ML20128H120

Certificate of Compliance 9139,Rev 5,for Model 589.Approval Record Encl

ML20128H120
Person / Time
Site:	07109139
Issue date:	05/22/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20128H101	List: ML20128H098 ML20128H120
References
NUDOCS 8505300424
Download: ML20128H120 (4)

Text

_--

m.- p - - - - = = = = = = E s = = = m - m ient y

E" CERTIFICATE OF COMPLIANCE AR RE a c a miss a lj io Cm "

FOR RADIOACTIVE MATERIALS PACKAGES j

I 1 a CERTIFICATE NUMBER

,5 USA /9139/A 1

3 D REVISION NUMBER C PACsLAGE IDENilFiCATION NUMBER

d. PAGE NUMBER e TOTAL NUMBER PAGES 9139 li 2 PREAMBLE O

fll a This certificate is issued to certify that the pacitaging t.nd contents described in item 5 below, meets the apphcable safety standards set forth in Title 10. Code lE of Federal Regulations. Part 71. ~ Packaging of Radioactive P8at..ls for Transport and Transportation of Radioactive Matenal Under Certain Conditions "

Nj b This certificate does not reheve the consignor from comphance witn any requirement of the regulations of the U.S Depar ment of Transportation or other

k appheable regulatory agencies. including the government of any ceuntry throi gh or into which the package will be transported.

k i

)&==.m=~~:h=====

k.

h

.i c a,.

.gl General Electric Company General Electric Company application dated lE 1

P.O. Box 460 March 24,1980, as supplemented.

lE 3l Pleasanton, CA 94566 i@ _

1l 4

i3

^

C '71 9139 7

jl

c. DoCxET NuiER 4 CONOitiCNS 3

This certificate is conditional upon fulfilbng the requirernents of 10 CFR Part 71, as apphcable, and the conditions specified below i

1 15-(a)

Packaging l

j%

i (1) Model No.:

589 l

/

l g!

(2) Description 1

,h 4

A steel encased lead shielded cask for low specific activity material, f

The cask is a right circular cylinder with 79-inch OD by 80-inch f

g height, and a cavity 74-inch ID by 74-inch height. The 1.5-inch thick j

l

.gl lead shield is supported by outer and inner carbon steel shells 0.75-In i

inch and 0.375-inch thick, respectively.

The bottom 1.56-inch thick p

I

1l lead shield is supported by outer and inner carbon steel plates 1.0-E J

inch and 0.375-inch thick.. respectively.

The 1.5-inch thick lead lid f

3 shield is supported by outer and inr.er carbon steel plates 1-inch and j

j 0.5-inch thick, respectively.

The carbon steel used is SA516, Grade l

4 70.

The lid is attached to the cask with eight (26,000 lb proof load

!g

~

g j

each) ratchet type load binders and sealed with a Buna N 0-ring. The lR

1!

cask is equipped with a 3/4-inch drain line, sixteen-hole bolt-down

)j A

fiange (1-inch bolts) aM two, 2-1/2-inch diameter lifting lugs.

The l!

catk lid seal and lifting lugs are protected by a wooden sacrificial ylp f

impact limiter (about 8'x 10 inches thick).

Gross weight of package gj and impact limiter, 50,000 lbs.

jy 4

P 1

(3) Draing l?

E t

The packaging is constructed in accordance with PX Engineering Company, f

l Inc., Drawing No. 589-L, Sheets 1 through 3, Revision No. O.

g 1

R 3

i 1

i 1

(

41 l#

fl 8505300424 050522 j

g PDR ADOCK 07109139 C

q pog l

t 41 i

l t

l t

1!t

-- mmw-m------x-

k I *Q '""

conom:Ns tcontinued) 1 I

Page 2 - Certificate No. 9139 - Revision No. 5 - Docket No.

1 71-9139 l

1 I

m

)

5.

(b) Contents 1

~

l (1) Type and form of material 1

l Dewatered or solidified waste material in sealed secondary containers j

or solid irradiated hardware, meeting the requirements for low specific j

activity material.

I I

(2) Maximum quantity of material per package r

1 j

Greater than Type A quantity _of radioactive material with the weight

~

j of the contents, secondaQ contalnegs,an.d shoring not exceeding 20,150

~

)

pounds.

GW

• ' ' b (,/ /

l 1

For any package conta'Y' r

%4 1

6.

