ML17158B270

Northwest Medical Isotopes, LLC - NWMl-2015-021, Rev. 1, Chapter 4.0 - Radioisotope Production Facility Description - Construction Permit Application.

ML17158B270
Person / Time
Site:	Northwest Medical Isotopes
Issue date:	05/31/2017
From:	Northwest Medical Isotopes
To:	Office of Nuclear Reactor Regulation
References
NWMI-LTR-2017-005 NWMl-2015-021, Rev 1
Download: ML17158B270 (274)

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. NORTHWEST MEDICAL ISOTOPES Chapter 4.0 - Radioisotope Production Facility Description Construction Permit Application for Radioisotope Production Facility NWMl-2015-021, Rev. 1 May 2017 Prepared by:

Northwest Medical Isotopes, LLC 815 NW gth Ave, Suite 256 Corvallis, Oregon 97330

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• HOmfWEITMEDtcALISOTOPES NWMl-2015-021 , Rev. 1 Chapter 4 .0 - RPF Description Chapter 4.0 - Radioisotope Production Facility Description Construction Permit Application for Radioisotope Production Facility NWMl-2013-021, Rev. 1 Date Published:

May19, 2017 Document Number: NWMl-2013-021 I Revision Number. 1

Title:

Chapter 4.0 - Radioisotope Production Facility Description Construction Permit Application for Radioisotope Production Facility Approved by: Carolyn Haass Signature:

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' ~ *.* !' : NOflJTHWESTMEDtCAllSOTOf"ES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description REVISION HISTORY Rev Date Reason for Revision Revised By 0 6/29/2015 Initial Application Not required Incorporate changes based on responses to 1 5/19/17 C. Haass NRC Requests for Additional Information

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• ~ ~.* ~ * . NDl'THWUT MmtCAL ISOTOPtl NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description CONTENTS 4.0 RADIOISOTOPE PRODUCTION FACILITY DESCRIPTION ................................ .................. 4-1 4.1 Facility and Process Description ................................................................ ...... .................. 4-2 4.1.1 Radioisotope Production Facility Summary ....................... .......... ....................... 4-2 4 .1.2 Process Summary .......................................... .... .... .. .... .. ................ ....................... 4-7 4.1.2. 1 Process Design Basis .......................................................................... .4-8

4. 1.2.2 Summary of Reagent, Product and Waste Streams .. ... .... ..... ............. 4-10 4.1.2 .3 Radioisotope Production Facility Spent Nuclear Material Inventory ................ ..... ..... ........................................................ ..... .... 4-11

4. 1.2.4 Radioisotope Production Facility Anticipated Maximum Radionuclide Inventory .......................................... .... .. ... ..... ...... ....... 4-13 4.1.3 Process Overview .... ................ ..... ..... ..... ........ ...... ...... ... ... ... .... ... .... ....... ... ...... .... 4-15 4.1.3.1 Target Fabrication ............ .. ...... .... .. .................................................. .4-15 4.1.3.2 Target Receipt and Disassembly ...................................................... .4-19 4.1.3.3 Target Dissolution .. ...... .. .................................................................. .4-21 4.1.3.4 Molybdenum Recovery and Purification .................................. .. ..... .4-23 4.1.3 .5 Uranium Recovery and Recycle .... ... ...... .... .... ... ......... ...................... .4-25 4.1.3.6 Waste Handling ......... .. ... ...... ........ .... ... ...... ... ... .. ... ... ..... ..................... 4-27 4.1.4 Facility Description .......... .............................. ... ... ... ................. ..... ..... ................ 4-31 4.1.4.1 General Construction .. ...................................................................... 4-32 4.1.4.2 Site and Facility Access ......................... ...................... ........ .. ........... 4-34 4.1.4.3 Facility Ventilation ................. ..... .... ...... .... ............... .. .... ... ... .... .. .... .. . 4-34 4.1.4.4 Target Fabrication Area ................................................. .................. .4-35 4.1.4.5 Irradiated Target Receipt Area .. .......................................... .. ............ 4-37 4.1.4.6 Hot Cell Area .................................................................................... 4-3 8 4.1.4.7 Waste Management Area ........ ........ ...... .... .. .. ................ .. .................. 4-42 4.1.4.8 Laboratory Area ................ ..... ........... ...... ................. ... ...................... 4-46 4.1.4.9 Chemical Makeup Room ........ ... ....................................................... .4-47

4. 1.4.10 Utility Area .... .... ......................................................................... ....... 4-4 7

4. 1.4.11 Administration and Support Area ................ .......... ...... ..... ...... .. ........ 4-51 4.2 Radioisotope Production Facility Biological Shield .............. ..... ............. ... .....................4-53 4.2.1 Introduction ........................................ ............. .... .. ... ....................................... ... 4-53 4.2. l. 1 Biological Shield Functions ........... .. .......... .............. ...... ........ .......... . 4-53 4.2.1.2 Physical Layout of Biological Shield .... ............................... .. ..... ..... .4-53 4.2.2 Shielding Design ......... ............. ....... .. ................................................................. 4-55 4.2 .2. 1 Shielding Materials of Construction .. ............ ..... ... ... ....................... .4-56 4.2.2.2 Structural Integrity of Shielding .............................. ................ ...... .... 4-56 4.2.2.3 Design of Penetrations ......... .. ... .. ...... ......... ... ............................. ....... 4-57 4.2.2.4 Design of Material Entry and Exit Ports .......................................... .4-57 4.2.2.5 Design of Operator Interfaces ................... .............. ......................... .4-59 4.2 .2.6 Design of Other Interfaces .... ...... ........ .... .. ........................................ 4-59 4.2 .3 Methods and 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 Dose Rates .................................................. 4-63 4.2.3.4 Geometries ............................. ... .......... .............. ........... ..... ................ 4-64 4-i

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• ~ * .* ~ ' NORTifWHT MEDICAL ISOTOf'tl NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.2 .3.5 Estimated Hot Cell Wall Thickness .. ...... ..... ... ................ ..... .. .. ........ .4-70 4.2.3 .6 Estimated Minimum Hot Cell Window Thickness .. ..... ... ... ... ..... ...... 4-73 4.2.4 Calculated Dose Equivalent Rates and Shield Thickness Requirements ....... .... 4-73 4.2.5 Ventilation Systems for the Biological Shield Structure .......... .. ... ............. ...... .4-73 4.3 Radioisotope Extraction System ... ... .. ... ................ ....... .... ........ .. ........... ... ..... ... ........ ........ . 4-74 4.3 .1 Extraction Time Cycle .. ..... ... ..... ..................................................... .. .... .... ......... 4-74 4.3.2 Irradiated Target Receipt. ...... .. ..... .... .............. ............... ........ ... ........ ... .. .... .. .. ..... 4-75 4.3.2.1 Design Basis ...... ...... ... .. ......... .. .... ... ....... .... .... ........ ... .... .......... .. .. ....... 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 Process Equipment Arrangement ........ ........ .... .... ........ .... .. ..... ...... .. ... 4-88 4.3 .3.3 Process Equipment Design ...... ....... .. ... ... ..... ..... .. .... .. .... ... .................. 4-89 4.3.3.4 Special Nuclear 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 Equipment Design .............................................. .... .... ........ 4-105 4.3.4.4 Special Nuclear Material 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 Description .. ..... ................. ... .. ........... .... .4-133 4.3.5.5 Radiological Hazards ......... ......... .. ... .... .......... ............. ... ..... .... .. ..... . 4-136 4.3.5.6 Chemical Hazards ........... ..... .... ........ ......... ..... ............ ..... ..... .... .. .. ... 4-141 4.4 Special Nuclear Material Processing 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 Design .................... ... .. ... ......... ........... ... ....... ... .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 4.4.2 Processing ofUnirradiated 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 Waste Subsystem .. ..... .... ... ........ ...... ... .............. .4-232 4-ii

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, *. ~ ~.~~ ." . NOUKWHTMEDtCAllSOTOPU 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

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~ ~.* ! * - NORJHWESTMEOICALISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description FIGURES Figure 4-1. Radioisotope Production Facility Site Layout ................................................................. 4-2 Figure 4-2. Building Model of the Radioisotope Production Facility ........ ....................................... .4-3 Figure 4-3. General Layout of the Radioisotope Production Facility ................ ............................ .... .4-4 Figure 4-4. Preliminary Layout of the Radioisotope Production Facility First Level Floor Plan and Associated Dimensions ..................................................................................... 4-5 Figure 4-5. Preliminary Layout of the Radioisotope Production Facility Second Level Floor Plan ..... ..... ..... ... ......... ................ .... .. ................................ ... .. ..... .. ............. .... ..... ........... .... 4-6 Figure 4-6. Radioisotope Production Facility Hot Cell Details ........................... ......... ...... ...... ...... .... 4-6 Figure 4-7. Radioisotope Production Facility Block Flow Diagram ...... .. ...... ................. ................. .. 4-7 Figure 4-8 . Reagents, Product, and Waste Summary Flow Diagram .......................... .. ......... ........ .. 4-10 Figure 4-9. Radioisotope Processing Facility at 0 to 40 Hours End of Irradiation ............ .. ........ .... .4-14 Figure 4-10. Radioisotope Processing Facility at Greater than 40 Hours End oflrradiation ........ .... .4-14 Figure 4-11 . Target Fabrication Block Flow Diagram .. .. .......... .... ................... .................................. 4-16 Figure 4-12 . Target Assembly Diagram ............................................................................................. 4-17 Figure 4-13 . Target Fabrication Location ................... ........... ... .. ... ...................... ... ....... ........... ........ .. 4-18 Figure 4-14. Target Receipt and Disassembly System Flow Diagram .. .. .... .. .......................... .......... .4-19 Figure 4-15. Target Receipt and Disassembly System Facility Location ......... ............................. .... .4-20 Figure 4-16. Simplified Target Dissolution Process Flow Diagram ............................. ............ ........ .4-21 Figure 4-17 . Target Dissolution System Facility Location .... ............................................................ 4-22 Figure 4-18. Simplified Molybdenum Recovery and Purification Process Flow Diagram ................ 4-23 Figure 4-19. Molybdenum Recovery and Purification System Facility Location ......... .. ................... 4-24 Figure 4-20. Simplified Uranium Recovery and Recycle Process Flow Diagram ............................. 4-25 Figure 4-21. Uranium Recovery and Recycle System Location ................................ .. .......... ............ 4-26 Figure 4-22 . High-Dose Liquid Waste Disposition Process ............................................................... 4-28 Figure 4-23. Low-Dose Liquid Waste Disposition Process ........................................ .... .. ......... ...... .. 4-28 Figure 4-24. Waste Handling Locations ...... .. .. ... ....... ............................... .. ... .. ............. ........... ........... 4-29 Figure 4-25. Low-Dose Liquid Waste Evaporation Facility Location .... ..... ...................................... 4-30 Figure 4-26. Radioisotope Production Facility Areas ....................................................................... .4-31 Figure 4-27. Target Fabrication Area Layout ..................................................................................... 4-35 Figure 4-28 . Irradiated Target Receipt Area Layout .. ............................................................ ............ 4-37 Figure 4-29. Hot Cell Area Layout ..................................................................................................... 4-39 Figure 4-30. High-Integrity Container Storage and Decay Cells Layout ........................................... 4-42 Figure 4-31 . Waste Management Loading Bay and Area Layout ...................................................... 4-43 Figure 4-32. Waste Management Area - Ground Floor ..................................................................... 4-43 Figure 4-33. Waste Management Area - Low-Dose Waste Solidification Location .. ..................... .. 4-44 Figure 4-34. Laboratory Area Layout. .... .... ........................ ............. ........... ..... ............... .. ... ... ............ 4-46 Figure 4-35 . First Floor Utility Area .......... ..... .... .......... .. ..... ... ...... ... .... ......... ......... ................. ........... 4-48 Figure 4-36. Second Floor Mechanical and Electrical Room ........ .. .................................. .. .... ........... 4-48 Figure 4-37. Second Floor Mechanical Area .. ................. .... .. ................................. ...... .............. .... .... 4-48 Figure 4-38. Administration and Support Area Layout.. ................................................. .......... ......... 4-51 4-iv

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• . ! : . NORTHWHT MEDICAL ISOTOPES Chapter 4.0 - RPF Description Figure 4-39. Facility Location of Biological Shield ........... ........... .. ..... ... ...... ... .................................. 4-54 Figure 4-40. Hot Cell Arrangement ................................ ........ ...... ...... ..... ...... .......... ... .... ....... ............. 4-55 Figure 4-41. Hot Cell Target Transfer Port ........ ..................................... ......... .................. ............... .4-57 Figure 4-42. Waste Shipping Transfer Port .... ........................... .................. ... ..... ........ ....... ..... ... ... ..... 4-58 Figure 4-43. Manipulators and Shield Windows .................... ................. ... .............. ... ....... ........ ... ..... 4-59 Figure 4-44. Cover Block Configuration ... ..... .... ....... ... ............... ....... ... .. ..... .... ... ............................... 4-60 Figure 4-45 . Dose Equivalent Rate from an Irradiated Target as a Function of Time ....... ................ 4-68 Figure 4-46. Dose Equivalent Rate Variation through Base Case 120 Centimeter (4-Foot)

Composite Wall ......................... .. ..... ............................................................................. 4-71 Figure 4-47 . Extraction Time Cycle ............ ................. .... ..... ..... ........................................ ...... .... .. .. .. 4-74 Figure 4-48. Cask Receipt Subsystem Flow Diagram .................... .... .. .............. ...... .................. .... ... .4-76 Figure 4-49. Irradiated Target Handling Equipment Arrangement Plan View .. ... ..... ... .................... .4-76 Figure 4-50. Irradiated Target Handling Equipment Arrangement Isometric View ......................... .4-77 Figure 4-51. Cask Preparation Airlock ................. ....... ........... ........................................................... . 4-79 Figure 4-52. Cask Preparation Airlock Equipment Arrangement ..... .. ...... ............................. ............ 4-79 Figure 4-53 . Target Receipt Hot Cell Equipment Arrangement ............................... ... .. .................... .4-80 Figure 4-54. Target Receipt In-Process Radionuclide Inventory Streams .......... .... .... .. ... ...... ........... .4-83 Figure 4-55. Target Disassembly Hot Cells Equipment Arrangement.. ...... ... ... ....... ... ........ ............... 4-88 Figure 4-56. Target Disassembly In-Process Radionuclide Inventory Streams ... ... .. .... ... ......... ......... 4-91 Figure 4-57 . Simplified Target Dissolution Flow Diagram ............... ........ ... .............. ... ............. ....... .4-97 Figure 4-58. Dissolver Hot Cell Locations ................ ............ ........ .... ........ ....... ...... .. ........ ................ 4-102 Figure 4-59. Dissolver Hot Cell Equipment Arrangement (Typical of Dissolver I Hot Cell and Dissolver 2 Hot Cell) ............. ..... ...... ............... ...... ... ... ... ........... ............... ................... 4-103 Figure 4-60. Target Dissolution System Tank Hot Cell Equipment Arrangement ... ...................... .4-104 Figure 4-61. Target Dissolution System Mezzanine Equipment Arrangement.. ......................... .... .4-105 Figure 4-62. Target Dissolution In-Process Radionuclide Inventory Streams ............................... ..4-l l 0 Figure 4-63. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory Streams ... ... ............ .. .4-115 Figure 4-64. Fission Gas Treatment In-Process Radionuclide Inventory Streams ......................... ..4-118 Figure 4-65. Simplified Molybdenum Recovery and Purification Process Flow Diagram ........ ... .. .4-123 Figure 4-66. Molybdenum Product Hot Cell Equipment Arrangement ....... ........ ........... ................ .4-127 Figure 4-67. Molybdenum Recovery Hot Cell Equipment Arrangement ....... .. ... .. ..... ..................... 4-128 Figure 4-68. Molybdenum Purification Hot Cell Equipment Arrangement.. ................................... 4-129 Figure 4-69. Product and Sample Hot Cell Equipment Arrangement ......... ..... ... ............... ............. .4-130 Figure 4-70. Molybdenum Feed Tank Hot Cell Equipment Arrangement.. ............. ....................... .4-131 Figure 4-71. Molybdenum Recovery and Purification In-Process Radionuclide Inventory Streams ........................... ........................... ..... ......................... ..... .. .... ... ..... .................. 4-136 Figure 4-72. Uranium Recovery and Recycle Process Functions ...................... .... ...... .. ... ...... .. ... ... .4-143 Figure 4-73. Uranium Recovery and Recycle Overview ... ... ........ .. .................................... ....... .. ... .. 4-144 Figure 4-74. Simplified Uranium Recovery and Recycle Process Flow Diagram ........... .. ............. .4-146 Figure 4-75. Condensate Tank #1 Configuration Concept.. ...... ... .................... .................. .............. 4-150 Figure 4-76. Tank Hot Cell Equipment Arrangement.. .... ................... .............. .... ............... .. ......... .4-156 Figure 4-77. Alternative Pencil Tank Diameters for Equipment Sizing .......................................... . 4-157 4-v

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• NORTHW£St MEDICAL ISOTOPES Figure 4-78. Conceptual Ion Exchange Column for Uranium Purification ...................................... 4-158 Figure 4-79. Conceptual Uranium Concentrator Vessel ... .. .... ..... ........... ........... ............... ......... ....... 4-15 8 Figure 4-80. Impure Uranium Collection Tanks In-Process Radionuclide Inventory Streams ........ 4-166 Figure 4-81 . Uranium Recovery and Recycle In-Process Radionuclide Inventory Streams ...... ...... 4-170 Figure 4-82 . Key Subsystem Interfaces within Target Fabrication ...... .......... ... .. ... .... ...... ................ 4-176 Figure 4-83 . New Target Handling Flow Diagram .......................................................................... 4-181 Figure 4-84. ES-3100 Shipping Container .. ..... ..... ...... .... ..... .... ... .... ..... .. ..... ...... .. ........... .. ... .... ......... 4-182 Figure 4-85. Fresh Low-Enriched Uranium Handling and New Target Handling Equipment Arrangement ............. ....................................... ......... .. ......... ... ... ........ .. ........................ 4-183 Figure 4-86. Fresh Uranium Dissolution Process Flow Diagram ............ .. .. .............. ................ .... .. .4-184 Figure 4-87. Fresh Uranium Dissolution Equipment Arrangement ................................................ .4-185 Figure 4-88. Dissolution Equipment Layout ................. .. ............ ................ ..... ................................ 4-186 Figure 4-89. Nitrate Extraction Process Flow Diagram .... .. .. ...... .. ............ .... .. ........ ................. ...... .. 4-191 Figure 4-90. Nitrate Extraction Equipment Layout ................................ ........ .. ........ .................. .... .. 4-194 Figure 4-91. Uranyl Nitrate Storage Tank Arrangement.. ................................................................ 4-195 Figure 4-92. Nitrate Extraction Equipment Arrangement ................................................................ 4-196 Figure 4-93 . Acid-Deficient Uranyl Nitrate Concentration Process Flow Diagram .............. .......... 4-201 Figure 4-94. Acid-Deficient Uranyl Nitrate Concentration Equipment Layout.. .. .......................... . 4-202 Figure 4-95 . Acid-Deficient Uranyl Nitrate Concentration Feed Equipment Arrangement ............ 4-203 Figure 4-96. Acid-Deficient Uranyl Nitrate Concentration Equipment Arrangement ........ .... ...... .. .4-203 Figure 4-97. Sol-Gel Column Feed Process Flow Diagram .......... .. ............................................... .. 4-208 Figure 4-98. Sol-Gel Column Feed Equipment Layout.. .................................................................. 4-209 Figure 4-99. Concentrated Acid-Deficient Uranyl Nitrate Storage Equipment Arrangement ......... 4-210 Figure 4-100. Sol-Gel Column Feed Equipment Arrangement.. ........................................................ 4-210 Figure 4-101. [Proprietary Information]Flow Diagram ..... ................................................ ... ... ... ........ 4-215 Figure 4-102. [Proprietary Information] Layout ..... ..... .... .......... .. ..... ...... ........ ... ...... .. ..... ............ ....... 4-216 Figure 4-103. [Proprietary Information] Arrangement. .... ... .... ... .. ......... ... ..... .. .... .................... ........... 4-217 Figure 4-104. [Proprietary Information] Flow Diagram .... .... .. ....... ..... .. ... .. ..... .... .. ... ....... ... ...... .......... 4-221 Figure 4-105 . [Proprietary Information] Layout .. ... .. ... .... ... .... ... ....... .. ......... ... ... .. .... .. ... .. ................... 4-225 Figure 4-106. [Proprietary Information] Arrangement .............. ... ...... ... ........ .. .... ............. ............ ...... 4-225 Figure 4-107. [Proprietary Information] Arrangement.. ............................................................. ........ 4-226 Figure 4-108. [Proprietary Information] Layout ........... ......... .... .... .... ..... ..... ... ...... .. .. ...... ..... .. ............ 4-226 Figure 4-109. [Proprietary Information] Arrangement ....................................................................... 4-227 Figure 4-110. Target Fabrication Waste Process Flow Diagram ................................ ......... ............... 4-233 Figure 4-111. Target Fabrication Waste Equipment Layout .............. ....... ...... ............... .. .......... ....... .4-234 Figure 4-112 . Aqueous Waste Holding Tank ..................................................................................... 4-235 Figure 4-113 . Trichloroethylene Recovery Skid Arrangement .......................................................... 4-235 Figure 4-114. Target Loading Preparation and Target Loading Workstation ................................... .4-239 Figure 4-115. Target Welding Enclosure ........................................................................................... 4-240 Figure 4-116. Target Weld Finishing Workstation ....... ...... ......................... .................. ...... .. .... ......... 4-240 Figure 4-117. Target Weld Inspection Station and Target Weight Inspection Equipment ............... .4-241 4-vi

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' ~ ~.* ! . NORTlfWUT MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Figure 4-118. Target Disassembly Workstation ................................................................................. 4-242 Figure 4-119. Target Assembly Equipment Layout ...... ............ .......... .. .......... .. ................................ .4-242 Figure 4-120. Target Assembly Diagram (Doc-No 50-243) .............................................................. 4-243 Figure 4-121. Low-Enriched Uranium Storage Equipment Layout .. .... .. .... .. .... .............. .... .... .......... .4-247 Figure 4-122 . Low-Enriched Uranium Can Rack .... .. ... ..... .. ...... .. ... .... ............. ..... ..... ...... .... ... ...... ...... 4-248 Figure 4-123. 12-Position Target Cart ................................................................................................ 4-248 TABLES Table 4-1. Special Nuclear Material Inventory of Target Fabrication Area .................................. .4-11 Table 4-2. Special Nuclear Material Inventory of Irradiated Material Areas ................................ .4-12 Table 4-3. Radionuclide Inventory for Radioisotope Production Facility Process Streams .......... .4-13 Table 4-4. Radioisotope Production Facility Area Crosswalk ............................ .... .................. .. .... 4-32 Table 4-5. Facility Areas and Respective Confinement Zones .... ........ ............................ .............. .4-34 Table 4-6. Target Fabrication Area Room Descriptions and Functions (2 pages) .......................... 4-35 Table 4-7 . Irradiated Target Receipt Area Room Descriptions and Functions ............................... 4-37 Table 4-8. Hot Cell Area Room Descriptions and Functions (2 pages) .......................................... 4-39 Table 4-9. Waste Management Room Descriptions and Functions ................................................ 4-44 Table 4-10. Laboratory Area Room Descriptions and Functions ...................................................... 4-46 Table 4-11. Utility Area Room Descriptions and Functions ...... .......... ............ ...... .......................... .4-49 Table 4-12. Administration and Support Area Room Descriptions and Functions .......... ................. 4-52 Table 4-13. Master Material List. ...................................................................................................... 4-62 Table 4-14. Target Model Materials ................................................................................................. 4-64 Table 4-15 Pencil Tank Model Data ... ............ .... ..... ...... ......... .. ............ .. ....... .... .... .. ........ ................ 4-65 Table 4-16 Carbon Bed Model Geometric Parameters ........................... .. .......... .......... .................. .4-65 Table 4-17 . Waste Container Geometric Data .................................................................................. 4-65 Table 4-18 . Material Assignment for Steel/Concrete Composite Wall Model ................................ .4-66 Table 4-19 . Dose Equivalent Rate from an Irradiated Target as a Function of Time at Various Distances in Air .. ... ..... ...... ........................ ....... .. ......... ... .... ......... .... .. .. .... ........... ... ..... .... 4-67 Table 4-20. Target Fabrication Incoming Process Stream Dose Rates ............................................. 4-69 Table 4-21. Carbon Bed Model Dose Rate Results .... .. ................... .. .. .................... .... .............. .. ...... 4-69 Table 4-22. High-Dose Waste Container Bounding Dose Equivalent Rates .................................... 4-70 Table 4-23 . Estimation of Coefficient .A.2 ......................................................................................... 4-72 Table 4-24. Required Steel Thickness in Composite Wall for Various Total Wall Thicknesses ..... .4-72 Table 4-25 . Exterior Dose Rates for 120 Centimeter (4-Feet) Total Wall Thickness and Various Steel Thicknesses ....................... .. ........ .. .... ... ........ ................... .. ..... .............. ... 4-72 Table 4-26. Estimated Dose Equivalent Rates on the Outside of the Hot Cell Window ............. .... .4-73 Table 4-27 . Radioisotope Extraction Systems .................................................................................. 4-74 Table 4-28 . Irradiated Target Receipt Auxiliary Equipment... ......................................................... .4-80 Table 4-29. Irradiated Target Receipt In-Process Special Nuclear Material Inventory .................... 4-81 Table 4-30. Irradiated Target Receipt Radionuclide In-Process Inventory (3 pages) ............. .......... 4-83 4-vii

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' ! *.* ! ' HORTHWHT MEDICAl ISOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-31. Target Disassembly Auxiliary Equipment .... ............... ........ ..... ....... ..... .... .. .. ... .. ....... .... . 4-89 Table 4-32 . Individual Irradiated Target Disassembly Hot Cell In-Process Special Nuclear Material Inventory ....... ..... ....... .. ... ......... .... ... ............. .... ... ..... ..... ... ....... .... .... .. ...... ..... .... 4-89 Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages) .... ....... ... ... .. .... ... .... .4-92 Table 4-34. Irradiated Target Dissolution Process Equipment ...... ...... ..... ..... .. ......... .. ... .... ...... .... ...4-106 Table 4-35. Target Dissolution Auxiliary Equipment ...... ..... ....... ......... .......... ...... .......... ... ... ... ..... .. 4-107 Table 4-36. Individual Target Dissolution Hot Cell In-Process Special Nuclear Material Inventory ... .. ....... ... ... .. ..... ....... .... .. ..... ...... ..... ............ ..... ..... ... ... .... ..... ... .... .... ... ... .. .. ... ... 4-108 Table 4-37 . Target Dissolution In-Process Radionuclide Inventory (4 pages) .. ..... .......... ... ... .. ..... .4-111 Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages) ..... ... ......... ..4-115 Table 4-39. Fission Gas Treatment In-Process Radionuclide Inventory (3 pages) .... ...... ... ... ...... ...4-119 Table 4-40. Chemical Inventory for the Target Dissolution Area ..... ....... .......... ...... ... .. .. .... .... ..... ...4-121 Table 4-41. Typical Ion Exchange Column Cycle .... ...... ....... .... .. .. ... ... ......... ............ ..................... .4-124 Table 4-42 . Strong Basic Anion Exchange Column Cycle ........ ..... ....... ... ...... ... ...... .... ........ .... ....... 4-125 Table 4-43. Purified Molybdenum Product Specification ..... .............. .... ... ... ........ ... .. .... ... ............. . 4-126 Table 4-44. Molybdenum Recovery and Purification Process Equipment .... .... ... .. .... ... .. ... ............ 4-132 Table 4-45 . Molybdenum Recovery and Purification Auxiliary Equipment ... .... .... .... .... ..... ......... .4-132 Table 4-46. Molybdenum Recovery and Purification System In-Process Special Nuclear Material Inventory ... ... ... ......... ..... .. ..... ....... .... ... ..... ..... ... ... ..... ... .. ... .. ........ ........ ... ... ... .. . 4-134 Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages) ...... ...... ... .... .... ...... .... ..... .. ... .. .......... ...... .......... ..... .. .... .... .... ... ... .... .... ...... .... .. .. . 4-137 Table 4-48. Chemical Inventory for the Molybdenum Recovery and Purification Area .. ....... ..... ..4-142 Table 4-49. First-Cycle Uranium Recovery Ion Exchange Column Cycle Summary ............. ... ... . 4-148 Table 4-50. Uranium Recovery and Recycle Process Equipment (2 pages) ..... ....... ..... ... ... .... .... ... .4-159 Table 4-51 . Uranium Recovery and Recycle In-Process Special Nuclear Material Inventory (2 pages) .... ... ..... ........... ............... .. ...... ... .... ....................... ... ... ...... ...... ..... ... ... ... .... ... .... 4-161 Table 4-52 . Impure Uranium Collection Tanks In-Process Radionuclide Inventory (4 pages) ... .. .4-166 Table 4-53. Uranium Recovery and Recycle In-Process Radionuclide Inventory (4 pages) ......... .4-170 Table 4-54. Uranium Recovery and Recycle Chemical Inventory ........ .. ... ..... ..... ........... .... ... ... ... ...4-175 Table 4-55. Target Fabrication Subsystems .... ... .. .. ...... ...... .......................... ... ... .. .... ..... ... ... .... .. ... ... 4-176 Table 4-56. Fresh Uranium Metal Specification (3 pages) .. ......... ....... ...... ... ... .......... .... .. ... ..... .. .....4-177 Table 4-57. Low-Enriched Uranium Target Physical Properties .. .. ...... ..... .... .............. ..... ........ ..... .4-180 Table 4-58. Fresh Uranium Dissolution Process Equipment ... ..... ..... .. .. ..... ... ............... .. ............... .4-186 Table 4-59. Fresh Uranium Dissolution Design Basis Special Nuclear Material Inventory .. ......... 4-187 Table 4-60. Fresh Uranium Dissolution Chemical Inventory .... ......... ..... ... ...... ... ..... ... ... ... .... .. .. ... ..4-190 Table 4-61. Recycled Uranium Specification (2 pages) .. .... ....... ......... .. .... ...... ............ .. ...... ............ 4-192 Table 4-62. Nitrate Extraction Process Equipment ..... ......... ........ ... ...... ... ... ..... .. ... .... ... .. ... ...... ........ 4-197 Table 4-63. Nitrate Extraction Special Nuclear Material Inventory .................. ... .......... .. .. .......... ..4-198 Table 4-64. Nitrate Extraction Chemical Inventory ..... ... ..... ........ ...... .. .. ......... ........ .. .. ... .. ... ... .... ..... 4-200 Table 4-65. Acid Deficient Uranyl Nitrate Concentration Process Equipment ... ... ....... ... .... .. ....... .4-204 Table 4-66. Acid-Deficient Uranyl Nitrate Concentration Maximum Special Nuclear Material Inventory ..... .... ............ .. ..... ......... ..... ...... ...... ...... ... .. ....... .. ......... ... .. .. ... .......... ..... .. ........ 4-205 4-viii

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. * ~ ~. *! . . NOmfWln MtDtCAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-67. [Proprietary Information] Process Equipment ........ .. .. .... ...................... .. .................... .4-211 Table 4-68. [Proprietary Information] Special Nuclear Material Inventory ...... ............................ .4-21 2 Table 4-69 . Chemical Inventory for the Sol-Gel Column Feed Subsystem .. .... .. ...... .. .. .. .... .. .. .. .. .. .. 4-2 13 Table 4-70. [Proprietary Information] ......... ............ ........... ..... ...... ..... .......... ............ .. .. ...... ......... .... ...... 4-2 18 Table 4-71 . [Proprietary Information] Subsystem ...... .. ...... .... .. ... .......... ........ ... .... ... ... .. ....... .. ........ .4-220 Table 4-72 . [Proprietary Information] .. ........ .............. .... ..... ... .. ....... ............... .. ... .... ............... .. ....... 4-224 Table 4-73 . [Proprietary Information] .. ............ .. ...... .. ....... ... .. ...... .. .... .... ....... ........ .. .. ....... .. .......... ... 4-228 Table 4-74. [Proprietary Information] ...... ........... .... ........ ... .... ............ .................. ..... .. ... .......... .. ..... 4-229 Table 4-75 . Chemical Inventory for the [Proprietary Information] Subsystem ........ .. ............ ........ 4-23 1 Table 4-76. Target Fabrication Waste Process Equipment .......... .. .... ........ .... .... .. .................... .. ..... 4-236 Table 4-77. Target Fabrication Waste Chemical Inventory ...... .. ........................... .. ... .... .. .. ............ 4-23 8 Table 4-78. Target Assembly Auxiliary Equipment .......... ....... ...... .. ... ... .. .... ... ..... ..... ... .. .. .............. 4-243 Table 4-79. Target Design Parameters ....... ... ......... ..... .... .......... ..... ... ................. .. .. .. ... ............. ...... . 4-244 Table 4-80. Target Assembly Special Nuclear Material Inventory .................... ..................... ...... .. 4-245 Table 4-81. Low-Enriched Uranium Storage Maximum Special Nuclear Material Inventory ...... . 4-249 4-ix

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' ~ *.*! ' HORTifWEST MEOICAl ISOTOPE.I NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description TERMS Acronyms and Abbreviations 89Sr strontium-89 9osr strontium-90 99Mo molybdenum-99 99mTc technetium-99m 13 1I iodine-131 133 Xe xenon-133 234u uranium-234 mu uranium-235 236u uranium-236 231u uranium-237 238u uranium-238 239Np neptunium-239 239pu plutonium-239 AC administrative control ACI American Concrete Institute ADUN acid-deficient uranyl nitrate AEF active engineered feature AHS ammonium hydroxide solution ALARA as low as reasonably achievable As arsemc ASME American Society of Mechanical Engineers Ba barium BHMA Builders Hardware Manufacturers Association Br bromine BRR BEA Research Reactor CFR Code of Federal Regulations C02 carbon dioxide CSE criticality safety evaluation DBE design basis event Discovery Ridge Discovery Ridge Research Park DOE U.S . Department of Energy DOT U.S. Department of Transportation EBC equivalent boron content EOI end of irradiation EPDM ethylene propylene diene monomer FDA U.S . Food and Drug Administration Fe(S03NH2)2 ferrous sulfamate H2 hydrogen gas H20 water HJP04 phosphoric acid HEPA high-efficiency particulate air HIC high-integrity container HMTA hexamethylenetetramine HN03 nitric acid HS03NH2 sulfamic acid HVAC heating, ventilation, and air conditioning I iodine ICP-MS inductively coupled plasma mass spectrometry 4-x

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' ~ -.* ~ * . NORTMWlnM(DICAl.ISOTOP£S NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description ICRP International Commission on Radiation Protection IROFS items relied on for safety IRU iodine removal unit IX ion exchange Kr krypton LEU low-enriched uranium MC&A material control and accountability MCNP Monte Carlo N-Particle Mo molybdenum MOC materials of construction MURR University of Missouri Research Reactor Na2S03 sodium sulfite NaH2P04 sodium dihydrogen phosphate NaN02 sodium nitrite NaOCl sodium hypochlorite NaOH sodium hydroxide Nb niobium NESHAP National Emission Standards for Hazardous Air Pollutants NH40H ammonium hydroxide NO nitric oxide NOx nitrogen oxide N02 nitrogen dioxide NRC U.S . Nuclear Regulatory Commission NWMI Northwest Medical Isotopes, LLC ORNL Oak Ridge National Laboratory OSTR Oregon State University TRIGA Reactor osu Oregon State University Pb lead PDF passive design feature QC quality control QRA qualitative risk analysis R&D research and development RCT radiological control technician Rh rhodium RPF Radioisotope Production Facility Ru ruthenium Sb antimony Se selenium Sn tin SNM special nuclear material SS stainless steel SSC structures, systems and components TBP tributyl phosphate TCE trichloroethylene Tc technetium Te tellurium

[Proprietary Information] [Proprietary Information]

TMI total metallic impurities TRU transuranic u uramum U.S. United States 4-xi

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• ~ *.*! ' NomfWEn MlDICAl ISOTOPU UN uranyl nitrate UNH uranyl nitrate hexahydrate

[Proprietary Information] [Proprietary Information]

[Proprietary Information] [Proprietary Information]

USP U.S. Pharmacopeial Convention Xe xenon Units oc degrees Celsius op degrees Fahrenheit

µ rrucron

µCi m1crocune

µg rrucrogram

µm micrometer atm atmospheres Bq becquerel BV bed volume Ci cune cm centimeter cm2 square centimeter cm3 cubic centimeter CV column volume ft feet ft2 square feet g gram gal gallon GBq gigabecquerel gmol gram-mo!

ha hectare hr hour

m. inch in.2 square inch kg kilogram km kilometer kW kilowatt L liter lb pound m meter M molar m2 square meter mCi millicurie MBq megabecquerel MeV megaelectron volt mg milligram rm mile mm minute mL milliliter mm millimeter mo! mole mR milliroentgen mrem millirem 4-xii

~ . NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

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• NOmfWHTMlDM:AllSOTOPE.S MT metric ton MW megawatt nCi nanocune rem roentgen equivalent in man ppm parts per million ppmpU parts per million parts uranium by mass sec second t tonne vol% volume percent w watt wk week wt% weight percent 4-xiii

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NWMl-2015-021, Rev. 1 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 reactors.

The primary RPF operations will include the following:

• Receiving LEU from the U.S. Department of Energy (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 waste generation Treating/packaging wastes generated by 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 strategy, 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 understand the associated moderating, reflecting, or other nuclear-reactive properties.

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• NORTHWEST MEDICAL ISOTOl'fS 4.1 FACILITY AND PROCESS DESCRIPTION 4.1.1 Radioisotope Production Facility Summary 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, "Environmental 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 reactors, and uranium recovery and recycle to produce 99 Mo.

The RPF site is 3.0 hectare (ha) (7.4-acre) and is 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 Building (outside of the protected area) , a Waste Staging and Shipping Building for additional Class A waste storage (inside the protected area), and a Diesel Generator Building. These major facilities also receive, store/hold, or process chemicals, oil, diesel fuel , and other hazardous and radioactive materials.

DISCOVERY RIOOB LOT 15 PROPERTY UNB PlltE WATER PUMP SXID 7.4ACRES WASTB MANAGBMl!NT Bun.DINO SPACB llESElt.VED POil FDlE WATER STORAOI! T Al<<. AND 1IJ!Cl!IVE1t. T ANJ; BElt.M - - -

SIDE SET BACIC. - U Fl!ET PARKINO LOT 32 'IOTAL,- - -

PAllX.INO SPACBS S11lPVAN GUARDHOUSE N

SITE PLAN PARX.ING LOT~ TOTAL 0 100' 200' Bl!RM PARXING SPACl!S P.LCURVB 1...-359.14' R- 1542.83' Figure 4-1. Radioisotope Production Facility Site Layout 4-2

........;.*.*...NWMI NWMl-2015-021, Rev. 1

~ ~.* ! : . NORTHWHTM£01CALISOTOPES Chapter 4.0 - RPF Description The building will be divided into material accountability areas that are regulated by Title 10, Code of Federal Regulations, 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 personnel access to the RPF and include personnel support areas such as access control, change rooms, 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 (m2) (46,088 square feet [ft2]) and 1,569 m2 (16,884 ft 2) of floor space, respectively. The processing hot cell and waste management temporary storage floor space area is approximately 544 m 2 (5,857 ft 2). The maximum height of the building is 19.8 m (65 ft) with a maximum stack height of 22.9 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 cell area, laboratory area, waste management area, utility area, and administrative support area. Figure 4-4 provides a ground-floor layout of the facility, 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 recovery and recycle, and waste management.

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.*.*.NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

, * ~ ~.* ~ .' NORTHWESTME.OICALISOTOPH 0

l,l) 0::

LL u

0 Figure 4-3. General Layout of the Radioisotope Production Facility 4-4

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.......... NWMl-2015-021, Rev. 1

. ', ~ ~.* ~ ." . NORTHWHT MEOJC.U ISOTOPES Chapter 4.0 - RPF Description

[Proprietary Information]

Figure 4-4. Preliminary Layout of the Radioisotope Production Facility First Level Floor Plan and Associated Dimensions 4-5

. .~ ..*...NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• *. ~ ~.~! * . NORTHWESTMEl>>CAl.ISOTOHS

[Proprietary Information]

Figure is not drawn to scale.

Figure 4-5. Preliminary Layout of the Radioisotope Production Facility Second Level Floor Plan

[Proprietary Information]

Figure is not drawn to sca le.

Figure 4-6. Radioisotope Production Facility Hot Cell Details 4-6

. ~; *..*...NWMI NWMl-2015-021, Rev. 1

, * ~ *.*! _- , NORTHWHT MEDICAllSOTOPES 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.

Irradiate Targets in Reactor Irradiated Target Disassembly Target Fabrication and Dissolution C)

Ta get Cladding to

\._ - un*- - -ed -

radia Irradiated Solid Waste Handling Target Shtpping Target to University Shipping and Reacto s ReceiVing Fresh Uranium Blended Recovery and uranium Purified U Recycle lmpuje U l Solunon Solu!ion Fission Product Solution to liquid Waste Handling Leeend

• Reacto r Operations Product Cask

- RPF Operat ions Shipments to Customer 99Mo Production Figure 4-7. Radioisotope Production Facility Block Flow Diagram Facility operation will include the following general process steps (which correspond with Figure 4-7).

Target Fabrication 0 LEU target material is fabricated using a combination of fresh LEU and recycled uranium.

f) Target material is encapsulated using metal cladding to contain the LEU and fission products produced during irradiation.

