ML19343B136
| ML19343B136 | |
| Person / Time | |
|---|---|
| Site: | 07105796 |
| Issue date: | 11/19/1980 |
| From: | Kelbley N ADVANCED MEDICAL SYSTEMS, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19343B137 | List: |
| References | |
| 17930, NUDOCS 8012110356 | |
| Download: ML19343B136 (17) | |
Text
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2/- 5 794 Advanced Medical Systems,Inc.
1020 London Road Cleveland. OH 44110 (216)692-3268 U.
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November 19, 1980 3
U.S. Nuclear Regulatory Commission O
O Transportation and Certification Branch
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Division of Fuel Cycle and Material Safety idt Washington, D.C.
20555
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M Attention:
Mr. Charles E. MacDonald, Chief I
o o
Gentlemen:
The enclosed is an application for renewal, with minor changes, of Certificate of Compliance USA /5796/B (U).
This application is also referenced to Picker Corporation application dated December 19, 1974 and Supplements dated October 1975; M:.y 29 and August 15, 1979; and January 4, 1980.
'd Picker Corporation has sold its therapy products to Advanced Medical Systems, Inc. Picker Corporation will register as a user of the permit by separate letter.
Our check in the amount of $690.00 fee is attached.
If additional information is needed, please contact the writer at (216) 692-3268.
Sincerely, ytwse' 0 l
Norman D. Kelbley Radiation Safety Officer O
NDK/ cmc yr.
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O' Application for U.S.N.R.C. Licensing By A.M.S., Inc.
1.0 General Information 1.1 Introduction 1.2 Packaging Description 1.2.1 Packaging 1.2.1.1 Two slightly different demensional forms 1.2.1.2 Materials of construction for the 181375 Overpack 1.2.1.3 Source containment vessel in package 181375 is a special form capsule 1.2.1.4 The shutter rotor in irradiator machine head of package 181375 1.2.1.5 The shutter plug in irradiator machine head of package 181375 1.2.1.6 The cubical Overpack 181375 1.2.1.7 The cover of overpack 181375 1.2.1.8 The pallet base of Overpack 18375 1.2.1.9 Particulors for 181375 package 1.2.1.10 Drawing list for 181375 1.2.1.11 Source containment vessel in package 181361 is a special form capsule (m) 1.2.1.12 Materials of construction for the 181361 Overpack 1.2.1.13 Source shipping and exchange containers 181361 1.2.1.14 The cubical Overpack 181361 1.2.1.15 Particulars for 181361 l
1.2.1.16 Drawing list for 181361 1.2.2 Operational features 1.2.3 Contents of package 1.3 Appendix 2.0 Structural evaluation l
2.1 Structural design l
2.1.1 Discussion 2.1.2 Design Criteria 2.2 Weights & Center of Gravity 2.3 Mechanical properties of materials 2.4 General standards for all packages 2.4.1 Chemical and galvanic reactions i
l 2.4.2 Post.ive closure 2.4.3 Lifting devices 2.4.3.1 Lifting devices for 181375 overpack Container 2.4.3.1.1 Calculation for " factor of safety" using only one of four pickup ears (181375) i 2.4.3.2 Lifting devices for a 181361 Overpack Container 2.4.3.2.1 Calculations for " factor of safety" using only one of four pickup ears (181361) 2.4.3.3 General strength of lifting device w
(2) 2.4.4 Tiedown devices.
2.4.4.1 Tiedown devices for 181375 Overpack.
2.4.4.2 Tiedown devices for 181361 Overpack.
2.5 Standards for type "B" and large quantity package.
2.5.1 Load resistance, overpack sizes.
2.5.2 External pressure.
2.6 Normal conditions of transport.
2.6.1 Heat.
2.6.1.1 Summary of pressures and temperatures.
2.6.1.2 Differential thermal expansion.
2.6.1.3 Stress calculations.
2.6.1.4 Comparison with allowable stresses.
2.6.2 Cold.
2.6.3 Pressure.
2.6.4 Vibration.
2.6.5 Water Spray.
2.6.6 Free Drop 2.6.7 Corner Drop.
2.6.8 Penetration 1 1/4" Dia.
13# Rod dropped from 40".
2.6.9 Compression.
2.7 Hypothetical accident condition.
2.7.1 Free Drop of 30'.
2.7.1.0.1 Velocity and "G" Load Developed by a 30' Drop.
2.7.1.0.2 Stress on Hold Down Balts and Tie Bars.
2.7.1.0 3 Stress on Skids and Bottom Panel.
