ML15258A379
| ML15258A379 | |
| Person / Time | |
|---|---|
| Site: | SHINE Medical Technologies |
| Issue date: | 08/27/2015 |
| From: | Bynum R V Shine Medical Technologies |
| To: | Office of Nuclear Reactor Regulation |
| Lynch S | |
| References | |
| SHINE, SHINE.SUBMISSION.22, SHN.PSAR.P, SHN.PSAR.P.10 | |
| Download: ML15258A379 (128) | |
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Chapter 9 - Auxiliary SystemsTable of ContentsSHINE Medical Technologies9-iRev. 1CHAPTER 9AUXILIARY SYSTEMSTable of Contents SectionTitlePage9a1HETEROGENEOUS REACTOR AUXILIARY SYSTEMS.....................................9a1-19a2IRRADIATION FACILITY AUXILIARY SYSTEMS.................................................9a2-19a2.1HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS.......................9a2-1 9a2.1.1RADIOLOGICALLY CONTROLLED AREA VENTILATION SYSTEM...................9a2-19a2.1.2NON-RADIOLOGICAL AREA VENTILATION SYSTEM.......................................9a2-4 9a2.1.3FACILITY CHILLED WATER SUPPLY AND DISTRIBUTION SYSTEM...............9a2-59a2.1.4FACILITY HEATING WATER SYSTEM................................................................9a2-69a2.1.5TESTING REQUIREMENTS.................................................................................9a2-7 9a2.1.6MECHANICAL HVAC DESIGN CODES AND STANDARDS................................9a2-7 9a2.1.7TECHNICAL SPECIFICATIONS...........................................................................9a2-79a2.2HANDLING & STORAGE OF TARGET SOLUTION...........................................9a2-13 9a2.
2.1INTRODUCTION
.................................................................................................9a2-139a2.2.2TARGET SOLUTION PREPARATION................................................................9a2-13 9a2.2.3IRRADIATION FACILITY TARGET SOLUTION STORAGE AND HANDLING...............................................................................9a2-139a2.2.4IRRADIATION FACILITY TARGET SOLUTION HANDLING EQUIPMENT........9a2-14 9a2.2.5STORAGE OF SNM............................................................................................9a2-149a2.2.6CRITICALITY CONTROL....................................................................................9a2-159a2.2.7BIOLOGICAL SHIELDING..................................................................................9a2-159a2.3FIRE PROTECTION SYSTEMS AND PROGRAMS...........................................9a2-169a2.
3.1INTRODUCTION
.................................................................................................9a2-169a2.3.2DESIGN BASES..................................................................................................9a2-169a2.3.3FACILITY FIRE PROTECTION SYSTEM DESCRIPTION..................................9a2-18 9a2.3.4FIRE HAZARDS ANALYSIS................................................................................9a2-189a2.3.5TECHNICAL SPECIFICATIONS.........................................................................9a2-439a2.4COMMUNICATIONS SYSTEMS.........................................................................9a2-469a2.4.1ON-SITE COMMUNICATIONS...........................................................................9a2-469a2.4.2OFF-SITE COMMUNICATIONS..........................................................................9a2-469a2.4.3TECHNICAL SPECIFICATIONS.........................................................................9a2-47 Chapter 9 - Auxiliary SystemsTable of ContentsSHINE Medical Technologies9-iiRev. 0Table of Contents SectionTitlePage9a2.5POSSESSION & USE OF BYPRODUCT, SOURCE AND SPECIALNUCLEAR MATERIAL........................................................................................9a2-489a2.5.1BYPRODUCT MATERIAL...................................................................................9a2-489a2.5.2SOURCE MATERIAL..........................................................................................9a2-499a2.5.3SPECIAL NUCLEAR MATERIAL........................................................................9a2-499a2.5.4TECHNICAL SPECIFICATIONS.........................................................................9a2-499a2.6COVER GAS CONTROL IN CLOSED PRIMARY COOLANT SYSTEMS..........9a2-509a2.7OTHER AUXILIARY SYSTEMS..........................................................................9a2-519a2.7.1TRITIUM PURIFICATION SYSTEM....................................................................9a2-519a2.7.2OFF-NORMAL AND ACCIDENT SCENARIOS...................................................9a2-549a2.8IRRADIATION FACILITY AUXILIARY SYSTEMS TECHNICALSPECIFICATIONS...............................................................................................9a2-609a
2.9REFERENCES
....................................................................................................9a2-619bRADIOISOTOPE PRODUCTION FACILTY AUXILIARY SYSTEMS......................9b-19b.1HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS.........................9b-1 9b.2HANDLING & STORAGE OF TARGET SOLUTION...............................................9b-29b.2.1TARGET SOLUTION LIFECYCLE..........................................................................9b-29b.2.2DISSOLUTION OF URANIUM METAL....................................................................9b-29b.2.3TARGET SOLUTION PREPARATION....................................................................9b-3 9b.2.4SHIPMENT AND RECEIPT OF SNM......................................................................9b-39b.2.5TARGET SOLUTION PREPARATION HANDLING EQUIPMENT..........................9b-39b.2.6STORAGE OF SNM................................................................................................9b-5 9b.2.7CRITICALITY CONTROL........................................................................................9b-59b.3FIRE PROTECTION SYSTEMS AND PROGRAMS...............................................9b-6 9b.4COMMUNICATION SYSTEMS...............................................................................9b-79b.5POSSESSION AND USE OF BYPRODUCT, SOURCE AND SPECIALNUCLEAR MATERIAL............................................................................................9b-89b.5.1BYPRODUCT MATERIAL.......................................................................................9b-89b.5.2SOURCE MATERIAL............................................................................................9b-129b.5.3SPECIAL NUCLEAR MATERIAL (SNM)...............................................................9b-12 9b.5.4TECHNICAL SPECIFICATIONS...........................................................................9b-14 Chapter 9 - Auxiliary SystemsTable of ContentsSHINE Medical Technologies9-iiiRev. 1Table of Contents SectionTitlePage9b.6COVER GAS CONTROL IN CLOSED PRIMARY COOLANT SYSTEMS............9b-159b.6.1PROCESS VESSEL VENT SYSTEM....................................................................9b-159b.6.2NOBLE GAS REMOVAL SYSTEM.......................................................................9b-179b.7OTHER AUXILIARY SYSTEMS............................................................................9b-259b.7.1MOLYBDENUM ISOTOPE PRODUCTPACKAGING SYSTEM.........................................................................................9b-259b.7.2RCA MATERIAL HANDLING................................................................................9b-269b.7.3RADIOACTIVE LIQUID WASTE EVAPORATION AND IMMOBILIZATIONSYSTEM................................................................................................................9b-289b.7.4AQUEOUS RADIOACTIVE LIQUID WASTE STORAGE SYSTEM......................9b-32 9b.7.5SOLID RADIOACTIVE WASTE PACKAGING SYSTEM.......................................9b-349b.7.6RADIOACTIVE DRAIN SYSTEM..........................................................................9b-369b.7.7MATERIAL HANDLING.........................................................................................9b-38 9b.7.8FACILITY POTABLE WATER SYSTEM...............................................................9b-38 9b.7.9FACILITY INSTRUMENT AIR SYSTEM................................................................9b-389b.7.10FACILITY COMPRESSED AIR SYSTEM.............................................................9b-399b.7.11FACILITY BREATHING AIR SYSTEM..................................................................9b-39 9b.7.12FACILITY INERT GAS SYSTEM...........................................................................9b-399b.7.13FACILITY ROOF DRAINS SYSTEM.....................................................................9b-399b.7.14FACILITY SANITARY DRAINS SYSTEM.............................................................9b-39 9b.7.15FACILITY ACID REAGENT STORAGE AND DISTRIBUTION SYSTEM..............9b-409b.7.16FACILITY ALKALINE REAGENT STORAGE AND DISTRIBUTION SYSTEM.....................................................................................9b-409b.7.17FACILITY SALT REAGENT STORAGE AND DISTRIBUTION SYSTEM.............9b-409b.7.18FACILITY ORGANIC REAGENT STORAGE AND DISTRIBUTION SYSTEM.....................................................................................9b-409b.7.19ORGANIC LIQUID WASTE STORAGE AND EXPORT........................................9b-409b.7.20OFF-NORMAL AND ACCIDENT SCENARIOS.....................................................9b-409b.8RADIOISOTOPE PRODUCTION FACILITY AUXILIARYSYSTEMS TECHNICAL SPECIFICATIONS.........................................................9b-539b.9REFERENCES......................................................................................................9b-54 Chapter 9 - Auxiliary SystemsList of TablesSHINE Medical Technologies9-ivRev. 0List of Tables NumberTitle9a2.1-1HVAC Design Codes and Standards9a2.1-2HVAC Damper Design Codes and Standards9a2.1-3HVAC Ductwork Design Codes9a2.3-1SHINE Facility IBC and LSC Classifications 9a2.7-1TPS Interfaces9a2.7-2Tritium Supply/Return Properties9a2.7-3TPS Process Equipment 9a2.7-4TPS Preliminary Control System Interface9b.6-1PVVS Interfaces9b.6-2PVVS Process Equipment9b.6-3NGRS Interfaces9b.6-4NGRS Process Equipment 9b.7-1Master-Slave Manipulators9b.7-2RLWE System Interfaces9b.7-3RLWE Process Equipment 9b.7-4RLWS System Interfaces9b.7-5RLWS Process Equipment9b.7-6Solid Radioactive Waste Packaging System Equipment List 9b.7-7Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility9b.7-8RDS Interfaces9b.7-9RDS Process Equipment Chapter 9 - Auxiliary SystemsList of FiguresSHINE Medical Technologies9-vRev. 1List of Figures NumberTitle9a2.1-1RVZ1 Ventilation Flow Diagram9a2.1-2This figure number not used9a2.2-1Irradiation Facility Target Solution Storage and Handling Process Flow Diagram9a2.2-2Subcritical Assembly Cross-Section9a2.3-1Fire Area and Fire Zone Boundaries9a2.3-2Fire Protection Site Layout9a2.3-3Fire Protection Process Flow Diagram9a2.7-1TPS Process Flow Diagram9b.2-1TSPS Flow Diagram9b.2-2Uranium Oxide/Metal Storage Rack9b.6-1Process Vessel Vent Syst em (PVVS) Process Flow Diagram9b.6-2Noble Gas Removal System (NGRS) Process Flow Diagram9b.7-1Molybdenum Extraction, Purification, and Packaging GA 19b.7-2Molybdenum Extraction, Purification, and Packaging GA 2 9b.7-3RCA Overhead Crane Locations and Coverage9b.7-4RCA Hot Cell Locations9b.7-5RLWE Liquid Waste Evaporator and Storage System Process Flow Diagram9b.7-6RLWE Liquid Waste Immobilization System Process Flow Diagram9b.7-7Solid Radioactive Waste Handling Hot Cell Inputs and Outputs9b.7-8RDS Process Flow Diagram Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-viRev. 0Acronyms and Abbreviations Acronym/AbbreviationDefinitionACGIHAmerican Conference on Governmental Industrial HygienistsAGSAmerican Glovebox SocietyAHRIAir-Conditioning Heating and Refrigeration InstituteAHAacetohydroxamic acidAHUair handling unit AIHAAmerican Industrial Hygiene Association ALARAas low as is reasonable achievable AMCAAir Movement and Control Association ANSAmerican Nuclear Society ANSIAmerican National Standards Institute APIAmerican Petroleum Institute ASHRAEAmerican Society of Heating, Refrigerating, and Air-Conditioning Engineers, Inc.ASME American Society of Mechanical EngineersASTMAmerican Society for Testing and Materials atmatmosphere (unit of pressure)
BPVCBoiler and Pressure Vessel Code Btu/lbbritish thermal unit per pound CAAScriticality accident alarm system CAMScontinuous air monitoring system CASChemical Abstracts Service CFRCode of Federal Regulations Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-viiRev. 0 Acronyms and Abbreviations (cont'd)
Acronym/AbbreviationDefinitionCicuries (unit of measurement of radioactivity)CMAACrane Manufacturers Association of America Cscesium DOEU.S. Department of Energy DOTDepartment of Transportation DPTEdouble door for leaktight transfer ESFengineered safety feature ESFASengineered safety features actuation system FFahrenheit FAfire area FCHSfacility chilled water supply and distribution systemFDAU.S. Food and Drug AdministrationFFPSfacility fire detection and suppression system FHAfire hazards analysis FHWSfacility heating water system FICSfacility integrated control system FLRSfacility alkaline reagent storage and distribution systemFIGSfacility inert gas systemFMFactory Mutual FSARFinal Safety Analysis Report ft.feet FVZ4Facility Zone 4 ventilation system Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-viiiRev. 1 Acronyms and Abbreviations (cont'd)
Acronym/AbbreviationDefinitionggramg U/Lgram of uranium per liter GTCCgreater than Class C gpm gallons per minuteHCFDhot cell fire detection and suppression systemHEPAhigh efficiency particulate air HMIhuman machine interface hphorsepower HVACHeating, ventilation, and air conditioning IBCInternational Building Code IEEEInstitute of Electrical and Electronic Engineers IESNAIlluminating Engineering Society of North AmericaIFCInternational Fire CodeIGSinert gas control IMCInternational Mechanical Code ISAIntegrated Safety Analysis IUirradiation unit J/gjoules per gram Lliter lb U/galpound of uranium per gallon lbspounds LCOlimiting conditions for operation Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-ixRev. 0 Acronyms and Abbreviations (cont'd)
Acronym/AbbreviationDefinitionLEULow enriched uraniumLFLlower flammability limit LOOPloss of off-site power LSAlow specific activity LSCLife Safety CodeMmolarity (moles per liter)mmeter MEPSmolybdenum extraction and purification systemminminutesMIPSmolybdenum isotope product packaging systemMo-99molybdenum-99MPFLmaximum possible fire lossNDASneutron driver assembly system NECNational Electrical CodeNEMANational Electrical Manufacturers AssociationNFPANational Fire Protection Association NGRSnoble gas removal systemNPSSNormal Electrical Power Supply SystemNRCU.S. Nuclear Regulatory Commission OIToperator interface terminalsPACprocess automation controllerPFBSproduction facility biological shield system PFDprocess flow diagram Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-xRev. 0 Acronyms and Abbreviations (cont'd)
Acronym/AbbreviationDefinitionPLCprogrammable logic controllerPLC/PACprogrammable logic controller/process automation controllerPPEpersonal protective equipmentppmparts per millionPSARPreliminary Safety Analysis ReportPuplutonium PVVSprocess vessel vent systemRAMradiation area monitorRAMSradioactive area monitoring system RCAradiologically controlled areaRDSradioactive drain systemRICSradiological integrated control systemRMHSradioactive area material handling systemRLWEradioactive liquid waste evaporation and immobilization systemRLWSradioactive liquid waste storageRPCSradioisotope production facility cooling systemsRDSradioactive drain systemRMHSradioactive area material handling system RLWEradioactive liquid waste evaporation and immobilization systemRLWSradioactive liquid waste storageRPCSradioisotope production facility cooling systems Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-xiRev. 1Acronyms and Abbreviations (cont'd)
Acronym/AbbreviationDefinition RVRCA ventilation System RVZ1radiological controlled area ventilation system zone 1RVZ2radiological controlled area ventilation system zone 2RVZ3radiological controlled area ventilation system zone 3SCASsubcritical assembly systemsccmstandard cubic centimeter per minute SHINESHINE Medical Technologies, Inc.SMACNASheet Metal and Air Conditioning Contractors National Association SNMspecial nuclear material SRWPsolid radioactive waste packaging SSCstructures, systems and components Tctechnetium TCAPthermal cycling absorption process TDNthermal denitration TELCOtelephone company TOGStarget solution vessel off gas system TPCSTSV process control system TPStritium purification system TRPStarget solution vessel reactivity protection systemTSPStarget solution preparation system Chapter 9 - Auxiliary SystemsAcronyms and AbbreviationsSHINE Medical Technologies9-xiiRev. 0 Acronyms and Abbreviations (cont'd)
Acronym/AbbreviationDefinitionTSVtarget solution vesselU-233uranium-233 U-235uranium-235UHFultra high frequencyULUnderwriters LaboratoriesUNCS uranyl nitrate conversion systemUNPuranyl nitrate preparation (subsystem of UNCS)UOxuranium oxideUPSuninterruptible power supplyUPSSuninterruptible power supply systemUREXuranium extractionvol%volume percent WCBWisconsin Commercial Building CodeXLPE-FRcross-linked polyethylene Chapter9 -Auxiliary SystemsHeterogenous Reactor Auxiliary SystemsSHINE Medical Technologies9a1-1Rev. 0CHAPTER 9AUXILIARY SYSTEMS9a1HETEROGENOUS REACTOR AUXILIARY SYSTEMSThe SHINE Medical Technologies, Inc. (SHINE) facility is not a reactor-based facility; therefore, this section does not apply to the SHINE facility.
Chapter 9 - Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-1Rev. 19a2IRRADIATION FACILITY AUXILIARY SYSTEMS9a2.1HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS9a2.1.1RADIOLOGICALLY CONTROLLED AREA VENTILATION SYSTEM The RCA ventilation system (RV) includes supply air and exhaust subsystems required to condition the air and maintain radiological confinement in the RCA. The supply and exhaust air systems perform safety functions to protect workers and the public from releases of radiological materials and hazardous chemicals.A ventilation flow diagram is provided in Figure 9a2.1-1 (the legend for process flow diagrams is provided on Figure 1.3-6).RV consists of the following:*RCA Ventilation Zone 1 (RVZ1)RVZ1, the primary confinement zone, includes those areas where high levels of airborne contamination are anticipated during normal operations. RVZ1 areas draw ambient supply air from adjacent RVZ2 spaces. RVZ1 areas are maintained at negative pressure with respect to their surrounding RVZ2 spaces. RVZ1 area air inlets are equipped with automatic isolation dampers (fail closed), manual isolation dampers, and non-credited high efficiency particulate air (HEPA) filters. These HEPA filters are not assumed to be present in accident analyses, but are present to provide additional protection to workers and equipment.The exhaust air from each RVZ1 area filters through local HEPA filters. In addition to the automatic isolation dampers on the air inlet, each RVZ1 area exhaust outlet includes automatic isolation dampers to enable confinement of the RVZ1 area. These automatic dampers are safety-related and isolate the RVZ1 areas upon a signal from the Engineered Safety Features Actuation System (ESFAS) or the Radiological Integrated Control System (RICS), and reduce the exhaust of released airborne material.Negative space pressure in RVZ1 is controlled through modulation of local exhaust air flow control valves for each cell.
The RVZ1 exhaust system is equipped with redundant fans. During normal operation, one fan is operating while the other fan is on standby. If the operating fan fails, the standby fan will start automatically. The RVZ1 system exhaust fans draw air through the inlet filters, dampers, and piping, providing the pressure drop needed to maintain pressure negative within the RVZ1 area.The speed of the RVZ1 exhaust fans is controlled to maintain a negative pressure set point in the RVZ1 exhaust duct header. RVZ1 exhaust also receives treated output from the Noble Gas Removal System (NGRS) through the Process Vessel Vent System (PVVS). The exhaust from RVZ1 areas collects in the RVZ1 system duct header and then draws through final, testable, HEPA filters and carbon adsorbers prior to discharge into the exhaust stack.RVZ1 exhaust discharges to the nominally 56 inch diameter exhaust stack with a radiation monitoring system. The discharge point of the stack is approximately 10 feet above the roof line.
Chapter 9 - Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-2Rev. 2The RVZ1 exhaust heating, ventilation, and air conditioning (HVAC) control components operate through the Facility Integrated Control System (FICS) and are nonsafety-related, except for the isolation dampers noted above, and the automatic isolation dampers located in the RVZ1 exhaust ductwork downstream of the final filters. These isolation dampers are controlled by ESFAS and RICS, which are safety-related. The isolation dampers located in the RVZ1 exhaust ductwork downstream of the final filters perform a safety function and close when required to provide confinement at the RCA boundary.*RCA Ventilation Zone 2 (RVZ2)RVZ2, the secondary confinement zone, includes those areas where airborne contamination could be (but is not routinely) generated during normal operations, or as a result of a breach of an RVZ1 confinement area. RVZ2 areas are transient spaces prone to fluctuations in pressure because of changing airflows based on door movements and fume hood activity.RVZ2 areas are directly supplied air via the RCA supply air handling units (AHUs). The AHUs supply 100 percent outside air to the RVZ2 areas. Each AHU contains filters, pre-heat and cooling coils, and supply fans. The supply system includes three AHUs, each sized for 50 percent of total system capacity. If a single AHU fails, the standby AHU will start automatically. The AHUs normally supply a constant volume of conditioned air to RVZ2 and RVZ3 areas. In addition to the outside air supplied directly to RVZ2 areas, RVZ3 air is cascaded into RVZ2 areas through engineered airlock door leakage pathways by a negative pressure differential, maintaining the desired pressure drop between the zones. RVZ2 areas are maintained at negative pressure with respect to RVZ3 areas.Terminal unit components in the supply duct system include air flow control valves and reheat coils. The terminal reheat coils provide final tempering of supply air to maintain the RVZ2 temperature set point. RVZ2 supply airflow control valves operate in conjunction with exhaust valves to control the negative pressure differential in each zone by maintaining a fixed offset between the total supply and exhaust air flows for each RVZ2 areas.RCA supply air controls operate through the FICS and are nonsafety-related, except for the automatic isolation dampers (bubble-tight dampers) in the supply duct system at the RCA boundary. These dampers are operated by the safety-related RICS, and perform a safety function, closing when required to provide confinement at the RCA boundary.RVZ2 areas exhaust through general room exhausts and fume hood enclosures (where present). A portion of the air in RVZ2 areas is also transferred to RVZ1 areas through RVZ12 area air inlets, which contain automatic isolation dampers (fail closed), manual isolation dampers, and non-credited HEPA filters. As described above, the RVZ2 supply and exhaust systems will have airflow control valves, reacting to maintain the design differential pressure and ensuring the zone pressures are negative with respect to atmosphere and RVZ3. Flow control valves in fume hood exhaust ducts (where present) maintain a constant volume through each fume hood. The control valves automatically modulate to compensate for changes in pressure drop due to loading of local filters.
The RVZ2 exhaust system is equipped with redundant fans. During normal operation, one fan is operating while the other fan is on standby. If the operating fan fails, the standby fan will start automatically. Exhaust from RVZ2 areas collects in an RVZ2 exhaust header, and then draws through final, testable, HEPA filters and carbon adsorbers, prior to discharge into the exhaust stack. The RVZ2 exhaust fan speed is controlled to maintain the desired Chapter 9 - Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-3Rev. 2negative pressure in the RVZ2 exhaust header, and local automatic control valves adjust to maintain the negative pressure in the zone.Along with RVZ1, RVZ2 exhaust discharges to the nominally 56 inch diameter exhaust stack, which contains a stack monitoring system. The discharge point of the stack is approximately 10 feet above the roof line.The RVZ2 controls operate through the FICS and are nonsafety-related, except for the automatic isolation dampers in the supply duct at the RCA boundary and in the RVZ2 exhaust duct system located downstream of the final filters. These perform a safety function and close when required to provide confinement at the RCA boundary.*RCA Ventilation Zone 3 (RVZ3)RVZ3, the tertiary confinement zone, includes those areas where airborne contamination is not expected during normal facility operations.RVZ3 areas have airflow control valves on the supply side delivering air balanced to the design values. Forced air supplied to RVZ3 is then transferred to RVZ2 spaces through engineered airlock door leakage pathways. RVZ3 areas are maintained at an elevated pressure relative to RVZ2 areas, and a negative pressure relative to FVZ4 spaces. No RVZ3 exhaust system is anticipated, as the air from RVZ3 areas is transferred to RVZ2 areas.9a2.1.1.1Design BasesThe RV is designed to provide environmental conditions suitable for personnel and equipment. The functions of the system include conditioning the RCA environment for workers and equipment, and confinement of hazardous chemical fumes and airborne radiological materials. The ventilation system includes functions designated as nonsafety-related and safety-related. System safety functions are achieved through maintaining negative pressure gradients between confinement zones and to the outside atmosphere, air-exchange rates, exhaust stream air filtration, and isolation (closure) of ventilation duct systems at designated boundaries. The RV is designed such that the FICS monitors and controls the RCA ventilation system equipment, flow rates, pressures, and temperatures. Instrumentation monitors the ventilation systems for off-normal conditions and signal alarms as required. The FICS starts, shuts down, and operates the RV in normal operating modes, which prevent positive pressurization of contaminated areas and creates flow patterns that direct air toward areas of increasing contamination potential.The primary operational design functions of the RCA ventilation system are summarized below:*Provide ventilation air and condition the RCA environment for workers.*Provide makeup air and condition the RCA environment for process equipment.*Confine airborne radiological materials.*Limit the spread of airborne contamination.*Maintain dose uptake through ingestion to levels as low as reasonable achievable (ALARA) per 10 CFR 20 - Standards for Protection against Radiation.*Confine hazardous chemical fumes.
Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-4Rev. 09a2.1.1.2Safety Design FunctionsThe safety design functions of the RV are:*Provide confinement at irradiation unit cell, TOGS shielded cell, noble gas storage cell, and RPF hot cell boundaries.*Provide confinement at RCA boundary.9a2.1.2NON-RADIOLOGICAL AREA VENTILATION SYSTEMThe non-radiological area ventilation system is the facility ventilation Zone 4 (FVZ4) system, which consists of a supply air subsystem and an exhaust air subsystem.*FVZ4 Supply Air Subsystem The supply air subsystem provides conditioned air for workers and equipment in the non-RCA, make-up air for exhaust air systems, and outside air to maintain positive pressure with respect to the RCA. The supply AHU draws at least 10 percent of outside air to make up for air exhausted and exfiltrated. The outside air is mixed with the air recirculated from the room and conditioned through the AHU before being supplied to the non-RCA. Each AHU contains filters, pre-heat and cooling coils, and supply fans. The supply system includes two AHUs, each sized for 50 percent of total system capacity. The AHUs normally supply a constant volume of conditioned air to FVZ4 spaces. The supply air system HVAC controls operate through the FICS and are nonsafety-related.*FVZ4 Exhaust Air SubsystemThe exhaust subsystem serves the following locations of the non-RCA:-Change out lockers.-Chemical storage.-Men's and women's restrooms.-Uninterruptible power supply system battery rooms.
-Control room.The exhaust air subsystem controls operate through the FICS and are nonsafety-related.9a2.1.2.1Design BasesThe FVZ4 is designed to provide environmental conditions suitable for personnel and equipment, and to maintain positive pressure with respect to the RCA. The FVZ4 is designed such that the FICS monitors and controls the non-RCA ventilation system equipment, flow rates, pressures, and temperatures. Instrumentation monitors the ventilation systems for off-normal conditions and signal alarms as required.
Chapter 9 - Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-5Rev. 1The primary functions of the FVZ4 are summarized below:*Provide conditioned air for workers and equipment.*Provide outside makeup air for ventilation and pressurization.*Remove hazardous chemical fumes.*Maintain hydrogen concentration below 2 percent.9a2.1.2.2Safety Design FunctionsFVZ4 has no safety functions.9a2.1.3FACILITY CHILLED WATER SUPPLY AND DISTRIBUTION SYSTEMThe facility chilled water supply and distribution system (FCHS) provides chilled water to the RCA and non-RCA of the SHINE facility. The FCHS provides chilled water to the cooling coils of the RCA supply AHUs, and to the process cooling heat exchangers of the radioisotope production facility cooling system (RPCS). See Chapter 5 for more information on the RPCS. Also, FCHS provides chilled water to the cooling coils of the FVZ4 AHUs. The primary components of the FCHS include: *Air-cooled condensers.*Chiller evaporators.*Chilled water pumps, associated piping and valves, and makeup water and water treatment equipment.*Expansion tank.The FCHS is a closed loop system serving the RV and FVZ4 cooling coils that are located outside the RCA boundary. The FCHS also supplies water to the heat exchanger in the RPCS, located inside the RCA. The water-to-water heat exchanger provides separation between the RCA and non-RCA chilled water systems to limit the potential for cross-contamination. Isolation valves on the chilled water supply and return lines to each cooling coil and heat exchanger allow isolation from the water loop for maintenance. If supplemental ventilation system cooling is required in the RCA, the RPCS serves HVAC cooling coils within the RCA.The FICS monitors and controls the FCHS equipment status, flow rates, pressures, and temperatures. Instrumentation monitors the system for off-normal conditions and signal alarms as required. The FICS starts, shuts down, and operates the FCHS. Chiller controls are nonsafety-related.Temperature control valves in the chilled water coil piping for each RCA supply AHU are controlled by a supply air temperature controller with input from a temperature element (sensor) located in the discharge ductwork of each supply AHU. The control valve regulates the chilled water flow to the cooling coil to maintain the setpoint for the supply air discharge temperature.
Chapter 9 - Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-6Rev. 19a2.1.3.1Design BasisThe FCHS is designed such that the FICS can monitor and control the equipment, flow rates, pressures, and temperatures. Instrumentation monitors the ventilation systems for abnormal conditions and signal alarms as required.The primary functions of the FCHS are as follows:*Remove the heat and condition the air passing through the cooling coils of the RCA supply AHUs. Circulate chilled water through the cooling coils of RCA supply AHUs utilizing water as the working fluid.*Remove heat from the RPCS. Circulate chilled water through the RPCS heat exchanger using water as the working fluid.*Remove heat and condition the air passing through the cooling coils of the FVZ4 AHUs. Circulate chilled water through the cooling coils of the FVZ4 AHUs utilizing water as the working fluid.*Maintain FCHS water quality.9a2.1.3.2Safety Design FunctionsThere are no safety functions identified for the FCHS.9a2.1.4FACILITY HEATING WATER SYSTEMThe facility heating water system (FHWS) provides heating water to the RCA and non-RCA of the SHINE facility. The FHWS provides heating water to the preheat and reheat coils in the RVZ2 and FVZ4 supply systems.The primary components of the FHWS include:*Gas boiler.*Pump, associated piping and valves, and makeup water and water treatment equipment.*Expansion tank.The FHWS is designed as a closed loop system where the water is heated by the gas boiler and circulated by the pump to the preheat and reheat coils of the RVZ2 and FVZ4 supply systems where it exchanges heat with the air before returning back to the boiler. Isolation valves on the hot water supply and return lines to each heating coil and heat exchanger allow isolation from the water loop for maintenance. The FICS monitors and controls the FHWS equipment status, flow rates, pressures, and temperatures. Instrumentation monitors the system for off-normal conditions and signal alarms as required. The FICS starts, shuts down, and operates the FHWS.
Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-7Rev. 0Temperature control valves in the preheat coil piping for each AHU are controlled by a supply air temperature controller with input from a temper ature element (sensor) located in the discharge ductwork of each AHU. The control valve regulates the heating water flow to the preheat coil to maintain the setpoint for the supply air discharge temperature. Area thermostats control the reheat coil discharge temperature. Controls are nonsafety-related.9a2.1.4.1Design Basis The design basis for the FHWS is:*Respond to heating loads during winter in order to satisfy supply air temperaturerequirements leaving the preheat and reheat coils for the RV and FVZ4.*Circulate water heated by the gas boiler, then distribute to the preheat and reheat coils by the circulating pump.9a2.1.4.2Safety Functions There are no safety functions identified for the FHWS.9a2.1.5TESTING REQUIREMENTSThe design of the HVAC system permits routine testing and inspection without disruption to normal operation. Testing will be performed on an appr opriate basis to detect and correct any problems or degradation of the components.9a2.1.6MECHANICAL HVAC DESIGN CODES AND STANDARDS Tables 9a2.1-1, 9a2.1-2, and 9a2.1-3 provide a list of the primary mechanical HVAC design codes, standards, and references. These are to be used as guidance do cuments for designing the RV, FVZ4, FCHS, and FHWS components.9a2.1.7TECHNICAL SPECIFICATIONS Potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the heating, ventilation, and air conditioning systems are provided in Chapter 14.
Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-8Rev. 0Table 9a2.1-1 HVAC Design Codes and Standards(Sheet 1 of 3)Document No.Title/DescriptionVersionAir-Conditioning, Heating, and Refrigeration Institute (AHRI), Standard 410Forced-Circulation Air-Cooling and Air-Heating Coils2001Air Movement and Control Association (AMCA),
Publication 201Fans and Systems2002AMCA, Publication 203Field Performance Measurement of Fan Systems2011AMCA, Publication 99Standards Handbook2010 American Conference on Governmental Industrial Hygienists (ACGIH)Industrial Ventilation: A Manual of Recommended Practice2004American National Standards Institute (ANSI) Z21.13 ANSI Gas Fired Low Pressure Steam & Hot Water Boilers2010ANSI/AHRI Standard 430Performanc e Rating of Central Station Air Handling Units2009ANSI/AHRI Standard 365Performance Rating of Commercial and Industrial Unitary Air-Conditioning Condensing Units 2009ANSI/AHRI Standard 551/591Performance Rating of Water-Chilling and Heat Pump Water Heating Packages Using the Vapor Compression Cycle 2011ANSI/AHRI Standard 850Performance Rating of Commercial and Industrial Air Filter Equipment 2004ANSI/American Industrial Hygiene Association (AIHA)
Z9.5Laboratory Ventilation2003ANSI/AMCA 204-05Balance Quality and Vibration Levels for Fans2012ANSI/AMCA 210-07Laboratory Methods of Testing Fans for Certified Aerodynamic Performance Rating 2007AMCA 301-06Methods for Calculating Fan Sound Ratings from Laboratory Test Data 2006ANSI/AMCA Standard 500-D-12Laboratory Methods of Testing Dampers for Rating2012 ANSI/AMCA Standard 500-HL-12Laboratory Methods of Testing Louvers for Rating2012 ANSI/AMCA Standard 510-09Methods of Testing Heavy Duty Dampers for Rating2009 Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-9Rev. 0Table 9a2.1-1 HVAC Design Codes and Standards(Sheet 2 of 3)Document No.Title/DescriptionVersionANSI/American Society of Heating, Refrigerating, and Air-Conditioning
Engineers, Inc. (ASHRAE) Standard 15Safety Standard for Refrigeration Systems2010ANSI/ASHRAE Standard 34Designation and Safety Classification of Refrigerants2010ANSI/ASHRAE Standard 52.2Method of Testing General Ventilation Air-Cleaning Devices for Removal Efficiency by Particle Size2007ANSI/ASHRAE Standard 55Thermal Environmental Conditions for Human Occupancy2010ANSI/ASHRAE Standard 62.1Ventilation for Acceptable Indoor Air Quality2010 ANSI/ASHRAE/IlluminatingEngineering Society of North
America (IESNA), Standard 90.1Energy Standard for Buildings Except Low-Rise Residential Buildings, I-P Edition (ANSI Approved; IESNA Co-sponsored)2010ANSI N13.1Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts
of Nuclear Facilities1999ANSI/American Society of Mechanical Engineers (ASME)
N509-2002 Nuclear Power Plant Air-Cleaning Units and Components2008ANSI/ASME N510Testing of Nuclear Air Treatment Systems2007ASHRAE Standard 111Measurement, Testing, Adjusting, and Balancing of Building HVAC Systems2008ASME AG-1, including Addenda 1a & 1bCode on Nuclear Air and Gas Treatment2009, Addenda 1a, Addenda 1-b-2011ASME B31.5Refrigeration Piping and Heat Transfer Components2010ASME N511In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems2007IMCInternational Mechanical Code2009National Electrical Manufacturers Association (NEMA) MG-1Motors and Generators2011NFPA 90AStandard for the Installation of Air Conditioning and Ventilating Systems 2012NFPA 45Standard on Fire Protection for Laboratories Using Chemicals 2011NFPA 70National Electrical Code2011NFPA 72National Fire Alarm and Signaling Code2013 Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-10Rev. 0Table 9a2.1-1 HVAC Design Codes and Standards(Sheet 3 of 3)Document No.Title/DescriptionVersionNFPA 801Facilities Handling Radioactive Materials2008NFPA 90BStandard for Installation of Warm Air Heating and Air Conditioning Systems 2012NFPA 92AStandard for Smoke-Control Systems Utilizing Barriers and Pressure Differences 2009SMACNASeismic Restraint Manual: Guideline for Mechanical Systems, 3 rd ed.2008SMACNA 1143HVAC Air Duct Leakage Test Manual2012SMACNA 1520Round Industrial Duct Construction Standards1999 SMACNA 1922Rectangular Industrial Duct Construction Standards2009 SMACNA 1966HVAC Duct Construction Standards - Metal and Flexible2005 UL 900Standard for Air Filter Units - Seventh Edition2012 UL 1995Heating and Cooling equipment - Fourth Edition2011 UL 555Standard for Fire Dampers - Seventh Edition2012 UL 555SStandard for Smoke Dampers - Fourth Edition2009
Wisconsin Administrative CodeChapter SPS 345 Mechanical RefrigerationN/A Wisconsin Administrative CodeChapter SPS 363 Energy ConservationN/A Wisconsin Administrative CodeChapter SPS 364 Heating, Ventilating and Air Conditioning N/A Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-11Rev. 1Table 9a2.1-2 HVAC Damper Design Codes and StandardsComponentCodes and Standards Safety-Related DampersCode on Nuclear Air and Gas Treatment ASME AG-1, including 2009 Addenda 1a and 1b (2011), Section DA, Dampers and Louvers.Nonsafety-Related DampersSMACNA 1966 (Version 2005), HVAC Duct Construction Standards, Metal and Flexible (Use for Low Pressure Duct
Sections).SMACNA 1520 (Version 1999), Round Industrial Duct Construction Standards (Use for High Pressure Duct Sections).SMACNA 1922 (Version 2009), Rectangular Industrial Duct Construction Standards (Use for High Pressure Duct Sections).
AMCA 500-D-12 (Version 2012), Laboratory Methods for Testing Dampers for Rating.
Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9a2-12Rev. 0 Table 9a2.1-3 HVAC Ductwork Design CodesComponentCodes and Standards Exhaust DuctworkCode on Nuclear Air and Gas Treatment ASME AG-1, 2009, Addenda 1a, Addenda 1-b-2011, Section SA, Ductwork. SMACNA 1520 (Version 1999), Round Industrial Duct Construction Standards (Use for High Pressure Duct
Sections).SMACNA 1922 (Version 2009), Rectangular Industrial Duct Construction Standards (Use for High Pressure Duct
Sections).SMACNA 1143 (Version 2012), HVAC Air Duct Leakage Test Standard. NFPA 45 (Version 2011), Standard on Fire Protection for Laboratories Using Chemicals. NFPA 90A (Version 2012), Standard for the Installation of Air Conditioning and Ventilating Systems. NFPA 801 (Version 2008), Facilities Handling Radioactive Materials.AIHA Z9.5 (Version 2003), Laboratory Ventilation.
ACGIH Industrial Ventilation: A Manual of Recommended Practice (Version 2004).Supply DuctworkSMACNA 1520 (Version 1999), Round Industrial Duct Construction Standards (Use for High Pressure Duct
Sections).SMACNA 1922 (Version 2009), Rectangular Industrial Duct Construction Standards (Use for High Pressure Duct
Sections).SMACNA 1143 (Version 2012), HVAC Air Duct Leakage Test Standard. NFPA 45 (Version 2011), Standard on Fire Protection for Laboratories Using Chemicals. NFPA 90A (Version 2012), Standard for the Installation of Air Conditioning and Ventilating Systems. NFPA 801 (Version 2008), Facilities Handling Radioactive Materials.AIHA Z9.5 (Version 2003), Laboratory Ventilation.
ACGIH Industrial Ventilation: A Manual of Recommended Practice (Version 2004).
Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9a2-13Rev. 09a2.2HANDLING & STORAGE OF TARGET SOLUTION9a2.
2.1INTRODUCTION
This section describes the handling and storage of special nuclear material (SNM) and byproducts within the target solution within the irradiation facility (IF), which is shown in Figure 9a2.2-1. The preparation of the target solution is located outside of the IU cell. The piping used for transfer of the target solution to the IU cell includes penetrations of the cell through redundant sets of isolation valves.Detailed descriptions of the processing and storage of irradiated and unirradiated SNM and byproducts in the RPF are found in Subsections 4b.4.1 and 4b.4.2. Equipment and design features involved in the SNM lifecycle are included in these subsections.The physical protection of uranium against theft or diversion will be described in the facility physical security plan. The facility physical security plan will be provided with the FSAR.9a2.2.2TARGET SOLUTION PREPARATION Target solution is derived from 19.75 +/- 0.2 percent low enriched uranium (LEU) and is prepared in the target solution preparation system (TSPS) by dissolving uranium oxide in sulfuric acid. See Section 9b.2 for a detailed discussion of target solution preparation process steps.Target solution must meet the chemical propert y requirements discussed in Subsection 4a2.2.1 before it is transferred from the target solution hold tank (1-TSPS-03T) to the TSV. If the target
solution is not within the required chemical specifications, operators make appropriate adjustments while the target solution is being prepared in the TSPS.The storage and process tanks in the TSPS use double-contingency, criticality-safe controls. 9a2.2.3IRRADIATION FACILITY TARGET SOLUTION STORAGE AND HANDLING After target solution has been prepared in the uranyl sulfate preparation tank (1-TSPS-01T), it is pumped to the target solution hold tank (1-TSPS-03T) to await being loaded into the TSV. The reagent addition portion of the pr eparation tank is located within a glovebox. The hold tank is located within a tank vault. Target solution is pumped from the target solution hold tank (1-TSPS-03T) to the TSV. If a recycled (previously irradiated) target solution batch is used, the recycled target solution is pumped from the recycle target solution tank (1-UNCS-09T) to the target solution hold tank (1-TSPS-03T) instead of using unirradiated target solution prepared in the TSPS.See Figure 9a2.2-2 for a cross-section of the TSV and subcritical assembly.After irradiation in the TSV, the target solution is gravity-transferred to the TSV dump tank (1-SCAS-01T) where it is held for decay prior to being pumped to the molybdenum extraction and purification system (MEPS) and then on to the uranyl nitrate conversion system (UNCS) for further processing. SNMand byproducts in the ta rget solution remain in solution until they are separated downstream in the MEPS and UNCS processes. Fissile material in these systems is held in double-contingency, criticality-safe design equipment.
Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9a2-14Rev. 0[Security-Related Information - Withhold Under 10 CFR 2.390][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]See Section 9b.2 for a detailed discussion of storage and handling for SNM outside of the IF.9a2.2.4IRRADIATION FACILITY TARGET SOLUTION HANDLING EQUIPMENTThe following is a list of equipment necessary for loading/unloading the TSV with target solution. The equipment listed is either included in the IU cell or directly feeds/receives target solution from the TSV. See Figure 9a2.2-1 for the flow diagram that shows the irradiation facility target
solution handling equipment.*Target Solution Hold Tank (1-TSPS-03T-A-H)-Quantity: 8-Nominal Size: [Proprietary Information][Security-Related Information]-Normal Operating Pressure: atmospheric (vented)
-Double-Contingency, Criticality-Safe Design-Design/Fabrication Code: ASME BPVC Section VIII Div 1 (ASME, 2012)-Location: Outside of IU cell*Target Solution Feed Pump (1-TSPS-03P-A-H)-Quantity: 8
-Nominal Power: 0.25 horsepower (hp)
-Design/Fabrication Code: ANSI/HI 3.1-3.5 (ANSI/HI, 2008)-Location: Outside of IU cell*Target Solution Vessel (1-SCAS-01S-A-H)-Quantity: 8-See Subsection 4a2.2 for a detailed description of the TSV
-Location: Inside IU cell*TSV Dump Tank (1-SCAS-01T-A-H)-Quantity: 8-Nominal Size: [Proprietary Information][Security-Related Information]-Normal Operating Pressure: atmospheric
-Double-Contingency, Criticality-Safe Design-Design/Fabrication Code: ASME BPVC Section VIII Div 1 (ASME, 2012)-Location: Inside IU cell*Irradiated Target Solution Pump (1-SCAS-01P-A-H)-Quantity: 8
-Type: Positive Displacement-Nominal Power: 0.25 hp-Design/Fabrication Code: ANSI/HI 3.1-3.5 (ANSI/HI, 2008)9a2.2.5STORAGE OF SNMStorage of SNM and byproducts in the IF is done in the double-contingency, criticality-safe process/storage tanks. SNM is not otherwise stored in the IF. The IF-related process/storage tanks provide the necessary storage and handling for this area of the facility.
Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9a2-15Rev. 09a2.2.6CRITICALITY CONTROL Processing of unirradiated and irradiated SNM and byproducts prevents inadvertent criticality through double-contingency, criticality-safe tanks and other components that handle or store the fissile SNM and byproducts in all conditions. The Nuclear Criticality Safety Program is discussed in 6b.3.9a2.2.7BIOLOGICAL SHIELDINGBiological shields are included around the IF-related equipment discussed in this section. The IU cell which houses the neutron driver assembly system (NDAS), light water pool, TSV, and TSV dump tank includes biological shielding. The target solution hold tank is located in a shielded tank vault outside of the IU cell. See Section 4a2.5 for information on the IF biological shield and Section 4b.2 for RPF biological shielding.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-16Rev. 19a2.3FIRE PROTECTION SYSTEMS AND PROGRAMS9a2.
3.1INTRODUCTION
The fire protection system at the SHINE site is designed to protect the SHINE facility from damage by fire and to provide means to safely shut down the IUs in case of a fire. The fire
protection system detects and suppresses fires, and is an integral part of the fire protection program.The sections that follow include the fire protection system design basis and the associated fire hazards analysis for the SHINE facility. The procedures for operation, testing, and surveillance of the fire protection systems, including relationships between fire protection plans, operating procedures, and the emergency plan will be developed and maintained under the fire protection program.9a2.3.2DESIGN BASESThe fire protection program will comply with American National Standards Institute (ANSI)/American Nuclear Society (ANS) Standard for Fire Protection Program Criteria for Research Reactors (ANSI/ANS, 1981). The fire protection system at the SHINE site meets the design criteria of National Fire Protection Association (NFPA) Standard for Standard for Fire
Protection for Facilities Handling Radioactive Materials (NFPA, 2008c). Other nationally-recognized codes and standards, listed at the bottom of this subsection, are also used in the design of the fire protection system as applicable in order to achieve reasonable assurance of fire safety. The facility fire protection system (FFPS) is designed to: *Prevent fire initiation by controlling, separating, and limiting the quantities of combustibles and sources of ignition.*Isolate combustible materials and limit the spread of fire by subdividing the SHINE facility into fire areas separated by fire barriers.*Separate redundant safe shutdown components and associated electrical divisions to preserve the capability to safely shut down the IUs following a fire.*Separate redundant trains of safety-related equipment used to mitigate the consequences of a design basis accident (but not required for safe shutdown following a fire) so that a fire within one train will not damage the redundant train.*Provide confidence that failure or inadvertent operation of the fire protection system cannot prevent SHINE facility safety functions from being performed.*Preclude the loss of structural support, due to warping or distortion of SHINE facility structural members caused by the heat from a fire, to the extent that such a failure could adversely affect safe shutdown capabilities.*Provide firefighting personnel access and life safety escape routes for each fire area.*Minimize exposure to personnel and releases to the environment of radioactivity or hazardous chemicals as a result of a fire.*The fire protection system is classified as a nonsafety-related, non-seismic system. The fire protection system is not required to remain functional following an accident or the most severe natural phenomena.*Maintain fire pump design capacity with two 100 percent capacity fire pumps.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-17Rev. 0The fire protection system is designed to perform the following functions:*Detect and locate fires and provide operator indication of their location.*Provide the capability to extinguish fires in any SHINE facility area, to protect SHINE facility personnel and limit fire damage.*Supply fire suppression water at a flow rate and pressure sufficient to satisfy the demand of any automatic sprinkler system plus 500 gallons per minute (gpm) for fire hoses, for a
minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.In addition to NFPA 801 (NFPA, 2008c), the design, testing, and surveillance of the fire protection system is based on guidance from the following codes and standards:*International Fire Code (IFC) (IFC, 2009).*International Building Code (IBC) (IBC, 2009) as amended by Wisconsin Commercial Building Code (WCB), SPS 360-366 (WCB, 2011).*Institute of Electrical and Electronic Engineers (IEEE) 1202, Standard for Flame-Propagation Testing of Wire and Cable (IEEE, 2006).*NFPA 10, Standard for Portable Fire Extinguishers (NFPA, 2010a).*NFPA 13, Standard for the Installation of Sprinkler Systems (NFPA, 2013a).
- NFPA 14, Standard for the Installation of Standpipe and Hose Systems (NFPA, 2010b).
- NFPA 15, Standard for Water Spray Fixed Systems for Fire Protection (NFPA, 2012a).*NFPA 20, Standard for the Installation of Stationary Pumps for Fire Protection (NFPA,2013b).*NFPA 22, Standard for Water Tanks for Private Fire Protection (NFPA, 2008a).*NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances (NFPA, 2013c).*NFPA 25, Standard for the Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems (NFPA, 2011a).*NFPA 30, Flammable and Combustible Liquids Code (NFPA, 2012b).
- NFPA 45, Standard on Fire Protection for Laboratories Using Chemicals (NFPA, 2011b).*NFPA 55, Compressed Gases and Cryogenic Fluids Code (NFPA, 2013d).*NFPA 70, National Electrical Code (NFPA, 2011c).
- NFPA 72, National Fire Alarm and Signaling Code (NFPA, 2013e).*NFPA 80, Standard for Fire Doors and Other Opening Protectives (NFPA, 2013f).*NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating System (NFPA,2012c).*NFPA 101, Life Safety Code (NFPA, 2012d).*NFPA 220, Standard on Types of Building Construction (NFPA, 2012e).
- NFPA 255, Standard Method of Test of Surface Burning Characteristics of Building Materials (NFPA, 2006).*NFPA 430, Code for the Storage of Liquid and Solid Oxidizers (NFPA, 2004).
- NFPA 484, Standard for Combustible Metals (NFPA, 2012g).*NFPA 780, Standard for the Installation of Lightning Protection Systems (NFPA, 2011d).*NFPA 2001, Standard on Clean Agent Fire Extinguishing Systems (NFPA, 2012h).
