ML20210A033
| ML20210A033 | |
| Person / Time | |
|---|---|
| Site: | 07109192 |
| Issue date: | 10/02/1985 |
| From: | Jerome Murphy ANEFCO, INC. |
| To: | |
| Shared Package | |
| ML20210A028 | List: |
| References | |
| 25866, NUDOCS 8511140146 | |
| Download: ML20210A033 (150) | |
Text
.
O DESIGN t
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SAFETY ANALYSIS REPORT AP-300
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ANEFCO INC.
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ANEFCOINC.
1 904 Ethan Allen Hwy.
Riogefield, Conn.06877 203 431 3358
DOCUMENT APPROVAL SIGNATURE SHEET DOCUMENT NO.
TYPE OF DOCUMENT AP-300 SAFETY ANALYSIS REPORT DESIGN AND SAFETY ANALYSIS REPORT ANEFC0 AP-300 Greater Than Type A - LSA Dated 3/1 /84 EXT.
5 PREPARED BY: John D. Murphy J r.
EXT.
5 ORIGINATED BY:
John D. Murphy Jr.
ORGANIZATION DATE APPROVAL & REVIEW SIGNATURES Technical Review Co:n:nittee 7,/, [g (q
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-TABLE OF CONTENTS
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GENERAL INFORMATION 1.1 Introduction 1.2 Package Description l.2.1 Packaging 1.2.2 Operational Features 1.2.3 Contents of Packaging 1.3 Appendix 2.
STRUCTURAL EVALUATION 2.1 Structural Design
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'2.1.1 Discussion 2.1.2 Design Criteria
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2.2 Weights and Centers of Gravity-2.3 Mechanical Properties of Materials 2.4 General Standards for All Packages
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2.4.1 Chemical and Galvanic-Reactions
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2.4.2 Positive Closure
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2.4.3 Lifting Devices 2.4.4 Tiedown Devices 2.5 Standards for. Greater 'Than. Type A -Packaainer 2.5.1 Load Resistance 2.5.2 External Pressure 1 2.6 Normal Conditions of Transport 2.6.1 Heat 2.6.2 Cold 2.6.3
-Pressure 2.6.4 Vibration 2.6.5.
Water Spray
'2.6.6
. Free Drop 2.6.7 Corner Drop 2.6.8 Penetration 2.6.9 Compression i
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s TABLE OF CONTENTS (Con't) 2.7 Hypothetical Accident Conditions 2.8 Special Form 3.
THERMAL EVALUATION 3.1 Discussion 3.2 Summary of Thermal Properties of Materials 3.3 Technical Specifications of Components 3.4 Thermal Evaluation for Normal Conditions of Transport 3.4.1 Thermal Model 3.4.2 Maximum Temperatures
?.4.3 Minimum Temperatures 3.4.4 Maximum Internal Pressures 3.4.5 Maximum Thermal Stresses 3.4.6 Evaluation of Packaae Performance for Normal Conditions of Transport h
3.5 Hypothetical Accident Thermal Evaluation 3.6 Appendix 4.
CONTAINMENT 4.1 Containment Boundary 4.1.1 Containment Vessel 4.1.2 Containment Penetrations 4.1.3 Seals and Welds 4.1.4 Closure O
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4.2 Requirements for Normal Conditions of Transport 4.2.1 Release of Radioactive Material 4.2.2 Pressurization of Containment Vessel 4.2.3 Coolant Contamination 4.2.4 Coolant Loss 4.3 Containment Requirements 4.3.1 Fission Gas Products 4.3.2 Releases of Contents 4.4 Appendix 5.
SHIELDING EVALUATION 5'1 Discussion and Results 5.2 Source Specification 5.2.1 Gamma Source 5.2.2 Neutron Source 5.3 Model Specification O
5.3.1 Description of the Radial and Axial Shielding Configuration 5.3.2 Shield Regional Densities 5.4 Shielding Evaluation 5.5 Appendix 6.
CRITICALITY EVALUATION.
7.
OPERATING PROCEDURES 7.1 Procedures for Loading the Package 7.2 Procedures for Unloading the Package 7.3 Preparation of an Empty Package'for Transport 7.4 Appendix 8.
ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 ' Acceptance Tests
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8.1.1 Visual Inspection 8.1.2 Structural and Pressure Tests 8.1.3 Leak Tests.
8.1.4 Component Tests r~g 8.1.5 Test for Shielding Integrity
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8.1.6 Thermal Acceptance Tests i
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TABLE OF CONTENTS (Con't)
O 8.2 Maintenace Tests 8.2.1 Structural and Pressure Tests B.2.2 Leak Tests 8.2.3 Subsystems Maintenance 8.2.4 Valves, Rupture Discs, and Gaskets on Containment Vessel 8.2.5 Shielding 8.2.6 Thermal 8.2.7 Miscellaneous i
APPENDIX A
- Drawings I
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GENERAL INFORMATION I
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1.0 CENERAL INFORMATION 1.1 Introduction 7'
The AP-300 A is a f erritic steel shielded shipping cask designed to meet the criteria of greater than Type A low specific activity (LSA) packages (as defined 11n10CFR 71.4).
