ML19212A444
| ML19212A444 | |
| Person / Time | |
|---|---|
| Site: | 07105797 |
| Issue date: | 09/20/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19209C143 | List: |
| References | |
| NUDOCS 7910120045 | |
| Download: ML19212A444 (7) | |
Text
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Form NRC-018 U.S. NUCLEAR REGULATORY COMMISSION U
CERTIFICATE OF COMPLI ANCE 10 C R 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 5797 0
USA /5797/AF 1
3
- 2. PRE AMBLE 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 ' 'P 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 cf the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and centents 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 does not relieve the consignor from corr.pliance 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:
Department of Energy Safety Analysis Report for Packaging: The ORNL P.O. Box E HFIR Unirradiated Fuel Element Snipping Containers, Oak Ridge, TN 37830 ORNL/ENG/TM-9, November 1977, as amended.
3.(c)
Docket No.
71-5797 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requ. aments of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents. Model Number, Fissile Class. Other Conditions, and
References:
(a) Packaging (1) Models Nos.:
Inner HFIR Unirradiated Fuel Element Shipping Container, and Outer HFIR Unirradiated Fuel Element Shipning Container (2) Description Packaging for unirradiated fissile radioactive material as fuel elements for the High Flux Isotope Reactor (HFIR). The container is a right circular cylinder with an ll-gauge carbon steel shell.
Closure is provided by 16, 3/8-inch diameter steel bolts which attach the lid to the cylindrical steel shell.
The steel shell is filled with laminated Douglas fir plywood with a minimum thickness of 6 inches. A central cavity is formed in the plywood, and lined with a 1-inch thickness of polyetheylene foam.
The packaging for the inner HFIR fuel element has overall dimensions of 25-inch 0.D. by 45-inch high, a 10-7/8-inch diameter by 30-1/4-inch deep cavity, and a 660 pound gross weight.
The packaging for the outer HFIR fuel element has overall dimensions of 31.5-inch 0.D. x 45.75-inch high, a 17-3/8-inch diarater by 31-1/8-inch deep cavity, and a 1050 pound gross weight.
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Page 2 - Certificate of Compliance No. 5797 - Revision No. O, Docket No. 71-5797 5.
(a) Packaging (Cont'd)
(3) Drawings (i) The packaging for the inner HFIR fuel is constructed in accordance with Dak Ridge National Laboratory Drawing No. M-20978-EL-003, Rev 6.
(ii) The packaging for the outer HFIR fuel is constructed in accordance with Dak Ridge National Laboratory Drawing No. M-20978-EL-002, Rev. 6.
(b) Contents (1) Type and form of material Uranium as U 0 -Al cermet, enriched up to 93% in the U-235 isotope, 3 3 and clad in aluminum,10-mils thick, and:
(i) For the packaging described in 5(a)(3)(i) the contents are described in Oak Ridge National Laboratory Drawing No. D-42118, Rev. J.
(ii) For the packaging described in 5(a)(3)(ii) the contents are described in Oak Ridge National Laboratory Drawing No. D-42126, Rev. G.
(2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i) not more than 2.6 kg of U-235.
(ii) For the contents described in 5(b)(1)(ii) not more than 6.8 kg of U-235.
(c) Fistile Class I
6.
Prior to delivery to a carrier for transport, the shipper shall ensure that at no point along the proposed shipping route that the ambient temperature will be less than 32 F; or, the shipment shall be made in a heated vehicle such that the package temperature shall not be less than 32 F along the shipping route.
7.
The pcckage authorized by this certificate is hereby approved for use under general license provisions of 10 CFR 571.12(b).
8.
Expiration date:
September 30, 1984.
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Page 3 - Certificate of Compliance No. 5797 - Revision No. O, Docket No. 71-5797 REFERENCES Oak Ridge National Laboratory Report No. ORNL/ENG/TM-9, Nov.1977.
Supplements dated: July 31,1978; and September 17, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Da te:
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U.S. Nuclear Regulatory Commission Safety Evaluation by the Transportation Certification Branch of the Models Nos. Inner HFIR Unirradiated Fuel Element Shipping Container and Outer HFIR Unitradiated Fuel Element Shipping Container, Packages SEP 2 01979 Enclosure to Ltr Dated Summary By application dated February 14, 1978, as supplemented July 31, 1978 and September 17, 1979, the United States Department of Energy requested review of the Models Nos. Inner HFIR Unirradiated Fuel Element Shipping Container, and Outer HFIR Unirradiated Fuel Element Shipping Container, packages to be used for the shipment of unirradiated fissile radioactive r.aterial.
Based on the statements and representations contained in the application, we have concluded that the Models Nos. Inner HFIR Unirradiated Fuel Element Shipping Container, and Outer HFIR Unirradiated Fuel Element Shipping Container, packcging and contents, as described, meet the requirements of 10 CFR Part 71, subject to the conditions specified below.
Reference Safety Analysis Report for Packaging:
The ORNL HFIR Unirradiated Fuel Element Shipping Container, Oak Ridge National Laboratory Report No. ORNL/ENG/TM-9, dated November 1977.
U.S. Department of Energy, Oak Ridge Operations Office Report, OR0 Review of Report ORNL/ENG/TM-9 Safety Analysis Report for Packaging The ORNL HFIR Unir-radiated Fuel Element Shipping Container, Revision dated June 26, 1978 and letter dated September 17, 1979.
Packaging Description The Inner HFIR Unirradiated Fuel Element Shipping Container and the Outer HFIR Unirradiated Fuel Element Shipping Container are the packaging for shipment of unirradiated fissile radioactive material in the form of fuel elements for the High Flux Isotope Reactor (HFIR).