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-18Rev. 09a2.3.3FACILITY FIRE PROTECTION SYSTEM DESCRIPTIONThe SHINE facility is subdivided into fire areas that are separated by fire barriers to isolate combustible materials and limit the spread of fire. The fire area boundaries are shown in Figure
9a2.3-1. In each fire area the fire protection system detects fires and provides the capability to extinguish them using fixed automatic and man ual suppression systems, manual hose streams, and/or portable firefighting equipment. The FFPS consists of the following: *Detection systems for early detection and notification of a fire.*Fixed automatic fire suppression systems.*Manual fire suppression systems and equipment, including hydrants, standpipes, hose stations, and portable fire extinguishers.*A fire water supply system including the fire pumps, yard main, and interior distribution piping.*The descriptions and characteristics of the fire detection and suppression systems in each of the fire areas of the SHINE fa cility are provided in Subsection 9a2.3.4. The components of the fire water supply system are shown in Figure 9a2.3-2, Fire Protection Site Layout, and Figure 9a2.3-3, Fire Protection Process Flow Diagram. Fire water is supplied from two separate fresh water storage tanks. There are two 100 percent capacity fire pumps. The lead pump is electric motor-driven and the secondary pump is diesel engine-driven. The fire water tanks are permanently connected to the fire pumps' suction piping and are arranged so that the pumps can take suction from either or both tanks. Piping between the fire water sources and the fire pumps is in accordance with NFPA 20 (NFPA, 2013b), Standard for the Installation of Stationary Pumps for Fire Protection. A failure in one tank or its piping cannot cause both tanks to drain. Sprinkler and standpipe systems are supplied by connections from the yard main.
Manual valves for sectionalized control of the yard main or for shutoff of the water supply to suppression systems are administratively controlled. Hydrants are provided on the yard main in accordance with NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances (NFPA, 2013c), with at least two hydrants provided within 300 feet (91 meters) of the SHINE facility. The lateral to each hydrant is controlled by an isolation valve.9a2.3.4FIRE HAZARDS ANALYSISThe fire hazards analysis (FHA) contained in this subsection evaluates the potential for occurrence of fires within the SHINE facility, documents the capabilities of the fire protection system, and provides reasonable assurance of the capability to safely shut down the IUs. The FHA is used to assess each fire area (FA) separately to ensure the fire protection program objectives are met.9a2.3.4.1Objective The objective of the FHA is to ensure that fire protection requirements established in NUREG-1537 have been applied to the SHINE facility and are sufficient in:*Preventing fires, including limiting combustible materials.*Detecting, controlling, and extinguis hing fires to limit consequences.*Protecting systems required for safe shutdown of the IUs or to prevent an uncontrolled release of radioactive material.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-19Rev. 0The FHA considers potential in situ and transient fire hazards to accomplish the following objectives:*Determine the effects of a fire in any location in the SHINE facility on the ability to safely shut down the IUs or to minimize and control the release of radioactivity to the environment, *Specify measures for fire prevention, fire detection, fire suppression, and fire containment for each fire area containing structures, systems and components (SSC) important to safety in accordance with U.S. Nuclear Regulatory Commission (NRC) guidelines and regulations identified in NUREG-1537.*Document known deviations and associated approved evaluations, waivers and equivalences.9a2.3.4.2ScopeThe scope of the FHA consists of the comprehensive assessment of the fire or explosion hazards for the SHINE facility, including a description of the fire protection defense-in-depth features provided to minimize the consequences of such an event.9a2.3.4.3Methodology and Acceptance Criteria9a2.3.4.3.1DefinitionsAuthority Having Jurisdiction: The organization, office, or individual responsible for approving equipment materials, an installation, or a procedure (NRC or local Fire Marshal).
Defense-in-Depth: Fire protection for radiological handling facilities uses the concept of defense-in-depth to achieve the required degree of fire and criticality-safety. This concept entails the use of echelons of administrative controls, fire protection systems and features, and safe shutdown capability to achieve the following objectives:*Prevent fires from starting.*Detect rapidly, control, and extinguish promptly those fires that do occur.*Protect SSCs to ensure the IUs can safely shut down.
Fire Area: A portion of the SHINE facility that is separated from other areas by fire barriers.
Fire Barrier: Components of construction (i.e., walls, floors and their supports, including beams, joists, columns, penetration seals or closures, fire doors and fire dampers) that are rated by approving laboratories in hours of resistance to fire and are used to prevent the spread of potential fire.Fire-Resistive Construction: A construction type in which the structural members are noncombustible and have a fire-resistant rating.
Fire Zone: A self-contained, controlled-environment wo rk enclosure providing a primary fire and radiological barrier from an occupied work area.
Operations are performed either remotely or through sealed openings in order to protect the wo rker and the ambient environment from the hazards of the working material.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-20Rev. 1Noncombustible Material: Materials having the characteristics listed below: a)Material which, in the form in which it is used and under the cond itions anticipated, will not ignite, burn, support combustion, or release flammable vapors when subjected to
fire or heat.b)Material having a structural base of noncombustible material, as defined in (a) with a surfacing not over 3.2 millimeter (0.13 inches) thick which has a flame spread rating not higher than 50 when measured in accordance with American Society for Testing and Materials (ASTM) Standard Test Method for Surface Burning Characteristics of Building Materials (ASTM, 2006).c)There is an exception to this definition that allows the use of combustible interior finishes when listed by a nationally recognized testing laboratory, such as Factory Mutual (FM) or Underwriters Laboratories (UL) Incorporated, for a flame spread, smoke, and fuel contribution of 25 or less in its use configuration.
Mezzanine: An intermediate level or levels between the floor and ceiling of any story that meet IBC (IBC, 2009) floor area and openness requirements.Non-combustible Construction: A construction type in which the structural elements are entirely of noncombustible or limited-combustible materials. Type IIB noncombustible construction has no fire resistant rating.9a2.3.4.3.2General The FHA provides descriptions of construction, operations, and fire hazards associated with each fire area in the SHINE facility. The following are considered and assessed in the analysis:*The applicable NRC fire protection requirements and guidance.*Amounts, types, configurations, and locations of cable insulation and other combustible materials.*In-situ fire hazards.*Automatic fire detection and suppression capability and other fire protection features
- Reliance on and qualifications of fire barriers.*Location and type of manual firefighting equipment and accessibility for manual fire fighting.*Potential for a toxic, biological, or radiation incident due to a fire.*Damage potential: maximum possible fire loss (MPFL).*Protection of SSCs.
- Life safety considerations.The collected data is used to perform the FHA review for every room or area, on a floor-by-floor basis. The collected data contain the following items: *Identification of the safety and nonsafety-related systems, and associated cabling within each fire area that could provide support for ensuring a safe shutdown condition.*Identification of fire areas containing radioactive material that could be released to the site boundary or beyond should a fire occur in that fire area.*Definition of the fire barriers surrounding a specific room or area which qualify rating the room or area as a separate fire area.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-21Rev. 0*A specific listing of types, quantities, and characteristics of all combustibles within a fire area that could constitute a fire load.*Listing of all the fire detection and suppression capabilities provided and their accessibility for each fire area.*Design provisions for protecting the functional capability of safety systems and associated cabling from the results of inadvertent operation, careless operation, or rupture of the extinguishing systems for each fire area are considered.*The means of containing and inhibiting the progress of a fire in each fire area; this is defined as the use of a fire-resisting enclosure or barrier, fire seals at wall penetrations, dampers, curbs, or fire doors into the area.The collected data is used in the FHA to formulate the following: An analysis of each fire area identifying the design criteria employed in providing fire protection for the equipment within the fire area. Divisional safety equipment is separated by 3-hour rated fire barriers. Fire detection, fire suppression, and fire seal capabilities are also discussed in the analysis.An analysis defining the consequences of the fire for each fire area; this is stated as loss of function and identifies the divisional backup capability available for safety systems. The loss of function that would not impair the capability of safe shutdown is identified where nonsafety-related systems are involved.9a2.3.4.3.3Function and Arrangement9a2.3.4.3.3.1General Construction Description Table 9a2.3-1 provides the IBC and Life Safety Code (LSC), NFPA 101 (NFPA, 2012d), classification summary for the SHINE facility. The IBC is used to classify the use and the construction of the SHINE facility. The LSC is used to classify the SHINE facility occupancy.9a2.3.4.3.3.2Fire Area Boundaries The SHINE facility is divided into twenty-one fire areas. The fire area boundaries are shown in Figure 9a2.3-1. A fire area is defined as that portion of the SHINE facility that is separated from other areas by fire barriers, including components of construction such as beams, joists, columns, penetration seals or closures, fire doors, and fire dampers. Fire barriers that define the boundaries of a fire area have a fire resistance ra ting of three hours or more. Self-contained fire zones inside fire areas are also shown in Figure 9a2.3-1. 9a2.3.4.3.4Acceptance Criteria The following items serve as the acceptance criteria for changes in the configuration of the SHINE facility fire areas and the associated des ign of fire protection systems and features:*Automatic water suppression systems are provided in the design for areas in which a transient fire loading is most likely to occu r as a result of combustibles introduced by normal maintenance operations. The FHA is based on the introduction of combustibles to any area of the SHINE facility, subject to SHINE's administrative control.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-22Rev. 0*The SHINE facility is generally of reinforced concrete construction. The walls, floors, and ceilings have 3-hour fire resistive rating where required by a high combustible loading in the room or where an adjacent room contains equipment or systems from a different safety train. Stair towers which do not communicate between areas of different divisions may have walls and doors with a 2-hour fire rating for personnel protection during egress from the areas. Non-concrete interior walls are constructed of metal studs and gypsum wallboard to the required fire resistive rating.*Doors, in general, are 3-hour rated, complying with NFPA ratings. There are also doors, not labeled, which provide area separation. Typical of these are the doors for the personnel air lock into the radiological control area (RCA) and the missile/tornado doors at the equipment access entrance to the SHINE facility. The term doors, where used in the analysis, shall mean doors, frames, and hardware.*Surface finishes are specified to hav e a flame spread, fuel-contributed and smoke-evolved index of 25 or less (Class A), as determined by ASTM-E84, Standard Test Method for Surface Burning Characteristics of Building Materials (ASTM, 2006), or NFPA255, Standard Method of Test of Surface Burning Characteristics of Building Materials (NFPA, 2006).*The use of plastic materials, including electrical cable insulation, has been minimized in the design.*Suspended ceilings are used in some areas of the SHINE facility. The ceilings, including the lighting fixtures, are of noncombustible construction.*The electrical cable fire seals are tested to demonstrate a fire rating equal to the rating of the barrier they penetrate. The tests are performed or witnessed by a representative of a qualified, independent testing laboratory. The documented test results for the acceptable fire seals are made a part of the SHINE facility design records.*Control, power, or instrument cables of redundant systems that are used for bringing the IUs to safe shutdown are separated by 3-hour fire barriers.*Certain areas of the SHINE facility have trays in stacked array. Where stacking of trays occurs, power cable, which is the most susceptible to internally generated fires, is routed in the uppermost tray to the greatest extent possible to provide maximum isolation from other trays in the stack. The fire loading of electrical cable in trays is based on flame-retardant, cross-linked polyethylene (XLPE-FR) insulation having a calorific value of 3.256 x 10 4 joules per gram (J/g) (1.40 x 10 4 british thermal units per pound [Btu/lb]).*Electrical cabling specified for the project meets flame-testing requirements IEEE 1202, Standard for Flame Testing of Cables for Use in Cable Tray (IEEE, 2006).-The cable trays are estimated at the maximum design fill to contain between 11.91and 15.63 kilograms (kg) of insulation per running meter of tray (between 8.0 and10.5 pounds [lbs] of insulation per running foot of tray).-The analysis uses an average 13.77 kg of insulation per meter of tray (9.3 lbs ofinsulation per foot of tray). The combustible loading is based on maximum loading.The loading reduces as cables drop out of (exits) trays and the fire loading decreases.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-23Rev. 0*Total reliance is not placed on a single fire suppression system. A minimum of two fire suppression means is available to each fire area. The SHINE facility design provides the following types of suppression and utilizes them in suitable combination for the fire hazard considered:-Automatic supervised air double interlock preaction systems.-Water spray deluge systems.
-Clean agent suppression systems.-Standpipes.-Class ABC hand extinguishers.*Piping penetrations are provided with fire-seals when penetrating fire resistive walls.*HVAC penetrations are provided with fire dam pers equal in rating to the fire barrier penetrated.*The design provides ventilating systems which minimize the release of radioactive materials through the use of HEPA and charcoal filtration systems. 9a2.3.4.4Safety Evaluation of Fire Hazards9a2.3.4.4.1Life Safety Considerations9a2.3.4.4.1.1GeneralLife safety provisions of the SHINE facility design are in accordance with LSC and IBC. Compliance with the LSC satisfies the exit requir ements of the Occupational Safety and Health Standard Title 29 of the Code of Federal Regulations Part 1910 (29 CFR 1910).
Automatic fire detectors are installed where required. In addition, manual pull stations are installed to allow personnel to activate the fire alarm system. Upon actuation of the fire alarm system, audible and visual indicating devices provide notification to personnel to evacuate the SHINE facility. Interior finishes consist of noncombustible and combustible materials. Exposed interior walls or ceilings (including ceilings formed by the underside of roofs) and any factory-installed facing materials have an UL listed/FM approved surface flame spread rating of 25 or less, and a smoke
development rating of 50 or less.9a2.3.4.4.1.2Occupancy The LSC is used to determine the SHINE facility occupancy classification. The occupancy classification for the SHINE facility is provided in Table 9a2.3-1.9a2.3.4.4.1.3Means of Egress Features Emergency exits are available from all areas of the SHINE facility within the IBC allowed maximum travel distance of 250 ft. (76 meters [m
]). Common path of travel does not exceed the allowed maximum of 100 ft. (30 m) per the IBC. Dead-end corridors do not exceed the allowed maximum of 50 ft. (15 m) per the IBC.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-24Rev. 09a2.3.4.4.1.4Illumination and Marking of the Means of EgressThe illumination of means of egress is provided in accordance with the LSC and IBC. Emergency lighting and marking of the means of egress are provided in accordance with the LSC and IBC.9a2.3.4.4.2Fire Protection FeaturesThis FHA is predicated on the assumption that a fire may occur in any one fire area within the SHINE facility. The nature of the postulated fire depends on the hazards present at any given time within the SHINE facility. The following fire protection features are designed to ensure a fire is successfully controlled or contained until such time as the fire department arrives to provide firefighting efforts.9a2.3.4.4.2.1Fire Water Supply SystemThe fire protection yard main piping arrangement and fire protection water supply system are shown in Figure 9a2.3-2. The fire protection process flow diagram is shown in Figure 9a2.3-3. Automatic fire water suppression systems are provided for the entire SHINE facility except for the following areas:*Hot cells. *Gloveboxes. *Vaulted storage tanks.
- Where water based suppression is ineffective for firefighting.9a2.3.4.4.2.2Special Suppression Systems Clean agent fire suppression systems are provided for fire protection of RPF areas containing flammable gas, if any, such as hot cells, gloveboxes and vaulted storage tanks. These systems are designed in accordance with American Glovebox Society (AGS) Standard of Practice for Glovebox Fire Protection (AGS, 2011), and NFPA 2001, Standard on Clean Agent Fire Extinguishing Systems (NFPA, 2012h).9a2.3.4.4.2.3Manual SuppressionManual fire suppression is conducted by a fully staffed, completely equipped, and adequately trained off-site fire department, capable and committed to respond to fires and related emergencies in a timely and effective manner. Personnel trained in the use of portable fire extinguishers are assumed to voluntarily conduct firefighting efforts on fires in the incipient stage.Class I standpipes are provided for manual fire suppression capability in the SHINE facility. ClassI systems include 21/2 inch hose connections. The 21/2 inch connection is not provided with a hose and is there for "trained fire-fighter" use only. The Class I standpipes are designed and installed in accordance with NFPA 14, Standard for the Installation of Standpipe and Hose
Systems (NFPA, 2010b).
Means for supporting manual fire suppression efforts in the SHINE facility consist of portable multipurpose dry-chemical and clean-agent extinguishers. These extinguishers are selected, installed, inspected, tested, and maintained in accordance with NFPA 10, Standard for Portable Fire Extinguishers (NFPA, 2010a).
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-25Rev. 29a2.3.4.4.2.4Fire Detection and Alarm SystemsFire alarm and detection systems are provided throughout the SHINE facility and are designed, installed, located, inspected, tested, and maintained in accordance with NFPA 72, National Fire Alarm and Signaling Code (NFPA, 2013e).Fire detection is provided as part of the facility fire detection and suppression system (FFPS) and the hot cell fire detection and suppression system (HCFD). The HCFD provides fire detection and suppression capabilities for the supercells and the hot cells in the RPF. Fire detectors in the HCFD send a signal to isolate the fire-rated dampers in the supercells and the hot cells in the event of a fire in one of these cells. These dampers prevent the spread of fire from the hot cell or supercell.
The fire detection in the HCFD is classified as non-safety related, since radiation detectors and associated interlocks with bubble-tight dampers controlled by RICS perform the SR function of reducing potential release of radioactive materials from the hot cell or supercell due to a fire. The suppression subsystem of the HCFD is classified as nonsafety-related.The fire detection in the rest of the SHINE facility is part of the FFPS. The FFPS is classified as nonsafety-related.9a2.3.4.4.3Fire Barriers and Protection of PenetrationsThe SHINE facility is generally of reinforced concrete construction. The walls, floors, and ceilings have a 3-hour fire resistive rating where required by a high combustible loading in the room or where adjacent room contains equipment or systems from a different safety train. Stair towers which do not communicate between areas of different divisions may have walls and doors with a 2-hour fire rating for personnel protection during egress from the areas. Non-concrete interior walls are constructed of metal studs and gypsum wallboard to the required fire resistive rating.The areas within the SHINE facility are subdivided into separate fire areas for the purposes of limiting the spread of fire, protecting personnel, and limiting the consequential damage to the SHINE facility. Determination of fire area boundaries is based on consideration of the following: *Types, quantities, density, and location of combustible materials.*Location and configuration of equipment.*Consequences of inoperable equipment.
- Location of fire detection and suppression systems.*Personnel safety/exit requirements.*Location of major electrical equipment.
- Location of process confinement areas.*Location of storage areas.*Separation of office areas from adjacent areas.Three-hour fire-rated barriers separate the individual fire areas within the SHINE facility. Fire barrier design and construction is in accordance with NRC regulations and NFPA 221, Standard for High Challenge Fire Walls, Fire Walls, and Fire Barrier Walls (NFPA, 2012f).
Where fire-rated assemblies are partially or fully penetrated by pipes, duct s, conduits, raceways or other such penetrates, fire barrier penetration material is placed in and around the penetrations to maintain the fire-resistance rating of the assembly. All openings in fire barriers are protected consistent with the designated fire-resistance rating of the barrier. Fire doors and Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-26Rev. 0dampers are rated commensurate with the fire barrier in which they are installed and comply with the requirements of NFPA 80, Standard for Fire Doors and Other Opening Protectives (NFPA, 2013f), and NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating System (NFPA, 2012c), respectively.
Certain doors and access hatches throughout the SH INE facility have a multipurpose function such as fire, pressure, radiation, seismic, watertight, and airlocks. Where possible, these doors and hatches are specified to rated and labeled cri teria and are then identified as rated doors. When other criteria require the manufacturer to delete the label, the door is identified as equivalent. Where the door is not constructed as a fire door, such as a containment personnel airlock, it is identified by its main function. 9a2.3.4.4.4Fire Water Collection Firefighting water expended within the SHINE facility during a fire event is collected, sampled and removed, as necessary. The method of collection will be identified in the FSAR. If HEPA
filters require deluge protection, the expended water is collected, sampled, and removed.9a2.3.4.4.5Ventilation and Smoke ControlThere are no smoke control design requirements associated with the life-safety features of the SHINE facility.9a2.3.4.4.6Fire AreasThere are 21 fire areas in the SHINE facility. These fire areas are separated by fire barriers as shown in Figure 9a2.3-1.9a2.3.4.4.6.1Radiological Control Area Overview The RCA is a unique fire area because it separates the radiological area from peripheral support areas of the SHINE facility and contains multiple smaller fire areas (Fire Areas 1 - 5) and fire zones. The RCA is entirely surrounded and separated by a 3-hour fire-rated barrier. The fire areas located within the RCA are broken down further into fire zones.The RCA consists of multiple areas that include process equipment, vaults, storage, and office space and allows an overhead bridge crane system to transfer material. Process equipment (i.e., hot cells, gloveboxes, supercells and vault tank units), also defined as fire zones, generate and contain hydrogen gas products that may pose an explosion and fire hazard. Hydrogen gas is classified as a highly flammable gas. A dedicated ventilation system is used to limit concentrations to less than the lower flammability limit (LFL).
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-27Rev. 09a2.3.4.4.6.2FA Tank Farm and Supercell Area9a2.3.4.4.6.2.1DescriptionThis area consists of a number of below-grade tanks that contain aqueous mixtures. In addition, this fire area contains several supercell unit s and hot cells. Specific fire zones include the uranium extraction (UREX) hot cell, pump transfer hot cell, solid waste hot cell, waste evaporation hot cell, thermal denitration (which includes a glovebox), and liquid waste solidification.9a2.3.4.4.6.2.2Life Safety ConsiderationsThis fire area is not normally occupied during normal plant operations. The egress route from this area is through the airlock and Fire Area 6, and exit to the exterior. There is no occupant access into the hot cell units; therefore, emergency egress provisions are not required.9a2.3.4.4.6.2.3Fire Protection Features This fire area is protected to provide a defense-in-depth approach to fire protection. This approach results in a fire being quickly detected and suppressed and reduces fire-induced damage.SuppressionA gaseous fire suppression system is designed and installed within each vault and hot cell.
DetectionAn early warning air sampling smoke detection system is designed and installed for each hot cell as well as the thermal denitration glovebox.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.2.4Potential for Toxic or Radioactive Incident Due to a FireToxic materials are not anticipated within the hot cells. However, radioactive hazards are present within the RCA and pose a radiological threat in the event of a fire.9a2.3.4.4.6.2.5Combustible LoadingThe area contains small amounts of stored radioactive/contaminated combustible materials such as protective clothing, decontamination supplies, and trash. This material is stored after processing in non-combustible containers, such as vented drums, barrels, and boxes.Several gallons of hydraulic fluid are contained in the crane gear box which can move throughout the area. Each of the hot cells contains mechanical systems and the associated supporting electrical systems.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-28Rev. 0In vaults, supercells and hot cells that contain processes that generate and contain hydrogen gas, ventilation systems are used to limit concentrations to less than the LFL in air.
The UREX hot cell contains nominally 5 ga llons of odorless kerosene (dodecane).9a2.3.4.4.6.3FA Irradiation Cell Areas9a2.3.4.4.6.3.1DescriptionThis fire area primarily contains material associated with the TSV and NDAS, TPS, and multiple pump skids. The IU cell, TOGS cell, and TPS area are subdivided into fire zones that contain a variety of processes and support equipment. Ea ch TPS glovebox is considered a single fire zone. Each of the sixteen IU and TOGS cells is considered an individual fire zone. Each cell is encased in at least 36 inches (91 centimeters) of concrete which is used for radiation shielding.9a2.3.4.4.6.3.2Life Safety Considerations This fire area is not normally occupied during normal plant operations; therefore, emergency egress provisions are not required. The egress route from this area is through the airlock and Fire Area 6, and exit to the exterior. 9a2.3.4.4.6.3.3Fire Protection Features SuppressionA non-water based fire suppression system is designed and installed within each hot cell and glovebox as required.
DetectionAn early warning air sampling smoke detection system is designed and installed for each IU cell, TOGS cell, hot cell, and glovebox.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.3.4Potential for Toxic or Radioactive Incident Due to a FireTritium is contained within each of the TPS gloveboxes and IU cells.
9a2.3.4.4.6.3.5Combustible LoadingIn IU cells, TOGS cells, and gloveboxes that generate and/or contain hydrogen gas, ventilation systems are used to limit concentrations to less than the LFL in air. Each of the cells contains mechanical handling and associated supporting electrical systems.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-29Rev. 09a2.3.4.4.6.4FA Labs9a2.3.4.4.6.4.1Description General office combustibles (e.g., chairs, desks and paper products) are present in the U.S.
Food and Drug Administration (FDA) lab, hot lab, decon, tool crib, and health physics rooms. 9a2.3.4.4.6.4.2Life Safety ConsiderationsThis fire area is normally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 1, the airlo ck, and Fire Area 6, and exit to the exterior.9a2.3.4.4.6.4.3Fire Protection Features
SuppressionA gaseous fire suppression system is designed and installed in the area.
