ML19210B753

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Requests Renewal of Certificate of Compliance 5980 for Model 600 Shipping Container.Forwards Consolidation of Application W/Subsequent Applications for Amends.Oversize Drawings for PDR & Fee Encl
ML19210B753
Person / Time
Site: 07105980
Issue date: 10/10/1979
From: Cunningham G
GENERAL ELECTRIC CO.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
14427, NUDOCS 7911120253
Download: ML19210B753 (38)
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ENGINEERING GENERAL ELECTRIC COMPANY, P.O. BOX 460, PLEASANTON CALIFORNIA 94566 DIVISION October 10, 1979 Mr. Charles E. MacDonald, Chief Transportation Branch Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ref:

Certificate of Compliance No. 5980

Dear Mr. MacDonald:

The General Electric Co., Vallecitos Nuclear Center (VNC), requests that Certificate of Compliance No. 5980 for the G.E. Model 600 shipping con-tainer be renewed.

In support of this request we are enclosing a consolidation of our original

. application with subsequent applications for amendment into a single package. This consoli'dation includes the changes contained in our appli cation of October 8, 1979. The submittal of May 21, 1974, a criticality analysis demonstrating the safety of the approved 1200 gram fissile loading is enclosed as Attachment A.

As the certificate expires on October 31, 1979, and as the. container is in frequent use, VNC requests that a temporary extension be granted to permit the use of the container while the application for renewal is evaluated.

Enclosed is a check for $150.00 for the renewal fee as required by 10CFR170.31.

If your staff has any questions concerning this application for renewal, please contact me at 415-862-2211, Ex. 4330.

Sincerely,

h. l. h _

G. E. Cunningham Sr. Licensing Engineer

/11 cc:

R. R. Rawl FEE PAID U.S. Dept. of Transportation Office of Hazardous Materials Operations}3 )89 Washington, D.C. 20590 7911130 M

