ML15075A346
| ML15075A346 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/10/2015 |
| From: | AREVA |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML15075A350 | List: |
| References | |
| NUH32PHB-0203, Rev. 2 | |
| Download: ML15075A346 (24) | |
Text
ENCLOSURE 13Non-Proprietary NUH32PHB-0203, Revision 2,PWR Fuel Rod Accident Side Drop Loading Stress Analysis forNUHOMS 32 PHB SystemCalvert Cliffs Nuclear Power PlantMarch 10, 2015 Controlled Copy E-281A Form 3.2-1 CalculaflonNo.:
I NUH32PHB-0203 AR EVA Calculation Cover Sheet Revision No.. 2TRANSUCLEAR INC. TP 3.2 (Revision
- 6) Page I of 23DCR NO (ifapplicable)
- NUH32PHB-013 PROJECt NAME: NUHOMS 32PHB SystemPROJECT NO: 10955 CLIENT: CENG -Calvert Cliff Nuclear Power Plant (CCNPP)CALCULATION TITLE:PWR Fuel Rod Accident Side Drop Loading Stress Analysis for NUHOMS 32PHB SystemSUMMARY DESCRIPTION:
- 1) Calculation SummaryThe purpose of this calculation is to verify the structural adequacy of the fuel cladding subject to side drophypothetical accident loading condition for PWR fuel assemblies to be loaded in the NUH32PHB transfer cask. Inaddition, structural integrity of spacer grids is discussed to assess grid deformation impact onto fuel rod pitch aswell as modal analysis for fuel cladding Is conducted to determine lateral natural frequencies.
- 2) Storage Media Description Secure network server Initially, then redundant tape backup. (Same as Rev.0)IIIIf original Issue, Is licensing review per TIP 3.5 required?
N/AYes [l No [I (explaln below) Licensing Review No.:Software Utilized (subject to test requirements of TIP 3.3): Version:ANSYS lO.OA1Calculation is complete:
10- 22-13Originator Name and Signature:
Ashley SpryDate:Calculation has been checked for consistency, completeness and correctness:
Raheel HaroonChecker Name and Signature:
Date:Calculation is approved for use:Project Engineer Name and Signature:
/Date:II A Calc. No.: NUH32PHB-0203 AREVA CalcUlation Rev. No.: 2TRANSNUCLEAR INC. Page: 2of23REVISION SUMMARYAffected AffectedRev. Description of Changes Pages Computational 11o0 Initial Issue All All1 Add discussion about M-5 material for AREVA fuel assembly so that all 1,2,5-8,11,15 Nonethe fuel assemblies for NUJH32PHB are taken into account.2 Change oxidation thickness from 120 microns to 125 microns.
Stresses 5,6,8,9,11, 12 None,are updated accordingly, A Caic. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 2TRANSNUCLEAR INC. Page: 3of23TABLE OF CONTENTS1.0 Purpose .....................................................................................................................................................
52.0 References
.................................................................................................................................................
53.0 M ethodology
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64.0 Assumptions
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! .................................................................................................................................
65.0 Design Criteria
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76.0 Computation
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76.1 Finite Element M odel ............................................................................................................................
76.2 M aterial Properties
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76.3 Selection of Bounding Case ....... ......................................................
86.4 Calculation for Bending Stress ...............................................................................................................
86.5 Loading ............................................
! ..............................
L ........................................................
, ........
97.0 Results ......................................................................................................................................................
98.0 Conclusion
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99.0 Listing of ANSYS Computer Files ............................................................................................................
1IAppendix A: -M odal Analysis
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Appendix B: -Fuel Assembly Spacer Grid Integrity
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22 A Caic. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 2TRANSNUCLEAR INC. Page: 4,of23List of TablesTable 1 Analyzed Fuel Rod Characteristics
...................................................................................................
11Table 2 Finite E lem ent M odel ..............................................................................................................................
12Table 3 Summary of Stress Results for Accident Condition 75g Side Drop ...........................................................
12Table 4 Fuel Cladding Natural Frequencies
...................................................................................................
16List of FiguresFigure 1 PW R Fuel Cladding G eom etry ..............
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13Figure 2 Finite Elem ent M odel Setup ..................................................................................
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13Figure 3 Typical PWR Fuel Assembly Grid and Constraints
.............................................................................
14Figure 4 Bounding Fuel Assembly Bending Stress Under 75g Load ..................................................................
