ML20207G295
| ML20207G295 | |
| Person / Time | |
|---|---|
| Site: | 07109222 |
| Issue date: | 03/04/1999 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20207G287 | List: |
| References | |
| NUDOCS 9903120044 | |
| Download: ML20207G295 (5) | |
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- f NRc FORM 618 u.s. NUCLEAR REGULATORY CoMMIM'ON gj
! J aSo CERTIFICATE OF COMPLIANCE I 'O C'" 7'
! FOR RADIOACTIVE MATERIALS PACKAGES Nli l yl 3.a CERTIFICATE NUMBER El l ) b. REVISION NUMBLR c. PACKAGE IDENTIFICATION NUMBER d. PAGE NUMBER e. TOTAL NUMBLR PAGES gl ,
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ll j 2. PREAMBLE 9222 7 USA /9222/A 1 4 E!I Nl j
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- a. This certificate is issued to cenify that the packaging and contents described in Item 5 below. meets the applicable safety standards set forth in Title 10.
Code of Federal Regulations. Part 71. Packaging and Transportation of Radioactise Material."
k l h b. This cenificate does not reheve the consignor from compliance with any requirement of the regulations of the u.S. Department of Transponation or other N l
applicable regulatory agencies, including the government of any country through or into which the package will be transponed. N h
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$l 3 TH15 CERTIFICATE l$ ISSUED ON THE B ASIS OF A S AFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a 15$UED To(Nuw arid Adderss; g I
- b. TITLE AND IDENTIFICATION OF REPORT OR APPLICAT10N: R i '
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) ij; ATG Nuclear Services, L.L.C. Hittman Nuclear application dated E 3j 669 Emory Valley Road December 14,1987. as supplemented. E ;
3 Oak Ridge, TN 37830 W d
) c. DOCKET NUMBER 71-9222 g
% 4 CONDITIONS g Lj This cenificate is conditional upon fulfilling the requirements of 10 CFR Pan 71. as apphcable. and the conditions specified below. g i I. ) 5.
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!! E l :3 (a) Packaging g l 'i Model No.: 14-215
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- 3 (1) g i
- )! Description E l
- 3 (2) g j
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gl Steel encased lead shielded cask for radioactive material. The cask is a right circular cylinder g I l :g l with a 77.25-inch ID by 80.25-inch IH cavi*y The outside diameter of the cask is 83.5 inches g i st with a 92.25-inch height. The walls of the cask contain a lead thickness of 1.88 inches encased g
-il in 0.38-inch thick inner steel shell and 0.88-inch thick outer steel shell. The top cover and cask g
- s! bottom are made up of two steel plates with thickness of 2.0 inches. The primary cask lid is g
'il secured to the cylindrical cask body by eight,1-1/4-inch rachet binders. A secondary lid is g il centered in the primary lid and is secured to the primary lid with eight, 3/4-inch studs and nuts. g il Each lid is provided with a Neoprene gasket seal. The cask is provided with a 12-gauge g y stainless steel liner (seal welded along all edges), a lid vent line with pipe plug, and a 3/4-inch g
- W drain line and pipe plug. The cask is provided with four equally spaced lifting / tie-down devices. g i
ji The ptimary lid is provided with three lifting lugs and the secondary Ibl is provided with one g
, lifting lug. The cask gross weight is 58,400 pounds.
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j (3) Drawings 4 g
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)jg The package is fabricated in accordance with Scientific Ecology Group, Inc. Drawing No. STD-02-077, Sheets 1 and 2, Rev.11. l g
The optional shield inserts are fabricated in accordance with Scientific Ecology Group, Inc. I Drawing No. STD-02-086, Rev. O.
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usw w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w W W W w w w e w w a l g NRC FORM 618A coNDirtoNs tronimud; u.s. NUCLEAR REGULATORY Commission l 5 %ge 2 - Certificate No. 9222 - Revision No. 7 - Docket No. 71-9222 l
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D B 5. (b) ' Contents I b
b (1) Type and form of material D
D Dewatered, solids, or solidified waste, or activated solid components, in secondary D containers, and limited to the following:
B B it) Materials in which the radioactivity is essentially uniformly distributed and in which p the estimated average concentration per gram of contents does not exceed:
R p 0.0001 millicune of radionuclides for which the A, quantity in /gpendix A of p 10 CFR Part 71 is not more than 0.05 curie; 9 .
p 0.005 millicurie of radionuclides for which the A2 quantity in Appendix A of p 10 CFR Part 71 is more than 0.05 curie, but not more thsn 1 curie; or W
p 0.3 millicurie of radionuclides for which the A2 quantity in Appendix A of p 10 CFR Part 71 is more than 1 cui;e.
g (ii) Objects of nonradioactive material extemally contaminated with radioactive y material, provided that the radioactive materialis not readily dispersible and the g surface contamination, when averaged over an area of 1 square meter, does not g exceed 0.0001 millicurie (220.000 disintegrations per minute) per square g centimeter of radionuclides for which the A2 quantity in Appendix A of y 10 CF"s o art 71 is not more than 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per squere centimeter for other a
j radionuclides.
f (2) Maximum quantity of material por package Greater than Type A quaittity of radioactive material which may contain fissile material y provided that the fissile inaterial does not exceed tha limits in 10 CFR $71.18 and g $71.22. The decay heat 'o6d it timited to 9 watts.
