ML19323F687
| ML19323F687 | |
| Person / Time | |
|---|---|
| Site: | 07109007 |
| Issue date: | 05/08/1980 |
| From: | Santoro M AUTOMATION INDUSTRIES, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 16297, NUDOCS 8005290337 | |
| Download: ML19323F687 (10) | |
Text
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O ^ PERRY DIVISION r7 S
,I; P.O. BOX 245 a.
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FHCENIXVILLE, PA.19460 L.
(215) us3-e961 May 8, 1980 Mr. Charles E.
MacDonald, Chief Transportation Branch Div. of Fuel Cycle & Material Safety U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Ref:
Your Dockqt #71-9007 Renewal of Certificate of Compliance Package Ident. No. USA /9007/B Expires May 31, 1980.
Dear Mr. MacDonald:
Confirming our telecon of May 6, 1980, I am submitting eight (8) complete sets of Test Data with results which were used for qualifying the above referenced package.
The above data has been revised to incorporate all applicable supplemen-tal data which is referenced on the present Certificate of Com-pliance.
Please note that the above revision does not consolidate the supplementary data covered in my letter to the NRC dated Nov. 28, 1973.
This referenced data was to clarify source pig-tail models and various connector types which do not relate to the structural integrity of the package.
However, by revision, I have. incorporated the additional test data which is referenced in my letters to your office dated Feb. 18 and April 4, 1975.
These two (2) referenced letters relate to additional drop t e s ts perfomed on the Model 520 device to assure that impact occurred to the most 'ulnerable part of the shielded device (ie., Lockbox and, v
protruding seal plug.)
The above test data with results have been added by revision I
to Page 1 of the Test Report and by adding an appendix to Page 8.
THIS DOCUMENT CONTAINS
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P00R QUAUTY PAGES 16237 i
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AUTOMATION INDUSTRIES, INC.
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SPERRY DIVISION r-e P.O. BOX 245 O
PHOEfJtXVILLE, PA.19460 L
(215) 933-8961 May 8, 1980 Page 2, Continued...
'E We will appreciate your prompt attention regarding renewal of the USA /9007/B certificate of Compliance due to the impending expiration date of May 31, 1980.
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Sincerely,
.h (L (. -
N Michael P.
S a n t o.r o, Gen'l Mgr.,
Nuclear Products.
MPS: deb cc: NRC File J.
Dwight S.
Boyko Enc: (8) Test results for Type "B"
Packaging.
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Q AUTOMATION INDUSTRIES, INC.
SPERRY DMSION PA SCX 245 PHCENXVlu& PA,19440 cm 92u964 TEST RESULTS-NR TYPE "B" PACKAGING IRIDIUM SOURCE CHANGER-SPENT URANIUM TYPE AND MODEL 520 IRIDITRON EXPOSURE DEVICE In an effort to reduce transportation costs and also as an effort towards product improvement, Automation Industries, Inc has de-signed and constructed a new Iridium Source Changer for servicing our Iridium-192 customers.
Our new Source Changer will use Spent Uranium as the shielding medium. By utilizing Spent Uranium, our new changer is approxi-mately one quarter the volume and one-third the weight of our present lead shielded Changers. The gross shipping weight of the nee Source Changer will be sixty (60) pounds. This reduction in size and weight renders a very compact, rugged, and structurally sound design, capable of withstanding severe abuse encountered during shipment and in field use.
The container design consists of a rectangular box, approxi=ately 5" wide x 7" high x 11" long, fitted with a hinged cover to permit access to the internal compartment. The entire unit is fabricated j
from type 18-8 Stainless Steel sheet, s/10 Gage, (0.140" thick),
with all corners and seams continuously welded. The Spent Uranium shield is completely encased in an all-welded leak tight compart-ment.
The shield is fixed in the compartment by seal welding the two (2) exit tubes through the partitioning sheet, and then potting with a high temperature solid epoxy. The unit is designed to met the requirements of D.O.T.-55 Specification.
