ML20006F489

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Application for Renewal of Certificate of Compliance 5980 for Model 600.Weights of Components Modified to Agree W/ Weights on Certification Drawing 129D4742.Small Lead Liner Eliminated.Fee Paid
ML20006F489
Person / Time
Site: 07105980
Issue date: 02/27/1990
From: Cunningham G
GENERAL ELECTRIC CO.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9002280082
Download: ML20006F489 (22)
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Text

{{#Wiki_filter:.y )( (M 1/: 5910 i .V-o a GE Nuclear'Enctgy Geners! Deanc comew l V. %4evros kieer Cente' rc aw no vesa ws aus E ?iv653'It0!\\ (A Mb(N - g i ? . February 27,'1990 t I f C. E. MacDonald, Chief i . h. Transportation Branch .a as Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission. Washington, D.C. 20555

Reference:

Certificate of Compliance No. 5980 Docket 71-5980

Dear ~Mr. MacDonald:

Certificate of Compliance No. 5980 for the Model 600 shipping container-expires on March 31 1990. Ceneral Electric requests that this certificate. be renewed. 'A consolidated application for the Model 600 was submitted to your staff on

November 15,J1984. That application (Enclosure A to this renewal application) remains essentially unchanged except for

1.- The-weights of the components [ Sections 1.0(a) and 1.0(d)) were modified to agree with those on Certification Drawing 129D4742. A total packago -weight has-been listed. I 2; 'A small lead liner'(~500 pounds) has been eliminated [Section 1.0(d)]. i 3. -The length of the bolt attaching the protective jacket to the base was i changed from 5 -inches to 4-1/2 inches (change reflected on Certification Drawing 129D4742). The 5 inch bolt extends 1/2-inch below the nut and I can interfere with forklift operations. There are no safety consequences as the 4-1/2-inch bolt fully engages the nut. 4. References to neutron sources have been eliminated [ Sections 2.0(a), (d), and (e)). 5. The description of the fissile contents [Section 2.0(c)] has been g modified to reflect the wording of the current certification. ,[3 6. The-results of a THTD thermal analysis for the hypothetical accident conditions were added [Section 3.0(c)]. '9002280082 900227 h ,_I s PDR ADOCK 07105900 NpJ PDC

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d' 1 .C. E. MacDonald. February 27, 1990-The Certification Drawings are included as Enclosure B. .:i ' - Revised preshipment and maintenance summary procedures are included as Enclosure C. Loading / unloading procedures are being revised and will be submitted separately. If you or your staff have any questions concerning this application, please contact'me on (415) 862 4330. Thank you.. .An application fee check of $150.00 is enclosed. Sincerely, l' h / 1 i G. E. Cunnin am Senior Licensing Engineer /ca Enclosures I 1 i i 1 I u

I i' I + ENCLOSURE A-i CONSOLIDATED APPLICATION I OCTOBER 10, 1979 UPDATED: FEBRUARY 21, 1990 LI I ~ LI "I

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T' I q k GENERAL ELECTRIC SHIELDED CONTAINER - MODEL 600 .I 1.0 Packace Descrintion - Packacinc (a) General: All containers of this model, for purposes of-constructing additional containers of_this model, will have dimensions of plus or minus i el'_- 5% of the container dimensions specified in this application; and all lifting and/or tiedown devices for additional containers 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 GE Drawings 129D4742, 129D4743, 129D4744, and 129D4745 attached. Shape: An upright circular cylinder chielded cask and an upright circular cylinder _ protective .I jacket with attached square base. Size: Shielded cask is 34 inches in diameter by E.. 59-7/8 inches high. The protective jacket is _5 72 7/8 inches high by 63-1/2 inches across the_ box section. The base is 63-1/2 inches I square. Construction: The cask is a lead filled carbon and stainless steel weldment. The protective .I jacket is a' double-walled structure of 1/2-inch carbon steel plate and surrounds the cask during transport. The square base .I. is 1/2-inch carbon steel with four I-beams attached. Weight: The cask weighs 15,000 pounds. The I protective jacket and base weigh 5,750 pounds. The lead liner weighs 4,650 pounds. The total weight of the package is g ap,rox1. ate 1, 2e,2ee pounes. I I I

