ML20205G199
| ML20205G199 | |
| Person / Time | |
|---|---|
| Site: | 07109176 |
| Issue date: | 03/11/1999 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20205G174 | List: |
| References | |
| NUDOCS 9904070159 | |
| Download: ML20205G199 (6) | |
Text
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$m CERTIFICATE OF COMPLIANCE I
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FOR RADIOACTIVE MATERIALS PACKAGES g!
L e. CERTIMCATE NUMHER b REVISION NUMBER c PACKAGLIDENTIDCATION NUMBER d PAGE NUMBER
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9176' 15 USA /9176/A 1
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- 2. PRLAMBLE h i a This censficate is issued to cenify that the packaging and contents desenbed in item $ below. meets the apphcable safety standards set fonh in Title 10.
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$j Code of Federal Regulations. Part 71. " Packaging and Transponation of Radioactive Material."
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- b. This cenificate does
'ieve the consi nor from compliance uith any requirement of the regulations of the U.S. Depanment of Transportation or other F
applicable regulator + 4: Iies, including the government of any country through or into which the package will be transponed.
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Bl 3 THl5 CERTIMCATE IS ISSUED ON THE B ASIS OF A S AfTTY ANALYSIS REPORT OF THE PACK AGE DESIG D
a ISSUED 10 (%me and AddressJ b TITLE ANDIDENTIMCATION OF REPORT OR APPLICATION:
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6l fl ATG Nuclear Services L.L.C.
NUPAC application dated February 29,1988, y
669 Emory Valley Road as supplemented.
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Oak Ridge, TN 37830 l
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- c. DOCKET NUMBER 71-9176 g
4 CONDITIONS
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This cenificate is cond!tional upon fulfillmg the requirements of 10 CrR Part 71. as apphcable. and the conditions specified below.
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B (a)
Packaging 6
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Model Nos.: NUPAC 14/210L, NUPAC 14/210H, CNSI 14-215H Series A, LN 14-195L,
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and LN 14-195H q
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Description g
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Steel encased lead shielded casks for radioactive material. The casks are right circular g,
pl cylinders with a 77.25-inch ID by 80.25-inch IH cavity. The walls of the casks contain a lead gj 5,
thickness ranging from 1.25 to 1.88 inches encased in 0.38-inch thick inner steel shell and qj 9
0.88-inch thick outer steel shell. The top cover and cask bottom are made up of two steel E i 9
plates with thickness of 2.0 inches. The primary cask lid is secured to the cylindrical cask body N
5 by eight,1-1/4 3 ch rachet binders. An optional secondary lid is centered in the primary lid and W
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is secured to the primary lid with eight,3/4-inch studs and nuts. Each lid is provided with a E
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Neoprene gasket seal. The casks may be provided with an optional 12 gauge stainless steel I
liner (seal welded along all edges), an optional lid vent line with pipe plug, and an optional 3/4-g!
inch drain line with pipe plug. The casks are provided with four equally spaced lifting / tie-down y
g devices. The primary lid is provided with three lifting lugs and the optional secondary lid is g
g provided with one lifting lug. The casks gross weights range from 51,600 to 58,400 pounds.
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Model OD, Lead Tk, Top Tk, Bottom Tk, Gross Wt,
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Number inches inches inches inches counds
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n' NUPAC 14/210L, LN 14-195L 82.25 1.25 4.0 4.0 51,600 4
5 NUPAC 14/210H, LN 14-195H 83.5 1.88 4.0 4.0 58,400 4
- l CNSI 14-215H Series A 83.8 1.85 4.0 4.0 58,400 W
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gN FORM 618A CONDmONS kemnnwh U.S. NUCLEAR RE2uLAToRY CoMMISSloN g
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p Page 2 - Certificate No. 9176 - Revision No.15 - Docket No. 71-9176 g
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(a)
(3) Drawing B
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B Model Nos. NUPAC 14/210L and NUPAC 14/210H k
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The packages are fabricated in accordance with Nuclear Packaging, Inc., Drawing No. X-E l
20-306-SNP, Sheets 1,2 and 3, Revision No. A.
