ML19312D988
| ML19312D988 | |
| Person / Time | |
|---|---|
| Site: | 07109045 |
| Issue date: | 04/21/1980 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19312D989 | List: |
| References | |
| 16165, NUDOCS 8006030034 | |
| Download: ML19312D988 (15) | |
Text
4 h~
i h
NUCLEAR ENERGY s
ENGINEERING GENERAL ELECTRIC COMPANY, P.O. box 460. PLEAsANTON, CALIFORNIA 94566 DIVISION April 21,1980 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. 9045
Dear Mr. MacDonald:
The General Electric Co., Vallecitos Nuclear Center (VNC), requests that Certificate of Compliance No. 9045 for the G.E. Model 1000 shipping container be renewed.
In support of this request we are enclosing a consolidation of our original application with subsequent applications for amendment into a single package.
Some minor editorial changes are denoted by vertical lines in the margins.
As the certificate expires on May 31, 1980, it is our understanding that the certificate is automatically extended under the provisions of 10CFR2.109.
Enclosed is a check for $150.00 for the renewal fee as required by 10CFR170.31.
If your staff has any questions concerning this application for renewal, please contact me at 415-862-2211, Ext. 4330.
Sincerely, l
,~
j G. E. Cunningham Sr. Licensing Engineer
/11 enclosure 800603003M lulus
GENERAL ELECTRIC SHIELDED CONTAINER - MODEL 1000 1.0 Package Description - Packaging (a) General All containers of this model, for pur-poses of constructing additional con-tainers of this model, will have dimen-sions of plus or minus 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 10CFR 71.31 (c)(d).
This container is detailed in G.E. Drawings 161 F478, Rev. 2,161 F479, Rev. 2,106D3879, Rev. 2, and 10603880, Rev. 2, attached.
Shape:
An upright circular cylinder shielded cask and an upright circular cylinder protec-tive jacket with attached square base.
Size:
Shielded cask is 21-3/4 inches diameter by 28-1/2 inches high.
The protective jacket is 38-1/4 inches high by 33-3/4 inches across the box section. The base is 47-1/2 inches square.
Construction:
The cask is a lead-filled carbon and stain-less steel weldment.
The protective jacket is a double walled structure of 5/16 inch carbon steel plate and surrounds the cask during transport.
The square base is 1/2 inch carbon steel with four I-beams attached.
Weight:
The cask weighs 4,200 pounds. The pro-tective jacket and base weigh 1,000 pounds.
(b)
Cask Body Outer Shell:
3/8 inch thick steel plate, 28-1/2 inches high by 21-3/4 inches diameter with a 3/8 inch bottom plate and a 1/2 inch top flange.
Cavity:
1/8 inch stainless steel wall and bottom plate,1-3/4 inches diameter by 9-1/2 inches deep.
Shielding Thickness:
9-1/2 inches of lead on sides, 8-3/4 inches of lead beneath cavity.
Penetration:
None.
Fil ters :
None.
Lifting Devices:
Two diametrically opposed ears welded to sides of cask, covered by protective l
Jacket during transport.
l l
Primary Coolant:
Air.
l l
(c)
Cask Lid Shape:
Two right cylinders of decreasing diameter l
attached to flat plates.
l i
Size:
Top plate is 8 inches diameter by 1/8 inch I
thick. Bottom plate is 3 inches diameter by 1/8 inch thick. The top right cylinder is 5-1/2 inches diameter by 3-3/8 inches
Size: (continued) high. The bottom right cylinder is 3 inches dianieter by 6-1/8 inches high.
Construction:
Lead filled steel clad cylinders welded to circular steel plates.
Closure:
Three 1/2 inch UNC-2A steel bolts equally spaceo 120 apart on a 6-3/4 inch diameter bolt circle.
Closure Seal:
A minimum 1/8 inch thick flat silicone rubber or equivalent gasket between body and lid.
None.
Shield Expansion Void:
None.
Lifting Device:
Single steel loop, 5/8 inch diameter steel rod located in center of lid top.
Covered by protective jacket during transport.
(d)
Liners - Plugs Shape:
Bottom plug - right circular cylinder.
Top plug - right circular cylinder with l
lifting loop.
Size:
Bottom plug 5/16 inches high by 1-11/16 inches diameter.
Top plug 7/16 inches high by 1-11/16 inches diametar.
Construction:
Bottom plug - Kennertium Grade W-2.
Top plug - Kennertium Grade W-2 attached to stainless steel plate by screw fasteners.
Lifting Device:
1/8 inch diameter rod, lifting bail.
(e)
Protective Jacket Body Shape:
Basically a right circular cylinder with open bottom and with a protruding box section diametrically across top and vertically down sides.
