LD-88-050, Application for Rev to Certificate of Compliance 9022 for Model CE-250-2,increasing Allowable Enrichment That Can Be Transported by CE-250-2 Shipping Container.Fee Paid
| ML20207E327 | |
| Person / Time | |
|---|---|
| Site: | 07109022 |
| Issue date: | 07/01/1988 |
| From: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 24497, LD-88-050, LD-88-50, NUDOCS 8808180009 | |
| Download: ML20207E327 (43) | |
Text
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COMBUSTIOphENGiNEERING p}
JUL15;ggg)10, calq Nun xN MML swnou Q
DOCKET CLERK f
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,g, July 1,1988
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Docket No. 71-9022 d
Package Identification No. USA /9022/ AF g/ rg E
Package Model No. CE-250-2 g,
f, c n g2 Le JF
-9 Mr. Charles E. MacDonald, Cnief c:
- J/ f 3 ~d 73- " - - - - ---
Transportation Branch 4
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Division of Safeguards and Transportation fb -
A -~p Attn:
Document Control Desk Tr-
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U. S. Nuclear Regulatory Commissio 1 C$t;c$hg j"P *"# --
Washington D. C. 20555 Date 4Q By _,.
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Subject:
Certificate of Compliance No. 9022 Amendmentdtequest
Reference:
Letter, C. E. MacDonald-(NRC).to P. L. McGill (C-E), daMd June 10, 1988
.1 u
Dear Mr. MacDonald:
m Enclosed is Combuation Engineering's submittal of an amendment request for Certificate of Compliance No. 9022 for chipping container Model Number CE-250-2.
The application fee for this amendment request is being transmitted under separate cover.
Three (3) c6ples of the Enclosure are fp provided for your use.
The enclosed application involves a request to increase the allowable enrichment that can be transported by the CE-250-2 shipping Container from 4.1 to 5.0 weight t U235.
In order to meet our current commitments, it is requested that a revised Certificate of Compliance be issued by August 1,1988.
In order to facilitate your review of this application, we n ym would be pleased to meet with you at your convenience to explain the gg changes to the application and respond to any questions that you may co have.
IEo gg Combustion Engineering has also recently received your letter (Reference) k po) no concerning Vermiculite insulation in the CE-250-2 container.
As indicated in your June 30 conversation with C. M. Molnar of my staff, we are j
$g investigating your concern with the CE-250-2 cask and will audress the g g
-o issue before October 1,1988, as requested.
~
N Power Systems 1000 Prospect Hal Road (203) 688 1911 G,mbustion Eng'neenng. Inc.
Post OMce Box 500 Telex: 99297 Windsor, Connecticut 06095 0500 A H 97
l s
l Mr. Charlos E. MacDonald LD-88-050 l
July 1,1988 Page 2 of 2 l
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l If I can be of further assistance on this matter, please do not hesitate to call me or Mr. D. L. Sibiga of my staff at (203) 295-5216.
Very truly yours, COMBUSTION ENGINEERING, INC.
Director Nuclear Licensing AES ss
Enclosure:
As Stated cc:
R. F. Burnett (NRC)
R. E. Cunningham (NRC)
W. G. Mcdonald (NRC)
J. Roth (NRC - Region 1)
L
'M APPENDIX A June 1988 Model CE-250 _ Granium Oxide Powder / Pellet Shipping Container, Certificate of Compliance Number 9022, Docket Number 71-9022, Package Identification Number USA /9022/AF 1.0 GENERAL INFORMATION 1.1 Introduction This application is submitted for approval for delivery to a carrier for transport of Combustion Engineering's.7E-250-2 shipping container.
The CE-250-2 shipping container is uset.
the transport of uranium oxide with a measured moisture content oi less than 5 wt %
1 and enriched to a maximum of 5.0% U235.
This shipping container meets the criteria of 10 CFR Part 71 for shipping as Fissile Class II, with a maximum of 90 packages per shipment and a transport index of 0.56.
1.2 Packace Descriotion 1
The CE-?50-2 package consists of a 16 gauge steel inner container 11-5/8" inner diameter by 57-1/4" long with a bolted and gasketed top flange closure and steel welded bottom plate.
The inner container is centered within a 22-1/2" I.D. by 68-3/8" long (inside dimension) 16 gauge cuter steel drum.
The inner container is supported by twelve 1/4" diameter steel spring connected to the inner container at the top flange and the bottom of the container.
The void space between the inner and outer container is filled with vermiculite.
l The CE-250-2 package design incorporates two containment boundaries excluding the inner stainless steel can containing the uranium oxide.
The secondary containment consists of the bolted and gasketed inner container.
The primary cohtainment consists of the surrounding 16 gauge steel drum.
Closure of the inner container is maintained by a gasket (silicone rubber or an Anchor Packing Company gasket:
"Target" or "425") and j
(6)1/2" hex head bolts and nuts.
These bolts and nuts secure the 1/2" steel inner lid to the package.
The outer container is then sealed with a standard 17H 12 gauge nut and bolt ring over the gasketed 16 gauge outer lid.
The weight of the package is approximately 575 lbs. When loaded and is constructed in accordance with Combustion Engineering's Drawing No. NFM-E-Z2175, Rev. 03 (Appendix 1.3).
It should be noted that the CE-250-2 package does not contain any valves, sampling ports or protrusions.
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1.2.2 Operational Features Not Applicable - The CE-250-2 package is a simple design with no operational features.
1.2.3 Contents of Packacina Each package will be limited to four cans of uranium oxide in powder form enriched to a maximum of 5.0 w/o U235 and having a measured moisture content of 5 wt % or less.
A spacer will be used to make up the rema.ining volume within the inner package.
Each can contains a maximum of 30 Kg uranium oxide for a total of 120 Kg uranium oxide per CE-250-2 package.
At a maximum of 5.0 w/o in the isotope U235, the package would contain a maximum of 5.5 Kg U235.
The weight of the total contents will not exceed 300 lbs.
1.3 Accendix i
Dimensional details of the CE-250-2 shipping container are described in CE Drawing NFM-E-Z2175, Rev. 03.
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2.0 STRUCTURAL EVALUATION 2.1 Structural Desian 2.1.1 Discussion The secondary containment of the package is the 11-5/8" I.D. x 57-1/4" long 16 gauge steel inner container.
The inner container closure is achieved by securing a 1/2" steel lid to the inner flange with (6) 1/2" Hex Head Bolts and Nuts tack welded to the flange.
An alternate closure method is shown in View B of Drawing NFM-E-Z2175, Rev. 03.
The primary containment vessel consists of two modified 55-gallon drums which have been welded together to the following dimensions:
22-1/2" I.D.
x 68-3/8" long (inside dimension).
The closure of the outer container is assured by a standard 17H 12 gauge ring with 5/8" bolt and nut.
See Drawing NFM-E-Z2175, Rev. 03 in Appendix 1.3 2.1.2 Desian Criteria The test results described in Appendices 2.10-1, 2.10-2, 2.10-3 support the structural requirements specified in 10 CFR Part 71.
2.2 Weichts and Centers of Gravity
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The CE-250-2 container weighs approximately 575 lbs. When loaded.
The 4 cans of uranium oxide (30 Kg each) weigh approximately 300 lbs.
with the CE-250-2 container weighing approximately 275 lbs.
The container is approximately symmetrical; the center of gravity is at the center of the container.
When the cans are loaded inside the inner container, the center of gravity shifts vertically to a slightly lower point because of the spacer used to make up the remaining volume within the inner package.