(a) ining water and/or organic sub' stances which could I

radiolytically. gen'erate combustible gases, determination must be made by l

tests and measurements or by analysis of a representative package such that l

r y

the following c'riteria are met over a period of, time that is twice the j

expected shipnient' time:s d-D l

L0 Y

//

~s I

(1) The hydrogen generated must;be;11mi,tedsto:a molar q,uantity that would J

l 1

be no'more than 5%;by; volume-(oriequivalent limits for, other inflam-

]

mablergases) of theisec'ondary,contafjer gas void if'present at STP 3

j (i.ee,jo more than 0;'063 g-moles /ft.f attl4.7f p,sia and~ 70'F); or M4 9#<D,,,

5 N.%4 (ii) The s(econdarycJcontainen andicask, cavity ~ myst be ineited with a diluent I

s 1

i f

1 to assure thatfoxy' gen imistibei: limited to 5% by volume in those portions 1

of the(packageMich co'ldpaVeWdrogen gre'ater than 5%.

u l

M

~'fiMP 8M@~ CP W

1 For any package. delivered ~ to acarrierMor1 transport,Cthe secondary container 1

must be prepared,for shipme~ilt 'in gthe same~ manner in.which detemination for i

s 1

gas generation l's'inade.

Shipment' period begins whenithe package is prepared

[

}

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

L l

E

,s v

V j

(b)

For any package shipped withinl10,daysfof preparation, or within 10 days 1

after venting of drums or other secondary containers, the detemination in 1

(a) above need not be made, and the time restriction in (a) above does not 1

a pply.

}

}

7.

Shoring must be placed between secondary containers (or activated components)

)

and the cask cavity to prevent movement during nomal conditions of transport.

1 l

8.

The lid lifting lugs cust not be used for lifting the cask and must be covered I

in transit.

1 I

I l

(

i I

I i

1 1

4 I

I i

i I

, ___ mg un, - - - ~n-- - -. aq g.~ c m se' n

U ' * ^ M * * '

conosinons (continued) d I

H g

a g

Page 3.- Certificate No. 9139 - Revision No. 5 - Docket No. 71-9139 q

I I

N 9.

The packaging acceptance tests and maintenance program must be in accordance

[l j

{g with Section 7.0 of the application except:

4 g

4 g

(a) The lid 0-ring seal must be replaced if inspection prior to each shipment U

g shows any defects or every twelve (12) months, whichever occurs first.

l ll (b)

During inactive periods, the maintenance and testing frequency may be

[i disregarded provided that the packaging is brought into full compliance i

prior to the next use of the package.

[!

t

10. The package autho'rized by this certi.ficate-must be transported on a motor vehicle, t

railroad car, aircraf t, inland witericrift,~. orjh'old.or deck of a seagcing vessel t,

assigned to sole use of the li'censee.

V/

I

.s ev N.O s t

~

i.. +

t;

11. The package authorized'b this certificate is hereby approved for use under the tl general license provis,% ns of 10 CFR 971.12.

(,'a tl n.

e N

N is T

12.

Expiration Date: c" July 31 d1985.

/ '/

.f

.f _

m e

i%

pri REFERENCES ( j n t

s GeneralElectric' App!"lication jated: March _24h1980g\\ ?a f 7-t>

a ::py

/_ i L.

t; 1:M' L:

iM tin NM. / '

55 L

l j a : i s ; 'W ' C

Supplement dated:

May'29, 1980^.

%N ii jb I

42

.mc w

+-

b kk 0\\ES

?r 1

& n C EOR THEcU.SS NUCLEAR REGULAT n

c

(%

Q&

t P

17 ii g g3 7 t

f u

,y/ f : 1Nm W

C s /

W/ig\\N O

[

'p f

(

"/

Charles E. MacDonald, Chief 0

' i Transportation Certification Branch ti IDivision'of Fuel Cycle and t

'~

Mate' rial Safety, NMSS

(

MAY 2 21993

[

Date:

L:

C!

C t!

ti titi til' t:

L:

L; L:

L:

E:

L:

L L:

L:

---

,--,._,..,..u.u,.c.--,._v.,.u..._,.u,,,...,.,w,,,,,.u_.u,n,.,,,,a

@S RIG (f e

t

'o,,

UNITED STATES g

8 NUCLEAR REGULATORY COMMISSION o

g E

WASHINGTON, D. C. 20555

\\...../

=

l Transportation Certification Branch Approval Record Combustible Gas Mixtures Conditions were imposed on packages containing water and/or organic substances to limit the accumulation of radiolytically generated gases l

over the shipping period to preclude the possibility of significantly 1

, reducing the packaging effectiveness due to explosion.

Part of the conditions included "...it must be detemined by tests and measurements of a representative package whether or not...."

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 determined by tests and measurements or by analysis of a representative package i

whether or not...."

l

~

The analytic approach involves detemining the hydrogen generated 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 are known. These properties may be detemined from test and measurement of representative waste foms or from data that is applicable to the waste form.

The detemination should be documented and retained as part of the records for the shipment.

b Charles E.

acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:

MAY 2 21985 l

=

.