ML20207K685
| ML20207K685 | |
| Person / Time | |
|---|---|
| Site: | 07109159 |
| Issue date: | 03/11/1999 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20207K683 | List: |
| References | |
| NUDOCS 9903170270 | |
| Download: ML20207K685 (6) | |
Text
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4 g NRCFORM61D u.S. NUCLEAR REGULATORY CoMMISSloN J ow CERTIFICATE OF COMPLIANCE "C"
p FOR RADIOACTIVE MATERIALS PACKAGES gl I.a CERTIFICATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER d. PAGE NUMBER e. TOTAL NUMBER PAGE.S I
p 9159 9 USA /9159/A 1 5 l
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- 2. PREAMBLE N
- a. This cenificate is issued to cenify that the packaging and contents described in item $ below, meets the applicable safety standards set forth in Title 10 hl Code of Federal Regulations. Pan 71. " Packaging and Transponation of Radioactive Material."
$l b. This cenificate does not relieve the consignor from compliance wnh ary requirement of the regulations of the U.S. Depanment of Trasportation or other fg applicable regulatory agencies. including the government of any country through or into which the package will be transported.
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- 3. THIS CERTIRCATE IS ISSUED ON THE B ASIS OF A SAFETY AN ALYSIS REPOiG OF THE PACK AGE DESIGN OR APPLICATION q a 15 SUED TOIName and AddressJ b. TITLE AND IDENTIMCATION OF REPORT OR APPLICATION s
A h ATG Nuclear Services L.L.C. NUPAC application dated February 29,1988, I il 669 Emory Valley Road as supplemented. .
i Oak Ridge, TN 37830 j!
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- c. DOCKET uuMBER 71-9159 g y a CONDITIONS g
) This cenificate is condmonal upon fulfilling the requirements of 10 CFR Pan 71. as applicable, and the conditions specified below. g Nj 5 l sj E
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% (a) Packaging N
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El (1) Model Nos.: NUH LN
,/190L, NUPAC 14/190M, NUPAC 14/190H, LN 14-170L,
,,0M, and LN 14-170H I
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q (2) Description g
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p Steel encased lend shielded casks for radioactive material. The casks are right circular g sl cylinders with a 75.5-inch ID by 73.38-inch IH cavity. The walls of the casks contain a lead g ,
thickness ranging from 1.25 to 2.63 inches encased in 0.38-inch thick inner steel shell and ( l s% 0.88-inch thick outer steel shell. The top cover and cask bottom are made up of two steel (
!ll plates ranging in thickness from 2.0 to 3.0 inches. The primary cask lid is secured to the E
?l cylindrical cask body by eight,1-1/4 inch rachet binders. An optional secondary lid is centered i Ei in the primary lid and is secured to the primary lid with eight,3/4-inch studs and nuto. Each lid I j is provided with a Neoprene gasket seal. The casks may be provided with an optional 12- 4 p gauge stainless steel liner (seal welded along all edges), an optional lid ve9 line with pipe plug, gl and an optional 3/4-inch drain line and pipe plug. The casks are provided with four equally l l al spaced lifting / tie-down devices. The primary lid is provided with three lifting lugs and the g il optional secondary lid is provided with one lifting lug. ine casks gross weights range from g 49,200 to 65,200 pounds, g ;
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$ Model OD, Lead Tk, Top Tk, Bottom Tk, Gross Wt, g p
%g Number NUPAC 14/190L, LN 14-170L inches 80.5 inches inches inches ,oounds )
1.25 4.0 4.0 49,200 g
% NUPAC 14/190M, LN 14-170M 81.5 1.75 4.0 4.0 53,500 N f
p' NUPAC 14/190H, LN 14-170H 83.25 2.63 5.0 5.0 65,200 al 9 qi
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b r 1 pl Page 2 - Certificate No. 9159 - Revision No. 9 - Docket No. 71-9159 g
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r D 5. (a) (3) Drawings r D;
- t Model Nos. NUPAC 14/190L. NUPAC 14/190M. and NUPAC 14/190H E D
L l The packages ars fabricated in accordance with Nuclear Packaging, Inc. Drawing No. X- I li g 20-307-SNP, Sheets 1,2 and 3, Revision No. A.
