ML20211A871

Certificate of Compliance 9177,rev 8,for Model Nupac 10/140 & Ln 10-135A Packages

ML20211A871
Person / Time
Site:	07109177
Issue date:	09/12/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20211A869	List: ML20211A861 ML20211A871
References
NUDOCS 9709240427
Download: ML20211A871 (6)

Text

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"" CERTIFICATE OF COMPLIANCE i l FOR RADIDACTIVE MATERIALS PACKAGES gI 1.a ClRTillCATL NUMBLR = tt REYl510N NUMBE R < PACA AOLIDENTinCATION NUMhl R d PAGE NUMalLR e.101 AL NUMBLR PAGES i g

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l Nl 2 PREAMBLE '

I a This cemficate is issued to certify that the packaging and contents desenbed in item 5 telos meets the apphcable safety standards set forth in Title 10. N

${4 Code of Iederal kegulations, Pan 71 TacLaging and Transportation of Radioactne Material?

b. This cemficate does not rehese the consignar from comphance with any requirernent of the regulations of the U.s. Departrnent of Transpanation or other N l

Ng apphcable regulatory agencies, including the gosernrnent of any country through or into which the package will be transported. N I 1 TH15 CERTIFICATE 15155ULD ON THE B A515 OF A SAFTTY AN ALY51$ REPORT OF THE PACAAGE DESIGN Ok APPLICA a 155UED TO f %mt sad 4ddirad b 11111 AND IDENT10 CATION OF Rf PORT Of APPLICATION. N h{

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Molten Metal Technology, Inc.

1009 Commerce Park Drive NUPAC application dated February 29, 1988, as supplemented. f Oak Ridge, TN 37830 ,

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s.DoCArtNUuBtR 71-9177 g 4 CONDITIONS ~~ - ~ ~ ~

pj g T)us cemficate is conditional upon ful6thng the requirements of 10 CTR Pan 71 as applicable, and the conditions spectfled below. y c Nj S M f (a) Packaging l

(1) Model Nos.: NUPAC 10/140 and LN 10-135A I (2) Description

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

right circular cylinders with a 66.0-inch ID by 73.0-inch IH cavity. The d t walls of the casks contain a lead thickness of 2.75 inches encased in 0.50- E I

i inch thick inner steel shell and 1.13-inch thick outer steel shell. The top d

1. j cover and cask bottom are made up of-two steel plates ranging in thickness N

1. j from 2.0 to 3.0 inches. The )rimary cask lid is secured to t,he cylindrical E 6 :ask body by eight, 1-1/4-inci rachet binders. An optional secondary lid is 4

% centered in the primary lid and is secured to the primary lid with eight, 4 bj 3/4-inch studs and nuts.. Each lid is provided wit 1 a Neoprene gasket seal. W 8l The casks may be provided with an optional 12-gauge stainiess steel liner q (seal welded along all edges), an optional lid vent line with pipe plug, and W an optional 3/4-inch drain line and pipe plug. The casks are provided with q

>l four equally snaced lifting / tie-down devices. The primary lid is provided

> a with three lifting lugs and the optional secondary lid is provided with one g B lifting lug. Each cask'has a gross weight of 56,500 pounds.. p 4

Dj (3) Drawings q b

g B Model No. NUPAC 10/140 g Nj E

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

% 4 R Model No. LN 10-135A '

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%j W Dj The package is fabricated in accordance with LN Technologies Corporation g bj Drawing 5'o. 5025-M-2005: Sheets 1 and 2, Rev. O. g

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[l{- Page 2 ' Certificate No. 9177 - Revision No. 8 - Docket No. 71-9177 I

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5. (b) Contents r L ,

(1) Type and form of material r r

Dewatered, solid, or solidified waste, or activated solid components, in t 1[ secondarf, containers, and limited to the following: I I

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(1) Materials in which the radioactivity is essentially uniformly t 1l distributed and in which the estimated average concentration per I p gram of contents does not exceed: I

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a! 0.0001 millicurie of radionuclides for which the A qu ntity in i Appendix A of 10 CFR Part 71 is not more than 0.05, curie; ll 6

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> 0.005 millicurie of radionuclides for which the A quantity in r Appendix A of 10 CFR Part 71 is more than 0.05 cu,rie, but not

)) more than 1 curie; or i g

- 0.3 millicurie of radionuclides for which the A quantity in

> AppendixAof10CFRPart71ismorethanIcurie, t e ,

! (ii) Objects of nonradioactive material externally contaminated with g 7 radioactive material, provided that the radioactive material is

-p net readily dispersible and the surface contamination, when r p

averaged over an area of I square meter, does not exceed r

[)l . 0.0001 millicurie (220,000 disintegrations per minute) per square centimeter of radionuclides for which the A quantity in p

)li Appendix A of 10 CFR Part 71 is not more th,an 0.05 curie, or p g

y 0.001 millicurie (2,200,000 disintegrations per minute) per p square-centimeter for other radionuclides. ,