C) Fabricated targets are packaged 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 processing.

Molybdenum Recovery and Purification 8 Dissolved LEU solution is processed to recover and purify 99 Mo.

0 Purified 99 Mo is packaged in certified shipping containers and shipped to a radiopharmaceutical distributor.

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.*:.**.*.* NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• . ! ~.~ ~ ." . NORTHWlSTMEDICAllSOTOPH Uranium Recovery and Recycle 0 LEU solution is treated to recover uranium and remove trace contaminants and is recycled back to Step 1 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, Process System Functional Specification. 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 target batch within [Proprietary Information]

• Receive MURR targets nominally [Proprietary Information] EOI

• Control/prevent flammable gas from reaching lower flammability limit conditions of 5 percent hydrogen gas (H2); design for 25 percent of lower flammability limit

• Ensure that uranium-235 {2 35U) 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 target material, assemble LEU targets and packages, and ship LEU targets. The overall process functional requirements include:

• Fabricating a [Proprietary Information]

• Considering target fabrication as a material balance accountability area requiring measurements for SNM The process irradiated LEU targets function will receive, disassemble, and dissolve irradiated targets.

The overall process functional requirements include:

• Accepting weekly irradiated targets in multiple shipping casks (e.g., BEA Research Reactor cask)

• Disassembling irradiated targets to remove the irradiated LEU target material , and containing fission gases released during target disassembly

• Dissolving irradiated LEU target material in nitric acid (HN03)

• Providing the capability to transfer dissolved solution to the molybdenum (Mo) recovery and purification system

• Removing nitrogen oxides (NOx), as needed, to ensure proper operation of downstream process steps

• Providing the capability to collect scrubber liquid waste generated during dissolution

• Providing the capability to treat fission gases generated during dissolution

• Removing radioiodine sufficiently to allow discharge to the stack 4-8

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.*.*NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

, * ~ ~.. ! ." . NO<<fHWtsT M£DICALISOTOP£S

• Retaining fis sion product noble gases for a period of time until the gases have decayed sufficiently to allow discharge to the stack

[Proprietary Information]

[Proprietary Information]

The Mo recovery and purification function will produce 99 Mo product from the acidified target solution stream. The overall process functional requirements include:

• Providing the capability to recovery 99 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 capability for 99 Mo product packaging and shipping

• Recovering more than [Proprietary Information] of 99 Mo from the target solution

• Removing radioiodine sufficiently from vessel ventilation to allow discharge to the stack

• Providing hot cell capability to transfer 99 Mo solution to a "clean cell" for an appropriate level of purification per U.S. Food and Drug Administration requirements

• Confirming that the 99 Mo product meets the product specifications

• Shipping the 99 Mo product per 49 CFR 173, "Shippers - General Requirements for Shipments and Packages" The U recovery and recycle function will receive, purify, and recycle U from the Mo recovery and purification system. The overall process functional requirements include:

• Providing the capability to recover U from the Mo waste solution

• Providing the capability to [Proprietary Information]

• Providing the capability to dilute the [Proprietary Information]

• Recovering the U-bearing solution using [Proprietary Information]

• Providing the capability for first-stage IX [Proprietary Information]

• Ensuring that each concentrator has [Proprietary Information]

• Providing [Proprietary Information]

The handle waste function will process the waste streams generated 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 [Proprietary Information]

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. * ~ ~**. ! . NORTHWEST MlDICAl lSOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• Providing the capability to treat, package, and transfer Class A waste to the separate waste storage building prior to disposal

• Providing the capability to package waste streams from all RPF systems

• Measuring SNM (material accountability) prior to transfer to the waste handling system

• Accumulating and segregating waste based on waste type (e.g., Class A, Class C, hazardous waste, chemical compatibility) and/or dose level

• Providing the capability to shield the waste storage area in the RPF to decay waste - to meet shipping and disposal requirement

• Treating waste to comply with the disposal facility's waste acceptance criteria

• Assaying waste to verify compliance with shipping and disposal limits 4.1.2.2 Summary of Reagent, Product and Waste Streams This section presents a summary of the reagents, byproducts, wastes, and finished products of the RPF.

Figure 4-8 provides a summary 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 reagent, product, byproduct, and waste streams are provided in later sections of this chapter.

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i:**:*:**: NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

' ~ * ,* ~ ' NOJITifWHT M(DICALISOTO'£S 4.1.2.3 Radioisotope Production Facility Spent Nuclear Material Inventory The SNM inventory of the RPF is summarized below based on material accountability areas. The target fabrication area is governed by 10 CFR 70 and described by Table 4-1. [Proprietary Information] The dissolver process enclosure will include uranium metal that is being dissolved to produce uranyl nitrate (UN) solution. Composition ranges indicate the variation of solution compositions present in different vessels at a particular location.

Table 4-1. Special Nuclear Material Inventory of Target Fabrication Area SNM massb Location 3 Form Concentration Boundingc,d 1gmum e

[Proprietary Information] Solid U-metal [Proprietary [Proprietary [Proprietary [Proprietary pieces/LEU target Information] Information] Information] Information]

material in sealed containers Dissolver process enclosure U-metal/UNH [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] Information] Information]

Recycled uranium process UNH [Proprietary [Proprietary [Proprietary [Proprietary enclosures Information] Information] Information] Information]

ADUN concentration and ADUN [Proprietary [Proprietary [Proprietary [Proprietary storage process enclosures Information] Information] Information] Information]

Wash column and drying [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary tray enclosures Information] Information] Information] Information] Information]

[Proprietary Information] LEU target material in [Proprietary [Proprietary [Proprietary [Proprietary sealed targets Information] Information] Information] Information]

a All process enclosures and storage systems are located in the target fa brication process area.

b SNM concentration and mass represent total amount of LEU (combined m u and 238 U at :S I 9.95 wt% m u).

c [Proprietary Information]

d The indicated masses are not additi ve to describe the total 10 CFR 70 area inventory because material is transferred from one location to another during a processing week.

[Proprietary Information].

ADUN acid deficient uranyl nitrate solution . U uranium.

LEU low-enriched uranium. UNH uranyl nitrate hexahydrate.

NIA not applicable. [Proprietary Information) =[Proprietary Information]

SNM special nuclear material.

Bounding and nominal SNM inventories are indicated on Table 4-1 and shown in terms of the equivalent mass of uranium, independent of the physical form. The bounding inventory in each location is based on the full vessel capacity and composition of in-process solution. The nominal inventory is based on the assumption that storage areas are generally operated at half capacity to provide a buffer for potential variations in process throughput during normal operation. Summation of the location inventories does not necessarily provide an accurate description of the total target fabrication area inventory due to the batch processing operation. Material from one process location is used as input to a subsequent location so that material cannot be present in all locations at the indicated inventories under normal operating conditions.

Irradiated material areas are governed by l 0 CFR 50 and described by Table 4-2. Equipment and vessels containing SNM will be located in a variety of hot cells within the RPF. Multiple forms are shown for the target dissolution hot cell because material entering [Proprietary Information] to produce UN solution.

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• ~* * ~ . NORTHWEST Ml.DfCAl JSOTOPH Chapter 4.0 - RPF Description Table 4-2. Special Nuclear Material Inventory of Irradiated Material Areas

- SNM massa Location Concentration Boundingb,c Nominalc,d Target receipt hot cell [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information) In formation) Information] Information)

Target disassembly hot cells* [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] In formation] Information] Information]

Target dissolution hot cells* [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information) Information] information) information]

Mo recovery and purification [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information) Information) Information) Information) In formation) hot cells Tank hot cell Mo recovery tanks [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary Information] In formation) Information] In form ation] Information]

Impure U collection tanks [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] In formation) Information] information]

IX columns and support [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] In formation] In form ation] In formation]

tanks Uranium concentrator #1 [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information) Information] Information] Information)

Uranium concentrator #2 [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary Information] In formati on] Information] In formation] In format ion)

U decay tanks [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] Information] Information] In formation]

U IX waste tanks [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary Information] Information) In formation] In formation] Information]

High dose liquid [Proprietary [Proprietary [Proprietary [Proprietary (Proprietary Information] Information] Information] In formation] information) accumulations Solid waste vesselsh [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary Information) Information) Information] In formation] Information]

• SNM concentration and mass represent tota l amount of LEU (combined m u and 238 U at ::: 19.95 wt% m u) b [Proprietary Information]

c The indi cated masses are not additive to describe the tota l I 0 CFR 50 a rea inventory, as the materia l is transferred from one location to another during a processing week.

ct [Proprietary Information] .

• [Proprietary Information] .

r [Proprietary Information].

g [Proprietary Information].

h [Proprietary Information] .

IX ion exchange. OSTR Oregon State University TRJGA Reactor.

LEU low-enriched uranium. SNM special nuclear material.

Mo molybdenum. U uramum MURR Univers ity of Mi sso uri Research Reactor. UNH uranyl nitrate hexahydrate sol uti on NIA not applicable. [Proprietary In formation] = [Proprietary Information]

[Proprietary Information] . A more detailed description of the vessel volume and composition ranges is described in Section 4.4.1.4.

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, ' ~ ~.~! : . NORTHWEITMEOlCAllSOTOPH Summation of the location inventories does not necessarily provide an accurate description of the total irradiated material area inventory due to the batch processing operation. Material from one process 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. Radionuclide Inventory for Radioisotope Production Facility Process Streams Time System (hr EOI)

Target dissolution [Proprietary Information] [Proprietary Information]

Mo feed tanks [Proprietary Information] [Proprietary Information]

U system [Proprietary Information] [Proprietary Information]

Mo system [Proprietary Information] [Proprietary Information]

Mo waste tank [Proprietary Information] [Proprietary Information]

Offgas system* [Proprietary Information] [Proprietary Information]

High-dose waste tanksc [Proprietary Information] [Proprietary Information]

Uranium recycled [Proprietary Information] [Proprietary Information]

• Offgas system radionuclide inventory is based on NWMI-2013-CALC-O 11 b to account for accumu lation of isotope buildup in the offgas system [Proprietary Information] .

b Materia l decay time is based on the total equilibrium in-process inventory, as described in NWMI-2013-CALC-O 11 ,

Source Term Calculations, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

c [Proprietary Information].

d [Proprietary Information) .

EOI end of irradiation. Mo molybdenum.

RIC high-integrity container. u uranium.

IX ion exchange.

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. *. ~ ~.*~: NORTHWESTM(DfCAl ISOTOHS 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 of Irradiation 4-14

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' ~ * . *~

• NOITMWEIT MlOtcAl ISOTOPlS 4.1.3 Process Overview 4.1.3.1 Target Fabrication 4.1.3.1.1 Target Fabrication Process Overview The target fabrication process centers on the production of LEU target material that will be generated through an [Proprietary Information], which will subsequently be loaded into aluminum target elements.

The LEU feed for the [Proprietary Information] will be chilled uranyl nitrate and consist of a combination of fresh LEU, recovered recycled LEU, and LEU recovered from the processing of irradiated targets. The

[Proprietary Information].

The aluminum target components will be cleaned, and then a target subassembly will be welded and loaded with LEU target material. This target subassembly will subsequently be filled with a helium or air cover gas and sealed by welding on the remaining hardware end cap. The completed targets will be inspected and quality checked using a process similar to that performed for commercial nuclear fuel. The targets will then be shipped back to the reactor sites for irradiation.

The target fabrication process will begin with the receipt of fresh uranium from DOE, target hardware, and chemicals associated with microsphere production and target assembly. [Proprietary Information]

The target hardware components will be cleaned, and a target subassembly will be welded and loaded with [Proprietary Information] LEU target material by means of a vibratory target loading assembly. This target subassembly will subsequently be filled with helium or air cover gas and sealed by welding on the remaining hardware end cap. The completed targets will then be inspected and quality checked.

A simplified target fabrication diagram is shown in Figure 4-11 . The figure shows the fresh and recycled LEU 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 dissolution

• 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.

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• ~ *.* ! ' . NOllTHWEST Mf.OJCAl JSOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

Figure 4-11. Target Fabrication Block Flow Diagram 4-16

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NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. ',! ~.* ! .' . NORTHWtST MEDICAL ISOTOPES

[Proprietary Information]

Figure 4-12. Target Assembly Diagram 4-17

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. *.~ *.~! ' . NORTHWEST MEDICAL ISOTOPES 4.1.3.1.2 Target Fabrication Physical Location The target fabrication area will be located as shown in the area outlined in yellow in Figure 4-13 .

Additional information on the layout of the equipment and subsystems for the target fabrication system is 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

• Producing LEU target material from fresh and recycled LEU material

• Assembling, loading, and fabricating LEU targets

• Minimizing uranium losses through the target fabrication system 4.1.3.1.4 Target Fabrication Safety Functions The target fabrication system will perform safety functions that provide protection of on-site and off-site personnel from radiological and other industrial related hazards by:

• Preventing criticality within the target fabrication system

• Preventing flammable gas composition within the target fabrication system

• Limiting personnel exposure to hazardous chemicals and offgases 4-18

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' ~ ~.* ~

• NOknfWUTMU>tCALISOTOPES Chapter 4 .0 - RPF Description 4.1.3.2 Target Receipt and Disassembly 4.1.3.2.1 Target Receipt and Disassembly Overview The target receipt and disassembly process will be operated in a batch mode, starting with receipt of a batch of targets inside a shipping cask. The targets will 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.

Target Shipping material cask dissolution receiving 1or2 NWMl-04115r02 Empty shipping cask ,.___ _ _ _ _ _ _ _ _ _ _ _ _ _ ___,

return Legend:

- Inputs Output

- Process - Waste management Figure 4-14. Target Receipt and Disassembly System Flow Diagram The target receipt and disassembly subsystems will include the following :

• Cask receipt

• Target receipt

• Target disassembly I

• Target disassembly 2 The trailer containing the shipping cask will be positioned in the receipt bay, and the truck will be disconnected 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 located along the rows of the processing hot cells within the RPF. The target receipt, target disassembly 1, and target disassembly 2 subsystems will be located in the tank hot eel 1. The subsystem locations are shown in Figure 4-15 .

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[Proprietary Information]

Figure 4-15. Target Receipt and Disassembly System Facility 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, closing, and lifting operations

• Retrieving irradiated targets from a shipping cask

• Disassembling targets and retrieving irradiated target material from targets

• Reducing or eliminating the buildup of static electricity wherever target material is handled 4.1.3.2.4 Target Receipt and Disassembly Safety Functions The target receipt and disassembly 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 handling

• Maintaining positive control of radiological materials (irradiated target material and target hardware)

• Protecting personnel and equipment from industrial hazards associated with the system equipment, such as moving parts, high temperatures, and electric shock 4-20

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• ~ * .* ~ ' NOfllTHWHT M£01CA1. ISOTOPU 4.1.3.3 Target Dissolution 4.1.3.3.1 Target Dissolution Process Overview 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 offgas containing the fission product gases will go through a series of cleanup columns. The NOx will be removed by a reflux condenser and several NOx 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 99 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 l

• Pressure relief

• Target dissolution 2

• Primary fission gas treatment

• NOx treatment l

• Secondary fission gas treatment

• NOx treatment 2

• 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.

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• NOATHWESTMfDfCAllSOTOPfS 4.1.3.3.2 Target Dissolution Physical Location The target dissolution I and target dissolution 2 subsystems will be located along the rows of the processing hot cells within the RPF. The NOx treatment I , NOx treatment 2, pressure relief, primary fission gas treatment, and waste collection subsystems will be located in the tank hot cell. The subsystem locations are shown in Figure 4-1 7.

[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

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. NORTHWU f MEDICAL ISOTOPES Chapter 4.0 - RPF Description

• 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 of radiological 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 4.1.3.4 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

• Tertiary ion exchange

• Secondary 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.

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[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 following two main functions:

• Recovery of Mo product from a nitric acid solution created from dissolved irradiated uranium targets

• Purification of the recovered Mo product to reach specified purity requirements, followed by shipment of the Mo product The high-dose nitric acid solution created from dissolved irradiated uranium targets, along with the high-dose Mo product solution, will require that all functions be carried out in a remote environment 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 hazards by:

• Preventing inadvertent criticality 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 components 4-24

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• Maintaining positive control of radiological materials (99 Mo product, intermediate streams, and radiological waste)

• Providing appropriate containers and handling systems to protect personnel from industrial hazards such as chemical exposure (e.g., nitric acid, caustic, etc.)

4.1.3.5 Uranium Recovery and Recycle 4.1.3.5.1 Uranium Recovery and Recycle Process Overview The U recovery and recycle system will process aqueous LEU solutions generated in the Mo recovery and purification system to separate unwanted radioisotopes from uranium. Uranium will be separated from the unwanted radioisotopes using two IX cycles. A concentrator will be provided for the uranium-bearing solution as part of each IX cycle to adjust the LEU solution uranium concentration. Vent gases from process 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 will be transferred to the target fabrication system for use as a source to fabricate new reactor targets.

Waste generated by the U recovery and recycle system operation will be transferred to the waste handling system for solidification, packaging, and shipping to a disposal site.

A simplified U recovery and recycle diagram is shown in Figure 4-20 . The U recovery and recycle subsystems will include the following:

• Impure uranium collection

• Uranium recycle

• Primary ion exchange

• Uranium decay and accountability

• Primary concentration

• Spent ion exchange resin

• Secondary ion exchange

• Waste collection

• Secondary concentration

[Proprietary Information]

Figure 4-20. Simplified Uranium Recovery and Recycle Process Flow Diagram 4-25

.:........~ .*:****.NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. * ~ ~.~~ : . NORlHWESTMEDICALISOTOPES 4.1.3.5.2 Uranium Recovery and Recycle Physical Layout The U recovery and 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, and 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 purification system and provide a

[Proprietary Information] in preparation for the purification process (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 impure uranium solution (NWMI-2013-049, Section 3.6.2).

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• Decay and recycle LEU solution - [Proprietary Information] (NWMl-2013-049, Section 3.6.3) .

• Transfer process waste - This sub-function 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:

• Providing radiological shielding during U recovery and recycle system activities

• Preventing inadvertent criticality through inherently safe design of the U recovery and recycle equipment

• Preventing radiological release during U recovery and recycle system activities

• Controlling and preventing flammable gas from reaching lower flammability limit conditions

• Maintaining positive control of radiological materials

• Protecting personnel and equipment from industrial hazards associated with the system equipment, such as moving parts, high temperatures, and electric shock 4.1.3.6 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 will be split into high-dose and low-dose streams by concentration. The high-dose fraction composition will be adjusted and mixed with adsorbent material in high-integrity containers (HIC), stored, and loaded into a shipping cask for disposal. A portion of the low-dose fraction is expected to be suitable for recycle to selected hot cell systems as process water. Water that is not recycled will be adjusted and then mixed with an adsorbent material in 55-gallon (gal) drums.

The solid waste disposal system will consist of an area for collection, size-reduction, and staging of solid wastes. The solids will be placed in a 208 L (55-gal) waste drum and encapsulated by adding a cement material to fill voids remaining within the drum. Encapsulated waste will be stored until the drums are loaded into a shipping cask and transported to a disposal site.

A specialty waste disposal system will deal with the small quantities of unique wastes generated 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, stabilized as appropriate, and shipped offsite for treatment and disposal.

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' ', ~ ~.~~:. NORTHWESTMlOICA&. ISOTOPES 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

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. *. ~ . .. ~ .' . NORTHWHT MEDICAL ISOTOPES Chapter 4.0 - RPF Description 4.1.3.6.2 Waste Handling System Physical Layout 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 Systems,"

provides additional details).

[Proprietary Information]

Figure 4-24. Waste Handling Locations 4-29

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. °. ~ ~.~ ~ :. NORTifWUTMlOICAllSOTOPfS 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 Liquid 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 HICs 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 4-30

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~ ~.~! *. NOltTHWUTMEDtcALISOTOPES 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:

• 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 4.1.4 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.

Administration and support area 10 CFR 70 10 CFR 50 Figure 4-26. Radioisotope Production Facility Areas Table 4-4 provides a crosswalk of the seven different areas with the primary functions and primary systems.

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~ *.~ ~ : . NOllTHWESTMEDICA.llSOTOPES Table 4-4. Radioisotope Production Facility Area Crosswalk Target Area (room designator) fabrication (T)

Irradiated target Process irradiated LEU receipt bay (R)

Primary functions Fabricate LEU targets targets Primary systems

• Target fabrication (TF)

• Material handling (MH)

• Material handling (MH)

• Target receipt and disassembly (TD) 10 CFR 70" 10 CFR 50b Hot cell (H or Ge) Process irradiated LEU

• Target receipt and disassembly (TD) 10 CFR 50b targets

• Target dissolution (DS)

Recover and purify

• Molybdenum recover and purification (MR) 10 CFR 50b 99 Mo product Recover and recycle

• Uranium recovery and recycle (UR) 10 CFR 50b LEU solution Handle waste

• Waste handling 10 CFR 50b Waste Handle waste

• Waste handling (WH) 10 CFR 50b management (W)

• Material handling (MH)

Laboratory (L) Support systems

• Chemical supply (CS) 10 CFR 50b

• Gas supply (GS)

• Material handling (MH)

Utility (U) Support systems

• Normal facility electrical power 10 CFR 50b

• Process utility systems

• Facility ventilation systems Administration Support systems

• Facility process control and communications (FPC) NIA and support (S)

• Fire protection (FP)

• Radiation protection

• Safeguards and security

• 10 CFR 70, "Domestic Licensing of Special Nuclear Material," Code of Federal Regulations, Office of the Federal Register, as amended.

b 10 CFR SO, "Domestic Licensing of Production and Utilization Facilities," Code of Federal Regulations, Office of the Federal Register, as amended .

c H indicates a hot cell, G indicates a hot cell operator gallery, or other room that may be occupied.

99 Mo molybdenum-99 NIA = not applicable.

LEU = low-enriched 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 Building 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 of 25. The entire assembly will be fully 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 barrier liner under the purlins on a linear support system. The insulation liner will be a white, reinforced polypropylene material with a less than 75 flame-spread rating and less than 450 smoke-developed rating.

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• ...*NWMI

' ! *.* ! ' NORTHWEST M£DtcA.l ISOTOPES NWMl-2015-021, Rev. 1 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 wind-driven missiles in ASCE 7 Minimum Design Loads for Buildings and Other Structures, 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, low-e coated, heat strengthened, or fully tempered glass.

4.1.4.1.2 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 with a scrubbable resinous finish. Ceilings in the production areas without radiation control 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 walls 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 cladding 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, sealer 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 (18-gauge) hollow metal with a durable paint finish. Doors exposed to light traffic in the production area will be Level 3 ( 16-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 1. Where available, hardware will have a brushed stainless steel finish for durability and resistance to chemical exposure. Otherwise, the finish will be brushed chrome plate, except closer covers, which will have an aluminum paint finish. High-frequency and security doors will have full-height, continuous geared hinges. Other doors will have mortised, anti-friction hinges, with mortise locksets and rim exit devices. Closers will be adjustable for closing force and size.

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• * ~ *.~~ * . NORTHWUTMEOICAl.ISOTOPU 4.1.4.2 Site and Facility Access Vehicular and personnel access to the site and personnel access within the facility will be controlled as part of the physical security requirements. Additional information on the site and facility access is provided in the NWMI RPF Physical Security Plan (Chapter 12.0, "Conduct of Operations,"

Appendix B).

4. t .4.3 Facility Ventilation The facility ventilation system will maintain a Table 4-5. Facility Areas and Respective series of cascading pressure zones to draw air from Confinement Zones the cleanest areas of the facility to the most Area w+M+

contaminated areas. Zone IV will be a clean zone Hot cells (production) I that is independent of the other ventilation zones. Tank hot cell I Zone III will be the cleanest of the potentially Solid waste treatment hot cell contaminated areas, with each subsequent zone High-dose waste solidification hot cell being more contaminated and having lower Uranium decay and accountability hot cell pressures. Table 4-5 defines the ventilation zone HIC vault I applicable to major spaces. Analytical laboratory gloveboxes A common supply air system will provide R&D hot cell laboratory hot cells 100 percent outdoor air to all Zone III areas and Target fabrication room and enclosures II some Zone II areas that require makeup air in Utility room II addition to that cascaded from Zone III. Three Analytical laboratory room and hoods II separate exhaust systems will maintain zone R&D hot cell laboratory room and hoods II pressure differentials and containment: Waste loading hot cell II Maintenance gallery II

• Zone I exhaust system will service the hot Manipulator maintenance room II cell, waste loading areas, target fabrication Exhaust filter room II enclosures, and process offgas subsystems Airlocks* II, Ill in Zone I Irradiated target basket receipt bay III

• Zone II/III exhaust system will service Waste loading truck bay III exhaust flow needs from Zone II and Operating gallery and corridor Ill Zone III in excess of the flow cascaded to Electrical/mechanical supply room III interior zones Chemical supply room Ill

• A laboratory exhaust system will service Corridors III fume hoods in the laboratory area. Decontamination room III The supply air will be conditioned using filters, Loading docks IV heater coils, and cooling coils to meet the Waste management loading bay IV requirements of each space. Abatement Irradiated target receipt truck bay IV technologies (primarily high-efficiency particulate Maintenance room IV air [HEPA] filtration and activated carbon) will be Support staff areas IV used to ensure that air exhausted to the atmosphere

• Confinement zone of airlocks will be dependent on the meets 40 CFR 61, "National Emission Standards two adjacent zones being connected.

for Hazardous Air Pollutants" (NESHAP) and HIC high-integrity container.

applicable State law. A stack sampling system will R&D = research and development.

be employed to demonstrate compliance with the stated regulatory requirements for exhaust.

The systems and components of the facility ventilation system are described in Section 9 .0, Section 9. l.

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• NO<<THWHTM£04CALISOTOHS 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 recycled 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 solutions will confirm that the LEU material can be handled without shielding.

Figure 4-27 illustrates the layout of the target fabrication rooms. The function of each room in the target fabrication area is summarized in Table 4-6.

[Proprietary Information]

Figure 4-27. Target Fabrication Area Layout TlOl Room name Fresh LEU and unirradiated shipping and receiving Table 4-6. Target Fabrication Area Room Descriptions and Functions (2 pages) 147 IV Room functions/features

• Shipping bay and truck loading dock for unirradiated target shipping Receiving bay and truck unloading dock for fresh LEU receipt Tl03 Target fabrication airlock 139 III

• Separates the Zone IV ventilation of Room T 10 I and Zone II ventilation of Room Tl04A T 104A Target fabrication room 1445 II

• Shipping and receiving area within the target fabrication room

• Staging area for incoming and outgoing shipping containers Tl 04B Target fabrication room 920 II

• Target assembly activities from [Proprietary Information] through welded LEU target quality checks 4-35

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' ~e *~ . NORTHWUT MlOtCAL lSOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

- Tl 04C Tl05 Room name Target fabrication room Water entry #2 Table 4-6. Target Fabrication Area Room Descriptions and Functions (2 pages) 1748 65 II IV Room functions/features

• [Proprietary Information]

• Fire riser room

[Proprietary [Proprietary Information] 225 II * [Proprietary Information]

In fo rmati on] * [Proprietary Information]

• [Proprietary Information]

LEU = low-enri ched uranium. = uranium trioxide.

The target fabrication rooms will include the following.

• Room TlOl (Fresh LEU and unirradiated shipping and receiving) - Room TlOl 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 targets will enter the loading dock from Room T 103 in ES-3100 shipping containers and immediately be loaded onto the truck.

• Room T103 (Target fabrication airlock) - Room T 103 is the airlock that will separate the Zone II ventilation of Room Tl 04C from the Zone IV ventilation of Room Tl 01. 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 T 101 to Room T 104A. Sealed targets in ES-3100 shipping containers will be transported through the airlock on pallet jacks from Room Tl04A to Room TIO!.

• Room Tl04A (Target fabrication room) - Room Tl04A is part of Room T104, and no dividing walls will separate the room from Room T 104B. The north wall will be an exterior concrete wall.

The west wall and parts of the south wall will 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 Tl04A and Tl04C. 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 target 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 TI04C will provide the main personnel access point, and Room T 104A will provide the main material access point.

[Proprietary Information] will be transferred manually in containers from Room T 104C. Finished targets will be transferred to [Proprietary Information] for storage, or Room TI 04A for packaging in shipping containers.

• Room Tl05 (Water entry #2) - Room Tl05 is one of two rooms where fire-protection water will enter the RPF. The walls will consist of 1-hr and 2-hr fire-rated interior partitions. The only access to Room Tl05 will be from the exterior.

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• [Proprietary Information]

4.1.4.5 Irradiated Target Receipt Area 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 during target unloading procedures and when the hot cell

[Proprietary Information]

cover block is removed for maintenance. The 67.8 metric ton (MT) (75-ton) traveling bridge crane 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 irradiated target receipt area is summarized in Table 4-7.

ROI I R012 Cask transfer tunnel Cask preparation airlock Table 4-7. Irradiated Target Receipt Area Room Descriptions and Functions Room name 323 314 III II Room functions/ features

• Transport of cask from truck trailer to RO 12

• Ventilation confinement from Zone III ROI 1 to Zone I Hl 05/H 106

• Cask de-lidding and cask gas sampling R013 Irradiated target bay stairwell 314 III

• Personnel access/egress RlOlA/B Irradiated target receipt truck 3,206 IV

• Truck entry port and truck wash down bay A and B Rl02A/B Irradiated target receipt 3,150 III

• Cask impact limiter removal bay A and B

• Cask impact limiter removal

• Move cask to transfer tunnel R201 Irradiated target receipt TBD III

• Crane access space mezzanme 4-37

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, * ~ *.* ~ : NOllTHWEITMEOtcA&.ISOTOPlS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The irradiated target receipt rooms will include the following.

• Room ROll (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 transfer 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 ROl l 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 (Rl 02A) with the cask transfer tunnel (RO 11 ). Room RO 13 will be open to Rooms RO 11 and Rl 02A.

• 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 wall. 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 Rl02A/B through the high bay doors.

• Room R102A/B (Irradiated target receipt bay A and B) - Rooms Rl02A and Rl02B are the truck bays 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 interior partitions, and a non-fire-rated interior partition to the hot cell operating gallery. The tractor-trailer will enter from Rooms RlOlA/B, the trailer will be disconnected, and the tractor will then exit to Rl OlA/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 mezzanine) - Room R201 is the high bay 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.

4.1.4.6 Hot Cell Area Irradiated target processing will be performed using equipment that is located in heavily shielded hot cells to protect operating personnel from doses generated by radioactive materials. The hot cells will provide the capability for remote operation and maintenance of the process equipment by features that include shielding windows and in-cell and through-wall manipulators for operation and maintenance of equipment, access via cover blocks and bridge crane to support remote maintenance activities, 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 handling process dissolution cells

• Operating gallery

• Mo recovery and purification cells

• Maintenance gallery

• LEU recovery and recycle area

• Remote support systems 4-38

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' ~ * .* ~

• NOmfWEST M(DICAl tSOTOPU NWMl-2015-021, Rev. 1 Chapter 4 .0 - RPF Description 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 Layout

• H013 Uranium decay and Room name accountability vault Table 4-8. Hot Cell Area Room Descriptions and Functions (2 pages) 240 Room functions/features

• Uranium lag storage H014B Waste collection tanks

• Bermed area on the floor to contain waste collection tanks within the hot cell area GIOIA Operating gallery - B 769 Ill

• Manipulators and window - access for hot cells HlOI, Hl02 and HI03 GlOIB Operating gallery - A 1,564 III

• Manipulators and window - access for hot cells HI04, HI05 , HI06, HI07 and HI08 GIOIC Operating gallery - C 278 III

• Access to truck bay and maintenance rooms-GI02 Maintenance gallery 1,200 lI

• Manipulators and window access to HOl4A, solid waste ports and solid waste hot cells GI03 Maintenance gall ery airlock 339 II

• Airlock between maintenance gallery and corridor LI 06A HlOI Dissolver 2 hot cell 92

• Target dissolution activities HI02 Target di sassembly 2 hot cell 77

• Target di sassembly acti vities H103 Target receipt hot cell 81

• Transfer of targets from the target transfer port docked to the shipping cask into the target staging rack hot cell 4-39

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' ~**! . NORTKWUT MflMCAL ISOTOf'H NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• Hl04 HI05 Room name Target disassembly I hot cell Dissolver 1 hot cell Table 4-8. Hot Cell Area Room Descriptions and Functions (2 pages) 77 93 Room functions/features

• Target disassembly activities

• Target dissolution activities HI 06 Mo recovery hot cell 61

• Mo recovery activities Hl07 Mo purification hot cell 79

• Mo purification activities Hl08 Product and sampl e hot ce ll IOI

• Mo packaging and loading the product shipping container

• Sampling and sample load out activities G201 Hot cell cover block access III

• Cover block access and high bay G202 Exit passageway 209 III

• Personnel egress Mo = molybdenum.

The hot cell rooms will include the following.

• Room 0013 (Uranium decay and accountability vault) - The uranium decay and accountability vault will be for decay storage of uranyl nitrate. The walls will consist of concrete with a steel liner, as described in Section 4.2 . Purified uranyl nitrate will be piped from the south wall , and once decayed, will be piped to the target fabrication room through the north wall.

• Room 0014B (Waste collection tank hot cell) - The waste collection tank hot cell will be open to Room H l 04A, but a berm will divide the two cells. The walls and berm will consist of concrete with steel liners. Room H014B will contain process equipment associated with liquid waste in the waste handling system.

• Room G 1OlA/B/C (Operating gallery - A/B/C) - Room G 101 wi 11 be the operating gallery for hot cells H 10 I through H 111. The south wall will be a concrete shear wall, and walls dividing the gallery from the hot cells will serve as biological shielding, as described in Section 4.2. Local control stations will be provided in the operating gallery to physically operate remote wall-mounted manipulators and support system operation. Personnel access will be through the access corridor, LI 08.

• Room G102 (Maintenance Gallery) - Room Gl02 on the back side of the hot cells (HlOl to HI 05) and tank hot cell (HO 14). The north, south, east, and west wall material will be concrete.

The maintenance galleries will include enclosures for repair of contaminated equipment, areas for tool storage, and spare parts storage. GI 03 will provide the main personnel access point.

• Room G103 (Maintenance gallery airlock) - The north and south wall material will be concrete. Corridor LI 08B will provide the main personnel access point to Room G 103 .

• Room 0101 (Dissolver 2 hot cell) - Room HlOl wall material will be concrete required for shielding. Rooms GIOlB and Gl02A will be adjacent to Room HlOl. Room Hl02 will be the hot cell next to Room HI 02. The Room HI 0 I hot cell area will support the target dissolution process and will house the dissolver.

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NWMI NORTHWEST MEDICAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• Room H102 (Target disassembly 2 hot cell) - Room HI 02 wall material will be concrete required for shielding. Rooms GI 0 lB and GI 02B will be adjacent to Room H102 . This hot cell area will support the target disassembly process. The target disassembly station will pick one target at a time from the shipping basket, de-lid the target, and 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 leaded windows and/or cameras and master-slave manipulators.

• Room H103 (Target receipt hot cell) - Room HI06 wall material will be concrete required for shielding. Rooms GIOIA and GI02B will be adjacent to Room HI03 . Rooms HI02 and HI04 will be the hot cells next to Room HI03. The Room HI03 hot cell area will support target receipt and include a feature that mates with the shielded transfer cask to lower the target basket into the hot cell.

• Room H104 (Target disassembly 1 hot cell) - Room HI04 wall material will be concrete required for shielding. Rooms GI02 and Gl02B will be adjacent to Room HI07. This hot cell area will support the target disassembly process. The disassembly station will pick one target at a time from the shipping basket, de-lid the target, and 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 leaded windows and/or cameras and master-slave manipulators.

• Room H105 (Dissolver 1 hot cell) - Room HI05 wall material will be concrete required for shielding. Rooms GIOIA and GI02B will be adjacent to Room H105. Rooms HI04 and H106 will be the hot cells next to Room HI 05. The H 105 hot cell area will support the target dissolution process and house the dissolver.

• Room H106 (Mo recovery hot cell) - Room H106 wall material will be concrete required for shielding. Room GI02B will be adjacent to Room HI06. Hot cells HI05 and HI07 will be next to Room HI06. The hot cell will include the primary and secondary small IX columns with containers, peristaltic pumps, and collection tanks. Operation of the process will be performed using the hot cell remote manipulators.

• Room H107 (Mo purification hot cell)- Room HI07 wall material will be concrete required for shielding. Room GI02B will be adjacent to Room HI07 . Hot cells H106 and HI08 will be next to Room HI07. The cell will include tertiary IX column with containers, peristaltic pumps, and collection tanks. Operation of the process will be performed using the hot cell remote manipulators from Room GI 02 . This area of the hot cell will have design features that support U.S. Food and Drug Administration (FDA) cleanroom requirements.

• Room H108 (Product and sample hot cell) - Room HI 08 wall material will be concrete required for shielding. Room GI02B will be adjacent to Room HI08, with hot cell Hl07 next to Room H 111. An access point will be included for load-in and load-out of the 99 Mo shipping 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 will consist of concrete shear wall.

• Room G202 (Exit passageway) - Room G202 will provide personnel egress from the maintenance gallery (Gl02) .

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~ ~.* ~

• NORTHWEST MEDICAL ISOTOPES 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 short-lived radioisotopes to decay to lower doses

• Hot cell solid waste export area, where equipment and empty targets will 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 4-31 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

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[Proprietary Information]

Figure 4-31. Waste Management Loading Bay and Area Layout

[Proprietary Information]

Figure 4-32. Waste Management Area- Ground Floor 4-43

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NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description

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[Proprietary Information]

Figure 4-33. Waste Management Area - Low-Dose Waste Solidification Location The function of each room in the waste management area is summarized in Table 4-9 .

Table 4-9. Waste Management Room Descriptions and Functions IBWOl lA/B HIC vault aw1,865 IV Room functions/features

• Decay storage for HICs WlOl Waste management 1,647 IV

• Truck entry port for waste shipment loading bay

• Remove upper impact limiter Wl02 Waste loading area 1,086 Ill

• Loading area, where drums of high- and low-dose waste are loaded into cask WI 03A/B High-dose waste 534 II

• Movement of high-dose waste containers by crane handling hot cell Wl04 High dose waste

• Add encapsulation agent to drums treatment hot cell

• Add high dose liquid and solidification agent to HIC Wl05 Stair #3 209 III

• Stairwell in the target fabrication area provides access between the airlock or outdoors and the mechanical/

electrical room in the utility area on the second floor Wl06 Waste management 161 III

• Separates the Zone IV ventilation of stairwell and airlock Zone II ventilation of room W107 Wl07 Low-dose liquid 550 II

• Houses equipment for the low-dose solidification solidification process

• Control station for waste handling operations W201 Stair #3 209 III

• Access between first and second floor HIC = high-integrity container.

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• ~ *.*! . NORTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The waste management area rooms will include the following.

• 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 may be part of a pre-engineered metal building. The wall to Room W 102 wi II be a concrete shear wall with a high bay door.

• Room W102 (Waste loading area)- Room Wl02 will house the trailer during cask loading operations. Room W102 will be beneath a portion of Room W103 . The loading operations will consist of a crane transporting the HIC into the cask through a telescoping port, which will connect Room W 103 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 HICs and drums from Room W 104. 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 W104 (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 W105 (Stair #3) - Room Wl05 will be the stairwell connecting Room W106 with Room U201. Walls will consist of concrete shear wall and 2-hr fire-rated interior partitions.

Room W 105 will provide personnel access to the second floor and egress from the second floor.

• Room W106 (Waste management airlock) - Room W106 is the airlock that will separate the Zone II ventilation of the low dose liquid solidification room (W107) from the Zone IV ventilation of the waste management loading bay (WlOl) . The walls will consist of concrete shear wall and 1-hr fire-rated interior partitions. Low-dose waste containers will be transported from Room Tl 0 l to Room Tl 04C by pallet jack.

• Room W107 (Low-dose liquid solidification) - Room W 107 will house equipment for the low-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 WI 07 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 W 106 with Room U201. Walls will consist of concrete shear wall and 2-hr fire-rated interior partitions. Room W 105 will provide personnel access to the second floor and egress from the second floor.

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~e * ~ . NORTHWEST MEDICAL tsOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.1.4.8 Laboratory Area An on-site analytical laboratory will support production of the 99 Mo product and fabrication 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 of 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

[Proprietary Information]

like balances, pH meters, ion-chromatography, etc.

Figure 4-34 shows the layout Figure 4-34. Laboratory Area Layout of the laboratory area rooms.

The function of each room in the laboratory area is presented in Table 4-10.

Table 4-10. Laboratory Area Room Descriptions and Functions

- Ll 01 LI 02A/B Chemical supply Ll03 Receiving 99 Room name Mo product shipping 424 932 265 III IV Room functions/features Allows the flow of material supplies into the faci lity Storage of chemicals Preparation of 99 Mo product for shipping L 104 Shipping airlock 264 III Separate confinement zones LI 05 Analytical laboratory 1694 II Area for laboratory activities (e.g., sample analysis) with glovebox ventilation 1 Ll 06 R&D hot cell laboratory 724 II Containment area for R&D with glovebox ventilation Zone 1 LI 07 Laboratory corridor 694 III Personnel access/egress LI 08 Access corridor 1289 III Personnel access/egress 99 Mo = molybdenum-99. R&D = research and development.

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, * ~ *.*! . NCMmfW(ST M£DtcAl ISOTO'fS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The laboratory rooms will include the following .

• Room LlOl (Receiving)- Room LlOl will be adjacent to Rooms Ll02, Ll03, and Ll04. 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 LlOl will support receipt of chemical supplies and materials for the laboratory.

