ML20141E877
| ML20141E877 | |
| Person / Time | |
|---|---|
| Site: | 07109049 |
| Issue date: | 12/24/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20141E867 | List: |
| References | |
| NUDOCS 8601080405 | |
| Download: ML20141E877 (4) | |
Text
p -mmmmm:mammw.am mmmmmmm.acAwwAac.muerawrs'rerswsersa I ^ NRC FORM sts U.S. NUCLEAR REGULATORY COMMISSION '
i = CERTIFICATE OF COMPLIANCE l io Cm T' FOR RADIOACTIVE MATERIALC PACKAGES 1.a CERTitlCATE NUMBER D REVISION NUMBER C. PACKAGE iOENTIF4 CATION NUMBER d PAGE NUMBER e. TOTAL NUMBER PAGES g 9049 5 USA /9049/B( ) 1 2 #
$ 2. PREAMBLE l a. This certificate is issued to certify that the packaging and contents desenbed in item 5 below, meets the apphcabh safety standards set forth m Title 10. Code of Federal Regulations. Part 71. Packaging and Transportation of Radioactive Material"
- b. This certificate does not reheve the consignor from Comphance with any requirement of the regulations of the U.S. Department of Transportation or other appleCable regulatory agencies, including the government of ar'y country through or into which the package will be transported.
E I E
RT OF 1HE P AC ES G O CA N a Ty,gTi,r;C,ATysjS,U,EgN
, THE BASIS OF A SAFETY ANALYSIS RE Advanced Medical Systens, Inc. Advanced fledical Systems, Inc. apolication y 5463 Horning Road dated June 27, 1985, as supplemented. jh Pittsburgh, PA 15436
- c. DOCxET NUusER
'71-9049 y 4 CONDITIONS This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 7t. as apphcable. and the conditions specified below s >
(a) Packaging l (1) fiodel No.: -GE-500 .
g W (2) Description x N H _
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g Steel encased lead shielded Tshipping cask. A double-walled steel g cylinder protective jacket encloses the cask during trarisport. It is p g bolted to a steel pallet. -The cask is iclosed by a lead-filled flanged E N plug fitted with a silicone rubber gasket and bolted closure. The N N cavity drain 'line 'is ' closed by~either a~ stainless steel or fusible N plug (nelting poi _nt 500 F). The physical ~ description is as follows: f l
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g Caskfieight,in' 29.0 g 4 Cask diameter,'in ~ -
28.0, n 4 ',Cavi ty height, _in 7.0 R i
l Cavity diameter, in' , 7.0
'I Lead shielding, in 10.0 l Protective jacket height, in 38.9 ~
h) g Protective .iacket width, in ~
40.75 p g Packaging weight, lb 8,100 N I
l E I (3) Drawings N I >
l The packaging is constructed in accnrdance with the following General f g Electric Company Drawing Nos.: y i N I 212E246, Rev. 7 106D3855, Rev. 4 1 10603870, Rev. 11 12904690, Rev. 0 l i I 706E790, Rev. 4 I i l I I I I I I l I I I I I '
8601080405 851224 '
l kDR ADOCK 07109049 i
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' i l CONDITIONS (continued) !
N.
E Ej Page 2 - Certificate No. 9049 - P,evision No. 5 - Docket No. 71-9049 b
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+l 5. (b) Contents [g (1) Type and form of material (i) Byproduct material meeting the requirements o' special form k j
- 1 radioactive material . f,I 1 (2) flaximun ouantity of material per package j!]
l3 iQ;
] Radioactive decay heat not to exceed 780 watts. $E a
3 !r g 6. Shoring ru:t be provided to mininize movem'ent' of contents during accident 1 conditions of transport. . ~~
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.] ;E; 1 7. Package contents must be delivered to a carrier dry. Jj lE ' -
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[gj 8. Prior to each shipnent the silicone rubber lid gasket nust be inspected. This gasket nust be replaced if inspection shows any defects or every 12 months,
- El a 's I whichever occurs first. _ Cavity drain line must be- sealed with appropriate sealant applied to threads _ of. pipe plug.
f) lA 1
- 9. Fabrication of 'ad'ditional packagings is not authorized. '
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- g 10. The package authorized by this ' certificate"is hereby approved for use under the gh g; general license pro.isions of 10.CFR Q71.12'. ~
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.E' 5 i 11. Expiration date: December 31, 1985. ;E:
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( ' REFERENCE'S --
t 1 Advanced tiedical Systens, Inc. aoplidation dated June 27, 1985.
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- ] lr:
T Supplement dated: October 29,"1985. -
E 1 E:
f'd h s. FOR "THE U.S. NUCLEAR REGULATORY C0fif11SSION [
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a ji Charles E. fiacDonald, Chief y Transport'ation Certification Branch f:
g' gl Division of Fuel Cycle and g-t Material Safety, ft1SS E
- E I DEC 2 4155 Date: E 1 E 1 E 1 E 4
E! E t E T Ei i
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e AR4%fC 8 o UNITED STATES
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NUCLEAR REGULATORY COMMISSION ll; f WASHINGTON, D. C. 20555 e
Transportation Certification Branch Approval Record flodel No. GE-500 Package Docket No. 71-9094 By application dated June 27, 1985, as supplemented, Advanced ifedical Systems, Inc. reauested renewal of Certificate of Compliance flo. 9049
. for the tiodel No. GE-500 package. In support of the renewal reouest,
! Advanced ifedical Systens, Inc. submitted a consolidated safety analysis repo rt . Advanced ftedical Systems, Inc. initiated the renewal request since General Electric Company had indicated that they would not request i renewal of the certificate.
A review of the consolidated application confirmed that all pertinent supplement information 'and the application dated February 21, 1930, had i been incorporated into the consolidated safety analysis report which has been expanded to inclv?e information pertaining to Operating Procedures and ifaintenance Progran. flowever, the~ following discrepancies are noted:
o The packaging weight is reported to be 8,100 pounds instead of the 7,800 pounds as previously stated 'in the certificate of compliance.
The applicant has used the 8,100 pounds in analyzing oackage perfornance with satisfactory results. The applicant further states that the weight difference occurs in the weight of the base and protective jacket and not in the cask.
o Section ? 3, tiedical Properties of fiaterials, needs clarification.
The values given should be the miniaun values as reported by a recognized body such as ASTit, ASf'E, or AISI.
o Section 2.4.4, Tie Down Devices. The statenent comparing the strength of the components involved is not correct based on the strength values reported in Section 2.3.
o Section 2.6.9, Compression. The statement referring to the analysis in Section 2.5.1 as satisfying the compression loading is not correct. Section '2.5.1 analyzes the packing as a simple , bean supported at its ends.
The above listed discrepancies are not considered critical to the renewal of the certificate of compliance since the criqinal approval was based on a safety analysis report supported by prototype testing (f'odel No. GE-100, Certificate of Compliance No. 5926) which demonstrated compliance with performance requirements of 10 CFR Part 71.
. o The applicant stated that additional units of the . packaging will not be fabricated and, therefore, the application does not contain a section on Acceptance Testing. Accordingly, the certificate of compliance has been conditioned to preclude the fabrication of additional packagings. It is also noted that the application addresses only one type and form of contents, " Byproduct material meeting the requirenents of special form, maximun decay heat load of 780 watts." Therefore, a second - type and j form presently listed in the certificate has been deleted. !
Based on the consolidated application, as supplemented, and the original Safety Evaluation Report dated itay 1,1969, the staff concludes that the requirement for renewal of the certificate of compliance has been satisfied.
6/'wA. l6 Charles E. tiacDonald, Chief
' Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS i
Date:
I I
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