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1.0 Packace Descriotion - Packaging (Continued)

(b) Cask Body f Outer Shell: 3/8 inch-thick steel plate, 59 1/8 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 .a plate, 20 1/2 inches inner diameter by 46 fg inches deep. Shielding Thickness: 6 inches of lead on sides, 6 inches of lead beneath cavity. Penetration: One 1/2 inch outer diameter by 0.065 wall L 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, at its discretion, may permanently close and seal the drain line for this container model with no interference to other structural properties of the cask. 1 Filters: None. IT' Lifting Devices: Two diametrically opposed ears welded to j sides of cask, covered by protective jacket 1.. during transport. Two additional ear Ll mounting hole patterns are provided for . E redundant ears which are shipped separately. .l g Primary Coolant: Air.

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(c) Cask Lid I Shape: A right conical' cylinder attached to flat plate. IL Size: Top plate is 34 inches 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. j Construction: Lead-filled steel clad cylinder welded to "j circular steel plates. Closure: Six 1-inch 8-UNC-2A steel bolts equally !.g spaced 60* apart on a 30-inch-diameter bolt I g_ circle. l L. .h;

l g (g -1.0' Packane Descriotion - Packacine - [} (c) Cask Lid (Continued) i . Closure Seal: l A minimum 1/4 inch thick flat silicone rubber - [ or equivalent gasket between body and lid, or a molded silicone rubber seal bonded to an i aluminum backup plate as shown in CE Drawing 129D4744. Penetrations: None. .I s Shield Expansion Void: None. Weight: 1,450 pounds. Lifting Device: Single steel loop, 1-inch-diameter steel rod located in center of lid top. Covered by I-protective jacket during transport. l (d) Liner (Body) I. Shape: Basically, a right 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. . eight: l 4,400 pounds (without lid). W g Attachments: Two 3/4 10 UNC-2B x 2-inch-deep holes 180' 'i5 8Part in t P P ate to accept a 3/4 10 UNC-2A l l eyebolt. l l Liner (Lid) Shape: Two right circular cylinders of different , g diameters attached to flat plates. . 3 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 L-l high. g-Construction: Lead-filled steel clad cylinders welded to .g; circular steel plates. Weight: l 250 pounds.

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' Package Descrintion' - Packaging ~ (Continued). (e).. Protective Jacket Body I Shape: Basically, a right circular cylinder with open bottom and with a protruding box section P diametrically across top and vertically down sides. 'g-Size: 72 7/8 inches high by 63 1/2 inches wide >E

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"'ar x 1"dri a' ~ diameter is 40 1/2 inches. Inner diameter is 36 inches. A 5 1/2-inch wide by 1/2 inch-il thick steel flange is welded to the outer 5 wall of the open bottom. 'g Construction: Carbon steel throughout. Double walled g' construction. The walls are 1/2-inch thick. v One-inch air gap between cask shell and inner jacket wall and a 1 1/4-inch gap between inner and outer jacket walls throughout. Ten 12-inch high by 1/2-inch thick gussets are welded to the outer cylindrical wall and flange. Including the two box sections, the gussets are spaced 30' apart.- g,

Attachment:

l Eight 4-1/2-inch bolts connect the protective g jacket body through the flange to the pallet. Jacket Lifting Two rectangular 1 inch-thick steel double ,l. -Device: loops located on top of the box section at

5 the corners. The loops are, respectively, 7 inches long by 3 inches high by-3 inches wide I;

and 9 inches long by 3 inches by 6 inches. l These loops are used only for lifting the jacket, not the complete assembly. I;- Assembly Lifting Two diametrically opposed 3-inch-thick steel-and Tiedown Devices: ears welded to sides of box section; each car has a 1-1/2-inch hole to accept cable clevis or cable. l penetrations: Slots along periphery of the protective jacket at the bottom; slots in box section I-under lifting loops. Allows natural air circulation for cooling, h:I I I 4-

