ML19309E926

From kanterella
Jump to navigation Jump to search
Requests That Certificate of Compliance 5971 for GE Model 200 Shipping Container Be Renewed W/Minor Changes.Forwards Drawings Indicating Changes Made to Cask Drawing List. Drawings Available in Central Files Only.Amend Fee Encl
ML19309E926
Person / Time
Site: 07105971
Issue date: 02/20/1980
From: Cunningham G
GENERAL ELECTRIC CO.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML19309E927 List:
References
15642, NUDOCS 8004250084
Download: ML19309E926 (16)


Text

. __

7prL-7/ - D 71 bw NUCLEAR ENERGY

.w=* lins]u y jw:

=, g a~1AlC

=

u i

ENGINEERING GENERAL ELECTRIC COMPANY. P.O. BOX 460. PLEASANTON. CALIFCANIA 94566 DIVISION February 20, 1980 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. 5971

Dear Mr. MacDonald:

General Electric has for several years shipped large quantities of radio-active materials in the G.E. Model 200 shipping container.

General Electric hereby requests that Certificate of Compliance No. 5971 for that container be renewed.

In support of this request a consolidated application for certification is enclosed with this letter.

Some minor changes, either editorial or re-flecting the current cask drawings, have been made and are designated by vertical lines.

In addition, several minor changes have been made in the cask drawing list (these changes are reflected in the consolidated application). A brief description of each change is given below:

I.

Drawing 212E236 Rev. 1 Rev. 2: This revision consisted of redrawing a bolt (Part 5) for clarification.

Rev. 3: The title of the drawing was changed to "Model 200 Transport Package". A reference to the new closure seal was added. The lock wire location was changed from the cask lid bolts to the jacket hold-down bolts and a hole in the adjacent gusset plate.

The two horizontal shear bolt assemblies (Parts 8, 9, and 10) be-tween the jacket and the base were deleted. These shear bolts were changed to four vertical attachment bolts as a result of discussion with Commission personnel in 1969 to improve the attachment of the jacket to the base. The drawing revisions eliminating the horizontal bolts were never completed.

15GC Y

8004250 Og

A E

GENER AL h ELECTRIC Mr. Charles E. MacDonald February 20, 1980 I.

Drawing 212E236 Rev. 1 (continued)

Rev. 3 (continued)

The reference to the nameplate drawing was deleted. The description of a bolt (Part 5) was added to the drawing and the tie-down shackles were also added.

II.

Drawing No. 612D136, Rev. 4 Rev. 5: The drawing title was changed to reflect the "Model 200" designation. A reference to a new nameplate drawing was added and an obsolete identification note was deleted.

III.

Drawing No. 706E788, Rev. 1 Rev. 2: The hexnut and sleeve (Parts 5 and 6) were made optional as they are no longer ^ necessary due to the deletion of the horizontal shear bolts (see 212E236, Rev. 3).

Six parts (8, 9, 22, 23, 24 and 25) were identified for an optional fabrication technique. The change allows the use of either angle sections or fabricated plate sections.

Painting specifications were removed and referenced to engineering specifications.

The new 1/4-inch hole for the lock wire in a g tsset was added. An option was added to delete the notch in Part 29. The notch is no longer necessary without the deleted horizontal shear bolts.

IV.

Drawing No. 106D3852, Rev. 1 Rev. 2: The length of the locating pin (Part 11) was changed to 2-1/2 inches to conform with the as-built cask. Three "I" beam sec-tions and spacers were added to the base to augment forklift handling capabilities.

Rev. 3: The hole for the deleted horizontal shear bolts was made optional, and the paint specification was referred to the engineering specifications.

An optional location rotated 45 from the normal location was added for Part 5 to allow for the screw fastening of the capture plate.

The weld specification was changed to allow tack welding. This change facilitates disassembly for cleaning.

"~*

GENER AL h ELECTRIC Mr. Charles E. MacDonald February 20, 1980 V.

Drawing No. 693C292, Rev. 4 Rev. 5: This revision removed the original Notes 2, 3, and 4 and added a new Note 2 which provides for stamping the lid with its weight. An option was added to permit Parts 1 and 4 to be made of stainless steel. The drawing title was expanded to indicate that it is for the cask lid. The "next assembly" drawing reference was de-leted, and the "first made for" reference was updated. An optional seal weld was added to the lifting eye attachment to ease decontamin-ation of the lid.

VI.

Drawing No. 129D4702, Rev. O This is a drawing for the new generic cask seal.

VII.

