ML20211D478

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Certificate of Compliance 9159,rev 8,for Models Nupac 14/190L,NUPAC 14/190M,NUPAC 14/190H,LN 14-170L, Ln 14-170M & Ln 14-170H
ML20211D478
Person / Time
Site: 07109159
Issue date: 09/17/1997
From: Chappell C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20211D476 List:
References
NUDOCS 9709290147
Download: ML20211D478 (6)
v • d • e


Text

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h '* " FOR RADIOACTIVE MATER 14LS PACKAGES Nl I 1 a Cf RTlHCATE,NUMBLR - b. RLvislON NUMBLR e PACKAGE IDENTIHCATION NUMBER d. PAGE NUMBER e. Tot AL NUMBER PAGLS 9159 8 USA /9159/A 1 5 y  ;

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s This ccmficate is inued to certify that the packaging and contents described in Itern 5 below, rnects the apphcable safety standards set forth in Title 10 Nl Code of Federal Regulations, Part 71,' Packaging and Transportation of Radioactive Material

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b. This certificate does not teheve the consignor from comphance with any requirement of the regulatons of the U.s. Department of Transportation or other N

I fg apphcable regulatory agencies, including the gowrnment of any country through or into which tne package will be transported. N ,

k Nl 1 THis CERTIHCATE 15 ISSUED ON THE 8 A515 OF A S Af1TY AN ALYS15 REPORT OF THE PACKAGE DESIGN OR APPUCATION I

a ISSUED 10(Name set A4 hens k h b TITLE AND IDENTIMCATION OF REPORT OR APPLICATION.  ;

I Molten Metal Technology, Inc. NUPAC application dated February 29, 1988, l p! 1009 Commerce Park Drive as supplemented. ,

p l Oak Ridge, TN 37830 g

e. IXEKET NtHBER 4 CONDITIONS g

, This certificate is conditional upon fulfilhng the requirements of 10 CFR Par 171, as apphcable, and the conditions specified below. g N3 g g

Bj E (a) Packaging I Model Nos.: NUPAC 14/190L, NVPAC 14/190M, NUPAC 14/190H, LN 14-170L, I si I (1)

LN 14-170M, and LN 14-170H N

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'l (2) Description N U

't Steel encased lead shielded casks for radioactive material. The casks are d Ei right circular cylinders with a 75.5-inch ID by 73.38-inch IH cavity. The E S

i walls of the casks contain a lead thickness ranging from 1.25 to 2.63 inches d Ni encased in 0.38-inch thick inner steel shell and 0.88-inch thick outer steel W s shell. The top cover and. cask bottom are made up of two steel plates ranging i i

  1. i in thickness from 2.0 to 3.0-inches. . The primary cask lid is secured to the d si cylindrical cask body by eight,1-1/4-inch rachet binders. An optional (

si secondary lid is centered in the primary lid and is secured to the primary 4 9 lid with eight, 3/4-inch studs and nuts. Each lid is provided with a E Nlj Neoprene gasket seal. The casks may be provided with an optional 12-gauge d Bj stainless steel liner (seal welded along all edges), an optional lid vent q sj line with pipe plug, and an optional 3/4-inch drain line and pipe plug. The g Bi casks are provided with four equally spaced lifting / tie-down devices. The y si primary lid is provided with three lifting lugs and the optional secondary g Bj lid is provided with one lifting lug. The casks gross weights range from q

% 49,200 to 65,200 pounds. g

$ 4 Rj Model OD, Lead Tk, Top Tk, Bottom,Tk, Gross Wt, g

% Number inches inches inches inches counds g NUPAC 14/190L, LN 14-170L 80.5 1.25 4.0 4.0 49,200 g

% NVPAC 14/190M, LN 14-170M 81.5 1.75 4.0 4.0 53,500 g NVPAC 14/190H, LN 14-170H 83.25 2.63 5.0 5.0 65,200 g E

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u! 5. (3) Drawings r B (a) r D'

p Model Nos. NVPAC 14/190L. NVPAC 14/190M. and NUPAC 14/190H [ ,

Dl' p The packages are fabricated in accordance with Nuclear Packaging, Inc.

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e Drawing No. X-20-307-SNP, Sheets 1, 2 and 3, Revision No. A. g Bl p Model Nos. LN 14-170L. LN 14-170M. and LN 14-170H E

g 9l! The packages are fabricated in accordance with LN Technologies Corporation Drawing No. 5025-M-2005: Sheets 1 and 2, Revision No. O.

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(b) Contents g Il p , . , ,

I (1) Type and form of. material g F

h Dewatered, solid, or solidified waste, or activated solid components, in I p secondary containers, and limited to the following: ,

E (i) Materials in which the radioactivity'is essentially uniformly hl distributed and in which the estimated average concentration per E g

y gram of contents does not exceed: [

0.0001 millicurie of radionuclides for which the A2 quantity in I f Appendix-A of 10 CFR Part 71 is not more than 0.05 curie; E

l q quantity in E f

gl 0.005 millicurie of radionuclides for which Appendix A of 10 CFR Part 71 is more than 0.05 cur the A,ie, but not E l more than 1 curie; or 0.3 millicurie of radionuclides for which the A q d fl Appendix A of 10 CFR Part 71 is more than 1 curie.uantity E

' E Objects of nonradioactive material externally contaminated with a

' h) (ii) radioactive material, provided that the radioactive material is W

'1I not readily dispersible and the surface contamination, when E

% averaged over an area of I square meter, does not exceed E E) l 0.0001 millicurie (220,000 disintegrations per minute) per square W

  1. i centimeter of radionuclides for which the A 2 quantity in d k

E Appendix A of 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per d

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square centimeter for other radionuclides. g

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  1. (2) Maximum quantity a material per package