DetectionA fire detection system is provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.4.4Potential for Toxic or Radioactive Incident Due to a FireThis area contains small amounts of chemicals and radioactive/contaminated materials.9a2.3.4.4.6.4.5Combustible Loading This area contains small amounts of stored radioactive/contaminated combustible materials such as office equipment, protective clothing, decontamination supplies, and trash. The combustibility of the materials is low and the associated quantity of combustibles is moderate.9a2.3.4.4.6.5FA Noble Gas Storage 9a2.3.4.4.6.5.1DescriptionPressurized gas canisters are stored in this fire area.9a2.3.4.4.6.5.2Life Safety Considerations This fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 1, the airlo ck, and Fire Area 6, and exit to the exterior.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-30Rev. 09a2.3.4.4.6.5.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionA fire detection system is provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.5.4Potential for Toxic or Radioactive Incident Due to a Fire There is a potential for radioactive r eleases due to a fire in this area.9a2.3.4.4.6.5.5Combustible LoadingThe combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.6FA Uranyl Sulfate Storage9a2.3.4.4.6.6.1Description This area serves as a storage and preparation area for uranyl sulfate. There are two gloveboxes present. There is also a fumehood in this area.9a2.3.4.4.6.6.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 1, the airlo ck, and Fire Area 6, and exit to the exterior.9a2.3.4.4.6.6.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionA fire detection system is provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-31Rev. 09a2.3.4.4.6.6.4Potential for Toxic or Radioactive Incident Due to a FireThis fire area contains LEU. Hazardous materials are used for processing in the area (nitric acid, sulfuric acid, uranium metal, uranyl nitrate, uranyl sulfate). 9a2.3.4.4.6.6.5Combustible LoadingThe combustibility of the materials is low and the associated quantity of combustibles is low. Combustible metals are stored and handled in accordance with NFPA 484 (NFPA, 2012g), Standard for Combustible Metals.9a2.3.4.4.6.7FA Offices/Corridors/Miscellaneous Area9a2.3.4.4.6.7.1DescriptionThis fire area consists of several office and miscellaneous rooms. All corridors outside of the airlock are included in this area. General office supply combustibles (i.e., chairs, desks and paper products) are in offices and storage rooms. This area also contains materials associated with neutron driver test/assembly. Shipping and receiving rooms are in this area. Other miscellaneous rooms include staging rooms, restroom and locke r room facilities, janitor supply room, the operations briefing room, and a security station.9a2.3.4.4.6.7.2Life Safety Considerations This fire area is normally occupied during normal SHINE facility operations. The egress route from this area is via multiple exits to the exterior. 9a2.3.4.4.6.7.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionA fire detection system is provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.7.4Potential for Toxic or Radioactive Incident Due to a FireThere is a potential for toxic or radioactive materials to be in this area during material transport. 9a2.3.4.4.6.7.5Combustible Loading This fire area contains cables in conduit/trays, electrical panels, and other ordinary combustibles.
The combustibility of the materials is low and the associated quantity of combustibles is low.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-32Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9a2.3.4.4.6.8FA Chemical Storage Area9a2.3.4.4.6.8.1DescriptionThis fire area is comprised of a total of five rooms. Three chemical storage rooms are in this fire area. In addition, there is a separate acids storage room and a separate alkalines storage room.9a2.3.4.4.6.8.2Life Safety ConsiderationsThis fire area is not normally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.9a2.3.4.4.6.8.3Fire Protection Features
SuppressionSupervised air preaction fire water suppression systems are provided for the three chemical storage rooms in this area. Automatic suppression systems are also provided for the acids storage room and the alkalines storage room.
DetectionA fire detection system is provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. The acids storage room and the alkalines storage room have fire-rated construction to separate them from other rooms and other fire areas.9a2.3.4.4.6.8.4Potential for Toxic or Radioactive Incident Due to a FireThere are no radioactive materials in the area. Toxic and hazardous chemicals are stored in the area. Stored chemicals in the area include: nitric acid, [Proprietary Information]sodium hydroxide (caustic), potassium permanganate, ammonium hydroxide, sodium iodide, silver nitrate, hydrochloric acid, alpha benzoin oxime, hydrogen peroxide, calcium nitrate, dodecane, tributyl phosphate, and acetohydroxamic acid. 9a2.3.4.4.6.8.5Combustible LoadingFlammable liquids are stored and handled in accordance with NFPA 30 (NFPA,2012b), with solid and liquid oxidizing agents stored and handled in accordance with NFPA 430 (NFPA,2004). The quantities and storage of the chemicals are in compliance with IFC (IFC,2009) and IBC (IBC, 2009).
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-33Rev. 09a2.3.4.4.6.9FA Main Switchgear A9a2.3.4.4.6.9.1DescriptionThis fire area contains electrical equipment (e.g., panels, motor control centers), cable trays, and conduits.9a2.3.4.4.6.9.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior. 9a2.3.4.4.6.9.3Fire Protection Features
SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
Detection Photoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.9.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.9.5Combustible LoadingThis fire area contains cables in conduit/trays. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.10FA Main Switchgear B 9a2.3.4.4.6.10.1DescriptionThis fire area contains electrical equipment (e.g., panels, motor control centers), cable trays, and conduits.9a2.3.4.4.6.10.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-34Rev. 09a2.3.4.4.6.10.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
Detection Photoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.10.4Potential for Toxic or Radioactive Incident Due to a Fire There are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.10.5Combustible LoadingThis fire area contains cables in conduit/trays. The combustibility of the materials is low and the associated quantity of combustibles is low.9a2.3.4.4.6.11FA Control and Instrument Air 9a2.3.4.4.6.11.1DescriptionAir compressors and control equipment are located in this fire area. 9a2.3.4.4.6.11.2Life Safety Considerations This fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior. 9a2.3.4.4.6.11.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-35Rev. 09a2.3.4.4.6.11.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.11.5Combustible LoadingThis fire area contains cables in conduit/trays. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.12FA Battery A and UPS A9a2.3.4.4.6.12.1Description This fire area contains two train A rooms: battery room and uninterruptible power supply (UPS) room. The batteries are located on steel racks.9a2.3.4.4.6.12.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior. 9a2.3.4.4.6.12.3Fire Protection Features
SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.12.4Potential for Toxic or Radioactive Incident Due to a Fire There are no combustible toxic or radioactive materials in the area that could be released to the atmosphere. Thus, there is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.12.5Combustible LoadingThis fire area contains cables in conduit/trays and combustibles associated with batteries. The combustibility of the materials is moderate and the associated quantity of combustibles is low. Ventilation systems are used to limit hydrogen concentrations in the battery room to less than 2percent by volume in air.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-36Rev. 09a2.3.4.4.6.13FA FICS and TPCS/RICS Rooms9a2.3.4.4.6.13.1DescriptionThis fire area contains two rooms: the FICS room and the target solution vessel (TSV) process control system (TPSC) and the radiological integrated control system (RICS) room.9a2.3.4.4.6.13.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.9a2.3.4.4.6.13.3Fire Protection Features
SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.13.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.13.5Combustible LoadingThis fire area contains cables in conduit/trays. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.14FA TRPS Room 9a2.3.4.4.6.14.1Description This fire area is the TSV reactivity protection system (TRPS) room.9a2.3.4.4.6.14.2Life Safety Considerations This fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6, and exit to the exterior.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-37Rev. 09a2.3.4.4.6.14.3Fire Protection Features Suppression 1Supervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.14.4Potential for Toxic or Radioactive Incident Due to a Fire There are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.14.5Combustible LoadingThis fire area contains cables in conduit/trays. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.15FA HMI/TELCO and FFPS/CAAS/RAMS/CAMS Rooms 9a2.3.4.4.6.15.1DescriptionThis fire area includes the human machine interface/telephone company (HMI/TELCO) room and the facility fire detection and suppression (FFPS) system, criticality accident alarm system (CAAS), radioactive area monitoring system (RAMS) and continuous air monitoring system (CAMS).9a2.3.4.4.6.15.2Life Safety Considerations This fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6, and exit to the exterior. 9a2.3.4.4.6.15.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-38Rev. 0 Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas.9a2.3.4.4.6.15.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.15.5Combustible LoadingThis fire area contains cables in conduit/trays. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.16FA Control Room 9a2.3.4.4.6.16.1DescriptionThis fire area consists of three rooms: the facility's control room, the shift supervisors office, and a bathroom. Computer equipment and general office combustibles (e.g., chairs, desks, and paper products) are in this fire area.9a2.3.4.4.6.16.2Life Safety ConsiderationsThis fire area is normally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.9a2.3.4.4.6.16.3Fire Protection Features
SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.16.4Potential for Toxic or Radioactive Incident Due to a Fire There are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-39Rev. 09a2.3.4.4.6.16.5Combustible Loading This fire area contains ordinary combustibles. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.17FA Fire Brigade and Hazmat Room9a2.3.4.4.6.17.1DescriptionFire brigade and hazmat equipment is stored in this fire area.
9a2.3.4.4.6.17.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.9a2.3.4.4.6.17.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.17.4Potential for Toxic or Radioactive Incident Due to a Fire There are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.17.5Combustible Loading This fire area contains ordinary combustibles. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.18FA HVAC Zone 4 (Boiler) Room9a2.3.4.4.6.18.1Description This fire area contains the HVAC boiler and associated equipment.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-40Rev. 09a2.3.4.4.6.18.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.9a2.3.4.4.6.18.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.18.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.18.5Combustible Loading
This fire area contains ordinary combustibles. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.19FA HVAC Zone 4 (Chillers) Room9a2.3.4.4.6.19.1DescriptionThis fire area contains the HVAC chillers.
9a2.3.4.4.6.19.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6 and exit to the exterior.9a2.3.4.4.6.19.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-41Rev. 0 Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.19.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.19.5Combustible Loading This fire area contains ordinary combustibles. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.20FA HVAC Zones 1, 2, and 3 (Supply Air Handler Room) 9a2.3.4.4.6.20.1DescriptionThis fire area is the supply air handler room for HVAC zones 1, 2, and 3.9a2.3.4.4.6.20.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is via the mezzanine stairwell, Fire Area 6, and exit to the exterior at grade level.9a2.3.4.4.6.20.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.20.4Potential for Toxic or Radioactive Incident Due to a FireThere are no toxic or radioactive materials in the area. There is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.20.5Combustible Loading
This fire area contains ordinary combustibles. The combustibility of the materials is low and the associated quantity of combustibles is low.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-42Rev. 09a2.3.4.4.6.21FA RCA HVAC Zones 1, 2, and 3 (Exhaust Filters) and Exhaust Fan &
Stack Room9a2.3.4.4.6.21.1Description
HEPA filters are provided to support contamination mitigation for the RCA. Fire protection features such as a deluge system are provided to minimize/mitigate the risk of interior and
exterior contamination. 9a2.3.4.4.6.21.2Life Safety Considerations This fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is via airlock, Fire Area 19, the mezzanine stairwell, Fire Area 6, and exit to the
exterior at grade level.9a2.3.4.4.6.21.3Fire Protection Features
SuppressionThe exact fire suppression method will be determined when the safety function and housing configuration is determined.
DetectionA fire detection system is provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.21.4Potential for Toxic or Radioactive Incident Due to a Fire There is a potential for a radioactive release from this area due to a fire. 9a2.3.4.4.6.21.5Combustible LoadingThis fire area contains HEPA and charcoal filters and other ordinary combustibles. The combustibility of the materials is low and the associated quantity of combustibles is low. 9a2.3.4.4.6.22FA Battery B and UPS B Rooms 9a2.3.4.4.6.22.1DescriptionThis fire area contains two train B rooms: battery room and UPS room. The batteries are located on steel racks.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-43Rev. 09a2.3.4.4.6.22.2Life Safety ConsiderationsThis fire area is occasionally occupied during normal SHINE facility operations. The egress route from this area is through Fire Area 6, and exit to the exterior.9a2.3.4.4.6.22.3Fire Protection Features SuppressionSupervised air preaction fire water suppression systems are provided through this entire area.
DetectionPhotoelectric smoke detectors are provided for this area.
Passive ProtectionPassive fire protection is provided in the form of fire-rated construction to provide separation between fire areas. 9a2.3.4.4.6.22.4Potential for Toxic or Radioactive Incident Due to a FireThere are no combustible toxic or radioactive materials in the area that could be released to the atmosphere. Thus, there is no potential for a toxic or radioactive incident due to a fire. 9a2.3.4.4.6.22.5Combustible Loading This fire area contains cables in conduit/trays and combustibles associated with batteries. The combustibility of the materials is moderate and the associated quantity of combustibles is low. Ventilation systems are used to limit hydrogen concentrations in the battery room to less than 2percent by volume in air.9a2.3.5TECHNICAL SPECIFICATIONSPotential variables, conditions, or other items that will be probable subjects of a technical specification associated with the fire protection system and program are provided in Chapter 14.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9a2-44Rev. 0Table 9a2.3-1SHINE Facility IBC and LSC ClassificationsArea CodeFacility Description IBC Use Classification IBC Construction ClassificationLSC Occupancy Classification 1Medical Isotope Production Facility F-1(SpecialIndustrial)Type I or II (Non-Combustible/
Non-Rated)Special Purpose Industrial Chapter9 -Auxiliary SystemsCommunication SystemsSHINE Medical Technologies9a2-46Rev. 09a2.4COMMUNICATIONS SYSTEMSThe communication systems provide communications during normal and emergency conditions between essential areas of the SHINE facility, as well as locations remote to the facility. The systems are designed such that a failure of any system does not impair the ability of the other systems to function. This is accomplished through the use of diverse technologies as described in Subsections 9a2.4.1 (on-site communications) and 9a2.4.2 (off-site communications) below.A more detailed description of the communication systems, including drawings and specifications of the principal components will be provided in the FSAR.9a2.4.1ON-SITE COMMUNICATIONS 9a2.4.1.1Normal Communication The facility utilizes a communication system that provides for paging, alarming, and party-line-type voice communications. Stations for this system are located throughout the facility. The system provides communications between any two areas of the facility. The system is designed so that a failure of any one station does not impact the other stations. The stations are modular in design for ease of replacement. In an emergency, this system is used to alert personnel.9a2.4.1.2Private Exchange Line A private exchange system is provided in various areas of the facility. These phones serve as a backup to the normal communications system. The system is tied to the commercial telephone system, which serves as the main off-site communications channel. The system is powered separately from the normal communications system.9a2.4.1.3Sound-Powered PhonesSound-powered phones are installed in strategic areas to supplement the normal communications system. These are hard wired independent of any room or system and are provided with handsets to be plugged in at each strategic area. The phones operate independent of any power source, and so are not affected by loss of power to the facility.9a2.4.1.4Radio System Hand-held portable radios operating on ultra high frequency (UHF) bands are provided. These radios are powered by replaceable, rechargeable battery packs and once charged are
independent of facility power until recharging is needed. Base station radios for communication with the portable radios are provided for the facility.9a2.4.2OFF-SITE COMMUNICATIONS9a2.4.2.1Telephone System Commercial telephones are provided in normally-manned areas. These phones allow personnel to contact any outside telephone number in the case of an emergency.
Chapter9 -Auxiliary SystemsCommunication SystemsSHINE Medical Technologies9a2-47Rev. 09a2.4.2.2Testing RequirementsThe design of the communications systems permits routine testing and inspection without disruption to normal communications. Testing is performed on an appropriate basis to detect and correct any problems or degradation of the communications systems.9a2.4.3TECHNICAL SPECIFICATIONS There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associ ated with the communication systems.
Chapter9 -Auxiliary SystemsPossession & Use of Byproduct, Source,and Special Nuclear MaterialSHINE Medical Technologies9a2-48Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9a2.5POSSESSION & USE OF BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIALThis section applies to the auxiliary systems within the IF that normally interact with byproduct, source, and special nuclear material. Refer to Section 9b.5 for the discussion of possession and use of byproduct, source, and special nuclear material in the radioisotope production facility.9a2.5.1BYPRODUCT MATERIAL
Within the SHINE facility, byproduct material is generated by the fission and irradiation of target solution in TSV (see Subsection 11.1.1). In addition, tritium is used in the facility and is classified as byproduct material. Possession and use of byproduct material is authorized and regulated under 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities, and also regulated under 10CFR Part 30.The IF-related auxiliary systems that process byproduct material are the tritium purification system (TPS) and target solution preparation system (TSPS).9a2.5.1.1Tritium Purification System The byproduct material present in the TPS is tritium. The TPS controls the distribution and processing of tritium for the neutron driver. TPS provides tritium at a purity of [Proprietary Information] to the tritium target chamber in the neutron driver assembly system (NDAS), and cleans up impurities in the tritium return stream from the NDAS. Tritium is fed to the tritium target chamber to generate neutrons for nuclear fission of uranium, and remains isolated from the target solution.Tritium is located throughout the TPS in tanks, piping, and adsorption beds. A raffinate waste stream from the tritium cleanup is sampled before being released to RCA Zone 1 Exhaust.Tritium processing occurs within the TPS gloveboxes which have a tritium capture system to trap any tritium released to the glovebox atmosphe re. The gloveboxes minimize the exposure of workers to tritium. TPS tritium piping external to the glovebox is double-walled with tritium detection. Tritium circulated to the NDAS is at sub-atmospheric pressure. There are redundant TPS process trains in separate gloveboxes. Refer to Subsection 9a2.7.1 for additional details regarding the TPS.9a2.5.1.2Target Solution Preparation System The target solution hold tanks contain the majority of the byproduct material in the TSPS. These tanks receive irradiated target solution that is recycled from the UNCS. This material contains most of the fission products present in the target solution with the exception of those fission products that are removed in the MEPS. The target solution hold tanks are criticality-safe by geometry, and are located in shielded tank vaults within the RCA. Access to the tank vault is strictly controlled, to prevent worker exposure to the radiation within the tanks. The tank vaults are equipped with sumps, to detect leakage of byproduct material from the primary fission produc t barrier (the tank and associated piping).
Chapter9 -Auxiliary SystemsPossession & Use of Byproduct, Source,and Special Nuclear MaterialSHINE Medical Technologies9a2-49Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]Thetanks are used for staging target solution prior to filling the associated TSV. If necessary, minor chemical adjustments may be made to the target solution in the target solution hold tanks.9a2.5.2SOURCE MATERIAL Source material is defined as natural uranium or thorium or depleted uranium that is not suitable for use as reactor fuel, per 10 CFR 40, Domestic Licensing of Source Material. There is no
source material normally present in the auxiliary systems in the IF. [Proprietary Information]
9a2.5.3SPECIAL NUCLEAR MATERIALSpecial nuclear material (SNM) is defined as plutonium (Pu), uranium-233 (U-233), or uranium enriched in the isotopes U-233 or uranium-235 (U-235). LEU is irradiated to produce molybdenum-99 by fission within theIF. During this process, a small quantity of Pu is also generated in the target solution [Proprietary Information]. The target solution hold tank contains LEU and a single TSV batch of Pu.9a2.5.4TECHNICAL SPECIFICATIONSPotential variables, conditions, or other items that will be probable subjects of a technicalspecification associated with the possession and use of byproduct, source, and SNM areprovided in Chapter 14.
Chapter9 -Auxiliary SystemsCover Gas Control in Closed Primary Coolant SystemsSHINE Medical Technologies9a2-50Rev. 09a2.6COVER GAS CONTROL IN CLOSED PRIMARY COOLANT SYSTEMSThe PCLS is a closed loop cooling system that provides cooling to the TSV. Details for the cover gas control in the PCLS cooling water tank (1-PCLS-01T) will be provided in the FSAR.The LWPS is not a closed-loop system. No cover gas control for the LWPS is utilized. Buildup ofradiolysis products in the IU cell is prevented by the RCA ventilation system Zone 1 and thevolume of the cell.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-51Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9a2.7OTHER AUXILIARY SYSTEMSThis section describes other auxiliary systems in the IF that are not described in the rest of Section 9a2 or other chapters of the PSAR. The TPS is the only auxiliary system in the IF.
9a2.7.1TRITIUM PURIFICATION SYSTEM9a2.7.1.1TPS Process DescriptionThis subsection applies to the tritium purification system (TPS). The portion of the system that separates tritium and deuterium is the thermal cycling absorption process (TCAP).The TPS is responsible for providing high-purity tritium to the neutron driver. The tritium return stream contains significant quantities of deuterium and other impurities. These impurities are removed in a semi-batch process, and the tritium is stored until it is recycled to the NDAS. 9a2.7.1.1.1System Process FunctionsThe following is a list of the process functions of the TPS:a.Provide approximately [Proprietary Information] tritium gas [Proprietary Information] to the NDAS.b.Receive tritium gas from a bottle periodically.
c.Receive approximately [Proprietary Information] tritium/deuterium gas from theNDAS.d.Remove water, organic impurities, and deuterium from the tritium.e.Receive flush gas from the NDAS and remove tritium from the flush gas.
f.Monitor TPS waste streams that are discharged to the exhaust systems.g.Scrub the glovebox atmosphere for tritium that may escape from the purification processes.9a2.7.1.2Safety-Related FunctionsMinimize chronic or acute tritium releases.a.Robust TPS construction and confinement provided by the glovebox and double-walled pipe.b.TPS confinement system (e.g., relief valves or rupture discs, monitoring instrumentation, isolation valves).c.TPS cell volume combined with TPS tritium inventory sufficient to maintain less than LFL assuming a TPS tritium leak.9a2.7.1.2.1Primary System InterfacesFor a list of system interfaces, refer to Table 9a2.7-1.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-52Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9a2.7.1.2.2Tritium Purification Process SequenceThere are two TPS gloveboxes, which are each sized to supply the entire facility tritium demand. The following are the fundamental steps performed in the gloveboxes to support TCAP. Detailed descriptions of these steps will be provided in the FSAR.*Target Gas Receiving - Recirculating tritium is transferred to the glovebox by vacuum pumps located in the NDAS and inside the glovebox. The recirculating tritium is stored in storage tanks prior to treatment.*Impurity Removal - The first purification step is to remove water and other non-hydrogen species. This is accomplished by ambient and cryogenic molecular sieve beds, heated permeators, and getter beds. The cryogenic molecular sieve beds are cooled with liquid nitrogen, and the nitrogen gas is exhausted to the Zone 1 exhaust. The raffinate from the impurity removal feeds into the flush gas evacuation treatment process. *Storage and Separation - After impurity removal, the gas contains mainly tritium and deuterium. This gas is stored in feed beds prior to separation. From the feed beds, the tritium fills a feed volume tank, and then is fed into TCAP where separation occurs. The product is fed into a product volume tank and then stored on palladium beds. One of the palladium beds is heated to provide tritium to the NDAS. The motive force to supply the NDAS is provided by vapor pressure from heating the palladium beds. The raffinate from TCAP is primarily deuterium with no more than [Proprietary Information] tritium. This raffinate is captured in the TPS exhaust sampling tank.*Flush Gas Purification - During routine startup of the NDAS, a flush gas is routed to the TPS and treated to remove tritium. This gas will be oxidized on a catalytic reactor, and then dried by passing through an ambient molec ular sieve bed. The molecular sieve bed will be regenerated periodically to recover and dispose of the tritium oxide. This raffinate is captured in the TPS exhaust sampling tank. The raffinate from the impurity removal process is also treated in the flush gas evacuation step to minimize the amount of tritium released.*The raffinates in the TPS exhaust sampling tank (1-TPS_-01T) are sampled for tritium before they are released to the Zone1 Exhaust. If excessive tritium is present, the gas will be recycled to the flush gas purification process.See Figure 9a2.7-1 for the TPS process flow diagram (PFD), as well as interfacing systems.
9a2.7.1.2.3Tritium Stream PropertiesSee Table 9a2.7-2 for the properties of the trit ium supply, return, and raffinate streams. In addition to these streams, the TPS receives flush gas from the NDAS before irradiation of target solution begins. This gas is treated in the flush gas purification step to remove tritium before it is exhausted.9a2.7.1.2.4Process Equipment See Table 9a2.7-3 for a list of major process equipment associated with the TPS.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-53Rev. 09a2.7.1.3TPS Glovebox Description9a2.7.1.3.1Glovebox Physical DescriptionThe TPS process equipment is enclosed in two separate gloveboxes, one for Train A and a second for Train B. Both trains are sized to accommodate the entire demand of the eight NDASs in case one train is unavailable.
Each glovebox has an airlock co nnected to a centrally-located air hood. The airlocks and air hood facilitate the removal and replacement of internal equipment as needed to each glovebox train. Each glovebox has an internal maintenance crane and hois t on the inside ceiling of the glovebox and sliding trays on the floor of the glovebox to allow internal equipment to be removed from its supports, lifted, lowered and placed onto the sliding tray below. The sliding tray is manually pushed using the gloveports in the windows.Both gloveboxes have gloveport windows mounted on both sides, internal and external electrical receptacles, and top and side mounted lighting fixtures.The gloveboxes are operated in a nitrogen environment and each uses a blower mounted inside the glovebox to circulate the nitrogen through a water chiller system to provide cooling to the glovebox atmosphere.The glovebox volume is sized such that a release of stored tritium would not result in exceeding the LFL in the glovebox.9a2.7.1.3.2Glovebox Atmosphere Treatment Tritium is released into the glov ebox occasionally, so the glov ebox is designed to treat the atmosphere to minimize the tritium concentration. The glovebox atmosphere normally has a very low tritium concentration. The most significant releases of tritium to the glovebox atmosphere are likely during maintenance activities (e.g.
disconnecting beds or pumps for replacement).The glovebox has a recirculating inert atmosphere with minimal nitrogen makeup. The oxygen content in the glovebox is monitored, and at high levels the operator is notified by alarms. The recirculating loop cleans the atmosphere to mi nimize the amount of tritium. The glovebox atmosphere exhausts through a HEPA filter and a bubbler into the RVZ1.
