ML20009D368
| ML20009D368 | |
| Person / Time | |
|---|---|
| Site: | 07105595 |
| Issue date: | 07/08/1981 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 19381, NUDOCS 8107230403 | |
| Download: ML20009D368 (5) | |
Text
Aerueo 7 -55 6 76 a emee w
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j (h\\ [V' Departrnent of Energy
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Oak Ridge Operations
$v& 4 P.O. Box E i
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Oak Ridge, Tennessee 37830 s _
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T July 8,1981'p' 4
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-U.S. Nuclear Regulatory Ccnmission ATIN:
Mr. Charles E. MacDonald, Chief Q fa,;j""b
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3 Transportation Certificaticn Branch Q
Divisicn of Fuel Cycle & Material Safety N: //
f,>g Washington, D.C.
20553 Gentlemen:
SAFEIY ANALYSIS REPORT FOR PACKAGING: THE ORNL GRANIU4-SHIELDED SHIPPITU CASK, REPORT ORNL/ErU/'IM-4 Reference is given to the subject SARP and to your Docket No. 71-5595.
In reply to the specific additional information which you requested, ORNL pre-pared the enclosed supplemental data. DOE-ORO has reviewed this data and con-curs with the conclusims.
We request only a secondary priority review at this time.
Sincerely, W4eemeen. Y William H. Travis, Director SE-332:WAP Safety & Envircrmental Control Division FSS: 1224
Enclosure:
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ORNL Answers (1C) g C) cc w/ encl:
p 40 C. H. Durham, AM
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JUL i 61981>
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D. M. Ross, EV-133, G-135, GIN [
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8107230403 810708, PDR ADOCK 0710559-PDR C
V Uranium Shielded Shipping Container Structural Section 1.3.2 in the SARP, contains all the justifications for the shear 1.
strength of uranium that we have identified.
- 2. - Analytical verification of lid retention is not practical. ORNL has drop tested several shipping containers under accident conditions. ORNL/TM-1312, Vol.17, describes the testing of the HWCTR cask, and a report is being pre-The drops pared on an oblique drop of the knapp mill spent. fuel container.
have not produced any lid separation on any cask.
We have found that a major portion of the cask energy is translated to rotation upon initial impact, and is spent upon deformation on the end of the cask opposite the closure and the deformation of the closure end tends to jar the lid in The oblique drop of the knapps mill container jammed the lid such place.
It is that two 25-ton hydraulic jacks were required to remove the lid.
noted that the lid of the uranium cask does not form primary containment.
These have been The special forms container provides primary containment.
evaluated and meet accid,ent condition requirements.
Containment The analysis in the report demonstrates that the inner containers have rc 1.
Therefore detectable leaks under either the normal or accident conditions.
a containment acceptance criteria is not needed.
The design of the inner containers used for normal forms are fully described 2.
in Section 1.9.
The analysis demonstreats that no detectable leaks are No containment criteria is present under normal or accident conditions.
needed.
Test and Maintenance 1 & 2 - Each container is leak te'sted prior to shipment. Attached is the procedure.
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JL OPERATIONS DIVISION 1
or 3
eAcc RADIOISOTOPE DEPARTMENT 2n 2180 an, a
BUILDING 3029 SOURCE DEVELOPMENT LABORATORY LEAK TESTING PROCEDURE FOR RADIOACTIVE MATERIALS
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CONTAINED IN SPECIAL FORM OR DOT 2R CAPSULES
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9 I.
Leak Testing A.
General All radioactive materials contained in Special Form or DOT 2R The method used is capsules are leak tested before shipment.
the air bubble, vacuum, and glycol as described in ANSI Standard N14.5 A3.6.
B.
Equipment The leak test equipment consists of a glass test chamber with a 1.
removable sealable top.
A line penetrates the top and is The size and shape of the connected to an in-cell vacuum pump.
test chamber may vary with the design of the piece being tested; and must be large enough that the piece can be completely immersed in the test liquid, leaving at le'ast one inch of test liquid above the weld area.
Racks, suspension assemblies, or similar positioning devices 2.
These will be
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'may be required for some radioactive sources.
designed so.as not to interfere with observation of the weld g { s -)
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area during testing.
i' Unless otherwise specified,.the test liquid for liners
. 3.
The final test liquid for radioactive r
is distilled water.
sources is ethylene glycol. The final leak test has a 3
l at.cm /sec.
6
. sensitivity greater than 1 x 10
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C.
Procedure The test chamber is filled with test liquid to a depth 1.
sufficient to cover the piece being tested and leave at least one inch, but not more than three inches, of test liquid above the weld area when the piece is in the test position.
The top is placed on the test c'namber and a vacuum of 6
2.
at least 20 inches Hg is imposed.
The piece, and especially the~ weld area, is observed for l
3.
t l
10 seconds while the vacuum is maintained. A,1cak is l
iadicated by a steady stream of air bubbles coming from a fixed point on the source.
Af ter the 30-second observation the vacuum is relieved; 4.
then the piece is removed from the test chamber.
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OPERATIONS DIVISION
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BUILDING 3029 SOURCE DEVELOPMENT LABORATORY LEAR TESTING PROCEDURE FOR RADIDACTIVE MATERIALS
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CONTAINED IN SPECIAL FORM OR DOT 2R CAPSULES Leaking piece,s are rejected and defueled.
a.
Non-leaking pieces are transferred to the furnace b.
testing area.
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, n.,.. n BUILDING 3029 SOURCE DEVELCPMEWT LABORATORY LEAK TESTING PROCEDURE FOR RADIOACTIVE MATERIALS
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CONTAINED IN SPECIAL FORM OR DOT 2R CAPSULES
_ RADIOACTIVE S0t.RCE DATA SHEET Customer
_ Capsule No.
S.II. No.
Fuel Form Curies Fuel Batch No.
Assay Nom. Dim.-0.D.
2.D.
Length Cap. Thk.
Caps,u e Comp.
Spec. Sheet Accepted Reject Date Supvr.
I Capsule & Cap Degreased
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Liner No.
Liner Cleaned Liner Dried (
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~ Welding Procedure Test Weld No.
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Capsule Welded Co-no-go Test Leak Test Oven Tc'st (
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Co-no-go Test i
Leak Test Dect taminated Max. Smear Avg.
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Shelf Test Star'ted Shelf Test Completed Re-smear Max. Smear Avg.
Co-no-go Test Source Disposition
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