2.3 Mechanical Procerties of Materials Mate
_ls of all structural components used in the manufacture of the conta
- have physical and mechanical properties equivalent to or better th
.6 gauge steel.
2.4 General Standards for All Packacina 2.4.1 Chemical and Galvanic Reactions There are no significant chemical, galvanic or other reactions among the packaging components and the package contents.
The CE-250-2 shipping container is fabricated of carbon steel.
The contents are:
i vermiculite for insulation between the outer and inner containers, stainless steel cans containing uranium oxide in the powder form and having a moisture content of 5 w/o or less.
2.4.2 Positive Closure Pesitive closure of the CE-250-2 containers is assured by:
1)
The inner container being gasketed and sealed with 6 Hex Head Bolts and
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Nuts and 2) the outer container being sealed by a standard 17H 12 gauge ring with a 5/8" bolt and nut.
Both of these closure systems insure that the container cannot be inadvertently opened.
2.4.3 Liftina Devices No lifting devices are incorporated as a structural part of this container.
2.4.4 Tiedown Device 3 No tiedown devices are incorporated as a structural part of this j
container.
2.5 Standards for Tvoe B and Larce Ouantity Packacina N/A (Type A quantity per package).
2.6 Normal Conditions of Transoort The CE Model 250-2 package is identical to the Westinghouse BB-250-2 package except that the overall length is 68-3/8" (inside dimension) and the inner container length is 57-1/4" (compared to 74" and 63-1/2" respectively).
These packages both utilize design concepts which are similar to those used in the design of the NUMEC LA-36 and pu 10-1 packages.
These packages were tested in accordance with the requirements specified in 10 CFR Part 71 Appendix A for normal conditions to assure compliance with the standards outlined in 10CFR71.
2.7 Hvoothetical Accident Conditions This sectio'. describes the hypothetical accident conditions as specified in Appenlix B to 10 CFR Part 71.
The inner container of the CE-250-2 when fully loaded weighs approxi=ctely 340 lbs. over a base area of 121 in resulting in a vertical loading of 2.8 lbs/in.
The inner, container of the NUMEC Pu 10-1 package, when fully loaded, including the neutron moderator weighs 279 lbs. over a base area of 78.54 in resulting in a vertical loading of 3.55 lbs/in.
Thus, the tests performed on the latter container are valid for the CE-250-2 package.
As a result it is concluded that:
1)
The integrity of the package is not affected by the tests, i
Because the lid is bolted in a minimum of six places around the top of the drum, separation of the lid from the drum does 1
not occur.
In this connection, test experience with the BB-250-2 shows that as a result of a top corner drop, the lid and the body are folded together into a tighter closure.
i 2)
The incorporation of five inches of vermiculite is equal to j
that provided in the NUMEC package, and is sufficient to i
assure that after the drop and thermal tests, the temperature l
of the inner container of the CE-250-2 package would not exceed the observed maximum of 500 F.
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3)
The test series does not result in the addition of moderation to the contained fissile material.
4)
The dimensions of a damaged package are conservatively taken to be 20" O.D.
x 64-3/8" long (inside dimension).
This assumes a reduction of 2-1/2" in diameter as the result of a drop test with the package in a horizontal position, plus a reduction of 4" in height as the result of a drop test with the package in a vertical position.
No deformations in excess of these values were experienced during the testing of the Pu 10-1 package.
2.8 Soecial Form N/A (All radioactive material in the packages is in normal form) 2.9 Fuel Rods N/A (The CE-250-2 package is not used for the shipment of fuel rods) l 2.10 Accendix 1.
BB-250-2 Test Results - Westinghouse SNM-338 2.
NUMEC Pu 10-1 Test Results 3.
NUMEC LA-36 Test Results l
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3.0 THERMAL EVALUATION Materials of all structural components used in the manufacture of the container have physical and mechanical properties equivalent to or better than mild steel throughout a temperature range of -40*F to 1500 F.
(See Appendix 2.10-2, page (VI-7) of NUMEC Pu 10-1 tests "No damage was suffered by any of the components or materials of construction due to exposure to the thermal test.")
4.0 CONTAINMENT 4.1 Containment Boundarv The primary containment of the CE-250-2 package is the outer 16 gauge 55-gallon drums which have been welded together (22-1/2" I.D. x 68-3/8" long inside dimension).
The secondary containment boundary is the 16 gauge steel inner container, 11-5/8" inner diameter x 57-1/4" long.
As a result of the tests performed on the Westinghouse BB-250-2 and the NUMEC Pu 10-1 containers, it was determined that the integrity of the CE-250-2 package would not be affected by the test conditions.
4.1.1 Containment Vessel The outer shell of the CE-250-2 package is composed of two modified 55 gallon drums made of 16 gauge steel welded together.
4.1.2 Containment Penetrations There are no penetrations into the primary containment.
4.1.3 Seals and Welds All seals and welds are specified in Drawing NFM-E-Z2175, Rev. 03.
4.1.4 Closure Closure of the outer container is achieved by using a standard 55 gallon 12 gauge Nut and Bolt ring securing the gasketed 16 gauge outer lid.
The closure of the inner container is maintained by a gasket and 6 Hex Head Bolts.
These two closure devices provide positive sealing of the container.
4.2 Recuirements for Normal Conditions of TransDort It is concluded that under normal conditions of transport (as specified in 10 CFR Part 71, Appendix A) the tests results indicate the following:
1)
There will be no release of radioactive material from the containment vessel.
2)
The ef fectiveness of the packaging will not be reduced.
3)
There will be no mixture of gases or vapors in the container which could, through any credible increase of pressure or an explosion, significantly reduce the effectiveness of the package.
4)
The package is so designed and constructed, and its contents so limited, that under the normal conditions of transport specified in Appendix A of 10 CFR Part 71:
i
.s a.
The package will be subcritical.
Criticality safety j
calculations are presented in Section 6 of this application.
b.
The geometric form of the package contents will not be substantially altered.
c.
There will be no substantial reduction in the effectiveness of the packaging, inc.1.uding:
(i)
Reduction by mcre than 5 percent in the total effective volume of the packaging on which nuclear safety is assessed; (ii)
Reduction by more than 5 percent in the effective spacing on which nuclear safety is assessed, between the center of the containment vessel and the outer surface of the packaging, or; j
(iii)
Occurrence of any aperture in the outer surface of the packaging large enough to permit the entry of a 4" cube.
4.3 Containment Recuirements for the Hvoothetical Accident Conditions The effect on the loaded CE-250-2 container of conditions hypothesized to occur in an accident was assessed during the testing of a loaded NUMEC Pu 10-1 container.
Two 30-foot free drop tests and puncture tests as specified in Appendix B of 10 CFR Part 71 were conducted.
These tests demonstrated that no radioactive material would be released.
The thermal tests performed on the NUMEC Pu 10-1 container demonstrated that no damage was suffered by any of the components or materials of construction during the thermal test.
Examination of the containers subsequent to their removal from 24 l
hours of immersion under three feet of water revealed that no water leaked into the containment vessel.
i It was evident from the above tests that the package would remain subcritical because the material remains confined to a subcritical geometry and the geometric form of the contained material is not altered.
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5.0 SHIELDING EVALUATI0ff N/A (The packages are used'Yor the shipment of uranium oxide in powder form im stata.less steel cans which are then placed in the container.
External dose rates are less than 1 mR/hr 8 y at the surface of the CE-250-2 i
package.)
