ML20105A305
| ML20105A305 | |
| Person / Time | |
|---|---|
| Site: | SHINE Medical Technologies |
| Issue date: | 03/27/2020 |
| From: | SHINE Medical Technologies |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20105A242 | List:
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| References | |
| 2020-SMT-0025 | |
| Download: ML20105A305 (137) | |
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AUXILIARY SYSTEMS TABLE OF CONTENTS tion Title Page IRRADIATION FACILITY AUXILIARY SYSTEMS ........................................... 9a2.1-1
.1 HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS ................. 9a2.1-1 9a2.1.1 RADIOLOGICALLY CONTROLLED AREA VENTILATION SYSTEM ......................................................................................... 9a2.1-1 9a2.1.2 NON-RADIOLOGICAL AREA VENTILATION SYSTEM ................ 9a2.1-6 9a2.1.3 FACILITY CHILLED WATER SYSTEM .......................................... 9a2.1-9 9a2.1.4 FACILITY HEATING WATER SYSTEM ....................................... 9a2.1-10
.2 HANDLING AND STORAGE OF TARGET SOLUTION ................................... 9a2.2-1 9a2.
2.1 INTRODUCTION
............................................................................ 9a2.2-1 9a2.2.2 IRRADIATION FACILITY TARGET SOLUTION STORAGE AND HANDLING ..................................................................................... 9a2.2-1 9a2.2.3 IRRADIATION FACILITY TARGET SOLUTION HANDLING EQUIPMENT .................................................................................. 9a2.2-1 9a2.2.4 STORAGE OF TARGET SOLUTION ............................................. 9a2.2-2 9a2.2.5 CRITICALITY CONTROL FEATURES ........................................... 9a2.2-2 9a2.2.6 BIOLOGICAL SHIELDING ............................................................. 9a2.2-2 9a2.2.7 TECHNICAL SPECIFICATIONS .................................................... 9a2.2-2
.3 FIRE PROTECTION SYSTEMS AND PROGRAMS ........................................ 9a2.3-1 9a2.3.1 FIRE PROTECTION PLAN AND PROGRAM ................................ 9a2.3-1 9a2.3.2 DESIGN BASES ............................................................................. 9a2.3-1 9a2.3.3 FIRE HAZARD ANALYSIS ............................................................. 9a2.3-1 9a2.3.4 SAFE SHUTDOWN ANALYSIS ..................................................... 9a2.3-2 9a2.3.5 ADMINISTRATIVE CONTROLS .................................................... 9a2.3-2 NE Medical Technologies 9-i Rev. 0
AUXILIARY SYSTEMS TABLE OF CONTENTS tion Title Page 9a2.3.6 REGULATORY AND CODE REQUIREMENTS ............................. 9a2.3-2 9a2.3.7 FACILITY FIRE PROTECTION SYSTEM DESCRIPTION ............. 9a2.3-3 9a2.3.8 RADIOLOGICAL FIRE HAZARDS ................................................. 9a2.3-3 9a2.3.9 TECHNICAL SPECIFICATIONS .................................................... 9a2.3-5
.4 COMMUNICATION SYSTEMS ........................................................................ 9a2.4-1 9a2.4.1 TELEPHONES ............................................................................... 9a2.4-1 9a2.4.2 PUBLIC ADDRESS SYSTEM ........................................................ 9a2.4-1 9a2.4.3 SOUND-POWERED PHONES ....................................................... 9a2.4-2 9a2.4.4 RADIO SYSTEM ............................................................................ 9a2.4-2 9a2.4.5 INFORMATION TECHNOLOGY .................................................... 9a2.4-2 9a2.4.6 TESTING REQUIREMENTS .......................................................... 9a2.4-2 9a2.4.7 PHYSICAL SECURITY ................................................................... 9a2.4-3 9a2.4.8 TECHNICAL SPECIFICATIONS .................................................... 9a2.4-3
.5 POSSESSION AND USE OF BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIAL ..................................................................................... 9a2.5-1 9a2.5.1 BYPRODUCT MATERIAL .............................................................. 9a2.5-1 9a2.5.2 SOURCE MATERIAL ..................................................................... 9a2.5-1 9a2.5.3 SPECIAL NUCLEAR MATERIAL ................................................... 9a2.5-1
.6 COVER GAS CONTROL IN CLOSED PRIMARY COOLANT SYSTEMS ....... 9a2.6-1 NE Medical Technologies 9-ii Rev. 0
AUXILIARY SYSTEMS TABLE OF CONTENTS tion Title Page
.7 OTHER AUXILIARY SYSTEMS ....................................................................... 9a2.7-1 9a2.7.1 TRITIUM PURIFICATION SYSTEM ............................................... 9a2.7-1 9a2.7.2 NEUTRON DRIVER ASSEMBLY SYSTEM SERVICE CELL ........ 9a2.7-5
.8 REFERENCES ................................................................................................. 9a2.8-1 RADIOISOTOPE PRODUCTION FACILITY AUXILIARY SYSTEMS ................ 9b.1-1 1 HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS ................... 9b.1-1 2 HANDLING AND STORAGE OF TARGET SOLUTION ..................................... 9b.2-1 9b.2.1 TARGET SOLUTION LIFECYCLE ................................................... 9b.2-1 9b.2.2 RECEIPT AND STORAGE OF UNIRRADIATED SNM .................... 9b.2-1 9b.2.3 TARGET SOLUTION PREPARATION ............................................. 9b.2-2 9b.2.4 TARGET SOLUTION STAGING SYSTEM ....................................... 9b.2-2 9b.2.5 VACUUM TRANSFER SYSTEM ...................................................... 9b.2-2 9b.2.6 RADIOACTIVE LIQUID WASTE STORAGE .................................... 9b.2-4 9b.2.7 RADIOACTIVE LIQUID WASTE IMMOBILIZATION ........................ 9b.2-4 9b.2.8 SOLID WASTE PACKAGING AND SHIPMENT .............................. 9b.2-5 9b.2.9 CRITICALITY CONTROL ................................................................. 9b.2-5 3 FIRE PROTECTION SYSTEMS AND PROGRAMS .......................................... 9b.3-1 4 COMMUNICATION SYSTEMS .......................................................................... 9b.4-1 5 POSSESSION AND USE OF BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIAL ....................................................................................... 9b.5-1 9b.5.1 BYPRODUCT MATERIAL ................................................................ 9b.5-1 9b.5.2 SOURCE MATERIAL ....................................................................... 9b.5-2 NE Medical Technologies 9-iii Rev. 0
AUXILIARY SYSTEMS TABLE OF CONTENTS tion Title Page 9b.5.3 SPECIAL NUCLEAR MATERIAL ..................................................... 9b.5-2 9b.5.4 QUALITY CONTROL AND ANALYTICAL TESTING LABORATORIES .............................................................................. 9b.5-3 6 COVER GAS CONTROL IN THE RADIOISOTOPE PRODUCTION FACILITY ........................................................................................................... 9b.6-1 9b.6.1 PROCESS VESSEL VENT SYSTEM ............................................... 9b.6-1 9b.6.2 NITROGEN PURGE SYSTEM ......................................................... 9b.6-4 7 OTHER AUXILIARY SYSTEMS ......................................................................... 9b.7-1 9b.7.1 MOLYBDENUM ISOTOPE PRODUCT PACKAGING SYSTEM ...... 9b.7-1 9b.7.2 MATERIAL HANDLING SYSTEM .................................................... 9b.7-2 9b.7.3 RADIOACTIVE LIQUID WASTE IMMOBILIZATION SYSTEM ........ 9b.7-5 9b.7.4 RADIOACTIVE LIQUID WASTE STORAGE SYSTEM .................... 9b.7-7 9b.7.5 SOLID RADIOACTIVE WASTE PACKAGING SYSTEM ............... 9b.7-10 9b.7.6 RADIOACTIVE DRAIN SYSTEM ................................................... 9b.7-11 9b.7.7 FACILITY POTABLE WATER SYSTEM ........................................ 9b.7-13 9b.7.8 FACILITY NITROGEN HANDLING SYSTEM ................................ 9b.7-14 9b.7.9 FACILITY SANITARY DRAIN SYSTEM ......................................... 9b.7-16 9b.7.10 FACILITY CHEMICAL REAGENT SYSTEM .................................. 9b.7-17 8 REFERENCES ................................................................................................... 9b.8-1 NE Medical Technologies 9-iv Rev. 0
mber Title
.7-1 Tritium Purification System Interfaces
.7-2 Nominal Tritium Supply/Return Properties
.7-3 Tritium Purification System Process Equipment
.7-4 NDAS Service Cell Interfaces 2-1 Liquid Transfers Using Vacuum Lift Method 2-2 Direct Transfer of Liquid via Application of Vacuum to Destination Tank 2-3 Vacuum Transfer System Interfaces 5-1 Quality Control and Analytical Testing Laboratories System Interfaces 6-1 Process Vessel Vent System Interfaces 6-2 Process Vessel Vent System Process Equipment 6-3 Nitrogen Purge System Interfaces 7-1 Radioactive Liquid Waste Immobilization System Interfaces 7-2 Radioactive Liquid Waste Storage System Interfaces 7-3 Solid Radioactive Waste Packaging System Interfaces 7-4 Radioactive Drain System Interfaces 7-5 Facility Nitrogen Handling System Interfaces 7-6 Facility Chemical Reagent System Interfaces NE Medical Technologies 9-v Rev. 0
mber Title
.1-1 Ventilation System Zone Designations Within the SHINE Facility
.1-2 Radiological Ventilation Zone 1 Recirculating Cooling Subsystem (RVZ1r) Flow Diagram
.1-3 Radiological Ventilation Zone 1 Exhaust Subsystem (RVZ1e) Flow Diagram
.1-4 Radiological Ventilation Zone 2 Exhaust Subsystem (RVZ2e) Flow Diagram
.1-5 Radiological Ventilation Zone 2 Supply Subsystem (RVZ2s) Air Handling Units (AHUs)
.1-6 Radiological Ventilation Zone 2 Supply Subsystem (RVZ2s) and Radiological Ventilation Zone 2 Recirculating Cooling Subsystem (RVZ2r) Flow Diagram
.1-7 Radiological Ventilation Zone 3 (RVZ3) Flow Diagram
.1-8 Radiological Ventilation Zone 1 Exhaust Subsystem (RVZ1e) and Radiological Ventilation Zone 2 Exhaust Subsystem (RVZ2e) Mezzanine
.1-9 Facility Ventilation Zone 4 Supply and Transfer Air Subsystem (FVZ4s) Distribution
.1-10 Facility Ventilation Zone 4 Supply and Transfer Air Subsystem (FVZ4s) Return Air Flow Diagram
.1-11 Facility Ventilation Zone 4 (FVZ4) Air Handling Units (AHUs) (Typical)
.1-12 Facility Ventilation Zone 4 Exhaust Subsystem (FVZ4) Distribution Flow Diagram
.7-1 TPS Process Flow Diagram 2-1 Vacuum Transfer System Process Flow Diagram 6-1 PVVS Process Flow Diagram 6-2 N2PS Process Flow Diagram 7-1 RLWI System Process Flow Diagram 7-2 RLWS Uranium Liquid Waste Tanks Process Flow Diagram 7-3 RLWS Liquid Waste Collection Tanks Process Flow Diagram 7-4 RLWS Liquid Waste Blending Tanks Process Flow Diagram 7-5 RDS Process Flow Diagram 7-6 FNHS Process Flow Diagram NE Medical Technologies 9-vi Rev. 0
onym/Abbreviation Definition S American Glovebox Society U air handling unit RA as low as is reasonably achievable S American Nuclear Society SI American National Standards Institute ME American Society of Mechanical Engineers atmosphere (unit of pressure)
VC Boiler and Pressure Vessel Code AS criticality accident alarm system O Chemical Hygiene Officer curies (unit of measurement of radioactivity)
AA Crane Manufacturers Association of America cesium W dry active waste depleted uranium NE Medical Technologies 9-vii Rev. 1
onym/Abbreviation Definition C emergency support center FAS engineered safety features actuation system HS facility chilled water system RS facility chemical reagent system U fan coil unit CS facility data and communication system WS facility demineralized water system S facility fire detection and suppression system A fire hazards analysis WS facility heating water system HS facility nitrogen handling system Fire Protection Program WS facility potable water system S facility sanitary drain system R facility structure NE Medical Technologies 9-viii Rev. 1
onym/Abbreviation Definition 4 facility ventilation zone 4 4e FVZ4 exhaust subsystem 4r FVZ4 room cooling recirculation subsystem 4s FVZ4 supply and transfer air subsystem gram l gram of uranium per liter PE high-density polyethylene PA high efficiency particulate air I human machine interface LC high-performance liquid chromatogrpahy AC heating, ventilation, and air conditioning 1 iodine-131 S irradiation cell biological shield
-MS inductively coupled plasma mass spectroscopy
-OES inductively coupled plasma optical emission spectroscopy irradiation facility NE Medical Technologies 9-ix Rev. 1
onym/Abbreviation Definition impurity removal system information technology irradiation unit iodine and xenon purification and packaging liter S quality control and analytical testing laboratories low enriched uranium lower flammability limit PS light water pool system PS molybdenum extraction and purification system S material handling system S molybdenum isotope product packaging system 99 molybdenum-99 S nitrogen purge system AS neutron driver assembly system PA National Fire Protection Association NE Medical Technologies 9-x Rev. 1
onym/Abbreviation Definition SS Normal Electrical Power Supply System C NDAS service cell HA Occupational Safety and Health Administration public announcement LS primary closed loop cooling system P process control program SS process evacuation separation system S production facility biological shield S process integrated control system B primary system boundary plutonium VS process vessel vent system quality control A radiologically controlled area S radioactive drain system WI radioactive liquid waste immobilization system NE Medical Technologies 9-xi Rev. 1
onym/Abbreviation Definition WS radioactive liquid waste storage CS radioisotope production facility cooling system F radioisotope production facility radiological ventilation Z1 radiological ventilation zone 1 Z1e RVZ1 exhaust subsystem Z1r RVZ1 recirculating subsystem Z2 radiological ventilation zone 2 Z2e RVZ2 exhaust subsystem Z2r RVZ2 recirculating subsystem Z2s RVZ2 supply subsystem Z3 radiological ventilation zone 3 SS subcritical assembly support structure AS subcritical assembly system m standard cubic centimeter per minute sulfur hexafluoride NE Medical Technologies 9-xii Rev. 1
onym/Abbreviation Definition S standby generator system M special nuclear material S Wisconsin Department of Safety and Professional Services MS stack release monitoring system WP solid radioactive waste packaging C structures, systems, and components S storage and separation system AP thermal cycling absorption process RS target gas receiving system GS TSV off-gas system tritium purification system PS TSV reactivity protection system S target solution preparation system S target solution staging system target solution vessel NE Medical Technologies 9-xiii Rev. 1
onym/Abbreviation Definition F ultra high frequency S uninterruptible power supply SS uninterruptible electrical power supply system SS uranium receipt and storage system C/ITS vacuum/impurity treatment subsystem V variable air volume D variable frequency drive P voice over internet protocol vacuum transfer system NE Medical Technologies 9-xiv Rev. 1
.1 HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS
.1.1 RADIOLOGICALLY CONTROLLED AREA VENTILATION SYSTEM radiological ventilation (RV) systems include supply air, recirculating, and exhaust systems required to condition the air and provide the confinement and isolation needed to gate design basis accidents. The SHINE facility utilizes three ventilation systems in the ologically controlled area (RCA) to maintain the temperature and humidity of the RCA and to gress air from areas of least potential for contamination to areas with the most potential for tamination:
- Radiological ventilation zone 1 (RVZ1)
- RVZ1 recirculating subsystem (RVZ1r)
- RVZ1 exhaust subsystem (RVZ1e)
- Radiological ventilation zone 2 (RVZ2)
- RVZ2 exhaust subsystem (RVZ2e)
- RVZ2 supply subsystem (RVZ2s)
- RVZ2 recirculating subsystem (RVZ2r)
- Radiological ventilation zone 3 (RVZ3) re 9a2.1-1 provides the ventilation zone designations within the SHINE facility.
pter 6 provides a detailed description of the SHINE confinement strategy for limiting the ential for release of radioactive materials to occupied spaces and the environment.
.1.1.1 Design Bases design bases of the RV systems include:
- Provide confinement at ventilation zone 1 confinement boundaries. See Chapter 6 for a description of the specific portions of the RVZ1 system credited as being a confinement boundary.
- Provide isolation at the RCA boundary. See Section 7.5 for a description of the specific portions of the RVZ1, RVZ2, and RVZ3 systems that provide the isolation functions.
- Confine airborne radiological materials in an accident scenario.
- Provide ventilation air and condition the RCA environment for workers.
- Provide makeup air and condition the RCA environment for process equipment.
- Filter exhaust streams prior to them being exhausted out of the RCA.
- Maintain occupational exposure to radiation as low as reasonably achievable (ALARA) and to ensure compliance with the requirements of 10 CFR 20.
- Exhaust hazardous chemical fumes.
safety-related portions of the RV systems are constructed to the requirements of pters SPS 362, SPS 363 and SPS 364 of the Wisconsin Administrative Code. Nonsafety-ted piping is designed, installed, tested and inspected in accordance with American Society echanical Engineers (ASME) B31.9, Building Services Piping (ASME, 2017).
NE Medical Technologies 9a2.1-1 Rev. 2
.1.1.2 System Description iological Ventilation Zone 1 Z1 is divided into two subsystems: RVZ1r and RVZ1e. A flow diagram of RVZ1r is provided in ure 9a2.1-2. A flow diagram of RVZ1e is provided in Figure 9a2.1-3.
Z1r provides cooling for systems within the irradiation unit (IU) cell and the target solution sel (TSV) off-gas system (TOGS) cell. RVZ1r recirculates, filters, and cools air within the ell and the TOGS cell. The system includes two fan coil units and associated ductwork and pers per each set of lU/TOGS cells. Each set of RVZ1r units is located within the cooling m and forms a portion of the confinement boundary for the lU/TOGS cells that it serves.
Z1r provides sampling, ventilation, and cleanup connections for the primary confinement.
Z1e exhausts air from the areas with a high potential for contamination in the facility. The air is red and directed out of the SHINE facility through the exhaust stack. The subsystem includes
, filters, ductwork, dampers, and high efficiency filter banks. It also includes the necessary sfer ductwork to allow makeup from the RCA general area into the exhausted areas.
Z1e is designed to maintain ventilation zone 1 areas at a lower pressure than ventilation e 2 areas. The design inhibits backflow with the use of backflow dampers at the discharge of RVZ1e and RVZ2e exhaust fans in order to minimize the spread of contamination. RVZ1e twork provides sampling locations for radiation detectors, fire detection equipment, stack ase monitoring, and an exhaust stack connection point for RVZ2e and the process vessel t system (PVVS).
RVZ1 serves the following areas:
- IU cells
- TOGS cells
- Tritium purification system (TPS) process equipment
- Primary closed loop cooling system (PCLS) expansion tank
- Uranium receipt and storage system (URSS) glovebox
- Radioactive liquid waste immobilization (RLWI) shielded enclosure
- Supercell
- Target solution preparation system (TSPS) glovebox
- Target solution dissolution tanks
- Target solution preparation tank iological Ventilation Zone 2 Z2 includes three subsystems: RVZ2e, RVZ2s, and RVZ2r. A flow diagram of RVZ2e is vided in Figure 9a2.1-4. A flow diagram of RVZ2s air handling units (AHUs) is provided in ure 9a2.1-5. A flow diagram of RVZ2s distribution and RVZ2r is provided in Figure 9a2.1-6.
Z2e exhausts air from the general areas of the RCA. The subsystem includes fans, filters, twork, dampers, and high efficiency filter banks. It also includes the necessary transfer NE Medical Technologies 9a2.1-2 Rev. 2
- from the irradiation facility (IF) general area to the TPS room;
- from each of the cooling rooms to the IF general area;
- from the storage to the preparation room;
- from the transfer aisle to the storage room;
- from the analytical lab to the quality control (QC) lab;
- from the QC lab to the workspace;
- from RCA labyrinth to the workspace; and
- from the workspace to the transfer aisle.
Z2 provides ventilation and humidity control for ventilation zone 2 rooms within the RCA.
Z2e provides an exhaust path for the QC lab and analytical laboratory fume hoods within the A and maintains the QC lab and analytical labs at positive pressure with respect to the tilation zone 2 general area. The system is designed to maintain the RCA at a lower pressure n areas outside of the RCA. The RVZ2e design inhibits backflow within ductwork that could ead contamination. RVZ2e ductwork provides sampling locations for engineered safety ures actuation system (ESFAS) radiation detectors and fire detection equipment.
Z2s supplies conditioned outside air into the RCA to provide ventilation and to make up for Z1e and RVZ2e exhaust volumes. The system includes AHUs, filters, ductwork, and pers. RVZ2s provides cooling, heating, humidification for all systems within ventilation e 2 as well as maintains the QC lab and analytical labs at positive pressure with respect to ventilation zone 2 general area.
Z2r recirculates, filters, and conditions air within the RCA. The system includes AHUs, filters, twork, and dampers. The RVZ2r units are located within the RCA. RVZ2r provides additional ling for systems within ventilation zone 2. RVZ2r is also used to cool air being supplied to the ercell, which reduces the flow rate required to cool the equipment within the supercell. The rs and bubble-tight dampers on the inlet side of the supercell are part of RVZ1e.
as served by RVZ2 include:
- TPS fume hoods
- QC lab hood
- Analytical lab hood
- RCA exhaust filter room
- Access control area
- Don/doff rooms
- Decontamination room
- Labyrinths
- Analytical lab
- QC lab
- Workspace
- Transfer aisle
- Radioisotope process facility cooling system (RPCS) room
- Storage rooms
- Preparation room
- Tool crib NE Medical Technologies 9a2.1-3 Rev. 2
- IF general area
- Neutron driver assembly system (NDAS) service cell
- TPS room
- Supercell iological Ventilation Zone 3 er normal operating conditions, RVZ3 transfers air from ventilation zone 4 to ventilation e 3 then from ventilation zone 3 to ventilation zone 2 via engineered pathways. RVZ3 eives air from RVZ2s in the IF exit labyrinth. A flow diagram of RVZ3 is provided in ure 9a2.1-7. Under accident conditions, bubble tight dampers close, isolating ventilation e 2. The design of RVZ3 inhibits backflow within ductwork that could spread contamination.
.1.1.3 System Operation Z1e areas draw ambient supply air from adjacent ventilation zone 2 spaces, except for the ercell. During normal operation, areas ventilated by RVZ1e are maintained at negative ssure with respect to their surrounding ventilation zone 2 spaces. The supercell is supplied air ctly from RVZ2r. The air supplied to the supercell is exhausted by RVZ1e.
