ML20134B443
| ML20134B443 | |
| Person / Time | |
|---|---|
| Site: | 07109073 |
| Issue date: | 07/30/1985 |
| From: | Temus C NUCLEAR PACKAGING, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25588, RR4376, NUDOCS 8508150624 | |
| Download: ML20134B443 (19) | |
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July 30, 1985 DE7cttg7 File: OH-142 g
Ref:
RR4376 ef Mr. Charles E. Ma a,
hef Nuclear Regulatory C M ssion Transportation Certification Branch M
g J(gfj Washington, D. C. 20555
Dear Mr. MacDonald:
Enclosed please find eight copies of the revised pages to convert Revision 11 of the OH-142 Safety Analysis Report to Revision 12 of that report.
The changes made to the Safety Analysis Report are in response to some concerns expressed to Stephen Goetsch of our company by your associate, Dick Odegaarden.
The changes made to the SAR for revision 12 merely limit the requested revision of foam properties to the OH-142 MK I design with a 16 inch diameter central secondary lid.
This smaller, lighter lid requires much less bolt strength to secure it during end impact.
The margin of saf ety of the secondary lid closure bolts on the 16 inch lid is
+2.36 against yield criteria, whereas the margin of safety of the other lid designs for the unrevised foam properties is
+.27 against ultimate criteria.
The margin of safety against yield criteria for the other designs, although not reported in the SAR, would be +.0 6 7.
- Clearly, the margin of safety for the combination of revised foam properties and 16 inch diameter secondary lid is very much greater than the previously acceptable positive margin.
In addition to the analysis previously contained in the SAR, a thread engagement calculation was included in this submittal.
To assure that the thread engagement required to fully develop the strength of the bolt is present on packages in service, the required thread engagement has been added to Drawing AL-20-202, as well as a note specifying that the revised foam properties allowed in NPI.F6 foam are allowed only for the 16 inch central secondary lid option.
This revision, including the revised drawings, has been copyrighted.
This entire submittal contains proprietary information per the notice on the flyleaf of this report.
We are aware of your requirements to place this submittal in the Public Documents Room.
This may be cone with our permission; however, this permission should not be construed as a waiver of or in any way prejudicial to our lawful proprietary rights to this material.
It is done only to facilitate the issuance of a Certificate of Compliance.
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O July 30,.1985 Mr. Charles E. MacDonald, Chief Nuclear Regulatory Commission Page 2 I
j Photostatic copies of this copyrighted material may be made by i
NRC review personnel for convenience and for record purposes j
within the Commission's files; however, permission to copy the material is expressly denied to persons other than Commission personnel of for any other reason.
Copies of the material may not be released by the commission except to the Public Documents i
Room.
1 If you have any questions, please do not hesitate to call either j
myself or Stephen Goetsch.
Thank you very much.
Very truly yours, I
NU A
INC.
/ //
g.,p h, a
j Char es J. Temus Te nical Director j
Enclosure:
As stated l
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'NhPts OH-142 SAR Rev. 12. 7/85 5
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Insert / Delete Instructions for Rev.12, OH-142 SAR I
li i
Delete Pages Insert Panes i
1-147 1-147 1-150 1-150 i
1-151 1-151 l
1-152 1-152 j
1-153-1-153 i
i 1-154 1-154 1-155 1-155 1-156 1-156 Dws. AL-20-202 Rev. J Dws. AL-20-202 Rev. E i
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- NuPas OH-142 SAR Rav. 12, 7/85 APPENDIX 1.10.2 EIPANSION OF ACCEPTABLE STRESS-STRAIN RANGE FOR IMPACT LIMITERS OPMEnsme rmgje; 1.10.2.1 Introduction a
Due to minor changes in the formulation of the NPI.F6 polyurethane foam used in the OH-142 ove rpacks, it has become apparent that some foam placed in accordance with it may not exhibit stress-strain properties as shown in Figure 1 of Section 1.3 above.
Some samples of foam taken during f abrication activ-ities indicate that the uppe r bound of the stress-strain curve in Figure i should be raised.
The revised limits of the stress-strain curve are shown in Figure 1.10.2-1.
An analysis of the effect of this revised upper bound on the package margins of safety is presented below.
These revised limits apply to the Model OH-142 MK I design with 16 inch diameter secondary lid opening only.
