ML20207J293
| ML20207J293 | |
| Person / Time | |
|---|---|
| Site: | 07109073 |
| Issue date: | 03/04/1999 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20207J289 | List: |
| References | |
| NUDOCS 9903160237 | |
| Download: ML20207J293 (5) | |
Text
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$ ! NRC u.S. NUCLEAR REGULATORY Commission m) FORM 618 CERTIFICATE OF COMPLIANCE Nl 4 w cm i k
FOR RADIOACTIVE AMTERIALS PACKAGES N ~
g i i. a. CERTinCATE N5usiER b. REvls ON Neusta c. PACK AoE iDeNTiriCATiON Neusta d. P4cE Neusta e. TOTAL NeuBEn paces k
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& This ceruficate is issued to certify that the packaging and contents desenbed in item 5 below, meets the applicable safety standards set forth in Title 10, kg Code ef Federal Regulations. Pan 71. " Packaging and Tur.sponation of Radioactive Material." @
- b. This certificate dces not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or uher N h ajylicaNe regulatory agencies, including the government of any country through or into which the package will be transponed. k l!P re l 3 Tills CERT 1FICATE li 15$UEDON THE BAS!S OF A SAFETY ANAL YSIS REPORT OF THE PACK AGE DESIGN OR APPLICATION
- a. ISSUED TO(Name and Addam) b. TITLE AND 'DENTIMCAllON OF REPORT Ok APPLICATION: k.
N{i I i ATG Nuclear Services LLC. Scientific Ecology Group, Inc., application I 669 Emory Valley Road dated January 26,1994. E
@h Oak Ridge, TN 37830 71-9073
- c. DOCxET NeuBEn g
4 CONDmONS g
Thn certificate is condnional upon fulfilling the requirements of 10 CTR Part 71. as applicable, and the conditions specified below. g y 5.
g k i I (a) Packaging E
!- I (1) Model No.: 10-142A a (2) D6scription g
9, A steel encased, lead shielded cask for solid radioactiva material. The overall y h dimensions of the cask are 101-inch diameter by 120-inch height. The cask g
% consists of two concentric carben steel cylindrical shells surrounding a 3-1/2- 4 N
i inch thick lead shield. The 1/2 inch thick inner shell has a 66-inch ID, and the d N
l 1-inch thick outer shell has a 76-1/4-inch OD; the base consists of two,3-inch 4 hl thick welded steel plates. The base is welded to the steel cylindrical shells. A E stepped welded lid, secured by eight ratchet binders, is comprised of two,3-g!
g inch thick steel plates containing openings for a secondary lid of similar g sf construction with an additional 1-inch thick upper plate. The secondary lid is q kj secured to the primary lid through eight,1-inch diameter bolts. The g B. containment cavity is 66 inches in diameter by 72 inches high. The package g
> design is provided with a lid test port. Toroidalimpact limiters are located at 5l j the top and bottom of the cask. The impact limiters are 10-gauge stainless E
4 h steel filled with rigid polyurethane foam. Interior and exterior surfaces of the 5 h cask body and interior surfaces of the upper lid are covered with 12-gauge,304 g stainless steel cladding and seal welded, g
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p The primary lid is closed by means of eight ratchet binders. The 29-inch g B diameter secondary lid is closed by eight,1-inch diemeter stud bolts. Both lids g 5 are sealed using silicone gaskets bonded to the lid plates. Lifting is facilitated W
$l with three lugs welded to the primary lid. The secondary lid has a redundant E Neoprene seal, and a centrally located lift lug.
p All exposed side walls are covered with a stainless steel thermal barrier. Four y
pl skewed lugs, welded to the outer shell, are used for tie-down. The package 4
B; gross weight is approximately 64,000 pounds. g
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g 5. (a) (3) Drawings 3
The packaging is fabricated in accordance with Scientific Ecology Group, Inc.,
p Drawing No. STD-02-10'7, Sheets 1 and 2, Rev. O.
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'ln' (b) Contents WI N Type and form of material (1) )
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E Dewatered ion exchange resins, solid waste, or activated solid components; in
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g secondary containers; and limited to the following: )
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) (i) Materials in which the radioactivity is essentially uniformly distributed and in l s which the estimated average concentration per gram of contents does not B exceed:
9, E 0.0001 millicurie of radionuclides for which the A2 quantity in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; d 0.005 millicurie of radionuclides for which the A2 quantity in Appendix A E! of 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or d
2 B! 0.3 millicurie of radionuclides for which the A2 quantity in Appendix A of-bl 10 CFR Part 71 is more than 1 curie.
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5 (ii) Objects of nonradioactive material externally contaminated with radioactive Ej material, provided that the radioactive material is not readily dispersible and the surface contamination, when averaged over an area of 1 square meter, h c'oes not exceed 0.0001 millicurie (220,000 disintegrations per minute) per y
p square centimeter of radionuclides for which the A2 quantity in Appendix A
) of 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie 9 (2,200,000 disintegrations per minute) per square centimeter for other W radionuclides.