Z1e contains redundant fans that are capable of continuous operation. During normal ration, one fan is operating while the other fan is on standby. If the operating fan fails, the dby fan will start automatically.
exhaust from RVZ1e areas collects in the RVZ1e system duct header and then is drawn ugh the final filter banks on the mezzanine. These filter banks contain high efficiency iculate air (HEPA) filters and carbon adsorbers upstream of the building isolation dampers.
se filters and adsorbers are equipped with differential pressure monitoring equipment and are odically monitored by operations personnel. The building isolation dampers are safety-related omatic isolation dampers controlled by ESFAS. These dampers are located at the RCA ndary, upstream of the exhaust fans and exhaust stack.
ative pressure is maintained in the ductwork to control contamination and maintain pressure dients. System operation between RVZ1e, RVZ2e, and RVZ2s is coordinated such that the rall airflow and pressure gradients are maintained. The pressure gradients create flow erns that direct air towards areas of increasing contamination potential. This is maintained by variable frequency drives (VFDs) on the exhaust fans. Minimum airflow will be maintained ng normal system operation.
ing upset conditions, affected sections of the RVZ1e, RVZ2s, and RVZ2e ventilation systems isolated as required for the specific event or indication. Bubble tight dampers close, based on ection of increased radiation. The RVZ1e supply flow path to the supercell includes safety-related HEPA and carbon filters. The RVZ1e exhaust flow path from the supercell udes nonsafety-related HEPA filters and safety-related carbon filters. The remaining RVZ1e paths that exhaust confinements for fission products contain nonsafety-related HEPA and bon filters. The RVZ1e safety-related, redundant bubble-tight dampers are situated as near to confinement boundary as practical.
NE Medical Technologies 9a2.1-4 Rev. 2
rumentation and redundant isolation valves. Between the RVZ1e IU cell radiation rumentation and RVZ1e IU cell ventilation valves is an isolation lag tank. If radiation asurements exceed predetermined limits, the TSV reactivity protection system (TRPS) ates an IU Cell Safety Actuation, which closes the RVZ1e IU cell ventilation valves. The ation lag tank provides an exhaust gas delay time greater than the closing time of the valves.
n loss of power, loss of signal, or ESFAS initiation of confinement, dampers seal the affected finement areas within 30 seconds.
RVZ1r fan coil units (FCUs) are capable of continuous operations. The RVZ1r recirculates, cools air within the IU cell and TOGS cell. The IU cell and TOGS cell are established as low age boundaries.
Z2e fans are capable of continuous operation. RVZ2e exhausts the various normally upiable rooms within the RCA as well as fume hoods, filters the air via HEPA filter banks and harges to the facility stack. Exhaust headers are maintained at a negative pressure by the D. Negative pressure is maintained in the ductwork to control contamination and maintain ssure gradients. The exhaust from RVZ2 areas collects in the RVZ2 system duct header and n is drawn through final HEPA filters and carbon adsorbers prior to discharge to the exhaust k.
ing normal operation, ventilation zone 2 areas are maintained at negative pressure with pect to RVZ3 airlocks. The speed of the RVZ2e exhaust fans is controlled to maintain a ative pressure setpoint in the RVZ2e exhaust header. Minimum airflow will be maintained ng normal system operation.
Z2s AHUs are capable of continuous operation. Ventilation zone 2 and portions of ventilation e 3 areas are directly supplied air via the RVZ2s AHUs. The AHUs supply conditioned, percent outside air. Each AHU contains filters, pre-heat and cooling coils, and supply fans.
supply system includes redundant AHUs. If a single AHU fails, the standby AHU will start omatically. The AHUs normally supply a constant volume of conditioned air to RVZ2 and Z3 areas.
RVZ2s supply duct contains safety-related automatic isolation dampers controlled by FAS. These dampers are located at the RCA boundary.
Z2r AHUs are capable of continuous operation. The RVZ2r AHUs further condition the air in RCA general area to comfort levels.
RVZ1e and RVZ2e subsystems combine downstream of each subsystems respective filter ks, RCA isolation bubble-tight dampers, and exhaust fans, as shown in Figure 9a2.1-8. The VS delay bed discharge is also combined with the RVZ1e and RVZ2e flow downstream of the aust fans and upstream of the stack release monitor. The discharge of the stack is roximately 10 feet above the roofline of the facility and will maintain a minimum discharge city of 3,000 fpm.
NE Medical Technologies 9a2.1-5 Rev. 2
RV systems are designed such that the process integrated control system (PICS) monitors system equipment, flow rates, pressures, and temperatures. Instrumentation monitors the tilation systems for off-normal conditions and signal alarms as required. The PICS starts, ts down, and operates the RV system in normal operating modes. Coordinated controls ntain negative pressurization to create flow patterns that direct air toward areas of increasing tamination potential.
S monitors the differential pressures across all the filters in the RVZ1e and RVZ2e filter ks and produces an alarm if the differential pressure of any filter is above its established limit.
.1.1.5 Inspection and Testing ventilation systems are balanced upon installation. Control systems are tested to assure that trol elements are calibrated and properly adjusted. Safety-related isolation dampers are ected and tested as required by, and in accordance with, Section DA of ASME AG-1, Code Nuclear Air and Gas Treatment (ASME, 1999). Safety-related ductwork will be inspected and ed as required by, and in accordance with, Section SA of ASME AG-1 (ASME, 1999).
.1.1.6 Nuclear Criticality Safety section 6b.3.2.7 provides a discussion related to the nuclear criticality safety requirements he URSS glovebox ventilation. Subsection 6b.3.2.4 provides discussion related to the lear criticality safety requirements for the TSPS glovebox ventilation.
.1.1.7 Technical Specifications tain material in this subsection provides information that is used in the technical cifications. This includes limiting conditions for operation, setpoints, design features, and ans for accomplishing surveillances. In addition, significant material is also applicable to, and y be used for, the bases that are described in the technical specifications.
.1.2 NON-RADIOLOGICAL AREA VENTILATION SYSTEM non-radiological area ventilation system is the facility ventilation zone 4 (FVZ4) system.
tilation zone 4 consists of areas which are located within the SHINE facility, but outside of the A. The FVZ4 system is completely independent of the RV systems described in section 9a2.1.1. The FVZ4 system supply AHUs draw at least 10 percent outside air to make or air exhausted and exfiltrated. The outside air is mixed with recirculated air and conditioned ugh the AHUs before being supplied to FVZ4 areas. FVZ4 exhaust streams exhaust directly he outside of the SHINE facility. No radiation detectors are provided in the FVZ4 exhaust, as tamination is not expected to be present in the FVZ4 system.
NE Medical Technologies 9a2.1-6 Rev. 2
design bases for the FVZ4 system include:
- Provide environmental conditions suitable for personnel and equipment, and to maintain positive pressure with respect to the RCA.
- Provide outside makeup air for ventilation and pressurization for spaces outside of the RCA.
- Remove hazardous chemical fumes from spaces outside of the RCA.
4 is constructed to the requirements of Chapters SPS 362, SPS 363 and SPS 364 of the consin Administrative Code.
.1.2.2 System Description FVZ4 system is nonsafety-related. The FVZ4 system is a variable air volume (VAV) type ting, ventilation and air conditioning (HVAC) system that supplies conditioned air into tilation zone 4 areas. The FVZ4 system supplies outside air as required and exhausts air to ntain indoor design conditions in ventilation zone 4 areas. The FVZ4 provides transfer air into austed ventilation zone 4 rooms and into the RVZ3 system airlocks. The FVZ4 system is prised of the following three subsystems:
- FVZ4 supply and transfer air subsystem (FVZ4s)
- FVZ4 exhaust subsystem (FVZ4e)
- FVZ4 room cooling recirculation subsystem (FVZ4r)
.1.2.3 System Operation 4 Supply and Transfer Air Subsystem (FVZ4s) supply air subsystem provides conditioned air for workers and equipment in the non-RCA ion of the facility, makeup air for exhaust air systems, and outside air to maintain positive ssure with respect to the RCA. The distribution of the FVZ4s is provided in Figure 9a2.1-9.
supply AHU draws outside air to make up for air exhausted and exfiltrated. The outside air is ed with the return air recirculated from the spaces served by FVZ4s and conditioned through AHU before being supplied to the non-RCA areas of the facility. Each AHU contains filters, ting and cooling coils, and supply fans. The FVZ4s subsystem includes two AHUs, each d for 100 percent of total system capacity. One FVZ4s subsystem AHU operates at a time the other unit on standby. The AHUs normally supply a variable volume of conditioned air to tilation zone 4 areas, with a minimum flow determined by ventilation requirements mpers are provided to isolate the FVZ4s subsystem to each battery room and each terruptible power supply (UPS) room, independently, on an initiation signal from each tions fire suppression system.
ow diagram of the return air associated with the FVZ4s subsystem is provided in ure 9a2.1-10. A diagram of the FVZ4s subsystem AHUs is provided in Figure 9a2.1-11.
NE Medical Technologies 9a2.1-7 Rev. 2
4e serves the following locations of the non-RCA area of the facility:
- Janitor closets
- Chemical storage
- Restrooms
- Battery rooms
- Control room FVZ4e subsystem exhausts the battery rooms and UPS rooms within ventilation zone 4 to ntain the hydrogen concentration below 2 percent and the temperature under 120°F. Upon a of power, the battery rooms will be exhausted by dedicated fans powered by the standby erator system (SGS).
mpers are provided to isolate the FVZ4 exhaust air subsystem to each battery room and each S room, independently, on an initiation signal from each locations fire suppression system.
distribution of the FVZ4e subsystem is provided in Figure 9a2.1-12.
4 Room Cooling Recirculation Subsystem (FVZ4r)
FVZ4r subsystem recirculates and cools air within the human machine interface (HMI)/
communication room and the process/server room. The system is made up of two split tems that cool the server space. The FVZ4r subsystem provides equipment status to the S.
.1.2.4 Radiation Protection and Criticality Safety re are no radiation contamination hazards or criticality safety hazards associated with the 4 system.
.1.2.5 Instrumentation and Control supply air subsystem HVAC controls operate through the PICS. The FVZ4 system is igned such that the PICS monitors and controls the non-RCA recirculation air subsystem tilation equipment, flow rates, pressures, and temperatures. Instrumentation monitors the tilation systems for off-normal conditions and signal alarms as required.
PICS performs the following functions relative to FVZ4:
- starts, shuts down, and operates FVZ4 in normal operating modes;
- monitors the return and supply temperature from the AHUs; and
- monitors the pressure differential across the filters.
.1.2.6 Inspection and Testing FVZ4 system is balanced upon installation. HVAC control systems are tested to assure that trol elements are calibrated, adjusted, and in proper working condition.
NE Medical Technologies 9a2.1-8 Rev. 2
re are no technical specification parameters associated with the FVZ4.
.1.3 FACILITY CHILLED WATER SYSTEM facility chilled water system (FCHS) is a closed-loop, forced circulation system which vides chilled water to the cooling coils of the RVZ2s subsystem AHUs, which are located ide of the RCA. FCHS also provides chilled water to the cooling coils of the FVZ4 AHUs. The HS rejects heat to the atmosphere.
.1.3.1 Design Bases design bases of the FCHS include:
- Circulate chilled water through the cooling coils of RVZ2s subsystem AHUs.
- Circulate chilled water through the cooling coils of the FVZ4 AHUs.
FCHS is constructed to the requirements in Chapters SPS 361 and SPS 363 of the consin Administrative Code.
.1.3.2 System Description FCHS is nonsafety-related. Primary components of the FCHS include:
- Air-cooled chillers;
- Chilled water pumps, associated piping and valves, and makeup water and water treatment equipment; and
- An expansion tank.
.1.3.3 System Operation system is powered by the normal electrical power supply system (NPSS) under normal rating conditions.
system is a variable closed-loop cooling system using VFDs on each centrifugal pump to ply a single pump header. Each chiller supply line maintains a modulating flow control valve able of fully-open or fully-closed valve position. Each RVZ2s subsystem and FVZ4 AHU ling fluid supply line maintains a modulating flow control valve capable of fully-open or fully-ed valve position. System flow, temperature, and differential pressures are utilized by an HS controller to signal valves, pumps, and chillers to come online, vary speed, or secure as essary to meet system setpoints during normal system operation.
S monitors the RVZ2s and FVZ4 airstream delivery temperatures. An FCHS controller nitors flow control valve position and delivers a signal to individual valves to adjust cooling er flow rates in response to signals sent to the load instrumentation. A flow control valve is ntained on the system bypass line and is controlled by input signals from FCHS controller ts made by chiller supply, RVZ2s, and FVZ4 modulating flow control valves.
NE Medical Technologies 9a2.1-9 Rev. 2
n issued from the control panel, an alarm is generated at the control panel and the standby p is automatically started.
al chiller equipment monitors differential pressures across each chiller and the chillers ning status. Upon communication of a fault alarm, an FCHS controller isolates that chillers dulating flow control valve and issues a start command to the back-up chiller. System pumps pond accordingly to the loading of the chillers via a local controller. Chiller fault alarms on tiple chillers initiates an automatic shutdown of the system through an FCHS controller.
system maintains alarms monitored by PICS and displays them at operator workstations for tem volumes out of range.
.1.3.4 Radiation Protection re are no radiation contamination hazards associated with the FCHS.
.1.3.5 Instrumentation and Controls rumentation monitors the system for off-normal conditions and signal alarms as required.
HS controls are nonsafety-related.
FCHS provides the necessary output signal to the PICS for the monitoring of heating water peratures, pressures, and flow rates.
.1.3.6 Inspection and Testing FCHS testing requirements for water piping, pipe supports, and valves are in accordance ASME B31.9, Building Services Piping (ASME, 2017). Hydrostatic tests are performed in ordance with Section 937.3 of ASME B31.9 (ASME, 2017). Visual welding inspections are ormed on piping and piping supports in accordance with ASME B31.9 (ASME, 2017).
.1.3.7 Technical Specifications re are no technical specification parameters associated with the FCHS.
.1.4 FACILITY HEATING WATER SYSTEM facility heating water system (FHWS) is a hydronic hot water heating system configured in a able primary flow piping arrangement.
.1.4.1 Design Bases design bases of the FHWS include:
- Supply heated water to the RVZ2s subsystem and the FVZ4 system as well as other heating coils outside of the RCA.
- Maintain system operation in the event of a single pump or single boiler failure.
NE Medical Technologies 9a2.1-10 Rev. 2
National Fire Protection Association (NFPA) 54, National Fuel Gas Code (NFPA, 2018), as uired by Chapter SPS 365 of the Wisconsin Administrative Code.
.1.4.2 System Description FHWS is nonsafety-related.
FHWS consists of equipment required to deliver heating hot water to RVZ2 and FVZ4 AHUs on-RCA portions of the SHINE facility. The boilers, pumps, air separator and expansion tank in the resource outbuilding. Three boilers and three pumps are provided to maintain the tem flow rate and supply temperature. When one pump or boiler is down for maintenance, 50 percent capacity pumps and boilers are capable of meeting system demands. Two ps each are provided on the FVZ4s subsystem and the RVZ2s subsystem to maintain freeze ection. When one pump is down for maintenance the other can ensure freeze protection.
primary components of the FHWS include:
- three 50 percent natural gas-fired boilers;
- three 50 percent centrifugal hot water pumps;
- eight 100 percent centrifugal hot water circulating pumps for heating coil freeze protection;
- an air separator; and
- an expansion tank.
.1.4.3 System Operation ngle set of pumps provides flow through both the boilers and the heating coils. The flow ugh the system is varied by modulating the pump speed based upon maintaining the perature differential across the boilers. A bypass valve (supply to return) is installed at the of the coil loop piping to maintain the minimum flow required to operate the pumps.
h boiler is a natural gas-fired, fully modulating condensing type with high mass and high me to allow large variations in flow through the boiler with no minimum return water perature requirement and low water pressure drop.
.1.4.4 Radiation Protection and Criticality Safety re are no radiation contamination hazards or nuclear criticality safety hazards associated with FHWS.
.1.4.5 Instrumentation and Control FHWS provides the necessary output signal to the PICS for the monitoring of heating water peratures, pressures, and flow rates. Low water cutoff controls and flow sensing controls are vided which automatically stop the combustion operation of the boiler when the water level ps below the lowest acceptable water level or when water circulation stops. Boilers are ipped with controls and limit devices, as required by the manufacturer.
NE Medical Technologies 9a2.1-11 Rev. 2
WS piping is designed, installed, tested and inspected in accordance with ASME B31.9, ding Services Piping (ASME, 2017).
FHWS testing requirements for water piping, pipe supports, and valves are in accordance ASME B31.9 (ASME, 2017). Hydrostatic tests are performed in accordance with tion 937.3 of ASME B31.9 (ASME, 2017). Visual welding inspections are performed on ng and piping supports in accordance with ASME B31.9 (ASME, 2017).
.1.4.7 Technical Specifications re are no technical specification parameters associated with the FHWS.
NE Medical Technologies 9a2.1-12 Rev. 2
Security-Related Information - Withheld under 10 CFR 2.390(d)
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Ventilation System Zone Designations Within the SHINE Facility SHINE Medical Technologies 9a2.1-13 Rev. 2
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 1 Recirculating Cooling Subsystem (RVZ1r)
Flow Diagram SHINE Medical Technologies 9a2.1-14 Rev. 2
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 1 Exhaust Subsystem (RVZ1e) Flow Diagram
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SHINE Medical Technologies 9a2.1-15 Rev. 2
Security-Related Information - Withheld under 10 CFR 2.390(d)
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 2 Exhaust Subsystem (RVZ2e) Flow Diagram SHINE Medical Technologies 9a2.1-16 Rev. 2
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 2 Supply Subsystem (RVZ2s) Air Handling Units (AHUs)
SHINE Medical Technologies 9a2.1-17 Rev. 2
Security-Related Information - Withheld under 10 CFR 2.390(d)
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 2 Supply Subsystem (RVZ2s) and Radiological Ventilation Zone 2 Recirculating Cooling Subsystem (RVZ2r) Flow Diagram SHINE Medical Technologies 9a2.1-18 Rev. 2
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 3 (RVZ3) Flow Diagram SHINE Medical Technologies 9a2.1-19 Rev. 2
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Radiological Ventilation Zone 1 Exhaust Subsystem (RVZ1e) and Radiological Ventilation Zone 2 Exhaust Subsystem (RVZ2e) Mezzanine SHINE Medical Technologies 9a2.1-20 Rev. 2
Security-Related Information - Withheld under 10 CFR 2.390(d)
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Facility Ventilation Zone 4 Supply and Transfer Air Subsystem (FVZ4s) Distribution SHINE Medical Technologies 9a2.1-21 Rev. 2
Security-Related Information - Withheld under 10 CFR 2.390(d)
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Facility Ventilation Zone 4 Supply and Transfer Air Subsystem (FVZ4s) Return Air Flow Diagram SHINE Medical Technologies 9a2.1-22 Rev. 2
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Facility Ventilation Zone 4 (FVZ4) Air Handling Units (AHUs) (Typical)
SHINE Medical Technologies 9a2.1-23 Rev. 2
Security-Related Information - Withheld under 10 CFR 2.390(d)
Chapter 9 - Auxiliary Systems Heating, Ventilation, and Air Conditioning Systems Figure 9a2.1 Facility Ventilation Zone 4 Exhaust Subsystem (FVZ4) Distribution Flow Diagram SHINE Medical Technologies 9a2.1-24 Rev. 2
2.1 INTRODUCTION
section describes the handling and storage of target solution within the irradiation facility
. The chemical properties of the target solution are described in Section 4a2.2, including nium concentration, density, and pH.
ailed descriptions of the processes involving irradiated and unirradiated special nuclear erial (SNM), including the byproduct material produced as a result of the irradiation of SNM, provided in Section 4b.4. Equipment, application of administrative controls, and design ures related to the target solution lifecycle are also discussed in Section 4b.4. A detailed cription of the target solution lifecycle is provided in Section 9b.2.
sical protection of the target solution from theft or diversion is ensured via the implementation he Physical Security Plan, described in Section 12.8. The primary closed loop cooling system LS) removes heat from the target solution vessel (TSV), neutron multiplier, and components he subcritical assembly system (SCAS) during irradiation of the target solution, as described ection 5a2.2. Radiological considerations during normal operations related to the handling storage of target solution are described in Section 11.1. An analysis of accident scenarios lving the mishandling or malfunction of target solution within the IF is provided in section 13a2.1.4.
.2.2 IRRADIATION FACILITY TARGET SOLUTION STORAGE AND HANDLING r target solution is prepared and qualified in the target solution preparation system (TSPS), it ansferred to the target solution hold tank prior to transfer into the TSV. Target solution is sferred from the target solution hold tank to the TSV via the TSV fill lift tank.
target solution hold tank is at an elevation below that of the TSV to prevent an accidental vity-driven transfer of target solution to the TSV. The vacuum transfer system (VTS) is used to sfer the target solution to the TSV in a controlled manner, both with respect to fill rate and fill me. A description of the incremental process used to fill the TSV is provided in tion 4a2.6.1. Target solution batches that have been previously irradiated are returned to the et solution hold tank from processes in the hot cells or from the target solution storage tank.
.2.3 IRRADIATION FACILITY TARGET SOLUTION HANDLING EQUIPMENT following is a list of major equipment that interacts with target solution in the IF.
- Target Solution Vessel
- Quantity: 8
- Location: Inside irradiation unit (IU) cell
- TSV Dump Tank
- Quantity: 8
- Location: Inside IU cell NE Medical Technologies 9a2.2-1 Rev. 0
age of target solution in the IF is limited to storage in the TSV dump tanks following irradiation in TSV.
.2.5 CRITICALITY CONTROL FEATURES tection against inadvertent criticality in the TSV dump tank is discussed in section 4a2.6.3. Protection against inadvertent criticality in the TOGS is discussed in section 4a2.8.5. Reactivity control for the SCAS is discussed in Section 4a2.6.
.2.6 BIOLOGICAL SHIELDING irradiation cell biological shield (ICBS) ensures that the projected radiation dose rates and umulated doses in occupied areas within the IF do not exceed the limits of 10 CFR 20.
hermore, the dose reduction by the ICBS supports the radiation exposure goals defined in as low as reasonably achievable (ALARA) Program, as described in Section 11.1.
tion 4a2.5 provides a detailed description of the ICBS.
.2.7 TECHNICAL SPECIFICATIONS trols on target solution during handling and storage, including testing and surveillance, are cribed in the technical specifications.
NE Medical Technologies 9a2.2-2 Rev. 0
.3.1 FIRE PROTECTION PLAN AND PROGRAM Fire Protection Plan describes the overall facility Fire Protection Program (FPP). The FPP cribes the fire protection organization and responsibilities, design and programmatic roach, and means to limit the probability and consequences of fire at the SHINE facility. The Protection Plan establishes the requirements to be satisfied by the facility fire protection gram. This plan establishes a program that represents an integrated effort involving ponents, procedures, analyses, and personnel used in defining and carrying out activities of protection. It includes system and facility design, fire prevention, fire detection, annunciation, finement, suppression, administrative controls, inspection and maintenance, training, quality urance, and testing. The established fire protection program elements, systems, structures, components are subject to the SHINE Quality Assurance Program, as described in the lity Assurance Program Description. The elements of the FPP work together to satisfy the uirements of applicable regulatory requirements presented in 10 CFR 50.48(a). The FPP is prised of the following lower tier documents which are developed and maintained as part of overall FPP.