15Figure 5 Natural Frequency
-1i Mode ...........................................................................
1..Figure 6 N atural Frequency
-2nd M ode ...........................................................
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1Figure 7 Natural Frequency
-3rd Mode .........................................................................
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1Figure 8- N atural Frequency
-4th M ode ................................................................................................................
2.Figure 9- N atural Frequency
-5 MM ode ...............................................................................................................
21Figure 10 Schematic Diagram of Spacer Grid Response (Ref [2.15], Figure nI-1i5) .............................
23 A I Calc. No.: NUH32PHB-0203 AR-EVA CalcUlation Rev. No.: 2TRANSNUCLEAR INC. Page: 5_of231.0 PurposeThe purpose of this calculation is to verify the structural adequacy of the fuel assemblies to be loaded in theNUH32PHB transfer cask. Side drop analysis is performed for hypothetical accident
'load conditions.
In addition, structural integrity of spacer grids is discussed to assess grid deformation impact onto fuel rod pitch. Modalanalysis for fuel cladding is also conducted to determine lateral natural frequencies.
2.0 References
2.1 NUH32PHB.0101, Rev. 2, "Design Criteria Document (DCD) for the NUHOMS 32PHB System forStorage".
2.2 TN Calculation No. 972-179, Rev. 0, "TN-68 High BurnUp Cladding Mechanical Properties".
2.3 ANSYS Computer Code and User's Manuals, Release 10.0.2.4 DOE/RW-0184, Volume 3 of 6, December 1987, "Characteristics of Spent Fuel,. .High Level Waste, andOther Radiological Wastes which May Require Long-Term Isolation",
USDOE, Office of CivilianRadioactive Waste Management.
2.5 TN Calculation NUH32PHB-0403, Rev. 0, "Thermal Evaluation of NU1HOMS 32PHB DSC for Storage andTransfer Conditions".
2.6 H.E. Adkins, Jr., B.J. Koeppel and T. Tang, "Spent Nuclear Fuel Structural Response when Subjected to anEnd Impact Accident",
- PVP2004, San Diego, CA, July 25-29, 2004.2.7 TN Calculation NUH32P+--0204, Rev 1, "Fuel 'End Drop Analysis for NUH32P+ Using LS-DYNA".
2.8 Raymond J, Roark and Wafren C. Young, "Formulas For Stress and Strain",
5u' edition, McDraw-.HiU BookCompany,2.9 Calvert Cliffs Calculation
- CA06525, Rev. 0, "Calvert Cliffs Unit 2 Cycle 16 Bounding Fuel Performance Analysis for ZrB2 Implementation at 2746 MWt Core Power".2.10 UCID -21246, "Dynamic Impact. Effects on Spent Fuel Assemblies",
Lawrence Livermore NationalLaboratory, October 20, 1987,2.11 NUREG/CR-0200, Vol. 3, Rev. 5 (Table M8.2,4),
ORNL/NUREG/CSD-2/V3/R6, "SCALE, A Mod.ular Code.System for Performing Standardized Computer Analysis for Licensing Evaluation for Workstations andPersonal Computers",
Oak Ridge National Laboratory, RSIC Computer Code Collection.
2.12 Not used.2.13 Not used.2.14 Chun, R., M. Witte, M. Schwarz, "Dynamic Impact Effects on Spent Fuel Assemblies",
- October, 1987, pp.3.2.15 Report SAND90-2406, "A Method for Determining the Spent-Fuel Contribution
'to Transport CaskContainment Requirements'",
Sandia National Laboratories,.
November 1992.2.16 TN Calculation No. NUHPHB-0205, Rev. 1, "NUHOMS 32PHB Basket Evaluation for Storage andTransfer Loads".2.17 TN Calculation No. NUH-HBU-0249, Rev: 0, "M5 Cladding Mechanical Properties".
A Calc. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 2TRANSNUCLEAR INC. Page: 6of23Proprietary I
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8.0 Conclusion
The maximum stress under Accident drop conditions among all PWR fuels to be transported, in the NUH32PHB Caskis 45.4 ksi for Zircaloy-4 and 48.0 ksi for M-5, respectively.
Those stresses significantly lower than the yield stress ofZircaloy-4 (92 ksi) and M-5 (67.3 ksi) at 750 TF. It is, therefore, concluded that the fuel claddings will not fail underaccident side drop load condition.
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