ML20126B886
| ML20126B886 | |
| Person / Time | |
|---|---|
| Site: | 07109011, 07105796 |
| Issue date: | 01/22/1980 |
| From: | Pengov C PICKER INTERNATIONAL, INC. |
| To: | Rawl R TRANSPORTATION, DEPT. OF |
| Shared Package | |
| ML20126B888 | List: |
| References | |
| 15313, NUDOCS 8003210204 | |
| Download: ML20126B886 (11) | |
Text
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- 7DL 7/ ~ MI PICKER CORPORATION 6671 BETA DRIVE / CENT. BLDG.
I MAYFIELD VILLAGE, OHIO 44143 2
January 22,1980 Office of Ilazardous Materials Operations U.S. Department of Transportation Washington D. C. 20500 i
Attention: Mr. R. R. 'Rawl
Dear Mr. Rawl:
We wish to amend our IAEA Certificates of Competent Authority numbers l
USA /5706/B and USA /90ll/B changing the certificate from the 1967 to the 1973 IAEA regulations.
We have compared the 1967 edition of IAEA Regulations and 10CFR part 71 to i
l the 1973 edition of the regulations and determined the only change is the addition of a water spray.
Accordingly we have conducted an engineering study relative to the water spray tests. Enclosed is a copy of the study, copies of Certificates of Complinnce and copies of our Certificates of Competent Authority.
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Your expeditious help in processing this amendment will be greatly appreciated.
Sincerely, d.w 1 enclosure C.A. Pe v
Safety Officer cc: R. A rndt-A MS
- Special Systems Division W. Ashby.
Picker Corp D. Churchill.
(8) Charles 3 tac Donald W., Mog.
R. Novacek +
J. Stidiney +
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- -those with cover sheet only.
M i 8003210 PICK
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PICKER CORPORATION 6671 BETA DRIVE / CENT. BLOG.
MAYFIELD VILLAGE OHIO 44143 To:
C. A. Pengov FROM:
W., F. Mog DATE:
January 21, 1980 SUSJECT:
Evaluation of Overpack Containers Enclosed is a report which demonstrates that the Picker Corporation overpack containers 151361, 151375 and E-MEH-00-00004 comply with the IAEA,1973 Safety Standards.
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l EVALUATION OF OVERPACK CONTAINERS 191361
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181375 E-M Elf-00-00004 TO COM PLIANCE WITH IAEA,1973 SAFETY STANDARDS BY WALTE R F. MOG, P. E.
JANUARY 21, 1980 l
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d I.
PURPOSE The purpose of this application is to demonstrate that the overpack containers 181361, 181375 and E-MEH-00-00004 comply with the IAEA,1973 Safety Standards. Previously these overpack designs were in compliance with the 1967 IAEA Standards. The difference between the two Standards is that the 1973 edition requires a water spray test,Section VII paragraph 711, which was not required in 1967. Previously these overpacks have been approved by the NRC and DOT for shipment within the continental USA. Copies of these certificates are included in the appendix. In these applications and subsequent approvals it was shown that the above overpacks comply with the free drop.
compression, penetration and thermal tests. This report will demonstrate that these three overpacks will also comply with the water spray test and are to be acceptable for over seas shipments as indicated in the 1973 edition of the IAEA
. Safety Standards.
II.
CONSTRUCTION All three overpacks are of the same basic construction. The outer jacket is made up of 1/4" structural steel elements which are welded together to form a rectangular parallelepiped which the longest side is 41 inches. A 16 gauge steel plate encloses all six sides of the rectangular parallelepiped. An inner-jacket is comprised of hard maple wood which is laminated together with steel tie rods. Six of these laminated assemblies, which are treated with wood preservative, comprise the inner-jacket (reference drawings are attached in the appendix). The nominal 3 5/8" thick lamination assemblies provide the thermal bearer to satisfy the 30 min.14750F j
exposure which is required by the NRC. The only exposed wood are two skids which are on the bottom of the container which enable a fork lift truck to transport the package which weighs approximately 4000 lbs.
III.
APPROACH Three approaches were explored to verify that the overpacks comply with the water spray test. They are as follows:
1.
Two overpacks, 181375 and 191363 were sent to an independent test lab, Herron Testing Labs Inc., and subjet ed to the water spray test. Their report is included in the appendix.
2.
An analytical evaluation was made to determine the effect on the possible wood expansion due to the absorption of water which was absorbed in the spray test.
3.
Hard maple wood samples were submersed in water for one hour and five hours to measure the amount of water absorption. Three sample pieces of wood were used in this experiment. They are as follows:
a.