In essence, this new changer is a miniature version of our present lead shieldsd changer. All threaded connections, threaded seal caps, transfer tubes, method of packaging, securing and sealing are the same for both units. The procedures to be followed for effect-ing a source change in the field are also the same for both units.
The same operating instructions will apply for both Source Changers.
As designed, the Spent Uranium Changer is a D.O.T.-55 shipping con-tainer; however, at this time, Automation Industries, Inc. would also like to qualify it as a Type "3" shipping container. In order to substantiate this qualification, the Spent Uranium Source Changer was subjected to the following test requirements of the International Atomic Energy Agency. Tests were performed sequentially in the order listed below:
A.
MECHANICAL TEST Free Drop 3Al The package was dropped from a height of thirty-four (34) feet onto a flat, horizontal, 5/8 inch thick steel plate.
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Julv 24, 1973 1
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Michael P. Santoro N@Rev.
Product Manager, Nuclear 31 Dated 5-8-00 t
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$ AUTOMATION INDUSTRIES, INC.
SPERRY DMSiON P.o. BCX 245 PHCENIXVlif. PA 19460 ats 9um Free Drop #2 The package was dropped from a height of forty (40) inches onto the upper end of a steel circular bar which was perpendicular to the concrete pad.
The target surface of the circular bar was flat with its outer edges rounded off to a radius of six (6) mm.
Devia tion s :
(a) For the Free Drop #1, the 5/8" steel plate was not wet floated onto the concrete pad.
However, the eight (8) inch thick concrete apron was flat and horizontal, as was the steel plate, and the contact interface was intimate.
(b) For the Free Drop #2, the circular steel bar was three (3) inch diameter in lieu of the fifteen (15) cm. diameter called fo r.
OBSERVATIONS:
Subsequent to Drops #1 and #2, visual in-spection and radiation surveys indicate, that the container and/or containers, as presently designed, would have sustained more severe test conditions, and still maintained integrity. Results of the drop tests showed negligible effects.
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3.
THERMAL TEST The container and/or containers were suspended by wire rope from an "A" frame, centered over a 66 inch by 66 inch fuel pan, having five (5) inch sides.
The container and/or container, were positioned approximately twelve (12). inches above the surface of the fuel. The fuel consisted of a 50/50 percent i
mixture of Kerosene and #2 Fuel 011. Total time of exposure to flame was fourty-seven (47) minutes.
This exceeded the required test period by seventeen (17) minutes, since we were unable to extinguish the flame by use of three (3) conventional CO2 extin-guishers. Two (2) local Fire Companies arrived with suitable foam generating equipment to blanket the flame. The container and/or containers were allowed to cool naturally for a period of three (3) hours.
Devia tions :
Total time of exposure to flame was fourty-seven (47) minutes, due to difficulty encountered in attempting to extinguish the fire at the thirty (30) minute mark.
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_ July 24, 1973 Pdchael P. Santoro Product Manager, Nuclear
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@ AUTOMATION INDUSTRIES, INC.
SPERRY DMSION PCL Box 245 PMoeeXVluf. PA 19460 G5193&a961 For ecological reasons and also potential fire haz-ards, the same fire was used to expose two (2) dif-ferent containers siguitaneously.
(The Spent Uranium Source Changer and Our Ebdel 520 Iriditron Exposure Dev;ce.)
An attempt to monitor the flame temperature, using a Weed Ebdel 8000 Temperature Indicator with platinum resistance probe (0 to 1600 *F) failed, due to a malfunction in the instrument or a short in the probe ele men t.
OBSERVATIONS:
Af ter the three (3) hour cooling period, both contain-ers were inspected visually for structural damage, and also monitored for any radiation hazards. There were no apparent high surface radiation levels. Both con-tainers exhibited bulged or " pregnant" attitudes, due to extremely high internal pressures resulting from the decomposition of the trapped epoxy potting resins at the elevated temperatures. The internal gas pres-sures had to be exceedingly high in order to permanently set a convex bow on all surfaces of the containment shells (#10 Gage, 0.140 inch thick, type 304 Stainless Steel Place).