The cleanup involves a molecular sieve bed to remove most oxidized tritium, a nickel bed to remove the remaining oxidized tritium, and a zirconium-iron getter bed to capture elemental and gaseous tritium. The zirconium-iron getter bed operates at approximately 662°F (350°C). Since nitrogen reacts with the getter material above 842°F (450°C), the getter bed has high-temperature protection. All beds are regenerable, and are installed with backups in parallel. 9a2.7.1.4Radiological Protection
The processes associated with the TPS are performed within a glovebox to minimize the exposure of individuals to tritium. The vacuum pumps are oil-less to avoid the spread of tritium contamination. Outside of the glovebox, TPS tritium piping is double-walled with tritium detection monitors and alarms to alert operators of any leaks. Additionally, the tritium outside the glovebox is normally under vacuum. Monitors are located near tritium piping and at glovebox workstations Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-54Rev. 0to identify tritium leaks. The TPS is designed to maintain chronic and acute exposures to tritium ALARA. Releases of tritium to the facility or environment are within 10 CFR 20 limits.Outside the glovebox boundary, TPS tritium piping is double-walled. The annular space is open to the glovebox atmosphere treatment, with monitoring to identify potential leaks. The connections are welded or metal gasket face sealed to ensure high integrity. Tritium is supplied to the NDAS at sub-atmospheric pressure. The tritium within the NDAS is circulated to and from the target chamber by vacuum pumps. A molecular drag pump is used to aid in returning the tritium gas to the glovebox.9a2.7.1.5Hazardous ChemicalsExcept tritium, described in Subsection 9a2.7.1.3.2, the current design has not identified any hazardous chemicals in the TPS.9a2.7.1.6Instrumentation and ControlsThe TPS process equipment within the glovebox is operated through a programmable logic controller/process automation controller (PLC/PAC). The process is performed in semi-batch process steps of treating the contaminated flush gas and purifying the contaminated tritium gas.Process steps and local interfaces (operator interface terminals [OIT]) are controlled and monitored by the PLC system. See Table 9a2.7-4 for the preliminary control system interface with the TSV process control system (TPCS).9a2.7.1.7Technical SpecificationsPotential variables, conditions, or other items that will be probable subjects of a technical specification are provided in Chapter 14.9a2.7.2OFF-NORMAL AND ACCIDENT SCENARIOS Part of the evaluation of other auxiliary systems is to determine that the design, functions, and potential malfunctions of the auxiliary system will not cause malfunctions or accidents that could result in uncontrolled release of radioactivity. This evaluation for auxiliary systems in both the IF and the RPF were reviewed as part of the development of the integrated safety analysis (ISA) for potential as a design basis accident (DBA) or initiating event (IE). The bases for the identification of DBAs and their IEs and associated accident scenarios were:*Hazard and operability study (HAZOPS) as part of the development of the integrated safety analysis (ISA) summary, in accordance with NUREG-1520.*List of IEs and accidents identified in the Final Interim Staff Guidance Augmenting NUREG-1537, Part 1.*Experienced hazards analysis team.*Preliminary design for the processes and facility.The ISA development process identified process equipment by breaking it down into 56 systems and nearly 400 scenarios for both the IF and RPF.
Causes for deviations and their potential out-comes were then identified. Finally, potential protective controls, safety functions, and functional Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-55Rev. 0requirements were identified. This led to the identification of the accident scenarios addressed in Chapter 13. For the FSAR a final HAZOPS analysis will be performed. The above noted process considered the other auxiliary systems identified in this chapter.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-56Rev. 0Table 9a2.7-1 TPS InterfacesInterfacing SystemInterface Description Neutron Driver Assembly System (NDAS)TPS interfaces with the NDAS at two locations: the inlet and outlet connections to the NDAS.Radiological Control Area (RCA) Ventilation Zone1TPS interfaces with the RCA Ventilation Zone 1 at two locations: the point of connection from the glovebox exhaust to the Zone 1 header duct, and the point of connection from the TPS exhaust sampling tank.
Radioisotope Process Facility Cooling System (RPCS) TPS interfaces with the RPCS at two locations: the inlet and outlet connections on the glovebox chiller heat exchanger.
Normal Electrical Power Supply System (NPSS)
TPS interfaces with the NPSS at the following locations: the glovebox electrical penetration(s), and connections to equipment located external to the glovebox. Electrical power
is distributed within the gloveb ox to operate the various pumps and heaters in the TPS, and other ancillary
equipment.Inert Gas Control (IGS)TPS interfaces with IGS at one location. Desiccants or other methods of providing dry inerting to the glovebox may be required to avoid excessive loading of the glovebox atmosphere desiccant bed.
Solid Radioactive Waste Packaging (SRWP)The TPS produces solid radioactive waste that is processed in the SRWP system.Facility Inert Gas System (FIGS)The TPS receives liquid nitrogen for cooling components. The interface point is the glovebox wall.
TSV Process Control System (TPCS)The TPCS receives output signal from the TPS controller(s) and provides some limited input to the TPS controller(s).
Engineered Safety Features Actuation System (ESFAS)The ESFAS receives input from loss of TPS confinement sensors (radiation and/or pressure), and outputs to the TPS
confinement isolation valves.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-57Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]Table 9a2.7-2 Tritium Supply/Return PropertiesStreamSupplyReturnRaffinateCompositionTritium[ProprietaryInformation][ProprietaryInformation][ProprietaryInformation] maxDeuteriumBalanceBalanceBalanceNominal Flow[ProprietaryInformation][ProprietaryInformation]10 sccmPressure< 1 atm< 1 atm< 1 atm Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-58Rev. 0Table 9a2.7-3 TPS Process EquipmentComponentDescriptionCode/Standard Glovebox Atmosphere Recirculation Blower (1-TPS_-02C-A/B)
The blower is used to recirculate the atmosphere so that the glovebox atmosphere treatment equipment may remove any tritium from the glovebox
atmosphere. The blower is a positive-displacement type used in a nitrogen environment up to 140°F.ANSI/API 617 TPS Glovebox Atmosphere Chiller
(1-TPS_-02A-A/B)This water-to-water heat exchanger cools the glovebox cooling water. The glovebox
cooling water is used to cool components and/or glovebox atmosphere to maintain the glovebox atmosphere temperature.
Commercial grade TPS Glovebox Chiller Pump (1-TPS_-01P-A/B)
The positive-displacement pump serves torecirculate the glovebox cooling water.
Commercial grade TPS Exhaust Sampling Tank (1-TPS_-01T)The tank is a reservoir to collect TPS effluents before they are released to the RCA Ventilation Zone 1. The tank contents are sampled for acceptance and released, or recycled to the flush gas purification treatment.
ASME BPVC Section VIII Glovebox Atmosphere Molecular Sieve
(1-TPS_-01D-A-D)The molecular sieve traps water in the glovebox atmosphere.
ASME BPVC Section VIII Glovebox Atmosphere Nickel Bed (1-TPS_-02D-A-D)
The nickel bed traps water in the gloveboxatmosphere.
ASME BPVC Section VIII Glovebox Atmosphere ZrFe Bed (1-TPS_-03D-A-D)The zirconium-iron bed traps elemental and gaseous tritium in the glovebox atmosphere.
ASME BPVC Section VIIITPS Glovebox A/BThe negative-pressure, inert-atmosphere glovebox acts as secondary confinement of the tritium. It is protected from overpressure by a bubbler on the exhaust.
AGS-G001 Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9a2-59Rev. 0Table 9a2.7-4 TPS Preliminary Control System Interface (a)a) For TPS trains A and B, the following signals will be relayed between the TPS PLC and TPCS.Signal Description TypeTPS Run Status Output from the TPS PLC.TPS Fault Status Output from the TPS PLC.
TPS Mass FlowInput request from the TPCS. Output from the TPS PLC.TPS Shutdown InterruptInput request from the TPCS. Output from the TPS PLC.
TPS Run RequestInput request from the TPCS at TSV start-up.
Chapter9 -Auxiliary SystemsIrradiation Facility Auxiliary Systems Technical SpecificationsSHINE Medical Technologies9a2-60Rev. 09a2.8IRRADIATION FACILITY AUXILIARY SYSTEMS TECHNICAL SPECIFICATIONSPotential variables, conditions, or other items that are probable subjects of a technical specification associated with the IF auxiliary systems are provided in Chapter 14.
Chapter9 -Auxiliary SystemsReferencesSHINE Medical Technologies9a2-61Rev. 09a
2.9REFERENCES
AGS, 2007. Guideline for Gloveboxes, AGS-G001, American Glovebox Society, February, 2007.AGS, 2011. AGS-G010-2011, Standard of Practice for Glovebox Fire Protection, 2011.
ANSI/ANS, 1981.
ANSI/ANS 15.17, Standard for Fire Protection Program Criteria for Research Reactors, 1981.
ANSI/HI, 2008. Rotary Pumps (A109), 3.1-3.5, American National Standards Institute, January1, 2008.ASME, 2011. Boiler & Pressure Vessel Code - Rules for Construction of Pressure Vessels,Section VIII, American Society of Mechanical Engineers, July 1, 2011.ASME, 2012. Process Piping, Code for Pressure Piping, B31.3-2012, American Society of Mechanical Engineers, January 10, 2103.ASTM, 2006. ASTM E84, Standard Test Method for Surface Burning Characteristics of Building Materials, 2006.DOE, 2008. DOE Handbook for Tritium Handling and Safe Storage, DOE-HDBK-1129, Department of Energy, December 2008.
IBC, 2009.
International Building Code, 2009.
IEEE, 2006. Institute of Electrical and Electronic Engineers 1202, Standard for Flame-Propagation Testing of Wire and Cable, 2006.
NFPA, 2004. NFPA 430, Code for the Storage of Liquid and Solid Oxidizers, 2004 Edition.
NFPA, 2006. NFPA 255, Standard Method of Test of Surface Burning Characteristics of Building Materials, 2006 Edition.
NFPA, 2008a. NFPA 22, Standard for Water Tanks for Private Fire Protection, 2008 Edition.
NFPA, 2008b.
NFPA 69, Standard on Explosion Prevention Systems, 2008 Edition.
NFPA, 2008c. NFPA 801, Standard for Fire Protection for Facilities Handling Radioactive Materials, 2008 Edition.
NFPA, 2010a.
NFPA 10, Standard for Portable Fire Extinguishers, 2010 Edition.
NFPA, 2010b. NFPA 14, Standard for the Installation of Standpipe and Hose Systems, 2010 Edition.
Chapter9 -Auxiliary SystemsReferencesSHINE Medical Technologies9a2-62Rev. 0 NFPA, 2011a. NFPA 25, Standard for the Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems, 2011 Edition.
NFPA, 2011b. NFPA 45, Fire Protection for Laboratories Using Chemicals, 2011 Edition.
NFPA, 2011c.
NFPA 70, National Electrical Code, 2011 Edition.
NFPA, 2011d. NFPA 780, Standard for the Installation of Lightning Protection Systems, 2011Edition.
NFPA, 2012a. NFPA 15, Standard for Water Spray Fixed Systems for Fire Protection, 2012Edition.
NFPA, 2012b. NFPA 30, Flammable and Combustible Liquids Code, 2012 Edition.
NFPA, 2012c. NFPA 90A, Standard for the Installati on of Air-Conditioning and Ventilating System, 2012 Edition.
NFPA, 2012d. NFPA 101, Life Safety Code, 2012 Edition.
NFPA, 2012e. NFPA 220, Standard on Types of Building Construction, 2012 Edition.
NFPA, 2012f.
NFPA 221, Standard for High Challenge Fire Walls, Fire Walls, and Fire Barrier Walls, 2012 Edition.
NFPA, 2012g. NFPA 484, Standard for Combustible Metals, 2012 Edition.
NFPA, 2012h. NFPA 2001, Standard on Clean Agent Fire Extinguishing Systems, 2012 Edition.
NFPA, 2013a.
NFPA 13, Standard for the Installation of Sprinkler Systems, 2013 Edition.
NFPA, 2013b. NFPA 20, Standard for the Installation of Stationary Pumps for Fire Protection, 2013 Edition.
NFPA, 2013c. NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances, 2013 Edition.
NFPA, 2013d. NFPA 55, Compressed Gases and Cryogenic Fluids Code, 2013 Edition.
NFPA, 2013e. NFPA 72, National Fire Alarm and Signaling Code, 2013 Edition.
NFPA, 2013f. NFPA 80, Standard for Fire Doors and Other Opening Protectives, 2013 Edition.
WCB, 2011. Wisconsin Commercial Building Code, SPS 360-366, 2011.
Chapter9 -Auxiliary SystemsHeating, Ventilation, and Air Conditioning SystemsSHINE Medical Technologies9b-1Rev. 09bRADIOISOTOPE PRODUCTION FACILITY AUXILIARY SYSTEMS9b.1HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMSThe SHINE facility HVAC systems are described in Section 9a2.1.
Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9b-2Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390]9b.2HANDLING & STORAGE OF TARGET SOLUTION9b.2.1TARGET SOLUTION LIFECYCLEThe target solution is a uranyl sulfate solution that is prepared by dissolving uranium oxide in sulfuric acid. The target solution is loaded into the TSV where it undergoes irradiation. After irradiation is complete, the irradiated target solution is transferred to the molybdenum extraction and purification system (MEPS) where molybdenum is extracted. The target solution is then either recycled back to the TSV to go through irradiation and MEPS processing again, or is sent to the UNCS to be converted into uranyl nitrate and subsequently into uranium oxide in order to repeat the overall process.The chemical properties of the target solution can be found in Subsection 4a2.2.1, which includes uranium content, density, and solubility. Detailed descriptions of the processing of irradiated and unirradiated SNM and byproducts are found in Subsections 4b.4.1 and 4b.4.2. Equipment and design features involved in the SNM lifecycle are included in these chapters. This section focuses on the storage and handling of SNM and byproducts during the lifecycle of the ta rget solution in the facility (preparation to shipment off-site).Refer to Figures 9a2.2-1 and 9b.2-1 for the flow diagrams of the process equipment discussed in this section.9b.2.2DISSOLUTION OF URANIUM METALNewly introduced unirradiated SNM is in the form of uranium metal. Uranium metal is dissolved in 12 M nitric acid in the uranium metal dissolution tank (1-TSPS-02T) to form a uranyl nitrate solution. The uranyl nitrate solution is then transferred to the recycle uranyl nitrate hold tank (1-UNCS-06T) and then transferred to the thermal denitration (TDN) process to be processed into uranium oxide. Addition of uranium metal makes up for uranium losses throughout the processes within the RCA. The dissolution process also allows the facility to be loaded or charged with uranium during facility startup.The uranium metal dissolution tank (1-TSPS-02T) dissolves up to [Security-Related Information] of uranium metal in [Security-Related Information] of 12 M nitric acid in a single batch. The uranium metal dissolution tank (1-TSPS-02T) is maintained between 167 to 185°F (75 to 85°C) during dissolution without an agitation mechanism. To accommodate various amounts of uranium metal to be dissolved, [Security-Related Information] of nitric acid is used per [Security-Related Information] of uranium metal. The uranium oxide produced from the dissolution and thermal denitration of unirradiated uranium metal is stored in uranium oxide storage cans in criticality-safe configuration within the uranium oxide storage rack. Uranium oxide is stored until needed by the facility for the production of target solution.
Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9b-3Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390
][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9b.2.3TARGET SOLUTION PREPARATIONTarget solution (uranyl sulfate) is prepared in the target solution preparation tank (1-TSPS-01T) by dissolving uranium oxide in approximately 0.8 M sulfuric acid with the tank maintained at approximately 158°F (70°C) and agitated until the uranium oxide is fully dissolved. The range of uranyl sulfate concentration is [Proprietary Information][Security-Related Information], and the desired concentration is prepared with an accuracy better than 1 percent. The pH of the target solution is between [Proprietary Information].
The volume range of the target solution is [Proprietary Information][Security-Related Information] per TSV batch. See Subsection 4a2.2.1 for a list of the target solution chemical properties.The mass of uranium oxide used to prepare target solution is measured in the target solution preparation hood and transferred to target solution preparation tank (1-TSPS-01T) by emptying the required number of uranium oxide storage cans into the tank. Operators adjust the amount of sulfuric acid to be added based on the amount of uranium oxide loaded into the target solution preparation tank (1-TSPS-01T).9b.2.4SHIPMENT AND RECEIPT OF SNMUnirradiated SNM is received in the form of uranium metal in solid form from a Department of Energy (DOE) supplier. The shipments consist of LEU metal enriched to 19.75 +/- 0.2 weight percent U-235, with a maximum of 19.95 weight percent U-235. Shipment of uranium metal is received on pallets containing transport containe rs and is transferred to the uranium metal receipt area within the RCA. Uranium metal is stored in a criticality-safe geometry. The uranium metal receipt area has the capacity to store transport containers. The transport containers containing three convenience containers with up to [Security-Related Information] of uranium metal each (up to [Security-Related Information] total) are individually removed from the transport container and placed in the receipt ventilation hood. Within the receipt ventilation hood the convenience container is opened, the contents are verified. Up to [Security-Related Information] of uranium metal is then repackaged into the uranium metal storage can. The uranium metal storage can is designed to be criticality-safe in this configuration. The uranium metal storage can is then transferred to the uranium metal storage rack prior to further processing. See Figure 9b.2-2 for the assem bly view of the uranium metal/oxide storage rack.Shipments of uranium oxide are received in containers and are transferred to the RCA. These containers are individually placed in the receipt vent ilation hood. Within the receipt ventilation hood, the container is opened, the contents are verified. Up to [Security-Related Information] of uranium oxide is then repackaged into the uranium oxide storage can. The uranium oxide storage can is then transferred to the criticality-safe uranium oxide storage rack prior to further processing. Uranium oxide is also received as a product from TDN. This uranium oxide is packaged in uranium oxide storage cans and stored in the uranium oxide storage rack prior to further processing. See Figure 9b.2-2 for the assembly view of the uranium metal/oxide storage rack.Refer to Chapter 4b.4.2 for additional shipment and receipt information.9b.2.5TARGET SOLUTION PREPARATION HANDLING EQUIPMENT The flow diagrams that include the equipment discussed in this subsection are Figures 9a2.2-1 and 9b.2-1.
Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9b-4Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390
][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]After target solution has been prepared in the target solution preparation tank (1-TSPS-01T), it is pumped to the target solution hold tank (1-TSPS-03T) to wait for loading into the TSV. Target solution is pumped from the target solution hold tank (1-TSPS-03T) to the TSV before irradiation operations begin. If a recycled (previously irradiated) target solution batch is used, the recycled target solution is pumped from the recycle target solution tank (1-UNCS-09T) to the target solution hold tank (1-TSPS-03T) instead of using unirradiated target solution prepared in the TSPS.After irradiation in the TSV, the target solution is gravity-transferred to the TSV dump tank (1-SCAS-01T) where it waits to be pumped to MEPS and then on to UNCS for further processing. SNM and byproducts in the target solution remain in solution until they are separated downstream in the MEPS and UNCS processes. Fissile SNM is held in criticality-safe geometry equipment. See Section 4b.3 and 4b.4.1 for a detailed description of MEPS and UNCS SNM
processing. The following is a list of equipment necessary for preparing target solution in the RPF. See Figure 9a2.2-1 for the flow diagram that shows the TSV-related equipment and Figure 9b.2-1 for the TSPS-related equipment. *Uranyl Sulfate Preparation Tank (1-TSPS-01T-A/B)Quantity: 2-Nominal Size: [Proprietary Information][Security-Related Information]
-Normal Operating Pressure: atmospheric (vented)-Double-Contingency, Criticality-Safe Geometry-Design/Fabrication Code: ASME BPVC Section VIII Div 1 (ASME, 2011)*Uranyl Sulfate Pump (1-TSPS-01P-A/B)Quantity: 2-Type: Positive Displacement-Nominal Power: 0.25 hp Design/Fabrication Code: To be determined at final design*Uranium Metal Dissolution Tank (1-TSPS-02T-A/B)Quantity: 2-Nominal Size: [Security-Related Information]
-Normal Operating Pressure: atmospheric (vented)-Double-Contingency, Criticality-Safe Geometry-Design/Fabrication Code: ASME BPVC Section VIII Div 1 (ASME, 2011)*Dissolution Solution Pump (1-TSPS-02P-A/B)Quantity: 2-Type: Positive Displacement-Nominal Power: 0.25 hp Design/Fabrication Code: To be determined at final design Chapter9 -Auxiliary SystemsHandling & Storage of Target SolutionSHINE Medical Technologies9b-5Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390
][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]*Uranium Receipt Ventilation HoodQuantity: 1-Design/Fabrication Code:
-AGS-G001-2007 (AGS, 2007)9b.2.6STORAGE OF SNM Uranium metal is stored in the uranium metal storage rack within the uranium metal receipt area. The uranium metal storage rack holds up to [Proprietary Information][Security-Related Information]uranium storage cans in a criticality-safe configuration.Uranium oxide is stored in the uranium oxide storage rack within the uranium oxide storage area. The uranium oxide storage rack holds up to [Proprietary Information][Security-Related Information]uranium oxide storage cans in a criticality-safe configuration. Refer to Subsection 4b.4.2 for additional SNM storage information.
Areas and vessels that contain SNM are appr opriately shielded to limit exposure to facility personnel. Refer to Section 4b.2 for more information on the RPF biological shield.9b.2.7CRITICALITY CONTROLInadvertent criticality during processing of fiss ile materials is prevented by double-contingency, criticality-safe design of cans, racks, tanks, and other components that handle or store the fissile material. The Nuclear Criticality Safety Program is discussed in 6b.3.
Chapter9 -Auxiliary SystemsFire Protection Systems and ProgramsSHINE Medical Technologies9b-6Rev. 09b.3FIRE PROTECTION SYSTEMS AND PROGRAMSThe facility fire protection system and program for the SHINE facility are common to the IF and the RPF and are discussed in Section 9a2.3.
Chapter9 -Auxiliary SystemsCommunication SystemsSHINE Medical Technologies9b-7Rev. 09b.4COMMUNICATION SYSTEMSThe communication systems for the SHINE facility are common to the IF and RPF. See Section9a2.4 for the description of the SHINE facility communication systems.
Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-8Rev. 09b.5POSSESSION AND USE OF BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIALThis section covers the possession and use of byproduct, source, and special nuclear material in auxiliary systems inside the RPF. The possession and use of byproduct, source, and special nuclear material within the IF is found in Section 9a2.5.9b.5.1BYPRODUCT MATERIAL Within the SHINE facility, byproduct material is generated by the fission and irradiation of target solution in the TSV. Byproduct material is regulated under 10 CFR Part 30.
The auxiliary systems that process byproduct material in the RPF are:*Target Solution Preparation System (TSPS).*Radioactive Drain System (RDS).*Aqueous Radioactive Liquid Waste Storage System (RLWS).*Radioactive Liquid Waste Immobilization System (RLWE).*Process Vessel Vent System (PVVS).
- Molybdenum Isotope Product Packaging System (MIPS).*Solid Radioactive Waste Packaging (SRWP).*Noble Gas Removal System (NGRS).9b.5.1.1Target Solution Preparation System The recycled uranium, which has been through the UNCS system, contains trace quantities of byproduct material, chiefly technetium and neptunium. This is present in the uranium oxide storage racks and the uranyl sulfate preparation tanks. The radionuclides are not present in quantities that cause a dose hazard to facility workers or the public. Local area monitors confirm the absence of hazardous radiation fields, and alert operators if allowable fields are exceeded. The uranium oxide storage racks are located in the uranyl sulfate storage room. The uranyl sulfate preparation tanks are located in the uranyl sulfate preparation area. Both of these are inside the RCA. The uranyl sulfate preparation tanks are accessible via a glovebox.9b.5.1.2Radioactive Drain SystemThis system is further described in Subsection 9b.7.6. The RDS is a network of sumps and pipes that converge at the criticality safe sump catch tank, located at the lowest point of the facility. The RDS receives byproduct material in the event of a leak of a tank or pipe containing byproduct material, or the overflow of a tank containing byproduct material. These are events that are not anticipated to occur frequently. They only result from a mechanical or control system failure.
Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-9Rev. 0The RDS piping and equipment is located within shielded tank vaults, hot cells, and pipe trenches in order to reduce worker radiation expo sure. The RDS exists to contain radioactive liquids in the event of a leak, spill, or overflow, and to route the liquid to a controlled location such that the material can be returned to the process.
The quantity, and chemical and radiological composition of byproduct material in the RDS depends on the location in the process that the leak, spill, or overflow occurs. The highest concentration of radionuclides is present in the target solution at the end of irradiation in the TSV.The byproduct material is collected in the criticality-safe sump catch tank and pumped to the uranyl nitrate conversion tank for use in the process.
The RDS sump catch tank is equipped with radiation monitoring and level instrumentation to detect the presence of material in the system. 9b.5.1.3Aqueous Radioactive Liquid Waste Storage This system is further described in Subsection 9b.7.4. The RLWS provides receipt, mixing, and buffer storage for aqueous radioactive wastes generated by processing operations within the RCA. The primary feed to the RLWS is raffinate from the UREX section of the UNCS system.