1.10.2.2 Eqd Imeset The end impact drop orientation is the drop orientation most se riou sly af f ected by the rev ised foam propertie s.
NuPac's EYDROP program is used to i
evaluate the forces generated from a 31 foot drop onto an unyielding surface.
EYDROP, like its sister programs CYDROP and SYDROP, has been used to demonstrate compliance of several other packages (such as the T-3 Spent Fuel Shipping Cask, Certificate of Compliance No. 9132, and the NuP:.
PAS-1 package, Ce rtifica te of Compliance No. 9184) to the 10 CFR 71 drop events.
Table 1.10.2-1 pre sent s output f rom EYDROP for the OH-142 using the rev ised l
uppe r bound of the stress-strain curve as shown in Figure 1.10.2-1.
The t able 4
was generated using the equivalent out side diameter of the package.
- This, equivalent diame ter is calculated by determining the actual end area of the overpack and finding that diameter of a circle which has the same end area as i
the actual overpack.
Also, the analysis assumes the entire overpack area is effective, corresponding to both the most conservative assumption presented in the body of this report as well as the results of numerous test programs.
O 1-147
' NuPaa OH-142 SAR R v. 12, 7/85 The table predicts that for the revised stress-strain limits, the acceleration 4
j experienced by the package would be 117 g's, slightly higher than previous analysis had predicted.
The predictal deflection, 3.94 inches, is slightly less than previously predicted.
J r
1 The 16 inch diame ter lid we ighs approxima tely 450 lbs, and the projected weight of the payload on the 16 inch lid is 2
2 (16 /66 )(10000) = 590 lbs.
l Therefore, the 16 inch diameter lid bolts must react 1040 lbs of weight.
The force in each bolt may be calculated as below:
(1040)(117)/8 = 15210 lbs.
l The yield strength of the A320 L7 bolts is 105000 p si.
Since the 7/8 inch 2
bolts have a tensile stross area of.487 in, the al lowable load in the bolt 1
may be calculated:
(105000)(.487) = 51135 lbs.
1 The margin of safety for the bolt is then l
(51135/15210) - 1 = +2.36 The thread engagement required to fully develop the strength of the A320 L7 stud may be calculated using the following formula from An Introduction lg 1]ur.
De s ian ad B.g]ta v lo r 2.f. Bo l t ed J o i n t s, by J. H. B ic k f o rd, p. 272, f o r th e c a s e j
where the nut resterial is weaker than the bolt material:
i s t(2A )/ ((S,g) (n) (n) (D) [(1/2n) + 0.57735(D - E,,,)])
L, = S 3
where S,g = yield strength of the stud = 105000 psi 2
A
= tensile area of the stud =.487 in g
l Snt = yield strength of the nut material = 38000 ps!
n
= number of threads per inch = 9 1-150
Ray. 12, 7/85 NmPaa OH-142 SAR
)
D
= Stud nominal diameter =.875 in.
E,,, = pitch diameter of nut =.8028 in.
5 I
PP Substituting into the above equation ytekD5.P"W2T~AR3 JY a/N\\!!,ejt n-I u
m L, = (105)(2)(.487)/((38)(n)(9)(.875)[(1/(2)(9)) +.57735(.875
.8028)])
L, = 1.12 in.
The studs are required to have at least 1.25 inches of engagement, so the threads are stronger than the studs themselves.
The margin of safety against 1
bolt thread failure can be calculated, assuming that development strength of l
the lid threads is proportional to the length of engagement:
M. S. = (1.25/1.12)(51135/15210) - 1 = +2.75 i
Therefore, the revised stress-strain limits do not affect the ability of the l
package to resist the ef fects of a 31 foot end impact onto an unyielding f
surface.
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1-151 i
l
- NaPas OH-142 SAR Ray. 12, 7/85 3][
1.10.2.3 Corner Imonet The change in the upper bound of the stress-strain curve causes Cases 3 and 4 discus sed in the body of this report to be obsolete.
Tables 1.10.2-2 and 1.10.2-3 p r e s e nt the same drop orientation (approximately 40 degrees f rom vertical) as previously analyzed. From the tables, it can be seen that the maximum acceleration experienced by the package is 77.2 g's, slightly higher than previously used for design. This slight increase in the package acceler-ation (77.2 s's versus 76.4 g's used previously) will have an af fect on the package primary closure device design loads.
