ML20217G162
| ML20217G162 | |
| Person / Time | |
|---|---|
| Site: | 07201015, 07109270 |
| Issue date: | 04/23/1998 |
| From: | Thompson T NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE |
| To: | Mcginty T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9804290074 | |
| Download: ML20217G162 (178) | |
Text
.-
^t!*nta Corporate Headqu rters 655 Engineering Drive INTERNATIONAL sorcross, ceorgi 30092 770-447-1144 l
Fax 770-4471797 www nacintl. coin April 23,1998 Mr. Timothy J. McGinty, Project Manager Spent Fuel Projects Office U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockvi!!e, Maryland 20852-2738
Dear Mr. McGinty:
Subject:
Revised Pages - UMS SAR and TSAR Supplemental Information i
Reference:
1.
TAC No. L22452, Safety Analysis Report for the UMS Universal Transport Cask, Docket No. 71-9270, submitted April 30,1997, NAC International.
2.
TAC No. L22511, Topical Safety Analysis Report for the UMS Universal Storage System, Docket No. 72-1015, submitted August 29,1997, NAC International, 3.
NAC Letter, ED970981, to U.S. NRC Document Control Desk, Supplemental Information Submittal in Support of the UMS SAR and TSAR, dated
)
December 24,1997.
J NAC International (NAC) herewith submits ten (10) copies of changed (revised) pages for the UMS SAR and TSAR (References No. I and 2) to replace some of the pages included in the Supplemental Information
{
submittal (Reference No. 3). Included in this submittal are: (1) a List of Effective Pages and a set of changed pages for the Safety Analysis Report for the UMS Universal Transport Cask; and (2) a List of Effective Pages and a set of changed pages for the Topical Safety Analysis Report for the UMS Universal Storage System. These revised pages are to be inserted in the SAR and TSAR to replace the previous revision pages. Please note that for the convenience of double-sided copying some pages that have not changed from Revision 0 are included in the change pages.
The revised pages have been prepared in accordance with the following conventions:
Revision indicators (shading and revision bars) are used to highlight changes from Revision 0.
These revisions of the UMS SAR and TS AR are designated (UMST-97B) and (UMSS-978),
respectively, for case of understanding the correlation of these revisions to the earlier ones,(UMST-97A) and (UMSS-97A).
i The Lists of Effective Pages are all designated " Revision UMST-97B" or " Revision UMSS-97B" as e
applicable. by definition, and no revision bars are used on those pages.
)
Revision Bars in the margin are used to indicate a change in the text flow, i.e., pagination from Rev,ision
- 0. No Revision bars are used in the lleaders.
g 9804290074 900423 PDR ADOCK 07109270 g
B PDR O
ED980387. doc l
AllAN1A W A $ H l N C 10 h NIwYORK ZURICH LONDON TOKYO MOstOW
, S NAC FBINTERNATIONAL Timothy J. McGinty April 23,1998 Page 2 The only highlighting in the lieader is the "T" added in front of"SAR" so as to identify what may be e
the only change on the page from Rev. UMSS-97A. The date and the revision number in the right-hand corner of the lleader are considered self-explanatory and are not highlighted.
Those pages (usually on the opposite side of a page with a Rev. UMSS-97A change), where the "T" in
" TSAR" was inadvenently dropped w hen we submitted Rev. UMSS-97A, and the "T" is now being added back in to return the pages to their original Revision 0 form, are designated August 1997, Revision 0,.vith no highlighting.
Several Revision 0 pages, which were distributed with Revisions UMSS-97A and UMST-97A for ease of incorporation, included headers that were inadvertently changed. These Revision 0 pages have been replaced within the enclosed package. No shading is shown on these pages since there is no change in content from the original Revision 0 pages.
One page has been included which is of improved copy quality over that page submitted in Revision UMST-97A.
These changed (revised) pages have resulted from NAC's identification of typographical and administrative
{
errors in the changed pages previously submitted as supplemental information. The errors are believed to have occurred due to some inconsistencies in the commercial word processing software used by NAC (Microsoft Word, Version 7.0) and inadequate review of the final changed pages immediately prior to copying. In accordance with NAC's Quality Assurance Program, a Corrective Action Report has been completed to identify the probable cause, extent of condition, corrective action, and actions taken to prevent recurrence.
As you are aware from previous discussions, the UMSTM System has been selected by Arizona Public Service for implementation at the Palo Verde Nuclear Plant and is under serious consideration by several other U.S. utilities for dry cask storage of spent fuel at their planned ISFSis. Therefore, NAC requests that the NRC continue the technical review on a priority basis for the approval of the Universal Multi-Purpose Canister System. If you have any comments, questions, or require additional information, please contact me or Mr. Bill Lee at (770) 447-l 144.
Sincerely, Y
$f7/fN/>1./
Thomas C. Thompson Director, Licensing & Competitive Assessment Engineering & Design Services Enclosures cc:
U.S. NRC Document Control Desk ED980387. doc
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TSAR - UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B List of Effective Pages Table of Contents 1.2-5................................... Revision 0 i
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................................... Revision 0 1.2-10............................... Rc asion 0 vi
.................................... R evision 0 1.2-1 1................................ Revision 0 vii................................. Revisio n 0 1.2-12................................ Revision 0 viii.................................... Revision 0 1.2-13............................... Revision 0 I
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xiii................................. Revision 0 1.2-18................................. Revision 0 xiv.................................. Revision 0 1.2-19................................. Revision 0 1.2-20................................. Revision 0 Chapter 1 1.2-21................ Revision Rgyp 1-i............................... Revision 0 1.2-22............... Revision f W *ti!
1 -ii................................... Revision 0 1.2-23................................ Revision 0 1 - 1.................................. Revision 0 1.2-24................................. Revision 0 1 -2.................................. Revision 0 1.2-25................................. Revision 0 1 -3................................. Revision 0 1.3-1.................................. Revision 0 1 -4.................................. Revision 0 1.3-2.................................. Revision 0 1 -5................................. Revision 0 1.4-1................................... Revision 0 1 -6............................... Revision 0 1.4-2................................. Revision 0 1.1 -1.............................. Revision 0 1.5-1................................... Revision 0 1.1 -2............................... Revision 0 1.5-2................................... Revision 0 1.1 -3................................ Revision 0 1.5-3................................. Revision 0 1.1 -4.......................... Revision 0 1.6-1.................................. Revision 0 1.2-1................................ Revision 0 1.6 '................................ Revision 0 1.2-2.................................. Revision 0 26 drawings ( see page 1.6-1 )
C 1.2-3................................ Revision 0 1.2-4.................................. Revision 0 1
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TSAR - UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
List of Effective Pages (continued)
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TSAR - UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B List of Effective Pages (continued) 1 1.2-105.......................... Revision 0 12.2-18............................. Revision 0 1 1.2-106............................. Revision 0 12.2-19....................... Revision 0 1 1.2-107............................ Revision 0 12.3-1............................... Revision 0 t
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l 1.2-109............ Revision.U_lWS_S47._B Chapter 13 1 1.2-1 10............................ Revision 0 13-i.................................... Revision 0 1 1.2-1 1 1............................. Revision 0 13.1 - 1................................ Revision 0 1 1.2-1 12............................. Revision 0 13.1 -2............................... Revision 0 11.3-1................ Revision UM.SS-9.-.7B..-
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e
[SAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 1.2-4 Major Physical Design Parameters of the Vertical Concrete Cask Parameter Value Height (in.)
Class 1 (PWR) 209.2 l
Class 2 (PWR) 218.3 Class 3 (PWR) 225.9 i
Class 4 (BWR) 219.7 Class 5 (BWR) 224.5 Outside diameter (in.)
136.0 Nominal weight (Ibs), Without Canister Class 1 (PWR) 221,696 Class 2 (PWR) 230,390 Class 3 (PWR) 237,649 Class 4 (BWR) 231,728 Class 5 (BWR) 236,314 Shielding (side wall)
Concrete thickness (in.)
28.2 Steel liner thickness (in.)
2.5 Radiation dose rate (mrem /hr):
Side surface
< 50 (average)
Top surface
<)j (average)
Airinlet/outiet vents
< 100 (maximum)
Air flow at design heat load (Ib-m)/sec 1
Material of construction Concrete Type 11 Portland Cement Reinforcing steel A615 Grade 60 Steel liner A36 Carbon Steel Service life (years) 50 Maximum concrete temperatures for normal 150 (bulk) operation (*F) 200 (local)
O 1.2-21
TSAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 1.2-5 Vertical Concrete Cask Fabrication Specification Summary g
Materials
. Concrete mix shall be in accordance with the requirements of ACI 318 [18] and ASTM C94
[19].
. Type Il Portland Cement, ASTM C150 [20].
. Fine aggregate ASTM C33 [21] and C637 [22].
Coarse aggregate ASTM C33.
Admixtures Water Reducing and Superplasticizing ASTM C494 [23].
Pozzolanic Admixture (Loss on Ignition 6% or less) ASTM C618 [24].
Minimum Compressive Strength 4000 psi at 28 days.
Specified Air Entrainment 3% - 6%.
All steel components shall be of material as specified in the referenced drawings.
Weldine Visual inspection of all welds shall be performed to the requirements of AWS D1.1 [25],
Section B.6d.
g Constnietion Specimens shall be obtained or prepared for each batch or truck load of concrete per ASTM C172 [26] and ASTM C31 [27].
Test specimens shall be tested in accordance with ASTM C39 [28].
Formwork shall be in accordance with ACI 318.
All sidewall formwork and shoring shall remain in place for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Grade, type, and details of all reinforcing steel shall be in accordance with the referenced drawings.
Embedded items shall conform to ACI 318 and the referenced drawings.
The placement of concrete shall be in accordance with ACI 318.
Surface finish shall be in accordance with ACI 318.
Ouality Assurance The concrete cask shall be constructed under a quality assurance program that meets 10 CFR 72 Subpart G. The quality assurance program must be accepted by NAC hiternational and the licensee prior to initiation of the work.
1.2-22
4
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B
/O V
Table 2-1 Summary of Universal Storage System Design Criteria (Continued)
Parameter Criteria Radiation Protection / Shielding:
Concrete Cask Side Wall Contact Dose Rate
< 50 mrem /hr. (avg)
Concrete Cask Top Lid Contact Dose Rate
< @0 mrem /hr. (avg)
Concrete Cask Air Inlet / Outlet Dose Rate
< 100 mrem /hr. (max)
Owner Controlled Area Boundary Dose [11]
Normal /Off-Normal Conditions 25 mrem (Annual Whole Body)
Accident Whole Body Dose 5 rem (Whole Body)
O j
U l
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s TSAR-UMS Universal Storage Syst:m August 1997 Docket No. 72-1015 Revision 0
,n 2.3.4.2 Error Contincency C.;teria N_.]
The calculated values of k,n include error contingencies and calculation and modeling biases.
The standards and regulations of criticality safety require that k,,, including uncertainties, k,, be less than 0.95. The bias and 95/95 uncertainty are applied to the calculation of k, by using:
k, = k,,, + 0.0052 + [(0.0087)2 + (20,c )2 jv2 s 0.95 where k,
= the nominal k,y for the cask, and o,c = the Monte Carlo uncertainty.
The calculation of error contingencies and uncertainties is presented in Section 6.4.
2.3.4.3 Verification Analyses The CSAS25 criticality analysis sequence is benchmarked through a series of calculations based on 63 critical experiments. These experiments span a range of fuel enrichments, fuel rod pitches, p
poison sheet characteristics, shielding materials, and geometries that are typical of light water V
reactor fuel in a cask. To achieve accurate results, three-dimensional models, as close to the actual experiment as possible, are used to evaluate the experiments.
The results of the benchmark calculations are provided in Section 6.5.
2.3.5 Radiolocical Protection The Universal Storage System, in keeping with the As Low As Is Reasonably Achievable (ALARA) philosophy, is designed to minimize, to the extent practicable, operator radiological exposure.
2.3.5.1 Access Control Access to an Universal Storage System ISFSI site is controlled by a peripheral fence to meet the requirements of 10 CFR 72 and 10 CFR 20 [20]. Access to the storage area, and its designation as to the level of radiation protection required, are established by site procedure. The storage area is surrounded by a fence, having lockable truck and personnel access gates. The fence has intrusion-detection features as determined by the site procedure, v
2.3-7
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B 2.3.5.2 Shieldine g
The Universal Storage System is designed to limit the dose rates as follows:
external surface dose (gamma and neutron) to less than 50 mrem /hr (average) on the Vertical Concrete Cask sides; external surface dose to less than $0 mrem /hr (average) on the Vertical Conote Cask top, e
a maximum of 100 mrem /hr at the Vertical Concrete Cask air inlets and outlets.
e less than 300 mrem /hr (average) on the transfer cask side wall.
the design maximum dose rate at the top of the canister structural lid, with supplemental shielding to less than 300 mrem /hr to limit personnel exposure during canister closure operations.
Sections 72.104 and 72.106 of 10 CFR 72 set whole body dose limits for an individual located beyond the controlled area at 25 millirems per year (whole body) during normal operations and 5 rems (5,000 millirems) from any design basis accident. The analyses showing the actual Universal Storage System doses, and dose rates, are included in Chapters 5.0,10.0 and 11.0.
2.3.5.3 Ventilation Off-Gas i
The Universal Storage System is passively cooled by radiation and natural convection heat transfer at the outer surface of the concrete cask and in the canister-concrete cask annulus. The bottom of the cask is conservatively assumed to be an adiabatic surface. In the canister-concrete cask annulus, air enters the air inlets, flows up between the canister and concrete cask liner in the annulus, and exits the air outlets. The air flow in the annulus is due to the buoyancy effect created by the heating of the air by the canister and concrete cask liner walls. The details of the passive ventilation system design are provided in Chapter 4.0.
The surface of the canisteris exposed to cooling air when the canisteris placed in the concrete I
cask. If the surfaceis contaminated, the possibility exists that contamination could be carried O
l 2.3-8
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 Table of Contents
{
1 1
3.0 STR UCTURAL EVAL UATION........................................................................... 3.1 - 1 3.1 Structural Design.......................................................................................................
3.1.1 D i sc us si on...............................................................
3.1.2 Desi gn Criteria...................................................................................................
3.2 Weights and Centers of Gravity..................................................................................... 3 11 3.3 Mechanical Properties of Materials............................................................................... 3.3-1 3.4 General Standards..............................................................................
3.4.1 Chemical and Galvanic Reactions........................................................................... 3.4-1 3.4.1.1 Component Operating Environment...................................................... 3.4 1 3.4.1.2 Component Material Categories............................................................... 3.4-2 3.4.1.3 General Effects ofIdentified Reactions.................................................... 3.4-5 3.4.1.4 Adequacy of the Canister Operating Procedures...................................... 3.4-5 3.4.1.5 Effects of Reaction Products................................................................... 3.4-6 3.4.2 Positi ve Closure..............................................................................
3.4.3 Li fting Devices...................................................................................................... 3.4-8 3.4.3.1 Vertical Concrete Cask Bottom Lift....................................................... 3.4-12 3.4.3.2 Cani ster Lin....................................................................................
3.4.3.3 Transfer Cask Li n.........................................................................
3.4.4 Normal Operating Conditions Analysis............................................................. 3.4-49 3.4.4.1 Canister and Basket Analyses............................................................. 3.4-50 3.4.4.2 Vertical Concrete Cask Analyses........................................................ 3.4-102 3.4.5 Cold..................................................................................................................3.4-111 3.5FuelRods.....................................................................................................................3.5-1
- 3. 6 R e feren ces....................................................................
3.7 A ppendix A..........................................................................................................
s 3-1 i
[fSAR-UMS Universal Storage System Apiil 1998 Docket No. 72-1015 Revision UMSS-97B List of Figures Figure 3.1-1 Principal Components of the Universal Storage System....................... 3.1-7 Figure 3.4.2-1 Universal Storage System Welded Canister Closure........................... 3.4-7 Figure 3.4.3-1 Transfer Cask Lifting Trunnion.......
......... 3.4-10 Figure 3.4.3-2 Canister Hoist Ring Design...................
.......................3.4-11 Figure 3.4.3.2-1 Canister Lift Finite Element Model......................................... 3.4-22 Figure 3.4.3.2-2 Canister Lift Model Stress Intensity Contours (psi).................... 3.4-23 Figure 3.4.3.3-1 Finite Element Model for Transfer Cask Trunnion and Shells................ 3.4-38 Figure 3.4.3.3-2 Node Locations for Transfer Cask Outer Shell Adjacent to Trunnion.... 3.4-39 Figure 3.4.3.3-3 Node Locations for Transfer Cask Inner Shell Adjacent to Trunnion... 3.4-40 Figure 3.4.3.3-4 Stress Intensity Contours (psi) for Transfer Cask Outer Shell Element Top Surface..........
...............................................3.4-41 Figure 3.4.3.3-5 Stress Intensity Coritours (psi) for Transfer Cask Outer Shell Element Bottom S urface..................................................... 3.4-4 2 Figure 3.4.3.3-6 Stress Intensity Contours (psi) for Transfer Cask Inner Shell Element Top Surface..
......................................3.4-43 Figure 3.4.3.3-7 Stress Intensity Contours (psi) for Transfer Cask Inner Shell h
Element Bottom Surface....................................................3.4-44 Figure 3.4.4.1-1 Canister Composite Finite Element Model.................................[43 Figv:14.4.1-2 Weld Regions of Canister Composite Finite Element Model at Structural and Shield Lids.................................................. 3.4-69 Figure 3.4.4.1-3 Bottom Plate of the Canister Composite Finite Element Model......... 3.4-70 Figure 3.4.4.1-4 Locations for Section Stresses in the Canister Composite Finite Element Model..
........ 3.4-71 Figure 3.4.4.1-5 BWR Fuel Assembly Basket Showing Typical Fuel Basket Components...
............... 3.4-72 Figure 3.4.4.1-6 PWR Fuel Basket Support Disk Finite Element Model....
............. 3.4-73 Figure 3.4.4.1-7 PWR Fuel Basket Support Disk Linearized Sections and Node Locations (Left Half)................................................. 3.4-74 l
Figure 3.4.4.1-8 PWR Fuel Basket Support Disk Linearized Sections and Node Locations (Right Half)...................................................... 3.4-75 Figure 3.4.4.1-9 PWR Class 3 Fuel Tube Configuration.......................................... 3.4-76 Figure 3.4.4.1-10 PWR Top Weldment Plate Finite Element Model......................... 3.4-77 Figure 3.4.4.1-11 PWR Bottom Weldment Plate Finite Element Model...................... 3.4-78 Figure 3.4.4.1-12 BWR Fuel Basket Support Disk Finite Element Model.................. 3.4-79 h
3-ii
[SAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B
((
List of Tables (continued)
Table 3.4.4.1-8 Summary of Maximum Canister Normal Handling, plus Normal Pressure, plus Secondary (P+Q) Stresses (ksi).............................. 3.4-94 Table 3.4.-l.1-9 Canister Normal Internal Pressure Primary Membrane (P )
S tresses (ksi)................................................................ 3.4-95 Table 3.4.4.1-10 Canister Normal Internal Pressure Primary Membrane plus Bending (P + P,) Stresses (ksi)................................................ 3.4-96 Table 3.4.4.1-11 P, + P Stresses for BWR Support Disk 20g @ Impact (T., = 516 F, T., = 106 F)...................................................... 3.4-9 7 Table 3.4.4.1-12 P, + P, + Q Stresses for BWR Support Disk 20g @ Impact (T., = 516 F, T., = 106 F)............
.....................................3.4-97 Table 3.4.4.1-13 Strye for the PWR Top / Bottom Weldments for 20g End Impact....... 3.4 98
~
Table 3.4.4.1-14 Strisici for the BWR Top / Bottom Weldments for 20g End Impact........ 3.4-99 Table 3.4.4.1-15 Summary of Maximum Stresses for BWR and PWR Fuel Basket Weldment and Support Disks-Normal Conditions............ 3.4-100 Table 3.4.4.2-1 Summary of Maximum Stresses for Vertical Concrete Cask Load Combinations..
tO
.................................... 3. 4 - 1 0 8 Table 3.4.4.2-2 Maximum Concrete and Reinforcing Bar Stresses....................... 3.4-109
\\_/
v 3-v
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O
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 3.4.4.1.7 Canister Pressure Test The canister is designed and fabricated to the requirements of ASME Code, Subsection NB, to the extent possible. A 20 psig pneumatic pressure test is performed in accordance with the requirements of ASME Code Subsection NB-6320 [5]. The test pressure slightly exceeds 1.2 x design pressure (1.2 x 15 psig = 18 psig).
The ASME Code requires that the pressure test loading comply with the following criteria from Subsection NB-3226:
(a) P, shall not exceed 0.9S, at test temperature. For convenience, the stress intensities developed in the analysis of the canister due to a normal internal pressure of 15 psig (Tables 3.4.4.1-9 and 3.4.4.1-10) are ratioed to demonstrate compliance with this requirement. From Table 3.4.4.1-9, the maximum primary stress intensity, P,, is 2.51 ksi. The canister material is ASME SA-240, Type 304L stainless steel, and the test temperature is 100*F.
(P,),, = (20/15)(2.51 ksi) = 3.35 ksi, which is < S = 24.2 ksi.
y Thus, criterion (a)is met.
(b) For P, <0.67S, (see criterion a), the primary membrane plus bending stress intensity, P, + P,
shall be s 1.35S. From Table 3.4.4.1-10, P + P = 10.27 ksi.
y (P + P ),, = (20/15)x(10.27 ksi) = 13.7 ksi, which is s 1.35S, = 32.7 ksi (1.35x24.2 ksi).
3 Thus, criterion (b) is met.
(c) The external pressure shall not exceed 135% of the value determined by the rules of NB-3133. The exterior of the canister is at atmospheric pressure at the time the pressure test is conducted. Therefore, this criterion is met.
(d) For the 1.20 to 1.25 Design Pressure pneumatic test of NB-6321, the stresses shall be calculated and compared to the limits of criteria (a), (b), and (c). This calculation and the fatigue evaluation of(e) need not be revised unless the actual pneumatic test pressure exceeds 1.25 Design Pressure.
3.4-59
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B The test pressure slightly exceeds 1.25 x Design Pressure. However, the stresses used in this evaluation are ratioed to the test pressure. Thus, the stresses at the test pressure are calculated.
(e) Tests, with the exception of @ the first 10 pneumatic tests in accordance with NB-6320, shall be considered in the fatigue evaluation of the component.
The canisters are not reused, and the pneumatic test will be conducted only once. Thus, the pressure test is not required to be considered in the fatigue analysis.
The canister pneumatic pressure tests complies with all NB-3226 criteria.
3.4.4.1.8 Fuel Basket Sunnort Disk Evaluation
@$WICiii'dWe:Bylff5"el?jIskifsTu@EilEare evafGiiiil usinit1pute#i=4 ---MiiiiHE
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RF56ff[2]2N5ipiili5n~difEnT5ffaEnsWeVarnaTed7Whfeidemam2Wam"5E Eii61Qthe transportfzElieTelement'aiihlyili'iii~MI@t6TXEYN idijEMTaiiTsNEY4.X1T13?i6]tE6_"ajl sWiiBIs stmEEW6 g
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55g6sarggirnarir6rigsgsigigtH8rerGyrs) 3.4.4.1.8.1 PWR Sunnort Disk Two finite element models are generated guiij@iEUMITISIMMl!PJfnisiisil[T!IW
.GF81reFMfsHWMt2]) to analyze the PWR fuel basket - one for the side load case, in which the loads act in the plane of the disk, and one for the end load case, in which the loads are perpendicular to the plane of the disk, [oErriiil.i isil65iiE51%isiifoH$5EiiiilipEiliililiifd5
~
$g]p@l6ad Feli_Tal_@Be[eWthe itresses foTnid@_alMitioniserstoragg The finite element model EiliSWTiliFigBiefGilW5Eir!NM13376f7 BET @!TUiF6lBR]
15iSEPl@lS5fs5[M81bi[2.]l9@3[@MPtippeMel]
O 3.4-60
TSAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B A
For normal handling operations forfoM6, only 1.1 g end loads are applied to the fuel basket.
V For off-normal handling, both end and side loads are present (see Chapter 11). Under accident conditions, the basket experiences both end and side loads (see Chapter 11).
The results of the support disk structural analyses for dead load, handling load, and thermal load are presented in Table 3.4.4.1-15. Figures 3.4.4.1-7 and 3.4.4.1-8 show the sections taken when calculating the linearized stress. As shown in the table, the support disks maintain large positive margins of safety for the conditions analyzed.
