ML18016A964: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:1Exhibit NWMI-004-R1Northwest Medical Isotopes, LLC Radioisotope Production Facility OverviewJanuary 23, 2018U.S. Nuclear Regulatory CommissionCommission Mandatory Meeting 2Exhibit NWMI-004-RNWMI MissionFabricatedTargetsIrradiation services supplier99MosupplierTechnetium generator supplier99mTcsupplierIrradiatedtargetsCaptive Network of University Research ReactorsReliability/assurance of supplyMultiple shipments/weekRadioisotope Production Facility (RPF)Fabrication of LEU targets99Mo productionUranium recycle and recoveryDomestic 99Mo Generator DistributorsHold FDA Drug Master FileNo changes to generatorsNo changes to supply chain99MoTechnetium generators99mTcradiopharmaceuticalsAssure a Domestic, Secure, and Reliable Supply of Molybdenum-99 (99Mo) End User 3Exhibit NWMI-004-RPrimary AssumptionsSingle radioisotope production facility RPFRPF includes target fabrication, 99Mo production, and uranium recycle and recovery99Mo produced by a fission-based method using LEUNominal capacity 3,500 6-day curies (Ci); surge capacity of 1,500 6-day CiUse network of university reactorsSame target design used for all reactors Intellectual property obtainedU.S., Australia, Russia, South Africa, Korea, Europe AllowedIndia, China PendingFission product releases will comply with environmental release criteriaGenerate Class A, B, and C wastes; no greater than Class C (GTCC) waste 4Exhibit NWMI-004-RSite Location and DescriptionSite located within Discovery Ridge Research Park 550 acreUniversity of Missouri (MU)-owned research park in Columbia Boone County, MissouriDiscovery Ridge located in central Missouri ~125miles east of Kansas City and ~125miles west of St.Louis4.5miles south of Interstate-70 andjust to north of USHighway633.5miles to southeast of main MU campus9.5miles west of Missouri RiverRPF will be located on Lot 15 7.4-acre No existing structuresUsed for agriculture for past centuryecosystem; two existing companies 5Exhibit NWMI-004-RLicensing ApproachLicense Request:NWMI has submitted a Construction Permit Application to obtain a license for a production facility under Title10,Code of Federal Regulations,Part50 (10CFRUsing guidance in NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Format and ContentProposed Action:Issuance of an NRC license under 10CFR50 that would authorize NWMI to construct and operate a 99Mo RPF at a site located in Columbia, MissouriRPF will:Receive irradiated low-enriched uranium (LEU) targets (from a network of university research or test reactors)Process irradiated LEU targets for dissolution, recovery, and purification of 99MoRecover and recycle LEU to minimize radioactive, mixed, and hazardous waste generationTreat/package wastes generated by RPF process steps to enable transport to a disposal siteProvide areas for associated laboratory and other support activities 6Exhibit NWMI-004-RAdditional RPF Licensing ActivitiesAdditional RPF operational activities are subject to other NRC regulations10CFRtransfer special nuclear materialReceiving LEU from U.S. Department of Energy (DOE)Producing LEU target materials and fabrication of targets10CFRprocess and transport 99Mo for medical applicationsHandling of byproduct materialUniversity reactor(s) and cask licensee(s) will amendtheir current operatinglicenses 7Exhibit NWMI-004-RProposed Schedule (Calendar Year)Start date of site preparation/construction Q22018End date of construction Q32019Start date of facility startup and cold commissioning (pre-operational) Q42019Date of hot commissioning and commercial operations Q1 2020Date of decommissioning: 2050 8Exhibit NWMI-004-RRPF Operating CharacteristicsLEU target material is fabricated (both fresh LEU and recycled U)LEU target material encapsulated using metal cladding LEU targetLEU targets are packaged and shipped to university reactors for irradiationAfter irradiation, targets are shipped back to RPFIrradiated LEU targets disassembledIrradiated LEU targets dissolved into a solution for processingDissolved LEU solution is processed to recover and purify 99MoPurified 99Mo is packaged/shipped to a radiopharmaceutical distributorLEU solution is treated to recover U and is recycled back to Step1Irradiate Targets in ReactorLEU Target Material ProductionEncapsulationIrradiated Target