometry (CSE-04-PDF 16). For the case of a liquid leak , the floor is criticality-safe (CSE-04-PDF 1 ), and a barrier or seal prevents penetration of fissile material into the floor (CSE-04-PDF2). The active engineered features will include: Continuous ventilation of tanks containing fissile material (CSE-04-AEFl) The administrative controls will include: *

Size limit of process apparatus holding target material (CSE-04-ACl and CSE-04-AC2)

Minimum s pacing between movable containers and process equipment (CSE-04-AC3) Carrying limit of one fissile-bearing container per operator (CSE-04-AC4) Some or all of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0, Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the [Proprietary Information] activities.

* [Proprietary Information]

[Proprietary Information] 4-230 ..... NWMI ...... .. *.. .......... NOITifWEST MEDICAL ISOTOPfS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

*
The surge tanks and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality.

This approach applies limitations on the configuration, includin g (1) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equipment with fissile so lution (IROFS CS-07). The offgas heat exchanger (TF-E-670) on the [Proprietary Information] presents a source of water that could cause criticality or other hazard if the heat exchanger fails. A drain pot on the exhaust line dischar ges water to the floor in the case of a heat exchanger leak (IROFS CS-12). The drain pot is a liquid-filled pot beneath the vent header. Under normal conditions, there is no flow through the drain pot. In the case of a heat exchanger failure, the vent piping is slope d to drain water into the drain pot. [Proprietary Information] In addition to the features that apply the double-contingency principle, several features will provide defense-in-depth in criticality control. These features will include: * * *

Administrative batch limits are set based on worst-case moderation , even though most uranium is dry during normal conditions.

Administrative interaction controls are based on man y evenly spaced units contributing to the return of neutrons. Administrative failures during handling between workstations ge nerally involve only two containers. Criticality calculations analyzed concentrations, mass limits, and vo lumes that are not anticipated under normal conditions, so the controls can sustain multiple upset s. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed , or stored, as described in Chapter 6.0. The criticality control features provided throughout the irradiated target receipt process will be in accordance with the double-contin ge ncy principle , and the RPF will provide suitable defense-in-depth for the contained proce sses. 4.4.2.7.5 Chemical Hazards Chemical Inventory The chemical reagents for the [Proprietary Information] subsystem are listed in Table 4-75. In addition to the chemical reagents , offgases are released during the dryin g and reduction steps. Table 4-75. Chemical Inventory for the [Proprietary Information] Subsystem Chemical [Prop ri etary In fonnation J [Propri etary lnfonnation) Quantity [Propri etary lnfonnation] [Proprietary Infonnation )' Note: This table does not includ e the SNM identifi ed in Table 4-74. * [Proprietary Information]. SNM = s p ecial nuclear m a t eria l. 4-231 Physical form [Propr i etary lnfonn at ion) [Proprietary Information) Concentration (if applicable) [Propri etary ln fonnation] [Proprietary lnfonnation) ...... NWMI ...... ..* *.. ........... "NOllTHWESTMEDICAUSOTDPES Chemical Protection Provisions NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description The primary chemical hazard in the [Proprietary Information]. The method of v entilation will be determined for the Operating License Application. Tanks with the bulk chemicals will be maintained at a negative pressure and vented to the vessel ventilation system. The off gases formed during [Proprietary Information] will be contained within the process equipment and vented to the vessel ventilation system. 4.4.2.8 Target Fabrication Waste Subsystem The target fabrication waste subsystem description provides information regarding the pro c ess, process equipment, SNM inventory, and the hazardous chemicals used in the subsystem. The process description (Section 4.4.2.8.1) provides a detailed account of the SNM in process during normal operation and provides the basis for equipment design. The arrangement and design of the processing e q uipment, including normal operating conditions, are described in Sections 4.4.2.8.2 and 4.4.2.8.3. A description of the SNM in terms of physical and chemical form , volume in process, and criticality control features is provided in Section 4.4.2.8.4. The hazardous chemicals that are used or may e v olve durin g the process , along with the provisions to protect workers and the public from exposure , are described in Section 4.4.2.8.5. 4.4.2.8.1 Process Description Figure 4-110 provides the stream numbers corresponding to the target fabrication waste process description. Trichloroethylene Recovery [Proprietary Information]. The TCE will be pumped to TCE recycle tanks (TF-TK-720 , TF-TK-725), where the solvent will accumulate for one week and then sampled to verify the absence of fissile material. Once the absence of fissile material is verified, the solvent will be fed to a commercial distillation-type TCE recovery package (TF-Z-740). The recovered solvent will be pumped to the solvent fe ed tank. The waste from the solvent recovery package will be collected locally to be discard e d. Aqueous Waste Holding Aqueous waste will be generated in the nitrate extraction, ADUN concentration, and [Proprietary Information] subsystems. Under normal operating conditions , no fissile materi a l will be p r esent in the aqueous waste; however , process upsets may cause fissile solution to be transferred to the aqueous waste pencil tanks (TF-TK-700, TF-TK-705). Each tank will be sized to receive the highest normal operations demand in 2 days of operation to allow time for recirculation, sampling , and transfer. When one tank is full , the inlet will be manually changed from one tank to the other. The aqueous waste pump will recirculate the contents to ensure adequate mixing for representative samples. Independent aliquots will be drawn from the tanks and analyzed. After the laboratory analysis verifies the content o f fissile material is below [[Proprietary Information], the valve lineup will be changed manually to transfer the aqueous waste to the waste handling system. The value will be determined during deve l opment of the final RPF design. 4-232 NWM I ...... * * ! NOITNWHT Mfbk:Al 150TDPES [Proprietary Information] NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Descr iption Figure 4-110. Target Fabrication Waste Process Flow Diagram 4-233 Target Fabrication Vessel Ventilation Overflow Protection NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Based on the configuration of tanks and pumps, a tank with fissile material could potentially overflow to the v essel ventilation header due to equipment failure or operator error. In this accident scenario , the first line of defense will be the vessel ventilation overflow tank. The overflow tank will receive the solution and alarm to notify operators of the accident. Overflows that exceed the volume of the overflow tank , or otherwise enter the vessel ventilation header , would be discharged to the floor through a drain pot. 4.4.2.8.2 Process Equipment Arrangement The fresh target fabrication waste equipment will be mounted on three skids within room Tl 04C , the wet side of the target fabrication room. Figure 4-111 shows the location of the process equipment. [Proprietary Information] Figure 4-111. Target Fabrication Waste Equipment Layout 4-234 .; ... ;. NWMI ..*... ..* *.. ........... ' *.* ' NomtWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Figure 4-112 shows the typical arrangement of the aqueous waste holding tank skids. Figure 4-113 shows the equipment arrangement of the TCE recovery skid. Spent TCE from the [Proprietary Information] will accumulate in one of the TCE recycle tanks (TF-TK-720 or TF-TK-725). The recycle tanks will be sampled before feeding the TCE recovery package (TF-Z-740). As the solvent is recovered , TCE will drain to the regenerated TCE tank (TF-TK-750) and then be pumped to the TCE tank (TCE-TK-760 , not pictured). [Proprietary Information] Figure 4-112. Aqueous Waste Holding Tank 4.4.2.8.3 Process Equipment Design [Proprietary Information] Figure 4-113. Trichloroethylene Recovery Skid Arrangement This section identifies the processing apparatus and auxiliary equipment supporting the target fabrication waste subsystem. This equipment is listed in Table 4-76 with design data developed during preliminary design. Because dimensions have not yet been defined, two fields are provided to identify the basis for equipment dimensions