Using the method shown in the Safety Analysis Report to be very conse rvative, the loads in the ratchet binders can be calculated:
(19900)(77.2)(38.125)cos 400= (1011660)(15.83)cos 40' +
+ 2(3 8.125) P (3.5) b Pb = 122,195 lbs. per bindo'r The margin of Safety for the binder is then:
M. S. = (160,000/122,195) - 1 = +0.31 1-152
/
NaPac OH-142 SAR Rev. 12, 7/35 p
p s
(
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TABLE 1.10.2-2
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NUCLEA4 PACEAG!NG PR0P4!EfARY 87.19.11 45/ se/ 84 OH-142 FULL 55 INCH Nott PActAGE WEIGHf e 64000. (t33)
PACKAGE EXIERNAL L ENGTH
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OVERPACK LENGIN e
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CWGP Mf!CNT 31.30 (FT)
ORIENT &f!DN ANGLE o 44.09e (DEC4EE3 WRf 70 VERTICAL)
PLATEAU CRUSN STRESS
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(CEFAULT TAEf.N AT 10 PC? STRAIND STRES$/3fRAIN EVALUATES IN 1/2 CRu5N PL ANE ELLIPSE 47.
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- NuPa3 OH-142 SAR h
'C 9
Ray. 12, 7/85 The effect of losing the capability of one of the ratchet binders prior to the drop event is analyzed in a more realistic manner, which results in a ratchet binder load approximately one third of that used for design.
It is 3
inconceivable that the slight change in the foam stres s-strain curve would affect that analysis such that the resulting margin of safety would be less than that calculated conservatively above.
The binder retaining pins are calculated to have a capacity of 261,316 lb s.
I The resulting margin of safety is therefore:
M. S. = (261,316/122,195) - 1 = +1.14 i
The Mark I overpack retainer pins have a capacity of 32,800 lbs. in double shear.
The body of the report demonstrates that shear of the pin is the controlling condition rather than shear out.
1he pin load is calculated as below:
P = (122195 lbs.)(3000 lbs.)/(19900 lbs.) = 18421 lbs.
o The margin of safety is then:
i l
M. S. = 32,800 lbs./18,421 lbs. - 1 = +0.78 i
Bearing stresses in the overpack attachment lugs (p. 1-75) can be calculated as follows:
i l
l fbeg = 122,195/((1.50)(1.625)) =.50,131 psi l
The margin of safety is then:
l M. S. = (90,000/50,131) - 1 = +0.80 i
l
{
The weld capability of the Mark I hold-down lus weld is 157,500 lb s.
The margin of safety is then:
1 i
i r
1 i
1-1$$
h 9) s7 Ray. 12, 7/85
'NaPa] 011-142 SAR p
M. S. = (157,500/122,195) - 1 = +0.29
\\d' The shear-out capacity of the binder attachment lugs is calculated to be 197,350 lbs. Therefore, the margin of safety is:
M. S. = (197,250/122,195) - 1 = +0.62 All of the margins of safety calculated in Section 1.7.1.2 of the report that are affected by the revised stress-strain limit on the foam have been presented above.
None of the margins have been affected s ignif ic an t l y, sud all remain positive, even with very conservative analysis techniques. There-fore, the revised stress-strain limit s do not affect the ability of the package to resist the ef fects of a 31 foot corner drop onto r.n unyleiding surface.
1.10.2 1 11dg. I n o a e t NuPac's SYDROP program was used to evaluate the ef fects of a 31 foot drop onto
\\v the package side.
Analyses were performed assuming the the entire length of the overpack is ef fective in resisting the impaut and as suming that only that portion of the overpack between the cask shleid and the impact surface is effective in resisting the impact.
The latter assumption was made to develop a very conservative prediction of acceleration.
Tests have shown that this assnaption does not accurately model the actual response of an overpack to impact loads.
The res ul t s of the saa lyse s a re pre s e nt ed in Tab le s 1.10.2-4 and 1.10.2-5.
The tables show that the more rigorous integration techniques employed by the SYDROP program result in predicted accelerations less than those used for design.
As a result, the margins of safety presented in the body of this report under predict the actual margins of safety, even with the revised foam data.
Therefore, the revised stress-strain limits do not affect the ability of the package to resist the ef fect s of 31 foot side drop onto an unyielding surface.
U 1-156
-~
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.N.OTES : UNLESS OTHERWISE SPECIFIED 1.