3.4.4.1.8.2 BWR Sunnort Disk The Universal Transport Cask BWR basket is similar in design to the PWR basket. It is a right-circular cylinder structure fabricated with 56 square fuel tubes, a number of circular support disks, a number of heat transfer disks, six tie rods with split spacers, and two end weldment plates. The ntunber of support disks and heat transfer disks varies depending upon the class of BWR fuel the basket is designed to contain. The basket components and their geometry are illustrated in Figure 3.4.4.1-5. Figure 3.4.4.1-17 shows the details of the BWR fuel tube with the encasing BORAL on two sides. The fuel tubes are open at each end; therefore, longitudinal fuel
(
assembly loads are imparted to the canister shield lid or bottom plate, and not the fuel basket structure. The fuel basket contains the fuel and is laterally supportM hy the cariister shell. The
{
fuel assemblies, together with the tubes, are hterally supported in the holes in the carbon steel support disks. The aluminum heat transfer disks located at the mid section of the cavity are used i
to fully optimize the passive heat rejection from the package and are self-supporting.
The primary function of the spacers and the threaded top nut is to locate and structurally assemble the support disks. The aluminum heat transfer disks are located throughout the cavity to fully optimize passive heat rejection from the package. They serve no structural function other
{
than to support their own weight. The stainless steel fuel tubes are not considered to be structural components with respect to the disks other than consideration of their mass contribution to loading. The only component that requires a detailed finite element analysis is the support disk.
As is the case for the analysis of the PWR basket, two finite element models are generated to analyze the BWR fuel basket for the pririaltransportEc6Ldi[o~n7sshown in 5'e'HIBli2'.T.TF6f; R@Spji@@ Trdis@@1SAR]2]2Q{ey6dil li~us~ed foDhWdli@@, in which the p
loads are perpendicular to the plane of the disk, and one for the side-impact, in which the loads V
3.4-61
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B act in the plane of the disk. Both models accommodate thermal expansion effects by using the temperature distribution from the thermal analysis and the coefficient of thermal expansion. A complete basket support disk is modeled for the side impact evaluation because planes of symmetry are not present when the impact can be at an arbitrary angle. The support disk model for the side-impact is shown in Figure 3.4.4.1-12. Although the end-impact orientation exhibits a quarter symmetry, the model conversion is simplified by using the same nodal pattern as that for the side-impact model[JTe~SEcliSii2A{5Tofithe! OMS?UirvEalTransp_ortfCis163XR',[oH ETscM~I6iibf,thifidiiFilEisini~m~odelj.
t For normal haadling operations [ol[tRa~gg, only 1.1 g end loads are applied to the fuel basket.
MeWisEfrEFgygEthe3Fgi@@isWdeFeminTysWWEW25Wpg[
[65figjinifefEiBEi[tM##[Mals The ANSYS plane stress element, PLANE 42,is used to model the BWR support disk. Because, the model is planer, the thickness of the support disk is input as a constant.
Structural design criteria for the BWR basket are similar to those for the PWR basket. The main structural components in the fuel basket-the carbon steel support disks-are shown to have a h
maximum primary membrane stress intensity and primary membrane plus bending stress intensity that are less than the design stress intensity values S, and 1.5S., respectively. The value of S, is defimed at the temperatures for the component being analyzed.
Membrane (P ) and bending stresses (P ) for normal storage conditions are detennined by 3
scaling the values from a 20g end impact analysis using a 0.06 (1.lg/20g) scaling factor. The 1.lg load for normal storage conditions includes a 10% load factor to ensure the analysis bounds all storage condition loads. Secondary stresses (Q) are added directly to the scaled values of P, +
P, without scaling. The 20g end impact analysis results are presented in Tables 3.4.4.1-11 and 3.4.4.1-12. The nodes and sections that the stresses used in the evaluation are shown in Figures 3.4.4.1-13 through 3.4.4.1-16. The maximum primary and secondary stresses for the 20g end impact analysis, analysis, along with the scaled values for normal storage conditions are summarized in Table 3.4.4.1-15.
O 3.4-62
[SAR-UMSS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B y
3.4.4.1.9 Fuel Basket Weldments Evaluation The PWR and BWR fuel basket weldments are evaluated for normal storage conditions by applying an acceleration of 1.0g on to the entire model in the axial direction. An additional 10%
dynamic load factor is added to account for handling loads. Therefore, a total acceleration of 1.lg is applied to the canister in the axial direction. The worst-case thermal stresses are also included. The results of the scaled structural analyses for dead load, handling load, and thermal load are summarized in Table 3.4.4.1-15.
The responses of the top and bo: tom weldment plates of the PWR and BWR fuel assemblies to 1.lg normal loads, in conjunction with the thermal expansion stress, are evaluated in this section.
The stresses for storage conditions are scaled from the 20g end impact analysis results presented in Tables 3.4.4.1-13 and 3.4.4.1-14, EliiEhW.. M G My JH f j;e3 o..m.n EMiWMI21 3.4.4.1.9.1 PWR Fuel Basket Weldments The PWR top and bottom weldment plates are 1.0-in. thick Type 304 stainless steel. The weldments support their own weight plus the weight of up to 24 PWR fuel assembly tubes. An ANSYS finite element analysis was prepared for both plates because the support location for each weldment is different. Both models use the SHELL63 elements, which permits out-of-plane loading. The finite element models for the top and bottom weldments are shown in Figures 3.4.4.1-10 and 3.4.4.lM, respectively. The load from the fuel tube is represented as point forces applied to the nodes at the periphery of the fuel assembly slots. An average point force is applied. The application of the nodal loads at the slot periphery is accurate because the tube weight is transmitted to the edge of the slot, which provides support to the fuel tubes while in the vertical position. The analysis using the applied nodal forces demonstrates that the weldment design satisfies the primary membrane (P ) and the primary membrane plus bending (P. + P,)
stress criteria. Thermal expansion stresses are also analyzed. The determination of the weldment temperatures is discussed in Chapter 4.0.
The stresses, scaled for a 1.1 g load, and the margins of safety for the weldments are shown in Table 3.4.4.1-15.
The weldments satisfy the stress criteria in the ASME Code,Section III, Division I, Subsection NG [6].
O 3.4-63
\\
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B 3.4.4.1.9.2 BWR Fuel Basket Weldments i
In the BWR fuel basket transport analysis, the responses of the top and bottom weldment plates to normal storage conditions are evaluated in con, junction with the thermal expansion stress. The weldment plates are 1.0-in. thick Type 304 stainless steel. The weldments support their own weight and the weight of up to 56 BWR fuel assembly tubes. A finite element analysis was performed for the top and bottom plates because the support for each weldment differs depending upon the location of the welded ribs for each. Both models use SHELL63 elements, which permit out-of-plane loading. The finite element models for the top and bottom weldments are shown in Figure 3.4.4.1-18 and Figure 3.4.4.1-19, respectively. The load from the fuel tube is represented as average point forces applied to the nodes at the periphery of the fuel assembly slots because the tube weight is transmitted to the edge of the slot in the end-impact condition.
The analysis demonstrates that the weldment design satisfies the primary membrane (P ) and the primary membrane plus bending (P, + P ) stress criteria. An analysis including the thermal 3
expansion stresses is also performed.
The stresses, scaled for a 1.1 g load and the margins of safety evaluated for the weldments are g
shown in Table 3.4.4.1-15. The weldments satisfy the stress criteria in the ASME Code,Section III Division I, Subsection NG [6].
3.4.4.1.10 Fuel Tube Analysis Under normal storage conditions, the fuel tubes, Figure 3.4.4.1-9 (PWR) and Figure 3.4.4.1-17 (BWR), support only their own weight. The fuel assemblies are supported by the canister bottom plate, not by the fuel tubes. Thermal stresses are considered to be negligible since the tubes are free to expand axially and radially. The handling load is taken as 10% of the dead load.
The weight of the fuel tube, with a load of 1.lg (to account for both the dead load and handling l
load) is carried by the tube cross-section. The cross sectional area of a PWR fuel tube is:
Area = (8.9 in)2 - (8.9 in. - 2 x 0.048 in.)2 = 1.7 in:
The weight of the heaviest (longest) PWR fuel tube, including the 0.075 in. thick BORAL plates, is about 153 lb. Considering a g-load of 1.1, the maximum compressive and bearing stress in the fuel tube is about 99 psi (153 lb x 1.1/1.7 in ). Limiting the compressive stress level in the 2
3.4-64
ISAR-UMS5 Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B tube to the material yield strength ensures the tube remains in position in storage conditions. The yield strength of Type 304 stainless steel is 17,300 psi at a conservatively high temperature of 750'F.
MS = 17,300/99 - 1 = +Large The cross sectional area of a BWR fuel tube is:
Area = (5.996 in)2 - (5.9969 in. - 2 x 0.048 in.)2 = 1.14 in 2
The weight of the heaviest (longest) BWR fuel tube, including 0.135 in. thick BORAL plates on two sides, is about 83 lb. Considering a g-load of 1.1, the maximum compressive and bearing stress in the fuel tube is about 80 psi (83 lb x 1.1/1.14 in.2). Limiting the compressive stress level in the tube to the material yield strength ensures the tube remains in position in storage conditions. The yield strength of Type 304 stainless steel is 17,300 psi at a conservatively high temperature of 750 F.
Margin of Safety
= 17,300/80 - 1 = +Large O
Thus, the tubes are structurally adequate under normal storage and handing conditions.
O 3.4-65
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Figure 3.4.4.1-1 Canister Composite Finite Element Model g
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I'SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
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I 3.4 67
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
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THIS PAGE INTENTIONALLY LEFT BLANK O
3.4-68
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 3.4.4.1-11 P,+ P, Stresses for BWR Support Disk 20g BiilImpact}
(T, = 516'F, T = 106 F)
Principal Stresses (ksi)
Stress Node S1 S2 S3 Intensity 86 25.6 0.0
-1.0 26.6 474 32.5 2.1 0.0 32.5 1129 29.9 1.5 0.0 29.9 1444 32.5 2.1 0.0 32.5 1564 25.6 0.0
-1.0 26.6 2236 29.9 1.5 0.0 29.9
{
2558 32.5 2.1 0.0 32.5 i
2680 25.6 0.0
-1.0 26.6 3332 29.9 1.5 0.0 29.9 3647 32.5 2.1 0.0 32.5 3765 25.6 0.0
-1.0 26.6 l
4407 29.9 1.46 0.0 29.9 ERefer to, Table 2.6.15.4-2, UMS UniversalTrangp_ortCasif5AlQ2]
~
Table 3.4.4.1-12 P + P. + Q Stresses for BWR Support Disk 20g $6d Impactj (T., = 516 F, T,i,, = 106 F)
Principal Stresses (ksi)
Stress Node S1 S2 S3 Intensity 474 52.7 7.2 0.0 52.7 481 34.9 0.0
-3.1 38.1 1129 40.3 3.6 0.0 40.3 1444 52.7 7.2 0.0 52.7 1451 34.9 0.0
-3.1 38.1 2236 40.3 3.6 0.0 40.3 2558 52.7 7.2 0.0 52.7 2565 34.9 0.0
-3.1 38.1 3332 40.3 3.6 0.0 40.3 3647 52.7 7.2 0.0 52.7 3654 34.9 0.0
-3.1 38.1 4407 40.3 3.6 0.0 40.3 12M[er toJable 2.f:15.5-1, UMS Universal Transport Cabif4Ml2]
a O
3.4-97
y
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O]
Table 3.4.4.1-13 $M for the PWR Top / Bottom Weldments for 20g End Impact l Allowable
)(argiapf,$,afetyll Component / Condition P. (ksi)
S. (ksi))
[2@
Top Weldment/20g p.86
$5.6 End Impact Bottom Weldment/20g 6113 l16 gli5$
End Impact Allowable Ef;*"77~G Component / Condition P, + P (ksi) 1.5S, (ksi))
g) 3 Top Weldment/20g 124 g316 18gl 3
End Impact Bottom Weldment/20g 4 33 g3.4 t,4j40 End Impact O
P, + P + Q Allowable M W @ afetyl 3
Component / Condition (ksi) 3S,(ksi)$
gg)
Top Weldment/20g End 35.41 g6;8 gj2 Impact + Thermal Bottom Weldment/20g End 3547 46_.8
$13 Impact + Thermal $6Eii j
JERefetto_Ja)Je 2.,.p11113.;1fUMSyniy_egTranspgg,,Ca4SAR{2]
[All6Eh61e sfiEQIn]Esjitym(SliakiifaT730T.
~~
O l
3.4-98 l
l 1
i lSAR-UMSu Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 3.4.4.1-14 M for the BWR Top / Bottom Weldments for 20g End Impact]
Allowable M
Component / Condition P (ksi)
S (ksi)$
MM Top Weldment/20g End
$.11, ggg ll185 Impact Bottom Weldment/20g
[1!14 lgg End Impact Allowable l(ting $
Compon -at/ Condition P + P,(ksi) 1.5S (ksi)[
M Top Weldment/20g End 16.50 M
Impact Bottom Weldment/20g 18.98 g
g End Impact O
Allowable Wj Component / Condition P + P + Q (ksi) 3S,(ksi){
M ")
3 Top 20g End Impact +
16J
$!J L126 Thermal Spisis Bottom 20g End Impact 27.26
$$2 M.172
+ Thermal $@
Jjf_ReferpJgl2e 2:6.15)l3-lyUMS _ Univ'enalTMPS S$3
$@]e_sgess,M.,ffj f 6 @ M.
)
I O
3.4-99
1
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 3.4.4.1-15 Summary of Maximum Stresses for BWR and PWR Fuel Basket Weldments and Support Disks - Normal Conditions Stress Intensity Allowable Stress' Load 1.lg Value Margin of Component Condition Reported 20g Value Value'(ksi)
Criteria (ksi)
Safety (f.lg) 2 PWR Top Dead Load +
P,,,
p.86,g
[1.32);
S.
15.6
+Large Weldment Handling P,,,+ P.
2.54/
0.14e 1.5 S,,,
23.4
+Large Dead Load P,,, + P + Q 35.4,11
@3Alj 3.0S,,,
46.8
+0.4 5
+ Handling
+ Thermal PWR Bottom Dead Load P,
6.13; 0 34 Weldment
+ Handling S.
15.6
+Large P,,, + P,,
433$
0.24 1.5 S,,,
23.4
+Large Dead Load P,,, + P + Q 35.2L 3.1d8 3.0S, 46.8 to.5
+ Handling
+ Theual PWR Support Dead Load P,
0.0j 0:0j S.
41.9 foty Disks
+ Handling Applicabli P,,, + P,,
7.87 0.431 1.5S,,,
62.8
+Large Dead Load P,,, + P, + Q p.5, g.13; 3.0S,,,
125.7 RLarge
+ Handling
+ Thermal BWR Top Dead Load +
P.
8.41 0.46 S,,,
15.6 169J Weldment Handling P,,,+ P, 16.50 0.91 1.5 S,,,
23.4
+24.7 Dead Load P,,, + P + Q
- 16.95 1.36 3.0S, 46.8 13_4.4
+ Handling
+ Thermal BWR Bottom Dead Load +
P,,,
11.14 0.61 S,,
15.6 12 9 Weldment Handling P,,,+ P.
I8.98 1.04 1.5 S,,,
23.4
+21.5 Dead Load P,,, + P + Q 27.26 p.32 3.0S,,,
46.8 14.0_2
+ Handling
+ Thermal BWR Support Dead Load P,,,
0.0 0.0 S,,,
29.0 fot-l Disks
+ Handling Applic~abli P,,, + P.,
32.5 1.8 1.5 S,,,
43.5 F23.2 Dead Load P,,, + P + Q 52.7 22.0 3.0S,,,
87.0
+3.0
+ Handling
+ Thermal
' Allowable stress values are taken at actual temperatures.
2 Stresses from 20g end impact taken from Tables 3.4.4.1 1I through 3.4.4.1-14.
' Stresses scaled to 1.lg normal conditions from the 20g impact analysis.
P,,, and P values were scaled by 1 1/20 Secondary stresses (Q) were not scaled, but were added directly to the scaled values for P,,, + P..
See Sections 3.4.4.1.8 and 33.4.1.9.
i O'
3.4-100
$AR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B 3.6 References 1
CFR 72, Code of Federal Regulations, " Licensing Requirements for the Independent Storage of Spent Fuel and High Level Radioactive Waste," January,1996.
2
" Safety Analysis Report for the UMS" Safety Analysis Report for the UMSm Universal Transport Cask," @ EA790-SAR-001, Docket No. 71-9270, NAC International, Atlanta, GA.@
3 ANSI 57.9-1992, " Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type)," American National Standards Institute, May 1992.
4 ACI-349-85, " Code Requirements for Nuclear Safety Related Concrete Structures,"
American Concrete Institute, March 1986.
5 ASME Boiler and Pressure Vessel Code,Section III, D. Asion I, Subsection NB, " Class 1 Components," 1995 Edition with 1995 Addenda.
6 ASME Boiler and Pressure Vessel Code,Section III, Division I, Subsection NG, " Core Support Structures," 1995 Edition with 1995 Addenda.
7 NUREG/CR 6322, " Buckling Analysis of Spent Fuel Baskets," U.S. Nuclear Regulatory Commission, May 1995.
8 NUREG-%12, " Control of Heavy Loads at Nuclear Power Plants," U.S. Nuclear Regulatory Commission, July 1980.
9 American National Standards Institute, " Radioactive Materials - Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4,500 kg) or More," ANSI N14.6-1993, 1993.
10 ASME Boiler and Pressure Vessel Code,Section II, Part D, " Material Properties," 1995 Edition, with 1995 Addenda.
I1 ASME Boiler and Pressure Vessel Code, Division I,Section III, Appendices,1995 Edition, with 1995 Addenda.
12
" Metallic Materials Specification Handbook," 4* Edition, R. B. Ross, London, Chapman and Hall,1992.
13 ASME Boiler and Pressure Vessel Code, Code Cases-Nuclear Componer.ts,1995 Edition, American Society of Mechanical Engineers, New York, July 1995.
O 3.6-1
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 14 ASTM A 615-95b, Standard Specification for Deformed and Plain Billet-Steel Bars for Concrete Reinforcement, Annual Book of ASTM Standards, Vol. 01.04, American Society for Testing and Materials, Conshohocken, PA,1996.
15
" Standard Handbook for Mechanical Engineers", 7* Edition Baumeister and Marks, McGraw-Hill, New York,1967.
16 Metallic Materials and Elements for Aerospace Vehicle Structures, Military Hardbook MIL-HDBK-5F, U.S. Department of Defense, November,1990.
17 Handbook of Concrete Engineering,2"d Edition, M. Fintel, Van Nosttrand Reinhold Co.,
18 "NS-4-FR Fire Resistant Neutron and/or Gamma Shielding Material," GESC Product Data, Genden Engineering Services & Construction Co., Tokyo, Japan.
19 NRC Bulletin 96-04, " Chemical, Galvanic, or Other Reactions in Spent Fuel Storage and Transportation Casks," U.S. Nuclear Regulatory Commission, July 5,1996.
20 ASM Handbook, Corrosion, Vol.13, ASM Intemational,1987.
21
" Guidelines for the use of Aluminum with Food and Chemicals (Compatibility Data on Aluminum in the Food and Chemical Process Industries," Aluminum Association, Inc.,
Washington, DC, April 1984.
22 TRW, Nelson Division, "Embedment Properties of Headed Studs," Design Data 10,1975.
23
" Design of Weldments, Omer Blodgett, The Lincoln Arc Welding Foundation, Cleveland, OH, August 1976.
24
" Manual of Steel Construction, Allowable Stress Design," American Institute of Steel Construction, Inc., Ninth Edition, Chicago, Illinois,1991.
25
" Machinery's Handbook," 22"d Edition, Erik Oberg, et. al, First Printing, Industrial Press, Inc., New York,1984.
26 NUREG/CR-1815, " Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," U. S. Nuclear Regulatory Commission, Washington, DC,1981.
27 "Roark's Formulas for Stress and Strain," Sixth Edition, Warren C. Young, McGraw-Hill, Inc., New York,1989.
28
" Machinery's Handbook," 23'd Edition, Erik Oberg, Fourth Printing, Industrial Press, Inc.,
New York,1990 3.6-2
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 0
ASME Boiler and Pres.sure Vessel Code,Section II, Part C, " Specifications for Welding 29 Rods, Electrodes, and Filler Metals," 1995 Edition, American Society of Mechanical Engineers, New York, July 1995.
30 American Society of Civil Engineers, " Minimum Design Loads for Buildings and Other Structures," ANSI /ASCE 7-93, May 1994.
O O
3.6-3
l 0
THIS PAGE INTENTIONALLY LEFT BLANK O
O
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 5.0 SHIELDING EVALUATION Specific dose rate limits for individual casks in a storage array are not established by 10 CFR 72
[1]. Annual dose limit criteria for the independent spent fuel storage installation (ISFSI) controlled area boundary are established by 10 CFR 72.104 and 10 CFR 72.106 for normal conditions and for design basis accidents. These regulations require that, for an array of casks in an ISFS1, the annual dose to an individual outside the controlled area boundary must not exceed 25 mrem to the whole body,75 mrem to the thyroid, and 25 mrem to any other organ during normal operations. For a design basis accident, the dose to an individual outside the area boundary must not exceed 5 rem to the whole body. The ISFSI must be at least 100 meters from the owner controlled area boundary, In e.ddition, the occupational dose limits and radiation dose limits established in 10 CFR Part 20 (Subparts C and D [2] for individual members of the public must be met.
This chapter describes the shielding design and the analysis used to establish bounding radiological dose rates for the storage of various types of PWR and BWR fuel assemblies. The analysis shows that the Universal Storage System meets the requirements of 10 CFR 72.104 and 10 CFR 72.106 when the system is configured and used in accordance with the design basis established by this Safety Analysis Report.
The Universal Storage System compliance with the requirements of 10 CFR 72 with regard to annual and occupational doses at the owner controlled area boundary is demonstrated in Section 10.3 and 10.4.
5.1 Discussion and Results The Universal Storage System is comprised of a transportable storage canister, a transfer cask, and a vertical concrete cask. A multi-walled shielding arrangement is employed in both the radial and axial shields of the concrete cask and the transfer cask. The transfer cask has a radial shield comprised of 0.75 inch oflow alloy steel,3.75 inches oflead,3 inches of solid borated polymer (NS-4-FR), and 1.25 inches of low alloy steel. An additional 0.625 inch of stainless steel shielding is provided, radially, by the canister shell. Gamma shielding is provided primarily by the steel and lead layers, and neutron shielding is provided primarily by the NS-4-FR. The transfer cask bottom shield design is a solid section of 7.5 inches of low alloy steel and 1.5 5.1-1
TSAR - UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B in6h~cT6f NSWfRI. Theltop3hieldisg~~ofMeT@jryifsWo"Wded5byitfiEi5iintisiisteel canister shield and structural lids which are 7 inches and 3 inches thick, respectively. In addition, 5 inches of steel is used as temporary shielding during welding, draining, drying, helium backfill, and other operations related to closing the canister. This temporary shielding is removed prior to storage.
The vertical concrete cask radial shield design is comprised of a 2.5-inch thick carbon steel inner liner surrounded by 28.25 inches of concrete. Gamma shielding is provided by both the carbon steel and concrete, and neutron shielding is provided primarily by the concrete. As in the transfer cask, an additional 0.625 inch thickness of stainless steel radial gamma shielding is provided by the canister shell. The concrete cask top shielding design is comprised of 10 inches.of stainless steel from the canister lids, a shield plug containing a 1 inch thickness of NS-4-FR and 4.1 inches of carbon steel, and a 1.5 inch thick carbon steel lid. Since the bottom of the concrete cask rests on a concrete pad, the cask bottom shielding is comprised of 1.75 inch of stainless steel from the canister bottom plate, 2 inches of carbon steel (pedestal plate) and 1 inch of carbon steel cask base plate. The base plate and pedestal base are structural components that position the canister above the air inlets. The cask base supports the concrete cask during lifting, and forms the g
cooling air inlet channels at the cark bottom.
The spent fuel that may be stored in the Universal Storage System is divided into 5 classes, three PWR and two BWR, depending on the length of the fuel assembly. The transportable storage canister, transfer cask, and vertical concrete cask are provided in 5 lengths, corresponding to the lengths of the fuel assemblies.
The designs for PWR and BWR fuel are similar, but differ slightly in the design of the basket structure. The shielding analysis is based on the use of bounding dose rates for the design basis PWR and BWR fuel assembly, and its associated canister, transfer cask, and concrete cask.
