ML20128F878

Application for Renewal of & Rev to Certificate of Compliance 5942 for Model GE-700,revising Drawing 129D4770 to Show Added Fillet Weld.Supporting Documentation from 700225 Application for Amend to Model GE-700 Encl.Fee Paid

ML20128F878
Person / Time
Site:	07105942
Issue date:	05/30/1985
From:	Cunningham G GENERAL ELECTRIC CO.
To:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20128F883	List: ML20128F878 ML20128F886
References
25343, NUDOCS 8507080395
Download: ML20128F878 (65)

Text

,

$$h GENER AL $ ELECTRIC NUCLEAR ENERGY BUSINESS OPERATIONS GENERAL ELECTRIC COMPANY e VALLECITOS NUCLEAR CENTER e PLEASANTON, CAUFORNIA 94566 May 30,1985 N

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(y May,pngDgS a Mr. C. E. MacDonald, Chief Transportation Certification Branch o.n Office of Nuclear Material Safety and Safeguards g,l,i.py %

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Washington, D.C.

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Reference:

Certificate of Compliance No. 5942, Docket No. 5942.

Dear Mr. MacDonald:

General Electric hereby requests that Certificate of Compliance No. 5942 for the General Electric Model 700 shipping container be renewed. Enclosed in support of this request is an updated version of our consolidated application for the previous renewal (March 18, 1980).

This version has been reviewed to assure agreement between the text of the application and the certification drawings and to assure inclusion of applicable supplements to the application.

In addition, one of the certification drawings (129D4770) has been revised to show an added fillet weld on the cavity step (Zone E-4) to reinforce the weld joint.

Maintenance and handling procedures for the Model 700 are enclosed.

No quality assurance procedures for the manufacture or receipt of new containers are included as GE does not currently plan to obtain new containers.

All procedures are for demonstration only and are subject to change.

GE also requests that item 5.(a)(1) of the certificate be modified to read "Model No. 700".

A check for $150.00 is enclosed.

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l GENERAL ELECTRIC SHIELDED CONTAINER - MODEL 700 1.0 Package Description - Packaging (a) General All dimensions referenced in the descriptive section are nominal dimensions. Actual dimensional tolerances are contained in the certification drawings. 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 10CFR71.45.

This container will be used l

with and without the extension. The same protective jacket is used for both configurations. This container is shown in G.E. Drawings 129D4768 Rev. 3, 12904769, Rev. 4, and 12904770, Rev. 5, attached.

s Shape:

An upright circular cylinder shielded cask and an upright circular cylinder protective jacket with a rectangular base which bolts to the jacket.

Size:

The cask body is 36.80 inches in diameter by 64.25 inches high. With the extension, the cask is 78.62 inches high.

The protective jacket and its base are 100.30 inches high by 67 inches across the box section.

Construction:

The cask is a lead-filled carbon and stainless steel weldment. The protective jacket is a double walled structure of 0.62 l

inch carbon steel plate and surrounds the cask during transport. -

f

Weight:

The cask and lid weigh 24,000 pounds. The cask with extension weighs 28,700 pounds.

The protective jacket and base weigh 9,803 pounds. The maximum gross weight of the package is 40,200 pounds with the extension and 35,500 pounds without the extension.

(b) Cask Body-Outer Shell The body-outer shell is 0.38 inch steel plate, 64.25 inches high by 36.80 inches diameter. The top plate is made of two 0.38 inch plates welded together, while the bottom is a 0.38 inch thick spherical head, protected by.50 inch plate bottom support.

The extension is 0.50 inch thick steel plate 36.75 inches diameter and 14.12 inches high in the exposed portion, 21.00 inches diameter and 10.26 inches high for the portion which extends into the cask. The top plate is 0 F0 inch thick and the bottom plate is 0.25 inch thick.

Cavity:

0.25 inch stainless steel wall and bottom plate, 15 inches diameter by 40 inches deep.

With the extension, the cavity is 15 inches diameter by 54.50 inches deep.

l Shielding Thickness:

10.25 inches of lead on sides, 9.90 inches of lead beneath cavity and 9.88 inches of lead above cavity, both with and without the extension..