• Room L102 (Chemical supply) - The chemical makeup room will include tanks supplying aqueous chemicals to the process systems, flammable material storage cabinets used to segregate incompatible materials, and storage of chemical solids used in the process systems.

• Room L103 (99 Mo product shipping) - Room Ll 03 will support shipping and receiving activities, and the staging of outgoing shipping containers

• Room L104 (Shipping airlock) - Room Ll 04 will have a 1-hr fire-rated partition wall adjacent to Rooms Ll05 and Ll07.

• Room LlOS (Analytical laboratory) - Room Ll 05 will have a 1-hr fire-rated partition wall adjacent to Room Ll 07. The analytical laboratory will support production of the 99 Mo product and fabrication of targets.

• Room L106 (R&D hot cell) - Room Ll 06 will have a 1-hr fire-rated partition wall adjacent to Rooms Ll05 and Ll07.

• Room L107 (Laboratory corridor) - Room Ll 07 will be adjacent to Rooms LI 04, Ll 05, and Ll 06. The interior wall will be a 2-hr fire-rated partition wall adjacent to operating gallery A (G 102). The interior wall will be a 1-hr fire-rated partition wall adjacent to Rooms Ll 04 and L105. Room Ll07 will provide a main personnel access point.

• Room Ll08 (Access corridor) - Room Ll 08 will provide access from the administration and support area to the production areas. The walls will consist of concrete shear wall and 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 cabinets used to segregate incompatible materials, and storage of chemical solids used in the process systems. The gas distribution room (not shown) will serve as a location for storage of small quantity gases (stored 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 shows the layout of the chemical makeup room. Further detail for chemical supply 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 ventilation supply equipment.

The utility 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.

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• NOll:TtlWUT M£DtCAl ISOTOf'lS Figure 4-35, Figure 4-36, and Figure 4-37 show the layout of the utility area, second floor mechanical/electrical room, and mechanical area, respectively.

[Proprietary Information]

Figure 4-35. First Floor Utility Area

[Proprietary Information]

Figure 4-36. Second Floor Mechanical and Electrical Room

[Proprietary Information]

Figure 4-37. Second Floor Mechanical Area The function of each room in the utility area is summarized in Table 4-11.

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• NOmfWEST MEDtcAl ISOTOl'£S IIUl 01 U102 Electrical Room name Manipulator maintenance Table 4-11. Utility Area Room Descriptions and Functions 698 473 IV II Room functions/features

• Facility power supply

• Perform maintenance on manipulators U 103 Maintenance shop 567 III

• Perform maintenance on equipment U104 Stair #2 297 IV

• Personnel access/egress UI05 Corridor 227 IV

• Personnel access/egress U 106 Janitor 11 l IV

• Storage U107 Elevator machine room 60 IV

• Houses equipment for elevator operation UI08 Freight elevator 96 IV

• Moves equipment and supplies to/from second floor UI09 Utility area loading 1,487 IV

• Equipment receipt

• Personnel access/egress UllO Men's restroom 350 IV

• Personal hygiene Ull I Women's restroom 314 IV

• Personal hygiene Ul 12 Water entry # l 158 IV

• Fire-protection water Ul 13 Communications room 157 IV

• Houses communication equipment Ull4 Process equipment and parts 342 IV

• Storage area for spare process equipment storage U201 Electrical and mechanical supply 6,320 III

• Housing for electrical and mechanical utility equipment

• Housing for supply air handling units U202 Corridor 566 III

• Personnel access/egress U203 Ventilation exhaust 8,616 II

• Housing for Zone I and Zone II/III Exhaust filter housings

• Housing for process offgas final treatment The utility area rooms will include the following.

• Room UlOl (Electrical) - Room U I 0 I 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 generator. Room U 102 will provide the main personnel access point.

• Room U102 (Manipulator maintenance shop) - Room Ul02 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.

• Room U103 (Maintenance shop) - Room Ul03 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. Personnel access will be provided through corridor Ll07.

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• Room U104 (Stair #2) - Room Ul 04 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 UlOS (Corridor) - Corridor Ul 05 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 L 107.

• Room U106 (Janitor)- Room Ul06 will be ajanitor storage area. Walls will consist offire-rated and non-fire-rated interior partitions and a concrete shear wall. Personnel access will be through Corridor U105 .

• 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 U105.

• Room U108 (Freight elevator) - Room U108 will be the freight elevator. Walls will consist of concrete shear wall and I-hr fire-rated interior partitions. Personnel access will be through Corridor U105 .

• 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 personnel 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 UllO (Men's restroom) - Room Ul 10 will be the men' s restroom. Walls will mainly be non-fire-rated interior partitions.

• Room Ulll (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 Ul 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 only 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 for 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 U201 will be concrete shear walls.

• Room U202 (Corridor) - Corridor U202 will provide personnel access 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-rated concrete shear walls.

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• 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 Production 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 [Proprietary Information]

support area will be an annex to the RPF and include various rooms supporting production.

The general construction of Figure 4-38. Administration and Support Area Layout the administration and support 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 fire-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 of a 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, Ethernet switches, power supplies, uninterruptable power supply). This control system will be supported by a data highway of sensing instrument signals in the facility process areas that will be gathered onto the highway 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).

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• ~ *.*! ' NORTHWUT MlDtcAl ISOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• SlOl Sl02 Vestibule Entry Room name * ..

Table 4-12. Administration and Support Area Room Descriptions and Functions 225 637 IV IV Room functions/ features Personnel access/egress Personnel access/egress Sl03 Entry hall 1,033 IV Personnel access/egress S104 Corridor 1,033 IV Personnel access/egress Sl05 Women 's change room 284 IV Personnel area for changing clothes S105A Vestibule 46 IV Personnel access/egress SI06 Women 's restroom 281 IV Personnel hygiene Sl06A Vestibule 38 IV Personnel access/egress SI07 Men 's restroom 426 IV Personnel hygiene S108 Men 's change room hall 49 IV Personnel access/egress SI09 Men 's change room 199 IV Personnel area for changing clothes SllO Men's shower 164 IV Shower enclosure Sl 12 Decontamination room 253 IV Area to remove contamination S113 Hall 94 IV Personnel access/egress SI 14 Airlock 193 IV Personnel access/egress S115 RCT office 119 IV Functional RCT workspace Sl 16 Shift manager office 148 IV Functional workspace Sl 17 Stair #1 200 IV Personnel access/egress SI 18 Closet 30 IV Storage S118A Server room 267 IV Space devoted to computer servers SI 19 Control room 366 IV Provides the majority of interfaces for the RPF process control system Sl20 Corridor 275 IV Personnel access/egress Sl20A Vestibule 36 IV Personnel access/egress Sl21 Break room 858 IV Personnel lunch room Sl22 Communications/electrical 134 IV Housing for electrical utility equipment Sl23 Office #4 121 IV Functional workspace Sl24 Janitor 70 IV Storage Sl25 Office #3 126 IV Functional workspace SI26 Office #1 124 IV Functional workspace Sl27 Office #2 127 IV Functional workspace Sl28 Restroom 72 IV Personnel hygiene Sl29 Hall 192 IV Personnel access/egress Sl30 Conference room 598 IV Workspace area for meetings RCT = radiological control technician. RPF = Radioisotope Production Faci li ty.

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• NORTHWUT MEDICAi. ISOTOPES Chapter 4.0 - RPF Description 4.2 RADIOISOTOPE PRODUCTION FACILITY BIOLOGICAL SHIELD 4.2.1 Introduction 4.2.1.1 Biological Shield Functions The RPF biological shield will provide an integrated system of features that protect workers from the high-dose radiation generated during the radioisotope processing to recover 99 Mo. The primary function of the biological shield will be to reduce the radiation dose rates and accumulated doses in occupied areas to not exceed the limits of 10 CFR 20, "Standards for Protection Against Radiation," and the guidelines of the facility ALARA (as low as reasonably achievable) program. The shielding and its components will withstand seismic and other concurrent loads, while maintaining containment and shielding during a design basis event (DBE).

Functions of the biological shield, as related to the RPF process systems, are described in Section 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 cell arrangement within the biological shield is shown in Figure 4-40 .

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[Proprietary Information]

Figure 4-39. Facility Location of Biological Shield 4-54

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• NORTHWEST MEOK:Al ISOTOPl:S

[Proprietary Information]

Figure 4-40. Hot Cell Arrangement 4.2.1.2.1 Location of Hot Cell Appurtenances The number and location of hot cell appurtenances (e.g., windows, manipulators, and optics) will be developed for the Operating License Application. The hot cell appurtenances 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 construction of radiation shielding structures specified in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.69, Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants, to the extent that the recommended standards apply to a composite (concrete and steel) shield.

The design of the concrete for shielding structures, including materials selection, durability requirements, quality control (QC), mixing, placement, formwork, embedded pipes, construction joints, reinforcement, analysis, and design, conforms to the provisions outlined in Chapters 3 through 8 of American Concrete Institute (ACI) 349, Code Requirements for Nuclear Safety-Related Concrete Structures.

The final minimum thickness of a concrete shield structure is the greater of the: (1) thickness determined based on radiation shielding requirements, and (2) thickness determined based on structural requirements.

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, ' ~ *,* !° ' . NORTMWEST MlDK:Al tsOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.2.2.1 Shielding Materials of Construction The RPF biological shield will be constructed primarily of steel-reinforced normal (2.2 to 2.4 g/cubic centimeter [cm3]) and high-density (2.5 to 4.5 g/cm3) concrete walls. In areas where shielding requirements are higher than the nominal average, steel cladding will be used to increase 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 by computer codes to calculate interaction probabilities for both neutrons and photons. When used, 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 using applicable structural and construction standards.

4.2.2.2.2 Effects of Radiation on Structural Materials The effects of radiation on structural materials in the RPF were not quantified during preliminary design.

ANS 6.4-2006, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants, provides the following guidance that will be used to evaluate the effects of radiation on structural materials:

• Section 5.4 - "Jn the design of a concrete radiation shield, it is necessary that the temperature and temperature distribution throughout the shield be calculated prior to construction. In addition to radiation heating sources, these calculations must include detailed consideration of other heat sources and sinks. Although structural considerations are outside the scope of this standard, the shield designer should be aware that thermal changes resulting from the radiation environment may affect the ability of concrete to meet its structural requirements. "

• Section 8.1.1 - "The operating temperature of the concrete should be considered in the selection of concrete mixtures and in the prediction of the attenuation characteristics. "

"When neutrons and gamma rays interact with concrete, energy is deposited in the concrete. The resultant increase in temperature is the primary radiation effect that has been found. For incident energy fluxes < 10 10 megaelectron volt (Me V)/square centimeter (cm 2)/second (sec), a negligible temperature rise takes place in concrete. In addition, if concrete temperatures are to be maintained below 65 C, no special consideration needs to be given to temperature effects in concrete shields. "

• Section 8.1.2 - "A major consideration of heating ofconcrete shields is the impact on the structural characteristics. Laboratory experiments clearly indicate that the mechanical properties of concrete are related to temperature. Compressive strength is reduced as the temperature of concrete is increased, and even greater relative losses in tensile strength, modulus of elasticity, and bond strength have been noted. The thermal properties of concrete are also known to be influenced by the type of aggregate employed. In the design of a concrete radiation shield, structural considerations are paramount in those cases where the shield also serves a necessary and vital structural role. This would be the case, for example, if the shield wall also provided a containment barrier in addition to forming an integral part of the building structure.

In some instances, the structural characteristics of a concrete shield might not be important; concrete 's dual role as shield and structure, however, is usually an important feature. "

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[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 system. 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.

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• 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 waste 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 sensors and control system. 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-TP-410) in the product and sample hot cell (HI 08) are an adaptation of a double-door transfer system typically used with 55-gal drums. The system will use a double-door-type sealing concept that will enable safe and efficient transfer 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) will provide radiation shielding between the shield wall of the hot cell and the cask.

[Proprietary Information]

Figure 4-42. Waste Shipping Transfer Port 4-58

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• ~ *.*! ' NomfWEST M£0tcAL ISOTOf'£S NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.2.2.5 Design of Operator Interfaces Operator interfaces will include the following.

• Through-wall manipulators will be provided throughout the biological shield where activities requiring high dexterity are performed, including 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 ergonomics. A typical through-wall manipulator workstation is shown in Figure 4-43.

[Proprietary 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. Eac h radiation shi elding window will provide adeq uate radiation shielding for the radiation source in the respective cel l. The attenuation of the window will be matched to the attenuation of the hot cell wall.

4.2.2.6 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.

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Figure 4-44. Cover Block Configuration 4.2.3 Methods and Assumptions for Shielding Calculations 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 of 2 rem.

To evaluate the necessary shielding required to maintain these limits, a series of photon-spectrum 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 requiring 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] .

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[Proprietary Information] The SCALE package of neutronics and depletion codes was used to perform the calculation. Specifically, a two-dimensional model of the OSTR was created in SCALE using TRITON, the depletion was calculated with NEWT, and the output was formatted with OPUS.

The OSTR core was modeled in a configuration similar to the existing core configuration. [Proprietary Information]. The TRITON model consists of an x-y slice of the active core at approximately mid-height.

The model only included the core, the graphite reflector assembly, and surrounding 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 zirconium pin. Smear densities were created for each target by smearing [Proprietary Information] with the inner and outer cladding. [Proprietary Information]. Dimensions, locations, and number densities for the fuel elements were taken from the OSTR safety analysis report. Dimensional values of the targets were taken from the target drawings. The calculations using this model were run with the ENDF/B-V 44 group library (v5-44).

The TRITON model was used to calculate the relative distribution of fuel and target power for a designated irradiation (called "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 and a reactor power of980 kilowatt (kW) (reduction of 2 percent from licensed power to account for uncertainty in measured power [Proprietary Information].

Calculations were performed to predict the mass (g), activity (Ci), and decay heat power (W) before irradiation, at EOI, and at specific points in time following irradiation for the targets. The top 400 isotopes in order of importance at each requested decay (cooling) interval were provided. Because this code package was originally intended to perform depletion 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 heavy metal/cm.

To convert this to more useful 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 by

[Proprietary Information] (SCALE normalizing factor) and further divided by [Proprietary Information]

(the number of targets in the model) to produce average target values in units of grams, curies, or watts, as applicable.

Finally, a power correction was applied. The output of the calculation does not represent a core that could be configured to meet the technical specifications of the OSTR because the total power exceeds the license limit. However, because the production of isotopes is largely going to be a function of the target power, this calculation was useful to predict the quantity of isotopes based on the distribution of isotopes identified by SCALE at the identified power. The average power per target predicted by the SCALE modeling was estimated to be [Proprietary Information]. Other work using the Monte Carlo N-Particle (MCNP) simulation on the OSTR and MURR reactors estimated prototypical target powers to be

[Proprietary Information].

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

' ~ * ,* ~

• NOfllTHWEn MEDtcAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The photon source strength for the NWMI shielding analysis was determined based on the activity associated with [Proprietary Information] for different process streams and initial decay times because the MURR irradiated targets will present the highest source term. Photon source spectra are computed based on the associated radioisotope inventories for each process stream. The ORlGEN-S code was then used to evaluate the source photon spectra at the indicated minimum decay time and at subsequent decay times for each process stream. Photon spectra were evaluated using a l 9 energy group structure that was based on the SCALE V7 27Nl9G gamma library. A suitable bremsstrahlung master photon library was employed to capture the effects of bremsstrahlung radiation production associated with beta decay processes in the process streams. For the preliminary safety analysis phase of the NWMI project, photon source terms were generated for the processes associated with the targets, pencil 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 Reg-Concrete composition at 2.3 g/cm3 was used for the concrete material description. This represented density is conservatively lower than those listed for ordinary concretes in Table 1 of ANSI/ANS-6.4, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants.

The lead-glass composition is based on the Table 4-13. Master Material List composition for glass code RWB46 offered by Radiation Protection Products, Inc. Relevant Material Description models employing leaded glass report results in both thickness and areal density. The areal Air Dry air l .2929E-03 density results are not sensitive to the Poly Polyethylene 9.2000E-Ol particular leaded glass composition and were Water H20 l .OOOOE+OO used to determine the required thickness for SS304 Scale SCL SS304 7.9400E+OO alternative leaded glass compositions.

Concrete Scale SCL Reg-Concrete 2.3000E+OO The compositions and number densities of Target material Target material [Proprietary [Proprietary

[Proprietary Information] were obtained using Information] Information]

the SCALE Material Information Processor Carbon Steel Scale SCL carbon steel 7.8212E+OO solution model. Aluminum Scale SCL al uminum 2.7020E+OO The solidified high-dose waste stream is Lead Glass Leaded glass (48% Pb, 15% Ba) 4 .8000E+OO represented based on masses for water, UNSoll50 [Proprietary Information] [Proprietary solidifying agent, and sodium nitrite. No Information]

other constituents are credited. GAC Granular activated carbon [Proprietary Information]

Table 4-13 lists materials used in the analysis, Hdsolid Solidified high-dose waste [Proprietary along with nominal densities. Number Information]

densities are provided in Ldsolid Solidified low-dose waste [Proprietary NWMI-2015-SHIELD-OO 1, Radioisotope Information]

Production Facility Shielding Analysis. Source: NWMl-2015-SHIELD-OO I, Radioisotope Production Facility Shielding Analysis, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

Ba barium. UN uranyl nitrate.

Pb lead. [Proprietary Information]

u uramum.

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

.... NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

, ' ~ *,*!

• NOR'TlfWHT M(DfCAl ISOTOPES 4.2.3.3 Methods of Calculating Dose Rates 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 of radiation 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 analysis 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 group-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, criticality 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 particle 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 more simple 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 shielding or dose assessment. For the RPF, the tally was recorded as energy-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 calculations was the International Commission on Radiation Protection (ICRP) 1974 photon flux-to-dose conversion factors .

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• .......;"...NWMI NORTHWHT MEDICAL ISOTOPlS NWMl-201 5-021 , Rev. 1 Chapter 4.0 - RPF Description For the NWMI target analysis, ring detector tallies are placed at the surface, 1 m, 2 m, 3 m, and 4 m from the target material axial midpoint [Proprietary Information] . For the NWMI pencil tank analysis, point-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 pencil 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 near the surface and at 1 m, 2 m, 3 m, and 4 m from the tank at the axial mid-plane [Proprietary Information]. 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 axial 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 the wall at the inside position, the material interface, and at the midpoints of each composite material. Due to the variations in wall thickness, the hot cell wall analysis did not employ dose rate response 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.

Table 4-14. Target Model Materials 4.2.3.4.1 Target Geometry Model Master Density The NWMI target model dimensions are material material (g/cm 3 )

based on reference drawing OSTR-M0-100, Void [Proprietary [Proprietary "Molybdenum Production Project." Materials Informati on] Information]

Target [Proprietary [Proprietary employed in the model are shown Table 4-14. Information] Information]

Number densities for each material are [Propri etary [Proprietary Cladding provided in NWMI-2015-SHIELD-001. Information] Information]

End fitting [Proprietary [Proprietary Information] Information]

Bottom washer [Propri etary [Proprietary Information] In formati on]

Top washer [Proprietary [Proprietary Information] Information]

Ambient [Proprietary [Proprietary In fo rmati on] Information]

Source: NWMI-2015 -SHIELD-OO I, Radioisotope Production Facility Shielding Analysis, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 20 15 .

[Proprietary Information]

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.*:.**.* NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description

. '. ~ *.* !

• NDRTHWEITMEDtCAllSOTOf'fS 4.2.3.4.2 Pencil Tank Geometry The models for a 5-inch (in.) Schedule 40S Table 4-15 Pencil Tank Model Data pencil tank were developed based on the data shown in Table 4-15 . The tank diameter and wall thickness were taken from standard Description Reference industry American Society of Mechanical Outer diameter ANSI/ ASME 36. l 9M* [Propri etary Information]

Engineers (ASME) references. Other Schedule 40S dimensions were assumed based on Tank wall thickness ANSl/ASME 36.19M* [Proprietary Information) engineering judgement. Schedule 40S Tank height Assumed [Proprietary The tank contents were represented In formation]

[Proprietary Information]. Tank walls are Floor thickness Assumed [Proprietary Information) modeled as SS304. Number densities for each Roof thickness Assumed [Proprietary material are provided in In formation)

NWMI-20 l 5-SHIELD-00 I. Floor offset Assumed [Proprietary Information) 4.2.3.4.3 Offgas Carbon Bed Geometry [Proprietary Roof offset Assumed Information)

The geometry for the offgas carbon bed was Source: NWMI-2015 -SHIELD-OO I, Radioisotope Production similar to the pencil tank model, but a nominal Facility Shielding Analysis, Rev. A, Northwes t Medical Isotopes,

[Proprietary Information] . Schedule 40S pipe LLC, Corvallis, Oregon, 2015 .

was used instead, and the tank content was

• ANSI/ASME 36.19M, Stainless Steel Pipe, American Society granular activated carbon at [Proprietary of Mechanical Engineers, 4th Editi on, New York, New York, 2015.

Information] . The dimensions used for the model are shown in Table 4-16. Number Table 4-16 Carbon Bed Model Geometric densities for each material are provided in NWMI-2015-SHIELD-001. Parameters Description Reference 4.2.3.4.4 Waste Container Geometries Outer diameter ANSI/ ASME 36 . l 9M* [Propri etary Waste container models are developed based Schedule 40S In formation]

on the geometric and material data shown in Tank wall thickness ANSI/ ASME 36. l 9M* [Proprietary Table 4-17 . The high-dose waste container Schedule 40S Information) contents are based on streams WOO 15 Tank height Assumed [Proprietary (Hdsolid, high-dose solidified waste). Number Information) densities for each material are provided in Tank separation Assumed [Proprietary Information)

NWMI-2015-SHIELD-OO 1. The solidifying Shield wall thickness Assumed [Proprietary agent is assumed to be sodium Information]

montmorillonite. For the high-dose waste, the

• ANSI/ ASME 36. 19M, Stain less Steel Pipe, American Society sorbent, water, and sodium nitrite were of Mechanical Engineers, 4th Edition , New York, New York, 20 15.

considered.

Table 4-17. Waste Container Geometric Data Container High-dose waste Reference C-003-001456-007," Note 8 111111*11*

5.4583 6.2292 5.89 14 0.5 Poly 3785

• C-003-00 1456-007, "Poly Hl C CRM Flat Bottom Liner," Rev. 3, EnergySo lutions, Columbia, South Carolina.

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............ NWMI

..... ~

' ~ *.*! ' NORTifWtST MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.2.3.4.5 Hot Cell Wall Geometry 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 wall at a location directly 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 inner stainless steel wall and an outer concrete wall. For the composite wall analysis, windows were not Table 4-18. Material Assignment for represented in the model, and the tally Steel/Concrete Composite Wall Model locations were conservatively placed directly Model Density adjacent the source. To evaluate the hot cell material Master material (g/cm 3 )

window, the primary bioshield wall was Void Void [Proprietary Information]

replaced with a composite of leaded glass Ambient Air [Proprietary Information]

window and air. Wall Concrete [Proprietary Information]

The composite wall materials and thicknesses Window LeadGlass [Proprietary Information]

were parameterized in the model, with values Cell Wall SS304 [Proprietary Information]

varied to determine the required wall [Proprietary Information]

Ground Concrete composition to meet an external surface dose Outside Air [Proprietary Information]

rate limit of 0.5 mrem/hr.

WindowWell Air [Proprietary ln formation]

Materials used in the model are shown in Comp Wall I CarbonSteel [Proprietary Information]

Table 4-18 for the steel/concrete composite wall analysis. For the window analysis, model CompWall2 Concrete [Proprietary Information]

material "Comp Wall I" was set to LeadGlass Floor Concrete [Propri etary Information]

and "CompWall2" was set to Air. Number densities for each material are provided in NWMI-2015-SHIELD-001.

4.2.3.4.6 Expected Dose Equivalent Rates in Air To understand the hazards associated with the radioactive material inventory, an estimate of the dose equivalent rate was calculated with MCNP, based on the source spectrums generated from ORIGEN-S for each of the five configurations.

4.2.3.4.7 Irradiated Target Estimated Dose Equivalent 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 could be received by the RPF from a shipment originating from MURR. Substantial shielding will be required to handle the irradiated targets.

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. ' ~ *.*!

• NORTHWHT MEDtcAl ISOTOH.S Table 4-19. Dose Equivalent Rate from an Irradiated Target as a Function of Time at Various Distances in Air Dose equivalent Dose equivalent Dose equivalent Dose equivalent Dose equivalent rate at surface rate at 1 m rate at 2 m rate at 3 m rate at 4m (rem/hr) (rem/hr) (rem/hr) (rem/hr) (rem/hr)

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] ln fonnation] lnfonnation] Infonnation] Infonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Propri etary [Proprietary [Proprietary Infonnation] lnfonnation] ln fonnatio n] lnfonnation] lnfonnation] lnfonnati on]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] In fonnation] Infonnation] lnfonnation] Lnfonnation] lnfonnation]

[Proprietary [Propri etary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] lnfonnation ] Infonnation] lnfonnation] In fonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] Lnfonnation] lnfonnation] ln fonnation] Infonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] ln fonnation] lnfonnation] In fonnation ] Infonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] Infonnation] lnfonnation] Infonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary Infonnation] lnfonnation] lnfonnation] ln fonnat ion] In fonnation] ln fonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] lnfonnation] Infonnation] Lnfonnation] ln fonnation] lnfonnati on]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] lnfonnation] lnfonnation] lnfonnation] ln fonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] Infonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] ln fonnation] lnfonnation] ln fonnation] ln fonnat ion] Infonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] Infonnation] Lnfonnation] ln fonnation] Infonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] ln fonnation ] lnfonnation] Informati on] In formation ] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation] lnfonnation] Lnfonnation] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary Infonnation] lnfonnation] Infonnation] ln fonnation] Information ] lnfonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] ln fonnation] lnfonnation] lnfonnation] lnfonnation] Information]

[Propri etary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] lnfonnation] Information] In fonnation] Information] Infonnation]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] Information] Infonnation] Infonnation] lnfonnation]

[Propri etary [Propri etary [Proprietary [Proprietary [Propri etary [Proprietary lnfonnation] ln fonnation] Information] ln fonnation] Information] lnfonnation]

4-67

. . NWMI

. :~ .-.~** :

' ~ * .* ~ ' NORTHWEST Ml.DIC.Al JSOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

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 received into the target fabrication area will be a purified uranium solution with a concentration of [Proprietary Information] . This time period will allow sufficient time for the

[Proprietary Information]. This material will be fed into a 5-in. diameter pencil tank described previously. Results of the estimated dose equivalent rate as a function oftime post-EOI and distance in air are given in Table 4-20. There are two primary observations from the results [Proprietary Information] .

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.*. ..;..:;.-~~ .*-. . NWMI

.**.* NWMl-2015-021, Rev. 1

, * ! ~.* ~ ." . NORTHWESTMlDftAl ISOTOPES Chapter 4.0 - RPF Description Table 4-20. Target Fabrication Incoming Process Stream Dose Rates Time after Dose equivalent Dose equivalent Dose equivalent Dose equivalent Dose equivalent irradiation rate at surface rate at 1 m rate at 2 m rate at 3 m rate at 4m (week) (mrem/hr) (mrem/hr) (mrem/hr) (mrem/hr) (mrem/hr)

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

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

[Proprietary Information] [Proprietary Information] [Proprietary Information] {Proprietary Information] [Proprietary Information] [Proprietary In formation]

{Proprietary In formation] [Proprietary Information] [Proprietary Information] {Proprietary Information] [Proprietary Information] [Proprietary Information]

[Proprietary In formation] [Proprietary Information] [Proprietary Information] (Proprietary Information] [Proprietary Informatio n] [Proprietary In formation]

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

[Proprietary Information) [Proprietary Information) [Proprietary In formation] (Proprietary Information] [Proprietary Information] [Proprietary In formation]

[Proprietary Information) [Proprietary Information] [Proprietary In formatio n] [Proprietary Information] [Proprietary Information] [Proprietary Informa tion]

[Proprietary In formation) [Proprietary Information] (Proprietary Information] {Proprietary Information] [Proprietary Information] [Proprietary In formation]

[Proprietary Information) [Proprietary Information] [Proprietary Information] {Proprietary Informat ion] [Proprietary Information] [Proprietary Information]

[Proprietary Information) {Proprietary Informat ion] [Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary In format ion]

[Proprietary Information) {Proprietary Information] [Proprietary Information] [Proprietary Info rmation] [Proprietary Information] [Proprietary Information]

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] (Proprietary Information] [Proprietary In formation]

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

[P roprietary Information] [Proprietary Informat ion] [Proprietary Information) [Proprietary In fo rmation] (Proprietary Information] [Proprietary Information)

[Proprietary Information] [Proprietary Informat ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

(Proprietary Information] (Proprietary Information] [Proprietary Information) [Proprietary Info rmat ion] [Proprietary Information) [Proprietary In format ion]

[Proprietary Information] [Proprietary Information] [Proprietary Information) [Proprietary Informat ion] [Proprietary Information] [Proprietary Information)

[Proprietary Information] (Proprietary Information] [Proprietary Information] [Proprietary Info rmation] [Proprietary Information] [Proprietary In formation]

[Proprietary Information] [Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

4.2.3.4.9 Secondary Carbon Adsorbers Table 4-21. Carbon Bed Model Dose Rate Estimated Dose Equivalent Rate in Air Results The dose equivalent rate off of the dissolver offgas Average weekly Cumulative dose dose equivalent equivalent rate secondary carbon bed is of interest because its - rate (rem/hr) (rem/hr) function is to delay (i.e., create decay time) the [Proprietary [Proprietary Information] [Proprietary Information]

release of the halogen and noble gases by collecting Information]

the offgas effluent over time. Table 4-21 shows the [Proprietary [Proprietary In format ion] [Proprietary Information]

Information]

weekly average and cumulative dose equivalent [Proprietary [Proprietary In formation] [Proprietary Information]

rates for the carbon bed assuming a weekly Information]

deposition of offgas. Due to rapid decay of the [Proprietary [Proprietary Information] [Proprietary Information]

Information]

retained radioisotopes, the cumulative dose rate [Proprietary [Proprietary Information] [Proprietary Information]

from the carbon bed soon reaches a limiting value Information]

after approximately [Proprietary Information]. [Proprietary [Proprietary Information] [Proprietary Information]

Information]

[Proprietary [Proprietary Informat ion] [Proprietary In formation]

Information]

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• NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. * ~ ~.* ~ : , NOflTHWESTMfDICAllSOlOPU 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 container 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 Time after Dose equivalent Dose equivalent Dose equivalent Dose equivalent Dose equivalent irradiation rate at surface rate at 1 m rate at 2 m rate at 3 m rate at 4 m (weeks) (rem/hr) (rem/hr) (rem/hr) (rem/hr) (rem/hr)

[Proprietary [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprieta ry Information]

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

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

Information]

[Proprietary [Proprieta ry Information] [Proprietary In fo rmation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

Information]

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

Information]

[Proprieta ry [Proprietary Information] [Proprietary In fo rmation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

Information]

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

Information]

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

Information]

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

Information]

[Proprietary [Proprietary Information] [Proprietary Info rmation] [Proprietary Information] [Proprietary Information] [Proprietary Info rmation]

Information]

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

Information]

4.2.3.5 Estimated Hot Cell Wall Thickness Based on the source terms identified above, the most important shielding 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.

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• NomtWUTM(DfCALISOTCWES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The calculated dose equivalent rate through the composite wall is shown in Figure 4-46.

[Proprietary 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 equivalent rate with thickness exhibited in Figure 4-46 suggests that the dose rate variation can be characterized by determining the exponential coefficients ,l1 and Az describing the dose rate decay through the steel and concrete walls, respectively.

For each region i = 1,2, the dose rate variation through region i is modeled as:

Equation 4-1 Where di-l = d(xi_ 1 ) = Dose rate at source-side boundary of region i x0 = 0 is the inside surface of the composite wall To determine the exponential coefficients ,l1 and ,l 2 , a series of three cases was executed with a fixed total wall thickness of [Proprietary Information]. The exponential coefficient ,l1 was then determined by an exponential fit to the calculated dose rate at the extent of the steel wall d(x 1 ). The fitted value for ,l1 was estimated to be [Proprietary Information].

To determine ,l 2 , Equation 4-1 is first rearranged as follows:

1

_ ln(d 0 )-ln(d 2 )-A. 1 x 1

/l2 - Equation 4-2 Xz-X1 4-71

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• !* * ~ . NOATNWHT MCDICM mlTOHI NWM l-2015-021, Rev. 1 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 is taken as the best estimate.

Table 4-23. Estimation of Coefficient .A. 2

[Prop rietary Information] [Pro prietary In fo rmation] [Proprietary In formation] [Pro prietary Info rmation] [Proprietary In fo rmation] [Pro prietary In fo rmation]

[Pro prieta ry Information] [Proprietary Information] [Proprietary Information] [Pro prietary In fo rmation] [Proprietary Information] [Proprietary Information]

[Proprietary Information] [Proprietary Information] [Proprietary Informa tion] [Proprietary Information] [Prop rietary Information] [Proprietary Info rmation]

Average [Proprietary Information]

Solving Equation 4-2 for x 1 and setting the through-wall dose rate d 2 to 0.5 mrem/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(dz)-AzXz X1 = Equation 4-3 Ai-Az Using Equation 4-3 , the required steel thickness to shield the design basis source term for various total wall thicknesses is shown in Table 4-24.

Table 4-24. Required Steel Thickness in Composite Wall for Various Total Wall Thicknesses Total shield thickness Steel Concrete (cm) (in.) (cm) (in.)

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

[Proprietary Info rmation] [Proprietary In formation] [Proprietary Informa tion] [Proprietary In format ion] [Proprietary In formatio n] [Proprietary Info rmation]

[Proprietary Information] [Proprietary Information] [Proprietary In fo rmation] [Proprietary Information] [Proprietary Information] [Pro prietary Information]

[Proprietary In fo rmation] [Proprietary In fo rmat ion] [Proprietary In fo rmation] [Proprietary In forma tion] [Proprietary In forma tion] [Proprietary Info rmatio n]

[Proprietary Information] [Proprieta ry Information] [Proprieta ry Information] [Proprietary Information] [Proprieta ry In fo rmation] [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

• • [Proprietary In fo rmation]

[Proprietary

[Proprietary Info rmation]

[Proprietary

' Dose equivalent rate at surface (mrem/hr)

[Propri etary In fo rmatio n]

[Proprietary Dose equivalent rate at 1 m (mrem/hr)

[Prop ri etary Info rmatio n]

[Proprietary Dose equivalent rate at 2 m (mrem/hr)

[Pro prietary Info rrnation]

[Proprietary Dose equivalent rate at 3 m (mrem/hr)

[Proprietary In fo rmation]

[Proprietary Dose equivalent rate at4 m (mrem/hr)

[Pro prietary In fo rmation]

[Proprietary Information] Information] Informat ion] Information] Information] Information] Information]

[Proprietary [Proprietary [Proprietary [Pro prietary [Propri etary [Proprietary [Pro pri etary Info rmation] In fo rmation] In forma tio n] In fo rmation] In fo rmat ion] In for mation] In formation ]

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• NORTHWHT MEDICAL ISOTOH.S 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 accomplish the goal of minimizing the external wall dose rates to 0.5 rnrem/hr, significantly below the 5 rnrem/hr goal. This also represents the thickness required for the largest 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 entirely 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 the 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 shielding 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 Dose Dose Dose Dose Dose

• • equivalent rate equivalent rate equivalent rate equivalent rate equivalent rate at surface at 1 m at 2 m at 3 m at4 m (mrem/hr) (mrem/hr) (mrem/hr) (mrem/hr) (mrem/hr)

[Proprietary [Propri etary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] In formation ] Informati on] Information] Information] Information]

[Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] Information] Informati on] Information] Information] Information]

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

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

4.2.4 Calculated Dose Eq uivalent Rates and Shield Thickness Requirements The shielding boundary provides shielding for workers and the public during normal operations to reduce worker exposure to an average of 0.5 rnrem/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 11/111 supply and the Zone I exhaust.

The biological shielding will be subjected to ambient temperature conditions. The Zone I exhaust will provide ventilation 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 offgas 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 vessel ventilation, is described in Chapter 9.0, Section 9.1.

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• NORTHWUT Ml:DM:Al ISOlWH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.3 RADIOISOTOPE EXTRACTION SYSTEM Table 4-27. Radioisotope Extraction Systems This section describes the radioisotope extraction process from the time irradiated targets enter the RPF System name Ji#aH*J.*

through the 99 Mo product shipment. The Irradiated target receipt and disassembly 4.3 .2 radioisotope extraction processes will include the (irradiated target receipt subsystem) major systems listed in Table 4-27, which are Irradiated target receipt and disassembly 4.3.3 (target disassembly subsystem) described in thi s section.

Target dissolution 4.3.4 4.3.1 Extraction Time Cycle Molybdenum recovery and purification 4.3.5 NWMI-2015-RPT-007, Process Time-Cycle Analysis Report (Part 50 License), 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 4-47.

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 solution 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 ion-exchange separation steps, lasting [Proprietary Information]. A sample of the recovered 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]. [Proprietary Information]

The relationship and overlap of activities from irradiated target receipt through product shipment is shown in Figure 4-47. [Proprietary Information]. Figure 4-47. Extraction Time Cycle 4-74

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• NOflJTHWlSTM£0tcAllSOTOPU 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 Preparing and Reviewing Applications for the Licensing of Non-Power Reactors - 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 disassembly. The design basis for this subsystem is to :

• Receive irradiated targets in casks per the cask certificate of compliance

• Provide the capability to complete gas sampling 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 targets from the truck port to a hot cell

• Meet ALARA principles during target transfer activities 4.3.2.2 System Description The irradiated target receipt system description provides information regarding the process, 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 normal 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 physical and chemical form , volume in process, required criticality control features, and radioactive inventory in process is provided in Sections 4.3.2.2.5 and 4.3 .2.2.6. 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 4.3.2.2.7.

These descriptions provide a detailed account of the SNM in process during the cask receipt activities.

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.

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• NORTHWEST MEDICAl ISOTOPES Chapter 4.0 - RPF Description 4.3.2.2.1 Cask Receipt Process Description A simplified operational flow diagram for the cask receipt subsystem is shown in Figure 4-48.

[Proprietary Information]

Figure 4-48. Cask Receipt Subsystem Flow Diagram The subsystem activities will begin with the arrival of the truck and lowboy trailer with the shipping cask containing the irradiated targets. The truck, trailer, and shipping cask will enter the NWMI RPF via an exterior facility high bay door. The truck, trailer, and shipping cask will enter the facility in one of the irradiated target receipt bays (Figure 4-49 and Figure 4-50). The shipping cask will then be documented for material tracking and accountability requirements. Operators will use the truck bay overhead spray wand for any necessary wash-down of the truck, trailer, or shipping cask while located in the irradiated target receipt truck bays . The truck, trailer, and shipping cask will then enter the irradiated target receipt bay via a high bay door.

[Proprietary Information]

Figure 4-49. Irradiated Target Handling Equipment Arrangement Plan View 4-76

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• NOflllfW'EST MEDtCAL ISOTC,,H NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

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), if entering 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 target receipt truck bay B. The truck will be disconnected from the trailer and exit the facility via the high bay 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 platforms (TD-MP-100, 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 notify operators in the operating gallery that the BRR shipping cask transfer cart (TD-MC-100) is in position and 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 shipping 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 target transfer port (TD-TP-2 I 0, 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 ready for preparation for hot cell transfer.

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' ~ * .* ~ ' NORTHWEST MlDtCAl tSOTOHI NWMl-2015-021, Rev. 1 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 loading/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 target 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 bays. 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 Description 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 handling 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 targets 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-lidding 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 installed.

The lid area will again be surveyed and decontaminated, as required. The powered [Proprietary Information] transfer cart will move the empty cask out of the airlock to its park position 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, 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 this facility.

4.3.2.2.3 Process Equipment Arrangement The cask preparation airlock, shown in Figure 4-51 , will be located under the operating gallery between the shipping cask truck bay and the hot cell. The [Proprietary Information] transfer cart will move the casks into and out of the cask preparation airlock.

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[Proprietary Information]

Figure 4-51. Cask Preparation Airlock The equipment arrangement within the cask preparation airlock is shown in Figure 4-52.

[Proprietary Information]

Figure 4-52. Cask Preparation Airlock Equipment Arrangement 4-79

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• NOflTHWEn MEDICAl tsOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The equipment arrangement within the target [Proprietary Information]

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 Figure 4-53. Target Receipt Hot Cell targets from the casks, and targets will be moved Equipment Arrangement by manipulators through the transfer doors to target disassembly hot cells.

4.3.2.2.4 Process Equipment Design Table 4-28. Irradiated Target Receipt Auxiliary Equipment During irradiated target receipt activities, the Equipment name Equipment no.

irradiated target material will remain within the Impact limiter removal platform IA TD-MP-100 targets, and the targets will remain within the Impact limiter removal platform I B TD-MP-110 shielded shipping cask. Section 4.4.2.9.3 provides a description of the target. The shipping container Impact limiter removal platform 2A TD-MP-120 license describes the shipping cask. Impact limiter removal platform 2B TD-MP-130 Facility overhead crane TD-L-100 Auxiliary equipment will be used to remove the [Proprietary Information] transfer TD-MC-100 cask impact limiters, move the cask, and mate the cart cask to the port on the hot cell. This equipment is Cask de-lidding backdraft hood TD-EN-110 listed in Table 4-28 .

