ML20207K661
| ML20207K661 | |
| Person / Time | |
|---|---|
| Site: | 07109178 |
| Issue date: | 03/11/1999 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20207K658 | List: |
| References | |
| NUDOCS 9903170264 | |
| Download: ML20207K661 (6) | |
Text
g NRc FORM 514 I **o CERTIFICATE OF COMPLIANCE u.s. NUCLEAR RE2uLAToRY CoMMisCo urcmn I
, Nl FOR RADIOACTIVE MATERIALS PACKAGES 1.a CERitMCATE NUMBER b. REVISION NUMBER . c. PACKAGE IDENTIMCATION NUMBER d. PAGE NUMBER e TOTAL NUMBER PAGES D
i 9178 9 USA /9178/A 1 5 t Nl. 2. PREAMBLE ~I I
Nl a. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10.
Ng Codiof Federar Regulations. Part 71,
- Packaging and Transportation of Radioactive Material." I N
- b. This certiricate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other I; applicable regulatory agencies, including the government of any country through or into which the package will be transported. I l
1 TH15 CERTIMCATE IS 155UED ON THE B AS!$ OF A S AFETY ANALYSIS REPORT OF ntE PACKAGE DESIGN OR APPLICATION
- a. ISSUED TO (Name sad Address 1 b. TITLE AND IDENT1MCATION OF REPORT OR APPLICATION: I D{ E pl ATG Nuclear Selvices L.L.C. NUPAC application dated February 29,1988, g ,
p 669 Emory Valley Road as supplemented. g p Oak Ridge, TN 37830 g l
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p c. DOCKET NUMBER 71 9178 I i p t CONDITIONS ;- I g This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71. as applicable, and the conditions specified below. , l l 5 I l
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B p l (a) Packaging (1) Model Nos.: NUPAC 7/100 and LN 7-100
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4 b i (2) Description g pl' t !
R Steel encased lead shielded casks for radioactive material. The casks are right circular i b;, cylinders with a 75.5-inch ID by 40.75-inch lH cavity. The walls of the casks contain a lead 1 I Dj thickness of 3.00 inches encased in 0.38-inch thick inner steel shell and 0.88-inch thick outer I I steel shell. The top cover and cask bottom are made up of two steel plates ranging in I Ill thickness from 2.0 to 3.5 inches. The primafy cask lid is secufed to the cylindrical cask body I by eight,1-1/4-inch rachet binders. An optional secondary lid is centered in the primary lid and I h i is secured to the primary lid with eight,3/4-inch studs and nuts. Each lid is provided with a g ,
gl Neoprene gasket seal. The casks may be provided with an optional 12-gauge stainless steel i
gl liner (seal welded along all edges), an optional lid vent line with pipe plug, and an optional 3/4-l i
i inch drain line and pipe plug. The casks are provided with four equally spaced lifting / tie-down i pl devices. The primary lid is provided with three lifting lugs and the optional secondary lid is g p provided with one lifting lug. Each cask has a gross weight of 48,900 pounds. I D I D (b) Drawings 1 D I E Model No. NUPAC 7/100 1 9 I The packago is fabricated in accordance with Nur v.sar Packaging, Inc., I hl Drawing No. X-20-309-SNP, Sheets 1,2, and 3, Revision No. A.
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Dj The package is fabricated in accordance with LN Technologies Corporation Drawing No. 5025-M-2005, Sheets 1 and 2, Revision No O.
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b (1) Type and form of material 8 5 5 l Dewatered, solid, or solidified wastes, or activated solid components, in secondary llg! containers, and limited to the following: l b E pl (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 y exceed: 3 D I b 0.0001 millicurie of radionuclides for which the A, quantity in Appendix A of R b 10 CFR Part 71 is not more than 0.05 curie; I b B i I 0.005 millicurie of radionuclides for which the A, quantity in Appendix A of 5) 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or 0.3 millicurie of radionuclides for which the A2 quantity in Appendix A of l}
p 10 CFR Part 71 is more than 1 curie, y
b I y (ii) Objects of nonradioactive material extemally contaminated with radioactive g b material, provided that the radioactive material is not readily dispersible and the g b surface contamination, when averaged over an area of 1 square meter, does I b not exceed 0.0001 millicurie (220,000 disintegrations per minute) per square I B centimeter of radionuclides for which the A, quantity in Appendix A of N b; 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie N
- l (2,200,000 disintegrations per minute) per square centimeter for other I radionuclides.
l (2) Maximum quantity of material per package ll ll Greater than Type A quantity of radioactive material which may contain fissile material g g provided the fissile material does not exceed the limits of 10 CFR $71.53. The decay heat g g load is limited to 17 watts. l Te N b N b I b I b I b d <
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himNRC FORM 618A CONDmONS d> U.s. NUCLEAR REGULATORY Commission g
. p! P ge 3 - Certificate No. 9178 - R; vision No. 9 - Dock:t No. 71-9178 g; s' El s' E!