Size:
38-1/4 inches high by 33-3/4 inches wide across the box section.
Outer cylindrical diameter is 26-7/8 inches.
Inner diameter is 23-5/8 inches. A 5-1/2 inch wide by 5/16 inch thick steel flange is welded to the outer wall of the open bottom.
Construction:
Carbon steel throughout.
Double walled construction. The walls are 5/16 inch thick.
One inch air gap between cask shell and inner jacket wall and between inner and outer jacket walls, throughout. Six 12 inch high by 5/16 inch thick gussets are welded to the outer cylindrical wall and rim.
Including the two box sections, the U
gussets are spaced 45 apart.
Attachment:
Four inch bolts connect the protective jacket body, through the flange, to the pallet.
I Lifting Devices:
Two rectangular 3/4 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 3-1/4 inches wide.
l Tiedown Devices:
Two diametrically opposed 1-3/4 inch thick steel ears welded to sides of box section, each ear has a 1-1/2 inch hole to accept clevis or cable. -, -
Slots along periphery of the protective jacket at the bottom, slots in box section under lifting loops. Allows natural air circulation for cooling.
(f) Protective Jacket Base Shape:
Hollow cylindrical weldment with square bottom plate.
Four I-beams are welded to square bottom of plate.
Size:
Bottom plate is 47-1/2 inches square and 1/2 inch thick.
The cylindrical collar is 23 inches in 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 1/8 inch steel energy absorbing angles separated by a 1/4 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.
(b)
Form Clad, encapsulated or contained in a metal encasement of such material as to withstand I
the combined effects of the internal heat l'oad and the 1475 F fire with the closure pre-tested for leak tightness.
l._
(c)
Fissile Content Not to exceed 15 grams, fissile.
(d)
Radioactivity That quantity of any radioactive material which does not generate spontaneously more than 250 thermal watts by radioactive decay and which meets the requirements of 49CFR173.393.
(e) Heat Total maximum internally generated heat load not to exceed 250 thermal watts.
Although equilibrium temperature recordings were not taken for this package loaded to 250 watts thermal, the resulting tempera-tures are expected to be less than those recorded for the GE Shielded Container -
Model 100 because 1) the thermal watt loading for th'e GE Shielded Container -
Model 1000 is 62.5% of the Model 100 loading,
- 2) the surface area for heat dissipation is 112% of the Model 100 container, and 3) the cavity spacing in the Model 1000 container is smaller, offering less air resistance for heat transfer to the cask.
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
(
(a) General There are no components of the packaging or its contents which are subject to chemical or galvanic reaction; no coolant j
is used during transport.
The protective jacket is bolted closed during transport.
If that portion of the protective jacket which is used in the tiedown system or that portion which constitutes the principal --. -.
(a) General (continued) lifting device failed in such a manner to allow the protective jacket to sep-arate from the tiedown and/or lifting de-vices, 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, 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 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 require-ments of the U.S. Nuclear Regulatory Commission and the Department of Trans-portation 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,
- TI D-7651, SE-RR 98..
(a) General (continued) a new protective jacket could be readily supplied and the shipment continued with minimal time delay.
The effectiveness of the strain rate cal-culations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the General Electric Shielded Container - Model 100 (Re f. : Section 3.0 of the Model 100 Appl ication). The protective jacket design for the General Electric Shielded Container -
Model 1000 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 Thermal :
Packaging components, i.e., steel shells and lead, uranium and/or tungsten shielding, are Laaffected by temperature extremes of
-40 F and 130 c.
Package contents, at least singly-encapsulated or contained in specification 2R containers, or other inner containers, but not simited 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 1000 casks used since 1958 reveals no evidence of damage of significance to transport safety.
Water Spray and Free Drop:
Since the container is constructed of metal, 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 ex-posed surface of the packaging.
Compression:
The loaded container is capable of with-standing a compressive load equal to five times its weight with no change in spacing.
Summary and
Conclusions:
The tests or assessments set forth above provide assurance that the product con-tents are contained in the Shielded Con-tainer - Model 1000 during transport and there is no reduction in effectiveness of the package.
(c) Hypothetical Accident Conditions General :
The effectiveness of the strain rate calculations and engineering intuitive-ness in the design and construction of protective jackets was demonstrated with the GE Shielded Container - Model 100
( Re f. : Section 3.0 of the Model 100 Appl ication).
Extrapolations of the
_9_
General (continued)
Model 100 data were used in the design and construction of the GE Model 1000 protective jacket. The increased weight and dimensions of the Model 1000 container over the Model 100 container necessitated a protective jacket wall of 5/16 inch steel compared to a 1/4 inch wall for the Model 100.
