ML20137R425

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Certificate of Compliance 9073,Rev 15,for Models OH-142 & NUS10-135.Approval Record Encl
ML20137R425
Person / Time
Site: 07109073
Issue date: 11/25/1985
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20137R418 List:
References
NUDOCS 8512050495
Download: ML20137R425 (5)


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I senc pois eis U.S. NUCLEAR REIULATORY C MMISSION I i l *= CERTIFICATE OF COMPLIANCE I l to esR H FOR RADIOACTIVE MATERIALS PACKAGES >I i 1 a CERTIFICATE NUMBER D REVISION NUMBER C PACKAGE loENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 1

l 9073 15 USA /9073/A 1 4 1 l s PRuustE '

l a. This certificate is issued to certify that tne packaging and contents desenbod in item 5 beiow, meets the applicable safety standards set fortn in Titie 10. Code f[

q of Federai Reguiations. Part 71. ' Packaging and Transportation of Radioactive Matenal." (

I b. inis enriificate does noi reneve ene consignor from compiiance witn any requirement of the resuistions of ine u s. oeoartment of Transportation or otner E ;

I appheabie r.guiatory agencies. inciuding ine government of any country tnrouan or into -nica ine packase wiii be transported i f ,

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icArioN q t i Nuclear Packaging, Incorporated Nuclear Packaging, Incorporated, application dated lt i 1010 South 336th Street fiay 6, 1985, as supplemented. I I Federal Way, WA 98003 jI I I I I I c. ooexEr NuM.ER 71-9073 L sc f cate is conditionai upon fuifdhng tne requirements of 10 CFR Part 71, as apphcable. and the conditions specified below

, , t g (a) Packaging l l I i (1) flodel Nos.: OH-142, OH-142 f1KI, OH-142 f1KIB, OH-142 MKII, and l I NUS10-135 I I I (2) Description [

l l Steel encased, lead shielded casks for solid radioactive material.

l l l-l The overall dimensions of the casks are 101-inch dianeter by 120-inch .I I height. The casks consists of two concentric carbon steel cylindrical lI I shells surrounding a 3-1/2-inch thick lead shield. The 1/2-inch thick inner shell has a 66-inch ID, and the 1- or 1-1/8-inch thick outer ]

lg shell has a 76-1/4-inch OD; the base consists of two, 3-inch thick t g

g welded steel plates of 66- and 74-inch diameters. The base is either t I welded to the steel cylindrical shells or sealed and held by ratchet t l l binders . A stepped welded lid, secured by eight ratchet binders or I

( l eight studs and nuts, is comprised of two, 3-inch thick steel plates l containing openings for secondary lids of similar construction with at {!g l least one additional 1-inch thick upper plate. The containment cavity l g !g i is 66 inches in diameter by 72 inches high. A plugged drain port is I t

i located at the cask bottom. The flodel No. NUS10-135 package design [

[ l is provided with a lid test port in lieu of a cask drain line. Toroidal r l l impact limiters are located at the top and bottom of the cask. The I l

i i

impact limiters are 10-gauge steel sheets filled with rigid polyurethane, k i

and are equipped with fusible plastic plugs. As an option, interior r i fnd exterior surfaces of the cask body and interior surfaces of the t l

l upper lid nay be covered with 12-gauge 304 stainless steel cladding i i I and seal welded. l l l l l

i There are four alternate lid closure designs for the Model No. 0H-142 [

i Series casks. The designs are referred to as: 1) Baseline design, 2) l i i Mark 1, 3) Mark 1 with bolt on lid, and 4) Mark 2. t l I l l 1

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E>i i Page 2 - Certificate No. 9073 - Revision No. 15 - Docket No. 71-9073 f 4

5. (a) (2) Description (Continued)

Baseline closure design. Closure of the primary lid is accomplished i by eight ratchet binders; and of the 24-inch (29-inch) secondary lid g' by eight, 7/8-inch (1-inch) diameter stud bolts. Both lids are sealed i using silicone gaskets bonded to the lid plates. Lifting is facilitated g( '

with three lugs weldea to the primary lid. The secondary lid has a g

redundant Neoprene seal, and a centrally located lift lug.