- Fire Hazards Analysis (FHA);
- Safe Shutdown Analysis;
- Pre-Fire Plans; and
- Administrative controls (e.g., implementing procedures, drawings, calculations, analyses, specifications).
elopment of the FPP is informed by the guidance provided in National Fire Protection ociation (NFPA) 801, Standard for Fire Protection for Facilities Handling Radioactive erials (NFPA, 2014). The structure and content of the FPP are based on the precepts of CFR 50.48(a) and NFPA 801. The FPP ensures, through the application of the defense-in-th concept, that a fire will not prevent the performance of necessary safety-related functions that radioactive releases to the environment, in the event of fire, will be minimized.
.3.2 DESIGN BASES concept of defense-in-depth is fundamental to the FPP. Fire protection defense-in-depth for SHINE facility is defined as follows:
- Prevent fires from starting, including limiting combustible materials;
- Detect, control, and extinguish those fires that do occur to limit consequences; and
- Provide protection for safety-related structures, systems, and components (SSCs) so that a continuing fire will not prevent the safe shutdown of the irradiation units or cause an uncontrolled release of radioactive material to the environment.
FPP is developed and implemented to accomplish these criteria.
.3.3 FIRE HAZARD ANALYSIS foundation of the facility fire protection design is the FHA. The FHA establishes and cribes individual facility fire areas, which are unique areas separated by fire-rated struction or administrative controls to prevent the spread of fire between adjacent fire areas.
NE Medical Technologies 9a2.3-1 Rev. 1
ired confinement/control of postulated fires. The analysis demonstrates the adequacy of ection provided, and, if necessary, the need for additional protection.
primary objectives of the FHA are:
- Establish or identify fire area boundaries,
- Identify fire hazards within the analyzed area,
- Determine worst case fire effects on safe shutdown capability of the irradiation units (IUs) and the potential for uncontrolled release of radioactive materials, and
- Evaluate the adequacy of fire protective features provided.
FHA is maintained in accordance with the FPP for identified fire areas and facility changes.
.3.4 SAFE SHUTDOWN ANALYSIS FPP includes performance of a safe shutdown analysis to demonstrate a means of safe tdown of the SHINE IUs to ensure they can be placed and maintained in a safe and stable dition following a severe fire in any facility fire area. The analysis also considers the effect of ere fires on safety-related equipment required to prevent uncontrolled releases of radioactive erial. A deterministic evaluation is conducted on a fire area by fire area basis to ascertain ential damage and assess the effectiveness of the provided protection.
fire safe shutdown analysis identifies the means by which safe shutdown of the IUs is omplished and uncontrolled release of radioactive material is prevented for a fire in each lity fire area. Conduct of the safe shutdown analysis is discussed in detail in implementing cedures and reports. Analysis of safe shutdown and prevention of uncontrolled release of oactive material for the facility is generally conducted through conduct of the following types nalyses:
- Development of performance goals and analysis methodology
- Selection of credited equipment and systems
- Performance of cable selection and circuit analysis
- Performance of functional analysis
- Development of necessary safe shutdown implementing procedures
.3.5 ADMINISTRATIVE CONTROLS ministrative controls and procedures are established by the FPP to ensure satisfaction of the gram goals and maintenance of a fire safe workplace. These procedures ensure policies and cedures are in place to minimize the possibility of fire and to provide equipment and systems essary to mitigate the effects of fires that do occur. Each of the fire-related procedures is igned to strengthen the defense-in-depth approach to fire protection.
.3.6 REGULATORY AND CODE REQUIREMENTS NE fire protection systems are designed to comply with the applicable portions of the onally recognized codes and standards identified below. Adherence to these codes and dards ensures that the facility fire protection features and systems are available to perform NE Medical Technologies 9a2.3-2 Rev. 1
- 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 facility into fire areas separated by fire-rated barriers.
- Separate redundant safety-related components and associated electrical divisions to ensure the capability to achieve and maintain safe shutdown and prevent uncontrolled releases of radioactive material as a result of fire.
- Provide confidence that failure or inadvertent operation of firefighting systems does not significantly impair the safety capability of credited SSCs.
- Provide incipient firefighting capability and access for professional firefighters.
- Minimize exposure to personnel and releases to the environment of radioactivity or hazardous chemicals as a result of a fire.
facility fire protection features and systems are classified as nonsafety-related and generally
-seismic. Facility fire protection features and systems are not required to remain functional wing a design basis accident or the most severe natural phenomena.
design, installation, testing, and surveillance of the facility fire protection features and tems are based on applicable guidance from nationally recognized codes and standards. The es and standards used and the code-of-record is as defined in the FPP and applicable design umentation.
.3.7 FACILITY FIRE PROTECTION SYSTEM DESCRIPTION facility is subdivided into fire areas that are separated by fire-rated barriers to limit the spread re. The fire area boundaries are described and illustrated in the FHA. In each fire area, the lity fire detection and alarm system provides for the detection and alarm of fire conditions.
ility fire suppression systems and manual firefighting capability provide for the suppression of
- s. These systems consist of the following:
- Detection systems for early detection and notification of fire;
- Fixed automatic fire suppression systems;
- Manual fire suppression systems and equipment, including hydrants, standpipes, hose stations, and portable fire extinguishers; and
- A fire water supply system including the fire pump, yard main, and interior distribution piping.
facility FPP and lower tier documentation provide a complete description of the facility fire ection features and systems.
.3.8 RADIOLOGICAL FIRE HAZARDS ionable materials in the form of low-enriched uranium metal and uranium oxide are brought the facility and used to produce target solution. Target solution is an aqueous uranyl sulfate tion which is irradiated to produce molybdenum-99 (Mo-99) and other medical isotopes.
owing irradiation, the target solution is transferred through piping and tanks for chemical cessing in the radioisotope production facility (RPF) to extract Mo-99, other radioisotopes, NE Medical Technologies 9a2.3-3 Rev. 1
rce that can drive release. Radiological release due to fire is typically associated with bustion of radiologically contaminated ordinary combustible materials or fire damage to finement systems that could allow release of collocated radiological materials.
nium oxide and uranium metal are received and stored in the uranium receipt and storage tem (URSS) room. Storage of the uranium metal and uranium oxide is in metal storage isters. Canisters are stored on metal storage racks to ensure a safe configuration of the ed materials. Uranium metal is received in sufficiently massive configurations that it is not ophoric.
TSPS and URSS rooms are protected with automatic fire detection and provided with ropriate portable fire extinguishers for incipient stage fire suppression. Combustible loading ese rooms is maintained low to prevent fire. Fire response using water-based extinguishants rohibited; elevated floors of the URSS and TSPS fire area are provided to prevent flooding of e rooms.
diation is performed in the irradiation facility (IF). Chemical processing, to extract medical opes from the target solution, is performed in the RPF. The irradiation and chemical cessing of radiological materials is discussed in detail in Chapter 4.
e target solution is introduced to the irradiation process, it is contained in pipes and tanks.
se pipes and tanks are located in the IU cells, hot cells, tank vaults, and pipe trenches ughout the IF and RPF. The IU cells, hot cells, tank vaults, and pipe trench structures are structed of massive steel and concrete barriers to provide radiation shielding. The monolithic struction of these structures provides significant fire separation from the general areas of the nd RPF. This construction provides protection to the pipes and tanks containing radiological erials. Combustible loading in the spaces within the IU cells, hot cells, tank vaults, and pipe ches is maintained very low. Combustible materials in these spaces are limited to cable and ipment. Combustible loading in the IF and RPF general areas is maintained low to present a imal potential for fire. The IF and RPF general areas are equipped with automatic fire ection and provided with portable fire extinguishers to provide incipient fire suppression ability.
rs contained in the facility ventilation systems that may contain fission products are replaced a regular basis. Filters are contained in non-combustible ductwork. Areas of the radiologically trolled area (RCA) containing filters are protected with automatic fire detection and portable extinguishers. Combustible loading is maintained low in these areas.
carbon guard beds located in the process vessel vent system (PVVS) are equipped with perature detection. The guard beds are isolated upon indication of an unacceptable increase mperature. The carbon delay beds are monitored with in-bed temperature detection and bon monoxide detectors at the outlet of each carbon delay bed group. The carbon delay beds equipped with a nitrogen purge line that may be used to extinguish hot spots if detected.
ee facility systems are provided to mitigate hydrogen generation due to radiolysis. These tems are the TSV off-gas system (TOGS), PVVS, and nitrogen purge system (N2PS).
NE Medical Technologies 9a2.3-4 Rev. 1
ng cool down. The TOGS is located in the TOGS cell of each IU. During target solution diation, iodine and noble gases are formed by fission and decay, and hydrogen and oxygen formed by radiolysis. The hydrogen concentration in the TSV headspace is normally ntained below lower flammability limit (LFL) by using air as a sweep gas. The TOGS system escribed in detail in Section 4a2.8.
PVVS provides ventilation for the tanks in the RPF. The system dilutes radiolytic hydrogen erated in RPF tanks and captures or delays radiological off-gas prior to release out the stack.
wers at the discharge of the system develop a slight vacuum to pull air across the headspace ach tank. The flow rates across each tank are balanced such that radiolytic hydrogen erated in each tank is diluted below the hydrogen LFL. The PVVS is described in detail in tion 9b.6.
N2PS provides back-up sweep gas flow in the form of stored, pressurized nitrogen gas.
n a loss of power, or the loss sweep gas flow in an IU as determined by the TSV reactivity ection system (TRPS), solenoid valves on the N2PS discharge manifold will fail open asing nitrogen to the IU cell supply header. Upon a loss of sweep gas flow in an IU, nitrogen supply solenoid isolation valves for that cell will be deenergized to the open position, asing nitrogen gas to the TSV dump tank in that cell. A flow switch will give indication that ogen sweep gas is flowing to the IU cell distribution system. The flow rates into each TSV p tank are balanced such that the radiolytic hydrogen generated in each tank is diluted to eptable concentrations. The sweep gas flows through the TSV dump tank, the TSV, and GS equipment and piping and is discharged into the PVVS.
n a loss of power or loss of sweep gas flow through PVVS as determined by the engineered ty features actuation system (ESFAS), normal radiological ventilation zone 2 (RVZ2) flow is ated and nitrogen purge gas is directed to the RPF distribution header. A flow switch provides cation that nitrogen sweep gas is flowing to the RPF distribution system. The flow rates oss each tank are balanced such that the radiolytic hydrogen generated in each tank is diluted w the LFL. The nitrogen gas flows through the existing PVVS piping and into the PVVS.
.3.9 TECHNICAL SPECIFICATIONS FPP is included in the Administrative Controls section of the Technical Specifications.
uding the FPP in the Administrative Controls section of the Technical Specifications ensures the FPP elements are available and reliable by requiring that testing, surveillance, and ntenance activities are conducted as required.
NE Medical Technologies 9a2.3-5 Rev. 1
facility data and communication system (FDCS) provides the ability to communicate during mal and emergency conditions between the different areas of the main production facility and lity support buildings, as well as locations remote to the SHINE site. Employing the FDCS, NE facility operations staff maintain the ability to contact other facility staff as well as ounce the existence of an emergency to all areas of the site. The FDCS is designed using tiple diverse subsystems such that a failure of any system does not impair the ability of the er systems to function. The nonsafety-related FDCS supports implementation of SHINE ign Criteria 8, Emergency Capability, as described in Table 3.1-3.
FDCS consists of five subsystems:
- Facility voice over internet protocol (VoIP) telephone system
- Facility overhead public announcement (PA) system
- Facility sound-powered telephone system
- Facility radio system (on-site and off-site communications)
- Facility information technology (IT) subsystem
.4.1 TELEPHONES facility uses a commercial telephone communication system that provides for on-site two-communication, paging and public address, and party-line-type voice communications.
tions for this system are located throughout the main production facility and outbuildings. In emergency, this system is available to alert on-site personnel.
telephone system allows personnel to contact or receive calls from any outside telephone ber. In an emergency, this system is used to contact off-site SHINE and emergency support anization personnel, as described in the SHINE Emergency Plan. Designated emergency cell nes are also maintained in the facility control room, emergency support center (ESC) and kup ESC.
part of the telephone communication system, certain phones are designated as private hange phones. Communication between these phones takes priority over any activity from ide of the private exchange. The private exchange system allows for incoming and outgoing
- s. The telephone communication system contains redundant servers and a battery backup as eans of improving the reliability of the phone system, public address, and private exchange munication paths. The system is also provided standby power from the standby generator tem (SGS), as described in Section 8a2.2.
.4.2 PUBLIC ADDRESS SYSTEM PA system uses the telephone communication system to initiate public address ouncements. The system also includes dedicated base transmitting units, which are igned to continue to function in the event of a failure of the phone system. Announcements be made site-wide or to specific predefined zones. The public address system is audible in following areas:
- Occupiable areas of the main production facility radiologically controlled area (RCA)
- Normally occupied areas of the main production facility and support buildings NE Medical Technologies 9a2.4-1 Rev. 0
PA system provides speakers and power distribution for volume levels meeting the audibility uirements of National Fire Protection Association (NFPA) 72, National Fire Alarm and Signaling e, Chapter 24 (NFPA, 2016).
PA system includes a prioritization of phone lines such that announcements from the control m override any other use of the PA system. The public address system uses the same redundant ers and battery backup as the telephone communication system.
.4.3 SOUND-POWERED PHONES nd-powered phones supplement the telephone system for on-site communications. The tem uses portable sound-powered telephones that can plug into local terminal jacks. The nd powered telephones are located in areas where critical operations and response activities anticipated to occur. The sound-powered telephones utilize the users voice to create the essary power for reliable and uninterrupted communications in the event of an emergency.
phones operate independent of any power source and are not affected by loss of power to facility.
.4.4 RADIO SYSTEM d-held portable radios operating on ultra high frequency (UHF) bands are provided. These os are powered by replaceable, rechargeable battery packs and once charged are pendent of facility power until recharging is needed. Base station radios for communication the portable radios are provided in select locations.
radio system contains equipment necessary to communicate with designated off-site ergency support organizations. The system allows for communication with the two primary ergency support organizations (the Janesville Fire Department and the Janesville Police artment) using P25 transmission protocols. Standby power for the facility radio system is vided by the SGS.
.4.5 INFORMATION TECHNOLOGY information technology system provides corporate network services and connectivity to the rnet for the SHINE facility. The IT system supports nonsafety-related personnel information nology needs. The IT system acts as the historian for the process integrated control system S), receiving information from the PICS via data diode such that no inputs can be provided to PICS from off-site sources. The IT system can also be used to transmit information received from S to off-site locations if required.
.4.6 TESTING REQUIREMENTS design of the communications systems permits routine testing and inspection without uption to normal communications. Testing is performed in accordance with the SHINE ergency Plan in order to ensure communications systems operability.
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use of the FDCS for security purposes is addressed in the SHINE Physical Security Plan.
.4.8 TECHNICAL SPECIFICATIONS re are no technical specifications associated with the communication systems.
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section applies to the possession and use of byproduct, source, and special nuclear erial (SNM) within the irradiation facility (IF). Refer to Section 9b.5 for the discussion of session and use of byproduct, source, and special nuclear material in the radioisotope duction facility (RPF).
IF is designated as a radiologically controlled area as shown in Figure 1.3-1. Radiation ection program controls and procedures, including the as low as reasonably achievable ARA) program, applicable to the IF are described in Section 11.1. Radioactive waste nagement is discussed in Section 11.2. A discussion of the Security Plan is provided in tion 12.8. Discussion of the Emergency Plan is included in Section 12.7. Fire protection ails applicable to the IF are described in Section 9a2.3. Technical Specifications include limits apply to the possession, management, and use of byproduct, source, and SNM.
.5.1 BYPRODUCT MATERIAL SHINE facility is designed to generate byproduct materials (e.g., molybdenum-99) for use as dical isotopes. Byproduct materials within the IF include fission and activation products erated during irradiation unit (IU) operations, as well as tritium which is used within the tron driver assembly system (NDAS) to create deuterium-tritium fusion reactions as cribed in Section 4a2.1.
tritium purification system (TPS) controls the distribution and processing of tritium for the AS as described in Section 9a2.7. The quantity of tritium within the facility is described in le 11.1-5. The types and quantities of fission and activation byproduct materials, as well as systems where these byproduct materials are located, are discussed in Section 11.1.
itionally, up to eight (alpha, neutron) neutron sources (e.g., Am-241/Be) with combined ngth up to [ ]SRI are used, one in each IU, for IU start-up operations, as described in tion 4a2.2.
.5.2 SOURCE MATERIAL rce materials in the IF include the depleted uranium (DU) within TPS and the natural uranium tron multiplier within the subcritical assembly. The DU within TPS is used as storage beds for m gas as described in Section 9a2.7. The use of source material within the neutron multiplier escribed in Section 4a2.2. SHINE uses up to 330 lbs (150 kg) of DU and 51,000 lbs.
000 kg) of natural uranium for these purposes.
.5.3 SPECIAL NUCLEAR MATERIAL cial nuclear material (SNM) in the IF includes low enriched uranium (LEU) within the target tion vessel (TSV). LEU is irradiated to produce molybdenum-99 by fission within the IF.
ing this process, plutonium is generated in the target solution and the neutron multiplier. Up
]PROP/ECI of LEU are used in the IF to support facility operations. The total inventory for the SHINE facility is discussed in Section 9b.5.
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h IU, for IU start-up operations, as described in Section 4a2.2. Additionally, up to 0.55 lbs.
0 g) of uranium-235 are used within neutron flux detectors.
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primary closed loop cooling system (PCLS) is the closed loop cooling system that provides ling to the target solution vessel (TSV). Buildup of radiolysis products in the PCLS is trolled by the ventilation of the PCLS expansion tank by radiological ventilation zone 1 Z1). Cover gas control for the PCLS is further described in Section 5a2.2.
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section describes auxiliary systems in the irradiation facility (IF) that are not described where.
.7.1 TRITIUM PURIFICATION SYSTEM tritium purification system (TPS) is a tritium-deuterium isotope separation system designed eceive mixed tritium-deuterium gas from operating neutron driver assembly system (NDAS) s and provide high purity tritium and deuterium streams to each operating NDAS unit. The components are located in the TPS room. The TPS consists of three trains which service eight NDAS units.
.7.1.1 Tritium Purification System Subsystems
.7.1.1.1 Isotope Separation Subsystem isotope separation subsystem of each TPS train receives mixed tritium-deuterium gas from rating NDAS units, removes trace impurities from the gas stream, performs isotope aration of the mixed gas stream, and provides controlled flows of high purity tritium to rating NDAS units to drive the tritium-deuterium fusion reaction in the NDAS target chamber.
TPS isotope separation subsystem also flushes and evacuates process lines before entering aintenance period and after maintenance is complete.
.7.1.1.2 TPS-NDAS Interface Lines TPS-NDAS interface lines consist of multiple transfer lines between the main TPS process ipment and each NDAS. The transfer lines travel through subgrade penetrations between the room and each NDAS. Monitoring capability is provided for the interface lines to detect ential tritium leaks. The TPS-NDAS interface lines are protected from mechanical impact ween the TPS gloveboxes and subgrade penetrations.
.7.1.1.3 TPS Gloveboxes TPS gloveboxes are confinement gloveboxes that enclose the isotope separation process ipment. The TPS gloveboxes are maintained at negative pressure relative to the TPS room have a helium atmosphere. The glovebox atmospheres are cleaned by the secondary losure cleanup (SEC) to maintain low levels of tritium contamination and oxygen. A detailed sical description of the TPS glovebox is provided in Subsection 9a2.7.1.4.
.7.1.1.4 Secondary Enclosure Cleanup Subsystem SEC removes tritium from the helium atmosphere of the TPS gloveboxes. The SEC removes m in glovebox environments from both chronic sources (leakage and permeation) and idental releases. The SEC also maintains low levels of oxygen and moisture in the glovebox ospheres. The SEC uses a combination of cleanup beds to capture elemental tritium and ted water. The cleanup beds are periodically replaced to ensure proper SEC function. The C recirculates the TPS glovebox atmospheres.
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vacuum/impurity treatment subsystems (VAC/ITS) evacuate TPS process lines and remove e tritium in process waste streams to support normal operations and maintenance rations. Process streams are evacuated through an arrangement of tritium capture beds, and waste streams are monitored for tritium concentration before exhausting to the facility tilation.
.7.1.1.6 NDAS Secondary Enclosure Cleanup NDAS SEC removes tritium from the atmosphere of the NDAS secondary enclosures. The AS SEC removes tritium in NDAS secondary enclosure environments from chronic sources kage and permeation) that occur during NDAS operation.
.7.1.1.7 Tritium Purification System Room TPS room houses the TPS gloveboxes, VAC/ITS equipment, NDAS secondary enclosure nup equipment, TPS fume hoods, SEC equipment, and supporting control and process ipment.
.7.1.2 Design Bases TPS maintains the integrity of the TPS confinement boundary by preventing leakage to the om the TPS gloveboxes, SEC process equipment, and TPS-NDAS interface lines, which ld result in potential off-site exposures to individual members of the public or occupational e exposures to individual workers in excess of prescribed dose criteria, which are described ection 11.1. TPS isolation functions are actuated by the engineered safety features actuation tem (ESFAS) as described in Section 7.5.
TPS prevents leakage from primary confinement boundary through isolation of interface cess lines between TPS process equipment and NDAS during and after a design basis mic event which could result in potential off-site exposures to individual members of the lic or occupational dose exposures to individual workers in excess of SHINE's dose criteria, ch are addressed in Section 11.1. Primary confinement isolation functions are actuated by the et solution vessel (TSV) reactivity protection system (TRPS), as described in Section 7.4.
NE design criteria applicable to the TPS are described in Section 3.1.
.7.1.3 Tritium Purification Process Sequence TPS isotope separation process begins with a pair of liquid-nitrogen cooled cryopumps that w in mixed tritium-deuterium target chamber exhaust gas from NDAS units that interface with TPS respective train. A guard bed in front of the two cryopumps removes moisture impurity ore it reaches the cryopumps. The cryopumps are cycled to either capture gas from operating AS units or heated to deliver gas to a permeator that provides additional impurity removal of gas stream.
permeator inlet receives gas from the target gas receiving cryopumps. As the gas moves ugh the permeator, impurities are prevented from passing through the permeator wall while rogen isotopes permeate across to the permeator outlet, resulting in high purity hydrogen NE Medical Technologies 9a2.7-2 Rev. 1
to the isotope separation process. Impurities that build up on the permeator are periodically cuated to maintain proper permeator functionality.
r passing through the permeator, deuterium and tritium isotopes are separated through the rmal Cycling Adsorption Process (TCAP). The TCAP separates deuterium and tritium ugh the thermal cycling of a palladium-based column and a molecular sieve column. By mally cycling the TCAP columns, pure tritium gas is collected at one end of the palladium-ed column and pure deuterium is collected at one end of the molecular sieve column. Tritium en drawn from the end of the palladium-based column and deuterium is drawn from the ecular sieve column.
AP is a batch process. To receive and deliver a continuous supply of gas to and from rating NDAS units, an arrangement of feed, product, and raffinate tanks is used together with separation columns. The feed tank is used to supply mixed tritium and deuterium gas to the AP separation columns, which separates the two isotopes and fills the product and raffinate
. The product tank is used to supply the tritium target gas interface line, which is used to ply target gas to each operating NDAS. In-process tritium instrumentation monitors the aration process to ensure proper TCAP functionality, isotope separation equipment is confined inside the TPS gloveboxes. The TPS gloveboxes vide a tritium confinement boundary along with isolation valves to ensure excessive tritium ases to the facility and environment do not occur. The TPS gloveboxes also provide finement in the event of a breach in the TPS process equipment.
eceive new tritium gas or store process tritium before entering maintenance, the TPS tains tritium storage vessels, such as depleted uranium beds. The uranium storage beds w tritium to be safely stored during maintenance operations on the TPS. A supply volume vides the ability to add measured amounts of tritium to the TPS from either the storage bed or external source.
