ML20211A854

Certificate of Compliance 9179,rev 8,for Model Nupac 6/100L, Nupac 6/100H,LN 6-80L & Ln 6-80H Packages

ML20211A854
Person / Time
Site:	07109179
Issue date:	09/12/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20211A852	List: ML20211A849 ML20211A854
References
NUDOCS 9709240420
Download: ML20211A854 (6)

Text

i wwwwwwwwwwwwwwwwwwwwwwwwwwwww wwwwwwwg_w_wwwww.g p NRc FORM 618 I is CERTIFICATE OF COMPLIANCE U.S. NUCLEAR RE!ULATORY c0MMISSION g ':

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- 1. a CERTIFICATE NUMBLR b REVISION NtMBER c. PACAAGE IDENT1f1 CAT 10N NtNBf R d PAGE NUlHbt'R e TOTALNUMBLR PAGE5 I 9179 8- 5 USA /9179/A 1 g 2 PRLAMBLE N

e. Thir certificate is issued to certify that the padaging and contents described in Itern 5 below, meets the applicable safety standards set forth in Title 10, N Og Code of Federal Regulations, Part 71," Packaging and Transportation of Radionetive Material

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b. This cemficate does not reheve the consignor from comphance with any requirement c.f the regulations of the U.SSepar' ment of Transportation or other N Ng appleable rerdatory agencies,includmg the government of an) country through or into which , package will be transported. I 3 THl$ Cf RTIFICATE 1515$UED ON DE B A515 OF A $ AlTTY AN ALYSIS REPORT OF TIE PACKAGE DESIGN OR APPLICA110N kl a ISSUED 10(%=r a=f A4fresil b TITLE ANDIDENTlf1 CATION OF REPORT OR APPLICATION , N

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l Holten Metal Technology, Inc. NUPAC application dated February 29, 1988, E g

pl 1009 Commerce Park Drive as supplemented. g p

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$ 4 CONDI110NS g g 1his cemficate is conditional upon fulfahng the requirements of 10 CFR Part 71, as applicable, and the conditions ,,recified irlow. g I 5.

• l (a) Packaging l

lI (1) Model Nos.: NUPAC 6/100L, NUPAC 6/100H, LN 6-80L,'and LN 6-80H I (2) Description U 8

1 Steel encased lead shielded casks for radioactive material. The casks are d

$ right circular cylinders with a 61.0-inch ID by 62.0-inch IH , cavity. The d

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E walls of the casks contain a lead thickness ranging from 2.43 to 3.56 inches 8 8

l encased in 0.50-inch thick inner steel shell and 1.13-inch thick outer steel N 1 shell. The top cover and cask bottom are made up of two steel plates ranging I

! in thickness from 2.0 to 3.0-inches. The primary cask lid is secured to the 1 8

1 cylindrical cask body by eight, 1-1/4-inch rachet binders. fi utional N

% secondary lid is centered in the primary lid and is, secured to tie primary a Dj lid with eight, 3/4-inch studs and nuts. Each lid is proviJed with a d D

Neoprene gasket seal. The casks may be provided with an optional 12-gauge d B

stainless steel liner (seal wolded along all edges), an optidnal lid vent E

% line with pipe plug, and an optional 3/4-inch drain line and pipe plug. The d

% casks are provided with four equally spaced lifting / tie-down devices. The d

% primary lid is provided with three lifting lugs and the optional secondary I b lid is provided with one lifting lug. The casks gross weights range from E B 42,900 to 53,900 pounds, d 8

b Hodel 00, Lead Tk, Top Tk, Bottom Tk, Gross Wt, I

% Number inches inches inches inches counds q

% NUPAC 6/100L, LN 6-80L 69.11 2.43 4.5 4.5 42,900 g Dj NUPAC 6/100H, LN 6-80H 71.37 3.56 6.0 6.0 53,900 g b; g

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5. (a) (3) Drawings I +

d l hodel Nos. NUPAC 6/100L- and NUPAC 6/1003 4 i I hj The packages are fabricated in accordance with Nuclear Packaging, Inc., d D; Drawing No. X-20-310-SNP, Sheets 1 and 2, Revision No. A. I R{ d Bi Model Nos. LN 6-80L and LN 6-80H E Dj d D, The packages are fabricated in accordance with LN Technologies I Rj Corporation Drawing No. 5025-M-2005, Sheets 1 and 2, Revision No, O. I B i i

B; (b) Contents ,

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(1) Type and form of material 9l:

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l Dewatered, solid, or solidified wastes, or activated solii components, a e in secondary containers, and limited to the following: g D d pl (i) Materials in which the radioactivity is essentially uniformly I a g distributed and in which the estimated average concentration per g

,- p gram of contents does not exceed: g b d g 0.0001 millicurie of radionuclides for which the A quantity in g p Appendix A of 10 CFR Part 71 is not more than 0.05, curie; g 1

b' d g! O.005 millicurie of radionuclides for which the A, quantity in g p- l Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not g p more than 1 curie;~or g

,I 0.3 millicurie of radionuclides Tor which the A, quantity in l g! Appendix A of 10 CFR Part 71 is more than 1 curie. ,

(ii) Objects of nonradioactive material externally contaminated with l

g radioactive material, provided that the radioactive .naterial is not readily dispersible aad the surface contamination, when 8 g-i averaged over an area of I square meter, does not exceed I g!

0.0001 millicurie (220,000 disintegrations per minute) per square U

,l centimeter of radionuclides for which the A quantity in I p 2 Appendix A of 10 CFR Part 71 is not more than 0.05 curie, or I l 0.001 millicurie (2,200,000 disintegrations per minute) per I g

square centimeter for other radionuclides.