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6.0 CRITICALITY SAFETY EVALUATION 6.1 Discussion and Results The CE-250-2 shipping drum design incorporates a steel inner cylinder which can hold up to 4 fuel-bearing stainless steel cans.
The void between the outer drum and the inner steel cylinder is filled with vermiculite.
It has been shown that the hypothetical accident conditions do not compromise the leak-tight feature of the container.
The inner cylinder design thus provides an added margin of criticality safety by maintaining a greater separation distance between fuel-bearing containers and by excluding moderator from this region.
A summary of the criticality evaluation (as Fissile Class II) is presented as follows:
NORMAL CONDITIONS Number of undamaged packages calculated to be 144 suberitical (full water reflection) 3 Package size, cm 444,333.03 ACCIDENT CONDITIONS Number of damaged packages calculated to be subcritical with optimum interspersed hydro-geneous moderation and full water reflection 144 3
Package size, cm 330,485.36 Transport Index 0.56 6.2 Packace Fuel Loadina All material to be shipped in the CE-250-2 package will meet one of the following two restrictions:
1.
The material to be shipped will be homogeneous and sampled to verify that the moisture content is less than 5 wt %.
or 2.
The material to be shipped will be heated to at least 600 C in a moist atmosphere for at least one hour to assure dryness.
In additien, a maximum of 30 kg of uranium oxide per can will be allowed (four cans maximum per package).
6.3 Model Soecification 6.3.1 Description of Calculational Model The calculational model (Figure 6.1) is nearly identical to the actual package dimensions.
The following assumptions were incorporated in the model:
I 1)
Each stainless steel can was assumed to be packed full with UO at a bulk density of 3.5 gm UO /cc.
This translates to 2
over 46 kg UO2 Per container.
A maximum of 30 kg uranium oxide is allowed.
2)
The fuel was assumed to contain 5 wt % H 0.
The limit is 2
verified by analysis.
3)
The package was assumed to contain the maximum number of cans (4) all at the maximum allowable enrichment of 5.0% U235.
4)
A 1 foot thick external water reflector was assumed for each Case.
5)
For the array cases, a square pitch was assumed.
6)
For the accident case, it was assumed that the drums were reduced 2-1/2" in diameter and 4" in height.
These reductions were obtained from the previously referenced test results.
7)
Optimum interspersed hydroceneous moderation was assumed for tha accident case.
6.3.2 Packace Recional Densities Fuel ComDosition U235 -.00039524 atoms / barn - cm U238 -.00741468 Hydrogen
.01231512 Oxygen
.02177740 Vermiculite Comoosition (Drvi*
.00043133 atoms / barn - cm Silicon
.00043155 i
.00086310
.00258930 Oxygen
- 3 mg o (Fe - A1)O 023 3 SiO2 6.4 Criticality Calculations The KENO-IV Code with 16 group Hansen-Roach cross section sets was used to datermine the reactivity of the CE-250-2 drums under normal conditions of transport and under hypothetical accident conditions.
The following results were obtained:
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Normal Conditions of Transoort Descriotion eff 12 x 12 x 1 array, 1 ft. thick external H2O reflector, 5% H O in fuel:
2 Dry external mist between drums 0.6361 1 0083 Wet external mist (1gm/cc H O) 0.5519 i.0093 2
Hvoothetical Accident Conditions Descriotion eff 12 x 12 x 1 array, 1 ft. thick O.7015 1 0064 external H O reflector, 2
5% H O in fuel 2
The last case was the highest reactivity calculated in a parametric study of an array of damaged packages under various external mist densities.
Results of this study are shown in Figure 6.2.
6.5 Code Validation The KENO Code with 16 group Hansen-Roach cross sections was validated in an Oak Ridge report entitled "Validation of the "KENO" Code for Nuclear Criticality Safety Calculations of Moderated, Low-Enriched Uranium Systems" by G. R. Handley and C. M. Hopper, Y-1948, issued June 13, 1974.
In the study, the Monte Carlo computer code, KENO, was employed to calculate 40 critical experiments with i
uranium enrichments in the U235 isotope of 5% or less.
A variety of
. geometries and materiala were considered.
The code input parameters and the 16 energy-group-cross sections were included.
It was concluded J
that the code and cross sections are adequate and that reliable criticality safety calculations may be made for systems of general interest.
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l' R-NE- 005 Al Page 5 Figure 6.1 CE-250-2 SHIPPING CONTAINER KENO-N MODEL 14.7638 CELL 80uNDARY 14.9035 VERMICULITE p ulsi
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.(25.5307) ACCIDENT CASE 28.71t7 NOM AL CASE CARICN STEEL p.139 7 WD 1.27 VERMICULITE j
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7.0 MAINTENANCE TESTS AND MAINTENANCE PROGRAM 7.1 Acceotance Tests All containers to be fabricated will be constructed in accordance with CE Drawing NFM-E-Z2175, Rev. 03 and shall be source inspected i
prior to leaving the vendor's facility.
Changes to the design of the l
container which fall outside of the safety envelope specified in this application will be submitted to NRC for approval.
This may include j
ratesting of the container if analytical results are not capable of demonstrating that the test sequence previously performed would be applicable to the changes made.
7.2 Maintenance Procram Health Physics personnel determine during the loading inspections when any repair or replacement of material is required.
i 1
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APPENDIX 2.10-1 WESTINGHOUSE LICENSE SNM-338 BB-250-2 TEST RESULTS l
SNM-338 I
Shipping - nro N-.
^
16.4 Limits and controls The Fissile Class II limit, Fissile Class III limit, and the Procedural Controls presented in Sections 4.4, 4.5, and 4.6, respectively, will apply directly to this package, if "Equipment Specification E-676498" is sub-stituted for "Equipment Specification E-676200".
17.
NUMEC LA-36 shiocino Packace The construction, limits on contents, and loading procedures will be in strict compliance with those given in Amendment 71-1 of License SNM-145, Docket 70-135, 18.
BB 250-2 shiccine Packace 18.1 Packacine Descriotion Designati*on - BB 250-2 Gross height - 575 pounds, sauxiluam Fabrication,- The design and fabrication details for this container are given in Westinghouse sketch 1
\\
- SKA-252 which is attached as Appendix L to this y
application.
l Coolants - Not applicable r
18.2 contents Descriotion i
Radicactivity - Not applicable Identification and enrichment of SNM - The SNM will be unirradiated uranium enriched to a maximum of 4 w/o in the isotope U-235.
i R
a Dockel 70-337 Date: 11/10/66 Revision No.13 Date: 3/1/68 Pace U
a SNM-338 Shipping - Nr; 18.2 (continued'- BB 250-2)
Form of SNM - The SNM will be in the form of bulk a density I 2 uranium o'ide (UO
- U0 w
x 2
38 grams / cubic centimeter.
The moisture content of the SNM will not exceed 0.5 w/o and 'the total H/U ratio, including all packaging materials, will ne:
exceed 1.13.
Neutron Absorbers, etc. - None Maximum Weight of Fissile Content - 4.0 kilograms U-235 Maximum Net Weight of Contents - 250 pounds of oxides enriched I 4 w/o contained in 9.5 inch diameter Fiberpak drums or other containers having equiv-alent strength.
These are contained in an 11.5 inch-
$)
diameter (maximum) cylindrical inner container.
Maximum Decay Heat - Not applicable 18.3 Compliance with Suboart C of 10 CFR 71 General Standards - The materials which have been*
specified for this package will not result in significant chemical or galvanic reactions.
There will be no specific lif ting or tie down devices.