The design basis PWR fuel for the shielding evaluation is the Westinghouse 17x17 standard assembly with an average burnup of 40,000 MWD /MTU, an initial enrichment of 3.7 wt % U n 2
and a 5-year cooling time. The shielding design basis BWR fuel is a GE9x9 assembly with a bumup of 40,000 MWD /MTU, an initial enrichment of 3.25 wt % U ", and a 5-year cooling 2
time. The source term specification is provided in Section 5.2. The shielding evaluation for fuel having a higher bumup is provided in Section 2.5.
g 5.1-2
TSAR - UMSm Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B
.o( )
Criticality Values for the Transfer Cask The maximum multiplication factor with uncertainties for the transfer cask containing PWR fuel assemblies is 0.9368 under normal transfer conditions and 0.9450 under accident conditions.
For the transfer cask containing BWR fuel, the multiplication factor is 0.9062 under normal transfer conditions and 0.9083 under accident conditions. These values reflect the following conditions:
A method bias and uncertainty associated with KENO-Va and the 27 group ENDF/B-IV library An infinite cask array (even though there will only be one built)
Full interior, exterior and fuel clad gap moderator (water) density e
24 Westinghouse 17x17 OFA fuel assemblies at 4.2 wt % U235 (most reactive PWR fuel assembly type) or 56 Ex/ANF 9x9-79 rod fuel assemblies at M5 wt % U235 (most reactive BWR fuel assembly type) l no fuel burnup 75% ofnominal B" loading in BORAL e
(7 Most reactive mechanical configuration for PWR: (Assemblies centered in the fuel tubes; fuel tubes moved toward the center of the basket; maximum fuel tube openings; closely packed disk openings)
Most reactive mechanical configuration for BWR (Assemblies and fuel tubes moved toward the center of the basket)
Analysis of moderator density variation inside the transfer cask basket shows a monotonic decrease in reactivity with decreasing moderator density. Thus, the full moderator density situation bounds draining and drying operations in the transfer cask.
Criticality Values for the Vertical Concrete Storace Cask The maximum multiplication factor with uncertainties for the Vertical Concrete Cask containing PWR fuel assemblies is 0.3808 under normal storage conditions, 0.3717 under off-normal conditions and 0.9446 under accident conditions involving full moderator intrusion.
Corresponding value for the cask containing BWR fuel assemblies is 0.3685 under normal storage conditions, 0.3720 urider off-normal conditions and 0.9077 under accident conditions 7'V; involving full moderator intrusion. These values reflect the following conditions:
6.4-11
TSAR - UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 A method bias and uncertainty associated with KENO-Va and the 27 group ENDF/B-IV e
library An infinite cask anay e
Normal conditions is defined to be a dry basket, dry heat transfer annulus and dry exterior Accident conditions is defined to be full interior, exterior and fuel clad gap moderator (water) intrusion Westinghouse 17x17 OFA fuel assemblies at 4.2 wt % U " (most reactive PWR fuel 2
assembly type) or 56 Ex/ANF 9x9-79 rod fuel assemblies at 3.75 wt % U " (most 2
reactive BWR fuel assembly type) no fuel bumup e
75% of nominal B' loading in BORAL e
Most reactive mechanical configuration for PWR (Assemblies centered in the fuel tubes; e
fuel tubes moved toward the center of the basket; maximum fuel tube openings; and closely packed disk openings)
Most reactive mechanical configuration for BWR (Assemblies and fuel tubes moved e
toward the center of the basket)
Analysis of simultaneous moderator density variation inside and outside the concrete cask shows a monotonic decrease in reactivity with decreasing moderator density. Thus, the full moderator density situation bounds any off normal or accident condition. Analysis of moderator intrusion into the cask heat transfer annulus with the a dry canister shows a slight decrease in reactivity from the completely dry situation. This is due to better neutron reflection from the concrete cask steel shell and concrete shielding with no moderator present.
6.4.3.2 Criticality Results for PWR Transfer Cask Results of the calculations for the transfer cask containing PWR fuel are provided in Tables 6.4-11 through 6.4-13. CSAS input for the normal conditions analysis for the transfer cask is provided in Figure 6.7-1. Figure 6.7-2 provides CSAS input for the transfer cask analysis under hypothetical accident conditions.
As the tables show, under normal conditions involving loading, draining and drying, the maximum k, including bias and uncertainties is 0.9368 for the transfer cask. In the accident 6.4-12
TSAR - UMS Universal Sto. age System April 1998 Docket No. 72-1015 Revision UMSS-97B C
Figure 7.1-1 Transportable Storage Canister Primary and Secondary Confimement Boundaries SE COND AR Y CONFINMf N1 BOUNDARY
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TSAR - UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
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7.1-10
TSAR - UMSm Universal Storage System August 1997 Docket No. 72-1015 Revision 0 p
Table of Centents
\\
l 0.0 RADI ATI ON PROTECTION............................................................
10.1 Ensuring That Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA)...................
................................................10.1-1 10.1.1 Policy Considerations............................................................................ 10.1 - 1 10.1.2 Design Considerations.............................................................................. 10.1 - 1 10.1.3 Operational Considerations.................................................................... 10.1 -2 10.2 Radiation Protection Design Features....................................................................... 10.2-1 10.2.1 Design Basis for Normal Storage Conditions............................................. 10.2-1 10.2.2 Design Basis for Accident Conditions........................................................ 10.2-2 10.3 Estimated On-Site Collective Dose Assessment.................................................... 10.3-1 10.3.1 Estimated Collective Dose for Loading a Single p
Universal Storage System............................................................................ 10.3-I t
10.3.2 Estimated Annual Dose Due to Routine Operations....................................10.3-2 10.4 Expo sure to the P ublic...................................................................................
10.5 Re fere n c es................................................................
)
10-i i
j
@SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
List of Figures Figure 10.3-1 Typical ISFSI 20 Cask Array Layout............
....... 10.3 -4 Figure 10.4-1 Controlled Area Boundary Determination for a Single Cask Containing Design Basis PWR Fuel.......................................
.10.4-3 Figure 10.4-2 Controlled Area Boundary Determination for a Single Cask Containing Design Basis BWR Fuel.
................ 1 0.4 -4 List of Tables l
l Table 10.3-1 Estimated Person-Mrem Exposure for Operation of the Universal Storage System.........
..............................................10.3-5 Table 10.3-2 Contents and Assumed Cooling Time of the Vertical Concrete Casks Depicted in the Typical ISFSI Array.................................................... 10.3-6 Table 10.3-3 Vertical Concrete Cask Radiation Spectra Weighting Factors..................10.3-7 Table 10.3-4 Estimate of Annual Exposure for the Operation and Surveillance o f a S in gl e P WR Cask.....................................................................,10. 3 -8 Table 10.3-5 Estimate of Annual Exposure for the Operation and Surveillance of a 20 Cask Array of PWR Casks.................................................... 10.3-8 l
l Table 10.3-6 Estimate of Annual Exposure for the Operation and Surveillance of a S ingle B WR Cask.....
..................................................... 10.3-9 Table 10.3-7 Estimate of Annual Exposure for the Operation and Surveillance of a 20 Cask Array of BWR Casks.................................................. 10.3-9 I
Table 10.4-1 Dose Versus Distance For a Single Cask Cor.taining Design Basis PWR or BWR Fuel................................................... 10.4-5 Table 10.4-2 fniitial.Fi_ji_o'su._rei_Froiii_i._P_WR."_o7BWI_C2._X,7._0._'CB, ear _ ray.......
........ 10.4-6 1
O 10-ii D
[SAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B 10.2 Radiation Protection Desien Features O
The description of the radiation shielding design is provided in Section 5.3.1. The design basis radir. tion exposure rates are summarized in Table 2-1. The principal radiation protection design features are the shielding necessary to meet the design objectives, the placement of penetrations near the edge of the canister shield lid to reduce operator exposure and handling time, and the use of shaped supplemental shielding for work on and around the shield lid, as necessary. This supplemental shielding reduces operator dose rates during the welding, inspection, draining, drying and backfilling operations that seal the canister.
Radiation exposure rates at various work locations are determined for the principal Universal Storage System operational steps using a combination of the SAS4 [3] and SKYSHINE III [4]
computer codes. The use of SAS4 is described in Section 5.1.2. The SKYSHINE-III code is discussed in Section 10.4. The calculated dose rates decrease with time.
10.2.1 Desien Basis for Normal Storace Conditions The radiation protection design basis for the Universal Storage System vertical concrete cask is derived from 10 CFR 72 and the applicable ALARA guidelines. The design basis surface dose rates, and the calculated surface and 1 meter dose rates are:
Design Basis Surface Dose Rate 1 Meter Maximum Vertical Surface Dose (mrem /hr)
Dose Rate (mrem /hr)
Concrete Cask Rate (mrem /hr)
PWR BWR PWR BWR Side wall 50.0 (avg.)
37.3
@J2 25.3 15.4 Airinlet 100.0 6.8 8.5
<5.0' 5.0 AiToutlet 100.0 65.6 50.6 12.5 7.5 Top lid 30p (avg.)
g6.1
}9,.2 13.3 8.5 The calculated dose rates at these, and at other dose points, are reported in Sections 5.1.3 and 5.4.3. The dose rates presented are for the design basis 40,000 MWD /MTU,5-year cooled, fuel.
These dose rates bound those of the higher bumup, but longer cooled, fuel described in Sections 2.1 and 2.5.
O 10.2-1
[fSAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Activities associated with closing the canister, including welding of the shield and structural lids, draining, drying, backfilling and testing, may employ temporary shielding to minimize personnel dose in the performance of those tasks.
10.2.2 Desien Basis for Accident Conditions Damage to the vertical concrete cask after a design basis accident does not result in a radiation exposure at the controlled area boundary in excess of 5 rem to the whole body or any organ. The high energy missile impact is estimated to reduce the concrete shielding thickness, locally at the point ofimpact, by approximately 6 inches. Localized cask surface dose rates for the removal of 6 inches of concrete are estimated to be less than 250 mrem /hr for the PWR and BWR configurations.
Two hypothetical accident events, rupture of 100% of the fuel rods with a subsequent breach of the canister, and vertical concrete cask tip over, are considered in Sections 11.2.2 and 11.2.12, respectively. There are no design basis events that result in the tip over of the vertical concrete cask or the release of any radioactive material from the canister.
O 10.2-2
%AR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-978 Calculation of the dose due to annual operation and surveillance requirements is estimated based on a single cask containing design basis fuel, and on an ISFSI array of 20 casks that are assumed to be loaded at the rate of 2 casks per year over a ten year period. Consequently, the casks in the array are assumed to have the cool times as shown in Table 10.3-2. To account for the reduction in source term with cool time, weighting factors are applied to the neutron and gamma radiation spectra as shown in Tcble 10.3-3.
The annual operation and surveillance requirements result in an estimated annual collective exposure of 71.4 person-mrem for a single PWR cask containing design basis fuel, and 46.8 person-mrem for a single design basis BWR cask. The annual operation and surveillance requirements for the assumed single cask and total estimated dose is shown in Table 10.3-4 for I
the single PWR cask, and in Table 10.3-6 for the BWR cask. The annual operation and surveillance requirements for the assumed 20 cask ISFSI are shown in Tables 10.3-5, and 10.3-7 for PWR and BWR configurations, respectisely. These tables show an estimated annual collective exposure of M3 person-mrem for the PWR cask configuration, and $R person-mrem for the BWR cask configuration.
O I
O 10.3-3
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 Figure 10.3-1 TypicalISFSI 20 Cask Array Layout h
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10.3-4
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 O
Table 10.3-3 Vertical Concrete Cask Radiation Spectra Weighting Factors 4
Axial Neutron Axial Gamma Radial Neutron Radial Gamma Weighting Weighting Weighting Weighting Factor Factor Factor Factor Cask Numbers PWR BWR PWR BWR PWR BWR PWR BWR A-1, B-1 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 A-2, B-2 0.96 0.96 0.83 0.84 0.96 0.96 0.83 0.83 A-3, B-3 0.93 0.93 0.72 0.74 0.93 0.93 0.72 0.74 A-4, B-4 0.89 0.89 0.65 0.67 0.89 0.89 0.65 0.67 A-5, B-5 0.86 0.86 0.59 0.62 0.86 0.86 0.59 0.62 A-6, 3-6 0.83 0.83 0.55 0.58 0.83 0.83 0.55 0.58 A-7, B-7 0.80 0.80 0.52 0.55 0.80 0.80 0.52 0.55 A-8, B-8 0.77 0.77 0.50 0.52 0.77 0.77 0.50 0.52 A-9, B-9 0.74 0.74 0.47 0.50 0.74 0.74 0.48 0.50 A-10, B-10 0.72 0.72 0.45 0.48 0.72 0.72 0.46 0.48 l
O 10.3-7
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
Table 10.3-4 Estimate of Annual Exposure for Operation and Surveillance of a Single PWR Cask Dose Rate Total Distance Frequency Time Dose Rate Personnel Exposure Activity (meters)
(days)
(min)
(mrem /hr)
Required (Pers-mrem)
Visual inspection 4
365 1
7.40 1
45.0 Radiological surveillance 4
4 15 7.40 1
7.4 Annualinspection Operations 1
1 15 25.30 1
6.3 Radiological Support 1
1 3
25.30 1
1.3 Grounds maintenance 10 26 15 1.76 1
11.4 Total Person-mrem 71.4 Table 103-5 Estimate of Annual Exposure for Operation and Surveillance of a 20 Cask Array of PWR Casks Dose Rate Total Distance Frequency Time Dose Rate Personnel Exposure Activity (meters)
(days)
(min)
(mrem /hr)
Required (Pers-mrem)
Visual inspection 4
365 1*
5.,8]
1 209.3 8
Radiological surveillance 4
4 60
[.83 1
@3.]
Annualinspection Operations 1
1 15W 47.91 1
239.6 Radiological Support 1
1 3m 47.91 1
47.9 Grounds maintenance 10 26 60
@.55 1
66.3
)
Total Person-mrem for the 20 Cask Array
[0_86.4 Total Person-mrem for a Single Cask in the Array gi0 (1) Time listed is per cask; it is multiplied by 20 for the cask array O
10.3-8
[SAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
Table 10.3-6 Estimate of Annual Exposure for the Operation and Surveillance of a Single BWR Cask Dose Rate Total Distance Frequency Time Dose Rate Personnel Exposure Activity (meters)
(days)
(min)
(mrem /hr)
Required (mrem)
Visualinspection 4
365 1
4.9 1
29.8 Radiological surveillance 4
4 15 4.9 1
4.9 Annual inspection Operations 1
1 15 15.2 1
3.8 Radiological Support 1
1 3
15.2 1
0.8 Grounds maintenance 10 26 15 1.16 1
7.5 Total Person-mrem 46.8 Table 10.3-7 Estimate of Annual Exposure for the Operation and Surveillance of a 20 Cask Array of BWR Casks Dose Rate Total Distance Frequency Time Dose Rate Personnel Exposure Activity (meters)
(days)
(min)
(mrem /hr)
Required (mrem)
Visualinspection 4
365 l'"
5 04 1
[9,1j5, l
Radiological surveillance 4
4 60
$0,4 1
16@
Annualinspection Operations 1
I 15(4 29.85 1
149.3 Radiological Support 1
1 3m 29.85 1
29.9 Grounds maintenance 10 26 60 ly I
ggg Total Person - mrem for the 20 Cask Array gg Total Person - mrem for a Single Cask in the Array
[73 (1) Time listed is per cask; it is multiplied by 20 for the cask array O
10.3-9
O THIS PAGE INTENTIONALLY LEFT BLANK O
O
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B fl V
10.4 Exposure to the Public The SKYSHINE Ill code is used to evaluate the placement of the controlled area boundary for a single cask containir; design basis fuel, and for a 20 cask array. For the 20 cask array, the casks are assumed to be loaded with design basis fuel at the rate of two casks per year. SKYSHINE III calculates dose rates for user defined detector locations for up to 100 point sources.
SKYSHINE-III creates an equivalent axial, and a radial, point source for each cask in the array of casks. The code is benchmarked by modeling a set of Kansas State University Co" skyshine experiments and by modeling two Kansas State University neutron computational benchmarks.
The code compares well with these benchmarks for both neutron and gamma doses versus distance.
The source distribution for neutron and gamma radiation are provided by the SASI [5] radial and axial shielding analysis for a reference PWR or BWR cask. The one-dimensional shielding analysis produces surface fluxes over the radial and axial surface of the vertical concrete cask.
The SASI produced fluxes are converted to equivalent point sources for use in the SKYSHINE
(]
Ill analysis. As stated in Section 10.3, the array cask murce strengths are multiplied by d
weighting factors to correct for the differences in cooling times that results from the assuruption of a loading rate of 2 casks per year. Skyshine dose rates are also adjusted to reflect the higher cask surface fluxes calculated by the SAS4 3-D shielding evaluation.
Exposures are determined at distances ranging from 100 to 300 meters surrounding a single PWR and BWR cash containing design basis fuel. The results are presented graphically in Figures 10.4-1
{
and 10.4-2, for the PWR or BWR single cask, respectively. The casks in the 2x10 array are assumed to be leaded at the rate of 2 per year with design basis PWR and BWR spent fuel, with credit taken for the cool time that occurs during the 10 year period that the ISFSI array is completed. The controlled area boundary, based on the 25 mrem / year limit, is calculated for the 2x10 atray based on superpositioning of single cask results. pccupanEMHtiMedlareaj E5dN3.slaMed alt]D,!0MilEFEeEMil.h,ighfpe_cupagc.yjaW5sEdiatW1 MEFEEr6E6MEMI33!aik~eliigafrgbrgirassaantmspramburnupj Table 10.4-1 presents a summary of the results of the SKYSHINE-III evaluation for single PWR and BWR cask containing design basis fuel. The results show that minimum distances from $j f'
jiiigl[e}isk to the site boundary of @l00 meters (PWR) and LOG meters (BWR) are required for i
10.4-1
@SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B l
compliance with the requirements of 10 CFR 72.104(a), i.e., a dose rate of 25 mrem / yea q
Table 10.4-2 results show that a site boundary of Q8) meters is required for a [EID PWR cask array to meet the 10 CFR 72.104(a) 25 mrem / year tequirement. The glifj BWR cask anay requires a minimum site boundary of Q65 meters to meet 10 CFR 72.104(a).
O O
10.4-2
{SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B p.)
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@SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Figure 10.4-1 Controlled Area Boundary Determination for a Single Cask Containing Design Basis BWR Fuel W, WW..c"MK, "*yy"W"W%KTY"W7;*~'#W*Tl""?"WWi"*?'WWQ. iQ. W.W. JW~lH_bau n
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10.4-4
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 10.4-1 Dose Versus Distance For a Single Cask x
Containing Design Basis PWR or BWR Fuel Detector PWR Cask Total BWR Cask Total Distance Dose Rate Dose Rate (Meters)
(mrem / year)
(mrem / year) 100 17,05) 12.7RA 110 13.651 80359 120 11003
$$l3 130 9.192 pgW 140 7.583
- N 150 6356 WB 160 5.35A 53 h 170 4.541 M M 180 3.87.1 Et98%
190 3.32?
R3tPt 200 2.86a S.254 210 2.48:
Rt9&tt 220 2.1.5:
1W0 230 1.87A 1495 240 1.63b to*1 250 1.43;;
R31si 260 1.26%
DB8%
270 l.'117 0.861 280 0.97; 0.761 290 0.86; 0.674 300 0.76i 0.604 310 0.68' O.53#
320 0.60:
0.4' 7a 330 0.53 >
DA2ft 340 0.48" 9.384 350 0.43t-0343 360 0.38:
030E 370 0.34:
0274 380 0.31:
p.244 390 0.274
- 0223, O
10.4-5
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 10.4-2 MtsfEfpTosu7re Fsm~aPM~~olBWIE2Tf0tisT@~y D,._etector;j P_WR. C..ask T_otale
.B_WR:C. a.s..k. J.o_ta_lf
.~
Distancel seLRarel DostERidei!
'MeidsN
[r$ rim / yen)1
[ mrem /yedN
(
300.00<
308.12i
$647it 125.002 64.454 51;.933 350.00i 40.97J B3:217 375.00c 27.'169 2246 200.001 18.56:
45.085 225.00.t 32,993 10:53R 250.00 g 9.29:s M04 275.003 6:72R 5A23 300.007 4.931 S.9 71!
S25.002 3.66?;
2.9.4:e 9
1 i
l l
O 10.4-6 l
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0
(]
List of Figures V
Figure 11.1.1-1 Concrete Temperature for Off-Normal Storage Condition 106*F Ambient Temperature (PWR Fuel).............................................. I 1.1 4 Figure 11.1.1-2 Vertical Concrete Cask Air Temperature Profile for Off-Normal Storage Condition 106'F Ambient Temperature (PWR Fuel).................. I 1.1-5 Figure 11.1.1-3 Concrete Temperature for Off-Nonnal Storage Condition -40 F l
{
Ambient Temperature (PWR Fuel)........
....I1.1-6 Figure 11.1.1-4 Vertical Concrete Cask Air Temperature Profile for Off-Normal Storage Condition -40 F Ambient Temperature (PWR Fuel).............. I 1.1-7 Figure 11.2.2-1 PWR Failed Canister Dose Rate Plot........................................ I 1.2-17 Figure 11.2.2-2 BWR Failed Canister Dose Rate Plot......
.............................. I 1.2-1 7 Figure 11.2.4-1 Canister Suppon Stand and Vent Structure....................................... I 1.2-35 Figure 11.2.8-1 Time Histories for the Fault Components....................................... I 1.2-61 Figure 11.2.8-2 3-D Beam / Mass / Interface Storage Cask Model............................ I 1.2-62 Figure 11.2.8-3 Additional Tip Angle (A$) Due to Stop for a Typical Case..............I1.2-63 Figure 11.2.8-4 Angle of Cask Diagonal (0,) After Stop Impact for a Typical Case.......... I 1.2-64
(
Figure 11.2.11-1 Principal Dimensions and Moment Arms Used in Tornado Evaluation.....
...................................................................... I 1.2-90 Figure 11.2.12-1 Finite Element Model of Cask...................................................... I 1.2-1 00 Figure 11.2.12-2 Concrete Crush Pattern.............................................................. I 1.2-101 Figure 11.2.12-3 Relative Displacement Of Cask End Points During Tip-Over (Case 1 )................................................................... I 1.2-1 Figure ! 1.2.12-4 Relative Displacement Of Cask End Points During Tip-Over (Case 2)...................................................................... I 1.2-103 Figure 11.2.12-5 Relative Displacement Of Cask End Points During Tip-Over (Case 2)...............
............................................. I 1. 2-1 04 Figure 11.2.13-1 PWR Configuration Temperature History-All Vents Blocked.........11.?.-l 12 Figure 11.2.13-2 BWR Configuration Temperature History-All Vents Blocked......... I 1.2 i 12 g'**
O l
11-v i
1 l
TSAR-UMSS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B h1 List of Tables Table 11.1.2-1 Component Temperatures (*F) for All Inlets and Outlets Half-Blocked oft-Normal Event............................................................ I 1.1 -10 Table 11.1.3-1 Canister Off-Normal Handling (No Intemal Pressure) Primary Membrane (P,) Stresses (ksi)............................................................ I 1.1 -14 Table 11.1.3-2 Canister Off-Normal Handling (No Intemal Pressure) Primary Membrane plus Bending (P + P ) Stresses (ksi)..............................I1.1-15 3
Table 11.1.3-3 Canister Off-Normal Handling plus Normal /Off-Normal Intemal Pressure (15 psig) Primary Membrane (P ) Stresses (ksi)....................... I 1.1-16 Table 11.1.3-4 Canister Off-Normal Handling plus Normal /Off-Normal Internal Pressure (15 psig) Primary Membrane plus Bending (P. + P )
3 Stresses (ksi)...........
.............. I 1.1 - 17 Table 11.1.3-5 Canister Off-Normal Handling plus Normal /Off-Normal Intemal Pressure (15 psig) Primary plus Secondary (P + Q) Stresses (ksi).......... I 1.1-l8 Table 11.1.3-6 P,+ P, Stresses for BWR Support Disk 20g End Impact, (T, = 516 F, T,s = 106 F)...........
.................................................I1.1-19 Table 11.1.3-7 P + P, + Q Stresses for BWR Support Disk 20g End Impact, h
(T., = 516 F, T,5 = 106 F)........................................................... I 1.1 - l 9 Table 11.1.3-8 P Stresses for BWR Support Disk-20g Side-Impact,90 Orientation, (T,j 40 F, T,[ 40 F)................................................... I 1.1 -20 Table 11.1.3-9 P, + P, Stresses for BWR Support Disk-20g Side Impact.