The container is built to comply with Title 10 Code of Federal Regulations (as amended September-6, 1983), Subpart E, parts 71.41, 71.43, 71.45, 71.47 and 71.51.
In addition, it has been evaluated under Subpart F, 71.71 and 71.73 and Subpart G 71.81, 71.83, 71.89, 71.91, 71.93, 71.95 and due to capacity of the container 71.97.
The cask is fabricated under Subpart H Quality Assurance License Docket Number 71-0001 and is labeled and marked in accordance with Title 49 Code of Federal Regulations Parts 176.350, 173.24 and Part 72.
The specifications for this cask are as follows:
MODEL AP-300 A (referred to as AP-300 in remainder of the text.)
Classification:
" Greater Than Type A LSA" Overall Dimensions:
83 " dia. x 96 " high Shielding:
3" lead equivalent (Cobalt 60)
Il Cask Weight:
46,720 lbs.
Capacity:
76" dia. x 82" high Max. Quantity /Pkg:
20,000 lbs., not to exceed 20 curies of Cobalt 60 The AP-300 is a steel encased, lead shielded cask. The cask consists of f~)
two concentric cylindrical shells.
The inner shell is inch thick by 76" I.D., made of ASTM A240 Type 304 S.S. material. The outer shell is ik inches thick by 83.625 inches O.D., made of ASTM A516 Grade 70 steel.
The annulus between the two concentric shells is filled with 2 inches of poured lead;to'act as a shield. The base has 2 inches of poured lead and is the same total thickness as the vertical walls of the cask. The flanged lid consists of three ASTM-A240. Type 304 S.S. plates attached to 4
a riser ring. Concrete is placed between the two upper plates, and lead shielding is placed between the two lower plates.
A positive closure is provided by thirty-six (36) 3/4 inch diameter hex socket bolts and a J.M. " Red Devil" (or Neoprene equivalent) compressed sheet gasket.
The cask is equipped with four independent (2 redundant pairs) lif ting lugs. These lugs are also used to tie the cask down during transport. The cask is provided with a security wire seal block that f[
provides means for detecting tampering with the loaded cask after a wire seal is placed in position. A toroidal ring is velded to the top of the cask to act as a crash barrier.
A double bolted seal test port is provided in the lid. This allows test pressurization of the cask. cavity after loading to insure the positive seal of the cask lid and thereby provides reasonable assurance-that the contents will not leak during accidents.
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1.1-1 Revision 5 - 6/10/85
1.1 Introduction (Con't)
The AP-300 cask is desianed to transport areater than Tvna a 7.m
.09 curies /cu ft of W
waste with an approximate curie level of Cobalt 60 or a total of 20 curies Cobalt 60.
The waste
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The AP-300 form may be solid, dewatered or solidified.
one liner / catch tank up to 74" diameter can accamodate by 80" high or ten (10) DOT 17-H 55 gallon drums.
e 1.2 Package Description 1.2.1 Packaging 1.2.1.1 Shape The external shape of the cask is approximately a smooth-surfaced right circular cylinder.
(See Figure 1.2.1.1).
1.2.1.2 Size The cask body has an overall height of 96 inches and a diameter of 83.625 inches.
The internal cavity of the cask is 82 inches high and 76 inches in diameter.
1.2.1.3 Weigh _t The weight breakdown ^of the AP-300 cask is as follows:
Weicht (lbs.)
Components Cask Body 37,255 9,462 i
Cask Lid 4f Total Cask (Empty) 46,717 Cask Contents 20,000,_
Total Cask & Contents 66,717 i
1.2.1.4 General Construction Materials of construction are:
stainless steel (used in the inner containment vessel), A516 Grade 70 carbon steel (used in the outer shell), chemical grade lead (used for radiation shielding) and high temperature elastomer seals.
The primary containment structure of the AP-300 cask is fabricated from ASTI: - A240, Type 304 stainless steel.
The inner and outer shells of the cask body are both welded to the closure ring at the top of the cavity flange l
1.2-1 Revision 4 - 4/15/85 l
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O Both shells are welded at the bottom to their own separate bottom closure plates. The annulus between the outer and inner shell is
~ filled with lead for GA9fA shielding. The bottom closure plate of 1.25 inch thick outer shell consists'of a 1.25 inch ASTM A516-Grade 70 steel plate. The outer.shell is a 1.25 inch thick sheet of ASTM A516, Grade 70.
Four lif ting eye pads (redundant pairs for those sites requiring four-f point lif ts) are attached to the side of the outer shell of the cask.
These pad eyes, attached to the side of the cask, are also used to tie the cask down during transport.
The cask lid'is shown in Appendix A on Drawing No. 135-1.
It consists of two major components namely:
f An outer plate with provisions to attach lifting eye bolts, which a.
is fastened to the cask closure ring with 36 bolts. This plate is two inches thick and made of ASTM A240 type 304 stainless steel.
b.