[Proprietary Information] lift TD-L-110

[Propri etary Information] lift TD-L-120 Lid hoist TD-L-130 Target receipt hoist TD-L-200 Target transfer port TD-TP-210 Target transfer port TD-TP-220

[Proprietary Information]

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, * ~ ~* * ~ .° NORllfWtST MEDICAL ISOTO~S NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.3.2.2.5 Special Nuclear Material Description Special Nuclear Material Inventory 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 receipt 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 Concentrationa SNM massa Irradiated targets [Proprietary lnfonnation] [Propri etary lnfonnati on] [Proprietary lnfonnation]

• SNM concentration and mass represent total amount of LEU (combined m u and 238 U at ::; 19.95 wt% m u)

LEU low-enri ched uranium. SNM = special nuclear material.

NIA = not applicable. [Proprietary Information]

NWMI-20l5-CSE-001 , NWMI Preliminary Criticality Safety Evaluation: Irradiated Target Handling and Disassembly, 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 parameter limits for uranium containing 20 wt% 235 U indicate that an unmoderated, but [Proprietary Information] at theoretical density remains subcritical. Licensing documentation for the [Proprietary Information] indicates that a single shipping basket with all positions filled [Proprietary Information]. However, the current double-contingency analysis 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 system, as defined in NWMl-2015-CSE-001. This evaluation covers handling of the targets beginning with their removal from their shipping casks. The criticality control features, including passive design features and administrative controls, allow for adherence to the double-contingency principle. This section applies the criticality control features that are described in Chapter 6.0, "Engineered Safety Features," Section 6.3. The administrative controls and technical specifications required for criticality control will be developed for the Operating License Application and described in Chapter 14.0, "Technical Specifications."

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

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• NOflTHWEST MlOfCAL tSOTOP'fS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The passive design features will include:

• Exclusion of liquid lines (CSE-01-PDFI)

• Geometry requirements of the basket holding wells within the hot cell (CSE-01-PDF2)

The administrative controls will include:

• Limited movement to one irradiated target basket at a time (CSE-0 l-AC4)

• Limited number of targets that may be in the target receipt hot cell (CSE-Ol-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 features will provide defense-in-depth in criticality control. These features will include the following.

• 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 applicable radiation exposure limits prescribed in l 0 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.

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• NOllTHWUT MEDIC"1. ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 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-O 14, Selection of Dominant Target Isotopes for N WMI Material Balances, 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 Targets transfers to radionuclide inventory as described in Section 4.1. Targets arriving in disassembly hot cells shipping casks The radionuclide inventory will be based on a

[Proprietary Information]. The targets will be Figure 4-54. Target Receipt In-Process received in the target receipt system and staged for Radionuclid e Inventory Streams transfer to the target disassembly hot cells.

Figure 4-54 provides a simplified 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 decay that occurs during the time to perform receipt activities.

Table 4-30. Irradiated Target Receipt Radionuclide In-Process Inventory (3 pages)

I MURR target MURR target processing Item Item processing '

Target receipt IUnit operation: Targ et rece ipt IDecay Time after EOP [Proprietary Information]

Stream descri tionh Targets

[Proprietary Information]

136mBa [Proprietary Information] 240pu [Proprietary Information]

137mBa [Proprietary Information] 241pu [Proprietary Information]

139B a [Proprietary Info rmation] 103mRh [Proprietary Information]

140Ba [Proprietary Information] 105Rh [Proprietary Information]

141ce [Proprietary Information] 106Rh [Proprietary Information]

143Ce [Proprietary Information] J06mRh [Proprietary Information]

144Ce [Proprietary Information] 103Ru [Proprietary Information]

242cm [Proprietary Information] 105Ru [Proprietary Information]

243 C m [Proprietary Information] 106Ru [Proprietary Information]

244Cm [Proprietary Information] 122 [Proprietary Information]

sb 134Cs [Proprietary Information] 124Sb [Proprietary Information]

134mcs [Proprietary Information] 125 Sb [Proprietary Information]

136 [Proprietary In formation] 126 [Proprietary Information]

Cs Sb 131c 8 [Proprietary Information] 127 Sb [Proprietary In formation]

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MURR target MURR target processing Item Item processing Unit operation Target receipt IUnit operation: Target receipt Decay Time after EOP [Proprietary Information] IDecay Time after EOP [Proprietary Information]

~~ Streamdescri ti_onh 155Eu [Proprietary Information] I 128Sb [Proprietary Information]

[Proprietary Information] I 12smsb [Proprietary Information]

[Proprietary Information] I [Proprietary Information]

1291 [Proprietary Information] , ~---- [Proprietary Information]

[Proprietary Information] I [Proprietary Information]

1311 [Proprietary Information] I ----------

[Proprietary Information]

[Proprietary Information] I [Proprietary Information]

[Proprietary Information] I____ [Proprietary Information]

[Proprietary Information] I [Proprietary Information]

[Proprietary Information] ,----- [Proprietary Information]

[Proprietary Information] J [Proprietary Information]

1351 [Proprietary Information] I [Proprietary Information]

83m](r [Proprietary Information] I [Proprietary Information]

[Proprietary Information] , -~-- [Proprietary Information]

[Proprietary Information] J [Proprietary Information]

[Proprietary Information] I [Proprietary Information]

[Proprietary Information] J [Proprietary Information]

[Proprietary Information] I------- [Proprietary Information]

[Proprietary Information] J 13ImTe [Proprietary Information]

[Proprietary Information] I ~----

[Proprietary Information]

[Proprietary Information] I [Proprietary Information]

[Proprietary Information] ,- - - [Proprietary Information]

[Proprietary Information] I [Proprietary Information]

[Proprietary Information] '-~---- [Proprietary Information]

[Proprietary Information] I 234Th [Proprietary Information]

[Proprietary Information] ,~--~-"~ [Proprietary Information]

[Propri etary Information] I [Proprietary Information]

236mNp [Proprietary Informationl Ir------- [Proprietary Information]

231Np [Proprietary Information] I [Propri etary Information]

23sNp [Proprietary Information] I ~---

[Proprietary Information]

[Proprietary Information] I [Proprietary Information]

[Proprietary Information] j _ ---* u1mxe [Proprietary Information]

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MURR target MURR target processing Item Item processing Unit operation Target receipt I Unit operation: Target receipt Decay Time after EOI" [Proprietary Information] IDecay Time after EOI"

~ Tarets tionb 234pa [Proprietary Information] 133 Xe [Proprietary Information]

234mpa [Proprietary Information] I33mxe [Proprietary Information]

11 2pd [Proprietary Information] 135 Xe [Proprietary Information]

I47pm [Proprietary Information] 1Jsmxe [Proprietary In formation]

I48pm [Proprietary Information] 89my [Proprietary Information]

I48mpm [Proprietary Information] 90y [Proprietary Information]

I49pm [Proprietary Information] 90my [Proprietary Information]

1sopm [Proprietary Information] 9Iy [Proprietary Information]

15Ipm [Proprietary Information] 9Imy [Proprietary Information]

I42pr [Proprietary Information] 92y [Proprietary Information]

I43pr [Proprietary Information] 93y [Proprietary Information]

I44pr [Proprietary Information] 93zr [Proprietary Information]

I44mpr [Proprietary Information] 9szr [Proprietary Information]

I45pr [Proprietary Information] 91zr [Proprietary Information]

23sPu [Propri etary Information] Total Ci [Proprietary Information]

• In-process inventory based on a [Proprietary Information] , neglecting the time required to receive targets in [Proprietary Information).

b Figure 4-54 provides a simplified description of the process streams indicated.

c In-process inventory based on total of [Proprietary Information] , representing the weekly process throughput. Normal operation expected to begin target transfers to target disassembly when the targets become available after receipt from the first shipping cask.

EOI = end of irradiation. MURR = University of Missouri Research Reactor.

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 l 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 and receipt of radiological material will require approved procedures that implement U.S. Department of Transportation (DOT) requirements.

• The cask lifts and docking ports will be equipped with mechanical or electrical interlocks to ensure cask mating. The cask lifts will have locking bars that prevent lowering of the lift until the bars are removed.

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• NORTIMUT MEDK:Al tSOTOHI NWMl-2015-021, Rev. 1 Chapter 4 .0 - RPF Description

• 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 irradiated 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 shielding 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 of liquid, wi ll 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 release of radioactive material and limiting radiation exposure will also protect workers and the public from exposure to hazardous chemicals.

4.3.3 Target Disassembly Target disassembly will include the disassembly of the targets and the retrieval 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 l hot cell (H 105) and dissolver 2 hot cell (H 10 l) 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 system. The process description (Section 4.3 .3.1) 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 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 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 4.3.3.4 and 4.3.3.5 . 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.

4.3.3.1 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 material 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. Individual targets will be transferred from the target receipt hot cell (Hl03) into either the target disassembly 1 hot cell (H 104) or target disassembly 2 hot cell (H 102) for processing.

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0

• . *

• NOmfWtST MlDICAl. ISOTOPES 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, H104). 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 wi ll 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 disassembly enclosure until outgassing of fission product gases is sufficiently complete. 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 scale 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 assembly (TD-Z-400)

• Fission gas capture hood (TD-Z-310) or fission gas capture hood (TD-Z-410) 4-87

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~ *.*~ ' NORTifWfST MEDtcAL ISOTOPES NWMl-2015-021, Rev. 1 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 described 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 [Proprietary Information]

target disassembly hot cell (Hl 02 , Hl 04) 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 Figure 4-55 ..Target Disassembly Hot Cells gas capture hood (TD-Z-310, TD-Z-410). Eqmpment Arrangement The targets will be cut, and the target material collected in a container. The target material collection container will then be transferred to the target dissolution hot cells.

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.' ~ * .* ~ ." NORTHWEST MEDICAL ISOTOPES 4.3.3.3 Process Equipment Design Table 4-31. Target Disassembly Auxiliary During target disassembly activities, the irradiated Equipment target material will be transferred from the target to Equipment name Equipment no.

the target material collection container. Target cutting assembly TD-Z-300 Section 4.4.2.9.3 provides a description of the target. Fission gas capture hood TD-Z-310 Auxiliary equipment supporting target disassembly, Target disassembly hoi st TD-L-300 including the cutting assembly, fission gas capture Waste drum transfer port TD-TP-300 hood, and handling equipment, is listed in Table 4-31.

Target cutting assembl y TD-Z-400 Process Monitoring and Control Equipment Fission gas capture hood TD-Z-410 Target disassembly hoist TD-L-400 Process monitoring and control equipment was not defined during preliminary design. The process Waste drum transfer port TD-TP-400 description identifies 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 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 of 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 target disassembly cell. The target disassembly SNM inventory is planned to be zero during a majority of the RPF operating week (Section 4.3 .1 ). Two disassembly hot cell s 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 inventory 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 targets [Proprietary In formation] [Proprietary In formation] [Proprietary Information]

a SNM concentration and mass represent total amount of LEU (combined m u and U at ~ 19.95 wt% m u) 238 b SNM in-process inventory of an individual disassembly hot cell. Two disassembly hot cells are available and both cells may contain SNM inventory at the same time.

mu uranium-235. SNM = special nuclear material.

238u uranium-238 . U = uranium LEU low-enriched uranium. [Proprietary Information]

NIA not applicable.

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• ~ *,*! . NOJITHWtn MlOfCAl ISOTOPU NWMl-2015-021, Rev. 1 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 conditions. The single parameter limit for an ideally reflected and moderated sphere [Proprietary Information] . The single parameter volume limit for a homogeneous [Proprietary Information]. Further evaluation 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-001 . 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 double-contingency principle. This section applies the criticality control features that are 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. Chapter 6.0 provides detailed descriptions of the criticality control features.

The passive design features will include:

• Exclusion of liquid lines (CSE-0I-PDF1)

• Geometry requirements of the basket holding wells within the hot cell (CSE-Ol -PDF2)

• Inline HEPA filter installed in the gas capture hood (CSE-01-PDF3)

The administrative controls will include:

• Limited number of targets that may be in the target disassembly hot cells (CSE-01-AC3)

• Volume limit of the container that collects [Proprietary Information] during disassembly (CSE-Ol-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 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 the [Proprietary Information] collection container.

• IROFS CS-08 controls the geometry of the floor to prevent criticality in the event of spills .

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• . * *

• NORTlfWHT MfDtcAl ISOTOftES 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 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.

4.3.3.5 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 exposure 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 License 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 (NWMI-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 process targets irradiated in the MURR represent the [Proprietary Information]

radionuclide inventory as described in Section 4.1 .

The radionuclide inventory will be based on a weekly throughput of [Proprietary Information] .

Figure 4-56. Target Disassembly In-Process Targets will be [Proprietary Information] receipt to the target disassembly hot cells. During MURR 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.

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• NOAlHWESTMlDICALtlOTOPH NWMl-2015-021, Rev. 1 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. The in-process radionuclide inventory passing through target disassembly 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 target receipt and disassembly activities.

Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target disassembly Decay time after EOI" [Propri etary Info rmation]

Stream descriptionh Targets cladding Di sassembly offgas Di ssolver charge Isotopes Ci 0 241Am [Proprietary Information]

136mBa [Proprietary Information] I [Proprietary Information] [Proprietary Information]

137mBa [Proprietary Information] I [Proprietary Information] [Proprietary Information]

139Ba [Proprietary Information] I [Proprietary Information] [Proprietary Information]

140Ba [Proprietary Information] I [Proprietary Information] [Proprietary Information]

141ce [Propri etary Info rmation] I [Proprietary Info rmation] [Proprietary Information]

143Ce [Proprietary Information] I (Proprietary Information] [Proprietary Information]

144Ce [Proprietary Information] I [Proprietary Information] [Proprietary Information]

242cm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

243Cm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

244Cm (Proprietary Information] I [Proprietary Information] [Proprietary Information]

134Cs [Proprietary Information] I [Proprietary Information] [Proprietary Information]

134mcs [Proprietary Information] I [Proprietary Information] [Proprietary Information]

136Cs [Proprietary Info rmation] I [Propri etary Information] [Proprietary Information]

137 Cs [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1ssEu (Proprietary Information] I [Propri etary Information] (Proprietary Information]

1s6Eu [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1s1Eu (Proprietary Information] I [Propri etary Information] (Proprietary Information]

129J [Proprietary Information] I (Proprietary Information] [Proprietary Information]

1301 (Proprietary Informati on] I [Proprietary Information] (Proprietary Info rmation]

1311 [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1321 [Propri etary Information] I [Propri etary Information] [Proprietary Information]

132mJ [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1331 [Propri etary Information] I [Propri etary Information] (Proprietary Information]

133mJ [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1341 (Proprietary Information] I [Proprietary Information] [Proprietary Information]

135J [Proprietary Information] I [Proprietary Information] [Proprietary Information]

83mKr [Proprietary Informa tion] I [Propri etary Informatio n] [Proprietary Information]

85Kr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

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, ' ~ *,*! . NOkllfWUT MEOtcAL lSOTOPf:S Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target disassembly Decay time after EOI" [Proprietary Information]

Stream descriptionb Targets cladding Disassembly offgas Dissolver charge Isotopes 85mKr [Proprietary Information]

I [Proprietary Information] [Proprietary Information]

87Kr [Proprietary Information]

I [Proprietary Information] [Proprietary Information]

88Kr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

140La [Proprietary Information] I [Proprietary Information] [Proprietary Information]

141La [Proprietary Information] I [Proprietary Information] [Proprietary Information]

142La [Proprietary Information] j [Proprietary Information] [Proprietary Information]

99Mo [Proprietary Information] [Proprietary Information] [Proprietary Information]

95Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

95mNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

96Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

97Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

97mNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

141Nd [Proprietary Information] [Proprietary Information] [Proprietary Information]

236mNp [Proprietary Information] [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

23sNp [Proprietary Information] [Proprietary Information] [Proprietary Information]

239Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

233Pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234mpa [Proprietary Information] [Proprietary Information] [Proprietary Information]

11 2pd [Proprietary Information] [Proprietary Information] [Proprietary Information]

147pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

t48pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

I48mpm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

t49pm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1sopm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1s 1pm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

142pr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

143Pr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

t44pr [Proprietary Information] j [Proprietary Information] [Proprietary Information]

144mpr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

145pr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

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• NOATHWEn MlOtCAl tSOTOH.S NWM l-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target disassembly Decay time after EOI" [Proprietary Information]

Stream descriptionb Targets cladding Disassembly offgas Dissolver charge Isotopes 23sPu [Proprietary Information] [Proprietary Information] [Proprietary Information]

239pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

240pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

24Ipu [Proprietary Information] [Proprietary Information] [Proprietary Information]

103mRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

1osRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

106Rh [Proprietary Information] [Proprietary Information] [Proprietary Information]

106mRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

103Ru [Proprietary Information] [Proprietary Information] [Proprietary Information]

1osRu [Proprietary Information] [Proprietary Information] [Proprietary Information]

106Ru [Proprietary Information] [Proprietary Information] [Proprietary Information]

122sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

124Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

125 [Proprietary Information] [Proprietary Information]

Sb [Proprietary Information]

126Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

127 [Proprietary Information] [Proprietary Information]

Sb [Proprietary Information]

12ssb [Proprietary Information] [Proprietary Information] [Proprietary Information]

12smsb [Proprietary Information] [Proprietary Information] [Proprietary Information]

129Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

153 [Proprietary Information] [Proprietary Information]

Sm [Proprietary Information]

1s6sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

s9sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

90Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

9'Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

92Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

99Tc [Proprietary Information] [Proprietary Information] [Proprietary Information]

99mTc [Proprietary Information] [Proprietary Information] [Proprietary Information]

125mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

121Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

I27mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

129Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

129mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

131Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

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. ~ ! ~,* ! : . NORTHW1ST MfOfCAl ISOTOPES Chapter 4.0 - RPF Description Table 4-33. Target Disassembly In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target disassembly Decay time after EOP [Proprietary Information]

Stream descriptionb Targets cladding Disassembly offgas Dissolver charge Isotopes Cic Cic Cic 131mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

132Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

133Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

133mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

134Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

231Th [Proprietary Information] [Proprietary Information] [Proprietary Information]

234Th [Proprietary Information] [Proprietary Information] [Proprietary Information]

232u [Proprietary Information] [Proprietary Information] [Proprietary Information]

234u [Proprietary Information] [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information] [Proprietary Information]

236u [Proprietary Information] [Proprietary Information] [Proprietary Information]

231u [Proprietary Information] [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information] [Proprietary Information]

131mxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

133 Xe [Proprietary Information] [Proprietary Information] [Proprietary Information]

J33mxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

135 Xe [Proprietary Information] [Proprietary Information] [Proprietary Information]

13smxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

89my [Proprietary Information] [Proprietary Information] [Proprietary Information]

90y [Proprietary Information] I [Proprietary Information] [Proprietary Information]

90my [Proprietary Information] I [Proprietary Information] [Proprietary Information]

9Jy [Proprietary Information] I [Proprietary Information] [Proprietary Information]

9Jmy [Proprietary Information] I [Proprietary Information] [Proprietary Information]

92y 93y

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

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

93zr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

9szr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

91zr [Proprietary Information] j [Proprietary Information] [Proprietary Information]

Total Ci [Proprietary Information] I [Proprietary Information] [Proprietary Information]

• In-process inventory based [Proprietary Information] , neglecting time required to receive and disassemble targets.

b Figure 4-56 provides a simplified description of the process streams.

c In-process inventory based [Proprietary Information] , representing the weekly process throughput. Normal operation expected to prepare a dissolver charge [Proprietary Information] such that the in-process inventory of an individual target disassembly cell is described by one-half the listed radionuclide inventory.

EOI = end of irradiation. MURR = Un iversity of Missouri Research Reactor.

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' ~ * .* ~

• HOfmfW'EST MEDICAi. ISOTOPH 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 levels below 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:

• The workspaces within the target disassembly hot cell s are designed to contain spilled material.

• Alarming 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 following IROFS will be applicable to the target disassembly activities and will provide radiological protection to workers and the public:

• 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).

4.3.3.6 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 chemical form, volume in process, required criticality control 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.

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NORTHWEST MEDtCAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.3.4.1 Process 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 will then dissolve the target material, 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 through the pass-through to a dissolver basket positioned over a dissolver, the target material dissolved, and the resulting solution transferred to the separations step.

Dissolution Process Description The function of the dissolution process is to dissolve the irradiated target material 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 cell 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

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• NORTHWHT ME.DICAl ISOTOPES NWMl-2015-021, Rev. 1 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 used to return the empty collection container into the dissolver 1 hot cell isolation door for transfer back to the target disassembly 1 hot cell (Hl04). 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 target material for a full dissolver batch.

The dissolver design includes a valve arrangement allowing placement and removal of a dissolver basket.

To initiate dissolution, the operator will open the valve assembly, and the dissolver hoist will lift a dissolver basket from the filling station and lower it into the dissolver (DS-D-1 OO/DS-D-200). Markings on the hoist cable will indicate when the basket is at the proper position, and the hoist hook will 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-boiling 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, Overall Summary Material Balance - OSU Target Batch, 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, Irradiated Target Dissolution System Equipment Sizing). Based on these concentrations and a [Proprietary Information].

Dissolution with nitric acid will produce nitrogen oxide gases (NOx) and evolve gaseous fission products.

The offgas treatment is described in the following section. In addition to the gaseous fission products, the intense radiation field in the dissolver will generate hydrogen and oxygen gas in the dissolver 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 flammability limit.

When dissolution is 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 assembly will be opened for dissolver basket removal. The dissolver hoist hook will be lowered down through the valve assembly and into the dissolver until markings on the hoist 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 assembly, and the basket will be placed in the drying area within the hot cell.

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NWMl-2015-021, Rev. 1

, ',~ ~-~! : NORTHWtsTM£01CA1.ISOTOffl Chapter 4.0 - RPF Description Nitrogen or air will be used to purge the dissolver at the end of dissolution. This process will reduce the concentration of radioactive gases in the dissolver to minimize the risk of release into the cell airspace when the dissolver entry valves are opened to allow fresh target material to be added for the next batch.

Between dissolver batches, the dissolver and offgas system will be filled with nitrogen or air to prevent buildup of flammable hydrogen gas mixtures. Continuous sweep gas flow is not expected to be required for hydrogen mitigation during these periods.

Dissolver Offgas Process Description The dissolver offgas will consist of NO,, nitric acid vapors, water vapor, and gaseous fission products (iodine [I], Xe, and Kr). The first step in offgas treatment will be removing the NO, and nitric acid vapors, followed by treatment of the gaseous fission products. The gaseous fission products from the offgas treatment will be mixed with the offgas from the target disassembly activities. Iodine will be absorbed from the offgas stream by the iodine removal unit (IRU). The release of other gaseous fission products will be delayed by adsorption beds to allow sufficient decay. The following subsystems will comprise the dissolver offgas treatment process:

• NO, treatment 1

• NO, treatment 2

• Primary fission gas treatment

• Secondary fission gas treatment

• Waste collection NOx Treatment Description The NO, treatment subsystem will remove NO, nitrogen dioxide (N02), HN03, 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 use in the downstream fission gas retention equipment. The NO, treatment design is based on minimizing total net gas flow from the dissolver and offgas system to minimize impacts to the required fission gas retention equipment size.

Two trains will be provided for NO, treatment, one dedicated to each dissolver (DS-D-1 OO/DS-D-200) where the condensers (DS-E-130/DS-E-230) are mounted above the dissolvers. The downstream equipment for control of fission product gases will be shared between the two dissolver systems. Gas components removed by this system will include nitrogen oxides (NO and N02), and carbon dioxide (C02) gases plus water (H20) and HN03 vapors.

To facilitate the dissolution and offgas treatment processes, a small amount of air or oxygen will be added to the dissolver. A portion of the oxygen will react with the dissolver solution to reduce acid consumption and reduce NO, generation. The balance of the oxygen will mix with the evolved gases and continue to react with nitric oxide (NO) in the downstream process steps.

Secondary reactions between NO, gas species, water, nitric and nitrous acids, and oxygen will take place by the reactions shown in Equation 4-4 and Equation 4-5 . The production of nitric acid will reduce the amount of nitric acid initially required. The N02 produced will be more readily reacted and absorbed by scrubbing solutions.

Equation 4-4 Equation 4-5 4-99 L

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.*:.**.* . NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• ~ -.~ ~ * . NORTHWEST MlDICAl ISOTOPES 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. N02 will be absorbed into the condensate, producing additional HNOJ and NO, while oxygen will react with NO present in the offgas producing additional N02. 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, by reaction with a sodium hydroxide (NaOH) solution to produce a sodium nitrate/nitrite solution. [Proprietary Information] may be added to the scrubber solution if needed to improve NO, removal. Any C02 in the condenser vent stream will also be removed by reaction with NaOH, producing sodium carbonate. Reaction of oxygen 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 radio iodine present in the offgas 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 cooling coil or jacket will 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, . 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, oxidizer (DS-C-340 or DS-C-440), where it will be contacted with a liquid oxidant solution to convert the remaining NO to N02. A number of reagents may be considered for the liquid oxidant, including sodium hypochlorite, 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 gas will flow from the NO, oxidizer to a NO, absorber (DS-C-370 or DS-C-470), where it will be contacted with a solution of [Proprietary Information to remove the remaining N02. Treated gas from the NO, 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, absorber will evacuate the dissolver 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 radioiodine 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.

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, ', ~ ~.*~ : NORTHWEST MEDICAL ISOTOPES 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 NOx treatment systems are expected to retain [Proprietary Information of the iodine from the target material. Each IRU (DS-SB-600A/B/C) is expected to retain [Proprietary Information] of the iodine in its inlet gas stream, and the primary adsorbers (DS-SB-620A/B/C) and iodine guard beds (DS-SB-640A/B/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 expectancy 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 adequately 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 NOx absorbers will flow to IRUs (DS-SB-600A/B/C). The IRUs will 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-640A/B/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 IRUs, the gas stream will flow to gas dryers (DS-E-610A/B/C) and primary adsorbers (DS-SB-620A/B/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 will reduce the radioisotope content sufficiently to allow the decayed noble gases to be safely discharged to the stack. Preliminary information suggests that xenon-133 (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 sequential noble gas retention steps will 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, particulate filter, vacuum receiver tank, vacuum pump, and then to secondary adsorbers. The secondary adsorbers (DS-SB-730A/B/C) will provide an extended delay of xenon, on the order of [Proprietary Information].

The primary and secondary adsorbers will 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-700A/B), located between the primary and secondary adsorbers, will act as buffer tanks for the vacuum system to reduce the cycling and peak capacity requirement for the vacuum pumps.

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. *. ~ ~.~~ .' . NORTHWEST MlDICAL ISOTOPES Waste Collection During normal process operations, liquid wastes will be generated by the primary caustic scrubbers, NOx 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 generated by maintenance operations, such as tank and line flushes . Waste volume estimates have not yet been developed.

The above description provides a detailed account of the SNM in process during the target dissolution activities. The SNM, along with any included fission-product radioactivity, is described in Sections 4.3.4.4 and 4.3.4.5. Based on this description, these operations can be conducted safely in the RPF.

4.3.4.2 Process Equipment Arrangement The target dissolution 1 and target dissolution 2 subsystems will be located along the rows of the processing hot cells within the RPF. The NOx treatment 1, Nox treatment 2, pressure relief, 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.

The dissolver 1 hot cell (H 104) and dissolver 2 hot cell (H 101) location within the rows of the processing hot cells is shown in Figure 4-58. Irradiated target material will be transferred from the target disassembly hot cells to the dissolver hot cells via manipulators. Following dissolution, the uranyl nitrate 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

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. ' ~ -.* ~

• NORTHWESTMEO~AllSOTOPU The equipment arrangement within the dissolver 1 hot cell (HI 04) is shown in Figure 4-59. Irradiated target material in containers will be brought in through the dissolver hot cell isolation door and 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 valve assembly into the dissolver (DS-D-100). During dissolution, the reflux condenser (DS-E-130) will cool the offgas and return water and nitric acid to the dissolvers. The primary caustic scrubber (DS-C-310) will be the first step of the offgas treatment.

[Proprietary Information]

Figure 4-59. Dissolver Hot Cell Equipment Arrangement (Typical of Dissolver 1 Hot Cell and Dissolver 2 Hot Cell) 4-103

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• ~ *.* ~

• NOlllTHWEST MUNCAUSOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The remainder of the offgas treatment equipment will be located in the tank hot cell , as shown in Figure 4-60. The gas from the primary caustic scrubbers will flow to NOx treatment 1 or NOxtreatment 2 and then to the primary fission gas treatment equipment. Liquid waste from the offgas treatment equipment will be pumped to the waste collection equipment.

[Proprietary Information]

Figure 4-60. Target Dissolution System Tank Hot Cell Equipment Arrangement 4-104

. .~ .*..*. NWMI NWMl-2015-021, Rev. 1

. * ~ ~. *! ." NORTifWUT MEDICAL ISOTOPES 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 geometrically 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.

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' ~ * .* ~ ' NORTHWEST MEDICAL ISOTOPlS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The assumed geometry requirement influences the configuration of the dissolvers and offgas treatment columns and liquid waste tanks. For each dissolver, there will be two vertical risers with the required spacing between risers. Each dissolver will be include a vertically oriented condenser that sits on top of one of the risers. Circulation will be induced by an agitator. Offgas from each dissolver condenser will flow directly to dedicated offgas treatment equipment that will include a primary caustic scrubber, NOx oxidizer, and NOx absorber. IRUs, gas dryers, and adsorber systems will be shared between the two dissolver systems and treat gases from the dissolution and target evacuation steps . Pending formal analysis, the geometrically favorable configuration requirements are assumed to apply to the dissolvers, condensers, primary caustic scrubbers, NOx oxidizers, NOx absorbers, and waste collection and sampling tanks. The geometrically favorable configuration requirements are assumed to not apply to the IRUs, gas dryers, and downstream offgas treatment equipment.

Details for design parameters of the processing equipment, including normal operating conditions, are summarized in Table 4-34.

Table 4-34. Irradiated Target Dissolution Process Equipment Operating range Temperature Equipment name Equipment no. oc (oF)a Pressure Dissolver DS-D-100/200 [Proprietary [Proprietary 304L SS [Proprietary [Prop ri etary Info rmation] In format ion] In formation] In formatio n]

Dissolver reflux DS-E-130/230 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary In formation] Information] Information] Information]

condenser NOx treatment (primary DS-C-310/340/370 [Prop ri etary [Prop ri etary 304L SS [Proprietary [Prop ri etary Info rmation] In fo rmatio n] In fo rmation] In forma tion) caustic scrubber, NOx DS-C-410/440/470 oxidizer, and NOx absorber Iodine removal unit DS-SB-600NB/C [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information)

Gas dryer DS-E-61 ON BIC [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Info rm ation] In fo rmation] In fo rmatio n] In fo rmation]

Primary absorber DS-SB-620NB/C [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] In formation] Information]

Iodine guard bed DS-SB-640NB/C [Proprietary [Proprietary 304L SS [Pro prietary [Pro prietary In formation] In formation] Info rmation) In fo rmation]

Secondary absorber DS-SB-730NB/C [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information) Information) Information) Information]

Vacuum receiver tank DS-TK-700N B [Proprietary [Prop rietary 304L SS [Proprietary [Proprietary In fo rmation] Info rmation] In fo rmation] Information]

Waste collection and DS-TK-800/820 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

sampling tanks Pressure relief DS-TK-500 [Proprietary [Proprieta ry 304L SS [Pro prietary [Pro prietary Information] Information] In fo rma tion] In fo rmation]

confinement tank NIA not applicable. SS stainless steel.

NOx = nitrogen oxide. TBD to be determined.

The primary caustic scrubber, NOx oxidizer, and NOx absorber will each be nominal [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 mechanical pump to maintain adequate liquid downflow. The bottom of each column will be a liquid reservoir that holds accumulated scrubber solution.

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~ ~.* ! * , NOftTHWESTMEDICALISOTOPES Chapter 4.0 - RPF Description The IRUs will consist of a sorption bed that uses a Table 4-35. Target Dissolution Auxiliary

[Proprietary Information]. The gas dryers will Equipment each have a vertical pipe heat exchanger Equipment name Equipment no.

[Proprietary Information]. The heat exchanger will be cooled with chilled glycol solution. Dissolver agitator DS-A-100/200 Dissolver offgas pipe cooler DS-E-140/240 The primary and secondary adsorbers will consist Dissolver hoist DS-L-100/200 of carbon-filled columns made from nominal Dissolver basket filler DS-Z-100/200

[Proprietary Information] pipe segments.

Dissolver waste drum port DS-TP-100/200 In addition to the process equipment, auxiliary Venturi eductor DS-ED-300/400 equipment will be used for material handling, NOx treatment solution DS-P-330/360/390 (A/B) pumping, and waste handling. This equipment is pumps DS-P-430/460/490 (A/B) listed in Table 4-35 . Pressure relief tank pump DS-P-510 Fission gas treatment filters DS-F-630A/B/C Process Monitoring and Control Equipment Vacuum pump DS-P-710A/B Process monitoring and control equipment was not Waste collection and DS-TK-800/820 defined during preliminary design. The process sampling tanks descriptions identify the control strategy for Waste tank pumps DS-P-810/830 normal operations, which will set requirements for NOx nitrogen oxide.

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.

4.3.4.4 Special Nuclear Material Description This section provides a summary of the maximum amounts of SNM and the chemical 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. Criticality control features provided will be in accordance with the double-contingency principle, and the RPF will provide suitable defense-in-depth for the contained processes.

Special Nuclear Material Inventory The SNM inventory within the irradiated target dissolution system will be determined by the mass of uranium in a dissolver charge that has been transferred into the dissolver hot cell from the target disassembly hot cell. Irradiated LEU target 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 dissolver charge. [Proprietary Information]. The target dissolution system SNM inventory will be reduced when targets from MURR are being processed [Proprietary Information] .

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. '. ~ ~! ~ ." . NORTHWEST MlDICAl ISOTOPES Table 4-36 summarizes the in-process SNM inventory for an individual target dissolution cell. The target dissolution SNM inventory is [Proprietary Information] (Section 4.3.1). Two dissolution hot cells will be available in the RPF, and both hot cells could contain an in-process inventory at the same time. During dissolution activities, the maximum dissolution cell in-process SNM inventory will vary [Proprietary Information], depending on the target reactor source in a particular operating week. The dissolution system will produce uranium solution 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 range from approximately

[Proprietary Information]. Initial dissolver solution transfers will be followed by a dissolver vessel and transfer line water flush volume ranging from [Proprietary Information]. The design is 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 3 SNM massa Dissolver 1 or dissolver 2 (DS-D-100, [Proprietary Information] [Proprietary Information] [Proprietary Information]

DS-D-200) a SNM concentration and mass represent total amount of LEU (combined mu and mu at :S 19.95 wt% 235U).

b Dissolution reaction changes chemical form from [Proprietary Information] to aqueous uranyl nitrate solution .

c SNM in-process inventory of an individual dissolver hot cell. Two dissolver hot cells are available, and both cells could conta in SNM inventory at the same time.

mu uranium-235 . SNM = special nuclear material.

mu uranium-238 . U = uranium.

LEU low enriched uranium. [Proprietary Information]

Nuclear criticality evaluations performed in NWMI-2015-CRITCALC-002, Irradiated Target Low-Enriched Uranium Material Dissolution , indicate that the target dissolution system vessels remain subcritical under normal and abnormal conditions when all vessels contain solution at a concentration of 750 g U/L after dissolution. NWMI-2015-CSE-002, NWMI Preliminary Criticality Safety Evaluation:

Irradiated Low-Enriched Uranium Target Material Dissolution , describes CSEs of the target dissolution system. The current double-contingency analysis in NWMI-2015-CSE-002 imposes [Proprietary Information] on the dissolution hot cell inventory as a criticality safety control.

Current criticality safety controls are based on single parameter limits under flooded conditions. The single parameter limit for [Proprietary Information]. Further evaluation of the target dissolution hot cell criticality controls will be performed and included in the Operating License Application.

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. ' ! ~.* !

• NO<<THWlSTMEOICALISOTOPES Chapter 4 .0 - RPF Description Criticality Control Features Criticality control features are required in this system, as defined in NWMI-20 l 5-CSE-002. These features, including passive design and active engineered features , allow for adherence to the double-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, respectively, listed below. The passive design features will include geometric constraints of the floor, process 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 control features .

• For the case of a liquid leak, the floor will be criticality-safe (CSE-02-PDF 1), and the floor will have a minimum area to preclude collection ofleaked 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-02-PDF3) and will maintain a subcritical geometry during and after a facility DBE (CSE-02-PDF5 and CSE-02-PDF6). Dissolver design and operability of the ventilation system will preclude pressurization of the process vessels (CSE-02-AFE-l ).

• 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 systems (CSE-02-PDF7 and CSE-02-PDFS).

Some or all of the engineered safety features and admjnistrative 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 Control on Fixed Interaction Spacing oflndividual Tanks," defines maximum tank diameters and minimum spacing between process equipment, which is applicable 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 spills .

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.

• The batch limits in the dissolution hot cell are set conservatively low such that the adrillnistrative 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 rilltigated by the shielding 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.

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". ~ ~-~~ ,' , NOATHWESTMEDICALISOTOPES 4.3.4.5 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 exposure limits 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-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 [Proprietary Information]

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 Figure 4-62. Target Dissolution In-Process dissolver hot cells for processing. Figure 4-62 Radionuclide Inventory Streams provides a simplified description of process 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 disassembly is summarized 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.

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.*.*~ *.~ *.*.

.**.*.* NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

' * ,*

• NORTHWtST lll(DfCM. ISOlWH Table 4-37. Target Dissolution In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target dissolution Decay time after EOI" [Propri etary Information]

Stream descriptionb Dissolver offgas Di ssol ver solution Filter solids Isotopes 24 1Am [Proprietary Information]

136mBa [Proprietary Informatio n] [Propri etary Info rmation] [Proprietary Information]

137mBa [Proprietary Information] [Proprietary Information] [Proprietary Information]

139 Ba [Proprietary Information] [Propri etary Information] [Proprietary Information]

140Ba [Proprietary Information] [Proprietary Information] [Proprietary Information]

141ce [Proprietary Information] [Proprietary Informati on] [Proprietary Information]

143Ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

144Ce [Proprietary Informati on] [Proprietary Info rmation] [Proprietary Informati on]

242cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

243Cm [Proprietary Info rmation] [Proprietary Informati on] [Proprietary Information]

244Cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

134Cs [Proprietary Information] [Propri etary Information] [Propri etary Information]

134mcs [Proprietary Information] [Proprietary Information] [Proprietary Information]

136Cs [Propri etary Informati on] [Propri etary Informatio n] [Proprietary Information]

137 Cs [Proprietary Information] [Proprietary Information] [Proprietary Information]

1ssEu [Proprietary Info rmati on] [Proprietary Informati on] [Propri etary Information]

1s6Eu [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1Eu [Proprietary Info rmation] [Propri etary Informatio n] [Propri etary Informati on]

1291 [Proprietary Information] [Propri etary Information] [Propri etary Information]

130I [Proprietary In fo rmation] [Propri etary Information] [Proprietary Information]

1311 [Proprietary Information] [Proprietary Information] [Proprietary Information]

132I [Proprietary Information] [Propri etary Information] [Propri etary Information]

132mI [Proprietary Information] [Proprietary Information] [Proprietary Information]

my [Proprietary Info rmation] [Proprietary In fo rmation] [Proprietary Information]

133mI [Proprietary Information] [Proprietary Information] [Proprietary Information]

1341 [Proprietary Information] [Proprietary Information] [Propri etary Informati on]

135I [Proprietary Information] [Proprietary Information] [Proprietary Information]

83mK.r [Proprietary Information] [Propri etary Information] [Proprietary Informati on]

85K.r [Proprietary Information] [Proprietary Information] [Proprietary Information]

85mK.r [Proprietary Information] [Propri etary Information] [Proprietary Information]

87Kr [Proprietary Information] [Proprietary Information] [Proprietary Information]

88Kr [Proprietary Information] [Proprietary Info rmatio n] [Proprietary Informati on]

140La [Proprietary Information] [Proprietary Information] [Proprietary Information]

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NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-37. Target Dissolution In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target dissolution Decay time after EOI" [Proprietary Information]

Stream descriptionb Dissolver offgas Dissolver solution Filter solids Isotopes 141La [Proprietary Information] [Proprietary Information] [Proprietary Information]

142La [Proprietary Information] [Proprietary Information] [Proprietary Information]

99Mo [Proprietary Information] [Proprietary Information] [Proprietary Information]

9sNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

95mNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

96Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

97Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

97mNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

141Nd [Proprietary Information] [Proprietary Information] [Proprietary Information]

236mNp [Proprietary Information] [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

23sNp [Proprietary Information] [Proprietary Information] [Proprietary Information]

239Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

233pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234mpa [Proprietary Information] [Proprietary Information] [Proprietary Information]

11 2pd [Proprietary Information] [Proprietary Information] [Proprietary Information]

I47pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

I4Spm [Proprietary Information] [Proprietary Information] [Proprietary Information]

I48mpm [Proprietary Information] [Proprietary Information] [Proprietary Information]

I49pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1sopm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

142Pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

I43pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

1<<pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

144mpr [Proprietary Information] [Proprietary Information] [Proprietary Information]

I45pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

23Spu [Proprietary Information] [Proprietary Information] [Proprietary Information]

239pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

240pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

241pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

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• NWM l-2015-021, Rev. 1 Chapter 4.0 - RPF Description

' ~ *.*! . NCNITNWHT M£0tCAl lSOTOPES Table 4-37. Target Dissolutio n In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target dissolution Decay time after EOI" [Proprietary Information]

Stream descriptionb Dissol ver offgas Dissolver solution Filter solids Isotopes Ci c Ci c Cic 10JmRh 105Rh

[Proprietary Information]

I [Proprietary Information] [Proprietary Information]

106Rh

[Proprietary Information]

I [Proprietary Information] [Proprietary Information]

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

I 106mRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

I 103Ru [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1osRu [Proprietary Information]

I [Proprietary Information] [Proprietary Information]

106Ru [Proprietary Information] I [Proprietary Information] [Proprietary Information]

122 sb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

124Sb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

12ssb [Proprietary Information] J [Proprietary Information] [Proprietary Information]

126Sb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

127 Sb [Proprietary Information] J [Proprietary Information] [Proprietary Information]

128 Sb [Proprietary Information] J [Proprietary Information] [Proprietary Information]

12smsb [Proprietary Information] J [Proprietary Information] [Proprietary Information]

129Sb [Proprietary Information] J [Proprietary Information] [Propri etary Information]

1s1sm [Proprietary Information] J [Proprietary Information] [Proprietary Information]

153 Sm [Proprietary Information]

I [Proprietary Information] [Proprietary Information]

1s6sm [Proprietary Information] I [Proprietary Information] [Proprietary Information]

89Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

I 9osr [Proprietary Information]

I [Proprietary Information] [Proprietary Information]

91sr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

92 Sr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

99Tc [Proprietary Information] I [Proprietary Information] [Proprietary Information]

99mTc 125mTe

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

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

121Te [Proprietary Information] J [Proprietary Information] [Proprietary Information]

127mTe [Proprietary Information] I [Proprietary Information] [Proprietary Information]

129Te [Proprietary Information] J [Proprietary Information] [Proprietary Information]

129mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

I 131Te [Proprietary Information] I [Proprietary Information] [Proprietary Information]

131mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

I 132Te [Proprietary Information] I [Proprietary Information] [Proprietary In formation]

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' ~ *,*! . NORTHWEST M£01CAL lSOTOPlS Table 4-37. Target Dissolution In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Target dissolution Decay time after EOP [Proprietary Information]

Stream descriptionh Dissolver offgas Dissolver solution Filter solids Isotopes t33Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

133mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

t34Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

231Th [Proprietary Information] [Proprietary Information] [Proprietary Information]

234Th [Proprietary Information] [Proprietary Information] [Proprietary Information]

232u [Proprietary Information] [Proprietary Information] [Proprietary Information]

234U [Proprietary Information] [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information] [Proprietary Information]

236u [Proprietary Information] [Proprietary Information] [Proprietary Information]

231u [Proprietary Information] [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Propri etary Information] [Proprietary Information]

u1mxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

133 Xe [Proprietary Information] [Proprietary Information] [Proprietary Information]

t33mxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

135 Xe [Proprietary Information] [Proprietary Information] [Proprietary Information]

1Jsmxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

89my [Proprietary Information] [Proprietary information] [Proprietary Information]

90y [Proprietary Information] [Proprietary Information] [Proprietary Information]

90my [Proprietary Information] [Propri etary Information] [Proprietary Information]

91y [Proprietary Information] [Proprietary Information] [Proprietary Information]

91my [Proprietary Information] [Proprietary Information] [Proprietary Information]

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

93y [Proprietary Information] [Proprietary Information] [Proprietary Information]

93zr [Proprietary Information] [Proprietary Information] [Proprietary Information]

9szr [Proprietary Information] [Proprietary Information] [Proprietary Information]

91zr [Proprietary Information] [Proprietary Information] [Proprietary Information]

Total Ci [Proprietary Information] [Proprietary Information] [Proprietary Information]

• In-process inventory based on [Proprietary Information], neglecting time req uired to receive, disassemble, and dissolve targets.

b Figure 4-62 provides a simplified description of the process streams.

c In-process inventory based [Proprietary Information] , representing the weekly process throughput. Normal operation expected to prepare a dissolver charge containing [Proprietary Information] such that the in-process inventory of an individual target dissolution cell is described by [Proprietary Info rmat ion]

EOI = end of irradiatio n. MURR = Uni versity of Missouri Research Reactor.