capacity and whether the equipment is designed to be criticality-safe by geometry.

Additional detailed information (e.g., dimensions) will be developed for the Operating License Application. 4-235 ... ;.-;; .. NWM I ...... ........ *. NORTHWUTMEDICAllSOTOPES NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-76. Target Fabrication Waste Process Equipment ' Equipment name Equipment no. Operating range *** i .. !.@llllllllm Aqueous waste pencil tank TF-TK-700 [Proprietary Yes 304L SS (Proprietary [Proprietary Information] Information] Information] Aqueous waste holding tank TF-TK-705 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Inform a tion] Information] Aqueous waste pump TF-P-710 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information] Information] Aqueous waste pump TF-P-715 [Proprietary Yes TBD [Proprietary (Proprietary Information] Information] Information] TCE recycle tank TF-TK-720 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information] TCE recycle tank TF-TK-725 [Proprietary Yes 304L SS [Proprietary [Propriet a ry Information] Inform a tion] Information] TCE recycle pump TF-P-730 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information] Information] TCE recovery package TF-Z-740 [Proprieta ry No TBD [Propriet ary [Propriet ary Information] Information] Informati o n] Regenerated TCE tank TF-TK-750 [Proprietary No 304L SS [Proprietary [Proprietary Information] Information] Information] Regenerated TCE pump TF-P-755 [Proprietary No TBD (Proprietary [Propri e tary Information] Information] Information] TCEtank TF-TK-760 (Proprietary No 304L SS (Proprietary (Proprietary Information] Information] Information] Target fabricat i on overflow tank TF-TK-770 [Proprietary Yes 304L SS [Proprietary [Propri e t a ry Information] Information] Informati o n] Target fabrication overflow TF-P-775 [Proprietary Yes TBD [Proprietary [Proprietary pump Information] Information] Information] N I A not applicable. TBD to be determined. SS stainless steel. TCE trichloroethylene. Process Monitoring and Control Eq u ipment Process monitoring and control equipment were not defined during preliminary design. Preliminary process sequences are provided in this section to identify the control strategy for normal operations, which sets requirements for the process monitoring and control equipment and t he associated instrumentation. Other information on instrumentation and controls is provide d in Chapter 7.0. Additional detailed information of the process monitoring and control equipment will be developed for the Operating License Application. The aqueous waste holding function will be a batch process. The aqueous waste ho l ding function will have one tank available for filling at all times. When one tank is full, the opera t or will change the valve alignment to direct incoming aqueous waste to the parallel tank (TF-TK-700 or TF-TK-705). The recirculation pump (TF-P-710 or TF-P-715) will mix the full tank by recirculation for [TBD] hr (the value will be determined during development of the final RPF design). Samples will be analyzed in the l aboratory system for uranium concentration before transfer. The product discharge valve will be opened , and the aqueous waste will be transferred to the waste handling system. 4-23 6 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description TCE recovery will be a batch process: *

The TCE recovery function will have one tank available for filling at all times. When one tank is full , the operator will change the valve alignment to direct incoming spent TCE to the parallel tank (TF-TK-720 or TF-TK-725). The recirculation pump (TF-P-730) will mix the full tank by recirculation for [TBD] hr (the value will be determined during development of the final RPF design). Samples will be analyzed in the laboratory system for uranium concentration before transfer.

