ML20147B743
| ML20147B743 | |
| Person / Time | |
|---|---|
| Site: | 07105805 |
| Issue date: | 12/07/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20147B736 | List: |
| References | |
| NUDOCS 7812180024 | |
| Download: ML20147B743 (6) | |
Text
Form NBC418 U.S. NUCLE AR REGULATORY COMMISSION U 8 8
.10 CFR 71 CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.(a) Certincate Number 1.(b) Revision No. 1.(c) Package identification No. 1,(d) Pages No. 1.(e) Total No. Pages 5805 7 USA /5805/B( )F 1 6
- 2. PREAMBLE 2.(a) This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b) The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c) This certificate dees not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through 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 application-3.(a) Prepared by (Name and address): 3.(b) Title and identification of report or application:
Chem-Fuclear Systems, Inc. ATCOR, Incorporated application dated p.0. Box 1866 April 3,1974, as supplemented Bellevue, WA 98009
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3.(c) Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. De;cription of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No. : Vandenburgh Cask (2) Description The package is a steel-encased, lead-shielded cask with crushable impact limiters. The basic cask is a steel cylinder 133-3/4 inches long by 50-1/2 inches in diameter with maximum cavity dimensions of 36 inches in diameter by 116 inches long. Shielding is pro-vided by 6 inches of chemical lead in the sides and closure base plate and 5-1/4 inches in the closed end.
The outside steel encasement is made up of two,1/2-inch plates on the sides and three plates totaling 2-5/8 inches on the end. The containment vessel is a 1/4-inch thick cylinder with a 1/2-inch end plate. The shells are welded together with the lead shielding poured to fill the annular and end spaces.
The removable, flanged and recessed base plate weldment consists of 0.38-inch and 1-1/4-inch outside plates and a 1/2-inch inside plate.
The space between the plates is lead-filled.
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o Page 2 - Certificate No. 5805 - Revision No. 7 - Docket No. 71-5805
- 5. (a) Packaging (continued)
(2) Description (continued)
The base plate is secured to the cask body by means of twelve,1-1/2-inch high strength bolts and nuts and sealed with two silicone gaskets.
The cavity is penetrated by a vent line at the closed end and a drain line through the base plate. The vent line is sealed by a gasketed and shielded plug. The drain line is sealed with a 25 psig vent valve.
Cask appendages include two, 8-inch lifting trunnions and two, 4-inch removable tilting trunnions of the cask side.
Removable impact limiters are provided at the cask ends and at the two, 8-inch trunnions. The former consist of a series of 6-inch diameter closed and tubes. Each impact
, limiter has tubes approximately 6 inches long around the i end periphery. The closure end impact limiter has 12 tubes, I six about 6 inches long and six about two inches long, I around the sides. The closed end impact limiter has six tubes about 6 inches long around the sides. A gusseted tube acts as the trunnion impact limiter.
The cask is secured horizontally to a skid which is mounted to the transport vehicle for shipment. A sunshade is provided.
The gross weight of the package, excluding the skid and sunshade is approximately 70,000 pounds. The skid weighs about 4,200 pounds.
(3) Drawings The Vandenburgh Cask is described by BMI Drawing No.
MOD 100, Rev. E; and ATCOR Drawings Nos. : MOD 139-1, Rev. D; MOD 140, Rev. A; 0990-D-1, Rev. F; OS99-D-02, Rev. G; 0999-D-03, Rev. G; 0999-D-04, Rev. B; 0999-D-07, Rev. F; 0818-D-01, Rev. A; 1000-D-0024-0, Rev. 0; and 0648-D-0001.
Page 3 - Certificate No. 5805 - Revision No. 7 - Docket No. 71-5805 .
- 5. (b) Contents (1) Type and form of material (i) Irradiated stainless steel shroud cans, or ,
miscellaneous non-fissile or fissile exempt irradiated components packaged in secondary containers.
(ii) Irradiated BWR uranium oxide fuel assemblies.
The minimum cooling time of each assembly shall
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be 365 days. Prior to irradiation, the fuel assemblies shall have the following diinensions and specifications:
Fuel form Clad UO2 pellets Cladding material Stainless Steel -',.