This contains the majority of byproduct material within the facility; specifically, the fission products generated in the TSV. Each of the two RLWS storage tanks can hold a maximum of 21TSV batches of UREX raffinate. The two RLWS liquid waste storage tanks are locat ed in shielded tank vaults to reduce worker exposure to radiation. The tanks normally contain byproduct material, and have a relatively high radiation field. The tank vaults contain radiation monitoring instrumentation, which detect elevated levels of radiation and alert operators. The liquid waste in the RLWS is fed to the RLWE for treatment prior to disposal.9b.5.1.4Radioactive Liquid Waste Evaporation and Immobilization SystemThis system is further described in Subsection 9b.7.3. The RLWE concentrates and immobilizes aqueous radioactive wastes generated by proce ssing operations within the RCA. As such, it processes, for disposal, the majority of the byproduct material within the facility. The RLWE system is located in hot cells, with normal operations being conducted remotely. The hot cells are shielded to reduce worker exposure to radiation.Within the RLWE, the radioactive waste is first concentrated by evaporation. The evaporator is a submerged-tube, forced-recirculation design. This is the configuration most frequently used for radioactive waste evaporation. The waste is evaporated to the extent possible while enabling it to be immobilized and disposed of as Class C waste. The condensed overheads stream may contain trace quantities of byproduct material. The le vel of byproduct material present is verified before the overheads are recycled for use within the process. The evaporator bottoms product, containing most of the byproduct material, is pumped to the immobilization system. It is pumped into 55 gal. (208.2 L) drums, which have been pre-loaded with grouting materials (Portland cement, blast furnace slag, and calcium hydroxide or other components as required to meet the receiving facilities' waste acceptance criteria). The filled drum is then sealed with a lid and mixed via mechanical means. This mixes the liquid waste and Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-10Rev. 0grouting solids. The drum is then moved to the curing area in the hot cell, to allow the cement to cure and form a monolithic solid waste form, suitable for final disposal.The drums containing cured, grouted waste are moved to the waste staging and shipping building, outside of the production facility building. From here they are exported to a radioactive waste disposal site.The RLWE hot cells are equipped with radiation detection instrumentation to monitor radiation fields within the cells. If elevated levels are detected, the operators are alerted. The design of the hot cells also includes liquid sumps with level instrumentation, radiation area monitors (RAMs),
and CAMs. These detect leaks or spills of byproduct material within the hot cells and alert the operators.9b.5.1.5Process Vessel Vent SystemThis system is further described in Subsection 9b.6.1. The PVVS is not anticipated to contain significant quantities of byproduct materials. The PVVS receives vent gases from the majority of the process tanks, plus the vent gas from the noble gas removal system (NGRS). The gas from the NGRS has been stored for decay for at least 40 days, so the majority of byproduct material, specifically short-lived isotopes of noble gases, has decayed to stable isotopes.The vents from process tanks are not anticipated to contain substantial quantities of byproduct material. The only process step that employs gas sparging for mixing and mass transfer is
thermal denitration. The byproduct material present in this step is insignificant. Some process tanks include pumped recirculation loops for mixing, so there is some entrainment of liquids in the tank vent. This includes byproduct material s that are present in liquid contained in the tank. The PVVS is located within an area in the RCA that is not occupied during normal operations. This area includes the necessary shielding to reduce worker exposure to radiation. The PVVS area is equipped with RAMs, CAMs, and leak detection equipment. The PVVS process includes an acid gas scrubber that uses a caustic solution (sodium hydroxide) to remove acid gases from process tank vent streams. The acids are primarily sulfuric acid and nitric acid, one or both of which are present in the majority of process tanks. In addition to neutralizing and removing the acid gases, the scrubber also removes the majority of the byproduct material from the gas stream by mass transfer. The byproduct material then leaves the PVVS in the spent scrubber solution. This is transferred to the RLWS system and then evaporated and immobilized in the RLWE system.9b.5.1.6Molybdenum Isotope Packaging SystemThis system is further described in Subsection 9b.7.1. The MIPS loads the molybdenum-99 (Mo-99) into the final product packaging, for shipment. The primary byproduct material in the MIPS is Mo-99. The Mo-99 product contains trace quantities of other byproduct radionuclides.
These concentrations of contaminants are measured by sampling and analysis to ensure they are below the maximum allowable concentrations.
Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-11Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]The MIPS is located inside a shielded hot cell, with all operations performed remotely, using manipulators. This reduces the dose to the worker from the byproduct material. When the Mo-99 product has been loaded into its product bottle, the bottle is loaded into a shielded shipping container before the material leaves the MIPS hot cell. The cell design includes radiation detection instrumentation to monitor radiation fields. If elevated levels are detected, the operators are alerted.9b.5.1.7Solid Radioactive Waste PackagingThis system is further described in Subsection 9b.7.5. The SRWP system packages solid waste generated by processing and mechanical handling operations within the RCA. The SRWP receives and handles solid waste that is contaminated with byproduct material. The majority of SRWP operations are performed in hot cells. The operations are performed remotely, using manipulators. The hot cells are shielded to reduce worker radiation exposure. The hot cell design includes radiation detection instrumentation to monitor radiation fields. If elevated levels are detected, the operators are alerted.Some SRWP operations are performed in normally occupied areas. One example of this is spent NDAS disassembly and packaging. The specific byproduct material that is present in the SRWP depends on the source of the solid waste being packaged. The highest levels of radionuc lides that are anticipated to be present on solid waste are associated with equipment that is us ed to process, or has been in contact with, irradiated target solution. This may be scrap e quipment, such as pumps, or spent processing equipment that is generated by routine operations, such as spent [Proprietary Information] adsorption columns from the MEPS system.9b.5.1.8Noble Gas Removal SystemThis system is further described in Subsection 9b.6.2. The NGRS monitors, stores, and releases radioactive isotopes of iodine and noble gases (primarily xenon and krypton) that are received from the TSV off-gas system (TOGS) after an irradiation cycle. The gases are byproduct material resulting form the fissioning of the target solution in the TSV. These gases are circulated in a closed loop in TOGS and the subcritical assembly system (SCAS) during the irradiation cycle, and are purged to NGRS following shutdown of the neutron driver and a hold time for decay in the TOGS and SCAS.The NGRS collects this byproduct material from the eight irradiation units, compresses the gas into noble gas decay tanks to allow for further decay, and after verification of acceptable radioactivity levels, releases the gases to PVVS.
The NGRS compressors and tanks are located in the noble gas shielded cell, which is not occupied during normal operations. The noble gas shielded cell provides the necessary shielding to reduce worker exposure to radiation.
Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-12Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390
][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9b.5.2SOURCE MATERIALSource material is defined as natural uranium or t horium or depleted uranium that is not suitable for use as reactor fuel, per 10 CFR 40. There is none of this material normally present in the RPF auxiliary systems.[Proprietary Information]
9b.5.3SPECIAL NUCLEAR MATERIALSNM is defined as Pu, U-233, or uranium enriched in the isotopes U-233 or U-235. Within the SHINE facility, LEU is irradiated to produce Mo
-99 by fission. During this process, a small quantity of Pu is also generated. This is less than [Proprietary Information][Security-Related Information] total Pu per TSV batch. The auxiliary systems in the RPF that are anticipated to contain more than trace quantities of SNM are:*Target Solution Preparation System (TSPS).*Radioactive Drain System (RDS).*Aqueous Radioactive Liquid Waste Storage System (RLWS).*Radioactive Liquid Waste Immobilization System (RLWE).
- Solid Radioactive Waste Packaging (SRWP).9b.5.3.1Target Solution Preparation SystemThe following process equipment in the TSPS contains LEU:*The uranium metal dissolution tank.*The target solution hold tank.*The uranium metal storage rack.
- The uranium oxide storage racks.*The uranyl sulfate preparation tank.Equipment containing the SNM is criticality-safe by geometry. The target solution hold tank is located in a shielded tank vault. This is required because of the concentration of fission products in the recycled target solution rather than the presence of SNM.
The UO3 storage racks are located in the uranyl sulfate storage room. The uranyl sulfate preparation tanks are located in the uranyl sulfate preparation area. Both of these are inside the RCA. The uranyl sulfate preparation t anks are located inside a fume hood.
Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-13Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390
][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9b.5.3.2Radioactive Drain SystemThe RDS is a network of sumps and pipes that converge at the criticality-safe sump catch tank, located at the lowest point of the facility. The RDS receives SNM in the event of a leak of a tank or pipe containing SNM, or the overflow of a tank containing SNM. These are events that are not anticipated to occur frequently, and would represent a mechanical or control system failure.The RDS piping and equipment is located within shielded tank vaults, hot cells, and pipe trenches, in order to reduce worker radiation exposure. Due to the potential for LEU to be present in the RDS, the system is criticality safe by geometry throughout. The RDS contains radioactive liquids in the event of a leak, spill, or overflow, and routes the liquid to a controlled location such that the material can be returned to the process. This also applies to SNM, which can be returned to the process from the RDS in the event of a leak, spill, or overflow.The quantity and composition of SNM in the RDS depends on the location in the process that the leak, spill, or overflow occurred. The [Security-Related Information]. At this point, the LEU concentration is [Security-Related Information]. Within the target solution, the maximum concentration of SNM is [Proprietary Information][Security-Related Information].The SNM is collected in the criticality-safe sump catch tank.9b.5.3.3Aqueous Radioactive Liquid Waste Storage The RLWS provides receipt, mixing, and buffer storage for aqueous radioactive wastes generated by processing operations within the RCA. The primary feed to the RLWS is raffinate from the UREX section of the UNCS.There is an insignificant quantity of LEU in the RLWS. The UREX raffinate is analyzed to verify LEU levels are within limits prior to transfer from the UNCS to the RLWS. The RWLS contents will be administratively controlled to ensure criticality-safety. The Pu generated in the TSV does pass through the RLWS. The maximum inventory of Pu in each of the liquid waste storage tanks in the RLWS is less than [Security-Related Information].The two RLWS liquid waste storage tanks are locat ed in shielded tank vaults to reduce worker exposure to radiation. This is required due to th e presence of fission products rather than SNM.9b.5.3.4Radioactive Liquid Waste Evaporation and ImmobilizationThe RLWE concentrates and immobilizes aqueous radioactive wastes generated by processing operations within the RCA. There is not a significant quantity of LEU in the RLWE. There are no criticality controls required or implemented in the RLWE. There is a small quantity of Pu within the RLWE. The maximum inventory of Pu in the RLWE is less than [Security-Related Information]. The RLWE system is located in hot cells, with normal operations being conducted remotely. The hot cells are shielded to reduce worker exposure to radiation. This is due to the presence of fission products rather than SNM.
Within the RLWE, the radioactive waste is firs t concentrated by evaporation. The waste is evaporated to the extent possible while enabling it to be immobilized and disposed of as Class C waste. The condensed overheads from the evaporator are ostensibly free of SNM. This is verified before the overheads are recycled for use within the process.
Possession and Use of Byproduct, Source,Chapter9 -Auxiliary Systemsand Special Nuclear MaterialSHINE Medical Technologies9b-14Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390
][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]The evaporator bottoms product, containing essentially all of the SNM, is pumped to the immobilization system. Here it is converted into a monolithic solid waste form suitable for final disposal.The RLWE hot cells are equipped with RAMs and CAMs to monitor radiation fields within the cells. If elevated levels are detected, the operators are alerted. The design of the hot cells also includes liquid sumps with level instrumentation. These detect leaks or spills within the hot cells and alert the operators.9b.5.3.5Solid Radioactive Waste Packaging The SRWP system packages solid waste generated by processing and mechanical handling operations within the RCA. The SRWP receives and handles solid waste that may be contaminated with SNM. The majority of SRWP operations are performed in hot cells, which are not normally occupied. The operations are performed remotely, using manipulators. The hot cells are shielded to reduce worker radiation exposure. This is due to the presence of fission products, rather than SNM. The hot cell design includes CAMs and RAMS to monitor radiation fields. If elevated levels are detected, the operators are alerted.Some SRWP operations are performed in normally occupied areas. One example of this is spent NDAS disassembly and packaging.The specific SNM that is present in the SRWP depends on the source of the solid waste being packaged. This may be scrap equipment, such as pumps, or spent processing equipment that is generated by routine operations, such as spent [Proprietary Information] adsorption columns from the MEPS system.There is no processing of SNM in the SRWP. The presence of SNM is incidental to the operation of the system and the intent is to retain the SNM on the solid waste being packaged for disposal.9b.5.4TECHNICAL SPECIFICATIONSPotential variables, conditions, or other items that will be probable subjects of a technical specification associated with the possession and use of byproduct, source, and SNM are provided in Chapter 14.
Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-15Rev. 19b.6COVER GAS CONTROL IN CLOSED PRIMARY COOLANT SYSTEMSThere are no primary coolant systems in the RP F. This section will discuss systems that handle radioactive gases from process vessels.9b.6.1PROCESS VESSEL VENT SYSTEM9b.6.1.1Process Description9b.6.1.1.1Process Functions
The PVVS collects and treats the off-gases from process vessels in the SHINE facility. The PVVS collects off-gases from each vented vessel containing a significant quantity of radioactive material in the RPF, and receives noble gases from the NGRS after a period of decay. The PVVS consists of an acid gas scrubber loop and a blower to vent treated gases out of the RCA.
The process functions for the PVVS are the following:*Receive off-gas from the process systems within the RPF.*Treat off-gas to remove excess acids.
- Transfer treated off-gas to the RVZ1 exhaust system.*Maintain process vessels at a negative pressure for confinement.*Prevent detonations or deflagrations in process vessels from potential hydrogen accumulation.9b.6.1.1.2Safety FunctionsPVVS preliminary safety functions and classifications:
- Prevent detonation or deflagration of radiolytic hydrogen gas by maintaining the hydrogen concentration below the LFL. Classification: SR.
- Capture noble gases from process vessel vents. Classification: SR9b.6.1.1.3Primary System Interfaces Vented process vessels within the RPF that contain significant quantities of radioactive material are connected to the PVVS, which exhausts the off-gas from the tank ullage. For a list of system interfaces, refer to Table 9b.6-1. The stream numbers referred to in the interface descriptions can be found in Figure 9b.6-1.9b.6.1.1.4Process SequenceThe PVVS receives off-gas from vented process vessels in the RPF. The majority of process vessels contain sulfuric acid or nitric acid solutions, and the off-gas is assumed to entrain some of these acids. A blower maintains the tank ullage at a slight negative pressure and draws all the off-gas through an acid-gas scrubber. The scrubber is a packed column with countercurrent flow: the off-gas in up-flow and a 1 M sodium hydroxide caustic scrub solution in gravity down-flow.
The caustic scrub solution neutralizes the acids present in the off-gas, and is recycled through the scrubber until it is spent and requires replacing. A heat exchanger, cooled with process Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-16Rev. 1 chilled water, removes the acid-base heat of reaction, heat introduced by the pump, and the excess heat from any high-temperature off-gases.Off-gas is provided to the PVVS intermittently in varying quantities depending on what processes are occurring in the RCA at any given moment. The caustic scrub solution flow rate is set to process the maximum quantity of off-gas that may enter the scrubber at any one time. The caustic scrub solution is periodically purged from the acid-gas scrubber loop when it no longer neutralizes the acid off-gas, as measured by a pH meter located in the acid-gas scrubber loop.
Radioactive particles potentially entrained in the process off-gas are either absorbed in caustic scrub solution in the acid-gas scrubber, or are vented out of the PVVS. Treated off-gas is vented to the RVZ1 where, following HEPA and charcoal filtration, the gas is exhausted out the facility stack. Spent caustic scrub solution is pumped to the RLWS system for waste treatment. Fresh caustic scrub solution is supplied by the facility alkaline reagent storage and distribution system (FLRS), located outside the RCA.See Figure 9b.6-1 for the PFD of the PVVS. Refer to Table 9b.6-2 for a description of the process equipment.9b.6.1.1.5Hydrogen MitigationHydrogen may be generated by radiolysis in the target solution or uranyl nitrate solution contained in various process vessels downstrea m of the IU. The hydrogen may cause detonations or deflagrations if the concentration reaches the lower flammability limit (LFL) of 4 volume percent. PVVS is a SR system to prevent hydrogen detonation or deflagration in the process vessels.PVVS maintains low hydrogen concentrations in the ullage of process tanks by diluting the evolved gases. Vents located above the overflow lines of tanks provide an inlet for air to sweep the tank ullage and dilute any hydrogen that is present. The required sweep rate for each process tank will be determined in detailed design based on hydrogen generation rate calculations and, if necessary, hydrogen monitors will be installed.In the case of loss of off-site power (LOOP), the PVVS blower is connected to a UPS. There are redundant blowers connected to separate UPS systems. A differential pressure switch across the blower indicates whether or not the blower is operating properly. The PVVS blower continues to operate even if the RVZ1 exhaust system is no longer functioning.The current design of the UPSS provides for a two hour duration of Class 1E power following LOOP. The effects of post-shutdown hydrogen generation have not been fully determined. Final hydrogen generation rates and associated mission time for the emergency power system will be determined as part of final design. Design studies are on-going to establish design features that could be used for maintaining st able long-term post-accident co nditions assuming that the off-site power is not available. These potential design features include:*Passive hydrogen recombiners*On-site safety-related emergency diesel generators
- Robust piping systems*Deflagration flame arrestors Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-17Rev. 0*Other potential design features identified during the detailed designThe emergency power system will operate for the required mission time as delineated in the final analysis which will be provided in the FSAR. 9b.6.1.1.6Noble Gas CaptureThe systems and processes in the RPF have the potential to release noble gas radioisotopes from the target solution or uranyl nitrate solution, especially xenon and krypton. The final design will ensure that 10 CFR 20 limits are met.9b.6.1.1.7Instrumentation and Control The PVVS includes differential pressure instrumentation to ensure normal operation of the blower. The PVVS instrumentation is tested periodically.
Pressure instrumentation in PVVS monitors the differential pressure across the blower and switches to the redundant blower if one fails to operate properly. The normal operating range of the PVVS blower pressure will be determined in detailed design. See the detailed alarm description in Subsection 7b.4.1.2.6.9b.6.1.2Radiological Protection and Criticality Control There is no significant amount of SNM present in the PVVS. As such, the vessels and equipment in the PVVS are not designed for criticality safety. PVVS processes are normally
remotely controlled. Occasional manual maintenance operations are required. Shielding of PVVS ensures that exposure of individuals to radiation is within the regulatory limits of 10 CFR 20.1201 and 10CFR20.1301. Radiation monitors and alarms are used to monitor the potential
release of radiological materials.9b.6.1.3Technical Specifications Potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the process vessel vent system are provided in Chapter 14.9b.6.2NOBLE GAS REMOVAL SYSTEM9b.6.2.1Process DescriptionThe NGRS receives the cover gas from the eight independent TOGS. This gas is primarily air, with small gram quantities of krypton, xenon, and iodine. The gases are compressed up to 100psig (680kPa), then stored in one of five noble gas decay tanks for at least 40 days. This enables the noble gases to largely decay. The stored gases can then be vented to the RCA
ventilation Zone 1 (RVZ1).There is no significant quantity of SNM within the NGRS system. Therefore, no criticality controls or safeguards are required.
Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-18Rev. 19b.6.2.1.1Process FunctionsThe NGRS monitors, stores, and releases the radioactive isotopes of iodine and noble gases (primarily krypton and xenon) that are received from the TSV off-gas system (TOGS) following an irradiation cycle. Radioactive gases are generated and released from the target solution in the TSV during irradiation. The NGRS collects the off-gas from the TSV after irradiation is complete, and holds the gases in order to allow the short-lived noble gas radioisotopes to decay prior to release of the off-gas to the PVVS. The radiation level in the decayed gases is verified with radiation monitors prior to release.
The process functions for the NGRS are the following:
- Store TSV off-gas to allow for noble gas radioactive decay.
- Release decayed off-gas to PVVS.
- Monitor off-gas releases to ensure radioactivity levels are below regulatory limits for discharge to the environment.9b.6.2.1.2Safety FunctionsNGRS preliminary safety functions and classifications:
- Prevent the release of radioactive material to the environment beyond the applicable regulatory limits. Classification: SR
.*Limit the exposure of the worker, public, and environment to radioactive material.
Classification: SR
.*Contain and store noble gases (primarily xenon and krypton) generated in the TSV for at least 40 days. Classification: SR.9b.6.2.1.3Primary System InterfacesRefer to Table 9b.6-3 for a list of system interfaces. The stream numbers referred to in the interface descriptions can be found in Figure 9b.6-2.9b.6.2.1.4Process Sequence The NGRS consists of two gas compressors, five noble gas decay tanks, a condensate knock-out tank, associated piping components, and monitoring instrumentation. After a TSV completes an irradiation cycle, a mixture of gases is present in the TOGS loop, mainly air sweep gas with small amounts of radioactive gaseous isotopes including iodine, krypton, and xenon. Hydrogen is also present, and the TOGS catalytic recombiner maintains the hydrogen concentration below the LFL. Refer to Subsection 4a2.8 for more detail regarding the TOGS.The TOGS transfers the TSV off-gas to the NGRS, where a compressor stores the off-gas in decay tanks. Prior to transfer to the NGRS, hydrogen sensors in the TOGS ensure hydrogen concentration is below the acceptable limit. The NGRS uses five noble gas decay tanks to provide temporary storage of TSV off-gas containing radioactive noble gases. The tanks allow for the decay of short-lived noble gas radioisotopes, including xenon-133, which is an isotope of concern for nuclear non-proliferation monitoring. The tanks are sized to store the TSV off-gas for Cover Gas Control in ClosedChapter9 -Auxiliary SystemsPrimary Coolant SystemsSHINE Medical Technologies9b-19Rev. 0[Security-Related Information - Withhold Under 10 CFR 2.390][Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]
approximately 40 days post-irradiation to allow the noble gas radioisotopes to decay to within applicable regulatory limits for discharge to the env ironment. The decay tanks are rated pressure vessels, with an approximate working volume of [Proprietary Information][Security-Related Information]. The off-gas in the decay tanks is compressed to approximately [Proprietary Information][Security-Related Information]. The decay tanks are filled and emptied sequentially to allow for continued operation of the IUs. The NGRS is designed to provide redundancy and storage capacity to process anticipated T SV off-gas volumes due to equipment downtime and maintenance activities. The NGRS design is in compliance with ANSI/ANS-55.4 (ANSI/ANS, 1993).Upon completion of 40 days of decay, the off-gas is processed through a condensate knock-out tank, analyzed for radioactivity, and released to the PVVS. In the PVVS, the off-gas is mixed with other exhaust gases, treated further, and released to the environment via the facility stack. Refer to Subsection 9b.6.1 for more detail regarding the PVVS. The condensate is mainly water from the off-gas, and is routed to the RLWS system for further processing. Refer to Subsection 9b.7.4 for more detail regarding the RLWS system. If the off-gas has not sufficiently decayed, it is recycled back to the NGRS compressor and stored again in a noble gas decay tank.See Figure 9b.6-2 for the PFD of the NGRS. Refer to Table 9b.6-4 for a description of the process equipment.9b.6.2.1.5Instrumentation and ControlNGRS includes pressure and radioactivity instrumentation on the noble gas decay tanks. These instruments monitor the tanks to ensure no gas is leaking as evidenced by a pressure drop, and determine the level of radioactive decay. Radioactivity monitors are also located downstream of the condensate knock-out tank. If the off-gas is released from a decay tank and does not meet regulatory limits, it is recycled back to the compressor to be stored in a decay tank again.9b.6.2.2Safety-Related Effects9b.6.2.2.1Radiological Protection and Criticality Control
There is no significant amount of SNM pres ent in the NGRS. As such, criticality-safety requirements are not required for vessels or equipment in the NGRS. The NGRS is located in a shielded cell, which limits the exposure of individuals to radiation within the regulatory limits of 10 CFR 20. The processes are remotely controlled, manually controlled, or performed with telemanipulators, with minimal automated sequences. Radiation monitors and alarms are used to monitor release of radiological materials, monitor high background gamma dose levels, and to detect criticality events.Gases and liquids that contain potentially-radiological material are transferred through shielded pipe chases to limit the exposure of individuals to radiation.
Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-20Rev. 09b.6.2.3Technical SpecificationsPotential variables, conditions, or other items that will be probable subjects of a technical specification associated with the noble gas removal system are provided in Chapter 14.
Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-21Rev. 0 Table 9b.6-1 PVVS InterfacesInterfacing SystemInterface DescriptionTarget Solution Preparation System (TSPS)The PVVS interfaces with the TSPS at three locations: the vent lines from the uranyl sulfate preparation tank (1-TSPS-01T), the uranium metal dissolution tank (1-TSPS-02T), and the target solution hold tank (1-TSPS-03T).
Molybdenum-99 Extraction and Purification System (MEPS)The PVVS interfaces with the MEPS at one location: the vent line from the Mo eluate hold tank (1-MEPS-02T).
Uranyl Nitrate Preparation (UNP) subsystem of the UNCSThe PVVS interfaces with the UNP subsystem at three locations: the vent lines from the uranyl nitrate conversion tank (1-UNCS-01T), the UREX feed tank (1-UNCS-02T), and the recycle target solution tank (1-UNCS-09T).
Uranium Extraction (UREX) subsystem of the UNCSThe PVVS interfaces with the UREX subsystem at three locations: the vent lines from the solvent hold tank (1-UNCS-04T),
the raffinate hold tank (1-UNCS-05T), and the recycle uranyl nitrate (UN) hold tank (1-UNCS-06T).Thermal Denitration (TDN) subsystem of the UNCSThe PVVS interfaces with the TDN subsystem at one location: the vent line from the thermal denitrator (1-UNCS-08T), downstream of the thermal denitrator overheads cooler (1-UNCS-04A).
Noble Gas Removal System (NGRS)The PVVS interfaces with the NGRS at one location: the discharge line from the noble gas condensate knockout tank (1-NGRS-02T), downstream of the radiation monitor and recycle loop back to the noble gas compressor (1-NGRS-01C).