The product discharge valve will be opened, and the spent TCE will be transferred to the solvent recovery package (TF-Z-740). The operator will then begin the automated solvent recovery cycle. The product will drain to a collection tank during operation. At the end of the solvent recovery cycle , the waste will be collected for organic waste disposal. 4.4.2.8.4 Special Nuclear Material Description Special Nuclear Material Inventory The target fabrication waste subsystem will be capable of holding aqueous SNM for off-normal or accident scenarios , but there will be no regular SNM inventory. Criticality Control Features Criticality control features are required in this subsystem , as defined in NWMI-20 l 5-CS E-009 , NWMJ Pr e liminary Criti ca li ty Saf e ty E v aluation: Liquid Wa s t e Pro cess ing. These features , consisting of administrative controls , allow for adherence to the double-contingency principle. This section applies the criticality control features that are described in Chapter 6.0, Section 6.3. The technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0. The criticality accident sequences are described and analyzed in Chapter 13.0 , Section 13.2, where accident prevention measure s and features are identified. The criticality control features for this subsystem are the administrative controls, with a designator of AC, listed below. Chapter 6.0 provides detailed descriptions of the criticality control features. The administrative controls will include: * *

Mass limit of accumulation within the low-dose waste tanks (CSE-09-AC

1) Sampling requirements before transferring aqueous waste to large geometry low-dose tanks (CSE-09-AC2)

Management or supervisor verification of sampling results before transferring aqueous waste to large geometry low-dose tanks (CSE-09-AC3). Some or all of the en g ineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 13.2 provides a description of the IROFS. The following IROFS will be applicable to the target fabrication waste activities.

The TCE recycle tanks (TF-TK-720, TF-TK-725) and the aqueous waste pencil tanks (TF-TK-700 , TF-TK-705) do not contain uranium during normal operations.

For the case of an upset, the tanks and associated piping and equipment are designed to be inherently safe by geometry to prevent criticality. This approach applies limitations on the configuration, including (1) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equipment with fissile solution (IROFS CS-07). These tanks discharge to large geometry equipment, so measurements are needed to prevent fissile solution s from entering large geometry equipment. This measurement is accomplished by two independent samples and analyses of uranium concentration by the analytical laboratory (IROFS CS-l 6/CS-17). 4-237 .; .. ;. NWMI ...... .. .. ... NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

* *
NORTHWEST MElMCAl ISOTOPU
Instrument air piping for level measurement is a potential source for backflow of fissile solution to the large geometry of the instrument air system. To prevent backflow , the instrument air supply piping has a high point above the maximum liquid level before connecting to the vented tank (IROFS CS-20). If instrument air supply pressure is lost , the highest liquid level is below the supply piping high point, so backflow is impossible.

In addition to the features that apply double-contingency principle , several features will provide in-depth in criticality control. These features will include: *

During normal operations, no uranium is present within the target fabrication waste subsystem . Criticality calculations analyzed concentrations, mass limits , and volumes that are not anticipated under normal conditions, so the controls can sustain multiple upsets.
The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed, or stored, as described in Chapter 6.0. The criticality control features provided throughout the irradiated target receipt process will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes.

4.4.2.8.5 Chemical Hazards Chemical Inventory The target fabrication waste chemical inventory is s ummarized in Table 4-77. Table 4-77. Target Fabrication Waste Chemical Inventory Chemical Trichloroethylene Aqueous waste (may contain ammonium hydroxide, ammonium nitrate, HMTA, nitric acid, sodium hydroxide , sod ium nitrate, and urea) [Proprietary [Propri etary Inform at i on] In format i on] [Proprietary [Proprietary In formation] Information] HMTA = he xa m et h y len ete tramin e. N I A = not app lic ab le. Chemical Protection Provisions Concentration (if applicable) [P roprietary Inform a ti on] [Proprietary Information] The primary chemical hazards in the target fabrication waste subsystem will be a chemical spray of aqueous waste or TCE, and personnel exposure to offgases. A spray shield installed on the skids will protect the operator from chemical burns in the event of a spray leak from the process equipment or associated piping. The headspace above the process equipment will be maintained at a ne ga tive pressure and vented to the vessel ventilation sys tem to prevent personnel exposure to offgases. 4.4.2.9 Target Assembly Subsystem The target assembly subsystem description provides information regarding the process, process equipment, SNM in ve ntory , and the hazardous chemicals used in the subsystem. The process description (Section 4.4.2.9.1) provides a detailed account of the SNM in process during normal operations and provides the basis for equipment design. The arrangement and design of the processing equipment, in cluding normal operating conditions , are described in Sections 4.4.2.9.2 and 0. A description of the SNM in terms of physical and chemical form , volume in process, and criticality control features is provided in Section 4.4.2.9.4. The hazardous chemicals that are used or ma y evolve durin g the process , along with the provisions to protect workers and the public from exposure, are described in Section 4.4.2.9.5. 4-238 4.4.2.9.1 Process Description Target Loading NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Target loading wi ll be performed using the target lo ading preparation workstation (TF-WT-8 00) and target loadin g workstation (TF-WT-810) locat ed wit hin the target asse mbl y area (TF-800), as s ho w n in F i gure 4-114. An interim transfer container of LEU target material wi ll be received from the LEU can rack. A ll handlin g of ope n LEU target material containers will occ ur in an anti-stat i c wo rk area. Target h ardware from the target hardware storage rack wi ll be weighed , and the partially assembled target will be vertica ll y secured in a target-l oading fixture in preparation for lo a din g. An [Proprietary Information] will be weig h e d following the material accountability procedure and l oaded into a feed hopper of the target loading fixture. [Proprietary Information]. [Proprietary Information] Figure 4-114. Target Loading Preparation and Target Loading Workstation 4-239 ... ;. NWMI *:.**.*; ........ *. * * *

NDmfW£ST MEDfCAI. tsOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description After target loading is complete, the upper aluminum washer and temporary upper end fitting will be installed.