Maximum U content, kg 121.1
- Maximum U-235 enrich- 3.94 ment, w/o -
Maximum bundle cross section, sq. in. 5.63 ' <>
Fuel pin array 10x10 Fuel diameter, in. 0.351
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Maximum active f uel \
length, in. 83.3 (2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i):
47,140 curies total, with a package internal decay heat lead not to exceed 800 watts. ,
E' s
Page 4 - Certificate No. 5805 - Revision No. 7 - Docket No. 71-5805
- 5. (b) Contents (continued)
(2) Maximum quantity of material per package (continued)
(ii) For the contents described in 5(b)(1)(ii):
Maximum package decay heat shall not exceed 3,500 watts. In any given foot of the fuel assembly, the average linear heat generation rate (averaged over all the rods within that foot of the assembly) shall not exceed 9.1 kw/ft per rod during irradia-tion within the reactor core.
Eight (8) BWR fuel assemblies with a maximum burnup of each assembly not to exceed 12,000 MWD /MTU and with a contra 11y located poison rod as shown in ATCOR Drawing No. 0999-D-01, Rev. F or Seven (7) BWR fuel assemblies with a maximum burnup of each assembly not to exceed 14,000 MWD /MTV and with a centrally located poison rod as shown in ATCOR Drawing No. 0999-D-01, Rev. F, or t
Six (6) BWR fuel assemblies with a maximum burnup of each assembly not to exceed 16,000 MWD /MTV and with a centrally located poison rod as shown in ATCOR Drawing No. 0999-D-01, Rev. F.
(c) Fissile Class III For the contents described in 5(b)(1)(ii) and limited in 5(b)(2)(ii):
Maximum number of packages per shipment One (1) package
- 6. Forthecontentsdescribedin5(b)(1)(i),andlimitedin5(b)(2)(i):
(a) Both the inner cask cavity and the secondary container shall be free of water when the package is delivered to a carrier for transport.
(b) Shoring shall be placed between contents, secondary container and cask cavity to minimize secondary impacts due to accident sequence. .
(c) The maximum gross weight of the contents, secondary container and shoring is limited to 9,220 pounds.
s Page 5 - Certificate No. 5805 - Revision No. 7 - Docket No. 71-5805
- 7. For the contents described in 5(b)(1)(ii), and limited in 5(b)(2)(ii):
(a) The containment cavity shall be equipped with a vent valve, either Teledyne Republic Manufacturing Model No. 684-2-3/4-SS with a stainless steel seat or Circle Seal Products Model No. 0520T-6M-25. The valve setting is to be 25 psig +10% '
-0 (b) For less than 8 fuel assemblies, empty fuel canisters shall be placed in the fuel basket.
(c) The poison tube and canister shall be maintained in the central position of the fuel basket.
(d) The poison rod annulus shall be filled with a homogeneous mixture of BuC and sand. The mixture shall contain a minimum of 80% BqC by volume.
(e) Periodic tests, inspections and maintenance of the cask shall be performed in accordance with the plan outlined in Section III-2 (Vandenburgh Cask Inspection and Preventive Maintenance) of the application, Revision C, April 23, 1976.
(f) Cask loading and unloading shall be performed in accordance with the procedures outlined in Section III-1 (Vandenburgh Cask Handling Procedures - LACBWR Fuel) of the application, Revision C, April 23, 1976.
(g) The maximum gross weight of the contents is limited to 10,800 pounds.
- 8. The containment vessel (base plate and vent plug) shall be sealed with silicon 0-rings.
- 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: December 31, 1980.
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Page 6 - Certificate No. 5805 - Revision No. 7 - Docket No. 71-5805 REFERENCES ATCOR, Incorporated's application dated April 3,1974.
Supplements dated: July 23,1974; August 15, October 9, and December 2, 1975; and April 29 and August 30, 1976. l FOR THE U.S. NUCLEAR REGULATORY COMMISSION C arles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety Date: DEC 0 71978 l
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