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i 1.0 Packare Descrintion -'Packarinn- (Continued) (f)- Protective' Jacket Base Shape: ' Hollow cylindrical weldment with square i bottom plate. Eight I-beams are welded to the bottom plate. . Size: Bottom plate is 63-1 2 inches. square'and f

  • 3 1/2-inch thick.- The cylindrical collar is 36 5

inches outer diameter.by 3 inches high.- The I-beams are 3 and _4 inches high by 63 1/2-and 62-3/8 inches long. ] i; Construction: The cylindrical collar houses two' sets of 1-1/4 inch by 1 1/4-inch by'1/8-inch steel ' g _.. energy absorbing angles separated by a i 3. 1/2 inch thick carbon steel mid plate'.- The' I cask rests'on'this assembly. The collar is l' g_ welded to the 1/2-inch thick carbon steel g' base plate. Four I beams 'are welded in parallel to the base plate. l - ~ I-_ Attaclaent: Eight.2-inch diameter nuts are welded to the j bottom of the base for jacket attachment. 1.'I: l l l l l LI. Lg E, LI n,

u~p-p 3 l-2.0' Packare Descrintion - contenta- .) j [lB i (a) General Radioactive material as the metal or metal 3 oxide, but specifically not loose powders. l Radioactive materials in special form. (b) EME Clad, encapsulated or contained.in a metal encasement of such material as to withstand l ,I the combined effects of the internal heat load and the 1,475'F fire with the closure L generically pre tested for leak tightness. j (c) Fissile Content Not to exceed 500 grams of U 235, 300 grams U-233, 300 grams Pu, or a prorated quantity l of each such that the sum of the ratios does not exceed unity. When the contents of this-l paragraph are in the form of irradiated-reactor fuel, the fuel must have been cooled for a' minimum of 90 days, and no more than. 10,000 Ci of noble gases must be available

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for release from the fuel rod plenums. ) Lg The cask must be leak tight to 1 x 10'3 'g 8 ata cm /see under normal conditions of - 1 transport. Not to exceed 1,200 grams fissile provided: (1) the fissile material is ll contained in standard waste liners L q constructed of 5-inch Schedule 40 pipe with a maximum inside length of 39-5/16 inches, (2) L I.. no more than four such liners are shipped at one time,.(3) each liner contains no more 'l than 300' grams fissile, and (4) the cask is provided with a positioning lattice to L maintain separation between the liners. (d) Radioactivity That quantity of any radioactive material I which does not generate. spontaneously more than 600 thermal watts by radioactive decay and which meets the. requirements of 49CFR173.393.

(e) lita Total maximum internally generated heat load

~j not to exceed 600 thermal watts, iE I IE-Although equilibrium temperature recordings were noc taken for this package loaded to 600' l I'. watts thermal, General Electric will analyze 9 by test or other assessment each container p heat loading with and without liners, as the f specific case dictates, prior to shipment to verify that the requirements of 10CFR71.35 will be satisfied. Reference is made to the GE Model 100 Application, Section 5.1, i Exhibit B, for a method of internal heat load analysis and heat dissipation. t o" LI

m. LI 3.0 Packane Evaluation (a) ceneral There are no components of the packaging or its contents which are subject to chemical or I galvanic reaction; there is no coolant except for air. The protective jacket is bolted closed during transport. A lock wire and g seal of a type that must be broken if the l3 package is opened is affixed to the cask closure. If that portion of the protective lg jacket which is used in the tiedown system or 'E rh*' P " "hi*h * "****"*** 'h* Pri"**Pa2 lifting device failed in a manner to allow + the protective jacket to separate from the I tiedown and/or lifting devices, the basic protective features of the protective jacket and the enclosed cask would be retained. The -g package (contents, cask, and protective E Ja*kat) retarded== a 81mP c beam supported l at its ends along its major axis, is capable of withstanding static load, normal to and I distributed along its entire length equal to five times its fully loaded weight, without generating stress in any material of the I packaging in excess of its yield strength. The packaging is adequate to retain all contents when subjected to an external pressure of 25 pounds per square inch gauge. I Reference is made to the GE Model 100 Application, Section 5.1, Exhibit C, for a method of determining static loads. The calculative methods employed in the design of the protective jacket are based on

I strain rate studies and calculations and on a literature search of the effects on materiais under impact conditions.