The loaded target will be removed from the target holding fixture, and the material accountability procedure will be followed. The filled target will be placed in the target transfer cart for further processing at the target welding enclosure (TF-EN-820). Target Welding and Weld Finishing The target and its necessary components will be transferred to the target welding enclosure (TF-EN-820) via the target entry airlock. The airlock will be sized to minimi ze helium consumption durin g target entry activities. The airlock will be configured at an angle with target capture features to provide safe and controlled target entry into the g lovebox. A helium environment in the enclosure will provide a cover gas within the tar get and allow for the subsequent [Proprietary Information] Figure 4-115. Target Welding Enclosure [Proprietary Information] Figure 4-116. Target Weld Finishing Workstation helium leak check. Targets will be sec ured in a target welding fixture. The temporary upper end fittin g will be manually removed , and the upper cap washer po s itioned for the first weld. The g lovebox environment will be maintained at a minimum concentration of 90 percent helium and monitored and maintained by a circulation loop with a gas analyzer and a helium feed stream. The upper cap washer and the upper end fitting will be manually loaded into the target welding fixture through glove ports. The fiber optic laser will have three fixed positions; the first position for welding the inner seam of the upper cap washer, the second position for welding the outer seam of the upper cap washer, and the third position for welding the outer seam of the upper end fitting. The target welding fixture will rotate durin g welding. A layout of the target welding enclosure is shown in Figure 4-115. Welded target s will be routed to the tar get weld finishin g workstation (TF-WT-820) for grinding and polishin g of the welded areas of the target. A layout of the target weld finishing workstation is s hown in Figure 4-116. 4-240 Target Qualification NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Immediately following the removal of welded targets from the we ldin g enclosure, the welds will be finished at the target we ld finishing workstation (TF-WT-820) and inspected at the target we ld inspection workstation (TF-WT-830) (Figure 4-1 17). Following the weld inspection, the target assemb l y will be weighed and checked for dimensional conformance u sing go/no-go gauges. Targets wi ll be placed in the helium leak test chamber where background gases are pumped out, and the chamber pressure will be lowered to draw out helium if l eaks exist in the target. A helium mass spectrometer will indicate the helium leak rate for the tested target. Targets that pass the helium l eak test will be scanned and cleaned of any surface contamination. These ana l yses will verify that the: ( 1) targets are sealed, (2) weld integrities are adeq uate , and (3) target physical dimensions and weig h t meet specifications. [Proprietary Information] Figure 4-117. Target Weld Inspection Station and Target Weight Inspection Equipment 4-241 Target Qualification Failure Complete d targets that fai l any of the quality checking and ve rifi catio n analyses wi ll be recycled and the LEU target material will be recovered as off-specification uranium. The primary steps NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description involved in handlin g fai l e d targets are pro v ided in [Proprietary Information] Section 4.1.4.4. The fai l ed target will be transferred to a target disassembly workstation (TF-WT-870), which wi ll house a target cutting tool and a target unloading system for collecting the LEU target material. The retrieved LEU target Figure 4-118. Target Disassembly Workstation mat eria l will be h and led as off-specification uranium for uranium recovery, since unwanted foreign materi a l ma y be present. A la yout of the target di sassemb l y workstatio n is shown in Figure 4-118. 4.4.2.9.2 Process Equipment Arrangement The target assembly process equipment will be l ocate d throughout room Tl04B , the dry side of the target fabrication room. Figure 4-119 shows the lo cation of the process eq uipm ent. The arrangement of the target asse mbl y process equipment is discussed throu g hout the process description. [Propr ietary Information] Figure 4-119. Target Assembly Equipment Layout 4-242 NWM I ...... ' *.*

NOWTHWUT Mt:DtcAl ISOTOPfS 4.4.2.9.3 Process Equipment Design The process equipment in the target assembly s ubs yste m will consist of containers and target assemblies that house the LEU target material, target filling equipment, target welding equipment, target QC equipment, and storage carts, as identified in the process description.

The target assemblies are described in this section, and the target storage carts are described in Section 4.4.2.10.3. The auxiliary equipment that is identified in Section 4.4.2.9. l is listed in Table 4-78. Additional detailed information on the target assembly equipment will be developed for the Operating License Application. Target Design The target hardw are ph ys ical description is as described in Docket Number 50-243, "O regon State TRIGA Reactor License Amendment for Irradiation of Fuel Bearing Targets for Production ofMol y bdenum-99." [Proprietary Information] as shown in Figure 4-120. NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description Table 4-78. Target Assembly Auxiliary Equipment Equipment name LEU can transfer cart Target loading prep workstation Target loadin g workstation Target welding enclosure Target weld finishing workstation Target weld inspection workstation Target s pecific atio n check wo rk stat ion Target leak check workstation Target s urfac e co ntaminati on check workstation Target disassembly workstation LEU = low-enriched uranium. [Propri etary Information] Equipment no. TF-MC-800 TF-WT-800 TF-WT-810 TF-EN-820 TF-WT-820 TF-WT-830 TF-WT-840 TF-WT-850 TF-WT-860 TF-WT-870 Source: Docket N umber 50-243 , "Orego n State TRIGA Reactor License Amendment for Irradi ation of Fuel B earing Targets for Production of Molybd e num-99," Apri l 20 1 2. 4-243 Figure 4-120. Target Assembly Diagram (Doc-No 50-243) .; ... ;. NWMI .... ** ...... .*.* .. *.*.* ' *. *

NOllTHWUT MEDK:Al tsOTOPES [Proprietary Information].

