ML20010A178
| ML20010A178 | |
| Person / Time | |
|---|---|
| Site: | 07105795 |
| Issue date: | 06/22/1979 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20010A176 | List: |
| References | |
| 19433, NUDOCS 8108110148 | |
| Download: ML20010A178 (6) | |
Text
,
e U.S. DEPARTMENT OF ENERGY coE Form Ev41a u l-7 n CERTIFICATE OF COMPLIANCE U C" U For Radioactive Materials PaJages Ia. Certificate Number Ib. Revision No.
Ic. Package identification No.
Id. Page No.
Ie. Total No. Pages.
5795 1
USA /5795/BLF(DOE-OR) 1 3
- 2. PREAMBLE 2a.
This certificate is issued to satisfy Sectior s 173.393a,173.394,173.395,and 173.396 of the Decertrnent of Transportation Hazardous Materiais Regulations (49 CFR 170 f 89).
2b.
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Ti le 10, Code of Federal Regmations, Part 71," Packaging of Radioactive Material for Transoort and Transportation of Radioactive Ma erial Under Certain Conditions."
2c.
This certificate does not relieve the consignor f rom compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate as issued on the basis of a safety analysis report of the package design or application-(1) Prepared by (Name and address /:
(2) Title and identification of report or application:
(3) Date:
Oak Ridge National Laboratory Safety Analysis Report for Pack-January 1979 Post Office Box E aging (SARP) of the Oak Ridge National Laboratory Oak Ridge, TN 37830 Foamglas Shipping Container Report No.: ORNL-5407/R1
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71,as applicable,and the conditions specified in item 5 below.
- 5. Descr ation of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions. and
References:
(a) Packaging (1) Model: ORNL Foamglas (2)
Description:
Packaging for fissile material. The containment vessel is a flanged DOT Specification 2R inside container consisting of a 4.81" I.D. x 18" long Schedule 80 stainless steel pipe (0.375" wall thickness) with a 1/4" thick welded bottom plate. The flange is sealed with a 1/8" thick x 5" I.D. x 10" 0.D. silicone gasket. Fissile material is contained inside sealed metal cans within the containment vessel. Void space inside the concain-ment vessel may be filled with crumpled aluminum foil. The containment vessel is supported inside a DOT Specification 17H 55-gallon drum by solid foamed boron silicate glass (foamglas). The outer steel drum is 23" 0.D. x 35 1/16" long.
It has a 12-gage bolted closure ring W h drop forged lags, one of which is threaded, and has a 5/8" steel bolt and lock nut.
The package gross weight is 215 lb.
(3) Drawing:
The packaging is as described and is fabricated in accordance with ORNL A91/M tM.
ym43 6a. Date of issuance:
June 22, 1979 l Gb. Expiration Date:
FOR THE U.S. DEPARTMENT OF ENERGY 7a. Address (o/ OOE fsswng Officel 7b. Signature, Name, and Title (o/ OOE Aoprowng O//icia//
U. S. Department of Energy
\\
Post Office Box E 4 -
- h Yeamd Oak Ridge, Tennessee 37830 William H. Travis, Director Safety & Environmental Control Division 8108110148 810724 PDR ADOCK 07105795
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C PDR
o Page 2 - certificate of Compliance, No.: 5795, Revision 1 (b) Centents (1) Type and form of material:
Uranium and plutonium isotcpes either singly or in mixture, 233U, 235U,or 238U.
as metal oxide. Uranium may contain up to 100%
Plutonium in guantities greater than 50g will contain at 240Pu than 2 t+ 1Pu, and.23ePu will least 60wt %
39Pu, more be considered as 239pu, (2)
Maximum quantity of materiel per package:
Not to exceed ib watts ther=al decay and for the fissile contents decribed in 5(b)(1), the assignment of the trans-port Index for Fissile Class II is consistent with the following limitations of form, mass, H:X ratio, and density:
Mass (kt of X)
Transport D0 Oxide CD,Cxide 3
Index M tal H:I E O.h H:I $ 3 Uraniun-235 (p = 18.76 (o = 6.07 (p = h.h8 3
3 3
g U/cm )
g U/en )
g U/cm )
0.1 17.2 kg 18.8 kg 15.h kg 0.2 19.5 2L.1 18.h 0.3 20.8 28.2 20.h 0.5 23 0 33.8 23.0 1.0 25.6 h3.7 27.h 2.0 28.9 56.1 32.8 Phtonium-239 (p- --19.7 (p = 8.73 (p - L.71 3
3 3
g Pden )
g Pu/en )
g Pde 1 )
0.1 5.3 kg 10.5 kg 9.2 kg 0,2 5.6 11.6 10.7 0.3 5.8 12.h 11.8 0.5 6.2 13.5 13.3 1.0 6.5 1h.9 15.6 2.0 7.0 16 5 18.3 Uranium-233 (p = 18.h (p = 8.c3 (p - L.L6 3
3 3
g U/cm )
g U/cm )
g U/cm )
0.1 7.5 kg 11.1 kg 8.3 kg 0.2 8.0 12.6 10.1 0.3 8.3 13.7 11.5 0.5 8.8 15.0 13.3 1.0 9.2 17.1 16.2 2.0 9.9 19 3 19.8
o l
Page 3 - Certificate of Compliance, No.: 5795, Revision 1 (c) Fissile Class jg[ and III (1) Minimum transport index to be be shown on label for Class II 0.1 (2) Maximum Transport Indexes er shipment for Class III 100 (d) External radiation levels will conform to US DOT Regulations, 49 CFR 173.393.