A gamma shielding assembly, consisting of lead, sandwiched between 2 steel plates. This assembly consists of 2.06 inches of lead between an inner, h inch plate and an intermediate 3/8" plate, both of which are ASTM A240 type 304 stainless steel.. All plates are
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permanently attached to a h" thick riser ring which is also made 4
of ASTM A240 Type 304 SS, and 3.8125" of concrete.is placed between plate (a) and assembly (b).
1.2.1.5 Primary Containment Vessel The containment vessel is a inch thick inner cavity shell and a inch thick bottom closure plate. The containment vessel, including all penetrations, is fabricated of 304 stainless steel. The cask cavity is closed and sealed by a bolt-on-plug-type closure lid consisting of a 2 inch thick outer stainless steel plate and a steel weldment contain-ing lead shielding which extends into the' cavity opening.
1.2.1.6 Capacity The AP-300 cask is capable of accommodating a gross load of up to 20,000 pounds'of LSA waste material of greater than type A quantity.
1.2.1.7 Shipping Configuration
. Transportation of the AP-300 cask is normally by (although not limited to) truck-shipment with the' cask in a vertical position, carried on a specially modified transporter. The transporter is basically of reinforced beam type construction.
O 1 2-2 Revision 5 6/10/85
1.2.1.7 Shipping Configuration (Con't) g A protective personnel barrier cover shield is not required.
Four tie-down pad-eyes are used as the cask tie-downs to support the entire load of the cask and its contents under 'the 10 G axial load conditions.
A kick plate rino is provided, to prevent movement due to the chocking forces.
The transverse imposed loads are taken/ shared by two of the pad eyes and the vertical load is shared by four of the pad eyes.
The load is tied down with 1-1/2 inch cable with adjustment tie-down plates to provide the correct torque and flow for expansion and contraction differences between the cask and the transporter.
1.2.1.8 Outer Shell The outer shell is a steel cylinder, which has an outer diameter of 83.625 inches, is 1.25 inches thick and is fabricated from ASTM A516, Grade 70 steel.
The shell is welded to the closure ring and to a 1.25 inch thick bottom plate which is fabricated from ASTM A516, Grade 70 steel.
1.2.1.9 Closure Rino The closure ring is fabricated from ASTM A240, Type 304 a
stainless steel and is 81.125 inch O.D.,
76 inch W
I.D.
and 2-1/4 inches thick.
The ring is welded to the inner and outer shells to form the top closure for the lead shielded cavity.
Thirty-six (36) 3/4" diameter holes with helically coiled threaded inserts are provided for bolting the closure lid to the ring.
l.2.1.10 Lid closure Seal The seal between the closure lid and ring is made of high teperature, compressed SBR (neoprene blend), flange ga ske t of Jo!. 's+'2enille, Red Devil material.
The mating surfaces are machined to a concentric surface.
The lid is bolted to the closure ring by thirty-six (36) 3/4 inch diameter hex socket bolts; the bolt heads bear on the cask lid, the shanks penetrate through the lid flange and are threaded into the closure ring-1.2.1.11 Cask Bottom The cask bottom is a plate 81.125 inch 0.D. and 1.25 inch thick and is fabricated from ASTM A516, Grade 70 steel.
The plate is welded to the outer shell to form the bottom closure for the lead shield.
O 1.2-3
1.2.1.12 Closure Lid
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The lid is bolted to the 81.125 inch diameter closure ring. The lid is fabricated from an ASTM A240, type 304 stainless steel plate 81.125" 0.D. and 2" thick.
It has welded to it an ASTM A240, type 304 stainless steel riser ring 76" 0.D., 0.5" thick and 6.75" high.
An ASTM A240, type 304 stainless steel plate 75" 0.D. and 0.375" thick is welded to the riser ring at a distance 2-1/16" up from the other end, and an ASTM A240, type 304 stainless steel plate 76" 0.D.
and 0.5" thick is welded to the riser ring at the other end. The 4l cavity between the two lower plates contains the top lead shield.
Concrete is placed between the upper plates.
The plug portion of the lid has a radial clearance less than that of the lid bolts clearance holes, preventing contact of the lid with the closure bolts during the hypothetical accident conditions which would put a shear load on the closure bolts. There are thirty-six (36) counter bored clearance holes for the 3/4 inch closure bolts.
The top surface of the lid has four ik" diameter holes, ik" deep with helicoil inserts plugged with Ik" bolts. During loading and unloading 6
operations, four lifting eye bolts are inserted to lift the lid.
Each. eye bolt is 1 " diameter, has a shank 3" long and is fabricated of drop forged steel. A seal test connection is provided in the lid.
The seal test connection, constructed of a k" diameter hole with heli-coil threaded inserts, is 16cated 2" below the outer surf ace of the lid. The seal test connection is in turn sealnd by a k inch T'
hex socket. ASTM 320 stainless steel bolt and a 1/8" thick Johns-( )T
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Manville Red Devil gasket. The seal test connection and plug are in turn protected by a second seal plug in a " ASTM A320 hex socket bolt 1 " long.
This provides a gap between the two plugs to prevent shear damage to the internal plug during accident condition.
