ML20207J879

Certificate of Compliance 9177,rev 9,for Model Nupac 10/140 & Ln 10-135A

ML20207J879
Person / Time
Site:	07109177
Issue date:	03/11/1999
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20207J869	List: ML20207J866 ML20207J879
References
NUDOCS 9903160424
Download: ML20207J879 (6)

Text

g. NRC FORM 618 u.s. NUCLEAR R'iluLAToRY COMM!sloN J ow CERTIFICATE OF COMPLIANCE E Ej wcmn FOR RADIOACTIVE MATERIALS PACKAGES Nl s

't. a CERTIMCATE NUMBER b. REVISION NUMBER Er

c. PACKAGE IDENTIRCAT10N NUMBER d PAGE NUMBER e TOTAt. NUMBER PAGLS n 9177 9 USA /9177/A 1 5

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2. PREAMBLE l kl l a. This certificate is issued to certify that the packaging and contents described in Item 5 below. meets the applicable safety standards set fonh in Titi- 10. k yj- Code of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Material." k ll E{ b. This certificate does not reheve the consanor from comphance with any requirernent of the regulations of the U.S. Department of Transponation or other kl sj spphcable regulatory agencies,includmg the government of any country through or into which the package will be transponed.

5 kl d 3. THIS CERTIMCATE IS ISSUED ON THE B ASIS OF A $ AFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION kI I 4

sg a ISSUED TOINamt and AdhessJ b TITLE ANDIDENT1MCATION OF REPORT OR APPLICATION.

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ATG Nuclear Services L.L.C. er NUPAC application dated February 29,1988,

@l 669 Emory Valley Road g

g Oak Ridge, TN 37830 as supplemented. g ll g g s E g, c. DOCKET uuMBER 71 9177 g

); 4 CONDmONS g

) This cenificate is conditional upon fulfilling the requirements of 10 CrR Pan 71. as applicable, and the conditions specified below. g 5, 5 E i

(a) Packaging E

$q 1 (1) Model Nos.: NUPAC 10/140 and LN 10-135A E

j (2) Description E g

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gl Steel encased lead shielded casks for radioactive material. The casks are right circular g hg cylinders with a 66.0-inch ID by 73.0-inch IH cavity. The walls of the casks contain a lead g s; thickness of 2.75 inches encased in 0.50-inch thick inner steel shell and 1.13-inch thick outer E si steel shell. The top cover and cask bottom are made up of two steel plates ranging in E

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thickness from 2.0 to 3.0 inches. The primary cask lid is secured to the cylindrical cask body E

by eight,1-1/4-inch rachet binders. An optional secondary lid is centered in the primary lid and E El is secured to the primary lid with eight,3/4-inch studs and nuts. Each lid is provided with a U

$1 Neoprene gasket seal. The casks may be provided with an optional 12-gauge stainless steel

! liner (seal welded along all edges), an optional lid vent line with pipe plug, and an optional 3/4-

Q inch drain line and pipe plug. The casks are provided with four equally spaced lifthg/ tie-down g

g ji devices. The primary lid is provided with three lifting lugs and the optional secondary lid is g gl provided with one lifting lug. Each cask has a gross weight of 56,500 pounds. g 2 E M (3) Drawings (

N; E sj Model No. NUPAC 10/140 E s E

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The package is fabricated in accordance with Nuclear Packaging, Inc., Drawing No. X-20-308- E 1 SNP, Sheets 1,2, and 3, Rev. A. E B

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El Model No. LN 10-135A r al g il The package is fabricated m accordance with LN Technologies Corporation Drawing No. 5025- g M-2005: Sheets 1 and 2, Rev. O. (

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I DI , Page 2 - Certificat] No. 9177 - R:iviahn N3. 9 - Docket No. 71-9177 1 j I

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p 5. (b) Contents y b; '

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e (1) Type and form of material 3 i B,

j I i 5; Dewatered, solid, or solidified waste, or activated solid components, in secondary I Ij containers, and limited to the following: I- I D

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{ (i) Materials in which the radioactivity is essentially uniformly distributed and in I gl which the estimated average concentration per gram of contents does not g exceed: [

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D g-g 0.0001 millicurie of radionuclides for which the A, quantity in Appendix A of g p 10 CFR Part 71 is not more than 0.05 curie; g 1 B,

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B{ 0.005 millicurie of radionuclides for which the A, quantity in Appendix A of 3:

D 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or 3

1. j 3-I 0.3 millicurie of radionuclides for which the A, quantity in Appendix A of I; Il 10 CFR Part 71 is more than 1 curie. I B

j i I (ii) Objects of nonradioactive material extemally contaminated with radioactive I l

I g material, provided that the radioactive material is not readily dispersible and the  ;

y surface contamination, when averaged over an area of 1 square meter, does , l pl not exceed 0.0001 millicurie (220,000 disintegrations per minute) per square  :

g p! centimeter of radionuclides for which the A, quantity in Appendix A of l g

t 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie g )

5 (2,200,000 dicintegrations per minute) per square centimeter for other g b; radionuclides.

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(2) Maximum quantity of material per package I I

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fl Greater than Type A quantity of radioactive material which may contain fissile material I '

y provided the fissile material does not exceed the limits in 10 CFR $71.53. The decay heat I gl load is limited to 24 watts.