AC/ITS contains the support equipment necessary to evacuate TPS process lines to support mal operations and to prepare for TPS maintenance. The VAC/ITS are capable of removing h elemental and oxide forms of tritium. TPS waste streams are monitored for tritium centration before exhausting to the facility ventilation. The NDAS may be evacuated before e maintenance operations, so the NDAS evacuation waste streams may also be treated in VAC/ITS to remove tritium before exhausting the NDAS waste stream to the facility tilation.
terium source gas is supplied to the NDAS for the NDAS ion source from an external bottle ply. Deuterium source gas exhaust is exhausted to the facility ventilation. NDAS target mber exhaust consisting of tritium and deuterium gas is returned to the TPS for isotope aration. The NDAS may also be flushed with air and evacuated down to vacuum through the C/ITS, which may remove trace tritium before the waste stream enters the facility ventilation.
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cess equipment associated with the TPS.
ure 9a2.7-1 provides a TPS process flow diagram.
.7.1.4 TPS Glovebox Description TPS process equipment is enclosed in three gloveboxes, one for each TPS train. The eboxes have a stainless steel shell with gloveports and windows on both sides for operator ess to equipment. The glovebox has feedthrough connections to allow process tubing, trical power, and instrumentation lines to pass through the gloveboxes to the TPS process ipment. The gloveboxes have antechambers to facilitate the removal and replacement of rnal equipment as needed. External lighting fixtures provide light to the glovebox interiors.
glovebox volumes are sized such that a release of the tritium and deuterium stored in the ebox would not result in exceeding the lower flammability limit (LFL) in the glovebox.
.7.1.5 Glovebox Atmosphere Treatment all amounts of tritium are released into the gloveboxes during normal operation, so the eboxes each have a cleanup system designed to treat the atmosphere to minimize the tritium centration. The glovebox atmosphere normally has a very low tritium concentration. The most ificant releases of tritium to the glovebox atmosphere are expected to occur during ntenance activities (e.g., disconnecting beds or pumps for replacement).
gloveboxes have a recirculating inert atmosphere with minimal helium makeup. The sture and tritium content in the glovebox is monitored, and at high concentrations the rator is notified by alarms. The SEC cleans the atmosphere to minimize the amount of tritium e glovebox atmospheres. The glovebox atmospheres exhaust through the SEC into the ological ventilation zone 1 exhaust (RVZ1e).
SEC involves molecular sieve beds and a hydride bed to remove most elemental and ized tritium. The cleanup beds are replaced as required over the course of operations.
.7.1.6 Radiological Protection processes associated with the TPS are performed within gloveboxes to minimize the osure of individuals to tritium. The TPS equipment outside the gloveboxes that can contain m is normally under partial vacuum. Monitors are located near tritium tubing and at glovebox kstations to identify tritium leaks. The TPS is designed to maintain occupational exposures to m to within as low as reasonably achievable (ALARA) program goals. Releases of tritium to facility or environment are within 10 CFR 20 limits.
cess lines that penetrate the glovebox confinement boundaries have isolation valves that e on high tritium alarm in the glovebox. In the event of a tritium release, the glovebox may be ated from the rest of the TPS process and IF through actuation of the isolation valves.
ation valves are also located on process lines at the interface between the TPS and NDAS s that can be closed to support confinement of an irradiation unit (IU) cell.
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he NDAS at sub-atmospheric pressure which reduces leakage potential.
luation of accidents involving releases of tritium from the TPS is discussed in section 13a2.1.12.
.7.1.7 Instrumentation and Controls process integrated control system (PICS) provides normal monitoring and control of process ables and control components not important to the safe operation of the TPS. Section 7.3 vides a detailed description of the PICS.
TRPS monitors TPS variables important to the safety functions of the irradiation process ng each operating mode of the IU to perform an IU Cell Safety Actuation. Section 7.4 vides a detailed description of the TRPS.
ESFAS monitors variables important to the safety functions for confinement of tritium within IF to perform isolation of the TPS. Section 7.5 provides a detailed description of the ESFAS.
.7.1.8 Technical Specifications tain material in this subsection provides information that is used in the technical cifications. This includes limiting conditions for operation, setpoints, design features, and ans for accomplishing surveillances. In addition, significant material is also applicable to, and y be used for the bases that are described in the technical specifications.
.7.2 NEUTRON DRIVER ASSEMBLY SYSTEM SERVICE CELL NDAS service cell (NSC) is a dedicated work area provided to support the staging, missioning, maintenance, and disposal of a single NDAS unit. The NSC provides additional ce for maintenance activities that are difficult or impossible to perform when an NDAS is alled in an IU cell.
.7.2.1 Design Bases NSC accommodates commissioning, maintenance, and disposal activities for the rational lifetime of each NDAS.
.7.2.2 System Description NSC is a roofless room formed by a shared wall with the [ ]SRI on the north, an rior building wall on the east, a wall facing the laydown area on the south, and a wall on the
- t. The NSC contains a service pit to allow installation of a dedicated target for NDAS beam ing. Outside of the NSC, there is sufficient space (either in the laydown area outside the NSC n the roof of the TPS room) for placement of a control station, high voltage power supply, ling and electrical cabinets, and NDAS-related consumables and tooling to support NDAS ing. Figure 4a2.5-1 provides a plan and section view of the NSC. A list of system interfaces ociated with the NSC is provided in Table 9a2.7-4.
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- Commissioning An NDAS may be tested in the NSC prior to installation in an IU cell. The NDAS sub-assemblies will be staged, mounted to the supporting pads in the NSC, and assembled with the support of the facility crane. The assembled NDAS is connected to service utilities such as electrical, control, cooling water, and supply gases inside and outside the NSC. The commissioning activities to be carried out in the NSC may include establishing vacuum, helium leak rate testing, filling the pressure vessel with sulfur hexafluoride (SF6) gas, and beam performance testing.
- Maintenance If portions of an NDAS require maintenance or replacement, it may be moved from an IU cell to the NSC. The NDAS is lifted by the IF bridge crane and transferred to the NSC where work can be performed.
- Disposal The NSC may also be used to disassemble an NDAS into smaller parts that can fit more easily into containers before sending to an appropriate waste repository.
.7.2.3 Radiological Protection mma radiation monitoring of the NSC is provided to allow for safe operation and interlocking ctivities in the NSC. The NSC has a directed airflow system to manage residual tritium tamination of NDAS components. This airflow system maintains the capability to interface the facility heating, ventilation, and air conditioning (HVAC) through radiological ventilation e 2 exhaust (RVZ2e). A passive tritium sample collector at the interface to RVZ2e provides a ord of tritium content entering RVZ2e from the NSC. The NSC provides a real-time tritium nitor at the interface to the RVZ2e to measure real-time tritium content in exhaust gas from AS testing sent to RVZ2e.
NSC shield walls are made from approximately 24-inch (61 centimeter) thick concrete walls reinforcing carbon steel bars. Additional local shielding, such as water or polycarbonate ks, may also be installed during testing in the NSC. Implementation of local shielding in the and around an installed NDAS as necessary, provides radiation shielding during NDAS ing. This local shielding functions in conjunction with the shielding provided by the NSC shield s and door to maintain occupational exposures to neutron and gamma radiation to within RA program goals. Table 11.1-4 provides radiation areas at the SHINE facility, and includes e rates to the IF general area during accelerator testing in the NSC. Calculated dose rates ng accelerator operation in the NSC are approximately 8 mrem/hr outside the NSC walls. The ual average neutron flux to the NSC surrounding soil is expected to be less than 100 n/cm2-s.
.7.2.4 Instrumentation and Controls NSC provides instrumentation and controls to perform testing of an NDAS to verify proper ration before returning to service. Interlocks for safe testing of the NDAS, such as preventing ration of the NDAS while the service cell door is open are provided. A radiation interlock on located inside the NSC prevents or shuts down operation of the NDAS when actuated by sonnel in the NSC.
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re are no technical specifications associated with the NSC.
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Table 9a2.7 Tritium Purification System Interfaces Interfacing System Interface Description Tritium purification system (TPS) interfaces with the NDAS through utron driver assembly system process tubing connections that allow delivery of tritium and DAS) deuterium gas along with return of mixed tritium and deuterium exhaust gas or NDAS evacuation.
PICS provides normal monitoring and control of all process variables ocess integrated control and control components not important to the safe operation of the stem (PICS)
TPS.
The TRPS provides monitoring and indication of the TPS variables rget solution vessel (TSV) important to the safe operation of individual irradiation unit (IU) cells activity protection system and provides control of all TPS isolation valves into the primary RPS) confinement boundary in the event of a design basis event.
The ESFAS provides monitoring and indication of the TPS variables important to the safe operation of the TPS glovebox and glovebox gineered safety features stripper system. The ESFAS also provides control of all TPS isolation tuation system (ESFAS) valves out of the TPS and the glovebox stripper system in the event of a design basis event. The ESFAS controls the position of the safety-related actuation components of the TPS.
Liquid nitrogen is supplied to TPS process equipment to operate cility nitrogen handling cryopumps and TCAP equipment. Gaseous nitrogen is used to stem (FNHS) actuate air-operated valves throughout the TPS process.
TPS interfaces with RVZ1 at the points of connection from the diological ventilation zone 1 gloveboxes pressure control exhaust and the points of connection VZ1) from the TPS vacuum/impurity treatment subsystem process equipment to the zone 1 header duct.
TPS interfaces with RVZ2 at the exhaust point of the liquid nitrogen diological ventilation zone 2 cooling lines (in the form of nitrogen gas), TPS fume hoods, and the VZ2) overall ventilation of the TPS room.
TPS interfaces with the NPSS at the following locations: the glovebox electrical penetrations and connections to equipment located rmal electrical power supply external to the glovebox. Electrical power is distributed within the stem (NPSS) glovebox to operate the various pumps and heaters in the TPS, and other ancillary equipment.
andby Generator System The SGS provides nonsafety-related backup power to TPS GS) components.
TPS interfaces with the UPSS at the connections to safety-related interruptible electrical power equipment and instrumentation that require safety-related backup pply system (UPSS) power. Some nonsafety-related portions of the SEC are also on the UPSS.
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Table 9a2.7 Nominal Tritium Supply/Return Properties External Mixed Tritium-Parameter Tritium Supply Deuterium Supply Deuterium Return tium Concentration [ ]PROP/ECI NA [ ]PROP/ECI uterium Concentration Balance 100% Balance PROP/ECI PROP/ECI w Rate (per TPS train) [ ] [ ] [ ]PROP/ECI essure < 1 atm 40 psig < 1 atm NE Medical Technologies 9a2.7-9 Rev. 1
Table 9a2.7 Tritium Purification System Process Equipment Design/Fabrication Component Description Code or Standard AGS-G001-2007 is The TPS gloveboxes provide a confinement considered as tium purification system barrier that prevents tritium leakage from guidance for the PS) gloveboxes isotope separation process equipment from design of the releasing to the facility gloveboxes.
(AGS, 2007)
The cryopumps recover gas from neutron driver assembly system (NDAS) units and yopumps Note (a) deliver gas to the thermal cycling absorption process (TCAP) feed The permeator removes impurities from the rmeator TPS gas stream before it is delivered to TCAP Note (a) for isotope separation The TCAP columns are a palladium-based column and a molecular sieve column that are AP Note (a) thermally cycled to isotopically separate tritium and deuterium The TPS secondary enclosure cleanup beds remove tritium, moisture, and oxygen from the S secondary enclosure glovebox atmospheres to maintain an inert Note (a) anup beds glovebox atmosphere with minimal tritium contamination TPS isolation valves are located on process lines to provide confinement in conjunction S isolation valves with the TPS glovebox and IU cells in the Note (a) event a radiological release is detected in the IU cell or TPS gloveboxes Commercially available equipment designed to standards satisfying system operation.
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Table 9a2.7 NDAS Service Cell Interfaces Interfacing System Interface Description utron driver assembly system The NDAS service cell (NSC) supports the NDAS maintenance and DAS) testing needs.
rmal electrical power supply The NPSS provides power to NSC equipment to support testing of an stem (NPSS) NDAS.
dioisotope process facility The RPCS provides cooling water to the NDAS cooling cabinet oling system (RPCS) associated with the NSC to support testing of an NDAS.
The NSC is open to RVZ2 air and exhausts to RVZ2 exhaust diological ventilation zone 2 (RVZ2e).
VZ2)
RVZ2 will receive heat rejected by NSC equipment.
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Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9a2.7 TPS Process Flow Diagram PROCESS EXHAUST TO FACILITY VENTILATION RVZ1e LIQUID NITROGEN EXHAUST TO FACILITY VENTILATION RVZ2e LIQUID NITROGEN SUPPLY TRITIUM CONFINEMENT BOUNDARY VAC/ITS VAC/ITS VAC/ITS SEC SEC SEC PNEUMATIC EQUIPMENT GAS (TYP A-C)
TPS PROCESS TRAIN C TPS PROCESS TRAIN B TPS PROCESS TRAIN A INERT FLUSH GAS (TYP A-C)
GLOVEBOX ATMOSPHERE HELIUM SUPPLY (TYP A-C)
DEUTERIUM SUPPLY IU CELL 8 IU CELL 7 IU CELL 6 IU CELL 5 IU CELL 4 IU CELL 3 IU CELL 2 IU CELL 1 NDAS SECONDARY ENCLOSURE CLEANUP RETURN PRIMARY CONFINEMENT BOUNDARY (TYP 1-8)
NOTES
- 1. ISOLATION VALVES THAT CONSTITUTE PART OF THE TRITIUM TARGET CHAMBER SUPPLY NDAS SECONDARY ENCLOSURE CLEANUP SUPPLY CONFINEMENT BOUNDARY MAY BE LOCATED INSIDE OR OUTSIDE THE (TYP 1-8) ION SOURCE EXHAUST TO FACILITY ION SOURCE SUPPLY GLOVEBOX SHELL VENTILATION RVZ1e (TYP 1-8) TARGET CHAMBER EXHAUST INERT OR FLUSH GAS ISOLATION VALVE LOCATION SHINE Medical Technologies 9a2.7-12 Rev. 1
S, 2007. Guideline for Gloveboxes, AGS-G001-2007, American Glovebox Society, 2007.
ME, 2009. Code on Nuclear Air and Gas Treatment, AG-1, American Society of Mechanical ineers, 2009.
ME, 2017. Building Services Piping, ASME B31.9, American Society of Mechanical ineers, 2017.
PA, 2016. National Fire Alarm and Signaling Code, NFPA 72, National Fire Protection ociation, 2016.
PA, 2018. National Fuel Gas Code, NFPA 54, National Fire Protection Association, 2018.
PA, 2014. Standard for Fire Protection for Facilities Handling Radioactive Materials, PA 801, National Fire Protection Association, 2014.
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1 HEATING, VENTILATION, AND AIR CONDITIONING SYSTEMS heating, ventilation, and air conditioning (HVAC) systems for the SHINE facility are common he irradiation facility (IF) and the radioisotope production facility (RPF). The SHINE facility AC systems are described in Section 9a2.1.
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2.1 TARGET SOLUTION LIFECYCLE section addresses the lifecycle of the target solution from the time that it enters the diction of the SHINE facility until it is released from such jurisdiction.
get solution is a low-enriched, uranyl sulfate solution that is prepared by converting solid nium oxide into the uranyl sulfate solution using the target solution preparation system PS). Low enriched uranium (LEU) is received by the uranium receipt and storage system SS) as either uranium metal or uranium oxide. If metal is received, the URSS converts the al to uranium oxide, as described in Subsection 4b.4.2. After preparation, the target solution eld in the target solution preparation tank until it is transferred to the target solution staging tem (TSSS) and loaded into the target solution vessel (TSV) from the TSSS for an irradiation
- e. After irradiation is complete, the irradiated target solution is transferred to the molybdenum action and purification system (MEPS) where molybdenum is separated from the target.
owing processing in MEPS, the target solution may be delivered to the TSSS for storage or ther irradiation cycle, to the radioactive liquid waste storage (RLWS) system for disposal, or he iodine and xenon purification and packaging (IXP) system for separation of iodine and on isotopes as products. At the end of its lifecycle as target solution, the uranyl sulfate tion is transferred to the RLWS. In the RLWS, the uranyl sulfate solution is blended with er waste streams and held in storage until it is ready to be solidified by the radioactive liquid te immobilization (RLWI) system. Solidified wastes are transferred to the material staging ding for preparation for shipment off-site.
chemical properties of the target solution are described in Subsection 4a2.2.1.
ailed descriptions of the processes involving irradiated and unirradiated special nuclear erial (SNM) are provided in Subsection 4b.4.1 and Subsection 4b.4.2, respectively.
ipment, application of administrative controls, and the design features involved in the SNM ycle are included in this section.
tion 12.8 provides a discussion of the physical security of the SNM. Section 4b.2 provides a ussion of the shielding requirements associated with irradiated target solution. Section 5a2.2 vides a description of the primary closed loop cooling system (PCLS), which is used to ove heat from the TSV and neutron multiplier during irradiation of the target solution.
pter 13 provides the accident analysis accident analysis of the SHINE facility, including those narios related to the storage and handling of target solution. Detailed discussions of ological considerations related to the handling and storage of target solution are provided in tion 11.1.
2.2 RECEIPT AND STORAGE OF UNIRRADIATED SNM URSS receives, handles, and stores unirradiated uranium. The URSS facilitates the pling of received SNM and converts uranium metal to uranium oxide prior to its use in TSPS.
nium is stored in canisters placed on racks designed for criticality safety. Subsection 6b.3.2 vides information on criticality safety controls for receipt and storage of uranium.
etailed description of the URSS is provided in Subsection 4b.4.2.1.
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TSPS converts uranium oxide into a uranyl sulfate solution for use as a target solution batch s makeup solution. Uranium is transferred from the URSS and imported into the TSPS ebox for dispensation into the dissolution tanks. After conversion to uranyl sulfate in the olution tank, the uranium solution is pumped to the target solution preparation tank for age until it is needed for an irradiation cycle or as makeup solution.
etailed description of the TSPS is provided in Subsection 4b.4.2.2.
2.4 TARGET SOLUTION STAGING SYSTEM get solution batches prepared for irradiation are transferred from the TSPS to the TSSS. The S consists of target solution hold tanks and target solution storage tanks. Target solution tanks stage the target solution for transfer into the primary system boundary (PSB). Target tion storage tanks provide additional storage capacity for the facility. Tanks in the TSSS can eive target solution discharged from processes in the hot cells. The target solution may be pled from each tank.
etailed description of the TSSS is provided in Subsection 4b.4.1.1.
2.5 VACUUM TRANSFER SYSTEM vacuum transfer system (VTS) provides the transport of radioactive liquids, including target tion, throughout the radioisotope production facility (RPF). The VTS operates by applying uum to an intermediary lift tank or directly to a destination tank. The VTS also provides uum service to RPF systems.
2.5.1 Design Bases VTS is designed to:
- Prevent inadvertent criticality in accordance with the criticality safety evaluation.
- Relieve the system to atmospheric pressure upon actuation of the engineered safety features actuation system (ESFAS) to terminate transfers of target solution.
2.5.2 System Description VTS consists of vacuum pumps, a knockout pot, vacuum lift tanks, and associated piping ponents and instrumentation. Process piping and pipe components are designed to meet the uirements of ASME B31.3, Process Piping (ASME, 2013).
transfers liquid by one of the two following distinct methods:
- The first method moves liquid in batches via small volume tanks. These tanks are collectively named lift tanks. In the VTS, a vacuum is drawn on the knockout pot by a set of vacuum pumps, which discharge to the process vessel vent system (PVVS) for off-gas treatment. Solution transfers occur by aligning a vacuum lift tank with the knockout pot.
Vacuum is applied to the lift tank, and solution flows from the source tank. Once the vacuum lift tank level setpoint is reached, the lift tank is isolated from the knockout pot NE Medical Technologies 9b.2-2 Rev. 1
additional elevation gain. Liquid transfers using vacuum lift tanks in the RPF are identified in Table 9b.2-1.
- The second method facilitates solution transfers without using a vacuum lift tank. Vacuum from the knockout pot is applied directly to the selected destination tank, and valves in the pathway between the source tank and destination tank are aligned to allow flow. This method is typical for transfers in the RLWS system, the RLWI system, and between laboratory scale processes that are part of the isotope separation process. Direct liquid transfers between tanks facilitated by VTS are identified in Table 9b.2-2.
separate vacuum headers are provided based on the liquid being transferred. Tanks igned to contain target solution are provided with vacuum from a separate header than tanks concentration controls or other tanks or services that are not intended to contain fissile erial. The headers are air gapped at the knockout pot as shown in Figure 9b.2-1.
VTS provides an interface for sampling of solution in the target solution hold tanks, target tion storage tanks, RLWS system tanks, and the radioactive drain system (RDS).
VTS is the only system used to transport SNM between the RPF and IF. A description of the cess used to fill the TSV is provided in Subsection 4a2.6.1. The VTS is one of the systems d to transport solutions of SNM or byproduct material in the RPF. The other systems used to sport solutions containing SNM or byproduct material in the RPF are TSPS, MEPS, IXP, and RLWI system, which use pumps to provide the motive force to transport the solutions.
le 9b.2-3 identifies the systems which interface with the VTS.
ure 9b.2-1 provides a process flow diagram of the VTS.
2.5.3 Instrumentation and Controls perature of solution in the source tank is monitored prior to a transfer to ensure that the sfer does not induce the solution to flash in the pipe. Level of each vacuum lift tank is also nitored to allow the process integrated control system (PICS) to control each transfer.
omatic flow shut-off valves and liquid detection instruments are provided in the VTS to vent solution from entering the knockout pot. On detection of liquid by these instruments, FAS actuates valves that act as vacuum breakers on the knockout pot and trips the breakers he vacuum pumps, terminating solution transfers. The knockout pot drains to favorable metry tanks in the RLWS system in the event of high-level alarm. ESFAS also trips the uum breaking valves and pump on detection of high radiation in radiological ventilation e 1 (RVZ1) or on level detection in the RDS. A detailed description of the ESFAS is provided ection 7.5.
2.5.4 Safety Analysis VTS is a safety-related system. The VTS structural framework and pipe supports are igned to withstand design basis seismic events. The VTS is classified as Seismic Category I.
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pter 13 provides additional discussion of potential accident scenarios involving the VTS.
2.5.5 Criticality Control Features icality safety controls for the VTS are described in Subsection 6b.3.2.5.
2.5.6 Shielding and Radiological Protection equipment is located in the hot cells and shielded in below-grade vaults. Piping that may tain radiological materials is routed through shielded pipe chases to limit the exposure of viduals to radiation.
tion 11.1 provides a description of the radiation protection program, and Section 4b.2 vides a detailed description of the production facility biological shield (PFBS).