The outer seal test connection plug is in turned sealed by a 1/8" thick Johns-Manville Red Devil Casket. The outer plug is recessed below the top surface to prevent accidental damage to the plug.
The entire lid assembly is located 1 inch below the top surface of the outer body shell to protect the lid during accident conditions.
1.2.1.13 Lifting Eyes Four lif ting pad eyes are located on the side of the outer shell of the cask body.
Each consists of a lug 8" high by 22" long by 4" thick mounted on a plate 24" square by 1" thick f abricated f rom ASTM A 516, Grade 70.
Each pair of opposite lifting eyes are designed in accordance with the regulations and may be used inde-pendently of each other. The four lif ting eyes design is used to meet the requirements of those reactor sites which require independent four point lifts.
The lif ting pad eyes are used during transport as tie down points during shipment.
1.2-4 Revision 8 - 10/2/85
1.2.2 Operational Features g
The ANEFC0 AP-300, Greater Than Type A cask is not a complex package system.
It is used for exempt fissile materiallin conformance with 10 CFR 79.53 and hence does not require a neutron shield.
It also does not require fluid cooling means to dissipate the small internal thermal loads of the contents to be shipped in the cask. The decay heat i
generated by 20 Ci of Co-60 is less than 1 watt and the heat dissipating capacity of the cask has been calculated to be in excess of 150 watts.
1.2.3 Contents of Packaging 1.2.3.1 Description of Contents The contents shall be process solids, either dewatered, solid or solidified material meeting the requirements of low specific activity (LSA) radioactive material, or large quantities of by-product material and fissile material in the form of dry, solid metallic waste material and activated reactor components which meet the requirements of 10 CFR 71.53.
Maximu= quantity of material per shipment will be for Greater Than Type A quantities of radioactive material with the weight of contents and secondary containers not to exceed 20,000 pounds. Decay heat of I
contents will be less than 1 watt.
O All materials will be packaged in disposable inner containers.
O 1.2-5 Revision 5 - 6/10/85
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STRUCTURAL EVALUATION O
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2.0 STRUCTURAL EVALUATION
\\,j 2.1 STRUCTURAL DESIGN 4
2.1.1 Discussion The principal structural members of the package consists of The two major structural systems and other components.
primary containment is made up of the inner <shell and its bottom plate, the closure ring and gasket, the closure bolts and closure assembly.
These components are designed to contain the contents under maximum conditions of csvity pressure and The next temperature and prevent puncture from the top.
major structural system is the shielding envelope which is composed of the closure lid, outer shell and bottom plate.
These components keep the lead shield in tact and prevent puncture from the side and bottom.
Four pad eyes are provided on the side of the cask. They 5
serve the dual function to lift the cask durino operation and tie it down Curing transport.
2.1.2 Design Criteria
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The desian conditions used to evaluate the structural intearitv of the packaging are specified in 10 CFE 71.
Specific paragraphs that apply are: 71.41, 71.43, 71.45, 71.47, 71.51,71.71, 71.73 and 71.107.
In addition, t'1e cask is evaluated in accordance with NUREG-CR-1815, "Recomnandations for Protection Acainst Failure by Brittle Fracture in Ferritic Steel Shipping Containers up to 4 Inches Thick" and EcF. Guide., Task ME 144-4, June, 1983, Dra
For primary containment vessels, design conditions of 600*F and 100 psig were used with the assumption that it is a free standing vessel with support from the lead.
All cask components and structures were designed to withstand an acceleration of 30 g's in any direction.
The theory of failure used for this SAR, was the maximum shear stress theory.
In general, the approaches in the ASME Boiler and Pressure Vessel Code,Section VIII, Division 2, i
1974 Edition, were used to size components, obtain material properties, and evaluate design safety margins.
Both operating and accident conditions were evaluated and compared Division 2.
with the stress and fatigue limits of Section VIII,
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l 2.1-1 Eevision 5 - 6/10/85
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presented in ORNL-68, these were used to either size or evaluate components and parts.
Design criteria used to eva3uate stresses and strains caused by the 1 foot free drop and the 6 inch bar puncture were either the static yie3d, or where appro-priate by comparison with the dynamic yield or ultimate tensile strength.
Permanent deformations were allowed to occur provided that the ultimate strain was nct reached and the primary containment sea 3s remained operable.
WEIGHTS AND CENTERS OF GRAVITY 2.2 The individua) weights of the major individual sub-assemblies are tabulated in the table of cask weights and oenters of gravity.
Each sub-assemb]y is referenced to the cask assembly Drawing No. 133 respectively.
The tota) empty cask weight is 46,717 pounds.
The loaded 4
cask weight, with maximum design load is 66,717 pounds.
4I The center of gravity of the Joaded cask is 47.66 inches above the bottom of the cask at the center axis of the cask.
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l 2.2-1 Revision 4 - 4/15/85 l
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TABLE 2-1 CASK WEI' HTS & CENTERS OF FItAVITY O
PART W LBS.
Y IN.
