ML20236Q901
| ML20236Q901 | |
| Person / Time | |
|---|---|
| Site: | 07109860 |
| Issue date: | 11/02/1987 |
| From: | Torres J ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20236Q843 | List: |
| References | |
| NUDOCS 8711200350 | |
| Download: ML20236Q901 (6) | |
Text
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' DOE F 5822.1 U S. DEPARTMENT OF ENERGY (s.85)
CERTIFICATE OF COMPLIANCE O M B Approval' (Formerly EV 618)
For Radioactive Materials Packages No.191o 2000 k
1a. Certificate Number -
1b. Revision No.
1c. Package identification No.
1d. Page No.
1e. Total No. Pages.
9860 3
4
- 2. PREAM BLE 2a.
This certificate is issued under the authority of 49CFR Part 173.7 (d).
2b.
The packaging and contents described in item 5 below, meets the safety standards set forth in subpart E "Packege Approval Standards" and subpart F " Package and Special Form Tests" Title 10, Code of Federal Regulations, Part 71.
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2c.
This certificate does not relieve the consignor from 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 is issued on the basis of a safety analysis report of the package design or application-l (1) Prepared by(Name and address):
(2) Title and identification of report or application:
(3)Date:
l U.S. Department of Energy Safety Analysis Report for Packaging January 13, 1984 Oak Ridge Operations Office (0ak Ridge Y-12 Plant Model DT-14A P.O. Box E Packaging for Enriched Uranium) Report Y/DD-326 Dak Ridge, TN 37831 Rev.1, as supplemented.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the applicable Operational and Quality Assurance requirements of 49CFR parts 100199 and 10CFR Part 71, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No. DT-14A (2) Description Packaging for uranium enriched in the U-235 isotope. The steel f
l containment vessel has a 6- -inch ID and 15- -inch deep cavity.
Positive closure is provided by a flanged and bolted arrangement.
The closure is sealed by a Neoprene 0-ring. The. cadmium and rubber coated containment vessel is centered and supported by l
cane fiberboard within an 18-gauge D0T Specification 17H 30-gallon steel The cane fiberboard insulation has a minimum 14lb/ftgrum.
. density.
Plywood discs,
-inch thick are located at the end and flange of the container.
The overall container size is 20 inches in diameter by 30 inches high. The drum is provided with four, 3/8-inch vent holes which are taped or provided with fusible plugs. The package gross weight is 210 pounds.
l 6a. Date of issuance:
November 2, 1987 l 6b. Expiration Date:
December 31, 1989 l
I FOR THE U.S. DEPARTMENT OF ENERGY
- 70. Address (of DOEIssuing Office) 7b. Signature, Name, and Title (of DOE Approving Official) 71 f.,YG4'th
]
Julio L Torres, Director q
U.S. Department of Energy Office of Security Evaluations (DP-4)
Washington, D. C.
20545
,I 8711200350 871103 R
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'(3) Drawings
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- The packaging:-is constructedLin accordance with the drawings shown-sin figures 1 thru 4 of' Oak Ridge.Y-12 Plant' Report.No. Y/DD-326,.
_)
-)-
- January 13, 1984, Revision ~1.
j (b).. Contents 1 9
(1)~ Type'and Form of Material'
-9 Uranium'as metals, alloys,: compounds,' mixtures, or. solutions.
1 enriched to.:any degree..in:the U-235 isotope.
<h R (2) Maximum quantity.of material per package and fissile class.
(1) Not to ex.ceed 10 watts. internal-decay heat.
(ii) Type A ' quantities of tiraniumlin which the maximum content
. l-weight within the containment' vessel does not exceed 30' 3
Kg', the.U-235 density not to exceed 18'.8 g/c'm, and contents are further:restrictsd as follows:
)
' Maximum U-235 Mass <(kg)
Metals or
~
Alloys
' Mixtures and Compounds
. Liquids-235 3
0 density (g/cm )
18.8 8.33' 4.55 2.05 1.15'
'18.8 -
235 H/
0 atom ratio 0.00 0.43 3.22 10.7 21.4-Unlimited 235Umass/ package (kg)18.0 21.0 16.0~
8.5-5.5 1.0-Minimum Transport.
FC-I*
FC-I*
0.1.
