ML19203A169
| ML19203A169 | |
| Person / Time | |
|---|---|
| Site: | 07109385 |
| Issue date: | 07/19/2019 |
| From: | Industrial Nuclear Co |
| To: | William Allen Spent Fuel Licensing Branch |
| Allen W | |
| Shared Package | |
| ML19203A163 | List: |
| References | |
| EPID L-2019-LRM-0040 | |
| Download: ML19203A169 (27) | |
Text
Mobile Source Transit Security System PROJECT OVERVIEW
Office of Radiological Security (ORS)
PROTECT REMOVE REDUCE PROTECT radioactive sources used for vital medical, research, and commercial purposes REMOVE and dispose of disused radioactive sources REDUCE the global reliance on radioactive sources through replacement with viable non-isotopic alternative technologies MISSION: ORS enhances global security by preventing high activity radioactive materials from use in acts of terrorism.
The ORS Team can assist you with any of the above options.
Mobile Source Transit Security System OVERVIEW The ORS has developed a Mobile Source Transit Security (MSTS) system to enhance security of mobile radioactive devices used around the world for industrial radiography (IR) and well logging (WL).
Risk Solution
Mobile Source Transit Security System The ORS MSTS DIFFERENCE MSTS Solution
Enhanced security with ability for heightened awareness of device/source throughout usage cycle
Revised material prioritization level reduces total number of IR and WL sites
Average upgrade cost per site is significantly lower
MSTS and new strategy results in reduction in implementation timeline
One system designed for domestic and international deployment Non-MSTS
Traditional facility enhancements do not address devices outside of storage/facility Sources/Devices spend 75% of their
time outside of storage/facility
ORS Lifecycle plan assumed 840 domestic IR and WL sites in scope MSTS Development Process
MSTS SYSTEM DESIGN CONSIDERATIONS 3
Mobile Source Transit Security System INDUSTRIAL RADIOGRAPHY Persistent Monitoring Tag (PM-Tag)
Jacket w/integrated PM-Tag Secure Transport Box (STB)
Integrated Secure Container (ISC) w/Charging Mats
INDUSTRIAL RADIOGRAPHY - Operational Use Mobile Source Transit Security System
CAMERA: The PM-Tag has been integrated into the camera jacket to allow for real time monitoring of the device/source.
PM-Tag is equipped with wireless communication devices, radiation detector, tamper, and rechargeable batteries. In the case of an alarm event it will report to home base directly. The PM-Tag communicates with all the vault, truck, and homebase.
VAULT: The ISC has been developed to address home base facility storage needs. It is equipped with access control, tamper, networked and wireless communications.
TRUCK/VEHICLE: Truck enhancements focus on protecting the device/source when it is in transit or in the field.
Transit: The camera will be placed the STB while in transit or not in use. STB is equipped with on board charging station, tamper, radiation detection, and ability to send event information
In Use: The STB will monitor and communicate event information to home base while the device/source while in range. Once device is out of range the PM-Tag will communicate if there is an event.
The device autonomously maintains communication as it moves between all the various components. This automated handoff ensures that the device is with an authorized user and helps ensure system is always in correct state.
Software Applications July 26, 2019 8
The IR Dashboard is the software application that works with the IR-MSTS components Status and alerts being transmitted from the MSTS system are pulled from the cloud provider and displayed for user Data access is conducted via a monitoring software application on a computer Endpoint software designed by PNNL Mobile Source Transit Security System
Industrial Nuclear Company, Inc.