Penetration:

(1) A 0.50 inch, schedule-40 stainless steel l

siphon drain from the cask cavity bottom terminating in a valve on the upper surface of the cask.

(2) A 0.50 inch, schedule-40 l

stainless steel liquid fill line from the - _ _ _ - - _ _ - _ _ _ - _ _ _ _ _ _ -

side of the cavity to the side of the outer cask shell terminating in a valve guarded by a surrounding pipe sleeve. Both valves are covered by the protective jacket during transport.

Filters:

None.

Lifting Devices:

Two diametrically opposed, vertical 12 inch structural tees, 3.50 feet long welded to the cask shell with reinforced lifting slots located in the web. Covered by protective jacket during transport.

Pressure Rating Tested to 100 psig; normally unpressurized.

Primary Coolant:

Water or air.

Means for Sampling Vent and drain lines; both closed by valves and covered by protective jacket during transport.

Extension Closure Seal A 0.25 inch thick flat silicone rubber or equivalent gasket between extension and cask body when extension is used.

(c) Lid-Shape Flat plates and a cylindrical plug.

Size Top plate is 30.50 inches diameter by 0.75 inch thick, thickened to 1 inch by a disc at the flange. The bottom plate is 21 inches diameter by 0.25 inch diameter thick.

The right cylinder is 10 inches high.

Construction:

Steel weldment, lead filled.

3-

Closure:

Eight 3/4 UNC-2A by 3.00 inches long l

stainless steel bolts equally spaced 45*

apart on a 28 inch bolt circle. The bolts, which attach the extension to the cask body, are 15 inches long when the extension is used.

Lid Closure Seal:

A 0.25 inch thick flat gasket between body and lid. A metal backup ring is used in conjunction with the rubber gasket to prevent the gasket from moving out from its original position prior to the pressurization of the cask cavity.

Penetrations:

A 0.50 inch schedule-40 stainless steel l

pressure-vent line through the lid, terminating in a relief valve assembly guarded by a surrounding pipe sleeve and covered by the protective jacket during transport.

Pressure Relief Device 100 psi rating.

Shielding Expansion None.

Void Lifting Device:

0.75 inch thick by 8 inch high by 13 inch l

long vertical plate welded to the lid with a l

1.50 inch diameter hole centered 2.50 inches i

from the top edge to accommodate lifting hook or cable. Covered by protective jacket during transport.

(d) Protective Jacket Basically a right circular cylinder with Body Shape open bottom and with a protruding box 4

section diametrically across top and --

vertically down sides with a smaller box section extending from only one portion of the cylinder.

Size:

81 inches high by 67 inches across the main l

box section. Outer cylindrical diameter is 51.25 inches.

Inner diameter is 46 inches.

Construction:

Carbon steel throughout. Double walled construction. The walls are 0.62 inch thick, with a 4.60 inch air gap between outer cask wall and inner jacket wall and 1.50 inch air gap between inner and outer jacket walls.

Attachments Eight 2-inch hex head bolts connecting the jacket to the cask base at the bottom edge of the jacket.

Lifting and Tiedown Two 10 by 7 by 6 inch tapped to 3 inch at Devices the front steel blocks located on the sides of the main box section. A 4 inch diameter hole is cut through each block to accept cables or shackles.

Eight 1.25 inch diameter by 1.38 inch steel studs welded to the main box section at the level of the center of gravity of the assembly.

These are designed to allow the use of a basket hitch tiedown for the assembly.

Penetrations:

Air passage through a 4 inch diameter hole in the top of the inner protective jacket and out through two 1 inch by 6 inch horizontal slots on top of box section of outer protective jacket. _

(e) Cask Base - Shape 0.75 inch top and bottom plates separated by 0.50 inch steel ribs with center well for cask. Four hollow rectangular members underneath to provide strength and guides for lift forks.

Size:

The base is 66.50 inches by 51.50 inches by 18.55 inches.

Construction:

Carbon steel weldment.

Attachment Eight 2-inch hex head bolts connecting the base to the jacket at the bottom edge of the jacket.

-5A-

2.0 Package Description - Contents (a) General By-product material, source material ano special nuclear material contained in solid oxide or metal form and in special form.