14 Mark 1 closure design. Closure of the primary lid is accomplished by h g

eight ratchet binders, and a bonded silicone gasket provides the r,;

primary seal . Lifting is facilitated with three lugs welded to the primary lid. Six,19-inch (or one,16-inc.h, centered) diameter secondary lids with centers located on a 44-inch circle each have six, 3/4-inch diameter hex head bolts. They each have a primary bonded silicone

! seal, a redundant Neoprene seal, and a centrally located lif t lug.

An alternate flark l configuration utilizes eight,1-3/8-inch studs and i

nuts for primary lid closure and two lifting lugs on the primary lid.

Mark 2 closure design. Closure of the primary lids located at the top and bottom of the cask is accomplished by eight ratchet binders, and a bonded silicone gasket on each primary lid provides a seal. Lifting is facilitated with three lugs welded to the upper primary lid. The upper lid contains a centrally located 24-inch (or 29-inch) diameter secondary lid comprised of two stepped and welded 3-inch steel plates above and below a 1-inch steel plate. Closure of the secondary lid is provided by eight, 7/8-inch (or 1-inch) diameter stud bolts. The secondary lid has a bonded silicone seal, a redundant Neoorene seal and three lift lugs.

The fiodel No. NUS10-135 cask is nearly identical to the baseline Model No. OH-142 cask with a 29-inch diameter secondary lid.

All exposed side walls are coated with an intumescent naterial or covered with a stainless steel themal barrier. Four skewed 7dgs, f

welded to the outer shell are used for tie-down. The package gross ,

weight is approximately 64,000 pounds.

(3) Drawings i

! The flodel No. 0H-142 Series packagings are fabricated in accordance i

with Nuclear Packaging, Incorporated Drawing Nos.: 0H-142 - Y-20-2010, l

Sheets 1 through 3 Rev. Q; OH-142 MKI - AL-20-202, Sheets 1 through j 3, P.ev. L; OH-142 f1KIB - AL-20-203, Sheets 1 through 3, Rev. J; and j OH-142 flKII - Y-20-202D, Sheets 1 through 3, Rev. ft.

! The Model No. NUS10-135 packaging is fabricated in accordance with l NUS Corporation Drawing No. 5025-M-2001, Sheets 1 and 2, Rev. B.

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!l Page 3 - Certificate No. 9073 - Revision No.15 - Docket No. 71-9073 i

(b) Contents (1) Type and form of material.

(1) Dewatered, solids, or solidified waste meeting the requirements k

i for low specific activity material in secondary containers; or l

(ii) Activated solid components meeting the requirements for low specific activity material in secondary containers.

(2) Itaximum quantity of material per package.

Greater than Type A quantities of radioactive materials which nay- l contain fissile contents not to exceed the generally 1icensed mass  ;.

, linits as specified in 10 CFR $671.18, 71.20, and 71.22. Internal i H decay heat not to exceed 400 watts and the naximum weight of contents I-including secondary containers not to exceed 10,000 pounds.  ;

!! 6. (a) For any package containing water and/or organic substances which could radiolytically generate combustible gases, detemination must be made by tests and neasurements or by analysis of a representative package such that the following criteria are met over a period of time that is twice the expected shipment tine:

(i) The hydrogen generated cust be limited to a molar quantity that would g:

be no more than 5% by volume (or equivalent limits for other inflam- n:

mable gases) of the secondary contaiger gas void if present at STP (i.e., no more than 0.063 g-moles /ft at 14.7 psia and 70*F); or A(

(ii) The secondary container and cask cavity must be inerted with a diluent k to assure that oxygen nust be limited to 5% by volume in those portions 3; of the package which could have hydrogen greater than 5%. W r

., For any package delivered to a carrier for transport, the secondary container  ;

.' must be prepa.ed for shipment in the same manner in which determination for

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

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

(b) For any package containing naterials with radioactivity concentration not ,E

.; exceeding that for low specific activity material, and shipped within 10 p i days of preparation, or within 10 days after venting of drums or other 'g l secondary containers, the detemination in (a) above need not be made, and g! 1 the time restriction in (a) above does not apply, g:

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Except for close fitting contents, dunnage must be provided in the shipping cask K:

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cavity sufficient to prevent significant novement of the contents or secondary a

containers relative to the outer packaging une!er nomal conditions.