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. * ~ * .* ~ ' NOfllTKWHT MEDICAL ISOTOf'H NWMl-2015-02 1, Rev. 1 Chapter 4.0 - RPF Description Dissolver offgas will be treated by the dissolver offgas system to control radionuclide emissions. [Proprietary Information]

The dissolver offgas system includes two groups of unit operations: NOx scrubbers and fission gas treatment. Radionuclides in the dissolver offgas Figure 4-63. Nitrogen Oxide Scrubbers stream listed in Table 4-37 will enter the NOx In-Process Radionuclide Inventory Streams scrubbers, where NOx is removed and the radionuclide inventory is split into two streams (scrubbed gas, and waste), as shown in Figure 4-63 . The maximum in-process radionuclide inventory of the target dissolution offgas streams is listed in Table 4-38 .

Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Invento ry (4 pages)

Item MURR target processing Unit operation NOx scrubbers Decay Time after EOI" [Proprietary Information]

Strea m descriptionh Scrubbed gas Scrubber waste Isotopes 241Am [Proprietary Information]

I36mBa [Proprietary Information] [Proprietary Information]

I37mBa [Proprietary Information] [Proprietary Information]

139Ba [Proprietary Information] [Proprietary Information]

140Ba [Proprietary Information] [Proprietary Information]

141ce [Proprietary Information] [Proprietary Information]

143Ce [Proprietary Information] [Proprietary Information]

144Ce [Proprietary Information] [Proprietary Information]

242cm [Proprietary Information] [Proprietary Information]

243Cm [Proprietary Information] [Proprietary Information]

244Cm [Proprietary Information] [Proprietary Information]

134Cs [Proprietary Information] [Proprietary Information]

t34mcs [Proprietary Information] [Proprietary Information]

136Cs [Proprietary Information] [Proprietary Information]

137 [Proprietary Information] [Proprietary Information]

Cs 1ssEu [Proprietary Information] [Proprietary Information]

1s6Eu [Proprietary Information] [Proprietary Information]

1s1Eu [Proprietary Information] [Proprietary Information]

129J [Proprietary Information] [Proprietary Information]

130J [Proprietary Information] [Proprietary Information]

131 I [Proprietary Information] [Proprietary Information]

132J [Proprietary Information] [Proprietary Information]

132mI [Proprietary Information] [Proprietary Information]

1331 [Proprietary Information] [Proprietary Information]

133mI [Proprietary Information] [Proprietary Information]

134I [Proprietary Information] [Proprietary Information]

135J [Proprietary Information] [Proprietary Information]

83mKr [Proprietary Information] [Proprietary Information]

85Kr [Proprietary Information] [Proprietary Information]

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• ! ~.* ~ .'. NORTHWESTMlDICAl ISOTOPES Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation NOx scrubbers Decay Time after EOP [Proprietary Information]

Stream descriptionb Scrubbed gas Scrubber waste Isotopes 85mKr [Proprietary Information] [Proprietary Information]

87Kr [Proprietary Information] [Proprietary Information]

88Kr [Proprietary Information] [Proprietary Information]

140La [Proprietary Information] [Proprietary Information]

141La [Proprietary Information] [Proprietary Information]

142La [Proprietary Information] [Proprietary Information]

99Mo [Proprietary Information] [Proprietary Information]

95Nb [Proprietary Information] [Proprietary Information]

95mNb [Proprietary Information] [Proprietary Information]

96Nb [Proprietary Information] [Proprietary Information]

97Nb [Proprietary Information] [Proprietary Information]

97mNb [Proprietary Information] [Proprietary Information]

141Nd [Proprietary Information] [Proprietary Information]

236mNp [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary Information]

23sNp [Proprietary Information] [Proprietary Information]

239Np [Proprietary Information] [Proprietary Information]

233pa [Proprietary Information] [Proprietary Information]

234pa [Proprietary Information] [Proprietary Information]

234mpa [Proprietary Information] [Proprietary Information]

112pd [Proprietary Information] [Proprietary Information]

I47pm [Proprietary Information] [Proprietary Information]

I48pm [Proprietary Information] [Proprietary Information]

I48mpm [Proprietary Information] [Proprietary Information]

I49pm [Proprietary Information] [Proprietary Information]

1sopm [Proprietary Information] [Proprietary Information]

1s1pm [Proprietary Information] [Proprietary Information]

I42pr [Proprietary Information] [Proprietary Information]

I43pr [Proprietary Information] [Proprietary Information]

I44pr [Proprietary Information] [Proprietary Information]

I44mpr [Proprietary Information] [Proprietary Information]

I45pr [Proprietary Information] [Proprietary Information]

238pu [Proprietary Information] [Proprietary Information]

239pu [Proprietary Information] [Proprietary Information]

240pu [Proprietary Information] [Proprietary Information]

24Ipu [Proprietary Information] [Proprietary Information]

103mRh [Proprietary Information] [Proprietary Information]

I05Rh [Proprietary Information] [Proprietary Information]

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. '. ~ ~.~~ : NORTHWEST MEDICAL ISOTOPES Chapter 4.0 - RPF Description Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation NOx scrubbers Decay Time after EOP [Proprietary Information]

Stream descriptionh Scrubbed gas Scrubber waste Isotopes 106Rh [Proprietary Information] [Proprietary Information]

106mRh [Proprietary Information] [Proprietary Information]

103Ru [Proprietary Information] [Proprietary Information]

1osRu [Proprietary Information] [Proprietary Information]

106Ru [Proprietary Information] [Proprietary Information]

122 sb [Proprietary Information] [Proprietary Information]

124Sb [Proprietary Information] [Proprietary Information]

125 Sb [Proprietary Information] [Proprietary Information]

126Sb [Proprietary Information] [Proprietary Information]

127 Sb [Proprietary Information] [Proprietary Information]

12ssb [Proprietary Information] [Proprietary Information]

12smsb [Proprietary Information] [Proprietary Information]

129Sb [Proprietary Information] [Proprietary Information]

1s1sm [Proprietary Information] [Proprietary Information]

153 Sm [Proprietary Information] [Proprietary Information]

1s6sm [Proprietary Information] [Proprietary Information]

s9sr [Proprietary Information] [Proprietary Information]

9osr [Proprietary Information] [Proprietary Information]

9'Sr [Proprietary Information] [Proprietary Information]

92 Sr [Proprietary Information] [Proprietary Information]

99Tc [Proprietary Information] [Proprietary Information]

99mTc [Proprietary Information] [Proprietary Information]

I25mTe [Proprietary Information] [Proprietary Information]

121Te [Proprietary Information] [Proprietary Information]

127mTe [Proprietary Information] [Proprietary Information]

129Te [Proprietary Information] [Proprietary Information]

129mTe [Proprietary Information] [Proprietary Information]

131Te [Proprietary Information] [Proprietary Information]

13ImTe [Proprietary Information] [Proprietary Information]

132Te [Proprietary Information] [Proprietary Information]

133Te [Proprietary Information] [Proprietary Information]

133mTe [Proprietary Information] [Proprietary Information]

134Te [Proprietary Information] [Proprietary Information]

231Th [Proprietary Information] [Proprietary Information]

234Th [Proprietary Information] [Proprietary Information]

232u [Proprietary Information] [Proprietary Information]

234U [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information]

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• ~ * ,* ~ . NOfUHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-38. Nitrogen Oxide Scrubbers In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation NOx scrubbers Decay Time after EOI" [Proprietary Information]

Stream descriptionb Scrubbed gas Scrubber waste Isotopes 236u [Proprietary Information] [Proprietary Information]

231u [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information]

131mxe [Proprietary Information] [Proprietary Information]

133 Xe [Proprietary Information] [Proprietary Information]

I33mxe [Proprietary Information] [Proprietary Information]

usxe [Proprietary Information] [Proprietary Information]

13smxe [Proprietary Information] [Proprietary Information]

89my [Proprietary Information] [Proprietary Information]

90y [Proprietary Information] [Proprietary Information]

90my [Proprietary Information] [Proprietary Information]

91 y [Proprietary Information] [Proprietary Information]

9Imy [Proprietary Information] [Proprietary Information]

92y [Proprietary Information] [Proprietary Information]

93y [Proprietary Information] [Proprietary Information]

93zr [Proprietary Information] [Proprietary Information]

9szr [Proprietary Information] [Proprietary Information]

91zr [Proprietary Information] [Proprietary Information]

Total Ci [Proprietary Information] [Proprietary Information]

• In-process inventory based on [Proprietary Information] , neglecting time required to receive, disassemble, and dissolve targets.

b Figure 4-63 provides a simpl ified description of the process streams.

c In-process inventory based on [Proprietary Informatio n] , representing the weekly process throughput. Normal operation expected to prepare a disso lver charge containing [Proprietary Information] such that the in-process inventory of an individual target dissolution offgas system is described by one-half the listed radionuclide inventory.

EOI end of irradiation. NOx = nitrogen oxide.

MURR = Un iversity of Missouri Research Reactor.

Scrubbed gas from the NOx scrubbers and [Proprietary Information]

disassembly offgas will be passed through the fission gas treatment unit operations prior to release via the process vessel ventilation system.

Figure 4-64 provides a simplified description of Figure 4-64. Fission Gas Treatment process streams used to describe the in-process In-Process Radionuclide Inventory Streams radionuclide inventory. The in-process radionuclide inventory entering the fission gas treatment unit operations includes the disassembly offgas stream in Table 4-33 and the scrubbed gas stream in Table 4-38.

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• NORTHWEST MEDtCAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The fission gas treatment system will remove iodine isotopes from gas passing through the system 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 by a holdup of [Proprietary Information] and Xe isotopes will be reduced by a [Proprietary Information].

Iodine is captured on solid materials in the IRUs. The total in-process inventory of captured radionuclides and isotopes 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 isotopes are estimated in NWMI-2013-CALC-011. The bounding estimates produce a total equilibrium in-process inventory on fission gas treatment equipment of

[Proprietary Information] for all iodine isotopes, [Proprietary Information] for all Kr isotopes, and

[Proprietary Information] for all Xe isotopes.

Table 4-39. Fission Gas Treatment In-Process Radionuclide Inventory (3 pages)

Item MURR target processing Item MURR target processing Unit operation: Fission gas treatment IU nit operation: Fission gas treatment Decay time after EOP [Proprietary Information] IDecay time after EOI: [Proprietary Information]

~ Treated target dissolution offgas Strea m d:s~~i. tion: Treated target dissolution offgas 241 Am [Proprietary Information] 239 Pu [Proprietary Information]

136mBa [Proprietary Information] 240Pu [Proprietary Information]

137mBa [Proprietary Information] 241Pu [Proprietary Information]

139Ba [Proprietary Information] 103mRh [Proprietary Information]

140Ba [Proprietary Information] 105Rh [Proprietary Information]

141ce [Proprietary Information] 106Rh [Proprietary Information]

143Ce [Proprietary Information] 106mRh [Proprietary Information]

144Ce [Proprietary Information] 103Ru [Proprietary Information]

242cm [Proprietary Information] 1osRu [Proprietary Information]

243Cm [Proprietary Information] 106Ru [Proprietary Information]

244Cm [Proprietary Information] 122sb [Proprietary Information]

134Cs [Proprietary Information] 124Sb [Proprietary Information]

134mcs [Proprietary Information] 125 Sb [Proprietary Information]

1J6Cs [Proprietary Information] 126Sb [Proprietary Information]

137 127 Cs [Proprietary Information] Sb [Proprietary Information]

1ssEu [Proprietary Information] 128 Sb [Proprietary Information]

1s6Eu [Proprietary Information] 12smsb [Proprietary Information]

1s1Eu [Proprietary Information] 129Sb [Proprietary Information]

1291 [Proprietary Information] 1s1sm [Proprietary Information]

1301 [Proprietary Information] 1s3sm [Proprietary Information]

1311 [Proprietary Information] 1s6sm [Proprietary Information]

132I [Proprietary Information] s9sr [Proprietary Information]

132ml [Proprietary Information] 9osr [Proprietary Information]

1331 [Proprietary Information] 91sr [Proprietary Information]

133ml [Proprietary Information] 92 Sr [Proprietary Information]

1341 [Proprietary Information] 99Tc [Proprietary Information]

1351 [Proprietary Information] 99mTc [Proprietary Information]

83mKrd [Proprietary Information] 125mTe [Proprietary Information]

85Krd [Proprietary Information] 121Te [Proprietary Information]

85mKrd [Proprietary Information] 127mTe [Proprietary Information]

87Krd [Proprietary Information] 129Te [Proprietary Information]

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' ~ *.* ~

• NOATHWtn MlDICAL ISOTOltS Table 4-39. Fission Gas Treatment In-Process Radionuclide Inventory (3 pages)

Item MURR target processing Item MURR target processing Unit operation: Fiss ion gas treatment IUnit operation: Fission gas treatment Decay time after EOI" [Proprietary Information] IDecay time after EOI: [Proprietary Information]

~ Treated tar et dissolution off as Treated target dissolution off as 88Kr d [Proprietary Informatio n] 129mTe [Proprietary Information]

140La [Proprietary Information] 131Te [Proprietary Information]

141La [Propri etary Information] 131mTe [Proprietary Information]

142La [Proprietary Information] 132Te [Proprietary Information]

99Mo [Proprietary Information] 133Te [Proprietary Information]

95Nb [Proprietary Information] 133mTe [Proprietary Information]

95mNb [Proprietary Information] 134Te [Proprietary Information]

96Nb [Proprietary Information] 23 1Th [Proprietary Information]

97Nb [Proprietary Information] 234Th [Proprietary Information]

97mNb [Proprietary Information] 232 u [Proprietary Information]

141Nd [Proprietary Information] 234U [Proprietary Information]

236mNp [Proprietary Information] 23su [Proprietary Information]

231Np [Proprietary Information] 236u [Proprietary Information]

23sNp [Proprietary Information] 231u [Proprietary Information]

239Np [Proprietary Information] 23su [Propri etary Information]

233pa [Proprietary Information] 1J1mxed [Proprietary Information]

234pa [Proprietary Information] m xe d [Proprietary Information]

234mpa [Proprietary Information] 133mxed [Proprietary Information]

112pd [Proprietary Information] 1Jsxe d [Propri etary Information]

J47pm [Proprietary Information] 1Jsmxe d [Proprietary Information]

14sp m [Proprietary Information] 89my [Proprietary Information]

148mpm [Proprietary Information] 90y [Proprietary Information]

J49pm [Prop rietary Informatio n] 90my [Proprietary Information]

1sopm [Proprietary Information] 9Jy [Proprietary Information]

1s1pm [Proprietary Information] 9Jmy [Proprietary Information]

142pr [Proprietary Information] 92y [Proprietary Information]

J43pr [Proprietary Information] 93y [Proprietary Information]

144pr [Proprietary Information] 93zr [Proprietary Information]

144mpr [Proprietary Information] 9szr [Proprietary Information]

145pr [Proprietary Information] 91zr [Proprietary Information]

2Jspu [Propri etary Information] Total Ci [Proprietary Information]

a In-process in ventory based on [Proprietary Information] , eglecting time to receive, di sassemble, and di ssolve targets.

b Figure 4-64 provides a simplified description of the process streams.

c In-process inventory based on [Proprietary Information] , representing the weekly process throughput. Normal operation expected to prepare a disso lver charge containing [Proprietary Informat ion] such that the in-process inventory of an individual target dissolution offgas system is described by one-half the listed radi onuclide inventory.

d Fission gas treatment system based on nobl e gas holdup for decay. System provides [Proprietary Informati on] of Kr isotopes and [Proprietary Information] for Xe isotopes.

EOI end of irradiation. MURR University o f Missouri Research Reactor.

Kr = krypton . Xe xenon .

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0

• .

• NORTHWEST MEO.cAL ISOTOPES 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 1imits 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 likelihood of a 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 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 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 target dissolution offgas treatment, which is part of the hot cell secondary confinement boundary (IROFS RS-03).

4.3.4.6 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 designed into the process systems and components are also identified.

Chemical Inventory Chemicals used for the dissolution and offgas treatment processes will include oxygen gas, nitric acid, NaOH, Na2S03, and hydrogen peroxide solutions. Estimated quantities are listed in Table 4-40.

Table 4-40. Chemical Inventory for the Target Dissolution Area Chemical OSU batch MURR batch Annual quantity 20% (6.1 M) NaOH [Proprietary lnfonnation] [Proprietary Infonnation] [Proprietary lnfonnation]

5% NaOH + 5% Na2S03 solution [Proprietary lnfonnation] [Proprietary In formation] [Proprietary Information]

Hydrogen peroxide (30%) [Proprietary Information] [Proprietary lnformation] [Proprietary lnfonnation]

Nitric acid (10 M) [Proprietary Information] [Proprietary Information] [Proprietary Information]

Nitrogen gas [Proprietary Information] [Proprietary Information] [Proprietary Information]

Oxygen gas [Proprietary lnformation] [Proprietary lnformation] [Proprietary Information]

Note : This table does not include the special nuclear material identified in Table 4-36.

MURR University of Missouri Research Reactor. NaOH sodium hydroxide.

Na2S03 = sodium sulfite. OSU = Oregon State University.

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• ~ * *! . NOATNWUT MlDCAUSOTOPH Chemical Protection Provisions The chemical hazards for target dissolution system are described in Chapter 9.0. Chemicals 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 public 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 4.3.5.1) 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 4.3.5.2 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 exposure, are described in Section 4.3.5.6.

4.3.5. t Process Description The overall function of the Mo recovery and purification system is to extract 99 Mo from uranyl 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 99 Mo, and the U recovery and recycle system will receive the uranyl nitrate solution after the 99 Mo has been extracted.

The Mo recovery and purification flow diagram, Figure 4-65 , illustrates the basic process steps and diagrams the relationships between the five subsystems of the Mo recovery and purification system:

• Primary ion exchange

• Secondary ion exchange

• Tertiary ion exchange

• Molybdenum product

• Mo product handling 4-122

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....... ...*. NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

' ~ * ,* ~

• NORTHWEST M£DICA1. ISOTOPES

[Proprietary Information]

Figure 4-65. Simplified Molybdenum Recovery and Purification Process Flow Diagram Primary Ion Exchange The first set of IX columns (MR-IX-125 and MR-IX-165) will [Proprietary Information], which will retain molybdenum from an acidic solution while allowing other species to pass through. Other species that will be retained to some extent [Proprietary Information] .

The feed tanks (MR-TK-100 and MR-TK-140) for the primary IX subsystem will be located in the tank hot cell (H014), and the primary IX columns will be located in the Mo recovery hot cell (Hl06).

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• ~ *,*! ' NOkTM'WlST Ml.DICAl ISOTDPU The column operation will consist of pumping a sequence of solutions through the IX media (summarized in Table 4-4 l ). Column effluents will be routed to different vessels during a process cycle, depending on the processing step. The column operations wil l include the following.

• Loading cycle - Uranyl nitrate solution Table 4-41. Typical Ion Exchange Colu mn Cycle with 99 Mo will be pumped to the columns from the feed tanks to retain 99 Mo from the Column feed solution. [Proprietary Information]. Cycle solution Loading [Proprietary [Proprietary [Proprietary Column effluent during the loading cycle In formation] Information] In formation]

will be routed to the U recovery and [Proprietary [Proprietary [Proprietary Pre-elution rinse recycle system. Informat ion] Information] Information]

Elution [Proprietary [Proprietary [Proprietary

• Pre-elution rinse cycle - To ensure that In fo rmat ion] Information] Information]

the 99 Mo in the solution has had a chance Regeneration [Proprietary [Proprietary [Proprietary Information] Information] Information]

to load onto the column, a water rinse solution will be pumped from the chemical BY bed vo lume addition hood (MR-EN-110) through the HNOJ nitric acid.

Na OH sodium hydroxide.

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]. This solution will be pumped from the chemical addition hood (MR-EN-110). Molybdenum will be eluted off the column, and the effluent from the column will be routed to the Mo purification feed tank #2 (MR-TK-200).

• Regeneration step cycle - Restoring the column to a nitric acid condition will be done by rinsing the column with a [Proprietary Information]. Column effluent will be directed to the waste handling system.

Secondary Ion Exc hange The eluate from the primary IX column will be adjusted with [Proprietary Information] will be fed by 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 (Hl06). The [Proprietary Information] state so that it does not adsorb to the secondary IX column (MR-IX-225).

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' ~ * ,* ~ ' NOlfTHWEST MlDfCAL ISOTOPES Chapter 4.0 - RPF Description The second product recovery and purification IX column will be a [Proprietary Information] form Table 4-42. Strong Basic Anion Exchange prior to use. The column operation will consist of Column Cycle pumping a sequence of solutions (listed in 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.

• Loading cycle - Mo solution will be fed Loading Cycle Pre-elution rinse Column feed solution

[Proprietary In format ion]

[Proprietary In fo rmation]

[Proprietary

[Proprietary Informat ion]

[Proprietary Information]

[Proprietary

[Proprietary Info rmation]

[Proprietary Information]

[Proprietary Elution Information] Informa tion] In format ion]

to the column during the loading cycle to Regeneration (first) [Proprietary [Proprietary [Proprietary retain the Mo from the solution. The In formation] Information] Information]

material will adsorb [Proprietary Regeneration [Proprietary [Proprietary [Proprietary Information] of the incoming Mo, along In forma tion] Info rmation] Information]

(second) with only a trace of the [Proprietary [Proprietary [Proprietary [Proprietary Preconditioning Information] noted earlier. Column Information] Information] Information]

effluent during the loading cycle will be BY = bed volume routed to the waste handling system.

• 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 (Hl07).

• 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-EN-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 (H l 07), 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.

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• NORTifWHT MEDICAL JSOTCftl NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The eluate from the secondary IX media will require [Proprietary Information]. The third IX media will

[Proprietary Information] and the column (MR-IX-325) will be operated as described for the primary IX column. The exception is that during the loading cycle, the effluent will be directed to the waste handling subsystem. The volume of feed material to thi s column 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).

Molybdenu m Prod uct Once the 99 Mo product solution is eluted, a small amount of bleach solution will be added and samples taken for verification of product specifications, which are listed in Table 4-43. The product from one

[Proprietary Information] with a small amount of [Proprietary Information] added. This product will have an instantaneous 99 Mo content as high as [Proprietary Information] , depending on the time between the EOI and the molybdenum recovery.

Table 4-43. P urified Molybdenu m P r oduct Specification Item Lantheus requirement Mallinckrodt requirements Chemical form* [Proprietary Information] [Proprietary Information]

Specific activity [Proprietary Information] [Proprietary Information]

Concentrationb [Proprietary Information] [Proprietary Information]

Radiopurity"*d [Proprietary Information] [Proprietary Information]

Gamma [Propri etary Information] [Proprietary Information]

Other gammas [Proprietary Information] [Proprietary Information]

(excluding 99 mTc)

Beta [Proprietary Info rmation] [Proprietary Information]

Alpha [Proprietary Information] [Proprietary Information]

Source: NWMI-2013-049, Process System Functional Specification, Rev. C, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

• Product is normall y stabilized by addition [Proprietary Informatio n]

b Acti vity and co ncentrati on specifications are at buyer's calibration time.

c Radiopurity specifications are at 72 hr after buyer's official receipt time.

d Assay accuracy of material deli vered will be +/-5% of labeled value.

e Based on vendor's calibration date.

Na2MoQ4 = sodium molybdate. Na OH = sodium hydrox ide.

aOC I = sodium hypochlorite.

The operators will fill and weigh the 99 Mo product via the product holder/scale (MR-Z-420) from the product tank. Using hot cell manipulators, the operator wi ll fill the designated product vessels and transfer the product vessel containing the 99 Mo product to the capping unit (MR-Z-430). The 99 Mo product vessel will then be capped, sealed, and prepared for transfer to the product and sample hot cell (H 108) via an isolation door.

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' * ~ *.* ~

• NOATNWESTM£DtCAllSOTOH:S 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 Figure 4-66.

[Proprietary Information]

Figure 4-66. Molybdenum Product Hot Cell Equipment Arrangement 4-127

....... . NWMI

~*

' ~ *,*! . NORTKWEn M£DICA1. tsOTOltfS NWMl-2015-021, Rev. 1 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 Arrangement 4-128

.~ . .;.*.*NWMI

' * ~ *.* ~ ; NORTHWUTMEOrtALISOTOPES NWMl-2015-021, Rev. 1 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 seal the container with the capping unit (MR-Z-430). Product containers will be transferred by manipulators through the isolation door to the product and sample hot cell (H l 08).

[Proprietary Information]

Figure 4-68. Molybdenum Purification Hot Cell Equipment Arrangement 4-129

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

' ~* * ~

• NORTifWUT MlrMCAl '50TOl'(S NWMl-2015-021, Rev. 1 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

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

. * ~ *.*!

• NOtllHWEST MEOtCAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The tanks feeding the uranyl nitrate solution (MR-TK-100 and MR-TK-140), the tank collecting the post-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 (H014A), as shown 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 4.3.5.1) 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, which includes chemical feed equipment, chillers, and handling equipment, is listed in Table 4-45.

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NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description I ' ~ -.* ~

• NOUHWEITMEDICAltSOTOf'l:I Table 4-44. Molybdenum Recover y and Pu rification Process Equipment Individual Criticality-Equipment tank safe by Tank Temperature Pressure Equipment name no. capacity geometry material °C atm

[ Proprietary [Proprietary Informat ion] [Proprietary Feed tank IA MR-TK-100 Information]

Yes 304L SS In fo rmatio n]

( Proprietary Yes TBD [Proprietary Informatio n) [Proprietary IX column IA feed pump MR-P- 120 Info rmation] Informat ion]

(Prop rietary [ Proprietary Information] [Proprietary IX column IA MR-IX-125 Informat ion]

Yes 304L SS Information)

(Proprietary [Proprietary lnformat km] [Proprietary Feed tank IB MR-TK-140 In fo rmatio n]

Yes 304L SS Info rmation)

[Proprietary (Proprietary Informatio n] [Proprietary IX column IB feed pump MR-P-150 Informatio n]

Yes TBD Informat ion]

[Proprietary Yes 304L SS [Proprietary Informatio n] [Proprietary IX column IB MR-IX-165 Informatio n) lnformatKm]

[Proprietary [ Proprietary In formatio n] [ Proprietary U solution collection tank MR-TK-180 In format io n]

Yes 304L SS Information]

[Proprietary TBD [Proprietary Info rmatio n] [Proprietary U solution tank pump MR-P-190 Informat io n]

Yes In formation]

MR-TK-200 [Proprietary Yes 304L SS [Proprietary In forma tion] [Proprietary Feed tank 2 In fo rma tio n) Informat ion]

[Proprietary TBD (Proprietary Information] [Proprietary IX column 2 feed pump MR-P-2 10 Informat ion)

Yes Info rmation]

MR-IX-225 [Proprietary Yes 304L SS [Proprietary Informatio n] [Proprietary IX column 2 Info rmation] Information]

MR-TK-300 [ Proprietary Yes 304L SS [Proprietary Informatio n] [Proprietary Feed tank 3 In fo rmation] Informatio n]

[Pro prietary [Proprietary Informat ion] [Proprietary IX column 3 feed pump MR-P-310 Info rmation]

Yes TBD Information)

[Proprietary {Proprietary Informat ion] [Proprietary IX column 3 MR- IX-325 Information]

Yes 304L SS Informat ion)

MR-TK-340 [Proprietary 304L SS (Proprietary Informatio n] [Proprietary Waste collection tank Information]

Yes Informatio n]

MR-P-350 [Proprietary TBD [Proprietary Informatio n) [Proprietary Waste collection tank pump Information]

Yes Information)

MR-TK-400 [Proprietary 304L SS (Proprietary Information) {Pro prietary Product tank Informatio n]

Yes Informatio n]

[Proprietary (Proprietary Information] [Proprietary Product tank pump MR-P-410 Informatio n]

Yes TBD Informatio n]

IX ion exchange. TBD to be determ ined.

NIA not applicab le. u uranmm .

SS stainless steel.

Table 4-45. Molybdenum Recovery and Purification Auxiliary Equipment Equipment name Equipment no. Equipment name Equipment no.

Chemical addition hood MR-EN- 110 IX column 3 filter MR-F-320 IX column l chemical pump MR-P-115/ 155 Chiller 3 MR-Z-330 IX column I filter MR-F-1 20/ 160 Product ho lder/scale MR-Z-420 Chiller I MR-Z-13011 70 Capping unit MR-Z-430 IX column 2 chemical pump MR-P-2 15 Product and sample hot cell MR-EN-400 IX column 2 filter MR-F-220 Product transfer port MR-TP-400 Chi ller 2 MR-Z-23 0 Sample transfer port MR-TP-4 10 Mo purification hot cell MR-EN-300 Product and sample hoist MR-L-400 IX column 3 chemical pump MR-P-315 IX ion exchange. Mo molybdenum.

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• ~ * ,* ~ ' NORTHWEST MEDICAL ISOTOf'H 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 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. Additional 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 chemical 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. Criticality control features provided will be in accordance with the double-contingency principle, and the RPF will provide suitable defense-in-depth for the contained processes.

Special Nuclear Material Inventory The SNM inventory within the Mo recovery and purification system will be determined by the uranium in dissolver solution transfers into the IX column ! N IB feed tanks (MR-TK-100 and MR-TK-140).

Dissolver solution in the feed tanks will be passed through IX columns IA and lB (MR-IX-125 and MR-IX-165). During the IX column ! N IB 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 l N lB 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 also contain only trace uranium quantities.

Individual irradiated target dissolver solution transfers to the IX column lA/ lB 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] Table 4-46 summarizes the in-process SNM inventory for Mo recovery and purification SNM vessels 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 alternative transfer sequences from target dissolution, the solution concentration in [Proprietary Information], after the initial dissolver solution transfer.

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• NOUHWEST MlotCAl ISOTOHI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The uranium concentration wil l range from [Proprietary Information] (MR-TK-180) based on the solution concentration range after combination of dissol ver solution and flush water. Waste collected in MR-TK-340 will contain only trace uranium quantities. All vessels 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 3 Feed tank 1A - (MR-TK-100) [Proprietary ln fonnation] [Proprietary [Proprietary ln fonnation] lnfonnat ion]

Feed tank lB -(MR-TK-140) [Proprietary Information] [Proprietary [Proprietary lnfonnation] Information]

U so lution collection tank (MR-TK-180) [Proprietary ln fo nnation] [Proprietary [Proprietary In formation] lnfonnat ion]

Mo system waste collection tank (MR-TK-340) [Proprietary Information] [Proprietary [Proprietary lnfonnation] Information]

Mo system ion exchange vessels (MR-IX-1 25/165) [Proprietary ln fonnat ion] [Proprietary (Proprietary ln fonnation] In formation ]

• S M concentration and mass represent total amount of LEU (combined mu and mu at ~ 19.95 wt% mu) b Aq ueous solution of uranyl nitrate c Used as a transfer tank for feed tank so lutions after ion exchange column processing. The SNM in-process inventory is described by the co ntents of a single feed tank during normal operation. In ventory is limited to solution in two of the three tanks MR-TK-100, MR-TK-14 , and MR-TK- 180.

d Aqueous so lution with trace quantities of uranium ions that may be present in a variety of chemical forms .

e Based on two ion exchange columns, each with vo lume of0. 15 L mu uranium-235. Mo molybdenum.

mu uranium-238 . SNM special nuclea r material.

LEU low-enriched uranium. U uranium.

Feed tank IA and feed tank 1B were sized to contain solution from [Proprietary Information]. Therefore, the maximum inventory of each feed tank is described by solution from dissolution of [Proprietary Information] . Logistics to minimize the time for preparation of a 99 Mo product batch during MURR target 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 generated by processing material from a feed tank through IX column 1A or IX column 1B. Therefore, the bounding in-process SNM 99 Mo system inventory is descri bed by the contents of the two feed tanks during normal operation.

Nuclear criticality evaluations performed in NWMI-2015-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 subcritical under normal and abnormal conditions when all vessels contain solution at a [Proprietary Information]. NWMI-2015-CSE-003, NWMI Preliminary Criticality Safety Evaluation: Molybdenum-99 Product Recovery, describes CSEs of the Mo recovery and purification system. The current double-contingency 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 system criticality controls will be performed and included in the Operating License Application.

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• ~ *.* ~ * "°"TMWHTMEDICAllSOTOPU 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 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, respectively, listed below. The passive design features will include geometric constraints of the floor, process 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, ventilation 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-PDFl ), 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 ventilation system will preclude pressurization of the process vessels (CSE-03-AFE-l ).

• The molybdenum 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-PDFS).

• The internal volume for the molybdenum local chiller will be limited (CSE-03-PDF 10) .

• 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 systems (CSE-03-PDFl 1 and CSE-03-PDF12).

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 Mo recovery and purification activities.

• IROFS CS-02 sets batch limits on samples .

• IROFS CS-04 affects location, spacing, and design of workstations .

• IROFS CS-07 defines maximum tank diameters and minimum spacing between process equipment, which is applicable to the feed tanks, IX columns, and waste collection tanks.

• IROFS CS-08 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 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.

• Under normal conditions, the product samples 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 stored, as described in Chapter 6.0.

• The effects of a criticality accident are mitigated by the shielding described in Section 4.2 .

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! 0 NOfUtfWUT MlDtCAl lSOTOPf.S NWMl-2015-021, Rev. 1 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 the 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

[Proprietary Information]

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 Figure 4-71. Molybdenum Recovery and operation will store large solution volumes in the Purification In-Process Radionuclide tank hot cell. Therefore, the in-process inventory Inventory Streams of the Mo recovery and purification hot cells 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.

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. ' ! *.* ! ' NORTHWEST M£0fCAl ISOTOPES Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Mo recovery and purification Decay time after EOI" [Proprietary Information] [Proprietary Information] [Proprietary Information]

Stream descriptionb Impure U Mo product Mo IX waste Isotopes 241Am [Proprietary Information]

136mBa [Proprietary Information] [Proprietary Information] [Proprietary Information]

137mBa [Proprietary Information] [Proprietary Information] [Proprietary Information]

139Ba [Proprietary Information] [Proprietary Information] [Proprietary Information]

140Ba [Proprietary Information] [Proprietary Information] [Proprietary Information]

141ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

t43Ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

144Ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

242cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

243Cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

244Cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

134Cs [Proprietary Information] [Proprietary Information] [Proprietary Information]

t34mcs [Proprietary Information] [Proprietary Information] [Proprietary Information]

136Cs [Proprietary Information] [Proprietary Information] [Propri etary Information]

137 Cs [Proprietary Information] [Proprietary Information] [Proprietary Information]

1ssEu [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s6Eu [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1Eu [Proprietary Information] [Proprietary Information] [Proprietary Information]

1291 [Proprietary Information] [Proprietary Information] [Proprietary Information]

1301 [Proprietary Information] [Proprietary Information] [Proprietary Information]

1311 [Proprietary Information] I [Proprietary Information] [Proprietary Information]

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

132mJ [Proprietary Information] [Proprietary Information] [Proprietary Information]

1331 [Proprietary Information] [Proprietary Information] [Proprietary Information]

133ml [Proprietary Information] [Proprietary Information] [Proprietary Information]

134J [Proprietary Information] [Proprietary Information] [Proprietary Information]

1351 [Proprietary Information] [Proprietary Information] [Proprietary Information]

83mKr [Proprietary Information] [Proprietary Information] [Proprietary Information]

85Kr [Proprietary Information] [Proprietary Information] [Proprietary Information]

85mKr [Proprietary Information] [Proprietary Information] [Proprietary Information]

87Kr [Proprietary Information] [Proprietary Information] [Proprietary Information]

88Kr [Proprietary Information] [Proprietary Information] [Proprietary Information]

140La [Proprietary Information] [Proprietary Information] [Proprietary Information]

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• NOITHWHT MlOICAL tsOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Mo recovery and purification Decay time after EOI" [Proprietary Information] [Proprietary Information] [Proprietary Information]

Stream descriptionb Impure U Mo product Mo IX waste Isotopes t4'La [Proprietary Information] I [Proprietary Information] [Proprietary Information]

t42La [Proprietary Information] I [Proprietary Information] [Proprietary Information]

99Mo [Proprietary Information] I [Proprietary Information] [Proprietary Information]

95Nb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

95mNb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

96Nb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

97Nb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

97mNb [Proprietary Information] I [Proprietary Information] [Proprietary Information]

141Nd [Proprietary Information] I [Proprietary Information] [Proprietary Information]

2J6mNp [Proprietary Information] I [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

2JsNp [Proprietary lnformati on] [Proprietary Information] [Proprietary Information]

239Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

233pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234mpa [Proprietary Information] [Proprietary Information] [Proprietary Information]

11 2pd [Proprietary Information] [Proprietary Information] [Proprietary Information]

147pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

14spm [Proprietary Information] [Proprietary Information] [Proprietary Information]

148mpm [Proprietary Information] [Proprietary Information] [Proprietary Information]

149pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1sopm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s 1pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

142Pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

t43pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

144pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

144mpr [Proprietary Information] [Proprietary Information] [Proprietary Information]

145pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

238pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

239pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

240pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

241pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

103m Rh [Proprietary Information] [Proprietary Information] [Proprietary Information]

105Rh [Proprietary Information] [Proprietary Information] [Proprietary Information]

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• NORTHWElTM£0tCAltSOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Mo recovery and purification Decay time after EOI" [Proprietary Information] [Proprietary Information] [Proprietary Information]

Stream descriptionh Impure U Mo product Mo IX waste Isotopes 106Rh [Proprietary Information] [Proprietary Information] [Propri etary Information]

106mRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

103Ru [Proprietary Information] [Proprietary Information] [Proprietary Information]

1osRu [Proprietary Information] [Proprietary Information] [Proprietary Information]

106Ru [Proprietary Information] [Proprietary Information] [Proprietary Information]

122sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

124Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

12ssb [Proprietary Information] [Proprietary Information] [Proprietary Information]

126Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

127 Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

12ssb [Proprietary Information] [Proprietary Information] [Proprietary Information]

12smsb [Proprietary Information] [Proprietary Information] [Proprietary Information]

129Sb [Proprietary Information] [Propri etary Information] [Proprietary Information]

1s1sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1sJ sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s6sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

s9sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

9osr [Proprietary Information] [Proprietary Information] [Proprietary Information]

91Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

92 Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

99Tc [Proprietary Information] [Proprietary Information] [Proprietary Information]

99mTc [Proprietary Information] [Proprietary Information] [Proprietary Information]

125mTe [Proprietary Information] [Proprietary Information] [Propri etary Information]

121Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

127mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

129Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

129mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

1J1Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

13 1mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

132Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

133Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

133mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

134Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

23 1Th [Proprietary Information] [Proprietary Information] [Proprietary Information]

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• NORTHWHTMEDICALllOTOHI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-47. Molybdenum Recovery and Purification In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation Mo recovery and purification Decay time after EOI" [Proprietary Information] [Proprietary Information] [Proprietary Information]

Stream descriptionb Impure U Mo product Mo IX waste Isotopes 234Th [Proprietary Information] [Proprietary Information] [Proprietary Information]

232u [Proprietary Information] [Proprietary Information] [Proprietary Information]

234U [Proprietary Information] [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information] [Proprietary Information]

236u [Proprietary Information] [Proprietary Information] [Proprietary Information]

231u [Proprietary Information] [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information] [Proprietary Information]

t3tmxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

133 Xe [Proprietary Information] [Proprietary Information] [Proprietary Information]

t33mxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

135 Xe [Proprietary Informatio n] [Proprietary Information] [Proprietary Information]

t3smxe [Proprietary Information] [Proprietary Information] [Proprietary Information]

89my [Proprietary Information] [Proprietary Information] [Proprietary Information]

90y [Proprietary Information] [Proprietary Information] [Proprietary Information]

90my [Proprietary Information] [Proprietary Information] [Propri etary Information]

9ty [Proprietary Information] [Proprietary Information] [Proprietary Information]

9tmy [Proprietary Information] [Proprietary Information] [Proprietary Information]

92y [Proprietary Information] [Proprietary Information] [Proprietary Information]

93y [Proprietary Information] [Proprietary Information] [Proprietary Information]

93zr [Proprietary Information] [Proprietary Information] [Proprietary Information]

9szr [Proprietary Information] [Proprietary Information] [Proprietary Information]

91zr [Proprietary Information] [Proprietary Information] [Proprietary Information]

Total Ci [Proprietary Information] [Proprietary Information] [Proprietary Information]

• In-process inventory based on decay time rangi ng fro m [Proprietary Information] , disassemble, and dissolve targets for transfer to the first stage Mo IX feed tank and describe the generation of impure U. An [Proprietary Info rmation] of process time is allowed to complete recovery and purification acti vities to describe the Mo product and Mo IX waste generated. The allocations produce decay times ranging from [Proprietary Information] when combined with a minimum receipt target decay of

[Proprietary Information].

b Figure 4-7 1 provides a simplified description of the process streams.

c In-process inventory based [Proprietary Information], representing the [Proprietary Information] throughput. No rmal operation stores large solution vo lumes in the tank hot cell. Therefore, the in-process inventory of Mo recovery and purification hot cells is described by a small fraction of the impure U and Mo IX waste streams, combined with the total Mo product stream.