Design parameters are summarized in Ta ble 4-79. The inner and outer aluminum cladding sections will be welded to a cap washer at the top and bottom to provide the primary seal. The [Proprietary Information]. Upper and lower end fittings will be welded to the top and bottom of the annular bearing section. The upper fitting will be designed to interface with the upper gridplate holes and will incorporate a pin that allows handling of the tar get using the sta ndard [Proprietary Information]. The lower fitting will be designed to position the LEU material portion of the target at a fixed hei g ht and incorporate a pin that interfaces with the indexing holes in the lower gridplate. Fittings will be mounted to the LEU material-bearing portion of the target by a welded triangular spider that allows coolant flow through the inner portion of the target. NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description Table 4-79. Target Design Parameters Parameter [Proprietary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] Nominal design value [Proprie tary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propriet ary Information] [Proprietary Information] [Proprietar y Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Propri etary Information] So urce: Docket Number 50-243 , "O r ego n State TRI GA Reactor License Amendment for Irr adiation of Fuel B earing Targets for Production ofMo l ybde num-99," Ap r il 20 1 2. LEU = low-enrich ed uraniu m. [Proprietary In for mati o n]. 4-244 NWMI ...... *

NOITKWEST MEDICAL ISOTOPlS NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF D escription 4.4.2.9.4 Special Nuclear Material Description Special Nuclear Material Inventory The SNM inventory in the target assembly subsystem will consist [Proprietary Information]. Table 4-80 li s ts the SNM inventory , which will be limited per workstation to the amount of LEU in one target. Table 4-80. Target Assembly Specia l Nuclear Material Inventory Location Form Target loading pr eparat i o n [Propr i etary Information]

workstation (TF-WT-800) Target loading workstation [Proprietary In formation] (TF-WT-810) Target we ldin g enclosure [Propri etary Information ] (TF-EN-820) Target weld finishing [Propri etary Information] workstation (TF-WT-820) Target weld in s pecti o n [Proprietary Informat i on] workstation (TF-WT-830) Target specification check [Proprietary Information] workstation (TF-WT-840) Tar get leak check workstation [Propri etary In forma ti on] (TF-WT-850) Target surface contamination (Proprietary Information] check workstation (TF-WT-860) Concentration a [P roprietary Inform ation] [Proprietary Information] [Propri e t ary Information] [Proprietary Information] [Propri etary lnform at i on] [Proprietary Information] [Pro pri e t ary lnformation] [Proprietary Information] -[Proprietary Information] [Proprietary Information] [P roprie t ary lnformation] [Proprietary Informati o n] [Propri etary I nformation] [Propri etary Inform at ion] [P ropr i e t ary In format i on] [Proprietary Information] SNM mass* [Proprietary lnformation] [Proprietary Information] [Prop ri etary Information] [Propriet ary Information] [Proprietary Inform at i on] [Proprietary Information] [Propri e t ary Inform a t ion] [Proprietary Information]

SNM co n ce ntr ation a nd m ass represent total amount of LEU (com b ined 235 U and 238 U at :'S 1 9.95 wt% 235 U). 235 U 238 u N I A ur ani um-235. uranium-238. n ot app li ca bl e. SNM = specia l nu c l ear material.

[Proprietary Inform ation] Criticality Control Feat u res Criticality control features are required in this s ub sys tem , as defined in NWMI-20 l 5-CSE-006. These features, consisting of passive desi gn features, a llow for adherence to the double-contin ge nc y principle. This section applies the criticality control features that are de sc ribed in Chapter 6.0, Section 6.3. The technical specifications required for criticality control will be developed for the Operatin g License Application and de scr ibed in Chapter 14.0. The criticality accident sequences are de sc ribed and analyzed in Chapter 13.0 , Section 13.2, where accident prevention mea s ure s and features are identified. The critical i ty control features for this subsystem are the pas sive design features, with a de s ignator of PDF , listed below. Chapter 6.0 provides detailed description s of the criticality control features. The passive design features will define the following requirements of the workstations:

Workstation s where LEU target material is handled , including the equipment on the workstations, remain in place durin g and following a facility DBE (CSE-06-PDFl). Spill-prevention lip s on the workstations do not exceed 2.54 cm (1 in.) (CSE-06-PDF2) 4-245

.... ; NWMI ...... ..* .. ... NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description

* *
NOKTKWEST MEDtCAl ISOTOPlS The administrative controls will define the following requirements for which containers should be used for specific activities, quantity limits of handling fissile material, and spacing requirement s: * *
Size limit of process apparatus holding target material (CSE-06-ACl and CSE-06-AC2)

Minimum spacing between movable containers and process equipment (CSE-06-AC3) Carrying limit of one fissile-bearing container per operator (CSE-06-AC4), limit of one container or target per workstation (CSE-06-AC6), and containers are closed or covered when unattended (CSE-06-ACS) Some or all of the engineered safety features and administrative controls are cl a ssified as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 13.2 p rovides a description of the IROFS. The following IROFS will be applicable to the tar ge t assembly act i vities. *

LEU target material is handled in approved containers and within the mass and ba tc h handling limits (IROFS CS-02). While movin g the [Propr ietary Information], minimum spacing between the container and other fissile material is managed administratively (IROFS CS-03). These measures:

(1) limit the operator to handle [Proprietary Information], (2) require use of approved workstat i ons with interaction control spacing from other fissile material , and (3) provide interaction guards at normall y accessible fissile solution process equipment. In addition to the features that apply the double-contingency principle, several features will provide defense-in-depth in criticality control. These features will include the following.