1 General Criticality Standards - Tests demonscrate that immersion in water, alone, is not sufficient to affect the structural integrity of the 9.5 inch di-ameter Fiberpak drums.
Calcula tions using LEOPARD procedures show that a fully reflected, 11.5 inch diameter, infinitely leig cylinder is nuclearly n
\\
,)
safo for homogeneous urariium enriched I 4 w/o in U-235 under any conditions of moderation.
Docket 70-337 Defe: 11/18/66 Revision No.13 Dola:
3/1/G8 Pena M
g SNM-338 a
~
Shipping - NPD C
18.3 (continued - BB 250-2) c Nornal and Accident Conditions Evaluation - This package utilizes design concepts which are similar to those used in the design of the NUMEC LA-36 and Pu-lO-1 packages, described in SNM-145 and SNM-414, i
respectively.
The outer shell consists of two 16 ga,.22.5" diameter (nominal) steel drums welded
)
end-to-end to form a package approximately 74" l
long.
The inner container is an 11.5" diameter (maximum), 16 gauge (nominal) steel cylinder with a flanged closure consisting of a 1/2 inch thick (minimum) bolted flange and flange cover.
A min-
'l imum of six 1/2"-13 NC bolts are used to seat a 1/8 inch thick Anchor Packing Company "Target" or
('S "425" gasket which is provided to assure. a leak-L/
tight closure.
Six tightly closed Fiberpak drums contain the uranium oxide.
These drums have a nominal '9.5 inch diameter.
Vermiculite is used to provide thermal and mechanical insulation for the gasketed inner container which is positioned with a minimum of 12 steel spring spacers, as shown in i
the sketch #SKA-252.
The top insulation plug may 4
be fabricated of unibestos.
At least 5 inches of vermiculite insulates the inner container from the drum, except at the bottom where its thickness may be 4 inches.
j The effects of the hypothetical accident conditions specified in Appendix C of 10 CFR 71 arc considered on the basis of the results described by NUMnc.
^'.
Decket 70-337 Daio: ll/10/6ci Revision No.16 Date: 4/8/68 Pena 45
g SNM-338' r
Shipping - NPD 18.3 (continued - BB 250-2)
Normal Conditions of Transport - All conditions deceribed in the referenced licenses apply to this package.
Because the package array is based on the consid-eration that each vertical projection of packages is replaced by a continuous cylinder having an identical length, the loss of spacing incurred in a vertical four foot drop test is not of concern.
It is considered that the icw horirontal loading will result in minimal displacement of the inner container in a horizontal drop test.
%ccident Test Conditions - The inner container of the BB 250-2, when fully loaded, weighs 329.4# result-2 ing in a vertical loading of 3.17 lbs/in over a
(.s) 2 base area of 103.87 in.
The inner container of the NUMEC Pu-10-1 container, when fully loaded, and ine'luding the neutron moderator weighs 279=,
resulting in a vertical ' loading of 3.55 lbs/in 2
over a base area of 78.54 in.
When placed in a horizontal position, the leadings are 0.456 lb/in f or the BB 25 0-2, and 0.442 lb/in for the NUME Pu-10-1 container.
Thus the tc ts perferr.rd en the latter centainer are valid for the 33 250-2 pa cka ge.
As a result, it is concluded that:
1.
The integrity of the package is not affected by the tests.
Because the lid is bolted in a minimum of six places around the top of the drum body, separation of the lid from
- ~ ~.
the drum body does not occur.
In thic conner Docket 10-337 Date: 11/i0/6o Rovision No.16 Dole: 4/8fse Pgpn u
{
SNM-338 1
Shipping - NFD
(
18.3 (continued - BB 250-2)
.g.
tion, test experience with the BB 250,1 shows that as a result of a top corner drop the lid and the body are folded together into a tighter closure.
2.
The incorporation of five inches of vermic-ulite is equal to that provided in the NUMEC package, and is sufficient to assure that after the drop and fire tests the temperature of the inner container would not exceed 'the observed maximum of 500 F.
Since the gasket is service rated to,800 F, the closure of the inner container is not compromised.
.3..
The test series does not result in the addi-()
tion of moderation to the contained fissile material.
4.
The dimensions of a damaged package are con-servatively taken to be 20" O.D. X 70" Lg.
This assumes a reduction of 2 1/2" in' diam-eter as the result of a drop test with the package in a horizontal position, plus a re-duction of 4" in height as the result of a drop test with the package in a vertical posi-tion.
No deformations in excess of these values were experienced during the testing of the Pu-10-1 package.
Single Package Evaluation - The safety considerations which pertain to a single package will assure nuclea:
sa'foty even assuming that the failure of the inner
/
Dockot 70-337 Dofe: 11/18/66 Revision No.18 Defe: 5/21/68 hele 4 */
SNM-338-Shipping-NFD 23.
Pellet ShiDoina Packace 23.1 Packaaina Descriotion The packaging will be the BB-250-2 packaging as described in part 18.
23.2 Contents Descriotion Radioactivity - Not applicable Identification and enrichment of SNM -
The SNM will be unirradiated uranium enriched to a maximum of 5 w/o in the isotope U235.
Form of SNM -
The SNM will be solid uranium compounds that will not react chemically or decompose to temperatures below 750 F.
The material will be enclosed within a container constructed of steel having a 24 gage specified minimum thickness.
The container will have a maximum ID of 8.5" and a nominal height of 15.375", and will utilize a gasketed lid with bolted locking ring.
The container will be constructed in accordance with U.S. Military Standard MS 24347.
As an inner container within the BB-250-2 packaging's inner cylinder, it is considered completely adequate to retain the SNM under the hypothetical accident conditions.
A comparison between the structural features of this container and a DOT Spec. 17-H container is shown in Table 23.2.1.
A maximum of four of these containers will be inserted in each package.
The maximum allowable H/U ratio, considering all sources of hydrogenous material within the inner cylinder of the packaging will not exceed 1.5.
A typical arrangement for shipping material in the form of pellets is shown in Westinghouse Drawing C7108D10, which is enclosed as part of Appendix R.
Military Standard MS 24347 also is enclosed as part of Appendix R.
Neutron Absorbers, etc.
None Maximum Weight of Fissile Content -
235 5.0 kilograms centained U
Docket 70-337 Date: 11/18/66 Revision No. 26 Date: 7/23/71 Page 60
, _ ~. _ _..
i SNM-338 Shipping-NFD 23.2 Contents Descriotion (continued) i l
Maximum Net Weight of Contents -
250 pounds of uranium compounds Maximum Decay Heat - Not applicable 4
Table 23.2.1 Structural MS24347 Spec. 17-H Feature Container Container Capacity (gal.)
3.5 5
Type Straight Side Straight Side Diameter (in.)
8.5 11.25 Height (in.)
15.375 12.75 Metal Gauge Body 24 24 Cover 24 20
)
Bottom 24 24 Closure Bolted Locking Multiple Lugs Ring Construction Welded Seam Welded Seam j
l l
Docket 70-337 Date:
11/18/88 Revision No. 26 Date:
7/23/71 Page 60,1
SNM-338 APPENDIX L Shipping - NED C..,
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APPENDIX 2.10-2 NUMEC LICENSE SNM-414 Pu 10-1 TEST RESULTS i
I
4 VI.1 NUMEC Pu-10-I Container VI.1.1 Container Descriotion a.
Gross Weight - 400 lbs. (max.)
b.
Model Number - Pu 10-I c.
Materials of construction, weights, dimensions, and methods of f ab'cication.
