ML20128M623
| ML20128M623 | |
| Person / Time | |
|---|---|
| Site: | 07109176 |
| Issue date: | 05/22/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20128M610 | List: |
| References | |
| NUDOCS 8506030039 | |
| Download: ML20128M623 (4) | |
Text
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CERTIFICATE OF COMPLIANCE
.'* c'Q " " F5] RADIOACTIVE MATERIALS PACKA7ES j l 1.a CEATIFICATE NUM8ER D. REVISION NUMBER c. PACKAGE :oENTIFICATION NUMBER d.PAGE NUMBER e. TOTAL NUMBER PAGES g
g 9176 4 USA /9176/A 1 3 i I a. PRE 4ustE. rN l
l c. This certificate is issued to certify that the packaging and contents desenbed in item 5 below, meets the a pphcable safet y standards set forth in Title 10, Code E j i of Federal Regulations, Part 71JPackaging of Radsoactive Matenals for Transport and Transportation of Radioactive Material Under Certain Conditions." %
lE I b, .This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U.S. Department of Transportation or other M I
I appbcable regulatory agencies, including the government of any country through or into which the package will be trh.isported, i I E l
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'R ll Nuclear Packaging, Inc. NUPAC application dated October 29, 1982, E I 1010 South 336th Street as supplemented. N l
Federal Way, WA 98003 -j c I . c O 7 ^. . '
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71-9176 E
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! This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as applicable, and the cond6tions specified below
[U 5-l (a) Packaging g.-
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y (1) Model Nos.: 7 NUPAC 14/210L, NUPAC 14/210H, and CNSI 14-215H Series A g (2) Descript$on 4lN H
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cm, H c Steel 6ncased lead shielded casks for low specific activity material. .
-j The casks are right: circular cylinders;with a 77.25 inch ID by 80.25- g' inch IH cavity. The walls ~of' the casks contain a lead thickness
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y ranging from:1.25 to 11.88 inches encased in 0.38-inch thick inner i steel shell andLO.88-inch thick outer'~ steel shell. The top cover and N cask bottom areimade up.bf two steel plates with thickness of 2.0 N i inches. The primary cask ;11d is secured to the cylindrical cask body- l l by eight,il-1/4-inch rachet. binders. JAn; optional secondary lid is y centered in the primary lid and'is secured to the. primary lid with y eight, 3/4-inch studs and nuts. Each lid is provided with a Neoprene p gasket seal . The casks may be provided with an optional 12 gauge H stainless steel liner (seal welded along all~ edges), an optional lid j
N vent line with pipe plug, and an optional 3/4-inch . drain line and pipe plug. The casks are provided with four equally spaced lifting / tie-down devices. The primary lid is provided with three lifting lugs and y the optional secondary lid is provided with one lifting lug. The casks gross weights range from 51,600 to 58,400 pounds.
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Model OD, Lead Tk, Top Tk, Bottom Tk, Gross Wt, ly Number inches inches inches inches pounds NUPAC 14/21GL- 82.25 NUPAC 14/210H 83.5 1.25 1.88 4.0 4.0 4.0 4.0 51,600 58,400 j
CNSI 14-215H lgE Series A 83.8 1.85 4.0 4.0 58,400
, lEl (3) Drawings ! :
The NUPAC packages are fabricated in accordance with Nuclear Packaging,
. j, Inc. Drawing No. X-20-204D, Sheets 1 and 2, Rev. No. D. g_
II IN The CNSI package is fabricated in accordance with Chem-Nuclear Systems, Inc. Drawing Nos. 24500-08, Sheets 1 and 2, Rev. 2; and 24500-05,
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E Page 2 - Certificate No. 9176 - Revision Nc. 4 - Docket No. 71-9176 W lt (b) Contents ..
[ N (1) Type and form of material y n
(1) Dewatered, solids, or solidified waste, meeting the requirements E
'for. low specific activity material, in secondary containers; or E E
(ii) Activated solid components meeting the requirements for low specific activity material, in secondary containers,
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- (2) Maximum quantity of material per package E E _
Greater than Type A quantity.of radioactive material which may contain (
fissile material providedithe-fissile. material does not exceed the j limits in 10 CFPs 571.53? Thed 'Ec'apheatiload is limited to 9 watts
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!: for the Model Nos. NOPAC 14/210L and NUPAC414/210H casks. E h) 4 ,h >
l 6. (a) For any package s *containing water and/or organic substances which could E
radiolytically generate combustible gases, detennination itust be made by f a tests and measurements or by analysis of a representative package such that l 1, the following{ crit'er a are met over a period 4, ftime that> is twice the y expectedshipmentti{me;Q r N
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(i) The hydrogen generated must,b'e 1,imited-to;a molar quantity that would
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be no rmore than 5%:byjvolum fy mable. gases) .of, thelseconda,e7(or;equiv~alent limits ry contaigerigas void if -present for other inflam at STP l j (i.e!, no moreithaEO.063.g-moles /ft< !at-14:7, p'sia and 70*F); or g l1 W Q ' j )) i [M' O . / @inerted with a diluent N
- (ii) The secondar$ ,iner'an'd ytconta , cask ]ca~vity mustLbe b 4
to assuFa that' oxygen miJsts be .liniit'ed to.5% by volume in those portions
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E of the jackage'which uld}have} dr dn greater tpan 5%.