The intent was to design a protective jacket that would not I only satisfy the requirements of the U.S. Nuclear Regulatory Commission and the Department of Transportation prescribing the l I' procedures and-standards of packaging and shipping and the requirements governing such packaging and shipping but would protect the l-shielded cask from significant deformation in L the event of an accident. In the event that the package was involved in an accident, a ll new protective jacket could be readily l supplied and the shipment continued with l5 minimal time delay. I' The effectiveness of the atrain rate calculations and engineering intuitiveness in the design and construction of protective i 7 nI

I 3.0 Egekage Evaluation (a) Ceneral (Continued) jackets were demonstrated with the CE Shielded Container Model 10 (Ref. Section I 5.1.3 of the Model 100 Application). The protective jacket design for the CE Shielded Container Model 600 will be scaled from the I design of the Model 100 in accordance with the cask weight and dimensions, maintaining static load safety factors greater than or equal to unity, and in accordance with the I intent to protect the shielded cask from any deformation in the event of an accident. (b) Normal Transport Conditions Thermal: Packaging components, i.e., steel shells and lead, are unaffected by temperature extremes I of -40'F and 130*F, Package contents, at least singly encapsulated or contained in specification 2R containers, but not limited I to special form, will not be affected by these temperature extremes. I. 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 raiveals no evidence of damage of significance to transport safety. Water Spray and Since the container is constructed of metal, Free Drop; there is no damage to containment resulting I from dropping the container through the standard drop heights after being subjected to water spray. Penetration: There is no effect on containment or overall spacing from dropping a 13 pound by I 1-1/4 inch diameter bar from four feet onto the most vulnerable exposed surface of the packaging, Compression: The loaded container is capable of withstanding a compressive load equal to five times its weight with no change in spacing. Summary and The tests or assessments set forth above

== Conclusions:== provide assurance that the product contents are contained in the Shielded Container - I-Model 600 during transport and there is no reduction in effectiveness of the package. I 4 8 I

v i a 3.0 Packace Evaluation (Continued) (c) Hvoothetical Accident Conditions' General: The effectiveness of the strain rate calculations and engineering intuitiveness in !g the design and construction of protective ) 'g jackets were demonstrated with the GE i Shielded Container Model 100 (Ref. Section l 5.1.3 of the Model 100 Application). ,E Extrapolations of the Model 100 data were ,5 used in the design and construction of the CE Model 600 protective jacket. The increased i ,g weight and dimensions of the Model 600 )

g container over the Model 100 container i

necessitated a protective jacket wall of i 1/2 inch steel compared to a 1/4 inch wall for the Model 100, j i Drop Test: The design and construction of the CE Model I 600 protective jacket were based on an extrapolation of the proven data generated during the design and construction of the CE Model 100 and on the results of cask drop i experiments by C. B. Clifford(1)(8) and H. G. Clarke, Jr. s. The laws of similitude were used in en analytical evaluation (s)(4) I to determine the protective jacket vall E thickness that would withstand the test conditions of 49CFR173.398(c) and 10CFR71.36 I g without breaching the integrity of the Model 5 600 cask. The' evaluation described in the CE Model 1000 Application, Section 5.9, Exhibit t A, indicated a protective jacket wall thick. ness of 1/2 inch. l I 3C. B. Clifford, The Desien. Fabriention and Testine of a Ouarter Scale of i the Demonstration Uranium Fuel Element Shionine Cask, KY.546 (June 10,1968). [ W 8C. B. Clifford, Demonstration Fuel Element Shionine Cask from faminated Uranium Metal Testinc Procram, Proceedings of the Second International I Symposium on Packaging and Transportation of Radioactive Materials; October 14 18, 1968; pp. 521 556, I all. C. Clarke, Jr., Some Studies of Structural Response of Casks to Imnaet, l Proceedings of the Second International Symposium on Packaging and Trans-l. portation of Radioactive Materials; October 14 18, 1968; pp. 373 398. ll

