ML20237L372

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Certificate of Compliance 9073,Rev 16 for Models OH-142, OH-142 MKI,OH-142 MKIB,OH-142 Mkii & LN-142.Approval Record Encl
ML20237L372
Person / Time
Site: 07109073
Issue date: 08/25/1987
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20237L353 List:
References
NUDOCS 8708280074
Download: ML20237L372 (6)


Text

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NRC FOAM 618 U.S. NUCLEAR REGULATORY COMMISSloN cai CERTIFICATE OF COMPLIANCE io CFR n FOR RADIOACTIVE MATERIALS PACKAGES 1 a CERTIFICATE NUMDER b Revision NUMBER C PACKACsE IDENTIFICATION NUMUER d PAGE NUMBER e TOTAL NUMBEH PAGE5 l 9073 16 USA /9073/A 1 5 2 PREAMBLE a Th s cert frcate 's its sed to ce'th inat me packageg and corteNS destnood m item 5 beiow enects the av mcacie safety starda-ds set fe"n m T' tie 'O Code ,

! Of F9deral Regulations Part 71 Pacnagmg and Transportation of Radioactive Material' P' N b This certificate does aot reheve the consignor from comptance with any requirement of the regulations of the U S Department of Transportation or other Ng apphcable regulatory agencies, inc'- ag the government of any Country through or into which the paChage well be transported ,

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I I i q Nuclear Packaging, Inc. Nuclear Packaging, Incorporated, application i 1 1010 South 336th Street dated May 6, 1985, as supplemented. i N Federal Way, WA 98003  :

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(a) Packaging g (1) Model Nos.: 0H-142, OH-142 MKI, OH-142 MkIB, OH-142 MKII, and ,

I LN-142  !

I i (2) Description l l

l Steel encased, leao shielded casks for solid radioactive material.  !

q; The overall dimensions of the casks are 101-inch dianeter by 120-inch <

qj height. Thecasksconsistsoftwoconcentriccarbonsteelcylindricall I! shells surrounding a 3-1/2-inch thick lead shield. The 1/2-inch thicki N

inner shell has a 66-inch ID, and the 1- or 1-1/8-inch thick outer '

fr shell has a 76-1/4-inch OD; the base consists of two, 3-inch thick i f

welded steel plates of 66- and 74-inch diameters. The base is either g!

g welded to tht steel cylindrical shells or sealed ano held by ratchet N' binders. A stepped welded lid, secured by eight ratchet binders or ;j ll I

eight studs and nuts, is comprised of two, 3-inch thick steel plates i' I

containing openings for secondary lids of similar construction with at i least one additional 1-inch thick upper plate. Thecontainmentcavityl is 66 inches in diameter by 72 inches high. A plugged drain port is l .

i located at the cask bottom. The Model No. LN-142 package design l' 1, is provided with a lid test port in lieu of a cask drain line.

Toroidal impact limiters are locatcd :t the top and bottom of tne cask.!

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The impact limiters are 10-gauge steel sheets i m ed with rigid i i

( polyurethane, and are equipped with fusible plastic plug:. A: an q option, interior and exterior surfaces of the cask body and interior l: i y surfaces of the upper lid may be covered with 12-gauge 304 stainless I steel cladding and seal welded. f> '

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There are four alternate lid closure designs for the Mcdel No. OH-142 l

Series casks. The designs are referred to as: 1)Baselinedesign,2)j  !

i Mark 1, 3) Mark I with bolt on lid, and 4) Mark 2. llg l

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Page 2 - Certificate No. 9073 - Revision No.16 - Docket No. 71-9073 l

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I 5. (a) (2) Description (Continued) i Baseline closure design. Closure of the primary lid is accomplished I by eight ratchet binders; and of the 24-inch (29-inch) secondary lid l by eight, 7/8-inch (1-inch) diameter stud bolts. Both lids are sealed i using silicone gaskets bonded to th! lid plates. Lifting is i facilitated with three lugs welded to the primary lid. The secondary f 'id has a redundant Neoprene seal, and a centrally located lift lug.

d I Mark l closure design. Closure of the primary lid is accomplished by l eight ratchet binders, and a bondad silicone gasket provides the ,

i primary seal. Lifting is facili'.ated with three lugs welded to the l l primary lid. Six,19-inch (or cc ,16-inch, centered) diameter l l secondary lids with centers located on a 44-inch circle each have s'x, i I 3/4-inch diameter hex head' bolts. They esch have a primary bonded '

! silicone seal, a redundant Neoprene seal, and a centrally located lift l lug. l An alternate Mark 1 configuration utilizes eight, 1-3/8-inch studs and f nuts for primary lid closure and two lifting lugs on the primary lid.

