ML20236C307

Rev 15 to Certificate of Compliance 9044 for Model 1600. Approval Record Encl

ML20236C307
Person / Time
Site:	07109044
Issue date:	10/23/1987
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20236C297	List: ML20236C294 ML20236C307
References
NUDOCS 8710270092
Download: ML20236C307 (7)

Text

.

--.-----------------------------------------------.c-1 i nac ecau s1s u.s. NUCLEAR RE!ULATC.;Y COMMISSION i =

CERTIFICATE GF COMPLIANCE 1 CERTWICATE NUMBER

b. RE NU SE AC AGE ENT F N NUMBER d.PAGE NUMBER

e. TOTAL NUMaER PAGES i

9044 15 USA /9044/B( )F

'1 5-1 muuets

c. This certificate is issued to certify that the packaging and contents described in item $ below, meets the applicable safety standards set forth in Title 10. Code of F;deral Regulations, Part 71," Packaging and Transportation of Radioactive Material."

EL Thes certificate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other appilCable regulatory agencies. Including the government of any country through or into which the package will be transported.

j 33 THIS CE'eTIFICATE IS ISSUED ON THE SA$lS OF A SAFETY ANALYSTS REPORT OF THE PACKAGE DESIGN OR APPLICATION

{

a ISSutD TO (Ausme and A#esal

b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

k'

{VallecitosNuclearCenter General Electric Company General Electric Company application dated i

February 1, 1982. as supplemented.

Picasanton, CA 94566 71-9044 I

c. OOCav NUuSER 4 CONOfflONS This certificate is conditional upon fulfilling the requirements of to CFR Part 71. as appbcable, and the conditions specified below.

S.

(a)

Packaging (1) Model No.:

1600 i

(2) Description Steel encased lead shielded shipping cask.

A double-walled steel cylinder protective jacket encloses the cask during transport.

It is bolted to a steel pallet.

The cask is closed by a lead-filled flanged plug fitted.with a silicone rubber gasket and bolted closure.

The cavity is equipped with a drain'line and the physical. description is as follows:

Cask height, in 67.19 Cask diameter, in 38.5 Cavity height, in 54.0 Cavity diameter, in 26.5 Lead shielding, in 5.0-Protective jacket height, in 81.88-Protective jacket width, in 68.0 Packaging weight, lb 25,500 8710270092 871023 PDR ADOCK 07109044 C

PDR a

^'

M

"*o*'"'M c: nom:ns to:ntinveoi.

Page 2 -.. Certificate-No.19044J-Revision-No. 15

-Docket:No.: 71-9044 L 5.,

(a) : Packaging-(continued)'

i.

(3) Drawings I

-The'Model No..1600 packaging..is' constructed in-accordance with the'

}-

following General Electric Company-Drawing Nos.: L.129D4735, Rev. 4*;.-

[

129D4736, Rev. 3;,12904737, Rev. 6; and 12904738, Rev.:1.

p i

• Except Item'2 hex.hd bolts'must be. ten,-2.0-4.5.

l UNC-2A.x:4.5' inches to 5.0 inches'long, A-449 bolts.n Lifting and/or.tieidown devidi' lshichzare.a structural part ofithe s

package must be in accordance withithe above: drawings.

,3 (b)

Contents (1) Type, form and: maximum quantity of material-per package

~Plutoniumin-excessof20 curies.per'packagemustbe[in'theformof metal,, metal alloy or reactor fuel elements; and:

(i)

Byproduct material?and specialinuclear materiaifas solid ' metal-or oxides.

Decay heat not to exceed 600: watts.

The radioactive-material shall be in the foru of fuel, rods, or plates,l fuel-assemblies, or meeting the requirements of special form radioactive.

j material.

j 500 gm U-235 equivalent mass;{or.

(ii)

Neutron scurces meeting the requirements of special form radioactive s

material.

l 500 gm.U-235 equivalent mass'.

Decay heat not to exceed.50 watts; or (iii). Irradiated Pu0 and U0 fuel rods clad.in Zircalloy or stainless:

steel. 'Decaybeatnottoexceed600 watts.-Allfuelrods~shall' 2

be contained within'a' closed 5-inch Schedule-40 pipe with a" maximum useable length of 39-5/8-' inches.

1,200 gm fissile material with no more than 300 gm-fissile material.

