ML20154B317
ML20154B317 | |
Person / Time | |
---|---|
Site: | 07109287 |
Issue date: | 10/01/1998 |
From: | David Tiktinsky NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
References | |
NUDOCS 9810050159 | |
Download: ML20154B317 (16) | |
Text
. . . _ . __ -
l 1
',i October 1, 1998
, MEMORANDUM TO: Cass R. Chappell, Chief Package Certification Section, SFPO FROM: David Tiktinsky, Project Manager i Package Certification Section, SFPO !
1
SUBJECT:
MEETING
SUMMARY
CONCERNING THE STERIGENICS INTERNATIONAL TRANSPORTATION CASK l
l l Attendees: l NB.C SteriGenics PacTec l David Tiktinsky Eric Beers Steve Streuther !
! Andrew Gaunt Mark Smith Joe Nichols l Bernie White j Li Yang i Chris Brown Ross Chappell jotroduction A meeting was held at the request of SteriGenics, in Rockville, Maryland, on September 15,1998, concerning a possible request for a Certificate of Compliance for the SteriGenics International Transportation Cask.
Discussion
- 1. Storige.iics discussed the design of a tranportation package for
- Co as a sealed 3 o' "9.
- 2. Discussion centered around the scale model testing and computer analysis of the impact limiters and the thermal performance of the package.
Docket No: 71-9287
Attachment:
Meeting Handout Distribution:
SeBeill NMSS r/f $N9CNCinted Attendees SFPO r/f Meeting Notebook NLOsgood h \ b@D l "C" = Copy without attachment / enclosure "E' = Copy with attachment / enclosure 'N' = No copy OFC NMSS/SFPO E NMSS/SFPO O NMSS/SFPO C NAME DHbnsky ERZiegler CR M DATE 9/ b/98 9d/98 /8/ / /98 9810050159 981001 D PDR C
ADOCK 07109287 pog agg,$4C[,,h g g t!
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DACTEC ~
~~. Lock.ging .Lehnacinc. .9/15/98 i ay. --
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l Presentation to the NRC l
SteriGenics International Transportation Cask .
Design and Certification Update ,
I I
September 15,1998 ;
i p nc_scusac Page 1
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DACTEC hkaging 5 -ha<Jogy,Inc.
9/15/98
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Meeting Agenda
. Cask Design Changes
. Current Packaging Description
. Analysis Result Updates
. Completed Static Testing
. Planned Testing
. Discussion i
fi!e: NRC_SGud,a Page 2
i 9/15/98
~
Cask Design Changes ,
Parameter Previous Current 8
Payload Co Sealed Source Weight 20,000 18,500 Size 036 x 50 036E x 50 i
Drain Design Bottom Drain Bottom Drain Shielding Design Enhanced Enhanced Thermal Shield Internal Double External impact Limiters 020 x % O20 x M Body Construction SStl Forgings / Pipe SStl Castings w/ (2) weld joints w/ (1) weld joint p,: nc_saw Page 3
b8,3,Tl?,.1 ei,sies
, A Q smannenuoumn. noa. Company l
Previous Cask Design bumwhu%weggvf
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AC TEC
'-_ _ackaging .1.echnology,Inc. 9/15/98 a y e .-- - - c-pa,,,
1 Current Cash Design
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WSW##627#9Akr lMIhl
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19.00 j
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lDACTEC
'L=ck= ring I echnoiery.Inc.