DisassemblyTarget DissolutionMo Recovery and PurificationUranium Recovery and RecycleMo Product PackagingFreshBlendedUraniumProduct Cask Shipments to CustomerUnirradiated Target Shipping to University ReactorsIrradiated Target Shipping and ReceivingPurified U SolutionImpure U SolutionPurified 99Mo SolutionTarget Cladding to Solid Waste HandlingDissolved TargetsFission Product Solution to Liquid Waste HandlingOffgas treatment and release to stack via Primary VentilationLegendReactor OperationsRPF OperationsTarget PackagingTarget Fabrication99Mo ProductionIrradiated Target Disassembly and Dissolution2013-021_010r4 9Exhibit NWMI-004-RRPF Operating Characteristics (continued)Ventilation SystemVentilation system will be divided into four zones (ZoneI, ZoneII, Zone III, and ZoneIV) with airflow directed from lowest to highest potential for contaminationZone I ventilation system will be initial confinement barrier (e.g., gloveboxes, tank hot cell, processing hot cells, and ZoneI exhaust subsystem)Biological ShieldProvides an integrated system of features that protects workers from high-dose radiation generated during facility operationsWill withstand seismic and other concurrent loads, while maintaining containment and shielding during a design basis eventPrimary function is to reduce radiation dose rates and accumulated doses in occupied areas to not exceed limits of 10CFR20 and RPF ALARA guidelines programEngineered Safety Features (ESF)Active or passive features designed to mitigate consequences of accidents and to keep radiological exposures to workers, the public, and environment within acceptable valuesConfinement is considered a general ESF 10Exhibit NWMI-004-RReagent, Product, and Waste Summary Flow Diagram 11Exhibit NWMI-004-RRPF DescriptionFirst level footprint ~52,000square feet (ft2)Target fabrication areaHot cell processing area (dissolution, 99Mo, and 235U recovery)Waste management, laboratory, and utility areasBasement ~2,000 ft2(tank hot cell, decay vault)Second level ~17,000 ft2(utility, ventilation, offgas equipment)Waste Management Building ~1,200 ft2Administration Building (outside secured RPF area) ~10,000 ft2High bay roof 65 ftMechanical area, second floor 46 ftTop of exhaust stack 75 ftLoading dock (back) roof 20 ftSupport and admin (front) roof 12 ftDepth below grade for hot cell/high-integrity container (HIC) storage 15 ft 12Exhibit NWMI-004-RRPF Consequences and Radionuclide Inventory SummaryPrimary consequences resulting from operation of RPF operations are radiologicalLEU target material production/fabricationIrradiated LEU target material processing (e.g., extract 99Mo and recycle and recover 235U)Radioactive waste materials processingRPF radionuclide inventory is based on a weekly throughputof irradiated targets MURR 8 targetsOSTR 30 targets Maximum radionuclide inventoryis based on accumulation in various systems dependent onprocess material decay times>100K Ci>50K Ci>10K Ci<10K CiLegend< 40 hr EOI> 40 hr EOI 13Exhibit NWMI-004-RTransportationFresh LEU ES-3100 package (Certificate of Compliance No.9315)Unirradiated targetsES-3100 or similar package Irradiated targetsBEA Research Reactor cask or similar (Certificate of Compliance No.9341)99Mo product Medical Isotope Depleted Uranium Shielded (MIDUS) TypeB(U) container (Certificate of Compliance USA/9320/B(U)-96) Radioactive waste High-dose radioactive waste High integrity casks (e.g., Model 10-160B cask)Low-dose radioactive waste 208liter (L) (55-gallon [gal]) waste drumsContact-handled waste Standard industrial waste drums or other appropriate [<2millisievert (mSv)/hr (200millirem [mrem]/hr) on contact and 0.1mSv/hr (10mrem/hr) at 1meter (m) (3.3ft)] | {{#Wiki_filter:1Exhibit NWMI-004-R1Northwest Medical Isotopes, LLC Radioisotope Production Facility OverviewJanuary 23, 2018U.S. Nuclear Regulatory CommissionCommission Mandatory Meeting 2Exhibit NWMI-004-RNWMI MissionFabricatedTargetsIrradiation services supplier99MosupplierTechnetium generator supplier99mTcsupplierIrradiatedtargetsCaptive Network of University Research ReactorsReliability/assurance of supplyMultiple shipments/weekRadioisotope Production Facility (RPF)Fabrication of LEU targets99Mo productionUranium recycle and recoveryDomestic 99Mo Generator DistributorsHold FDA Drug Master FileNo changes to generatorsNo changes to supply