(e) ORNL foamglas containers loaded with Pu in excess of 20 Ci will be transported in SST's (Safe Secure Trailers) operated by USDOE-ALO in order to conform to 10 CFn 71.42(b).
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ORO REVIEW OF REPORT ORNL-5407/R1 Safety Analysis Report for Packaging (SARP)
Oak Ridge National Laboratory Fcmglas Shipping Container Raynond E. Harris William A. Pryor t
The outer housing of the Foamglas Shipping Container is a 55-gallon carbon steel dra identified as a Specification 17 H package.
The inner container is a
flanged 5-in.-diameter schedule-80 pipe with 0.375-in.-wall thickness. The bottcm of the inner container is a 1/4-in.-thick plate welded to the pipe wall.
The top removable flange is 1/2-in.-thick plate and is held to the body by eight 3/4-in. by 1-1/4-in. long NC hex bolts. A silicone rubber gasket is used in conjunction with t.'e
- t. g flange.
Stainless steel is the material of construction of all ccrrpcnents of the inner container.
The inner container meets specificaticn 2R.
This review is made under the requirments of DOD1-0529 and -5021.
It is ccn-cerned with the Fissile Class II transport of uranium and plutonim isotopes either singly or in mixture, in the form of metal or oxide.
A.
General Standards for all Packagina:
1.
The material and construction are such that there will be no signifi-cant chemical, galvanic, or other reaction among container ccrnponents or between the package carpcnents and the package contents.
2.
Not applicable.
3.
The container is equipped with positive closure as required.
4.
Lifting devices for pacxaging:
The container does not have special lifting devices.
Therefore, the requirements in this section are not applicable.
5.
Tiedown devices for packaging:
The container does not have special tiedown devices.
Therefore, the requirements in this section are not applicable.
ea, f =3 "))
Q:1. V -
-. - 8.
Structural Standards for Type B and Large Ouantity Packagirp Well recognized theory is used in the SARP to demonstrate the capability of the package relative to requirements in the structural standards for Type B and lartje quantity packaging.
OR review indicaten that ORNL has adequately covered and adequately dertonstrated in the SARP the ability of the package to meet these requir ments.
C.
Normal Conditions of Transport Standarti calculationsl techniques and/or test recalts have been used in the SARP to demonstrate carpliance of the package with all requirements for norwal conditions of transport.
The OR review substantiates the ORNL conclusion that the package meets these requirements.
D.
Hypothetical Accident Conditions The evaluation in the SARP of the package to meet requirements under hypo-thetical accident conditions is based on tests of similar packages.
Results fran the tests indicate ccrplie-re of the package with' all of these ccrriitions.
OR review of the test results substantiate the conclusion in the SARP that the package meets the requirements for hypothetical accident J
conditions.
E.
Nuclear Criticality Safety (Report Y-DR-20)
The ORNL Foamglas Package has been analyzed for nuclear criticality safety using the multigroup Monte Carlo Criticality Corputer Program, KENO, utiliz-ing the multigroup Hansen-Roac 1 cross sections. 'Ihe programs and crrss sec-tierts are recognized as standanis within the nuclear criticality safety ccm-munity.
Arrays were assumed to be reflected with an equivalent of 8 in. of water and in a triangular pitch.
The original evaluaticn assuned that the inner container would be fabri-cated frun a schedule 40 pipe with an I.D. of 5.05 in.
The actual inner container is fabricated frcm schedule 80 pipe with o I.D. of 4.81 in.
The 2
wall thickness of the schedule 80 pipe is approximately 50% larger than
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. that of the schedule 40 pipe.
Thus, the additional steel and the smaller diameter and cavity size ccntribu'ce additional conservatism to the nuclear criticality safety evaluation.
A single, water-reflected package will be subcritical should water leak into the package.
This is the cmse for each fissile isotope being shipped.
4 Although the package has been eval.2ated for solt. tion shipnents, only solids either as metal or oxide are authorized.
The evaluation of loadings and the corresponding assigrrnent of TI's is conservative.
F.
,Special Recuirements for Plutoniun All plutoniun is shipped as a solid, either metal or oxide. The plutoniun is placed within isotope cans which are used for containnent in standard ORNL Type A nonreturnable isotope shipping containers. Wha plutoniun con-tents per contMner exceed 20 C1, shipnents are made via SST vehicles under direct control of US ROE.
G.
Quality Assurance The quality assurance requirements for fabrication and maintenance were reviewed by the CR Quality & Reliability Division and were found to be generally acceptable.
I I
H.
Distribution The SARP was distributed under TID 4500, UC71.
I.
Conclusion The requirements of DOB4 0529 and 5201 have been met.
Therefore, it is rewmmaled that the ORNL Foamglas Shipping Container be certified.
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