  • J. K. Vennard, Elementary Pluid Meehanies, Wiley and Sons, New York, 1962,

.ie pp. 256 259. lI 9 l ---s--u-

3 v-i i 3.0 Packag Evaluation ) (c) Hvoethetical Accident Conditions ,I Drop Test: The intent of the design for the GE Model 600 l (Continued) is, during accident conditions, to sustain t-damage to the packaging not greater than the I damage sustained by the GE Model 100 during i its accident condition tests (Ref. Section 5.1.3(c) of the Model 100 Application). It is expected that damage not exceeding that I 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 I deformation suffered by the GE Model 100. It is expected that deformation not greater than that sustained by the GE Model 100 will be I received by the GE Model 600 in the event that the package is subjected to the puncture test. Thermal Test: A thermal analysia of the Model 600 using the THTD computer code determined a maximum lead t.emperature of 508'F during the 1,4M'F fire. I With the liner, the maximum lead temperature was 440*F. .I 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 _I was pressure tested under water to 11 psig with no detectable leakage. .E Summary and The accident tests or assessments described L5

== Conclusions:== above demonstrated that the package is adequate to retain the product contents and that there is no change in spacing. .I~ Therefore, it is concluded that the GE Shielded Container Model 600 is adequate as packaging for the contents specified in 2.0 l of this application. 1 I 'I j l

I 4.0 Procedural Controla Vallecitos Site Safety Standards have been established and implemented to I assure that shipments leaving the Vallecitos Nuclear Center (VNC) comply with the certificates issued for the various shipping container models utilized by VNC in the normal conduct of its business. Routine audits are performed to assure compliance with these licenses and permits. Each cask b '.'nd, leak tested, and radiographed prior to first use to ascertain tha. re are no cracks, pinholes, uncontrolled voids or I other defects which could significantly reduce the effectiveness of the packaging. I 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 10CTR71 and any other information as required by the Department of Transportation. I 5.0 Fissile Class - Class III I An analysis has indicated that not greater than the following amount of fissile material may be shipped in any single container: lg Grams U-2M h p U-233 Mrs Pu(Pissild ig 500 300 300 j I 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). 1 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 calculations. Although this method normally is used to calculate the number of units for transport under Class II, it was used in this case to l demonstrate that one shipment of two casks would be subcritical. l ll No credit was taken in the calculations for Pu 240 or other poisons l3 present. The cask cavity was filled with water, and the fuel was homogenized with the water in the volume of the 7.0 inch liner. This l water filling was done to represent the accident case and to allow for l wet loading of the casks. The full results of the calculations are shown in the table below: Fissile Material Ouantiry Safe Number l g. Pu 239 0.3 kg 33 / U 233 0.3 kg $1 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. . I i

.. - _ - - - -. - -.. -. ~ - I I I I m-- A I CRITICALITY ANALYSIS I L 'I J l i 1 l' I' l lI L s I I I I-I

M F J .I I G E N Eli A L h E LE CTRIC " * '^" ENERGY fi GENERAL ELECTRIC COMPANY, VALLECITC$ NUCLEAR CENTER, VALLECITOS ROAD DIVISION PLEASANTON, CALIFORNIA 94566, Phone (415) 862 2211 May 21, 1974 j b Hr. C. E. MacDonald, Chie f I Transportatior. Branch Directorate of Licensing Regula tion l U.S. Atomic Energy Commission i Washiustot4 D.c. 20545 j 4 P Ref:

1) License SNM-960 l

,I Docket 70-754 1

2) Amendment 71-31 to SNM 960, 4/18/69
3) Amendment 71-57 to SNH 960,11/19/73 i

I, Dear Mr. MscDonaldt General Electric has shipped large quantities of byproduct materials and i limited quantities of fissile materials in the Model 600 Shipping Cask r under Amendment 71-31 (4/18/69) to License SNM-960 without incident for l several years. General Electric now petitions the Atomic Energy Commission I for an amendment to SNM-960 which will increase the allowable loading of fissile material. I specifically, General Electric requests that the fissile loading of the Model 600 Shipping Cask be increased to 1200 grams provided: (1) the fissile material is contained in standard waste liners constructed of five-inch schedule 40 pipe with a maximum inside length of 39-5/16 inches; I (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 positioning lattice such that the geometry shown in Figure 1 is maintained. I W e purpose of 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 k-inch "0" ring gasket. We 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 cask will be shipped as Fissile Class III. I' y E 4 m a x @e g