Drawing No. 693C293, Rev. 2 Rev. 3: This revision updated the drawing title and the "first made for" reference. The reference to Drawing No. 212E236 was deleted.

i VIII. Drawing No. 985C540, Rev. 0 i

Rev. 1: This revision updated the drawing title.

Rev. 2: The reference on Part 6 to lead density was deleted.

IX.

Drawings Nos. 211A7528, Rev. O and ll5A8106, Rev. 2 These obsolete drawings for a nameplate and a bolt have been deleted.

Section 5(b)(1) of certificate 5971 should be revised to read:

....or in solid oxide form; or other non-decomposable (at 650 F) solid materials".

Section 6 should also be revised to read:

"....in the General Electric Company's submittal dated February 12, 1969, l

or in special form (10CFR71.4(o)).".

1 These changes are consistent with our previous applications for other containers.

i A check for the $150.00 renewal fee is enclosed.

l --

l

i GENER AL h ELECTRIC Mr. Charles E. MacDonald February 20, 1980 As this application is being submitted at least thirty days prior to the expiration date of the certificate, it is our understanding that the exten-sion provisions of 10CFR2.109 are applicable.

Sincerely, f[

~ - - '

G. E. Cunningham Sr. Licensing Engineer

/11 enclosure I

l ~

l l

r

L GENERAL ELECTRIC SHIELDED CONTAINER - MODEL 200 1.0 PACKAGE DESCRIPTION - PACKAGING (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 specified in this application, and all lifting and/or tiedown devices for addi-tional containers of this model if different from the lifting and/or tiedown devices ddscribed in

~

this application will satisfy the requirements of 10CFR71.31(c)(d).

This container is detailed in G.E. Drawings 12904702 Rev. O, 693C292 Rev. 5, 693C293 Rev. 3, 985C540 Rev. 2, 10603852 Rev. 3, 612D136 Rev. 5. 212E236 Rev. 3, and 706E788 Rev. 2, attached.

Shapa:

An upright circular cylinder shielded cask and an upright circular cylinder protective jacket with attached square base.

Size:

The shielded cask is 20-1/4 inches in diameter by 53-7/8 inches high. The protective jacket is 65-3/8 inches high by 37-5/8 inches across the box section. The base is 47-1/2 inches square.

Construction:

The cask is a lead-filled carbon and stainless steel weldment. The protective jacket is a double-welled structure of 3/8 inch carbon steel plate ar.d surrounds the cask during transport.

The sq;are base is 1/2 inch carbon steel with four I-beams attached.

Weight:

The cask weighs 8250 pounds. The protective jacket and base weigh 1750 pounds..

(b) Cask Body Outer Shell:

3/8 inch thick steel plate, 53 inches high by 20-1/4 inches in diameter with a 3/8 inch bottom plate and a 1-1/8 inch top flange.

Cavity:

1/8 inch stainless steel wall and bottom plate, 7-9/16 inch inner diameter by 37 inches deep.

Shielding Thickness:

5-27/32 inches of lead on sides, 7-15/16 inches of lead beneath cavity.

Penetration:

One,1/2 inch outer diameter by 0.125 inch wall stainless steel tube gravity drain line from the side of the cavity bottom to the side of the cask outer shell near the cask bottom closed with a fusible lead cored 1 NPT hex head pipe plug which protrudes 1/2 inch outside of shell surface or equivalent 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.

Lifting Devices:

Two diametrically opposed ears welded to sides of cask, covered by protective jacket during transport.

Primary Coolant:

Air.

(c) Cask Lid Shape:

A cylinder of decreasing diameter attached to flat plates.

Size:

The top plate is 20-1/4 inches in diameter by 3/4 inch thick. The bottom plate is 10-1/2 -

inches in diameter by 1/8 inch thick. The cylinder is 14-7/8 inches in diameter at the top by 10-1/2 inches in diameter at the bottom by 7-7/16 inches high.

Construction:

Lead fied steel clad cylinders welded to circular steel plates.

Closure:

Six, 1-inch 8-UNC-2A steel bolts equally spaced 0

60 apart on a 17-5/6 inch diameter bolt circle.

Closure Seal:

Molded silicone rubber seal bonded to an aluminum back-up plate.

Penetrations:

None Shield Expansion Void: None Lifting Device:

Single steel loop,1-1/4 inch diameter steel rod located in center of lid top.

Covered by protective jacket during transport.

(d) Protective Jacket Body Shape:

Basically a right circular cylinder with open bottom and with a protruding box section dia-metrically across top and vertically down sides.

