ML20010F628
| ML20010F628 | |
| Person / Time | |
|---|---|
| Site: | 07106088 |
| Issue date: | 06/30/1981 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20010F627 | List: |
| References | |
| 19557, NUDOCS 8109100529 | |
| Download: ML20010F628 (8) | |
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U.S. OEPARTMENT OF ENERGY (11 77)
CERTIFICATE OF COMPLIANCE
""'I For Radioactive Materials Pacmages ta. Certificate Number 1b. Revision No.
Ic. Pacuage Identification No.
Id. Page No.
Ie. Total No. Pages.
6088 1
USA /6088/BLF(DCE-CR) 1 2
- 2. PREAMBLE 2a.
This certificate is issueo to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Deoer. nent of Transportation Hazarcous Materiais Regulateons (49 CFR 170-189).
23.
The packaging and contents described in item 5 below, meets the safety standaros set 'ortn in Subpart C of Titte 10. Coce of Feoeral Reguiations. Part 71,"Pacxaging of Radioactive Material for Transport and Transoortation of Radioactive Material Uncer Cartain Conditions."
2c.
This certificate does not reheve tne consignor from comonance witn any reouirement of tne regulations of tne U.S. Geoartrrient of Transoortation or other aposicanie regulatory agencies, including the government of any tauntry througn or into wnicn the pacmage will be transported.
- 3. This certif;cate is issued on the basis of a safety anaiysis report of the pacnage design or apohcation-(1) Prepared by (Name and ac*fressl (2) Title and toentification ci report or apoocation:
(3) Date:
August 1979 Safety Analysis Report for Oak Ridge flational Laborator/
Packagirq (SARP) of the Oak Ridge Post Office Scx X Naticnal Laboratorf Garden arrier IIo. 2, '.evisicn 1.
c Oak Ridge, Temessee 37830 Repcrt CPUL-5408/R1
- 4. CONOtTIONS This certificate is conditional upon the fetiinng c,f ine requirements of Subpart O of 10 CF R 71, as apphcaolo, and the cond:tions specif;ed in stem 5 below.
- 5. cescription of Pacmaging and Autnorized Contents. Medei Ni.mt.ier, Fissile Class Other Concitions,and
References:
(a) Packacina (1) Model: CRNL Gartien Carrier No. 2.
(2)
Description:
A 304L stainless steel e-: cased lead shipping cask.
Packaging for solid radioactive materials as whole or sectioned tW radiated ard irradiated fuel elements, fissicn products, and wastes. The 25 in. ODx45 in.
high cylindrical cask consists of lead, 8-3/16 in tLck, ercased in 304L stain-less steel. The inner cavity is 7 in. IDx24 in. high. Access to the cavity is through a plug equipped with an 0-ring for top loading ard two sliding drawers for bottcm cpening. Side cover plates for the drawers and the bottcm cover plate, which are equipped with gaskets, are bolted to the cask body. The O-ring and gaskets are made of necprene.
The radioactive material is centained within a DOI' Specification 2R centainer as specified, which is positioned within an inner centainer made cf 304L stainless steel 5 in, diameter schedule 10 pipe. The overall dimersicrs are 6-7/8 in. CD :
23-1/2 in. high and the inside dimersions are 5.36 in. dia. x 20-11/16 in. high.
The inner container is covered with a 10-bolt flange equipped with an 0-ring trade of neoprene or Silastic.
During shipnent, the cask is bolted with 8 1-1/2 in. x 5-1/2 in.1cng bolts to a 5 ft. x 5 ft. x 7-1/4 in. high skid. The cask is covered with a 43 in. CD x 52 in. high fire shield consisting of a 2 in. thickness of Kaowood irsulation 6a. Date of issuance:
June 30, 1981 l 6b. Exoiration Date:
FOR THE U.S.OEPARTMENT OF ENERGY la. Address lof OCEissuing Omcel Tb Signature. Name, and Title (of DOE Approvong Official)
U.S. Depart:nent of Enert;y Post Office Bcx E William H. Travis, Director Oak Ridge, Tennessee 37830 Safety & Envircrriental Centrol Division l
8109100529 810824
{DRADOCK071*ne, PDR
)
sd Page 2 cf 2 (Batrock f,Wilca cerami cutside and 3/16 in. irsidec fiber irsulaticn) encased in maple wood pads fastened to thof the fire shield is pa The void between the tcp ofsteel plate--1/2 in t e inside of fire s,hield are po illed with drawer the cask ard irside cover plates.
and is atcached to the skid by The fire shield is aligned maple ; cod Tm (3) s ticned ever.