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p NRC FORM 618A CONDm0NS enmimw.t; U.S. NUCLEAR REGULATORY Commission g Page 3 - Certificate No. 9222 - Revision No. 7 - Docket No. 71-9222
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- 6. I l (a)
- For any package containing water and/or organic substances which could radiolytically generate combustible gases, deteiminatiun must be made by tests ud measurements or by
,' analysis of a representative package such that the following criteria are met over a period of -
time that is twice the expected shipment time:
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E I (1) The hydrogen generated must be limited to a molar quantity that would be no more than E I 5% by volume (or equivalent limits for other inflammable gases) of the secondary E
container gas void if present at STP (i.e., no more than 0.063 g-moles /ft8 at 14.7 psia and I I 70'F); or i B E E
(2) The secondary container and cask cavity must be i,.erted with a diluent to assure that I E
oxygen must be limited to 5% by volume in those portions of the package which could I I have hydrogen greater than 5% I. '
W t l D For any package delivered to a carrier for transport, the secondary container must be prepared I b for shipment in the same manner in which determination for gas generation is made. Shipment I B period begins when the package is prepared (sealed) and must be completed within twice the I N expected shipment time. L 9 E D (b) For any package shipped within 10 days of preparation, or within 10 days after venting of L Bj drums or other secondary containers, the determination in (a) above need not be made, and I B the +ime restriction in (a) above does not apply. 1-R E i 7. Maximum gross weight of the contents, secondary containers, shield inserts and shoring is imited to E l B 20,000 pounds. E i
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D' 8. Except for close fitting contentr, shoring must be placed between secondary containers and the cask i I D. cavity to minimize movement during normal conditions of transport. .
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p 9. The lid and shield plug lifting lugs must not be used for lifting the cask, and must be covered in transit. t 1
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) 10. In addition to the requirements of Subpart G of 10 CFR Part 71: E l B t l p (a) Prior to each shipment, the pachging Neoprene lid seals must be inspected. The seals must a p be replaced within twelve (12) c ( nths prior to shipment. Also, seals must be replaced with l y new sec!s if inspection shows s/ defects. Cavity drain and vent lines must be sealed with r y appropriate sealant applied to the pipe plug threads. g i p i p (b) The package shall be prepared for shipment and operated in accordance with the Operating g !
p Procedures of Section 7.0 of the application and Scientific Ecology Group, Inc. supplements a y dated May 16,1990 and September 7,1995. i ,
D E p (c) Each cask must meet the Acceptance Tests and Maintenance Program of Section 8.0 of the g p application, as supplemented. In addition, the cask must be leak tested witt}in twelve (12) g b months prior to shipment and each seal must be leak tested after replacement in accordance i p with Paragraph 8.1.3 of the application, g i B E D E D E D L p' t B E pl i
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>{ w mPage 4 - Certificate No. 9222 - Revision No. 7 - Docket No. 71-9222 Nl D
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- 11. The, cask t3 ody and each lid must be marked in accordance with 10 CFR 571.85(c).
- 12.
The packages authorized by this certificate must be transported on a motor vehicle, railroad car, l aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the lj ,
licensee. Ei 9-4l ,
8 13. Optional shield inserts may be used as needed. The optional shield inserts must be fabricated in Nl l
- { accordance with Scientific Ecology Group, Inc., Drawing No. STD-02-086, Revision 0. Nl l N{
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- 14. The package authorized by this certificate is hereby approved for use under the general license l '
B provisions of 10 CFR $71.12. U-B E D 15. Expiration date: April 1,1999. This certificate is not renewable. N b N b
9 REFERENCES E
E ll l
b E b d B Hittman Nuclear application dated December 14,1987. 5 E 4 B Hittman Nuclear supplements dated: January 26, March 25, and June 10,1988. d 9 4 I
B Scientific Ecology Group, Inc. supplements dated: April 3 and May 16,1990; January 26, June 10, and 4 1 n! October 4,1993; February 3, February 25, and March 2,1994; September 6,1995; and October 10,1997. E I
B .
N pl ATG Nuclear Services, LL.C., supplement dated December 1,1998. l
- I la b 4 y FOR THE U.S. NUCLEAR REGULATORY COMMISSION q !
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, d, 1 g Cass R. Chappell, Chief g g Package Certification Section g g Spent Fuel Project Office g ,
y Office of Nuclear Material Safety g g and Safeguards g l Date: 1%rch 4, 1999 p
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- , UNITED STATES
[o j NUCLEAR REGULATORY COMMISSION A' WASHINGTON, D.C. 20666-0001 APPROVAL RECORD Model No.14-215 Certificate of Compliance No. 9222 Revision No. 7 By letter dated December 1,1998, ATG Nuclear Services L.L.C., and Molten Metal Technology, Inc., requested that the certificate holder for Certif;cate of Compliance No. 9222 for the Model No.14-215 package be changed from Molten Metal Technology, Inc., to ATG Nuclear Services -
L.L.C. ATG Nuclear Services L.L.C., has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. ATG Nuclear Services LL.C., will be responsible for maintenance of the certificate, the safety analysis report for the package design, and the quality assurance records in accordance with 10 CFR 671.91(c). ATG Nuclear Services L.L.C., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71.
The Certificate has been revised to show ATG Nuclear Services L.L.C., as certificate holder.
These changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.
in fd -
Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date: March 4, 1999