Size:

65-3/8 inches high by 37-5/8 inches wide acress the box section. The outer cylindrical diameter is 26-3/4 inches. The inner diameter is 23-1/4 inches. A 5-1/2 inch wide by 3/8 inch thick steel flange is welded to the outer wall of the open bottom.

Construction:

Carbon steel throughout.

Double walled construc-tion. The walls are 3/8 inch thick. One and l l l

l

one-half inch air gap between cask shell and inner jacket wall and a 1-inch air gap between inner and outer jacket walls throughout. Six, 12-inch high by 3/8 inch thick gussets are welded to the outer cylindrical wall and flange.

Including the two box sections, the gussets are spaced 45 apart.

Attachment:

Four, 2 inch bolts connect the protective jacket body, through the flange to the pallet.

Lifting Devices:

Tro rectangular, 1-1/8 inch thick steel loops located on top of the box section at the corners.

The steel is 7-inches long by 3-inches high by 3-1/2 inches wide.

Tiedown Devices:

Two diametrically opposed 2-inch thick steel ears welded to sides of box section, each ear has a 1-1/2 inch hole to accept clevis or cable.

o Penetrations:

Slots along periphery of the protective jacket at the bottom, slots in box section under lifting loops, allows natural air circulation for cooling.

(e) Protective Jacket Base

(

l Shape:

Hollow cylindrical weldment with square bottom plate.

Four I-beams are welded to square bottom I

of plate.

Size:

Bottom plate is 47-1/2 inches square and 1/2-inch j

thick. The cylindrical collar is 22-inches in outer diameter by 3-inches high. The I-beams are 3-inches high by 47-1/2 inches long.

Construction:

The cylindrical collar houses two sets of 1-1/4 inch by 1-1/4 inch by 1/4 inch steel energy absorbing angles separated by a 3/8-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:

Two diametrically opposed tie blocks to accept jacket attachment bolts.

2.0 PACKAGE DESCRIPTION - CONTENTS (a) General Radioactive material as the metal or metal oxide (but specifically not loose powders); or other non-decomposable (at 650 F) solid materials.

(b) Form Clad, encapsulated or contained in a metal encase-ment of such material as to withstand the combined effects of the internal heat load and the 1475 F fire with the closure pre-tested for leak tightness, or in special form.

(c) Fissile Content Not to exceed 500 grams of U-235, 300 grams of U-233, 300 grams of Pu, or a prorated quantity of each such that the sum of the ratios does not exceed unity.

(d) Radioactivity That quantity of any radioactive mate.ial which does not generate spontaneously more than 78C thermal watts by radioactive decay and which meets the requirements of 49CFR173.393.

(e) Heat Total maximum internally generated heat-load not to exceed 780 the,rmal watts.

An analytical determination, described in Exhibit B to the Application for the GE Model 700 container, of the container temperature profile and heat load resulted in the following:.

1 0

175 F Cask Surface 119 F 0

Inner Shield 0

93 F Outer Shield U

80 F Ambient 780 watts Heat Load General Electric will analyze by test or other assessment each container heat loading prior to shipments to verify that the requirements of 10CFR71.35 will be satisfied. Reference is made to the GE-Model 100 Application, Exhibit B, for a method of internal heat load analysis and heat dissipation.

3.0 PACKAGE EVALUATION l

(a) General There are no components of the packaging or its contents which are subject to chemical 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 is opened is affixed to the cask closure.

If that portion of the protective jacket which is used in the tiedown system or that portion which constitutes the principal lifting device failed in such a manner to allow the protective jacket to separate from the tiedown and/or lifting devices, the basic j

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 support at its ends along its major axis, is capable of withstanding a static load, normal 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 to retain all contents l

i 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 U. S. Nuclear Regulatory Connission and the Department of Transportation prescribing the procedures and 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

. ti'me, del ay.

The effectiveness of the strain rate calculations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with General Electric Shielded Container - Model l

100(Ref.: Model 100 Application, Section 3.0).

The protective jacket design for the General Electric Shielded Container, Model 200 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.

  • TID-7651, SE-RR-65-98 4

(b).trr641 Transoort Conditions Thermal:

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

unaffected by temperature extremes of -40 F 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 pressure of 0.5 times standard atmospheric pressure.

Vibration:

Inspection of the Model 200 casks used since 1958 reveals 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 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 thirteen pound by 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 loaq equal to five times its weight with no change in spacing.

l l

Summary and The tests or assessments set forth above provide

==

Conclusions:==

assurance that the product contents are contained in the Shielded Container - Model 200 during transport and there is no reduction in effective-ness of the package.