0.1 0.2 FC-I*
Index to be shown on label for Fissile i
Class II j
- Fissile Class I
- i (iii) Type B quantities of uranium in which the maximum content within the containment vessel does not exceed 13.21 kg.of-o naval fuel material..The uranium may. be enriched to.any.
degree in.the U-235~ isotope. Maximum isotopic content shall not exceed 9.Kg.of U-235; 0.05 w/o U-233; 2.0_w/o-U-234; and 0.05 w/o U-236.
.]
.'l Maximum quantity of material per package is 1.6 Curies._
l (c)
Fissile Class I
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di.___.._i__..'__.__..__
___m._:.__
3 (d) Conditions l
3 1.
Any amount of low-density ($1.0 g/cm ) packaging material, providing it is not intermingled within the loading, may be used to cushion the loading within the inner containment vessel.
2.
Up to 120 grams of packaging material may be interstitially used for metal pieces; however, greater packaging material masses require that the limits on mixtures, compounds,andsolutionsbeobsgrved. Alloys with U-235 densitiesS 8.33 g/cm niay'be packaged under the limits for mixtures, compounds, and solutions specified in 5(b)(2)(ii).
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3.
Vranium hydrides with densities greater than 4.55 g/cm are not permitted.
4.
Metals or alloys in solid form must be held within the containment cavity in screw top polyethylene bottles with a-1-mm (40 mils) minimum-wall thickness or in metal cans with nominal wall thickness of 0.254-mm (10' mils).
5.
Powders must be packaged in a water-tight, screw-top polyethylene bottle with a 1-mm minimum wall thickness. Before loading, the lid on the polyethylene bottle must be visually inspected to ensure the gasket is present and functional.
Each l
loaded polyethylene bottle must be inverted and handshaken; a smear must be taken and checked with an alpha detector to ensure non-leakage of the powder.
If all of these conditions are satisfied, the lid must be sealed and closed using i
pressure-sensitive tape.
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6.
Naval fuel material must be packaged in a water-tight nickel shipping can. The shipping can is to be 3 inches in outside diameter by 4-9/16 inches in overall height and has a nominal wall thickness of 30 mils.
The shipping can has a screw type lid with an elastomeric "0" ring gasket. Can lids will be sealed and closed with pressure-sensitive tape to ensure product containment. A maximum of 5 cans are to be placed within the containment vessel cavity. Each can will contain a maximum of 1.8 Kg of U-235 under the limits specified in 5(b)(2)(iii).
3 7.
Solutions must be packaged in a water-tight, screw-top polyethylene bottle with a 1-mm minimum wall thickness.
Before loading, the lid on the polyethylene bottle must be visibly inspected to ensure the gasket is present and functional.
Each filled polyethylene bottle must be inverted and observed for 5 minutes.
If no leakage is visible, a smear must be taken and checked with an alpha detector to ensure non-leakage of the solution.
If all of these conditions are satisfied, the lid must be sealed using pressure-sensitive tape.
_-___.w-~._-ma
4 8.
Upon receipt and within the preceding 12. month period prior to e, the containment vessel must thefirstuseofeachn9wpackag/secatstandardtest be leak tested to 1x10~ atm-cm i
conditions of ANSI N14.5.
tainment vessel must be leak tested to 1x10~7 Thecog/secatstandardtestconditionsofANSIN14.5afterthe 9.
atm-cm third usage, and within 1 year from the last inspection date thereafter, prior to use.
- 10. The inside walls of the containment vessel must be lined with a 0.011-inch thick full density cadmium sheet bonded to the walls of the vessel. High-density polyurethane rubber must be applied over the inside bottom and sides of the containment vessel with an average. thickness of 0.22 inch.
Prior to each shipment, the polyurethane rubber coating must be inspected and kept in good repair. Any damage to the cadmium i
sheet must require its replacement with a new sheet. New inner containment vessels and vessels with replaced cadmium sheet must be tested in accordance with the first paragraph on top of i
page 25 of Oak Ridge Y-12 Plant Report No. Y/DD-326, dated January 13, 1984-11.
The 1/4-inch pipe plug threads must be coated with Teflon tape and tightened into the lid of the containment vessel.
- 12. The package authorized by this certificate is hereby approved for use under the general provisions of 49 CFR 6 173.7(d).
i 13.
Fabrication of additional packaging is not authorized after August 31, 1986.
