ML20148E476
| ML20148E476 | |
| Person / Time | |
|---|---|
| Site: | 07109128 |
| Issue date: | 05/21/1997 |
| From: | Roughan C AMERSHAM CORP. |
| To: | Yang L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9706030112 | |
| Download: ML20148E476 (6) | |
Text
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1 Amersham Corporation i
May 21,1997 40 North Avenue Burlington, MA 01803 Mr. Li Yang tel (617) 272-2000 Cask Certification Section tel (800) 815-1383 Storage and Transport Systems Branch fax (617) 273-2216 j
Division of Industrial and Medical Nuclear Safety NMSS U. S. Nuclear Regulatory Commission Washington, DC 20555 PAmersham QSA RE: Docket Number 71-9128 i
Dear Mr. Yang:
l We are providing the additional information as requested in your letter dated 24 Dec 96.
1)
Drawings are enclosed. I have enclosed a copy of drawing number 801-1001-159, we believe
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this is the proper drawing as it is referenced on the Certificate of Compliance. There is no drawing numbered 821-1001-159, 2)
The drawings which reference the other models were originally included as supporting information as the test reports reference the other models. As we are not manufacturing the model C-8, we have not updated these drawings.
3, 4)
We are not manufacturing the model C-8 and there is only one unit in existence, as such we
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do not have the information requested. The certificate is being renewed to allow for continued j
transport only.
UTot Chapter 8 has been updated to reference the specific sections of the regulations.
Amersham is not manuf acturing this device and has no plans to manufacture in the future. We do not request IAEA-85 approval as we do not have the appropriate level of manufacturing detail to provide the necessary information needed for the -85 approval.
I trust this contains the information to allow continued processing of the renewal request. If you have any questions, please coritect me. Thank you for your assistance.
Sincerely, d
Cathleen Roughan Regulatory Aff airs Manager 9706030112 970521 PDR ADOCK 07109128 C
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5 LOCK INSERT 801-1001-253 6 ROLL PIN 311-7001-0 01 LOCKBOX ASSY.
DRAWING N'JMS=R 801-lOOH 59 e%cse penwtuo on we.seeen cLsAmposw?
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Acceotance Tests and Maintenance Procram 8.1 Accentance Tests J
8.1.1 Visual Insoection The package is visually examined to assure:
1.
It was constructed in accordance with all referenced drawings on the
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Certificate of Compliance.
2.
The labels are inspected to assure they contain the required information and are marked in accordance with 10 CFR 71.85(c),10 CFR 40.13(c)(6) and are securely attached to the package.
3.
All appropriate f asteners are seal wired properly.
8.1.2 Structural and Pressure Tests The entire source assembly is subjected to a tensile test with a load of 200 lbs. (890N) for 60 seconds. Failure of this test will prevent the source assembly from being used.
8.1.3 Leak Tests The radioactive source capsule (the primary containment) is wipe tested for leakage of radioactive contamination and must be less than 0.005 microcuries. The source capsule is also subjected to a vacuum bubble leak test. Failure of either of these tests will prevent use of this source 1
assembly.
j 8.1.4 Comoonent Tests I
All components of the package are inspected in accordance with an inspection instruction for conformance with engineering drawings and specifications. The depleted uranium shield is tested for shielding integrity by radiation measurement prior to incorporation into the package.
8.1.5 Tests for Shieldina Inteority The radiation levels at the surface of the package and at 40 inches (1m) from the surface are measured using a small detector survey instrument (i.e.
AN/PDR-27). These radiation levels, when extrapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour at the surf ace nor ten milliroentgens per hour at 40 inches (1M) from the surf ace of the package. Failure of this test will prevent use of the package as a type 8(U) package.
8-1 Revision 5 May 1997 i
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-8.1.6 Thermal Accentance Tests -
Not Applicable 8.2 Maintenance Proaram i
8.2.1 Structural and Pressure Tests Not Applicable 8.2.2 Leak Tests i
As described in Section 8.1.3, the radioactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe tested for leakage of radioactive contamination at intervals not to exceed six months and must not exceed 0.005 microcuries.
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8.2.3 Subsystem Maintenance The package is inspected for tightness of f asteners, proper seal wires and general condition prior to each use.
8.2.4 Valves. Ruoture Discs and Gaskets on Containment Vessel m
Not applicable 8.2.5 Shieldino Prior to each use, a radiation survey of the package is made to assure that radiation levels do not exceed 200 milliroentgens per hour at the surface of the package nor ten milliroentgens per hour at 40 inches (1M) from the surface of the package.
8.2.6 Thermal Not Applicable 8.2.7 Miscellaneous Inspections and tests designed for secondary users of this package under j
the general license provisions of 10 CFR 71.12(b) are included in Section 8.2 Appendix A.
8-2 Revision 5 May 1997
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UNITED STATES g-g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20545 4001 p
j May 7, 1997 I
Ms. Cathleen Roughan i
Amersham Corporation j
40 North Avenue Burlington, MA 01803
Dear Ms. Roughan:
.This is in regard to your application dated November 6,1995, as supplemented l
on August 19, 1996, requesting an amendment to Certificate of Compliance No.
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9128 for the Model No. C-8 package.
On December 24, 1996, we requested additional information which we needed to complete our review. To date we have not received the information we requested.
This is to advise you that we plan to terminate our review of your application on June 20, 1997, unless we have received the information we requested by that date.
If our review is terminated, you may re-submit an application at a j
later date.
If you have any questions regarding this matter, we would be pleased to meet with you and your staff. Mr. Li Yang is the project manager for our review of your application. Mr. Yang may be contacted at (301) 415-8514.
Sincerely, is44 Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket No.:
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