Wood block A - Which is hard maple with no preservative, b.
Wood block B - Which is hard maple with the ends covered with rubber cement, c.
Wood block C - Which is hard maple painted with a wood life preservative.
IV.
R ESULTS The independent testing lab reported that the average increase in weight of the container was less than 20 lbs after the water spray test was conducted. This analysis was done by weigling the overpack assembly before and after the water spray test. It does not Indicate that all of the water was absorbed by the wood inner-jacket. A portion of the water may have been absorbed, but m, ore than likely most of it flowed to the bottom of the container, liowever, if we make the asumption that 20 lbs of water, which has a volume of 554 cu. in.,
is completely absorbed in the wood it would result in only a 2.S?c (554/19572) expansion of the wood. The total volume of wood is 19572 cu. in. It seems even hard maple wood has some porosity. The expansion of the wood would be less than 39, but even if the wood expanded 37o the linear expansion of the wood would not create a stress condition to such a magnatude that it would create any significant distortion to either the wood inner-f acket or the welded steel outer jacket. Neither overpack exhibited any physical stress damage during the water spray test conducted at IIerron Labs.
Calculations indicate that the 2.870 expansion would create an expansion of the j
typical wood laminated assembly of 32. 5 in, in length to 32.78 in. If the wood was in the free state, an approximate expansion of 1/4 inch would occur; but since the wood is bolted together and could also be resisted by the weldment the free expansion does not take place.
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The design clearance between the wood assemblies and metal frame is 1/2 in.
Therefore if full expansion were to take place 0. 22 in (. 50
.28) clearance would remain.
The results of the wood block immersion tests are as follows:
Block A - Ilard maple, no preservative - I hour:
.011 Average percentage increase in thickness, 0.0%
1.636
.008 Average percentage increase in width, 0.2%
3.499 1
.002 Average percentage increase in length, 0. 007o 11.977 Block B - liard maple with ends covered with rubber cement - 1 hour:
Average percentage increase in thickness, 0.270
-M 1.G30
.000 Ave rage percentage increase in width, 0. 270 3.484 No measurable increase in length
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_ IV.
R ESU LTS Block C - Hard maple, painted with wood life preservative - 1 hr. test:
.005 Average percentage increase in thickness 0.37o 1.620 No measurable increase in width No measurable increase in length The five hour immersion test indicate thet water absorption increases are negligible.
V.
CONC LUSION The results indicate that the water spray tests have no detrimental effects on the overpacks 181161, 181375 and E-MEH-00-00004 for the following reasons:
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1.
If all the 20 lbs. of added water which was tested in the Herron Testing Lab test was absorbed in the wood the 2.87c free expansion would leave almost a 1/4" clearance between wood inner jacket and the steel weldment.
2.
The water spray tests produced no detrimental effects on the two overpacks which underwent physical examination, 3.
The hard wood maple block samples which were immersed in water for one hour had only a minimal increase (less than 17c) in expansion in all directions.
Therefore it can be concluded that the overpacks 181361, 181375 and E-MEH-00-00004 comply with the 1973 IAEA Safety Standards. Insomuch as the water spray evaluation indicates negligible effects with respect to other evaluations such as free drop, compression, penetration and thermal which were shown to comply with NRC regulations when the certificates of competent authority were issued on October 28, 1977.
1
a APPENDIX 1.
Certificates of Cometent Authority USA /5796/B and USA boll /B.
2.
Report from Herron Testing Laboratories 3,
Calculations 4.
Test Data of Wood Block Samples 5.
Drawings l
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IAEA CERTIFICATE OF COMPETENT AUTHORITY am
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l' Type B Fissile Radioactive Material Package Design
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Certificate Number USA /5796/B L. ', 3 (Revision 1)
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' 1]1 This establishes that the packaging designs described herein, j
when loaded with the authorized radioactive contents, have l
been certified by the National Competent Authority of the United l States,. as meeting the regulatory requirements for Type B l
- 1'j packaging for radioactive materials as prescribed in IAEA1 1
Regulations and.ss 49 CFR 173. 393b and 173. 394 (c) (2) of the
{j USA 2 Regulations for the transport of radioactive materials.
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Package Identification - Picker Models Nos: 181375 and 181361.
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Packaging Description - Packaging authorized by this certificate consists of an overpack that provides impact and thermal protection for teletherapy head assemblies or source i
exchange assemblies.
The cubical overpacks are.contructed from 2" by 4" maple panels bolted together and covered with 16 gage steel panels with opening limiting steel straps and f.
j angles.
