ML19323H405

Application to Amend License SNM-960,to Increase Allowable Loading of Fissile Matl to 1200 G

ML19323H405
Person / Time
Site:	07109044
Issue date:	07/03/1973
From:	Cunningham G GENERAL ELECTRIC CO.
To:
Shared Package
ML19323H393	List: ML19323H392 ML19323H405
References
16385, NUDOCS 8006120480
Download: ML19323H405 (10)

Text

'

GENER AL( ELECTRIC

""""^" ""'" '

C DIVISION GENERAL ELECTRIC COMPANY VALLECITOS NUCLEAR CENTER IRRADIATION PROCESSING OPERATION VALLECITOS ROAD, PLEASANTON, CALIFORNIA 94566, Phone (415) 862-2211 July 3, 1973 Mr. C. E. MacDonald, Chief Transportaticn Branch Directorate of Licensing U.S. Atomic Energy Cocaission Washington, D.C. 20545 Re f:

1) License Smt-960 Docket 70-754

2) Amendment 71-32 to Smi-960, 4/18/69

3) Amendment 71-50 to S21-960, 4/5/71

Dear Mr. MacDonald:

General Electric lus shipped large quantities of byproduct materials and limited quantities of fissile materials in the Model 1600 Shipping Cask under Amendments 71-32 (4/18/69) and 71-50 (4/5/71) to License Smi-960 tithout incident for.aeveral years. General Electric now petitions the Atemic Energy Commission for an amendment to Smi-960 shich will increase the allowable loading of fissile material.

Specifically, General Electric requests that the fisaile loading of the Model 1600 Shipping Cask be increased to 1200 grams provided:

(1) the fissile sca torial is contained in s tandard was te liners cons truc ted of 5-inch schedule 40 pipa,iich a maximum inside length o2 39-3/16 inches, (2) no more than four such liners are shipped at one ti=e, (3) each liner contains no more than 300 grams fissile, and (4) the cask is provided uith a positioning lat.tice such that the geometry shcim in Figure 1 is main-ta i ned.

The purpose of the positioning lattice is to improve the criticality characteris tics o f the cask.

However, as noted in the criticality analysis, the liner is not necessary to maintain the cask is a suberitical conditica (i.e., the close proximity cases).

The waste liners are closed with either a bronze or brass screw top with a h-inch "0" ring gaske t.

The gasket material cuy be either buna-N rubber or neoprene, t

IRRADIATION SERVICES AND RADIOISOTOPES FOR RESEARCH AND INDUSTRY

=

8006130 g

Mr. C. E. MacDonald July 3, 1973 The cask will be shipped as Fissile Class III.

The criticality analysis was performed using the computer code ANISN(

a discrete ordinates, one-dimensional transport theory code. The problem was solved in two parts using geometries as shown on Figure 1.

The dimensions and material regions for this figure are given in Tables 1 and 2.

The normal transport configuration is shown on Figure 1 as solid lines.

The dotted lines represent one of t!.e accider.t cases considered.

From this analysis we conclude that the 1600 series cask is critically safe for the shipment of fggg) standard waste liners each containing 300 gm fissile (Pu239, n233, or U for a total cask limit of 1200 grams fissile.

This limit is safe with no restriction as to fissile type or composition.

Four cases were considered in this analysis, the design shipping geometry, the design geometry flooded, and the cases when the four liners are in close proximity.

These geometries are shown in Figure 1.

The results of the criticality calculations are as follows:

1.

Design Geometry k, ff 0.720

=

2.

Design Geometry - Flooded k,gg 0.713

=

3.

Clore Proximity Geodetry k,f f 0.959

=

4.

Close Proximity - Flooded k, gg 0.976

=

The case of two casks adjacent to each other was consigered by calculating the infinite multiplication (k ) and migration area (M ) from properties determined by the ANISN calculation for the cask. The effective multipli-cation of the two cask system was then determined from the buckling rela tionship. This value was found as:

k,ff 0.773

=

Table 1.

1600 Series Cask Dimensions Radius R-cm R1 48.895 R2 47.625 R3 34.925 R4 33.655 R5 31.4325 R6 31.115 R7 Dimension determined by liner cell calculation

• R8 7.7203 R9 7.065 RIO Dimension determined by liner cell calculation

• R11 17.96 1.414YR, where R

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Mr. C. E. MacDonald July 3, 1973 Table 2.

Material Regions Region Ma terial Identification 1

S tainless Outer Liner 2

Lead Shield 3

S tainless Inner Liner 4

Void Void 5

S tainless Liner Bucket 6

Fuel Cell Homogenized Fuel, Liner, Void 7

Aluminum Liner 8

Fissile Material Fuel Material The first part of the problem consisted of an infinite cylinder cell calculation for the individual fuel liners. This calculation was performed to obtain cell-weighted cross-sections to be used in subsequent calculations.

Each cell consisted of the fissile material / moderator combination contained within the wasta liner, the waste liner itself, and the void surrounding each liner. The waste liner dimensions are as shown in Table 1.

Each liner was assumed to contain 300 grams of plutonium-239, the VNC limit for each liner, with the remainder of the liner filled with water. For the actual waste liner volume, the resulting Pu density was 8

0.023 "2 cm The voluce fraction for the water was determined by assuming a theoretical plutonium density of 11.46 gm/cm3 (the most likely density of fissile was te material to be shipped). The atom densities used in the cell calculation are shown in Table 3:

Table 3.