(c) Hyoothetical Accident Conditions General:

The effectiveness of the strain rate calculations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the GE Shielded Container - Model 100 (Ref.: Model 100 of Application, Sectit.. LO).

Extrapolations of the Model 100 data were used in the design and construction of the GE Model 200 protective jacket.

Drop Test:

The design and construction of the GE Model 200 protective jacket 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 the cask drop experiments by C. B.

Clifford(1)(2) and H. G. Clarke, Jr.(3) The laws of similitude were used in an analytical evalua-tion (3)(4) to determine the protective jacket wall thickness that would withstand the test conditions of 49CFR173.398(c) and 10CFR71.36 without breaching the integrity of the Model 200 cask. The evaluation, described in GE -

Model 100 Application, Exhibit A, indicated a protective jacket wall thickness of 3/8 inch.

The intent of the design for the GE Model 200 is, during accident conditions, to sustain damage to the packaging not greater than the damage sustained by the GE Model 100 during its accident (1) C. B. Clifford, The Design, Fabrication and Testing of a Quarter Scale of the Demonstration Uranium Fuel Element Shiocing Cask, KY-56 (June 10,1968).

(2) C. B. Clifford, Demonstration Fuel Element Shiocing Cask from Laminated Uranium Metal-Testing Program, Proceedings of the Second International Symposium on Packaging and Transportation of Radioactive Materials, October 14-18, 1968, pp. 521-556.

(3) H. G. Clarke, Jr., Some Studies of Structural Resoonse of Casks to Imoact, l

Proceedings of the Second International Symposium of Packaging and Transporation of Radioactive Materials, October 14-18, 1968, pp. 373-398.

(4) J. K. Vennard, Elementary Fluid Mechanics, Wiley and Sons, New York, 1962, pp. 256-259.

9-

condition tests (Ref.: Model 100 Application, Section 3.0).

It is expected that damage not exceeding that suffered by the GE Model 100 will result if the GE Model 200 is subjected to the 30 foot drop test.

Puncture Test:

The intent of the design for the GE Model 200 is to sustain less or equal damage to the packaging during accident conditions than the defonnation j

suffered by the GE Model 100.

It is expected that deformation not greatr than that sustained by the GE Model 100 will be "ceived by the GE Model 200 in the event that the package is sub-jected to the puncture test.

Thermal Test:

A fire transient using the THTD Code was not run on this container. However, reference is made to the shielded containers Models 100, 700, and 1500 which demonstrate the effectiveness of the double walled steel jacket as a fire as well as crash shield.

General Electric will analyze by test or other assessment each container heat load to verify that the loaded container will withstand the 30 minute 1475 F fire without significant lead melting in the cask.

Water Imersion:

Since optimum moderation of product material is assumed in evaluations of criticality safety under accident condition the water imersion test was not necessary.

l Sumary 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 200 is adequate as packaging for the contents specified in this. Application.

4.0 PROCEDURAL CONTR0 g Vallecitos Site Safety Standards have been established and implemented to assure 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.

Each cask is inspected and radiographed 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 Commission approval, each package will be identified with a welded on steel plate in accordance with the labeling-requirements of 10CFR71 and any other information as required by the Department of Transportation.

5.0 FISSILE CLASS - CLASS II An analysis has indicated that no greater than the following amount of fissile material may be shipped in any single container:

Grams U-235 Grams-233 Grams Pu (fissile)

< 1.0 500 300 300 The density analog method was used to determine the number of containers which may be shipped as Class II.

Each container was assumed to hold 500 grams U-235, or 300 grams U-233, or 300 grams of fissile Pu (Pu-239). No credit was taken for Pu-240 content.

Critical data used in the calculations was taken from TID-7028 water-metal curves, Figures 8, 27, and 34.

The container was assumed to be filled with water, (1) for the accident condition, and (2) to allow for container wet loading. The fissile material -

was assumed to be homogenized with the water.

In all cases, this resulted in nearly optimum moder2 tion.

Physically, there is little difference between the accident and non-accident cases except for the addition of water.

Both cases were calculated for the Pu loading. The " wet" case was limiting.

The density analog method is described in SNM License Application for VNC, Docket 70-754, Section 5.4.4, dated April 18, 1966. As the shipment will be Class II, the transport index for each loading was calculated, allowing a maximum number of fifty for each shipment.

The full results for the calculations are shown below:

Fissile Content Safe Number Transport Index 300 grams Pu (wet) 22 2.3 f

300 grams U-233 (wet) 120 0.5 300 grams U-235 (wet) 54 1.0 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.

l l

l 15642.