Radioactive Liquid Waste Evaporation and Immobilization (RLWE)The PVVS interfaces with the RLWE at two locations: the vent lines from the liquid waste condensate collection tank (1-RLWE-01T) and the liquid radioactive waste collection tank (1-RLWE-02T).RCA Ventilation Zone 1 The PVVS interfaces with the RVZ1 at one location: the discharge line from the process vent gas blower (1-PVVS-01C).
Radioactive Liquid Waste Storage (RLWS)The PVVS interfaces with the RLWS at two locations: the bottoms discharge from the PVVS acid-gas scrubber loop (stream 0926) and the vessel vent from the liquid waste storage tank (1-RLWS-01T-A/B).Facility Alkaline Reagent Storage and Distribution System (FLRS)The PVVS interfaces with the FLRS at one location: the supply line providing caustic to the acid-g as scrubber loop (stream 0924).Radioisotope Process Facility Cooling System (RPCS)The PVVS interfaces with the RPCS at two locations: the process chilled water supply and the process chilled water return. Process chilled water is supplied to the acid gas scrubber cooler (1-PVVS-01A).Normal Electrical Power Supply System (NPSS)The PVVS interfaces with the NPSS. The NPSS is distributed to operate the process vent gas blower (1-PVVS-01C), acid gas scrubber pump (1-PVVS-01P), and ancillary equipment.Uninterruptible Power Supply System (UPSS)The PVVS interfaces with the UPSS at one location: the process vent gas blower (1-PVVS-01C) is on UPS power.
Radiological Integrated Control System (RICS)The RICS controls the PVVS.
Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-22Rev. 0Table 9b.6-2 PVVS Process EquipmentComponentDescriptionCode/Standard1-PVVS-01DAcid Gas Scrubber. Packed column contacts off-gas with caustic scrub solution to neutralize acids, knock out entrained particulate, and remove any excess heat. ASME BPVC Section VIII1-PVVS-01AAcid Gas Scrubber Cooler. Heat exchanger transfers heat from caustic
scrub solution in acid-gas scrubber loop to the RPCS. Plate and frame type.ASME BPVC Section VIII1-PVVS-01CProcess Vent Gas Blower. Draws off-gas from process vessels and
through the acid-gas scrubber, then exhausts off-gas to RCA Ventilation Zone 1. Redundant blowers connected
to UPSS.ASME AG-1, Section BA - Fans and Blowers1-PVVS-01PAcid Gas Scrubber Pump. Circulates caustic scrubber solution through the acid-gas scrubber loop, and transfers spent caustic scrubber solution to RLWS.ANSI/HI 3.1-3.5Piping ComponentsPVVS piping, valves, in-line components.ASME B31.3 Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-23Rev. 0 Table 9b.6-3 NGRS InterfacesInterfacing SystemInterface Description TSV Off-Gas System (TOGS)The NGRS interfaces with the TOGS at one location: the isolation valve on stream 0428 between the TSV off-gas blower (1-TOGS-01C) and the noble gas compressor (1-NGRS-01C).Process Vessel Vent System (PVVS)
The NGRS interfaces with the PVVS at one location: the discharge line from the noble gas condensate knockout tank (1-NGRS-01T), downstream of the radiation monitor and recycle loop back to the noble gas compressor (1-NGRS-01C).
Radioactive Liquid Waste Storage (RLWS)The NGRS interfaces with the RLWS at one location: the condensate drain line (stream 0432) from the noble gas
condensate knock-out tank (1-NGRS-01T).Radioactive Drain System (RDS)The NGRS interfaces with the RDS at one location: the drain line penetrations for the NGRS hot cell. The drain lines are sloped to the criticality-safe sump catch tank.Radiological Integrated Control System (RICS)The RICS controls the NGRS.
Normal Electrical Power Supply System (NPSS)The NGRS interfaces with the NPSS. The NPSS is distributed to operate the noble gas compre ssor (1-NGRS-01C) and ancillary equipment/instrumentation.
Cover Gas Control in ClosedChapter9 -Auxiliary Systems Primary Coolant SystemsSHINE Medical Technologies9b-24Rev. 0Table 9b.6-4 NGRS Process EquipmentComponentDescriptionCode/Standard1-NGRS-01C-A/BNoble Gas Compressor. Compresses off-gas into decay tanks for storage. Backup compressor maintained on standby. Water seal or metal diaphragm compressor to eliminate gas leakage.
API Standard 6171-NGRS-01V-A-ENoble Gas Decay Tank. Pressure vessel that stores compressed off-gas to allow decay of noble gas radioisotopes.
Multiple tanks allow for filling, discharge, and storage simultaneously.
ASME BPVC Section VIII1-NGRS-01TNoble Gas Condensate Knock-Out Tank. Remove moisture from gas stream released from decay tanks.
ASME BPVC Section VIIIPiping ComponentsNGRS piping, valves, in-line components.
ASME B31.3 Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-25Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9b.7OTHER AUXILIARY SYSTEMSThis section describes auxiliary systems in the RPF not captured in other chapters of the PSAR.9b.7.1MOLYBDENUM ISOTOPE PRODUCT PACKAGING SYSTEMThe molybdenum isotope product packaging system (MIPS) receives the Mo-99 product collection bottle from the MEPS. Once in the MIPS area of the supercell, the product goes through an assay and quality control procedure. The final Mo-99 product is then transferred to the Mo-99 product shipping container. The lot number and expiration date on the Mo-99 final product shipping container is recorded and the final product shipping container is transferred into the shipping casks for delivery.The MIPS is located in each of three supercells dedicated to the extraction, purification, and packaging of the Mo-99 product. The supercell provides the appropriate shielding to limit personnel radiation exposure. The radiological in tegrated control system (RICS) provides the process monitoring and control of the MIPS (see Section 7b.2.3). Figure s 9b.7-1 and 9b.7-2 show the physical layout of the MIPS equipment within the supercell.9b.7.1.1Molybdenum-99 Receipt The Mo-99 product collection bottle is received from the MEPS through the shielded pass-through between the two systems. The Mo-99 product collection bottle contains purified Mo-99 solution. The Mo-99 packaging area of the supercells has the capability of holding up to [Proprietary Information] TSVs worth of Mo-99 product.9b.7.1.2Molybdenum-99 Assay After receipt of the Mo-99 product from MEPS, a product sample is sent through the quality control process to ensure the produc t meets customer specifications. 9b.7.1.3Molybdenum-99 PackagingOnce the quality control process is complete, the Mo-99 product is removed from the Mo-99 product collection bottle and placed in an inner Mo-99 product shipping container. The inner shipping containers meet customer requirements.The inner shipping containers are expected to be labeled with lot number, date, and bar code for recording, identification, and tracking purposes.9b.7.1.4Molybdenum-99 TransferThe Mo-99 inner product shipping containers are transferred to approved shipping containers for delivery.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-26Rev. 09b.7.1.5Process Functions*Receive Mo-99 from MEPS.*Perform Mo-99 assay.
- Package Mo-99 for shipment.9b.7.1.6Safety Functions This system is nonsafety-related. 9b.7.1.7Criticality Control FeaturesThere is no SNM within the system.
9b.7.1.8Shielding and Radiological Protection The MIPS are located in shielded hot cells. This limits the radiation exposure of individuals to within the regulatory limits of 10 CFR 20. Refer to Chapter 11 for the radiation exposure goals, and Section 4b.2 for further detail of shielding requirements. Internal local shielding will be
added for protection of inte rnal equipment as necessary.9b.7.1.9Technical SpecificationsThere are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the MIPS.9b.7.2RCA MATERIAL HANDLINGThe RCA material handling system (RMHS) includes overhead cranes, fork trucks, hand trucks, carts, and master-slave manipulators that are used to move or manipulate radioactive material within the RCA. The RICS provides the proce ss monitoring and control of the RMHS (See Section 7b.1). The equipment and locations of the equipment are discussed further in the
sections below.9b.7.2.1RCA Overhead Cranes The three overhead cranes in the RCA provide the necessary crane coverage to support operational and maintenance activities within the RCA. Crane locations and coverage are shown on Figure 9b.7-3. The overhead cranes meet the requirements of ASME B30.2 and CMAA 70.Overhead Crane OC-0001 has a 75-ton capacity and provides crane coverage over the IU cells and the TPS.
Overhead Crane OC-0002 has a 40-ton capacity and provides crane coverage over the tank farm and UREX hot cell (HC-0003), SRWP hot cell (HC-0004), RLWE evaporation hot cell (HC-0008) and RLWE immobilization hot cell (HC-0009) (see Figure 9b.7-4).Overhead Crane OC-0003 has a 40-ton capacity a nd provides crane coverage over the receipt area and supercells (HC-0001 and HC-0002).
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-27Rev. 09b.7.2.2RCA ForkliftA forklift is used in the RCA for manipulation of shielded waste casks, shipping containers, and other material handling needs.9b.7.2.3In-Cell Overhead HoistsThere are in-cell overhead hoists in each of the hot cells and the supercell areas listed below:
- Supercell molybdenum extraction area of MEPS.*Supercell molybdenum purification area of MEPS.*Supercell molybdenum packaging area of MIPS.
- UREX hot cell.*RLWE evaporation hot cell.
- RLWE immobilization hot cell.*SRWP hot cell.The in-cell overhead hoists are controlled remotely from outside the cells. The hoists are used to handle remotely operated tooling to replace failed equipment, as well as transport equipment between points in the cell. The in-cell overhead hoists meet the requirements of ASME B30.2.
The hoists perform only nonsafety-related functions.9b.7.2.4Hot Cell Master-Slave ManipulatorsThe hot cells and supercells are fitted with master-slave manipulators on the front of the cells. The location and quantity of the master-slave manipulators is given in Table 9b.7-1. The master-slave manipulators are used for process and maintenance activities. The master-slave manipulators are in accordance with the guidance provided by ASTM C1554-2011.9b.7.2.5DPTE Transfer Carts The hot cells and supercells are fitted with double doors for leaktight transfer (DPTE) systems. The DPTE systems are used for waste, material, and equipment transfer into and out of the cells.
The DPTE system requires a transfer cart for docking and transport of the DPTE drums. Each of the following cells and cell areas utilize a DPTE transfer system and require a DPTE transfer cart:*Supercell molybdenum extraction area of MEPS.*Supercell molybdenum purification area of MEPS.*Supercell molybdenum packaging area of MIPS.*UREX hot cell.
- RLWE evaporation hot cell.*RLWE immobilization hot cell.*SRWP hot cell.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-28Rev. 09b.7.2.6Uranium Metal/Oxide Material Transfer Cart The TSPS and TDN systems require a uranium metal/oxide material transfer cart. The transfer cart is used to transfer canned uranium metal from the uranium metal storage rack to the uranium metal dissolution tank and to transfer canned uranium oxide from the thermal denitrator to the uranium oxide storage rack. The uranium metal/oxide material transfer cart is designed to be criticality-safe.9b.7.2.7Safety FunctionsThe RMHS prevents inadvertent criticality through inherently safe design of equipment.9b.7.2.8Criticality Control Features
SNM handled by the RMHS meet the criticality sa fety limits of the material being handled.9b.7.3RADIOACTIVE LIQUID WASTE EVAPORATION AND IMMOBILIZATION SYSTEM9b.7.3.1RLWE Process DescriptionThis section applies to the RLWE. The primary purpose of the RLWE is to reduce the volume of radioactive liquid wastes generated by facility operations and convert them to a form suitable for shipping and disposal.9b.7.3.1.1System Process Functions The process functions of the RLWE system are:*Receive radioactive liquid waste from the RLWS system.*Reduce the volume of the liquid waste to the extent allowable to meet final waste criteria.*Convert the liquid waste to a form suitable for shipping and disposal as radioactive waste.9b.7.3.1.2Primary System InterfacesFor a list of system interfaces, refer to Table 9b.7-2.The RLWE system receives aqueous radioactive liquid waste from the RLWS tanks (1-RLWS-01T-A/B). The radioactive liquid waste is derived from operations within the RCA.
These are primarily routine process wastes, but also include liquid wa stes generated by non-routine operations such as equipment flushes, cell wash-down, and maintenance activities.The RLWE includes two primary operations:*Liquid waste evaporation.*Liquid waste immobilization.See Figure 9b.7-5 for the PFD of the radioactive liquid waste evaporation subsystem and Figure9b.7-6 for the PFD of the radioactive liquid waste immobilization subsystem.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-29Rev. 0The liquid waste evaporation step reduces the liquid waste volume to the extent allowable to meet final waste criteria. It is anticipated that plutonium concentration will be the limiting factor in the evaporation step, in order to ensure the immobilized waste is Class C or less. There may be instances where another material or isotope becomes the limiting factor for volume reduction.
The evaporator system includes monitoring and sampling capabilities to identify such occurrences and adjust operations accordingly.The evaporator is a submerged-tube, forced-circulation design. This is the most widely-used design for radioactive liquid waste evaporation. The high recirculation rate and submerged tubes in this design prevent boiling within the heater.
This reduces corrosion and fouling within the heater tubes compared to designs in which the boilin g occurs within the heater tubes. The high tube-side velocities further limit fouling. The submerged-tube, forced-recirculation design also provides a high degree of operational flexibility, as it is able to accommodate wide variability of
feed rates and compositions.The evaporator feed is supplied by the liquid waste evaporator feed pump (1-RLWE-01P-A/B). The feed is added to the liquid waste evaporator tank (1-RLWE-01D). This tank functions as the reservoir of aqueous waste for the evaporator and the vapor-liquid separator for the overheads and bottoms product. This tank is operated at nominally atmospheric pressure. For the anticipated evaporator feed composition, the temperature in this tank is approximately 220°F (104.4°C). This varies by a few degrees depending on the radioactive liquid waste feed composition.Liquid from the liquid waste evaporator tank (1-RLWE-01D) is pumped around the evaporator loop by the liquid waste evaporator recirculation pump (1-RLWE-02P-A/B). The pump-around rate of the evaporator loop is relatively high compared to the feed rate and bottoms product draw rate. The liquid is heated by 4-6°F (1.9-2.8°C) in the liquid waste evaporator heater (1-RLWE-01A). This is an electric al heater, with the current to t he heater controlled by pressure in the vapor space of the liquid waste evaporator tank (1-RLWE-01D). The low temperature rise
and the hydrostatic head of liquid above the hea ter tubes suppress boiling in the heater tubes. The super-saturated liquid from the heater recirculates back to the liquid waste evaporator tank (1-RLWE-01D), where it flashes to equilibrium.
The vapor rises in the liquid waste evaporator tank (1-RLWE-01D), passing through a demister, which removes entrained moisture droplets, then out to the liquid waste condenser (1-RLWE-02A). The liquid in the recirculation loop return falls to the bottom of the liquid waste evaporator tank (1-RLWE-01D).The overhead vapor from liquid waste evaporator tank (1-RLWE-01D) is condensed in the liquid waste condenser (1-RLWE-02A). This condenser is cooled by process chilled water from the RPF cooling system (RPCS). This water is supplied at approximately 60°F (15.6°C) and returned to the RPCS at approximately 75°F (
23.9°C). The condenser sub-cools the overheads vapor to approximately 100°F (37.8°C). The co ndensate drains to one of two liquid waste condensate collection tanks (1-RLWE-01T-A/B). These tanks are operated in an online/offline configuration. One tank is in filling mode, wh ile the other is being sampled and emptied. The condensate is sampled in the offline tank to ensure the radioactive contamination is below the level required for recycle and reuse within the facilit
- y. If the condensate does not meet the requirements for water recycle, it is pumped to the liquid waste collection tank (1-RLWS-01T-A/B) for re-processing through the evaporator.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-30Rev. 0The bottoms product from the evaporator is drawn off between the liquid waste evaporator recirculation pump (1-RLWE-02P-A/B) and the liquid waste evaporator heater (1-RLWE-01A). The bottoms product is cooled to approximately 100°F (37.8°C) in the liquid waste evaporator product cooler (1-RLWE-03A). The cooled bottom product is routed to one of two liquid
radioactive waste collection tanks (1-RLWE-02T-A/B). These tanks are operated in an online/offline configuration. One tank is in filling mode, while the other is being sampled and emptied.The evaporator bottoms product in the liquid radioactive waste collection tank (1-RLWE-02T-A/B) is pumped by the liquid waste pump (1-RLWE-04P A/B) to the immobilization system.The immobilization system mixes the bottoms product from the evaporator with a cement formula to produce a monolithic solid waste form that is suitable for shipping and disposal as radioactive waste.The waste is immobilized in standard 55 gal. drums. The solid grouting reagents are added to the drums in a filling station that is located outside the liquid waste solidification hot cell. This facilitates maintenance of this equipment in a clean environment. The solidification reagents typically are:*Ordinary Portland cement - to create the cementitious final product.*Blast furnace slag - to improve concrete durability.
- Calcium hydroxide - to raise the pH of the liquid waste to 7.0-7.5.The solidification reagents are added to the drum from dedicated hoppers: one hopper for each reagent. They are metered into the drum using rotary valves. Each reagent is added separately, such the quantity of each reagent is measured on the weigh scale (1-RLWE-01Z). Once a drum has been loaded with solidification reagents, it is moved into the liquid waste solidification hot cell. Here the evaporator bottoms product is pumped into the drum by the liquid waste pump (1-RLWE-04P-A/B). This is a positive displacement pump that allows close control of the liquid volume. The liquid is pumped through a line that is connected to the drum lid, to eliminate splashing of the waste and reduce contamination of the hot cell.Once the liquid has been added to the drum, it is sealed. The sealed drum is then mixed using a drum mixer. This rotates the drum through 360 degrees, ensuring thorough mixing of the grout components with the liquid waste.After mixing, the drum is moved from the mixer to a curing area. Once cured, the drum is ready for testing and transport to the waste staging and shipping building. 9b.7.3.1.3Process EquipmentSee Table 9b.7-3 for a list of major process equipment associated with the RLWE.
9b.7.3.2Safety-Related EffectsThe RLWE processes material with a significant concentration of radioactive byproduct materials. In order to limit the exposure of individuals to radiation, the RLWE vaults are shielded.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-31Rev. 0Radiation monitors and criticality alarms are used to monitor releases of radiological materials and detect potential criticality events.9b.7.3.2.1Safety Functions The safety design functions of the RLWE are:*Maintaining piping, valve, and component integrity to ensure radiological material iscontained.*Instrumentation to prevent tank overfills.*Level trips to ensure no spillage. 9b.7.3.2.2Criticality Control Features The RLWE does not contain appreciable quantities of fissile material. The primary feed to the RLWE is raffinate from the UREX system. The absence of appreciable quantities of fissile materials from this process stream is verified in the raffinate hold tank before the raffinate is transferred to the liquid waste storage tank. The UREX raffinate contains the plutonium produced in the irradiation cycle. This does not present a criticality hazard for the facility. None of the other process streams fed to the RLWE contain appreciable quantities of fissile material.As an additional precaution, the RLWE hot cells are monitored by the CAAS.9b.7.3.2.3Shielding and Radiological ProtectionThe RLWE processes are performed in shielded hot cells, which limit the exposure of radiation to individuals within the regulatory limits of 10 CFR 20. Refer to Chapter 11 for the radiation exposure guidelines, and Subsection 4b.2.5 for further detail of shielding requirements.Radiation monitors and alarms are used to monitor gamma dose levels and detect the release of radiological materials within the hot cell.Piping that contains radioactive and potentially radioactive materials is routed through shielded pipe chases to limit the exposure of radiation to individuals.9b.7.3.3Technical SpecificationsThere are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with RLWE.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-32Rev. 09b.7.4AQUEOUS RADIOACTIVE LIQUID WASTE STORAGE SYSTEMThe primary purpose of the RLWS is to provide buffer storage of the liquid wastes generated by facility operations.9b.7.4.1System Description The RLWS is designed to provide buffer storage for liquid radioactive wastes generated from processing operations. Buffer storage decouples radioisotope production operations from liquid
waste treatment operations.9b.7.4.1.1System Process FunctionsThe process functions of the RLWS system are:*Receive radioactive liquid waste from the following systems:-Uranyl nitrate conversion system (UNCS).-Mo extraction and purification system (MEPS).-Process vessel vent system (PVVS).-Noble gas removal system (NGRS)
-Receive radioactive liquid waste from non-routine operations.*Store the received liquid wastes to allow for smoothing of feed rate and composition offeed to the RLWE.*Provide additional time for radioactive decay of isotopes in the liquid waste.*Allow sampling of the stored liquid waste.9b.7.4.2Safety-Related EffectsThe RLWS contains significant quantities of radioactive materials. To limit the exposure of individuals to radiation, the RLWS vaults are shielded. Radiation monitors and alarms are used to monitor releases of radiological materials and detect criticality events.9b.7.4.2.1Safety FunctionsThe safety design functions of the RLWS are:*Maintaining piping, valve, and component integrity to ensure radiological material iscontained.*Instrumentation to prevent tank overfills.*Level trips to ensure no spillage.9b.7.4.2.2Primary System InterfacesFor a list of system interfaces, refer to Table 9b.7-4.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-33Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390]9b.7.4.2.3Processing SequenceThe RLWS system receives liquid radioactive waste from a variety of sources within the RCA. The liquid waste is primarily routine effluents from within the process, but also includes liquid
wastes generated by non-routine operations such as equipment flushes, cell wash-downs, and maintenance activities.See Figure 9b.7-5 for the PFD that shows the radioactive liquid waste storage system.
The RLWS is comprised of two liquid waste storage tanks (1-RLWS-01T-A/B). These tanks are configured in parallel, with one tank being in filling, sampling, and radioactive decay mode, while the other is in evaporator feed mode. The tanks are located in individual tank vaults.Each tank has a working volume of approximately [Security-Related Information]. This provides around 40 days of buffer storage capacity of liquid wastes produced by normal facility operations. The liquid waste generation varies in frequency, composition, and flowrate. The liquid waste storage tanks provide smoothing of these variations. This allows the evaporator in the RLWE system to be operated at near steady state conditions while it processes the contents of each liquid waste storage tank.Each tank has liquid recycle capability to enable t he tanks to be mixed prior to sampling. The recycle is via the liquid waste evaporator feed pump (1-RLWE-01-A/B). The tank sampling is located on the liquid recycle line. The waste in the tanks is sampled to verify the chemical and radiological composition prior to feeding to the liquid waste evaporator in the RLWE system.9b.7.4.2.4Process Equipment See Table 9b.7-5 for a list of major process equipment associated with the RLWS.9b.7.4.3Operational Analysis and Safety Function9b.7.4.3.1Criticality Control Features The RLWS does not contain appreciable quantities of fissile material (see Subsection 9b.5.3.3). The primary feed to the RLWS is raffinate from the UREX system. The absence of appreciable quantities of fissile materials from this process stream is verified in the raffinate hold tank before the raffinate is transferred to the liquid waste storage tank. The UREX raffinate contains the plutonium produced in the irradiation cycle. This does not present a criticality hazard for the facility. The other process streams fed to the RLWS also do not contain appreciable quantities of fissile material.As an additional precaution, the RLWS tank vaults are monitored by the CAAS.9b.7.4.3.2Shielding and Radiological Protection The RLWS tanks are located in shielded tank vaults. This limits the radiation exposure of individuals to within the regulatory limits of 10 CFR
- 20. Refer to Chapter 11 for the radiation exposure goals, and Section 4b.2 for further detail of shielding requirements.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-34Rev. 0Radiation monitors and alarms are used to monitor gamma dose levels and detect the release of radiological materials within the tank vaults. Piping that contains radioactive and potentially radioactive materials is routed through shielded pipe chases to limit the exposure of radiation to individuals.9b.7.4.4Instrumentation and ControlThe primary control for the RLWS is the tank and valve configuration to control which tank is filling and which tank is emptying. This cont rol is accomplished by valving on the liquid inlet and outlet lines from each tank. The tank in fill mode has the inlet valve open and the outlet valve closed. The tank in emptying mode has t he inlet valve closed and the outlet valve open.The two liquid waste storage tanks (1-RLWS-01T-A/B) also include:*Level measurement - including low and high level alarms, plus low-low and high-high level trips. The low level alarm alerts the operator and allows an intervention to prevent the tank emptying and running the liquid waste evaporator feed pump (1-RLWE-01P-A/B) dry. The low-low level trip automatically stops the online liquid waste evaporator feed pump (1-RLWE-01P-A/B) to prevent damage from running dry. The high level alarm alerts the operator and allows an intervention to prevent the tank overfilling. The high-high level trip automatically stops pumps that feed the liquid waste storage tanks.*Pressure measurement - including a high pressure alarm, which alerts the operator to a rise in the tank pressure.9b.7.4.5Technical Specifications There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with RLWS.9b.7.5SOLID RADIOACTIVE WASTE PACKAGING SYSTEMThe SRWP provides a means to collect, process, store, package, and prepare for off-site shipment, solid radioactive waste material produced by the normal operation of the facility. The single SRWP described herein services the wastes from systems throughout the IF and RPF.9b.7.5.1System Process FunctionsThe SRWP is designed to provide for the collection, processing, packaging, and storage of solid wastes resulting from normal plant operations without limiting the normal operation or availability of the facility.9b.7.5.2Safety-Related Effects9b.7.5.2.1Safety Functions This system is nonsafety-related.