f .h GENERAL ELECTR7" SHIELDED CONTAINER - MODEL 600 1.0 Package Description - Isckaging (a) General: All containers of this model, for purposes of constructing additional containers of this model, will have dimensions of plus or minus 5% of the container dimensions spec-ified in this application, and all lifting and/or tiedown devices for additional con-tainers of this model if different from the lifting and/or tiedown devices described in this application will satisfy the requirements of 10CFR71.31(c)(d). ~ This container is detailed in G.E. drawings 161F470, 693C293, 144F650, 212E247, 106D3892, 129D4684, 12904685, 195F162, and 106D3898 attached. Shape: An upright circolar cyl.inder shielded cask and an upright circular cylinder protective jacket with attached square base. Size: Shielded cask is 34 inches in diameter by 59-7/8 inches high. The protective jacket is 72-7/8 inches high by 63-1/2 inches across the box section. The base is 63-1/2 inches square. , Construction: The cask is a lead-filled carbon and stainless steel weldment. The protective jacket is a double walled structure of 1/2 inch carbon steel plate and surrounds the cask during transport. The square base is 1/2 inch carbon steel with four I-beams attached. 1313 190 1.0 Package Description - Packaging (continued) (a) (continued) Weight: The cask weighs 15,000 pounds. The protective jacket and base weigh 3,000 pounds. The weight of the additional plastic shielding for neutron sources is approximately 750 pounds. The lead liners weigh 500 pounds and 4810 pounds respectively for a maximum total weight of approximately 23,300 pounds. (b) Cask Body Outer Shell: 3/8 inch thick steel plate, 59-7/8 inches high by 34 inches diameter with a 3/8 inch bottom plate and a 3/8 inch top flange. Cavity: 3/8 inch stainless steel wall and bottom plate, 20-1/2 inches inner diameter by 46 inches deep. Shielding Thickness: 6 inches of leak on sides, 6 inches of lead. beneath cavity. In the wet shipment case the cavity will be filled with water with a 5 inch air space. Penetration: One 1/2 inch outer diameter by 0.063 wall stainless steel tube gravity drain line from the center of the cavity bottom to the side of the outer shell near the cask bottom with a 1/2 - 14 NPT pipe plug. General Electric may, at its discretion, permanently close and seal the drain line for this container model with no interference to other structural properties of the cask. Filters: None. }3}) ] Lifting Devices: Two diametrically opposed ears welded to sides of cask, covered by protective jacket during transport. Two additional ear mounting hole patterns are provided for red'undant' ears which are shipped separately. 1.0 Package Description - Packaging (continued (b) Cask Body (continued) Primary Coolant: l Air (c) Cask Lid Shape: A right conical cylinder attached to flat plate Size: Top plate is 34 inc6 1s diameter by 3/4 inch thick. Bottom plate is 24 inches diameter by 3/8 inch thick. The conical cylinder is 26-1/4 inches diameter at top by 6-3/8 inches high by 24 inches diameter at bottom. Construction: Lead-filled steel clad cylinder welded to circular steel plates. Closure: Six - 1 inch UNC-2A steel bolts equally spaced 60* apart on a 30 inch diameter bolt ci rcle. Closure Seal: A minimum 3/15 inch thick flat silicone rubber or equivalent gasket between body and lid. Penetrations: None. Shield Expansion Void: None. Weight: l 1450 pounds. Lifting Device: Single steel loop, 1 inch diame' ' steel rod locatdd in center of lid top. t.vvered by pro-tective jacket during transport. T 192 1.0 Package Description - Packaging (continued) (d) Liner - Inner Liner: Shape: Basically a right circular cylinder with a hollow center. Size: 7-1/2 inch outer diameter by 3-3/8 inch inner diameter by 36 inches high. Construction: 1/8 inch thick top and bottom circular plates wel P " a 1/8 inch thick lead-filled stainless steel clad cylinders. Weight: l 500 pounds Attachments: 3/8 inch diameter stainless steel curved rod 7 inches long is attached to the top plate. Liner - Outer Liner (Body) Shape: Basically a ri.ght circular cylinder with a ~ hollow center. Size: 20 inch outer diameter by 7-7/8 inch inner diameter by 43 inches high. Construction: 3/8 inch thick top and bottom circular plates welded to 3/8 inch thick' lead filled stainless steel clad cylinders. Weight: l 4530 pounds (without lid). Attachments: Two - 3/4 - 10VNC-2B x 2 inch deep holes 180 apart in top plate to accept a 3/4 - 10VNC-2A eyebolt. Liner - Outer Liner (Lid) Shape: Two right circular cylinders of different diameters attached to flat plates. 1313 J93 1.0 Package Description - Packaging (continued) (d) Liner - Inner Lirer, (continued) Liner - Outer l'ner (Lid):(continued) Size: All plate is 3/8 inch thick. Top plate is 17 inches diameter while the bottom plate is 14 inches diameter. Both cylinders are 2 inches high. Construction: Lead filled steel clad cylinders welded to circular steel plates. Weight: l 280 pounds. Liner - Poly-ethylene: Shape: A right circular cylinder with a hollow center cavity. Size: 20-inch outer diameter by.38-3/4 inches high; the inner cavity is 2-1/4 inches in diameter by 22-1/4 inches deep; the liner is equipped with an 8-inch diameter by 8-1/2 inch stepped plug. Construction: The liner is of 6061 aluminum with welded construction. The cylinder walls are 1/8-inch thick. The top and bottom plates on the lid and the bottom of the cylinder are 1/4-inch thick. The top plate of the cylinder is 1/2 inch thick. Shielding is provided by 2% borated polyethylene filler. Weight: l Aporoximately 750 pounds. Attachments: Two 3-inch by 3-inch by 1/2-inch ears with 1-1/2 inch diameter connection hales for lifting device attachments. )T)b bb y 1.0 Package Description - Packaging (continued) (e) Protective Jacket Body Shape: Basically a right circular cylinder with open bottom and with a protruding box section diametrically across top and vertically down sides. Size: 72-7/8 inches high by 63-1/2 inches wide across the box section. Outer cylindrical diameter is 40-1/2 inches. Inner diameter is 36 inches. A 5-1/2 inch wide by 1/2 inch thick steel flange is welded to the outer wall of the open bottom. Construction: Carbon steel throughout. Double walled con-struction. The walls are 1/2 inch thick. One and a quarter inch air gap between cask shell and inner jacket wall and a one and a half inch gap between inner and outer jacket walls, throughout. Six 12 inch high by 1/2 inch thick gussets are welded to the outer cylin-drical wall and flange. Including the two box sections, the gussets are spaced 45 apart.