Model 181375 is approximately 37" x.40" x 41" with a 1
gross weight of 3325 pounds and Model 181361 is approximately
,I 39".x 39.5" x 48" with a gross weight of 4000 pounds.
l III.
Authorized Radioactive Contents - The authorized contents I
1 I consist of large quantities of Cobalt-60 as special form packed in a secondary container and limited to a maximum of 3,
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13,680 curies and a decay heat load of 200 watts.
IV.
General Conditions -
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a.
Each user of this certificate must have in his f ;
possession a copy of this certificate.
b.
Each user of this certificate, other than the 4:
Picker Corporation, Cleveland, Ohio shall register
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his identity in writing to the Office of Hazardous I'
Materials Operations, Materials Transportation M
j; Bureau, U.
S. Department of Transportation, q
y Washington, D. C.
20590.
1.
This certificate does not relieve any consignor c.
or carrier from compliance with any requirement of
..y ' H the Government of any country through or into which
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the package is to be transported.
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Marking and Labeling - The package must bear the d;%
marking USA /5796/B as well as the other marking and labels
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prescribed by the USA Regulations.
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Expiration Date - This certificate, unless-renewed,
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of the IAEA and USA Regulations and in response to the 1JJ 3;
October 20, 1977 petition by Picker Corp., Cleveland, ' Ohio u..
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in U.
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Operations Materials Transportation Bureau i
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..' _ g 1" Safety Series No. 6, Regulittions for.the Safe Transport of
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International Atomic Energy Agency (IAEA), Vienna, Austria.
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Title 49, Code of Federal Regulations, Parts 100-199, USA.
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m ITIA CERTIFICATE OF COMPETENT IsUTHORITY
'Iype B Radioactive Material Package Design Certificate Nurber USA /9011/B This establishes that the packaging design described herein, when loadcd with the authorized radioactive contents, has been certified by tbc Uc tional Competent Authority of the United States, as meeting the regulatory requirements for 4
Type B packaging for radioactive natorials as prescribed in III Al Regulations and SS 49 CTF 173.393b, 17 3. 3 9 5 (c) ( 2 ) ; 46 CFR 116.19-100 ; and 14 CFR 10 3 of the US A2, 3, 4 Fegulations for the transport of radioactive materials.
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Package Iden ti fica tion - Model
'.s'o E-tiEH-0 0-0 0 00 4.
II.
Fackaging Description - Pachugir.g authorized by this certificate consist of a steel encased wooden everpack containing a teletherapy head assembly and measuring 36" X 36" x 41" with a maximum gross weight of 4000 pounds.
III. Authorized Radioactive Contents - The authorized contents consist of large quan ti ty radioac tive ma terial n.c. s., as not more than 13,6 80 Ci of Cobal t-60 which r us t rect the recuirc-ments of special form as defined in 49 CFR 173.369(g) and with a decay heat load of not more than 200 wa tts, IV.
General Conditions -
a.
Each user of this certificate r.ust have in his possession a copy of this ccrtificate.
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b.
Each user of this certificate, other than Picker Corporation, Cleveland, Ohio shall register his identity In writing to the Of fice of Hazardous Materials Operations, Materials Transportation Dureau, U.
S.
Departnent o f Trans-portation, Washington, D.C.
20590.
c.
This certificate does not relieve any consignor or carrier f rom cer:pliance wi th any requir.e.nont of the Government of any country thrcugh or into which the package is to be transported.
a V.
- larking and Labelin.3 - The package must bear the marking t'S7s/90ll/D as well as the other marking and labels prescribed by the USA F.egulations.
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Certificate Number USA /9011./B Fage 2 i
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Expiration Dato_ - This certificate, unless renewed, expires on January 31, 1979.
This certificate is issued in accordance with the requirements of the IAEA and USA Pcgulations and in response to the January 6, 1976 petition by Picker Corporation, Cleveland, Ohio, and in consideration of the associated information provided in U.S.
Nuclear Regula tory Cemenission Certificate US A/90ll/B (!ppendix A).
Certified by:
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Chief, TechnoloUy Division
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Of fice of llazardous fiatorials Operations U.S. Department of Transportation
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6, Regulations for the Safe Transport of Radioac ti.'e Ma terials, 1967 Edition" published by the Inter-national Atomic Energy Agency (IAEA), Vienna, Austria.
d 2 Title 49, Code of Federal Degulations, Parts 100-199, USA.
," Title 46, Code of Federal Regulations, Fart 146, USA.
4 Title 14, Code o f Federal Regulations, Fart 103, USA.
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