(b) Form Clad encapsulated or contained in a metal encasement of such material as to withstand the combined effects of the internal heat 0

load and the 1475 fire with the closure pre-tested for leak tightness; or in special form.

(c)

Fissile Content (1) 740 grams U-235, provided that the maximum U-235 enrichment does not exceed 6 weight percent; or (ii) 1200 grams U-235, provided that the fuel material is in the fonn of MTR-type fuel elements with a minimum active fuel length of 23 inches; or (iii) 220 grams fissile; or (iv) 1650 grams U-235, provided that the maximum 235 enrichment does not exceed 3.5 weight percent; the fuel material is in the form of 88 rods loaded with 0.376 inch diameter pellets; and the fuel column length is at least 37 inches; or (v)

Not to exceed those values as presented in Figure 1. U0 weight litrits for the 2

model 700 shipping container, Exhibit A to this application; or (vi)

Not more than 10 ETR type fuel elements (GETRfuel)containingnotmorethan 510 grams U-235 per element; loaded and spaced in the stainless steel shipping basket as described in Drawing No.

10604150, Rev. O.

6-t i

2.0 (continued)

(d) Radioactivity That quantity of any radioactive material which does not spontaneously generate more than 6500 thermal watts by radioactive decay with, the package contents dry; or 1500 thermal watts for wet shipments, provided that the cavity shall contain at least a 1000 cubic-inch air void (at STP) at the time of delivery to a carrier for transport.

(e) Heat Total maximum internally generated heat load not to exceed 6500 watts. An analytical determination, described in Exhibit B to this application, of the container temperature profile and heat load resulted in the following:

0 Cask Surface 300 F 0

Inner Shield 101 F 0

Outer Shield 87 F 0

Ambient 80 F Heat Load 6566 Watts General Electric will analyze by test or other assessment each container heat loading prior to shipment to verify that the requirements of 10CFR71.71 will be satisfied.

Reference

's made to GE-Model 100 Application, Exhibit B, i

for a method of internal heat load analysis and heat dissipation.

3.0 Package Evaluation (a) General There are no components of the packaging or itscontentswhicharesubjecttochemical or galvanic reaction; no coolant is used during transport.

The protective jacket is bolted closed during transport. A lock wire and seal of a type that must be broken if the package 7

3.0 (continued)

(a) General (continued) is opened is affixed to the cask closure device.

If that portion of the prctective jacket which is used in the tie-down system or that portion which constitutes the prin-cipal lifting device failed in such 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 withstanding a static load, nomal to and distributed along its entire length equal to five times its fully loaded weight, without generating stress in any material of the packaging in excess of its yield strength.

The packaging is adequate i

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. Exhibit C, for a method of determining 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 impact conditions. The intent was to design a protective jacket that would not only satisfy the requirements of the l

U.S. Nuclear Regulatory Commission and the Department of Transportation prescribing the procedures and standards of packaging and shipping and the requirements governing such

' TID-7651, SE-RR 65-98

6 3.0 (continued)

(a) General (continued) packaging and shippirg but would protect the shielded cask from significant deforma-tion 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 calcu-lations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the General Electric Shielded Container - Model 100 (Ref: Section 3.0). The protective jacket design for the General Electric Shielded Container - Model 700 will be scaled from the 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 intent to protect the shielded cask from any deformation in the event of an accident.

(b) Normal Transport Conditions Thennal:

Packaging components, i.e., steel shells and lead, uranium and/or tungsten shielding, are 0

unaffected by temperature extremes of -40 F 0

and 130 F, Package contents, at least singly-encapsulated or contained in inner containers, but not limited to special form, will not be affected by these temperature extremes.

Pressure:

The package will withstand an external pres-sure of 0.5 times standard atmospheric pressure. :

O 3.0 (continued)

(b)

(continued)

Vibration:

Inspection of the Model 700 casks used since 1958 reveals no evidence of damage i

of significance 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 standard drop heights after being subjected to water spray.

Penetration:

There is no effect on containment or over-all 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.

i i

Compression:

The loaded container is capable of with-standing a compressive load equal to five times its weight with no change in spacing.