Attachment:

Eight inch bolts connect the protective jacket bo'dy, through the flange to the pallet. Jacket Lifting Two rectangular 1 inch thick steel double Device: loops located on top of the box section at the corners. The loops are respectively 7 inches long by 3 inches high by 6 inches wide and 9 inches long by 3 inches by 6 inches. These loops are used only for lifting the jacket, not the complete assembly. }3i3 1.0 Package Description - Packaging (continued) (e) Protective Jacket Body (continued) A;sembly Lifting and Two diametrically opposed 3 inch thick steel Tiedown Devices: ears welded to sides of box section, each ear has a 1-1/2 inch ho.le to accept cable clevis or cable; or an optional rectangular tie-down yolk fabriGced 3/16-inch wall rec-tengt h milled steel tubing. This yolk also has 3-inch thick shackle ears and surrounds the protruding box section on top of the cylindrical jacket. Penetrations: Slots along periphery of the protective jacket at the bottom, slots in box section under lifting loops. Allows natural air circulation for cooling. (f) Prott-tive Jacket Base Shape: Hollow cylindrical weldment with square bottom j plate. Eight I-beams are welded to the l bottom plate. Size: Bottom plate is 63-1/2 inches square and 1/2 inch thick. The cylindrical collar is 36 inches in outer diameter by 3 inches high. The I-beams are 3 and 4 inches high by 63-1/2 and 62-3/8' inches 1ong. Construction: The cylindrical collar houses two sets of l 1-1/2 inch by 1-1/2 inch by 1/8 inch steel energy absorbing angles separated by a 1/2 inch thick carbon steel mid-plate. The cask rests on this assembly. The collar is welded to the 1/2 inch thick carbon steel base plate. Four I-beams are welded in parallel to the base plate.

Attachment:

Eight 2-inch diameter nuts are welded to the bottom of the base for jacket attachment. 2.0 Package Description - Contents (a) General Radioactive materiai as the metal or metal oxide, but specifically not loose powders. Neutron sources and other radioactive materials in special form. (b) Form Clad, encapsulated or contained in a metal encasement of such material as to withstand the combined effects of % internal heat load and the 1475 F fire t the closure generically pre-tested for i u tightness. (c) Fissile Content Not to exceed 500 grams of U-235, 300 grams U-233, 300 grams Pu, or a prorated 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, (2) no more than four such liners are s'hipoed at one time, (3) each liner contains no more than 300 grams fissile, and (4) the cask is provided with a positioning lattice to main-tain separation between tha liners. (d) Radioactivity That quantity of any radioactive material which does not generate spontaneously more than 600 thermal watts by radioactive decay and which meets the requirements of 49CFR173.393. Shipments,of neutron sources will be limited to 50 thermal watts. (e) Heat l Total maximum internally generated heat load not to exceed 600 thermal watts. (50 thermal watts for neutron sources). 1313 197 2.0 Package Description - Contents (e) Heat (continued) Although equilibrium temperature recordings were not taken for this package loaded to 600 watts thermal, General Electric will analyze by test or other assessment each con-tainer heat loading with and without liners, as the specific case dictates, prior to ship-ment to verify that the requirements of 10CFR71.35 will be satisfied. Reference is made to the GE - Model 100 Application, Section 5.1, Exhibit B, for a method of internal heat load analysis and heat dissipation.