49.46 Orientation, (T,, [ 40 F, T,3 [ 40 F)........................................ I 1.1 -20 Table 11.1.3-10 P + P + Q Stresses for BWR Support Disk-20g Side Impact, 3
49.46 Orientation, (T,, = 600 F, T,5 = 150 F)................................... I 1.1 -21 Table 11.1.3-11 Canister Off-Normal Handling Loads-Basket Support Disks Stresses (ksi)
.......................................................I1.1-22 Table 11.1.3-12 Canister Off-Normal Handling Loads-Basket Weldments Stresses (ksi)... I 1.1-23 Table 11.2.2-1 Canister Accid 3ent Internal Pressure (65 psig) Only Primary
)
Membrane (P ) Stresses (ksi)....................................................... I 1.2-6 l
Table 11.2.1-2 Canister Accident Internal Pressure (65 psig) Only Primary Membrane plus Bending (P, + P ) Stresses (ksi).................................. I 1.2-7 3
Table 11.2.1-3 Canister Normal Handling plus Accident Internal Pressure (65 psig)
Primary Membrane (P,) Stresses (ksi)............................................ I 1.2-8 O
ll-vi
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 11.1.3 Off-Normal Canister Handline Load This section evaluates the consequence ofloads on the Transportable Storage Canister during the installation of the canister in the Vertical Concrete Cask, or removal of the canister from the concrete cask or from the transfer cask.
I1.1.3.1 Cause of Off-Normal Canister Handline Load Event Unintended loads could be applied to the canister due to misalignment or faulty crane operation, or inattention of the operators.
I1.1.3.2 Detection of oft-Normal Canister Handline Load Event The event can be detected visually during the handling of the canister, or banging or scraping noise associated with the canister movement. The event is expected to be obvious to the operators at the time of occurrence.
I1.1.3.3 Analysis of oft-Normal Canister Handline Load Event The canister structural analysis, including lifting loads, is performed by using an ANSYS finite element model. The model is described in Section 3.4.4.1. As discussed in that section, one finite element model was constructed to evaluate the canisters for both PWR and BWR fuel types by modeling the shortest canister (Class 1 PWR) with the heaviest fuel / fuel basket weight (Class 5 BWR ).
3 r
The off-normal canister handling loads are defined as 0.5g applied in all o
directions (i.e., in the global x, y, and 2 directions) in addition to a lg
%g,,
lifting load applied in the finite element model. The resulting of1 normal handling accelerations are 0.7071g in the horizontal directiot. and 059 y,
1.5g(0.5g + Ig) in the vertical direction.
G ),]
O 11.1-11
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B The resulting maximum canister stresses for off-normal handling loads are summarized in Tables 11.1.3-1 and 11.1.3-2 for primary membrane and primary membrane plus bending stresses, respectively.
3 The resulting maximum canister stresses for combined off-normal handling, maximum off-nonnal internal pressure (15 psig), and thermal stress loads are summarized in Tables 11.1.3-3, 11.1.3-4, and 11.1.3-5 for primary membrane, primary membrane plus bending, and primary plus secondary stresses, respectively.
The sectional stresses shown in Tables 11.1.3-1 through 11.1.3-5 at 16 axial locations are obtained for each angular division of the model (a total of 19 angular locations for each axial location). The locations of the stress sections are shown in Figure 3.4.4.1-4.
To determine the structural adequacy of the PWR and BWR fuel basket support disks and weldments for off-normal conditions, a structural analysis is performed by using ANSYS to evaluate off-normal handling loads (see Section 3.4.4.1.8.) To simulate off-normal loading conditions, a load amplification factor of 1.5g is applied to the support disk in the axial direction and 0.5g in two onhogonal horizontal directions (0.7071g resultant). For the weldments, a load factor of 1.5g is applied in the axial direction.
Stresses in the PWR support disk are calculated by applying the off-normal loads to the ANSYS jidi"sid[E63?dr5Bi5defii@iSid in Section 3.4.4.1.8.1. However, the BWR support disk results are scaled and combined from the p]6risalToiidiiidi5~of4 20g impact results for Q end and side impacts (see Tables 11.1.3-$ through 11.1.3-10). [fKe(boanconditippC(fj MH@ils aEWalidii~tliE~saftitpTdiljy'sjyponT6FiliED105TDniversalTransportci4
[3] Primary membrane (P,) and membrane plus bending (P, + P ) stress values are scaled by the 3
appropriate scale factor (1.5/20 for axid t.nd 0.7071/20 for side). Secondary stresses (Q) are not scaled, but added directly to the scaled values for P, + P,. The side and end impact loads are combined by adding the stresses together (see Table 11.1.3-11 for load combination). Stresses for the PWR and BWR weldmenu are scaled from the 20g end impact loads presented in Tables 3.4.4.1-13 and 3.4.4.1-14. Stresses for the support disks and weldments are summarized reported in Tables 11.1.3-11 and 11.1.3-12, respectively.
O 11.1-12
[SAR-UMS$ Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-978 O
The canisters and fuel baskets maintain positive margins of safety for the off-normal handling condition. There is no deterioration of canister or fuel basket performance. The Universal Storage System is in compliance with all applicable regulatory criteria.
11.1.3.4 Corrective Actions Operations should be halted until the cause of the misalignment, interference or faulty operation is identified and corrected. Since the radiation level of the canister sides and bottom is high, extreme caution should be exercised ifinspection of these surfaces is required.
I1.1.3.5 RadiolonicalImnact There are no radiological consequences associated with this off-normal event.
O 1
O 11.1-13
TSAR-UMS Universal Storege System August 1997 Docket No. 72-1015 Revision 0 0
Table 11.1.3-1 Canister Off-Nonnal Handling (No Internal Pressure) Primay Membrane (P )
Stresses (ksi)
Section No."'
Angle (degrees)
SX SY SZ SXY SYZ SXZ StressIntensity 1
0
-0.7 3.7 0.7 0.2 0
-0.1 4.47 2
0 3.2
-1.7
-2.3 0.1
-0.1
-0.5 5.59 3
0
-0.3 1.7
-3.5 1.3 0.1
-0.1 5.85 4
0
-0.1 0.8 0
0.1 0
0 0.91 5
0
-0.1 0.8 0
0 0
0 0.85 6
0
-0.1 0.8 0
0 0
0 0.91 7
0
-0.1 0.9 0
0 0
0 1.08 8
0 0
1.9 0
0 0.2 0
1.95 9
0 0.4 2.8 0.7 0.2 0.3 0
2.46 10 0
-0.6 3.4 0.4 0.3 0.4 0.1 4.11 11 0
-0.6 2.5 1.1
-0.7 0.4 0
3.45 12 0
0 4
0.9 0.4 0.2 0.1 4.03 13 0
-2.3
-0.2 1.2
-1.6 0.1 0.1 4.44 14 80 0.2 0
0.3 0.3
-0.2 0
0.86 15 160 0
0 0
0 0
0 0.01 16 180 0
0 0
0 0
0 0.09
"' See Figure 3.4.4.1-4 for definition oflocations and angles of stress sections.
O 11.1-14 1
lSAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B OV Table 11.1.3-[ P,+ P Stresses for BWR Support Disk 20g End Impact l (T., = 516*F, T, = 106'F) oi Principal Stresses Da0 Stress Node S1 S2 S3 Intensity 86 25.6 0.0
-1.0 26.6 474 32.5 2.1 0.0 32.5 1129 29.9 1.5 0.0 29.9 1444 32.5 2.1 0.0 32.5 1564 25.6 0.0
-1.0 26.6 2236 29.9 1.5 0.0 29.9 2558 32.5 2.1 0.0 32.5 2680 25.6 0.0
-1.0 26.6 3332 29.9 1.5 0.0 29.9 3647 32.5 2.1 0.0 32.5 3765 25.6 0.0
-1.0 26.6 4407 29.9 1.46 0.0 29.9
!.ggefor to Table 2.6.15Ag_UMS C, dTif __ ^^^ ~"*WJ m
O Table 11.1.3-7 P, + P, + Q Stresses for BWR Support Disk 20g End Impact]
(T, = 516*F, T,i,, = 106'F)
Principal Stresses (ksi)
Stress Node SI S2 S3 Intensity 474 52.7 7.2 0.0 52.7 481 35.0 0.0
-3.1 38.1 1129 40.3 3.6 0.0 40.3 1444 52.7 7.2 0.0 52.7 1451 35.0 0.0
-3.1 38.1 2236 40.3 3.6 0.0 40.3 2558 52.7 7.2 0.0 52.7 2565 B5.0 0.0
-3.1 38.1 3332 40.3 3.6 0.0 40.3 3647 52.7 7.2 0.0 52.7 3654 35.0 0.0
-3.1 38.1 4407 40.3 3.6 0.0 40.3 k.Rafe!rtoTablel2.6.15.E1LU_MSIA_ 2?:._ rikskRQJ O
11.1-19
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 11.1.3-) P, Stresses for BWR Support Disk-20g Side-Impact,90* Orientation, (T,, = [ 40*F, T., = [ 40 F)
' Point 1")
Point 2")
Sx Sy Sxy Stress Intensity (ksi)
)
53 54
-13.3 14.2
.0 27.4 153 154
-8.3 13.5 3.1 22.7 537 538
-8.3 13.5
-3.1 22.7 169 170
-6.5 12.7 1.2 19.4 553 554
-6.5 12.7
-1.2 19.4 57 58
-19.3
.1
.0 19.3 47 48
-11.3 7.3
.0 18.5 545 546
.1 17.4
.4 17.4 161 162
.1 17.4
.4 17.4 55 56
-16.0
.9
.0 16.9 51 52
-16.0
.2
.0 16.6 11 12
-11.0
-10.3
-5.9 16.5
") See Figures 3.4.4.1-13 through -16 for point locations and stress sections.
Table 11.1.3-y P, + P, Stresses for BWR Suppon Disk-20g Side Impact,49.46 g
Orientation, (T, = [ 40 F, T., = [ 40 F)
Point 1")
Point 2 '
Sx Sy Sxy Stress Intensity (ksi) 0 549 550
-30.2
-36.7 6.3 40.6 535 536
-31.7
-32.7 7.2 39.4 481 482
-33.4
-33.1 5.8 39.0 547 548
-29.8
-35.1 6.0 39.0 533 534
-30.3
-34.9 5.8 38.8 589 590
-10.8
-36.1 8.4 38.6 475 476
-32.7
-32.0 5.5 37.9 491 492
-35.4
-11.8 7.9 37.7 485 486
-36.6
-20.6 4.4 37.7 551 552
-25.6
-34.8 5.7 37.6 537 538
-26.3
-30.2 9.1 37.5 7
8
-35.6
-28.0 4.3 37.5
") See Figures 3.4.4.1-13 through -16 for point locations and stress sections e
11.1-20
[SAR-UMS Universal Storage System Docket No. 72-1015 April 1998 Revision UMSS-978
.Q V
Table 11.1.3-10 P, + P, + Q Stresses for BWR Support Disk-20g Side Impact, 49.46' Orientation,(Tg 600 F, T = 150'F)
Point 1"3 Point 2")
Sx Sy Sxy Stress Intensity (ksi) 47 48
-38.6
-38.5 18.2 56.8 535 536
-38.6
-38.5 18.2 56.8 533 534
-37.6
-38.9 17.7 56.0 41 42
-37.6
-38.9 17.7 56.0 475 476
-37.1
-39.8 16.1 54.6 547 548
-37.1
-39.8 16.1 54.6 481 482
-37.1
-39.8 15.8 54.3 549 550
-37.1
-39.8 15.8 54.3 35 36
-34.8
-38.9 16.9 53.9 531 532
-34.8
-38.9 16.9 53.9 53 54
-35.5
-35.4 17.3 52.8 lo See Figures 3.4.4.1-13 through -16 for point locations and stress sections O
11.1-21
[SAR-UMS" Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 11.1.3-11 Canister Off-Normal Handling Loads-Basket Support Disks Stresses (ksi)
Disk Irnpact Stress Si at 20g Acceleration SI Allowable Allowable Margin of Type Orientation Evaluated (ksi)
(g)
(ksi) Criteria (ksi)
Safety PWR*
Resultant P.
N/A 1.5 (z) and 0.5 gb S
83.6 pl.9j y
(xy)
Resultant P,+ P, N/A 1.5 (z) and 0.5 2R 1.8 S.
75.4 28A"1 (xy)
Resultant P,+ P,+Q N/A 1.5 (z) and 0.5 LOM 3.0 S.
125.7
)];6]
(xy)
BWR" End P,
0.0 1.5 0.0 End P,+ P, 32.5 1.5 2.4 End P +P,+Q Q=20.2"
- 1.5 22.6
)
Side (90.0)
P.
27.4 0.7071 1.0 Side (49.46)
P +P, 40.6 0.7071 1.4 Side (49.46)
P +P +Q Q= 16.2 * "
0.7071 17.6 Resultant P.
End + Side 1.0 S,
59.3 583 Resultant P,+ P, End + Side 3.8 1.8 S.
52.4 12.8 Resultant P + P,+Q End + Side 40.2 3.0S.
87.0 1.16
' Allowable temperature taken at 650 F
" Allowable temperature taken at 750*F
- Value -(Pm+P +Q)-(Pm+P ) then added to the scaled Pm+P stress (see Tables ll.l.3M through 11.1.33).
b b
b O
O 11.1-22
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B O
Table 11.1.3-)2 Canister Off-Normal Handling Loads-Basket Weldments Stresses (ksi)
Weldment impact Stress Si at 20g Si at 1.5g Allowable Allowable Margin of Location Orientation Evaluated (ksi)
(ksi)
Criteria (ksi)*
Safety PWR Top End P,
h88;i 0.13j S,
$8.73 Large End P +P.
- t.54]
p,193 1.8 S, 26g Esge End P +P.+Q Q=32.87 * *
$3.061 3.0 S.
46.8 0.4 PWR Bottom End P,
3.52 0.27 S,
)8.71,
$8.3J End P,+P.
M.33 0.32 1.8 S.
$@]
$0.33 End P,+P +Q Q=30.94"
$13il 3.0S.
46.8 0.5)
BWR Top End P,
).99 0.30 S,
gg.t S.33 End P + P.
)6:30
))i!
1.8 S.
RQJ B0.1)]
End P,+P +Q Q=0.45" 13 3.0S, 46.8 26;71 BWR Bottom End P.
J1;14 p14j S,
SJD Sp3 End P,+ P.
18.98 JMj 1.8 S.
M
$74%
End P,+ P.+Q Q=8.28" 9301 3.0S.
46.8
).81
' Allowable temperature taken at 750*F
- Value = (P,+P.+Q)-(P,,,+P.) then added to the scaled Pm+P stress (see Tables 3.4.4.1-13 and 3.4.4.1 14) b O
O 11.1-23
TSAR-UMSC Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B 11.1.4 Failure ofInstrumentation The Universal Storage System uses an electronic temperature sensing system to read and record the outlet air temperature at each of the four air outlets on each Vertical Concrete Cask. The temperatures are recorded during daily inspections of the ISFSI.
I1.1.4.1 Cause ofInstrumentation Failure Event Failure of the temperature measuring instrumentation could occur as a result of component failure, or as a result of another accident condition that interrupted power or damaged the sensing or reader terminals.
I1.1.4.2 Detection ofInstrumentation Failure Event The failure is expected to be identified by the lack of a reading at the temperature reader terminal. The failure could also be identified by disparities between outlet temperatures in a cask g
or between similar casks.
11.1.4.3 Analysis ofInstmmentation Failure l
Since the temperature of each outlet of each concrete cask is recorded daily (see Section j
12.2.1.2), the maximum time period during which the instrumentation failure may go undetected is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Therefore, the maximum time period during which an increase in the outlet air temperatures may go undetected is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The principal condition that could cause an increase in temperature is the blockage of the cooling air inlets or outlets. Section 11.2.13 shows that even if all of the inlets and outlets of a single cask are blocked immediately after a temperature measurement, it would take longer than B'diyi before any component approaches its allowable temperature limit. Therefore, the opportunity exists to identify and correct a defect prior to reaching the temperature limits. During the period of loss of instrumentation, no significant change in canister temperature will occur under normal conditions.
The purpose of the daily inspection is to ensure that the inlets and outlets are not obstructed such that the cooling efficiency of the system is reduced. Instrument failure would be of no consequence, if the affected storage cask continued to operate in normal storage conditions.
I1.1-24 I
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 Figure 11.2.41 Canister Support Stand and Vent Structure 72.0in.
~
'~,w
/
4 -20.2 inn, j
\\
' C.D-*
%/
<f f
=
2.0 in.
17.4 in/
4 e.o in. _
s' D
\\
N O
11.2-35 1
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 11.2.4-1 Maximum Canister Stresses During 60g Bottom Impact (25 Psig Internal Pressure)
Section*
Impact Acceleration Stress SI Allowable Allowable Margin of (Angle)
Orientation (g)
Evaluated (ksi)
Criteria (ksi)*
- Safety 4(180)
End 60 P,,,
7.9 0.7 S, 40.5 4.1 2(180)
End 60 P,,,+ P,,
10.9 1.05 S, 60.7 4.6
- Section locations given in Figure 3.4.4.1-4
- Allowable temperature taken at 500*F l
1 Table 11.2.4-2 Fuel Basket Suppon Disks-Accident Conditions Disk Impact Acceleration Stress SI Allowable Allowable Margin of Type Orientation (g)
Evaluated (ksi)
Criteria (ksi)
Safety PWR*
End p0j P.
p.07 0.7 S, 89.9 f!A End 603 P,+P,,
23:45 1.05 S, 134.9
,4i76 B WR*
- End 55 Pm 0.0 0.7 S, 61.0 N!4 i
End 55 P,,,+Ps 88.4 1.05 S, 91.6 0.04
- allowable temperature taken at 500*F (actual temperature < 500'F)
- allowable temperature taken at 750*F l
I l
O i
11.2-36
[SAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B Table 11.2.4-3 Fuel Basket Weldments-Accident Conditions Weldment Impact Acceleration Stress SI Allowable Allowable Margin of Location Orientation (g)
Evaluated (ksi)
Criteria (ksi)*
Safety PWR Bottom End 60 P,
0.7 S, 44.2 3.1 End 60 P,,, + P 1.05 S.
66.3 4.1 3
BWR Bottom End 60 Pm 0.7 S, 44.2 D2 End 60 P, + P, 1.05 S, 66.3 0.17
- allowable temperature taken at 750*F a
O 11.2-37
l TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 g
11.2.5 Explosion The analysis of a design basis flood presented in Section 11.2.9 shows that the flood exerts a pressure of 22 psig on the canister, and that the Universal Storage System experiences no adverse effects due to this pressure. The pressure of 22 psig is considered to bound any pressure due to an explosion occurring in the vicinity of the ISFSI.
I1.2.5.1 Cause of Explosion An explosion affecting the Universal Storage System may be caused by industrial accidents or the presence of explosive substances in the vicinity of the ISFSI. However, no flammable or explosive substances are stored or used at the storage facility. In addition, site administrative controls exclude explosive substances in the vicinity of the ISFSI. Therefore, an explosion affecting the site is extremely unlikely. This accident is evaluated in order to orovide a bounding pressure that could be used in the event that the potential of an explosion must be considered at a given site.
I1.2.5.2 Analysis of Explosian
}
l Pressure due to an explosion event is bounded by the pressure effects of a flood having a depth of 50 feet. The Transportable Storage Canister shell is evaluated in Section 11.2.9 for the effects of the flood having a depth of 50 feet, and the results are summarized in Tables 11.2.9-1 and 11.2.9-2.
l There is no adverse consequence to the canister as a result of the 22 psig pressure exerted by a design basis flood. This pressure conservatively bounds an explosion event.
I1.2.5.3 Corrective Actions In the unlikely event of a nearby explosion, inspection of the concrete casks is required to ensure that the air inlets and outlets are free of debris, and to ensure that the monitoring system and i
\\
screens are intact. No further recovery or corrective actions are required for this accident.
I1.2.5.4 RadiolocicalImpact I
There are no radiological consequences for this accident.
I1.2-38
TSAR-UMS" Universal Storage System August 1997 Docket No. 72-1015 Revision 0 O
E, = [ U, x F,,
where, E, is the summation of the crush energy over the COMBIN40 elements, Ui the distance (in) that COMBIN40 element has " slid" or the clastic deformation (prior
=
to exceeding the compressive strength), and F,
compressive force (Ibf) of the i* element which represent the reaction of the concrete to
=
the cask. Only those elements corresponding to the elements which are closed exhibit
" sliding action" or elements which have a compressive load smaller than the compressive strength of the concrete (lbf). This force cannot exceed the force corresponding the compressive strength.
The analysis continues until the E, equals the total potential energy. As the cask moves into the concrete, the product of the cask weight and the extra downward displacement of the CG is added to the potential energy, therefore, the potential energy term increases.
Maximum Accelerations Durine Cask Tio Over The acceleration of the top end of the canister is computed by the product of the angular acceleration and the distance from point of rotation to the top of the canister plus 386.4 in/sec.
2 The angular acceleration, a, at any time is computed by considering the dynamic equilibrium of i
the cask, I, a = [ r, x F, - W x r,,
)
where, the summation considers only the COMBIN40 elements, l
I,
= moment ofinertia of the cask about the point of the rotation (Ibf-in-sec ),
2 r,
moment arm from the point of rotation to the i* COMBIN40 element (in),
=
O i1.2-95
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B compressive force of the i* element which represent the teaction of the concrete to the g F,
=
cask. Only those elements corresponding to the elements which are closed and exhibit
" sliding action" or elements which have a compressive load smaller than the compressive strength of the concrete (lbf),
W weight of cask (Ibf), and
=
r,,
distance from point of rotation to the CG (in).
=
The maximum accelerations of the canister for Case 1 and Case 2 are 51.2 and 57.9 g, respectively. The loads generated by these accelerations are bounded by the loads developed in the hypothetical accident 60 g side impact analyses [oitlieWKUdivenialTriiidMCask safel Eljyyp6dJ3]l Axial Acceleration of Canister Durine Cask Tin-Over Accident As the cask. accelerates during tip-over, an axial acceleration is developed that may allow the canister to apply a force against the cask lid. The axial acceleration is calculated as length times h
m,2, where m, is the angular velocity. In this calculation, the cask begins the tip-over accident with no initial angular velocity. The maximum value occurs at the beginning of the impact of the cask onto the storage pad. For the worst case cask configuration shown above, the angular velocity is 2(dr + h -r)W 0.156 rad 2
2 m,
I,,
see
- where, h
116.0 in., the axial distance from the base of the VCC to the CG,
=
68.0 in., the radius of the cask, r
=
l W
320,000 lb, the weight of the cask,
=
1.75 x 10'lbm-in.2 (from the solid model)
I,,
=
11.2-96
[SAR-UMS* Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B
(
Table 11.2.12-3 Maximum Canister Stresses During 60g Side Impact (25 Psig Internal Pressure)
Section*
Impact Acceleration Stress SI Allowable Allowable Margin of (Angle)
Orientation (g)
Evaluated (ksi)
Criteria (ksi)*
- Safety 12(0)* *
- Side 60 P.
39.3 0.7 Su 40.5 0.03 12(0)* *
- Side 60 P,+P, 45.1 1.05 Su 60.7 0.3 l
- Section locations given in Figure 3.4.4.1-4 l
" Allowable temperature taken at 500*F l
"' Side drop with basket oriented at 45 degrees from horizontal l
Table 11.2.12-4 Fuel Basket Support Disks-Accident Conditions l
Disk Impact Acceleration Stress S1 Allowable Allowable Margin of Type Orientation (g)
Evaluated (ksi)
Criteria (ksi)
Safety PWR*
Side 60 P,
$1.6]
0.7 Su 89.9 131 6 ]
Side 60 P +P, 105.6-1.05 Su 134.9
).284 B WR *
- Side 60 P,
56.4 0.7 Su 61.0 0.08 Side 60 P,+ P, 78.6 1.05 Su 91.6 0.17
- allowable temperature taken at 500'F (actual temperature < 500*F) m(J
" allowable temperature taken at 750*F 2
11.2-109
TSAR-UMS Universal Storage System August 1997 Docket No. 72-1015 Revision 0 11.2.13 Full Blockace of Cask Air inlets and Outlets This section evaluates the Vertical Concrete Cask for the steady state effects of full blockage of the air inlets and outlets at the normal ambient temperature (76 F). It estimates the duration of the event that results in the fuel cladding and the concrete reaching their design basis limiting temperatures (1058 F for the fuel cladding and 350 F for the concrete).
The evaluation demonstrates that there are no adverse consequences due to this accident, provided that debris is cleared within about 6 days (fewer than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> for a canister containing design-basis fuel). The maximum fuel cladding temperature and the maximum concrete bulk temperature remain less than the allowable temperatures for approximately 6 days (150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />) after the initiation of the event.