2.7.1.. 4 Relative Motion of Cobalt Head (Upside Down Drop).
lh 2.7.1.0.5 Energy absored by Overpack Top if Cobalt Head were to break loose (Upside Down Drop).
2.7.1.0.6 Stress on Shutter Plug Components due to Drop Normal to Shutter Plug Axis.
2.7.1.0.7 Stress on Mounting Devices and Side Movement of Cobalt Head due to side drop paralled to Rotor and Shutter Plug Centerline.
2.7.1.1 End Drop 2.7.1.2 Side Drop 2.7.1.2.1 Stress on Top (Upside Down Drop).
2.7.1.3 Most severe case of a 45 Corner Drop on Top.
l 2.7.1.4 Oblique Drop.
2.7.1.5 Su= mary.
i 2.7.2 Puncture Calculation for 40 inch fall of 181361 Overpack.
2.7.3 Thermal Calculation for Overpack subjected to flames.
2.7.3.1 Summary of Pressures and Temperatures.
2.7.3.2 Differen*.ial Thermal Expansion.
2.7.3.3 Stress Calculations.
l 2.7.3.4 Comparison with allowable stresses.
l 2.7.4 Water Immersion.
1 2.7.5 Summary of Damage.
2.7.5.1 Overpack 181375.
2.7.5.1.1 Free 30' Drop on Top of Overpack.
2.7.5.1.2 Free 30' Drop on Side Paralled to Rotor and Plug Centerline.
2.7.5.1.3 Free 30' Drop on Side Normal to Plug and Rotor Centerline.
2.7.5.1.4 Free 30' Drop on Bottom of Overpack.
2.7.5.1.5 Thermal.
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' 'm 2.7.5.2 Overpack 181361 2.7.5.2.1 Free 30' Drop on Side.
2.7.5.2.2 Free 30' Drop on Side.
2.7.5.2.3 Free 30' Drop on Bottom.
2.7.5.2.4 Thermal.
2.8 Special Form.
2.8.1 Description.
2.8.2 Free Drop.
2.8.3 Percussion.
2.8.4 Heating.
2.8.5 Immersion.
2.8.6 Summary.
2.9 Fuel Rod.
2.10 Appendix 3.0 Thermal Evaluation.
3.1 Discussion.
3.2 Summary of Thermal Properties of Materials.
3.3 Technical Specifications of Components.
3.4 Thermal Evaluation for normal conditions of transporation.
3.4.1 Thermal Model.
3.4.1.1 Analytical Model.
O 3.4.1.2 Test Model.
3.4.2 Maximum Temperatures.
3.4.3 Minimum Temperatures.
3.4.4 Maximum Internal Pressures.
3.4.5 Maximum Theral Stress.
3.4.6 Evaluation of package performance for normal conditions of transporation.
3.5 Hypothetical Accident Thermal Evaluation.
4.0 Containment.
4.1 Containment Boundary.
4.1.1 Containment Vessel.
4.1.2 Containment Penetration.
4.1.3 Seals & Welds.
4.1.4 Closure.
4.2 Requirements for Normal Conditiens of Transport.
4.2.1 Release of Radioactive Material.
4.2.2 Pressurization of Containment Vessel.
4.2.3 Coolant Contaminations.
4.2.4 Collant Loss.
4.3 Containment requirements for the Hypothetical Accident Conditions.
4.3.1 Fission Gas Products.
4.3.2 Release of Contents.
4.4 Appendix.
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O 5.0 Shielding Evaluation.
5.1 Discussion & Results.
5.2 Source Specification.
5.2.1 Gamma Source.
5.2.2 Neutron Source.
5.3 Model Specifications.
5.3.1 Description of Radial & Axial Shielding Configuration.
5.3.2 Shield Regional Densities.
5.4 Shielding Evaluation.
5.5 Appendix.
6.0 Criticality Evaluation.
7.0 Operating Procedures.
7.1 Procedures for Loading the Package.
7.2 Procedures for Unloading the Package.
7.3 Preparation of an Empty Package for Transport.
7.4 Appendix.
8.0 Acceptance Tests and Maintainence Program.
8.1 Acceptance Tests.
8.1.1 Visual Inspection.
8.1.2 Structural and Pressure Tests.
8.1.3 Leak Tests.
8.1.4 Valves, rupture discs., and fluid transport devices.
8.1.4.2 Gaskets.
8.1.4.3 Miscellaneous.
8.1.5 Tests for Shielding Integrity.
8.1.6 Thermal Acceptance Tests.
8.2 Maintainance Program.
NDK/ cmc
1.0 General Information Picker Corporation has sold it's therapy products to Advanced Medical Systems, Incorporated. Among these products are the radioactive sources, source heads, source shipping / exchange containers and the Overpack for use with these heads and containers.