Outside drum:
19" or 24" diameter Pressure vessel:
Solid stainless steel with flanged, gasketed, bolted closure Pressure vessel gasket:
1/8" target or blue asbestos comprassed asbestos sheet Moderator:
Polyethylene granules with polyester resin filling interstices Primary container:
11 liter polyethylene bottle contained in two sealed polyvinyl bags More detailed design information is provided in the enclosed drawings, and in the following sections, d.
Identification and maximum radioactivity of radioactive constituents.
154 Curies (Transport Group I) 1.
Pu-239 1.71 Curies (Transport Group II) 2.
U -233 3.
U -235 5.24 x 10 (Transport Group III) e.
Classification of material to be shipped:
Large source and fissile material f.
Identification, chemical and physical forn, and maximum quantities of fissile constituents:
1.
Uranyl nitrate solutions having a concentration of U-235 not to exceed 350 grams per liter, provided that (a) t'e combined U-233 and plutonium content is not more than 1% of the U-235 content, and (b) the minimum free acid is 2 molar.
i 2.
Uranyl nitrate solutions having a concentration of U-233 and U-235 not to exceed 250 grama per liter provided that (a) the U-233 content is not greater j
than 10% of the combined U-233 and U-235 content, and (b) the plutonium centent is not more than 1% of the combined U-233 and U-235 content, and (c) the minimum free acid is 2 molar.
i VI-l 11-22-66
3.
Plutonium nitrate solutions having a concentration not to exceed 250 grams Pu-239 per liter, provided that (a) the Pu-240 content is at least 3% of the total plutonium, and (b) the minimum free acid is 2 molar.
4.
Hsximum quantity of material per package:
Ten (10) liters of solution, containing not more than 2.5 kilograms of fissile isotope.
9 Extent of reflection, amount and identity of non-fissile neutron absorbers in the fissile constituents, and the atomic ratio of moderation to fissile constituents.
The fissile asterial is contained in a polyethylene bottle
,0.16" was thickness) which is contained in a cadmium wrapped 3/16" thick stainless steel pressure vessel.
A 2 inch thick polyethylene-polyester resin composite surrounds the cadmium wrapped pressure vessel.
Items fl,2,3 and 4 above specifies the atomic ratios of moderation to fissile constituents.
h.
Maximum weight of contents:
42 pounds including the polyethylene bottle.
i.
Maximum amount of decay heat:
For plutonium containing less than 1 w/o Pu-238, we estimate a 30 F temperature differential hetween the solution and the outside of the container, yielding an internal temperature of 160 F under condition 1 of Appendix A, 10 CFR 71.
VI-2 11-22-66
t VI.1.2 Containar Evaluation VI.1.2.1 ceners1 St.$nelpy;d.s, i-.j a.
Internal Rosetions Allfissilensteris:iiscontainedwithinapolyethylene bottic (0.16" wall 'thickncoc) which is doubic bacced in 0.017. inch PVC, and contained in a pressure vessel tsbri-cated fron stainicss stcol, precludinc the posJibility of internal chcaical reactions with the packaging naterial.
k.
Closurc ith Clo::ure of druiu con:ists of a 12 gauge bolted ring w/8" bolt:
drop forged lucs, one of which is thrceded, using a 5 c.
Lif ting D: vices No lif tina devicen are incorporated as a structural part of the centainer or its lid.
Tic down bevices d.
No tic down devices are incorporated as a structural part, of this container.
Strue'tural Standards for Largo quantity Packaging -
c.
Bceau:c the package may contain in execss of 20 curies'of transport Group I natorials, as defined in 10 CFR 71.4(f ),
, it is evalusted as a larce quantity package as well as a fissilo caterial package.
1.
Load Resist:nce Calculations denenstrate that the yield strencth 'of the packsging raterial is not exceeded urder, the conditions set forth in 10 CTR 71 32(a).
i 2.
ixtcrr.a1 Prcssure The cor.tsinc.cnt vc:sel is equivalent to an ICO 2R contrinct, and is therefore capable of withstending t
an external prescure of 25 psic.
Criti.flitv truards enr Fin :iie Materisi Packa-es VI.1.2.2 f
Optinun Uatcr Moderation is a Nornal Condition of Ship.ent.
N
- s.
REic/t.u.c To A Under this condition, 2 5 ke U-235 is suberitie.1 in a 5 625" I.D. cylinter with full water refic: tion (Fic..re cub:ritic:1; K-1.2(a), Y-1272), and up to 250 Cn Pu/ liter i:
in an infinite 5 625" I.D. water reficcted infinite cylinde l (Ficurc J-2.7, Y-1272).
YI-3 11226j
1 1
i b.
All fissile material is contained within a polyethylene bottle which is provided with a vented cap which has been tested to open at 8 ounces to 16 ounces internal pressure..
The bottle is enclosed in two 12 mil polyvinal seamless bags, each of which has been sealed to prevent leakage of liquid.
The enclosed bottle is placed within the containment vessel which is'provided with a gasketed flange closure.
Because this system provides double containment of the fissile material in a suberitical geometry, and precludes tha leakage of liquids into an unsafe geometry in spite of any single packaging error, the fissile content of any single packaging exceeds the minimum critical mass under conditions of optimum configuration (sphere) and reflection.
Administrativa procedures detailed in VI.1.2.5 below are used to verify the leak tightness of each containment vessel.
VI.1.2.3 Evaluation of a Sincle Packace a.
Normal Conditions of Transport 1.
Exposure to direct sunlight at an ambient temperature of 13 F in still air.
The external container is a steel drum inside of which is M vermiculite insulated steel structare containing a moderator, a stainless steel pressure vessel, and the product sciution.
All are exposed without damage to more severe thermal conditions during the required thermal test with no damage.
As previously indicated, the i
solution may achieve a temperature of 160 F, which is within the allowable limits for the ultra-ethylux bottle.
2.
Exposure to an ambient temperature of -40 F.
Loss of properties of the steel and insulating material i
at that temperature will not occur, and possible crystallization of the moderator will not change its moderating properties.
The polyethylene bottle is composed of "ultra-ethylux-28" as produced by Westlake Plastics Company, or equal, and does not embrittle until the temperature is reduced to -55 F.
To allow for expansion of the solution on thawing, at least 10% free space is provided in the bottle.
3.
Exposurs to atmospberic pressure of 0.5 times standard atmospheric pressura.
The drum lids have no gaskets, allowing the equilization of pressure.
VI-4 11-22-66
. ~..
4.
Vibration Each package is vibrated for 5 minutes as a part of the fabrication procedure in order to promote settling of the vermiculite insulation.
S.
Water Spray Experience with packages using similar drum designs (LA-36, HA-10, Ref:
SKM-14 5) demonstrate that exposure to heavy rain for extended periods of time does not result in water leakage.
6.
Free Drop This test was not performed because the Pu-10-I container does not depend on spacing for nuclear safety.
7.
Corner Drop Because the package is fabricated from steel, this test does not apply.
8.
Penetration The drums are fabricated from 16 Ga. steel, and are similar to those used for the NUMEC LA-36 centainers.
Therefore, the test results reported in Section X of SNM-145 apply.
9.
Compression J
A 2,000 pound load was placed on top of a sample package for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with no measurable deflection of the drum.
Based on the above, we conclude that requirements set j
forth in 10 CFR 71.35(a) (1), (2), (3); (b) (1) and,'4) 111 are satisfied.
10 CFR 71.35(a) (4) and (5) do not s
apply as there are no coolants in this package.