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Greater than Type A quantity of radioactive material which may contain d fissile material provided the fissile material does not exceed the limits g 4 in 10 CFR 571.53. The decay heat load is limited to 7 watts for the d Model Nos. NUPAC 14/190L, NUPAC 14/190M, LN 14-170L, and LN 14-170M; and g

  1. I 25 watts for the Model Nos. NVPAC 14/190H and LN 14-170H casks. pj f  ! .

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  • ULATORY COMMISS60N pj gcronusisA 8 r D 71-9159 r RlPage3-CertificateNo.9359-RevisionNo.8-DocketNo l

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6. (a) For any package containing water and/or organic substances wHich could r 9 radiolytically generate combustible gases, determination must be made by g p,

4 tests and measurements or by analysis of a representative package such that g Dj the following criteria are met over a period of time that is twice the r p expected shipment time: t l

>M (1) The hydrogen generated must be limited to a molar quantity that would be g no more than 5% by volume (or equivalent limits for other inflammable r gases) of the secondary coptainer gas void if present at STP (i.e., no g more than 0.063 g-moles /ft at 14.7 psia and 70*F); or r

  1. I p! (2) The secondary container and cask cavity must be inerted with a diluent to ,

p l assure that oxygen must be limited to 5% by volume in those portions of ,

p the package which could have hydrogen greater than 5%. ,

1 p For any package delivered to a carrier for transport, the secondary container r gl must be prepared for shipment in the same manner in which determination for I 4

1 gas generation is made. Shipment period begins when the package is prepared [

g (sealed) and must be completed within twice the expected shipment time.

hl (b) For any package shipped within 10 days of. preparation, or within 10 days after venting of drums or other secondary containers, the determination in I

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(a) above need not be made, and.the time restriction in (a) above does not t m 1y.

ql r gl 7. Maximum gross weight of the contents, secondary containers, and shoring is limited r g

to 20,000 pounds, I

8. Except for close fitting contents, shoring must be placed between secondary lli containers and the cask cavity to minimize movemtnt during normal conditions of r g I transport.

The lid and the shield plug lifting lugs must not be used for lifting the cask, and I f I 9.

must be covered in t'.4nsit. I E I l

10. The cask must be provided with either (or both) a drain line or a lid vent line as I h shown in the drawing in order to provide a method to leak test the package. I g 0 i

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$, 11. In addition to the requirements of Subpart G of 10 CFR Part 71: E f

  1. (a) Prior to each shi> ment, the packaging Neoprene lid seals if opened (or if 6

d security seal is aroken), must be inspected. The seals must be replaced with E

  1. , new seals if inspection shows any defects or every twelve (12) months, which I
  1. ever occurs first. Cavity drain and vent lines must be sealed with t

%; appropriate sealant applied to the pipe plug threads. t E

Each packaging must meet the Acceptance Tests and Maintenance Program of: q 4l.

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s' Model Nos. NVPAC 14/190L. NVPAC 14/190M and NVPAC 14/190H 9' E q' Section 8.0 of the application. g

( Model Nos. LN 14-170L. LN 14-170M and LN 14-170H q

  1. lI LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and W

g 9 WM-013, Rev. F. g 4 .

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(c) The package shall be prepared for shipment and operated in accordance with g g

l the Operating Procedures of: g d g Model Nos. NVPAC 14/190L. NUPAC 14/190M and NUPAC 14/190H g

{a e q Section 7.0 of the application, g Model Nos. LN 14-170L. LN 14-170M and LN 14-170H i LN Technologies Corporation Procedures WM-025, Rev. C. l

12. The ratchet binders on the cask lid must be torqued to 100110 ft-lb. l I

!! 13. The cask body and each cask lid must be n1arked in accordance with 10 CFR 671.85(c).

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! 14. The packages authorized by this certificate must be transported on a motor vehicle, h railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel I 41 assigned for the sole use of the licensee. U l

  • i 15. The packages authorized by this certificate are hereby approved for use under the (8

% general license provisions of 10 CFR 671.12.

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16. Expiration date: April 1, 1999. This certificate is not renewable. I si E i 5 E l
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D; E p! N D' REFERENCES E

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.E' p, Nuclear Packaging, Inc., application dated February 29, 1988. g B, N pl Supplements dated: April 19, 1988; February 16, 1993; and August 5, 1997. l g D E November 22, 1985.

pf NUS supplement dated:

g B E p! LN Technologies Corporation supplement dated: February 16, 1988. g B' d p Scientific Ecology Group, Inc., supplement dated: April 30, 1993 g Bj E h FOR THE U.S. NUCLEAR REGULATORY COMMISSION l f Cass R. Chappell, Chief Package Certification Section l U

Spent Fuel Project Office l!i l Office of Nuclear Material Safety 8 and Safeguards l

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Date: septmier 17. 1997 lI l

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\...../ 4 APPROVAL RECORD Model Nos. NUPAC 14/190L, NUPAC 14/190M, NUPAC 14/190H, LN 14-170L, LN 14-170M, and LN 14-170H Certificate of Compliance No. 9159 Revision No. 8 By letter dated August 5,1997, VECTRA Technologies, Inc., and Molten Metal Technology, Inc., requesteo '. hat the certificate holder for Certificate of Compliance No. 9159 for the Model No. NUPAC 14/190L, NUPAC 14/190M, NUPAC 14/190H, LN 14-170L, LN 14-170M, and LN 14-170H packages be changed from VECTRA Technologies, Inc., to Molten Metal Technology, Inc. Molten Metal Technology, Inc., has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. Molten Metal Technology, Inc., 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 571.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 671.91(c) for the package designs will be maintained at their document control center at 1556 Bear Creek Road, Oak Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71.

The Certificate has been revised to show Holten Metal Technology, Inc., 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: emt . 17. 1997

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