WY 5
4l Cask Lid Concrete 1462 92.09 1.35 x 10 Cask Lid Assembly 8000 89.86 7.19 x 105 Cask Outer Shell 6925 48.0 4.28 x 105 Closure Ring 405 45.375
.18 x 105 Inner Shell 3070 43.75 1.34 x 105 Inner Shell Bottom Plate 655 4
.03 x 1055 Outer Shell Bottom Plate 1825 1.12
.02 x 105 Gamma Shield 18560 44.5 8.26 x 10 Bottom Shield 3815 2.75
.10 x 105 4'.
46717 22.75 x 1F 4 YW 4l C G== E W 48.70" 5
Contents 20,000 45.25 9.05 x 10 5
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Loaded W 1 WL 66,717 31.80 x 10 3
i S Vu Q 4l Loaded C.G.
(R, _i_ YW )
( 41.-7 5 ", 4 7. 6 6 " )
O 2.2-2 Revision 4 - 4/15/85
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2.3 Mechanical Properties of Materials The materials to be used in the fabrication of the cask are listed below.
.The mechanical properties are listed in Table 2.3,1.
Materials Function 1.
ASTM B29, Pig Lead Chemical Shielding Grade
'2.
ASTM A516, Grade 70, Outer shell, outer shell bottom II normalized, fine grain process, plate, tie-down and lifting pad Charpy V-Notch tested eyes.
3.
ASTM A240 Type 304 Inner shell, inner'shell bottom plate, lid inner plate, lid outer plate, riser ring, closure ring i
4.
ASTM A320, Grade L7A Closure bolts, seal test connections O
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2.3-1 Revision 5 - 6/10/85
TABLE 213-1. MECIIANICAL PROPERTIES OF MATERIALS _
f Coefficient Values of Yield Spec Min.
Spec. Min.
of Linear Modulus of Material Temperature Material sq. in.)
sq. in. J Expansion (4)_ Elasticity (4)_ 100 300 400 500 600 Deferene Yield (KIPS /
Tens. (KKPS/ Thermal SA-516 38.0 70.0 6.5 x 10-6 28.3 +.5 38.0 33.7 32.6 30.7 28.1 Table (in/in/*F)
ACS-2*
Crade 70 SA-240 30.0 75.0 6.5 x 10 28.5 +.5 20.0 19.8 17.6 16.4 15.6 Table
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Type 304 Dynamic Strength - 5000 psi (1) (2) (3)
-6 Lead 0.84(4) 16.3 x 10 2
35.0 31.9 30.6 09.5 28.1 Table
'SA-320 105.0 125.0 N2' t $rade L 7A
- Division 2,Section VIII, ASME Boiler & Pressure Vessel Code (1) " Nuclear engineering and Design". Vol. 13, 1970, North-Holland Publishing Co.,
Y P.O. Box 3489, Amsterdam, The Netherlands.
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" Cask Designers Guide", ORNL-NSIC-68, United States Atomic Energy x
(2)
- Shappart, E
Commission, Oak Ridge, Tennessee.
p (3)
Goldsmith, W., " Impact - The Theory and Physical Behavior of Colliding Solids",
o Edwards Arnold Pub 31shers, Ltd. 1960.
a (4)
American Society for Metals, " Metals Handbook", 8th Edition.
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2.4 CDiERAL STANDARDS FOR ALL PACKAGCS
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2.4.1 chmie,1 rno Calvanin R9actirn The cask's materials of construction, those of the disposable canister and the contents are all metals that do not produce O-significant chemical galvanic or other reactions.
The packing components are either stainless steel, lead or carbon steel or polyethylene canister which is carried in the stainless steel primary containment.
These materials do not have any significant adverse interactions.
2.4.2 Positive Closure The closure system is made of positive screw type devices that must be deliberately opened andwill not be accidentally 4
The closure assembly is secured by 36 hex socAet unscrewed.
head bolts 3/4 inch in diameter. T.he seal test connection is closed by a 1/4 inch hex socket bolt.
This seal test c
connection is closed at the outer shell by a 1/2 inch hex socket bolt.
Therefore, the closure bolts and seal test port bolts cannot be inadvertently opened.
l Tha seal is made by a high terpreture gasket, which is placed between the lid plate
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cnd the ring plate, and secured by the 36 hex socket head bolts.
The gasket is icbricated by Johns Mansv111e and consists of DuPont aramid fibers which are bound by styrene butadiene rubber.
Th2 stress on the gasket is determined as follows:
The gasket is compressed by the weight of the lid and the preload applied by the tight ening of the bolts to a torque of 115 f t 1bs.
i 16" ID 3/4" bolts) is:
The area of the gasket (81.125" OD,
- 36 % (.75 ) g,2 2
2
} (81.125 - 76 ) in A=
2 632.45 - 15.90 = 616.55 in The f orce on each bolt, torqued to 115 f t 1bs,can be determined from the 3
relationship shown in ORN1.-NSIC - 68 page 37, formula (2.9):
T - 0.2 a T T = Torque (f t Ib), a = bolt disseter (f t), T = induced force (1bs)
Where 115 f t Ib 9200 lb
=
y-0.2(
) it J
The total force f rom each of the 36 bolts torqued to 115 f t Ib and the wieght of the lid ist i
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9200(36) + 9500 - 340,700 lbs.