Advar.ced Medical Systems, Inc. has all rights to these products.
Advanced Medical Systems, Inc. will manufa.cture sources, source heads and if necessary the source shipping /
exchange containers and Overpacks.
Advanced Medical Systems, Inc. will maintain the Cert-ficate of Complianco and the I.A.E.A. Certificate of Competant Authority. Picker Corportation will register as a user of the nermhs.
1.1 Introduction The packages will be used in the shipment of Type B and larger quantities of radioactive material, but no fissile material.
There are two " Overpack Shipping Containers " to be used. Part number 181375 is used in the shipment of source shielded irradator machine head models # 590C, 590D, 590E, 590F and 590G. Part number 181361 is used in the shipment of model 3320 AR source shipping / exchange containers.
The source shielded irradiator heads are used for Cobalt sources qualifying for special form.
The source shipping / exchange containers are used with Cobalt 60 sources in special form and Cesium 137 sealed sources as described in Picker Corporation letter dated January 4, 1980. The manufacture of Cesium 137 sources is not intended. However, shipment of these sources is necessary for the relocation, replacement and re-moval of existing units.
The Cobalt sources have been tested and registered with the U.S.N.R.C. (certificate is part of this application). The results of tests showing compliance for special form are also enclosed.
Advanced Medical Systems, Inc. will cortinue to man-ufacture source irradiator head models 590E, 590F, and 590G. The 3320 AR shipping / exchange containers hp may be manufactured, if necessary to complement the existing number of containers.
1
1.2 Package Description
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1.2.1 Packaging 1.2.1.1 The packages shall take on one of two slightly dif ferent dimesional forms dependig on its contents. One package will consist of a Cobalt special form capsule located within a rotor and shielded by a shutter plug--inside of an irradiator machine head which in turn will be secured and protected within an Overpack Container identified by drawing #181375. The end result will be for movement of a loaded irradiator machine head to a new location.
1.2.1.2 The primary materials of construction, for other than shielding purposes, are hardwood maple, stainless steel, mild steel and brass.
Shielding consists of nickel coated depleted uranium, tungsten and lead (99.8% pure).
The nickel encased depleted uranium shield weighs 49 pounds and its completely sealed in lead within a welded brass irradiator machine head. This depleted uranium is located near the center and in the area of the source "off position" cast brass irradiator machine head and will not be exposed to the atmosphere. The source capsule is located within a rotatable shutter plug and this in turn within the irradiator machine head identified by number 590D,E,F and G.
These heads are essentially all of the s,me construction. Parts #590F and G have the addition of a tungsten cap bolted above the depleted uranium t,nield for the "Off Position" before the head is lead filled.
1.2.1.3 The source containment vessel is the special form capsule.
It consists of a double stainless steel walled capsule sealed by TIG welding. The unused space within the inner capsule is filled with stainless steel or tungsten slugs.
The stainless steel capsules are housed in a tungsten cap-sule which is threaded on the outside. This threaded tungsten capsule.is securely threaded into the shutter wheel at the center of the irradiator machine head.
l 60
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Cobalt sources meet the requirements for "special form" j
as per #10 CFR 71 and I.A.E. A. safety series 1973.
A copy of the source design approval is included as reference documents.
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1.2.1.4 The shutter rotor is made of two matched stainless steel shallow cups welded together and further welded to a hallow shaft. Prior to welding, the stainless steel cups are machined to receive a 1415 pound nickel plated l
depleted uranium billet Letween two stainless steel 1
locating pins. A hollow tungsten block which eventually will house the source capsule, locks the uranium in position l
and is welded to the stainless steel cup assembly to form l
j a leak proof joint. After lead pouring all voids are filled, the uranium is completely encased and the hollow shaft 2
filled with lead for additional shielding.