IR-100ST Package A Presentation to the US Nuclear Regulatory Commission July 9, 2019
> NRC Meeting, July 9, 2019 2
Agenda Introduction Description of IR-100ST Package Materials of Construction Payload Description Certification Test Plan Schedule Summary
> NRC Meeting, July 9, 2019 3
Description of IR-100ST Package Modified IR-100 Package (Docket 71-9157)
Welded stainless steel rectangular body remains unchanged Eliminated existing stainless steel handle assembly Thermoplastic sensor jacket installed around IR-100 body
Incorporates a PM-tag NITS assembly for tracking Two Types of Source Lock Assemblies Current keyed rectangular assembly Optional keyed updated assembly Lock assemblies welded to stainless steel body Estimated Gross Weight: 58 lb (26 kg)
> NRC Meeting, July 9, 2019 4
Description of IR-100ST Package (cont)
Existing IR-100 Package (Docket 71-9157)
> NRC Meeting, July 9, 2019 5
Description of IR-100ST Package (cont)
Depicted with Optional Lock Assembly
> NRC Meeting, July 9, 2019 6
Description of IR-100ST Package (cont)
Depicted with Optional Outlet Plug
> NRC Meeting, July 9, 2019 7
Description of IR-100ST Package (cont)
Close-up of Optional Lock Assembly Engineering Test, HAC Free Drop w/ IR-100
> NRC Meeting, July 9, 2019 8
IR-100ST Materials of Construction Structural:
Type 304 stainless steel sheet, bar Copper shims between DU & stainless steel contact points Body - All welded construction Gamma Shielding Cast depleted uranium (DU)
Polyurethane foam for DU shield moisture barrier Sensor Jacket Stainless steel sheet skeleton Urethane elastomer ejection molded jacket surround Four (4) lithium ion rechargable batteries in jacket base
> NRC Meeting, July 9, 2019 9
IR-100ST Contents No Change from IR-100 Package License Contents Iridium 192 (Ir-192) capsule Selenium 75 (Se-75) capsule Licensed as Special Form Content Limit: 120 Ci (4.44 TBq) total limit Decay Heat Limit: 0.84 watts (2.87 Btu/hr)
> NRC Meeting, July 9, 2019 10 IR-100ST Certification Test Plan Objectives To demonstrate that, after a worst-case sequence of free and puncture drops, no degradation in shielding capability of payload packages occurs To demonstrate retention of special form capsule within the gamma shield
> NRC Meeting, July 9, 2019 11 IR-100ST Certification Test Plan (cont)
Three (3) Full-scale, Prototypic CTUs Demonstration basis: radiation dose rates comply with 10 CFR 71 radiation limits after full series of free and puncture drops Use of actual radioactive source capsule Post-test readings versus pre-test readings Normal speed filming of free drops planned Tests Compression, Lifting, & Tie-Down Free Drops Puncture Drops
> NRC Meeting, July 9, 2019 12 IR-100ST Certification Test Plan (cont)
Structural Evaluations:
Compression, Lifting, and Tie-Down by test NCT free drop, and HAC free & puncture drops, by test One NCT free drop Total of four HAC free and two puncture drops Thermal Evaluation NCT thermal by analysis HAC thermal based on furnace test of IR-100 CTU Shielding Evaluation by test
> NRC Meeting, July 9, 2019 13 IR-100ST Certification Test Plan (cont)
Initial conditions For maximum impact free drop, temperature will be -20 °F For maximum deformation free drops, temperature will be NCT hot condition Orientations NCT 4-ft bottom orientation HAC 30-ft CG-over-Lock Assembly orientation HAC 30-ft CG-over-Lock Assembly lower edge orientation Puncture tests will be performed at ambient temperature Orientations attack free drop damage of Lock Assembly
> NRC Meeting, July 9, 2019 14 IR-100ST Certification Test Plan (cont)
Free Drop Tests Purpose CG-over-Lock Assembly NCT & HAC (hot & cold)
Impact to damage lock assembly, dislodge source capsule CG-over-Lock Assembly Lower Edge HAC (hot & cold)
Impact to damage lock assembly, dislodge source capsule
> NRC Meeting, July 9, 2019 15 IR-100ST Certification Test Plan (cont)
Puncture Drop Tests Purpose CG-over-Lock Assembly HAC (hot & cold)
Impact free drop damage, dislodge source capsule CG-over-Lock Assembly Lower Edge HAC (hot & cold)
Impact free drop damage, dislodge source capsule
> NRC Meeting, July 9, 2019 16 IR-100ST Certification Test Plan (cont)
Data collection Temperature of CTU body Normal speed film Measurements (pre-and post-test)
Crush distance, puncture damage Radiation Dose Rates Photographs
> NRC Meeting, July 9, 2019 17 IR-100ST Certification Test Plan (cont)
Acceptance Criteria Radiation dose rates comply with 10 CFR §71.51(a)(2):
No dislodgement of source capsule No loss of gamma shielding Discussion
> NRC Meeting, July 9, 2019 18 Schedule CTU fabrication completion - 4th Quarter 2019 Certification testing - 1st Quarter 2020 Submittal of application to NRC for Type B(U)-96 certification - 2nd Quarter 2020 Planning on approximately 5 months to first round RAIs
> NRC Meeting, July 9, 2019 19 IR-100ST Package Summary