[ (2) Maximum quantity of material per package U U

8 Greater than Type A quantity of radioactive material which may contain U E

fissile material provided the fissile materiti does not exceed the limits 8 U

l of 10 CFR 571.53. The decay heat load is limited to 9 watts for the U E

i Model Nos. NUPAC 6/100L and LN 6-80L casks and 61 watts for the Model f Nos. NUPAC 6/100H and LN 6-80H casks. ,

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6. (a) For any package containing water and/or organic substances which could N D

i radiolytically generate combustible gases, determination must be made by I h tests and measurements or by analysis of a representative package such that N

1. j the following criteria are met over a period of time that is twice the N

>i expected shipment time: 1 4;, 4 p, (1) The hydrogen generated must be limited to a molar quantity that would be 4 p

g no more tl1an 5% by volume (or equivalent limits for other inflammable a e, gases) of U,e secondary coptainer gas void if present at STP (i.e., no a b, more than 0.063 g-moles /ft at 1.4.7 psia and 70*F); or I q

L' (2) The w on% ry container and cask cavity must be inerted with a diluent to a assure that oxygen is limited to 5% by volume in those portions of the a package which could have hydrogen greater than 5%. p 4

For any package delivered to a carrier for transport, the secondary container a must be prepared for shipment in the same manner in which determination for e'! gas generation is made. Shipment aeriod begins when the package is prepared a

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p (sealed) and must be completed witiin twice the expected shipment time. g 4 N p

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

,1 after venting of drur s or other secondary coiltainers, the determination in y

,I (a) above need not be made, and the time restriction in (a) above does not g

,1 apply, y ll 7. Maximum gross weight of th: contents, secondary containers, and shoring is limited to 15,000 pounds, l gj y h 8. Except for close fitting contents, shoring must be placed between secondary

,1 r.ontainers and the cask cavity to minimize movement during normal conditions of l transport.

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9. The lid and the shield plug lifting lugs must not be used for lifting the cask, and I ll must be covend in transit.

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't 10. The cask mu;tt be provided with either (or both) a drain line or a lid vent line as 8 l shown in the drawing in order to provide a method to leak test the package.

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' % Page 4 - Certificate No. 9179 - Revision No. 8 - Docket No. 71-9179 8 t;

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% 11. In addition to the requirements of Subpart G of 10 CFP Part 71: . E

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% (a) Prior to each shi > ment, the packaging Neoprene lid seals if o)ened (or if I

% security seal is aroken), must be inspected. The seals must )e replaced with I

% new soals if inspection shows any defects or every twelve (12) months, which a

% over occurs first. Cavity drain and vent lines must be sealed with I

% appropriate sealant applied to the pipe plug threads. N

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% (b) Each packaging must meet the Acceptance Tests and Maintenance Program of: N

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% Model Nos. NUPAC 6/100L and NUPAC 6/100H E D E D Section 8.0 of the application. N

,l D Model Nos. LN 6-80L and 6-80H I p LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and W

$l WM-013. Rev. F. . I 4'. E p, (c) The package shall be prepared for shipment and operated in accordance with u the Operating Procedures of: g e'

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p Model Nos. NUPAC 6/100 and NUPAC 6/100H g Section 7.0 of the application.

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• ' Model Nos. LN 6-80L and LN 6-80H e I

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e q pl LN Technologies Corporation Procedures WM-025, Rev. C. g i

12. The ratchet binders on the cask lid must be torqued to 100110 ft-lbs. g

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p 13. The cask body and each cask lid must be marked in accordance with 10 CFR 571.85(c). g

14. The packages authorized by this certificate must be trans veted on a motor vehicle, 1

railroad car, aircraft, inland watercraft, or hold or dec( of a seagoing vessel l

,l assigned for the sole use of the licensee, y e y lI 15. The packages authorized by this certificate are hereby approved for use under the general license provisions of 10 CFR 671.12. l

, y ll 16. Expiration date: April 1, 1999. This certificate is not renewable.

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Page 5 - Certificate No. 9179 - Revision No. 8 - Docket No. 71-9179 4 ,

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1. i REFERENCES d 8, 9 a

Dl:Nuclear Packaging, Inc., application dated February 29, 1988.

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1. lSupplementsdated:

$ April 19 and 26, 1988; February 16, 1993; and August 5, 1997. l u l a I 9;

HUS supplement dated:November 22, 1985. g l

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>; Scientific Ecology Group, Inc., supplement cated: April 30, 1993, a l 4 i p LN Technologies Corporation supplement dated: February 16, 1988.

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E p FOR THE U.S. NUCLEAR REGULATORY COMMISSION q

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Cass R. Chappell, Chief g p!

p Package Certificatior. Section y e

l Spent Fuel Project Office g

,I Office of Nuclear Material Safety g ,

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and Safeguards g Date: Septadcr 12, 1997 l

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4 APPROVAL RECORD Model Nos. NUPAC 6/100L, NVPAC 6/100H, i LN 6-80L, and LN 6-80H Certificate of Compliance No. 9179 1

Revision No. 8 ,

By letter dated August 5, 1997, VECTRA Technologies,, Inc. and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9179 for the Model No. NVPAC 6/100L, NUPAC 6/100H, LN 6-80L,

and LN 6-80H 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 c' 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 $71.91(c) for the package designs will be maintained at their document control center at 1556 Bear Creek Road, Oak l Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality 4 Assurance Program Approvh1 for Radioactive Material Packages No. 0870, under I

Subpart H of 10 CFR Part 71.

! The Certificate has been revited to show Molten 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.

es44 Cass R. Chappell, Chief Package Certification Section Spent fuel Project Office Office of Nuclear Material Safety and Safeguards Date: Sept. 12, 97

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