2.5.7 Technical Specifications tain material in this subsection provides information that is used in the technical cifications. This includes limiting conditions for operation, setpoints, design features, and ans for accomplishing surveillances. In addition, significant material is also applicable to, and y be used for the bases that are described in the technical specifications.
2.6 RADIOACTIVE LIQUID WASTE STORAGE id wastes from the isotope production processes may contain SNM. These liquids are ned from the hot cells to the first favorable geometry uranium waste tank in the RLWS tem. Once the liquid waste is verified to be below administrative limits, it is transferred to the ond uranium waste tank where it is sampled again prior to sending to the liquid waste ding tanks for additional storage time. Target solution batches are disposed of through the WS system. Once a batch is designated for disposal, it is transferred to the RLWS system to blended with other wastes.
etailed description of the RLWS system is provided in Subsection 9b.7.4.
2.7 RADIOACTIVE LIQUID WASTE IMMOBILIZATION id wastes in the RLWS system are solidified by the RLWI system. Liquid wastes in the RLWS tem may contain SNM. Solutions are transferred to the RLWI system by the VTS from the WS system. In the RLWI system, solution may be [
]PROP/ECI to remove isotopes that impact waste classification (e.g., Sr-90, Cs-137).
ids are solidified in drums pre-filled with immobilization agents. The cured waste drums are dled by the solid radioactive waste packaging (SRWP) system upon removal from the RLWI tem.
etailed description of the RLWI system is provided in Subsection 9b.7.3.
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solid radioactive waste packaging (SRWP) system collects, segregates, and stages solids tes for shipment. A detailed description of the SRWP system is provided in section 9b.7.5.
dified drums from the RLWI system are transported to the material staging building prior to ment off site. These wastes may contain SNM.
ope separation columns may also contain adsorbed SNM. The columns are loaded into ms and placed in bore holes for storage within the RPF. After storage, the drums are sported to the material staging building prior to shipment off site.
2.9 CRITICALITY CONTROL dvertent criticality is prevented in RPF systems involved in the processing of fissile materials ugh the application of the nuclear criticality safety program, described in Section 6b.3.
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Table 9b.2 Liquid Transfers Using Vacuum Lift Method Lift Description rget solution vessel (TSV) Target solution is transferred from the TSV dump tank to the mp tank to molybdenum MEPS using two stages of lift tanks. Extraction lower lift tanks raction and purification and extraction upper lift tanks. Extraction lower lift tanks are tem (MEPS) located in hold tank valve pits and extraction upper lift tanks are located in the extraction hot cells.
rget solution hold tank to Target solution is transferred from the target solution hold tank V to the TSV via the TSV fill lift tank. A dedicated TSV fill lift tank is provided for each irradiation unit (IU) cell. Excess target solution in the lift tank when the TSV fill has been completed is drained back to the target solution hold tank.
tween target solution Target solution may be transferred between TSSS tanks using ging system (TSSS) tanks the target solution storage lift tank. The target solution storage lift tank is located in one of the extraction hot cells.
SS tanks to first uranium Target solution may be transferred from a TSSS tank to the first uid waste tank uranium liquid waste tank using the liquid waste lift tank. The liquid waste lift tank is located in one of the extraction hot cells.
st uranium liquid waste Solution may be transferred from the first uranium liquid waste k to target solution tank to a target solution storage tank using the liquid waste lift rage tank tank. The liquid waste lift tank is located in one of the extraction hot cells.
tween uranium liquid Liquid waste is transferred between the uranium liquid waste ste tanks tanks using the liquid waste lift tank. The liquid waste lift tank is located in one of the extraction hot cells.
dioactive drain system Liquid in the RDS sump tank may be transferred to a target DS) sump tank to first solution storage tank using a two-stage lift through the RDS nium liquid waste tank lower lift tank and the liquid waste lift tank. The RDS lower lift tank is located in one of the RDS sump tank vaults and the liquid waste lift tank is located in one of the extraction hot cells.
S sump tank to target Liquid in the RDS sump tank may also be transferred to a target ution storage tank solution storage tank using a two-stage lift through the RDS lower lift tank and liquid waste lift tank. The RDS lower lift tank is located in one of the RDS tank vaults and the liquid waste lift tank is located in one of the extraction hot cells.
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able 9b.2 Direct Transfer of Liquid via Application of Vacuum to Destination Tank Lift Description cond uranium liquid waste Liquid waste from the second uranium liquid waste tank is k to liquid waste blending transferred to one of the liquid waste blending tanks by applying ks vacuum to the destination blending tank.
tween liquid waste Liquid waste is transferred between the liquid waste collection lection tanks tanks by applying vacuum to the destination collection tank.
uid waste collection tanks Liquid waste from the liquid waste collection tanks is transferred iquid waste blending to the liquid blending tanks by applying vacuum to the ks destination blending tank.
tween liquid waste Liquid waste is transferred between the liquid waste blending nding tanks tanks by applying vacuum to the destination blending tank.
uid waste blending tanks Liquid waste is transferred directly from a liquid waste blending mmobilization feed tank tank to the immobilization feed tank by applying vacuum to the immobilization feed tank.
her vacuum service The VTS is used to provide vacuum service to the molybdenum vided by VTS extraction and purification system (MEPS) and the target solution vessel (TSV) off-gas system (TOGS) as needed. The VTS is also used to provide sampling capability to the target solution staging system (TSSS) and the radioactive liquid waste storage (RLWS) system via the target storage lift tank, liquid waste lift tank, and dedicated sampling lines.
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Table 9b.2 Vacuum Transfer System Interfaces (Sheet 1 of 2)
Interfacing System Interface Description lybdenum extraction and The VTS transfers target solution to MEPS for rification system (MEPS) molybdenum extraction and provides vacuum service for the rotary evaporator and purification equipment. MEPS reduces load of evolved vapors within the system to VTS to reduce corrosion.
ocess vessel vent system (PVVS) The VTS discharges gases from the vacuum pumps to the PVVS. The PVVS provides ventilation to VTS vacuum lift tanks when they are not lifting.
rmal electrical power supply Electrical power is provided to the vacuum pumps and tem (NPSS) ancillary equipment by NPSS.
dioactive liquid waste storage The VTS interfaces with the RLWS in several locations.
LWS) system Solutions are transferred between the tanks using both a vacuum lift tank and by direct connections to VTS.
rget solution staging system The VTS transfers solutions from the target solution hold SSS) tanks to the target solution vessel (TSV). Solutions are also transferred between the TSSS tanks and from TSSS to the RLWS by VTS.
dioactive liquid waste Vacuum service is provided to the RLWI feed tank to mobilization (RLWI) system transfer solution from the RLWS.
dioactive drain system (RDS) The VTS is used to remove solution from the RDS sump tanks and transfers it to either RLWS or TSSS.
V off-gas system (TOGS) The VTS provides a source of vacuum to the TOGS.
cility chemical reagent system FCRS pumps solutions into vacuum lift tanks in the hot CRS) cell to introduce reagents to the RPF processes.
rogen purge system (N2PS) The N2PS injects sweep gas into the vacuum lift tanks to mitigate hydrogen accumulation during a PVVS failure.
gineered safety features The ESFAS actuates vacuum relief functions of the VTS uation system (ESFAS) on detection of high level to prevent an inadvertent criticality or on high radiation to minimize source inventory at risk in the spill location.
ocess integrated control system PICS allows operators to monitor VTS parameters and CS) control process functions.
ine and xenon purification and The VTS provides vacuum service to IXP for liquid ckaging (IXP) transfers between components within the IXP.
oduction facility biological shield The VTS components with radiological inventories are FBS) within a hot cell or shielded, below-grade vaults to minimize worker doses.
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Interfacing System Interface Description bcritical assembly system The TSV fill lift tank provides target solution to the TSV CAS) via gravity drain. The VTS provides transfer of target solution from the TSV dump tank to the MEPS. The VTS drains excess target solution in the TSV fill lift tank, not transferred to the TSV during filling, back to the target solution hold tank.
lybdenum isotope packaging The VTS provides vacuum service to the MIPS for tem (MIPS) shipping package leak detection.
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Chapter 9 - Auxiliary Systems Handling and Storage of Target Solution Figure 9b.2 Vacuum Transfer System Process Flow Diagram (Sheet 1 of 6)
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Chapter 9 - Auxiliary Systems Handling and Storage of Target Solution Figure 9b.2 Vacuum Transfer System Process Flow Diagram (Sheet 2 of 6)
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Chapter 9 - Auxiliary Systems Handling and Storage of Target Solution Figure 9b.2 Vacuum Transfer System Process Flow Diagram (Sheet 3 of 6)
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Chapter 9 - Auxiliary Systems Handling and Storage of Target Solution Figure 9b.2 Vacuum Transfer System Process Flow Diagram (Sheet 4 of 6)
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Chapter 9 - Auxiliary Systems Handling and Storage of Target Solution Figure 9b.2 Vacuum Transfer System Process Flow Diagram (Sheet 5 of 6)
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Chapter 9 - Auxiliary Systems Handling and Storage of Target Solution Figure 9b.2 Vacuum Transfer System Process Flow Diagram (Sheet 6 of 6)
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fire protection system and program for the SHINE facility are common to the irradiation lity (IF) and radioisotope processing facility (RPF). The SHINE fire protection system and gram are described in Section 9a2.3.
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communication systems for the SHINE facility are common to the irradiation facility (IF) and oisotope production facility (RPF). The SHINE facility communication systems are described ection 9a2.4.
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section applies to the possession and use of byproduct, source, and special nuclear erial (SNM) in the radioisotope production facility (RPF). The possession and use of roduct, source, and SNM within the irradiation facility (IF) is described in Section 9a2.5.
RPF is designated as a radiologically controlled area (RCA) as shown in Figure 1.3-1.
iation Protection Program controls and procedures, including the as low as reasonably ievable (ALARA) Program, applicable to the RPF, are described in Section 11.1. Radioactive te management is discussed in Section 11.2. A discussion of the Security Plan is provided in tion 12.8. Details of the Emergency Plan are described in Section 12.7. Fire protection details licable to the RPF are described in Section 9a2.3. Technical Specifications include limits that ly to the possession, management, and use of byproduct, source, and SNM.
SHINE facility design and procedures ensure that personnel exposures to radiation, uding ingestion or inhalation, do not exceed limiting values in 10 CFR 20 and are consistent the ALARA Program, as described in Section 11.1.
5.1 BYPRODUCT MATERIAL SHINE facility is designed to generate byproduct materials (e.g., molybdenum-99) for use as dical isotopes. Byproduct materials within the RPF include fission and activation products erated during irradiation unit (IU) operations. Target solution, containing byproduct and SNM, ansferred from the IF to the RPF for processing. Specific byproduct materials are separated
., molybdenum, iodine) from the irradiated target solution as described in Subsection 4b.3.1.
systems in which byproduct material may be present in the RPF include:
- The radioactive drain system (RDS), as described in Subsection 9b.7.6. The RDS contains radioactive liquids which contain byproduct materials collected in the event of a leak, spill, or overflow, and routes these liquids to a controlled location.
- The radioactive liquid waste storage (RLWS) system, as described in Subsection 9b.7.4.
The RLWS system provides receipt, mixing, and storage for aqueous radioactive wastes containing byproduct materials generated by processing operations within the RCA.
- The radioactive liquid waste immobilization (RLWI) system, as described in Subsection 9b.7.3. The RLWI immobilizes liquid radioactive wastes which contain byproduct materials generated by processing operations within the RCA.
- The process vessel vent system (PVVS), as described in Subsection 9b.6.1. The PVVS collects and treats off-gases containing byproduct materials from each RPF tank containing irradiated solutions, VTS vacuum pump discharge, and from the target solution vessel (TSV) off-gas system (TOGS).
- The molybdenum isotope product packaging system (MIPS), as described in Subsection 9b.7.1. The MIPS receives finished products (e.g., molybdenum-99, iodine-131, xenon-133) in their product bottles and places them in the applicable shipping container.
- The solid radioactive waste packaging (SRWP) system, as described in Subsection 9b.7.5. The SRWP system packages solid waste containing byproduct materials for shipment and disposal.
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from various locations throughout the SHINE process.
- The target solution staging system (TSSS), as described in Subsection 4b.1.3.5. The TSSS is a set of tanks and piping used to provide staging and storage of irradiated target solution containing byproduct materials.
- The vacuum transfer system (VTS) as described in Subsection 9b.2.5. The VTS provides transfer of radioactive liquids containing byproduct materials throughout the RPF and also provides vacuum service to the MIPS and the TOGS.
- The molybdenum extraction and purification system (MEPS) as described in Subsection 4b.3.1. The MEPS extracts molybdenum from irradiated target solution and prepares a concentrated form of molybdenum.
- The iodine and xenon purification and packaging (IXP) system as described in Subsection 4b.3.1. The IXP extracts iodine from an acidic solution following target solution irradiation.
types and quantities of byproduct materials within the SHINE facility are discussed in tion 11.1.
5.1.1 Byproduct Materials Extraction and Purification action and purification of byproduct materials occur in the MEPS and IXP. The MEPS and IXP are described in Subsection 4b.3.1. The primary byproduct material separated in the PS is molybdenum-99. The primary byproduct materials separated in the IXP are iodine-131 xenon-133. A batch of molybdenum-99 is up to [ ]PROP/ECI and up to 8 batches of ybdenum-99 may be produced a week. A batch of iodine-131 is up to [ ]PROP/ECI and o 8 batches of iodine-131 may be produced a week. A batch of xenon-133 is up to
]PROP/ECI and up to 8 batches of xenon-133 may be produced a week.
5.2 SOURCE MATERIAL rce material is not normally possessed or used within the RPF. There is a potential for oactive waste containing source material to be processed within the RPF. This may include omponents such as tritium storage beds (i.e., depleted uranium) or neutron multipliers. The s and quantities of source material within these components are described in Section 9a2.5.
ioactive waste management is discussed in Section 11.2.
5.3 SPECIAL NUCLEAR MATERIAL M in the RPF includes low enriched uranium (LEU) as well as plutonium generated in diated target solution located in systems throughout the RPF. The systems in which SNM y be present in the RPF are:
- The target solution preparation system (TSPS), as described in Subsection 4b.4.2. The TSPS is used to prepare LEU uranyl sulfate solution.
- The RDS, as described in Subsection 9b.7.6. The RDS contains liquids containing SNM collected in the event of a leak, spill, or overflow, and routes these liquids to a controlled location.
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processing operations in the RCA.
- The RLWI system, as described in Subsection 9b.7.3. The RLWI system immobilizes liquid radioactive wastes containing SNM.
- The SRWP system, as described in Subsection 9b.7.5. The SRWP system packages solid waste containing SNM.
- The TSSS, as described in Subsection 4b.4.1.1. The TSSS is a set of tanks and piping used to provide staging and storage of LEU uranyl sulfate target solution.
- Uranium receipt and storage system (URSS), as described in Subsection 4b.4.2. The URSS provides for receipt and storage of LEU metal and LEU oxide and converts LEU metal to LEU oxide.
- The LABS, as described in Subsection 9b.5.4. The LABS analyze samples containing SNM taken from various locations throughout the SHINE process.
- The VTS, as described in Subsection 9b.2.5. The VTS provides transfer of radioactive liquids containing SNM throughout the RPF.
- The MEPS, as described in Subsection 4b.1.3.2. The MEPS extracts molybdenum from irradiated target solution. SNM is only present in significant quantities in MEPS while extraction of molybdenum is taking place.
- The IXP system, as described in Subsection 4b.1.3. The IXP system extracts iodine from an acidic solution following target solution irradiation. SNM is only present in significant quantities in IXP while extraction of iodine is taking place.
to 6600 lbs. (3000 kg) of LEU, representing the total inventory of LEU for the SHINE facility, is d in the RPF to support facility operations.
5.4 QUALITY CONTROL AND ANALYTICAL TESTING LABORATORIES quality control and analytical testing laboratories (LABS) consist of the wet laboratory and instrument laboratory. The LABS are located in the RPF.
5.4.1 Design Basis LABS design basis is to provide analytical laboratory support relative to the production of ybdenum-99, iodine-131, xenon-133, qualification and production of target solution, and lysis of other process samples, as necessary. Analysis is used to determine: (1) enrichment, ty, and conversion of uranium; (2) identification, activity, concentration, and purity of ybdenum-99, iodine-131, and xenon-133 products; (3) process stream chemical and onuclide analyses; and (4) chemical and radionuclide analysis for waste characterization and osition.
5.4.2 System Description LABS analyze samples taken from various locations throughout the SHINE process. The tem processes samples using two adjacent laboratories designated the wet lab and the rument lab which are further described below. The wet lab is used for sample preparation, the instrument lab is used for sample analysis. The purpose of separating these two labs is ecrease the likelihood for cross-contamination and to protect the analytical instrumentation exposure to environments that may impact calibration and accuracy.
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rument laboratory analysis, samples are taken into the instrument laboratory and analyzed.
le 9b.5-1 identifies the systems that interface with the LABS.
5.4.2.1 Wet Laboratory ecessary, samples are first prepared and manipulated in the wet laboratory where they are in the appropriate chemical and radiochemical matrices for further analysis in the instrument While in the wet laboratory, samples may undergo general radiochemical and chemical cessing such as heating, cooling, concentration, dilution, separation, filtration, and cipitation. Basic analyses such as pH and density determination are performed in the wet ratory.
5.4.2.2 Instrument Laboratory ailed sample analysis takes place in the instrument laboratory. Examples of such analyses ude isotopic identification, isotopic quantification, radionuclide identification, radionuclide ntification, elemental identification, elemental quantification, pH, and density determination.
5.4.3 Operational Analysis and Safety Functions LABS perform no safety function.
LABS maintain positive pressure relative to the normally occupied areas of the RPF. The S are maintained at an ambient temperature and humidity commensurate with equipment uirements, and are designed to accommodate the effects of and to be compatible with the ironmental conditions associated with normal operation, maintenance, and testing.
sonnel contamination monitors, dosimetry, and training pertaining to good radiochemical and lth physics practices are incorporated into the LABS design. The wet laboratory and the rument laboratory have the ability to shield samples, standards, and waste using moveable bricks or other custom shielding. The design of the LABS satisfies the applicable uirements of the Radiation Protection Program.
LABS contain less than a combined 250 g of uranium at any given time in order to ensure cality safety.
lytical instruments in the LABS are appropriately qualified using installation, operational, and ormance qualifications. Equipment calibrations are performed using standards traceable to ified standards, if existing. Records of calibrations are maintained. The current calibration us of equipment is known and verifiable. Instruments that do not meet calibration criteria are used.
LABS satisfy applicable requirements in the Chemical Hygiene Plan. A Chemical Hygiene cer (CHO) oversees the effective implementation of the Chemical Hygiene Plan, in rdination with the Radiation Protection Manager. In addition to supervision and oversight of rations, SHINE will have a training program which emphasizes safety. The Chemical Hygiene n directs the use of protective equipment as appropriate.
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wet laboratory and the instrument laboratory each have oxygen level sensors to detect reased oxygen levels due to release of simple asphyxiant gas.
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able 9b.5 Quality Control and Analytical Testing Laboratories System Interfaces (Sheet 1 of 2) stem Interface Description cuum transfer system The LABS provide sample analysis for samples collected using VTS.
TS) diation cell biological The LABS provide sample analysis for ICBS.
eld (ICBS) ht water pool system The LABS provide sample analysis for LWPS.
WPS) mary closed loop The LABS provide sample analysis for PCLS.
oling system (PCLS) bcritical assembly The LABS provide sample analysis for SCAS.
tem (SCAS) rget solution vessel The LABS provide sample analysis for TOGS.
SV) off-gas system OGS) dioactive liquid waste The LABS provide sample analysis for RLWS.
rage (RLWS) system diological ventilation - Provides an exhaust for the radiochemical fume hoods within the ne 2 (RVZ2) wet laboratory and the instrument laboratory.
- Provides an exhaust for the product fume hood within the wet laboratory.
- Provides an exhaust for the ICP-MS in the instrument laboratory.
- Provides an exhaust for the ICP-OES in the instrument laboratory.
- Maintains a positive pressure in the LABS compared to the normally occupied areas of the radiologically controlled area (RCA).
- Maintains a temperature range and maximum rate of temperature change commensurate with equipment requirements in the LABS.
- The LABS have the capability to analyze RVZ2r condensate for radionuclide concentration.
rmal electrical power NPSS provides the instrument and wet labs with electrical power pply system (NPSS) commensurate with the requirements of the equipment in the LABS.
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stem Interface Description cility demineralized - The FDWS provides deionized water to the LABS for sample ter system (FDWS) preparation.
- The FDWS provides deionized water to each of the laboratory deionized water point of use locations.
- The FDWS provides water to each emergency eyewash and shower located in the LABS.
lid radioactive waste The SRWP system collects, transports, and packages for shipment cessing (SRWP) solid radioactive waste from the LABS including, but not limited to, tem laboratory glassware, personal protective equipment, and immobilized liquid waste.
ocess integrated The PICS monitors exhaust air flow rate from each fume hood and ntrol system (PICS) actuates a local alarm upon low flow conditions.
ck release The LABS provide sample analysis for the SRMS.
nitoring system RMS) ntinuous air The LABS provide sample analysis for the CAMS.
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section discusses radiolytic gas management systems located in the radioisotope duction facility (RPF) that manage radioactive gases associated with SHINE facility cesses.
6.1 PROCESS VESSEL VENT SYSTEM process vessel vent system (PVVS) collects and treats the off-gases from processes in the NE facility. The PVVS collects off-gases from each RPF tank containing irradiated tions, from the vacuum transfer system (VTS) vacuum pump discharge, and periodically the target solution vessel (TSV) off-gas system (TOGS). The PVVS consists of acid orbers, carbon filters, high-efficiency particulate air (HEPA) filters, condensers, reheaters, bon beds, and blowers which are employed to vent treated gases out of the radiologically trolled area (RCA). A description of system interfaces is provided in Table 9b.6-1.
6.1.1 Design Bases design bases of the PVVS include:
- Capture radioiodine from the off-gas stream;
- Delay the release of radioactive noble gases in gaseous effluents to the environment;
- Filter radioactive particulates from the gaseous effluents;
- Maintain RPF tanks and vessels at a negative pressure;
- Accept VTS vacuum pump discharge;
- Accept TOGS pressure relief discharge;
- Accept purges of TOGS, resulting from either a loss of TOGS capability to mitigate radiolytic hydrogen generation or maintenance requirements;
- Accept any sweep gases from TOGS used to purge gas analyzer instrumentation;
- Condition collected off-gas to improve reliability and performance of filtration equipment; and
- Discharge off-gases to the facility stack.
