ML19261E176
| ML19261E176 | |
| Person / Time | |
|---|---|
| Site: | 07106244 |
| Issue date: | 05/25/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Clayton F, Reynolds L, Utley E ALABAMA POWER CO., CAROLINA POWER & LIGHT CO., CHEM-NUCLEAR SYSTEMS, INC. |
| Shared Package | |
| ML19261E174 | List: |
| References | |
| NUDOCS 7907050232 | |
| Download: ML19261E176 (2) | |
Text
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Form NRC413 U.S. NUCLE AR REGULATCRY OCMVISCICN (1271 CERTIFICATE OF CCMPLIANCE 10 CFR 71 For RMicactive Yaterials Pacxages 1.f a) Certificate Numcer 1.(b) Rawsacn No.
1.(c) Package Icentificat.on No.
1.(d ) Pages No. 1.(e) Total No. Pages 6244 2
USA /6244/B(
l 1
3
- 2. PREAMB LE 2.fa)
This certificate is issued to satisfy Sec ions 173.090a.173.394.173.09s, and 173.096 of the Cecartrrent of Transportanon an:ardous Vaterials Regulanons (49 CFR 170129 and 14 CFR 100) and Sections 146-19-1Ca and 146--19-1C0 cf tne Cesar r ec+
Transportation Cangerous Cargces Regulaons (46 CF R 146-149), as amended.
2.(b)
The pacxa;ing and contents described in item 5 below, meets the safety standarcs set forth in Succart C of Titie 10. Code of Feceral Regulations P2rt 71, " Packaging of Radioacttve Materials for Transocrt and Transportation of Radicactive Matenal Under Cartain Conditions.**
e.a...
2.(c)
This certificate does not relieve the cons.gnor from ccmcliance with any recuirement of the regulation? of the U.S. Cecartment of Transportation or other apoticaele regulatory agencies, inc!ucing the government of any country thrcu n or into wnich the pacxage will be transported.
- 3. This certific. rte is issued on the basis of a safetv analysis report af tne pacxage oesign or accficatiorr 3.la)
Prepared by C.'ame at:d addres):
3.;b)
Title and icentification of rescrt or application:
Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application P.O. Box 1866 dated April 22, 1974, as supplemented Bellevue, WA 98009 71~6244 3.tc)
Cocket No.
4 CCNOITICNS This ceruficate is conditional uoon te fulfillirs of the requirernerrts of Subpart O of 10 CFR 71, as a:cticatie, and the certitions spscified in item s below.
S. Cescription of Packaging and Authc..ized Contents, Model Numcer, Fissile C: ass, Cther Canditions, and References.
(a) Packaging (1) Model No.-
6244 (2) Description
.c. a The package consists of a steel and lead shielded cask.
The cask i
is positioned within an overpack constructed of steel and honeycomb material. The gross weight of the package is 46,000 pounds.
The mild steel cask is approximately 111-1/2 inches in length and E8 inches in diameter. The walls, top, and bottom are of 2-inch thick steel plate.
Shielding is provided my 2 inches of lead within the walls and 2-inch thick steel walls of the cask. The space between the secondary container and the lead is filled with an aluminum honeycomb material for the Type B packaging.
The cask lid is secured to the cask body by twenty-four, 3/4-inch diameter bolts and is sealed by a compressible polyurethane seal.
Lifting devices are attached to the lid and body of the cask.
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Page 2 - Certificate No. 6244 - Revision No. 2 - 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 honeycomb material is confined by an outer steel shell 3/8-inch thick and an inner steel shell of 1/4-inch thickness.
The over-pack cover is of the same construction as the rest of the over-pack and is secured to the wails by eight, 5/8-inch diameter bolts.
Lifting desices are welded to the outer shell of the overpack cover.
(3) Drawings The package is constructed in accordance with Nuclear Waste Systems Drawing No. 6930-1, Rev. D (Sheet 1 of 1) and Chem-Nuclear Systems Drawing No. N-69-12-438, Rev. B (Sheet 4 of 4).
(b) Contents (1) Type and form of material i)
Ion-exchange resin or solids containing byproduct material.
ii)
Solids and solidified waste meeting the requirements of low specific activity radioactive material in secondary container (s) which meet the requirements for Type A (49 CFR 5173.389(j))
pac kagi ng.
iii)
Activated metal <
ponents meeting the requirements for low specific activity radioactive material.
(2) Maximum quantity of material per package Not to exceed 10 thermal watts of byproduct material per resin c or.ta i ner.
6.
Tne lif ting luge, on the outside of the overpack shall be covered during transport to prevent their accidental use for the purpose of tie-down or lif ting.
7.
Sr.oring shall be placed between the secondary containers (or activated components) and the cask cavity to minimize movement during normal concitions of transport.
99b E7 2ht
Page 3 - Certificate No. 6244 - Revision No. 2 - Docket No. 71-6244 8.
The lid polyurethane seal shall be replaced at least every six (6) months and prior to final closure for each shipment of contents specified in Item 5.(b)(1)(iii) above. The secondary container (s) specified in Item S.(b)(1)(ii) above need not meet the requirement for Type A packaging provided the lid polyurethane seal is replaced prior to final closure for each shipment.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
10.
Expiration date: May 31, 1934 REFERENCES Chem-Nuclear Systems, Inc. application dated April 22, 1974.
Supplement dated: June 19, 1978 FOR THE U.S. NUCLEAR REGULATORY COMMISSION hl ft y
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and
._m Material Safety
'AY 2 51979 Date:
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