Drop Test:
The design and construction of the GE Model 1000 protective jacket was based on an extrapolation of the proven data gen-erated during the design and constructio cask drop experiments b C. B. Clifford(1,2) and H. G. Clarke, Jr.(3 The laws of similitude were used in an analytical evalu-ation(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 1000 cask. The evaluation, included as Exhibit A, indicated a protec-tive jacket wall thickness of 5/16 inch.
The intent of the design for the GE Model 1000 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 (1)
C.B. Clifford, The Design, Fabrication and Testing of a Quarter Scale of the Demonstration Uranium Fuel Element Shipping Cask, KY-546 (June 10,1968).
(2)
C. B. Clifford, Demonstration Fuel Element Shipping Cask from Laminated Uranium Metal-Testing Program, Proceedings of the Second International Symposium on Packaging and Transportation of Radioactive Materials, Oct.14-18, 1968, pp. 521-556.
(3)
H. G. Clarke, Jr., Some Studies of Structural Response of Casks to Imr.act, 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. -
I Drop Test (continued)
(Ref.: Section 3.0 of the Model 100 Application).
It is expected that damage not exceeding that suffered by the GE Model 100 will result if the GE Model 1000 is subjected to the 30 foot drop test.
Puncture Test:
The intent of the design for the GE Model 1000 is to sustain less or equal damage to the packaging during accident conditions than the deformation suffered by the GE Model 100.
It is expected that deformation not greater than that sustained by the GE Model 100 will be received by the GE Model 1000 in the event that the package is subjected to the puncture test.
Thermal Test:
Since it is expected that the GE Model 1000 cask will sustain negligible damage 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, as esseatielly undamaged. Accordingly, the package was assessed using the General Electric Transient Heat Transfer Computer Program Version D (THTD), which allows the analysis of the general transient prob-lems involving conduction, convection and radiation. The program allows the thermal properties of the materials to be entered as a function of temperature and the boun-dary conditions to be entered as a function of.nne.
The significant assumptions, approximations, and boundary conditions used for the analysis are listed below:
. 1 b
Thermal Test (continued) 1.
Fire temperature 1472 F 2.
Effective fire Emissivity 0.9 3.
Fire shield surface Emissivity 0.8 and constant with temperature 4.
Emissivity of other Surfaces 0.8 and constant with temperature.
5.
There is intimate contact between the lead shielding and the stainless steel shell of the cask.
6.
There is negligible heat transfer by conduction through the pipes used as spacers between the cask and the first shield and between the two shields of the protective jacket.
7.
There is negligible heat transfer by convection between the two shields of the protective jacket and between the cask and first shield of the protective jacket.
l 8.
There is an internal heat load of 250 l
l watts with assessed temperatures equal l
to 0.625 times the temperatures recorded for the GE Model 100 as listed in Sec-tion 2.0 of th.s Model 100 Application.
l The computer program calculations were run for a 30 minute fire.
The calculations l
indicate a maximum temperature rise of less than 275 F for the lead after 30 minutes and no lead melting could be expected.
l Exhibit A to the Mocel 100 Application further describes the computer code THTD.
1,
r
\\
l Water Immersion:
Since optimum moderation of product material is assumed in evaluations of criticality safety snder accident conditions, the water immersic.> test was not necessary.
Summary and
Conclusions:
The accident tests or assessments described 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 1000 is adequate as packaging for the contents specified in 2.0 of this application.
4.0 Procedural Controls Vallecitos Site Safety Standards have been established and implemented to assure that shipments leaving the Vallecitos Nuclear Center (VNC) comply with all the Certificates of Compliance 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 - Exempt The fissile contents of this package are limited to not more than 15 grams and, therefore, in accordance with the provisions of 10CFR71.5(a) and 49CFR173.396(a)(1), the licensee is excmpt from the requirements of the above regulations concerning these fissile loadings..
6.0 Modes of Transportation All modes with the exception of passenger aircraft are requested.
l j
ja?ps Kso,4 UNITED STATES 1
X.
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 g
p f
MEMORANDUM FOR: TERA Corp.
FROM:
US NRC/TIDC/ Distribution Services Branch
SUBJECT:
Special Document Handling Requirements 1.
Please use the followf.g special distribution list for the attached document.
h 2.
The attached document requires the following special considerations:
D not send oversize enclosure to the NRC PDR.
3 l
Only one oversize enclosure was received - please
/
TIL _ _ _ _, _.
return L. ^_o_L...
te HRC Pot < ofenA., m s cro Dcl.e or, Proprietary information - send aff.idavit only to the NRC PDR O Other: (specify) t l
l 4
'/
d O
h cc: DSB Files TIDC/DSB uthbri Signature 1
.