The Spent Uranium Source Changer showed no structutel failure, nor any loss of shielding integrity, as a result of the fire test.
The Model 520 Iriditron did spring about 507, of the weld seam on the bottom portion of the rear end plate, (Lock Box End).
This occurred at approxi=ately the fourty (40) minute elapsed time mark, while the firemen were proppring to
'.anket the fire with foam. The weld failure was clearly evidenced by a muffled explosion, followed by a rapid release of expanding gases or epoxy vapors.
Close up inspection showed that the lower segment of the rear end plate had pulled away from the shell tube, forming an angle of approximately 15'off the perpen-dicular. Accordingly, this rotatien of the rear end plate caused the lockbox to be cocked upward approxi-mately 15* off the horizontal.
One end of each hold down tube on either side of the Model 520 base, had separated from the end plates.
These separations are not relevant to containment of shielding integrity, however, they do attest to the tremendous forces that were built up and released, in order to cause these weld failures.
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/6 M. AM 6-July 25, 1973 Michael P. Santoro Produc t Manager, Nuclear
(4) h AUTOMATION INDUSTRIES, INC.
SPERRY DillSION PO. box 245 PA, :9460 It was also noted that the leather handles, and alumi-num Radiation Warning Tags and Labels, had completely disintegrated. Stainless Steel Nameplates and chemi-cally etched engravings remained legible. On the Model 520, the aluminum Source Identification Plate was 60%
melted away, and the remaining portion not legible.
C.
CONTAINMENT AND SHIELDING INTEGRITY During each test, each container was loaded with a sealed source of Iridium-192 of following strengths:
1.
SPENT URANIUM SOURCE CHANGER i
Drop Tests 1 and 2, 34 Curies of Iridium-192 (See Chart "A")
30 Minute Fire Test, 30.7 Curies of Iridium-192 (See Chart "C")
2.
'ODEL 520 IRIDITRON (EXPOSURE DEVICE)
Drop Tests 1 and 2, 24 Curies of Iridium-192 (See Chart "B")
30 Minute Fire Test, 21.5 Curies of Iridium-192 (See Chart "D")
Radiation Surveys were performed on both centainers, prior to and af ter being subjected to each test.
Dose rates were measured and recorded for surface le rels; at six (6) inches from external surface, and at one (1) meter from the external surface. See Charts "A" to "D" for radiation survey results.
(a) The Spent Uranium Source Changer did not exhibit in any significant change in dose rates after each and cumulative tests.
(b) The Nbdel 520 Iridieron did not exhibit any significant change in dose rates after Drop Tests 1 and 2.
However, after the Ther=al Te s t, some of the surface and six (6) inch do a rates increased, while others directly opp.ite in location decreased, (see Chart "D").
The cumulative average of dose rates did not shift more than 15%. This could be considered negligible. This change in radia-tion dose levels can be attributed partly to the complete loss of epoxy resin, when the rear end plate seal weld ruptured and reliev-ed the internal pressure. It was calculated
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July 24, 1973
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Plchael P. Santoro Product >bnager, Nuclear
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SPERRY DIVISION PQboXid PHOEraIvu,os t PA,19440 m ma that the epoxy offered approximately l' of the shielding value. The major cause of shift in dose levels was caused when the lockbox cocked upwards. This motion of the lockbox pulled the Iridium-192 source capsule cet of center position in the shield; approximately 3/16" off center.
The source pigtail is positioned and fixed into the shield by means of the lock prongs and limiting orifice when the unit is in locked position. Accordingly, when the locking mechanism rotated upward, the source pigtai~ was displaced an equal amount. This explains why some dose read-ings increased, while others decreased.