I ~ Mr. C. E. MacDonald May 21,1974 General Electric reques ts that a very timely review be made of this application in order to expedite shipment of irradiated AEC-owned fissile material to I the AEC for disposal. We believe that this request is reasonabic in the light of your review of our submittal for the same fissile loading for the Model 1600 conta ine r (Re f. 3). The two containers are extremely similar with, from the viewpoint of criticality safety, the significant difference being the smaller l' cavity of the Model 600. Drawings of the two casks are enclosed as Attach-ment B to this submittal. O) The analysis was performed using the computer codes FISN , a discrete ordinates one-dimensional transport code, and KEN 0(2, a Monte Carlo code. 1 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 essk is critically safe for the shts ment of four standard waste lincu ea:h containing 300 gm fissile (Pu239 or U 35) for a total cask limit of 1200 gums fissile. This limit is safe with no restric tion as to fissile type or composition. It is not intended 233 to ship U in this container in excess of the presently permitted limit.s. The results of the criticality calculations are as follows: 0.869 1. Der,ign Geometry k,gg = 2. Accident (Close Proximity - Flooded) = k,fg 0.945 1 029 = i The error associated with the accident case result was computed at 33 The i infinite multiplication of this cask (i.e., an infinite array of such casks) was calculated for the design geometry to be 0.974 l k, = The design geometry was analyzed using the same method as was used to analyze I the 1600 series cask. This geometry is shown on Figure 1. The dimensions and material regions for this figure are given in Tables 1 and 2. The problem was solved in twg, parts using the ANISN code and Los Alamos 16-group cross-section se ts(,

5) with P1 sca ttering. The first part consisted of defining I

an infinite cylinder cell with a " white" boundary condition on the outer diameter for the individual fuel liner. This calculation resulted in a 16-group cell .g weighted macroscopic cross-section set to be used in subsequent calculations. 3 The outer dimension for the cell calculation was determined so as to preserve the atom densities of the materials within the cavity normalized to the cavity j volume. Each cell consisted of the fissile material / moderator combination contained within each liner, the vaste liner itself, and the void surrounding each liner. Each liner shall be limited to 300 gms of fissile material which will result in a fissile density of 0.023 gm/cm p = g I J

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I i Mr. C. E. NacDonald -3 Hay 21, 1974 { Table 1 600 Series Cask Dimensions Radius R-cm I k R 43.18 g R 42.2275 2 R 26.9875 j 3 R 26.035 4 R 15.00 5 R 7,7203 6 Table 2: Material Regions I Region Material Identifica tion 1 S tainless Outer Liner I 2 Lead Shield 3 S tainless Inner Liner ~ 4 Void void 5 Aluminum Waste Liner I 6 Pu&110 Fissile Waste i 2 LI This density was used to determine the atom density in the liner for the infinite cylinder. The volume fraction for the water was determined by g assuming a theoretical plutonium density of 11.46 gm/cm3 (the most likely g density of the fissile waste material to be shipped). The atom densities j for this problem are shown in Table 3. I I

m fj t I Mr. C. ' E. MacDonald May 21, 1974 i Table 3: Atom Densities I Material Isotopes Atom Densities (atom /b-em) l -5 Fissile Plutonium-239 5.796 x 10 Hydrogen 6.673 x 10' f -2 oxygen 3.337 x 10 Liner Aluminum 6.023 x 10*2 I I> -2 Stainless S teel tron 6.01 x 10 Chromium 1.72 x 10'I l Nickel 8.81 x 10' 3.31 x 10-2 shield Lead . I-With the homogenized cell-weighted set of cross-sections obtained for the j l liner in the first calculation, the entire cask was analyzed with ANISN. The cell weighted cross-sections were used to describe the cask cavity and the remainder of the cask was described discretely by material region. It I might be noted here that the resultant k,gg for this configuration is higher i than the corresponding results obtained for the 1600 series cask - f" 0.869 600 Series Caskt k,gg = 0.720 i 1600 Series Caskt k,gg = This is the result of the smaller cavity in the 600 cask causing the liners 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 manner similar to the approach used for the design geometry. The results of this calculation were: 0.981 k,ff = Although this number is less than 1.00, the confidence of suberiticality of "g the system is reduced because of the necessity in making assumptions deviating g from the true description of the system to facilitato 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 'I tecessary to go to a two-or three-dimensional code. For this problem, KENO, a Monte Carlo code, was selected. This code permits three-dimensional description ~ of sys tems for analysis. The cask was described in KENO as shown in Figure 2.