chain99MoTechnetium generators99mTcradiopharmaceuticalsAssure a Domestic, Secure, and Reliable Supply of Molybdenum-99 (99Mo) End User 3Exhibit NWMI-004-RPrimary AssumptionsSingle radioisotope production facility RPFRPF includes target fabrication, 99Mo production, and uranium recycle and recovery99Mo produced by a fission-based method using LEUNominal capacity 3,500 6-day curies (Ci); surge capacity of 1,500 6-day CiUse network of university reactorsSame target design used for all reactors Intellectual property obtainedU.S., Australia, Russia, South Africa, Korea, Europe AllowedIndia, China PendingFission product releases will comply with environmental release criteriaGenerate Class A, B, and C wastes; no greater than Class C (GTCC) waste 4Exhibit NWMI-004-RSite Location and DescriptionSite located within Discovery Ridge Research Park 550 acreUniversity of Missouri (MU)-owned research park in Columbia Boone County, MissouriDiscovery Ridge located in central Missouri ~125miles east of Kansas City and ~125miles west of St.Louis4.5miles south of Interstate-70 andjust to north of USHighway633.5miles to southeast of main MU campus9.5miles west of Missouri RiverRPF will be located on Lot 15 7.4-acre No existing structuresUsed for agriculture for past centuryecosystem; two existing companies 5Exhibit NWMI-004-RLicensing ApproachLicense Request:NWMI has submitted a Construction Permit Application to obtain a license for a production facility under Title10,Code of Federal Regulations,Part50 (10CFRUsing guidance in NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Format and ContentProposed Action:Issuance of an NRC license under 10CFR50 that would authorize NWMI to construct and operate a 99Mo RPF at a site located in Columbia, MissouriRPF will:Receive irradiated low-enriched uranium (LEU) targets (from a network of university research or test reactors)Process irradiated LEU targets for dissolution, recovery, and purification of 99MoRecover and recycle LEU to minimize radioactive, mixed, and hazardous waste generationTreat/package wastes generated by RPF process steps to enable transport to a disposal siteProvide areas for associated laboratory and other support activities 6Exhibit NWMI-004-RAdditional RPF Licensing ActivitiesAdditional RPF operational activities are subject to other NRC regulations10CFRtransfer special nuclear materialReceiving LEU from U.S. Department of Energy (DOE)Producing LEU target materials and fabrication of targets10CFRprocess and transport 99Mo for medical applicationsHandling of byproduct materialUniversity reactor(s) and cask licensee(s) will amendtheir current operatinglicenses 7Exhibit NWMI-004-RProposed Schedule (Calendar Year)Start date of site preparation/construction Q22018End date of construction Q32019Start date of facility startup and cold commissioning (pre-operational) Q42019Date of hot commissioning and commercial operations Q1 2020Date of decommissioning: 2050 8Exhibit NWMI-004-RRPF Operating CharacteristicsLEU target material is fabricated (both fresh LEU and recycled U)LEU target material encapsulated using metal cladding LEU targetLEU targets are packaged and shipped to university reactors for irradiationAfter irradiation, targets are shipped back to RPFIrradiated LEU targets disassembledIrradiated LEU targets dissolved into a solution for processingDissolved LEU solution is processed to recover and purify 99MoPurified 99Mo is packaged/shipped to a radiopharmaceutical distributorLEU solution is treated to recover U and is recycled back to Step1Irradiate Targets in ReactorLEU Target Material ProductionEncapsulationIrradiated Target DisassemblyTarget DissolutionMo Recovery and PurificationUranium Recovery and RecycleMo Product PackagingFreshBlendedUraniumProduct Cask Shipments to CustomerUnirradiated Target Shipping to University ReactorsIrradiated Target Shipping and ReceivingPurified U SolutionImpure U SolutionPurified 99Mo SolutionTarget Cladding to Solid Waste HandlingDissolved TargetsFission Product Solution to Liquid Waste HandlingOffgas treatment and release to stack via Primary VentilationLegendReactor OperationsRPF OperationsTarget PackagingTarget Fabrication99Mo ProductionIrradiated Target Disassembly and Dissolution2013-021_010r4 9Exhibit NWMI-004-RRPF Operating Characteristics (continued)Ventilation SystemVentilation system