1

'per 5-inch Schedule 40 pipe.

4 g

5 x"

+

j a----------------____________________________________~.

1 O'

CONOmtN8 (continuid)

LPage3'-CertificateNo.;9044"'RevisionNo'.15--DocketNo.71-9044:

~ 1

~

j5.j(b')'(1) Contents (continued)

~

(iv)

Process solids, either dewatered.. solid, or> solidified in;a secondary sealed container meeting the requi,rements for low specific activity radioactive material.

(v): Solid nonfiss'ile irradiated-metal hardware, reactor c'ontrol rods' (blades)/ reactor start-up sources.'and segmented boron carbidez t'ubes (tube contents'not to exceed a Type A quantity).t a

E (vi) Radioactive'(Hot Cell)-waste materials immobilized!with cement groutsandcontainedrindf55: gallon'(or. extended 55-gallon' drum) 00T Specification <17H 'or 17C steel! drum,111d -and closure.2 The Waste material'must be. packaged in"accordance withithetProcedural Outline of theJImobilization of Cell Waste lUsingLCement Grout, of the December 1,1981? supplement.

The~ cement grout:must;be at least.50Lvolume percent-(estimateo) of th'e drum contents and relatively uniformly, distributed throughout the drum. 'At least 3/4" thick layer of; grout must cover 'all radioactive-waste contents.

Decay heat not to' exceed 100 watts, and fissile' material not to exceed 500 grams U 235' equivalent mass.

(c)

Fissile Class III:

Maximum number of packages

. Contents 5.(b)(1)(i),5.(b)(1)(ii),-

per shipment 5.(b)(1)(iii),orf5.(b)(1)(vi):

Two(2).-

6.

The U-235 equivalent mass is determined by U-235 mass pluscl.66 times U-233' mass

,plus 1.66 times Pu mass.

7. ' (a)

For any package containing water and/or' organic substances which could radiolytically generate combustible gases, determination 1must be made by test.and measurements 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 time:

(1) The hydrogen generated must be limited to a molar quantity that would~

i te no more'than %S by volume (or equivalent limits for other 1

inflamable. gases) of the secondary contginer ' gas; void if present at

)

STP (i.e., no more than 0.063 g-moles /ft at 14.7 psia andL70 F);'or l

(ii)

The. secondary container and cask cavity must be inerted with a diluenti

~

to assure that oxygen must be limited to 5% by volume in those portions of the package which c~ould havel hydrogen greater than 5%.

A r

r

" q' m'._-

-L----

---

f

I O,

'Y l

CONOlTi:NS (continuid) m

~,!i l

gH l

Page 4~-' Certificate.No. - 9044

' Revisio'n No. J 15

? Docket' No. 7129044-g Il y

I For any package' delivered to a carrier for transport,ithe secondary container 3 l]

must be prepared for shipment in the same' manner in-which determination for

,a cas generation is.made.- Shipment: period begins when the package'is prepared:

ij lsealed);andmustlbecompletedwithintwiceitheexpected:shipmentLtime.

,I (b). For any package containingLmaterialsiwith radioactivity concentration not'.

I l;,

exceeding that for: low specific activity material,/and shipped within;10 days of preparation, or within 10l days after venting effdrums or other g

secondary containers, the determination in (a),above/need-not"be made...and i

the~ time restriction,..in:(a) above does not: apply.

Io G

Q T' O w I J) y^

For packaging of neutron' sources,E he c"avity'drii' aline' must-be~ closed with 'a I

8.'

t n

plug with a: melting temperature of?200 F and the cask lcavityj must be dry before j j delivery of the package.to'a carrier.

y-la 9.

For-packaging of other than neutron sources, the cask'm'st:be. delivered-to a, Iq u

carrier' dry and the cavity drain line'must be closedLwith a' plug which will

+

1

-1 maintain its seal at. temperatures up to,at.least.620*F.:

Il l

lJ 10.

Shoring must be provided to minimize movementioffcontents;duhin'g accident l conditions of transport.

j

!g j ga 11.

Prior to each shipment the silicone rubber 1id' gasket (s)'.must % inspected. 'This I"

gasket (s):must be. replaced if inspection'shows any defects or every twelve (12).

I 1

l jl months, whichever occurs first.