'i 9/15/98 A g nessumumsommasu. mesh Conyery Current Packaging Description Summary of Weights and Dimensions Cask Weight ~ 18,500 lbs (configured for transport) a impact Limiter Weight ~ 1,700 lbs each a
Payload Weight = 50 lbs
- Empty Cask Weight ~ 15,050 lbs
. Cask Enveloping Dimensions a
036-1/2" x 50" long without impact limiters 060" x 76"long with impact limiters i
n:nc_ sana Page 6 )
9/15/98 i
Current Packaging Description ,
Summary of Payload 6
. Maximum isotopic inventory of Co
. Two bounding payloads are considered:
i flie: NRcyco P8QO l
9/15/98 Analysis Result Updates Thermal '
. Payload consists of 8 Co
. Analytical methods used to demonstrate cask thermal response for both NCT and HAC fire event
. Thermal analyses using finite element computer code (ANSYS*)
. Double thermal barrier surrounding outer wall prevents lead gamma shield melting during the HAC fire event (external thermal shie!d)
. Localized hot spot due to puncture damage of thermal shield Personnel barrier maintains accessible packaging components below 185 F for an " exclusive use" shipment p,: sac _s<w Page 8
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lDACTEC '
' E _v ring bdeAMm 9/15/98
- a -gg. _
cm I Analysis Result Updates !
Shielding
. External dose rate levels below limits (cask surface bounds)
. Analysis being updated to reflect current cask design
. Monte Carlo Analysis used to calculate level of gamma heating in pencils, basket and cask walls; results used in thermal calculations-i fue: NRC_SGU doc SQO 0
lDACTEC ~
I _m.,ing'~~5 -hwy.Inc.
^
9/15/98 a -m- - - c ,, ,
Analysis Result Updates Structural (Drop Analysis)
. Wall thickness of impact limiters decreased to reduce impact loads
. Impact force-deflection values have been calculated and compared with static crush test results
. Excellent agreement with test results up to ~50% deflection; reasonable agreement with test results for >50% deflection p:ac_ scan Page 10 i
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DACTEC
'~L.ek.ging I -h-%y.Inc.
9/15/98 A-BS-- --
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1/4 Scale Static Crush Test Results (3) Orientations Tested
. CG Over Corner
. End
. Side ~
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DACTEC 3 ek.ging E ~W.Inc.
9/15/98 AN- - sumConcery CG Over Corner Test Results L
cornerori.nt non 160 t
u0 sie.T : /
LS-DYNA ResuRs e
--- w w m ,
120 , !
100 -
a0 5
80 . -
20 -
A O
0 0.5 1 1.5 2 2.5 3 3.5 h (in) i pu: a c_sc a u Page 12 -
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DACTEC
'.L.ck.ging I -haalogy;I=
9/15/98 a-gg-;--- - . cm End Test Results '
End Orientation 300 275 250 Static Test MYNA Anaysm
/
225 Finered LS-DYNA ResuRs
['
- - - wrim.ie c>on twm.iion ;/
$7s b /
I / D[N 5,so
,25 / i" 200 7$ [
so . l 2s _ ;
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0 0.2 0.4 0.6 0.8 1 1.2 1.4 1.6 Deformation On) pa: nac_scissac Page 13
DACTEC
'~Lackaging .1.cchnology;Inc.
9/15/98 x -gg ---- n.cm Side Test Results Side Orientation 15o 00 -
14o.00 /k 130.00 g
/,
120.00 NYNA Anaysis )
- - - Approximate Drop Deformation 110.00 =
soo m / Ml 9,M -
- N- -
h 8o.00 ,'
g mm. // -
60.00 s_
So, F :
.. / :
ao w l mm :
1o.00 -
. i o.oo ' -
o o.5 1 1.5 2 2.5 Deflection (in) pa:ac_scusoc Page 14 w_._ . , . - _- _ - -_e- - + _ , - u,- A-c .s_e_ .=_=~--_-_T-%, w.-- +
- _ _ _ _ _ - _ _ _ _ _ _ .___m - _ - _ . _ _ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _
.L, AC T.Lechnology;I=
"{k.ging EC
- 9/15/98 :
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Planned Testing 1/4 Scale Impact Limiter Drop and Puncture Test
. CG Over Comer
. End
. Side Drop Test Puncture Bar Drop Orientations .
Or.ientations t
vm f! + f a xx m x w xw p:nc sansoc Page 15 ,
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