3. 0 Package Evaluation (a)

Genera 1 There are no components of the packaging or its contents which are subject to chemical I or galvanic reaction; there is no coolant except f or air. The protective jacket is bolted closed during transport. A lock wire and seal of a type that must be broken if the package is opened is affixed to the cask closure. If that portion of the pro-tective jacket which is used in the tie-down system or that portion which constitutes the principal lifting device failed in a manner to allow the protective jacket to separate from the tiedown and/or lifting devices, the basic protective features of the protective jacket and the enclosed cask would be retained. The package (contents, cask, and protective jacket) regarded as a simple beam supported at its ends along its major axis, is capable of withs".anding static load, nonnal to and distributed along its entire length equal to five times its fully loaded weight, without generating stress in any material of the pac.kagin 3.0 Package Evaluation (continued) (a) General (continued) in excess of its yi51d strength. The pack-aging is adequate to retain all contents when subjected to an external pressure of 25 pounds per square inch gauge. Reference is made to the GE-Model 100 Application, Section 5.1, Exhibit C, for a method -of detennining static loads. The calculative methods employed in the design of the protective jacket are based on strain rate studies and calculations and on a literature search of the effects on materials under im-pact conditions. The intent was to design a protective jacket that would not only satisfy the requirements of the U.S. Nuclear Regulatory Cor, mission and tne Department of Transportation prescribing tne procedures 4d standards of packaging and shipping and the requirements governing such packaging and shipping but would protect the shielded cask from significant deformation in the event of an accident. In the event that the package was involved in an accident, a new protective jacket could be readily supplied and the shipment continued with minimal time delay. The effectiveness of the strain rate calcula-tions and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the General Electric Shielded Container - Model 100 (Ref.: Section 5.1.3 of the Model 100 Application). The protective jacket design for the General Electric Shielded Container - Model 600 will be scaled from the design of the Model 100 in accordance with the cask weight and dimensions, 1313 199 3.0 Package Evaluation (continued) (a) General (continued) maintaining static load safety factors greater than or equal to unity, and in accordance with the intent to protect the shielded cask from any defomation in the event of an accident. (b) Normal Transport Conditions Thermal: Packaging components, i.e., steel shells and lead are unaffected by temperature extremes of -40*F and 130 F. Package contents, at least singly-encapsulated or contained in specification 2R containers, but not limited to special form, will not be affected by these temperature extremes. Pressure: The package will withstand an external pressure of 0.5 times standard atmospheric pressure. The cask was pressure tested under water to 11 PSIG with no detectable leakage. Vibration: Inspection of the Model 600 casks used since 1961 reveals no evidence of damage of signifi-cance to transport safety. Water Spray and Since the container is constructed of metal, Free Drop: there is no damage to containment resulting from dropping the container through the stan-dard drop heights after being subjected to water spray. Penetration: There is no effect on containment or overall spacing from dropping a thirteen pound by 1-1/4 inch diameter bar from four feet onto the most vulnerable exposed surface of the packaging. 1313 100 3.0 Package Evaluation (continued) (b) Normal Transport Conditions (continued) Compression: The loaded container is capable of with-standing a compressive load equal to five times its weight with no change in spacing. Summary and

Conclusions:

