ML20010F659
| ML20010F659 | |
| Person / Time | |
|---|---|
| Site: | 07105787 |
| Issue date: | 07/24/1981 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20010F658 | List: |
| References | |
| 19558, NUDOCS 8109110105 | |
| Download: ML20010F659 (9) | |
Text
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U.S.CEPARTMENT CF CNE;tGY Cc2 rorm tv.sIa u t -n 1 CERTIFICATE CF COMPT.!ANCE IO For Rooicective Materials Pacmage.
1a. Carrificate Nurnoer j to. Revision No.
j ic. Tsemage iaentirication No.
to. Psge No. l 1e. Totae No. Psges.
S787 1
l USA /S787/SLF(DCE-CR) 1 l
2
- 2. P5 TEAM 8LE
- a.
TNs certificate is issued to satistv Sections 1733*.a.173.094,17335. and 17336 of tne Cecertment of hnsoor ation Mazarcous Matenais Reguations ta9 CPR 170 1891.
Ob.
The cecmaging and contents coscribed in item 5 besow, meets tne safety stanoarcs sat iortn n Succart C of Titte 10. Coos of itecerai Regusations.Part 71.**Pacmaging of Radioactive Meterial for Transport ena Transportation of Radioactive Mater as Under Cartain Concitions!*
Oc.
This certificate cose not reiseve tne consagnor from comosiance with any recuarernent of tne regulations of tne U1 Ceoartrnent of Trariscortation or otner apotecnole regusatory agencies,incluoing tne governrnent of any country trircug.a or into wnica tne cacxage will be transoorted.
- 3. This certificate is issued on tne casis of a safety anssysis report of tne cacmage cosign or acosication-(1) Prepared av IName and addressl (2) T;tle and scentification of reoort or acotecation:
(3) Cate:
Safety Aralysis Report fcr Acril 1978 Cak Ridge IIaticnal Lateratory Packaging (SAPP) of the Cak Post Office Scx X Ridge IIaticral Laborator / Shipping Cask D-38 Cak Ridge, Tennessee 37830 Report CPNL-S406
- 4. CcNCITICNS This certificate is concitionat upon tne fuifiliing of too reou.rernents of Sucoart O of 10 CF R 71, as acoticacie, and tne concitions saecified in item 5 meiow.
- 5. Cescriction of Pacmagsng and Autnoritec Contents. Moces Nurnoer, Fessite C ass. Ciner Caeciticns, and Aererences.
(a) Packacinc:
(1) Model: D-38 Shippirq Cask (2) Cescripticn:
Packagirq for transport of fissile and large q m tities of radioactive material as solids including mixed fissicn products, fuel elements, and waste, which are centained within irner DOT Speedal Fem Centainers er meet Special Fem encapsu-lat1Cn. Pluteniu:1 is doubly contaired.
The irrer cavity of the cask is a 300 Series Stainless Steel Schedule 40 pice with inside dimensicns 6-1/16 in. diameter x 13-13/16 in. high. Re cuter shel:
is a 300 Series Stainless Steel Schedule 30 pipe 20-1/2 in. high. Shieldirq censists of depleted uraniu:1 metal with a thickness of 2-3/4 in.
The tcp cpen-ing plug is held in place by eighteen 1/3-in, studs eqaipped with nuts. The cluq is sealed with a necprene gasket. The cask is neunted en a 14-in. square x S/8-in. thick base plate. Six of the st:.:ds are extra Iceg sc
- tat a protec-ive shrcud may be utilized during transpcrt. The cas't is bolted with tour 1-in.
bolts to a 3-ft. sqt.are pallett.
'Ihe gross weight of the package is 1S2S lb.
6e. Cate of issuance:
July 24, 1981 l 6b. Emoiration Cate:
FOR THE U.S. CEPARTMENT OF ENEAGY 7a Address (o/ OCE /nwap Offica/
7b. Signature, Navne, and Title lod DOE Accrowng Officiarl U.S. Depart =ent of Energy Post Office Scx E Cak Ridge, Tennessee 37830 William H. Travis, Director l Safety & Enviremental Centrol Divisicn 8109110105 810824 DR ADOCK 07105 J
x
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Page 2 cf Certificate No. 5787 (3) Drawirqs The cask is described arxi fabricated in accordance with thien Carbide Corpcra-tien, Nuclear Divisicn, Cak Ridge Naticnal Laboratcry drawirgs:
M-12133-CD-12SE. Rev. 12 ard M-12166-CD-022 Rev. 1.
(b) Centents:
Type ard form cf caterial:
(1) Solid, large c;uantity of radicactive caterials, fissile arxi ncnfissile, packaged in DCI' Specificatien 2R irrer Centainer(s) or meeting Special Fcnn. Pluteniun will be doubly centained inside the cask. Dry heat lead does not exceed 80 watts. Heat loads in excess of 20 watts are shipped " exclusive-use" of vehicle.