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?j 6. (a) For any package containing water and/or organic substances which could radiolytically generate El El combustible gases, determination must be made by tests and measurements or by analysis of a !l
?i representative package such that the following criteria are met over a period of time that is twice Nl ll a,
the expected shipment time:
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g El (1) The hydrogen genented must be limited to a molar quantity that would be no more than gl il 5% by volume (or equivalent limits for other inflammable gases) of the secondary gl il container gas void if present at STP (i.e., no more than 0.063 g-moles /ft* at 14.7 psia and gl 3 70*F); or gj Sl El s;j (2) The secondary container and cask cavity must be inerted with a diluent to assure that E; sj oxygen is limited to 5% by volume in those portions of the package which could have (l sj hydrogen greater than 5%. E, 5 I l
$jl For any package delivered to a carrier for transport, the secondary container must be prepared Ni
!I for shipment in the same manner in which determination for gas generation is made. Shipment ' N '
[1 ji period begins when the package is prepared (sealed) and must be completed within twice the expected shipment time. 'f gl al gl EIi (b) For any package shipped within 10 days of preparation, or within 10 days after venting of drums or gl s other secondary containers, the determination in (a) above need not be made, and the time restriction g In (a) above does not apply. g' sl '
s- E sf 7. Maximum gross weight of the contents, secondary containers, and shoring is limited to 13,000 pounds. E E
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!j 8. Except for close fitting contents, shoring must be placed between secondary containers and the cask El El cavity to minimize movement during normal conditions of transport. E 5 E
- 9. The lid and the shield plug lifting lugs must not be used for lifting the cask, and must be covered in ji transit.
g al g il 10.
l The cask must be provided with either (or both) a drain line or a lid vent line as shown in the drawing in g p order to provide a method to leak test the package. g I
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i E 9;, 11. In addition to the requirements of Subpart G of 10 CFR Part 71: E T E
$jt (a) Prior to each shipment, the packaging Neoprene lid seals if opened (or if security sealis broken), E El must be inspected. The seals must be replaced with new seats if inspection shows any defects or E
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El every twelve (12) months, which ever occurs first. Cavity drain and vent lines must be sealed with appropriate sealant applied to the r!pe plug threads.
q E j (b) Each packaging must meet the Acceptance Tests and Maintenance Program of; W
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sj Nodel No. NUPAC 7/100 g E
sg Section 8.0 of the application. E s; E s Model No. LN 7-100 E h E
$j - LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and WM-013, E El Rev.F. U sj d h (c) The package shall be prepared for shipment and operated in accordance with the Operating j Procedures of: y sl Model No. NUPAC 7/100 i
s g s d Section 7.0 of the application, g sf s j N s Model No. LN 7-100 W s 0
$l 5l LN Technologies Corporation Procedures WM-025, Rev. C. N W
- 12. The ratchet binders on the cask tid must be torqued to 100i10 ft-lbs.
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g jl 13. The cask body and each cask lid must be marked in accordance with 10 CFR 671.85(c). g al g El 14. The packages authorized by this certificate must be transported on a motor vehicle, railroad car, g s aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the g s licensee. q h R s The packages authorized by this certificate are hereby approved for use under the generallicense d
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j provisions of 10 CFR $71.12. E I
El p 16. Expiration date: April 1,1999. This certificate is not renewable.
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- h Page 5 - Certificate No. 9178 - Rsvisi:n No. 9 - Dock:t No. 71-9178 g R
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R REFERENCES B <
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- 5 B;
R ljl Nuclear Packaging, Inc., application dated February 29,1988. l Supplements dated: April 19,1988; February 16,1993; and August 5,1997.
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p NUS supplement dated: November 22,1985. g b I B LN Technologies Corporation supplement dated: February 16,1988. p
- B B Scientific Ecology Group, Inc., supplement dated: April 30,1993. B 5 B 8 ATG Nuclear Services L.L.C. supplement dated: December 1,1998. I 8 E 9 B l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l
8 B
- B
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i a Cass R. CN vell, Chief g
- Packagec .fication Section i 1 Spent Fuel Project Office B l 8
Office of Nuclear Material Safety Bl 8
and Safeguards E!
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- B i Date: March 11,1999 E l
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APPROVAL RECORD Model No. NUPAC 7/100 and LN 7-100 Packages . 1 Certificate of Compliance No. 9178 j Revision No. 9 l 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. 9178 for the Model No. NUPAC 7/100 and LN 7-100 packages be changed from Molten Metal Technology, Inc., to l 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 Program Approval for Radioactive Materiai 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 packages to meet the requirements of 10 CFR Part 71.
Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date: March 11,1999