1.2.1.5 The shutter plug is constructed of two brass end castings, plus brass tubing and a tungsten block shield. The tungsten block is welded within the brass weldment and the brass tubing brazed over these to form a closed container for lead pouring. Lead is then poured through a port in one end, lef t open for this purpose, and the filling port is then arc welded shut. The shutter plug serves to plug the large head bore supports and locates the shutter rotor in bearings and is designed to minimize crack radiation leakage. An added safety feature to prevent accidental opening of the shutter rotor at assembly is a shutter drive cover which completely conceals the shutter locking bar, lock bolt and safety wire.
When in transit the shutter rotor is mechanically locked in the "Off Position". A safety bolt is applied and is safety (lockwired) wired at the factory.
1.2.1.6 The cubical Overpack is composed of a pallet-base and cover which are rigidly secured together by a dovetail design and (20)
-13 socket headed bolts. The pallet construction is of laminated 2" x 4" hardwood maple blocks bolted together and contained within a welded k" x 3" x 3" n
angle-iron and strap steel frame. Skid runners are provided A')
under this pallet to facilitate lifting with a " fork-lift"
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truck.
1.2.1.7 The cover is similarly constructed with laminated 2" x 4" hardwood maple blocks forming a norminally l
3 5/8" thick wall and bolted together and covered with
- 16 gauge steel panels secured by welds on the inside and in a welded angle-iron and strap steel frame.
Designs restricts the open spaces between steel' straps to prevent entrance of a six inch diameter penetrating cylin-der. Steel panels over the hardwood blocks provide added puncture and fire protection for the wood and contents.
Lif ting of the package by the cover is accomplished by the use of four 3/8" x 6" straps and grusseted steel lifting eyes. The structural edges and lifting straps are welded together with (30) cross bars fab-ricated from k" x 4" hot rolled structured steel.
1.2.1.8 The pellet base is provided with a 13 1/8" diameter x 2b" steel weldment, lead filled for shielding toward the bottom and secured with (4) 3/8 - 16 through I
bolts. The irradiator machine head rests on and is roughly located by this weldment. In addition there are two gusseted steel hold down brackets secured to the base with (2) 3/4-10 diameter through bolts each.
O These brackets locate and secure the shielded irradiator l
machine head at its certer of gravity and by its trunnion mounting pads with (4) k-20 socket head cap screws from each of two opposite sides.
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1.2.1.9 Particulars For 181375 Package I
Net weight of shielded irradiator machine head and shutter plug 2123#
Cobalt 60 capsule 2#
Tare weight of Overpack shipping container 1200#
Gross weight of above 3325#
Overall exterior dimensions of overpack 37 x 40 x 41" high.
Lifting capability by (4) lifting ears or by fork lift truck.
60 Maximum radioactive contents of Cobalt special form 13680 curies.
Maximum decay heat load not to exceed 200 watts.
Maximum radiation leakage less than 10 mrh at one meter from source.
Maximum surface leakage to be below 200 mrh.
1.2.1.10 Drawing list for Package using 181375 Overpack.
Included in appendix 1.3 60 1.2.1.11 The second package will contain a Cobalt special form source or Cesium 137 source capsule located within a shipping / exchange container, which in turn will be secured and protected within an Overpack Container identified by drawing # 181361. The intended purpose of this package will be for relocation, replacement, or removal of such capsules.
60 The Cobalt sources meet the requirements for special form as per #10 CFR 71 and I.A.E.A. Safety Series 1973.
A copy of the source design approval is included as reference,(see appednix 1.3).
The Cesium source are sealed. They are constructed and inspected in accordance with Picker Corporation letter dated January 4,1980.
A copy of the letter is included as reference.
1.2.1.12 The primary materials for construction for other than shielding purposes, are again hardwood maple, stainless steel, mild steel and brass. Shielding consist of tungsten and lead, (99.8% pure).
1.2.1.13 Shipping / exchange container #3320 AR consists of a large steel sphere containing lead. Horizontal and verti-cal ports in container permit manipulation of the l
source for installation or removal from irradiator machine head. These ports are blocked'by plugs which are lock-wired in place to prevent inadvertent opening. The upper vertical opening is one through which a.
source capsule must pass when being transfered to an irrad-A l
iator machine head.
4 1
The upper vertical plug consistsof a brass cup O
filled with lead and closed by a silver soldered brass plate. This plug is positioned against a flange, gasketed and secured with (4) 7/16"-14 socket head cap screws and safety wire. An additional \\" bolt provides a safety feature to retain the upper vertical plug in place in case the top flange should be sheared off due to an accident.
