ML20059E834
| ML20059E834 | |
| Person / Time | |
|---|---|
| Site: | 07109167 |
| Issue date: | 10/29/1993 |
| From: | Podolak L AMERSHAM CORP. |
| To: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9311030373 | |
| Download: ML20059E834 (8) | |
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p-AmershamCorporation 40 North Avenue Burlington, MA 01803 tel(617) 272 2000 29 October 93 tens 00> 225-1383 Mr. Cass R. Chappell, Section Leader Cask Certification Section
[ Amersham Storage and Transport Systems Branch QSA Division of Industrial and Medical Nuclear Safety, NMSS U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, Maryland 20852 RE:
Docket No. 71-9167 i
Dear Mr. Chappell:
Enclosed are revisions to Sections 7 and 8 of the SAR for the Model 3206B, 3227B and 3218 shipping packages. These sections incorporate the information requested in your 28 Sept 93 letter.
Should you have any questions regarding this submission please contact me at (617) 272-2000, extension '230.
Sincerely, 0/
(
>cl h L Lori Podolak Assistant Radiation Safety Officer
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- 7. Ooeratino Procedures 7.1 Procedures for Loadina the Packaae The encapsulation of the radioactive sealed sources is performed under an NRC, Agreement State license or in accordance with International regulations.
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1.
Load the source capsule into either a machined stainless steel holder (source holder) or threaded onto " nose plugs" as applicable. A " nose plug" is a machined stainless steel holding l
device which attaches to the threaded source capsule by means -
j of mating threads. The source capsule is further secured to the nose plug by crimping a locking ring into the notched areas in the source capsule and nose plug.
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2.
Fix the assembly (source with holder or plug) inside the -
stainless steel insert.
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3.
Attach insert with source assembly to the outer support or source tube with M6 bolts.
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Insert the stainless steel encased WEP shielding plug into the l
support tube and secure in place using a knurled stainless steel screw cap. To ensure a positive closure, the screw cap shall be hand tight plus one quarter turn.
NOTE:
The screw cap will not fully close unless the source and shielding plug are correctly installed I
within the stainless steel insert.
5.
Lock the stainless steel latch bar into place over the screw cap with a key operated padlock.
(For Model 3218 packages, repeat steps 1-5 for the reference or calibration source and receptacle if a source will be shipped in that receptacle. For this receptacle, a stain! ass steel insert is used instead of the WEP shielding plug referenced in step 4.)
6.
Attach a tamper proof security seal with an identification mark to the lock and latch bar.
Revision 3 7-1 29 October 93 h--
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7.
Assure all the conditions of the Certificate of Compliance and Certificate of Competent Authority are met and the package has all the required markings.
8.
If the shipping container is to be packaged in a crate or other outer packaging, the outer packaging must be strong enough to withstand the normal conditions of transport. The shipping container should be put 5 the outer package with sufficient blocking to prevent shifting during transportation.
9.
Perform a radioactive contamination wipe test of the cuter shipping package. This consists of rubbing filter paper or other absorbent material, using heavy finger pressure, over an area of a
2 16 in (100 cm ) of the package surface. The activity on the filter paper should not exceed 0.0001 uCi of removable contamination.
10.
Survey the package at the surface and 40 inches (1 meter) from the surface using gamma and neutron radiation survey meters to determine the proper radioactive shipping labels to be applied to the package as required by 49 CFR 172.403. If radiation levels above 200 millirem /hr at the surface or 10 millirem /hr at 40 inches (1 meter) from the surface are measured, the container must not be shipped.
11.
Ship the container according to proper procedures for transporting radioactive material as established in 49 CFR 171-178.
NOTE:
The U.S. Department of Transportation, in 49 CFR 173.22(c) requires each shipper of Type B quantities of radioactive material to provide prior notification to the consignee of the dates of shipment and expected arrival.
7.2 Procedure for Unicadino the Packaae The procedure for unloading the package will be specific to the user's licensing provisions and their facilities for handling radioactive material. These will be covered by a specific license issued by the appropriate regulatory authority, however, the following describes a generic receiving procedure for tnese packages.
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Revision 3 1
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The consignee of a package of radioactive material must make arrangements to receive the package when it is delivered. If the package is to be picked up at the carrier's terminal,10 CFR 20 requires that this be done expeditiously upon notification of its arrival.
l Upon receipt, survey the package with a gamma and neutron survey meter as soon as possible, preferably at the time of pickup and no
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more than three hours after it was received during normal working hours. Radiation levels should not exceed 200 millirem /hr at the surface of the package, nor 10 millirem /hr at a distance of 40 inches (1 meter) from the surface. Actual radiation levels should be recorded on the receiving report. If the radiation levels exceed these limits, the container should be secured in a Restricted Area, and the appropriate personnel notified in accordance with 10 CFR 20.