Drawirgs:
8 1-1/2 in dia. x 3-1/2 inen the skid by 2 locatirg pin the
. Ices bolts.
described in Oak Ridge t;atiThe cask, skid, fire shield ocal Laboratcry Crawings:, ard inner flarged c M-ll332-D4-Olo-E-4 icatiens M-lli 32-D4-Oll-E-3 are W il332-D1-012-E-2 M-ll332-DI-013-E-0 M-ll332-D4-014-E-2 Wil332-Di-015-E-1 M-11332-Di-016-E-O M-ll332-DI-Ol7-I)-O Sll332-D4-018-E4 l
M-ll332-DI-Ol9-I)-0
\\
W ll332-D1-020-D-4
(
4 12124-CB-043-D-2 M-12166-CD-037-D-2 M-12166 '.".J-043-E-1 (b)
Centents (1)
Type and Fem of Material Solid, fissile, and large radiated er irradiated fuel quantity of radicactive trateri l and wastes elements, whole or The radioactive materials 2R irner co.
sections, solid i'issicn prcdua s in the fo ntainer Maximxn qumtipr 9*# E#as specified in Repcrt CEtL 540 are (2) contained within a DOT Specifi 8/Rl.
- cts, (a) 500gofh'5 3
9*
cation (b)
U cr 350 g of (c)
U or Pu cr 350 g of any carbiration of f (3)
Other limitatices:
issile material.
(a)
Maximun heat load-100 W (b)
Extemal radiation cbse rat (c)
Fissile Class:
es--limited to IX7T Regulatico I
s, 49 CFR 173.393.
_. _, - - ~ ~ ' ' ' '
ORO REVIEV OF REPORT ORNL-5408/R1 Safety Analysis for Packaging (SARP) of the Oa
'ge Natic.al Laboratory Garten Carrier No. 2, Revisicn 1 Raymond C. Harris William A. Pryor This review is made under the mquirments of DOB4 0529 and 5201.
Le container is one-of-a-kind arxi is used to transport fissile and large quantitie:s 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 chenical, galvanic, or other reacticn among container cmpo-nents or between the package cmpcnents and the package contents.
2.
A thennal shield consisting of solid cmponents covers the package during transport. The effectiveness of the package and its thennal shield would be unaffected under nonral conditions of transport.
3.
'1he reqairencnts for positive closure of the ccntak.ar are fully met.
4.
Lifting devides for packaging:
Three separate systems can be used for lifting the package: (1) Four ears are located symnetrically near the top of the fire shield. The ears are 5/8 x 12-1/2 x 12-1/4-inches and they are attached to the skin of the fire shield by 5/8-inch full-around fillet welds.
A 3-1/4-incti eye is located in each ear for lifting purposes. The material of construction is idmtified on drawing M-12166-CD-043, Rev.
1, as " steel," presunably carbon steel. (2) A 1-1/2-inch-diameter loop, in the form of an inverted "U,"
is located in each corner of the 5 x 5-ft. container-l' ire shield transport skid. The material of ccxwtructicn is designated " mild" steel (see Drawing D-55999, Rev. 6). Each loop is reportedly attached to the skid by a
_)
1/2-inch full-amund fillet weld. (3) Four 2-inch-dianeter lifting trunnims am located cn the ccntainer itself. Each set of trunnions is cmnected by a 3/4-inch-thick 304L stainless steel strap (see Dwg.
M-11332-D4-012).
The top closure plug is designed to be lifted by a 3/4-inch eye located in a lug attached to the top closure plug. The steel lug is 1-inch in thickness and is attached to the skin of the plug by a 3/8-inch full-around fillet weld. A cover is provided to prevent use of the lug for lifting the entire container.
The capabilities of each ccntainer lifting device and of the lifting lug for the top closure plug wem analyzed by ORNL based on mechani-cal pmrties of the materials of ecostructicn shown in Table 2 of the SARP ans on well-recognized analytical techniques. OR review indicates that reascnable basic assurptions are used in the analysis.
Further, OR calculaticns substantiate conclusicos in the SARP that the container and top plug lifting devices meet applicable cbserva-tion that failure of any of the devices would not inpair the ccntairment or shielding properties of the package.
5.
Tiedown devices for packaging:
The container is nonnally shipped bolted to a skid and enclosed in its fire shield. The fire shield is also bolted to the skid. Cables (eight total) are used to tie down the fire shield and the skid to the bed of the transport vehicle. For the sake of analysis, the l
following tiedown cases are ccnsidered in the SARP: (1) the tiedown of the ccntainer to the skid, (2) the tiedown of the fire shield to the skid, and (3) the tiedown of the fire shield to the bed of the transport vehicle. The first two cases involve the use of eight 1-1/2-inch-dianeter steel bolts, respectively. A 45-degree cable angle (as specified in the loading procedure) frun the verticle and use of the lifting ears are assuned for the third case. Mechanice
. properties referenced above am used for all cases. Standard calcula-ticnal techniques are used in the evaluaticos to denonstrate ccmpli-ance of each case with applicable requirements. OR believes that reascnable basic assurptions and calculational techniques have been used in the SARP for evaluating tiedown capabilities. Thus, OR agrees with ORNL that each case meets stress limitaticn requirenents for tiedown devices, when used for tiedown purposes, failure of the fire shield lifting ears under excessive load would obviously impair the ability of the package to meet other requirements of General Standards for All Packaging. However, OR feels that the device meets the intent of this latter requirement.