A horizontal plug composed of brass cylinders closed on both ends and joined with a stainless steel tube is filled with lead and silver soldered shut. A split plug of tungsten is attached to the horizontal plug and has a density of 16.9.
This assembly fC-13707A is coupled with Cobalt retainer tongue ass-embly. This combination is installed in the horiz-ontal ports such that the tungsten effective thickness 60 source will be 3 3/16" thick.
above the Cobalt This plug is located and secured with a one-inch thick steel flange, four 7/16-14 socket head cap screws and gasketed. These screws are safety wired and an inter-mediate stop tab utilizing a \\" socket head cap screw pro-vides additional safety to prevent accidental opening.
This also provides an additional safety feature so that the plug will remain locked in place even if the locking flange should be sheared off in an accident.
The lower plug or push-rod assembly consists primarily of a tungsten plug bolted to a seamless brass tube filled j
with lead. The port opening is gasket sealed with a l
inch steel flange and secured with three %-20 screws.
An important feature of this design source holder is that it is " fool proofed" so that seven steps must take place in order to remove the lower plug an,d source capsule.
A.
Removal of lower flange B.
Removal of lower plug lock bolt C.
Breaking of seal and removal of horizontal opening flange D.
Withdrawing horizontal plug 3 29/32 inches E.
Breaking of seal and removal of top vertical opening flange j
l F.
Removal of top plug hold down bolts i
G.
Removal of top plug 1.2.1.14 This cubical Overpack # 181361 is similarly designed to that of #181375.
Instead of the (20) bolts securing cover to pallet, this Overpack uses (2) Ik" special threaded horizontal through bolts which secure cover to pallet and shipping / exchange container to pallet.
A In addition the shipping / exchange container is secured to the pallet with (4) vertical through bolts.
1.2.1.15 Particulars for this second package Net weight of shipping / exchange i
container #3320 AR 3000#
Tare weight of Overpack shipping container 1000#
Gross weight of Overpack and contents 4000#
Overall exterior dimensions of Overpack 39" x 39.5" x 48" high Interior cavity dimensions of Overpack 24" x 30" x 28k" high Lif ting capability by (4) lif ting ears or by fork lift truck.
60 Maximu n radioactive Cobalt material not to exceed 13,680 curies 60 Maximum decay heat load of Cobalt special f orm not to exceed 200 watts.
Maximum radioactive Cesium 137 material noc to exceed 2200 curies Maximum decay heat load of Cesium 137 not to exceed 17 wattts.
Time maximum decay heat is insufficient to have any adverse effect on the package during normal conditions of transport.
1.2.1.16 Drawing List for Package Using # 181361 Overpack Included in appendix 1.3 1.2.2 Operational Features For operation of packages #181361 and #181375 refer to sections #1.2.1.1 thru 1.2.1.16.
There are no complexities involved since the packages are secured with external bolts, nuts, and lif ting eyes which are obvious on the outside of both packages.
1.2.3 Contents of Packaging For amount of radioactive material involved, radiation leakage and decay head load refer to section # 1.2.1.8 for
- 181375 overpack andl.2.1.15 for #181361 overpack.
1.3 Appendix Descriptions, f eatures, contents, and various part-iculars concerning both # 181361 and #181375 packages are well identified by the index and information pertaining to these may readily be obtained.
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DRAWING NUMBER DESCRIPTION D-T60-478 Shipping Container B-T60A-547 Rotor Lock & Seal D-T60-558 Exchange Container C-3800A Cobalt Sources C-13707A Drawer B-13709A Cesium Pushrod C-13709B Cobalt Pushrod B-14241A Tongue Assembly D-16423A Rotor Assembly l
D-16423B Rotor Assembly D-16423C Rotor Assembly D-16424D Shutter Plug D-16424E Shutter Plug Machining D-16479 Cobalt Head D-16568 Cobalt Head B-37092A Cover f-~
(j B-37840B Tungsten Rotor Insert C-40067 Source Capsule B-46411 Uranium Rotor Insert E-46671 Head Casting I
A-46675 Tungsten Shield A-46675A Tungsten Shield Uranium Shield C-46879 C-55156 Top Panel Cobalt Head Machine E-63790 B-66377A Tungsten Bore Cap D-80051 Head Pre-Machining l
B-100043 Cobalt Head Tree l
C-181356 Upper Body C-181357 Lower Body-Box for 3320AR D-181361 l
C-181368 Bottom Weldment D-181369 Upper Weldment Box for Heads D-181375 11-181390 Tie Bar Shutter Plug & Rotor Assv.