will be divided into four zones (ZoneI, ZoneII, Zone III, and ZoneIV) with airflow directed from lowest to highest potential for contaminationZone I ventilation system will be initial confinement barrier (e.g., gloveboxes, tank hot cell, processing hot cells, and ZoneI exhaust subsystem)Biological ShieldProvides an integrated system of features that protects workers from high-dose radiation generated during facility operationsWill withstand seismic and other concurrent loads, while maintaining containment and shielding during a design basis eventPrimary function is to reduce radiation dose rates and accumulated doses in occupied areas to not exceed limits of 10CFR20 and RPF ALARA guidelines programEngineered Safety Features (ESF)Active or passive features designed to mitigate consequences of accidents and to keep radiological exposures to workers, the public, and environment within acceptable valuesConfinement is considered a general ESF 10Exhibit NWMI-004-RReagent, Product, and Waste Summary Flow Diagram 11Exhibit NWMI-004-RRPF DescriptionFirst level footprint ~52,000square feet (ft2)Target fabrication areaHot cell processing area (dissolution, 99Mo, and 235U recovery)Waste management, laboratory, and utility areasBasement ~2,000 ft2(tank hot cell, decay vault)Second level ~17,000 ft2(utility, ventilation, offgas equipment)Waste Management Building ~1,200 ft2Administration Building (outside secured RPF area) ~10,000 ft2High bay roof 65 ftMechanical area, second floor 46 ftTop of exhaust stack 75 ftLoading dock (back) roof 20 ftSupport and admin (front) roof 12 ftDepth below grade for hot cell/high-integrity container (HIC) storage 15 ft 12Exhibit NWMI-004-RRPF Consequences and Radionuclide Inventory SummaryPrimary consequences resulting from operation of RPF operations are radiologicalLEU target material production/fabricationIrradiated LEU target material processing (e.g., extract 99Mo and recycle and recover 235U)Radioactive waste materials processingRPF radionuclide inventory is based on a weekly throughputof irradiated targets MURR 8 targetsOSTR 30 targets Maximum radionuclide inventoryis based on accumulation in various systems dependent onprocess material decay times>100K Ci>50K Ci>10K Ci<10K CiLegend< 40 hr EOI> 40 hr EOI 13Exhibit NWMI-004-RTransportationFresh LEU ES-3100 package (Certificate of Compliance No.9315)Unirradiated targetsES-3100 or similar package Irradiated targetsBEA Research Reactor cask or similar (Certificate of Compliance No.9341)99Mo product Medical Isotope Depleted Uranium Shielded (MIDUS) TypeB(U) container (Certificate of Compliance USA/9320/B(U)-96) Radioactive waste High-dose radioactive waste High integrity casks (e.g., Model 10-160B cask)Low-dose radioactive waste 208liter (L) (55-gallon [gal]) waste drumsContact-handled waste Standard industrial waste drums or other appropriate [<2millisievert (mSv)/hr (200millirem [mrem]/hr) on contact and 0.1mSv/hr (10mrem/hr) at 1meter (m) (3.3ft)] | ||
14Exhibit NWMI-004-RQuality Assurance Program PlanNWMI Quality Assurance Program Plan (QAPP) describes policies and requirements necessary to meet applicable Federal regulationsANSI/ANS 15.8, Quality Assurance Program Requirements for Research ReactorsRegulatory Guide2.5, Quality Assurance Program Requirements for Research and Test Reactors10CFR70.64(a)(1), Quality Standards and RecordsQAPP applies to all nuclear, quality-related projects and activities that require conformance to a nuclear quality assurance (QA) programNWMI RPF Organization 15Exhibit NWMI-004-RQuestions? | 14Exhibit NWMI-004-RQuality Assurance Program PlanNWMI Quality Assurance Program Plan (QAPP) describes policies and requirements necessary to meet applicable Federal regulationsANSI/ANS 15.8, Quality Assurance Program Requirements for Research ReactorsRegulatory Guide2.5, Quality Assurance Program Requirements for Research and Test Reactors10CFR70.64(a)(1), Quality Standards and RecordsQAPP applies to all nuclear, quality-related projects and activities that require conformance to a nuclear quality assurance (QA) programNWMI RPF Organization 15Exhibit NWMI-004-RQuestions?}} | ||
}} | |||
Revision as of 03:27, 18 May 2018
| ML18016A964 | |
| Person / Time | |
|---|---|
| Site: | Northwest Medical Isotopes |
| Issue date: | 01/23/2018 |
| From: | Northwest Medical Isotopes |