B.
Stmctural Standards for Ty'pe B and Larce Quantity Packaging Well recognized theory is used in the SARP to demonstrate the capability of 'che ccntainer relative to requirements in the structural standards for Type B and large quantity packaging. OR review indicates that ORNL has adequately covered and adequately dancnstrated in the SARP the ability of the package to meet these requirements.
C.
t W 1 Conditions of Transport Standard techniques and test results related to this container have been used in the SARP to demonstrate ccmpliance of the container with all requirements for nonnal ccnditicns of transport. The OR review substanti-ates the ORNL conclusicn that the container meets these requirenents.
D.
Hypothetical Accident Ccnditions The evaluaticn in the SARP of-the ccntainer to meet requirenents under hypothetical accident conditions is based on standard calculational tech-niques and/or special analytical methods developed by ORNL frun extrapola-ticn of test data related to this ccntainer. Results of the evaluaticn indicate ccmpliance of the ccntainer with all of the subject conditions.
-_-_-_-__a
. he OR review of the SARP and related reference docunents substantiates this ccoclusim. However, ORNL has assuned for part of-the analysis an unusually high specific energy value (100,000 psi) for steel in cmpres-sicn. As used in the SARP, OR believes that this specific energy number should be 60,000 psi. Additionally, scme test data frun drop tests by ORNL has not been interpreted in a ccnservative manner. Therefore, for the following reasms, OR feels that defonnation to the ccntainer frun a 30-foot free drop has been underestimated in the SARP by as much as a factor of about 1.6.
a.
The data for steel shown in Table 2 of the SPEP was obtained frun 30-foot drop tests using solid circular cylindrical specimens with diameter of 1"
x 1"
long (reference 1). Bis value for a large-diameter thin-walled member should be less than values reported in reference 1 for stall-diameter solid test specimens. Further, the data for steel in Table 2 was derived by a least square method. A curve alcog 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 dependenm on strain rate. A curve for a 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 respcose of cylindri-cal lead-snielded containers to end impacts (reference 3). The inter-polated curve also implied a specific energy significantly below 100,000 psi. Output frun the FORTRAN program was in reasonable agrement with results obtained frun drop tests by ORNL (references 3 and 4).
c.
The Hanforti Engineering Developnent Laboratory has reported rocm tmperature tensile test data for 304 stainless steel at intennediate and high-strain rates (reference 5). This test data implies a specif-ic energy of about 50,000 psi.
a-
. Based cn the above ccnsideraticns, OR believes that a 30-foot drop of the ccntainer fran any orientaticn would result in a rnaxinun defonnation to the ccntainer body of abcut 3 in. This deformation ccmpares with a value of 1.% in. shown in the SARP. The larger expected deformaticn value does not prevent the container meeting applicable ccntainment and shielding requirements.
E.
Nuclear Criticality Safety 2330, 235U, and Pu The specified mass limits for the fissile isotopes of are less than their respective mininun critical mass under all conditions of moderation. Due to the 9-in.-thick lead shield in the cask plus the spacing provided by the thennal shield, the fissile material is effective-ly isolated interacticnwise. Thus, the package meets cc.riitions for Fissile Class I.
F.
Quality Assurance The quality assurance requirements for fabrication and maintenance were reviewed by the OR Quality & Reliability Division and were found to be generally acceptable.
G.
Distribution The SARP was distributed under TID 4500, UC71.
H.
Conclusion The requirements of DOEM 0529 and 5201 have been met. Therefore, it is reccnmended that the Garden Carrier No. 2 be certified.
l l.
References 1.
J. H. Evans, Experimental Study of the Stress-Strain Properties of Cask Materials Under Specified Impact Conditions, Proceedings of the Internativ6;1 Sy=pasium on Packaging and Transportation of Radioactive Materials, CONF-740901-P1, Septeuber 1974.
D S. Clark, The Influence of Impact Velocity on the Tensile Characteristics 2.
of Some Aircraft Metals and Alloys, NACA TN-868, Washington, D.C.,
October 1942, A
3.
J. H. Evans, Structural Analysis of Shipping Casks, Vol.13, CEIR:
FORTRAN Program for Estimation of Response of Cylindrical Lead-Shielded Casks to End Impacts, ORNL/TM-1312, June 1974.
L. B. Shappert and J. H. Evans, The Obsolete Cask Program, Vol 14:
4.
Initial Tests, ORNL/TM-1312, November 1974.
304 J. M. Steicuan, High Strain Rate Mechanical Properties of Type 5.
Stainless Steel and Nickel 200 (RM-14), HEOL-TME-145, September 1971.
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