D-182355 B-184704
. Tungsten Plug Head Welding & Lead Pouring D-184713' Name Plate C-200002 Name Plate C-200003 Head Transport prawing D-200016 Container Transport Drawing I )T D-200017
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NDK/anc
QUALITY ASSURANCE DEPARTMENT NUMBER ADVANCED MEDICAL QA 1014 SYSTEMS, INC.
Inspection Procedure for Containers With Overpacks Authorized for the Shipment of Radioactive Material Date issued ting Practice Test Other November 7,1979 Paga 1 of 5 1.0 REQUIREMENTS AND DESCRPTION:
1.1 in order to comply with NRC/ DOT regulations concerning shipment of Radioactive materials, this inspection procedure must be completed for each shipment of radio-active materials prior to movement of the material to the corrier for transporation.
Defects found during inspection must le corrected prior to material movement.
1.2 The requirements are opplicable when moving radioactive material in authorized containers from one customer location to another, movement of on authorized container from the field back to the factory or shipment of material to the field from the factory.
1.3 Authorized Shipping Containers.
60 1.3.1 Cobolt Shipments.
h 1.3.1.1 590C, D, E, F and G Head in overpack 181375.
1.3.1.2 C-12 Head in overpack D-MEH-00-00004.
v) 1.3.1.3 3320 AR Exchange Container in overpack 181361.
1.3.2 137Cs Shipments - 3320 B Exchange Container in overpack 181361.
1.4 Authorized Personnel The only personnel permitted to perform the inspection, and maintenance are f
those individulais on current NRC Licenses. Extensive repairs may be permitted by a outside contractor however, these repairs must be inspected by a Licensed l
individual before use. Qualifications of the licensed individuals were included l
with the license opplications.
1.5 Audit in accordance with 10 CFR Port 71, Appendix E ltem 18, the Safety Officer will make on audit of the maintenance of the containers and overpacks according to the c. heck list. The audit shall be on on unannounced basis at intervals no preoter than one (1) year.
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PREPARED BY APPRO' VAL CATALOG "
REVISIONS
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QA 1014 PAGE 2 0F 5 Gb
2.0 INSPECTIONS
2.1 The Inspection Data Sheet for Radioactive Moaerial Containers and Overpacks (QA 1014A) must be completed then forwarded to the Sefety Officer, Isotope Focility for audit and record retention. Field operations are to return the inspection Data Sheet in the pre-stamped self addressed envelope along with the waybill copy of the return shipment.
2.2 Factory inspections are te be completed by licensed Isotope Facility Technicians and field inspections are to be completed by Licensed Field Servicemen. When a field operation is done by on isotope Facility Technician and not supported by a Licensed Field Serviceman the isotope Facility Technician will complete the inspection Data Sheet.
3.0 CONTAINER PROCEDURE:
Perform each inspection step as indicated. Defects found during inspection must be corrected and re-inspected by a NRC Licensed individual. Repairs must be noted on the Data Sheet along with the signature of the Inspector (Licensed Individual).
A check mark is to be placed on the Data Sheet after each step.
3.1 Make a wet-smear of the external surface of the container. Field operations use o Victoreen 491 or equal to evaluate the wipe. The meter must read less than 200 CPM when the wipe is held 1/4 inch from the geiger tube (Beta shield open).
Factory operations are to use a well counter to determine wipe activity. Results must indicate 500 cpm or less of removeable contamination.
3.2 Perform a preliminary radiation survey of the container. Results should be 200 mr/hr or less on the surface and 10 mr/hr or less at 3 ft. from the surface.
t 3.3 Verify that the shutter or drawer is locked.
i 3.4 Verify that the gaskets on 3320 AR are in good condition.
3.5 Inspect the lifting loops on 3320 AR. Loops must be in good condition, not bent, and welds must not exhibit cracks.
3.6 Inspect the container to insure there is no mechanical damage which will offect the radiation integrity of the unit.
i 4.0 OVERPACK/ PACKAGE PROCEDURE:
i p Perform each inspection step as indicated. Defects found during inspection must d
be corrected and re-inspec'ed by an NRC Licensed individual. Repairs must be listed on the Data Sheet along with signature of the inspector (Licensed individual).
