ML20023C101

Certificate of Compliance 9901,Rev 1,for Model 120

ML20023C101
Person / Time
Site:	07109901
Issue date:	05/06/1983
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20023C100	List: ML20023C099 ML20023C101
References
NUDOCS 8305110035
Download: ML20023C101 (6)

Text

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Ferm NRC418 U.S. NUCLE AR REGULATORY COMMISSION i' 5 '

CERTIFICATE OF COMPLIANCE 10 C1 R 71 For Radioactive Materials Packages 1.fal Certificate Number 1.(b) Revision No.

1.(c) Package Identification No.

1.(d) Pages No. 1.(e) Total No. Pages 1

USA /9901/Bf IF' 1

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2. PRE AMBLE 2.fal This certificate is issued to satisty Sections 173.393a.173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations.(49 CFR 170180 and 14 CFR 103) and Sections MG--19-10a and 146-19--100 of the Department of.

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' Transportation Dangerous Cargoes Regulations (46 CFR 146 :149), as amended.

2.(b)

The packaging and contents described irtitem,5 below,, meets the safety standards se; forth in Subpart.C of Title 10, Code of...,

Federet Regulations,' fart 77, Packaging bf Radioactis MaterMt for Transport ah'd Trerisportation of' Radioactive Material' Under ',..

Certain Conditions."

2.(c)

This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)

Prepared by (Name and address):

3.(b)

Title and identification of report or application:

Westinghouse Hanford Company, Hanford Engineering Development Laboratory Hanford Engineering Development Report No. HEDL-TI 76-018, December 1976.

Laboratory P.O. Box 1970 3.(c)

Docket No.

71-9901 D 4. c h l a n d tfn QQ'it;9 This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71. as applicable, and the conditions specified in item 5 below.

5. O,escription of Packaging and Authorized Conten.ts, Model, Number,, Fissile, Class,Other conditions,pnd

References:

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~ ('a )Packaging (1)

Model No.: Model 120 (2) Descrip' tion A metal " birdcage" enclosing a steel containment vessel for unir-radiated fuel pins. The stainless steel containment vessel is a 12-inch diameter,154-inch long, Schedule 40 pipe. One end is closed with a 1.25-inch thick cover plate, secured with sixteen 1-inch diameter bolts to a welded neck-type flange. The containment seal is a Flexitallic type-spiral wound, stainless steel, asbestos' filler gasket.

The containment' vessel is centered inside of a prismatic metal frame 21.5 x 21.5 x 190 inches, and is supported by six 5/16-inch thick and two 1-1/4-inch thick steel plates equally spaced and welded to the support frame perpendicular to the longitudinal axis. The support frame is constructed of 2-x 2-x 1/4-inch steel angles, covered with expanded, metal.. mesh.. Impact :. limiters comprised.of interspersed styrofoann and masonite are bolted to the ends. The package gross weight is l

2,200. pounds.

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' age 2 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901 P

5.

(a)

Packaging (Cont'd)

(3) Drawings The packaging is fabricated in accordance with Hanford Engineering Development Laboratory Drawings Nos. H-3-37350, Sheet 1, Rev. 4, Sheet 2, Rev. 2, Sheet 3, Rev. 3, Sheet 4, Rev. 2; H-3.39691, Sheet 1, Rev.

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1, Sheet 2, 'Rev. O'; H-3-32429, Sheet 3 of 4,:'Rev. ~6; H-3-38062, Rev.

1;H-3-37042; Rev."l; and H-3-37412,- Rev.1.

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(b) Contents (1) Type and form of material (1) Unirradiated fuel pins containing mixed Pu0, in natural UO2 as pressed sintered pellets of the following specification:

Pellet diameter, inch 0.19 to 0.20 Pin diameter, inch 0.22 to 0.24 Maximum length, inches 36.3 Maximum Pu0 in UO, w/o 31 2

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Maximum.U-235 enrichment-

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in~UO, w/o 0.72 2

Minimum Pu-240 enrichment in Pu0, w/o 10 2

Cladding material Type 304 SS or 316 SS Minimum cladding thickness, inch 0.010 (ii) Unirradiated fuel pins containing mixed Pu0 in UO enriched to 7

2 any degree in the U-235 isotope as solid peTlets of the following specification:

Maximum pin diameter, inch 0.290 Maximum length, inch 37

Minimum.Pu-24.0,

3, 3

enrichment in Pu0, w/o 10 2

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1' Page 3 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901 4

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(b) Contents (Cont'd) i Cladding material Type 304 SS or 316 SS Minimum cladding thickness, inch 0.010 Maximum linear density of.

