ML21183A146

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Enclosure 2: Publicly Available Presentation
ML21183A146
Person / Time
Site: 07109394
Issue date: 06/28/2021
From:
Holtec
To:
Office of Nuclear Material Safety and Safeguards
PSaverot NMSS/DFM/STL 301.415.7505
Shared Package
ML21183A144 List:
References
EPID L-2021-NEW-0005
Download: ML21183A146 (15)


Text

www.holtecinternational.com HI-STAR 240 New Type B(U) Transportation Package Pre-Application Presentation to NRC June 28, 2021 Holtec Information for Public Release

l Page 2 - Holtec Non-Proprietary Information Presentation Agenda Introduction General Overview Design Overview Package Contents to be Authorized Acceptance Criteria and Overview of Safety Analysis Approach Structural Safety Overview Thermal Safety Overview Containment Safety Overview Shielding Safety Overview Summary and Proposed Licensing Schedule

l Page 3 - Holtec Non-Proprietary Information Introduction Holtec is preparing to submit a license application for the new HI-STAR 240 Transportation Package.

The HI-STAR 240 package design incorporates containment boundary and shielding design elements and concepts derived from the HI-STAR ATB 1T but with key enhancements.

HI-STAR 240 Package impact limiting component design concept is an enhanced version of the HI-STAR ATB 1T's.

Lesson Learned from HI-STAR ATB 1T have been incorporated as appropriate.

HI-STAR 240 is not a pressure vessel. HI-STAR 240 design pressure is less than 15 psig (100 kPa), the pressure specified by ASME Code for classification as a pressure vessel.

The Safety Analysis Report, SAR, on the HI-STAR 240 follows essentially the same basic format as Holtecs SAR on the HI-STAR ATB 1T.

l Page 4 - Holtec Non-Proprietary Information General Overview General Content Non-Fuel Waste (NFW) in the form of power reactor-related waste in a solid form (up to 10,000 lbs).

No secondary packaging is required to meet safety functions and any that is used is solely for operational convenience.

Dunnage is allowed (secondary packaging may serve as dunnage).

Principal Package Performance Low design heat load (1.75 kW), low pressures and temperatures.

Leakage Rate Acceptance Criteria based on Containment Analysis.

ALARA: Shielding materials, system operating procedures and quick-actuating cask closure lid locking system promotes ALARA.

Corrosion and Radiolysis Mitigation Designed to be submerged in pool for loading.

Moisture content is procedurally limited (same as ATB-1T)

l Page 5 - Holtec Non-Proprietary Information Design Overview - Shipping Configuration Empty Cask Weight: 80,000 lbs Package Gross Weight 90,000 lbs Exterior Dimensions: Approx. 6 x 6 x 11

l Page 6 - Holtec Non-Proprietary Information Design Overview - Cask and Lid Interior Dimensions: Approx. 36" x 36" x 95"

l Page 7 - Holtec Non-Proprietary Information Package Contents to be Authorized Non-Fuel Waste (NFW) Description Segmented power reactor related waste in solid form Additional Characterization Activated non-dispersible solids with surface contamination Surface contamination consists of fixed and non-fixed surface contamination

l Page 8 - Holtec Non-Proprietary Information Structural Safety Overview Acceptance Criteria General Criteria: Type B(U) Provisions of 10CFR71 Containment Integrity:

NCT: Level A stress intensity limits of ASME B&PV Code Division 1 Subsection NB (same as HI-STAR 180, 190, 180D and ATB 1T) for all normal condition loads.

HAC: Level D stress intensity limits of ASME B&PV Code Division 1 Subsection NB (same as HI-STAR 180, 190, 180D and ATB 1T) for all HAC events Closure Lid Seal Joint:

NCT and HAC: joint maintains required leaktightness as set in the Safety Analysis Report Shielding Components: Remain functional after impactive events Cask Crushable Attachments: Sufficient energy absorption to protect containment boundary and shielding components.

l Page 9 - Holtec Non-Proprietary Information Structural Safety Overview Safety Analysis Approach LS-DYNA All structural components modeled as true stress-strain materials based on ASME Code minimum properties 10CFR71.71 and 10CFR71.73 Dynamic Analysis 0.3-meter drop (governing orientations based on 9-meter drop causing the most damage) 9-meter drop (bottom down, top down, side drop on small surface, CG over corner (CGOC) bottom down, CGOC top down, CG over short edge (CGOE) bottom down, CGOE top down) 1-meter puncture on cask large surface wall.

Static Analysis Lifting, immersion, component stability, fire accident, fatigue, fracture etc.

addressed in SAR with separate supporting report.

l Page 10 - Holtec Non-Proprietary Information Structural Safety Overview Benchmarking Based on HI-STAR ATB 1T HI-STAR 240 has similarities to the HI-STAR ATB 1T package viz.

rectangular package, custom (unconventional) impact absorbers, mechanical closure along with use of elastomeric seals The HI-STAR ATB 1T physical testing and corresponding benchmarking in LS-DYNA provides, with a high-level of confidence, that the numerical analysis code LS-DYNA is capable of accurately predicting the dynamic response of the high energy impact events even in the absence of conventional impact limiters.

Material benchmarking effort, carried in support of HI-STAR ATB 1T, will also be relevant to HI-STAR 240 package.

l Page 11 - Holtec Non-Proprietary Information Thermal Safety Overview Acceptance Criteria General Criteria Type B(U) Provisions of 10CFR71 Package Effectiveness Package Component Temperature Limits as specified in the SAR.

Closure Lid Seal Joint Temperature of seal shall remain below the manufacturer's recommended temperature limits under all conditions of transport.

Impact Limiting Components Sufficient energy absorption to protect containment boundary and shielding components

l Page 12 - Holtec Non-Proprietary Information Thermal Safety Overview Safety Analysis Approach 3-Dimensional thermal models developed ANSYS-Fluent CFD Code Methodology consistent with that adopted in HI-STAR ATB-1T application Heat rejected from the cask under passive conditions (i.e. no wind) by natural convection and radiation.

Analyzed Conditions NCT - Cask in Horizontal Orientation Cask in Shade Fire Condition Evaluation

l Page 13 - Holtec Non-Proprietary Information Containment Safety Overview Acceptance Criteria 10CFR71 NCT and HAC Allowable Release Rates Safety Analysis Approach ANSI N14.5, American National Standard for Radioactive Materials Leakage Tests on Packages for Shipment, 2014 NCT: Analysis based on 60Co source term from releasable surface contamination 15% of surface contamination is considered releasable.

HAC: Non-fixed surface contamination is limited to an activity of less than or equal to 1A2 (based on 10.8 Ci, 60Co) thus assuring 10CFR71.51(a)(2) accident release limits are not exceeded.

100% of surface contamination is considered releasable.

l Page 14 - Holtec Non-Proprietary Information Shielding Safety Overview Acceptance Criteria Normal Conditions of Transport: 10 CFR 71.47 Hypothetical Accident Conditions: 10CFR 71.51 Safety Analysis Approach MCNP shielding calculations (dose rates)

l Page 15 - Holtec Non-Proprietary Information Summary and Licensing Schedule Design details, materials and safety analyses approaches are essentially identical to those for HI-STAR family of casks or based on proven practice and/or techniques which supports an efficient licensing process.

Planned Submittal July 2021.

Questions and Discussion