1 For any package , delivered to aicarrierafor transport',+the secondary container !g 1 must be prepared,for shipment in"the4ame manner Lin.which determination for 'N f1 gas generation is 'made. Shipment period begins when the package is prepared E il (sealed) and must be# completed within twice the expected shipment time. g d Y ~L A J,r T- ,
!) (b) For any package shipped withini10 days of preparation, or within 10 days y
.1 after venting of drums or other secondary containers, the determination in p ..
1 (a) above need not be made, and the time restriction in (a) above does not E j a pply, j j
- 7. Maximum gross weight of the contents, secondary containers, and shoring is limited to 20,000 pounds.
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- 1 .8. Except for close fitting contents, shoring shall be placed between secondary N
! - containers and the cask cavity-to minimize movement during normal conditions of 4
)1 trans port. / :
3 l' y 9. The lid and shield plug lifting lugs shall not be used for lifting the cask, and g 1 shall be covered in transit. E 1 N .
1 10. The cask shall be provided with either (or both) a drain line or a lid vent line 'E j as shown in the drawing in order to provide a method to leak test the package. l, 2 '
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= ' Page'3 - Certificate No. 9176 - Revision No. 4 - Docket No. 71-9176
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l 11. In addition to the requirements of Subpart G of 10 CFR Part 71:
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p (i) Prior to each shipment, the packaging Neoprene lid seals must be inspected. l 3
The seals must be replaced with new seals if inspection shows any defects !
1 or every twelve (12) months, whichever occurs first. Cavity drain and vent I j lines shall be sealed with appropriate sealant applied to the pipe plug l J threads. ;
l l I (ii) Each cask must meet the Acceptance Tests and Maintenance Program of Section 8.0 l 1 l l[
3 of the application. In addition, the cask shall be leak tested at least every twelve (12) months in accordance with Appendix 8.4 of the application.
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- 12. The cask body and each cask 1,id 5 hat 1 be marked .in'accordance with 10 CFR Q71.85(c).
i l y' ~vi l Ij 13. The packages authorized bl.g th 'is certificate shall $e Y/_ansported on a motor i 1
vehicle, railroad car,?aircraf t, inland watercraft, or hold or deck of a seagoing 1 vessel assigned for thA' sole use of the licensee. U 1 T $; jN' l1 14. The package authorized 'by7this certificate is hereby approve'd'~,for use under the ;E 1
1 general license pr'6 vision's of?10 CFR 971.12. jE 1 q x5p , y /a -/ ,% ;E dl 15. Expiration dateE-March 31,Il9_88. ) %b [ , 3: i d. )
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Nuclear Packaging, Inc'.' application, dated October:29, ~1982*. ,' . y 1 n M%d d iiijil k <5 N 1 Supplements dated: February 18 andLMarch:24;71983*/6'f- <> N 1 W y3 g ; .; , x, ,
, E tl Chem-Nuclear Systems, Inc.#supplementUdated: LJanuary 24, 1985. -
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u See Docket No. 71-9159 Vf '"
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M [b Charles E. MacDonald, Chief W
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1 Transportation Certification Branch IP 1 Division of Fuel Cycle and lE l
'1 Material Safety, NMSS E
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j Date: MAY 2 2 M lE 1 lp E
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, gsa uru4 k o UNITED STATES NUCLEAR REGULATORY COMMISSION 4 m WASHINGTON, D. C. 20555 s i
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. Transportation Certification Branch Approval Record Co.nbustible Gas Mixtures l
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- Conditions were imposed on packages containing water and/or organic substances to limit.the accumulation of radiolytically generated gases 2 over the shipping period to preclude the possibility of significantly reducing the packaging effectiveness due to explosion.
Part of the conditions included "...it must be detennined by tests and measurements of a representative package whether or not...." '
1
.There' is-no reason to believe that calculational methods could not be used as means of determining gas ~ generation. So as not to preclude a -
valid-analysis, part of the condition to limit the accumulation of radiolytically generated gases is revised to read "...it must be detemined by tests and measurements or by analysis of a representative package <
whether or- not. . . ."
The analytic approach involves detemining the hydrogen gendrated in the waste by radiolysis based' on the absorbed dose of the waste over a given period of time. To satisfy the condition to preclude a combustible mixture, the period since closure:and twice the shipping time must be considered. The calculation' requires' that the properties of the waste
.a re - known. These properties may be detemined from test and-measurement of representative waste forms or from data that is applicable to .the waste form. The determination should be documented and retained as part of the records for the shipment.
W^=$ h Charles E. MacDonald, Chief Transportation Certification Branch _
Division of Fuel Cycle and .
Material Safety, NMSS Date: N 2 2 1Q a t
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