, 'i _ (2) Maximum' quantity of material per package I

GreaterthanTy$eAquantityofradioactivematerialwhichmaycontain l fissile materia provided the fissile raterial does not exceed the limits [

j,i in 10 CFR 571.53. The decay heat load is limited to 24 watts. r 1

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. Ei l Dj 6. (a) For any package containing water and/or organic substances which could E

! D; radiolytically generate combustible gases, determination must be made by E B tests and measurements or by analysis cf a representative package such that E b;j the following criteria are met over a period of time that is twice the E b

i expected shipment time: E Dj E B, (1) The hydrogen generated must be limited to a molar quantity that would be E B; no more than 5% by volume (or equivalent limits for other inflammable E D

D, gases)ofthesecondarycoptainergasvoidifpresentatSTP(i.e.,no E j more than 0.063 g-moles /ft at 14.7 psia and 70*F); or E 9, E b: (2) The secondary cortainer and cask cavity must be inerted with a diluent to E D assure that oxygen must be limited to 5% by volume in those portions of E B the package which could have hydrogen greater than 5%. E Bj E D

l For any package delivered to a carrier for transport, the seconaary container E p must be prepared for shipment in the same manner in which determination for 4 l

gas generation is made. Shipment period begins when the package is prepared E p!

p (sealed) and must be completed within twice the expected shipment time. E D' E I

D (b) For any package shipped within 10 days of preparation, or within 10 days a pI after venting of drums or other secondary containers, the determination in E (a) above need not be made, and the time restriction in (a) above does not 4 p{l p apply, g b E l

7. Maximum gross weight of the contents, secondary containars, and shoring is limited g pl p to 15,000 pounds, g

.i 8. Except for close fitting contents, shoring must be placed between secondary E p! g p containers and the cask cavity to minimize movement during normal conditions of g g transport. g h 9. The lid and the shield plug lifting lugs must not be used for lifting tha cask, and l g must be covered in transit. g li10. The cask must be provided with either (or both) a drain line or a lid vent line as g

i shown in the drawing in order to provide a method to leak test the package, l y

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> age 4 - Certificate No. 9177 - Revision No. 8 - Docket No. 71-9177 I bj E pp , , u

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

(a) Prior to each shipment, the packaging Neoprene lid seals if o)ened (or if a security seal is broken), must be inspected. The seals must se replaced with 8 Dj new seals if inspection shows any defects or every twelve (12) months, which I Dj ever occurs first. Cavity drain and vent lines must be sealed with 4 l b; appropriate sealant applied to the pipe plug threads. E I bp '

W D (b) Each packaging must meet the Acceptance Tests and Maintenance Program of: E 9

B; E Dj Model No. NUPAC 10/140 4 >

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% Section 8.0 of the application. I fj d B_ Model No. LN 10-135A q

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tl LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and q t WM-013, Rev. F. E u

tl e_ (c) The package shall be prepared for shipment and operated in accordance with the Operating Procedures of:

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3 Section 7.0 of the application, g 1

Q 3 Model No. LN 10-135A g 4

1. l 3 LN Technologies Corporation Procedures WM-025, Rev. C. g R

3 12. The ratchet binders on the cask lid must be torqued to 100110 ft-lb. g 3

4 3! 13. The cask body and each cask lid must be marked in accordance with 10 CFR 571.85(c). g

14. The packages Luthorized by this certificate must be transported on a motor vehicle,

.g railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel l g

13 1 assigned for the sole use of the licensee.

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'1 15. The packages authorized by this certificate are hereby approved for use under the 3

3 1 general license provisions of 10 CFR 571.12. l g

lI 16. Expiration date: April 1, 1999. This certificate is not renewable. l

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. E 6 REFERMCIS N D E I

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.fNuclearPackaging,Inc.applicationdatedFebruary B 29, 1988. E I Bf Supplements dated: April 19, 1988; February 16, 1993; and August 5, 1997. l 4 e a b

blNUSsupplementdated: Novcmber 22, 1985, d N

1. LN Technologies Corporation supplement dated: February 16, 1988.

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blScientificEcologyGroup,Inc.,supplementdated: April 30, 1993. I N

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B- . u pl FOR THE U.S. NUCLEAR REGULATORY COMMISSION q D

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,l 5, Cass R. Chappell, C ief- -

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. g APPROVAL RECORD Model Nos. NUPAC 10/140 and LN 10-135A Certificate of Compliance No. 9177 Revision No. 8 By letter dated August 5,1997, VECTRA Techno1cgies, Inc., and Holten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9177 for the Model No NUPAC 10/140 and LN 10-135A packages be changed from VECTRA Technologies, Inc., to Molten Metal Technology, I m .

Molten Metal Technology, Inc., has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holdtr. 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 witt, 10 CFR 671.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 571.91(c) for the package designs will be maintained at their document control center at 1556 Bear Creek Road, Oak Ridge, Tennessee, Molten Metal Technclogy, Inc., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71.

Certificate of Compliance No. 9177, Revision No. 7, contained a typographical error in paragraph 5(b)(2). This error has been corrected in Revision No. 8.

The Certificate has been revised 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.

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Cass R. Chappell, ief ,

Package Certification Section Spat Fuel Project Office ,

Office of Nuclear Material Safety and Safeguards Date: Sept.12. 97

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