ML19309D067
| ML19309D067 | |
| Person / Time | |
|---|---|
| Site: | 07109020 |
| Issue date: | 03/28/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19309D064 | List: |
| References | |
| NUDOCS 8004100038 | |
| Download: ML19309D067 (4) | |
Text
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O' Form NRC 618 U.S. NUCLEAR REGULATORY COMMISSION U
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10 crR 71 CERTIFICATE OF COMPLIANCE For Radsoactive Materials Packages 1.la) Cer t to Number 1.(b) evision No.
1.f c P (k i en ifica i n No.
1.(d) Pages No. 1.fel Total No. Pages
- 2. PRE AMBLE 7.(a)
This certificate is issued to satisf y Sections 173.393a,17.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 10; and Sections 146-19-10a and 146-10-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 6-149), as amendef.
2.(b)
The packaging arms contents descritet in item 5 below, m ets the safety standards set forth in Subpart C of Title 10, Code of Faferal Regulations, Part 71, " Packaging of Raficactive 1/a'arials for Transport and Transportation of Radioactive Material Under Cettain Corutetions."
2.(c)
That certificate does 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 e safety analysis report of the package design or application-3.(a)
Prepared by (thme and address)-
3.(b)
Title and identification of report or application:
Nuclear Containers, Incorporated Nuclear Containers, Incorporated application P. O. Box 1080 dated June 28, 1974, as supplemented.
Elizabethton, TN 37643 3.(c)
Docket No.
- 4. CONDITIONS This certificate is cork 1stional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 6 belovv.
- b. Description of Packaging arut Authorized Contents, Model Numoer, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No.: SL-10-1 (2) Description A shielded packaging for liquids and solids. The outer container is constructed from two,16-gage 55-gallon steel drums welded end-to-end, and having overall dimensions of 69-inches by 22-1/2-inches diameter. The outer container closure is accomplished be a reinforced drum lid, bolted to a nut ring using eight,1/2-13 NC hex head bolts.
The containment vessel has a usable cavity 5.047-inch diameter by 53-3/8-inch long, constructed of 304L stainless steel.
Closure is accomplished by a 5-inch, 300-pound blind flange, provided with a 1/4-inch valve, sealed by a pipe cap (threads wrapped with teflon tape) and protected by a steel enclosure. A double Viton-A 0-ring arrangement seals the containment vessel.
Provisions are made to leak test the closure lid seal.
Shielding is provided by a 1/2-inch thick lead annulus within a 6-inch 00,1/8-inch inner sleeve and a 7-1/2-inch 00, 1/4-inch outer steel sleeve..The space between the outer container and the containment vessel is filled with WEP (water extended polyester) and vermiculite. The weight of the packaging and contents is 1,200 pounds.
8 004100% h l
Page 2 - Certificate ilo. 9020 - Revision No. 3 - Docket tio. 71-9020 5.
(a) Packaging (continued)
(3) Drawings The SL-10-1 packaging is as described, and constructed in accordance with Nuclear Contaiaers, Incorporated Drawing Nos. DED-182-B, Rev. 4 and DED-183-B, Rev. 4.
The double seal gasket is as shown in Drawing No. DED-187-A-Rev. 1.
As an alternate to this configuration a double 0-ring flange and 0-ring may be provided as shown in Drawing No. DED-169-B, Rev. 2.
(4) Product Containers (i) Polyethylene bottles shall meet the specificaticns for: Sli t-vent model per CAPE-1170-37; or Duo-Vent model per Nuclear Fuel Services, Inc., Specification U-1, Drawing No. 5B-U-740.
(ii) Stainless steel bottles shall meet the specifications given in General Electric Co. Drawing Nos. FR0-140 and FRO-140A.
(iii) Scaled metal cans, constructed of corrosion resistant materials.
(b) Contents (1) Type and form of material (i) Uranyl nitrate solutions contained within a product container specified in 5(a)(4)(1) or (ii), and having a concentration of uranium 235 not exceeding 350 grams per liter and an H/U-235 atomic ratio not less than 80, provided that the combined U-233 and plutonium content is not more than 1% of the U-235 content; or (ii) Uranyl nitrate solutions contained within a product container specified in 5(a)(4)(i) or (ii), and having a combined concentration of uranium 233 and uranium 235 not exceeding 250 grams per liter and an H to fissile material atomic ratio of not less than 80 provided (1) the U-233 content is not greater than 20% of the combined U-233 and U-235 content, and (2) the plutonium content is not more than 1% of the combined U-233 and U-235 content; or (iii) Plutonium nitrate solutions contained within a product container specified in 5(a)(4)(i) or (ii) having a concentration not exceeding 250 grams fissile plutonium per liter; or Uranyl sulfate solution (UO SO ) containing uranium enriched in the (iv) 2 4 235 isotope contained within a product container specified in 5(a)(4)(i);or (v) Dry compounds and mixtures'of fissile plutonium-uranium 235, contained within a product container specified in 5(a)(4)(i), (ii) or (iii).
O Page 3 - Certificate fio. 9020 - Revision fio. 3 - Docket flo. 71-9020 5.
(b) Contents (continued).
(2) Maximum quantity of material per package ilot to exceed twenty (20) curies plutonium per package, and (1) for the contents described in 5(b)(1)(1), (ii), and (iii):
Hot more than 10.5 liters of solution.
Maximum decay heat load not to exceed 35 watts.
(ii) For the contents described in 5(b)(1)(iv):
flot more than 10.5 liters of solution and 950 grams fissile material.
Maximum decay heat load not to exceed 30 watts.
(iii) For the contents described in 5(b)(1)(v):
tiot more than 4.5 kilograms of fissile material.
The hydrogen to fissile material atomic ratio, including all hydrogeneous material within the containment vessel shall not exceed 10.
Maximum decay heat load not to exceed 125 watts for solids packed in metal product containers, and 50 watts for solids packed in polyethylene containers.
(c) Fissile Class I
6.
For packaging with a polyethylene product container a flexible restraining device shall be placed between the cap assembly of the polyethylene bottle 6nd the closure flange of the pressure vessel to restrict the relative vibration of the polyethylene bottle with respect to the pressure vessel during transport.
7.
Appropriate steps shall be taken to assure that from the time of sealing to the time of delivery to the consignee, the pressure in the containment vessel does not exceed 40 psig.
8.
Prior to each shipment of more than Type A quantities of radioactive material, the double 0-ring seal must be shown to be leaktight at 100 psig by a method having a leak sensitivity of 10 3 atm-cm3/sec at standard temperature and pressure.
9.
A test shall be performed on each containment vessel and associated 1/4-inch SS valve (without its associated pipe cap) initially and once each year at 300 psig, demon-3 strating leaktightness by a method having a leak sensitivity. of 10 6 atm-cm /sec at standard temperature and pressure.
Page 4 - Certificate No. 9020 - Revision No. 3 - Docket No. 71-9020
- 10. The weight of WEP/WEP-vermiculite shielding shall be determined at fabrication by weighting the packaging before and after pouring. The weights must be documented and retained. The final WEP/WEP-vermiculite weight must be more than 500 pounds prior to placing the packaging in service.
- 11. The empty packaging shall be weighed at the annual inspection.
No packaging shall be placed in service which shows a loss of 25 pounds from the initial recorded weight.
12.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
13.
Expiration date: March 31, 1985.
l REFERENCES duclear Containers, Incorporated letter dated June 28, 1974.
Supplements dated: October 14 and 28, 1974; and January 3,1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch l
Division of Fuel Cycle and Material Safety 0
Date:
- = = -
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