EOI end of irradiation. MURR University of Missouri Research Reactor.

IX ion exchange. u = uranium.

Mo molybdenum.

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, ' ! *.* ! ' NORTHWEST MEDtcALISOTOPU NWMl-2015-021, Rev. 1 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:

• 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).

4.3.5.6 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.

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• ~ * .* ~ ' NOftTHWHT MlDtCAI. tSOTOPIS NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description Table 4-48. Chemical Inventory for the Molybdenum Recovery and Purification Area OSU cycle MURR cycle Annual Chemical (L) (L) (L)a

[Proprietary lnfonnation] [Proprietary [Proprietary [Propri etary In fonnation] In fonnation] Infonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation]

[Proprietary lnfo nnation] [Proprietary [Propri etary [Proprietary In fo nnation] lnfonnation] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary In fonnation] lnfonnation] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] ln fonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnati on] lnfonnation]

[Proprietary ln fonnation] [Propri etary [Propri etary [Proprietary ln fonnation] ln fonnation] lnfonnation]

Note: This table does not include the special nuclear material identified in Table 4-46 .

a Computed as eight OSU campaigns of 30 targets, and 44 MURR campaigns of eight targets per year.

[Proprietary Info nnation] [Proprietary In formation]

[Proprietary Information] [Proprietary Information]

IX ion exchange. [Proprietary Information]

Mo = molybdenum. OSU = Oregon State Un ivers ity.

MURR = Un iversity of Mi ssouri Research Reactor. [Proprietary Information]

[Proprietary Information]

Chemical Protection Provisions The chemical hazards for the Mo recovery and purification system are described in Chapter 9.0.

Chemicals 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 public from exposure to hazardous chemicals.

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. ' ~ *.*! * . NOfllTHWHT MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 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 of Irradiated Special 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 of SNM in terms of physical and chemical form, volume in process, required criticality control features, and radioactive inventory in process is provided in Sections 4.4.1.4 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]

Figure 4-72. Uranium Recovery and Recycle Process Functions 4-143

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' ~ * *! . NORTHWEST MlDtCAl ISOTOftf:S NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The U recovery and recycle process will include three weeks of lag storage for feed solution 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 concentrated to control the stored volume of process solutions. Uranium from the first cycle will be purified by a nearly identical second-cycle system to reduce fission product contaminants to satisfy product criteria. 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 also 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

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. * ~ *.*! . NORTHWEST M£01CAllSOTOflfS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The process was divided into the following five major subsystems for design 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 final 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 process 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 delay 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 solutions 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 recycle to the target fabrication system. The goal operating time is to complete the weekly process load in [Proprietary Information]. Equipment sizing is based on processing feed solution from [Proprietary Information]. Throughput tum-down associated with [Proprietary Information] from the MURR reactor will be accomplished by processing fewer sub-batches [Proprietary Information] in the U recovery and recycle system equipment during a particular operating week.

A simplified process flow diagram for the U recovery and recycle system, indicating the major process 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.

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• NORTHWEn MlOtcAl ISOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

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 and recycle system will consist of uranium-bearing solutions generated by the first cycle of the Mo purification system, which will be accumulated in the impure U collection tanks. These vessels will provide a lag storage capability between the Mo purification and the uranium system equipment. The uranium-bearing solution has a nominal composition of approximately [Proprietary Information] when processing targets from MURR based on the material balance described in NWMI-20 l 3-CALC-006. The uranium-bearing solution concentration is increased to approximately

[Proprietary Information] when processing targets from the OSU reactor to reduce the solution volume stored by the impure U collection tanks.

Solution will be pumped from the Mo purification system feed tank through the IX beds to the impure U collection tanks. Tank capacity, when combined with the first-cycle uranium recovery IX feed tank, will be sized to contain feed solution lag storage such that uranium processed has been decayed at least

[Proprietary Information].

The vessel contents will be maintained at a nominal temperature of [Proprietary Information] by cooling jackets while residing in the lag storage tanks. Radiolytic decay is considered the primary heat source of solutions stored in these vessels, and the solution will be maintained at the IX media operating temperature to reduce evaporation during the decay storage time. Storage temperature control will also minimize the time required for temperature adjustment when preparing a feed batch for the IX system.

No system-specific offgas treatment will be provided for this vessel. However, the potential exists for iodine-131 (' 31I) to evolve in offgas from this vessel, and the vent system supporting the vessel is assumed to require treatment to control the iodine emissions.

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. * ~ *,*! ' NOltTHWUT MEDtCM. ISOTOPl.S NWMl-2015-021, Rev. 1 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 indicates that the reduction reaction is essentially complete in [Proprietary Information]. Holding reductant is added at a ratio of [Proprietary Information].

131 No system-specific offgas treatment will be provided for this vessel. However, the potential exists for 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 analytical chemistry sample 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 sizing (NWMI-2013-CALC-009, Uranium Purification System Equipment Sizing).

The uranium recovery column operation will consist of processing a sequence of solutions 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 IX feed tanks will be fed to the uranium recovery column during the loading cycle to capture uranium in the liquid phase on the IX media, allowing contaminants (e.g., fission products and plutonium) to pass through the column. [Proprietary Information]. Column effluent during the loading cycle will 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 considered a solution with potential contaminants at the end of the loading cycle.

The effluent composition is projected to be [Proprietary Information].

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• HOITNWHT MlDtCA&.ISOTOPfS

• 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 #1 during 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 replacing the liquid phase with a solution composition similar to the adjusted impure uranium feed solution. The column feed will be switched to a solution 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 Information].

Separation of the uranium system from the other major processes will provide the flexibility to select a column size to support the operation. NWMI-2013-CALC-009 performed a sensitivity study of column size 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 batches with the cost of maintaining a larger resin inventory in the facility. While not formally optimized, the sizing comparison selected a column size based on processing the uranium throughput in [Proprietary Information].

This allows a total [Proprietary Information] for processing each feed batch to complete 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 required to complete each cycle. The flows and volumes are based on a two-column system, operating in parallel, with a [Proprietary Information]. The two-column system was selected to achieve the required throughput using columns that satisfy geometrically favorable dimensions for criticality control. Pressure drop across a resin bed at the indicated flow rates is currently predicted to range from approximately [Proprietary Information].

Table 4-49. First-Cycle Uranium Recovery Ion Exchange Column Cycle Summary Loading Pre-elution rinse Elution Cycle Fluid

[Pro prietary In formatio n)

(Proprietary Information]

(P ro prietary Informa tio n]

[Pro prietary Informat io n]

[Proprietary Informa tio n]

(Prop rietary In forma tio n]

Dimensionless volume

[Proprietary In fo rmatio n)

[Propriet ary In fo rmatio n]

(Proprietary In fo rmation]

[Proprietary In for mation]

[Proprietary Information]

[Proprietar y Info rma tio n]

[Pro prietary Information]

[Proprietary Information]

[Proprietary Informat io n]

[Pro prietary Info rmation)

(Proprietary In fo rmat ion]

[Proprietary In fo rmatio n]

(Proprietary Informatio n] (Proprietary [Proprietary Informatio n] [Propriet ary [Proprietary [Proprietary Regeneration In fo rmatio n] In fo rmation] Information] Informat ion]

Note: Vo lumes and flow rates for a single process batch use two columns operating in parallel with a [Proprietary Information]

in each column . This information is provided for a single column in the two parall el column system. The recycled uran ium is processed in [Proprietary Informati on] during an individual week of operation.

BY bed volume. [Proprietary Information]

CV = column vo lume. [Proprietary Information]

Resin performance data provided by the vendor is at [Proprietary Information] which is used for the column operating conditions. Temperature control is provided for column feed streams and not on the IX column itself (no cooling jacket on column). Decay heat was evaluated as the primary heat 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.

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• NORTHWESTMEOtCAl.ISOTOf'ES Chapter 4.0 - RPF Description Primary Concentration The primary concentration subsystem will receive solution from the primary 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 system-specific offgas treatment will be provided for this vessel.

Uranium Concentrator/Condenser #1 (UR-Z-320)

The uranium concentrator/condenser #l 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 # l , 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 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] 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 # l 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 .

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[Proprietary Information]

Source: Figure 7-7 of NWMI-201 3-CALC-009, Uranium Purification System Equipment Sizing, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 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 interest for criticality control.

Continuous monitoring of the uranium concentration in condensate sample tank #lA will be provided by a sample loop to a uranium concentration detector (e.g., fluorimeter) . Circulation to the detector will be operated at flow rates that allow sample tanks to approximate a continuous, stirred tank flow pattern. The detector on Tank #lA will control the routing of transfers out of condensate sample tank #lB. Solution transfers out of condensate sample tank # 1B will be routed to waste handling, as long as condensate uranium concentrations comply with criticality control requirements.

A plug flow delay vessel was included between condensate sample tanks lA and lB 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 delay 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 line. A high uranium concentration reading will result in diverting the condensate back to the concentrator feed tank and will stop the column elution. Operation in this recycle mode will continue until the off-normal conditions causing the high uranium condensate concentrations are corrected.

Condensate sample tank #lB will support recovery from an off-normal event, and the uranium monitor at this vessel will not be used during routine concentrator operation. The condensate sample tank # 1B 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.

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• NORTNWUT MEDICAL ISOTOPES 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 vessel; 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 column #2 will 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 column #2, with a uranium loading of approximately

[Proprietary Information] during the loading cycle.

The column operation will 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 column during the loading cycle 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 cycle is complete, the uranium recycle 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 recycle column will be routed to the IX waste collection tanks during the pre-elution rinse cycle, 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].

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• 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 Information].

• Regeneration cycle - The regeneration cycle will prepare the uranium media for performing a new loading cycle by replacing the liquid phase with a solution composition similar to the adjusted impure uranium feed solution. The column feed will be switched 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 recycle 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 Information].

Column sizing for IX column #2 was assumed to be identical to IX column #1, based on processing

[Proprietary Information]. This sizing was considered appropriate for preliminary design because the dominant component feed composition is similar to the IX column # l feed composition. Therefore, Table 4-49 also provides a summary of the uranium recycle column cycles, including the volume processed, liquid phase flow rate, and time required to complete each cycle. The flows and volumes are based on a two-column system, operating in parallel, with a resin bed volume [Proprietary Information].

The column operating 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 secondary concentration subsystem will receive solution from the secondary IX subsystem during 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 concentrated, as the solutions are generated to control the stored volume of process solutions. 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 system-specific offgas treatment will be provided for this vessel.

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• HORlHWUTMEDICALISOTOftl:S Uranium Concentrator/Condenser #2 (UR-Z-530)

Uranium concentrator/condenser #2 will be similar to uranium concentrator/condenser #1 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 ofIX 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 recycled 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 by 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 # 1. 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.

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' ~ *.*! ' NOftTifWEST MEOfCAl tSOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description A nominal temperature of [Proprietary Information] is currently specified for solution stored in the recycled uranium collection tanks, and cooling jackets 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 Recovery and Recycle Process Evaluation Decisions, 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 throughput 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.

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.* NWMl-2015-021, Rev. 1

, * ~ *.* ! ' NORTHWUT MEDtcAL ISOTOPES Chapter 4.0 - RPF Description There will be a total of [Proprietary Information] in the RPF: [Proprietary Information]. Resin replacement activities will 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 cycle are anticipated to require more frequent replacement than the second uranium cycle resin beds .

The spent resin collection tanks will be provided to support removal of spent resin from the IX columns and sampling resin prior to transfer of resin to the waste handling system for disposal. The spent resin collection tanks are designed with geometrically favorable 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 handling system, where vessels are not expected to be designed to dimensions that control criticality by geometry. Two spent resin collection 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 will be supported by a resin transfer liquid tank to manage liquids 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 column after spent resin has been removed. The fresh resin makeup tanks will be located outside 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 control the potential for criticality. One fresh resin makeup tank per column is currently identified as a method for minimizing the potential for double-batching resin in a single column.

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 described in Section 4.4 .1.3. Based on this description, these operations can be conducted safely in this facility.

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' ~ *.*!

• NOATHWlSTMlOICALISOTO,U 4.4.1.2 Process Equipment Arrangement The U recovery and recycle system equipment arrangement within the tank hot cell is shown in Figure 4-76.

[Proprietary Information]

Figure 4-76. Tank Hot Cell Equipment Arrangement 4-156

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, ' ~ *,*! . NOflTHWEST MEDICAL lSOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.1.3 Process Equipment Design A common vessel geometry has been assumed for each vessel in the U recovery and recycle system based on dimensions that provide geometrically favorable designs for criticality control when process solutions contain uranium at 20 wt% 235 U. The assumed geometry is based on a [Proprietary Information].

Detailed design calculations were not developed for equipment as part of the preliminary design.

However, a description of the following major uranium processing equipment pieces can be developed from past experience with similar types of facilities. The major equipment for the uranium processing system will consist of tanks, IX columns, and concentrators.

Tanks will represent a dominant vessel used as equipment in the [Proprietary Information]

uranium system. Two different tank types have been assumed as equipment in the preliminary design: ( l ) uncooled tank Note: Pencil tank height varied based on tank capacity requirements.

configuration, and (2) cooled tank configuration. An example of an Figure 4-77. Alternative Pencil Tank Diameters for Equipment individual pencil tank for the Sizing alternative configurations is shown on Figure 4-77 . Both tank alternatives are intended to satisfy criticality requirements for a geometrically favorable design. The uncooled tank will be constructed from [Proprietary Information].

Schedule 40 pipe lengths as the primary tank wall. A cooled tank will be constructed from [Proprietary Information]. Schedule 40 pipe lengths as the primary tank wall, combined with a cooling jacket fabricated from [Proprietary Information]. Schedule 40 pipe. The cooled tank configuration will provide geometry control for the uranium-bearing solutions under unexpected accident conditions, where process liquid leaks into the cooling jacket due to corrosion or other vessel failure mechanism.

A major difference between the two tank configurations is the capacity of the alternatives to store process liquid. The uncooled tank configuration will have a capacity of [Proprietary Information] of primary vessel length, while the cooled tank configuration will have a capacity of [Proprietary Information].

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• ~ *.* ~ . NORTHWEST MlOtcAl lSOTOHI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Figure 4-78 is a conceptual sketch of an IX column for uranium purification. The vessel is currently envisioned as based on a [Proprietary [Proprietary Information]

Information]. diameter cylindrical geometry for criticality control, with the IX media supported on a screen to form a resin bed. An upper screen will be included in the column to Figure 4-78. Conceptual Ion Exchange Column for restrain the resin within a fixed portion of the Uranium Purification column. Inlet and outlet piping connections will communicate with the resin section of the column to allow periodic bed replacement using slurry transfer of the resin. The current concept is based on providing a configuration with two of the columns shown in Figure 4-78 that operate in parallel for each of the IX cycles.

Liquid phase will pass through the column in a down-flow such that feed for a particular column cycle will enter at the top of the column and cycle effluents will leave the column from the bottom. The column is anticipated to include a rupture disk-type safety pressure relief assembly as part of the column design. Pressure-relief capabilities will typically be required when using organic resins in a nitric acid system.

Figure 4-79 is a conceptual sketch of a typical concentrator for uranium-bearing solutions [Proprietary Information]

where uranium must be controlled by a geometrically favorable design. The configuration shown in Figure 4-79 is based on a natural convection thermosiphon Source: Figure 2 [modified] ofORNL/TM-5518 , Design and Test of arrangement, but could be configured as a a Thermosiphon Evaporator for Acid-Deficient Uranyl Nitrate, Oak forced convection equipment piece. Dilute Ridge National Laboratory, Oak Ridge, Tennessee, November, 1976.

feed will enter the concentrator near the Figure 4-79. Conceptual Uranium Concentrator bottom and circulate through the reboiler. The Vessel reboiler will heat the solution and partially evaporate the feed liquid. Vapor will migrate up the concentrator vessel, through a demister, and will then be condensed. Feed liquid will continue to circulate through the reboiler until the solution reaches a goal density. For the conceptual sketch, concentrate overflows from a mid-point position of the concentrator to a receiver vessel.

Table 4-50 provides a summary description of the U recovery and recycle process equipment.

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~

NORTHWEST MEDtcALISOTOl'U NWMl-2015-021, Rev. 1 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) 3 atm (lb/in 2 a)b Impure U collection tanks UR-TK- [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Info rmation] Info rmation] Information] Information]

100/ 120/ 140/ 160 IX feed tank #I UR-TK-200 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

IX column IA and UR-IX-240/260 [Proprietary [Proprietary 304L SS [Pro prietary [Proprietary Informatio n] Information] In fo rmation] Information]

IX column 1B Concentrator I feed tank UR-TK-300 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Concentrator I UR-Z-320 [Proprietary [Proprieta ry 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Condenser I UR-Z-320 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Concentrate cooler I UR-Z-320 [Prop rietary [Pro prietary 304L SS [Proprietary [Proprietary Information] In formation] In formation] In fo rmation]

Sample tank #IA UR-TK-340 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Plug flow delay vessel UR-TK-360 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary In formatio n] In fo rmation] In fo rmation] Information]

Sample tank #lB UR-TK-370 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Uranium feed batch UR-TK-400/420 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

adjustment tanks Uranium recycle exchange UR-IX-460/480 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

column #2 Concentrator 2 feed tank UR-TK-500 [Prop rietary [Pro prietary 304L SS [Proprietary [Proprietary Info rmation] Info rmation] Information] Information]

Concentrator 2 UR-Z-520 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Condenser #2 UR-Z-520 [Proprietary [Proprietary 304L SS [Pro prietary [Proprietary In fo rmation] In fo rmation] Information] Information]

Concentrate cooler #2 UR-Z-520 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Sample tank #2A UR-TK-540 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Info rmation] Information] Information]

Plug flow delay vessel UR-TK-560 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Sample tank #2B UR-TK-570 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary In fo rmation] Information] In formation] Information]

Concentrate receiver tank UR-TK-600 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Product sample tank UR-TK-620 [Proprietary [Proprietary 304L SS [Pro prietary [Proprietary Information] Information] Information] Information]

Uranium rework tank UR-TK-660 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

Uranium decay holdup UR-TK-700° [Pro prietary [Proprietary 304L SS [Pro prietary [Proprietary Information] Info rmation] Information] Information]

tanks 0 Uranium product transfer UR-TK-720 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary lnfonnation] Infonnation] Information] Information]

send tank 4-159

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• *. ~ *.* ~ .' . NORTHWt:ST MEO.CAL ISOTOPES 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)a atm (lb/in 2a)h UR-TK-820 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Spent resin collection tanks Information] Information] Information] Information]

Resin transfer liquid tank UR-TK-850 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Information] Information] Information] Information]

UR-TK-900/920 [Proprietary [Proprietary 304L SS [Proprietary [Proprietary Uranium IX waste Information] Information] Information]

Information]

collection tanks a Temperature range estimated for process solutions. The nominal operating temperature ofIX system-related solutions is

[Proprietary Information] based on controlling resin operating conditions. The nominal operating temperature of the concentrator systems includes transition to an operating temperature of [Proprietary Information], operating the concentrator at

[Proprietary Information], and operating the condenser at [Proprietary Information] . Condenser cooling water supply is assumed to be at [Proprietary Information] .

b Atmospheric pressure, as controlled by the vessel ventilation system to maintain a negative vessel pressure relative to the vessel enclosure (normally hot cell enclosure for these vessels).

c Uranium decay holdup tanks [Proprietary Information], labeled UR-TK-700A through UR-TK-700R.

IX ion exchange. u = uranium.

SS = stainless steel.

Process Monitoring and Control Equipment Process monitoring and control equipment was not defined during preliminary design. The process description in Section 4.4.1.1 identifies 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 details of the process monitoring and control equipment will be developed for the Operating License Application.

4.4.1.4 Special Nuclear Material Description This section provides a summary of the maximum amounts of SNM and the chemical and physical forms of SNM used in the process. This section also describes required criticality control features that are designed into the process systems and components. The criticality control features will be in accordance with the double-contingency principle, and the RPF will provide suitable defense-in-depth for the contained processes. All SNM discussed in this section is not be considered waste and will be returned to the U recovery and recycle system, purified, and reused.

Special Nuclear Material Inventory The U recovery and recycle system SNM inventory will be dominated by [Proprietary Information].

After holdup in the impure U collection tanks, the stored uranium solution will be processed by the IX system in multiple small batches that are collected in the U decay tanks. The U decay tanks will provide an additional [Proprietary Information] prior to transfer to the target fabrication system. [Proprietary Information] will control worker exposure during target fabrication operations.

Table 4-51 summarizes the U recovery and recycle SNM design basis inventory. Uranium solution concentrations vary from less than [Proprietary Information], depending on the process activities supported by a particular vessel and the reactor source for targets in a particular operating week. Nuclear criticality evaluations performed in Atkins-NS-DAC-NMI-14-006 indicate that the U recovery and recycle system vessels remain subcritical under normal and abnormal conditions when all vessels contain solution at a concentration of [Proprietary Information].

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' ~ * ,* ~ ' NomtWl:ST M(OICAl. ISOTOHS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-51. Uranium Recovery and Recycle In-Process Special Nuclear Material Inventory (2 pages)

Stream Form Concentrationa Volume SNM massa Impure U collection tanks - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-IOOA/B, 120A/B, Information] Information] Information]

I 40A/B, l 60A/B IX feed tank I - UR-TK-200b Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary Information] information] Information]

Concentrator I feed tank - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-300b Information] Information] Information]

Concentrator I holdup - UR-Z- Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary 320b Information] Information] Information]

Condensate sample tank 1A - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-340b Information] Information] Information]

Condensate delay tank I - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-360b Information] Information] information]

Condensate sample tank lB - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-370b Information] Information] Information]

IX feed tank 2A - UR-TK-400b Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary Information] Information] Information]

IX feed tank 2B - UR-TK-420b Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary Information] Information] Information]

Concentrator 2 feed tank - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-500b Information] Information] information]

Concentrator 2 holdup - UR-Z- Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary 520b Information] Information] information]

Condensate sample tank 2A - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-540b Information] Information] Information]

Condensate delay tank 2 - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-560b Information] Information] Information]

Condensate sample tank 2B - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-570b Information] Information] Information)

Concentrate receiver tank - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-600b Information] Information] Information]

Product sample tank- UR-TK- Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary 620b information] Information] information]

U rework tank - UR-TK-660b Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary Information] Information] Information]

U decay tanks ([Proprietary Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary Information]) UR-TK-700A to R Information] Information] Information]

U product transfer send tank - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-720 Information] Information] Information]

Spent resin collection tank A - Spent resin in water [Proprietary [Proprietary [Proprietary UR-TK-820A Information] Information] Information]

Spent resin collection tank B - Spent resin in water [Proprietary [Proprietary [Proprietary UR-TK-820B Information] Information] Information]

Resin transfer liquid tank - Resin transfer water [Proprietary [Proprietary [Proprietary UR-TK-850 Information] Information] Information]

IX waste collection tank I - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-900 Information] Information] Information]

IX waste collection tank 2 - Liquid uranyl nitrate [Proprietary [Proprietary [Proprietary UR-TK-920 Information] In formation] Information]

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~* * ~ . NORTHWEST MlOtCAL tSOTOPH Table 4-51. Uranium Recovery and Recycle In-Process Special Nuclear Material Inventory (2 pages)

Stream Form Concentration 3 Volume SNM mass 3 a SNM concentration and mass represent total amount of LEU (combined 235 U and 238 U at :::; 19.95 wt% 235 U) b Solution moves from impure uranium collection tanks, through the uranium process vessels, to the U decay tanks during a processing week.

c Concentrator eq uipment not currentl y designed . Holdup vo lume approxi mated [Proprietary Info rmation] .

d Condensate currently estimated to contain trace quantities of uranium [Proprietary In formation].

e Uranium concentration varies depending on targets being processed. [Proprietary Information]

r Resi n is eluted prior to disposal as spent resin. Disposal stream slurry projected to contain [Proprietary Information] . No data are currently ava ilable to predi ct eluted resin or transfer liquid uranium content, but ex pected to contain trace uranium quantities.

g IX waste currently estimated to contain trace quantities of uranium at an average [Proprietary Information] .

IX ion exchange. osu Oregon State Uni versity.

LEU low-enriched uranium. SNM special nuclear material.

MURR Uni versity of Missouri Research Reactor. u urani um.

[Proprietary Information]

Uranium solution collected for decay storage in the impure U collection tanks will be processed as multiple smaller batches through the IX separation system. The nominal weekly process throughput will range from [Proprietary Information]. The IX system is sized to process solution in batches containing approximately [Proprietary Information] , which will be prepared from impure U collection tank transfers in UR-TK-200. The U recovery and recycle system equipment design is based [Proprietary Information].

Uranium from the feed tank batch will be collected on the first-cycle IX columns and eluted 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-320, which is not intended as a major uranium collection point during normal operation, but can hold up to [Proprietary Information]. While not finalized, the current concentrator design (UR-Z-320) is based on a natural convection thermosiphon configuration with the potential to hold up to approximately [Proprietary Information] under normal operating conditions.

Condensate vessels (UR-TK-340, UR-TK-360, and UR-TK-370) are expected to contain trace quantities of uranium during normal operation.

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' ~ *: !

• NORTHWESTM£0tCAllSOTOP£S Uranium concentrate from UR-Z-320 will be collected in the second-cycle IX feed tanks (UR-TK-400 or UR-TK-420) using a batch size of approximately [Proprietary Information], collected on the second-cycle IX columns, and eluted to UR-TK-500 for feed to concentrator UR-Z-520. As with 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 has the potential to hold between [Proprietary Information], depending on the planned normal operating conditions. Concentrate from UR-Z-520 will be collected in the concentrate receiver UR-TK-600 from multiple IX batches for transfer to the product sample tank (UR-TK-620). The concentrate receiver and product sample tanks will be capable of holding up to [Proprietary Information] . During normal operation, one transfer per week of [Proprietary 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 Information]

The uranium product transfer send tank (UR-TK-720) will support accountability measurements between the U recovery and recycle system and target fabrication system. The tank will normally be empty when not supporting transfers between the two systems, but will have the capability to contain approximately

[Proprietary Information] .

The spent resin collection tanks (UR-TK-820A/B) and resin transfer liquid tank (UR-TK-850) will be used to support replacement of the IX resin columns in the U recovery and recycle system. The IX columns will be eluted to remove uranium from the media prior to replacement. However, trace uranium quantities are anticipated to remain after column elution. Estimates of residual uranium in spent resin and transfer liquid will be completed for inclusion in the Operating License Application.

Waste solution generated by the U recovery and recycle system is estimated to contain small quantities of uranium, which is characterized as a concentration of [Proprietary Information]. Multiple waste batches will be generated during IX column operation. The uranium inventory of each waste batch is estimated to average [Proprietary Information].

Criticality Control Features Criticality control features are required in this system, as defined in NWMI-2015-CSE-008, NWMI Preliminary Criticality Safety Evaluation: Hot Cell Uranium Purification. These features, including passive design and active engineered features, allow for adherence to the double-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 passive design and active engineered features, which are listed below. The passive design features will include geometric constraints of the floor, process equipment, workstations, and ventilation system. The active engineered features will include the requirement of continuous ventilation. Chapter 6.0 provides detailed descriptions of the criticality control features.

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• • • ~**::.

• • *

• NORTKWHT MlDtcAL ISOTDKI NWMl-2015-021, Rev. 1 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-PDFI ), 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 safe (CSE-08-PDF3 and CSE-08-PDF5) and maintain a subcritical geometry during and after a facility DBE (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 systems (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-PDFIO) .

• Backflow of tank solution into the gas system will be prevented (CSE-08-PDFl 1) .

• Backflow of uranium solution to the unfavorable geometry vessels of the chemical makeup systems will be prevented (CSE-08-PDF 12).

• Overpressurization of the uranium process vessels will be prevented (CSE-08-AFEl) .

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 U recovery and recycle system activities.

• The process equipment is designed to be inherently safe by geometry to prevent criticality. This approach applies limitations on the configuration, including: (I) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equipment with fissile solution (IROFS CS-07).

• The floor geometry and use of floor dikes are controlled to prevent criticality in the event of spills (IROFS CS-08).

• Chemical and water supplies are potential sources for backflow of fissile solution to the large geometry of the chemical supply system or demineralized water system. To prevent backflow, 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- I 0).

• Condensate from the uranium concentrators is monitored actively with isolation to 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 criticality-safe geometry prevents fissile leakage from accumulating in an unfavorable geometry (IROFS CS-09).

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....;. . NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. ' ~ -.* ~ ; NORTMWHTM£DfCA1. ISOTOPU 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 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 U recovery and recycle system will be in accordance with the double-contingency 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 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 the radionuclide inventory as described in Section 4.1. The radionuclide inventory will 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 solution lag storage in the impure U collection tanks. During MURR target processing, [Proprietary Information] will be stored after the 99 Mo has been extracted by the Mo recovery and purification system. 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 by 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 storage 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 will provide storage for a decay period of [Proprietary Information]. A fourth tank wi 11 store material that has been decayed to

[Proprietary Information], from which feed batches will be drawn for the uranium IX system.

4-165

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

• • • NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description

' ~ *.* !

• NOflTHWEnMlDtcALISOTOPH

[Proprietary Information]

Figure 4-80. Impure Uranium Collection T anks 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 by Table 4-52.

Table 4-52. Impure Uranium Collection Tanks In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit o p e r a tio n Impure U c o llecti o n tanks D ecay time a fte r EOJ* [Proprietary In fo rmat ion] [Prop rieta ry Information] [Proprietary Information] [Pro prietary Informat ion] [Prop rietary Information]

S tream d esc ripti o n b [Prop rietary In formation] [Prop rieta ry Information] [Proprietary In fo rmation] [Pro prietary Information] [Pro prietary In formation]

Isotopes Total Ci 241A m [Proprietary Information] [Proprieta ry Information] [Proprieta ry Informat ion]

136mBa I

[Proprietary Information] [Proprieta ry In forma tion] [Proprietary Info rmation] [Proprieta ry Information] [Proprietary Information]

137mB a I

[Proprieta ry Information] [Proprietary Information] [Proprieta ry In formation] [Proprietary Information) [Proprietary Information]

t39B a I

[Proprietary Information] [Proprietary Info rmation] [Proprietary Information] [Proprietary Informa tion] [Proprietary In fo rmation]

t4oBa I

[Proprietary Information] [Pro prietary Information] [Proprieta ry Informat ion] [Proprietary Information] [Proprieta ry Information]

t4t Ce I

[Proprieta ry Information] [Prop rietary Information] [Proprieta ry Information] [Proprietary Information] [Proprietary Information]

t43Ce I

[Proprietary Information] [Proprieta ry Information] [Proprieta ry Information] [Proprietary Information] [Proprietary Info rmation]

t44Ce I

[Pro prietary Informa tion] [Proprietary Info rmation) [Proprietary Information] [Prop rietary Information) [Propr ietary Information]

242cm [Proprietary Information] [Proprieta ry In formation] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

243Cm I

[Pro prietary In formation] [Proprieta ry In fo rmation] [Proprietary In formation] [Proprietary Information] [Prop rietary Information]

244Cm [Proprietary Information] [Proprietary In forma tion) ![Proprietary Info rmation) [Proprietary Info rmatio n) [Proprietary Information]

134Cs I

[Proprietary Informa tion] [Proprieta ry In formation] [Proprietary In forma tion] [Proprietary Information] [Prop rietary Information]

134mcs I

[Proprieta ry Information) [Proprieta ry Information] [Proprietary Information] [Proprietary Info rmation] [Proprietary Informa tion]

136Cs [Proprieta ry Informa tion] [Proprietary In formation] I[Proprietary Info rmation] [Proprieta ry Information] [Prop rietary Information]

137C s [Proprietary Info rmation] [Proprietary Information] ![Pro prietary Info rmation] [Proprietary Info rmation] [Proprietary Information]

tssE u [Proprietary In fo rma tion] [Proprietary Informat ion] ![Prop rietary In fo rmation] [Proprieta ry Information] [Pro prietary Informat ion]

ts6E u [Proprieta ry Info rmation] [Proprietary Information) ![Proprieta ry In fo rmation] [Proprieta ry Information) [Proprietary Information]

ts1E u [Prop rietary Info rma tion] [Proprietary In formation] ![Proprietary Info rmatio n) [Proprietary Info rmation] [Pro prietary Info rmation]

1291 [Proprietary Info rmation] [Proprieta ry Information] ![Proprietary Information] [Proprieta ry Information] [Proprietary Information]

1301 [Proprieta ry Info rmation] [Proprietary Informat ion) ![Proprietary Infor matio n] [Proprietary Information] [Proprietary Informa tion]

t3 t I I

[Pro prieta ry Information) [Proprietary Informa tion) [Proprietary Information) [Proprieta ry Information) [Proprietary Information]

4-166

. ....*.*. NWMI

~.

• ~ *.*! ' NORTtfW(ST MEDtcAl ISOTOPH NWMl-2015-021, Rev. 1 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 Information] [Proprietary Informat ion] [Proprietary Informat ion] [Proprietary Information] [Proprietary Information]

Stream descriptionb [Proprietary Information] [Propri etary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

Isotopes Total Ci 1321 [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Informatio n] [Proprietary In formation]

n2m1 [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

1331 [Proprietary In fo rmation] [Proprietary Informatio n] ![Proprietary Information] [Proprietary In formation] [Proprietary Information]

133ml [Proprietary In formation] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

1341 [Proprietary In formation] [Proprietary Informatio n] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

1351 I

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

83mK.r [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

85Kr [Proprietary In formation] [Proprietary In formatio n] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

85mK.r [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Info rmation]

87K.r I

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

88Kr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Informat ion] [Proprietary Info rmation]

I40La I

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

141La I

[Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

142La [Proprietary Information] [Proprietary In formatio n] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

99Mo I

[Proprietary In formation] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Info rmation]

95Nb [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

95mNb I

[Proprietary In formation] [Proprietary In formation] [Proprietary Information] [Proprietary Informatio n] [Proprietary Information]

96Nb [Proprietary Information] [Proprietary Information] I[Proprietary Information] [Proprietary Information] [Proprietary Information]

97Nb [Proprietary Information] [Proprietary In formation] I[Proprietary Informat ion] [Proprietary Information] [Proprietary In fo rmation]

97mNb [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

I47Nd I

[Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary In formation]

236mNp [Proprietary Information] [Proprietary Information] I[Proprietary Information] [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary In formation] I[Proprietary In formation] [Proprietary In formation] [Proprietary In formation]

23sNp [Proprietary Info rmation] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

239Np I

[Proprietary In formation] [Proprietary In formatio n] [Proprietary Information] [Proprietary In formation] [Pro prietary In formation]

233pa [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

234pa I

[Proprietary Information] [Proprietary In format ion] [Proprietary Information] [Proprietary Informat ion] [Proprietary Information]

234mpa [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

112pd I

[Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

I47pm [Proprietary Information] [Proprietary Information] I[Proprietary Information] [Proprietary Information] [Proprietary Information]

I48pm [Prop ri etary Information] [Proprietary In forma tion] I[Proprietary Information] [Proprietary Information] [Proprietary Information]

148mpm [Proprietary Information] [Proprietary In formation] I[Proprietary Information] [Proprietary Information] [Proprietary Information]

t49pm [Proprietary Information] [Proprietary In formation] I[Proprietary Information] [Proprietary In formation] [Proprietary In fo rmation]

1sopm [Proprietary In formation] [Proprietary Information] I[Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1 pm [Proprietary In formation] [Proprietary In formatio n] I[Proprietary Information] [Proprietary Information] [Proprietary In fo rmation]

I42pr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary In formation] [Proprietary Information]

4-167

..**~ ..* : NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 0

~ ~.* ~

• NORTifWESTMlDICA.LtSOTOPfS 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 Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

Stream descriptionb [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Informat ion] [Proprietary Information]

Isotopes Total Ci I43pr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Informat ion] [Proprietary Information]

t44pr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

144mpr I

[Proprietary In fo rmation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

I45pr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

238pu I

[Proprietary In formation] [Proprietary Informat ion] [Proprietary Information] [Proprietary In format ion] [Proprietary Information]

239pu I

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

240pu [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

24tpu I

[Proprietary Informatio n] [Proprietary Information] [Proprietary Information] [Proprietary Information) [Proprietary Information]

!03mRh I

[Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information) 105Rh I

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

106Rh I

[Proprietary In formation] [Proprietary Information) [Proprietary Information] [Proprietary Informatio n] [Proprietary Information]

!06mRh [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

103Ru I

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

wsRu I

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

io6Ru I

[Proprietary Informat ion) [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

122 sb [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

t24Sb I

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

125 Sb [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

126Sb [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

127 Sb [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

128 S b I

[Proprietary Informat ion] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

t2smsb I

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

t29Sb I (Proprietary lnfonnation] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information]

tstsm [Proprietary Information) [Proprietary Information) ![Proprietary Information] [Proprietary Information] [Proprietary Information]

1s3sm I

[Proprietary Information) [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Informat ion]

1s6sm [Proprietary Information) [Proprietary Information) ![Proprietary Information) [Proprietary Information] [Proprietary Information]

s9sr I

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

9osr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

9'Sr I

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

92 Sr [Proprietary Information) [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

99Tc I

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprietary Information) 99mTc [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

125mTe I

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

121Te [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information) 127mTe I

[Proprietary Information] [Proprietary Information] [Proprietary Information] [Proprieta ry Informat ion) [Proprietary Information]

129Te [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

4-168

...;. .. NWMI

• ~ *.*! '

NOlTHWEST MlOICAl ISOTOPES NWMl-2015-021, Rev. 1 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 coll e ction tanks Decay time after EOP [Proprietary In fo rmation] [Proprietary In fo rmation] [Proprietary In formation] [Proprietary In formation] [Pro prietary Information]

Stream descriptionb [Proprietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary In format ion] [Pro prietary Informat ion]

Isotopes Cic Cic Cic CiC Total Ci 129mTe I

[Proprietary In formation] [Proprietary Information] [Prop rietary Information] [Proprietary In formation] [Pro prietary Information) 131Te [Proprietary Information) [Proprietary Information] ![Proprietary Information) [Proprieta ry Information) [Proprietary Information]

131mT e I

[Proprietary In fo rmation] [Proprietary In formatio n) [Proprietary Information] [Proprietary Informatio n] [Proprietary In formation]

132Te [Proprietary Information] [Proprietary Information] ![Proprietary Information) [Proprieta ry Information) [Proprietary Information]

133 T e I

[Proprietary Info rmation] [Pro prietary In forma tion) [Prop rietary Information] [Proprietary Information] [Proprietary In forma tion]

133mTe [Proprietary Information) [Proprieta ry Information] ![Proprieta ry Information) [Proprietary Information) [Proprietary Information]

t34Te I

[Proprietary In fo rmation] [Proprietary In format ion] [Proprietary In formation] [Proprietary Information] [Proprietary Information]

23 1Tu [Proprietary Information] [Proprietary Information] I[Proprietary Information] [Proprieta ry Information] [Proprietary Information]

234Th [Proprietary In formation] [Proprietary In formatio n) I[Proprietary In formation] [Proprietary In formation] [Proprietary Information]

232u [Proprietary Information] [Proprietary In formation) J [Proprietary Information] [Proprietary Information) [Proprietary Information]

234U I

[Proprietary Informa tion) [Proprietary In forma tion] [Proprietary In formation] [Proprietary In formation] [Proprietary Information) 23su [Proprietary Information] [Proprietary Information) I[Proprietary Information) [Proprietary Information) [Proprietary Information]

236u [Proprietary Information) [Prop rietary In formation] I[Proprietary Information] [Proprietary Information] [Proprietary In formation) 231u [Proprieta ry Information] [Proprietary Information] I[Proprietary Information) (Proprietary Information] [Proprietary Information) 23su [Proprieta ry Informat ion] [Pro prietary In format ion) I[Proprietary Information] [Proprietary In formation] [Pro prietary In formation]

l31mxe [Proprietary Information) [Proprietary Information] I[Proprieta ry Information] [Proprietary Information] [Proprietary Information]

133 X e [Proprietary In formation] [Proprietary In formation) I[Proprietary In formation] [Proprietary Information) [Proprietary Information]

m mxe [Proprietary Information] [Proprietary Information] ![Proprieta ry Information] [Proprieta ry Information) [Proprietary Information]

135 X e I

[Proprietary In formation] [Proprietary In format ion] [Proprietary Information] [Proprietary Information] [Pro prietary Infor mation]

13smxe [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

89my I

[Proprietary In formation] [Proprietary In formatio n] [Proprietary Information] [Proprietary Information] [Pro prietary Information]

90y I

[Pro prietary Information] [Proprietary In formation] [Proprietary Information] [Proprietary Information] [Proprietary Information]

90my [Proprietary Informat ion] [Proprietary In formation] I[Pro prietary In formation] [Proprietary In formation] [Proprietary Informat ion]

91y [Proprietary Information] [Proprietary Information] J [Proprietary Information] [Proprietary Information] [Proprietary In formation]

91my [Proprietary In formation] [Proprietary Information] ![Pro prietary Information] [Prop rietary In formation] [Proprietary In formation]

92y [Proprietary Information] [Proprieta ry In formation] J [Proprietary Information] [Proprietary Information] [Proprietary Information]

93y [Proprietary In formation] [Proprietary Information] ![Proprietary Informat ion] [Proprieta ry Informatio n] [Proprietary Information]

93zr [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

9szr [Proprietary Info rmation] [Pro prietary Information] ![Proprietary Informat ion] [Proprietary In formation] [Proprietary Infor matio n]

97 [Proprietary Information] [Proprietary Information] ![Proprietary Information] [Proprietary Information] [Proprietary Information]

Zr Total C i [Propr ietary In fo rma tion] [Pro prietary Information] [Proprietary In formation] [Prop rietary In formation] [Proprietary In formation]

a In-process inve ntory o f each s torage t a nk based on indicate d d e cay times.