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Model Nos. LN 14-170L. LN 14-170M. and LN 14-170H g !
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p The packages are fabricated in accordance with LN Technologies Corporation Drawing L i p No. 5025-M-2005: Sheets 1 and 2, Revision No. O. L D t W (b) Contents L ;
D l- l D (1) Type and form of material I B I-l Dewatered, solid, or solidified waste, or activated solid components, in secondary containers, and limited to the following:
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(i) Materials in which the radioactivity is essentially uniformly distributed and in g p -
which the estimated average concentration per gram of contents does not g g exceed; i
l' I-pl 0.0001 millicurie of radionuclides for which the A, quantity in Appendix A of r 5 10 CFR Part 71 is not more than 0.05 curie; I 4 W t
- 0.005 millicurie of radionuclides for which the A, quantity in Appendix A of L U
10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or i b I hl 0.3 millicurie of radionuclides for which the A, qiiantity in Appendix A of g 10 CFR Part 71 is more than 1 curie. l!
g n I p (ii) Objects of nonradioactive material extemally contamingtad with radioactive i p material, provided that the radioactive material is not readily siispersible and the L p surface contamination, when averaged over an area of 1 square meter, does L p not exceed 0.0001 millicurie (220,000 disintegrations per minute) per square r 5, centimeter of radionuclides for which tha A, quantity in Appendix A of I-D. 10 CFR Part 71 is not more than 0.0'i cu;ie, or 0.001 millicurie r B (2,200,000 disintegrations per minute) per square centimeter for other L I radionuclides. I B l-I (2) Maximum quantity of matarial per package t
B I y Greater than Type A quantity of radioactive rnaterial vhich r say contain fissile r,1aterial p p provided the fissile material does not exceed the lir.. 10 CFR $71.30. The decay heat t p load is limited to 7 watts for the Model Nos. NUPAC ulM0' . NUPAC 14/190M, LN 14- I p 170L, and LN 14-170M; and 25 watts for the Model Nos. NUPAC 14/190H and LN 14- L 5 170H casks. L I
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- g gl Page 3 - Certificate No. 9159 - Revision No. 9 - Docket No. 71-9159 g p!
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b (a) For any package containing water and/or organic substances which could radiolytically generate r Dj combustible gases, determination must be made by tests and measurements or by analysis of a E hj representative package such that tha following criteria are met over a period of time that is twice 0I s the expected shipment time: I i
B E I I (1) The hydrogen generated must be limited to a molar quantity that would be no more than l
g 5% by volume (or equivalent limits for other inflammable gases) of the secondary container gas void if present at STP (i.e., no more than 0.063 g-moles /ft8 at 14.7 psia and
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y 70*F); or i
b I p (2) The secondary container and cask cavity must be inerted with a diluent to assure that i
) oxygen must be limited to 5% by volume in those portions of the package which could i i 5 have hydrogen greater than 5%. I b I b For any package delivered to a carrier for transport, the secondary container must be prepared 1 I for shipment in the same manner in which determination for gas generation is made. Shipment I E '
period begins when the package is prepared (sealed) and must be completed within twice the I expected shipment time. I h (b) For any package shipped within 10 days of preparation, or within 10 days after venting of drums or g
l other secondary containers, the determination in (a) above need not be made, and the time l
i g restriction in (a) above does not apply, i l l
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Maximum gross weight of the contents, secondary containers, and shoring is limited to 20,000 pounds. I i
B 8. Except for close fitting contents, shoring must be placed between secondary containers and the cask I b cavity to minimize movement during normal conditions of transport. l B 1 I 9. The lid and the shield plug lifting lugs must not be used for lifting the cask, and must be covered in I transit.