m N I l Mr. C. E. MacDonald May 21, 1974 I The liners were described as box types in the setup with the " core" region then described as a 2 x 2 array of such boxes. The cask itself was then input as reflector regions. The ANISN problem previously described was re-run to I obtain adjoint fluxes with which neutron weighting factors for the reflector regions were determined. The number densities used for this problem are iven in Table 3. The 6) }lansen and Roach (giculations were then performed using a Knight-modified set of cross-sections obtained from Oak Ridge Natienal Laboratory. I The results of this calculation are given on Figure 3. Af ter 4320 histories the average was 0.945 with the maximum of 0.974 and the minimum of 0.915 at the 997. confidenca level. I rig. 2: 600 Series Cask - Three-Dimensional Representation I 7.065 cm Liner: R = ,74 9 g 9 i R, 7.7203 cm = I I 99.854 H = l( (g, i s/g" E, l Vs* H, 106.998 = H, (> Cask R-in R-cm H-in H-cm r-Cavity 10.25 26.035 46 116.84 I Liner 10.625 26.9875 46.75 118.745 i Lead 16.625 42.2275 58.75 149.225 fu,f g I Liner 17.0 43.18 59.875 152.083 I I I i a. 3/8 ' l tw. I I -==wsmeg.em h o.m

0 I Mr. C. E. MacDonald May 21, 1974 - IL Fissile Box Geocietry t l l Y [R ql 21.84 cm l R = i _ _.. _.i R' = 18.6403 ll l l L General Electric believes that the above analysis clearly demonstratee the safety of the proposed fissile lo-d for the Model 600 Shipping Cask. Attachmen A to this subn.ittal contains the revised pages to our basic appli-cation for the Model 600 (Appendix D to License ShH.960). Thank you for your timely consideration of this application. Sincerely. i

4. c G. E. Cunningham Administrator - Licensing Att.

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~ 'I ~ I I l Re ference s 1. Engle, W. W., "A Usert Manuel for ANISN", K-1H3, Union Carbide, Oak Ridge, Tenn., March 30, 1907. 2. Yhitesides, G. E., and Cross, H. T., ")INO - A Multigroup Monte Carlo Criticality l*rograta", CTC-5, Oak Ridge Computing Technology Center (1969). 3. 11ansen, G. L., and Roach, W.11., "Six and Sixteen Group Cross-sections for Fast ar,d Intermediate Critical Assemblies", LAMS-2543, Los Alames Scientific La.b Los Alamos New Mexico, November,1961. i I 4.- Connolly, L. D., et al, "Los Alamos Group AveraSed Cress Sections", LAMS-2941, Los Alamos Scientific Lab., Los Alamos, New Mexico, July, 1963. 5. 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. I i I I I I I

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~. 03/22/90 g. r PRESHIPMENT INSPECTION AND MAINTENANCE

SUMMARY

ENERGY ABSORBING ANGLEG ENERGY ABSORBING TUBES SEPARATOR PIATE I 1. SCOPE This document provides the general requirements for the in service and annual inspections for the angles, tubes, and separator plate of the metal protective jacket assembly, l

I 2.