Fi g ure 4-80 prov ides a s implifie d des cription of th e p rocess stream s.

c In-process inve ntory b ased on processing o f [Proprie ta ry In fo rma tion] p e r operating week .

EOI e nd o f irra d iatio n . u uramum.

MURR U ni ver s ity of Mi ssouri R esearch R eacto r.

4-169

... NWMI

• ~* * ~

• NOllTMWUT M£DICAl tsOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Solution designated as decayed impure U in Table 4-52 will be withdrawn in multiple batches [Proprietary Information]

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 by Figure 4-81. Uranium Recovery and Recycle IX and concentrator equipment as feed solution passes through the system. The radionuclide In-Process Radionuclide Inventory Streams inventory will be split among the three streams (U condensate, recycled U, and U IX waste) by the separation system. All material in-process will be

[Proprietary Information] by storage in the impure 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 In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation: U recovery and recycle Decay time after EOI" [Proprietary Information]

Stream descriptionb U condensate Recycled U U IX waste Isotopes 241Am [Proprietary Information] I [Proprietary Information] [Proprietary Information]

136mBa [Proprietary Information] I [Proprietary Information] [Proprietary Information]

137mBa [Proprietary Information] I [Proprietary Information] [Proprietary Information]

139Ba [Proprietary Information] I [Proprietary Information] [Proprietary Information]

140Ba [Proprietary Information] I [Proprietary Information] [Proprietary Information]

14 1ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

143Ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

144Ce [Proprietary Information] [Proprietary Information] [Proprietary Information]

242cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

243Cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

244Cm [Proprietary Information] [Proprietary Information] [Proprietary Information]

134Cs [Proprietary Information] [Proprietary Information] [Proprietary Information]

134mcs [Proprietary Information] [Proprietary Information] [Proprietary Information]

136Cs [Proprietary Information] [Proprietary Information] [Proprietary Information]

137 [Proprietary Information] [Proprietary Information]

Cs [Proprietary Information]

1ssEu [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s6Eu [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1Eu [Proprietary Information] [Proprietary Information] [Proprietary Information]

129I [Proprietary Information] [Proprietary Information] [Proprietary Information]

1301 [Proprietary Information] [Proprietary Information] [Proprietary Information]

131I [Proprietary Information] [Proprietary Information] [Proprietary Information]

4-170

. .**.*.*.*.NWMI

~

. ' ~ *.-! . HOflTHWln M£DtcAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-53. Uranium Recovery and Recycle In-Process Radionuclide Inventory (4 pages)

, Item MURR target processing Unit operation: U recovery and recycle Decay time after EOP [Propri etary Information]

Stream descriptionh U condensate Recycled U U IX waste Isotopes 1321 [Proprietary Information] I [Proprietary Information] [Proprietary Information]

132ml [Proprietary Information] I [Proprietary Information] [Proprietary Information]

1331 [Proprietary Information] I [Proprietary Information] [Proprietary Information]

133ml [Proprietary Information] j [Proprietary Information] [Proprietary Information]

134I [Proprietary Information] [Proprietary Information] [Proprietary Information]

1351 [Proprietary Information] [Proprietary Information] [Proprietary Information]

83 mKr [Proprietary Information] [Proprietary Information] [Proprietary Information]

85Kr [Proprietary Information] [Proprietary Information] [Proprietary Information]

85mKr [Proprietary Information] [Proprietary Information] [Proprietary Information]

87Kr [Proprietary Information] [Proprietary Information] [Proprietary Information]

88Kr [Proprietary Information] [Proprietary Information] [Propri etary Information]

140La [Proprietary Information] [Proprietary Information] [Proprietary Information]

141 La [Proprietary Information] [Proprietary Information] [Proprietary Information]

142La [Proprietary Information] [Proprietary Information] [Proprietary Information]

99Mo [Proprietary Information] [Proprietary Information] [Propri etary Information]

95Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

95mNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

96Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

97Nb [Proprietary Information] [Proprietary Information] [Proprietary Information]

97mNb [Proprietary Information] [Proprietary Information] [Proprietary Information]

141Nd [Proprietary Information] [Propri etary Information] [Proprietary Information]

236mNp [Proprietary Information] [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary Information] [Proprietary Information]

23sNp [Proprietary Information] [Proprietary Information] [Proprietary Information]

239Np [Proprietary Information] [Proprietary Information] [Proprietary Informati on]

233pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234pa [Proprietary Information] [Proprietary Information] [Proprietary Information]

234mpa [Proprietary Information] [Proprietary Information] [Proprietary Information]

11 2pd [Proprietary Information] [Proprietary Information] [Proprietary Information]

147pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

148pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

148mpm [Proprietary Information] [Proprietary Information] [Proprietary Information]

149pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1sopm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s 1pm [Proprietary Information] [Proprietary Information] [Proprietary Information]

142Pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

143pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

144pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

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• NOATHWlSTMEOICAllSOTOHS Table 4-53. Uranium Recovery and Recycle In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation: U recovery and recycle Decay time after EOP [Proprietary Information]

Stream descriptionb U condensate Recycled U U IX waste Isotopes 144mpr [Proprietary Information] [Proprietary Information] [Proprietary Information]

t45pr [Proprietary Information] [Proprietary Information] [Proprietary Information]

238pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

239pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

240pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

241Pu [Proprietary Information] [Proprietary Information] [Proprietary Information]

103mRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

105Rh [Proprietary Information] [Proprietary Information] [Proprietary Information]

106Rh [Proprietary Information] [Proprietary Information] [Proprietary Information]

106mRh [Proprietary Information] [Proprietary Information] [Proprietary Information]

103Ru [Proprietary Information] [Proprietary Information] [Proprietary Information]

1osRu [Proprietary Information] [Proprietary Information] [Proprietary Information]

106Ru [Proprietary Information] [Proprietary Information] [Proprietary Information]

122sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

124Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

125 Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

126Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

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

Sb 12ssb [Proprietary Information] [Proprietary Information] [Proprietary Information]

12smsb [Proprietary Information] [Proprietary Information] [Proprietary Information]

129Sb [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s1sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s3sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

1s6sm [Proprietary Information] [Proprietary Information] [Proprietary Information]

s9sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

9osr [Proprietary Information] [Proprietary Information] [Proprietary Information]

91sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

92Sr [Proprietary Information] [Proprietary Information] [Proprietary Information]

99Tc [Proprietary Information] [Proprietary Information] [Proprietary Information]

99mTc [Proprietary Information] [Proprietary Information] [Proprietary Information]

125mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

121Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

127mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

129Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

129mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

131Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

131mTe [Proprietary Information] [Proprietary Information] [Proprietary Information]

132Te [Proprietary Information] [Proprietary Information] [Proprietary Information]

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, * ~ ~. ~ ~ .' . NORTHWHT MfOICAl ISOTOf'ES Chapter 4.0 - RPF Description Table 4-53. Uranium Recovery and Recycle In-Process Radionuclide Inventory (4 pages)

Item MURR target processing Unit operation: U recovery and recycle Decay time after EOI" [Proprietary Information]

Stream descriptionb U condensate Recycled U U IX waste Isotopes 133Te [Proprietary Information] I [Proprietary Information] [Proprietary Information]

I33mTe [Proprietary Information] I [Proprietary Information] [Proprietary Information]

134Te [Proprietary Information] I [Proprietary Information] [Proprietary Information]

231Th [Proprietary Information] I [Proprietary Information] [Proprietary Information]

234Th [Proprietary Information] I [Proprietary Information] [Proprietary Information]

232u [Proprietary Information] I [Proprietary Information] [Proprietary Information]

234u [Proprietary Information] I [Proprietary Information] [Proprietary Information]

235U [Proprietary Information] I [Proprietary Information] [Proprietary Information]

236u [Proprietary Information] I [Proprietary Information] [Proprietary Information]

231u [Proprietary Information] j [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] I [Proprietary Information] [Proprietary Information]

131mxe [Proprietary Information] j [Proprietary Information] [Proprietary Information]

133 Xe [Proprietary Information] I [Proprietary Information] [Proprietary Information]

133mxe [Proprietary Information] j [Proprietary Information] [Proprietary Information]

13sxe [Proprietary Information] I [Proprietary Information] [Proprietary Information]

J35mxe [Proprietary Information] j [Proprietary Information] [Proprietary Information]

89my [Proprietary Information] I [Proprietary Information] [Proprietary Information]

90y [Proprietary Information] j [Proprietary Information] [Proprietary Information]

90my

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

9Iy [Proprietary Information] I [Proprietary Information] [Proprietary Information]

9 Jmy [Proprietary Information] I [Proprietary Information] [Proprietary Information]

ny [Proprietary Information] j [Proprietary Information] [Proprietary Information]

93y [Proprietary Information] I [Proprietary Information] [Proprietary Information]

93zr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

9szr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

97zr [Proprietary Information] I [Proprietary Information] [Proprietary Information]

Total Ci [Proprietary Information] I [Proprietary Information] [Proprietary Information]

• In-process inventory based on decay time [Proprietary Information].

b Figure 4-81 provides a simplified description of the process streams.

c In-process inventory based on total [Proprietary Information] , representing the weekly process throughput.

EOI end of irradiation. U = uranium.

MURR = University of Missouri Research Reactor.

The weekly process throughput described by recycled U in Table 4-53 will be stored in U decay tanks prior to transfer to the target fabrication system. The U decay tanks will function similar to the impure U collection tanks described above, [Proprietary Information]. Similar to the impure U collection system, the U decay storage system will provide 13 positions for solution storage plus a position to support transfers to target fabrication [Proprietary Information]. The total activity of uranium solution produced during an operating week will decrease from [Proprietary Information].

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, *. ~ ~-~~ * . NORTHWEST MEDfCAl ISOTOPES Radioisotope inventory changes will be dominated by the [Proprietary Information] . The total activity of weekly solution transfers to target fabrication at the end of the decay period will be dominated 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 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.

• Most U recovery and recycle 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.

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 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).

• Before the uranyl nitrate solution is recycled 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 if the normal purge is lost (IROFS FS-03). Additional detailed information about which tanks require backup purge will be developed for the Operating License Application.

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• NOlmfWl.IT MEOtcAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.1.6 Chemical Hazards This section provides a summary of the maximum amounts of chemjcals used in the process 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, N02, and nitric acid fumes .

Table 4-54. Uranium Recovery and Recycle Chemical Inventory Chemical OSU batch" MURR batchb Annual quantity"

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

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

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

Demineralized waterd 24,320 L 6,450 L 480,000 L a Represents sum of chemical additions to uranium systems calculated by NWMI-2013-CALC-002, Overall Summary Material Balance - OSU Target Batch , material balances for processing an irradiated target batch [Proprietary Information] .

b Represents sum of chemical additions to uranium systems calculated by NWMI-20 I 3-CALC-006, Overall Summary Material Balance - MURR Target Batch , material balances for processing an irradiated target [Proprietary Information].

c Annual quantity based on [Proprietary Information] .

d Represents a combination of recycled water and fresh demineralized water.

[Proprietary Information] MURR University of Missouri Research Reactor.

[Proprietary Information] OSU = Oregon State University.

[Proprietary Information]

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 radiological hazards. The features will prevent release of radioactive material and limit radiation exposure to protect workers and the public from hazardous chemicals.

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~ NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. ', ~ ~.* ~ .' , NORTHWEST MlOtcAl ISOTOPH 4.4.2 Processing of Unirradiated Special Nuclear Material This section describes the target fabrication Table 4-55. Target Fabrication Subsystems system, which will produce LEU targets from fresh LEU metal and recycled uranyl nitrate. IN.M Subsystem name Kffi!!.h+

The system begins with the receipt of LEU 100 Fresh uranium receipt and dissolution 4.4.2.1.5 from the DOE supplier, and ends with 200 Nitrate extraction 4.4.2.3 packaging new targets for shipment to the irradiation facilities. 300 ADUN concentration 4.4.2.4 400 [Proprietary Information] 4.4.2.5 The uranium received in the target fabrication 500 [Proprietary Information] 4.4.2.6 will be both fresh LEU metal and purified recycled uranyl nitrate; therefore, the uranium 600 [Proprietary Information] 4.4.2.7 within target fabrication may be handled 700 Target fabrication waste 4.4.2.8 directly without shielding.

800 Target assembly 4.4.2.9 Due to the variety of activities performed 900 LEU storage 4.4.2.10 during target fabrication, the system _AD

_ UN

_ _ _ _a_c-id--d- e_fi_c-ie-nt_ u_r-an_y_l_n_itr-a-te-. - - - - - - - -

description is divided into the nine subsystems LEU 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

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• NORTifWHT M£01CA1. ISOTOPES 4.4.2.1 Target Fabrication Design Basis 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 H2, designing for 25 percent of lower flammability limit In addition to the overall design basis, more specific requirements 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 activities.

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 Information]

Fresh LEU impurities (based on draft DOE inputs) will be as specified in Table 4-56.

Table 4-56. Fresh Uranium Metal Specification (3 pages)

Specified item Symbol Units Specification limits EBC factor Uranium purity u gU/g [Proprieta ry Information] [Proprietary Informat ion) 232u U-232 µgig u [Proprietary In formation] [Proprietary In for mation]

234U U-234 µg/gU [Proprietary Information] [Proprietary Information]

23su U-235 wt% [Pro prieta ry Information] [Proprietary Information]

(+/-0.2%) [Proprietary Information] [Proprietary Information]

236u U-236 µg/gU [Proprietary In formation] [Pro prietary Info rmation]

99Tc + 90Sr Tc-99 Bq/gU [Proprietary Information] [Proprietary Information]

TRU (alpha) TRU Bq/gU [Proprietary In forma tion] [Proprietary Information]

Beta Beta Bq/gU [Proprieta ry Information] [Proprietary Information]

Activation products ActProd Bq/gU [Proprietary Info rmation] [Proprietary In formation]

Fission products FissProd Bq/gU [Proprietary In formation] [Proprietary Information]

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• NORltfWUT MlotCAl tSOTOPU NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description Table 4-56. Fresh Uranium Metal Specification (3 pages)

Specified item Symbol Units Specification limits EBC factor Moisture H10 ppm or µgig [Proprieta ry In fo rmation) [Proprietary Info rmation]

oxide sample Density Density glcm3 [Proprietary Information] [Proprietary Information)

Surface area m2/g [Proprietary In fo rmatio n) [Pro prietary In formation]

Aluminum Al µglgU [Proprietary Information] [Proprietary Information]

Antimony Sb µglgU [Proprietary In fo rmatio n] [Pro prietary Informat ion]

Arsenic As µgig u [Proprietary In formation] [Proprietary Information]

Barium Ba µglgU [Proprieta ry In formation] [Proprietary In formation)

Beryllium Be µglgU [Proprietary In formation) [Proprietary In formation]

Boron B µgig u [Proprietary In formation] [Proprietary In formation]

Cadmium Cd µglgU [Proprietary In formation] [Proprietary Information]

Calcium Ca µgig u [Proprietary Informa tion] [Proprietary Info rmation]

Carbon c µglgU [Proprietary Information) [Proprietary Information]

Cesium Cs µgig u (Pro prietary In fo rmation] [Proprietary Information]

Chromium Cr µgig u [Proprietary Information] [Proprietary Information]

Cobalt Co µgig u [Proprieta ry In formation) [Proprietary In fo rmation]

Copper Cu µglgU [Proprietary In formation] [Proprietary In formation]

Dysprosium Dy µgig u [Proprietary In formation] [Proprietary In fo rmation]

Europium Eu µglgU [Proprietary Information] [Proprieta ry In formation]

Gadolinium Gd µgig u [Proprietary Information] [Proprietary Information]

Hafnium Hf µgig u [Proprietary Information) [Proprietary Information)

Iron Fe µgig u [Proprietary In formation] [Pro prietary In fo rmation]

Lead Pb µgig u [Proprietary In formation) [Proprietary Information)

Lithium Li µglgU [Proprietary In formation] [Proprietary Information]

Magnesium Mg µglgU [Proprietary Information] [Proprietary In formatio n]

Manganese Mn µglgU [Proprietary In fo rmation] [Proprietary Information]

Mercury Hg µgig u [Proprieta ry Information] [Proprietary Information]

Molybdenum Mo µgig u [Proprietary In fo rmation] [Proprietary Information]

Nickel Ni µglgU [Proprietary In formation] [Proprietary In formation]

Niobium Nb µgig u [Pro prietary In formation) [Proprietary Information]

Nitrogen N µglgU [Proprietary Information] [Proprietary In formatio n]

Phosphorus p µglgU [Proprietary In fo rmation] [Proprietary Information]

Potassium K µglgU [Proprietary In formation] [Prop rietary In formation]

Samarium Sm µgig u [Proprietary In fo rmation] [Pro prietary Info rmation]

Silicon Si µglgU [Proprietary Information] [Proprietary Information]

Silver Ag µgig u [Proprietary In fo rmation] [Pro prietary In formation)

Sodium Na µglgU [Proprietary In formation] [Proprietary Information]

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• NOklHWHT MlDICAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-56. Fresh Uranium Metal Specification (3 pages)

Specified item Symbol Units Specification limits EBC factor Strontium Sr µg/g u [Proprietary In format ion) [Proprietary Information)

Tantalum Ta µglgU [Proprietary Information) [Proprietary Information)

Thorium Th µgig u [Proprietary In formation] [Proprietary Information]

Tin Sn µglgU [Proprietary Information] [Proprietary Information]

Titanium Ti µgig u [Proprietary Informatio n) [Proprietary Information)

Tungsten w µglgU [Proprietary Informat ion) [Proprietary Information)

Vanadium v µgig u [Proprietary In formatio n] [Proprietary Information]

Zinc Zn µglgU [Proprietary Information] [Proprietary Information]

Zirconium Zr µg/gU [Proprietary In format ion] [Proprietary Information]

TMI (total impurities) µglgU [Proprietary Information] [Proprietary Information)

Equivalent boron content EBC µg EB/g U [Proprietary In fo rmation] [Proprietary In formation]

• The values shown reflect the sum of the listed nuclides:

[Proprietary Informatio n]

[Proprietary Informat ion]

[Proprietary Informat ion]

[Proprietary Information]

b EBC factors are taken from ASTM C l233-09, Standard Practice for Determining EBC of Nuclear Materials. EBC calculations will include boron, cadmium, dyspros ium, europium, gadolinium, lithium, and samarium. Other EBC factors are provided for information only. The limit on EBC may restri ct some elements to lower values than those shown in the table.

e The limit on EBC may restrict some elements to lower values than shown in th e table.

EBC equi valent boron content. TM! total metallic impurities NM not measured. TRU transuranic.

TBR to be reported. u uranium.

4.4.2.1.2 Produce LEU target Material The produce target sub-function will produce LEU target material. The design basis for this sub-function is to:

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

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• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

4.4.2.1.3 Assemble Low-E nriched Uranium Targets The assemble LEU targets sub-function fills , seal Table 4-57. Low-Enriched Uranium Target welds, and examines targets. The design basis for Physical P roperties this sub-function is to: Target parameter Value

[Proprietary Information] [Proprietary Informat ion]

• Clean target hardware components prior to [Proprietary Information] [Proprietary Information]

fi lling with LEU target material [Proprietary Information] [Proprietary In format ion]

• Provide capability to collect LEU target [Proprietary Information] [Proprietary Information]

[Proprietary Information] [Proprietary Information]

material spilled during target filling

[Proprietary Information] [Proprietary Information]

• Provide capability to fill LEU targets to [Proprietary Information] [Proprietary In fo rmation]

specifications in Table 4-57 [Proprietary Information] [Proprieta ry Information]

• Perform qualification and verification * [Proprietary Information]

b [Proprietary Informati on] .

examinations on assembled targets 235 (e.g., helium leak check, weld inspection) U uranium-235 . U uranium.

TBD = to be determined. [Proprietary Information]

to meet licensing requirements

• 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, and 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 Ha ndling New target handling is generally addressed in Chapter 9.0. The discussion is located 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-1537, 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 .

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[Proprietary Information]

Figure 4-83. New Target Handling Flow Diagram New targets will be stored in the [Proprietary Information] (described in Section 4.4.2.10.3) 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. l ). 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 unirradiated targets will then be documented for material tracking and accountability per the safeguards and security system requirements. The ES-3100 shipping cask pallet wi ll 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).

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' ~ *.*! * . NORTifWHT MlDtCAl tSOTDPll NWMl-2015-021, Rev. 1 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 hazardous chemicals used in the subsystem. The process description (Section 4.4.2.2.1) 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 4.4.2.2.2 and 4.4.2.2.3. A description of the SNM in terms of physical and chemical form, volume in process, and criticality control features is provided in Section 4.4.2.2.4. 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 4.4.2.2.5 .

4.4.2.2.1 Process Description

[Proprietary Information]

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 Figure 4-84. ES-3100 Shipping Container uranium metal will be received in ES-3100 shipping containers. The ES-3100 shipping container design is shown in Figure 4-84.

Fresh uranium receipt handling - The fresh LEU handling subsystem function will begin with the arrival of the truck transporting the ES-3100 shipping casks containing the fresh LEU material to the fresh and unirradiated shipping and receiving area. The receiving area door will be opened, and the truck docked to the receiving bay, allowing 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) . 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 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 through the shipping and receiving airlock (Tl03) to the target fabrication room (Tl04).

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NORTHWUT MEOICAllSOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

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 Fl02) 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] .

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[Proprietary Information]

Figure 4-86. Fresh Uranium Dissolution Process Flow Diagram 4-184

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...... NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

, ' ! *,* ~ . NORTHWEST MEDICAl ISOTOPES 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 )z + 2 NO+ 2 HzO Equation 4-6 U0 2 + 4 HN0 3 ~ U0 2 (N0 3 ) 2 + 2 N0 2 + 2 H 2 0 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 offgas (Stream Fl05B) from exceeding 25 percent of the lower flammability limit. The offgas will be vented to the vessel ventilation system.

A pump (TF-P-110) 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 NOx emissions, along with an excessive loss of water, will be considered for the Operating License Application.

4.4.2.2.2 Process Equipment Arrangement Fresh Urani um Receipt The equipment arrangement associated with the fresh uranium receipt activities is described in Section 4.4.2.2.1.

Fresh Uranium Dissolution The fresh uranium dissolution process [Proprietary Information]

equipment will be mounted on a single skid within room Tl 04C, the wet side of the target fabrication room. Figure 4-87 shows the equipment arrangement, and Figure 4-88 shows the location of the process equipment. Figure 4-87. Fresh Uranium Dissolution Equipment Arrangement 4-1 85

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[Proprietary Information]

Figure 4-88. Dissolution Equipment Layout 4.4.2.2.3 Process Equipment Design Fresh Uranium Receipt Fresh uranium receipt activities will involve handling shipping casks and repackaging fresh LEU metal into criticality-safe containers. The design of the shipping containers is described in Section 4.4 .2.2. 1, and the design of the criticality-safe containers will be developed for the Operating License Application.

The auxiliary equipment that will be used to move sealed containers includes:

• TF-L-900, ES-3100 shipping cask floor crane

• TF-MC-900, ES-3100 shipping cask transfer cart

• TF-PH-900, ES-3100 shipping cask pallet jack Fresh Uranium Dissolution This section identifies the processing apparatus and auxiliary equipment supporting the fresh uranium dissolution subsystem. This equipment is listed in Table 4-58 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.

Table 4-58. Fresh Uranium Dissolution Process Equipment Uranium dissolver Equipment name TF-D-100 [Proprietary In formatio n)

Criticality-safe by geometry Yes lll11 *ii* Hi 304L SS 1111 Operating conditions 111

[Proprietary In formation)

Pressure

[Proprietary In formatio n]

Uranium dissolution filter TF-F-100 [Proprietary Yes TBD* [Proprietary [Proprietary Information) Information) Information]

Uranium dissolution pump TF _P-110 [Proprietary Yes TBD* [Proprietary [Proprietary In fo rmation] Information) Information]

Uranium dissolution cooler TF-E-120 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information) Information]

• Information will be provided in the Operating License Application submission.

MOC materials of construction . SS stainless stee l.

NIA = not app licable. TBD = to be determined.

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. ' ~ *.*! ." NORTNWtST M£01CAl ISOTOfl'ES NWMl-2015-021, Rev. 1 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 developed for the Operating License Application.

Fresh uranium dissolution will be a batch process. There 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 heating and recirculation pump (TF-P-110). The dissolution will proceed at [Proprietary Information].

Density instrumentation will 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. l 0.4). 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 Concentrationa l@ii!,,ij SNM massa Uranium dissolver (TF-D-100) [Proprietary In for mation] [Pro prietary In fo rmation] [Pro prietary [Proprietary In fo rmation] Information]

Uranium dissolver (TF-D-100) [Proprietary In formation] [Proprietary Information] [Proprietary [Proprietary lnfonnation] ln fonnation]

a SNM concentration and mass represent total amount of LEU (combined m u and 238 U at :S I 9.95 wt% m u) b Total uran ium in the di ssolver will not exceed this value. The form will change from uranium metal to uranyl nitrate during di ssolution, so the SNM mass in the di ssol ver will remain constant.

uranium-2 35. NIA not applicable.

uranium-2 38 . SNM special nucl ear material.

low-enriched uranium. u uranium.

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• NWMI NORTHWEST MEDICAi. ISOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-005, NWMI Preliminary Criticality Safety Evaluation : Target Fabrication Uranium Solution Processes. These features, including passive design features, active engineered features , and 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 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 criticality 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-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).

• Workstations where fresh LEU metal is handled do not have spill-prevention lips higher than 2.5 cm (1 in.) (CSE-05-PDF7).

• 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-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 active design features will include:

• The geometry of the closed-loop chilled water system is inherently criticality-safe (CSE-05-AEF 1), 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 controls 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-AC3) 4-188

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NORTHWHTMEDICALISOTOPES NWMl-2015-021, Rev. 1 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-18). 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-18) 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 many evenly spaced units contributing to the return of neutrons. Administrative failure s 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.

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. * ~ *.* ~ . NORJHWfST MEDICAL tsOTOPES 4.4.2.2.5 Chemical Hazards Chemical Inventory The chemical reagents for the fresh uranium dissolution are listed in Table 4-60. In addition to the chemical reagents, offgases will include NO, N02, and nitric acid fumes.

Table 4-60. Fresh Uranium Dissolution Chemical Inventory Concentration Chemical Quantity Physical form (if applicable)

Nitric acid (HN03) [Proprietary Information] [Proprietary Information) [Proprietary Informati on]

Note: This table does not include the SNM identified in Table 4-59.

SNM = special nuclear material.

Chemical Protection Provisions The primary chemical hazards in the fresh uranium dissolution subsystem will be a chemical spray of nitric acid or uranyl nitrate, and personnel exposure to offgases. A spray shield installed on the skid will protect the operator from chemical burns in the event of a spray leak from the dissolver or associated piping. The headspace above the dissolver will be purged by a sweep gas and maintained at a negative pressure to prevent personnel exposure to offgases.

4.4.2.3 Nitrate Extraction Subsystem The nitrate extraction subsystem description provides information regarding the process, process equipment, SNM inventory, and the hazardous chemicals used in the subsystem. The process description (Section 4.4.2.3 . 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 4.4.2.3.2 and 4.4.2.3 .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 .3.4. 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 4.4.2.3.5 .

4.4.2.3.1 Process Description Figure 4-89 provides the stream numbers corresponding to the nitrate extraction process description.

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' ~ * .* ~ : NORTHWUT MEDtcAL ISOTOPES

[Proprietary Information]

Figure 4-89. Nitrate Extraction Process Flow Diagram 4-191

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• NORTHW£ST Mf.OfCAl ISOTOP'lS NWMl-2015-021, Rev. 1 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]

mu [Proprietary Information] [Proprietary Information]

234U [Proprietary Information] [Proprietary Information]

23su [Proprietary Information] [Proprietary Information]

236U [Proprietary Information] [Proprietary Information]

Other Actinides 23Spu [Proprietary Information] [Proprietary Information]

239pu [Proprietary Information] [Proprietary Information]

24opu [Proprietary Information] [Proprietary Information]

242pu [Proprietary Information] [Proprietary Information]

241Am [Proprietary Information] [Proprietary Information]

231Np [Proprietary Information] [Proprietary Information]

231Pa [Proprietary Information] [Proprietary Information]

233pa [Proprietary Information] [Proprietary Information]

230Th [Proprietary Information] [Proprietary Information]

Fission Products 9szr [Proprietary Information] [Proprietary Information]

95Nb [Proprietary Information] [Proprietary Information]

103Ru [Proprietary Information] [Proprietary Information]

All others total [Proprietary Information] [Proprietary Information]

Other Impurities Iron [Proprietary Information] [Proprietary Information]

Chromium [Proprietary Information] [Proprietary Information]

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• NORTHWEST MEOtcAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-61. Recycled Uranium Specification (2 pages)

Chemical or physical propertya Specification Comment Nickel [Proprietary Information] [Proprietary Information]

Sodium [Proprietary Information] [Proprietary Information]

Source: NWMI-2013-049, Process System Functional Specification, Rev. C, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

• No constraint is imposed on the recycled uranium for chemical or phys ical properti es that are not listed in this table.

b (a, n) source limit = These isotopes represent potential sources of worker exposure due to interaction of alpha particles with light elements (e.g. , oxygen) that generate neutrons and could influence shielding requirements for target fabrication a nd handling systems. The specification is based on limiting th e neutron generati on rate increase of an individual isotope to

[Proprietary Information] . Estimate simplifications are described in NWMI-2013-049 .

c The facility will process LEU; processing hi gher uranium enrichments is not included in the process scope. A max imum product specification for mu is assumed to still be documented as part of the criticality safety controls. A minimum mu content is expected to be identified in the future based on target economjcs and is not included in the preconceptual design scope.

d y source limit = These isotopes represent potential gamma emitter sources of worker exposure and could influence shielding requirements for target fabrication and handling systems. The specification is based on limiting the unshielded dose

[Proprietary Information] . Estimate simplifications are described in NWMI-201 3-049.

LEU low-enri ched uranium. U = uranium.

ppmp U parts per million parts uranium by mass. [Proprietary Information]

TBD to be determined.

The uranyl nitrate solution will be stored in a tank (TF-TK-200) and blended and diluted with 235 demineralized water to create [Proprietary Information] uranyl nitrate solution with consistent U enrichment and impurities.

The nitrate extraction subsystem will use a solvent extraction process to remove nitrate from the solution to convert uranyl nitrate with excess nitric acid to ADUN with a ratio of [Proprietary Information]. The nitrate extraction process will last less than 4 hr/batch of uranyl nitrate received. The nitrate extraction reactions are given as:

Equation 4-8 Equation 4-9 The solvent extraction process will be accomplished with a [Proprietary Information]. Red oil formation is not a concern in this process because tributyl phosphate (TBP) is not present. The temperature for the solvent extraction process will be maintained at [Proprietary Information] by inline heaters for all feed s (TF-E-220, TF-E-223 , TF-E-226, and TF-E-255). To avoid uranium losses due to undesirable reactions, the uranium concentration will be controlled [Proprietary Information].

1. The nitrate extraction contactor (TF-Z-230) will mix the uranyl nitrate solution with [Proprietary Information] in solvent to extract nitrates (ORNL-5300, Resin-Based Preparation of HGTR Fuels: Operation of an Engineering-Scale Uranium Loading System). The inlet flow of uranyl nitrate will be [Proprietary Information]. An inline pH meter and transmitter on the uranyl nitrate stream will control the speed of the nitrate extraction solvent 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 will flow to the uranium recovery contactors (TF-Z-23 l A/B).

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2. The two uranium recovery contactors, configured in series (TF-Z-231A/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 solution to the aqueous waste holding subsystem, and the solvent will drain 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-231A/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 analyzed for uranium concentration in the analytical laboratory before 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 process equipment.

[Proprietary Information]

Figure 4-90. Nitrate Extraction Equipment Layout 4-194

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. ' ~ * .* ~ ' NORTHWEST MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Figure 4-91 shows the arrangement of the uranyl nitrate storage tank, which will receive [Proprietary Information]

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 nitrate extraction process. The solvent Figure 4-91. Uranyl Nitrate Storage Tank extraction will occur in bench-mounted Arrangement contactors. Uranyl nitrate will enter at the nitrate extraction contactor (TF-Z-230), and the ADUN product will flow to the phase 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-231A through TF-Z-233) before draining back to the nitrate extraction solvent feed tank (TF-TK-240) for recycle.

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[Proprietary Information]

Figure 4-92. 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 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.

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. * ~ *,~ ! .' , NORTHWHT MEDICAL ISOTOP£S Chapter 4.0 - RPF Description Table 4-62. Nitrate Extraction Process Equipment Criticality- ..

Equipment safe by Uranyl nitrate storage tank Equipment name no.

TF-TK-200

[Proprietary geometry Yes 304L SS Temperature

[Proprietary 14Mi!ii

[Proprietary Information] Information] Information]

Uranyl nitrate storage pump TF-P-210 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information] Information)

Uranyl nitrate feed pump TF-P-215 [Proprietary Yes TBD [Proprietary [Proprietary Informat ion] Information] Information]

Uranyl nitrate heater TF-E-220 [Proprietary Information]

NIA TBD [Proprietary Information]

[Proprietary Information]

Water heater TF-E-223 [Proprietary Information]

NIA TBD [Proprietary Information]

[Proprietary Information]

Caustic heater TF-E-226 [Proprietary Information]

NIA TBD [Proprietary Information]

[Proprietary Information)

Nitrate extraction contactor TF-Z-230 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information]

Uranium recovery contactor TF-Z-231A [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information]

Uranium recovery contactor TF-Z-23 lB [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information)

Organic regeneration contactor TF-Z-232 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information]

Wash contactor TF-Z-233 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information)

Nitrate extraction solvent feed TF-TK-240 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information]

tank Nitrate extraction solvent pump TF-P-250 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information) Information)

Solvent heater TF-E-255 [Proprietary Information]

NIA TBD [Proprietary Information]

[Proprietary Information)

Aqueous waste surge tank TF-TK-260 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information]

Aqueous waste surge pump TF-P-265 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information] Information]

Phase separator TF-SP-270 [Proprietary Yes TBD [Proprietary [Proprietary Informatio n] Information] Information]

ADUN surge tank TF-TK-280 [Proprietary Yes 304L SS [Proprietary [Proprietary Information) Information] Information]

ADUN surge tank pump TF-P-285 [Proprietary Yes TBD [Proprietary [Proprietary Informatio n] Information] Information]

ADUN acid-deficient uranyl nitrate. SS stainless steel.

NIA not applicable. TBD to be determined .

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 developed for the Operating License Application.

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.-.... NWMl-2015-021, Rev. 1

• * ~ *.* ~ ' NORTHWEST MEDICAl ISOTOPES Chapter 4.0 - RPF Description Nitrate extraction will be a semi-batch process. There are four normal modes of operation: standby, extraction preparation, nitrate extraction, and end of extraction.

• During standby mode, the uranyl nitrate storage tank (TF-TK-200) may receive recycled uranyl nitrate, fresh uranyl nitrate, and/or water for dilution. Pumps, heaters, and contactors will all 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 within TF-TK-200 by recirculation. The contactors (TF-Z-230- TF-Z-233),

solvent pump (TF-P-250), and solvent heater (TF-E-255) will be energized to preheat the contactors.

• To initiate nitrate extraction, all feed streams (uranyl nitrate, demineralized water, and 1.5 M caustic) will be opened, and their respective heaters energized. The first three contactors (TF-Z-230, TF-Z-231A/B) will recover ADUN as their aqueous product. The product will flow through the phase separator (TF-SP-270) to the ADUN surge tank (TF-TK-280), where product will be pumped to the ADUN evaporator feed tank (TF-TK-300).

• The end of extraction operations has not been defined .

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 uranyl nitrate.

Table 4-63 lists the SNM inventory, which includes the recycled uranyl nitrate storage tank.

Table 4-63. Nitrate Extraction Special Nuclear Material Inventory Location Form Concentration 3 p111,,1w SNM mass 3 Uranyl nitrate storage tank [Proprietary Information) [Proprietary [Propri etary [Propri etary Information] Information] Information]

(TF-TK-200) 238 a SNM concentration and mass represent the total amount of LEU (combined m u and U at ::O l 9.95 wt% m u )

uranium-235 SNM special nuclear material.

uranium-238 u = uranium.

low-enriched uranium.

Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-005 . These features, including passive design features, active engineered features, and 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 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 criticality control features.

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• ~ *.. ~ . NORTHWUT MEDICAi. ISOTOPES 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-PDFS).

• For the case of a liquid leak, the floor is criticality-safe (CSE-05-PDF l ), 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 provides 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: (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 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 siphoning 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 backtlow is impossible.

In addition to the features that apply the double-contingency principle, several features 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 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.

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• NORTHWEST MEDtCAL ISOTOnS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.2.3.5 Chemical Hazards Chemical Inventory The nitrate extraction chemical inventory is summarized in Table 4-64.

Table 4-64. Nitrate Extraction Chemical Inventory Concentration Chemical Quantity Physical form (if applicable)

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

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

Note: This table does not include 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 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 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 chemicals used in the subsystem. The process description (Section 4.4.2.4.1) 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 0 and 4.4.2.4.3. A description of the SNM in terms of physical and chemical form, volume in process, and criticality control features is provided in Section 4.4.2.4.4. 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 4.4.2.4.5.

4.4.2.4.1 Process Description 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].

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 ventilation system.

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• ** . * * ' NORTHWUT M£DtCAl ISOTOPES

[Proprietary Information]

Figure 4-93. Acid-Deficient Uranyl Nitrate Concentration Process Flow Diagram 4-201

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, ' ~ *.*! '

.. NORTHWEST ME.OICAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.2.4.2 Process Equipment Arrangement The ADUN concentration process equipment will be mounted on two skids within room Tl 04C, 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

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• ' ~ * .* ~

• NORTHWEST MEDICAL lSOTOPES NWMl-2015-021, Rev. 1 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 Figure 4-96. Acid-Deficient Uranyl Nitrate Concentration Feed Equipment Arrangement Concentration Equipment Arrangement 4.4.2.4.3 Process Equipment Design 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.