* *
Administrative batch limits are set based on worst-case moderation , even though u ranium is dry during normal conditions.

Administrative interaction contro l s are based on many evenly spaced u n its contribu t ing to the return of neutrons. Administrat iv e failures during handling between workstations generally involve only two containers. Criticality calculations analyzed concentrations , mass limits, and volumes that are not anticipated under normal conditions , so the controls can sustain multiple upsets. The criticality alarm system provides criticality monitoring and alarm in all areas where SNM is handled , processed , or stored , as described in Chapter 6.0. The criticality control features provided throughout the irradiated target receipt process will be in accordance with the double-contingency principle , and the RPF will provide suitable defense-in-depth for the contained processes. 4.4.2.9.5 Chemical Hazards Chemical hazards have not been identified during preliminary design for the target assembly subsystem. Assembled targets may require a solvent wash, which would be managed s imilar to the solvent in the [Proprietary Information] step. 4.4.2.10 Low-Enriched Uranium Storage Subsystem The LEU storage subsystem description provides information regarding the process , process equipment , SNM inventory, and the hazardous chemicals used in the subsystem. The process description (Section 4.4.2.10.1) identifies the normal operations and the basis for equipment design. The arrangement and design of the processing equipment, including normal operating conditions , are described in Sections 4.4.2.10.2 and 4.4.2.10.3. A description of the SNM in terms of ph ys ical and chemical form, volume in process , and criticality control features is provided in Section 4.4.2. l 0.4. 4-246

-NWMI ..*..... * * ' NCHnlfWHT MEOtcAl tsOTOltll NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description The hazardous chemicals that are used or may evolve during the process, along with the provisions to protect workers and the public from exposure , are described in Section 4.4.2.10.5. 4.4.2.10.1 Process Description The LEU storage will provide storage of fresh LEU, unirradiated target material, and welded targets. There will be no processes unique to the LEU storage subsystem.

Operations are described in Sections 4.4.2.1.5 and 4.4.2.9. 4.4.2.10.2 Process Equipment Arrangement The LEU storage equipment will be located within the [Proprietary Information]. Figure 4-121 shows the location of the process equipment. [Proprietary Information] Figure 4-121. Low-Enriched Uranium Storage Equipment Layout 4.4.2.10.3 Process Equipment Design [Proprietary Information] [Proprietary Information] 4-247 [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description [Proprietary Information] Figure 4-122. Low-Enriched Uranium Can Rack [Proprietary Information] Figure 4-123. 12-P o sition Target Cart 4-248 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description 4.4.2.10.4 Special Nuclear Material Description Special Nuclear Material Inventory [Proprietary Information] [Proprietary Information] Table 4-81. Low-Enriched Uranium Storage Maximum Special Nuclear Material Inventory Location Form Concentration a [Propri e t ary Information] [Propriet a ry In fo rmation] [Propriet ary Inform a tion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [P rop ri e t ary Inform a ti o n] [Pro p riet ary In fo rm a ti o n] [P ro pri e t ary In fo rm at i on] 1@111,,!j SNM mass a [Propri e t a ry [Propri e t ary I nform a ti o n] Information] [Proprietary [Proprietary Information] Information] [Propri e t ary [Propri e t ary In fo rm a ti o n] Inform a ti o n] a SNM concentrati o n and mass repre s ent total amount of L E U (combined m u and 23 8 U 19.95 wt% m u). [Proprietary Information] 2 35 u 23 8 u L EU N I A uranium-2 3 5. uranium-2 3 8. low-enrich e d uranium. not appli c able. Criticality Control Features SNM = s pecial nuclear mat e rial. U = uranium. [Propri e tary Informati o n] Criticality control features are required in this subsystem , as defined in NWMI-2015-CSE-007, N WMJ Pr e liminary Criti c ali ty Saf e ty Evaluation

Targ e t and Can Storag e and Cart s. These features, including passive design features and administrative controls , allow for adherence to the double-contingency principle. This section applies the critica l ity control features that are described in Chapter 6.0, Section 6.3. The technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0. The criticality accident sequences are described and anal y zed in Chapter 13.0 , Section 13.2 , where accident prevention measures and features are identified.

The criticality control features for this subsystem are the passive design features and administrative controls , with designators of PDF and AC , respectively, listed below. Chapter 6.0 provides detailed descriptions of the criticality control features. [Proprietary Information]

* [Proprietary Information]

[Proprietary Information] 4-249 NWMl-2015-02 1 , Rev. 3 Chapter 4.0 -RPF Description The following administrative controls define the requirements for which containers should be used for specific act i v iti es, quant i ty l imits of handling fissile material , and spac in g requirements

* *

Volume and mass limit s of target material containers (CSE-07-ACl , CSE-07-AC6) and fresh LEU metal containers (CSE-0 7-AC2, CSE-07-AC6)

Interaction limits between movable containers and process equipment (CSE-07-AC3) Carrying limit of one fissile-bearing container per operator (CSE-07-AC4), and containers will be closed or covered when unattended (CSE-07-ACS , CSE-07-AC7) Some or all of the engineered safety features and administrative controls are classified as IROFS according to the accident analyses in Chapter 13.0 , Section 13.2. Section 13.2 provides a description of the IROFS. The follow in g IROFS wi ll be applicable to the LEU storage activities.