The tests or assessments set forth above provide assurance that the product contents are contained in the Shielded Container - Model 600 during transport and there is no reduction in effectiveness of the package. (c) Hypothetical Accident Conditions General: The affectiveness of the strain rate calcu-lations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the GE Shielded Container - Model 100 (Ref.: l Sect, ion 5.1.3 of the Model 100 Application). Extrapolations of the Model 100 data were used in the design and construction of the GE Model 600 protective jacket. The in-creased weight and dimensions of the Model 600 container over the Model 100 con- - tainer necessitated a protective jacket wall of 1/2 inch steel compared to a 1/4 inch wall for the Model 100. Drop Test: The design and construction of the GE Model 600 protective jacket was based on an extrapo-lation of the proven data generated during the design and construction of the GE Model 100 and on the results of cask drop experi-ments by C.B. Clifford(1)(2) and H. G. Clarke, Jr.(3) The laws of similitude were used in an analytical evaluation (3)(4) to determine the protective jacket wall thickness 1313 01 3.0 Package Evaluation (continued) (c) Hypothetical Accident Conditions (continued) Drop Test: (continued) that would withstand the test conditions of 49CFR173.398(c) and 10CFR71.36 without breaching the integrity of the Model 600 cask. The evaluation, described in GE - Model 1000 Application, Section 5.9, Exhibit A, indicated a protective jacket wall thickness of 1/2 inch. (1) C.B. Clifford, The Design, Fabrication and Testing of a Quarter Scale of the Demonstration Uranium Fuel Element Shipping Cask, KY-546 (June 10, 1968). (2) C.B. Clifford, Demonstration Fuel Element Shipping Cask from Laminated Uranium Metal-Testing Program, Proceedings of the Second International Symposium on Packaging and Transportation bf Radioactive Materials, Oct. 14-18, 1968, pp. 521-556. (3) H.G. Clarke, Jr., Some Studies of Structural Response of Casks to Impact, Proceedings of the Second International Symposium of Packaging and Trans-portation of Radioactive Materials, Oct: 14-18,1968, pp. 373-398. (4) J.K. Vennard, Elementary Fluid. Mechanics, Wiley and Sons, New York,1962, pp. 256-259. Drop Test: (continued) The intent of the design for the GE Model 600 is, during accident conditions, to sustain damage to 'the packaging not greater than the damage sustained by the GE Model 100 during its accident condition tests (ref.: Section 5.1.3(c) of the Model 100 Application). It is expected that damage not exceeding that suffered by the GE Model 100 will result if the GE Model 600 is subjected to the 30 foot drop test. Puncture Test: The intent of the design for the GE Model 600 is to sustain less or equal damage to the packaging during accident conditions than the deformation suffered by the GE Model 100. It is expected that deformation 1313 102 3.0 Package Evaluation (continued) (c) Hypothetical Accident Conditions (continued) Puncture Test (cont.) not greater than that sustained by the GE Model 100 will be received by the GE Model 600 in the event that the package is sub-jected to the puncture test. Thennal Test: Because of the various combinations of lead liners and thermal loads available with this container, the THTD fire transient was not run. However, reference is made to the shielded container Models 100, 700, and 1500 which demonstrate the effectiveness of the double walled steel jacket as a fire as well as a crash shield. General Electric will analyze by test or other assessment each container heat load with and without liners as the individual case dictates, to verify that the loaded container will withstand the 30 minute 1475 F fire without significant lead melting in the cask. Water Immersion: Since optimum moderation of product material is assumed in evaluations of criticality safety under accident condition the water immersion test was not necessary. The cask was pressure tested under water to 11 PSIG with no detectable leakage. Summary and The accident tests or assessments described