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• NORTHW£STM£01CALISOTOP£S NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-65. Acid Deficient Uranyl Nitrate Concentration Process Equipment Operating range Criticality-Individual safe by Tank Temperature Pressure Equipment name tank capacity geometry material

[Proprietary [Proprietary [Proprietary ADUN evaporator feed ta nk TF-TK-300 Info rmati on] Y es 304L SS In formation] Information]

[Proprietary [Proprietary [Proprietary ADUN evaporator feed pump TF-P-310 information] Yes TBD information] Information]

[Proprietary [Proprietary [Proprietary ADUN evaporator pump TF-P-3 20 In formation] Yes TBD In formati on] Informati on]

[Proprietary [Proprietary [Proprietary ADUN evaporator reboiler TF-E-330 Information] Yes 304L SS Information] Information]

[Proprietary [Proprietary [Proprietary ADUN e v aporator TF-V-340 Information] Yes 304L SS Information] Informati on]

[Proprietary [Proprietary [Proprietary ADUN evaporator condenser TF-E-350 Information] Yes 304L SS Information] information]

[Proprietary [Proprietary [Proprietary ADUN product heat excha ng er TF-E-360 In formation] Yes 304L S S In formation] info rmation]

ADUN acid-defi c ient uranyl nitrate . SS stainless stee l.

NIA = not applicable. TBD to be dete rmin ed .

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 of the process monitoring and control equipment will be developed for the Operating License Application.

ADUN concentration is a semi-batch process. There will be three normal modes of operation: standby, concentration, and end of concentration.

• During standby mode, the ADUN evaporator feed tank (TF-TK-300) may receive dilute ADUN from the nitrate extraction subsystem. Steam and chilled water supply valves will be closed, and pumps de-energized. TF-P-310 may be energized to mix contents.

• The evaporator will concentr ate the ADUN [Proprietary Information]. Level measurement will control the dilute ADUN inlet valve, and density measurement will control the product discharge valve. The product will be cooled to ambient temperatures in TF-E-360. The operator will initiate concentration mode by:

Feeding dilute ADUN to the ADUN evaporator (TF-V-340)

Beginning forced recirculation by energizing TF-P-320 Opening steam and chilled water supply valves to TF-E-330, TF-E-350, and TF-E-360

• The end of concentration mode will begin when feed from TF-TK-300 is exhausted and the ADUN within the evaporator has reached a [Proprietary Information]. The steam supply valve will be closed, and the concentrated ADUN will be pumped by TF-P-320 to TF-TK-400.

TF-P-320 will be deenergized, and the chilled water supply valves will be closed. After the end of concentration mode, the ADUN concentration subsystem will return to standby mode.

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~*

' ~ * .* ~

• NOfllTHWEST MEOICAl ISOTOP£S NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.2.4.4 Special Nuclear Material Description Special Nuclear Material 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 Uranyl Nitrate Concentration Maximum Special Nuclear Material Inventory Location Form Concentration 3 Volume SNM mass 3 ADUN evaporator feed tank [Proprietary Informati on] [Propri etary [Propri etary [Propri etary In formation) Information] Informati on)

(TF-TK-300)

ADUN evaporator [Proprietary Information) [Proprietary [Proprietary [Proprietary Information] Information) Information)

• SNM concentration and mass represent total amount of LE U (combined m u and 238 U at '.S I 9.95 wt% mu) b ADUN evaporator cannot receive more SNM mass than is in the ADUN evaporator fe ed tank due to the nature of the batch processing, so the evaporator feed tank provides a bounding estimate for the subsystem.

uranium-235. LEU low-enriched uranium.

uranium-238. SNM special nuclear material.

acid-defi cient uranyl nitrate. u uranium.

Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-20 l 5-CSE-005. These features, including passive design features, active engineered features and 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 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 criticality control features .

The passive design features affect the design of process equipment, ventilation piping, and the room floor, which 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 the evaporator feed tanks and the evaporator 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-PDF 1), and a barrier or seal prevents penetration of fissile material into the floor (CSE-05-PDF2).

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. * ~ * .* ~ ' NORTHWEST MEDICAL lSOTOHS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The active design features will include:

• The geometry of the closed-loop chilled water system is inherently criticality safe (CSE-05-AEF 1), 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 condensate return from the ADUN reboiler is monitored for uranium. If uranium is detected, an isolation valve prevents the condensate from returning to the process steam system (CSE-05-AEF2).

The administrative controls will include:

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

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 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 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 ADUN evaporator reboiler (TF-E-330) is an interface between the large-geometry steam system and fissile material. In the case of a heat exchanger failure simultaneous with a change in pressure differential, the condensate return piping could contain fissile material. A conductivity switch and interlock would close an isolation valve on the condensate return to prevent fissile material from proceeding to the process steam system (IROFS CS-10).

• 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 the double-contingency principle, several features 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 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.

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~ *.- ! NOflTNWHT M£DtcALISOTOP'U NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.2.4.5 Chemical Hazards Chemical Inventory 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 spray 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 Description Figure 4-97 provides the stream numbers corresponding to the [Proprietary Information] .

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

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• a

• . ~ ~.* ~ ' . NOATHWHT MEOfCAl ISOTOHI NWMl-2015-021 , Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

Figure 4-97. Sol-Gel Column Feed Process Flow Diagram 4-208

.-. ~ *.. *.* NWMI NWMl-2015-021, Rev. 1 0

~ ~. ~ .° NORTHWEST MEDICAL ISOTOP£S 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

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• ~ *.* ~ ' NOfllTifWUTMlDtCAl&SGTOPfS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

[Proprietary Information]

Figure 4-99. Concentrated Acid-Deficient Figure 4-100. Sol-Gel Column Feed Equipment Uranyl Nitrate Storage Equipment Arrangement Arrangement 4.4.2.5.3 Process Equipment Design This section identifies the processing apparatus and auxiliary equipment supporting the [Proprietary Information] subsystem. This equipment is listed in Table 4-67 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.

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.*:.**.* NWMl-2015-021, Rev. 1 Chapter 4 .0 - RPF Description

, * ~ *.*! . NORTHWtsT MEOfCAl ISOTOPlS Table 4-67. [Proprietary Information] Process Equipment Operating range Individual Equipment name tank capacity ... Temperature

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprieta ry [Proprietary [Proprietary Informat ion] Information] In formation] Information] Information] Information]

[Proprieta ry Information] [Proprietary [Proprietary [Proprietary [Prop rieta ry [Proprietary [Proprietary Information] Information] In formation ] In formation] Information] Information]

[Proprietary Information] [Proprieta ry [Proprietary [Proprietary [Pro prietary [Proprietary [Proprietary Information] In fo rmation] In formation] Info rmation] Information] Information]

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] Information] Information] Info rmat ion] Informatio n] Information]

[Proprieta ry Information] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Information] In formation] In formation] Information] Information] Information]

[Proprietary Info rmation] [Proprietary [Proprietary [Proprietary [Pro prietary [Prop rietary [Proprietary In formation] In formation] Information] In fo rmatio n] Informatio n] In formation]

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprieta ry [Proprietary [Proprietary Information] Information] Information] In format ion] Info rmation] Information]

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprieta ry [Proprietary [Proprietary Information] Info rmation] Information] Information] Information] Information]

[Proprietary Info rmation] [Proprietary [Proprietary [Proprietary [Proprieta ry [Proprietary [Proprietary Information] Info rmation] Information] In format ion] Information] In formation]

[Proprieta ry Informatio n] [Proprietary [Proprietary [Proprietary [Proprieta ry [Proprietary [Proprietary In formation] Info rmation] Information] In formation] Information] In formation]

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary In formation] In formation] Information] Information] Information] Information]

[Proprietary Info rmatio n] [Propr ietary [Proprietary [Proprietary [Pro prietary [Pro prietary [Proprietary Information] In formation] In formation] In formation] In formation] Info rmation]

ADUN acid-deficient uranyl nitrate. SS stainless steel.

NIA not applicable. TBD to be determined.

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 of the process monitoring and control equipment will be developed for the Operating License Application.

[Proprietary Information]

• [Proprietary Information]

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. * ~ ~** ~ ' NORTHWEST MEDICAL tSOTOPfS

• [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 Concentrationa @il!i,!j SNM massa

[Proprietary Information] [Proprietary informati on] [Propri etary [Proprietary [Proprietary Info rmation] Information information]

l a SNM concentration and mass represent total amount of LEU (combined mu and mu at '.S I 9.95 wt% mu) mu uranium-23 5. LEU low-enriched uranium.

mu uranium-238. SNM special nuclear material.

ADUN acid-deficient uranyl nitrate. u uranium.

Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-004, N WMI Preliminary Criticality Safety Evaluation: Low-Enriched Uranium Target Material Production . These features, including passive design features , active engineered features , and 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.

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 criticality control features.

The passive design features will include:

• The geometry of the process equipment is inherently criticality safe (CSE-04-PDF3, CSE-04-PDF7) 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). 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-PDF12).

• The ventilation system connected to process equipment containing fis sile material is inherently criticality-safe by geometry, and overflow drains prevent liquid accumulation beyond 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).

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..... NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

' ~ *.*!

• NOllTHWEST MEDtcA.l tSOTOftES The active engineered features will include:

• Continuous ventilation of tanks containing fissile material (CSE-04-AEF 1)

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 HMT A-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 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 siphoning is impossible.

• 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 the double-contingency 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 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.

4.4.2.5.5 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 Concentration Chemical Quantity Physical form (if applicable)

[Proprietary Information] [Proprietary lnformation] [Propri etary Information] [Propri etary Information]

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

Note : This table does not include the SNM identified in Table 4-68.

SNM = special nuclear material.

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. *.~ ~.~! .' . NORTHWHTMlDICAL ISOTOPU Chemical Protection Provisions

[Proprietary Information] . 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 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 described in Sections 4.4.2.6.2 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 .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]

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.-.;**....**.*NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• _* NOllTIIW£ST MEDICAL ISDlOPU

[Proprietary Information]

Figure 4-101. [Proprietary Information]Flow Diagram 4-215

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

' ~ * .* ~ .° NOflTifWIU MEDICAl ISOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

4.4.2.6.2 Process Equipment Arrangement

[Proprietary Information]

[Proprietary Information]

Figure 4-102. [Proprietary Information] Layout 4-216

• ...*..... NWMI

.-.~ *

, ' ! *,* ~ ." NORTHWEST M(OtCM ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

[Proprietary Information]

4.4.2.6.3 Process Equipment Design This section identifies the processing apparatus and [Proprietary Information] column subsystem. Figure 4-103. [Proprietary Information]

This equipment is listed in Table 4-70 with design Arrangement 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.

4-217

........;... . NWMI

• ~ *.* !

• NORTHWEST MEOICAUSOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-70. [Proprietary Information]

Equipment name

[Proprietary lnfonnation]

[Proprietary Information]

(Proprietary Infonnation]

- [Proprietary lnfonnation]

[Prop rietary ln fo nnation]

[Proprietary Individual

[Proprietary Infonnation]

[Proprietary lnfonnation]

[Proprietary Criticality-safe tank capacity by geometry

[Proprietary lnfonnation]

[Proprietary ln fonnation]

[Proprietary

-[Proprietary Infonnation]

[Proprietary lnfonnation]

[Proprieta ry Operating range Temperature

[Proprietary lnfonnation]

[Proprietary In fo rmation]

[Proprieta ry Pressure

[Proprietary Infonnation]

[Pro prietary lnfonnation]

[Proprietary lnfonnation] lnfonnation] lnfonnation] Infonnation] Infonnation] lnfonnation]

[Proprietary ln fonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfo nnation] lnfo nnation] In formation] Information] ln fo nnation] ln fonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation] Infonnation] lnfonnation] lnfonnation]

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprieta ry [Proprietary [Proprietary In formation] lnfonnation] Info rmation] In fo rmation] In fo rmation] Info rmation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] Infonnation] lnfonnation] lnfonnation] lnfonnation] Infonnation]

[Proprietary Information] [Proprietary [Proprietary [Proprietary [Proprietary [Pro prietary [Proprietary ln fonnation] lnfonnation] In formation] In fo rmation] In formation] Info rmation]

NIA not applicable. TBD to be determined.

SS stainless steel.

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 set 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]

• [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: Target Finishing. These features, including passive design features, active engineered features, and administrative controls, allow for adherence to the double-contingency principle.

4-218

~ *~ -.*.- NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

,' ~ *.* ~ ' NORTNWHT M£0tcAl ISOTO~S 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-PDF 13). 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-PDF12).

• Workstations where LEU target material is handled do not have spill-prevention lips 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 beyond 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 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. 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

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.-.~ *

. ' ~ *.~ ! * . NOATHWUTM(DfCALISOTOPH NWMl-2015-021, Rev. 1 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 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 in 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.

4.4.2.6.5 Chemical Hazards Chemical Inventory

[Proprietary Information]

Table 4-71. [Proprietary Information] Subsystem Concentration Chemical Quantity Physical form (if applicable)

[Propri etary Information] [Proprietary [Proprietary [Proprietary Information] Information] Information]

Note: This table does not include the SNM identified in Table 4-68 .

SNM = special nuclear material.

Chemical Protection Provisions

[Proprietary Information].

4.4.2.7 [Proprietary Information] Subsystem 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 4.4.2.7. 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 4.4.2.7.2 and 4.4.2. 7.3 . A description of the SNM in terms of physical and chemical form, volume in process, and criticality control features is provided in Section 4.4.2.7.4. 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 .2.7.5.

4.4.2.7.1 Process Description Figure 4-104 provides the stream numbers corresponding to the [Proprietary Information] descriptions.

4-220

. .... NWMI

.-.~ *

• ~ * .* ~

• NORTHWEST MEDtcAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

Figure 4-104. [Proprietary Information] Flow Diagram 4-221

. NWMI

~ * .* ~

• NOtlTIIWEIT MEDICAi. lSCJTOHI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[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]

4-222

..;*....*.**NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

~ ~

0 0

• .

• NOl!:TifWHT MEDtCAl lSOTO"S

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

• [Proprietary Information]

[Proprietary Information]

[Proprietary Information]

4-223

.... ....... . NWMI

. :~ ~

' ~ *.*! ' NORTHWEST MlDM:AL ISOTOHS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

Table 4-72. [Proprietary Information]

[Proprietary Information]

Probable recycle

[Proprietary Information] Process operation material

[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]

LEU = low-enriched uran ium.

[Proprietary Informati on]

[Proprietary Information]

4-224

..... .;*

..*:*NWMI

. *. ~ ~.* ! :

NORTHWHTMEOICA.LISOTOftlS NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.2.7.2 Process Equipment Arrangement

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

Figure 4-105. [Proprietary Information] Layout

[Proprietary Information]

[Proprietary Information]

Figure 4-106. [Proprietary Information]

Arrangement 4-225

..~ ..: *. ..NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

• ~ *.~~ ' NORTHWEST MEDtCAL tsOTOPEI

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

[Proprietary Information] Figure 4-107. [Proprietary Information]

Arrangement

[Proprietary Information]

Figure 4-108. [Proprietary Information] Layout 4-226

~ . .;..

.....*.*. NWMI NWMl-2015-021, Rev. 1

~

. ' *.*! . NORTHWUT M£DtCAL l$0TOPH Chapter 4.0 - RPF Description Figure 4-109 shows the arrangement of the [Proprietary Information].

[Proprietary Information]

Figure 4-109. [Proprietary Information] Arrangement 4.4.2.7.3 Process Equipment Design

[Proprietary Information]. Equipment is listed in Table 4-73 with the 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.

4-227

.....*.**.......*..*.*.. NWMI

. ' ~ *.* ! :

~

NORTHWUTMfDICAllSOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-73. [Proprietary Information]

Operating range Equipment name

[Proprietary lnfonnation]

Equipment no.

[Proprietary [Proprietary

[Proprietary

[Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary ln fonnat ion] [Proprietary [Proprietary [Propri etary [Propri etary [Propri etary [Propri etary Infonnation] In fonnation] lnfonnation] ln fo nnation] lnfonnation] Infonnati on]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] In fonnation] lnfonnati on] lnfonnation] Infonnation] Infonnation]

[Proprietary ln fonnati on] [Propri etary [Propri etary [Propri etary [Proprietary [Proprietary [Proprietary Info nnati on] ln fonnation] ln fo nnati on] ln fo nnati on] Infonnation] lnfo nnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] Infonnation] Infonnation] Infonnation] lnfonnation]

[Propri etary Infonnati on] [Propri etary [Propri etary [Proprietary [Propri etary [Propri etary [Proprietary In fo nnati on] lnfonnation] In fo nnation] ln fonnati on] Infonnation] Infonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] Infonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary ln fonnation] [Proprietary [Proprietary [Propri etary [Propri etary [Proprietary [Proprietary Infonnation] In fo nnation] In fonnation] lnfonnation] Infonnati on] Info nnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary Infonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary lnfo nnati on] [Propri etary [Proprietary [Propri etary [Proprietary [Propri etary [Propri etary In fo nnati on] lnfonnation] Info nnati on] ln fo nnation] ln fonnati on] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary lnfo nnation] [Proprietary [Proprietary [Proprietary [Propri etary [Proprietary [Proprietary Ln fo nnation] ln fo nnation] In fonnation] Infonnation] lnfo nnation] Ln fonnati on]

[Proprietary lnfonnation] [Proprietary [Proprietary [Propri etary [Proprietary [Proprietary [Proprietary lnfonnation] Lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary ln fonnation] [Propri etary [Propri etary [Proprietary [Proprietary [Proprietary [Proprietary lnfo nnati on] lnfonnation] lnfo nnati on] ln fonnation] ln fonnati on] ln fonnati on]

[Proprietary Infonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] lnfonnation] lnfonnation] lnfonnation] Lnfonnation] lnfonnation]

[Proprietary ln fo nnation] [Proprietary [Propri etary [Proprietary [Proprietary [Propri etary [Proprietary Infonnati on] ln fo nnati on] Infonnation] ln fonnati on] lnfonnati on] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary [Proprietary lnfonnation] Lnfonnation] lnfonnation] lnfonnation] lnfonnation] lnfonnation]

[Proprietary lnfonnation] [Proprietary [Proprietary [Proprietary [Propri etary [Propri etary [Proprietary Ln fonnation] ln fo nnati on] In fonnation] ln fonnati on] lnfonnati on] lnfonnation]

[Proprietary In fo rmati o n] SS sta inl ess steel.

LEU lo w-e nric hed uranium. TBD to be determined .

NIA not applicable . TCE tric hl oroethylene .

[P ropri etary In fo rmati o n] .

4-228

......;. .. NWMI

. * ~ *.*! . NOkTifWHT Ml'.DtcAllSDTO.-£.S NWMl-2015-021, Rev. 1 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 of the process monitoring and control equipment will be developed for the Operating License Application.

[Proprietary Information]

• [Proprietary Information]

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

[Proprietary Information]

• [Proprietary Information]

4.4.2.7.4 Special Nuclear Material Description Spent Nuclear Material Inventory

[Proprietary Information]

Table 4-74. [Proprietary Information]

Location Form Concentration 3 l@il!,,!W SNM mass 3

[Proprietary Information] [Propri etary In formation] [Proprietary [Proprietary [Proprietary Information] Information] Information]

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

[Proprietary Information] [Proprietary In formation] [Proprietary [Proprietary [Proprietary Information] Information] Information]

a SNM concentration and mass represent total amount of LEU (combined 235 U and 238 U at ::; 19.95 wt% 235 U) 23su uraniurn-235 . SNM = special nuclear material.

23su uranium-238 . U = uranium.

LEU low-enriched uranium. [Proprietary Information]

NIA not applicable. [Proprietary Information]

4-229

....... ..**;*..: NWMI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 0

~ * , * ~: , NORTHWEST MEOICM ISOTOPES Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-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 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 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-PDF13). Process equipment and piping are designed for the normal process fluids and operating temperatures to minimize leakage (CSE-04-PDF6).

• Workstations where LEU target material is handled do not have spill-prevention lips 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 beyond 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-AEF 1)

The administrative controls will include:

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

• Minimum spacing 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

~

. ' ~ * ,* ~ ' NOfllTHWEST MEDtCAL ISOTOf'U NWMl-2015-021, Rev. 1 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, including (l) outside diameter of process equipment and piping (IROFS CS-06), and (2) fixed spacing between process equipment with fissile solution (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 discharges 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 sloped 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 many evenly spaced units contributing to the return of neutrons. Administrative 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. 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 drying and reduction steps.

Table 4-75. Chemical Inventory for the [Proprietary Information) Subsystem Concentration Chemical Quantity Physical form (if applicable)

[Proprietary lnfonnation) [Propri etary Jn fonnation) [Propri etary lnfonnati on] [Proprietary Jnfonnation]

[Proprietary lnfonnation) [Proprietary lnfonnation)' [Proprietary lnfonnation) [Proprietary lnfonnation)

Note: This table does not include the SNM identified in Table 4-74.

• [Proprietary Information]

SNM = special nuclear material.

4-231

....... . NWMI

.**.*.*. ~ *

.*.' *~ *.**.~ ** .**

NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. NORTHWESTMEOICMISOTOPH Chemical Protection Provisions The primary chemical hazard in the [Proprietary Information]. The method of ventilation 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 offgases 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 process, 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 equipment, 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 evolve during 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 feed tank. The waste from the solvent recovery package will be collected locally to be discarded.

Aqueous Waste Holding Aqueous waste will be generated in the nitrate extraction, ADUN concentration, and [Proprietary Information] subsystems. Under normal operating conditions, no fissile material will be present 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 of 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 development of the final RPF design.

4-232

NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information]

Figure 4-110. Target Fabrication Waste Process Flow Diagram 4-233

.. NWMI

• ~e *! . NOllTHWEST MU>ICM ISOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Target Fabrication Vessel Ventilation Overflow Protection Based on the configuration of tanks and pumps, a tank with fissile material could potentially overflow to the vessel ventilation header due to equipment fai lure 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 Tl04C, 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

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' ~ *.* !

• NOkTHWUTMEOICALISOTOPE.S Figure 4-112 shows the typical arrangement of the aqueous waste holding tank skids. Figure 4-1 I 3 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] [Proprietary Information]

Figure 4-112. Aqueous Waste Figure 4-113. Trichloroethylene Recovery Holding Tank Skid Arrangement 4.4.2.8.3 Process Equipment Design 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.

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• ~ * .* ~

• NORTHWEST MlDICAl ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Table 4-76. Target Fabrication Waste Process Equipment Operating range Equipment . .. .

Equipment name no. . . . . . Temperature 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] Information] 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 Informat ion] Information] info rmation]

TCE recycle tank TF-TK-720 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] Information]

T CE recycle tank TF-TK-725 [Proprietary Yes 304L SS [Proprietary [Proprietary In fo rmation] In formation] Information]

TCE recycle pump TF-P-730 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information] Information]

TCE recovery p ackage TF-Z-740 [Proprietary No TBD [Propri etary [Proprietary In formation] Information] Information]

Regenerated TCE tank TF-TK-750 [Proprietary No 304L SS [Proprietary [Proprietary Information] Information] Information]

R egenerated TCE pump TF-P-755 [Proprietary No TBD [Proprietary [Proprietary Informati on] Information] information]

TCE tank TF-TK-760 [Proprietary No 304L SS [Proprietary [Proprietary Information] Information] Information]

Target fabrication overflow ta nk TF-TK-770 [Proprietary Yes 304L SS [Proprietary [Proprietary Information] Information] information]

Target fabrication overflow TF-P-775 [Proprietary Yes TBD [Proprietary [Proprietary Information] Information] information]

pump NIA not app licable. TBD to be determined.

SS stain less stee l. TCE trichloroethylene.

Process Monitoring and Control Equipment 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 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.

The aqueous waste holding function will be a batch process. The aqueous waste holding 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 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 laboratory 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.

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. ' ~ *,*! . NOATHWUT MEDICAL ISOTOPfS 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-2015-CSE-009, NWMI Preliminary Criticality Safety Evaluation: Liquid Waste Processing. 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 measures 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 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 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 solutions 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).

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• 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 defense-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 vo lumes 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 summarized in Table 4-77 .

Trichloroethylene Chemical ....

Table 4-77. Target Fabrication Waste Chemical Inventory

[Propri etary in formation)

[Proprietary

[Propri etary Information)

[Proprietary Concentration (if applicable)

[Proprietary Info rmation]

[Proprietary Aqueous waste (may contain ammonium hydroxide, ammonium nitrate, information) Information] information]

HMT A, nitric acid, sodium hydroxide, sodium nitrate, and urea)

HMTA = hexamethylenetetramine. NIA = not applicable.

Chemical Protection Provisions 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 negative pressure and vented to the vessel ventilation system 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 inventory, 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, including 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 may evolve during the process, along with the provisions to protect workers and the public from exposure, are described in Section 4.4.2.9.5.

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NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

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• HOmfWl:ST MlOtcAL ISOTOPES 4.4.2.9.1 Process Description Target Loading Target loading will be performed using the target loading preparation workstation (TF-WT-800) and target loading workstation (TF-WT-810) located within the target assembly area (TF-800), as shown in Figure 4-114. An interim transfer container of LEU target material will be received from the LEU can rack. All handling of open LEU target material containers will occur in an anti-static work area. Target hardware from the target hardware storage rack will be weighed, and the partially assembled target will be vertically secured in a target-loading fixture in preparation for loading. An [Proprietary Information]

will be weighed following the material accountability procedure and loaded 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

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........ NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

~ * *! . NORTHWEST MlDICAl tsOTOPH 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 [Proprietary Information]

(TF-EN-820) via the target entry airlock. The airlock will be sized to minimize helium consumption during target entry activities. The Figure 4-115. Target Welding Enclosure airlock will be configured at an angle with target capture features to provide safe and controlled [Proprietary Information]

target entry into the glovebox. A helium environment in the enclosure will provide a cover Figure 4-116. Target Weld Finishing Workstation gas within the target and allow for the subsequent helium leak check. Targets will be secured in a target welding fixture. The temporary upper end fitting will be manually removed, and the upper cap washer positioned for the first weld.

The glovebox 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 during welding. A layout of the target welding enclosure is shown in Figure 4-115 . Welded targets will be routed to the target weld finishing workstation (TF-WT-820) for grinding and polishing of the welded areas of the target. A layout of the target weld finishing workstation is shown in Figure 4- 11 6.

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, * ~ *.* ~ : NOATHWHTM£DK:ALISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Target Qualification Immediately following the removal of welded targets from the welding enclosure, the welds will be finished at the target weld finishing workstation (TF-WT-820) and inspected at the target weld inspection workstation (TF-WT-830) (Figure 4-117). Following the weld inspection, the target assembly will be weighed and checked for dimensional conformance using go/no-go gauges.

Targets will 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 leaks exist in the target. A helium mass spectrometer will indicate the helium leak rate for the tested target. Targets that pass the helium leak test will be scanned and cleaned of any surface contamination. These analyses will verify that the: ( 1) targets are sealed, (2) weld integrities are adequate, and (3) target physical dimensions and weight meet specifications.

[Proprietary Information]

Figure 4-117. Target Weld Inspection Station and Target Weight Inspection Equipment 4-241

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• NOIUHWEnMlDtCAt.tSOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description Target Qualification Failure Completed targets that fail any of the quality checking and verification analyses will be recycled [Proprietary Information]

and the LEU target material will be recovered as off-specification uranium. The primary steps Figure 4-118. Target Disassembly Workstation involved in handling failed targets are provided in Section 4.1.4.4. The failed target will be transferred to a target disassembly workstation (TF-WT-870), which will house a target cutting tool and a target unloading system for collecting the LEU target material. The retrieved LEU target material will be handled as off-specification uranium for uranium recovery, since unwanted foreign material may be present. A layout of the target disassembly workstation is shown in Figure 4-118.

4.4.2.9.2 Process Equipment Arrangement The target assembly process equipment will be located throughout room Tl 04B, the dry side of the target fabrication room. Figure 4-119 shows the location of the process equipment. The arrangement of the target assembly process equipment is discussed throughout the process description.

[Proprietary Information]

Figure 4-119. Target Assembly Equipment Layout 4-242

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• ~ *.* ~ ' HORTNWHT M£0tCAl lSOTOPU NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 4.4.2.9.3 Process Equipment Design The process equipment in the target assembly Table 4-78. Target Assembly Auxiliary Equipment subsystem will consist of containers and target assemblies that house the LEU target material, Equipment name Equipment no.

target filling equipment, target welding LEU can transfer cart TF-MC-800 equipment, target QC equipment, and storage Target loading prep workstation TF-WT-800 carts, as identified in the process description.

The target assemblies are described in this Target loading workstation TF-WT-810 section, and the target storage carts are Target welding enclosure TF-EN-820 described in Section 4.4.2.l0.3 . The auxiliary Target weld fini shing workstation TF-WT-820 equipment that is identified in Target weld inspection workstation TF-WT-830 Section 4.4.2.9 .l is listed in Table 4-78 .

Additional detailed information on the target Target specification check workstation TF-WT-840 assembly equipment will be developed for the Target leak check workstation TF-WT-850 Operating License Application.

Target surface contamination check TF-WT-860 Target Design workstation Target disassembly workstation TF-WT-870 The target hardware physical description is as LEU = low-enriched uranium.

described in Docket Number 50-243, "Oregon State TRI GA Reactor License Amendment for Irradiation of Fuel Bearing Targets for [Proprietary Information]

Production of Molybdenum-99 ."

[Proprietary Information] as shown in Source: Docket Number 50-243, "Oregon State TRI GA Reactor Figure 4-120. License Amendment for Irradiation of Fuel Bearing Targets for Production ofMolybdenum-99," April 201 2.

Figure 4-120. Target Assembly Diagram (Doc-No 50-243) 4-243

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. ' ~ *.*! . NOflTHWEn MEDtCM. ISOTOl'ES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

[Proprietary Information] Design parameters Table 4-79. Target Design Parameters are summarized in Table 4-79.

Parameter Nominal design value The inner and outer aluminum cladding

[Proprietary Information] [Proprietary Information]

sections will be welded to a cap washer at the top and bottom to provide the primary seal. [Proprietary Information] [Proprietary Information]

The [Proprietary Information]. [Proprietary Information] [Proprietary Information]

[Proprietary Information] [Proprietary Information]

Upper and lower end fittings will be welded to the top and bottom of the annular target- [Proprietary Information] [Proprietary Information]

bearing section. The upper fitting will be [Proprietary Information] [Proprietary Information]

designed to interface with the upper gridplate

[Proprietary Information] [Proprietary Information]

holes and will incorporate a pin that allows handling of the target using the standard [Proprietary Information] [Proprietary Information]

[Proprietary Information]. The lower fitting [Proprietary Information] [Proprietary Information]

will be designed to position the LEU material [Proprietary Information] [Proprietary Information]

portion of the target at a fixed height and

[Proprietary Information] [Proprietary Information]

incorporate a pin that interfaces with the indexing holes in the lower gridplate. Fittings [Proprietary Information] [Proprietary Information]

will be mounted to the LEU material-bearing [Proprietary Information] [Proprietary Information]

portion of the target by a welded triangular

[Proprietary Information] [Proprietary Information]

spider that allows coolant flow through the inner portion of the target. [Proprietary Information] [Proprietary Information]

Source: Docket Number 50-243 , "Oregon State TRIGA Reactor License Amendment for Irradiation of Fuel Bearing Targets for Production of Molybdenum-99," April 2012 .

LEU = low-enriched uranium.

[Proprietary Information] .

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. * ~ * ,* ~ ' NO<<THWHT MEDICAL ISOTOPES NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 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 lists the SNM inventory, which will be limited per workstation to the amount of LEU in one target.

Table 4-80. Target Assembly Special Nuclear Material Inventory workstation (TF-WT-800)

Location Target loading preparation Target loading workstation (TF-WT-810)

Form

[Proprietary Information]

[Proprietary Information]

Concentration a

[Proprietary Information]

[Proprietary Information]

- [Proprietary Information]

[Proprietary Information]

SNM mass 3

[Proprietary Information]

[Proprietary Information]

Target welding enclosure [Proprietary Information] [Proprietary [Proprietary [Proprietary Information] Information] Information]

(TF-EN-820)

Target weld finishing [Proprietary Information] [Proprietary [Proprietary [Proprietary Information] Information] Information]

workstation (TF-WT-820)

Target weld inspection [Proprietary Information] [Proprietary [Proprietary [Proprietary Information] Information] Information) workstation (TF-WT-830)

Target specification check [Proprietary Information] [Proprietary [Proprietary [Proprietary information] Information] information]

workstation (TF-WT-840)

Target leak check workstation [Proprietary Information] [Proprietary [Proprietary [Proprietary Information] Information] Information]

(TF-WT-850)

Target surface contamination [Proprietary In formation] [Proprietary [Proprietary [Proprietary Information] Information) Information]

check workstation (TF-WT -860)

• SNM concentration and mass represent total amount of LEU (combined m u and m u at :5 19.95 wt% mu) 23s u uranium-235. SNM = special nuclear material.

mu uranium-238 . [Proprietary Information]

N IA not applicable.

Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-006. These features , consisting of passive design features, 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 measures and features are identified.

The criticality control features for this subsystem are the passive design features, with a designator of PDF, listed below. Chapter 6.0 provides detailed descriptions of the criticality control features.

The passive design features will define the following requirements of the workstations:

• Workstations where LEU target material is handled, including the equipment on the workstations, remain in place during and following a facility DBE (CSE-06-PDFl).

• Spill-prevention lips on the workstations do not exceed 2.54 cm (1 in.) (CSE-06-PDF2) 4-245

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' ~ * *! ' NORTHWEST lllDfCAl ISOTOHI NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description 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 requirements:

• Size limit of process apparatus holding target material (CSE-06-ACI 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 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 assembly activities.

• LEU target material is handled in approved containers and within the mass and batch handling limits (IROFS CS-02).

• While moving the [Proprietary Information], minimum spacing between the container and other fissile material is managed administratively (IROFS CS -03). These measures: (I) limit the operator to handle [Proprietary Information] , (2) require use of approved workstations with interaction control spacing from other fissile material, and (3) provide interaction guards at normally accessible fi ssile 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 uranium is dry during normal conditions.

• Administrative interaction controls are based on many evenly spaced units contributing to the return of neutrons. Administrative 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 wou ld be managed similar 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 physical and chemical form, volume in process, and criticality control features is provided in Section 4.4.2.10.4.

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• NORTHWEST M£DtcALISOTOf'ES NWMl-2015-021, Rev. 1 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]

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NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description

. * ~ ~.* ~

• NORTIIWUT MfDICAl ISOTOPfS

[Proprietary Information]

[Proprietary Information] [Proprietary Information]

[Proprietary Information]

Figure 4-122. Low-Enriched Uranium Can Rack

[Proprietary Information]

[Proprietary Information] [Proprietary Information]

[Proprietary Information]

Figure 4-123. 12-Position Target Cart

[Proprietary Information]

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• ~ *.*! ' HORTMWHT MEDtcALISOTOPf.S 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 Concentrationa ri!l!..!j SNM massa

[Proprietary Information] [Proprietary In format ion] [Proprietary [Proprietary [Proprietary Information] Information] Information]

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

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

• SNM concentration and mass represent total amount of LEU (combined mu and 238 U at :'.'S 19 .95 wt% mu)

[Proprietary Information]

mu uranium-235 . SNM = special nuclear material.

23su uranium-238. U = uranium.

LEU low-enriched uranium. [Proprietary Information]

NIA not applicable.

Criticality Control Features Criticality control features are required in this subsystem, as defined in NWMI-2015-CSE-007, NWMI Preliminary Criticality Safety Evaluation: Target and Can Storage and Carts. These features, including passive design features and 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 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]

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• ~!~!~**

0 NOmfWlSTMOHCAI. ISOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description The following administrative controls define the requirements for which containers should be used for specific activities, quantity limits of handling fissile material, and spacing requirements:

• Volume and mass limits of target material containers (CSE-07-ACl , CSE-07-AC6) and fresh LEU metal containers (CSE-07-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-AC5 , 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 following IROFS will be applicable to the LEU storage activities.

• [Proprietary Information] (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.

• [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 uranium is dry during normal conditions.

• Administrative interaction controls are based on many evenly spaced units contributing to the return of neutrons . Administrative 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.

4.4.2.10.5 Chemical Hazards Chemical hazards have not been identified, and are not anticipated, for the LEU storage subsystem.

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4.5 REFERENCES

10 CFR 20, "Standards for Protection Against Radiation," Code of Federal Regulations, Office of the Federal Register, as amended.

10 CFR 50, "Domestic Licensing of Production and Utilization Facilities," Code of Federal Regulations, Office of the Federal Register, as amended.

10 CFR 70, "Domestic Licensing of Special Nuclear Material ," Code of Federal Regulations, Office of the Federal Register, as amended.

40 CFR 61 , "National Emission Standards for Hazardous Air Pollutants," Code of Federal Regulations, Office of the Federal Register, as amended.

49 CFR 173 , "Shippers - General Requirements for Shipments and Packages," Code of Federal Regulations, Office of the Federal Register, as amended.

ACI 349, Code Requirements for Nuclear Safety-Related Concrete Structures, American Concrete Institute, Farmington Hills, Michigan, 2014.

ANS 6.4-2006, Nuclear Analysis and Design of Concrete Radiation Shielding /or Nuclear Power Plants, American Nuclear Society, La Grange Park, Illinois, 2006.

ANSVANS-6.4, Nuclear Analysis and Design of Concrete Radiation Shielding /or Nuclear Power Plants, American Nuclear Society, La Grange Park, Illinois, 2006.

ANSI/ ASME 36.19M, Stainless Steel Pipe, American Society of Mechanical Engineers, 4th Edition, New York, New York, 2015.

ASCE 7, Minimum Design Loads fo r Buildings and Other Structures, American Society of Civil Engineers, Reston, Virginia, 2013 .

ASTM C1233-09, Standard Practice for Determining EBC of Nuclear Materials, ASTM International, West Conshohocken, Pennsylvania, 2009.

C-003-001456-007, "Poly HIC CRM Flat Bottom Liner, Rev. 3, EnergySolutions, Columbia, South Carolina.

Docket Number 50-243 , "Oregon State TRIG A Reactor License Amendment for Irradiation of Fuel Bearing Targets for Production ofMolybdenum-99, License Number R-106, submitted by the Oregon State University Radiation Center, Oregon State University, Corvallis, Oregon, April 2012 .

[Proprietary Information]

INL/EXT-12-27075 , Iodine Sorbent Performance in FY 201 2 Deep Bed Tests, Idaho National Laboratory, Idaho Falls, Idaho, 2012 .

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NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non -Power Reactors - Format and Content, Part 1, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, D.C. , February 1996.

NWMI-2013-049, Process System Functional Specification , Rev. C, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

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• NORTtfWHTMlDICALISOTOPH NWMl-2015-021, Rev. 1 Chapter 4.0 - RPF Description NWMI-2013-CALC-002, Overall Summary Material Balance - OSU Target Batch, Rev. B, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2013-CALC-006, Overall Summary Material Balance - M URR 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 l , Source Term Calculations, Rev A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2013-CALC-013 , Irradiated Target Dissolution System Equipment Sizing, Rev. B, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

NWMI-2014-CALC-014, Selection of Dominant Target Isotopes for N WMI Material Balances, Rev. A, Northwest Medical Isot?pes, LLC, Corvallis, Oregon, 2014.

NWMI-20 l 5-CRITCALC-002, Irradiated Target Low-Enriched Uranium Material Dissolution , Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-CRITCALC-006, Tank Hot Cell Tank, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2014-RPT-005 , Uranium Recovery and Recycle Process Evaluation Decisions, Rev. 0, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2014.

NWMI-2015-CSE-001 , NWMI Preliminary Criticality Safety Evaluation: Irradiated Target Handling and Disassembly, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

NWMI-2015-CSE-002, N WMI Preliminary Criticality Safety Evaluation: Irradiated Low-Enriched Uranium Target Material Dissolution, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-CSE-003 , N WMI Preliminary Criticality Safety Evaluation : Molybdenum 99 Product Recovery, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-CSE-004, NWMI Preliminary Criticality Safety Evaluation: Low-Enriched Uranium Target Material Production, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

NWMI-20 l 5-CSE-005, N WMI Preliminary Criticality Safety Evaluation: Target Fabrication Uranium Solution Processes, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-CSE-006, N WMI Preliminary Criticality Safety Evaluation: Target Finishing, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

NWMI-20 I 5-CSE-007, NWMI Preliminary Criticality Safety Evaluation: Target and Can Storage and Carts, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015.

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Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-CSE-009, N WMI Preliminary Criticality Safety Evaluation: Liquid Waste Processing, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-RPT-007, Process Tim e-Cy cle Analysis Report (Part 50 License), Rev. 0, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

NWMI-2015-SHIELD-001 , Radioisotope Production Facility Shielding Analysis, Rev. A, Northwest Medical Isotopes, LLC, Corvallis, Oregon, 2015 .

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• ~ *.* ~ ' NOlmfWEIT M£DfCAL ISOTOPU ORNL-5300, Resin-Based Preparation of HGTR Fuels: Operation of an Engineering-Scale Uranium Loading System, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 1977.

ORNL/TM-5518, Design and Test of a Thermosiphon Evaporator for Acid-Deficient Uranyl Nitrate, Oak Ridge National Laboratory, Oak Ridge, Tennessee, November 1976.

ORNL/TM-6607, A Literature Survey of Methods to Remove Iodine from Offgas Streams Using Solid Sorbents, Oak Ridge National Laboratory, 1979.

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Regulatory Guide 1.69, Concrete Radiation Shields and Generic Shield Testingfor Nuclear Power Plants, Rev. 1, U.S. Nuclear Regulatory Commission, Washington, D.C., May 2009.

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