Cavity drain line-must'be sealed with appropriate-sealant' applied to threads'of_ pipe' plug.

id 12.

For packaging' of neutron sources, 50 : times the measured neutron dose rate at onel 1

1' meter from the' surface of a cask must be less than 1,000 mrem /hr.

I i

13. 'The contents c'escribed in 5(b)(1)(iv) must be transported'.on a. motor vehicle,-

I l1)

' railroad car, aircraft, inland water crafts, or hold lor deck;of a seagoing.

vessel' assigned for sole use of the licensee..

g 1

14.

The package authorized by this certificate is hereby. approved'.for use under the i

general license provisions ct 10 CFR 971.12.

I I

.15.

Expiration date:

October 31, 1992.

l; I

I I

I i

R I

R I

IIj

.I i1 1

'g

+

1 1

I

_ _ _ - _ _ _ - _ _ _ _ = _ - _ _ _ - _ _

.m:

N,.,,., s r.s

.,..,.,..,,.<,.c,-e,,c.,w C2NDITISNS (continu:d)

. Page 5'.- Certificate No. 9044 - Revision No. 15 Docket No.'71-9044 REFERENCES q

General Electric Company application dated February 1,1982.

Supplements dated: March 30, 1982;. January,17 and February 4, 1983; April 28, 1986; and September 29, 1987.

t l

FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

Charles acDona Transportation Branch,C 1et Division of Safeguards and Transportation, NMSS' Date:

OCT 2 31987 E

i 1

- -_ o

k.'

\\.k NQ UNITED STATES

[ 'I

~

[ ~,

NUCLEAR REGULATORY COMMISSION

,jg. i muu a. 2om d

Transportation Branch Ap3roval Record.

Model lo. 1600 Package I

Docket No. 71-9044 l

l Revision No. 15 By application dated March,20, 1987, General Electric Company requested renewal i

of Certificate of Compliance No. 9044 and by application dated September 29, 1

1987, General Electric Company < requested the certificate of compliance be amended to cite the latest revisionLlevel.of the packaging drawing.- The drawing (No. 1290437, Rev. 6) has been revised to show the corrective action i

taken to isolate the tapped holes.for the lift lugs.from the annulus formed by the outer cask wall and the lift lug backing ring. The~ corrective action is-

~

being taken in response to an operating problem which developed on a similar package (Certificate of Compliance No. 9001).. It was observed that a fluid had leaked from two of the lifting lug bolt holes located on the side of the cask.

To isolate the tapped holes from the annulus. formed by. the lifting -lug backing ring, each tapped hole will be drilled and tapped.to a larger diameter

-)

and fitted with a threaded insert.

The insert is seal welded to the lift lug.

adapter plate.

l 1

The staff considers _the proposed corrective action. to be 'a satisfactory-resolution to the problem of restricting the-entry.of fluid into the annulus formed by the lift lug backing ring.

The modification of the bolt holes has no adverse effect on the ebility of the packaging to meet the requirements of 10 CFR Part 71.

j Chem-Nuclear Systeras Inc, requested an amendment to the certificate that would authorized the identification of their Model No. 1600 package as Model No.

CNS 1-13G.

To accommodate this request a separate Certificate of Compliance (No. 9216) will be issued for Model No. CNS l'-13G.

All references to Chem-Nuclear j

Systems, Inc. have been removed from Certificate of Compliance No. 9044 including q

condition 9 and the reference to Nuclear Plant Services supplement dated July 7, i

1985 and the 'resulting Condition 5.(b)(1)(iv).

i j

1

]

L$j i

~-

1 c..

n, l

j 41 i

f j

J.

Y i

d-.

q

.i A new Condition 7.has been added to the. certificate which ado (,'resse tNe 4

-J preparation.of packa'ges' containing--water and/or organic. substances which could-y

.radiolytically generate combustible gases.

i,

i The certificate of _ compliance has been' renewed. for a five y' ear term which expires October 31, 1992, y

3-l r

1 Charles E. MacDonald, Chief Transportation Branch.

-Division of Safeguards and Transportation,.NMSS.

..1 1

OCT 2 31967

~y.

Date:

..t q

,1 I.

l 4

.s--

i.

- q

'l l

l l

4 l

-l 1

1 1

j 1

o

. Il

. }'

e

.a l

8

- ~..

_1