10 CFR 71.35(b) 1 and 3 are discussed in VI.1.2.2 ebove, and 10 CFR 71.35(b) (4), (1) and (II) does not apply as the spacing provided by the package does not effect nuclear safety.
With regard to 10 CFR 71.35(c), the vent valve is closed prior to all shipments, b.
Accident Test Conditions Five sample containers identified in Drawings ASK-1058-D-1, 2,
and 3 were subjected to the accident test conditions required by 10 CFF. 71.
These drawings show direction of impact for each cuntainer, and indicate maximum internal temperatures recorded.
VI-5 11-22-66
+
I i
Drop tests were conducted in a manner to assure that the lowest point-of the container was at least 30 feet above the i
point of impact on an unyielding surface at the time of release.
Thermal tests were performed in a furnace which provided the required conditions.
However, containers numbered 1 and 2 were exposed to high temperatures for 36 minutes to compensate for a temperature drop in the furnace observed immediately subsequent to the insertion of the containers.
The other containers were exposed for the 1
required period.
Here, the temperature drop was minimized by additional preheating of the furnace to 1600 F.
Jm 11 liter polyethylene bottle containing sand for ballast-was placed within each container.
Container number 5 suffered impact on the top corner-causing the drum lid to spring open and release some vermiculite, Resulting from this failure, further testing was held in abeyance pending evaluation of the damage, and the determination of corrective measures.
As finally determined, these measures consisted of the use of drum lids i
with a sufficient lip to completely enclose the upper half l
of the rolled lip on the drum body, and the omission of the lid gasket to assure better seating.
That these measures were sufficient to assure closure under accident conditions was demonstrated by container number 3 which was also corner dropped.
The lid remained properly seated on the drum, and vermiculite was lost.
container number 4 was impacted on both its top and bottom-r surface.
The impact onto its top surface-caused a seam in l
the upper drum body to separate slightly, yielding an opening measuring about 1/8" x 1".
No measurable amount of varmiculite was lost through this opening, and subsequent to the aoove tests, the drum was impacted from a-height of 40 inches onto a 6 inch diameter by 8 inch long bar, as specified by 10 CFR 71.
Impact occurred on the welded seam joining the drums.
Although a 1-1/2" to 2" deep depression i
resulted, the integrity of the drum and weld was not violated.
As previously indicated, other tests were performed as illustrated in Figures 1, 2,
and 3 of this application.
Examination of the containers subsequent to their removal from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of immersion under three feet of water i
revealed three principal facts; (1) no water leaked into the containment vessel, (2) no moderator was lost, and (3) the maximum temperature experienced within the containment vessel was in excess of 100 F, but less than 150 F.
Additionally, the cadmiam wrapping of the containment vessel was in no way effected by the test sequence.
From these findings, we conclude that:
VI-6 11-22-66
i 1.
No radioactive material will be released from the package under the stated accident conditions.
. ~.
The package will remain subcritical as the material remains confined to a suberitical geometry, and the geometric form of the contained material is not altered (10 CFR 71.35 (b) (2).
3.
Double containment is maintained in that the internal temperatures noted during the tests are insufficient to compromise the integrity of:
a.
the polyethylene bottle b.
the PVC bagging c.
the pressure vessel It is recognized, however, the pressure buildup within the polyethylene bottle may displace gram quantities of solution from the bottle.
However, such material remains doubly contained within the double PVC bag and the pressure vessel.
4.
No damage was suffered by any of the components or materials of construction due to exposure to the thermal test.
VI.1.2.4 Evaluation of an Array of Pu-10-I Containers In view of the fact that the test conditions did not effect the containment or moderation of the material within the container, we evaluate an array of Pu-10-I containers in both the damaged and undamaged condition on the basis of the following conditions:
Solution Diameter 5.56" H/X Ratio 44 Cadmium Thickness 0.016" Moderator Thickness 2.0" Equivalent Water Thickness 1.91" Two methods are considered herein to demonstrate that the cadmium wrapped 5.625" diameter cylinders are isolated when surrounded by the equivalent of 1.9 inches of water.
We consider first an analysis based on neutron penetration data, and correlated to interacting subcrita, as reported in K-1478.
By this method, a just critical array is described when K = 1.0 - hg where ke = reactivity of suberit F (1 - UF) (ab) p V
=
7 = fractienal solid angle VI-7 11-22-66
i 4
fast leakage probability l
(1-UF)
=
neutron penetration.
The weighting factor p is set (ab)p
=
equal. t:o 1, o To obtain values of geometric buckling Bg, and appropriate l
2 value of$is required.
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APPENDIX 2.10-3 NUMEC LA-36 TEST RESULTS 1
l i
1 i
l
.*.*. '5. o.o... l,y ::*:. 4 :.:y*;"<. -; p.yc....v...R...... ;.. ;
,.n
/.y...0 4.,'N:'M..f.. G," 5,..;..~:.
- ?*
...; '.. p
. s..* *. ;.o.;.,,. :.-
. ',.,s.. J. =..*.s.
.,s
.....(..
1-s...s g,.
.. s
... 7.J.,.. ' l,
~..*.
- p <
.....s...
.n............
- 1 NUMr Lb'M Containor.
c.
..'../.T/. l..
- 1..... <
M 7
.1.1 Pa'eksee Descrietion i
.. ~...
.'t",,.
l.
a.. Gross. Weight: '2501...
1[ ".:'.4./..
J.
3
.o a.
...a
[
.. '. ' F ' '.
' ;. .~,..%. :
' '; " ' i :
~t.:.:'..'b.
Mode 1 Numbet:
LA-36
~
Details'of Construction:
c This infernation is provided in the enclosed drawings (10 D 1167, 10-D-1168,' 10 A 214 and 10 A 215).
d.
Identification and maximun radioactiv!,ty of radioactive constituents:
2 U-234 + U-235 11.1 x 10 curles U-238 - 1 3 x 10 2 curies Classification of material to be shipped:.
e.
.s Fissile material only.
Identification', chenical ard physical form, and mm.dmun q'uant$ ties f.
of fissile constituents:
1.
Dry non-deconposable forms of uraniun liaving a maximun U 235 assay
~
.of.50%:
. Makinun Leading:
36 kg of material containing no more than
~
y 1 58 ks U 235
,Maximun Urmium Density:
Any i
. Maximun Vater Content:
0 5 w/o' 2.
36 kg of hydrbus deconposabic conpounds containing a maxinun of 1.0 kg U 235 The maximun weight of the uraniun bearing' matcrial shall be 36 kg.
Extent of reflection, ar.ount and identity of non-fissile neutron s
g,.
absorbers in the fissile constituents, a-d the atenic ratio of moderation to fissile constituents:
The fissile bearing r.aterial is contained in tuo scaled 5 c:.11on ICC-lE The above nass linits assure.that no singic packa;;e 'cantains a pails.
critical nass under any credible conditions of neders. tion and reflection. q Non-fissilo neutron absorbers, if present, are neg1ceted for the purpose of cvaluation.
Actual nodcration ratios arc as follet.s:
1.
Non-deco =posable forns of uraniun:
(150 5 w/o h20)
---.2)~5 Au.a.v 3/,f U--
g 12 14.8 2-3 7.h1
' 3-4 4 95, 4-5
.3.?
6 L.
}
.. '. Q :.l:.,... %..... m._
b
, ;.'; ?.
j
- ,. 2 p
- cor.poshio forns of urantun:.
. :. ;., "..: n N...
,.; :.~..