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- 10. The cask must be provided with either (or both) a drain line or a lid vent line as shown in the drawing in g! order to provide a method to !eak test the package. l I
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l p NR FORM 818A coNomoNs(caumwds - u.s. NUCLEAR RE@uLAToRY CoMMisslON h' l Page 4 - Certificate No. 9159 - Revision No. 9 - Docket No. 71-9159 l
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E DI 11. In addition to the requirements of Subpart G of 10 CFR Part 71: E 9 o E
D (a) Prior to each shipment, the packaging Neoprene lid seals if opened (or if security seal is broken), E D
must be inspected. The seals must be replaced with new seals if inspection shows any defects or E '
I every twelve (12) months, which ever occurs first. Cavity drain and vent lines must be sealed with E f appropriate sealant applied to the pipe plug threads.
l (b) Each packaging must meet the Acceptance Tests and Maintenance Program of:
l Model Nos. NUPAC 14/190L. NUPAC 14/190M and NUPAC 14/190H 5
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p Section 8.0 of the application. g D
E D Model Nos. LN 14-170L. LN 14-170M and LN 14-170H E D
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Rev.F. E l 9 l l (c) The package shall be pmpared for shipment and operated in accordance with the Operating E y Procedures of: E f
B.
Model Nos. NUPAC 14/190L. NUPAC 14/190M and NUPAC 14/190H f
E p' Section 7.0 of the application. g 5
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B Model Nos. LN 14-170L. LN 14-170M and LN 14-170H g-B R:
D' LN Technologies Corporation Procedures WM-025, Rev. C. B; D
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- 12. The ratchet binders on the cask lid must be torqued to 100i10 ft-lb. E!
D g: i l 13. The cask body and each cask lid must be marked in accordance with 10 CFR $71.85(c). E ll 14. The packages authorized by this certificate mst be transported on a motor vehicle, railroad car,
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p aircra*t, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the y p, licensee. g Dl 5 i 15. The packages authorized by this certificate are hereby approved for use under the general license g D provisions of 10 CFR $71.12. I B
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- 16. Expiration date: April 1,1999. This certificate is not renewable. I b
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Dl Page 5 - Certificate No. 9159 - Revision No. 9 - Docket No. 71-9159 p g D E pf . .
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D REFERENCES E D' E D L E
Nuclear Packaging, Inc., application dated Februsiy 29,1988. E D E I
Supplements dated: April 19,1988; February 16,1993: and August 5,1997.
l E E p NUS supplement dated: November 22,1985. g B E DI LN Technologies Corporation supplement dated: February 16,1988. g B E D Scientific Ecology Group, Inc., supplement dated: April 30,1993 E D' I b ATG Nuclear Services L.L.C., supplement dated: December 1,1998 t D l E D I FOR THE U.S. NUCLEAR REGUl.ATORY COMi41SSION B i 9 L 9 I B t p Cass R. Chappell, Chief r Package Certification Section y! t Spent Fuel Project Office E
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Office of Nuclear Material Safety and Safeguards E
I b I p L Date: thu;b ll.1999 I l
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g NUCLEAR REGULATORY COMMISSION t W^+ 'NOTON, D.C. 20666-0001 S.;'n.../-
APPROVAL RECORD Model No. NUPAC 14/190L, NUPAC 14/190M, NUPAC 14/190H, LN 14-170L, LN 14-170M, and LN 14-170H Packages j Certificate of Compliance No. 9159 l Revision No. 9 By letter dated December 1,1998, ATG Nuclear Services L.L.C., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9159 for the Model Nos. NUPAC 14/190L, NUPAC 14/190M, NUPAC 14/190H, LN 14-170L, LN 14-170M, and LN 14-170H Packages 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 L.L.C., will be responsible for maintenance of the certificate, the safety analysis report for the package designs, and the quality assurance records in accordance with 10 CFR $71.91(c). ATG Nuclear Services L.L.C., has been issued Quality Assurance 1 Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71. I 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 packages to meet the requirements of 10 CFR Part 71.
l Cass R. Chappell, Chief Package Certification Section i Spent Fuel Project Office Office of Nuclear Material
)
Safety and Safeguards Date: Fhrch 11. I m 9
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