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 13 Non-Proprietary NUH32PHB-0203, Revision 2, PWR Fuel Rod Accident Side Drop Loading Stress Analysis for NUHOMS 32 PHB System Calvert Cliffs Nuclear Power Plant March 10, 2015
Controlled Copy E-281 A Form 3.2-1 CalculaflonNo.: I NUH32PHB-0203 AR EVA Calculation Cover Sheet Revision No.. 2 I TRANSUCLEAR INC. TP 3.2 (Revision 6) Page I of 23 I
DCR NO (ifapplicable) : NUH32PHB-013 PROJECt NAME: NUHOMS32PHB System PROJECT NO: 10955 CLIENT: CENG - Calvert Cliff Nuclear Power Plant (CCNPP)
CALCULATION TITLE:
PWR Fuel Rod Accident Side Drop Loading Stress Analysis for NUHOMS 32PHB System
SUMMARY
DESCRIPTION:
- 1) Calculation Summary The purpose of this calculation is to verify the structural adequacy of the fuel cladding subject to side drop hypothetical accident loading condition for PWR fuel assemblies to be loaded in the NUH32PHB transfer cask. In addition, structural integrity of spacer grids is discussed to assess grid deformation impact onto fuel rod pitch as well 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)
If original Issue, Is licensing review per TIP 3.5 required? N/A Yes [l No [I (explaln below) Licensing Review No.:
Software Utilized (subject to test requirements of TIP 3.3): Version:
ANSYS lO.OA1 Calculation is complete:
10- 22-13 Originator Name and Signature: Ashley Spry Calculation has been checked for consistency, completeness and correctness:
Date: I Raheel Haroon Checker Name and Signature: Date:
Calculation is approved for use:
Project Engineer Name and Signature: /Date: I
A Calc. No.: NUH32PHB-0203 AREVA CalcUlation Rev. No.: 2 TRANSNUCLEAR INC. Page: 2of23 REVISION
SUMMARY
Affected Affected Rev. Description of Changes Pages Computational 11o 0 Initial Issue All All 1 Add discussion about M-5 material for AREVA fuel assembly so that all 1,2,5-8,11,15 None the 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,
Caic. No.: NUH32PHB-0203 A
AREVA Calculation Rev. No.: 2 TRANSNUCLEAR INC. Page: 3of23 TABLE OF CONTENTS 1.0 Purpose ..................................................................................................................................................... 5 2.0 References ................................................................................................................................................. 5 3.0 Methodology .............................................................................................................................................. 6 4.0 Assumptions .......... !................................................................................................................................. 6 5.0 Design Criteria .......................................................................................................................................... 7 6.0 Computation ............................................................................................................................................. 7 6.1 Finite Element Model ............................................................................................................................ 7 6.2 Material Properties ..................................................................................................................... ............. 7 6.3 Selection of Bounding Case ....... ...................................................... 8 6.4 Calculation for Bending Stress ............................................................................................................... 8 6.5 Loading ............................................
L !.............................. ........................................................ , ........ 9 7.0 Results ...................................................................................................................................................... 9 8.0 Conclusion .......................................................................................................................... ................ 9 9.0 Listing of ANSYS Computer Files ............................................................................................................ 1I Appendix A: - Modal Analysis ............. .................................. ............ .............. !...............................
Appendix B: - Fuel Assembly Spacer Grid Integrity ............ .............................. 22
A Caic. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 2 TRANSNUCLEAR INC. Page: 4,of23 List of Tables Table 1 Analyzed Fuel Rod Characteristics ................................................................................................... 11 Table 2 Finite E lem ent M odel .............................................................................................................................. 12 Table 3 Summary of Stress Results for Accident Condition 75g Side Drop ........................................................... 12 Table 4 Fuel Cladding Natural Frequencies ................................................................................................... 16 List of Figures Figure 1 PW R Fuel Cladding G eom etry .............. ............ ...................... . .................. . . .............. . ......... 13 Figure 2 Finite Element Model Setup .................................................................................. ............................... 13 Figure 3 Typical PWR Fuel Assembly Grid and Constraints ............................................................................. 14 Figure 4 Bounding Fuel Assembly Bending Stress Under 75g Load .................................................................. 15 Figure 5 Natural Frequency - 1i Mode ........................................................................... 1..
Figure 6 N atural Frequency - 2nd M ode ........................................................... .............................................. 1 Figure 7 Natural Frequency - 3 rd Mode ......................................................................... .............. 1 Figure 8- N atural Frequency - 4 th Mode ................................................................................................................ 2.
Figure 9- N atural Frequency - 5 MM ode ............................................................................................................... 21 Figure 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.: 2 TRANSNUCLEAR INC. Page: 5_of23 1.0 Purpose The purpose of this calculation is to verify the structural adequacy of the fuel assemblies to be loaded in the NUH32PHB 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. Modal analysis 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 for Storage".
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, and Other Radiological Wastes which May Require Long-Term Isolation", USDOE, Office of Civilian Radioactive Waste Management.
2.5 TN Calculation NUH32PHB-0403, Rev. 0, "Thermal Evaluation of NU1HOMS 32PHB DSC for Storage and Transfer Conditions".
2.6 H.E. Adkins, Jr., B.J. Koeppel and T. Tang, "Spent Nuclear Fuel Structural Response when Subjected to an End 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 Book Company, 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 National Laboratory, 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 and Personal 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 Cask Containment Requirements'", Sandia National Laboratories,. November 1992.
2.16 TN Calculation No. NUHPHB-0205, Rev. 1, "NUHOMS 32PHB Basket Evaluation for Storage and Transfer Loads".
2.17 TN Calculation No. NUH-HBU-0249, Rev: 0, "M5 Cladding Mechanical Properties".
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AR.EVA CalcUlation Rev. No.- 2 TRANSNUCLEAR INC. Page: 9.of23 Proprietary 8.0 Conclusion The maximum stress under Accident drop conditions among all PWR fuels to be transported, in the NUH32PHB Cask is 45.4 ksi for Zircaloy-4 and 48.0 ksi for M-5, respectively. Those stresses significantly lower than the yield stress of Zircaloy-4 (92 ksi) and M-5 (67.3 ksi) at 750 TF. It is, therefore, concluded that the fuel claddings will not fail under accident side drop load condition.
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