ML23115A191
| ML23115A191 | |
| Person / Time | |
|---|---|
| Site: | 07109385 |
| Issue date: | 04/27/2023 |
| From: | Industrial Nuclear Co |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| Download: ML23115A191 (1) | |
Text
Industrial Nuclear Company, Inc.
IR-100ST Package A Presentation to the US Nuclear Regulatory Commission Docket 71-9385 April 27, 2023
Agenda Introduction Description of IR-100ST Package Materials of Construction Payload Description Certification Test Plan Schedule Summary 2 > NRC Meeting, April 27, 2023
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 New Source Lock & Outlet Port Assembly Designs Keyed updated assemblies Assemblies welded to stainless steel body Estimated Maximum Gross Weight: 60 lbm (27 kg) 3 > NRC Meeting, April 27, 2023
Description of IR-100ST Package (cont)
Existing IR-100 Package (Docket 71-9157) 4 > NRC Meeting, April 27, 2023
Description of IR-100ST Package (cont)
Depicted with New Lock Assembly 5 > NRC Meeting, April 27, 2023
Description of IR-100ST Package (cont)
Depicted with New Outlet Plug 6 > NRC Meeting, April 27, 2023
Description of IR-100ST Package (cont)
Close-up of New Lock Assembly Engineering Test, HAC Free Drop w/ IR-100 7 > NRC Meeting, April 27, 2023
Description of IR-100ST Package (cont)
Close-up of New Outlet Plug Assembly 8 > NRC Meeting, April 27, 2023
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 rechargeable batteries in jacket base Secured to body by (8) Ø3/16 stainless steel pop rivets 9 > NRC Meeting, April 27, 2023
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) 10 > NRC Meeting, April 27, 2023
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 11 > NRC Meeting, April 27, 2023
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 12 > NRC Meeting, April 27, 2023
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 13 > NRC Meeting, April 27, 2023
IR-100ST Certification Test Plan (cont)
Initial conditions For maximum impact free drop, temperature will be NCT cold condition, -20 °F For maximum deformation free drops, temperature will be NCT hot condition Orientations NCT & 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 14 > NRC Meeting, April 27, 2023
IR-100ST Certification Test Plan (cont)
Free Drop Tests Purpose CG-over-Lock Impact to damage lock Assembly assembly, dislodge NCT & HAC source capsule (hot & cold)
CG-over-Lock Impact to damage lock Assembly Lower assembly, dislodge Edge source capsule HAC (hot & cold) 15 > NRC Meeting, April 27, 2023
IR-100ST Certification Test Plan (cont)
Puncture Drop Tests Purpose CG-over-Lock Impact free drop Assembly damage, dislodge HAC source capsule CG-over-Lock Impact free drop Assembly Lower damage, dislodge Edge source capsule HAC 16 > NRC Meeting, April 27, 2023
IR-100ST Certification Test Plan (cont)
Data collection Temperature of CTU stainless steel body Normal speed film Measurements (pre- and post-test)
Crush distance, puncture damage Radiation Dose Rates Photographs 17 > NRC Meeting, April 27, 2023
IR-100ST Certification Test Plan (cont)
Acceptance Criteria Radiation dose rates comply with 10 CFR §71.47(a) [NCT]
and 10 CFR §71.51(a)(2) [HAC]
No dislodgement of source capsule No loss of gamma shielding Discussion 18 > NRC Meeting, April 27, 2023
Schedule CTU fabrication completion - 2nd Quarter 2023 Certification testing - Early 3rd Quarter 2023 Submittal of application to NRC for Type B(U)-96 certification - Late 3rd Quarter 2023 Planning on approximately 3-5 months for RAIs 19 > NRC Meeting, April 27, 2023
IR-100ST Package Summary 20 > NRC Meeting, April 27, 2023