ML20211G225
| ML20211G225 | |
| Person / Time | |
|---|---|
| Site: | 07109071 |
| Issue date: | 10/15/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20211G221 | List: |
| References | |
| NUDOCS 8611030249 | |
| Download: ML20211G225 (4) | |
Text
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i 7.,m, ---------- - - - - - = - - - - - - a mmmmum mm mmmmm a mm msarm%m amA l NRC FonM s1s U.S. NUCLEA~1 [E2ULATLRY CCMMISS12N M 1 +=> CERTIFICATE CF CUMPLIANCE ,E 1 'o c'3 " FOR RADIOACTIVE MATERIALS PACKAGES l E
1 e CERTIFICATE NUMBER D REVISION NUMEF.R C PACKAGE iOENTiFICATION NUMBER d PAGE NUMBER e TOTAt NUMBER PAGES j 9071 4 USA /9071/B( ) 1 3 E 1;
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2 PREAMetE a This certificate is essued to certif y that the Dackaging and contents descnbed in item 5 below. meets the apphcable safety standards set forth in Titte 10. Code l?
M gl of Federal Regulations. Part 11.
- Packaging and Transportation of Radioactiv3 Material." g
$ 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 k
$j aDphCable regulatory agencies.' including the government of any country through or into which the paChage will be transported k
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(: 3 THIS CERitFIC, g i a >Ssuto To NATE IS, ISSUED eo ..; ON THE BASIS OF A SAFETY ANAtY$iS o TiTtE REPORT OF THE PACK ANO ioENTiFiCATiO~ OFAGE REPORT DESIGN OR APPLICATION Oa APPtiCATiON j
q iE q, ANEFCO, Incorporated ANEFC0 application received June 14, 1976, lE ti P.O. Box 433 with report, " Safety Analysis Report Cask i E
di Ridgefield, CT 06877 AP-101" iE i 71-9071 8 1 e coCKET NUMBER 4 CONOlfiONS k This certificate is conditional upon fulfilbng the requirements of 10 CFR Part 71. as apphcable. arid the conditions specified below 1 R 1 s E 1
/ lIF 1 (a) Packagina . il Mj l 4j (1) Model No.: AP-101
- i 4 E f E j (2) Description y
- E t A steel encased, lead shielded cask for non-fissile radioactive E material. The overall dimensions of the cask are 40 inches in E 4l j
i di diameter by 193 inches long. The cask consists of two concentric stainless steel cylindrical shells. The inner shell is 5/8-inch Ig j'gi thick by 28-inch ID; the outer stainless steel shell is 1-1/2-inch lg t thick by 39-1/4-inch OD and a 3-1/2-inch poured lead shield ;E f fills the space between. The outer shell is surrounded by a 1 E
il 0.140-inch thick stainless steel thermal shield separated by a *
,p 0.125-inch thick stainless steel spacer wire. The cavity is 28 4
inches in diameter by 167 inches long. The base is a welded :l
'p 4 stainless steel construction with 3 inches of poured lead. The y l q flanged lid is of stainless steel and lead. Closure is provided b l t by twenty, 1-1/2-inch diameter bolts and a GASK-0-SEAL, closure i k
seal. There are two penetrations into the containment vessel i j
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f for drain lines which are plugged and gasketed with a neoprene g seal. The cask is equipped with removable, canned balsa impact '
limiters at each end. The overall dimensions of the cask with !g l('l 3 impact limiters in place are 84 inches in dianeter by 236 inches long. The cask has four lifting trunnions, two redundant pairs tE g
for lifting. Three of the trunnions are used for tie-down of 4lE j
~1 I the cask for shipment. The package crrns weigtt is approximately j 62,000 pounds. g I ,k 1 1 1 1 1 lF l
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,h CONOITIONS (continued) 'l 1
'l M Page 2 - Certificate No. 9071 - Revision No. 4 - Docket No. 71-9071 l 5
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lli l 5. (a) Packaging (Continued) l M (3) Drawings l N I N The packaging is fabricated in accordance with ANEFCO, Incorporated I 3 Drawing Nos. SC-101, Rev. A; SC-102; SC-103, Rev. A; SC-104, Rev. B; I l SC-107, Rev. A; SC-108; SC-110, Rev. A; and SC-111.
l l (b) Contents l 1 I i (1) Type and form of material !
I i l Greater than Type A quantity of byproduct material in the form of dry, N y solid, metallic waste material and activated reactor components. l 1 i i (2) Maximum quantity of material per package ;
i If I Weight of contents not to exceed 10,000 pounds. Internal decay heat l l of contents not to exceed 300 watts. '
N l 6. The package must be shipped dry. In preparation for shipment, the cask l 1 cavity must be drained of all excess water. A vacuum pump must be used to y I reduce the cavity pressure below the vapor pressure corresponding to the W l measured temperature of the drained water. The cavity pressure must be p l held below the vapor pressure determined for at least 90 minutes. Dry l g loaded package need not be vacuum dried provided the " empty" cask cavity j l; and drain lines are verified not to contain liquid prior to each loading. t I
I 7. Except for close fitting contents, appropriate shoring must be used in b I the cask cavity to limit movement of the contents durino accident M
l conditions of transport.
l l 8. In addition to the requirements of Subpart G of 10 CFR Part 71, each l l package must meet all of the acceptance and periodic tests specified in p I Sections 5.2 and 5.3 of the Application. N i N
- 9. The package authorized by this certificate is hereby approved for use under the N l!
i general license provisions of 10 CFR Q71.12. j l 5 I ,li I jN I ;N I
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conoITsons tcontinued) N I N
! Page 3 - Certificate No. 9071 - Revision ho. 4 - Docket ho. 71-9071 l N
N I N I N l 10. Expiration date: October 31, 1991.
l l REFERENCES l
l .
I I ANEFCO, Incorporated Safety Analysis Report Cask AP-101, received June 14, 1976. N I I l Supplements dated: July 21, August 6, and October 21, 1976; and April 2, 1986.
l l FOR THE U.S. NUCLEAR REGULATORY CCMMISSION l
I Charles TkCL 4
.MacDonal,d, Chief' N
l Transportation Certification Branch Division of Fuel Cycle and l l g y Material Safety, hMSS y i N
- j Date: OCT 1h ;;;; I I
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Transportation Certification Branch Approval Record Model No. AP-101 Packaging Docket No. 71-9071 By application dated September 12, 1986, ANEFCO, Inc. requested renewal of Certificate of Compliance No. 9071. No changes have been requested or made to the package since approval of the latest supplement dated April 2,1986.
The applicant and~ users of this package should note the limitations on the fabrication of additional packagings and use of existing packagings as stated in 10 CFR 671.13.
Based on the statements of the original application, as supplemented, and the Safety Evaluation Report dated November 30, 1976, the staff concludes that the requirement for renewal of the certificate of compliance has been satisfied.
ar es E. MacDonald, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:
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