11.2.13.1 Cause of Full Blockace The likely cause of complete cask air inlet and outlet blockage is the covuing of the cask with earth in a catastrophic event that is significantly greater than the design basis earthquake or a land slide. This event is a bounding condition accident and is not credible.
h 11.2.13.2 Detection of Full Blockace Blockage of the cask air inlets and outlets will be visually detected during the general site inspection following an earthquake, land slide, or other events with a potential for such blockage.
I1.2.13.3 Analysis of Full Blockace The accident temperature conditions are evaluated using the thermal models described in Section 4.4.1. The analysis assumes initial normal storage conditions, with the sudden loss of convective cooling of the canister. Heat is then rejected from the canister to the Vertical Concrete Cask liner by radiation and conduction. The loss of convective cooling results in the fairly rapid and sustained heat-up of the canister and the concrete cask. To account for the loss of convective cooling in the ANSYS air flow model (Section 4.4.1.1), the elements in the model are replaced with thermal conduction elements. This model is used to evaluate the thermal transient resulting from the postulated boundary conditions. The analysis indicates that the maximum fuel cladding temperature and the maximum concrete bulk temperature remain less than the allowable 11.2-110
1
[SAR-UMS Universal Storage System April 1998 Docket No. 72-1015 Revision UMSS-97B r'~]
11.3 References LJ 1.
ANSI /ANS-57.9-1992, " Design Criteria for an Independent Spent Fuel Storage Installation f
(Dry Type)," American Nuclear Society, May 1992.
2.
Code of Federal Regulations, " Packaging and Transportation of Radioactive Materials,"
Part 71, Title 10, April 1996.
3.
NAC Document No. EA790-SAR-001, " Safety Analysis Repon for the UMSm Universal Transport Cask,"O Docket No. 71-9270[.
4.
Code of Federal Regulations, " Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste," Part 72, Title 10, January 1996.
5.
Olander, D.R., " Fundamental Aspects of Nuclear Reactor Fuel Elements," U.S. Department of Energy Technical Information Center,1985.
6.
NRC, " Standard Review Plan for Dry Cask Storage Systems," NUREG-1536, Final Report, January 1997.
l j
i 7.
EPA Federal Guidance Report No.11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation. Submersion and Ingestion,
(
)
1988.
8.
EPA Federal Guidance Report No.12, Extemal Exposure to Radionuclides in Air, Water and Soil,1993.
9.
NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I, 1977 10.
CFR Part 20, " Standards for Protection Against Radiation," 1993.
I 1.
NRC Regulatory Guide 8.34," Monitoring Criteria and Methods to Calculate Occupational Radiation Doses",1992.
12.
NRC Regulatory Guide 1.25, Assumptions Used for the Potential Radiological consequences of a Fuel Handling Accident and Storage Facility for Boiling and Pressurized Water Reactors,1972.
13.
Nuclear Regulatory Commission, " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants," Regulatory Guide 1.145, September 1980.
I1.3-1
[SAR-UMS Universal Storage System April 1998 i
Docket No. 72-1015 Revision UMSS-97B O
14.
$XNDg%21g(%~riiili6ii"XiicidenTS5iin7anf(C5ifimerclif*Siijfii fg$iiiidilii l@tional:G%eiesfebmarylf981.
15.
NRC, " Standard Review Plan for Dry Cask Storage Systems," Draft NUREG-1536, February 1996.
16.
Kreith & Bohn, Principles of Heat Transfer, 5* Edition, West Publishing Company, St.
Paul, Min'iesota,1993.
17.
Regulatory Guide 1.60, " Design Response Spectra for Seismic Design of Nuclear Power Plants," Revision 1, December 1973.
18.
ANSYS Revision 5.2, Computer Program, ANSYS,Inc., Houston, Pennsylvania.
19.
Blevins, R.D., Formulas for Natural Frequency and Mode Shape, Robert E. Krieger Publishing Co., Inc., Malabar, Florida,1979.
20.
" Topical Safety Analysis Report for the NAC Storable Transpon Cask for use at an Independent Spent-Fuel Storage Installation," NAC-T-90002, Revision 3, NAC Services, Inc., Norcross, Georgia, July 1994.
21.
Funk, R. " Shear Friction Transfer Mechanisms for Supports Attached to Concrete,"
American Concrete International Journal, Volume 11, No. 7, pp 53-58, July,1989.
22.
NRC, "Three Components of Earthquake Motion.", NUREG-0800, Revision 1, Section 3.7.2, Subsection II.6.
23.
" Steel to Concrete Coefficient of Friction, Preliminary Tests," Repon No. CEB 77-46, Tennessee Valley Authority, Knoxville, Tennessee, December 1977.
24.
Roberson, J.A. and C.T. Crowe, (1975). " Engineering Fluid Mechanics," Houghton Mifflin z
Co., Boston, Massachusetts.
25.
Cianos, N., and E.T. Pierce, "A Ground Lightning Environment for Engineering Usage,'
Technical Report No.1, Stanford Research Institute, Menlo Park, California, Contract No.
LS-2817-A3, SRI Project No.1834, August 1972.
4 26.
Summer, W.I., "American Electrician's Handbook," 10* Edition, McGraw-Hill, Inc., New York,1981.
27.
Fink, D.G., and Beaty, W. H., " Standard Handbook for Electrical Engineers'" 13*
Edition, McGraw-Hill, Inc., New York,1993.
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UNIVERSAL MPC SYSTEM SAFETY ANALYSIS REPORT for the UMS" UniversalTransport Cask
EA790-SAR-001 a
0 EMS UNIVERSAL MPC S Y S T E M*
SAFETY
~
ANALYSIS o
REPORT for the UMS UniversalTransport Cask Mr.E!E M O
NAC is-ERNK ONA_
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B I
l List of Effective Pages Table of Contents 1.1-2............. Revision M 1.1-3............. Revision M i................................. Revi si on 0 1.1 -4............................... Revision 0 ii................................... Revision 0 1.1 -5............................... Revision 0 1ii.................................... Revision 0 1.2-1............. Revision M iv................................ Revision 0 1.2-2............................. Revision 0 i
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SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B List of Effective Pages (continued)
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SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B p
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SAR - UMS" Universal Tram, port Cask April 1997 Docket No. 71-9270 Revision 0 f
Table of Contents (Continued) 2.6.5 Vibration.................................................................................................
2.6.6 Water Spray.................................................................................................. 2. 6-2 5 2.6.7.
Free Drop (1-Foot): Cask Body Analysis..................................................... 2.6-26 2.6.7.1 Or.e-Foot End Drop...................................................................... 2.6-27 2.6.7.2 One-Foot S ide Drop..................................................................... 2.6-40 2.6.7.3 One-Foot Corner Drop................................................................. 2.6-47 2.6.7.4 One-Foot Oblique Drop................................................................ 2.6-60 2.6.7.5 Impact Limiters............................................................................ 2.6-61 2.6.7.6 Closure Analysis......................................................................... 2.6-1 12 2.6.7.7 Neutron Shield Analysis............................................................. 2.6-1 16 2.6.7.8 Upper Ring / Outer Shell Intersection Analysis........................... 2.6-128 2.6.8 Corner Drop for Small Packages................................................................ 2.6-13 2 2.6.9 Compre s s i o n.............................................................................................. 2.6-1 3 2 2.6.10 Pe netrati on..............................................................................................
2.6.11 Fabrication Stresses.................................................................................... 2.6-13 3 r
2.6.11.1 L ead Po ur.................................................................................. 2. 6-2.6.11.2 Coo l do wn................................................................................... 2. 6-2.6.11.3 Lead C reep............................................................................... 2.6-13 9 2.6.12 PWR Transportable Storage Canister Analysi; Normal Conditions of Transport............................................................................ 2.6-143 2.6.12.1 Analysis Description................................................................. 2.6-14 3 2.6.12.2 Finite Element Model Description-PWR Canister................. 2.6-146 2.6.12.3 Thermal Expansion and Thermal Stresses Evaluation of Canister for PWR Fuel......................................... 2.6-154 I
2.6.12.4 Stress Evaluation of PWR Canister for 1-Foot End-Drop Load Con d it i o n.................................................................................. 2. 6-1 60 2.6.12.5 Stress Evaluation of PWR Canister for Combined Thermal and I
1 -Foot End-Drop Load Condition.............................................. 2.6-168 2.6.12.6 Stress Evaluation of PWR Canister for 1-Foot Side-Drop Load Co nd it i o n................................................................................... 2. 6-
\\
2.6.12.7 Stress Evaluation of PWR Canister for Combined Thermal and 1 -Foot Side-Drop Load Condition....................................... 2.6-179 2-iii
SAR - UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B Table of Contents (Continued) 2.6.12.8 Stress Evaluation of PWR Canister for 1-Foot Corner-Drop Lo ad Conditio n................................................................. 2.6-1 8 3 2.6.12.9 Stress Evaluation of PWR Canister for Combined Thermal and 1-Foot Corner-Drop Load Condition................................. 2.6-189 2.6.12.10 Shear Stresses for 1-Foot Drops.......................................... 2.6-195 2.6.12.11 Canister Bearing Stresses for 1-Foot Side-Drop........................ 2.6-195 2.6.12.12 Canister Buckling Evaluation for 1-Foot End-Drop............... 2.6-197 2.6.13 PWR Basket Analysis-Normal Conditions of Transport........................ 2.6-201 2.6.13.1 Analysis Description...................................................... 2.6-205 2.6.13.2 Finite Element Model Description - PWR Basket.................... 2.6-205 2.6.13.3 Thermal Conditions and Expansion Evaluation for PWR S upport D isks......................................................... 2.6-E 2.6.13.4 Stress Evaluation of PWR Suppon Disks for 1-Foot End-Drop Load Condition......
.. 2.6-E 2.6.13.5 Stress Evaluation of PWR Suppen Disk for Combined Thermal and 1 -Foot End-Drop Conditions............................................... 2.6-E 2.6.13.6 Stress Evaluation of PWR Suppon Disk for 1-Foot Side Drop Load Conditi ons................................................................... 2. 6-H 2.6.13.7 Stress Evaluation of PWR Support Disk for Combined Thermal and 1-Foot Side Drop Load Conditions.............................. 2.6-E 2.6.13.8 Stress Evaluation of PWR Support Disk for 1-Foot E-M Load Con d i ti ons.......................................................... 2.6-M 2.6.13.9 Stress Evaluation of Support Disk for Combined Thermal l
and 1 -Foot Off'ASTe Conditions........................................... 2.6-N d l
2.6.13.10 Stress Evaluation of Tie Rods and Spacers for 1-Foot End-Drop Load Condition....................................................... 2.6-E 2.6.13.11 Support Disk Shear Stresses for 1-Foot Drops......................... 2.6-E 2.6.13.12 Bearing Stress - Basket Contact with 05EliElfr Shell...... 2.6-E 2.6.13.13 Basket Weldment Analysis for 1-foot End-Drop........
........ 2.6-E 2.6.13.14 Support Disk Buckling Evaluation...
.................................2.6@
i l
O 2-iv 1
l l
i SAR - UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B i
I Table of Contents (Continued) 2.7.2.5 Puncture Accident - Shielding Consequences............................ 2.7-57 2.7.3 Thermal
.......................................................................................2.7-58 2.7.3.1 Summary of Pressures and Temperatures....................................... 2.7-58 2.7.3.2 DifTerential Thermal Expansion Stress.................................. 2-7-58 2.7.4 Crush 2.7-62 2.7.5 Immersion--Fissile Material............................................................ 2.7-62 2.7.6 Immersion-All Packages........
......................................................2.7-62 2.7.6.1 Membrane Stresses in Cask Outer Shell (away from ends)............ 2.7-65 2.7.6.2 Bending Stress in the Bottom Forging (at center)......................... 2.7-65 2.7.6.3 Bending Stress in the Cask Lid (at center)................................ 2.7-66 2.7.6.4 Bending Stress in the Cask Bottom (at center)........................... 2.7-6 6 2.7.6.5 Bending Stress in the Port Cover Plate (at center)............................ 2.7-67 2.7.7 PWR Transportable Storage Canister Analysis-Accident Conditions....... 2.7-69 2.7.7.1 Analysis Description..
........................................................2.7-70 2.7.7.2 Analysis Results - PWR Canister....................................... 2.7-70 2.7.7.3 Canister Buckling Evaluation for 30-Foot End Drop............... 2.7-84 gV 2.7.8 PWR Basket Analysis-Accident Conditions....................................... 2.7-87 2.7.8.1 Stress Evaluation of Support Disk........................................... 2.7-87 2.7.8.2 Stress Evaluation of Tie Rods and Spacers........................... 2.7-107
{
2.7.8.3 Buckling Evaluation of Support Disk................................... 2.7-!Td 2.7.8.4 Fuel Tube Analysis....
...........................................2.7-118 2.7.8.5
' Basket Weldment Analysis for 30-Foot End Drop.................. 2.7-123 I
2.7.9 BWR Transportable Storage Canister Analysis-Accident Conditions... 2.7-127 1
2.7.9.1 Analysis Description.............
.......................... 2.7-12 8 2.7.9.2 Analysis Results - BWR Canister.............................. 2.7-128 2.7.9.3 Canister Buckling Evaluation for 30-Foot End Drop............. 2.7-142 2.7.10 BWR Basket Analysis-Accident Conditions................................... 2.7-144 2.7.10.1 Stress Evaluation of Support Disk...............
............... 2.7-14 5 2.7.10.2 Stress Evaluation of Tie Rods and Spacers........................ 2.7-172 2.7.10.3 Buckling Evaluation of Support Disk.
............. 2.7-174 2.7.10.4 Fuel Tube Analysis.......
.. 2.7-180 2.7.10.5 Basket Weldment Analysis for 30-Foot End-Drop............. 2.7-185 O
v 2-vii
SAR-UMS* Universal Transport Cask April 1997 Dock t No. 71-9270 Revision 0 Table of Contents (Continued) h 2.7.11 Summary of Damage to Cask Due to Hypothetical Accident Conditions.. 2.7-189
)
2.7.12 Cask Inner Shell Buckling Analysis........................................................... 2.7-192 2.7.12.1 Analysis Methodology............................................................... 2.7-192 2.7.12.2 Analysis Results.................................................................... 2.7-193 2.7.12.3 Detailed Code Case N-284-1 Buckling Evaluation.................... 2.7-193 2.8 S pe c ial Fo rm................................................................................................................
2.9 FuelRods...................................................................................................................2.9-1 2.10 Appen di ce s............................................................................................................ 2.1 2.10.1 Computer Program Description................................................................... 2.10- 1 2.10.1.1 ANSYS.....................................................................................2.10-1 2.10.1.2 RB C UB E D................................................................................ 2.1 0-2 2.10.2 Finite Element Model - Universal Transport Cask....................................... 2.10-4 2.10.2.1 Load Application and Boundary Conditions................................ 2.10-8 2.10.2.2 Post-processing o f Results........................................................ 2.10-16 2.10.l Re fe re n c es....................................................................................... 2.1 0-22O O
2-viii
SAR-UMS Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 sJ' List of Figures Figure 2.5.1.1-1 Primary Lifling Tmnnion Geometry..................................................... 2.5-27 Figure 2.5.1.1-2 Secondary Lifling Trunnion Geometry................................................. 2.5-28 Figure 2.5.2.1-1 Front Support and Tiedown Geometry.................................................. 2.5-3 7 Figure 2.5.2.1-2 Shear Ring Geometry............................................................................ 2. 5 -3 8 Figure 2.5.2.1-3 Free-Body Diagram of Cask Subjected to Lateral Load........................ 2.5-39 Figure 2.6.7.5-1 Universal Transport Cask with Impact Limiters................................... 2.6-88 Figure 2.6.7.5-2 Cross Section of Lower Impact Limiter................................................ 2.6-89 Figure 2.6.7.5-3 Crush Stress-Strain Curves for Redwood (Crush Strength Parallel to Grain)........................................................ 2.6-90 Figure 2.6.7.5-4 Crush Stress-Strain Curves for Redwood j
(Crush Strength Perpendicular to Grain)............................................... 2.6-91 Figure 2.6.7.5-5 Cmsh Stress-Strain Curves for Balsa Wood (Crush Strength Parallel to Grain)......................................................... 2.6-92 Figure 2.6.7.5-6 Variation of Crush Strength of Redwood and Balsa Wood with Impact Angle at 40 Percent Strain............................ 2.6-93 r
(
Figure 2.6.7.5-7 Cask Side-Drop G eometry................................................................... 2.6-94 Figure 2.6.7.5 8 Cask End-Drop Geometry................................................................... 2.6-95 Figure 2.6.7.5-9 Cask Oblique-Drop Geometry............................................................. 2.6-96 Figure 2.6.7.5-10 Cask Slapdown G eometry..................................................................... 2.6-97 Figure 2.6.7.5-11 Force-Deformation Curve - Lower impact Limiter (Bottom End Impact, 0 Degrees)................................................... 2.6-98 Figure 2.6.7.5-12 Force-Deformation Curve - Lower Impact Limiter (Bottom Comer Impact, 24 Degrees)................................................ 2.6-99 Figure 2.6.7.5-13 Force-Deformation Curve - Lower Impact Limiter (Bottom Oblique impact, 75 Degrees).............................................. 2.6-100 Figure 2.6.7.5-14 Force-Deformation Curve - Upper Impact Limiter (Top End impact, 0 Degrees)........................................................... 2.6-101 Figure 2.6.7.5-15 Force-Deformation Curve - Upper impact Limiter (Top Corner Impact, 24 Degrees)................................................ 2.6-102 Figure 2.6.7.5-16 Force-Deformation Curve - Upper impact Limiter (Top Oblique Impact, 75 Der,rees)....-............................................. 2.6-103 Figure 2.6.7.5-17 Force-Deformation Curve - Sele Impact (90 Degrees)........................ 2.6-104 2-ix
SAR - UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B O
List of Figures (Continued)
Figure 2.6.7.5-18 Impact Limiter Attachment Geometry................................................ 2.6-105 Figure 2.6.7.7-1 Neutron Shield Geometry.................................................................... 2.6-1 19 Figure 2.6.12-1 PWR Transportable Storage Canister.................................................. 2.6-144 Figure 2.6.12-2 PWR Transportable Storage Canister Shell and Lids......................... 2.6-145 Figure 2.6.12.2 1 PWR Canister Assembly Finite Element Model................................. 2.6-149 Figure 2.6.12.2-2 Canister Structural and Shield Lid Finite Element Mesh................... 2.6-150 Figure 2.6.12.2-3 Structural and Shield Lid Weld Regions Finite Element Mesh........... 2.6-151 Figure 2.6.12.2-4 Canister Bottom Plate Finite Element Mesh....................................... 2.6-152 -
Figure 2.6.12.3-1 Identification of Sections for Evaluating Linearized Stresses in Canister.......................................................................... 2.6-15 7 Figure 2.6.13-1 PWR Fuel Assembly Basket..
........................................................2.6-202 Figure 2.6.13-2 Support Disk Cross Section Configuration......................................... 2.6-203 Figure 2.6.13-3 PWR Fuel Tube Configuration........................................................ 2.6-204 Figure 2.6.13.2-1 PWR Basket for Side-Drop........................................................... 2.6 9 Figure 2.6.13.2-2 $ide@iiE3EEEK65.................................................................... 2.6-E Eis==rri m m su..em m m e w w m m e
[lisM.................................................................................................WA 7152113Y-4 '. t,i..
3-G g4 g pitors k j,94G;gi g gy M g p gi'2...........................................................................................65 s
Figure 2.6.13.4-1 Locations of Maximum E r i 'ish Foot End-Drop, SM............................................................................2.6-@
Figure 2.6.13.5-1 Locations of Maximum ET'i.7in Foot End-Drop, 7tieM.......................................................................
Figure 2.6.13.6-1 Support Disk-Side Drop Orientations............................................... 2.6 3 Figure 2.6.13.6-[ Locations of Maximum Mlntensities - 0 E Drop Orientation, yJ.WM-.......................................................................2.6.%.
Figure 2.6.13.6-[ Locations of Maximum fffPM -l8.2[* E Drop Orientation.......,
~,..MR...........................................................................2.6.#
Figure 2.6.13.6-3 Locations of Maximum MtStresses @ M Drop Orientation, Thermaldiiiel................................................................ 2.6-E O
2-x
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B List of Figures (Continued)
Figure 2.6.13.6-[ Locations of Maximum,i o. ; 2., --g
...a Drop Orientation, M...............................................................................2.6-3 Figure 2.6.13.13-1 Finite Element Model of the Top Weldment Plate............................. 2.6-E Figure 2.6.13.13-2 Finite Element Model of the Bottom Weldment Plate...................... 2.6 Figure 2.6.14-1 BWR Transportable Storage Canister................................................ 2.6-266 Figure 2.6.14-2 BWR Transportable Storage Canister Shell and Lids......................... 2.6-267 Figure 2.6.14.2-1 BWR Canister Assembly Finite Element Mesh (with 45' Basket Orientation)...................................................................................... 2.6-2 71 Figure 2.6.14.2-2 Canister Structural and Shield Lid Finite Element Mesh................. 2.6-272 Figure 2.6.14.2-3 Structural and Shield Lid Weld Regions Finite Element Mesh.......... 2.6-273 Figure 2.6.14.2-4 Canister Bottom Plate Finite Element Mesh....................................... 2.6-274 Figure 2.6.14.3-1 Identification of the Sections for Evaluating the Linearized Stresses in the Canister......................
........................................ 2. 6-2 7 8 p
Figure 2.6.15-1 B WR Fuel Assembly Basket.......................................................... 2.6-3 22 V
Figure 2.6.15-2 Support Disk Cross Section Configuration.................................. 2.6-323 I
Figure 2.6.15-3 BWR Fuel Tube Configuration...................................................... 2.6-324 Figure 2.6.15.2-1 ANSYS Model of BWR Basket for Side Drop................................... 2.6-327 Figure 2.6.15.2-2 Close-Up of the Ligaments and the Interface with the Canister Shell and the Cask inner Shell....
.................................................2.6-328 Figure 2.6.15.4-1 Locations of Maximum Primary Nodal Stress Intensities for 1-Foot En d D ro p....................................................................................... 2. 6-3 3 1 Figure 2.6.15.5-1 Locations of Maximum Primary and Secondary Nodal Stress Intensities for 1 -Foot End Drop..................................................... 2.6-335 Figure 2.6.15.6-1 Support Disk Side-Drop Orientations.............................................. 2.6-340 Figure 2.6.15.6-2 Locations of the Sections Used to Obtain Linearized Stresses for the Support Disk for the 1st Quadrant (X>0,Y>0)....................... 2.6-341 Figure 2.6.15.6-3 Locations of the Sections Used to Obtain Linearized Stresses for the Support Disk for the 2nd Quadrant (X<0,Y<0).................... 2.6-342 Figure 2.6.15.6-4 Locations of the Sections Used to Obtain Linearized Stresses for the Support Disk for the 3rd Quadrant (X<0,Y<0)...................... 2.6-343 O
2-xi
SAR-UMS* Universal Transport Cask April 1997 Docke t No. 71-9270 Revision 0 List of Figures (Continued)
Figure 2.6.15.6-5 Locations of the Sections Used to Obtain Linearized Stresses for the Support Disk for the 4th Quadrant (X>0,Y<0)....................... 2.6-344 Figure 2.6.15.6-6 Locations of Maximum Linearized Stress Intensities -
0 Drop Orientation........................................................................... 2.6-3 4 5 Figure 2.6.15.6-7 Locations of Maximum Linearized Stress Intensities -
31.82 Drop Orientation..................................................................... 2.6-3 4 6 Fig'tre 2.6.16.6-8 Locations of Maximum Linearized Stress Intensities -
49.4 6* Drop Orientation...................................................................... 2.6-3 4 7 Figure 2.6.15.6-9 Locations of Maximum Linearized Stress Intensities -
77.92* Drop Orientation................................................................... 2.6-3 4 8 Figure 2.6.15.6-10 Locations of Maximum Linearized Stress Intensities -
9 0* D rop Orientati o n........................................................................... 2.6-3 4 9 Figure 2.6.15.13-1 Finite Element Model of the Top Weldment Plate............................ 2.6-387 Figure 2.6.15.13-2 Finite Element Model of the Bottom Weldment Plate...................... 2.6-388 Figure 2.7.2.1-1 Cask Body Model for Puncture Analysis............................................. 2.7-40 Figure 2.7.2.1-2 Location of Sections for Evaluation..................................................... 2.7-41 Figure 2.7.2.2-1 ANSYS Model for Cask Lid............................................................. 2.7-47 Figure 2.7.2.3-1 Bottom Puncture Finite Element Model and Boundary Conditions:... 2.7-52 Figure 2.7.2.3-2 Location of Sections for Evaluation:.................................................. 2.7-53 Figure 2.7.6-1 Cross Section of Cask Body................................................................. 2.7-6 8 Figure 2.7.7.2-1 Identification of the Sections for Evaluating the Linearized Stresses in the P WR Canister.............................................................. 2.7-72 Figure 2.7.8.4-1 PWR Fuel Tube Finite Element Model........................................ 2.7-122 Figure 2.7.9.2-1 Identification of Sections for Evaluating Linearized Stresses in BWR Canister................................................................ 2.7-13 0 Figure 2.7.10.4-1 BWR Fuel Tube Finite Element Model............................................. 2.7-184 Figure 2.10.2-1 Primary Components of the Universal Transport Cask........................ 2.10-6 Figure 2.10.2-2 Universal Transport Cask 3-D Model.................................................. 2.10-7 O
2-xii
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B
/~'N U
List of Tables (Continued)
Table 2.6.13.6-11 P, + P, Stresses for Support Disk Foot Side-Drop, ggg Orientation, Thermal Case B.............................................................. 2.6-E Table 2.6.13.6-12 P, Stresses for Support Disk Foot Side-Drop, E Orientation, Thermal Case E............................................................... 2.6-E Table 2.6.13.6-13 P, + P, Stresses for Support Disk Foot Side-Drop, R Orientation, Thermal Case [............................................................ 2.6-E J Yh #.Rt.