| To: | NRC/OGC |
| SECY RAS | |
| References | |
| 50-609-CP, Construction Permit Mndtry Hrg, RAS 54171 | |
| Download: ML18016A964 (15) | |
Text
1Exhibit NWMI-004-R1Northwest Medical Isotopes, LLC Radioisotope Production Facility OverviewJanuary 23, 2018U.S. Nuclear Regulatory CommissionCommission Mandatory Meeting 2Exhibit NWMI-004-RNWMI MissionFabricatedTargetsIrradiation services supplier99MosupplierTechnetium generator supplier99mTcsupplierIrradiatedtargetsCaptive Network of University Research ReactorsReliability/assurance of supplyMultiple shipments/weekRadioisotope Production Facility (RPF)Fabrication of LEU targets99Mo productionUranium recycle and recoveryDomestic 99Mo Generator DistributorsHold FDA Drug Master FileNo changes to generatorsNo changes to supply chain99MoTechnetium generators99mTcradiopharmaceuticalsAssure a Domestic, Secure, and Reliable Supply of Molybdenum-99 (99Mo) End User 3Exhibit NWMI-004-RPrimary AssumptionsSingle radioisotope production facility RPFRPF includes target fabrication, 99Mo production, and uranium recycle and recovery99Mo produced by a fission-based method using LEUNominal capacity 3,500 6-day curies (Ci); surge capacity of 1,500 6-day CiUse network of university reactorsSame target design used for all reactors Intellectual property obtainedU.S., Australia, Russia, South Africa, Korea, Europe AllowedIndia, China PendingFission product releases will comply with environmental release criteriaGenerate Class A, B, and C wastes; no greater than Class C (GTCC) waste 4Exhibit NWMI-004-RSite Location and DescriptionSite located within Discovery Ridge Research Park 550 acreUniversity of Missouri (MU)-owned research park in Columbia Boone County, MissouriDiscovery Ridge located in central Missouri ~125miles east of Kansas City and ~125miles west of St.Louis4.5miles south of Interstate-70 andjust to north of USHighway633.5miles to southeast of main MU campus9.5miles west of Missouri RiverRPF will be located on Lot 15 7.4-acre No existing structuresUsed for agriculture for past centuryecosystem; two existing companies 5Exhibit NWMI-004-RLicensing ApproachLicense Request:NWMI has submitted a Construction Permit Application to obtain a license for a production facility under Title10,Code of Federal Regulations,Part50 (10CFRUsing guidance in NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Format and ContentProposed Action:Issuance of an NRC license under 10CFR50 that would authorize NWMI to construct and operate a 99Mo RPF at a site located in Columbia, MissouriRPF will:Receive irradiated low-enriched uranium (LEU) targets (from a network of university research or test reactors)Process irradiated LEU targets for dissolution, recovery, and purification of 99MoRecover and recycle LEU to minimize radioactive, mixed, and hazardous waste generationTreat/package wastes generated by RPF process steps to enable transport to a disposal siteProvide areas for associated laboratory and other support activities 6Exhibit NWMI-004-RAdditional RPF Licensing ActivitiesAdditional RPF operational activities are subject to other NRC regulations10CFRtransfer special nuclear materialReceiving LEU from U.S. Department of Energy (DOE)Producing LEU target materials and fabrication of targets10CFRprocess and transport 99Mo for medical applicationsHandling of byproduct materialUniversity reactor(s) and cask licensee(s) will amendtheir current operatinglicenses 7Exhibit NWMI-004-RProposed Schedule (Calendar Year)Start date of site preparation/construction Q22018End date of construction Q32019Start date of facility startup and cold commissioning (pre-operational) Q42019Date of hot commissioning and commercial operations Q1 2020Date of decommissioning: 2050 8Exhibit NWMI-004-RRPF Operating CharacteristicsLEU target material is fabricated (both fresh LEU and recycled U)LEU target material encapsulated using metal cladding LEU targetLEU targets are packaged and shipped to university reactors for irradiationAfter irradiation, targets are shipped back to RPFIrradiated LEU targets disassembledIrradiated LEU targets dissolved into a solution for processingDissolved LEU solution is processed to recover and purify 99MoPurified 99Mo is packaged/shipped to a radiopharmaceutical distributorLEU solution is treated to recover U and is recycled back to Step1Irradiate