ML19321A804
| ML19321A804 | |
| Person / Time | |
|---|---|
| Site: | 07109132 |
| Issue date: | 07/15/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19321A801 | List: |
| References | |
| NUDOCS 8007240217 | |
| Download: ML19321A804 (4) | |
Text
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I Fonn NRC418 U.S. NUCLEAR.REGULA. TORY CoMMISSloN
[c R n CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.tal Certificate Number 1.(b) Revision No.
1.(c) Package identification No.
1.(d) Pages No. 1.le) Total No. Pages 9132 1
USA /9132/Bf IF 1
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- 2. PREAMBLc 2.tal This certificate is issued to satisfy Sections 173.393a.173.394,173.395, and 173.396 of the Department of Transportation Haza Materiass Regulations (49 CFR 170123 and 14 CFR 103) and sections 146 19-10s 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 subcort C of Title to. Code of
, Federal Regulations. Part 71. ** Packaging of Radioactive Materials for Transport arW Transportation of Radioactive Material Under Cartain Conditions.
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This certificate does nof relieve the consignor from compliance with any reouirement of the regulatioat of the U.S. Department of Transoortation or other aoolicable regulatory agencies, including the governtnent of any country througn or into which the pac 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 addreer):
3.!b) ' Title and identification of report or'appHeation:
Department of Energy NuPac application dated October 20, 1978, P. O. Box 550 as supplemented.
Richland, WA 99352
-s 3 (c) Docket No. 71-9132
- 4. CONDITIONS This certificate is conditior*:,; upon the fulfilling of the requirements of Subaut D of 10 CFR 71, as applicable. and the conditions specified
% n item s below.
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- 5. Description of Packaging ano Authorized Contents. Model Nurnber. Fissile Class. Other Conditions. and
References:
(a). Packaging (1) Model No.: T-3 (2) Description A stainless steel and lead shielded irradiated fuel shipping package (cask). The cask is a right circular cylinder with upper and lower steel encase rigid polyurethane foam (20 lb/ft ) impact limiters.
3 The overall dimensions are 213.2 inches in length and 52 inches in diameter. The cask without the impact limiters measures 177.2 inches in length and 26.44 inches in diameter.
The outer cask shell is cofr. prised of a one (1) inch thick sthinless steel shell overlayed with a ten (10) gauge stainless steel cover.
Between these two materials is a 0.08 inch diameter wire wrap, providing an air gap for additional thermal protection.
The inner shell (containment vessel) is a standard seamless stain-less steel Schedule 40 pipe having an outside diameter of 8.625 inches with a nominal wall thickness of 0.322 inches.
The annular space between the inner and outer shells is filled with lead having a thickness of approximately eight (8) inches.
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j Page 2 - Certificate No. 9132 - Revision No. 1 - Docket No. 71-9132
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Both the inner and outer shells are welded at each end to heavy steel closure plates with conical surfaces to assist in positioning and sealing.
The containment vessel measures 147 inches inches in length by 7.981 inches in diameter.
The containment vessel is sealed at the bottom end with a 12.375-inch thick stainless steel plug with two (2) Viton 0-ring seals.
The top end of the centainment vessel is sealed with a ll.625-inch thick stainless steel plug with two (2) Viton 0-ring seals.
The bottom plug is retained by a closure plate secured by eight (8), 1/2-13UNC x 2-1/4-inch ASTM A320, Grade L7 socket head cap screws.
The top plug is secured in place utilizing sixteen (16), 1/2-13UNC x l-3/4-inch ASTM A320, Grade L7 hex flange screws.
No drain or vents penetrate directly into the containment vessel.
A drain / vent line opens directly into the area between the two (2) 0-ring seals at each end of the cask (end plugs).
During shipment, the lines are sealed with Viton 0-ring sealed threaded fasteners.
The cask is provided with six (6) trunions, four (4) spaced 90 degrees apart at the top end and two spaced at 180 degrees apart at the bottom end of the cask.
The cask is tied down at the forward and aft ends by means of a cradle and yoke assembly.
The' gross weight of the cask and contents is 39,000 pounds.
(3) Drawing The packaging is constructed in accordance with Westinghouse Hanford Company Drawing No. H4-61289, Sheets 1 thru 3, Revision No. 3.
(b) Contents (1) Type and form of material The minimum cooling time of each fuel assembly and rod shall be 90 days; and (i) FTR driver pins prior to irradiation containing 25 w/o Pu02 and 75 w/o U(natural)0, 0.23" diameter by 36" active fuel length.
2 (ii) FTR carbide pins prior to irradiation containing 20 w/o Puc and 80 w/o U(natural)C, 0.37" diameter by 36" active fuel length.
(iii) EBR-II carbide pins prior to irradiation containing 25 w/o PuC and 75 w/o U(95)C, 0.315" diameter by 13.5" active fuel length.
i (iv) Standard driver pins (Item 5(b)(1)(i) above) plus experimental l
oxide pins prior to irradiation containing 25 w/o Pu02 and 75 w/o U(98)0, 0.23" diameter by 36" active fuel length.
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- o Page 3 - Certificate No. 9132 - Revision No. 1 - Docket No. 71-9132 r
' (2) Maximum quantity of material per package Not to exceed a decay heat generation of 600 watts; and (i) Item 5(b)(1)(i) above 4.4 kg U-235 plus Pu-239 contained within inner container Ident 69, Figure 3.1.5-1.
(ii) Item 5(b)(1)(fi) above 4.1 kg 05235 pibs Pu-239 contained with inner container Ident 69, Figure 3.1.5-1.
(iii) Item 5(b)(1)(iii) above 5.0 kg U-235 plus Pu-239 contained within inner container Ident 1578, Figure 3.1.5-3.
(iv) Item 5(b)(1)(iv) above 4.7 kg U-235 plus Pu-239 contained within inner container Ident 1578, Figure 3.1.5-3 (c) Fissile Class I
6.
The cask shall be shipped dry (no water coolant in cask cavity).
7.
In addition to the requirements of Subpart 0 of 10 CFR Part 71, each cask prior to first use shall meet the acceptance tests and criteria specified in Section 7.1 of the application.
The leak test to satisfy ANSI N 14.5 and Regulatory Guide 7.4 in Section 7.1.3 of the application shall be a test having sufficient sensitivity tg detect a leak rate (air at standard tempera-ture and pressure leaking to 10 2 atm) of 10 7 atm cc/sec.
The results of
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these tests shall be documented and retained for the life of the cask.
8.
In addition to the requirements of Subpart D of 10 CFR Part 71, each cask shall be maintained in accordance with Section 7.2 of the application.
9.
The cask authocized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12(b).
10.
Expiration date:
May 31, 1985.
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..s Page 4 - Certificate No. 9132 - Revision No. 1 - Docket No. 71-9132 REFERENCES Nuclear Packaging, Inc.
Application Dated October 20, 1978.
Supplements dated: May 18 and September 12, 1979; and January 25, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
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exs n G1si Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS JUL 151980 Date:
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