B 5 Maximum quantity of material per package (2) 9 f Greater than Type A quantities of radioactive materials which may contain y fissile contents not to exceed the generally licensed mass limits as specified in pl 10 CFR 6 5 571.18,71.20, and 71.22. Internal decay heat not to exceed 400 pI watts and the maximum weight of contents, including secondary containers, b not to exceed 10,000 pounds.
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J (SM i 8i Page 3 - Certificate No. 9073 - Revision No. 21 - Docket No. 71-9073 Wl
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- l 6. (a) For ar.y package containing water and/or organic substances which could radiolytically gl g
g! generate combustible gases, datermination must be made by tests and measurements or gl pl p by analysis of a representative package such that the following criteria are met over a .(j bg period of time that is twice the expected shipment tims: ( i
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$' (1) The hydrogen generated must be limited to a molar quantity that would be no -
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j more than 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- f gl moles /ft at 14.7 psia and 70*F); or gl 9
t NI p (2) The secondary container and cask cavity must be inerted with a diluent to gl 4 p g
assure that oxygen must be limited to 5% by volume in those portions of the g(
Y package which could have hydrogen greater than 5%. q; J
B Ni 5 For any package delivered to a carrier for transport, the secondary container must be k I prepared for shipment in the same manner in which determination for gas generation is k g
made. Shipment period begins when the package is prepared (scaled) and must be completed within twice the expected shipment time.
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p (b) For any package shipped within 10 days of preparation, or within 10 days after venting of gl p drums or other secondary containers, the determination in (a) above need not be made, el i
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and the time restriction in (a) above does not apply. (
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$ 7. Except for close fitting contents, dunnage must be provided in the shipping cask cavity Ul 8 sufficient to prevent significant movement of the contents or secondary containers relative to E' the outer packaging under normal conditions. ,
a g; j 8. In addition to the requirements of Subpart G of 10 CFR Part 71: g';
B 5 l 9 (a) Prior to each shipment, the packaging lid seats must be inspected. The seals must be g! I s replaced with new seals if inspection shows any defects or every 12 months, whichever gl B occurs first. The cavity test port must be sealed with appropriate sealant applied to the W Bj pipe plug threads. I Nj U ,
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(b) The package shall be prepared for shipment and operated in accordance with the Operating Procedures in chapter 7 of the application. f4 R R-p (c) The package must meet the Acceptance Tests and Maintenance Program in chapter 8 of g.
p the application. 0 4 5 9 9. The package authorized by this certificate must be transported on a motor vehicle, railroad dl 5 car, aircraft, inland watercraft, or hold ur deck of a seagoing vessel assigned for the sole use Ul of tha licensee.
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~ t a os) i Ni Page 4 - Certificate No. 9073 - Revision No. 21 - Docket No. 71-9073 Dj kl -
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g 10. Packagings fabricated after March 28,1980 must be constructed of A 516 Grade 70 I
p carbon steel.
5 i 11. The packaging authorized by this certificate is hereby approved for use under the general
% license provisions of 10 CFR 571.12.
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Expiration date: April 1,1999. This certificate is not renewable.
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- g REFERENCES B
b- Scientific Ecology Group, Inc., application dated January 26,1994.
N N Supplement dated October 10,1997; and December 1,1998.
i FOR THE U.S. NUCLEAR REGULATORY COMMISSION W
- f Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards j Date: _ March 4 1999 l
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p % UNITED STATES g j NUCLEAR REGULKTORY COMMISSION WASHINGTON, D.c. 20665 4001 4,.....go .
APPROVAL RECORD !
Model No.10142A l Certificate of Compliance No. 9073 I Revision No. 21 l
' 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. 9073 for the Model !
No.10-142A package be changed from Molten Meta! Technology, Inc., to ATG Nuclear i Services L.LC. 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 i Nuclear Services L.L.C. will be responsible for maintenance of the certificate, the safety i analysis report for the package design, and the quality assurance records in accordance with l 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.
l 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.
swd Cass R. Chappell, Chief Package Certification Section <
Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date: March 4, 1999 e