(2) External radiaticn levels will te within the levels prescribed by CCri Regula-tiens, Title 49 CFR 173.393.
(3) Specific 11::iits of centents:
235 (1) 500 g of g,
(ii) 350 g of 23 k er 239Pu, (iii) 350 g of any ccabination of (i) er (11) abcVe.
(c) Fissile Class:
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N
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.~ %W Cesartrr.ent ci Er.ercy Cak Ricce Cceratieni
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Cak R!cce.~ennessee 37830 July 27, 1981 Unicn Carbide Corporaticn Nuclear Divisicn ATIN:
Dr. Herman Postma, Director Oak Ridge Naticrial Laboratory P.O. Scx X Oak Ridge, Tennessee 37830 Gentlemen:
SAFETY ANALYSIS REPCRT FOR PACKAGING (SARP) OF die OAK RIDGE NATIONAL LABCRATORY SHIPPING CASK D-38, REVISION 1, REPCRT OPIL-5/.06/R1 Errlosed is Revisico 1 of DCE-OR Certificate of Carpliarre 5787 which is our approval for the subject D-38 Cask.
The criginal of this certificate Ms been transmitted directly to the authors so that it may beccme part of the SAPP.
Your cocperaticn is appreciated.
Sincerely,
/K Joseph A. L Assistant Manager SE-332:WAP for Energy Rese and DevelepTnt FSS: 1253
Enclosure:
Above stated (7) cc:
R. F. Hibbs, UCC-ND, w/o encl.
V. J. D'Amico, SE30, w/o encl.
C. H. Durham, AD-l.6, w/ encl.
W. H. Travis, SE-33, w/ encl.
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1
T ORO REVIEW OF REPORT ORNL-5406/R1 Safety Analysis for Packaging (SARP) of the Oak Ridge Natimal Laboratory Shipping Cask D-38, Revision 1 Raymond E. Harris William A. Pryor This review is made under the requirements of DOEM 0529 and 5201.
The container is cne-of-a-kind and is used to transport fissile and large quantities of radioactive materials. These materials will be shipped as solids.
A.
General Standards for All Packaging:
1.
The material and construction are such that there will be no signif-icant chmical, galvanic, or other reaction arrong container ccmpo-nents or between the package ccuponents and the package contents. The eutectic formation between the stainless steel shell and the uraniun metal shield has been prevented by the following:
a.
Building a 10-mil gap between the stainless steel and uraniun.
b.
Using nonnachined surfaces to prevent intimate contact the differ-ent metal.
c.
Filling the gap with heliun.
The use of the heliun also prevents oxidation of the uraniun.
2.
There is no external shield or shock absorber associated with the package; however, a shmud is utilized during shipment to prevent the closure plug lifting ears frun being used for cask tiedowns.
3.
The requirments for positive closure of the ccntainer are fully met.
4.
Lifting devides for packagirrJ:
The ccntainer is designed to be lifted by two radial 1-in.-300 series stainless steel diameter trunnicns. Each trunnion is fitted and welded into holes in the cuter skin of the container. They are supported outboarxi by a 3/8-in.-thick, 2-in.-wide stainless steel strap. See Fig. 3.1 in the SARP for more details about the trunnions.
The closure plug is provided with two 1/2-in.-thick lugs for lifting purpose. Each lug is attached to the skin of the top plug by 1/4-in.-full-around fillet welds. See Fig. 3.5 for more details about the lifting lugs. A shroud is provided to prevent use of the lugs for lifting the entire container.
The capabilities of the ccntainer lifting device and of the closure plug bail to meet applicable requirements were analyzed in the SARP based on mechanical properties of the material of ccnstruction shown in Table 2.1 of the SARP and cn standarti analytical techniques. ORNL also assumed that only cne of the container or closure plug lifting devices would be used for that purpose. OR review indicates that reascnable basic assumpticns are used in the analysis. OR calcula-tions also substantiate conclusions in the SARP that the container lifting device and the closure plug bail meet lifting requirements for those devices. Further, since both devices are located en the outer skin of the container, failure of the devices would not inpair the contairrnent or shielding properties of the package.
5.
Tiedown devices for packaging:
The container is normally shipped bolted to its skid. Four 1-in. 8-1.0 bolts are used for this purpose.
The container-skid ccrnbination is attached to the bed of the transport vehicle by use of eight wire ropes as shown in Fig. 3.7 of the SARP. The evaluation is based on a range of tieckun gecrnetries for the container to vehicle bed case ard on mechanical properties of the material of construction referenced
1 I
above. Standard calculaticnal techniques are used in the evaluaticn to denmstrate compliance of the device with applicable requirements.
OR believes that reasonable basic asstmpticos and calcuational tech-niques have been used in the SARP for evaluating tiedown capabili-ties. Thus, OR agrees with ORtL that the device meets stress limita-tion requirenents for tiedown devices.