4 i Mark 2 closure design. Closure of the primary lids located at the t9p :

[ and bottom of the cask is accomplished by eight ratchet binders, and a I g bonded silicone gasket on each primary lid provides a seal. Li f ting l g is facilitated with three lugs welded to the upper primary lid. The  !

'4 upper lid contains a centrally located 24-inch (or 29-inch) diameter  !

4i seconaary lid comprised of two stepped and welded 3-inch steel plates l 4! 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 l secondary lid has a bonded silicone seal, a redundant Neoprene seal g

y and three lift lugs.

4 p The Model No. LN-142 cask is nearly identical to the baseline j Model No. OH-142 cask with a 29-il.ch diameter secondary lid.

4 f All exposed side walls are coated with an intumescent material or covered with a stainless steel thermal barrier. Four skewed lugs,

.! welded to the outer shell 6re used for tie-down. The package gross i weight is approximately 64,000 pounds.

e (3) Drawings l The Model No. 0H-142 Series packagings are fabricated in accordance 1 with Nuclear Packaging, Incorporated Drawing Nos.: 0H-142 - Y-20-2010, 1 Sheets 1 through 3, Rev. 0; OH-142 MKI - AL-20-202, Sheets 1 through 3, Rev. L; OH-142 MKIB - AL-20-203, Sheets 1 through 3 Rev. J; and OH-142 MKII - Y-20-2020, Sheets 1 through 3, Rev. M.

%l l The Podel No. LN-142 packaging is fabricated in accordance with LN Technologies Corporation Drawing No. E-9414-M-3204, Sheets 1 and 3  ;

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.N CONofTIONS (continusd) 'l Page 3 - Certificate No. 9073 - Revision No. 16 - Docket No. 71-9073 I lX

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'N l (b) Contents a f 6 (l' Type and form of material. &

W !i I (i) Dewatered, solids, or solidified waste meeting the requirements il l for low specific activity material in secondary containers; or j i II l (ii) Activated solid components meeting.the requirements for lcw  !

i specific activity material in secondary containers, lyl l 'I ,

(2) Maximum quantity of material per package.

Greater tnan Type A quantities of radioactive materials which may contain fissile contents'not to exceed the generally licensed mass j l y

limits as specified in 10 CFR f5571.18, 71.20, and 71.22. Internal i i l decay heat not to exceed 400 watts and the maximum weight of contents i including secondary containers not to exceed 10,000 pounds. R l

l 6. (a) For any package containing water and/or organic substances which could q radiolytically generate combustible gases, determination must be made by !g W tests and measurements or by analysis of a representative package such that lp W the following criteria are met over a period of time that is twice the p expected shipment time: y l

I l (i) The nydrogen generated must be limited to a molar quantity that would be no more than 5% by volume (or equivalent limits for other inflam-j

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g q mablegases)ofthesecondarycontaigergasvoidifpresentatSTP 'g.

(i.e., no more than 0.063 g-moles /ft at 14.7 psia and 70'F); or lk N (ii) The secondary container and cask cavity must be inerted with a i l diluent to assure that oxygen must be limited to 5% by volume in those

g portions of tt e package which could have hydrogen greater than SL [!

g 4 l 4 For any package delivered to a carrier for transport, the secondary lFF 4 container must be prepared for shipment in the same manner in which 4 '

$,' determination for gas generation is made. Shipment period begins when the P!

8 packageisprepared(sealed)andmustbecompletedwithintwicetheexpectedf',

shipment time. g!