Targets in ReactorLEU Target Material ProductionEncapsulationIrradiated Target DisassemblyTarget DissolutionMo Recovery and PurificationUranium Recovery and RecycleMo Product PackagingFreshBlendedUraniumProduct Cask Shipments to CustomerUnirradiated Target Shipping to University ReactorsIrradiated Target Shipping and ReceivingPurified U SolutionImpure U SolutionPurified 99Mo SolutionTarget Cladding to Solid Waste HandlingDissolved TargetsFission Product Solution to Liquid Waste HandlingOffgas treatment and release to stack via Primary VentilationLegendReactor OperationsRPF OperationsTarget PackagingTarget Fabrication99Mo ProductionIrradiated Target Disassembly and Dissolution2013-021_010r4 9Exhibit NWMI-004-RRPF Operating Characteristics (continued)Ventilation SystemVentilation system will be divided into four zones (ZoneI, ZoneII, Zone III, and ZoneIV) with airflow directed from lowest to highest potential for contaminationZone I ventilation system will be initial confinement barrier (e.g., gloveboxes, tank hot cell, processing hot cells, and ZoneI exhaust subsystem)Biological ShieldProvides an integrated system of features that protects workers from high-dose radiation generated during facility operationsWill withstand seismic and other concurrent loads, while maintaining containment and shielding during a design basis eventPrimary function is to reduce radiation dose rates and accumulated doses in occupied areas to not exceed limits of 10CFR20 and RPF ALARA guidelines programEngineered Safety Features (ESF)Active or passive features designed to mitigate consequences of accidents and to keep radiological exposures to workers, the public, and environment within acceptable valuesConfinement is considered a general ESF 10Exhibit NWMI-004-RReagent, Product, and Waste Summary Flow Diagram 11Exhibit NWMI-004-RRPF DescriptionFirst level footprint ~52,000square feet (ft2)Target fabrication areaHot cell processing area (dissolution, 99Mo, and 235U recovery)Waste management, laboratory, and utility areasBasement ~2,000 ft2(tank hot cell, decay vault)Second level ~17,000 ft2(utility, ventilation, offgas equipment)Waste Management Building ~1,200 ft2Administration Building (outside secured RPF area) ~10,000 ft2High bay roof 65 ftMechanical area, second floor 46 ftTop of exhaust stack 75 ftLoading dock (back) roof 20 ftSupport and admin (front) roof 12 ftDepth below grade for hot cell/high-integrity container (HIC) storage 15 ft 12Exhibit NWMI-004-RRPF Consequences and Radionuclide Inventory SummaryPrimary consequences resulting from operation of RPF operations are radiologicalLEU target material production/fabricationIrradiated LEU target material processing (e.g., extract 99Mo and recycle and recover 235U)Radioactive waste materials processingRPF radionuclide inventory is based on a weekly throughputof irradiated targets MURR 8 targetsOSTR 30 targets Maximum radionuclide inventoryis based on accumulation in various systems dependent onprocess material decay times>100K Ci>50K Ci>10K Ci<10K CiLegend< 40 hr EOI> 40 hr EOI 13Exhibit NWMI-004-RTransportationFresh LEU ES-3100 package (Certificate of Compliance No.9315)Unirradiated targetsES-3100 or similar package Irradiated targetsBEA Research Reactor cask or similar (Certificate of Compliance No.9341)99Mo product Medical Isotope Depleted Uranium Shielded (MIDUS) TypeB(U) container (Certificate of Compliance USA/9320/B(U)-96) Radioactive waste High-dose radioactive waste High integrity casks (e.g., Model 10-160B cask)Low-dose radioactive waste 208liter (L) (55-gallon [gal]) waste drumsContact-handled waste Standard industrial waste drums or other appropriate [<2millisievert (mSv)/hr (200millirem [mrem]/hr) on contact and 0.1mSv/hr (10mrem/hr) at 1meter (m) (3.3ft)]
14Exhibit NWMI-004-RQuality Assurance Program PlanNWMI Quality Assurance Program Plan (QAPP) describes policies and requirements necessary to meet applicable Federal regulationsANSI/ANS 15.8, Quality Assurance Program Requirements for Research ReactorsRegulatory Guide2.5, Quality Assurance Program Requirements for Research and Test Reactors10CFR70.64(a)(1), Quality Standards and RecordsQAPP applies to all nuclear, quality-related projects and activities that require conformance to a nuclear quality assurance (QA) programNWMI RPF Organization 15Exhibit NWMI-004-RQuestions?