The two models are nearly identical in construction, differing only slightly in physical dimensions and weight, the outer model being slightly larger and heavier than the inner model.
Each model consists of a right circular cylindrical shell and end plate, constructed of ll gauge carbon st(el.
The inner model has a 25-inch outside diameter and is 45 inches in height, with cavity dimensions of 10.875 inches in diameter by 30.25 inches in length.
The outer model is 31.5 inches in diameter by 45.75 inches high and has a cavity 17.375 inches in diameter by 31.125 inches in length.
The bottom plate is welded to the steel shell.
The 11 gauge steel 1H3 077
2 lid is attached by sixteen, 3/8-inch steel bolts to an angle flange welded around t i top of the outside of the shell.
A 0.125-inch neoprene gasket is used to exclude rainwater, but does not function as a pressure seal.
A 1/16-inch diameter vent hole is provided to assure that the cask is not pressure sealed.
Six inches of laminated Douglas fir plywood, constructed from stacked plywood disks, lines the inside of the shell and acts as thermal insulation.
The inner surface of the plywcod is lined with one inch of polyethylene foam, which serves as additional insulation and as a shock absorber to protect the contents from physical damage.
The inner model weighs 660 pounds and the outer model weighs 1050 pounds, when fully loaded.
Contents The packages are designed to carry the inner and outer fuel elements of an unirradiated HFIR (High Flux Isotope Reactor) fuel assembly.
The outer fuel element contains 369, fifty-mil-thick involute geometry fuel plates with fifty mil thick channels between plates.
The inner fuel element contains 171 similar fuel plates.
The uranium in both elements is in the form of U 0 -cermet, 38 enriched up to 93% in the U-235 isotope and clad by a minimum 5f ten mils of aluminum.
The aluminum cladding contains the radioactive material, and the steel shell and lid contain the element.
The heat output of either unirradiated HFIR fuel elements is negligible.
The maximum quantity of radioactive material per package is not to exceed Type A quantities.
A maximum of 2.6 Kg of U-235 may be shipped as Fissile Class I in the Inner HFIR Unirradiated Fuel Element Shipping Container.
A maximum of 6.8 Kg of U-235 may be shipped as Fissile Class I in the Outer HFIR Unirradiated Fuel Element Shipping Container.
Structural Evaluation The applicant has demonstrated that the packages satisfy the structural require-ments of 10 CFR Part 71 for both the normal conditions of transport and hypo-thetical accident conditions, except in the area of brittle fracture at low temperature.
The applicant's evaluation of the packages' ability to meet these requirements is based primarily on test results or extrapolation of test results from packages similar to the HFIR unirradiated fuel element shipping containers.
However these tests do not address the problem of brittle fracture of the outer steel shell of the packages at low temperatures.
Therefore, the applicant has limited shipments to ambient conditions above 32 F; or, in a transport vehicle with package temperature maintained above 32 F.
Based on the test results, analysis, and condition (temperature) the applicant has concluded that the packages meet the structural requirements of 10 CFR Part 71.
The staff has reviewed the applicant's safety analysis and concurs with that conclusion.
Thermal Evaluation The applicant has demonstrated by thermal analysis that the packaging satisfits the thermal requirements of 10 CFR Part 71 for both the normal conditions of transport and the hypothetical accident conditions.
1143 078
3 The applicant has determined the maximum external surface temperature of the package to be 169 F, for the conditions of normal transport (130 F ambient temperature with full solar radiation).
This steady state temperature was determined by equating the heat removed by natural convection and radiation to the net solar flux absorbed by the cask.
The surface temperature for this environment was the maximum packaging temperature, assuming zero internal heat generation for the unirradiated contents.
The applicant used the HEATING-3 computer code to evaluate a finite difference thermal model of the casks subjected to the hypothetical accident environment, 30 minute exposure to a 1475 F source with emissivity of 0.9 and a package absorptivity of 0.8.
The thermal model assumes that the plywood does not char, a conservative assumption.
The grain orientation of fir plywood was properly accounted for by varying the thermal conductivity in the parallel and perpendicular direction.
The results of the transient thermal analysis showed that the maximum internal temperature in the packages peaked after the fire exposure.
Therefore, the resulting maximum temperatures for the contents would be less than these peak temperatures, 350 F for the Outer HFIR Unirradiated Fuel Element Shipping Container and 255 F for the Inner HFIR Unirradiated Fuel Element Shipping Container.
These maximum temperatures occur after one and two hours of cooling, respectively.
Therefore, the staff review of the applicant's thermal analysis supports the conclusion that the Inner HFIR Unirradiated Fuel Element Shipping Container and the Outer HFIR Unirradiated Fuel Element Shipping Container satisfy the thermal requirements of 10 CFR Part 71.
Criticality Evaluation The subcriticality of the packaging with either contents, inner fuel element (2.6 Kg of U-235) or outer fuel element (6.8 Kg of U-235), was established by comparison of the postulated worst accident with HFIR experimental data.
The contents of a single package comprise less than 80% of the HFIR critical mass under optimum conditions. Wher. inner and outer elements are fitted together (not possible in either package, since both elements cannot simul-taneously be contents) criticality cannot be attained by flooding alone, without the exclusion of water from the central space within the inner elements.
Neither the inner nor the outer fuel element can be made critical when con-sidered singularly, with or without void spaces, whether they are crushed or not crushed.
Furthermore, experimental data shows that after a fully assembled HFIR core is made critical by creating an inner void during the flooded condition, a second full core just interacts with the first (increasing keff by less than 0.001) 1143 079
4 at a separation of 6 inches in water.
Since more than 6 inches equivalent of water exists between packages in both the normal and accident mode, Fissile Class I requirements are met.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
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