ML15075A345
| ML15075A345 | |
| 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. 1 | |
| Download: ML15075A345 (23) | |
Text
ENCLOSURE 12Non-Proprietary NUH32PHB-0203, Revision 1,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 Calculation N,.: NUfI32PIIB-0203 A R EVA Calculation Cover Sheet Revision No.:TRANSNUCLEAR INC. TIP 3.2 (Revision
- 5) Page I of 22DCR NO (if applicable):
NUHI32PHIB-009 PROJEcr NAME: NUHOMS*32PIHB 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:
l) 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)!IIf original issue, is licensing review per TIP 3.5 required?
N/AYes [i No [I (explain below) Licensing Review No.:Software Utilized (subject to test requirements of TIP 3.3): Version:ANSYS I O.OA ICalculation is complete:
Originator Name and Signature:
Huan LiDate:Calculation has been checked for consistency, completeness and correctness:
Raheel Haroon dChecker Name and Signature:
Date:Calculation is approved for use:Project Engineer Name and Signature:
Date:
A,. JCalc. No.: NUH32PHB-0203 ARIEVA Calculation Rev. No.: 1TfRANSNUCLEAR INC. Page: 2 of 22REVISION SUMMARY AffectedRev. Description of Changes Pages Computational
_/o0 Initial Issue All AllI Add discussion about M-5 material for AREVA fuel assembly so that all 1,2,5-8,11,15 Nonethe fuel assemblies for NL-32PI-BB are taken into account.
A Caic. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 1TRANSNUCL.AR INC. Page: 3 of 22TABLE OF CONTENTSi.0 Purpose ............
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52.0 References
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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 Loading ............................................................................................................................................................
87.0 Results .........................................................................
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88.0 Conclusion
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a ........89.0 Listing of ANSYS.................
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99.0 Listing of ANSYS Computer Files ............
..... .. 9Appendix A: -M odal AnMlysis
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15Appendix B: -Fuel Assem bly Spacer Grid Integrity
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21 A ICaic. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 1TRANSNUCL.AR INC. Page: j4.6f 22List of TablesTable I Analyzed Fuel Rod Characteristics
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... .10Table~~ 2 iieEeetMdl..............
... ....... .....................
s..........11..
Table 2 Finite E lem ent M odel ....................................................................
v......................................................................
I1ITable 3 Summary of Stress Results for Accident Condition 75g Side Drop ..................................................................
11Table 4 Fuel Cladding N atural Frequencies
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15List of FiguresFigure I PW R Fuel Cladding Geom etry ....... .. ............................................................
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12Figure 2 Finite Elem ent M odel Setup ..............................................................................................................................
12Figure 3 Typical PWR Fuel Assembly Grid and Constraints
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13Figure 4 Bounding Fuel Assembly Bending Stress Under 75g Load.-......
....... ....... 14Figure 5 Natural Frequency
-1" M ode ..... .........
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16Figure 6 N atural Frequency
-2nd M ode .......................................................................................................................
..... 17Figure 7 N atural Frequency
-d M ode ............................................................................................................................
18Figure 8- N atural Frequency
-4th M ode ............................................................................................................................
19Figure 9- Natural Frequency
-51h Mode .... ................................................
20Figure 10 Schematic Diagram of Spacer Grid Response (Ref. [2.15], Figure uI-15) i ......................
2.. ;...22 A Calc. No.: NUH32PHB-0203 AREVA Calculation
.Rev. No..: 1T.RANSNUCLEAR INC.. Page: 5of221.0 PurposeThe purpose of this calculation is to verify the structbral 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 spaccr 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 NIJHOMS 32PHB System forStorage"...
2.2 TN Calculation No. 972-179, Rev. 0, "TN-68 High Bumup 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 NU32PHB-0403, Rev. 0, "Thermal Evaluation of NUHOMS 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 An Swam, L.F., Strasser A.A., Cook J.D., Burger J.M., "Behavior of Zircaloy-4 and Zirconium LinearZircaloy-4 Cladding at High Bumup", Proceedings of the 1997 International Topical Meeting on LWR FuelPerformance,
- Portland, Ofegon March 2-6, 1997.2.8 Raymond J, Roark and Warren C. Young, '"Formulas For Stress and Strain",
5k" edition, MoDraw-Hill 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".2.1.0 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 Modular CodeSystm 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 AR EVA Calculation Rev. No.: 1T.RANZNUCLEAR INC. Page: 6 of 22Proprietary II A Calc. No.: NUH32PHB-0203 ARIEVA Calculation Rev. No.: 1TRANSNUC-LE.R INC. Page: 7of 92Proprietary A Calc. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 1iTRANSNUCLEAR INC. PJage: 8 .of 22Proprietary
8.0 Conclusion
The maximum stress under Accident drop conditions among all PWR fuels to be transported in the NUH32PHB Caskis 44.5 ksi for Zircaloy-4 and 47.1 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 'F. It is, therefore, concluded that the fiel claddings will not fail urnderaccident side drop load condition.
.A Calc. No.: NUH32PHB-0203 AREVA Calculation Rev. No.: 1TRANSNUCLEAR INC. Page: 9.of 22Proprietary A Caic. No., NUH32PHB-0203 AR EVA Calculation Rev. No.: IT.RANSNUCLEAR INC. Page: 10of22Proprietary A ICalc. No.: NUH32PHB-0203 ARIEVA Calculation Rev. No.: 1T.RANSNUCLIAR INC. Page: 11 of 22Proprietary
.A Calc. No.: NUH32PHB-0203 AR EVA Calculation Rev. No.: 1TRANSNUCLEAR INC., Page: 12.of 22Proprietary A Calc, Noi,: NUH32PHB-.203 AREVA Calculation Rev. N6.: -ITRANNUCL.AR INC. Page: 113 of 22Proprietary A CaIlC No.:' NUH32PHf.0O203 AREVA Calculation Rev. NO. ITRANSNUCLEAR IN, Page: 14 of 22Proprietary
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