Since the Model 520 Shield is overdesigned, with resulting good safety factor; and a 1/2" safe dwell position in the center of the "S" tube, the source capsule can be translated at least 1/4" to eigher side of the theoretical center before appreciable changes in radiation dose levels are noticed.
This feature was designed into the unit.
D.
PHOTOG RAPHS The following photographs numbered one (1) through twenty-three (23), illustrate the set-up, progress, and effects of tests on the containers:
- 1------------------ 30 Foo t Free Drop
- 2------------------ Spen t Uran ium Change r -
Prior To Test
- 3------------------ Fbde l 520 Irid itron -
Prior To Test
- 4, 45-------------- Fbdel 520 Iridieron -
Af ter 34 Foot Free Drop
- 6------------------ Spen t Uranium Change r -
After 34 Foot Free Drop 47------------------ Fbdel 520 And Source Change r -
After All Mechanical Tests
- 8, 49-------------- Fbdel 520 Iridicron -
Before And After Drop Onto Circular Pin
- 110,
- 11------------ Source Changer -
Before And After Drop Onto Circular Pin
- 12,
- 13------------Close Up Of Fuel Pan -
Prior To Therma 1 Test
- 14, 415,
- 16------- Progress Of Ther=al Test
- 17,
- 18------------Source Changer And Model 320 -
Af ter Ther=al Test Note Source Pigtail Connectors Protruding From Lockboxes.
Note Seam tJeld Rupture On Model 520 Iriditron.
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July 24, 1973 Michael P. Santoro Product Mana ge r, Nuclear
(6) d AUTOMATION INDUSTRIES, INC.
SPERRY DIVISION P o. ScX 243 PA 19440
- 19-----------------Side View of Mode l 520 -
Af ter Thermal Test Note Cocked Position of Lockbox
- 20, 121------------ Radiation Surveys
- 22, 123------------ Radiation Surveys E.
I?.TEGRITY OF SOURCE CAPSULE (ENCAPSULATION)
After completion of all tests, both souice capsules were leak tested to deter =ine whether there was any leakage of radioactive contents. Both leak test re-suits were negative with respect to leakage.
Source Serial Number IR-6964, contained in Model 520 Iridicron.
Leak Tested on June 6, 1973 After Fire Test Removable Contamination: Less than 0.001 micro curies Source Serial Number IR-7056, contained in Spent Uranium Source Changer.
Leak Tested on June 6, 1973 After Fire Test Removable Contamination: Less than 0.001 micro curies Visual inspection of the two (2) Source Pigtails when inspected under =agnification while viewing through our Hot-Cell viewing window, indicated that there was no mechanical damage imparted to either capsule assembly as result of tests.
F.
RECOMMENDATIONS Due to dv severity of the Thermal Test, (011 Fire),
we would suggest that anyone performing this test, do so in a very isolated area, removed from any flace cable equipment or buildings. It is also recommended that t ained professional fire-fighting personnel and equipment, be on hand to terminate the test, and for obvious safety reasons. The heat intensity of this test is so overwhel=dng, that it is impossible to approach the flame with conventional hand-held fire extinguishers, when attempting to extinguish the flame after the thirty (30) minute exposure.
G.
CONCLUSION It is our opinion that both of these containers satis-factorily met the Type "3" test requirements of The International Atomic Energy Agency, and that they be certified as such by assignment of individual Cartifi-cation Marks as issued by the U.S. Department Of Trans-portation, (D.O.T.).
'4e desire that this certification July 24, 1973 Michael P.
Santoro Product Manager, Nuclear
(7)
$ AUTOMATION INDUSTRIES, INC.
SPERRY DMSlON Po. SCX 245 PA 19460 or permit be acceptable for both domestic and export shipments.