Perform a radioactive contamination wipe test of the outer shipping package. This consists of rubbing filter paper or other absorbent a
2 material, using heavy finger pressure, over an area of 16 in (100 cm )
of the package surface. The activity on the filter paper should not exceed 0.0001 uCi of removable contamination.
I All components should be inspected for physical damage. The
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radioisotope, activity, model number and serial number of the source j
and the package model number should be recorded.
The following procedure should be employed for unloading the package:
1.
Acquire the padlock key (s), unlock and remove padlock (s).
2.
Rotate the latch bar to the open position.
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Loosen and unscrew the threaded screw cap.
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4.
Using the appropriate remote handling tool, remove the i
stainless steel encased WEP shielding plug (as applicable).
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Affix the appropriate remote handling tool to the source assembly.
6.
Dislodge the source assembly from the insert and immediately upon removal, place the source assembly into an adequately shielded facility.
Flevision 3 7-3 29 October 93 l
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7.3 Preoaration of an Emotv Packaoe for Transoort The following procedure is employed in preparation of an empty package for transport.
1.
If the container is to be shipped empty, assure that there are no unauthorized source assemblies within the container by performing the following procedure:
a.
Measure the dose rate with appropriate gamma and neutron meters at the surface of the container while carefully removing the storage plugs.
4 b.
Visually inspect, using remote manipulators, mirrors and radiation levels as appropriate, to prove that the container is empty.
2.
Assure that the levels of removable radioactive contamination on the outside surface of the package does not exceed 0.0001 2
2 uCi per 16 in (100 cm ),
3.
When you have assured the package is empty, if container has been found free of contamination (as defined in 49 CFR 173.443) ship as non-radioactive material.
7.4 Anoendix Not applicable.
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Revision 3 7-4 29 October 93 J
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- 8. Acceotance Tests and Maintenance Proaram 8.1 Accentance Tests As of 01 August 91, all containers of these designs will be manufactured and used in accordance with Amersham Corporation's U.S. Nuclear Regulatory Commission Quality Assurance Program for Type B Radioactive Material Transport Packages, No. 0040. These containers will be acceptance tested in accordance with the Amersham Corporation Quality Assurance Program.
8.1.1 Visual Insoection The package is visually examined to insure proper assembly and that the package is correctly marked.
8.1.2 Structural and Pressure Tests Prototypes of each special form design are tested to a minimum of 290 psi external pressure.
8.1.3 Leak Tests Each radioactive source capsule will be subjected to the leak tests prescribed for special form sources in IAEA Safety Series No. 6, 1973 Edition and/or the USA Regulations in 49 CFR Part 173.
Failure of any of these tests will prevent the use of the source capsule.
8.1.4 Comoonent Tests The lock assembly, consisting of a padlock (s), latch bar(s), and screw cap (s) is tested for fit and function to insure that the security of the container will be maintained. Failure of this test will prevent the use of the container until the lock assembly is corrected and retested.
Revision 3 8-1 29 October 93
8.1. 5. Tests for Shieldino Intearity With the package containing an approved source capsule, the radiation levels at the surface of the package and at 3 feet from the surface of the package are measured using a small detector survey Instrument. These radiation levels, when extrapolated to the rated capacity of the package, must not exceed 200 millirem /hr at the surface nor 10 millirem /hr at 3 feet from the surface of the package.
8.1.6 Thermal Accentance Test l
Not applicable.
8.2 Maintenance Proaram 8.2.1 Structural and Pressure Tests l
Not applicable.
8.2.2 Leak Tests As described in Section 8.1.3, the radioactive source capsule is leak tested at manufacture.
8.2.3 Subsystem Maintenance The lock assembly is tested as described in Section 8.1.4 prior to each use of the package.
8.2.4 Valves. Ruoture Disks and Gaskets l
Not applicable.
8.2.5 Shieldino Before shipment of a source, a radiation survey of the package is done to ensure that the radiation levels do not exceed 200 millirem /hr at the surface of the container and 10 millirem /hr at one-meter from the surface.
Revision 3 8-2 29 October 93
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8.2.6 Thermal.
Not applicable.
8.2.7 Miscellaneous Not applicable.
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.i Revision 3 8-3 29 October 93 i
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