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  1. (b) For any package containing materials with radioactivity concentration not R:

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exceeding that for low specific activity material, and shipped within 10 k 8 aays of preparation, or within 10 days after venting of drums or other (j!

secondary containers, the determination in (a) above need not be made, and g:

lq the time restriction in (a) above does not apply. g!

W W 7. Except for close fitting contents, ounnage must be provided in the shipping cask lN: k!

cavity sufficient to prevent significant movement of the contents or secondary jkj lg containers relative to the outer packaging under normal conditions. (

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I CONDITIONS (conhnusd)

I Page 4 - Certificate No. 9073 - Revision No. 16 - Docket No. 71-9073 ,

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! 8. In addition to the requirements of Subpart G of 10 CFR Part 71:

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i (a) Prior to each shipment, the packaging lid seals must be inspected. The I seals must be replaced with new seals if inspection shows any defects or l I

every 12 months, whichever occurs first. Cavity drain and vent lines l l must be sealed with appropriate sealant applied to the pipe plug threads. ,

I i (b) Each package must meet the Acceptance Tests and Maintenance Program of- 'i I !g.

i-I Model No. H0-142 Series  :(

' Section 7.0 of the application. The package must be leak tested as k l required ey 7.1.1 and 7.2.5 and in accordance with 7.2.5.1 and 7.2.5.3. (;

I i Model No. LN-142 i LN Technologies Corportion Procedures WM-011, Rev. G; WM-013, Rev. F; and  ;

WM-022, Rev. F. j l

l (c) The package shall be prepared for shipment and operated in accordance with j the Operating Procedures cf:

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( Model No. 0H-142 Series  !

4 Section 6.0 of the application lj i;

l Model No. LN-142 i:

4 l LN Technologies Corporation Procedures WM-021, Rev. E.

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9. The packages authorized by this certificate must be transported on a vehicle, ':

d railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel  ;

assigned for sole use of the licensee. y l 10. Packagings fabricated after March 28, 1980 mustbeconstructedofA-516 Grade 70If carbon steel.

11. The packaging authorized by this certificate is hereby approved for use under '$

g the general license provisions of 10 CFR $71.12.

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12. Expiration date: March 31, 1988, s, L  ;

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^I-N; CONotTIONS (continued) e Page 5 - Certificate No. 9073 - Revision No. 16 - Docket No. 71-9073 -;

i-REFl?RENCES  ! '

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hucleor Packaging, Incorporated dpplicatf or. dotea May 6,1985.

[ fl l Supplements dated: May 16, June 3 and 12, July 30 and September 6, 1985. >:

i' i NUS Process Services supplements dated
October 15, 1984.  !

W LN Technologies Corporation supplements dated: June 1 and July 29, 1987.

l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION I

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i d Charles E. MacDona d, Chief k Transportation Branch l

q Division of Safeguards and )g" I:

( g gg g Transportation, NMSS l Date:

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Transportation Branch j Approval Record i Model Nos. OH-142 Series and LN-142 Packages

_ Docket No. 71-9073 Pevision No. 16 l i

i By application dated June 1, 1987, as supplemented July 29,1987, LN Technologies Corporation requested the Model No. NUS10-135 packaging be revised to Model No. LN-142. On September 30, 1986, London Nuclear Services purchased all the outstanding stock of the NUS Process Services Corporation.

The two organizations merged into a new comptuy called LN Technologies Corporation. The Operating Procedures, Leak .ast Procedures, Maintenance Procedures, Gamma Scanning Procedures, and the cask drawings have been revised to reflect the name change and the change in model number.

LN Technologies also requested that the use of procedure WN-011 Soap Bubble Leak Test, be authorized in lieu of WM-023 Halogen Leak Test presently cited in the certificate. The soap bubble test is an acceptable method of checking ,

the containment system of a package whose contents are limited to low specific activity material in the type and, form cited by the certificate.

Condition 9 has been added to the certificate to cite the requirements of 10 i CFR 971.52 relative to the transport of low specific octivity material.  ;

There have been no changes to the package design. The requirements of 10 CFR Part 71, have been met.

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Charles E. MacDonald, Chief Transportation Branch ,

Division of Safeguards and l Transportation, NMSS f Date:

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