Sunmary and The tests or assessments set forth above

==

Conclusions:==

provide asstrance that the product contents are contained in the Shielded Container -

Model 700 during transport and there is no l

reduction in effectiveness of the package.

1 (c) Hypothetical Accident Conditions General:

The effectiveness of the strain rate calcu-lations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the GE Shielded Con-tainer - Model 100 (Ref.: Section 3.0 of the j

-10 t

3.0 (continued)

(c)

(continued)

General (continued)

Model 100 Application).

Extrapolations of the Model 100 data were used in the design and construction of the GE Model 700 protec-tivejacket.

The increased weight and dim-ensions of the Model 700 container over the Model 100 container necessitated a protec-tive jacket wall of 0.62 inch steel compared to a 0.25 inch wall for thri Model 100.

Drop Test The design and construction of the GE Model 700 protective Jr.cket was based on an extrapolation of the proven data generated during the design and construction of the GE Model 100 and on the results of cask drop experiments by C. R. Clifford )(2) and H. G. Clarke, Jr.I3)

The laws of similitude were used in an analytical evaluationI3)(4)todeterminethe protective jacket wall thickness that would withstand the tett conditions of 10CFR71.73 without breaching the integrity of the Model 100 cask. The evaluation, described (1) C.8. Clifford, The Desion. Fabrication and Testino of a Quarter Scale of the Demonstration Uranium Fuel Element Shiopino Cag, KY-546(June 10,1968).

(2) C.B. Clifford, Demonstration Fuel Element Shiccino Cask from Laminated Uranium Metal-Testina Protrom, Proceedings of the Second International l

Symposium on Packaging anc

'ransportation of Radioactive Materials, Oct.1418,1968, 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.

l l l

3.0 (continued) in GE-Model 1000 Application Exhibit A.

(c)

(continued) indicated a protective jacket w311 thick-ness of 0.525 inch (see Exhibit D to this DropTest(continued)

Application).

The intent of the design for the GE Model 700 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 3.0 of the Model 100 Applica-tion),

it is expected that damage not exceeding that suffered by the GE llodel 100 will result if the GE Model 700 is subjected to the 30 foot drop test.

l Puncture Test The intent of the design for the GE Model 700 is to sustain less or equal damage to the packaging during accident conditions than the defonnation suffered by the GE Model 100.

It is expected that deformation not greater than that sustained by the GE Model 100 will be received by the GE Model 700 in the event that the package is subjected to the puncture test.

Thermal Test Since it is expected that the GE Model 700 I

cask will sustain negligible danage and only minor damage will occur to the protec-tive jacket in the drop and puncture tests, it is reasonable to consider the resultant package, for purposes of thermal resistance, l

as essentially undamaged. Accordingly, the package was assessed using the General Electric Transient Heat Transfer Computer Program. Version 0(THTO),whichallowsthe l

12-

1 l

3.0 (continued)

(c)

(continued)

Thermal Test (continued) analysis of the general transient problems involving conduction, convection and radiation.

The program allows the thermal properties of the materials to be entered as a function of temperature and the boundary conditions to be entered as a function of time.

The significant assumptions, approximations, and boundary conditions used for the analysis are listed below:

0 1.

Fire temperature 1472 F 2.

Effective fire i

Emissivity 0.9 3.

Fire shic1d surface Emissivity 0.8 and constant with temperature l

4.

Emissivity of other Surfaces 0.8 and constant with temperature.

5.

There is in lmate contact between t'io lead shielding and the stainless steel d

shell of the cask.

6.

The ce is negligible heat transfer b/

l conduction through the ofpes used as spacers Letween the cask and the first shield and between the two shields of theprotectivejacket.

7.

There is negligible heat transfer by i

convection between the two shleids of the protective jacket and between the cask and first shield of the protective jacket.

l 3.0 (continued)

(c)

(continued) 1 ThermalTest(cont.)

8.

