ML19323C686
| ML19323C686 | |
| Person / Time | |
|---|---|
| Site: | 07105086 |
| Issue date: | 04/22/1980 |
| From: | Kirk W UNITED NUCLEAR CORP., UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.) |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19323C687 | List: |
| References | |
| 16139, NUDOCS 8005190007 | |
| Download: ML19323C686 (3) | |
Text
8 00519 0D&?
[Q USC GRVR' PR.33UCTE 7/-5<9#
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((I In reply, please refer tc:
NIS-80-4-41 g'
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'3 April 22,1980 CM Apg3 L
0 Mr. Charles E. PacDonald, Chief 7
Og Iransportation Certification Branch
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s Division of Fuel Cycle & Material Safet
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e Washington, D. C. 20555 y
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Certificate Of Compliance No. 5086
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'W UNC 2600 Shipping Container
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Docket No. 71-5086
Reference:
1.
Letter - W. F. Kirk To C. E. MacDonald,
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Dated December 20, 1979 "e,
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2.
Letter - C. E. MacDonald To W. F. Kirk, Dated March 4, 1980
Dear Mr. MacDonald:
As requested by Reference (2), we are enclosing consolidated Drawing D-20354-6, Sheet 7. Rev. 4 to show important configuration items for this cautainer.
The revised drawing is consistent with the packaging that was subjected to J
the 30 ft. drop test and the puncture test, except as noted in Reference (1) and repeated below:
1.
Stop bar fastening bolts at either end are shown as either the 1/2" diameter with nut and washer, which was tested, or a 5/8" diameter bolt with lock washer tapped into the 3/8" cage plate at either end. No loss of containment strength is associated with this eption.
2.
Optional banding of wooden blocks to the outside of the container for handling purposes has been provided.
3.
The original webbing strap asse bly, #837A2, has been revised to a steel bandin5 strap. This modification i= proves the inner box closure.under accident cenditions involving heat or fire. liovever, the steel frane of the outer container is the main control on pre-venting opening of the inner container.
THIS L;CUMENT CONTAINS POOR QUALITY PAGES gg_.,,,n l
4
- 2. -
Mr. Charles E. MacDonald, Chief April 22, 1980 Transportation Certification Branch UMC U. S. Nuclear Regulatory Con ission 4
The use of other equivalent materials to the " oak" block and the specified box " hinge" do not affect the performance of the container under accident conditions, in answer to the third comment of Reference (2), review of the testing with our Plant Service Supervisor, who was present during the container testing. indicates that the cover was on after the 30 ft. drop but removed for photographing of the front and prior to the penetration test.
The cover could not be put on for the penetration test.
The 40 inch penetration. test if performed on the end of the package, with or without the cover and bumper in place, would not effect the closure or retention of the inner container.
The 6" diameter peaetration pin would partially flatten the rear end handle of the inner container from an original 1-3/4" height to an approximate 1" height while bringing the inner container against the stop bars at far end from the penetration pin.
Concurrently, the penetration pin would come against the 3/8" thick end cage plate of the cage assembly, which would absorb most all the impact leading as it moved against the bumper at the velded end closure of the outer container. Centered or of f-center impact of the 6" pin would result in the same situation since its dimensions are such that it would not move past the end cage plate.
As an indication of the maximum stresses that would be developed in the eight (8) longitudinal central angles, without consideration of the loading distri-bution to the remainder of the cage assembly:
Compression
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S=
2E WV-10,900 psi AL 2g h = 40 in. = 3.34 f t.
V= Vl[hI~
/ 2 (32.2) 3.34 14.7 ft./sec.
=
W = 1,200 lbs.
%=
176 in./sec.
g = 32.2 ft./sec. 2 388 in./sec. 2
=
E = 30 X 106 in.-lb./in. 3 A = 4 (.25 in. 2) + 4 (.375) = 2.5 in. 2 L = 96 in.
I I
6 a
- 3. -
Mr. Charles E. MacDonald, Chief April 22, 1980 Transportation Certification Branch UNC U. S. Nuclear Regulatory Comission Our conclusion is that the penetration test an the end would not affect the integrity of the inner or outer container.
As requested, we are enclosing a consolidated application encompassing past applications and amendments. For your convenience, we have followed the fermat of Regulatory Guide 7.9, Rev. 1, dated January, 1980.
In order to satisfy a need to ship by May 20, we would appreciate your prompt review of the consolidated application.
Very truly yours, j '/
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ad-W. F. Kirk, Manager Nuclear & Industrial Safety jr Att.
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