ML19249F049
| ML19249F049 | |
| Person / Time | |
|---|---|
| Site: | 07106375 |
| Issue date: | 09/10/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19249F048 | List: |
| References | |
| NUDOCS 7910030876 | |
| Download: ML19249F049 (3) | |
Text
O Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION OV U
CERTIFICATE OF COMPLIANCE O
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10 CFR D
For Radioactive Materials Packages v
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23 1.ta) Cartificate Nurnber 1.(b) Revision No.
1.f c) Pacmaoe Id ifi ion No.
1.le)Iotal No. Pages 6375 6
USA /6315/B 1 (d)1Pages No.
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a.173.394.173.395, and 173.396 of the Department of Transoortation Hazarcous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10e and 146-19-100 of the Decartment of Transoortation Dangerous Cargoes Regulations (46 CFR 146--149), as amended, i
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subcart C of Titte 10. Code of Federal Regulations, Port 71, Packagi.1g of,Radioective Materials for Transport and Transportation of Radioactive Material Under Certain Conditsons."
2.(c)
This certificate doeJ not relieve the consignor from comodiance with any reouirement of the regulations of the U.S. Departrnent of Transportatiori or other applicable regulatory agencmes, including the government af any country ;hrough or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or applicatior>-
3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or aprJication:
Chem-Nuclear Systems, Inc.
'hiladelphia Electric Company application P.O. Box 1866 dated March 6,1970, as supplemented.
Bellevue, WA 98009 3.tc)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71, as apodicable, and the conditions specified in item 5 below.
- 5. Description of Packagsng and Authorized Contents, Model Nurrber, Fissaie Class, Other Conditions, and
References:
(a) Packaging (1) Model No.: PB-1 (2) Description A lead shield shipping cask, encased in mild steel on the outside and stainless steel on the inside.
The cask is cylindrical in shape,173-1/8 inches long and 42-1/2 inches in diameter for all of its length except for a distance of 31-5/8 inches at each end which is 40-1/2 inches in diameter. The principal shielding consists of 6-1/4 inches of lead.
A nine-inch thick impact limiter is attached to both ends of the cask with four of.the twelve,1.25-inch ccver bolts (each end of.
the cask has a cover). The impact limiters are constructed by welding a bundle of 2-1/2-inch,13-gage tubing between 1/4-inch SS plates and enclosing the bundle with a 1/16-inch SS shell.
The cask cavity is 26 inches in diameter by 159 inches in length.
The net weight of the cask is 57,050 pounds. The gross weight, containing blanket fuel assemblies, is 67,050 pouncs.
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7910030 i
Page 2 - Certificate No. 6375 - Revision No. 6 - Docket No. 71-6375 5.
(a) Packaging (Cont'd)
(3) Drawings The Model No. PB-1 shipping cask is constructed in accordance with the following Battelle Memorial Institute Drawings Nos.:
9123-6PB-0001, Rev. B Whitehead & Kales PB-1 Shipping Container 00-000-552, Rev. 0 Fuel Basket Container Assembly PROC (b) Contents (1) Type and fonn of material (i)
Irradiated Peach Bottcm Unit 1, whole or partial fuel elements, circular in cross section, 3-1/2 inches in diameter and up to 144 inches long, sealed in canisters in a helium atmosphere.
In case that the canisters are found not to be lea 4 tight, salvage canisters shall be provided to ensure containment. The maximum U-235 loading of each fuel elament is 300 gm and the minimum atom ratio of thoriuni-232 to uranium-235 is 5.37, except that one such elemept per package may have a loading of 415 grams U-235 and minimum thorium-?32 to uranium-235 atom ratio of 4.0.
The maximum-enrichment of U-235 shall be 93.5 weight percent.
(ii)
Irradiated blanket fuel subassemblies from the Enrico Fermi Atomic Reactor. Each fuel rod contains an alloy of 97 w/o U-238 (0.3 w/o U-235)-3 w/o Mo.
(iii) Solid non-fissile i' radiated hardware and neutton source components.
(2) Maximum quantity of material per package (i)
Item 5(b)(1)(i) above, eighteen fuel elements, each weighing up to 90 pounds.
(ii)
Item 5(b)(1)(ii) above, 47 radial blanket subassemblies or 227 upper and lower axial blanket subassemblies sealed in Fuel Basket Container shown in,Battelle Memorial Institute Drawing No. 00-000-552,' Rev. O, and containing up to 9,000 curies of mixed fission products.
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Page 3 - Certificate No.,6375 - Revision No. 6 - Docket No. 71-6375 5.
(b) Contents (continued)
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(iii)
Item 5 (b)(1)(iii) above, maximum weight of contents, including any container, shall be 10,000 pounds. As needed, appropriate component spacers shall be used in the cask cavity to limit movement of contents during shipment..
(3) Maximum decay heat per package 3,715 watts (c) Fissile Class I and II.
(2)
Item $(b)(1)(1) above, II Minimum transport index to be shown on label 10 (2)
Item 5(b)(1)(ii) above, I
6.
If the cask contents are shipped wet, the licensee shall confirm that the pressure relief valve is operable to avoid damage of any cocponent of the package due to excessive pressure under normal or uccident conditions.
Also, when needed, sufficient antifreeze shall be used to prevent freezing.
Blanket full assemblies shall be shipped dry.
7.
Pipe plugs may be used as seals for the pressure gage, vent and drain lines.
8.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
9.
Expiration date: December 31, '979.
REFERENCES Philadelphia Electric Company application dated March 6,1970.
Supplements dated: May 19, June 10, and July 22, 1970; September 25, 1970; August 14 and December 17, 1974; and August 14, 1975.
Chem-Nuclear System, Inc. letter dated September 16, 1977.
FOR THE U.S. NUCLEAR REGULATORY CCMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety 0M Date:
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