ML24277A031
| ML24277A031 | |
| Person / Time | |
|---|---|
| Site: | 07109294 |
| Issue date: | 08/29/2024 |
| From: | Schichlein L Global Nuclear Fuel |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML24277A030 | List: |
| References | |
| EPID L-2023-LLA-0131, M240193 | |
| Download: ML24277A031 (1) | |
Text
Lisa K. Schichlein Global Nuclear Fuel - Americas, LLC Senior Licensing Engineer P.O. Box 780, M/C A70 Wilmington, NC 28401 USA T 910 819 4815 Lisa.Schichlein@ge.com M240193 August 29, 2024 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Submittal of Updated Final Presentation Slides for August 28, 2024 NPC Meeting Enclosed are the updated final presentation slides that Global Nuclear Fuel - Americas, LLC (GNF) presented during the New Powder Container (NPC) meeting with the NRC on August 28, 2024.
If you have any questions, please contact me at 910-819-4815.
Sincerely, Lisa K. Schichlein Senior Licensing Engineer, Regulatory Affairs Global Nuclear Fuel - Americas, LLC Docket No. 71-9294
Enclosure:
- 1. Updated Presentation Slides for New Powder Container Meeting - Non-Proprietary Information cc:
P Saverot, NRC MP Catts, GEH Wilmington PLM Specification 008N7858 Revision 1 Document Components:
001 M240193 Deliverable Package.pdf
ENCLOSURE 1 M240193 Updated Presentation Slides for New Powder Container Meeting Non-Proprietary Information
Non-Proprietary Information 1
August 28, 2024 NPC Certificate of Compliance Renewal Safety Analysis Report Revision to Introduce LEU+ Material Pre-Submittal Meeting Non-Proprietary Information
Non-Proprietary Information
- Overview of the New Powder Container (NPC) package
- Overview of NPC package analysis assumptions
- Overview of proposed changes to the NPC package criticality analysis assumptions
8 wt.% U-235
Limited moderator intrusion
Requirement to ship with poly bottles
Criticality analysis updated using KENO-VI 2
Agenda
Non-Proprietary Information Purpose of the Submittal A. Renew the NPC Certificate of Compliance (CoC) USA/9294/AF-96 B. Revise the criticality analysis as follows:
1.
Increase fissile material enrichment limitation to 8 wt.% U-235 2.
KENO-VI based analysis 3.
Credit certification test results for limited moderator intrusion 4.
Increase payload content of heterogeneous material C. Items not changing from approved CoC 1.
Criticality Safety Index (CSI) of 0.7 2.
Package or hardware 3.
Uranium material compounds 3
Non-Proprietary Information Overview of NPC Package 4
Non-Proprietary Information 4
Non-Proprietary Information General Information
- NRC approved for Type A fissile material up to 5 wt.% U-235
- Ceramic fiber and polyurethane insulation
- Nine SS Inner Containment Canister Assemblies (ICCAs)
- ICCAs sealed with rubber gasketed SS lid
- Each ICCA wrapped with 20-mil cadmium sheet and 15-mil high density polyethylene 5
Non-Proprietary Information END OF OPEN SESSION
Non-Proprietary Information START OF CLOSED SESSION
Non-Proprietary Information Objective Discuss changes to NPC SAR NEDE-33881P Increase enrichment to 8 wt.%
U-235 Include KENO-VI USL and benchmarking Credit certification testing to limit moderator intrusion Increase heterogeneous material payload 8
Non-Proprietary Information Changes to NPC SAR
- Redefine ICCA flooding during Hypothetical Accident Condition (HAC) based on physical test data documented in Chapters 2 & 3 of the NPC SAR per 10 CFR 71.55 and 71.59
- Require the use of poly bottles within ICCAs
- Include KENO-VI based criticality analysis and Upper Subcritical Limit (USL) of 0.9424 9
Non-Proprietary Information NPC Certification Testing Review 10 Non-Proprietary Information
Non-Proprietary Information Certification Tests
- Four full-scale NPC Certification Test Units CTU-1 thru CTU-4 tested as follows:
Free drop per 10 CFR 71.73(c)(1)
Puncture test per 10 CFR 71.73(c)(3)
Thermal testing per 10 CFR 71.73(c)(4); (except CTU-4)
Immersion testing per 10 CFR 71.73(c)(5) and (c)(6); (except CTU-4)
- Demonstrated compliance to 10 CFR 71
- Demonstrated watertight through immersion testing Documented in SAR but not previously required due to assumed in-leakage for criticality evaluation Certification Tests Summary 11 Testing and Results
Non-Proprietary Information Immersion Testing 10 CFR 71.73(c)(5)
- CTU-2 had no evidence of in-leakage following 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of 3 ft immersion testing
- CTU-3 and CTU-1 had evidence of limited moderator intrusion in one ICCA each Cause of in-leakage was identified and is mitigated through current package design and operation 10 CFR 71.73(c)(6)
- Nine undamaged ICCAs were immersed at 50 ft for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with no evidence of in-leakage 12
Non-Proprietary Information Immersion Testing Continued CTU-2: No evidence of water intrusion.