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The packages may include an optional removable shield ir. sert fabricated in accordance g l g
with Pacific Nuclear Drawing Nos. PS-121892-1 and PS-121892 submitted on December g
p 21,1992.
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Model No CNSI 14-215H Series A 5
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b The package is fabricated in accordance with Chem-Nuclear Syctems, Inc., Drawing Nos.
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24500-08, Sheets 1 and 2, Rev. D, and 24500-5, Rev. 2.
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The package may include an optional removable shield insert fabricated in accordance I
with Chem-Nuclear Systems, Inc., Drawing No. C-119-B-0017, Rev. 3 I
l Model Nos. LN 14-195L and LN 14-195H I
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p The packages are fabricated in accordance with LN Technologies Corporation Drawing g
p No. 5025-M-2005, Sheets 1 and 2, Rev. O.
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(b)
Contents I !
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(1) Type and form of material i I B
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I Dewatered, solid, or solidified waste, or activated solid components, in secondary I[!
l containers, and limited to the following:
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Materials in which the radioactivity is essentially uniformly distributed and in I
y which the estimated average concentration per gram of contents does not g
g exceed:
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p 0.0001 millicurie of radionuclides for which the A quantny in Appendix A of g
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10 CFR Part 71 is not more than 0.05 curie; E
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N 0.005 millicurie of radionuclides for which the A quantity in Appendix A of I
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10 CFR Part 71 is more than 0.05 curie but not more than 1 curie; or I
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l 0.3 millicurie of radionuclides for which the A quantity in Appendix A of I
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10 CFR Part 71 is more than 1 curie.
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Page 3 - Certificate No. gi76 - Revision No.15 - Docket No. 71-gi76 g
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1 (ii)
Objects of nonradioactive material extemally contaminated with radioactive t
3 material, provided that the radioactive material is not readily dispersible and the E
3 surface contamination, when averaged over an area of 1 square meter, does I
3 not exceed 0.0001 millicurie (220,000 disintegrations per minute) per square I
3 centimeter of radionuclides for which the A quantity in Appendix A of I
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10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie 3
3 (2,200,000 disintegrations per minute) per square centimeter for other
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radionuclides.
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3 (2) Maximum quantity of material per package i
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3 Greater than Type A quantity of radioactive material which may contain fissile material I
3 provided the fissile material does not exceed the limits in 10 CFR 971.53. The decay heat.
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load is limited to g watts.
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6.
(a)
For any package containing water and/or organic substances which could radiolytically I
3 generate combustible gases, determination must be made by tests and measurements or by I
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analysis of a representative package such that the following criteria are met over a period of I
time that is twice the expected shipment time:
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3 (1) The hydrogen generated must be limited to a molar quantity that would be no more than i
3 5% by volume (or equivalent limits for other inflammable gases) of the secondary i
i container gas void if present at STP (i.e., no more than 0.063 g-moles /ft* at 14.7 psia and i
1 70*F); or 1
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(2) The secondary container and cask cavity must be inerted with a diluent to assure that i
3 hydrogen must be limited to 5% by volume in those portions of the package which could I
3 have hydrogen greater than 5%.
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For any package delivered to a carrier for transport, the secondary container must be prepared l
for shipment in the same manner in which determination for gas generation is made. Shipment 3
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period begins when the package is prepared (sealed) and must be completed within twice the j
expected shipment time.
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(b)
For any package shipped within 10 days of preparation, or within 10 days after venting of i
i drums or other secondary containers, the determination in (a) above need not be made, and i
3 the time restriction in (a) above does not apply.
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7.
Maximum gross weight of the contents, secondary containers, shoring, and optional shield insert is I
I limited to 20,000 pounds.
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8.
Except for close fitting contents, shoring must be placed between secondary containers and the cask l
cavity to minimize movement during normal conditions of transport.
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The lid and the shield plug lifting lugs must not be used for lifting the cask, and must be covered in i
e 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 I
B order to provide a method to leak test the package.