References 1)
Department of Energy, Oak Ridge Operations Application dated March 3, 1986 2)
Oak Ridge Y-12 Plant Report No. Y/DD-326, January 13, 1984 3)
E.I. du Pont de Nemours & Company supplement dated: July 17, 1987
Department of Energy.
Washington, D.C.
Packaging Certification Branch Office of Security Evaluations A3 proval Record Model io. DT-14A Package Docket No. 86-4-9860 q
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By application, the Oak Ridge Operations Office requested an approval for the Model No. DT-14A package with additional contents.
The Model No. DT ' 14-A package described in reference 1 has previously been approved by the Department of Energy and Nuclear Regulatory Commission for shipment of i
contents described in paragraph 5(b)(2)(ii).
The above application described i
in reference 2 has been submitted to allow additional contents, described in 5(b)(2)(iii), to be shipped in the DT-14A and also presents an ' enhanced l
quality assurance program for the packaging.
A review of the structural evaluations indicates that the revised contents will not affect the structural considerations of the packaging or have any.
adverse effects on the integrity of the inner containment _ vessel.
A thermal review was conducted to determine whether the revised contents would exceed the previously authorized heat load of' 10 watts.
The. revised contents 5(b)(2)(iii) would generate a maximum of 0.034 watts of. heat.
The l
package temperatures and pressures, with the revised contents are determined i
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to be no more severe than those produced and experienced by the original contents.
Thecoptainmentvesselofthepackagingwasdeterminedtobeleaktight (1x10-atm cc/sec air at STP) prior to first use, after third ~ usage, and within 1 year from the-last inspection date thereafter (prior to use).
The when transporting the revised contents 5(b)(2)(iii) g leak test requirements DT-14A package has been exempted from the post loadin because of the particle size and non dispersability of the contents.
Without the performance of a post loading leak test, or an exemption, other contents are being restricted to Type A quantities.
The use of Teflon sealant around the i inch pipe plug threads in the containment vessel lid is a requirement.
l Evaluation of the shielding reveals dose rates are within acceptable limits.
Review of the criticality analysis shows it to be consistent with accepted' calculational techniques.
In addition, an independent criticality analysis was performed using the SCALE KEN 05A Monte Carlo code and a Hanson-Road 16 group cross section set. A single worst case was modeled and a resulting wNhisconsideredtheacceptableupperlimit.was obtained which is substantially below K
of 0.85+0.01
2 The application specifies an enhanced quality assurance plan for the procure-ment, use and maintenance of the packaging.
The plan has been evaluated for compliance with the 18 QA elements of ANSI /ASME NQA-1, and found to be acceptable. Specified implementing procedures, that were included in the applicants QA Manual, have also been reviewed and found acceptable. An Important-to-Safety list (Q-list) has been developed for the packaging. A review of this list shows it to be acceptable as it adequately addresses the safety criteria of each item in the packaging and applies the appropriate level of quality.
j The operating procedures, acceptance tests and maintenance procedures.
presented in reference 2 have been-reviewed. The revised contents have no adverse affects on the operating procedures.
The cadmium lined walls of the containment vessel are important in maintain-ing the suberiticality of an individual package, therefore a condition has 1
been added to assure the presence of the cadmium. There are no provisions i
for post loading leakage test of the containment vessel, therefore, a condition has been added to limit the contents to Type A quantities unless additional justification can be presented demonstrating leakage tests are not required.
Based on our review and the statements and representations contained in the application, we find the inclusion of the additional contents to the Model 1
N0. DT-14A package meets the requirements of 10 CFR71 subject to the 1
conditions listed in the Certificate of Compliance for the package, j
References:
)
l.
Safety Analysis Report for Packaging (SARP), (0ak Ridge Y-12 Plant Model DT-14A Package for Enriched Uranium); Y/DD-326, Rev. 1, January 13, 1984; Oak Ridge Y-12 Plant, Martin Marietta Energy Systems, Inc., Oak Ridge, Tennessee 37830.
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2.
Supplement No. 1, Rev. 2 r.f the Safety Analysis Report for Packaging i
(SARP),(0akRidgeY-12riantModelDT-14APackageforEnriched Uranium): Y/DD-326, Rep 9rt DPSPU 85-124-3, July 17, 1987, E.I. duPont de Nemours & Company, SavLnnah River Plant, Aiken, S.C.
29808.
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Prepared by:
M I.
u%,
I-Approved by:
C7 DATE:
$.2
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