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Table 2.6.13.7-1 P, + P + Q Stresses for Support Disk Foot Side-Drop,0 3
Orientation, Thermal Case $.......................................................... 2.6-E Table 2.6.13.7-2 P, + P, +Q Stresses for Support Disk Foot Side-Drop,18.2g DSentat 6n; Thermal Case $........................................................... 2.6-E Table 2.6.13.7-3 P, + P, + Q Stresses for Support Disk Foot Side-Drop, %.Qi8 Orientation, Thermal Case $.............................................................. 2.6-E
. tab _l.i.f_2E1_3_:74 P7_PT+7Stres,s_es.foTfupp7_o DliikTSF.6ai'SlEDhWS_ W 6
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Table 2.6.13.13-1 Minimum Margins of Safety for the Top / Bottom Weldments for 1 -Foo t En d-Dro p..........................................................
............ 2.6-3 Table 2.6.13.14-1 Minimum Margins of Safety from Buckling Evaluation of PWR Support Disk........................................
2.6-E N
Table 2.6.14.2-1 Real Constant Sets Defined in Canister Model.................................. 2.6-275 Table 2.6.14.2-2 Material Sets Defined in Canister Model................................... 2.6-275 Table 2.6.14.3-1 BWR Canister Linearized Q Stresses - Thermal Only (Hot 1)........... 2.6-279 Table 2.6.14.3-2 BWR Canister Linearized Q Stresses - Thermal Only (Cold 2)..... 2.6-280 Table 2.6.14.4-1 BWR Canister Critical Sections for the 1-Foot End-Drop Condition. 2.6-282 Table 2.6.14.4-2 BWR Canister P, Stresses - Internal Pressure........................... 2.6-283
\\
2-xxi
SAR-UMS* Universal Transport Cask Dectmber 1997 Docket No. 71-9270 Revision UMST-97A List of Tables (Continued)
Table 2.6.14.4-3 BWR Canister P, + P, Stresses - Intemal Pressure........................... 2.6-284 Table 2.6.14.4-4 BWR Canister P, Stresses Foot Top End-Drop......................... 2.6-285 Table 2.6.14.4-5 BWR Canister P, + P, Stresses Foot Top End-Drop................... 2.6-286 Table 2.6.14.4-6 BWR Canister P, Stresses Foot Bottom End-Drop, Internal Pressure................................................................................... 2. 6-2 8 7 Table 2.6.14.4-7 BWR Canister P, + P, Stresses Foot Bottom End-Drop, Internal Pre s sure....................................................................................... 2. 6-2 8 8 Table 2.6.14.5-1 BWR Canister Critical Sections for the Combined 1-Foot End-Drop and Therma! Load Condition............................................................. 2.6-290 Table 2.6.14.5-2 BWR Canister P, + P, + Q Stresses Foot Top End-Drop, Thermal Col d............................................................................... 2.6-2 91 Table 2.6.14.5-3 BWR Canister P + P, + Q Stresses Foot Top End-Drop, Thermal Heat......
.............................................................2.6-292 Table 2.6.14.5-4 BWR Canister P, + P + Q Stresses Foot Bottom End-Drop, Thermal Cold...................................................................... 2.6-293 Table 2.6.14.5-5 BWR Canister P, + P, + Q Stresses Foot Bottom End-Drop, Thermal Heat....
.......................................................................2.6-294 Table 2.6.14.6-1 BWR Canister Critical Sections for the 1-Foot Side-Drop Load Co n dition..................................................................... 2.6-29 7 Table 2.6.14.6-2 BWR Canister P, Stresses Foot Side-Drop............................... 2.6-298 Table 2.6.14.6-3 BWR Canister P, + P, Stresses Foot Side-Drop, Internal Pressure........................
..........................................2.6-299 Table 2.6.14.7-1 BWR Canister Cr'.tical Sections for the Combined 1-Foot Side-Drop and Thermal Load Condition................................................ 2.6-3 01 Table 2.6.14.7-2 BWR Canister P, + P + Q Stresses Foot Side-Drop, Thermal Cold.................................................................................. 2. 6-3 02 Table 2.6.14.7-3 BWR Canister P, + P, + Q Stresses Foot Side-Drop, Thermal Heat.................
........................................................2.6-303 Table 2.6.14.8-1 BWR Canister Critical Sections for the 1-Foot Corner-Drop Load Condition.............................................................. 2. 6-3 0 5 Table 2.6.14.8-2 BWR Canister P Stresses: 1-Foot Top Corner-Drop, I nternal Pressure.................................................................. 2.6-3 06 2-xxii l
SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B (o)
List of Tables (Continued)
Table 2.6.15.7-1 P, + P + Q Stresses for Support Disk Foot Side-Drop, 0 Orientation,ThermalCase 2........................................... 2. 6-3 7 9 Table 2.6.15.7-2 P, + P +Q Stresses for Support Disk Foot Side-Drop, 31.82* Orientation, Thermal Case 2........................................... 2. 6-3 8 0 Table 2.6.15.7-3 P + P + Q Stresses for Support Disk Foot Side-Drop,49.46' Orientation, Thermal Case 2..........................................................2.6-381 Table 2.6.15.7-4 P, + P, + Q Stresses for Support Disk Foot Side-Drop, 77.92 Orientation, Thermal Case 2................................................ 2. 6-3 8 2 Table 2.6.15.7-5 P, + P, + Q Stresses for Support Disk Foot Side-Drop, 90 Orientation, Thermal Case 2...........
............. 2.6-3 83 Table 2.6.15.13-1 Minimum Margins of Safety for the Top / Bottom Weldments for a 1-Foot End-Drop With and Without Thermal Stresses.................. 2.6-389 Table 2.6.15.14-1 Minimum Margins of Safety from Buckling Evaluation of BWR Support Disk (Weak Axi s)......................................................
...... 2.6-3 97 Table 2.6.15.14-2 Minimum Margins of Safety from Buckling Evaluation of BWR Support V
Disk (S trong Axis).............................................................. 2@-3 98 Table 2.7.1.1-1 P Stresses Foot Top End-Drop, Thermal Condition 1................. 2.7-5 Table 2.7.1.1-2 P, + P, Stresses Foot Top End-Drop, Thermal Condition 1........... 2.7-6 Table 2.7.1.1-3 Critical P Stress Summary Foot Top End-Drop, Thermal Condition 1..
.....................................................................2.7-7 I
Table 2.7.1.1-4 Critical P, + P Stress Summary Foot Top End-Drop, Thermal C o n d i ti o n 1....................................................................... 2. 7-7 Table 2.7.1.1-5 P Stresses Foot Bottom End-Drop, Thermal Condition 1........... 2.7-8 Table 2.7.1.1-6 P + P Stresses Foot Bottom End-Drop, Thermal Condition 1..... 2.7-9 Table 2.7.1.1-7 Critical P Stress Summary Foot Bottom End-Drop, Thermal Condition 1...
................ 2.7-10 Table 2.7.1.1-8 Critical P + P. Stress Summary Foot Bottom End-Drop, Thermal Condition 1................................
..................... 2.7-10 Table 2.7.1.2-1 P Stresses Foot Side-Drop, Thermal Condition 1..................... 2.7-12 Table 2.7.1.2-2 P, + P, Stresses Foot Side-Drop, Thermal Condition 1............ 2.7-13 Table 2.7.1.2-3 Critical P, Stress Summary Foot Side-Drop, Thermal m
Condition 1...
...............................................................2.7-14 2-xxv
SAR - UMS* Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A List of Tables (Continued)
Table 2.7.1.2-4 Critical P, + P, Stress Summary Foot Side-Drop, Thermal Co ndi ti o n 1.................................................................................... 2. 7-14 Table 2.7.1.3-1 P, Stresses Foot Top Corner-Drop, Thermal Condition 1........... 2.7-16 Table 2.7.1.3-2 P + P Stresses Foot Top Corner-Drop, Thermal Condition 1...... 2.7-17 Table 2.7.1.3-3 Critical P, Stress Summary Foot Top Comer-Drop, Thermal Condition 1...
....................................2.7-18 Table 2.7.1.3-4 Critical P, + P, Stress Summary Foot Top Corner-Drop, Thermal Conditi on 1.......................................................................... 2.7-1 8 Table 2.7.1.3-5 P, Stresses Foot Bottom Comer-Drop, Thermal Condition 1....... 2.7-19 Table 2.7.1.3-6 P + P Stresses Foot Bottom Corner-Drop, Thermal C o n di ti o n 1......................................................................................... 2. 7-2 0 Table 2.7.1.3-7 Critical P. Stress Summary Foot Bottom Comer-Drop, Thermal Con di ti o n 1....................................................................... 2.7-21 Table 2.7.1.3-8 Critical P, + P Stress Summary Foot Bottom Comer-Drop, Thermal Condition 1................................................. 2.7-21 Table 2.7.1.4-1 P. Stre.oes Foot Top 75' Oblique-Drop, Thermal Condition 1... 2.7-23 Table 2.7.1.4-2 P, + P Stresses Foot Top 75" Oblique-Drop, Thermal C o n d i ti o n 1..................................................................................... 2. 7-2 4 1
Table 2.7.1.4-3 Critical P, Stress Summary Foot Top 75 Oblique-Orop, Thermal Condition 1.............................................................. 2.7-25 Table 2.7.1.4-4 Critical P. + P Stress Summary Foot Top 75 Oblique-Drop, Thermal Condition 1.................................................................. 2.7-25 Table 2.7.1.4-5 P, Stresses Foot Bottom 75" Oblique-Drop, Thermal Condition I........................................................ 2.7-26 Table 2.7.1.4-6 P, + P. Stresses Foot Bottom 75' Oblique-Drop, Thermal Condition 1................................................................ 2.7-2 7 Table 2.7.1.4-7 Critical P Stress Summary Foot Bottom 75 Oblique-Drop, Thermal Condition 1.........
....................................2.7-28 Table 2.7.1.4-8 Critical P + P Stress Summary Foot Bottom 75' Oblique-Drop, Th ermal Co nd iti on i................................................................ 2.7-2 8 Table 2.7.2.1-1 Local Membrane Stresses - Puncture Cask Side.....................
... 2.7-42 Table 2.7.2.1-2 Stress Evaluation - Puncture Cask Side...................................... 2.7-43 Table 2.7.2.3-1 Cask Bottom Puncture Stresses................................................. 2.7-54 2-xxvi
SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B
,(
List of Tables (Continued)
Table 2.7.2.3-2 Puncture Stress Evaluation Results.......................................... 2.7-5 5 Table 2.7.3.1-1 Maximum Component Temperatures - Hypothetical Accident Conditions Fire Accident (PWR Cask)............................................... 2.7-59 Table 2.7.3.1-2 Maximum Component Temperatures - Hypothetical Accident Conditions Fire Accident (BWR Cask)............................................... 2.7-60 Table 2.7.3.1-3 Summary @ Maximum Canister Pressures During Hypothetical Accident Conditi ons....................................................................... 2.7-61 Table 2.7.3.1-4 Summary [f Maximum Cask Cavity Pressures During Hypothetical A ccid ent Co n diti ons...................................................................... 2.7-61 Table 2.7.7.2-1 PWR Canister P, Stresses Foot Side-Drop................................. 2.7-73 Table 2.7.7.2-2 PWR Canister P,,, + P, Stresses Foot Side-Drop........................ 2.7-74 Table 2.7.7.2-3 PWR Canister P, Stresses Foot Bottom End-Drop...................... 2.7-75 Table 2.7.7.2-4 PWR Canister P, + P, Stresses Foot Bottom End-Drop............. 2.7-76 Table 2.7.7.2-5 PWR Canister P Stresses Foot Top End-Drop........................... 2.7-77 Table 2.7.7.2-6 PWR Canister P + P, Stresses Foot Top End-Drop.................. 2.7-78 Table 2.7.7.2-7 PW'R Canister P, Stresses Foot Bottom Corner-Drop................. 2.7-79 Table 2.7.7.2-8 P'VR Canister P + P, o esses Foot Bottom Comer-Drop.......... 2.7 80 Table 2.7.7.2-9 PWR Canister P, Stresses Foot Top Corner-Drop.................... 2.7-81 Table 2.7.7.2-10 PWR Canister P + P, Stresses Foot Top Corner-Drop............. 2.7-82 Table 2.7.7.2-11 Summary of Minimum Margins of Safety for PWR Canister -
3 0-Foot Drops.............................
......................................2.7-83
)
Table 2.7.7.3.-l Buckling Evaluation Results for the PWR Canister for 30-Foot End-Drop.....
..............................................................2.7-86 Table 2.7.8.1-1 Summary of Stress Evaluation of Support Disk Foot S i d e - D ro p............................................................................. 2. 7-9 1 Table 2.7.8.1-2 P Stresses for Support Disk Foot Side-Drop,0* Orientation, Therm al Case 8.................................................................... 2.7-92 Table 2.7.8.1-3 P, + P, Stresses for Support Disk Foot Side-Drop,0* Orientation, Therm al Case f........................................................ 2.7-93 Table 2.7.8.1-4 P, Stresses for Support Disk Foot Side-Drop,0" Orientation, Thermal Case @.............
............... 2.7-94 Table 2.7.8.1-5 P, + P, Stresses for Support Disk Foot Side-Drop,0 Orientation, O)
Thermal Case @............................................... 2.7-95 (v
2-xxvii
SAR - UMS* Universal Transport Cask April 1998
)
Docket No. 71-9270 Revision UMST-97B i
List of Tables (Continued)
Table 2.7.8.1-6 P Stresses for Support Disk 30-Foot Side-Drop,18.R Orientation, Thermal Case [............................................................................
Table 2.7.8.1-7 P + P, Stresses for Support Disk Foot Side-Drop, 18.g Orientation, Thermal Case [............................................. 2.7-97 Table 2.7.8.1-8 P, Stresses for Support Disk Foot Side-Drop, 18 5 Orientation, Thermal Case [...................................................... 2.7-98 Table 2.7.8.1-9 P, + P, Stresses for Support Disk Foot Side-Drop, 18.Q Orientation, Thermal Case H.................................................... 2.7-99 Table 2.7.8.1-10 P, Stresses for Support Disk Foot Side-Drop,
[C{ Orientation, Thermal Case [................................................... 2.7-100 Table 2.7.8.1-11 P, + P Stresses for Support Disk Foot Side-Drop, 2D8 Orientation, Thermal Case [......
................................... 2.7-101 Table 2.7.8.1-12 P, Stresses for Support Disk Foot Side-Drop, 2GP Orientation, Thermal Case [................................................. 2.7-102 Table 2.7.8.1-13 P, + P, Stresses for Support Disk Foot Side-Drop, 26]{' Orientation, Thennal Case H................................................. 2.7-103 Table 2.7.8.1-14 KS~tEssesWSiiiip*'oKDEkT367 CiiEA................................................................................... 2. 7-1 04 Table 2.7.8.1-15 P, + P, Stresses for Support Disk Foot End-Drop, Thermal Case $............................................................................
Table 2.7.8.1-16 P3tmsses fi3QLJjgotik"M6-TWd33. J JEL. ).l. f,Mt paseB............................................................................................2.7-106 IriRe'DET7 PFWstressesRSupportDisF M6 %MM[isGa@
ppcss........................................................ gMEli TianialiT8 Eummary;orsessJfililiiEEsupponDEEGissiad-Dre...E h.
Time H C Q1]
[fAEASkesses"f6ESupportD3kMM
!IFe72iiFCa'Ki6...................................................................... @; 4 iablegiME-70 RyfPestresseiJdESiipikTQFsW3E-FoMIxt urozg ThMH!E'E.......................................................................' W.
7sMi7!7.[fE2I Sumniary;oFStmss Evaluation:of Support Diikl B_fffDBMgl6iU'ro~p......................................................... $I7M TM-Table 2.7.9.2-1 BWR Canister P Stresses Foot Side-Drop............................ 2.7-131 2-xxviii
SAR-UMS* UniversalTransport Cask April 1998 Docket No. 71-9270 Revision UMST-97B List of Tables (Continued)
Table 2.7.9.2-2 BWR Canister P + P, Stresses Foot Side-Drop.......................... 2.7-132 Table 2.7.9.2-3 BWR Canister P Stresses Foot Bottom End-Drop, Internal Pre s sure................................................................................
Table 2.7.9.2-4 BWR Canister P + P, Stresses Foot Bottom End-Drop, Intemal Pres sure.................................................................................
Table 2.7.9.2-5 BWR Canister P Stresses Foot Top End-Drop........................... 2.7-135 Table 2.7.9.2-6 BWR Canister P, + P, Stresses Foot Top End-Drop................... 2.7-136 Table 2.7.9.2-7 BWR Canister P, Stresses Foot Bottom Corner-Drop................ 2.7-137 Table 2.7.9.2-8 BWR Canister P, + P Stresses Foot Bottom Corner-Drop....... 2.7-138 Table 2.7.9.2-9 BWR Canister P, Stresses Foot Top Corner-Drop, Internal Pressure................................................................................. 2.7-13 9 Table 2.7.9.2-10 BWR Canister P, + P, Stresses Foot Top Comer-Drop............. 2.7-140 Table 2.7.9.2-11 Summary of Minimum Margins of Safety for BWR Canister -
3 0-Foot Drops................................................................................... 2.7-141 Table 2.7.9.3-1 Buckling Evaluation Results for the BWR Canister for 3 0-Foot End-Drop............................................................................. 2. 7-14 3 Table 2.7.10.1-1 Summary of Stress Evaluation of Support Disk Foot S id e-Drop........................................................................................... 2.7-1 4 8 Table 2.7.10.1-2 P, Stresses for Support Disk Foot Side-Drop,0 Orientation, Thermal Case 1..................................................................................2.7-149 Table 2.7.10.1-3 P, + P, Stresses for Support Disk-30-Foot Side-Drop,0* Orientation, Thermal Case 1....................................................................................2.7-150 Table 2.7.10.1-4 P, Stresses for Support Disk Foot Side-Drop,0" Orientation, Thermal Case 2................................................................................2.7-151 Table 2.7.10.1-5 P, + P Stresses for Support Disk Foot Side-Drop,0* Orientation, Thermal Case 2..................................................................................2.7-152 Table 2.7.10.1-6 P Stresses for Support Disk Foot Side-Drop,31.82* Orientation, Thermal Case 1.............................................................................2.7-153 Table 2.7.10.1-7 P, + P, Stresses for Support Disk Foot Side-Drop,31.82' Orientation, Thermal Case 1.................................................................................2.7-154 Table 2.7.10.1-8 P Stresses for Support Disk Foot Side-Drop,31.82* Orientation, Thermal Case 2..................................................................................2.7-155
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2-xxix
1 SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B List of Tables (Continued)
Table 2.7.10.1-9 P, + P Stresses for Support Disk Foot Side-Drop, 31.82* Orientation, Thermal Case 2................................................ 2. 7-1 5 6 Table 2.7.10.1-10 P, Stresses for Support Disk Foot Side-Drop,49.46 Orientation, Therrnal Case 1.............................................................................2.7-157 Table 2.7.10.1-11 P + P, Stresses for Support Disk Foot Side-Drop,49.46" Orientation, Thermal Case 1..................................................................................2.7-158 Table 2.7.10.1-12 P, Stresses for Support Disk Foot Side-Drop,49.46' Orientation, Thermal Case 2................................................................................. 2.7 'l 5 9 Table 2.7.10.1-13 P, + P, Stresses for Support Disk Foot Side-Drop,49.46' Orientation, Thermal Case 2.............................................................................2.7-160 Table 2.7.10.1-14 P, Stresses for Support Disk Foot Side-Drop,77.92 Orientation, Thermal Case 1.........
............................................................2.7-161 Table 2.7.10.1-15 P + P Stresses for Support Disk Foot Side-Drop,77.92* Orientation, Thermal Case 1.........................................................................2.7-162 Table 2.7.10.1-16 P, Stresses for Support Disk Foot Side-Drop,77.92* Orientation, Thermal Case 2.......................................................................2.7-163 Table 2.7.10.1-17 P, + P Stresses for Support Disk Foot Side-Drop,77.92 Orientation, Thermal Case 2............................................................................2.7-164 Table 2.7.10.1-18 P Stresses for Support Disk Foot Side-Drop,90 Orientation, Thermal Case 1.........................................................................2.7-165 Table 2.7.10.1-19 P, + P, Stresses for Support Disk Foot Side-Drop,90' Orientation, Thermal Case 1.......................................................................2.7-166 Table 2.7.10.1-20 P, Stresses for Support Disk Foot Side-Drop,90 Orientation, Thermal Case 2....................................................................2.7-167 Table 2.7.10.1-21 P, + P. Stresses for Support Disk Foot Side-Drop,90' Orientation, Thermal Case 2................................................................2.7-168 Table 2.7.10.1-22 Summary of Stress Evaluation of Support Disk -
30-Foot End-Drops........
.........................................................2.7-169 Table 2.7.10.1-23 P,+ P, Stresses for Support Disk Foot End-Drop, Thermal Case 1.................................................................2.7-170 Table 2.7.10.1-24 P,+ P, Stresses for Support Disk Foot End-Drop, Thermal Case 2........................................................................2.7-171 2-xxx l
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B nb List of Tables (Continued)
Table 2.7.10.3-1 Minimum Margins of Safety from Buckling Evaluation of BWR S upport Disk (Weak Axis)................................................................... 2.7-178 Table 2.7.10.3-2 Minimum Margins of Safety from Buckling Evaluation of BWR Support Disk (Strong Axis).................................................................. 2.7-179 Table 2.7.11-1 Summary of Maximum Calculated Stresses in Cask Foot Free Drop.....................................................................................................2.7-190 Table 2.7.11-2 Summary of Maximum Calculated Stresses in Cask - Puncture.......... 2.7-191 Table 2.7.12-1 Buckling Evaluation Load Cases and Results for the Universal Transport Cask.................................................................................... 2.7-201 Table 2.7.12-2 Geometry Parameters for the Universal Transport Cask...................... 2.7-202 Table 2.10.2.2-1 Component Section and Temperature Definition................................. 2.10-20 Table 2.10.2.2-2 Stress Section Locations.................................................................... 2.10-21
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i 2-xxxi i
i O
l THIS PAGE INTENTIONALLY LEFT BLANK t
O O
o SAR-UMS* Universal Transport Cask April 1997
)
Docket No. 71-9270 Revision 0 2.1 Structural Desien I
i 2.1.1 Discussion The transportation component of the Universal MPC System
- consists of a Universal Transport Cask containing a welded Transponable Storage Canister Assembly. The canister assembly includes a canister and a fuel basket loaded with intact PWR or BWR spent fuel. The impact limiters attached to the top and bottom of the cask protect the cask and contents from damage resulting from impacts that could occur during transport. These principal components are described in the following paragraphs.