MATERIAL: LOW CARBON HOT ROLLED STEEL:
~
{
. PLATE & SHAPES CONFORM TO ASTM-A516, GR70
'O
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MATERIAL : ASTM-A514 oR A517 g
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3.
FOAM: 1,000 PS! CRUSH STRENGTH RIGID POLYURETHANE. PER NUPAC FOAM SPECIFICATION NPI-F6. REVISED FOAM PROPERTIES ALLOWED O,
FOR 16 INCH DIAMETER CENTR AL LID OPTION.
A y' -* ~4k 4.
LEAD: PER FEDERAL SPECIFICATION QQ-L-171E. GRADE A OR C.
D Ol 5.
REMOVED 6.
REFERENCE CATA:
CASK WT: 54,000Las.
'* h PAY LOAD: 10,000Las.
g 'D GROS $ WT: 64,000Las.
7.
REMOVED 8.
ALL WEUING PROCE'URES AND PERSONNEL SHALL BE QUALIFIED IN ACCORDANCE WITH ASME CCCE, SECTION IX.
son os C
9.
ALL WELDS SHALL BE INSPECTED VIA NDT METHODS AS FOLLOWS:
LIFTING LUG AND CIRCUMFERENTIAL CONTINUOUS TOP VIE'4 SHOWING OPTIONAL, WELDS: MAGNETIC PARTICLE PER AS*E CODE SECTION lit, DIVISION I, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 7.
LONGITUDINAL SHELL WELD: RADIOGRAPHIC PER ASP.E CODE SECTION !!!, DIVISION I, SUBSECTION NB, ARTICLE NS-5000 AND SECTION V, ARTICLE 2.
- 10. AS AN OPTICN, 12 GA. NO. 304 STAINLESS STEEL CLADDING MAY BE INSTALLED ON THE INTERIOR & EXTERICR SURFACES OF THE FLASK BODY a INTERIOR SURFACES OF ottait S THE UPPER LID, s SEAL WELDED ALONG ALL EDGES SEAMS.
\\
[ot tan
= - - - -
g 4 ONE C0AT PHEN 0LINE 305, OR ONE PRIMER C0AT (5 MILS)
MOBIL CHEM EP0XY NO. 89W1 4 CNE FINISH COAT (5 MILS) MOBIL CHEM EP0XY N
L-NO. 89W9.
bl6 -
- 12. 'C0AT ALL EXPOSED EXTERIOR SURFACES OF FLASK BETWEEN UPPER AND LOWER g'
OVERPACKS WITH ONE (1) COAT (MIN 3/16 THK) "ALBl-CLAD
- NO. 81. AS AN OPTION, A 10 GA. NO 304 STAINLESS STEEL THERMAL SHIELD MAY BE INSTALLED PARTI AL SECT A. A SHOWING OPTIC BETWEEN THE OVERPACKS.
- 13. FLASKS FABRICATED PRIOR TO 3/84 MAY BE MADE USING ASTM A36 MATERIAL.
(FLASK BODY OUTER SHELL SHALL BE 11/8 IN. THICK, WITH FULL PENETRATION DOUBLE SIDED V GROOVE WELD FOR VERTICAL SEAN.)
h NOMINAL AIR GAP (MINIMUM.05. MAXIMUM A2 in.)
N, PACKAGE $ HALL $$ 44AM8t0 4 Enfra.0 se ACCORDA#sts wrfM fle MGAMEMr.MTS Of te CF98 F144fe)
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NUCLEAN PA CK A QlNO, INC.
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19ULK HCLIN LHil'l'ING f L A5K i
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UNITED STATES
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'o NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D. C. 20555 O.e U) t a
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FCTC: RHO P
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k AUG 0 3 1985
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MEM0RANDUM FOR:
Steve Scott, Chief
'i's Y #
Document Management Branch, TIDC FROM:
Charles E. MacDonald, Chief Transportation Certification Branch, FC, MiSS
SUBJECT:
PROPRIETARY / COPYRIGHTED DATA - PUBLIC DOCUMENT ROOM The following application and/or drawings marked " Proprietary / Copyrighted" should be placed in the NRC Public Document Room:
Nuclear Packaging, Inc. (NUPAC) application dated July 30,1985 Authorization:
NUPAC letter dated July 30, 1985.
b CarI'esE.
cDolaI,"Ctrief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS
Enclosure:
NUPAC ltr dtd 07/30/85 r
.