6.1.2 System Description PVVS provides radiolytic hydrogen mitigation capability for the RPF by ventilating the cess tanks and vessels. The PVVS also accepts gases discharged from VTS and TOGS.
ws from VTS and TOGS include vacuum pump discharge, sweep gas from gas analyzer ruments, nitrogen purges, and pressure relief. PVVS blowers upstream of the stack induce through the ventilation system. Flow rate requirements for PVVS are constant for nominal tilation in the RPF but increase when tanks are sparged for mixing, when VTS is operating, uring TOGS transients such as a purge during fill or maintenance, or pressure relief. PVVS ipment is designed for the maximum off-gas flow rate that could require processing at any time.
off-gases are processed to remove or delay iodine, noble gases, and radioactive iculates prior to gas being discharged to the facility stack. PVVS blower placement results e system being maintained at a negative pressure relative to ventilation zone 2. Intakes in ventilation zone 2 are the nominal air source for PVVS. Air flows from the intake, across NE Medical Technologies 9b.6-1 Rev. 1
idity of the off-gas.
densate is collected in the PVVS condensate tank within the PVVS hot cell, located within supercell. Condensate may be returned to the target solution staging system (TSSS) tanks makeup water or to the radioactive liquid waste storage (RLWS) system for waste cessing. An in-line heater, the PVVS reheater, downstream of the condenser heats the off-back to ambient temperature to reduce the relative humidity. The off-gas then flows through adsorber beds, HEPA filters, and the guard beds to neutralize entrained acid droplets or es, filter particulates, and capture iodine. The gas flows from the hot cell to a below-grade, lded vault, passing through a series of delay beds packed with carbon to delay the release ssion product noble gases such as xenon and krypton. The eight delay beds are organized three groups as shown in Figure 9b.6-1. Group 1 includes Delay Beds 1 and 2. Group 2 udes Delay Beds 3, 4, and 5. Group 3 includes Delay Beds 6, 7, and 8. A final set of HEPA rs removes any entrained carbon fines upstream of the blowers, and the treated gases are harged to the facility stack.
he event PVVS loses the capability to provide flow, the nitrogen purge system (N2PS) ates nitrogen flow to the RPF tanks to mitigate hydrogen generation. Upon actuation of the S, the isolation valves at the PVVS intake interface with ventilation zone 2 actuate closed, the PVVS isolation valve at the radioactive liquid waste immobilization (RLWI) interface ates closed, to prevent nitrogen backflow. During the nitrogen purge, the PVVS equipment piping continues to provide the flow path for the off-gas through the RPF. Safety-related asses are provided around filtration equipment in the hot cell that could contribute to a ked pathway and an alternate, safety-related exhaust point to the roof is actuated open.
branch to the alternate release point is upstream of the PVVS blowers.
protection is provided for the guard beds and delay beds. Temperature instrumentation carbon monoxide detection are used to monitor for oxidation. The beds may be isolated or ged with nitrogen to smother the reaction. Additionally, operators can attempt to increase system flow rate to increase convective cooling. The engineered safety features actuation tem (ESFAS) automatically isolates affected delay bed groups on high carbon monoxide centration in the effluent gas.
cipal components of the PVVS are identified in Table 9b.6-2.
rocess flow diagram of the PVVS is provided in Figure 9b.6-1.
6.1.3 Operational Analysis and Safety Function PVVS provides confinement of fission products to prevent release of radioactive material.
PVVS maintains hydrogen concentrations below the lower flammability limit (LFL) to clude a hydrogen deflagration or detonation, as discussed in Subsection 9b.6.1.3.1. The VS passively reduces the concentration of radionuclides in the gaseous effluent to the lity stack, including during postulated transients, as discussed in Subsection 9b.6.1.3.2.
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- Safety-related components in the PVVS remain functional during normal conditions, and during and following design basis events.
- Valves in PVVS fail to their designated safe position on loss of power.
- Redundant isolation capabilities are provided at confinement boundaries.
- Redundant isolation is provided for safety-related actuations.
- An open flow path through PVVS remains available during normal conditions, and during and following design basis events.
- PVVS components installed over, attached to, or adjacent to safety-related equipment are designed so as not to fail in such a way that is detrimental to the operation of safety-related equipment.
6.1.3.1 Hydrogen Mitigation rogen is generated by radiolysis in the target solution and the byproduct solutions tained in the process tanks of the RPF, excluding the target solution preparation system PS). Build-up of the hydrogen could result in a detonation or deflagration if the centration exceeds the LFL. PVVS ventilates the RPF tanks to prevent build-up of hydrogen ve LFL.
he event of failure of the PVVS discharge blowers, the PVVS filtration equipment continues rocess the sweep gas provided from N2PS through the tanks throughout the RPF. The ntity of sweep gas supplied is sufficient to maintain hydrogen concentration below the LFL.
er normal operation, the required quantity of sweep gas is induced into the process tanks he suction from the PVVS blowers. In the event of failure of the PVVS blowers, the N2PS provide the sweep gas flow, thereby maintaining the sweep gas component of the total VS flow.
6.1.3.2 Iodine and Noble Gas Abatement systems and processes in the RPF release radioactive isotopes of iodine and noble gases the target solution and from byproduct solutions. Gases discharged by TOGS from the ary system boundary, which contain noble gases and iodine, are also processed by the VS. The off-gas may also contain radioactive particulates such as cesium. HEPA filters are d to remove entrained particulates from the air flow. Carbon filters are used to capture ne and carbon beds are employed to delay the release of xenon and krypton isotopes. The ign ensures that 10 CFR 20 limits are met.
6.1.4 Instrumentation and Control ety-related PVVS instrumentation has redundant channels and provides output to ESFAS.
safety-related PVVS instrumentation provides output signals to the process integrated trol system (PICS).
perature instrumentation is used to monitor the performance of the condensers, heaters, acid adsorbers as well as the guard beds and delay beds.
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noxide concentrations in the bed effluent.
w instrumentation is used to monitor the flow rate of air from ventilation zone 2 into the RPF ks and vessels ventilated by PVVS. The PICS alerts operators on low flow. Flow rumentation is used to monitor the flow rate of air from the RPF tanks and vessels to the densers. The system is designed to maintain this flow rate above the minimum required to ntain hydrogen levels below the LFL.
ssure instrumentation is provided to monitor performance of the HEPA filters.
6.1.5 Radiological Protection and Criticality Control VS processes are performed within the production facility biological shield (PFBS) hot cells below-grade vaults, which supports compliance with the as low as reasonably achievable ARA) objectives and 10 CFR 20 dose limits. Section 11.1 provides a description of the ation protection program, and Section 4b.2 provides a detailed description of the PFBS.
re are no credible mechanisms by which to create a criticality hazard in the PVVS. As cribed in Subsection 6b.3.1.6, there are no identified criticality safety controls for the PVVS.
6.1.6 Technical Specifications tain material in this subsection provides information that is used in the technical cifications. This includes limiting conditions for operation, setpoints, design features, and ans for accomplishing surveillances. In addition, significant material is also applicable to, may be used for the bases that are described in the technical specifications.
6.2 NITROGEN PURGE SYSTEM N2PS provides a backup supply of sweep gas to each irradiation unit (IU) and to all tanks mally ventilated by the PVVS during a loss of normal power or loss of normal sweep gas
. The off-gas resulting from the nitrogen purge is treated by passive PVVS filtration ipment prior to being discharged to the stack, as discussed in Subsection 9b.6.1.2. The ogen supply pressure is regulated to overcome the pressure drop through pipe fittings, VS filtration components, and the facility stack. The N2PS is safety-related and Seismic egory I. A description of system interfaces is provided in Table 9b.6-3.
6.2.1 Design Bases design bases of the N2PS include:
- Ensure safe shutdown by preventing detonations or deflagrations from potential hydrogen accumulation in the IUs and RPF processes during deviations from normal conditions; and
- Remain functional during and following design basis events.
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S provides back-up sweep gas flow in the form of stored pressurized nitrogen gas.
wnstream pressure is controlled with self-regulating pressure reducing valves with rpressure protection by pressure relief valves. On actuation of the N2PS, nitrogen flows ugh the irradiation facility (IF) and RPF equipment to ensure the hydrogen concentration is w the LFL. The nitrogen purge flows through the normal PVVS path and filtration ipment, including the delay beds. After exiting the delay beds in PVVS, the nitrogen purge is rted to a safety-related alternate vent path in case of a downstream blockage. Valves figured to fail open allow the diversion to the alternate vent path. After actuation of the S, the pressurized storage tubes can be refilled by truck deliveries.
rocess flow diagram of the N2PS is provided in Figure 9b.6-2.
ge of an IU n loss of normal power as determined by the engineered safety features actuation system FAS) and after a delay or upon loss of normal sweep gas flow in the IU as determined by TSV reactivity protection system (TRPS), solenoid valves on the nitrogen discharge nifold actuate open, releasing nitrogen into the IU cell supply header. Upon loss of sweep flow in any IU cell, nitrogen solenoid isolation valves for the given cell actuate open asing nitrogen purge gas into the TSV dump tank, and valves in the TOGS actuate open to w the nitrogen purge gas to flow to the PVVS. The nitrogen purge gas flows through the dump tank, TSV, and TOGS equipment before discharging into PVVS. A flow switch vides indication that nitrogen is flowing to the IU cell. A detailed discussion of the IU Cell ogen Purge is provided in Section 7.4.
ge of RPF Equipment n loss of normal power or loss of normal sweep gas flow through PVVS, as determined by ESFAS, solenoid valves on the ventilation zone 2 air supply to PVVS fail closed and isolate sweep gas air flow to the RPF tanks. At the same time, solenoid valves on the nitrogen harge manifold actuate open, releasing nitrogen into the RPF distribution piping. The ogen flows through the RPF equipment in parallel before discharging into PVVS. A flow ch provides indication that nitrogen is flowing to the RPF distribution piping.
cesses that receive ventilation air from the PVVS during normal conditions are also tilated by N2PS during deviations from normal operation. In the RPF, the N2PS ventilates s in the TSSS, RLWS system, radioactive drain system (RDS), molybdenum extraction and fication system (MEPS), iodine and xenon purification and packaging (IXP) system, and
. A detailed discussion of the RPF Nitrogen Purge is provided in Section 7.5.
6.2.3 Operational Analysis and Safety Function he event of a loss of normal power, loss of sweep gas flow through PVVS, or loss of sweep flow through any TOGS, the N2PS controls the buildup of hydrogen which is released into primary system boundary and tanks or other volumes which contain fission products to ure that the system and confinement boundaries are maintained.
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rpressure protection provided by pressure relief valves. Tanks containing irradiated target tion in the RPF are supplied with a self-regulating pressure reducing valve with rpressure protection provided by a pressure relief valve. TSV dump tanks are supplied with lf-regulating pressure reducing valve. N2PS piping, valves, and in-line components are igned to ASME B31.3, Process Piping (ASME, 2013).
high-pressure nitrogen gas storage is contained in integrally forged pressure vessels
, high-pressure nitrogen gas tubes) designed to meet the requirements of ASME Boiler and ssure Vessel Code (BPVC),Section VIII, Rules for Construction of Pressure Vessels ME, 2010). The tubes and associated piping, manual isolation valves, high point vents, low t drains, self-regulating pressure reducing valves, relief valves, check valves, and pressure rumentation for the supply system are located in the N2PS structure, an above-grade forced concrete structure adjacent to the main production facility. The N2PS structure and ipment are designed to remain functional during and following a seismic event. Additionally, N2PS structure is designed to withstand the impact of tornado missiles.
tubes are manifolded so they will act in unison and have a common remote fill connection llow refill by tanker truck delivery. One redundant high-pressure nitrogen gas tube provides vice in the event of the loss of a tube or failure of the associated valves upstream of the mon manifold. Each high-pressure nitrogen gas tube and the downstream piping and ipment is protected from overpressure by relief valves discharging to atmosphere above the of the structure, through a nonsafety-related vent path.
N2PS is sized to provide three days of sweep gas flow to tanks containing irradiated target tion in the RPF during a loss of normal power or a loss sweep gas flow. The N2PS also vides three days of sweep gas flow to each TSV dump tank.
6.2.4 Instrumentation and Control N2PS includes pressure instrumentation to monitor the function of the self-regulating ssure reducing valves. The nitrogen tube pressure, tube discharge pressures, pressure to IU cells, and pressure to the RPF tanks are monitored. The pressure instrument output is vided to PICS.
N2PS includes flow switches on the piping to the IU cells and RPF tanks to provide cation of normal operation when the purge is actuated. The flow switch status is provided to S.
S solenoid valves include valve position indication. The position status for each valve is vided to TRPS if it serves the IU cells or to ESFAS if it serves the RPF tanks.
gen sensors are provided in locations near N2PS equipment. The oxygen instruments alert rators locally of an asphyxiation hazard in the event of a nitrogen leak.
PS actuates the N2PS purge of the affected IU on loss of normal power to an IU cell after a y or on loss of flow in TOGS.
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6.2.5 Radiological Protection and Criticality Control N2PS contains no special nuclear material or any other radioactive material. Therefore, the S does not require shielding nor is criticality safety considered in the design.
6.2.6 Technical Specifications tain material in this subsection provides information that is used in the technical cifications. This includes limiting conditions for operation, setpoints, design features, and ans for accomplishing surveillances. In addition, significant material is also applicable to, may be used for the bases that are described in the technical specifications.
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Table 9b.6 Process Vessel Vent System Interfaces (Sheet 1 of 2)
Interfacing System Interface Description gineered safety features The ESFAS monitors the operation of the process vessel vent system uation system (ESFAS) (PVVS). ESFAS actuates the nitrogen purge system (N2PS) and opens the PVVS filtration bypass on low ventilation flow through PVVS, and isolates the delay beds on high carbon monoxide concentration.
ine and xenon purification The PVVS ventilates tanks in the IXP.
packaging (IXP) system lybdenum extraction and The PVVS ventilates the molybdenum eluate hold tank and MEPS ification system (MEPS) condensate tank.
ogen purge system (N2PS) The N2PS provides sweep gas flow through the PVVS piping and filtration equipment on loss of normal power or normal flow in PVVS.
rmal electrical power supply The NPSS is distributed to the PVVS blowers, the PVVS reheater, and tem (NPSS) ancillary equipment.
cess integrated control The PICS controls the PVVS and monitors PVVS instrument signals.
tem (PICS) duction facility biological The PFBS provides shielding to workers from the PVVS. PVVS eld (PFBS) equipment is located in a hot cell and in a below-grade vault.
dioactive drain system The PVVS ventilates the RDS tanks.
S) dioactive liquid waste The PVVS ventilates the RLWS tanks. The PVVS drains condensate rage (RLWS) system water to the RLWS for disposal.
dioactive liquid waste The PVVS ventilates the immobilization feed tank.
mobilization (RLWI) system dioisotope process facility The RPCS provides cooling capacity to the PVVS for the off-gas ling system (RPCS) condensers.
diological ventilation zone 1 The PVVS blowers discharge into a header shared by RVZ1 to the Z1) facility stack. Some PVVS components are located in a hot cell, which is ventilated by RVZ1.
diological ventilation zone 2 The PVVS intake removes air from RVZ2 for use as sweep gas across Z2) the RPF tanks.
ck release monitoring The SRMS monitors the discharge from the PVVS delay beds to the tem (SRMS) stack.
ndby generator system The SGS provides nonsafety-related backup power to PVVS S) components.
get solution staging system The PVVS ventilates the TSSS tanks to mitigate hydrogen generation.
SS) The PVVS may also transfer condensate water to the TSSS for reuse in the irradiation cycle.
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Interfacing System Interface Description get solution vessel (TSV) The PVVS accepts sweep gas from the TOGS gas analyzers, purges gas system (TOGS) from the TOGS boundary, and discharge from the TOGS pressure relief valves.
cuum transfer system (VTS) The PVVS accepts the discharge of the VTS vacuum pumps. The PVVS also ventilates the vacuum lift tanks when they are not lifting to mitigate hydrogen generation.
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Table 9b.6 Process Vessel Vent System Process Equipment Component Description d adsorbers Filter cartridge packed adsorbent to neutralize potential acids in the off-gas rd beds Filter cartridge packed with activated carbon to adsorb iodine species from the off-gas ay beds Vessels packed with activated carbon to delay the release of noble gases in the off-gas (e.g., xenon and krypton) to the stack PA filters Filters to remove particulates and carbon fines from the off-gas VS condensers Heat exchanger to reduce dew point of the off-gas upstream of the carbon beds VS reheaters Electric heater to reduce relative humidity of the off-gas upstream of the carbon beds VS blowers Draws off-gas from process vessels and exhausts off-gas to facility stack densate tank Collects the condensate from the PVVS condensers VS condensate pump Positive displacement pumps to transfer condensate back into the process or to the waste system ng components PVVS piping, valves, in-line components NE Medical Technologies 9b.6-10 Rev. 1
Table 9b.6 Nitrogen Purge System Interfaces Interfacing System Interface Description gineered safety features ESFAS actuates the N2PS on loss of normal power or loss of uation system (ESFAS) normal flow in the process vessel vent system (PVVS). Outputs of instruments in N2PS are provided to ESFAS.
cess integrated control PICS monitors outputs of nonsafety-related instruments in N2PS.
tem (PICS)
VS N2PS uses the normal PVVS piping for sweep gas to the radioisotope production facility (RPF) tanks and through PVVS filtration equipment.
diological ventilation The N2PS discharges pressurized nitrogen into PVVS distribution ne 2 (RVZ2) piping. The normal intake of this distribution pipe is taken from RVZ2.
bcritical assembly N2PS provides sweep gas to the target solution vessel (TSV) tem (SCAS) dump tank, TSV, and TSV off-gas system (TOGS) on loss of normal power or loss of normal TOGS flow.
rget solution vessel TRPS actuates the N2PS on loss of normal power or loss of V) reactivity protection normal flow in TOGS. Outputs of instruments in N2PS are tem (TRPS) provided to TRPS.
interruptible electrical Emergency safety-related power is provided to N2PS equipment wer supply system by UPSS.
PSS)
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Chapter 9 - Auxiliary Systems Cover Gas Control in the Radioisotope Production Facility Figure 9b.6 PVVS Process Flow Diagram SHINE Medical Technologies 9b.6-12 Rev. 1
Chapter 9 - Auxiliary Systems Cover Gas Control in the Radioisotope Production Facility Figure 9b.6 N2PS Process Flow Diagram SHINE Medical Technologies 9b.6-13 Rev. 1
7.1 MOLYBDENUM ISOTOPE PRODUCT PACKAGING SYSTEM 7.1.1 Design Bases design bases of the molybdenum isotope product packaging system (MIPS) include:
- Receive the product collection bottle from either the molybdenum process lines or the iodine and xenon process line; and
- Package product collection bottle for shipment.
7.1.2 System Description MIPS prepares the molybdenum-99 (Mo-99) product bottle, iodine product bottle, or xenon duct bottle for shipment. The package is labeled and placed in the appropriate shipping tainer. The MIPS provides a quarantine area for products undergoing quality control testing r to shipment, as discussed in Subsection 9b.7.1.3.
ipment within the MIPS includes:
- Molybdenum product bottle
- Molybdenum secondary container
- Molybdenum shipping cask
- Iodine product bottle
- Iodine secondary container
- Iodine shipping cask
- Xenon product bottle
- Xenon secondary container
- Xenon shipping cask
- Leak test equipment
- Label printers r the finished radioisotopes are purified and sampled in the purification hot cell and the iodine xenon purification and packaging (IXP) hot cell, the product bottles are transferred to one of two packaging hot cells within the supercell. One of the packaging hot cells serves two ybdenum extraction and purification system (MEPS) process lines, and the other packaging cell serves a MEPS process line and the IXP process line. Figure 4b.2-4 shows a general iction of the supercell.
7.1.3 Operational Analysis and Safety Function els are applied to the product bottle, secondary container, and shipping container. The labels tain the appropriate information for shipment. The product bottles are secured within a ondary container and then into a shielded cask that is part of the shipping package. The lid of shielded cask is applied to the container, and the package is leak tested. If leakage eptance criteria are met, the shielded cask can be secured into the overpack and the shipping tainer may be released.
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duct being shipped meets specification. Shipping containers may also be quarantined after product bottle has been secured for the same reason.
SHINE product bottle for Mo-99 is a stainless-steel bottle with a stainless-steel screw cap tainer/closure system or high-density polyethylene (HDPE) with a plastic screw cap. The duct volume ranges from [ ]PROP, depending on the customer. The duct form will be an aqueous solution of sodium molybdate with an activity of up to
]PROP at time of dispatch. The product bottles would then be placed in approved ping containers and transported to the customers in accordance with regulatory uirements.
iodine product is expected to be packaged in solution vials less than one liter in size, taining the iodine in a solution of sodium hydroxide, which will then be packaged in an roved shipping container. The xenon product is expected to be packaged in gas cylinders an internal volume of less than one liter. These product cylinders would then be placed in roved shipping containers and transported to customers.
MIPS is located in shielded hot cells in the supercell. Shielding on the packaging hot cells ts the radiation exposure of individuals to within the regulatory limits described in 10 CFR 20.
tion 11.1 provides a description of the radiation protection program, and Section 4b.2 vides a detailed description of the production facility biological shield (PFBS).
re is no special nuclear material (SNM) present within the MIPS system boundary. There are nuclear criticality safety requirements associated with the MIPS.
MIPS is nonsafety-related.
7.1.4 Instrumentation and Control process integrated control system (PICS) accepts outputs from MIPS instruments.
tion 7.3 provides a detailed discussion of the PICS.
7.1.5 Technical Specifications re are no technical specifications applicable to the MIPS.
7.2 MATERIAL HANDLING SYSTEM 7.2.1 Design Bases material handling system (MHS) includes overhead cranes and hoists that are used to move anipulate radioactive material within the radiologically controlled area (RCA).
diation Facility Overhead Crane irradiation facility (IF) crane is designed to meet the applicable requirements of American iety of Mechanical Engineers (ASME) B30.2, Overhead and Gantry Cranes (Top Running ge, Single or Multiple Girder, Top Running Trolley Hoist) (ASME, 2011a); Crane NE Medical Technologies 9b.7-2 Rev. 2
ME NOG-1, Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, tiple Girder) (AMSE, 2015).
IF overhead crane is designed to the following criteria:
- Meet seismic requirements and prevent failures of the crane that could damage safety-related equipment such that the equipment would be prevented from performing its safety function.
- Meet the single-failure-proof design criteria and construction of ASME NOG-1, Type I cranes and be designed to perform as a Service Level B - Light Service crane as described in CMAA 70.
- Secure its load in place upon a loss of power and any fault condition. The hoisting machinery and wire rope reeving system, in addition to other affected components, is designed to withstand the most severe potential overload, including two-blocking and load hang-up.
ioisotope Production Facility Overhead Crane radioisotope production facility (RPF) overhead crane is designed to meet the applicable uirements of ASME B30.2 (ASME, 2011a), CMAA 70 (CMAA, 2004), and ASME NOG-1 ME, 2015).
RPF overhead crane is designed to the following criteria:
- Meet seismic requirements and prevent failures of the crane that could damage safety-related equipment such that the equipment would be prevented from preforming its safety function.
- Meet the design criteria and construction of ASME NOG-1, Type II cranes and be designed to perform as a Service Level B - Light Service crane as described in CMAA 70.
- Remain in place with or without a load during a seismic event.
7.2.2 System Description diation Facility Overhead Crane IF overhead crane is a 40-ton, double girder, bridge style crane designed for the handling of ld cover plugs and equipment such as neutron drivers and process skids inside the IF. The IF rhead crane is designed to span the width of the IF and travel the length of the IF.
use of a single-failure-proof crane with rigging and procedures that implement the uirements of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants (USNRC, 1980) ures that the potential for a heavy load drop is extremely small, and therefore, analysis of the ential effects of heavy load drops are not required.
