ML20055C591
| ML20055C591 | |
| Person / Time | |
|---|---|
| Site: | 07109230 |
| Issue date: | 03/22/1990 |
| From: | FRAMATOME COGEMA FUELS (FORMERLY B&W FUEL CO.) |
| To: | |
| References | |
| NUDOCS 9005250167 | |
| Download: ML20055C591 (60) | |
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B&W Fuel Company Presentation to the NRC - Transportation Branch March 22,1990 NRC Docket 71-9230 0
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NRC Docket 71-9230 4_
t B&W Fuel Company Presentation to the l
NRC - Transportation Branch March 22,1990 L
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BR-100 Rail / Barge Transportation Cask 1
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NRC MEETING AGENDA l
' INTRODUCTION P. C. CHILDRESS a
CASK DESIGN REVISIONS:
D.B. YOUNG BASKET OUTER SHELL
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CASK EVALUATION. STRATEGY:
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STRUCTURAL ANALYSIS E. J. MCGUINN
. THERMAL EVALUATION E. J. MCGUINN CRITICALITY ANALYSIS L A. HASSLER O
L ENGINEERING TEST PROGRAM:
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THERMAL SHIELD TEST E. J. MCGUINN/
K. E. KNEIDEL
-IMPACT. LIMITER DESIGN STATUS E. J. MCGUINN r
~ CERTIFICATION:
E. J. MCGUINN l'
VERIFICATION TEST PLAN HUMAN FACTORS P. C. CHILDRESS
,h WRAP-UP AND QUESTIONS P. C. CHILDRESS
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B&W Fuel Company Team t
L Paul Childress Project Manager r
Ed McGuinn Licensing Engineer r
. O DaniYoung Project Engineer L
Larry Hassler Criticality Engineer.
Kurt 'Kneidel Test Engineer y
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i mr Objectives e Present revised BR-100 design e Present analytical evaluation strategies 9
e Present thermal shield test e Present initial drop / puncture test plans B&WFUEL rg commnr 1
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Purpose l
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SAR Preparation 4/91-10/91 Verification Test 7/91
- O SAR Submittal 11/91 Licensing 11/91-5/93 L
Prototype Fabrication 10/92 - 3/95 Acceptance Testing 3/95-7/95 O
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Presentation O
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i Babcock & Wilcox BR-100
_pJ n Rail Barge Cask-Removable Fuel Basket Stainless Steel Inner Shell Cavities for 21 PWR or 52 BWR Fuel Assemblies Gamma Shield (Lead)
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1 Removable Skid Suitable for Rail or Barge Shipment i
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"Holddown Bracket. (Not Shown for Clarity) i impact Limiter Shear Pad-orpaarutur or curacy Patented by ROBATEL SA CONWACT NO DF.AC07-8tDl?701 b
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- Cask Body S.S. Containment Boundary
- Multilayer Construction
- Lead Gamma-Shield
- Borated Concrete Thermal / Neutron Shield
- Cha~nge Outer Shell Material
- Bolted Closure tid O
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- Impact Limiter.
- Balsa / Redwood l
- Kevlar/ Epoxy 1
- Basket Design l
- 21 PWR/52 BWR
- Unitized 1 Lifted in One Piece)
- Design / Materials Have. Changed o
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U Inner Shell Assembly 304L 88 Closure ud XM-18 88 Closure Bolts Alloy 718 Seals-Viton Gamma Shield Lead-Neutron Shield Borsted Concrete / Copper Fins Cook Boey'
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Bottom Head-304L 88 Forging 3
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Trunnien-XM-19 88. Forging Blank.
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- PWR Burnup Credit (28. GWd/mtu)
- Cask Body
- Change Outer Shell MaterLal SS 304 -+ XM-19 SS J
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O BR-100 Rationale for Changes
- Reduce Design / Fabrication Complexity (i.e., Lower Cost) e Fewer Development Needs
- Boral Is Developed. and Available
- Cermet Has Potential-A Size Limitations Flexibility Limitations A
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BR-100 Impacts on Design i
- Eliminato Pool Water Contact With Copper /Boral-
- Eliminate Flux Traps
- Simplifies Decontamination
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Improve Structural Margins in Basket O
Reduce Overall Weight of the PWR Configuration Still Anticipate. Transporting 98x of Fuel l
Population at Full Capacity Remaining 2x at Reduced Capacity F'
B&WFUEL COMPANY
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Cask Outer Shell Changed Material to XM-19 SS i
- Improve Structural Response to Puncture Accident:and Trunnion Loads sO SS 304L XM-19 $S y
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Design Improvements impact on BR-100
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- Simpilfled Decontamination L
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Structural Analysis Strategy e Preliminary Design Based on Proven Analytical Methods Conservative Empirical Equations ASME/ ASTM Material Properties O
Based on Previous Cask Designs L
Analysis Code: ANSYS e Final Design i
Refined Analysis to Remove Excess Conservatism Analysis Code: ABAQUS ANSYS O
BSWFUEL COMNNY
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O BR-100 CASK Thermal Evaluation Strategy 1
I Presentation 0
to NRC Transportation Branch March 22,1990 i
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O Thermal Design Limits o Personnel barrier. temperature limit of 180 F
o Concrete temperature limit of 250 F
o Aluminum temperature limit of 350 F
o Cladding temperature limit of 680 F
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BR-100 Thermal Enhancements in the Design i
e White epoxy paint exterior coating I
e Robatel concrete copper fin thermal / neutron i
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e Copper plates to enhance heat transfer in the basket e Aluminum Formers with anodized surfaces e Helium cask fill gas O
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Cask Wall Heat Transfer i.