Chapter 9 - Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-35Rev. 1[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]9b.7.5.3System Design Inputs9b.7.5.3.1NDAS Waste StreamThe NDAS creates a waste stream that consists of activated vacuum hardware, target chambers, and the upper portion of the neutron driver. 9b.7.5.3.2Solid Radioactive Waste Handling Hot Cell Waste StreamThe inputs to the solid radioactive waste handling hot cell are summarized in Figure 9b.7-7. These include spent Mo extraction columns, [
Proprietary Information
], scrap radioisotope purification process glassware, spent light water pool deionizer units, spent PCLS cooling water deionizer units, spent Tc removal columns, spent Cs columns, and scrap contaminated equipment.9b.7.5.3.3Miscellaneous Dry Waste StreamMiscellaneous dry waste in the form of rags, paper, and contaminated PPE is collected in specific locations within the facility based on operational and health physics approaches.9b.7.5.4System Storage and Packaging Requirements9b.7.5.4.1Neutron DriverThe neutron driver drift tubes and target chambers are placed into a DOT IP-1 cargo container (SC-0001) for storage after removal from the light water pool. They accumulate until the cargo container is either full or the container reaches its maximum gross weight capacity of 67,200 lb. The upper portion of the neutron drivers are placed into decay storage. They are then placed into a DOT IP-1 cargo container for disposal. Refer to Table 9b.7-7 for waste classification, quantities, and final destination of the neutron driver waste.9b.7.5.4.2Solid Radioactive Waste Handling Hot CellBoth the spent Mo extraction columns [
Proprietary Information
] are stored within the supercell Mo extraction area for a duration of no less than 2 weeks after use. After the initial decay period, the spent columns are transferred to the storage vault for an additional six months of decay time. The spent columns are then transferred to the solid radioactive waste handling hot cell for consolidation and packaging into an approved LSA container. Refer to Table 9b.7-7 for waste classification, quantities, and final destination of the Mo extraction [
Proprietary Information
].The scrap radioisotope purification process glassware is removed from the supercell purification area and transferred to the solid radioactive waste handling hot cell. The glassware is deposited into a drum that has had an absorbent added and crushed, until the drum is full and then removed for shipping. Refer to Table 9b.7-7 for waste classification, quantities, and final destination of the radioisotope purification process glassware waste.
Chapter 9 - Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-36Rev. 1The spent Cs columns are transferred to the solid radioactive waste handling hot cell. The resins are then extracted and sent to the liquid radioactive waste handling hot cell for further processing. The resin-free spent Cs column is then processed and placed into liners for Type B shipping. Refer to Table 9b.7-7 for waste classification, quantities, and final destination of the spent Cs columns.Scrap contaminated equipment is transferred to the solid radioactive waste handling hot cell, as necessary. The contaminated equipment is then packaged in a specifically designed LSA container.9b.7.5.4.3Miscellaneous Dry WasteThe miscellaneous dry waste is consolidated, packaged, and sent to the waste staging and shipping building. Refer to Table 9b.7-7 for waste classification, quantities, and final destination of the dry waste.9b.7.5.5Equipment DescriptionSee Table 9b.7-6 for a list of major equipment associated with the solid radioactive waste packaging system.9b.7.5.6System Shipping ProceduresSolid radioactive waste is shipped on a regular basis by a DOT licensed carrier.9b.7.5.7Criticality Control FeaturesNo criticality-safe control features are necessary in the solid radioactive waste packaging system as transuranic or fissile material is not present in significant quantities in these waste streams.
As an additional precau tion, the SRWP is mo nitored by the CAAS.9b.7.5.8Instrumentation and ControlThe RICS provides the process monitoring and control of the SRWP (See Subsection 7b.1).9b.7.5.9Technical SpecificationsThere are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the SRWP.9b.7.6RADIOACTIVE DRAIN SYSTEM9b.7.6.1RDS Process DescriptionThe RDS receives radioactive liquids from various systems. Its primary purpose is to collect spills and leaks of radioactive liquids from processing areas.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-37Rev. 09b.7.6.1.1System Process FunctionsThe following is a list of the process functions of the RDS system:*Receive and hold radioactive liquids from leaks and tank overflows in the processingareas.*Detect and alarm when radioactive liquids are received.
- Perform pH adjustment.*Route collected liquids to the UNCS.9b.7.6.2Safety-Related EffectsThere is a potential for radioactive material to be present in the RDS after an overflow or leak, so the RDS is located in shielded pipe chases to limit the exposure of individuals to radiation.Radiation monitors and alarms are used to monitor release of radiological materials and monitor high background gamma dose levels. CAAS provides monitoring for potential criticality events.9b.7.6.2.1Safety FunctionsThe safety design functions of the RDS are:*Contain loss of inventory from process vessels and components.*Provide sumps and drains that lead from the pipe trenches, tank vaults, hot cells, and process enclosures with a geometry that prevents an inadvertent criticality.9b.7.6.2.2Primary System Interfaces For a list of system interfaces, refer to Table 9b.7-8.9b.7.6.2.3RDS CollectionTank vaults, hot cells, process enclosures and the pipe trenches have drain lines to collect pipe and tank leaks, as well as wash-down sprays. Th e floors are sloped towards the drains. Small wells near the drain provide leak detection. A dditionally, tank overflow lines are hard-piped to drain lines. Refer to the schedule on Figure 9b.7-8 for a list of drain locations. 9b.7.6.2.4Processing SequenceThe RDS drain lines are sloped to the criticality-safe sump catch tank (1-RDS-01T), which is sized to contain a potential leak from the largest tank with radioactive liquids (UN recycle hold tank). Once the liquid is received in the critic ality-safe sump catch tank, it can be sampled and characterized, if needed. The liquid may be treat ed with caustic or nitric acid, depending on the pH. Finally, the liquid is transferred to the UNCS to allow the uranium to be recovered.See Figure 9b.7-8 for the PFD related to the RDS.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-38Rev. 09b.7.6.2.5Process EquipmentSee Table 9b.7-9 for a list of major process equipment associated with the RDS.9b.7.6.2.6Criticality Control Features The RDS prevents inadvertent criticality throug h inherently-safe geometrical design of sumps, tanks, drain lines, and in-line components that may handle fissile material. 9b.7.6.2.7Shielding and Radiological Protection Piping that contains potentially-radiological material is routed through shielded pipe chases to limit the exposure of radiation to personnel. The criticality-safe sump catch tank is shielded by a tank vault, which is a part of the process facility biological shield system (PFBS).Refer to Chapter 11 for the radiation exposure goals, and Section 4b.2 for further detail of shielding requirements.Radiation monitors and alarms are used to monitor for release of radiological materials, and monitor high background gamma dose levels.9b.7.7MATERIAL HANDLING The material handling system (MHS) provides equipment for the safe manipulation and transportation of material or equipment within t he facility, external to the RCA (for material handling inside the RCA, see the RMHS system). The MHS includes overhead cranes, hoists, fork trucks, hand trucks, and carts, as necessary, that are used to move or manipulate material, including chemicals, or equipment, within the facility. The MHS system is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the MHS system.9b.7.8FACILITY POTABLE WATER SYSTEMThe facility potable water system (FPWS) provides a potable water supply fo r the SHINE facility. The FPWS is fed by a connection to the City of Janesville water supply, and includes a meter house, backflow prevention valves, and distribution piping and valves as necessary, to the locations within the facility that use potable water. The FPWS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FPWS system.9b.7.9FACILITY INSTRUMENT AIR SYSTEMThe facility instrument air system (FIAS) serves the RCA and areas outside the RCA of the SHINE facility to provide clean, filtered, compressed, dry air to the facility's various pneumatic-controlled components. This system includes compressors, pre-filters, dryers, receivers, and after filters. The FIAS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FIAS system.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-39Rev. 09b.7.10FACILITY COMPRESSED AIR SYSTEMThe facility compressed air system (FCAS) serves the RCA and non-RCA of the SHINE facility to provide clean, filtered, compressed air for maintenance and miscellaneous use. This system includes compressors, filters, and receivers. The FCAS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FCAS system.9b.7.11FACILITY BREATHING AIR SYSTEM The facility breathing air system (FBAS) serves the RCA and non-RCA of the SHINE facility and provides clean, filtered air suitable for breathing hoods or masks. The system includes multiple compressors, receiver, control panel, and air purification equipment. The FBAS is not safety-related. A more detailed system descriptio n will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FBAS system.9b.7.12FACILITY INERT GAS SYSTEMThe facility inert gas system (FIGS) provides a clean source of nitrogen gas for the purpose of inerting. The FIGS consists of a bulk storage tank containing cold, compressed liquid nitrogen, a vaporizer, distribution piping, and controls. The FIGS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FIGS system.9b.7.13FACILITY ROOF DRAINS SYSTEMThe facility roof drains system (FRDS) removes rainfall precipitation from the flat roof of the main production building. Water is directed to exterior perimeter downspouts, discharge to the ground surface, and then overland flow to the site perimeter drainage ditch. The downspouts are connected directly to the catch basins inlets and the perimeter ditch via underground piping.
Downspout discharges are directed away from the buildings via surface flow and sloped lawn areas. The FRDS is not safety-related. A more detailed system description will be provided in
the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specificat ion associated with the FRDS system.9b.7.14FACILITY SANITARY DRAINS SYSTEMThe facility sanitary drains system (FSDS) remo ves normal domestic sanitary waste water from sinks, bathrooms, and cleaning maintenance closets vi a an interior gravity piping network, to an exterior lateral connected to the City of Janesville sewer system. If required due to elevation differences, the exterior gravity lateral will be replaced with a sanitary lift-pumping station that discharges to the City sewer. The FSDS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FSDS system.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-40Rev. 09b.7.15FACILITY ACID REAGENT STORAGE AND DISTRIBUTION SYSTEMThe facility acid reagent storage and distribution system (FARS) serves the RCA and areas outside the RCA of the SHINE facility to provide clean, filtered acid for use in the process. The system contains a storage tank, filters, metering pumps, and distribution piping. The FARS is not safety-related. A more detailed system descriptio n will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical
specification associated with the FARS system.9b.7.16FACILITY ALKALINE REAGENT STORAGE AND DISTRIBUTION SYSTEM The facility alkaline reagent storage and distribution system (FLRS) serves the RCA and areas outside the RCA of the SHINE facility to provide clean, filtered alkaline for use in the process.
The system contains a storage tank, filters, metering pumps, and distribution piping. The FLRS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical
specification associated with the FLRS system.9b.7.17FACILITY SALT REAGENT STORAGE AND DISTRIBUTION SYSTEMThe facility salt reagent storage and distribution system (FSRS) serves the RCA and areas outside the RCA of the SHINE facility to provide clean, filtered salts for use in the process. The system contains a storage tank, filters, metering pumps, and distribution piping. The FSRS is not safety-related. A more detailed system descriptio n will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the FSRS system.9b.7.18FACILITY ORGANIC REAGENT STORAGE AND DISTRIBUTION SYSTEMThe facility organic reagent storage and distribution system (FORS) serves the RCA and areas outside the RCA of the SHINE facility to provide clean, filtered organics for use in the process. The system contains a storage tank, filters, metering pumps, and distribution piping. The FORS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be pr obable subjects of a technical specification associated with the FORS system.9b.7.19ORGANIC LIQUID WASTE STORAGE AND EXPORTThe organic waste storage and export system (OLWS) is used to collect, store, and dispose of organic liquid wastes generated at various points in the RCA and areas outside the RCA of the SHINE facility during the Mo-99 production process. The system contains an organic liquid waste
storage tank with level instrumentation and alarms, a transfer pump and piping, and valves, as necessary. The OLWS is not safety-related. A more detailed system description will be provided in the FSAR. There are no potential variables, conditions, or other items that will be probable subjects of a technical specification associated with the OLWS system.9b.7.20OFF-NORMAL AND ACCIDENT SCENARIOS Part of the evaluation of other auxiliary systems is to determine that the design, functions, and potential malfunctions of the auxiliary system will not cause malfunctions or accidents that could Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-41Rev. 0result in uncontrolled release of radioactivity. This evaluation for auxiliary systems in both the IF and the RPF were reviewed as part of the development of the integrated safety analysis (ISA) for potential as a design basis accident (DBA) or initiating event (IE). The bases for the identification of DBAs and their IEs and associated accident scenarios were:*Hazard and operability study (HAZOPS) as part of the development of the integrated safety analysis (ISA) summary, in accordance with NUREG-1520.*List of IEs and accidents identified in the Final Interim Staff Guidance Augmenting NUREG-1537, Part 1.*Experienced hazards analysis team.*Preliminary design for the processes and facility.The ISA development process identified process equipment by breaking it down into 56 systems and nearly 400 scenarios for both the IF and RPF. Causes for deviations and their potential outcomes were then identified. Finally, potential protective controls, safety functions, and functional requirements were identified. This led to the identification of the accident scenarios
addressed in Chapter 13. For the FSAR a final HAZOPS analysis will be performed.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-42Rev. 0Table 9b.7-1 Master-Slave ManipulatorsMaster-Slave Manipulator LocationQuantitySupercell Molybdenum Extraction Area of MEPS (each supercell)2 Supercell Molybdenum Purification Area of MEPS (each supercell)2 Supercell Molybdenum Packaging Area of MIPS (each supercell)2 UREX Hot Cell2 RLWE Evaporation Hot Cell2 RLWE Immobilization Hot Cell2 SRWP Hot Cell2 Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-43Rev. 0 Table 9b.7-2 RLWE System InterfacesInterfacing SystemInterface Description Process Vessel Vent System (PVVS)Tanks in the RLWE vent to the PVVS.
Radioactive Drain System (RDS)Several of the process tanks in the RLWE overflow to the RDS. Aqueous Radioactive Liquid Waste Storage (RLWS)The RLWE receives radioactive liquid waste from the RLWS system. Radiological Integrated Control System (RICS)The RLWE is controlled by the RICS.
Normal Electrical Power Supply System (NPSS)The RLWE is powered by the NPSS.
Radioisotope Process Facility Cooling System (RPCS)The RLWE uses chilled water from the RPCS to cool process streams.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-44Rev. 0
[Security-Related Information - Withhold Under 10 CFR 2.390]Table 9b.7-3 RLWE Process EquipmentComponentDescriptionCode/StandardLiquid waste evaporator feed pump (1-RLWE-01P-A/B)
Centrifugal pump that tr ansfers aque ous liquid radioactive waste to the evaporator. Nominal flowrate is 0.4 gpm.
ASME, 2011Liquid waste evaporator tank (1-RLWE-01D)Evaporator recirculation tank, with dual functions of providing liquid hold-up and vapor-liquid separation.
The liquid hold-up is the limiting sizing criteria. The tank design includes a demi ster at the top to remove moisture droplets.
ASME, 2011Liquid waste evaporator recirculation pump
(1-RLWE-02P-A/B)
Centrifugal pump that reci rculates liquid radioactive waste through the heater to the liquid waste evaporator tank. Nominal flowrate is 35 gpm.
ANSI/HI, 2008Liquid waste evaporator heater (1-RLWE-01A)Electrical heater to provide heat input for evaporation. Nominal capacity is 87,248 Btu/hr (25.6 kW).Liquid waste condenser (1-RLWE-02A)Evaporator overheads condenser, cooled by RPCS chilled water. Nominal heat duty is 71,871Btu/hr (20.9 kW).Liquid waste condensate collection tank
(1-RLWE-01T-A/B)
Dual collection tanks for ev aporator condensate. Working capacity is 70 gal.
ASME, 2011Liquid waste condensate pump (1-RLWE-03P-A/B)
Centrifugal pump that transfers condensate from the liquid waste condensate collection tank. Nominal flowrate is 10 gpm.
ANSI/HI, 2008Liquid waste evaporator product cooler
(1-RLWE-03A)Evaporator bottoms product cooler, cooled by RPCS chilled water. Nominal heat duty is 14,128Btu/hr (4.1kW).Liquid waste collection tank (1-RLWE-02T-A/B)
Dual collection tanks for evap orator bottoms product. Working capacity is [Security-Related Information]
.ASME, 2011Liquid waste pump (1-RLWE-04P-A/B)Positive displacement pump s that meters evaporator bottoms product from the liquid waste collection tank to the immobilization system drum filling station. Nominal flowrate is 5 gpm.
ANSI/HI, 2008Cement hopper (1-RLWE-03T)
Storage hopper for cement.
Nominal capacity is 4981lb.Blast furnace slag hopper (1-RLWE-04T)Storage hopper for blast furnace slag. Nominal capacity is 3179 lb.Calcium hydroxide hopper (1-RLWE-05T)
Storage hopper for calcium hydroxide. Nominal capacity is 1591 lb.Waste drum solids weigh scale (1-RLWE-01Z)Weigh scale for measuring solidification materials additions to drums.Waste drum liquids weigh scale (1-RLWE-02Z)Weigh scale for measuring liquid waste addition to drums.Waste drum mixer (1-RLWE-03Z)
Rotating drum mixer for mixing liquid waste and solidification materials.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-45Rev. 0
[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]
Table 9b.7-4 RLWS System InterfacesInterfacing SystemInterface Description Process Vessel Vent System (PVVS)The process tanks in the RLWS vent to the PVVS. The interface is at the tank exhaust.The RLWS receives acid gas scrubber blowdown from the PVVS.
Mo Extraction and Purification System (MEPS)The RLWS receives liquid waste from the following sources within the MEPS:*Spent Mo extraction column washes*[Proprietary Information]
- Rotary evaporator condensate*Spent purification process liquids Radioactive Drain System (RDS)The process tanks in the RLWS overflow to the RDS. Radioactive Liquid Waste Evaporation and Immobilization (RLWE)The RLWS transfers radioactive liquid waste to the RLWE system.
Noble Gas Removal System (NGRS)The NGRS condensate is routed to the RLWS system.Radiological Integrated Control System (RICS)The RLWS is controlled by the RICS.
Normal Electrical Power Supply System (NPSS)The RLWS is powered by the NPSS.
Uranyl Nitrate Conversion System (UNCS)The RLWS receives raffinate from the UREX system in the UNCS.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-46Rev. 0Table 9b.7-5 RLWS Process EquipmentComponentDescriptionCode/StandardLiquid waste storage tank(1-RLWS-01T-A/B)These tanks provide buffer storage of the radioactive liquid waste generated by facility operations.ASME BPVC Section VIII Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-47Rev. 0Table 9b.7-6 Solid Radioactive Waste Packaging System Equipment ListEquipmentDescriptionWaste Stream DOT IP-1 Cargo Container (SC-0001)67,200 lb. gross weight capacity shipping container. The container is nominally 240 in. L x 96in. W x 102 in. H, and has a 1,162 cu. ft. internal volume.
Neutron Driver DPTE Drum Transfer System A DPTE drum transfer system is used for the introduction of waste being received from the supercell area.
Solid Radioactive Waste Handling Hot CellShielded Cask Shielded storage casks are used to store the waste in order to protect the environment and personnel from irradiated solid waste.
Solid Radioactive Waste Handling Hot CellTelemanipulators Telemanipulators are used when remote handling is required for handling of solid waste.Solid Radioactive Waste Handling Hot CellPackaging Drum Transfer System A drum transfer system is used to repackage solid waste into an acceptable storage container.
Solid Radioactive Waste Handling Hot CellOverhead Hoist An overhead hoist is used to assist in remote handling of solid waste within a hot cell environment.
Solid Radioactive Waste Handling Hot Cell Chapter 9 - Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-48Rev. 1[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]Table 9b.7-7 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility(Sheet 1 of 3)DescriptionMatrixClass as GeneratedContentsVolumeVolume as shipped (ft 3)55-gallon drum equivalent as shippedShipmentTypeNumber of Shipments/yrDestinationNeutron Generator SolidAActivated metal parts4338ft3/yr4338590LSA3ESExtraction Columns SolidAStainless resin
columnsClass A Trash SolidAPPE, Mo-99
purificatio n glassware, filters, etcCoolant Cleanup
Ion Exchange ResinResinAResin48 ft3/yr487.3LSA1ESSpent SolventLiquidAn-dodecane, tributyl phosphate22 gallons/yr--0.4LSA1DSSITc/I columns ResinCResin16 gallons/
yr233.1Type B0.3WCSZeolite Beds SolidGTCCSilver coated
beds0.4 ft3/yr0.40.05Type B1WCSCs/Ce Media ResinGTCCResin16 gallons/
yr233.1Type B0.3WCS[ Proprietary Information
][ Proprietary Information ]B[ Proprietary Information
]295 gallons/yr7911Type B1WCS Chapter 9 - Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-49Rev. 1[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]Table 9b.7-7 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility(Sheet 2 of 3)Description MatrixClass as GeneratedContentsVolumeVolume as shipped (ft 3)55-gallon drum equivalent as shipped Shipment TypeNumber of Shipments/yrDestinationSpent WashesLiquid(a)A[ Proprietary Information
]2100gallons/yr7540(b)1143(c)LSA19ESRotovap CondensateLiquid(a)A[ Proprietary Information
]200gallons/yrUREX RaffinateLiquid(a)B[ Proprietary Information
]27,000gallons/yrDecontamination WasteLiquid(a)ADecon fluid unknown 400gallons/yrSpent Eluate
SolutionLiquid(a)A[ Proprietary Information
]2600gallons/yrNOx Scrubber SolutionLiquid(a)A[ Proprietary Information
]20,000gallons/yr Chapter 9 - Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-50Rev. 1[Proprietary Information - Withhold from public disclosure under 10 CFR 2.390(a)(4)]Table 9b.7-7 Estimated Type and Quantity of Radioactive Wastes Associated with the SHINE Facility(Sheet 3 of 3)a)This liquid waste discharged from the various processes at the SHINE facility is either solidified and then shipped to a waste depository or reused.b)As shipped volume of waste is in the form of concrete. Total liquid volume of approximately 52,000 gallons/yr is reducedvia evaporation to approximately 35,000 gallons/yr (volume reduction factor of 1.5). The liquid waste is then solidifiedby adding Portland cement (or equivalent). Concrete volume is estimated using a conservative waste to cement massratio of 0.5. c)A 55-gallon drum, filled to 90 percent to account for minor voiding, has a volume of approximately 6.6 ft3.
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-51Rev. 0Table 9b.7-8 RDS InterfacesInterfacing SystemInterface Description Process Vessel Vent System (PVVS)The RDS vents to the PVVS which enables the criticality-safe sump catch tank to be vented to a system that treats radioactive gases.Target Solution Preparation System (TSPS)The RDS receives spills from the sumps in the TSPS area.Molybdenum Extraction and Purification System (MEPS)The RDS receives spills from the sumps in the MEPS hot cells (supercells).
Uranyl Nitrate Conversion System (UNCS)
The RDS receives spills from t he sumps in the tank vaults, sumps in the UREX hot cell, and sumps in the TDN area. Additionally, the liquids collected in the RDS are routed to the UNCS in order to recover any uranium.Radiological Integrated Control System (RICS)
The RDS is controlled by the RICS.
Normal Electrical Power Supply System (NPSS)
The RDS is powered by the NPSS.Radioactive Liquid Waste Evaporation and Immobilization (RLWE)
The RDS receives spills from the RLWE hot cell (not shown on PFD).Aqueous Radioactive Liquid Waste StorageThe RDS receives spills from the sumps in the RLWS tank vaults (not shown on PFD).
Chapter9 -Auxiliary SystemsOther Auxiliary SystemsSHINE Medical Technologies9b-52Rev. 0Table 9b.7-9 RDS Process EquipmentComponentDescriptionCode/Standard Radioactive Drain PumpThe positive-displacement pump serves to recirculate the collected liquids if pH balancing is required. It also serves to
transfer collected liquids to the UNCS. ANSI/HI 3.1-3.5Criticality-Safe Sump Catch Tank This catch tank is the reservoir for collecting fissile radioactive liquids from leaks or spills from the facility. It is criticality-safe by design. The tank is vented to the PVVS in order to maintain atmospheric pressure and treat radioactive gases. It is sized to collect the entire contents of the single-largest tank containing radioactive liquids.
ASME BPVC Section VIII Radioisotope Production FacilityChapter9 -Auxiliary Systems Auxiliary Systems Technical SpecificationsSHINE Medical Technologies9b-53Rev. 09b.8RADIOISOTOPE PRODUCTION FACILITY AUXILIARY SYSTEMS TECHNICAL SPECIFICATIONSPotential variables, conditions, or other items that are probable subjects of a technical specification associated with the RPF Auxiliary Systems are provided in Chapter 14.
Chapter9 -Auxiliary SystemsReferencesSHINE Medical Technologies9b-54Rev. 09b.9REFERENCESAGS, 2007. Guideline for Gloveboxes, AGS-G001, American Glovebox Society, February 1, 2007.ANSI/ANS,1993. American National Standard for Gaseous Radioactive Waste Processing Systems, American National Standards Institute, ANSI/ANS-55.4, 1993 edition.
ANSI/HI, 2008. Rotary Pumps (A109), 3.1-3.5, American National Standards Institute, January1, 2008.API, 2009. Axial and Centrifugal Compressors and Expander-Compressors for Petroleum, Chemical and Gas Industry Services, API Standard 617, American Petroleum Institute, January 2009.ASME 2009.
Code on Nuclear Air and Gas Treatment, AG-1, American Society of Mechanical Engineers, September 30, 2009.ASME, 2011. Boiler & Pressure Vessel Code - Rules for Construction of Pressure Vessels,Section VIII, American Society of Mechanical Engineers, July 1, 2011ASME, 2013. Code for Pressure Piping, B31.3-2012, American Society of Mechanical Engineers, January 10, 2013.