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Page 4 - Cartificate No. 9073 - Revision No.15 - Docket No. 71-9073 y _'

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8. In addition to the requirements of Subpart G of 10 CFR Part 71: g (i) Prior to each shipment, the packaging lid seals nust be inspected. The h seals rust be replaced with new seals if inspection shows any defects or ql every 12 months, whichever occurs first. Cavity drain and vent lines must b be sealed with appropriate sealant applied to the pipe plug threads.

(ii) Each cask must meet the Acceptance Tests and itaintenance Progran of Section 7.0 h of the application. flaintenance and Gamma Scanning may be in accordance y with NUS Process Services Procedures VI-022, Rev. A and Utt-013 Rev. E. In '

,. addition, the cask must be leak tested in accordance with Section 7.2.5 of h _

the application or NUS Process Services Procedure UM-023, Rev. 8, every 12  %

nonths and when repairs are made to the seal area. E

9. Packagings fabricated after fiarch 28, 1980 nust be constructed of A-516 Grade 70 h

$1 carbon steel. #

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10. The packaging authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR %71.12. f-l11 3 11. Expiration date: March 31,1988.

REFERENCES .

Nuclear Packaging, Incorporated application dated May 6,1905.

I Supplements dated: May 16, June 3 and 12, July 30 and September 6,1985. h Y

NUS Process Services supplements dated: July 31, October 15, and December 13, 1984. E N,

FOR THE V.S. NUCLEAR REGULATORY C0!1r1ISSION h 1v e4ML Charles E. flacDonald, Chief j M

Transportation Certification Branch y -

Division of Fuel Cycle and p flaterial Safety, f#tSS $

E' Date: M25 W p y .

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, i,9 o UNITED STATES

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E WASHINGTON, D. C. 20555 o f i 1

% Transportation Certification Branch Approval Record '

Model Nos. 0H-142 Series and NUS10-135 Packages Docket No. 71-9073 On December 31, 1985, Certificate of Compliance No. 9073 for the Model No. 0H-142 shipping container will be amended to authorize contents of

-low specific activity material only. The package identification number will also be changed to USA /9073/A at that time.

For this package, the Nuclear Packaging, Inc. safety analysis of hypothetical accident conditions is based upon the ultimate (breaking) strength of the ratchet binders. The staff recently obtained nanufacturer's literature for these devices. The literature for ratchet binders states: " Breaking strengths are approxirate and should be used as reference only. Good common practice dictates use of a safety factor suitable to the application; usually no less than 3 to 1." The unsuitability of basing ratchet binder designs on ultimate strength is further exemplified by the AISC code which specifies a safety factor of 5 to 1 for simple turnbuckles.

In addition, the Nuclear Packaging, Inc. safety analysis of the ratchet binders does not address the following:

1. The magnitude of the clamping force provided by ratchet binders.

(With bolts, the clanping force can be controlled by the amount of torque applied to the bolt).

2. The extent to which the clanping force could vary under routine operations due to temperature changes, wear of the ratchet binder components, vibration, fatigue, etc.
3. The effectiveness of ratchet binders for resisting lateral loads imposed by cover plates and impact limiters under side and oblique angle impacts.
4. The adequacy of using ratchet binders for shipping container closures as demonstrated by actual physical testing to the hypothetical accident conditions in 10 CFR Part 71.

Based upon the foregoing and in the absence of conclusive safety infonnation, the authorized contents for the Model No. OH-142 packaging will be

' limited as indicated above so that the ratchet binders need not be effective under hypothetical accident conditions.

M Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, 41SS Date: NOV 2 5 515