ML19276J393
| ML19276J393 | |
| Person / Time | |
|---|---|
| Site: | 07109046 |
| Issue date: | 04/22/1980 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19276J394 | List: |
| References | |
| 16168, NUDOCS 8005270339 | |
| Download: ML19276J393 (13) | |
Text
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n NUCLEAR ENERGY ENGINEERING GENERAL ELECTRIC COMPANY, P.O. BOX 460, PLEAsANTON, CALIFORNIA 94566 DIVISION April 22,1980 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. 9046
Dear Mr. MacDonald:
General Electric has for several years shipped large quantities of radio-active materials in the G.E. Model 1100 shipping container.
Electric hereby requests that Certificate of Compliance No. 9046 for that General container be renewed.
In support of this request a consolidated application for certification is enclosed with this letter.
vertical lines.
Some minor editorial changes are designated by A check for the $150.00 renewal fee is enclosed.
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,
- h. b G. E. Cunningham Sr. Ucensing Engineer ofL g
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/11 enclosures 8005270 S h
GENERAL ELECTRIC SHIELDED CONTAINER - MODEL 1100 1.0 Packace Description - Packacing (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 additional containers of this model if different from the lifting and/or tiedown devices described in this application will satisfy the require-ments of 10CFR71.31(c)(d). This container is detailed in G.E. Drawings 106D3991, Rev.1, 106D3992, Rev.1, 277E416, Rev.1, and 144F612, Rev. 3, attached.
Shape:
An upright circular cylinder shielded cask and an upright circular cylinder protective jacket with attached square base.
Size:
Shielded cask is 24 inches diameter by 31-1/4 inches high.
The protective jacket is 43-7/8 inches high by 40-3/4 inches across the box section.
The base is 41 inches square.
Construction:
The cask is a lead-filled carbon and stain-less steel weldment.
The protective jacket is a double walled strutture 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 5600 pounds.
The protec-tive jacket and base weigh 1400 pounds.
(b)
Cask Body:
Outer Shell:
3/8 inch thick steel plate, 30-5/8 inches high by 24 inches diameter with a 1/2 inch bottom plate and a 1/2 inch top flange.
Cavity:
0.120 inch stainless steel wall and a 3/16 inch bottom plate, 4.260 inches inner diameter by 7-3/4 inches deep.
Shielding Thickness:
9-3/8 inches of lead on sides,11 inches of lead beneath cavity.
Penetration:
None.
Filters:
None.
Lifting Devices:
Two diametrically opposed ears welded to sides of cask, covered by protective jacket during transport.
Primary Coolant:
Ai r.
(c) Cask Lid Shape:
A right cylinder attached to flat plates.
Size:
Top plate is 24-3/4 inches diameter by 1/2 inch thick.
Bottom plate is 15-3/8 inches diameter by 1/2 inch thick. The right cylinder is 15-3/8 inches diameter by 11 inches high.
Construction:
Lead filled steel clad cylinders welded to circular steel plates.
Closure:
Four - 1 inch UNC - 2A 1-1/2 inch 0
long steel bolts equally spaced 90 apa rt on a 19-1/2 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, 3/4 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 diametrically across top and vertically down sides.
Size:
43 - 7/8 inches high by 40-3/4 inches wide across the box section.
Outer cylindrical diameter is 30 inches.
Inner diameter is 26-3/4 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 Construction (continued) 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:
Two rectangular 7/8 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.
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 Shape:
Hollow cylindrical weldment with square bottom plate.
Four I-beams are welded to square bottom of plate.
Size:
Bottom plate is 41 inches square and 1/2 inch thick.
The cylindrical collar is 25-7/8 inches in outer diameter by 3 inches high.
The I-beams are 3 inches high by 41 inches long.
Construction:
The cylindrical collar houses two sets of 1-1/2 inch by 1-1/2 inch by 3-1/8 inch steel energy absorbing angles separated by a 5/16 Construction (cont.)
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 materials 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 with-stand the combined effects of the internal heat load and the 1475 F fire with closure pre-tested for leak tightness.
(c) Fissile Content Not to exceed 15 grams fissile.
(d) Radioactivity That quantity of any radioactive material which does not generate spontaneously more than 810 thermal watts by radioactive decay and which meets the requirements of 49CFR 173.393.