CTU-3: Deformation of OCA lid corner and ICCA closure lid due to drop testing. Evidence of limited water intrusion.
Mitigation: Reinforced the corner soffits and tested as CTU-1 (current design).
CTU-1: Evidence of limited water intrusion due to simulated payload (sand particles) migrating into ICCA closure seal during drop testing.
Mitigation: Resolved by procedural handling in Chapter 7. Poly bottles are required for powder uranium compounds.
CTU-4: No immersion testing performed. No leaked fluorescein identified.
13
Non-Proprietary Information Testing Summary
- Damaged package remains watertight following free drop, puncture and fire testing demonstrated by 10 CFR 71.73(c)(5) immersion testing
- Undamaged ICCAs remain watertight demonstrated by 10 CFR 71.73(c)(6) immersion testing
- 10 CFR 71.73(c)(5) and (c)(6) immersion testing data will be used to justify modifications to in-leakage assumptions in the criticality analysis 14
Non-Proprietary Information Criticality Study 15 Non-Proprietary Information
Non-Proprietary Information Conservative Assumption With the results of testing noted, it is credible that no ICCAs will flood during HAC For conservatism, up to two ICCAs in each NPC are assumed to leak (allow moderator intrusion with no material loss)
How many ICCAs can flood before USL is reached?
Results for damaged 2N array indicate two flooded ICCAs is near USL 16 NPC package with two flooded ICCAs Flooded Fuel ICCA Dry Fuel ICCA
Non-Proprietary Information NPC System Reactivity Assumptions
- Objective: Model limiting configuration of up two (2) flooded ICCAs Up to two (2) ICCAs are considered entirely flooded with full density H2O Three (3) poly bottles are modeled within each ICCA Spherical fuel treatment (fuel spheres, dodecahedral array of elements)
Determined bounding uranium load mass per ICCA (~ 60 kg UO2) 17 Cross section of ICCA with Dodecahedron Model Construct
Non-Proprietary Information 18 Isometric View Top Cross-Section Side Cross-Section Results - Example Visualization (Damaged Single Unit)
Non-flooded fuel region Flooded fuel region Poly bottle material
Non-Proprietary Information NPC Package Orientation Study 19 Non-Proprietary Information
Non-Proprietary Information 20 Results - NPC Package Orientation Study 2x2x2 Array Objective: To identify the most reactive configuration of two ICCAs flooded within the NPC package
- Most reactive configuration will be used as the base orientation pattern for the 5x6x5 (2N) array
- Limiting orientation identified:
Non-Proprietary Information Results - Limiting Orientation 5x6x5 (2N) Array
- Objective: Apply the limiting 2x2x2 array orientation to the 5x6x5 array
- Ensure the final column (outside of 2x2x2 pattern) is most reactive through iterative testing of orientation
- Exterior flooded ICCA orientations were found to be most reactive in the 2x2x2 array (central ICCA left dry)
- Most reactive orientation identified:
21
Non-Proprietary Information 22 Results - Limiting Orientations (Most Reactive Orientation of Damaged 2N Array)
Dodecahedral/Spherical Fuel Treatment NCT Array HAC Array
Non-Proprietary Information 23
Non-Proprietary Information 24 Summary of Analyses Credit results of certification testing documented in SAR
Conservatively model up to 2 ICCAs flooded Increase allowed UO2 enrichment from 5 wt.% to 8 wt.% U-235 Require poly bottles within ICCAs The model demonstrates that 60 kg heterogeneous net weight UO2 per ICCA remains below USL of 0.9424, independent of particle size This modeled safety demonstration is conservative since poly bottles have a known tare weight (each ICCA is restricted to 60 kg net, including inner packaging)
Heterogenous fuel model bounds homogeneous fuel model
Non-Proprietary Information 25 Summary of Changes to the NPC SAR NEDE-33881P Chapter 1
Administrative drawing revisions including incorporation of NUREG/CR-6407 safety category and creation of official poly bottle drawing to replace existing sketch Chapter 3
Revised calculation demonstrating negligible decay heat at 8 wt.% U-235 Chapter 6
General descriptions of 5 wt.% U-235 to 8 wt.% U-235
All plots redone using KENO-VI instead of GEMER
Inclusion of poly bottles
Adjustment of fuel loading masses to account for mass of poly bottles in ICCAs (Table 6.1, Table 6.2)
Re-evaluation of all packaging criticality assumptions for new moderator intrusion assumption
Material thicknesses, Material densities Chapter 7
All shipments shall be secured within a poly bottle
Non-Proprietary Information 26 NPC Certificate of Compliance Markups
Non-Proprietary Information 27 NPC Certificate of Compliance Markups
Non-Proprietary Information 28 Target Dates
- NPC SAR revision submission targeted for October 2024
- Business need date for review and approval of NPC SAR Revision 8 is October 2025