ML20138A881
| ML20138A881 | |
| Person / Time | |
|---|---|
| Site: | 07105874 |
| Issue date: | 09/09/1985 |
| From: | Anselmo A EG&G IDAHO, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25799, NUDOCS 8510110116 | |
| Download: ML20138A881 (13) | |
Text
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EETURN To 396-SS DB M n
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%S SEP13 47 September 9, 1985
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AMENDMENT TO CERTIFICATE OF COMPLIANCE USA /5874/B()F AAA-395-85 ATTN: Charles E. MacDonald, Chief, Transportation Certification Branch, Division of Fuel Cycle and Material Safety, NMSS Gentlemen:
Enclosed are seven (7) copies of the technical analysis and description to the certificate of compliance for USA 5874 package.
The enclosures cover the criticality analysis to assure that we are subcritical in any condition and also that the decomposition of the epoxy material will have no affect on that allowed in the cask. This will confirm our previous telephone conversations with both you and Charles Marotta, s - section regarding the contents should be made to read as follows:
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- 5) Contents g
UmRc SEP 2 31980 s, '2 (1) Type and form of material 2
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Byproduct and special nuclear material contained cocktrctfu in product containers.
The contents must be 1SL is request is for a one-time exemption to cover the shipment being made from this installation. Enclosed is a check in the amount of
$150.00 for the review of this amendment and the granting of the one-time exemption.
If you require further information on this matter, please feel free to contact this office at (208)526-2414 Very truly yours, 8510110116 850909 PDR ADOCK 07105874 6
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nselmo, Manager A
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Enclosures:
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C 7 copies of Technical Analysis A
r Check for $150.00 g
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cc:
J. O. Zane, EG&G Idaho d59#
A h. G a k e r w h k
,1 fiEGsG Idano N/
INTEROFFICE CORRESPONDENCE Date:
August 27, 1985 To:
B. R. Dabell From:
L. W. Fish
.d/g subject:
ESTIMATE OF MAXIMUM PRESSURE FROM THE THERMAL DECOMPOSITION OF EP0XY RESIN IN A WAPD-40 SHIPPING CONTAINER - LWF-2-85 Refs:
(a'
" Safety Analysis for Radioactive Material Shipping Cask No. WAPD-40," Docket No. 71-5874, December 1984 (b) Drawings 9710362, Rev. 2; 979C282, Rev. 2; 177F51, Rev. D, Westinghouse Electric Co., Bettis Atomic Power Laboratory, Pittsburgh, PA (c) Telephone conversation, August 20, 1985, Wally Wardzala, Buehler Co., Lake Bluff, IL (d)
J. D. Poberts, M. C. Caserio, " Basic Principles of Organic Chemistry," p. 1105, W. A. Benjamin, Inc., New York, NY 1965 (e) Telephone conversation, August 22, 1985, P. Canale, Bacon Industries, Watertown, MA (f) Telephone conversation, M. J. Schneider, Westinghouse Electric Co., Bettis Atomic Power Laboratory, Pittsburgh, PA (g)
"WAPD-40 Safety Analysis Report Packaging," Sec. 3.4.6, Table 3.6, p. 3.6, Ch. 3, Rev. 3, Westinghouse Electric Co., Bettis Atomic Power Laboratory, Pittsburgh, PA (h)
D. W. Green, Ed., " Perry's Chemical Engineers' Handbook, 6th Ed.," p. 3-95, McGraw-Hill Book Co., New York, NY, 1984 (i)
R. C. Reid, J. M. Prausnitz, T. K. Sherwood, "The Properties of Gases and Liquids," 3 ed., McGraw-Hill Book Co., New York, NY, 1977 The purpose of this task was to estimate the maximum internal pressure which would result from the potential thermal decomposition of the epoxy resin contents when the shipping container is subjected to an external thermal transient of 1475'F for one hour.
This thermal transient would be the result of an external unintentional fire.
The dimensions and description of the WAPD-40 shipping container were obtained from references (a) and (b).
The container contents include Epo-Kwick, an epoxy resin distributed by the Buehler Co.
Some physical properties of the resin, including its density, chemical classification, and temperature at which thermal decomposition becomes significant were obtained through reference (c). The resin is obtain~' by combining epichlorohydrin, bisphenol A, and a hardening agent, diethytene triamine. Although the exact chemical formula and expected decomposition products were not available from reference (c), a generic formula for the resin exists in reference (d).