A check mark is to be placed on the Data Sheet after each step.
(Con't)
QA 1014 l
PAGE 3 0F 5 V
4.1 Inspect the overpack for the following mechanical chorocteristics.
4.1.1 All wood joints inside the overpack must be tight. Tighten reinforcing bars if necessary.
4.1.2 The wood joints inside the overpack should be free of holes and voids.
Holes can be filled with wood plugs.
4.1.3 Lifting loops should be free of domoge.
4.1.4 Welds on the framework must be free of cracks and damage.
4.2 inspect the skid runners for tightness and/or damage.
4.3 inspect the container to insure it is properly secured to the overpack skid.
4.4 Inspect that the bolts securing the overpack top to the skid are tight.
4.5 Inspect the package and insure it is seal wired.
4.6 Survey the package with container inside. The radiation level must be
(]/
less than 10 mr/br at any point 3 feet from the surface of the container and 200 mr/hr or less at the surface.
4.7 Inspect the outside package for the following labels.
4.7.1 Two yellow Radioactive lll diamond labels filled out with the radioactive material, number of curies and radiation units (MAX) as measured in 4.6 (mr/hr). These must be on opposite sides of the package.
4.7.2 Verify that the overpack bears a-11" x 18" yellow sign with mogento lettering listing Picker Corp., Cleveland, Ohio U.S.A.,
part number of the overpack, DOT opproval number, gross and empty weights, mode in U.S. A. and the radiation symbol. All markings must be clear and legible.
4.7.3 Verify that the opening instructions have been included with the package.
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QA 1014 A i
1 PAGE 4 0F 5 RADIOACTIVE MATERIAL SHIPPING RECORD CUSTOMER:
LOCATION CONTROL NUMBER CERTIFICATE OF COMPLIANCE NO.
4 CERTIFICATE OF i
COMPLIANCE HOLDER:
I CERTIFICATE IN OUR FILES:
AMS REGISTERED USER:
1 i
DATE OF SHIPMENT:
B/L NO.
SOURCE-INFORMATION:
Isotope i
Mfg./ Cat. No.
Serial No.
j.
Curies:
Curies Date:
- Wipe Test Reading
Wipe Test Date: _
f 7 AINER INFORMATION:
Model No.
Serial No.
CONTAINER QA INSPECTION AND MAINTENANCE.
l CHECK IF OK REPAIR NOTES ***********
f Internal Contamination l
External Contamination j
Preliminary Radiation Survey Mechanical Functions.
I Shutter or Drawer Locked Shutter or Container Sealed l
Gaskets in Good Condition
( if any)
-Lifting Loops in Good Condition.
(if any)
Tie Down Devices In Good
-Condition and Secured
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QA 1014 A PAGF. 5 OF 5 s
O OVERPACK INFORMATION MODEL NO.
SERIAL NO.
OVERPACK QA INSPECTION AND MAINTENANCE INSTALLATION KIT INITIAL Check If OK Complete per B/M Mechanical Functions Survey Meter All Wood Joints Tight Model No.
Nr Holes or Voids Serial No.
Lifitng Loops In Good Condition Date Calibrated Tie Down Devices In Good Condition and Secure Skid In Good Con-List Any Items in Need of Repair dition and Tight All Bolts Tight Overpack Identification Legible
[]
Overpack Sealed
()
Maximum Radiation Level at 3 ft.
Maximum Radiation Level on Surface 1tansport Index Labels Attached Opening Instruction Attached Shipping Tags Attached General Condition DATE INSPECTED:
INSPECTOR (Initials)
APPROVAL OF LICENSED PERSON REPAIR NOTES: ****************
Ente. repairs made to bring container or overpack into proper condition. Include initials of individual (s) making repairs and date of repairs.
FIELD NOTE:
THIS SHEET MUST BE RETURNED IN THE PRESTAMPED, SELF ADDRESSED ENVELOPE ALONG WITH THE WAYBILL.
IN THE EVENT THE WAYBILL AND THIS SHEET AND THIS SHEET ARE SEPARATED, RETURN THESE.
SHEETS AF INDICATED BELOW:
A Advanced Medical-Fystems, Inc.
(y Norman D. Kelbley, Radiation Safety Officer 1020 London Road Cleveland, Ohio 44110 AUDIT DATE
.' REVISION B