== Conclusions:== above demonstrated that the package is adequate to retain the product contents and that there is no change in spacing. Therefore, it is concluded that the General Electric Shielded Container - Model 600 is adequate as packaging for the contents specified in 2.0 of this application. }3}3 4.0 Procedural Controls ! Vallecitos Site Safety Standards have been established and implemented to dssure that shipments leaving the Vallecitos Nuclear Center (VNC) comply with the certificates issued for the various shipping container models utilized by the VNC in the normal conduct of its business. Routine audits are perfonned to assure compliance with these licenses and permits. Each cask is inspected, leaktested, and radiographed prior to first use to ascertain that there are no cracks, pinholes, uncontrolled voids or other defects which co0ld significantly reduce the effectiveness of the packaging. After appropriate U.S. Nuclear Regulatory Commission approval, each package will be identified with a welded on steel plate in accordance with the labeling requirements of 10CFR71 and any other informati,on as required by the Department of Transportation. 5.0 Fissile Class - Class III An analysis has indicated that not greater than the following amount of fissile material may be shipped in any single container: Grams U-235, Grams U-233 Grams Pu(Fissile) < l.0 500 300 300 The container shall be provided with a rigid metal liner so that the fissile material is confined to a cylindrical geometry with an inner diameter not exceeding 7.0 inches (nominal). The Density Analog Method as described in SNM License Application for VNC, Docket 70-754, Section 5.4.4, dated April 18, 1966, was used for calcu-lations. Alth'ough this method is normally used to calculate the number of units for transport under Class II, it was used in this case to demon-strate that one shipment of two casks would be subcritical. No credit was taken in the calculations for Pu-240 or other poisons present. The cask cavity was filled with water, and the fuel was homo-genized with the water in the volume of the 7.0 inch liner. This water filling was done to represent the accident case and to allow for wet loading of the casks. The full results of the calculations are shown in the table below: 1313 104 5.0 Fissile Class - Class III (continued) Fissile Material Quantity Safe Number Pu-239 0.3 Kg 33 U-233 0.3 Kg 51 U-235 0.5 Kg 210 In all cases, regardless of fissile mixtures involved, the loadings will be assumed to be exclusively Pu. The contents will be shipped dry. 6.0 Modes of Transportation All modes with the exception of passenger aircraft are requested. 13i3 D E;

1 e e e ATTACHMENT A CRITICALITY ANALYSIS e 0 1313 106 .e n; Y:.$ 9.{ e ~5', .~ b . i~. y, e

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^ ENERGY GENERAL ELECTRIC COMPANY. VALLECITOS NUCLEAR CENTER. VALLECITOS ROAO DIVISION PLEASANTON, CALIFORNIA 94566. Phone (415) 862 2211 May 21, 1974 Mr. C. E. MacDonald, Chief Transportation Branch Direc torate of Licensing Regulation U.S. Atomic Energy Commission Washington, D.C. 20545 Ref:

1) License SNM-960 Docket 70-754
2) Amendment 71-31 to SNM 960, 4/18/69
3) Amendment 71-57 to SNM 960,11/19/73

Dear Mr. MacDonald:

General Elcetric has shipped'large quantitics of byproduct materials and limited quantities of fissile materials in the Model 600 Shipping Cask under Amendment 71-31 (4/18/69) to License SNM-960 without incident for several years. General Electric now petitions the Atomic Energy Comma.sion for an amendment to SNM-960 which will increase the allowable loading of ' fiss ile ma terial. Specifically, General Electric reques ts that the fissile loading of the Model 600 Shipping Cask be increased to 1200 grams provided: (1) the fissile material is contained in s tandard waste liners constructed of five-inch schedule 40 pipe with a maximum inside length of 39-5/16 inches ; (2) no more than four such liners are shipped at one time; (3) each liner contains no more than 300 grams fissile; and (4) the cask is provided with a punitioning la ttice such tha t the geometry shown in Figure 1 in co inta ined. Tlic purpose nf the positioning lattice is to improve the criticality charac-teristics of the cask. The waste liners are closed with either a bronze or brass screw top with a (-inch "0" ring gaske t. The gasket material may be either buna-N rubber or neoprene. These waste liners are exactly the same.as those used in the Model 1600 container. The cas'k'will be shipped as Fissile Class III. O / 1313 107 o