340,000 lbs
$52.6 psi
=
Theref ore, the stress on the gasket will be 616.55 in, 2.4-1 Revision 3 - 2/15/85
L.
hl_f" ~ !
w 9
_ 5 D
4 i
B c
/
E sk 3r CASK OUTLINE HOISTING BEAM CASK LIFTING PADS CASK LIFTING PAD'
\\
j O
N
/
w b
s E
k HOISTING BEAM I
n R z m
u e a n
a
?
().
m e
h
.f Q
FOUR VIRE ROPE g
4
~ SLINGS
(
h g
CASK LIFTING g
g g
/ PADS i
v) o p
E FOUR SCREW PIN p
5
/ ANCHOR SHACKLES y
TOP AND BOTTOM a
ANEFC0 MODEL AP-300
/
SHIPPING CASK N s
/
\\
k.*
/
p b g }. dIB in:s'._
- 2.
- a N
PO>
s O
[ ~_
E j
o E
5
-h I
I l
n n*
FIrU"E 2.4 CAEK LIFTING DEVICE 2.4 lh Revision.5.
r s
n The maximum ctre 3 and ctrain' the gasket ca3 with:tand tithout iciltra is in excess of 5000 psi. Therefore, a safety factor in excess of 9 is available when the bolts are torqued to 115 ft.lb. The frequency of leak I_)
test and-gasket replacement schedole is based on the following.
The fabricator data indicates that under 5000 psi the gasket material has a compressibility of 15 - 35% and a minimum recovery of 40%.
Assuming a maximum compressibility of '35% at 500 psi and, a linear relation-ship between stress and compressibility, the compressibility of the gasket material at 552.6 psi can be calculated.
6 compressibility = 35% x
= 3.87%
'3 If 40% of compressibility is recovered, then only 60% of the compressi-bility is lost for each compression.
compressibility = 0.6(3.87%) = 2.32% per use The gasket will be replaced after six (6) sequential uses and a leak test will be performed whenever a gasket replacement takes place or at a minimum of one leak test per year.
2.4.3 Lifting Devices O
2.4.3.1 Lifting Devices for Cask Assembly LJ The cask lifting device consists of a hoisting beam, four wire rope i
slings and a total of 8 shackles. The schematic outline is shown in figure 2.4-1.
2.4.3.1.1 Loading The empty cask weight is 46,717 lbs.
It is assun.ed that the cask
(
is loaded with its payload of 20,000 lbs, in evaluating the design of the 1.ifting/ tie down pad eye.
Total lifting weight is therefore:
Wt = 46,717 lbs. + 20,000 lbs. = 66,717 lbs.
According to Title 10 of the Code of Federal Regulations, Part 71.31 (c), the lifting system should be capable of lifting three times the 4
expected losd.
D = 3(Wt) g DesiEn load = 3(66,717) = 200,151 lbs.
6 Each pair of lifting / tie down pad eyes are designed to take the h
entire load, therefore, each ear is designed to take the load or 100,075 lbs.
2.4-2 revision 5 - 6/10/85 m
w 2.4.3.1.2 Lifting Pad Design The lifting / tie down pad is constructed of'A516 which has a yield Fy = 38 kip and will'be welded to the outer steel shell with a low hydrogen electrode.
(See Figure 2.4-2)
Check tte hole in the lifting pad for bearing and shear. (assuming 3
2.75" mialmum for pin)
~(actual bearing stress)
= 9.1 ksi F
=
p 2.75"x4 Safety factor to yield:
SF = "
4,1p '
=
g Check tear out of lifting device A = 2 x 3 x 4 - 24 sq. in.
y The shear capacity of' structural steci is 2/3 of thf tensile capacity.
Therefore, the tear out capacity is:
5
~
2/3 x 38 x 24 - 606 kip SF =
= 6.07 0.1 Check bending of pad Sm=f1h2,.Iir
= E0) 3 6
T- (1. 5. )
" 132.0 in 3w 3(66.72) = 100.1 kip F = T~ "'
i Bending moment = 100.1 kip x 41 " = 450.'5 kip-in'.
3 I"
Bending stress = # -
1.94 kni
=
232.0 in Safety factor 8
SF =
= 19.6
/
1.94 check welds bending along plane 1-2 (see figure 2.4-2)
'I
/
/
M = 4.5" x 100.1 = 450.3 kip =in Sm for 1" fillet veld 2
A = ' 2422 + 4),(1 x 0.707).=i.36.8 1h2
(.707)(22)3 +4(.707)(1 )
3 Sm = 2
= 176.19 in 11 O
s 2.4-3 R:.vis ion 7 - 8/22/85
cT I
vu, 1r-g-
t A
< y
-~.)
d
/ }
F= N h
2-N 2,3*
24' i
i
/
/
A
^
,s 1
x r
SIDE iLEVATjoAl 6
EI
.E
/r 3'D 4(R \\
)
0 b
f 2
\\
L gA t"
VESSE L ALL LUG Suc. noH A-A pap Figure 2.4-2 LIFTING /fIE-DOWN PAD AND LUG
'2.4-4 Revision 7 - 8/22/85
h 450.3 Fweld
=s 3.56 ksi
=
6.19 tension Fweld 100.1 2.74 ksi
=
stress 36.5 Combined stress = (2.56 + 2.74 )b = 3.75 ksi N
Allowable tensile stress for E70 ksi low hydrogen electrode is 21 ksi.