Since the Model 520 Iridieron is an Exposure Device, used in Industrial Radiography, and the Spent Uranium Source Changer is a shipping Container for transport-ing new replacement sources to our customers, and the returning of decayed sources to our Phoenixville faci-lity for ultimate disposal, it is hoped that this type "B" certification will not require that our domestic customers register with the D.O.T. to enable authoriaed receipt, ase, or transshipment of these con taine rs.
(They are D.O.T.
55 Spec. containers, and we do not feel that our domestic customers should be burdened with additional registration, simply be-cause we tested and proved that the containers will withstand the more rigorous tests of Type "B" packaging. )
H.
SP'CIAL FORM MATERIAL (a) The Spent Uranium Source Changer and the Model 520 Iridieron, will be used only as shielded containers for the isotope Iridium-192 in solid metallic form. The wafers of Iridium-192 are encapsulated into stainless steel capsules using a 1770* F silver brate, (Eutectic Welding Alloys Company,11807),
for the scaling process. The sealed sources are decontaminated and leak tested prior to inse.rtion into the shielding units.
(b) To date we have distributed over 7400 Iridium-192 Sealed Source Capsules of this design to licensed recipients.
(c) The isotope Iridiucr192 in solid metallic form, is an noble metal and meets all the require-ments of melting point, sublimation, percussion friability, low solubility or dissolution, and chemical stability tests, as outlined in the Lnternational Atomic Energy Agency regulations.
Since we encapsulate no wafers of metallic Iridiumm192 which have any dimension less than 0.5 =m, the radioactive material in itself is Special Form.
I.
RECUEST FOR APPROVALS (a) We request that the Spent Uranium Source Changer be certified as a Type "3" package for shipping Special Form, Sealed Sources of Iridiumm192, up to, but not exceeding, 300 Curies.
Specific Activity Range: 300 To 400 Curies / gram Y :' O M. /~
Ja y 24, 1973 Michael P.
Santoro Product Manager, Nuclear I
e (8)
$ AUTOMATION INDUSTRIES, INC, SPERRY DMSION P CL SCX 243 PHOEMXVt14 PA 1946o (2141 9314904 (b) We request that the Mode 1 520 Iridieron be certified as a Type "B" package for shipping Special Form, Sesled Sources of Iridium-192, up to, but not ex-ceeding,120 Curies.
Specific Activity Range: 300 To 400 Curies / gram.
(c) We request that our Iridium-192 Isotope be certified as Special Form Shipment and/or Special Form Material.
// M es July 24, 1973 Michael P. Santoro Product Manager, Nuclear REVISION 81.
APPENDIX "A" (ADDED 5-8-80)
ADDI!!ONAL OROP TEST PERFORMED TO MODEL 520 SHIELD TO INSURE THAT TORCE OF IMPAC* OCCrRRED TO MCST "LINERABLE PART OF *HE DEVICE.
(a) Dace of Test: April 2, 1975 (b) Description of Test: 30 ft. free drop onto unyielding target consisting of 6 inch thics flat steel plate.
(c) Orientation of Device A guy wire was e= ployed to maintain proper orientation to assure that maximum damage occurred to the locking mechanism and protruding seal plug connector.
(d) Test Seecimen: The 520 shield was the same unit which had previously been subjected to sequential drop, puncture, and fire exposure when qualifying the unit for Type "3" Packaging.
RESL'I.TS & OBSERVATIONS (a) Af ter I: coact: The locking mechanism remained locked - The protruding seal plug connector was slightly deformed-And the guy wire still maintained the 520 shield in a vertical attitude.
(b) Af ter removing guy wire, deformed seal plug connector was removed-There was no evidence of any damage to the source pigtail connector - And the source pigtail asse=bly was still retained in the proper locked, stored position.
(c)
Conclusion:
Results of this test clearly demonstrates the inherent stability of ths Macel $20 shield and that the device would withstand tests of this severity.
- 44. M 44h May 3. 1980.
Micnaal P. Santoro General Manager, Nuclear Products.
16297