Mr. C. E. HacDonald 2-Hay 21, 1974 o General Electric reques ts tha t a very timely review be made of this application in order to expedite shipment of irradiated AEC-owned fissile caterial to the AEC for disposal. We believe tha t this request is reasonable in the light of your review of our submittal for the same fissile loading for the Model 1600 conta iner (Re f. 3). The two containers are extremely similar with, from the viewpoint of criticality safety, the significant difference being the smaller cavity of the Model 600. Drawings of the two casks are enclosed as Attach-cent B to this submittal. The analysis was perforned using the computer codes ANISN a discrete ordina tes one-dimensional transport code, and KEN 0(2), a Monte Carlo code. ANISN was used to analyze the normal shipping design geometry while KENO was used for the accident case. From this analysis we conclude that the 600 series cask is critically safe for the shipment of four standard waste liners each containing 300 go fissile ~ (Pu239 or Uz35) for a total cask limit of 1200 grams fissile. This limit is safe with no restriction as to fissile type or composition. It is not intended 233 to ship U in this container in excess of the presently permitted limits. The results of the criticality calculations are as foll.ows: 1. Design Geometry k,gg-0.869 2. Accident (Close Proximity - Flooded) = k, gf 0.945 +.029 = The error associated with the accident case result was computed at 3. The infinite multiplica tion of this cask (i.e., an infinite array of such casks) was calculated for the design geometry to be k, 0.974 =

  • lhe design geometry was analyzed using the same method as was used to analyre the 1600 series cask.

This geometry is shown on Figure 1. The dimensions and ma terial regions for this figure are given in Tables 1 and 2. The problem was solved in two parts using the ANISN code and Los Alamos 16-group cross-sec tion se ts (3, 4, 5) with Pg sca ttering. -The first part consis ted of defining an infinite cylinder cell with 4 " white" boundary condition on the outer diameter for the individual fuel liner. This calculation resulted in a 16-group cell weighted macroscopic cross-section set to be used in subsequent calculations. The outer dimension for the cell calculation was determined so as to preserve the a tom densities of the materials within the cavity normalized to the cavity volume. Each c411 consisted of the fissile material / moderator combirtation contained within each liner, the vaste liner itself, and the void surrounding each liner. Each liner shall be limited to 300 gma of fissile material which will result' in a fissile density of 0.023 gm/cm p = g O 1313 108' l

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1313 109 ~

Mr. C. E. MacDonald May 21, 1974 Table 1: 600 Series Cask Dimensions Radius R-en R 43.18 g R 42.2275 2 R 26.9875 3 R 26.035 4 R 15.00 S R 7.7203 6 i l Tabic 2: Material Regions Region Ma terial Identification 0 1 S tainles s Outer Liner 2 Lead Shield 3 S tainless Inner Liner 4 Void Void 5 Aluminum Waste Liner 6 Pu & H O Fissile Waste 2 This density was used to determine the atom density in the liner for the ff in fini te cylin'dcr. The volume frac tion for the wa ter was de termined by assuming a theoretical plutonium density of 11.46 gm/cm3 (the most likely i density of the fissile waste material to bc shipped). The atom densities i for this problem are shown in Table 3. l l i \\h\\s I i

Mr. C. E. MacDonald I4-May 21, 1974 Table 3: Atom Densities Ma te r ial Isotopes Atom Densities (a tom /b-cm) Fissile Plutonium-239 5.796 x 10 ~ Hydrogen 6.673 x 10 ~2 Oxygen 3.337 x 10 -2 Liner Aluminum 6.023 x 10 S tainless S teel Iron 6.01 x 10" Chromium 1.72 x 10" ~ Nickel 8.81 x 10 -2 Shield 1.ga d 3.31 x 10 With the homogenized cell-weighted set of cross-sections obtained for the liner in the first ca lc ula t ion, the entire cask was analyzed with ANISN. O" The cell-weighted cross-sections were used to describe the cask cavity and the rema inder of the cask was described discre tely by ca terial region. It miy,ht be noted here tha t the resultant kegg for this configuration is higher than the corresponding results obtained for the 1600 series cask - 0.869 600 Series Cask: k,gg = 1600 Series Cask: k,ff 0.720 = This is the result of the smaller cavity in the 600 cask causing the linets to be closer together than in the 1600 cask. The accident case where the liners are assumed to be somehow arranged together in the center of the cavity and flooded, was first analyzed in a cannur similar to the apprcach used for the design geometry. The results of this ca*culation were: k,gg 0.981 = Although this number is less than 1.00, the confidence of suberiticality of j the system is reduced because of the necessity in making assumptions deviating from the' true description of the system to facilitate analysis. The assumption that could have the most effect on this number is the assumption of an infinite cylinder along the Z-axis. In order to account for axial leakage, it is O necessary to ao to a two-or three-dimensionat code. For thts grebtem. xts0 a Monte Carlo code, was selected. This code permits three-dimensionat description of sys tems for analysis.' The cask was described in KENO as shown in,' Figure 2. i l -~ <l ), l I. ; 3 l