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, pl . Page 3 - Certificata No. 9177 - R; vision No. 9 - Dock:t No. 71 9177 g 5 E D,, t

% 6. (a) For any package containing water and/or organic substances which could radiolytically generate t Tj combustible gases, determination must be made by tests and measurements or by analysis of a t

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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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(1) The hydrogen generated must be limited to a molar quantity that would be no more than lIf 5% by volume (or equivalent limits for other inflammable gases) of the secondary g ,

si container gas void if present at STP (i.e., no more than 0.063 g-moles /ft' at 14.7 psia and g 70*F); or g

@! t (2) The secondary container and cask cavity must be inerted with a diluent to assure that Bl p

i; oxygen must be limited to 5% by volume in those portions of the package which could E

I B have hydrogen greater than 5%. E R t Bj For any package delivered to a carrier for transport, the secondary container must be prepared t i for shipment in the same manner in which determination for gas generation is made. Shipment 8 I N{

I I l period begins when the package is prepared (sealed) and must be completed within twice the expected shipment time.

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(b) For any package shipped within 10 days of preparation, or within 10 days after venting of drums or g l

@l g other secondary containers, the determination in (a) above need not be made, and the time g ,

y restriction in (a) above does not apply. g ,

i t B 7. Maximum gross weight of the contents, secondary containers, and shoring is limited to 15,000 pounds. t B E i 8. Except for close fitting contents, shoring must be placed between secondary containers and the cask 8

$j cavity to minimize movement during normal conditions of transport. I  ;

pj t h9. The lid and the shield plug lifting lugs must not be used for lifting the cask, and must be covered in transit.

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5 The cask must be provided with either (or both) a drain line or a lid vent line as shown in the drawing in order to provide a method to leak test the package. fl g

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~ ^ ^^~ ~ ehTcaaldREluLAToRY CioMMISSION pI , Page 4 - Certificata No. 9177 - RIvision No. 9 - Dock:t Ns. 71-9177 [  :

• Dj 7 b r-Dl 11. In addition to the requirements of Subpart G of 10 CFR Part 71: E-Dj E-Bj I:

(a) Prior to each shipment, the packaging Neoprene lid seals if opened (or if security seal is broken),

I t must be inspected. The seals must be replaced with new seals if inspection shows any defects or I!

5{ every twelve (12) months, which ever occurs first. Cavity drain and vent lines must be sealed with Il appropriate sealant applied to the pipe plug threads. I l

,j d p j (b) Each packaging must meet the Acceptance Tests and Maintenance Program of: g; 9 ti gi Model No. NUPAC 10/140 g Bf Section 8.0 of the application.

E bj t Bj E D Model No. LN 10-135A E D E b LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and WM-013, I E

Rev.F. I B E (c) The package shall be prepared for shipment and operated in accordance vi h the Operating I gl Procedures of: g Model No. NUPAC 10/140 g B; I p Section 7.0 of the application. t b I B Model No. LN 10-135A E B E D LN Technologies Corporation Procedures WM-025, Rev. C. I B E

12. The ratchet binders on the cask lid must be torqued to 100*10 ft-lb. I l

h 13. The cask body and each cask lid must be marked in accordance with 10 CFR $71.85(c).

l B E p 14. The packages authorized by this certificate must be transported on a motor vehicle, railroad car, g g aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the g b licensee. s-B R b 15. The packages authorized by this certificate are hereby approved for use under the general license E D provisions of 10 CFR $71.12. I h B I 16. Expiration date: April 1,1999. This certificate is not renewable. I D I

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, Page 5 - Certificat] No. 91. , - R: vision N3. 9 - Docket No. 71-9177 fEl l

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REFERENCES gl )

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Nuclear PacRaging Inc application dated February 291988.

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Si E si Supplements dated: April 19,1988; February 16,1993; and August 5,1997. N!

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N i NUS supplement dated: November 22,1985. I a

e j LN Technologies Corporation supplement dated: February 16,1988.

gl 4l s q 3 Scientific Ecology Group, Inc. supplement dated: April 30,1993. gl 9 .

El ATG Nuclear Services L.L.C. supplement dated: December 1,1998. q d ll l l

FOR THE U.S. NUCLEAR REGULATORY COMMISSION El' 0; .

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Cass R. Chappell, hief Package Certification Section f g

i Spent Fuel Project Office g p- Office of Nuclear Material Safety q s and Safeguards y 5

I s I s Date: March 11,1999 g 9{ N Blj N sj u sj N sj d B

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APPROVAL RECORD Model No. NUPAC 10/140 and LN 10-135A Packages Certificate of Compliance No. 9177 Revision No. 9

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By letter dated December 1,1998, ATG Nuclear Services L.L.C., and Molten Metal Technology, i Inc., requested that the certificate holder for Certificate of Compliance No. 9177 for the Model l No. NUPAC 10/140 and LN 10-135A 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 i the completeness and accuracy of the statements and representations of the previous ceriificate i holder. ATG Nuclear Services L.L.C., will be responsible for maintenance of the certificate, the l safety analysis report for the package designs, and the quality assurance records in accordance with 10 CFR 971.91(c). ATG Nuclear Services L.L.C., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0876. e Jer Subpart H of 10 CFR l Part 71.

The Certificate has been revised to show ATG Nuclear Services L.LC., as certificate holder.

These changes do not affect the ability of the packages to meet the requirements of 10 CFR Part 71. l l

Cass R. Chappell, Chief Package Certification Section i Spent Fuel Project Office  !

Office of Nuclear Material Safety and Safeguards ]

j Date: March 11,1999 i

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