2.1.1.1 Universal Transport Cask The Universal Transport Cask is a cylindrical, multiwalled cask designed to safely transport a canister containing either 24 PWR fuel assemblies or 56 BWR fuel assemblies. The primary components of the cask are as follows:
- 1. Cask body (inner shell, outer shell, lead gamma shielding, and cask bottom)
- 2. Cask lid, bolts, and 0-rings
- 3. Port covers, port coverplates, bolts, and 0-rings
- 4. Neutron shield
- 5. Lifting trunnions and rotation pockets
)
- 6. Impact limiters (upper and lower)
The cask primary containment boundary consists of the (1) inner shell; (2) bottom forging;
-(3) top forging; (4) cask lid, lid bolts, and lid inner 0-ring; (5) vent port coverplate, vent port j
coverplate bolts, and vent port coverplate inner 0-ring; (6) drain port coverplate, drain port coverplate bolts, and drain port coverplate inner O-ring. A detailed discussion of the containment boundary is presented in Chapter 4.0. The geometry and materials of fabrication of the cask components are described in Section 1.2.1 and shown on the License Drawings presented in Section 1.3.3.
O 2.1-1
SAR - UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 The Universal Transport Cask body supports and protects the cask cavity contents for the normal conditions of transport and the hypothetical accident conditions. The lead located between the cask inner and outer shells provides the primary gamma radiation shielding for the cask in the radial direction. The bottom plate closes the cask bottom end and provides axial gamma radiation shielding. The bottom plate traps a layer of NS-4-FR which provides neutron radiation shielding in the axial direction. The cask lid, bolts, and 0-rings are the primary closure components of the cask.
The vent port is located in the cask lid and the drain port is located in the bottom forging. Each port is protected by a port coverplate. The primary containment boundary at the vent port and at the drain port is the port coverplate and its inner 0-ring. The 0-ring is located on the bottom surface of the port coverplate. A second 0-ring is also located on the bottom surface of the port coverplate outside of, and concentric with, the primary containment inner 0-ring. Each port cover has a test port that penetrates the region between the 0-rings to enable leak testing of the O-rings using the interseal region. The inner 0-ring is tested by pressurizing the cask cavity with helium and using a helium leak detector at the test ports in the cask lid and in the port coverplates. The outer 0-rings are tested by pressurizing the interseal regions with helium and using a helium leak detector around the edge of the cask lid and the two port coverplates.
The cask lid, bolts, and outer 0-ring provide the primary containment boundary. The lid is secured to the top forging by 48 bolts (2-8 UN-2A bolts) preloaded by an installation torque to restrain rotation of the edge of the lid and to maintain a containment seal for the critical load condition. The critical load condition is a uniformly distributed pressure resulting from the impact of the canister and cavity contents on the inner surface of the lid during a top-end or top-corner impact.
The neutron shielding material, NS-4-FR, is installed in the annulus that surrounds the cask outer shell along the length of the cask cavity and between the bottom forging and the bottom plate.
NS-4-FR is a solid, synthetic polymer that absorbs the neutron radiation emitted by the cask contents.
Four lifting trunnions, two primary and two secondary, are provided on the outside of the top l
forging at 90-degree intervals. Two diametrically opposed primary trunnions are welded into 2.0-in. deep recesses in the top forging. The two secondary trunnions are bolted to the top 2.1-2 1
l 1
SAR-UMS Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 3(V forging when redundant lifts are performed. The purpose of the trunnions is to enable lifting and handling of the cask. Two types oflining systems may be used: redundant (four trunnions) or nonredundant (two trunnions). The lifting trunnions are designed to satisfy the heavy lifting requirements of NUREG-0612 [3] and attendant standard ANSI N14.6 [4] for a nonredundant lin using the two primary lifting trunnions or a redundant lift using all four of the lifting trunnions, as well as the requirements of 10 CFR 71.45(a) and Paragraph 506 ofIAEA Safety Series No. 6.
Analyses show that overload failure of the trunnions will not impair the ability of the cask body to continue to perform its function.
Two rotation pockets are welded to the outer shell near the bottom of the cask. Neutron shield material is displaced to accommodate the placement of the rotation pockets, which are used to support the bottom of the cask on the shipping frame and also, as a pivot point to rotate the cask from the vertical lifting position to the horizontal position and vice versa. The rotation pocket design prevents lateral and rearward movement of the cask. The pocket welds are designed to fail in shear before the outer shell fails, thereby enabling the cask to continue to perform its primary function.
V)
I' Forward movement of the cask is prevented by the shear ring welded to the top forging of the cask. In the transport configuration, forward axial loads from the cask are passed through to the support frame where the shear ring contacts the frame. The shear ring welds are designed to fail in shear before the top forging, minimizing the damage to the cask, enabling the cask body to perform its primary function.
2.1.1.2 Transoortable Storace Canister The Transportable Storage Canister Assembly consists of a stainless steel canister shell assembly, a shield lid, and a structural lid. The shell assembly is a cylindrical shell welded to a bottom plate and a shield lid support ring welded to the interior of the canister shell. The shell assembly with both the shield and structural lid welded in place provides a double welded canister closure system for the fuel assemblies loaded in the basket. The canister assembly provides confinement for the spent fuel during storage. No credit is taken for the canister containment function during transport operations.
i
/b 2.1-3
SAR - UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 A tasket assembly, as described in Section 2.1.1.3, is positicaml inside the shell assembly. The i
basket structure locates and supports the basket contents. There are two basket designs, each of which is designed to accommodate either intact PWR or BWR fuel assemblies. The transportable storage canister assembly is moved in a transfer cask during fuel-loading operations. The shield aad structural lids are welded to the canister shell while the loaded canister is in the transfer cask.
In the spent fuel pool, the fuel is loaded into the basket / canister assembly positioned in the transfer cask. Upon completion of fuel loading, the shield lid is lowered into the top of the canister. The shield lid assembly is a 7-in.-thick Type 304 stainless steel disk positioned on the shield lid support ring above the basket assembly. Then the loaded canister assembly is moved to a decontamination pit for the remaining canister closure operations, including installation of the drain pipe.
Two penetrations through the shield lid are provided for draining, vacuum drying, and backfilling the canister with helium. The drain penetration is threaded on the top to accept the drain pipe. The pipe extends to within 1/8 in. of the bottom of the canister to facilitate draining water from the inside of the canister.
The vent port is used to pressurize the canister or as a vent / discharge port during cask operations.
Both the drain and vent ports have a cover welded over the quick disconnect prior to installation of the structural lid.
l
'lhe structural lid is a 3-in. thick Type 304L stainless steel disk positioned on top of the shield lid and welded to the shell ader the shield lid is welded in place and the canister is drained, dried,
(
and backfilled with helium. The structural lid is designed with removable hoist rings so that the loaded canister can be lifted. The canister design parameters for the transport of different classes of PWR and BWR fuel are provided in Chapter 1.0.
2.1.1.3 Fuel Basket l
The fuel basket assembly structure is located inside the canister shell assembly. The basket and I
canister shell assemblies are handled as one unit. The basket provides the fuel assemblies with lateral support, decay heat removal capability, and enticality control during all storage and 1
1 2.1 -4
SAR-UMS Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 transportation normal conditions of transport and hypothetical accident conditions. The basket can be loaded with up to 24 intact PWR fuel assemblies or up to 56 intact BWR fuel assemblies.
Some design features are common to both the PWR and BWR fuel baskets and some features are unique to each basket, as described in the following paragraphs.
The common design features between the PWR and BWR basket structure designs are the top and bottom weldments, support disks, heat transfer disks, fuel tubes, tie rods and nuts, and split spacers. When complete, the basket stmeture is a rigid cylindrical structure. The base of the structure is the stainless steel bottom weldment.
Either 8 (PWR) or 6 (BWR) stainless steel tie rods are welded to the bottom weldment. The tie rods are used to mechanically join the bottom weldment with the top weldment and hold in place all layers of the suppon disks and heat transfer disks. Each weldment is designed to support the entire basket stmeture for all loads. The axial loads are bounded by hypothetical accident condition top / bottom-end drop loads. The fuel assemblies are self-supporting in the axial direction.
b V
The basket structure is assembled by stacking the support disks and the heat transfer disks over the tie rods, each separated by either a spacer or split spacer and washer. The system of multiple support disks is designed to support the fuel assemblies and fuel tubes for all lateral loads. The lateral loads are bounded by hypothetical accident condition side-drop loads. The heat transfer disks do not transmit structural loads (other than self-weight) for any load condition.
The support disks satisfy structural design criteria requirements at temperatures that result from either the normal conditions of transport or hypothetical accident. The aluminum heat transfer disks enhance thermal performance of the basket structure by augmenting its overall heat the conduction properties.
The support disks in the PWR basket are separated and supported at 4.92-in. center-to-center intervals by tie rods and spacer nuts at eight locations. The heat transfer disks are located in the central region of the basket and supported by the eight tie rods and spacer nuts. The number of support disks and heat transfer disks in the PWR basket varies depending upon the class of fuel (Class 1,2, or 3 PWR fuel) the basket is designed to contain. The PWR fuel tubes are encased l
by BORAL poison plates on each of the four sides.
l 2.1-5
SAR-UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 The support disks in the BWR basket are separated and supported at 3.83-in. center-to-center intervals by tie rods and spacer nuts at six locations. The heat transfer disks are located in the central region of the basket and supported by the six tie rods and spacer nuts. As is the case for the PWR basket, the number of support disks and heat transfer disks in the BWR basket varies depending upon the class of fuel (Class 4 or Class 5 BWR fuel) the basket is designed to contain.
Three types of tubes are designed to contain BWR fuel: tubes with BORAL on two sides, tubes with BORAL one side, and tubes with no BORAL.
2.1.1.4 Impact Limiters The Universal Transport Cask packaging includes two removable, cup-shaped impact limiters.
The impact limiters absorb !he energy of a cask drop impact through the crushing of redwood and balsa wood.
Prior to shipment, the upper impact limiter is bolted to the top forging with 16 retaining rods, washers, and nuts. Likewise, the lower impact limiter is bolted to the bottom plate with 16 retaining rods, washers, and nuts. Both impact limiters are designed to limit impact loads on the g
cask and its contents resulting from either the normal conditions of transport or hypothetical w
accident drop scent.rios. The impact limiters are fabricated from redwood and balsa wood wedge-shaped sections glued together to form a cylindrical shape. The wood impact-absorbing medium is completely enclosed in a stainless steel shell that is fabricated from 0.25-in. stainless steel plate.
The maximum normal condition of transport (1-ft free drop) impact load is calculated to be 17.1 g in the bottom end drop orientation. The design load used in all normal conditions of transport impact calculations is 20 g. The maximum hypothetical accident condition (30-R free drop) impact load is calculated to be 54.9 g in the oblique-drop orientation. A design load of 60 g is used in all hypothetical accident condition impact calculations except the 30 R end-drop evaluation of the BWR basket, where a design load of 55 g is used.
l l
2.1-6 J
SAR-UMS" Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 2.1.2 Desian Criteria 2.1.2.1 Codes and Standards The structural design of the Universal Transport Cask incorporates criteria based on the following codes and standards.
General Criteria (Assembled Components) 10 CFR 71," Packaging and Transportation of Radioactive Material," April 1,1996. [1]
10 CFR 72, " Licensing Requirements for the Independent Storage of Spent Nuclear e
Fuel and High Level Radioactive Waste," April 1,1996. [5]
IAEA Safety Series No. 6, " Regulations for the Safe Transport of Radioactive e
Materials," 1985 Edition, as amended 1990. [2]
Cask Structural Desinn O
ASME Boiler and Pressure Vessel Code,Section III, Division I, Subsection NB,1995 e
Edition, with 1995 Addenda. [6]
NUREG/CR-3019, " Recommended Welding Criteria for Use in the Fabrication of Shipping Containers for Radioactive Materials," dated March 1984. [7]
NUREG/CR-3854, " Fabrication Criteria for Shipping Containers," dated March 1985.
e
[8]
NUREG/CR-6007," Stress Analysis of Closure Bolts for Shipping Casks," dated January 1993. [9]
]
Regulatory Guide 7.6," Design Criteria for the Structural Analysis of Shipping Cask e
Containment Vessels," Revision 1, March 1978. [10]
Regulatory Guide 7.8," Load Combinations for the Structural Analysis of Shipping e
Casks for Radioactive Material," Revision 1, March 1989. [11]
Cask inner Shell and Canister Bucklinn ASME Boiler and Pressure Vessel Code Cases, Nuclear Components, Case N-284-1,
" Metal Containment Shell Buckling Design Methods," Approved March 1995. [12]
2.1-7
SAR-UMS Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 Cask Structural Materials Fracture Touchness 1
Regulatory Guide 7.11, " Fracture Toughness Criteria of Base Material for Ferritic Steel e
Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 in. (0.1 m),"
dated June 1991. [13]
Regulatory Guide 7.12," Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater than 4 in. (0.1 m)
But Not Exceeding 12 in. (0.3m)," dated June 1991. [14]
Cask-Liftine Trunnions NUREG-0612," Control of Heavy Loads at Nuclear Power Plants," dated July 1980. [3]
ANSI N14.6,"Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More," dated June 1993. [4]
Basket Structural Desien ASME Boiler and Pressure Vessel Code,Section III, Division I, Subsection NG,1995 Edition, with 1995 Addenda. [15]
Regulatory Guide 7.8," Load Combinations for the Structural Analysis of Shipping
=
Casks for Radioactive Material," Revision 1, March 1989. [11]
NUREG/CR-6322," Buckling Analysis of Spent Fuel Baskets," dated May 1995. [16]
2.1.2.2 Exceptions to Codes and Standards Specific exceptions to the above codes and standards (Section 2.1.2.1) are identified in Table 2.1.2-1. These exceptions are justified based on other requirements for the design and analysis of the Universal Transport Cask and the Transportable Storage Canister, as well as based upon standard industry practice for the storage and transport of spent nuclear fuel.
O 2.1-8
1 SAR-UMS" Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 2.1.2.3 Load Combinations The load conditions that must be considered for the design of a spent-fuel transport cask are defined in 10 CFR 71 and Regulatory Guide 7.8 [11] and summarized in Table 2.1.2-2. The stresses in the containment structure and the noncontainment structures satisfy the stress limits defined in Regulatory Guide 7.6, " Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels." (10] These limits are essentially the same as those in the "ASME Boiler and Pressure Vessel Code,"Section III, Division 1, Subsection NB, for Class 1 Components. [6]
The Universal Transport Cask is analyzed as a pressure vessel, whose containment boundary is not breached during any Sading condition. The cask design allows for well-defined load paths that are analyzed by using straightforward, proven structural analysis methods. The structural analysis of the cask is a linear elastic analysis. In those cases where loadings are open to analytical interpretation, several load condition analyses are performed to bound the actual load conditions.
Each normal condition of transport and each hypothetical accident condition is characterized by a O.
combination of various loading types. These load type combinations define the total load criteria for each condition. The loading types that must be considered include ambient thermal, decay heat, external and internal pressures, bolt preload, inertia, and cask drop impacts. The cask is analyzed for normal conditions of transport in Section 2.6 and for hypothetical accident conditions in Section 2.7.
The total stresses in the cask components are calculated as the combination of stresses that results from each of the various load types (thennal, pressure, and mechanical) associated with a given load condition. For those load conditions and components analyzed by using classical hand-calculational methods, the total stress components are obtained by summing the individual stress components for each type ofload associated with the load condition. This summation is appropriate because the individual and total stress components are linear, elastic stresses.
2.1.2.4 Allowable Stress Limits - Ductile Failure Allowable stress limits are established for the cask containment structures, noncontainment structures, lifting trunnions, rotation pockets, bolts, and impact limiters. Regulatory Guide 7.6 O
4 2.1-9
i i
SAR-UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 and the ASME Code Section III, Subsection NB, are used to establish the allowable stress limits for the Universal Transport Cask primary containment boundary for both normal conditions of transport and hypothetical accident conditions. Material property data used in calculating the allowable stress limits correspond to the design stress intensities (S.), yield strengths (S ), and y
ultimate strengths (S ) presented in Section 2.3.
The cask primary containment boundary includes the following elements:
4.25 in.-thick cup-shaped bottom forging (Type 304 stainless steel),
67.61 in. ID,2 in.-thick inner shell (Type 304 stainless steel), to which the bottom forging is welded, Top forging (Type 304 stainless steel), to which the upper end of the inner shell is
- welded, 6.5 in. thick cask lid (Type 304 stainless steel), its inner 0-ring and 48 lid bolts (SB-637, Grade N07718 nickel alloy steel).
The vent port coverplate, inner 0-rings coverplate, bolts, drain port coverplate, inner 0-ring, and coverplate bolts are also part of the primary containment boundary. The allowable
~
stress criteria used for containment structures and bolting materials are summarized in Table 2.1.2-3. These criteria are consistent with Regulatory Guide 7.6 and applicable parts of Article NB-3000 and Appendix F of the ASME Boiler and Pressure Vessel Code. [17] Analysis section locations on the cask are identified in Section 2.10.2 to aid in the evaluations of the various load conditions.
In the evaluation of the cask primary containment boundary, no credit is taken for the Transportable Storage Canister, although the canister is designed as a confinement boundary to satisfy 10 CFR 72 [5] spent fuel storage requirements.
The noncontainment structural members are shown to satisfy essentially the same structural criteria as the containment structure, even though Regulatory Guide 7.6 applies only to containment structures. Noncontainment structures include all structural members other than the primary containment boundary components, but exclude the lifting trunnions, rotation pockets, and impact limiters. Allowable stresses for the noncontainment structures and noncontainment bolting materials are presented in Table 2.1.2-4.
2.1-10
SAR-UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 The allowable stresses for the lifting and handling components of the Universal Transport Cask are based on the requirements of 10 CFR 71.45(a) [1] which requires use of material yield strength with a load factor of 3.0. The lifting and handling components of the cask also satisfy the structural requirements ofNUREG-0612 [3] and ANSI N14.6 [4]: the maximum allowable stress is the material yield strength with a load factor of 6.0 or the material ultimate strength with a load factor of 10.0, whichever is less.
The lead (gamma-shielding material) is enclosed between the inner and outer cask shells and the top forging and bottom plate. The lead does not perform a structural function. However, the visco-clastic behavior of the lead is considered, where appropriate, in the analyses of cask shell components.
The impact limiters are not stress-limited. While performing their intended function during a free-drop impact, the impact limiters crush and thereby absorb the energy of the impact. The crushing of the redwood and balsa wood contained in the limiter dissipates the kinetic energy of
{
the cask while limiting the deceleration forces applied to the cask.
The Transportable Storage Canister is analyzed as a containmeut structure. The canister is structurally sound, criticality safe and contains a thermally efficient basket. The canister, which has a double welded closure, serves as a second enclosure of the spent fuel with the fuel cladding being the first enclosure. The basket provides the lateral structural support for the fuel assemblies and maintains the subcritical configuration during all normal conditions of transport and hypothetical accident conditions.
l O
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SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B Table 2.6.7.8-1 Resultant Stress Intensity Values in the Equivalent Ring Angle
(in-lb)
(in-lb)
(psi) 0.0
-1.693(10)*
3.060(10)'
13,819 5.0
-1.435(10)'
4.425(10)5 17,219 10.0
-1.178(10)'
5.564(10)5 20,498 15.0 6.482(10)5 23,310 i
20.0 7.181(10)5 25,525 25.0 7.669(10)5 27,098 30.0 7.952(10)5 28,021 35.0 8 039(10)5 28,309 40.0 7.942(10)5 27,987 45.0 7.671(10)5 27,093 50.0 7.242(10)5 25,671 55.0 6.667(10)5 23,775 60.0 5.962(10)5 21,466 65.0 5.145(10)5 18,817 j
70.0 1.094(10)'
4.232(10)5 15,917 J
75.0 1.171(10)6 3.243(10)5 12,892 80.0 1.227(10)6 2.194(10)5 9,952 85.0 1.261(10)'
l.107(10)5 7,531 90.0 1.272(10)'
O.0000 6,502 m The Angle is measured from the centerline of the trunnion.
0
- 2.6-131
SAR - UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 2.6.8 Corner-Dron The Universal Transport Cask is composed of materials other than fiberboard or wood, and the weight of the package exceeds 220 lb (100 kg). Therefore, according to 10 CFR 71.71(c)(8), this test is not applicable to the Universal Transport Cask.
2.6.9 Comoression According to 10 CFR 71.71(c)(9), this test is not applicable to the Universal Transport Cask because the package weight is greater than 11,000 lb (5,000 kg).
2.6.10 Penetration According to 10 CFR 71.71(c )(10), a penetration test involving a 13-lb (6-kg) penetration cylinder dropped from a height of 1 m is required for evaluation of packages during normal conditions of transport. However, Regulatory Guide 7.8 states that "the penetration test of 71.71 is not considered by the NRC staff to have structural significance for large shipping casks g
(except for unprotected valves and rupture disks) and will not be considered as a general W
requirement." Because the Universal Transport Cask has no unprotected valves or rupture disks that could be affected by normal conditions of transport, a penetration test is not performed.
O 2.6-132
SAR-UMS" Universal basport Cask April 1997 Docket N2. 71-9270 Revision 0 Figure 2.6.13-2 Support Disk Cross Section Configuration n=
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i y
(' ")-
. m..,s
<> wo3_
N_ ate:
Engineering drawings provide appropriate tolerances for dimensions shown.
I 2.6-203
SAR-UMS Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A O'
Figure 2.6.13-3 PWR Fuel Tube Configuration 9.65
=
- (. 25) e i
f o
I f
j c
u i
I i
l f
149 5 i
151.3 (153.00)
@7gg
^
v 158.3 (160.00) m i.,
j j
169.5 (171.20)
BORAL j
l 152.8 (1)
I 159.8 (2) j 170.9 (3) h.
l e
a u
(p, 1.3 o
e i
J i
.5 q
~ 1. 0 (8 90)
=
8 80 -
=
1 i
i b
i I
BORA.
(9 08)
=
O 2.6-204
SAR-UMS Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A q,
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13.6.4 3
Sf02 W
14 fi%:
- bbi;.
i%
- i Hb1 2.6-249
SAR - UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B e
g vs i-2 b;
i ah L
d d
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574 l
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63e 19.5-Li7.6 E r
g 2.6-250 l
SAR - UMS Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 Table 2.6.15.7-5 P,, + P + Q Stresses for Support Disk Foot Side-Drop, 90* Orientation, Thermal Case 2 Stress Allowable Margin of Section Sx Sy Sxy Intensity (ksi)
Stress (ksi)
Safety
)
29
-29.2
.1
.0 29.2 90.0 2.08 27
-15.5 13.0
-1.2 28.7 90.0 2.14 77
-15.5 13.0
-1.2 28.7 90.0 2.14 l
269
-15.5 13.0 1.2 28.7 90.0 2.14
)
17
-28.1
.4
.1 28.1 90.0 2.20 26
-26.9
.1
.1 26.9 90.0 2.34 23
-25.5
.0
.1 25.5 90.0 2.53 20
-24.3
.0
.1 24.3 90.0 2.70 14 17.1 10.0 9.5 23.6 90.0 2.81 15 17.1 10.0
-9.5 23.6 90.0 2.81 3
1.2 23.6
.8 23.6 90.0 2.82 4
1.2 23.6
.8 23.6 90.0 2.82 28
-18.9 2.2 5.1 23.4 90.0 2.84 16 14.5 9.4 8.1 20.5 90.0 3.40 13 14.5 9.4
-8.1 20.5 90.0 3.40 O
137
-13.7
-12.9 7.1 20.4 90.0 3.41 t
200
-13.7
-12.9
-7.I 20.4 90.0 3.41 31
-13.7
-12.9 7.1 20.4 90.0 3.41 33
-20.4
.1
.0 20.4 90.0 3.41 25
-l 7.2
-3.4 5.5 19.2 90.0 3.70 J
1
)
O 2.6-383 l
1 SAR - UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B e
2.6.15.8 Stress Evaluation of BWR Sunnort Disk for 1-Foot Comer-Dron Load Conditions As is the case in the PWR basket support disks (see Section 2.6.13.8), the g-loads of the corner-and oblique-drop conditions are bounded by the g-load of the end-and side-drop conditions-discussed in Section 2.6.15.6. Therefore, no separate evaluation of the 1-ft corner-and oblique-drop conditions is performed.
2.6.15.9 Stress Evaluation of BWR Sunnort Disk for Combined Thermal and 1-Foot Corner-Dron M Conditions The combined thermal and 1-f1 corner-drop and the combined thermal and 1-ft oblique-drop conditions are bounded by the results of combined thermal and 1-ft end-and side-drop conditions. Therefore, no separate evaluation of the combined thermal and 1-f1 corner-drop condition and the combined thermal and 1-ft oblique-drop condition is performed.
2.6.15.10 Stress Evaluation of Tie Rods and Spacers for a 1-Foot End-Dron Load Condition Tie rods and spacers are provided in the basket to maintain spacing of the support disks.