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(one-dimensional conduction) e Inner cask wall-to basket gap (thermal radiation and gaseous conduction) l 1
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230.9 BR-100 Cask Multi-Layer Wall Normal Operation Temperature Gradient 229.6 228.2 22&8 Stainless Steel 225.s T
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218.6 Concrete 217.3 4
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Basket Heat Transfer e Two dimensional model developed using PATRAN O. Thermal analysis performed using P/ THERMAL
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272.8 TEMPERATURE SCALE IN 267 3 DEGREES F 261. 8 256,3 l
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performance of cask waii for a licensing fire O
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O BR-100 CASK 4
Criticality Analysis Presentation O
to NRC Transportation Branch March 22,1990 e
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- 123 Group XSDRN Cross Section Set
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- NITAWL Resonance Treatment j
- XSDRNPM Spatial Self-shielding (Homogenization)
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- KENO-IV Monte Carlo Code (2% Blas)
- ORIGEN2 for Burnup Isotoples
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PWR:
- 17x17 Westinghouse OFA j
- 4.5 Weight Percent U-235
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- BU lsotopics from ORIGEN2
- no gessous fission products, eg. Xe-131,Kr-83
- 18 fission-product isotopes included l
- End: effects approximated by lower everage BU 4
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BWR:
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- 4.5 Weight Percent U-235
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- No zone loading
- No bumable poisons i
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i Cask Geometry
- Explicit Basket Region Radially
- Explicit. Cask Body Radially
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- 60/45 mg/cm' B-10 PWR Fuel Cell
- 40/30 mg/cm' B-10 BWR Fuel Cell
- Water Moderated, 50*F i
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O CRITICALITY RESULTS Km = K, + Keno Blas + Uncertainty Basket Conditions K..i, PWR Normal Transportation
-Air filled, fresh fuel 0.36
-Air filled, 24 GWD/MTU BU 0.30 Accident
-Flooded, 24 GWD/MTU BU 0.949
-Flooded, 35 GWD/MTU BU 0.829 BWR Flooded, fresh fuel 0.933 0
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NRC Transportation Branch March 22,1990 o
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L BR-100 CASK Testing Program e Engineering Tests Purpose Provide Cask Design Support Results - Materials Property Data 0
- Component Behavior Data 1
e Verification Tests Purpose Confirm Cask Accident L
Performance Results - Cask Mechanical Response to Hypothetical Accidents O
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e External Paint Emissivity Decontamination E 4 i
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Cask Wall Testing (Thermal / Neutron Shield) e Pre-fire steady state thermal conductivity determination O e Exposure to 1475 F fire for 30 minutes (10CFR71) e Controlled cooldown e Post cooldown steady state thermal conductivity determination
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Impact Limiter Design Status Presentation O
to NRC Transportation Branch March 22,1990
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i BR-100 CASK a.
D Certification l
Presentation i
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NRC Transportation Branch j
a March 22,1990 1
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BR-100 CASK O
Verification Test Strategy e Programmaticissues
' Develop Test Plan Approved by DOE Review with NRC Select Test Site g
Develop Testing Procedures Conduct Tests e Model Fabrication Quarter Scale Model Cask Body Fabricated by ROBATEL in France Other Cask Components Fabricated by BWFC EMMu9 e
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O BR-100 CASK 4
Verification Testing Strategy e Free Drop Test Nine Meter Drop to Flat, Unyielding Surface O
Top / Bottom Side Oblique e Puncture. Test One Meter Drop Onto Six-inch Diameter Steel Bar Side Top / Bottom
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L BR-100 Cask Verification Testing Milestones L
Schedule Start Model Design May 90 Release Model Design for Fabrication Oct 90 Complete Model Fabrication May 91 Start Verification Testing July 91 Final Test Report Aug 91 SARP Submitted Nov 91 8
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O Summary e Certification Plan in place O
e Resolve Certification issues e VerificationTesting e Timely NRC Review BBWFUEL COMPANY
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'O BR-100 CASK Human Factors Engineering Presentation O
to NRC Transportation Branch March 22,1990 O
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BR-100 Cask Human Factors Engineering e Design with a human factor approach Experienced personnel on the design.
L team ALARA O' e Periodic review of the design l
e Reliability studies Failure Modes and Effects Analysis (FMEA) e Independent final design review
.* Training Prototype casks L
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