21
- 5.6 SF to tnesile stress for lifting
= 3.75 The strength of the lifting / tie down pads and the welds with which they are attached to the cask shells are therefore adequate to lift the filled cask.
It should be remembered
-that the evaluation is based on using only two of the four pads.
In practice, the lifting device will be attached to all four pads.
O k
O 2.4-5 Revision 7 - 8/22/85 a
e,, ' -
[
2.4.3.2 Cask Ltd Lifting Device'
-2.4.3.2.'11 Loading 4
g
-Each' opposite pair of lifting' eye bolts are designed to lift the lid.:thereby providing for redundancy in the lifting of the lid.
According to Title 10'of the Code of Feeral Regulations, Part 71.31 (c). the lifting system must be capable of handling three times the expected' total load..
D 3(W )
The cask lid weight is 9,462 lbs.
9-
= 28,386 lbs.
-Design-load = (9,462)(3) 2
_Each ear will carry half of the design load:
2 -
4
- W = D /2 Where D = Design Load = 28,386 lbs.
b W = 28,386/2 = 14,193-lbs.
k Qu
= 3 0) n I
D E
1 e
f O
a l
3,.
q ti[1
+
er c
1-W _11 f:
7
+a0 m Figure 2.4-2a Cask Lid _ Lifting Device
, Figure 2.4-2a shows.the cask lid' lifting device. Four ik" D eye
-bolts are inserted into four threaded holes in the' lid. 90*fapart.
1 Each eye bolt.McMaster-Carr #3013T57 orl: equivalent has a 3" shank
. Land is th'eaded ik"'into'the lid threads which.are lined with r
'helicoil-inserts.
f:}.
t
-2.4 '6 Revision 5 - 6/10/851
~-
~
~
i The working load limit for each eye bolt is 15,000 lbs. and the tensile strength of the helicoil assembly is 150,000 lbs. All four lifting eycs will be used simultaneously. However, two f
opposite eyes can carry the design load of 28,386 lbs. which is three times the actual lid weight of 9,462 lbs.
The lid will always be lifted vertically, therefore, no bending in the lifting device is considered. The eye bolts will be removed during transport, and therefore will not be subjected to transportation accident conditions.
During transportation, four hexagonal lead bolts, Ik D x Ik" 1, will be inserted into the helicoil assemblies. These hexagonal lead bolts will be removed and replaced by four eye bolts when the lid is to be lifted.
The lifting capacity of two eye bolts is 30,000 lbs. The safety factor for lifting the cask lid is therefore:
1.06 SF=
=
The lid will ncrmally be lifted by a sling that will engage all four eye bolts simultaneously, thereby doubling the safety factor to a value of 2.12.
O O
- 2. 4-7 Revisicn 5 - 6/10/85
3,4.4 TIE-DOWN DEVICE f
173.412 (d) the cask In order to satisfy the requirements of (J'
tie-down blocks were designed to meet Title 10 of the code of (d) which stipulates that the tie-Federal Regulations 71.31 down structure be capable of sustaining at the center of j
gravity of the cask a "g" loading component of:
)
2 g's
=
Vertical 10 g's Forward horizontal
=
5 g's Sideward horitor.tal
=
2.4.4.1 TIE-DOWN FORCES
.- 27'-.
N i
73' 70*
I 7 0' '
f 70' t
e 1
/
14.7 5' t
- 41.81*---+
96*
l 4'7.7*
Y#'
o H
yj46.67 1
N 42.3*
42.3 \\
r FIGURE 2 4-3 TIE-DOWN CONFIGURATION 47.66 in. (See Section 2.2) 4 Cask center of gravity
=
41.8125 in.
=
Cask radius 96 in.
=
Overall Height Ibs.
66,720 4
Weight
]
O l
1 i
2.4-8 Revision 4-4/15/85
For a loaded cask wsight of 66,720 lbs, it is considered that the h
following forces will act simultaneously at the center of the cask in the folloWing directions:
Vertical - V 2g will act in the upward direction and lg will act in the downward direction for a net lg force or 66,720 lbs. upward.
Forward Horizontal
_Hp 10g will act in the forward horizontal direction or 667,200 lbs.
Sideward Horizontal - Hg Sg will act in the sideward horizonta3 direction or 333,600 Jbs.
Load in Tie-Down Rods Vertical As shown in Figure 2.4 -3, the vertical component of the g force in one rod is = F cos 47.7*.
y Where F
= the tension force in a tie-r6d due to the vertical y
6 g force Therefore, 4F cos 47.7* = 66,720 lbs.
y Thus, the tension in a tie-rod due to the vertical g force is:
F
= 24,784 lbs.
y O
2.4-9 Revision 6 -8/7/85
o l
t
~ s e
I
()
/
d' e
F,"
,e v
l To.