Atom Densities Calculation Ma terial Isotopes Atom Densities (Atom /b-cm)-

~

Liner Cell Liner Aluminum 6.023 x 10

-5 Fissile Plutonium-239 5.796 x 10

~

Hydrogen 6.673 x 10

-2 Oxygen 3.337 x 10 Cask S tainless Iron 6.01 x 10"

' Chromium 1.72 x 10" Nickel 8.81 x 10"

~

Shield Lead 3.31 x 10

/

s

Mr. C. E. MacDonald July 3, 1973 For the normal shipping configuration, the cell size was determined by dividing the total volume of the cash cavity into four equal volumes and calculating an equivalent cell radius. This radius represented the outer dimension of the ANISN problem with void between this and the actual outer diameter of the liner.

For normal shipping configura tion, this dimension was: R = 15.55 cm.

For the case where the liners were assumed o

in close proximity, as shown by the dotted circles in Figure 1, this dimension was taken as: R = 8.98 cm.

The geometry used in the liner cell calculation is shown $n Figure 2.

Figure 2.

Liner Cell Geometry R

4;\\

Fissile Waste

\\(

/,

w Aluminum Liner Void The p(2, 3, 4) with Problem was set up for ANISN using Los Alamos 16-group cross-section sets 1 scattering.

The problem was calculated for an infinite cylinder with a " white" boundary condition en the outer diameter.

The output from the calculaticn included flux and cell volume weighted 16-group macro-scopic cross-sections.

The second part of the problem consisted of evaluating the criticality safety of the entire cask. This was also done using ANISN where the neutron cross-sections obtained from the liner cell calculation were used for the material region that included the liners. For the normal transport con figura tion, this region included the entire volume within the stainless liner bucket. The dimensions for the "close proximity' case, the dotted areas in Figure 1, were determined by considering the total volume for four liner cells and calculating an equivalent radius for that volume. The region between this volume and the stainless liner bucket was assumed to be void. One additional off-normal case was considered, the normal transport geome try-flooded.

This was done by substituting water for void in the cell calculation to obtain cross-sections for the cask calculation.

General Electric believes that the above analysis clearly demonstrates the safety of the proposed fissile load for the Model 1600 Shipping Cask.

/

e NYN9* --

-

• we=e

%.eunup -me-g, ewe gemae pe -

ye.

,q,

5-July 3, 1973 Mr. C. E. MacDonald Attachment A to this subm ttal contains the revised pages to our basic i

application for the Moc'41 1600 (Appendix D to License SNM-960).

General Electric also requests that the provisions of this submittal and the provisions of Amendments 71-32 and 71-50 be consolidated into a single amendment to SNM-960 and that the new composite amendment be approved under the General License provisions of 10CFR71.12(b) (new designation).

Thank you for your timely consideration of this application.

Sincerely, G. E. Cunningham a

Adminis trator - Licensing SW Att.

s 9

t

/

s

6-l July 3, 1973 Mr. C. E. MacDonald i

Re ferences l

l 1.

Engle, W. W., "A User's Manual for ANISN", K-1693, Union Carbide, Oak Ridge, Tenn., March 30, 1967, i

2.

Hansen, G. E. and Roach, W.

H., "Six and Sixteen Group Cross-Sections for Fast and intermediate Critical Assemblies", LAMS-2543, Los Alamos Scientific Lab, Los Alamos, New Mexico, November,1961.

3.

Connolly, L. D., et al., "Los Alamos Group Averaged Cross-Sections,"

LAMS-2941, Los Alamos Scientific Lab., Los Alamos, New Mexico, July,1963.

4.

Personal Communication, Smith, D. R. to Walker, E. E., Los Alamos Scientific Lab, Los Alamos, New Mexico, February 26, 1971.

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ATTACHMEN1 A Amended Pages to Appendix D, SNM-960

/

• ****

• N ** * -N m en = me

.e % w.

.-.w

~_-

Sizs:

Bottom plata is 68 inchrs square end

-inch thick. The cylindrical collar is 39 inches in diameter by 3 inches high. The I-beams are 3 inches high by 68 inches long.

Conatruction:

The cylindrical collar houses two sets of 1-b inch by 1-inch by t-inch steel energy absorbing angles separated by a

-inch thick carban s teel mid-plate.

The cask rests on this assembly. The collar is welded to the %-inch thick carbon steel base pla te.

Four I-beams are welded in parallel to the base plate.

Attachment:

Two diametrically opposed tie blocks to accept jacket attachment bolts.

5.12.2 Package Description - Contents (a) General Radioactive material as the metal or metal oxide, but specifically not loose powders.

Two ABC neutron sources (d1 x 10 n/sec/

source)..

(b) Form Citd, encapsulated or contained in a me tal encasement of such material as to withs tand the combined effects of the internal heat load and the 1475 F fire with the closure pre-tested for leak tightness.

(c) Fissile Content Not to exceed 500 grams of U-235, 300 grams U-233, 300 grams Pu, or a pro-rated quantity of each such that the sum of the ratios does not exceed unity,*or not to exceed 1200 grams fissile provided:

(1) the fissile material is contained in standard waste liners con-structed of 5-inch schedule 40 pipe with a maximum inside length of 39-5/16 inches, License No.

SNM-960 Docket No.70-754 Sect. No.

5.12.2

pog, Appendi.c D Amend. No.

Date June 11, 1973 Amends Sect.(s) 5.12.2

• *- * ' w ee w e m e

. - +.~ n

v-(2) no more than four such liners are shipped at ont time, (3) each liner contains no more than 00 grams fissile, and (4) the cask is provided with a positioning lattice to maintain separation between the liners.*

(d) Radioactivity That, quantity ;of any radioactive material which does not generate spontaneously more than 600 thermal watts by radioactive decay (50 there:a1 watts for the wet shipment) and which meets the requirements of 49CFR173.393.

License No.

SNM-960 Docket No.70-754 s.ce, No, 5.12.2 Page Appendix D Amend. No.

Date J""* 11' 1973-5.12.2 7A Amends Sect.(s) l 16385 t

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