IF overhead crane is designed and constructed such that it will remain in place and support critical load during and after an aircraft impact but is not required to be operational after this NE Medical Technologies 9b.7-3 Rev. 2
ioisotope Production Facility Overhead Crane RPF overhead crane is a 15-ton, double girder, bridge style crane designed for the handling hield cover plugs and equipment in the RPF. The RPF overhead crane is designed to span width of the RPF and travel the length of the RPF.
RPF overhead crane employs the use of mechanical stops, electrical-interlocks, and determined safe load paths to minimize the movement of loads in proximity to redundant or l safe shutdown equipment. These safeguards ensures that off-normal load events from s containing radioactive materials or safety-related SSCs that are beneath, or directly cent to a potential travel load path of the RPF overhead crane, could not result in the plete loss of a safe shutdown function or the release of radioactivity in excess of 10 CFR 20 s.
RPF overhead crane is designed and constructed following the seismic requirements for an ME NOG-1, Type II crane so that it will remain in place with or without a load during a design is earthquake. The crane is not required to support the critical load nor remain operational ng and after such an event.
7.2.3 Operational Analysis and Safety Function IF overhead crane removes irradiation unit (IU) cell plugs, the target solution vessel (TSV) gas system (TOGS) cell plugs, primary cooling room plugs, and neutron driver transport to from IU cells and the neutron driver assembly system (NDAS) service cell. The IF overhead ne is used for lifting, repositioning, and landing operations associated with major components he subcritical assembly system (SCAS), the primary closed loop cooling system (PCLS), the GS, and the tritium purification system (TPS) as well as various planned maintenance vities throughout the IF.
RPF overhead crane is utilized for lifts including the removal of tank vault, valve pit, and pipe ch plugs, removal of carbon delay bed vault plugs, supercell slave manipulator replacements, the removal of column waste drums and post cooldown shielding/packaging. The RPF rhead crane is used for various planned maintenance activities. In addition, the crane orms lifting of empty tanks in the RPF, immobilized waste drums and the associated lding/packaging hardware, and other major components within the RPF.
IF and RPF overhead cranes are inspected, tested, and maintained in accordance with ME B30.2 (ASME, 2011a). The inspection requirements reduce the probability of a load drop could result in a release of radioactive materials or damage to essential safe shutdown ipment that could cause unacceptable radiation exposures. Inspection and testing of special g devices are performed in accordance with American National Standards Institute SI) N14.6, Radioactive Materials - Special Lifting Devices for Shipping Containers Weighing 000 Pounds (4500 kg) or More (ANSI, 1993). Inspection and testing of lifting devices not cially designed are in accordance with ASME B30.9, Slings (ASME, 2018).
h respect to the SHINE facility, a heavy load is defined as a load that, if dropped, may cause ological consequences that challenge 10 CFR 20 limits. For cranes operating in the vicinity of NE Medical Technologies 9b.7-4 Rev. 2
- 1. Safe load paths will be defined for the movement of heavy loads; deviations from the defined load paths will require written procedures approved by site safety personnel.
- 2. Procedures will be developed to cover load handling operations for heavy loads.
Procedures will include the identification of required equipment, inspections, and acceptance criteria required before movement of loads; the steps and proper sequence to be followed in handling the load; the defined safe load path and other special precautions.
- 3. Crane operators will be trained, qualified, and conduct themselves in accordance with Chapter 2-3 of ASME B30.2.
- 4. Special lifting devices used in the vicinity of safety-related SSCs will satisfy the guidelines of ANSI N14.6.
- 5. Lifting devices that are not specially designed will be installed and used in accordance with the guidelines of ASME B30.9.
- 6. Tests and inspections will be performed prior to use where it is not practical to meet the frequencies of ASME B30.2 for periodic inspection and testing, or where frequency of crane use is less than the specified inspection and test frequency.
- 7. The crane will be designed to meet applicable criteria and guidelines of ASME B30.2 and CMAA 70.
IF and RPF overhead cranes are nonsafety-related.
7.2.4 Instrumentation and Control IF and RPF overhead crane control systems provide for separate operation of the hoist, ge, and trolley motions. Overhead crane control switches for the main hoists, bridges, and eys are radio controlled with backup pendant controllers. Both IF and RPF overhead crane tems allow all motions to be controlled from the radio transmitter as well as a backup pendant hbutton station. The controls for both the IF and RPF overhead cranes are interlocked so only station (radio or pendant) can be operated at a time. The IF and RPF overhead crane trols are such that the release of the controller or loss of power automatically stops the nes motion and sets the brakes.
7.2.5 Technical Specifications tain material in this subsection provides information that is used in the technical cifications.
7.3 RADIOACTIVE LIQUID WASTE IMMOBILIZATION SYSTEM 7.3.1 Design Bases design bases of the radioactive liquid waste immobilization (RLWI) system include:
- Receive blended liquid waste from the radioactive liquid waste storage (RLWS) system for immobilization.
- Perform selective removal of classification-driving isotopes, as needed, from blended liquid waste [ ]PROP/ECI.
- Perform solidification of blended liquid waste.
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RLWI system piping is designed and constructed in accordance with ASME B31.3, Process ng (ASME, 2013). Nonsafety-related components within the RLWI system are designed to dards satisfying system operation.
7.3.2 System Description RLWI system solidifies blended liquid waste to a form suitable for shipping and disposal. The WI system removes selected isotopes, as needed, from the blended liquid waste and then obilizes the wastes for ultimate disposal. The headspace cover gas in the immobilization d tank is swept by the PVVS.
blended liquid waste sources and radionuclide and uranium concentrations are described in section 9b.7.4.
immobilization feed tank is filled from the liquid waste blending tanks on a batch basis by uum suction applied to the immobilization feed tank from the vacuum transfer system (VTS).
itive displacement pumps transfer the contents of the immobilization feed tank [
]PROP/ECI, and meter the tank contents to a disposable waste m.
waste drums are prefilled with measured amounts of dry, powdered solidification agent in ordance with the process control program (PCP). The prefilled drum is transferred into an losure for contamination control. The radiological ventilation zone 1 exhaust subsystem Z1e) equipment processes air from the enclosure through a high efficiency particulate air PA) and carbon filter before discharging to the facility stack. Transfer of the prefilled waste m inside the enclosure is by remote handling equipment and positioners.
liquid waste drum is filled with blended liquid waste and mixed. Subsequent to fill and mixing, fill and vent ports are disengaged. The drum is then remotely transferred to a curing station re the mixed contents of the waste drum hardens prior to removal from the enclosure. The ed drum is remotely transferred into a shielded cask and transported to the material staging ding for further radiological decay, as needed, prior to shipment to a licensed disposal facility.
mote sampling for waste characterization is performed in the RLWS prior to solidification vities. Radiation measurements are performed on the solidified waste drum prior to shipment e material staging building to verify it meets shipping dose rate requirements.
le 9b.7-1 identifies the systems which interface with the RLWI system. Figure 9b.7-1 vides a process flow diagram of the RLWI system.
7.3.3 Operational Analysis and Safety Function id waste solidification is performed in accordance with a PCP. The RLWI system is sized to cess approximately double the routine liquid waste generation rate from the RPF.
maximum level in the immobilization feed tank is limited to a predetermined level below the er gas supply and vent piping. The system is provided with the ability to drain unprocessed NE Medical Technologies 9b.7-6 Rev. 2
RLWI system valves and dampers fail in the safe position on loss of power.
le 11.2-5 provides the waste methodology for consolidated liquids.
RLWI system is designed to limit exposure to individuals by ensuring compliance with the licable requirements of 10 CFR 20. The immobilization feed tank, liquid waste drum fill ps, and valves are located in a shielded enclosure. Selective isotope removal and waste m filling and mixing are also performed within the shielded enclosure. Piping that contains oactive and potentially radioactive materials is routed through shielded pipe chases to limit exposure of individuals to radiation.
tion 11.1 provides a description of the radiation protection program, and Section 4b.2 vides a detailed description of the PFBS.
ng and components connected to, installed over, or installed adjacent to safety-related SSCs designed to meet seismic requirements because its failure could damage safety-related ipment such that the equipment would be prevented from performing its safety function.
safety function of the RLWI system is to prevent inadvertent criticality through design of ipment in accordance with the criticality safety evaluation. A description of provisions for cality control in the RLWI system is provided in Subsection 6b.3.2.9.
7.3.4 Instrumentation and Controls ve position indicators and temperature, flow, level, and pressure instrumentation provide ote indication of the operating state of the RLWI. Output of valve position indicators and other rumentation is provided to the remotely-located PICS.
7.3.5 Technical Specifications re are no technical specifications associated with RLWI.
7.4 RADIOACTIVE LIQUID WASTE STORAGE SYSTEM 7.4.1 Design Bases design bases of the RLWS system include:
- Collect liquid radioactive wastes from the MEPS, IXP, VTS, PVVS and non-routine operations such as decontamination flushes.
- Blend collected liquid radioactive wastes for feed to the RLWI system.
- Provide holdup time for radioactive decay of isotopes in the liquid waste.
- Allow remote sampling of the stored liquid waste.
- Control radioactive liquid waste solution pH to preclude precipitation of uranium and potential criticality.
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RLWS system collects, stores, blends, conditions, and meters liquid wastes for processing he RLWI for solidification. Included in the blended liquid wastes is PVVS condensate which also be recycled through the target solution staging system (TSSS) to minimize waste eration. The RLWS system can also transfer liquid via a normally removed pipe spool to a et solution storage tank for sampling and verification against target solution parameters. The dspace in each RLWS system tank is swept with air by the PVVS or by the nitrogen purge tem (N2PS) to remove the potential accumulation of radiolytically generated hydrogen gas.
oratory waste is preconditioned and manually processed separately from the RLWS system.
id waste collected, blended, and stored by the RLWS system includes:
- Uranium liquid waste, with uranium concentrations potentially exceeding 25 gU/l. This waste is located in the uranium liquid waste tanks.
- Radioactive liquid waste, with negligible uranium concentration with respect to criticality safety (< 1 gU/l). This waste is stored in the liquid waste collection tanks.
- Blended liquid waste, with low uranium concentrations (< 25 gU/l). Blended waste may originate from uranium liquid waste, radioactive liquid waste, or any combination of the two.
nium liquid waste tanks are geometrically favorable annular tanks similar in design to those d in TSSS. These tanks include two redundant overflow lines which drain to the radioactive n system (RDS) in the event of an overfill. The uranium liquid waste tanks are connected in es to ensure high concentration uranium-bearing waste (greater than 25 gU/l) is not vertently transferred to the non-geometrically favorable liquid waste blending tanks.
uranium liquid waste tanks are configured to operate in series, with the first tank receiving tes from the following sources:
- Mo-99 extraction column washes
- Iodine-131 (I-131) recovery column washes
- Spent target solution
- Solution in radioactive drain sump tanks
- Solution in VTS knockout pot
- Decontamination liquid waste
- PVVS condensate tank
- Solution from the second uranium liquid waste tank via gravity drain from the uranium liquid waste lift tank remaining liquid wastes are collected in four liquid waste collection tanks designed and sized aximize storage capacity. The liquid waste collection tanks are configured to receive wastes the following sources:
- [ ]PROP/ECI effluent and washes
- MEPS condensate and purification waste
- [ ]PROP/ECI washes NE Medical Technologies 9b.7-8 Rev. 2
tes from the following sources:
- Second uranium liquid waste tank
- PVVS condensate tank
- Liquid waste collection tanks nium liquid waste is combined with the radioactive liquid waste and/or PVVS condensate in liquid waste blending tanks for homogeneous radionuclide and uranium concentrations in the WI system feed.
tanks are sized to maximize decay time thereby minimizing dose rates from the immobilized te product. Each uranium liquid waste tank has a minimum nominal capacity of
]PROP/ECI, and each of the liquid waste collection tanks and liquid waste blending tanks a minimum nominal capacity of 600 gallons.
RLWS system piping is designed and constructed in accordance with ASME B31.3, Process ng (ASME, 2013).
le 11.2-6 provides the chemical composition and radiological properties of liquid waste ams.
le 9b.7-2 identifies the systems which interface with the RLWS system. Figure 9b.7-2, ure 9b.7-3, and Figure 9b.7-4 provide process flow diagrams of the RLWS system.
7.4.3 Operational Analysis and Safety Function enoid valves isolating radioactive liquid flow paths fail to the normally isolated positions.
enoid valves isolating the sweep gas flow path fail to the normally aligned flow from air to the VS vent header. Operators align the RLWS tank inlets and outlets based on procedures using rmation from the position indicators and instrumentation.
RLWS system tanks, valves, and piping are located in shielded tank vaults, valve pits, and trenches within the RPF. Section 11.1 provides a description of the radiation protection gram, and Section 4b.2 provides a detailed description of the PFBS.
mpling of RLWS system tank contents for pH verifies that waste solution acidity is maintained adjusted as necessary. Solution composition can be adjusted via the reagent addition line.
mpling of waste tanks is performed by vacuum lift to a hot cell, where samples are remotely ained.
owing a period of decay to reduce dose rates, waste is transferred from the liquid waste ding tanks to the RLWI system immobilization feed tank. Subsection 9b.7.3 provides a ailed discussion of the RLWI system.
WS system piping connected to, installed over, or installed adjacent to safety-related ipment is designed to meet seismic requirements because its failure could damage safety-ted equipment such that the equipment would be prevented from performing its safety tion.
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cality control in the RLWS system is provided in Subsection 6b.3.2.2.
7.4.4 Instrumentation and Control ve position indicators and temperature, level, and uranium concentration instrumentation vide remote indication of operating state of the RLWS tanks. Output of valve position cators and other instrumentation is provided to the remotely-located PICS.
7.4.5 Technical Specifications tain material in this section provides information that is used in the technical specifications.
includes limiting conditions for operation, setpoints, design features, and means for omplishing surveillances. In addition, significant material is also applicable to, and may be renced by, the bases that are described in the technical specifications.
7.5 SOLID RADIOACTIVE WASTE PACKAGING SYSTEM 7.5.1 Design Bases design bases function of the solid radioactive waste packaging (SRWP) system is to collect, regate, and stage for shipment, solid radioactive wastes from the IF and RPF in accordance the radioactive waste management program.
7.5.2 System Description SRWP system consists of equipment designed and specified to collect and package solid oactive waste from systems throughout the IF and RPF without limiting the normal operation vailability of the facilities. Solid waste may include dry active waste (DAW), spent ion hange resin, and filters and filtration media. The SRWP system also inventories materials ering and exiting the facility structure storage bore holes as the supercell imports and exports m.
le 11.2-1 includes a summary of the estimated annual waste stream and Table 11.1-10 udes a description of radioactive sources. Tables 11.2-2 through 11.2-4 present the waste hodology associated with the disposal of neutron drivers, spent columns, and process sware, respectively.
le 9b.7-3 identifies the systems which interface with the SWRP system.
7.5.3 Operational Analysis and Safety Function d radioactive waste is collected in segregated containers. Containers may be sorted for entially non-contaminated waste. Contaminated waste is sealed, labeled, and transported to material staging building for characterization, documentation, and staging for shipment. Solid tes potentially having high levels of radioactivity are collected and transported to the material ing building in shielded casks.
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osal.
aration columns used in the processes contained within the supercell are stored on supercell age racks for a minimum of 14 days following their use. Following decay on storage racks, mns are transferred to column waste drums imported by the supercell. The column waste ms are exported and transferred to the drum storage bore holes. Following extended decay, mn waste drums are removed from the bore holes by the supercell.
ending on weight, solid waste may need to be transferred to the material staging building g forklifts or other lifting devices. Once in the material staging building, solid wastes may be for decay. Waste is characterized and staged for shipment in the material staging building.
ste is handled and shipped off site in accordance with the radioactive waste management gram, described in Section 11.2.
WP system operations are performed in accordance with the requirements of the radiation ection program, described in Section 11.1.
nuclear criticality safety requirements are identified for the SRWP system. Nuclear criticality ty is controlled in upstream interfacing systems, where appropriate.
SRWP system is nonsafety-related.
7.5.4 Instrumentation and Control instrumentation or controls have been identified for the SRWP system.
7.5.5 Technical Specifications re are no technical specification parameters associated with the SRWP system.
7.6 RADIOACTIVE DRAIN SYSTEM 7.6.1 Design Bases design bases of the RDS include:
- Collect liquids leaked from tanks, piping, or other components which require favorable geometry for collection and storage.
- Collect liquids resulting from the overflow of the target solution storage tanks, target solution hold tanks, and uranium liquid waste tanks.
- Provide overpressure protection for the extraction cells and IXP cells of the supercell, as the RDS forms an open pathway through the RDS tanks to the PVVS.
- Allows a representative sample of the contents of the RDS sump tanks to be obtained.
- Provide a minimum collection volume equal to the maximum liquid volume of one annular tank.
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RDS consists of drip pans with drain lines, tank overflow lines, collection tanks and rumentation to alert operators of system status. The RDS includes drip pans located beneath extraction and IXP hot cells, favorable geometry tanks, and piping for systems that normally tain high concentration (> 25 gU/l) fissile solution. The RDS also collects overflow from target tion and uranium waste tanks. The RDS consists of two favorable geometry tanks (annular s) that collect leakage from postulated sources. The leakage and overflow are connected by ng that is substantially located within the basemat of the RPF as well as in the RPF pipe ch. Gravity provides the motive force between the various drip pans and the RDS tanks. No es are installed between the potential collection source and the collection tanks.
le 9b.7-4 identifies the systems which interface with the RDS.
ure 9b.7-5 provides a process flow diagram for the RDS.
7.6.3 Operational Analysis and Safety Function RDS includes two sump tanks, each sized to accept the largest volume of liquid containing M that is postulated to leak from a favorable geometry tank. The largest volume of liquid taining SNM postulated to leak into the RDS system is the volume of the largest favorable metry tank, assuming the tank is filled to the overflow line. The inclusion of two RDS tanks vides operational margin.
RDS sump tanks are connected to the target solution storage tanks, target solution hold s, and uranium liquid waste tanks. Additionally, the sump tanks are connected to drip pans in lts containing annular tanks, drip pans in valve pits servicing annular tanks, drip pans in the n pipe trench, and drip pans in the extraction and IXP hot cells. Redundant overflows to a mon RDS header are provided for each annular tank. The RDS is not used in any normal rating conditions. Instrumentation is provided to alert operators of the presence of liquid in the ous drip pans and of liquid level in the RDS sump tanks. If liquid is detected in the drip pans ump tanks, contingency actions may be performed by using systems other than the RDS.
tents of the RDS tanks are sampled and transferred by the VTS to the appropriate location.
racterization of the sample is performed by the quality control and analytical testing ratories (LABS).
RDS needs to remain open for drainage of fissile-containing liquids (for criticality safety),
e also not compromising the integrity of the confinement barrier. Fluids are contained within ropriate process piping and vessels, and the system is vented to the PVVS.
ng that contains potentially-radiological material is routed through shielded pipe chases to t the exposure of radiation to personnel. The RDS tanks are shielded by a tank vault, which is art of the PFBS. The PFBS shielding requirements are described in Section 4b.2.
S operations are performed in accordance with the requirements of the radiation protection gram, described in Section 11.1.
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visions for criticality control in the RDS is provided in Subsection 6b.3.2.8.
RDS is a Seismic Category I, safety-related system.
7.6.4 Instrumentation and Control RDS is designed as a passive system, and as such does not use any controls.
RDS provides liquid detection signals to the engineered safety features actuation system FAS), as described in Subsection 7.5.5.
safety-related monitoring and control is provided by PICS, as described in Subsection 7.3.3.
7.6.5 Technical Specifications tain material in this subsection provides information that is used in the technical cifications.
7.7 FACILITY POTABLE WATER SYSTEM 7.7.1 Design Bases design bases function of the facility potable water system (FPWS) is to provide the SHINE lity with potable water. The FPWS piping and system components are designed to the licable requirements of the Wisconsin Administrative Code, Safety and Professional vices, and the applicable City of Janesville Ordinances.
7.7.2 System Description FPWS provides a potable water supply to the SHINE facility and is connected to the City of esville water supply. The boundaries of the FPWS include the components from the City of esville water main to the fixtures in each of the buildings on the SHINE facility. The fixtures part of the facility sanitary drain system (FSDS), described in Subsection 9b.7.9. The FPWS s at the backflow prevention device interfacing with both the facility demineralized water tem (FDWS) and facility heating water system (FHWS). The FPWS does not supply water to facility fire detection and suppression system (FFPS) or any firefighting equipment.
7.7.3 Operational Analysis and Safety Function able water is distributed throughout the SHINE facility through a subgrade piping network.
FPWS site main connects to SHINE facility building mains, which include the main duction facility (outside the RCA), the storage building, and the resource building. The FPWS ects the public water system from contamination due to backflow of contaminants through water service connection into the public water system using backflow prevention devices.
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FPWS is nonsafety-related.
7.7.4 Instrumentation and Control FPWS hot water supply is equipped with automatic temperature controls capable of stments.
7.7.5 Technical Specifications re are no technical specification parameters associated with the FPWS.
7.8 FACILITY NITROGEN HANDLING SYSTEM 7.8.1 Design Bases facility nitrogen handling system (FNHS) is designed to supply liquid and compressed eous nitrogen to systems inside the RCA. The FNHS gaseous piping is designed, structed, and tested in accordance with the ASME B31.9, Building Services Piping (ASME, 1b). The FNHS liquid nitrogen piping is designed, constructed, and tested in accordance with ME B31.3, Process Piping (ASME, 2013). The FNHS vaporizers, receivers, and bulk liquid ogen tanks are designed, constructed, and tested to the ASME Boiler and Pressure Vessel e,Section VIII, Rules for Construction of Pressure Vessels (ASME, 2010). The balance of equipment included in the FNHS is commercially available and is designed to standards sfying the system operation.
design basis of the FNHS includes:
- Provide nitrogen gas at the pressures and flow rates to operate sampling equipment in the RLWS system, the RDS, the TSSS, the MEPS, and the target solution preparation system (TSPS).
- Provide nitrogen gas for sparging and mixing of tanks in the RLWS, the TSSS, the MEPS, the RDS, and the IXP system.
- Provide liquid and gaseous nitrogen to the TPS. Gaseous nitrogen is used by the TPS to operate pneumatic equipment. Liquid nitrogen is supplied to the TPS cryopumps and the thermal cycling absorption process (TCAP) isotope separation columns.
- Provide liquid nitrogen in dewars to the IXP system and the instrument laboratory for equipment cooling.
- Provide nitrogen gas to the TOGS for pressure regulation.
- Provide nitrogen gas to the PCLS and the FFPS for pneumatic control mechanisms.
FNHS is not relied upon to prevent accidents that could cause undue risk to the health and ty of the workers and the public or to control or mitigate the consequences of such accidents.
7.8.2 System Description k liquid nitrogen is stored in tanks outside the main production facility and is supplied to orizer units. The vaporizer units vaporize the liquid nitrogen to provide a clean gaseous NE Medical Technologies 9b.7-14 Rev. 2
duction facility via vacuum jacketed cryogenic piping.