(e) Heat Total maximum internally generated heat load not to exceed 810 thermal watts. An analytical determination, described in Exhibit B to the Application for the GE Model 700 container, of the container tem-perature profile and heat load resulted in the following:
(e)
Heat (continued)
Cask Surface 0
200 F Inner Shield 126 F U
Outer Shielo 95 F 0
Ambient 80 F Heat Load 810 watts General Electric will analyze by test cr other assessment each container heat loading prior to shipment to verify that the require-ments 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 dis-sipation.
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 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 whi;h is used in the tiedown system or that portion which con-stitutes the principal lifting device failed in such a manner to allow the protec-tive 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) re-garded as a simple beam supported at its ends along its major axis, is capable of with-standing a static load, normal to and dis-tributed along its entire length equal to (a) General (continued) 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 pres-sure 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 Commission and the Department of Transportation pre-scribing the procedures and standards of packaging and shipping ar.J the requirements governing such packaging and shipping but woD1d protect the shielded cask from signifi-cant deformation in the event of an accident.
In the event that the package was involved in an accident, a new protective jacket could be readily supplied and the shipment continued with minimal time delay.
The effectiveness of the strain rate calcu-lations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the General Electric Shielded Container - Model 100 (Ref.: Sec-tion 3.0 of the Model 100 Application).
- TID-7651, SE-RR-65-98 (a) General (continued)
The protective jacket design for the General Electric Shielded Container -
Model 1100 was 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 de-formation 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 unaffected by temperature extremes of 0
U
-40 F and 130 F.
Package contents, at least singly-encapsulated, or contained in specification 2R containers or other inner containers, but not limited to special form, will not be affected by these temper-ature extremes.
Pressure:
The package will withstand an external pressure of 0.5 times standard atmospheric pressure.
Vibration:
Inspection of the Model 1100 casks used since 1958 reveals no evidence of damage of significance to transport safety.
Water Spray and Since the container is constructed of Free kop:
metal, there is no damage t enatainment resulting from dropping the s
.ner 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.
Compression:
The loaded container is capable of with-standing a compressive load equal to five times its weight with no change in spacing.
Sumnary and
Conclusions:
The tests or assessments set forth above provide assurance that the product con-tents are contained in the Shielded Con-tainer - Model 1100 during transport and there is no reduction in effectiveness of the package.
(c) Hypothetical Accident Conditions General :
The effectiveness of the strain rate cal-culations and engineering intuitiveness in the design and construction of protective jackets was demonstrated with the GE Shielded Container - Model 100 (Ref.:
Section 3.0 of the Model 100 Application).
Extrapolations of the Model 100 data were used in the design and construction of the GE Model 1100 protective jack 2ts.
Drop Test:
The design and construction of the GE Model 1100 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 cask drop
.g.
Drop Test (continued) experiments by C. B. Clifford(I'2) and H. G. Clarke, Jr.(3)
The laws of simili-tude 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 1100 cask. The evaluation, described in GE -
Model 1000 Application, Exhibit A, indicated a protective jacket wall thickness of 5/16 inch. The intent of the design for the GE Model 1100 is, during accident conditions, to sustain damage to the packaging not greater than the damage sus-tained by the GE Model 100 during its acci-dent condition tests (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 Madel 1100 is subjected to the 30 foot drop tr.:st.
Puncture Test:
The intent of the design for the GE Model 1100 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 (l)
C. 8. 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 Raoioactive Materials, Oct. 14-18, 1968, pp. 521-556.
(3)
H.
'. Clarke, Jr., Some Studies of Structural Response of Casks to Impact, Proceedings of the Second International Symposium of Packaging and Transportation 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.
Puncture Test (cont.)
not greater than that sustained by the GE Model 100 will be received by the GE Model 1100 in the event that the package is subjected to the puncture test.
Thermal Test:
A fire transient using the THTD Code was not run on this container.
However, re f-erence is made to the shielded container Model s 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 eacn container heat load to verify that the loaded container will 0
withstand the 30 minute 1475 F fire without significant lead melting in the cask.
Water Immersion:
Since optimum moderation of product material is assumed in evaluations of criticality safety under accident conditions, the water immersion test was not necessary.
Summary and Conclu-The accident tests or assessments described sions:
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 1100 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 che Vallecitos Nuclear Center (VNC) comply with all 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 exempt from the requirements of the above regulations concerning these fissile loadi-as.
6.0 Modes of Transportation All modes with the exception of passenger aircraft are requested.