IN SERVICE INSPECTION ' I 2.1 The absorber angles and tubes must all be in place and serviceable. 2.2 Inspection of che visible angles on top of the Separator Plate prior to each shipment shall be used to infer the condition of the angles below I the plate. If the top angles are found to be damaged, the plate shall be removed to inspect the lower angles. If the top angles are acceptable, inspection of the lower set of angles is not required. 2.3 Angles, tubes, and plate shall be visually inspected for wear, crushing, or deformation prior to package assembly, t ' W 2.4 All angles, tubes, and plate ~shall be inspected at least once per year or at assembly for shipment, whichever comes later. 3. DOCUMENTATION g 3.2 Maintenance, repair, and replacement activities shall be documented. ) I 3 4

~. 08/23/90 [ e I i PRESHIPMENT INSPECTION AND MAINTENANCE SUFJLARY CASK LIFTING EARS I 1. 19911 This document provides the general requirements for the in service i inspections of cask lifting ears. 2. IN-SERVICE INSPECTION Prior to each usage, the lifting ears will receive a visual inspection to ( assure no significant physical / mechanical damage has been sustained from 't previous handling, such as cracked welds. f I 3. DOCUMENTATION I 3.1 Preshipment inspections shall be documented. I. 3.2 Maintenance, repair, and replacement activities shall be documented. 3 I g: - I I I M m e e m

i 02/28/90 I Ll l up PRESHIPMENT INSPECTION AND MAINTENANCE

SUMMARY

l 6. DRAIN PLUG l 1. SI.QIE This document provides the general requirements for the in service and i annual inspections for the cask drain plug. 2. IN SERVICE INSPECTION 2.1 Drain plugs shall be visually inspected for damage whenever they are f installed. 2.2 Plugs showing no obvious wear, corrosion or damage on the thread f diameter are acceptable for reuse. i I 3. e _ EN1 m eN j I 3.1 >< si e 1 1 P ti s 11 s e e. P

g 3.2 Maintenance and replacement activities shall he documented.

I I I I I

yv %D. 03/22/90' kg?' d: p 5 INSPECTION AND MAINTENANCE

SUMMARY

a ~,n CASK SEA 1 CASKETS h 1. SCOPE This docun.ent prevides the. general requirements for the in-service and. annual inspections for the cask seal gaskets. C 2.- IN SERVICE INSPECTION 2.1,Each cask seal gasket shall be examined ~ visually for defects prior to each shipment. I 2.2 A new cask seal' gasket will be installed every 12 months. 2,3' The gasket: shall provide a cask lid to body seal of greater than 0.001 atm cc/sec. l 3. DOCUMENTATION l 3 1 'Preshipment and annual. inspections shall be-documented, i l 4 3.2_ Repair and replacement activities shall be documented. I i - I E-

02/22/90 I PRESHIPMENT INSPECTION AND MAINTENANCE

SUMMARY

HIGH STRENGTH EAR BOLTS-LID BOLTS I 1. 10(TE I This document provides-the general requirements for the.in service and annual inspections for the cask lid bolts. I 2. IN SERVICE INSPECTION '2.1 Bolts shall be visually inspected fe;r proper identification and obvious . damage during each assembly. 2.2 Bolts with evidence of obvious wear or damage to the bolt shank or'to I the threads; corrosion; or improper < identification shall be replaced. I ~3. -DOCUMENTATION 3.1 Preshipment and annual inspections shall be documented. I 3.2 Maintenance, repair, and replacement activities shall be documented. I I I I I I I

w: 3 i 02/22/90 PRESHIPMENT INSPECTION AND MAINTENANCE

SUMMARY

JACKET BASE NUT JACKET HEX BOLTS I 1. SCOPE This document provides the general requirements for the in-service and annual inspections for the base nut and bolts. 2. IN-SERVICE INSPECTION' 2,1 In service inspection shall be performed during each assembly and consist'of insertion of an appropriate jacket bolt, by hand, into the-base nut, Bolts or nuts with minor damage shall_have their threads I-chased with an appropriate tap, Any-lubricants are acceptable. 2.2' Nuts and bolts shall be visually inspected at 1 cast once per year or at . assembly for shipment, whichever comes later, I I 3. DOCUMENTATION 3.1-Preshipment and annual inspections shall be documented.- 3,2 Maintenance, repair, and replacement activities shall be documented. I lI .I I: I "I}}

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