There is an internal heat load of 6500 watts with assessed temperatures as out-l lined in Section 2.0 of this application.

l l

The computer program calculations were run i

for a 30 minute fire. The calculations indicate a maximum temperature rise to less t

than 473"F for the lead after 30 minutes and no lead melting could be expected. A coast i

up analysis (Ref, the Model 100 Application) indicated that a temperature of 464'F could l

be expected at the innermost lead node after l

34 minutes.

The Model 100 Application further l

describes the computer code THTD.

l l

Water immersion Since optimum moderation of product material l

l 1s assumed in evaluations of criticality -

i safety under accident conditions, the water insnersion test was not necessary.

l Summary and The accident tests or assessments described Conclusions above demonstrated that the package is j

adequate to retain the product contents and i

that there is no change in spacing. There-i fore, it is concluded that the General Electric Shielded Container - Model 700 is adequate as packaging for the contents specified in 2.0 of this section.

l 4.0 Procedural Controls i

Vallecitos Site tafety Standards have been established and itipeleented f

toassurethatshipmentsleavingtheVallecitosNuclearCenter(VNC) l I

l 14-

4.0 Procedural Controls (continued) comply with the certificates issued for the various shipping container models utilized by the VNC in the normal conduct of its business.

Each cask is inspected and radfographed prior to first use to ascertain that there are no cracks, pinholes, uncontrolled voids or other defects which could significantly reduce the effectiveness of the packaging.

After appropriate U.S. Nuclear Regulatory Comission approval, each package will be identified with 7 welded on steel plate in accordance with the labeling requirements of 10CFR71 and any other information as re-quired by the Department of Trinsportation.

5.0 Fissile Class - Class lii The Density Analog Method as described in the $NM-960 License Application for VNC, Docket 70-754, was used for calculations. Although this method is nonnally used to calculate the number of units for transport under Fissile Class !!, it was used in this case to demonstrate that one ship-ment of two casks would be suberitical.

No credit was taken in the calculations for Pu 240 or other poisons present.

The cask cavity was filled with water, and the fuel wa: homo-genized with the water in the volume of the 5.0 inch liner.

This water filling was done to represent the accident case and to allow for' cask wot loading.

The calculations were based on the cavity volume without the extension resulting in the greatest homogenized concentration.

The full results of the calculations are shown below:

Fissile Material Ru4ntity Safe Numbar Pu 239 2.0 Kg 11 U 233 2.0 Kg 8

U 235 2.0 Kg 63 l

In all cases, at least two containers each containing 2.0 kg of fissile l

material were subcritical.

EXHIBIT A Supportive Information for Fissile loadings i

l l

8

APPLICATION AhtENDhiENT FOR GENERAL ELECTRIC SHIELDED CONTAINER --

htODEL 700 DATED FEBRUARY 25. 1970 SUPPOP T;VE INFORhtAT!ON License No. - SitM 460 Dechet He.

70 754 Seet. He, P eg.

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Date F"hroa rv 2 4 I470 Amende Sect.(e) - M N Amend. He.

Byproduct hiaterial and special nuclear material in solid metal or metal oxide form:

A.

hiaximum amount of fisslie material prior to trradiation:

(5)

Not to exceed those values as presented in Welaht Limits for the hiodel 700 Figure 1, tJ!O2 Shipping Containe r, of Gene ral Electric Company's app!! cation dated February 25, 1970; Figure I, calculated with the use of GERhl and CETHRht codes, glves fully moderated and reflected UO weight limits for shipment of fuel segments in 2

the hiodel 700 container. These values are based on 457. of the minimum critical UO Pellet mass for 2

pellet diameters greater than 0,400 inch.

The welght Ilmlt selected for a given container is based on the maximum untrradlated enrichment to be s hippe d.

(6)

Not more than 10 ETR. type elements (CETR Fuel) containing not more than 510 grams of U-235 per element loaded and spaced in the stainless steel fuel shipplng basket as described in General Electric Company's application dated February 25, 1970 and GE Drawing No. 106D4150.

Fuel Elemant Dascriptinn The fuel elements are ETR type, flat plate, uranium aluminum assemblies. The nominal not overall dimensions of each complete fuel element are 3. 00 inches by 3. 00 inches by 5 4. 3 5 inc ht,s.

This length is reduced to approxlmately 40 inches for shipment.