From that formula and the conservative assumption that "Providing research and development services to the government" i
August 26, 1985 B. R. Dabell LWF-2-85 Page 2 all the gaseous products consist of the lower molecular weight compounds such as carbon monoxide, hydrogen and nitrogen, chemical reaction equations were derived to determine the quantities of these gaseous species which might evolve from the resin and cardboard decomposition. The cardboard was assumed to be cellulose.
Using the quantities of gas produced, the volume of space available for the gas to occupy within the cask upon a hypothetical internal thermal transient increasing to 621'F at the resin location, the conservative assumption that the existing solids do not decrease in volume during the transient, the calculated maximum pressure is 2300 psia.
The details of the calculations are included in the attachment.
According to reference (e), epoxy resins similar to Epo-Kwick, but not identical, would be expected to decompose rather slowly at 621'F for one hour exposure. Consequently, reference (e) believes that there would be very little danger of overpressurization at these conditions. Reference (f) quoting reference (g) indicates that this shipping cask has a design maximum pressure -
rating of 2890 psia.
Therefore, with the inherent conservatism in the calculations, the author believes that the shipping cask would remain intact upon an external thermal transient at 14/5 f for one hour.
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Attachment:
As Stated cc:
D. R. Evans J. L. Liebenthal '/,-
L. W. Walrath Central File L. W. Fish File i
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ch;,,EGsGIdano INTEROFFICE CORRESPONDENCE Date:
August 16, 1985 To:
B. R. DaBell From:
H. A. Worle ;
Q c
sutnect: CRITICALITY ANALYSIS OF WAPD-40 CASK LOADING -WORLE-11-85 Attached is a criticality analysis of the proposed fuel rod shipment in the WAPD-40 cask.
It shows that a large margin of safety exists for the proposed loading containing epoxied met-mounts.
If you have any questions, call me at ext. 6-0510.
jic
Attachment:
As Stated cc:
P. E. Rohter H. A. Worle File (2)
Central File i
"Providing research and development services to the yesnmnuant" e
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76 i
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CRITICALITY ANALYSIS OF WAPD-40 The proposed cask loading consists of UO in which the uranium is enriched 2
to 10%
by weight in the isotope U-235.
The shipment contains a total of 679 of U-235.
The U0 is in the form of fuel pellets surrounded by 2
cladding material to form a fuel rod and portions thereof.
Some fuel rod pieces are encased in an epoxy compound which also occupies the space between cladding and pellets and the gaps between the pellets, if any.
For the purposes of this analysis the following conservative assumptions are made:
e The epoxy has a hydrogen atom density equivalent to that of water (Typical epoxy resins used for this purpose have a smaller H atomic density.)
e Sufficient epoxy is present to provide an optimum H/U-235 ratio of
~ 500 (The amount actually present will provide an H/U-235 ratio of less than 200 for the 24g of U-235 which are actually encased in epoxy.
The moderating ratio for the entire 679 is less than 30.)
e The fissile material is in the form of U-metal, 100% enriched and homogeneously mixed with the moderator.
(The actual situation is that the fissile material is in rod or rod pieces of U(10)0 )*
2 e The homogeneous mixture is in the form of a sphere enclosed by a close-fitting water reflector sufficient to be considered of infinite thickness (The actual system, far from spherical, is in a cylindrical cavity of 2 in, diameter, surrounded by 10 in. of lead on all sides.
Because of the cavity size, all fuel pieces must be placed end-to-end.)
The lead reflector in the last assumption is not conservative, but the small degree of nonconservativeness is easily outweighed by the conservatisms listed.
l l
e
Reference 1. indicates that, under the assumptions listed above, more than 600g of U-235 is critically safe in a single cask. When the cylindrical configuration of the cask is taken into account, it is indicated that the cask can probably not be made critical with any amount of U-235.
If the cask is placed in an array of similar casks, their individual loadings would be separated by layers of steel and 20 in. of lead.
Reference 2. gives 10.2 1 0.8 in, as the effective isolation distance provided by lead between fissile systems. The effective isolation distance is defined as that distance at which neutron interaction is effectively stopped.
It follows that an infinite array of WAPD-40 casks loaded as proposed would not become critical. Maintaining the Fissile Class at II and the Transport Index at ~3.2 provide additional, though unnecessary, safety margins.
Ref. 1:
J. T. Thomas, ed. Nuclear Safety Guide. TID-7016, Rev. 2., June,1978 Fig. 2.1 Ref: 2:
R. D. Carter, "Critigality Handbook,"-ARH-600, June 15, 1980 1
(update) pg. VI. E.2-1.
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