Transmission ofloads in different drop orientations of the BWR basket is similar to the transmission ofloads in the PWR basket discussed in Section 2.6.13.10. As is the case in the PWR basket, in drop orientations other than on the end, the spacers only experience a portion of the weight of the support disks, heat transfer disks, one end weldment, and the spacers that act along the axis of the cask. Thus, the end-drop is the critical loading condition.
During an end-drop, the weight of the support disks, weldment, aluminum heat transfer disks, and spacers and end nuts is supported by the spacers on the 6 tie rods. Compressive stress over the cross-sectional area of the spacers results. With the largest weight of the two BWR fuel classes, the total weight of the basket is [fflM lb. Because the weights of the bottom-end weldment @ lb) and the fuel tubes @@ lb) are transmitted directly into the end of the canister, the remaining load acting over the area of the spacers is QM lb. For the 1-ft end-drop the deceleration is 20 g, which results in a total end-drop load of @TpHD lb. The area in compression is n(3.0 - 1.75 )/4 = 4.66 in.2. The compressive stress is 2
2
%5R20/(6 x 4.66) = D35Tsj and is considered to be a membrane stress.
2.6-384
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B Table 2.6.15.13-1 Minimum Margins of Safety for the Top / Bottom Weldments for a 1-Foot End-Drop With and Without Thermal Stresses I
Allowable Component / Condition P (ksi)
S (ksi)
MS Top Weldment/1-ft 17.38 End-Drop Bottom Weldment/1-ft End-Drop Component / Condition P, + P (ksi) 1.5S (ksi)
MS 3
Top Weldment/1-ft M
26.07 l0.58 End-Drop Bottom Weldment/1-ft M
M M
End-Drop O
Component / Condition P + P, + Q (ksi) 3S,(ksi)
MS Top Weldment/1-ft M
52.14 g
End-Drop + Thermal Bottom Weldment/1-ft gg M
M End-Drop + Thennal O
2.6-389 1
SAR-UMS* Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 2.6.15.14 Suonort Disk Buckline Evaluation The BWR fuel basket support disk is subjected to compressive or inertial loads during a 1-ft drop j
of the cask onto an unyielding surface. Depending on the cask orientation for the 1-ft drop impact, both in-plane and out-of-plane loads may be applied to the support disk. The in-plane loadings (basket side impact component) apply compressive forces on the support disk and the out-of-plane inertial loading (basket end impact component) produces bending moments in the support disk.
Buckling of the support disk is evaluated in accordance with the methods and acceptance criteria i
of NUREG/CR-6322. The support disk buckling evaluation for the hypothetical accident conditions is presented in Section 2.7.10.3. The characteristics of the support disk are as follows:
2.6.15.14.1 Suonort Disk Buckline Evaluation Input Data Material:
SA-533, Type B, Class 2 carbon steel plate Material yield strength for buckling:
S, = 70.0 ksi at -40 F (Thermal Case 1)
S, = 59.3 ksi at 750 F (conservative)
S, = 60.5 ksi at 650 F (conservative)
Material modulus of elasticity for buckling:
E = 24.60 x 10 ksi at 750 F (conservative) 4 E = 29.90 x 10 ksi at -40 F (Thermal Case 1)
Impact load amplification factor:
20 g for the 1-ft side or end-drop.
4 E=25.56 x 10 ksi at 650'F (conservative)
Thermal Case 2 or 4 is bounding for Thermal Case 3.
2.6.15.14.2 Detailed Suonort Disk Buckline Evaluation Conservative temperatures are used in the support disk buckling evaluation.
O 2.6-390
SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B 2.7.1.7 Closure Analysis Section 2.6.7.6 provides a general description of the analysis approaches employed to demonstrate the structural integrity of the Universal Transport Cask closure assembly for hypothetical accident conditions. The materials of construction and the geometry of the components of the closure assembly are also identified in Section 2.6.7.6.
The Universal Transport Cask closure lid and the bolts are required to satisfy two criteria: (1) calculated maximum stresses must be less than the allowable stress limit (the material yield strength is conservatively selected), and (2) lid deformation or rotation at the O-ring must be less than the elastic rebound of the 0-rings. Analysis of the cask closure system in accordance with NUREG/CR-6007 is summarized below. Using consistently conservative assumptions, the analysis demonstrates that the cask closure assembly satisfies the performance and structural integrity requirements of 10 CFR 71.73(c)(1) for hypothetical accident conditions.
Accelerations for accident conditions are based on the impact limiter analysis for 30-ft drops.
Therefore, a design acceleration of 60 g bounds the calculated values. The following calculations are a summary of the NUREG/CR-6007 evaluation based on a calculated preload of lTi(86 lb/ bolt as presented in Section 2.6.7.6. Maximum stresses result during the top-end E drop (@ from axial plane of cask). Two load cases are considered for this evaluation.
The first case includes all load cases except rmw, which tends to counter the moment produced by internal pressurization. The second case conservatively applies puncture without internal pressurization Iwlen MIfsidernightyiEgl.
2.7.1.7.1 Closure Bolt Stress Evaluation Case 1-Accident Conditions (no puncture)
B552TELMSTlBitss72m Rb=ws;EssonRicasir. reg EFfJET97@sisTtIfimnYTro5ftWi5iiiiDRiilil[G 0
D~mTM9 2.7-31
i SAR-UMS* Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A p - f L& % G: w.xt JuGO gas ;lrL'.i1LV h,;a:
i M.Mk%%1 E lbs, load resulting from 0-ring compression t.! 3 where:
P,
=
Flf lbs, load resulting from internal pressure :
J P,
=
M lbs, load resulting from 60 g.-. ' A:. impact.
P.
=
.~ ;7)...gi4(dWQ.$th The shear load is l P, + P. + Pw@
= ]Ne. Ib 1
F,
=
z IM lb, load resulting from internal pressure an e ;;
where:
P,
=
O P.
=
ATWif4fm46mL*dthf6p, and
@j794Tb[loadJtesul_ ting:froml60 g toNwu cf drop]
P.
=
The bending moment is:
KbJM3RT-6Mc@M4 E_ 6 The resulting tensile stress in the bolt is o, =
'~
8 D
where D = 1.878 in., minimum bolt diameter.
The shear stress is 2.7-32
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B l
2.7.8.1.1 Finite Element Model Descriotion Finite element analyses are performed for the basket support disk for hypothetical accident conditions: the 30-ft side-drop impact co idition (60 g) and 30-ft end-drop impact condition (60 g).
f:','f.'.
. ~, '
' ~ 1 R.:.T..: G V. 3. MZ: J R O."
~
- b :";
2.7.8.1.2 i wx-=--= merlmpact Loadine Conditions The lateral impact load applied to the support disk for a side-drop accident includes the inertial weights of the canister, fuel assemblies, stainless steel tubes, and weight of the support disk itself. A detailed description of the loadings is provided in Section 2.6.13.2. The heat transfer disks are considered to be self-supporting. A 60 g load factor is used to amplify the weight of the basket components for the 30-ft side-drop condition.
2.7.8.1.3 PWR'siiritioWDIiESide-Dron Analysis Results Finite element stress analyses for the 60 g side impact load cases are performed for., different radial basket orientations---0,18.22*, ff14*, and 45*. The analyzed section locations are defined in Section f6.132and in Figures Ef3%fthtbugli27BWNEjlR5 Di6talchisted TaMiii2.R17ftM217'Rit?f15 lisiiiiiiSn55 plusadi5iiiii]isiidiiniItFssWSE55iiT0ZEm SilitimlEEtiMERE kmum mujemwmM9pm
. m,
.s 2.7.8.1.4 PWIFEHnbomomoEnd-Dron Analysis Results Finite element stress analyses of the PWR basket support disk are performed for a 60 g end impact (30-ft end-drop) ET6r711i~egnaTCEEd~BI%Me Biiili~fsr tSiriiid~d@fcSiidifi5ii'sTaie.,_s.seAti_ ally;z_gp&
O Fio!*
>a*aias p 53 -
2.7-89
SAR - UMS* Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A
+ ;-
,.y
..s.,.,.
' ' i ' l,~...,. I,$.
- t.,
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- 7... t -
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- T5_4di~dEiliTlii"TEF__2i71;F7TI 0
l l
2.7-90 l
l SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B j
O Table 2.7.8.1-1 Summary of Stress Evaluation of Support Disk-30-Ft Side-Drop Basket Stress Minimum Table Number Orientation (deg)
Thermal Case Evaluation Margin of Safety 2.7.8.1-2 0
P.
2.7.8.1-3 0
P,+P, 2.7.8.1-4 0
E P.
M 2.7.8.1-5 0
P,+P, 2.7.8.1-6 18.22 P.
2.7.8.1-7 18.22 i
P,+P, 2.7.8.1 -8 18.22 P.
2.7.8.1-9 18.22 P +P, ESNE Kh E
i.
E ESRW IEEE E
E c-M LT&t:03 vs 3
peri m anus a
c" O
EXIg!,133 45 a
P.
C 4.-
M TJ-13;"
45 6
P,+P, L6 45 E
P, c. ;s
@%8?f21H 45 E
P +P, M
O 2.7-91
i SAR-UMS Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A Table 2.7.8.1-2 P Stresses for Support Disk-30-Foot Side-Drop,0* Orientation, Thermal Case E M
M M E m
m.
=
1;b I
t p (I k
kN f
1 ph
{
!(
l g.
g
}f ll h'
I)!k Il91...
.9'.
4 I
i
?
68)
).0!
iii.72 1-i Ol 2.7-92
SAR-UMS" Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A O
imummms
&T h.
E m
E M
M u
M M
{
m mE as R
M M
M l
M M
M M
M M
g m
E M
M
\\
k>w gg M
E ME BM 151 M
M M
M M
11 8 Edig M
EE IE iiRE M
M I!E MBE ES IIIIB O
E iME ESM M
M M
M IE M
RE M
M M
D23 UEE M
B5 E
IBM M
EG M
M M
sLZi BE
~.
M N1 MB MB RM M
im RW ILE M
D R&E M:43 EM M
B2 M
AR F24 lif0 ME M
M g
pg gg s,..
BE M
DiB EE M
E DE N
IB M
DEIR BE M
M N
M Ma BRI M
32 w
21;g RE o
sg gm 45 2 EE wa M
w IG M
ElfAi HE 1515 15 i
M
!!!.M iis;53 gal gg BIE M
pm E2E B5 E Lfl w
M M
If41
[4%U f24f Esf RM M
IO l
2.7-106a
SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B O
Summary of Stress Evaluation of Suppoit Disk-30-Ft End-Drop O
t O
2.7-106b
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B O
N
~*
- V'
'f,.._
,-,. ',,h*',".
I i G
Gh *,
88
,83 8
1
I
'4 *
ie 8
+-.*i '-
NIEil"#EN O
KiGHeTaDiffiiilemonstraf5%RWRfs@MWdisWiiiseTihm O
l l
2.7-115 i
SAR-UMS* UniversalTransport Cask December 1997 Docket No. 71-9270 Revision UMST-97A 0
TIIIS PAGE INTENTIONALLY LEFT BLANK O
O 2.7-116
SAR-UMS" Universal Transport Cask December 1997 Docket No. 71-9270 Revision UMST-97A O
THIS PAGE INTENTIONALLY LEFT BLANK O
O 2.7-117
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B 2.7.8.4 Fuel Tube Analysis The fuel tube provides a foundation and sealed cavity to mount BORAL poison plates within the fuel basket structure. The fuel tube does not serve a structural function relative to the support of the fuel assembly. The fuel tube design is presented in Figure 2.6.13-3. To ensure that the fuel tube remains functional when the cask is subjected to design load conditions, a structural evaluation of the tube is performed for both the end and side-impact load conditions.
2.'.8.4.1 Fuel Tube End Impact Analysis During the postulated cask end impact, fuel assemblies are supported by the cask bottom for the bottom-end drop and the lid for the top-end drop. The fuel tubes do not carry fuel assembly load.
Therefore, evaluatien of the fuel tube for the end-impact load is performed by considering the weight of the fuel tube subjected to the cask deceleration carried by the minimum tube cross section. The minimum tube cross section is located at the contact point of the tube with the bottom weldment. From the dimensions of the tube shown in Figure 2.6.13-3, the minimum cross-sectional area is O
Area = (thickness)(mean perimeter)(0.048) 2
= [(8.8+0.048)4]
= 1.69 in,
The total bearing load on the tube and BORAL during the cask bottom-end impact is 9,180 lb, (60 g x 153 lb). The maximum compressive and bearing stress in the fuel tube is 5,432 psi (9180/1.69). Limiting the compressive stress level in the tube to the material yield strength ensures that the tube remains in position when the cask is subjected to the postulated end-drop.
Type 304 stainless steel yield strength is $@(j psi at a conservatively high temperature of 500"F for the axial location on the fuel tube that has the minimum cross-section area. Using this criterion to evaluate the tube for the end-drop load, a margin of safety of +2.57 is achieved.
2.7.8.4.2 Fuel Tube Side-impact Analysis During the cask side-impact load configuration, the fuel tube is supported by the fuel basket's stainless steel support disks. The fuel basket support disks support the full length of the fuel tube, and are spaced at 4.42 in. apart (which is ag_!! one half of the fuel tube width of 2.7-118
SAR-UMS Universal Transport Cask December 1997 j
Docket No. 71-9270 Revision UMST-97A l
8.8 in.). Considering the fuel tube subjected to the 60 g [1] side-impact deceleration and the 30 support locations provided by the basket support disks, the fuel tube shear stress is Impact shear load
(60)S/30
lb Shear area of tube
= (0.048)(@(2) = _
in 2
Shear stress of tube =OM-1 psi.
The yield strength of Type 304 stainless steel at " J is M psi. Using an allowable shear stress equivalent to half the yield strength of the tube wall material,9750 psi, results in a large positive margin of safety. The conservative evaluation of the tube loading resulting from its own mass during the side-impact configuration indicates that the tube structure will maintain position and will function.
The load transfer of a fuel assembly to the fuel basket support disk when the cask is subjected to a side impact will be through direct bearing and compression of the distributed load of the fuel O
assembly through the fuel tube to the support disk web. The analysis considers the fuel assembly load as a distributed pressure en the inside tube surface.
The fuel tube structural performance is nonlinear when subjected to either of the postulated impact loadings discussed above, and is not adequately evaluated by using classical methods.
Therefore, a finite element model of the tube representing three support-disk tube span lengths is developed to evaluate maximum accumulated plastic strain. The finite element model is then modified to consider the main tube wall thickness of 0.048 in. as the only material subjected to a distributed pressure load representative of the fuel assembly deceleration of 60 g. Figure 2.7.8.4-1 presents the half-symmetry fuel tube finite element model used for the maximum plastic stress fuel assembly distributed loading evaluation. Fuel assembly stiffness is not considered in the development of the imposed load to the fuel tube for either of the two analyses.
The tube is modeled with the ANSYS plastic, quadrilateral shell element (PLANE 43) with large deflection capability. All energy is absorbed into tube strain by conservatively fixing the displacement of the tube at support disk spacing perpendicular to the direction of load. Material properties reported in NUREG/CR-0481, SAND 77-1872, "An Assessment of Stress-Strain Data sO 2.7-119
SAR - UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B Suitable for Finite Element Elastic-Plastic Analysis of Shipping Containers [24)," are used in these analyses.
Results from the 60 g fuel assembly distributed load on the main tube wall verify that the maximum plastic stress in the tube is less than.
ksi. This maximum plastic stress is local to the sections of the tube resting on the steel support disks. The maximum plastic stress is more than a factor of two less than the tube wall material allowable strength of 62.7 ksi.
Defining acceptable elastic-plastic response at one half the material performance permits margins of safety to be evaluated with significant margin beyond the chosen limits relative to actual material failure. Using this methodology to evaluate total cumulative strain shows a margin of safety of (40/1.5)- 1 = + Large.
MS
=
Similarly, the margin of safety for elastic-plastic stress becomes MS = (62.7 - 19.5)- 1 = E
(@l9.5)
The evaluation of maximum cumulative plastic strain and maximum elastic-plastic stress result in significant margins when evaluated with respect to an allowable chosen to be 50% of the material allowable plastic response.
Both the maximum cumulative strain and the elastic-plastic stress analyses indicate that the tube position within the support basket is maintained.
Assurance that the BORAL poison remains within the sealed casing is evaluated by considering that loads produced by the BORAL and skin mass decelerated by 60 g are maintained by the seal weld. Total load and resultant stress are calculated as follows:
F = Volume x Density x 60 F m = (8.2 x 0.075 x 1.0) x 0.098 x 60 = 3.62 lb 30 2.7-120
SAR-UMS" Universal Transport Cask April 1997 Docket No. 71-9270 Revision 0 4.3.2.2 Correlation of Permissible Leakaoe Rates to Standard Leakaoe Rates The maximum allowable leak rates for the hypothetical accident conditions calculated previously are correlated with standard leakage rates by using the methodology described in Section 4.2.1.2.
The results are tabulated in Table 4.3-3 for the casks containing PWR and BWR fuel.
4.3.3 Containment criteria The allowable leak rates calculated previously for the hypothetical accident conditions are much greater than those for the normal conditions of transport calculated in Section 4.2.1. Because the cask containment is demonstrated to be maintained under hypothetical accident conditions (Section 2.7), the maximum permissible leak rates for normal conditions of transport are more limiting and are therefore used for the establishment of the maximum allowable leak rates for the containment system fabrication and periodic verification leak test calculations and test acceptance criteria.
O J
4.3-3
)
SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B e
Table 4.3-1 Allowable Release Rate Source and A Inputs for PWR Cask:
2 Accident Conditions Crud Gas Volatiles Fines Total Total Activity per Assembly (Ci)
N/C 3.06E+03 9.75E+04 1.61 E+05 2.61E+05 Releasable Activity per Cask (Ci) 2.92E+02 2.20E+04 4.68E+02 1.16E+02 2.29E+04 Cask Volumetric Activity (Ci/cm')
4.gE-05 3.lgE-03 N E-05 1.NE-05 3.g0E-03 A2 Value(Ci) 10.80 282.26 5.31 0.13 298.50 Fraction of Activity 0.013 0.962 0.020 0.005 1.000 Fraction of Activity / A2 (1/Ci) 0.0012 0.0034 0.0039 0.0390 0.0474 Mixture A2 Value(Ci) 21.09 Table 4.3-2 Allowable Release Rate Source and A Inputs for BWR Cask:
2 Accident Conditions O
Crud Gas Volatiles Fines Total Total Activity per Assembly (Ci)
N/C 1.09E+03 3.53E+04 5.58E+04 9.21 E+04 Releasable Activity per Cask (Ci) 3.33 E+03 1.84 E+04 3.95 E+02 9.37E+01 2.22E+04 Cask Volumetric Activity (Ci/cm')
4.82E-04 2.6SE-03 5.7lE-05 1.3[E-05 3.2[E-03 A2 Value (Ci) 10.80 282.24 5.28 0.14 298.46 Fraction of Activity 0.150 0.828 0.018 0.004 1.000 Fraction of Activity / A2 (1/Ci) 0.0139 0.0029 0.0034 0.0303 0.0505 Mixture A2 Value(Ci) 19.81 O
4.3-4
SAR-UMS* Universal Transport Cask April 1998 Docket No. 71-9270 Revision UMST-97B l
Table 4.3-3 Standard Leak Rates:
Accident Conditions Reactor Type PWR BWR Assembly Type B&W 15x15 GE 9x9-2 l
Flow Regime Choked Choked Standard Rate (cm'/sec) 4.gE-4 A
I l
O O
4.3-5
O THIS PAGE INTENTIONALLY LEFT BLANK O
i l
SAR-UMS Universal Transport Cask April 1998 Docket No. 71-9250 Revision UMST-978 List of Tables Table 5.1-1 PWR Maximum Total Dose Rate Summary - Normal Conditions [ mrem /hr]... 5.1-7 Table 5.1-2 PWR Maximum Total Dose Rate Summary - EAccident Conditions
[ mrem /hr]...............................................................I Table 5.1-3 6Md @dsb MEs db 3EiFdi).. 5.1-8 Table 5.1-4 J."shinn&161GysE651 X.MV%Ms60 M].....................................................................................................5.1-8 5
B B
E Table 5.2-1 Description of Fuel Assembly Types.......................................................... 5.2-10 Table 5.2-2 Representative PWR Fuel Assembly Physical Characteristics......................... 5.2-11 Table 5.2-3 Represen:ative PWR Fuel Assembly Hardware Data Per Assembly................ 5.2-12 Table 5.2-4 Nuclear and Thermal Parameters of PWR Fuel Assemblies with 3.7 wt. %
g U235 Enrichment,45,000 MWD /MTU Bumup,10 Years Cooling Time.... 5.2-13 d
Table 5.2-5 PWR Fuel Assembly Activated Hardware Comparison [y/s],10 Year Cooling Time...
.......................................................................5.2-13 Table 5.2-6 Representative BWR Fuel Physical Characteristics.................................... 5.2-14 Table 5.2-7 Representative BWR Fuel Assembly Hardware Data.................................... 5.2-14 Table 5.2-8 Nuclear and Thermal Parameters of BWR Fuel with 3.25 wt. % U235 Enrichment,40,000 MWD /MTU Burnup and 10 Years Cooling Time...... 5.2-15 Table 5.2-9 BWR Fuel Assembly Activated Hardware Comparison [y/s] at 40,000 MWD /MTU Burnup,10 Year Cooled....................................... 5.2-15 Table 5.2-10 One-Dimensional Dose Rate Results Relative to PWR Design Basis........... 5.2-16 Table 5.2-11 One-Dimensional Dose Rate Results Relative to BWR Design Basis.......... 5.2-17 Table 5.2-12 Design Basis PWR 10 Year Fuel Neutron Source Spectrum......................... 5.2-18 0
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SAR-UMS Universal Transport Cask December 1997 Docket Ns. 71-9270 Revision UMST-97A List of Tables (Continued)
Table 5.2-13 Design Basis PWR 10 Year Fuel Photon Spectrum........................................ 5.2-19 Table 5.2-14 Design Basis PWR 10 Year Hardware Photon Spectrum.............................. 5.2-20 Table 5.2-15 Design Basis BWR 10 Year Fuel Neutron Source Spectmm.......................... 5.2-21 l
Table 5.2-16 Design Basis BWR 10 Year Fuel Photon Spectrum....................................... 5.2-22 Table 5.2-17 Design Basis BWR 10 Year Hardware Photon Spectrum.............................. 5.2-23 Table 5.2-18 Source Rate Versus Burnup Fit Parameters................................................... 5.2-24 Table 5.2-19 Scale Factors Applied to Neutron Source Rate at Average Burnup................ 5.2-24 Table 5.2-20 PWR Axial S ource Profile.......................................................................... 5.2-25 Table 5.2-21 BWR Axial Source Rate Profile.................................................................... 5.2-26 Table 5.3-1 Radial Shield Regions Employed in One-Dimensional Model......................... 5.3-26 Table 5.3-2 Universal Transport Cask One-Dimensional Model Axial Dimensions........... 5.3-27 Table 5.3-3 Source Region Summary for PWR Three-Dimensional Model........................ 5.3-28 Table 5.3-4 Source Region Summary for BWR Three-Dimensional Model....................... 5.3-28 Table 5.3-5 PWR Top Model Radial Detector Description-Normal Conditions............... 5.3-29 Table 5.3-6 PWR Top Model Axial Detector Descriptien-Normal Conditions................. 5.3-29 Table 5.3-7 PWR Bottom Model Radial Detector Description -Normal Conditions......... 5.3-30 Table 5.3-8 PWR Bottom Model Axial Detector Description-Normal Conditions........... 5.3-30 Table 5.3-9 PWR Top Model Radial Detector Description - M............ 5.3-31 Table 5.3-10 PWR Top Model Axial Detector Description-M............ 5.3-31 Table 5.3-11 PWR Bottom Model Radial Detector Description - MMac WhM..... 5.3-31 Table 5.3-12 PWR Bottom Model Axial Detector Description-K6cidist96ndiB~ans....... 5.3-31 Table 5.3-13 Homogenized Fuel Region Isotopic Composition [ atom /b-cm]..................... 5.3-32 Table 5.3-14 Isotopic Compositions of PWR Fuel Assembly Non-Fuel Source Regions.
[at o m/b-c m].................................................................................
i Table 5.3-15 Isotopic Compositions of BWR Fuel Assembly Non-Fuel Source Regions
[a to m/b-c m]................................................................................... 5.3 Table 5.3-16 Isotopic Compositions of PWR Canister Annular Region Materials (One-Dimensional Analysis Only) [ atom /b-cm]................................................. 5.3-33 Table 5.3-17 Isotopic Compositions of BWR Canister Annular Region Materials (One-l Dimensional Analysis Only) [ atom /b-cm].................................................... 5.3-34 O
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