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Each fuel element consists of 19 fuel plates each 0.050 inch thick, 2. 80 inches wide and 37. 25 inches long. The fuel plates are roll-swaged into 6061-T6 aluminum alloy side pieces which hold.and space the fuel plates 0.110 inch apart. An aluminum " comb" spacer plate, inse rted at the uppe r end of the assembly, maintains the nominal 110-mit spacing between t!m fuel plates. Each fuel plate is composed of a 20-mil-thick uranium-aluminum central core sandwiched between two layers of 15-ml1 aluminum cladd'.ng. The central core region or " meat" is 36 inches long and starts 0. 625 inch from each end of the plate. A 1060 a.lloy aluminum " picture frame" surrounds the meat in each plate with 15-ml1 1060 aluminum cladding covering the meat and picture frame. Nominal finished not dimensions of each fuel plate are 0. 050 inch by 2. 80 inches by 37. 25 inches. The fuel meat alloy is a uranium-aluminum alloy containing 30. 5 wt% uranlum, 2% sillcon, and the balance aluminum. Fully enriched (93. 5% U-235) urannum and pure aluminum are meIted tokether to form the fuel alloy billets. Up to 2% s!!! con is added to promote homogenelty in the alloy. Afte r rolling the alloy billet to shape, indivlJual fuel plate cores are cut. These cores, inside aluminum picture frames, are then metallurgically bonded to the cladding by hot rolling in a series of paspes followed by cold ro!!!ng. Between hot and cold-rolling, the plates are heated to 1000'r for I hour and inspected to ensure freedom from blisters or laminatlons. After cold-rolling, the plates are assembled and swaged into finished fuel elements, l.icense No. 'l?lhi 960 Ded e, He, 70-754 $.ev, No, p e,. A. J, h pee Fahron ry 2 9, 1070 heads 5.et.(s) NEW 2 7

Each plate contains 26. 9 i 1. 0 gm U-235, and 6 each fuel element assembly contains 5101. O gm U-235. Fuel Element Summary Fuel type ETR flat plate U-235 concentration in meat, wt7e 30,5 hieat thickness, inch 0.020 Cladding tnickness, inch 0.015 Fuel plate thickness, Inch 0.050 Plates per element 19 Uranium enrichment, % 93.5 U-235 pe r element, gm 510 Element length, lnche s 54.35 Element cross section, lnches

3. 00 x 3. 00 Number of elements per shipment Normal 10 Maximum 10 Active element length, Inches 36 Polson Dasket Deserlption The shipping container Model 700 polson basket is comparable to the boral fuel magazine shown in the' Irradiated Fuel Shlpping Cask Design Guido", L. B. Shappe rt, ORNL-TM 2410, (cask DMI 1, issued AEC License SNM-807.

Amendment No. 4, dated March 31,1967 and DOT Special Pe rmit No. 5957, dated April 23, 1969). For the Model 700 basket, 304 stainless steel is used in place of boral, resulting in the advantages of Improved material properties at room and elevatail temperature and permitting the use of conventional labrication technl ques. Lisente No SMM.n 6 0 Dedet Ne, 70.7a4 _ 3, g g, g,,' p,, I MM MEW 3 N

r .g i The Model 700 poison basket is fully described l-in General Electric Drawing No. 106D4150. attached hereto. I l Nuclear Considerations A criticality analysis was performed for the loading and shipment of 10 GETR fuel elements in a Model 700 container. The elements are contained in a stainless steel basket (GE Dwg. No. 106D4150) with 0. 25 inch of steel between each element forming a stainless steel cell around each element. No burnup was assumed. Two basic conditions were evaluated: (1) fuel in the steel basket contained in the 10. 5 inches thick lead cask with all vold spaces in and around the cask f!!!ad with water and (2) fuel in the steel basket surrounded with water. The second case will be encountered during loading of the basket. No dry case was considered as the assembled fuel elements in the polson basket are already undermoderated in the flooded case, and the further removal of water would only reduce the keff. of the system. In each of the above cases, cross-sections were calculated using the GERM and GETHRM compu. ter codes. GERM and GETHRM are General Electric Company proprietary versions of THERMOS a Thermalisation Transport Theory Code for Reactor Lattice Calculations, H. C. Iloneck, Brookhaven National Laberatory. The calculated cross sections were in turn input to the TWOD code, Lleonee No. SNM.060 Deehoe No. 70 764 lost. No Pg 7 h._rakuuu_11___t27 o A d.s n.fal_ Sid _.__.__ 4