When used for tiedown purposes, failure of the ccntainer lifting device under excessive load would obviously impair the ability of the package to meet other requirenents of General Standards for all Packaging. However, OR feels that the device used for tiedown meets the intent of this latter requirement.
4 B.
Structural Standards for Type B and Large Ouantity Packaging Well recognized theory is used in the SARP to demonstrate the capability of the ccntainer to meet requirecer.ts in the stru:tural standards for Type B and large quantity packaging. OR review indicates that ort 1 has adequately covered and adequately demonstrated in the SARP the ability of the package to meet these requirements.
?
C.
!!cnnal Ccniitions of Transport Standarx1 techniques arr' test results related to this container have been used in the SARP to denonstrate ccmpliance of the ::entainer with all requirements for normal ccoditions of transport. The OR review substanti-ates.the ORIL conclusion that the container meets these requirements.
D.
Hypothetical Accident Ccnditicns The evaluation in the SARP of the ccntainer to meet requirements under hypo-thetical accident ccnditions is based cn standard calculational techniques ard/or spec.lal analytical methods developed by ORtL frun extrapolaticn of test data related to this container. Results of the evaluation indicate cczn-t pliance of the ccntainer with all of the subject ccmditions. The OR review of the SARP and related reference doc.unents substantiates this conclusion.
However, ORNL has assuned for part of the analysis an unusually high specific energy value (100,000 psi) for steel in conpression. As used in the SARP, OR believes that this specific energy nunber should be 60,000 psi. Additionally, scme test data frun drop tests by ORNL has not been interpreted in a cmservative manner. Therefore, for the folb.ing rea-sons, OR feels that defonnation to the ccntainer frcxn a 30-foot free drop has been underestimated in the SARP by as nuch as a factor of about 1.6.
a.
The data for steel shown in Table 2 of the SARP was obtained frun 30-foot drop tests using solid circular cylindrical specimens with diameter of 1"
x 1"
1 cog (reference 1). This value for a large-diameter thin-walled member should be less than values reported in reference 1 for small-diameter solid test specimens. Further, the data for steel in Table 2 was derived by a least square method. A curve alcng the lower portion of the actual test data inplies a specific energy significantly lower than the 100,000 psi value used in the SARP.
b.
Curves developed by Clark (reference 2). demonstrate the yield stress dependence on strain rate. A curve for 30-foot drop (velocity of 44 ft/sec) was interpolated frun Clark's data and was used by ORNL to develop a FORTRAN program for estimation of the response of cylindri-cal lead-shielded ccntainers to end impacts (reference 3). The inter-polated curve also implied a specific energy significantly below 100,000 psi. Output frun the FORTPAN program was in reascnable agreenent with results obtained frun drop tests by CRNL (references 3 l
and 4).
c.
The Hanford Engineering Developnent Laboratory has reported rcon temperature tensile test data for 304 stainless steel at intermediate and high-strain rates (reference 5). This test data implies a specif-ic energy of about 50,000 psi.
i
Based on the above ccnsideraticos, OR believes that a 30-foot drop of the container frun any orientation would result in a maxinun deformation to the container body of abou'.
1.7 in. This defonnation ccrupares with a value of 1.00 in. shown 1.
t SARP. The larger eged defonnation value does not prevent th r:.ainer meeting applicable contairinent and shielding requirements.
E.
Nuclear Criticality Safety 233 235 The specified mass limits for the fissile isotopes of U,
U, and Pu are less than their respective mininun critical mass under all conditions of nederation. KENO calculations show that the package meets conditions for Fissile Cl ss I.
F.
Quality Assurance The quality assurance requirements for fabricaticn and maintenance were reviewed by the OR Quality & Reliability Divisicn and wem found to be generally acceptable.
G.
Distributicn The SARP was distributed under TID 4500, UC71.
H.
Ccnclusion The requirements of DOD4 0529 and 5201 have been met. Therefom, it is reccmnended that the D-38 Shipping Cask be certified.
l t
References J. H. Evans, Experimental Study of the Stress-Strain Properties of 1.
Cask Materials Under Specified Impact Conditions, Proceedings of the International Sympc sium on Packaging and Transportation of Radioactive Materials, CONF-740901-P1, September 1974 2.
D. S. Clark, The Influence of Impact Velocity on the Tensile Characteristics of Some Aircraf t Metals and Alloys, NACA TN-868, Washington, D.C.,
October 1942.
3.
J. H. Evans, Structural Analysis of Shipping Casks, Vol. 13, CEIR: A FORTRAN Program for Estimation of Response of Cylindrical Lead-Shielded Casks to End Impacts, ORNL/TM-1312, June 1974.
4.
L. B. Shappert and J. H. Evans, The Obsolete Cask Program, Vol 14:
Initial Tests, ORNL/TM-1312, November 1974.
5.
J. FL Steichen, High Strain Rate Pkchanical Properties of Type 304 Stainless Steel and Nickel 200 (R>F14), HEOL-TME-145, September 1971.
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