. 3.0 fissile. material, kg/ft~

. (if1). : Fast' flux;tes& facility (FFTF.).fnel'.c' ve

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2-(iv)

Pu0, and U0, enriched in the U-235 isotope encapsulated in fuel pint or captules which meet the requirements of special form material as defined in 10 CFR i 71.4(o).

(v)

Solid dry oxides of Pu-238, Pu-239, Pu-240, Pu-241 (non-isolated fom), U-233, U-235, Np-237 and Am-241, contained within capsules which meet the requirements of special form material as defined in 10 CFR 9 71.4(o).

(vi)

Pu-241, Am-242, Cm-243, Cm-244, Cm-245, Cf-247 or Cf-251 in any form, contained in capsules which meet the requirements of special fonn material as defined in 10 CFR 9 71.4(o).

(2), Maximum,,qua,n,tJJy,,of material,. per,,pa,ckage Not to exceed 260 watts internal decay heat, and:

(1)

For the contents described in 5(b)(1)(i) and 5(b)(1)(ii) 120 fuel pins with no more.than 6.75 kg Pu.

(ii)

For the contents described in 5(b)(1)(iii) no more than one assembly.

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(iii)

For the contents described in 5(b)(1)(iv), greater than Type A quantity of radioactive material not to exceed the generally licensed mass limits as specified in 10 CFR i 71.11(a).

(iv)

For the contents described in 5(b)(1)(v) no more than 230 grams of fissile material.

l (v)

For the contents described in 5(b)(1)(vi) no more than 3 grams of the isotopes specified.

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Page 4 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901 (c)

Fissile Class II and III (1) Minimum transport index to be shown on label for Class II

('i)

For ' contents desdribid 'in 5(b)(1)(1) and limited in 5(b)(2)(i):

4.0 (ii)' For. contents described in 5(b)(1)(ii)-

andlimitedin.5(b)(2)(1):

7.0

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52- # '>-

-(.iti)-D For contents described in.5(b)-(1)tifi) ^

• and limited in 5(b)(2)(ii):

015 (iv)

For contents described in 5(b)(1)(v) i and limited in 5(b)(2)(iv):

3.5 (v)

For contents described in 5(b)(1)(vi) and limited in 5(b)(2)(v):

3.5 (2) Maximum number of packages per shipment for Class III For contents described in 5(b)(1)(iv) and limited in 5(b)(2)(iii):

One (1)

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For. the con, tents, described.in,5,(b),(1)'(1),(ii,(.i.v). an.d (,v), car,bi, des, or. nitrides,,,...

may replace the oxides ~of. uranium and pluton um..

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The package authorized by this certificate is hereby approved for use under general license provisions of 10 CFR 9 71.12(b).

8.

Expiration date: May 31, 1988.

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Page 5 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901 REFERENCE Hanford Engineering Development Laboratory Report.No. HEDL-TI 76-018, December 1976.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Cha &

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1 rles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and j

Material Safety MAY 0 61983 0 ate:

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s U.S. Nuclear Regulatory Commission Transportation Certification Branch Approval Record Model No.: Model 120 Packaging Docket No. 71-9901 i

Bi application dated March 22, 1983, Department of Energy, Safety Engineering and Analysis Division, requested renewal of Certificate of Compliance No. 9901.

No changes were requested or made to the package since approval

. of. the. original application dated December 1976.-

The staff concludes that the statements. of the original. application

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' '"'- satt.sfies' the" req 6irement'foFnnewar of' thf Certificateof CompliaricE.

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C rles E. MacDonald, Chief, Transportation Certification Branch Division of Fuel Cycle and Material Safety, PNSS Date:

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