TWOD is a General Electric Company proprietary version of PDQ, reported in. WAPD-TM-230. The following resules were obtained: Case Ke ff. (1) Flooded fuel array in Pb cask 0.81 (2) Flooded fuel array in water 0.75 In evaluating case (1) against the accident criteria of 10CFR71, reference is made to TID-7028, Critical Dimensions of Systems Containing U 235, Pu-239, and U-233 Figure 8, page 14. As the H/U-235 ratio is approximately 225 and the amount of U-235 per element is fixed, any accident which increases fuel density will make the system less reactive, The only credible accident in the Model 700 container would Involve the fuel breaking into pieces (itself highly suspect, as tests on the Irradiated fuel Indicate little or no embrlttlement) and settling, resulting in a more dense and consequently less reactive system. B, Maximum amount of radloactive decay heat: (2) Package contents wet - 1500 thermal watts, provided that the cavity shall contain at least a 1000-cubic. inch air vold (at standard-temperature-pressure) at the time of delivery to a carrier for transport. The calculations for the 1500 watt load in the Model 700 container with or without the extension were performed in the same manner as the calculations for the 500 watt License No, $NM o60 pode W. 10-754 gee,, w, Pop Amend. No. 7 Dope rebruarv 24 1970 w,sec,(,) NEW 5

3 load, submitted as Exhibit C to the Model 700 application dated August 4,1969 and resulting in License Amendment 71-43, dated August 19, 1969 The results of the calculations including the FRECON and THTD computer code runs indicate that a 100 psi wet load will not be exceeded under either normal or accident conditions provided that 700 cubic-inches of water are removed from the cavity, without the extenston, and 940 cubic. inches of water are removed from the cavity when the extension is used. In performing the calculations, the volume of the payload was assumed to be zero which makes the results a bit conservative but allows for an unlimited number of payload configurations up to 1500 watts, Lleense No. SNM.060

p. l,,, No, 70 754 3.,,, N.,

P., Asiend. Ms. 7 Deee F3brusre'* 1670 We Seet (e) " E "' 6

['L :.. L EXHIBIT B An Analytical Method for Detemining Container Temperature Profiles and Heat Loads. l I l

EXHIBIT B An analytical method for the determination of container temperature profile and heat load when the geometry and cask surface temperature conditions are known.

1. Scope The analytical method described in Exhibit B provides a means for determining the container heat load and temperature profile used in evaluating the package when subjected to the conditions normally incident to transport and for obtaining information necessary to the application of THTD in the evaluation of the container when subjected to the 1475' F fire for 30 minutes, including a coast-up analysis.

2. Assumptions, Approximations, and Boundary Conditions 2.1 Emissivities of all surfaces are constant with temperature, all surfaces painted white. i 2.2 Intimate contact between the lead shielding and the cask shell. 2.3 Negligible heat transfer by conduction through the pipes used as spacers between the cask and the first shield and between the two shields. 2.4 Maximum cask surface temperature allowed under normal transport conditions, 300* F. 2.5 Convective surface film coefficients obtained by using correlations found in "GE Heat Transfer and Design Data", Section G504. 3, page 5, figures 8B and 9B. 2.6 Surface film coefficient for outside of outer fire shield obtained from " Heat Transmission", page 172, Equetion 7 4A, McGraw Hill. ,.. = License No. SNM-960 Docket No. 70 754 Sect. No. Exhibit B p, Appendix D 24 Amend. No. 3 Date Da e a mha v-71 ioA8 Amenda Sect.( ) New