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i. Page 4 - Certificate No. 9176 - Revision No.15 - Docket No. 71-9176 i
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1 11.
In addition to the requirements of Subpart G of 10 CFR Part 71:
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(a)
Prior to each shipment, the packaging Neoprene lid seals if opened (or if security seal is L
1 broken), must be inspected. The seals must be replaced with new seals if inspection shows I
1 any defects or every twelve (12) months, which ever occur first. Cavity drain and vent lines I
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must be sealed with appropriate sealant applied to the pipe plug threads.
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(b)
Each packaging must meet the Acceptance Tests and Maintenance Program of:
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Model Nos. NUPAC 14/210L and NUPAC 14/210H l
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1 Section 8.0 of the application.
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Model No. CNSI 14-215H Series A '
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Chem-Nuclear Systems, Inc., Document No. CNSI 9176-S1, Rev.1, Section 4.0.
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Model Nos. LM 14-195L and LN 14-195H I
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l LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and WM-013, Rev.F.
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(c)-
The package shall be prepared for shipment and operated in accordance with the Operating i
1 Procedures of:
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Model Nos. NUPAC 14/210L and NUPAC 14/210H I
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Section 7.0 of the application. -
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Model No. CNSI 14-215H Series A l
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3 Chem-Nuclear Systems, Inc., Document No. CNSI 9176-S1, Rev.1, Section 3.0.
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Model Nos. LN 14-195L and LN 14-195H -
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1 LN Technologies Corporation Procedures WM-025, Rev. C.
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12.
The ratchet binders on the cask lid must be torqued to 100i10 ft-lb.
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13.
The cask body and each cask lid must be marked in accordance with 10 CFR $71.85(c).
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-14.
The packages authorized by this certificate must be transported on a motor vehicle, railroad car, j
aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the l
licensee.
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i 15.
The packages authorized by this certificate are hereby approved for use under the general license i
3 provisions of 10 CFR 971.12.
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- 16. ' Expiration date: April 1,1999. This certificate is not renewable.
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> Page 5 - Certificate No. 9176 - Revision No.15 - Docket No. 71-9176 L
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REFERENCES r
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N Nuclear Packaging, Inc., application dated February 29,1988.
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Supplements dated: April 19,1988; March 1,1993; and August 5,1997.
l Pacific Nuclear supplements dated: October 23 and December 2 and 21,1992.
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Chem-Nuclear Systems, Inc., supplements dated: February 19 and April 21,1988; January 18, and April 29, i
p 1993; and January 29,1996 r
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B NUS supplement dated: November 22,1985.
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LN Technologies Corporation supplement dated: February 16,1988.
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1 Scientific Ecology Group, Inc., supplement dated: April 30,1993.
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ATG Nuclear Services L.L.C., supplement dated: December 1,1998 l
p FOR THE U.S. NUCL' EAR REGULATORY COMMISSION i
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B Cass R. Chappell, Chief I
b Package Certification Section i
B Spent Fuel Project Office I
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Office of Nuclear Material Safety l
and Safeguards l
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p Date: March 11, 1999 f
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4 UNITED STATES i
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NUCLEAR REGULATORY COMMISSION i
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APPROVAL RECORD Model No.14/210L, NUPAC 14/210H, CNSI 14-215H Series A, LN 14-195L, and LN 14-195H Packages Certificate of Compliance No. 9176 Revision No.15 By letter dated December 1,1998, ATG Nuclear Services L.LC., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9176 for the Model Nos.14/210L, NUPAC 14/210H, CNSI 14-215H Series A, LN 14-195L, and LN 14-195H Packages be changed from Molten Metal Technology, Inc., to ATG Nuclear Services L.LC.
ATG Nuclear Services LL.C., has accepted responsibili;y for the completeness and accuracy of the statements and representations of the previous certificate holder. ATG Nuclear Services L.LC., 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 LL.C., has been issued Quality Assurance Program Approval for j
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.
i 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 Spent Fuel Prnject Office i
Office of Nuclear Material Safety and Safeguards i
Date: March 11, 1999 L