.c.,. :
surcd.*
,.;, f, j'., : s '.. -
(
- s.. ',,5.. '.,.. f, ',. Optinum hydFocen n 4cration is as.
2 i.......
,):.v,.-[',.,, j,l. ',, M,.
.".,,' y ?,
. '... ', *,'.: :.. ;. l. :, ' ' ',. h._
Maz.inun weight' of. contents:
M kg.
U N/".k3. :.N..*.ii. Maxinun anount of decay heat: Negligible..,,.,.,,.,,..,., $..M.j
,.:n. ~. ;. '.. ~.
,....s
...,j,.., -. D.$NtN *N h " ' i
,,,,.,.,,'? % **O*P .*h'.4. ; g...,.,. y.,,.
E.* '. -
. :,!='.,.. L...,',. l 14 2 'Containor Evaluation
+
..,,...,,,,,,..,,,[,
.......,:..... 1.2.1 General Standards
- a. :...
- . n.
Internal R.eactions
.* J..
- : ~. a ;
.,.c.. ;-- p.: -;;u,....f:c,e;;:.l., Non-deco':nposable forns of uraniu ::
,,,.1..
., p.,d, 2
,j,
~
No internal chenical reactions are considered credible.
'..'J
.m
...<...w.
I 2.* Decomposable forms of uraniun:
... *.,..t...
.s All' deconposable forns of u.raniun are packaged uithin an inart material, such as polyethylene in the form of sheet or a
.. ? ~..:.J(.....,:..,', ' '. bottle' in order to preclude chemical reactions betueen 't material, and the 5 gallon pails v.hich provide prinary i'
contain~.ent.
/.
.\\
l be Closure
(
(.
,' Closure of the dru..s consists of a 12 gauge bolted' ring ui.th drop forged lugs, one of which is threaded, using a 5/8" bolt.
.. -l.
ci. Lif ting Day' ices-
',, No lifting devices are incorp: rated as a structural part of the
.',..;,,.,, package or its lid.,
J..d.
Tie Down D:v. ices.
...t
,'.., No tie doun devices are incorporated as a. structural part. of the
- l package.
\\
. eC Structural Star.:!:.rds' for Large Qur.tity packagir'g.
- .. l Not applicable.
/*
Stsad..-ds for Fiestle :'aterial Packages, 4 2.2 Criticality 4
.i...
a.,.Each' container is linited to assure that it:i contents would rc..ain ;
I subcritical under any ' condition of water nederatica and reflection.,
b,.
Each container is 'further limit.ed to a:sure that its contents u:uld,
,, renain suberitical 'in an o.otinum configuration, with optinn.t water i
/
'. a' l
- p. \\
nodoration.ar.d toflect.Lon.
..,,,.....,..,t,,
% s. t.
.s.
e....,,
- u....:
,.,t 1
. l t
..s.s-m....
r
. :; j.... :... -j :;.;f '. w *: 3.:... r Q ;{.o....r : :.;.
.. ::1;n. cw q(),.. 7. ;f..i:y.;.;..;e ;
.:ew
- n..' *,. '. /,'... g;,,,'.
t i..,
- .. 1.2 3 Evalu ition of n Sinele Packare-
., :... :.. :.~.c...
f
)
.y
,y,,*.
..s,..,*
- =, -.....*g..~
p
- , '.... ;.../.
'. */..; a. No.rmal.gondition of Transport A
- /. '. ?. 2.".'} 1.Exposure to direct sunlight at an anblent tempor'ature"$f.'
l... ;;':. :.
130*T in still air.
s. :.
~
1
' t.' :
..~
a..
The external container is a steel,, drum inside of which is 'a
(
....;. f er../ '., i.'t. '.: ;;. :.. verniculito insulated steel sleeve which contains two ICC-17H
, p,ty,,.All are exposed without de ace to r. ore severe thernal c.v,7.... J 1.,.....c.,... e ;..
/-
I' conditions during the required thermal test.
g
' ~
'2.' 5xposure to an a.bient temperature of 40'F Exposure to 40 F will not a.ffect the structural naterials,'
=.
which are steel, or the ' insulating naterial, which is verniculite.
3 Exposure to at:.ospheric pressure of 0 5 tin.es standard
/
atnospheric pressure.
~
'.. ; _....The' drun lids have no gasket,l allowing equilization of press
~
4.
Vibrat' ion s.
Each package.is vibrated foi 3 ninutes as a'part of the fabri ' ~
cation procedure in enfer to pronote settling of the verniculite
' insulation.
.5.' Water Spray
., A nu.ber of containers have been exposed to h'eavy rain stoms 1 ! for extended periods of time, with no water,inlea< age.
Such
' exposuie exceeds the requirenants of the nater spray test.-
6.
Free Drop'
'two saaple packages were dropped fron a height of 4 feet onto
. an unyieldin; surface.. One pp.ekage was dropped botton end do.n, and experienced a less than 5' loss of spacing and reduction of volu.e.
The other was dropped in'a hetizontal position, and also experience:i a less than 5% loss of spacing and reduction
' of volu.e.
,Both sampic packages'were subjected to a penetration test as
.specified in Appendix A of 10 CFit 71. The resulting dents did not.execed a, depth of 3/16 inch.
8.
Co.pression
. A 3275 pound lohd uns placc.d on top.of a sanple packcco for a
' period of '24 hiurs uit no rcaturabic defic. ct. ion of.the dru.. 1'. Ba:cd on the above, uc conclude'that ttic requit enents cet for'th in 10.CTil 7135 are satisfipd to the ex. tent' th.at they are pcrtin:rlt.. m
...........L.. Z.$ '. *NE.f u..'. ; ;.., A. ; &...W..!n..'.i. :: h. ',,. 4. *. ? ? s.*r?. *. **. *.~..* ..T.*.'.' s.* ("4 ?.'.' ' 1 .a, .. ',.......'..N.m..- '<.....e. .... y r s ; .S
- ...1,9?.,,
..,r 4 '.' b. Accident Test Conditions
- -.M.*
5* ... :,r.,. f' .. r-:.. y..'.. ~- ,' ei '. / '
- 9 '
' ' Two sar':ple packages, each containing at least 36 kg of dry brick mortar, and designated as Druns !1 and $2, were subjected to the ' T: *. z. ' '.
- c...:, '....:.'r
- P.* accident test conditions, as set forth in Appendix A,10 CrR 71.
.,. v. '........ :. c
- ..,.,..r -
. + - ..c 1. 1mpact .? ,.?;..... .h. I was'dro'pped at a 4.9 angle fron a height of 30s..' ..,e.e. w.. : t.'. ...i. feet on its cover. The drun caved intrard several inches at ' the p'oint of inpact. The ring and cover were not dislodged. ' Drun nunber 2 was dropped from a' height' or 30 feet so as to strike flat or, its side. Inpact occurred approximately half way betueen the spacer rods. This drum was then droppd 30 fcet in a vertical position,, suffering inpact on its bottoa surface.' h
- 2.
Puncture o ' 'Druts ntnber 1 was droppsd through a distanco of 40 inches onto
- a 6 inch dia.eter cylindrical target.