9 2.7 Turbulent flow only. 2.8 Uniform heat flux. 2.9 Forced flow and drafts negligible. 2.10 All surfaces of cask and fire shields, except bottom, are available for heat transfer. 3. Des cription FRECON A BASIC language time sharing program to calculate container fire shield tem-peratures and heat load knowing the container geometry and cask surface tempera-ture was developed. Using data obtaine.d from the thermal testing of the GE Models 100 and 1500 shipping containers, an analytical correlation was developed to calculate a temperature distribution from the cask surface to the ambient air. This method also permits calculation of the container maximum allowable heat load.. A B ASIC language computer program was written for the GE 235 computer employing the aforementioned analytical correlation. Specifically, the program was written to calculate the equilibrium temperatures and heat load for containers employing a GE double wall steel protective jacket. It could, however, be modified to calculate temperatures and heat load for other fire shield configurations. The program user specifies the outside surface areas for the cask and fire shields and their emissivities. He also inputs an arbitrarily selected cask surface tem-perature, T, an ambient air temperature, T, and a first guess for' outer shield 1 4 temperature, T. For the given T and T, the program will iterate to explicit 3 3 4 values for T, inner fire shield temperature, T, and the container heat load. j 3 2 The temperatures between the cask surface and the cavity surface are then hand calculated using the equation for heat conduction through a composite cylinder wall: 12 b (*1 - *2I O (BTU HR I) = ( in (r /# I 2 1 l i l License No. SNM 960 Docket No. 70 754 Sect. No. Exhibit B

p.,

Appendix D 25 'l De cemher 2 3. 196 8-Now w s a

whara: Thermc1 conductivity in BTU /Hr Ft

• F K

= 12 Length of cylinder in feet L = Inside radius r = y Outside radius r = 2 The standard fire transient is then run using the THTD computer code and the total temperature distribution just obtained. If the post fire temperatures are is selected and the entire too high (lead melting occurs) a new value for T 3 ~ process is repeated. Data comparing the measured values with computed values for the GE Models 100 and 1500 containers are indicative of the success of the program. Heat Load, Measured Heat Load, Calculated Container Model 100 1310 BTU Hr-I 1101 BTU Hr-1500 10317 BTU-Hr-I 8190 BTU Hr-I License No. SNM 960 Docket No. 70 754 Sect. No. Exhibit B pag. Appendix D New 26 December 23,1968 Amends Sect.(s) 3 Date hd. W.

EXHIBIT C Lifting Devices

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J 4 3r EXHIBIT D SCALE-UP ANALYSIS 4 4 r t a e 2 m ?

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i 4 \\ t F 4 b i J t-1 h 5 . A 9 I b* I t' \\ 4 4 I s a j -4 p. t + f m

GENERAL $ ELECTRIC EXHIBIT D Calculation of the Weight Scale-Up Factor for the G.E. Model 700 The weight factor used to scale up the Model 100 drop test results to the Model 700 is calculated as follows: (W /W,)1/3 where: S, E the weight scale-up factor S, = p W E the weight of the prototype (Model 700) p W, E the weight of the model (Model 100) For the purposes of this calculation the following conservative values were assigned: W = 41,000 lbs. (This value represents the maximum possible weight permitted p by Drawing No.129D4768 Rev. 2, i.e., the combined weight of the cask assembly, extension, crash / fire shield and base plus 2h%, plus a 1,500-lb. allowance for cask contents. The cask contents allowance is very conservative as the normal load would be expected to be less than half that amount. For example, a typical shipment of GETR-type fuel would consist of a fuel spacing basket (~250 lbs.), fuel elements, and water for a total weight of approximately ( 600 lbs.). t W, = 4,450 lbs. (The total weight of the Model 100 cask assembly, crash / fire shield, and base. No allowance was made for cask contents for the Model 100. This is conservative as any increase in W, reduces the scale-up factor.) Therefore: (9.21)1/3 (h) 2.10 S, = = = The required thickness of the Model 700 crash / fire shield plate is obtained as follows: T = (S,)(T,) where: T E thickness of Model 700 shield plate p p S, E weight scale-up factor T, E thickness of Model 100 shield plate (2.10)(0.25") 0.525" Therefore: T = = p This is 'well within the 0.625-inch plate thickness used in the Model 700 crash / fire shield. (

EXHIBIT E MODEL 700 PROCEDURES

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