ML19249A041
| ML19249A041 | |
| Person / Time | |
|---|---|
| Site: | 07106244 |
| Issue date: | 07/30/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19249A034 | List: |
| References | |
| NUDOCS 7908170613 | |
| Download: ML19249A041 (3) | |
Text
'
Form NRC418 U.S. NUCLE AR REGULATORY COMMISSION 92-73)
CERTIFICATE OF COMPLI ANCE is CFR 71 For Radioactive Materials Psc: ages 1.f a) Certificate Numcer 1.Ibn Revision No.
1.(c)
USA /63e identifJcaticn No.
Pagei No. 1.!s) Tot $ No. Pages Pack 1.(d) 44/B(
)
6244 3
- 2. PR E AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a.173 394,173.395, and 173.396 of the Ceoartment of Transpor+ation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CF R 146-149), as amended.
2 Ib)
The packaging and contents described in item 5 below, meets the safety standards wt forth in Suboart C of Title 10. Code of Federal Regulations. Part 71, Packaging of Radioactive Vaterials for Transport and Transportation of Radioactive Matenal Under Certam Conditions.'
2.(c)
This certificato does not relieve the consignor from compliance with any reouirement of the regulations of the U.S. Ceoartment of Transportation or other apod cante reaulatory agencies, including the government of any country througn or into which the oackage will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the pack: je design or application-3.(al Prepared by (Name and addrass):
3.lb)
Title and identification of report or spotication:
Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application P.O. Box 1866 dated April 22, 1974, as supplemented Bellevue, WA 98009 3.lci Cocket No.
71-6244 4 CCNDITIONS This certificate is conditional upon the fulfilling of the recuirements or Suboart O of 10 CF R 71, as applicable, and the conditions specified in item 5 below.
- 5. Descriotion of Packaging and Authorized Contents. Model Numoer, Fissile C: ass, Other Conditions. and References.
(a) Packaging (1) Model No.:
6244 (2) Description The package consists of a steel and lead snielded cask.
The cask is positioned witnin an overpack constructed of steel and noneycomb material.
The gross weight of the package is 46,000 pounds.
The mild steel cask is approximately 111-1/2 inches in length and 58 incnes in diameter. The walls, top, and bottom are of 2-inc!. thick steel plate.
Snielding is provided by 2 inches of lead witnin tne walls and 2-incn thick steel walls of the cask.
The cask lid is secured to tne cask body by twenty-four, 3/4-incn diameter bolts and is sealed by a compressible polyuretnane seal. Lifting devices are attached to the lid arid body of the cask.
\\C.
0 o m!
1 Jq'E,[7DC]/q
'}
IP
/doE 2uost70 n
Page 2 - Certificate No. 6244 - Revision No. 3 - Docket No. 71-6244 5.
(a) Packaging (Continued)
(2) Description (Continued)
The cask is positioned within an overpack approximately 139-1/2 inches in overall length and 89-3/8 inches in diameter. Aluminum honeyccmb material is conficed by an outer steel snell 3/8-inch thick and an inner steel shell of 1/4-inch thickness.
The overpack cover is of the same construction as the rest of the overpack and is secured to the walls by eight, 5/8-inch diameter bolts.
Lifting devices are welded to the outer shell of the overpack cover.
(3) Drawings The package is constructed in accordance with Nuclear Waste Systems Drawi.1g No. 6930-1, Rev. E (Sheet 1 of 2) and Chem-Muclear Systems Drawing No. 6930-1, Rev. D (Sheet 2 of 2).
(b) Contents (1) Type and form of material (i) Greater than Type A quantities of byproduct material as process solids, either dewatered, solid, or solidified, in secondary container (s) which meet the requirements for Type A (49 CFR 1173.389(j)) packaging, or (ii) 0.ater than Type A quantities of byproduct material as solid metal components in secondary containers, as required.
(2) Maximum quantity of material per package Not to exceed 10 thermal watts of byproduct material.
6.
The lifting lugs on the outside of the. overpack shall be covered during trans-pcrt to prevent tneir accidental use for the purpose of tie-down or lif ting.
7.
Shoring snall be placed between the secondary containers (or activated com-ponents) and tne cask cavity to minimize movement during normal conditions of transport.
8.
The lid polyurethane seal shall be replaced at least every six (6) montns and prior to final closure for each snigment of contents specified in Item 5.(b)(1)(ii) above. The secondary container (s) specified in Item 5.(b)(1)(i) abose need not meet the requirement for Type A packaging provided the lid poly-uretnane seal is replacea prior to final closure for eacn shipment.
~!, G,
\\
Page 3 - Certificate No. 6244 - Revision No. 3 - Occket No. 71-6244 9.
The pac'Kage autnorized by this certificate is hereby approved for use under the general license rovisions of 10 CFR 571.12(b).
10.
Expiration date: May M,1984
. REFERENCES Chem-Nuclear Systems, Inc. application dated April 22, 1974.
Supplements dated: June 19, 1978 and June 5, 1979 FOR THE U.S. NUCLEAR REGULATORY COMMISSION
& [& n
-df Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
JUL 3 01979 I
.