A dent approxi.?.ately 1-1/8 inches deep resulted. h Thermal l. Both dru:.s were placed within a furnace heated in excess of 1500 F prior t'o insertion of the drums, and maintained at 147.5.F for 1/2 hour subsequent to' the, insertion of the drums. 4. Immersion ' Both druns were imersed under three feet'of water for a. period of 24 hours. t 5 .containe.r.Disnantlin; ar.d Insrection, The two sanple druns were disnantled, inspected and measured- .to detemine the locs of spacing suffered during the.iv. pact ,l tests, and the extent of water inleaka;;e into the 5 sallon Pails. l 51 Weight Checis All pails were weighed before the tests cc:-.enecd, and again, on the sans scale, en conpletion of the tests. , These weights are tabulated belo.r, and de..on:tra.te that no r.essurabic inlechago of water into the pails had i occurred. I I e ,i e l e' ,e X.1 4 _s - L -
- f. :
%.,. ' y. 9.[..:~y:..,:q .. :::y..l..nm. -:;9n,.:c-g ,...... a. : : g.,.,....,....... s.,. :..,
- u. ;;..y,"c
- s......:
.o.,
- 0.. ;..::.. e;:...:. '.h.. / " * '.
9,y... w.:, C.....,.: %r .. Q' W - v:. . v... < .:.. {. ;;L ::: f.q:..~,:....:<,. uncurs 0F em.s:.
- '.. :. '.c....';m. :. :.
.. > :s..'.. :r.. ....:...... s. .r....;.; a... . n.. :.. :...., :.\\.;:..
- ....y
..e u.:w.::..q :.... :. n...,v,.i.v.: n ..~;..- '...,.'..-l ,; e r.. -
- f ; # *:-,.: ?
NMEC ORGDP . ORODP (,a,f.}., r tes ts ),.)
- ).,'.'!.hl'. '.:.' '- Ibe fore tes.t,1),,
(betore tests),,. e
- ./
C*... - ........ <.. ~ ....:...,........~. . ; ; ?. :'....v... : :..' : x... :... n :.,. ,( e,,......:..
- .. f...,. :.' "
. r.. .d ..":i'.'..: :.. : *. ?..,7 '.
- b Number i n.
?
- '.. e l l.. '
.. : ' ;.? ~ r. : : .,:,,.:...,.,. ;;1,; ?:. : e;.'+. ; y * - lu:;'..n:- 470' .j 22,440 22,470* 22,470 ..,7s..=. Top Pall *pg. y...-20,470 20,. 20,440 .g s Numbei 2 20,490 20,490 .20,51'0 ' Top Pall Botto Pall 20,450 20,440 20,440 '5 2. Inspection Checks .l.. 5 2.1 cruct nunber i experienced. a maximun temperature of 500 F.
- ' on the cover plata.
Removal of the cover and the pails revealed that water had entored, but only half filled the inner'containcri The inner container had shifted approximately 1/4 inch as 'a result of the impact. 3. Both pails experienced haximun temperatures.of from 200 to 300 F, and appeared to have suffered little da.nage. - 0 When opened, dryness of the contents was confirmed. * .2.2 Drun nunber 2 also experienced a maxinu.ter.;erature'of 5 As with drun nunber 1, water had 5000F on ths cover plate. entered, but only half filled the inner c,ontainer. 'The e inner container had shif ted approximately 7/8 ' inch as a ' ' restilt of the impact. In addition, the drun had caved in at tho' point of impact, yield'ing a total loss of.21/2 inches s / spacing betueen the center of the inner container, and the nearest point on the out.er container. ~. The upper pail experienced a maximun temperature of 325 F. Pieces of the gasket pulled loose when the lid was removed J as a result 6b the cdherence to the side of the pail. The botto'n pail experienced deformation' on its rolling hoopi sufferingalossof1to1-1/2inchesinoverallheight. Howcycr, the tasket had not deteriorated ' appreciably, and maintained its scal.' A. strip of sceningly.ca'<cd powder 3/8 - inches.uideby3/4incheslongby1/64inchthichunsfound ,ncar t.he top *of the pail. No.other indictions of caked material uns noted. Atte.. pts to brush this =aterial from .the pail irith licht pressurc uera unsuccessful, but' s t have been completely reacted. No other attempt had been made to identify the nr.ture 'of this caking. Ho.:cyce, in /- tvic:t of the c.'n:ral tendency of. hyt;roscopic posdcre.d nat.crin1' l to' foin localir.ed adheciens on nanf ap'etrently dry sucrec..c, the r.att're of the nt'llicran e,u ntitlec,'of cS:cd paudce observed cc.nnot bo, ace:;t talncd uith eny de;;rce of cr.rtdn'r. It is therefore, on tho.bTsis of recotxted ucicht noe.mru.unts ok
_.,, d l** ' ' Q E&..: *;.*;.N Ev ':s*.f. I.* ?. '$....~ 's.&g.s ' *? '?.. '.' :.i'. s'.. /'s
- x..,,,.,.... 4.... :., !.
'.9 ..,,s.*>..e. ..t;.s;:s...r., .,.....,.r. . J. .: ; :.e. ...: -{%z.. .;;........*. ;......,%.'.c.,... s.. 4:. 9 ...s. ' ' ' ' ~ s. .s-f:.: ?.. k.,. n...'. W..(. r. ;,. y,_'. ;.'.. :.. ':.' ,.4 4
- .. *. L
- '..;o..
v. A series of additional tests has been carried out wherein .l *... % i 'V..
- ~.. < P ; l.* *f.;. pairs of ' pails have been dropped together without benefit
.. 0, .*. * ;* *. '$ W- (,..-: -l:;'l..;. ' of the surrounding,drun structure, exposed to tenp r!- ,' '...
- 1, *'., l q:
d d above, and im.orsed under three . ***4.-}.! *.k./.(,,,W. y4.~(t " typical of those recor e 'i.. : *".' *... :
- /.
test, of water for 24 hours. The results confirn'those e,. f.,,.... y.... reported above. Included in these tests.were pails uhich 'i .4 d 17-H lids,' '. I . '.'.".;..'. J,T,.:(..,.'.* g,,rt..f, were equ.ippd with lids identical to the standarexce . : +. ;... n...'... .. of. 032 steel sheet, 'in place of the standard lid closure ..q luss. The lids are identical in all other respects. ... ;.... ;.,, 5....
- Based on the above tests, we concitide thatt N.
1. The individual package renains suberitical under all conditions by ' irtue of _the cass linit. 2. The ability to exclude watei fron the material being. shipped provides the basis for evaluating an array of . e. packages on the basis of dryness of the material. ....s ..s..,. ..a
- 3. 2.,4 Evaluation of an Array of IJL-36 Centainers s
. '.1. 2. M 1 DrvCo.counds s In view of the pioven ability to exclude 1:ater moderation, we consider th.at. all. material b.eing shipped contains. 'a maxin.un of 0 5 w/o wa.ter. 1 a. Undanaged / ) Because this material is essentially unmoderated (H US 0 5, i l criticality c'annot be achieved with any finite mass. ' Accordingly, an infinit,e number of containers is safe. j ~'
- b..Danaged The ninimrt voluna occupied by the LA-36 containez in a close packed hexagonal array is 3 46 R H = 3 46 (.835)2 (3 16) = 7 6 ft3. !
2 Neb = Critical nass.of an unreflected sphere of UO (93,1 U-235) 2 Because the nederation ratio noy be as high as 14.8 for 1.00 ~ . enriched uranien, ue deternins the value of.lfeb fron Figure 10 cf LA-3366. t.hile the value of !!cb thus obtained represents a carbon-stater-uraniun systen, it yields slightly conservative l ~ ., l results, as seen in Figurc 9 of IA-3366. Thus., McB = 25 kg U 235 The, density (%=17gn/ce. The a'ver ge uranium density [for the systen is s f LJS kr U 23j k 0074 gn/cc ~' 215 liter j l l h'.6 ..}}