* [Proprietary Information]

(2) require use of approved workstations with interaction control spaci n g from other fissile material , and (3) provide interaction guards at normall y accessib l e fissile solution process equipment. [Proprietary Information] In addition to the features that apply the double-contingency principle , severa l features will provide defense-in-depth in criticality control. These features will include: * * *

Administrative batch l imits are set based on worst-case moderation , even though uranium is dry during normal condi ti ons. Administrative interaction contro l s are based on many even l y spaced units contributing to the return of neutrons. Admini s trative failures during handling between workstations ge nerally involve onl y two containers.

Criticality calcu l ations ana l yze d concentrations , mass limits, and volumes that are not anticipated under normal condit ion s, so the controls can sustain multiple upsets. The criticality a l arm s ys tem provides critica lity monitoring and alarm in all area s where SNM is handled , processed , or stored, as d escribed in Chapter 6.0. The critica li ty control features provided throughout the irradiated target receipt process will be in accordance with the double-contin ge ncy principle , and the RPF will provide suitab l e defense-in-depth for the containe d proce sses. 4.4.2.10.5 Chemical Hazards C h emica l hazards ha ve not been identified, and are not anticipated, for the LEU storage subsystem. 4-250 NWMI ...*.. * '!' NORTHWEn MEDICAL ISOTOPf.S

4.5 REFERENCES

NWMl-2015-021 , Rev. 3 Chapter 4.0 -RPF Description 10 CFR 20, "Standards for Protection Against Radiation ," Code of Fed e ral R egu la tions, Office of the Federal Register , as amended. 10 CFR 50 , "Domestic Licensin g of Production and Utilization Faci litie s," Code of F ede ral Regulation s, Office of the Federal Register , as amended. 10 CFR 70, "Domestic Licensing of Special Nuclear Material ," Code of Federal Regulati o n s, Office of the Federal Register, as amended. 40 CFR 61, "National Emission Standards for Hazardous Air Pollutants ," Code of Fed e ral Regulations , Office of the Federal Register , as amended. 49 CFR 173, "Shippers -General Requirements for Shipments a nd Packages ," Code of F ede ral R egu lati o n s, Office of the Federal Register , as amended. ACI 349, Code R e quir e m e nts for N ucl e ar Saf ety-R e lat e d Concrete Structures, American Concrete Institute , Farmingto n Hills , Michigan , 2014. ANS 6.4-2006 , Nuclea r Analysis and D es ign of Co ncr e t e Radiation Shi e ldingf or Nuclear Pow er Plant s, American Nuclear Society , La Grange Park , Illinoi s, 2006. ANS l/AN S-6.4 , Nuclear Analysis and D es ign of Co ncr e t e Radiation Shielding for Nu cl ear Pow e r Plant s, American Nuclear Society, La Grange Park , Illinoi s, 2006. ANS l/AS ME 36.19M, Stainless Steel Pip e, American Society of Mechanic a l Engineers, 4th Editio n , New York, New York, 2015. ASCE 7, Minimum D es ign Load s fo r Building s and Oth e r Structures, American Society of Civil E ngineers , Reston , Virginia , 2013. ASTM C1233-09, Standard Pra ctice for D ete rmining EEC of N ucl e ar Materials, ASTM International, West Conshohocken, Penns y lvania , 2009. C-003-00 1456-00 7, "Poly HIC CRM Flat Bottom Liner," Re v. 3, EnergySolutions, Columbia , South Caro lina. Docket Number 50-243, "O re gon State TRIGA Reactor License Amendment for Irradiation of F u e l Bearing Targets for Production of Mol y bdenum-99 ," License Number R-106 , submitted by the Oregon State University Radiation Center , Oregon State University, Corva llis , Oregon , April 2012. [Propri e tary Information] INL/EX T-12-27075 , Iodin e Sorb e nt P er forman ce in FY 2012 D eep B ed T ests, Idaho National Laborator y, Idaho Falls , Idaho , 2012. [Proprietary Information] NUREG-1537, Guidelines for Pr epa ring and R ev i ew ing Applications for the Licensing of No n-Pow e r R e actor s -Format and Content, Part l, U.S. Nuclear Regulatory Commiss ion , Office of Nuclear Reactor Regulation, Washington , D.C., Feb ruar y 1996. NWMI-2013-049 , Pro cess S ystem Functional Specification, Rev. C, Northwest Medical I so topes , LLC , Corva lli s, Oregon, 2015. 4-251 .. *;;: .. NWMI ..... .......... ' * *