}fr. C. E. MacDonald 5-May 21, 1974 O The liners were described as box types in the se tup with the " core" region then described as a 2 x 2. array of such boxes. The cask itself was then input as reflector regions. TheANISN problem previously described was re-run to obtain adjoint fluxes with which neutron weighting factors for the re ficc tor The number densities used for this problem are aiven regions were determined. 1culari ns were then performed using a Knight-modifiedI6) in Table 3. The llansen and Roach ( set of cross-sections obtained from Oak Ridge National Laboratory. The results of this calculation are given on Figure 3. Af ter 4320 historice the average was 0.945 with the eaxic:um of 0.974 and the minimum of 0.915 at the 99% confidence level. Fig. 2: 600 Series Cask - Three-Dimensional Representation 7.065 cm Liner: R = y79 g g 7.7203 cm j i R a o I-99.854 H = i' I .I ' l/a-yg-J.

  • /s "

ll M*M + o H,p Cask R-in R-cm H-in H-cm I r, Cavity 10.25 26.035 46 116,84 P,m a t i l s Liner 10.623 26.9875 46.75 118.745

  • O Lead 16.625 42.2275 58.75 149.125 7, g g I

l I I Liner 17.0 43.18 59.875 152.083 l 1 + i \\ j g l i e i t l 1 4 3/s ' 1 l l

3. y.

1;,ix 11, s O )

s Mr. C. E. MacDonald May 21, 1974 ~ Fissile Box Geometry I I I I R l g' 1 l ll ll 21.84 cm l R = I f l l R' = 18.6403 ll lI l3 L General Electric believes that the above analysis clearly demons trat.as the safety of the proposed fissile load for the Model 600 Shipping Cask. Q Attachmen A to this submittal' contains the revised pages to our basic appli-cation for the Model 600 (Appendix D to License SNM-960). Thank you for your timely consideration of this application. Sincerely, ~ G. E. Cunningham Administrator - Licensing EV Atts S O 1313 113 l ~

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Re fe rence s 1. Engle, W. W., "A Users Manual for ANISN", K-1693, Union Carbide, Oak Ridge, Tenn., March 30, 1967. 2. Whitesides, G. E., and Cross, N. F., " KENO - A Multigroup Monte Carlo Criticality Program", CTC-5, Oak Ridge Computing Technology Center (1969). 3. Hansen, G. E., and Roach, W. H., "Six and Sixteen Group Cross-Sections for Fast and Intermediate Critical Assemblies", LAMS-2543, Los Alamos Seidntific Lab, Los Alamos, New Mexico, November,1961. 4. Connolly, L. D., et al, "Los Alamos Group Averaged Cross-Sections", LAMS-2941. Los Alamos Scientific Lab., Los Alamos, New Mexico, July, lhh l S. Personal Communication, Smith, D. R. to Walker, E. E., Los Alamos Scientific Lab, Los Alamos, New Mexico, February 26, 1971. 6. Whitesides, G. E., KENO Cross-Section Library. t 4 f \\3,J f \\ l i O .i \\ .}}

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