FNHS supplies liquid nitrogen to an adjustable pressure phase separator inside the main duction facility that has the capability to store and deliver high quality liquid nitrogen to the
. Liquid nitrogen is supplied to a fill station inside the main production facility. The fill station stalled to fill portable dewars for the disbursement of liquid nitrogen in small quantities as ded by facility processes. Liquid nitrogen dewars supplying the IXP are equipped with an ess flow check valve for the protection of supercell and downstream equipment. Off-gassing the FNHS phase separator and fill station are ventilated through a connection to the ological ventilation zone 2 exhaust subsystem (RVZ2e) inside the IF.
de the RCA a portion of the nitrogen supply gas is piped to a main receiver storage tank ch feeds the FNHS ring header. The remainder of the nitrogen supply gas is piped to the TPS m serving the TPS.
NHS remote receiver tank is maintained on the FNHS ring header to supply abrupt demands provide consistent nitrogen gas flow and pressure to all serviced areas in the RCA. The HS ring header supplies nitrogen gas to sampling equipment, tank sparging and mixing ipment, and level indication equipment. The FNHS ring header supplies nitrogen gas to each HS cooling room receiver tank where it is used by TOGS.
le 9b.7-5 identifies the systems which interface with the FNHS. Figure 9b.7-6 provides a cess flow diagram for the FNHS.
7.8.3 Operational Analysis and Safety Function FNHS bulk liquid nitrogen storage tanks are continuously pressurized by the naturally urring liquid to gas phase change inside the tank with the presence of liquid nitrogen. The HS bulk liquid nitrogen storage tank head space pressure is regulated to provide flow to the orizer. A pressure relief system with a vent path to the atmosphere is maintained on each liquid storage tank to prevent overpressurization of the vessel.
id nitrogen is directed from the pressurized bulk storage tank to vaporizers where it is heated vaporized to nitrogen gas. The gaseous nitrogen supply is regulated through a control nifold designed to control the pressure and prevent possible liquid carryover to the FNHS end rs. The FNHS bulk liquid nitrogen storage tank and vaporizers supply nitrogen gas to the n FNHS receiver tank, the facility nitrogen gas ring header, and the FNHS remote receiver located inside the RCA. The control manifold ensures that adequate pressure is maintained in the production facility. Overpressure protection is provided on the FNHS gaseous facility ply line.
FNHS cooling room receiver tanks are filled from the facility nitrogen gas ring header by ning a normally closed manual valve allowing flow to the tank corresponding to the actuated
- e. Once pressure has equalized the valve is closed and the tank is placed in service.
undant isolation upstream of the cooling room remote receiver tanks ensures that a direct h from the atmosphere inside confinement boundaries to outside those areas are not created.
manual isolation provided is maintained normally closed and administrative controls ensure NE Medical Technologies 9b.7-15 Rev. 2
elding and radiological protection is not required for the FNHS. The FNHS contains no SNM.
FNHS is nonsafety-related.
7.8.4 Instrumentation and Control FNHS is comprised of a packaged skid control system that includes system instrumentation.
packaged control system interfaces with the PICS to deliver FNHS data to plant operators.
FNHS is designed with low temperature shutdown equipment to protect downstream ponents from cryogenic temperatures.
7.8.5 Technical Specifications re are no technical specification parameters associated with the FNHS.
7.9 FACILITY SANITARY DRAIN SYSTEM 7.9.1 Design Bases facility sanitary drain system (FSDS) collects domestic sanitary waste and wastewater, harging it to a city sewer main.
FSDS building sewer drain piping and system equipment outside the RCA are designed to applicable requirements of the Wisconsin Administrative Code, Safety and Professional vices, and the applicable City of Janesville Ordinances.
7.9.2 System Description FSDS removes domestic sanitary waste and wastewater from the areas of the main duction facility (not inside the RCA), the storage building, and the resource building; and harges sanitary waste and wastewater to the City of Janesville public sewer main.
FSDS building sewer removes sanitary waste via a gravity drainage system. The subsystem udes distribution piping, pipe fittings, isolation valves, backwater valves, vents, traps, nouts, manholes, and fixtures.
7.9.3 Operational Analysis and Safety Function piping in the FSDS building sewer is sloped per the Wisconsin Administrative Code to ure directed flow to the City of Janesville public sewer main. Building drains that are subject ackflow are protected with a backwater valve or sump and pumping equipment to comply applicable requirements of the Wisconsin Administrative Code.
elding and radiological protection is not required for the FSDS. Sanitary waste sources tain no SNM.
FSDS is nonsafety-related.
NE Medical Technologies 9b.7-16 Rev. 2
FSDS has no instrumentation or control equipment.
7.9.5 Technical Specifications re are no technical specification parameters associated with the FSDS.
7.10 FACILITY CHEMICAL REAGENT SYSTEM 7.10.1 Design Bases facility chemical reagent system (FCRS) provides storage and equipment for non-radioactive mical reagents used in the SHINE processes.
design basis of the FCRS includes:
- Provide intermediate storage for chemical reagents and bulk chemicals used to prepare chemical reagents.
- Provide for preparation of chemical reagents from bulk chemicals.
- Transfer reagents from their intermediate storage locations to process at tie-in locations.
- Deliver reagents into the SHINE process.
- Provide compressed oxygen to the TOGS.
7.10.2 System Description k chemical storage is provided in the storage building. Chemical storage is also provided in chemical storage and preparation room in the main production facility, which is located ide the RCA. Storage of compressed oxygen gas, used as a reagent, is provided by the RS. Compressed oxygen is supplied to the TOGS to facilitate the recombination of radiolytic rogen. Other chemical reagents are used for batch production, solution adjustment, and cess flushing.
mical reagents are placed into volume-limited FCRS containers for transfer to process tie-in tion tanks and into single-use laboratory scale containers (e.g., flasks, syringes, pipets) for ort into hot cells inside the RCA.
gents transported in portable containers are transferred into the tanks and pumped on and directly into the respective process tie-in locations for:
- TSPS uranyl sulfate solution preparation and adjustment;
- MEPS extraction, purification, and flushing;
- IXP system iodine extraction, purification, and flushing;
- RLWS system pH adjustment;
- RLWI system flushing;
- VTS flushing and adjustment of target solution in the TSSS;
- PVVS condensate pH adjustment and flush; and
- PSB flushing.
NE Medical Technologies 9b.7-17 Rev. 2
laboratory scale purification processes performed in the hot cells.
mpressed oxygen cylinders are stored inside the IF to service the TOGS. Compressed gen is routed through dry particulate filters, regulated, and distributed to the TOGS.
le 9b.7-6 identifies the systems which interface with the FCRS.
7.10.3 Operational Analysis and Safety Function k liquid and solid chemicals and chemical reagents are received, stored, maintained, and d in accordance with the chemical hygiene plan and are stored per their applicable safety a sheets.
FDWS provides demineralized water to both the storage building and the chemical storage preparation room for chemical reagent preparation. Individual acid, base, and organic waste tainers are provided for disposal of chemicals.
gents from FCRS process delivery tanks are pumped directly into the respective process tie-oints at controlled flow rates and temperatures in accordance with the process requirements.
ministrative and engineered controls, including accurate identification of reagents inside cess delivery tanks and containers, and color-coded and size specific connections, ensure reagents are not inadvertently supplied at incorrect process tie-in points. The FCRS process very tanks are volume limited, thereby setting maximum volume of reagents that can be plied to respective production-related processes.
ing of acids and bases could cause a highly exothermic reaction. As such, bulk quantities of s are stored separately from the bases and hydrogen peroxide in segregated storage spaces in the storage building. Small volumes of chemicals to be used in laboratory settings and in cesses are stored and labeled in accordance with their applicable safety data sheets.
le 13b.3-1 provides a list of chemicals within the SHINE facility.
storage and delivery of oxygen gas inside the RCA complies with fire hazard analysis (FHA),
escribed in Section 9a2.3, and applicable Occupational Safety and Health Administration HA) requirements.
RS operations are performed in accordance with the requirements of the radiation protection gram, described in Section 11.1.
FCRS contains no SNM; however, the addition of basic chemical reagents to interfacing tems may result in uranium precipitation. Therefore, chemical additions to process tanks are luated under the nuclear criticality safety program, as described in Section 6b.3.
7.10.4 Instrumentation and Control cess parameters for systems interfacing with the FCRS are monitored by the PICS, as cribed in Section 7.3.
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tain material in this subsection provides information that is used in the technical cifications.
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Table 9b.7 Radioactive Liquid Waste Immobilization System Interfaces Interfacing System Interface Description cess vessel vent system The immobilization feed tank cover gas and waste drum vent VVS) both discharge via a common header to the PVVS vent header.
dioactive liquid waste storage Immobilization feed tank receives radioactive liquid waste LWS) system from the RLWS system.
cuum transfer system (VTS) Suction from VTS provides the motive force for waste liquid transfer from the blending tanks to the immobilization feed tank.
diological ventilation zone 1 The RLWI shielded enclosure is ventilated by RVZ1.
VZ1) diological ventilation zone 2 The RVZ2 is the source of air supply to the shielded VZ2) enclosure through RVZ2 filtration equipment.
The RVZ2 is the source of air for the vacuum break between the VTS suction header and the drum fill head vacuum test tank.
cess integrated control The components of the RLWI system are controlled and tem (PICS) monitored by the PICS.
rmal electrical power supply The components of the RLWI system are powered by the tem (NPSS) NPSS.
cility chemical reagent system The FCRS pumps dilute sulfuric acid solution from a limited RS) capacity tank to support flushing of the immobilization feed tank, liquid waste drum fill pumps, and the RLWI system piping and valves.
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Table 9b.7 Radioactive Liquid Waste Storage System Interfaces (Sheet 1 of 2)
Interfacing System Interface Description rogen purge system (N2PS) The N2PS supplies sweep gas to the RLWS system tanks to remove potential accumulation of radiolytically generated hydrogen gas upon loss of normal power or loss of normal sweep gas flow.
cess vessel vent system The RLWS system provides a location to receive wastes from VVS) the PVVS condensate tanks. The PVVS provides zone 2 air as sweep gas to the RLWS system tanks to remove potential accumulation of radiolytically generated hydrogen gas.
lybdenum extraction and The RLWS system provides a location to receive wastes from ification system (MEPS) the MEPS. The MEPS provides flushing capabilities to the uranium liquid waste tanks and liquid waste collection tanks.
ine and xenon purification The RLWS system provides a location to receive wastes from d packaging (IXP) system the IXP system. Influents from the IXP system to the RLWS system are normally isolated unless actively processing solution through the IXP system.
dioactive drain system The RDS provides capacity to collect solution from the DS) uranium liquid waste tanks that results from off-normal overflow.
cility chemical reagent The FCRS supplies acid for pH adjustment in RLWS system tem (FCRS) tanks. This acid supply is through the supercell via a MEPS flow path.
cuum transfer system (VTS) The RLWS system provides a location to receive wastes from the VTS knockout pot. Suction from the VTS provides the motive force for waste liquid transfers within the RLWS system.
ality control and analytical The LABS maintain the capability to handle and measure ting laboratories (LABS) constituents in diluted samples obtained from the uranium liquid waste, liquid waste collection, and liquid waste blending tanks via remote sampler assemblies.
duction facility biological The PFBS provides a barrier to protect personnel, members of eld (PFBS) the public, and components and equipment by reducing radiation exposure from the RLWS system.
dioactive liquid waste The RLWS system transfers blended liquid waste to the RLWI mobilization (RLWI) system system for solidification. The RLWI system immobilization feed tank level instrumentation provides for metering of liquid waste transfers from the RLWS system blended liquid waste tanks.
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Interfacing System Interface Description cility nitrogen handling The FNHS provides instrument grade pressurized nitrogen to tem (FNHS) RLWS system tank level instrumentation and uranium liquid waste tank spargers.
cess integrated control The PICS receives and monitors control signals sent from tem (PICS) nonsafety-related RLWS system instrumentation, initiates actuation, and provides interlocks.
rmal electrical power supply The NPSS provides normal electrical power to the equipment tem (NPSS) and instrumentation in the RLWS.
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Table 9b.7 Solid Radioactive Waste Packaging System Interfaces (Sheet 1 of 2)
Interfacing System Interface Description ioactive liquid waste The SRWP system collects and provides for the packaging and obilization (RLWI) system shipment of potentially contaminated solid wastes generated by the RLWI system excluding the immobilized liquid waste and
[ ]PROP/ECI drums. Solid waste may include the high efficiency particulate air (HEPA) filters and failed equipment and components.
cess vessel vent system (PVVS) The SRWP system collects and provides for the packaging and shipment of PVVS solid wastes. Wastes may include spent HEPA filters, acid adsorbers, carbon guard beds, and failed equipment.
nium receipt and storage system The SRWP system collects and provides for the packaging and SS) shipment of potentially contaminated solid waste generated from the URSS. Wastes may include shipping package components, HEPA filters, glovebox gloves, materials and components used for uranium handling within the glovebox and spent cleaning materials used for decontaminating surfaces.
mary closed loop cooling system The SRWP system packages and ships spent PCLS deionizers LS) and spent PCLS cooling water filters for disposal.
ht water pool system (LWPS) The SRWP system packages and ships spent LWPS deionizers and spent LWPS filters for disposal.
get solution preparation system The SRWP collects and provides for packaging and shipment of PS) spent uranyl sulfate dissolution tank filters, TSPS glovebox air inlet and outlet HEPA filters, and uranyl sulfate dissolution tank demisters.
get solution vessel (TSV) off-gas The SRWP system collects and provides for the packaging and tem (TOGS) shipment of spent TOGS skid components. This includes the TOGS zeolite beds, recombiner beds, and demisters.
tron driver assembly system The SRWP system collects and provides for packaging and AS) shipment of portions of the NDAS.
iological ventilation zone 1 (RVZ1) The SRWP system collects and provides for packaging and radiological ventilation zone 2 shipment of solid waste generated by the radiologically controlled Z2) area ventilation systems. Waste may include HEPA filter and carbon filters.
duction facility biological shield The supercell includes features to package spent columns into BS) drums and transfer to the drum storage bore holes.
The supercell includes features to export column waste drums from the drum storage bore holes.
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Interfacing System Interface Description mal electrical power supply system NPSS supplies connections for portable electrically powered tools SS) at various locations through the radioisotope production facility (RPF) and material staging building to support potential requirements for disassembly and packaging of contaminated equipment as solid radioactive waste.
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Table 9b.7 Radioactive Drain System Interfaces Interfacing System Interface Description cess vessel vent system PVVS provides the RDS sump tanks with ventilation to mitigate VS) hydrogen accumulation in the tank headspace.
ogen purge system (N2PS) The N2PS provides a source of sweep gas to mitigate hydrogen accumulation in RDS sump tanks in the event of a failure of PVVS to provide the sweep gas.
ility nitrogen handling The FNHS provides compressed gas to the RDS sump tanks for tem (FNHS) solution agitation.
get solution staging system The RDS provides capacity to collect solution from the target solution SS) hold tanks and the target solution storage tanks that results from overflow of these tanks.
dioactive liquid waste The RDS provides capacity to collect solution from the uranium liquid rage (RLWS) system waste tanks that results from overflow of these tanks.
cuum transfer system (VTS) The VTS provides liquid transfer out of the RDS tanks.
gineered safety features ESFAS monitors tank level sensors and mitigates potential sources of uation system (ESFAS) leaks.
cess integrated control The RDS system provide measurement signals to the PICS of sump tem (PICS) tank levels as well as tank temperature.
rmal electrical power supply The RDS is powered by the NPSS.
tem (NPSS) nterruptible power supply The UPSS supplies electrical power to leak detection equipment that is tem (UPSS) part of the RDS in the event that normal electrical power is lost.
cess facility biological shield The PFBS provides shielding from sources of radiation in RDS to BS) ensure that accumulated doses in occupied areas do not exceed defined limits.
The RDS collects solution from drip pans located in the supercell, valve pits, tank vaults, and trenches that have the potential to contain liquid that requires favorable geometry.
ality control and analytical LABS measure properties of solution from the RDS.
ting laboratories (LABS)
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Table 9b.7 Facility Nitrogen Handling System Interfaces Interfacing System Interface Description ality control and testing The FNHS provides liquid nitrogen to dewars to supply the needs alytical laboratories of the instrument laboratory.
BS) cility fire detection and The FNHS provides nitrogen gas to pneumatic actuators for the ppression system (FFPS) pre-action fire system.
ine and xenon The FNHS provides a nitrogen gas supply line for product bottle ification and sparging. The FNHS portable dewars, containing liquid nitrogen, ckaging (IXP) system interface with the IXP cryotraps to cool system components.
lybdenum extraction and The FNHS provides nitrogen gas to sampling equipment ification system (MEPS) maintained by the MEPS.
mary closed loop cooling The FNHS maintains nitrogen gas supply to PCLS nitrogen tem (PCLS) operated valves in each of the cooling rooms.
dioactive drain system The FNHS provides nitrogen gas to sampling equipment DS) maintained by the RDS. The FNHS provides nitrogen gas to facilitate sparging and mixing operations in the RDS sump tanks.
The FNHS provides a nitrogen gas supply for liquid level detectors in the RDS sump tanks.
dioactive liquid waste The FNHS provides nitrogen gas to sampling equipment rage (RLWS) system maintained by the RLWS. The FNHS provides nitrogen gas to facilitate sparging and mixing operations in the uranium liquid waste tanks. The FNHS provides a nitrogen gas supply for liquid level detectors in the liquid waste blending tanks, uranium liquid waste tanks, and liquid waste collection tanks.
ium purification system The FNHS provides liquid nitrogen directly piped to the TPS. The S) FNHS provides nitrogen gas for the operation of pneumatic equipment.
rget solution vessel (TSV) The FNHS maintains nitrogen gas supply to each of the TOGS gas system (TOGS) skids through a penetration made in each cooling room.
rget solution preparation The FNHS provides nitrogen gas to sampling equipment tem (TSPS) maintained by the TSPS rget solution staging The FNHS provides nitrogen gas to sampling equipment tem (TSSS) maintained by the TSSS. The FNHS provides nitrogen gas to facilitate sparging and mixing operations in the target solution hold tanks and target solution storage tanks. The FNHS provides a nitrogen gas supply for liquid level detectors in the target solution hold tanks and target solution storage tanks.
NE Medical Technologies 9b.7-26 Rev. 2
Table 9b.7 Facility Chemical Reagent System Interfaces (Sheet 1 of 2)
Interfacing System Interface Description lybdenum extraction and The FCRS provides pumped MEPS extraction and purification ification system (MEPS) reagents.
ine and xenon The FCRS provides pumped IXP purification and recovery ification and reagents.
ckaging (IXP) system dioactive liquid waste The FCRS provides pumped chemical adjustment reagents via rage (RLWS) system VTS through MEPS for waste solution adjustment in the RLWS tanks dioactive liquid waste The FCRS provides pumped reagents for RLWI flushing and for mobilization (RLWI) acid makeup to liquid waste solidification drum on interruption of tem flow from immobilization feed tank.
rget solution staging The FCRS provides pumped chemical adjustment reagents via tem (TSSS) VTS pumped chemical adjustment and flush reagents for target solution composition adjustment in the TSSS tanks.
cess vessel vent system The FCRS provides acidification reagents to the PVVS for VVS) condensate adjustment as necessary and provides flushing reagents to the PVVS.
rget solution preparation The FCRS provides reagents to the TSPS for uranyl sulfate tem (TSPS) preparation and adjustments and provides reagents for flushing the TSPS.
cility ventilation zone 4 FVZ4 provides dedicated fume hood exhaust to the environment Z4) for the FCRS chemical preparation fume hoods.
cuum transfer system The FCRS provides process tie-in points to the VTS for the S) introduction of MEPS pumped extraction reagents. The FCRS provides process tie-in points to VTS for the introduction of pumped chemical adjustment and flush reagents for target solution composition adjustment in the TSSS tanks. The FCRS provides process tie-in points to VTS for the introduction of pumped chemical adjustment reagents through MEPS for waste solution adjustment in the RLWS tanks.
cility demineralized water Demineralized water from the FDWS is supplied to FCRS for tem (FDWS) process system flushing. The FDWS supplies the FCRS sinks with deionized water.
cility potable water The FPWS supplies water to the eye wash stations and chemical tem (FPWS) showers within the working areas of the chemical storage and preparation room and storage building where reagent preparation is performed.
NE Medical Technologies 9b.7-27 Rev. 2
Interfacing System Interface Description cility sanitary drain The FSDS provides drainage or catchments for emergency tem (FSDS) chemical showers, eye wash stations, and FCRS sinks.
rget solution vessel (TSV) The FCRS provides compressed oxygen to TOGS.
gas system (TOGS)
NE Medical Technologies 9b.7-28 Rev. 2
Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9b.7 RLWI System Process Flow Diagram SHINE Medical Technologies 9b.7-29 Rev. 2
Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9b.7 RLWS Uranium Liquid Waste Tanks Process Flow Diagram SHINE Medical Technologies 9b.7-30 Rev. 2
Proprietary Information - Withheld from public disclosure under 10 CFR 2.390(a)(4)
Export Controlled Information - Withheld from public disclosure under 10 CFR 2.390(a)(3)
Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9b.7 RLWS Liquid Waste Collection Tanks Process Flow Diagram SHINE Medical Technologies 9b.7-31 Rev. 2
Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9b.7 RLWS Liquid Waste Blending Tanks Process Flow Diagram SHINE Medical Technologies 9b.7-32 Rev. 1
Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9b.7 RDS Process Flow Diagram SHINE Medical Technologies 9b.7-33 Rev. 2
Chapter 9 - Auxiliary Systems Other Auxiliary Systems Figure 9b.7 FNHS Process Flow Diagram SHINE Medical Technologies 9b.7-34 Rev. 2
SI, 1993. Radioactive Materials - Special Lifting Devices for Shipping Containers Weighing 000 Pounds (4500 kg) or More, ANSI N14.6-1993, American National Standards Institute, 3.
SI/ANS, 1998. Guide for Nuclear Criticality Safety in the Storage of Fissile Materials, SI/ANS 8.7-1998 (R2007), American National Standards Institute/American Nuclear Society, 8.
ME, 2009. Code on Nuclear Air and Gas Treatment, AG-1-2009, American Society of chanical Engineers, 2009.
ME, 2010. Rules for Construction of Pressure Vessels, Boiler and Pressure Vessel Code, tion VIII, Division 1, American Society of Mechanical Engineers, 2010.
ME, 2011a. Overhead and Gantry Cranes (Top Running Bridge, Single or Multiple Girder, Running Trolley Hoist), B30.2-2011, American Society of Mechanical Engineers, 2011.
ME, 2011b. Building Services Piping, B31.9-2011, American Society of Mechanical ineers, 2011.
ME, 2013. Process Piping, B31.3-2012, American Society of Mechanical Engineers, 2013.
ME, 2015. Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, tiple Girder), NOG-1-2015, American Society of Mechanical Engineers, 2015.
ME, 2018. Slings, B30.9-2018, American Society of Mechanical Engineers, 2018.
AA, 2004. Specifications for Top Running Bridge & Gantry Type Multiple Girder Electric rhead Traveling Cranes, CMAA 70-2004, Crane Manufactures Association of America, Inc.,
4.
NRC, 1980. Control of Heavy Loads at Nuclear Power Plants, NUREG-0612, U.S. Nuclear ulatory Commission, July 1980.
NE Medical Technologies 9b.8-1 Rev. 1