NORTHWEST MEDICAl tsOTOPU NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description NWMI-2013-CALC-002, Overall Summary Material Balan ce -OSU Target Batch, Rev. B, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015. NWMI-2013-CALC-006, Overall Summary Material Balan ce -MURR Target Batch, Rev. D, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015. NWMI-2013-CALC-009, Uranium Purification System Equipment Sizing, Rev. B, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015. NWMI-2013-CALC-Ol 1 , Source Term Ca l culations, Rev A, Northwest Medic a l Isotopes , LLC, Corvallis, Oregon, 2015. NWMI-2013-CALC-Ol 3, Irradi ated Target Dissolution System Equipment Sizing, Rev. B, Northwest Medical Isotopes, LLC, Corva llis, Oregon, 2015. NWMI-2014-CALC-014, Selection of Dominant Target I sotopes for NWMI Material Bal ances, Rev. A, Northwest Medical Isotopes , LLC, Corvallis, Oregon, 2014. NWMI-2015-CRITCALC-002, Irradiated Target Low-Enriched Ura nium Material Dissolution, Rev. A, Northwest Medical Isotope s, LLC, Corvallis, Ore gon, 20 15. NWMI-20 l 5-CRITCALC-006, Tank Hot Ce ll Tank, Rev. A, Northwest Medic a l Isotope s, LLC, Corvallis, Oregon, 2015. NWMI-2014-RPT-005, Uranium Recovery and Recycle Process Evaluation Decisions, Re v. 0 , Northwest Medical Isotopes, LLC, Corva llis , Oregon, 2014. NWMI-2015-CSE-001, NWM I Preliminary Criticality Safety Evaluation:

Irradiated Tar get Handling and Di sassemb l y, Rev. A, Northwest Medical Isotope s, LLC, Corvallis, Oregon, 2015. NWMI-2015-CSE-002, NWMI Preliminary Criticality Safety Eva luation: Irradiated Low-Enriched Ura nium Target Material Dissolution, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015. NWMI-20 I 5-CSE-003, NWMI Preliminary Criticality Safety Evaluation: Molybdenum 99 Product R ecovery, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015. NWMI-2015-CSE-004, NWMI Preliminary Criticality Safety Evaluation: Low-Enriched Ura nium Target Material Production, Re v. A, Northwe st Medical I soto pes , LLC, Corvallis, Ore gon, 2015. NWMI-2015-CSE-005, NWM I Preliminary Criticality Safety Eva luation: Target Fabricat io n Uranium Solution Processes, Rev. A, Northwest Medical Isotope s, LLC, Corvallis, Ore gon, 2015. NWMI-2015-CSE-006, NWMI Preliminary Criticality Safety Evaluation: Target Finishing, Rev. A, Northwest Medical Isotope s, LLC, Corvallis, Oregon, 2015. NWMI-2015-CSE-007, NWMI Preliminary Criticality Safety Evaluation: Target and Can Storage and Ca rts, Rev. A, Northwest Medical Isotopes , LLC , Corvallis, Oregon, 2015. NWMI-2015-CSE-008, NWM I Preliminary Criticality Safety Eva luation: Hot Ce ll Uranium Purifi cation, Rev. A, Northwest Medical Isotopes , LLC, Corvallis, Oregon, 2015. NWMI-2015-CSE-009, NWMI Preliminary Criticality Safety Evaluation

Liqu i d Waste Processing, Rev. A, Northwest Medical Isotopes , LLC, Corvallis, Oregon, 2015. NWMI-2015-RPT-007, Process Time-Cycle Analysis R eport (Part 50 License), Rev. 0 , Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015. NWMI-2015-SHIELD-001, Rad ioiso top e Production Facility Shielding Analy s is , Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon , 2 015. 4-252 NWMl-2015-021 , Re v. 3 Chapter 4.0 -RPF Description ORNL-53 00 , R esin-Ba sed Preparation of HGTR Fue l s: Operation of an Engineering-Scale Uranium Loading System, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 1977. ORNL/TM-55 1 8, Design and Test of a Th e rmo sip hon Evaporator fo r Acid-Deficient Uranyl Nitrate, Oak Ridge National Laboratory, Oak Ridge , Ten n essee, November 1976. ORNL/T M-6607 , A literature Survey of Methods to R e mov e I od in e from Offgas Streams Us ing Solid Sorbents , Oak Ridge National Laboratory , 1979. OSTR-M0-100, "Mo lybdenum Production Project ," Ore go n State University , Corvallis , Oregon, 2013. Regulatory Guide 1.69, Concrete Radiation Shields and Generic Shie l d Testing for Nuclear Pow er Plants, Re v. 1, U.S. Nuclear Regulatory Commission, Washington , D.C., Ma y 2009. 4-253

.; ... ;. NWMI ..**.. ..* .. .*.* .. *.*.* . ' *. * : HOfllfWEST MfOICAl. lSOTOf'(I This page intentionally left blank. 4-254 NWMl-2015-021, Rev. 3 Chapter 4.0 -RPF Description}}

ML18025B160: Difference between revisions

Revision as of 08:09, 18 October 2018

Contents

Text

4.0 RADIOISOTOPE

4.1.1 Radioisotope

4.1.2 Process

4.1.3 Process

4.2 RADIOISOTOPE

4.2.3 Methods

4.2.4 Calculated

4.2.5 Ventilation

4.3 RADIOISOTOPE

4.3.2 Irradiated

4.3.3 Target

4.3.4 Irradiated

4.3.5 Molybdenum

4.4 SPECIAL

4.4.2 Processing

4.5 REFERENCES

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ML18025B160: Difference between revisions

Revision as of 08:09, 18 October 2018

Text

4.0 RADIOISOTOPE

4.1.1 Radioisotope

4.1.2 Process

4.1.3 Process

4.2 RADIOISOTOPE

4.2.3 Methods

4.2.4 Calculated

4.2.5 Ventilation

4.3 RADIOISOTOPE

4.3.2 Irradiated

4.3.3 Target

4.3.4 Irradiated

4.3.5 Molybdenum

4.4 SPECIAL

4.4.2 Processing

4.5 REFERENCES

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