/
F,: g4
/
<--4 l. SI
+- 27.4[4 p 2F sin 4T7'cmW y
(,b320 60) c.G
-~
n 2F e, 47.7 g
I
%L7" e
7g 2
06
,0
.v y
a l fww Ficure 2.4-3a Forward Horizontal Tie-Down Forward Horizontal' only the two rear rods are effective in resisting the-10g forward horizontal force, as shown in Figure 2.4-3a.
Let F
= tension force in a tie-rod for forward horizontal _gEforce FH IMoments-at.Pt. O at bottom (assume this is pt-of rotation)
{
Q 66,720 (10) -(46.67,) =
2F sin 47.7 cos 35 (72)
FH
+2F cos 47.7 (41.81+27.42)
FH 2.4 Revision.7 8/22/85-
31,138,224 =
87.245FH + 93.185 FFH g
31,138,224 180.43F
=
FH Thns,.the tensioniin a tie rod due to forward horizontal g force is F
= A 2,578 lbs.
FH Sideward Horizontal ~
Only two rods are effective in resisting the 5g sideward force as shown in Figure 2.4-3b.
-> A b~g
,e
+..
F s H-e
'su h
s
.i
(,
H
+--- 41.s rb
+ hqi+!
2.F p6 47 7%35 t
x 3
6;n.o(d) >~*6-4 73 2 F.,a tos9.7.7 o 6
V a
3 4 47" O
Y v
p A
SorrocT View A-A F
G.
Fioure 2.4-3b - Sideward Horizontal Tie-Down i
2.4-11 Revision 7 - 8/22/85
=
ens n
na e-r r sMeward hodzontal g force Let FSH
-J Moments at Pt. O at bottom 0
s'. C. I _'_' 6 66,720(5) (46.67 ) = - 2F sin 47.7 sin 35.0(72)
SH
+2F cos U.7 Hl.8.1-27.42)
SH
. _. ~
15,569,112 =
61.1 F
+ 19 4 F SH SH Y
15,569,112 80.5 F
=
SH Thns, the tension in a tie-rod due to sideward horizontal g force is SH " '193,405 lbs.
F Summary of Tie-Rod Forces The maximum tensile force in a rod from the simultaneous appli6ation of the 3 g forces is q
F1=Fy+FFH +
SH F
= 24,784 + 172;.578 + 193,405 1
1=
390,767
= 390.8 kip F
2.4.4.5 Tie-Down Pads for Cask Assembly 2.4.4.5.1 Loading The tie-down pads must be capable of sustaining the total force of 9
the maximum force previously calculated, viz. 390.8 kip.
The tie-down pads are designed to resist this maximum force.
Each pad is designed for 390.8 kip.
2.4.4.5.2 Tie-Down Pad Design) ksi Use steel of Fy - 38 min. weld with low hydrogen electrode.
Steel to be noted in Group II Table 4.2 of AWS Dl.1-80 Structural 1 Welding Code.
Check hole for bearing and shear. (assume 2375'i min, for Pin) 35.5 ksi (actual bearing stress) g F
=
=
p 2.75 2.4-11a Revision 7 - 8/22/85
O Safety Factor '
SF = 38/35.5 = 1,07 Check tear out of hold down device along lines 1-2 and 3-4, Section A-A (page 2.4-13)
Av = 2 x 3 x 4 = 24sq. in.
The shear capacity of structural steel is 2/3 of the tensile capacity.
Therefore, the tear out capacity is:
08 2/3 x 38 x 24 = 608 kip; SF =
1.56
=
390.8 At the highest loaded lug the tension force = 390.8 kip Therefore, horizontal component = 390.8 cos 42.3* =
289 kip and the vertical component = 390.8 sin 42.3* =
262 kip Bending on plane 1-2 Y
M = 4 " x 3 9 0. 8 = 1758. 6 ki -in P
Assume weld pattern is 22" x 4" pattern.
2-Area of weld material
= 2 (22+4) ( l x.707) 36.8 in
=
I=2
- (.707) (22) 3 + 4 (.707,)(11) 2
= 1938.1 in 1
12 C = 11" S_'= I/C = 1 8.1 3
176.19 in
=
15
= 10.0 ksi Tension stress on weld = F
=
g 776. 9
.6 ksi Shearstressonwelp=FSW "
3 8
Combined stress = f
( 10.0 ) 2 + (10.6)2 14.6 ksi
=
cod Allowable tensile stress
= 21 ksi S.F. on tension = 21- - -
=
1.438 514.6 O
2.4-12 Revision 7 - 8/22/85
2V i
.1r-
~
s g
\\
am 92s*
A s
/
'?
/
'n A
N
< i a
s m
SIDE ELEVATION 6
18 y
Y
~_
B' 45" \\
3"D
(
_l
^
h i
.i 3
44.
M V
kVESSEL
~
g 9
(3E ku;c BLL-sggr1og A-A l
TIE-DOWN PAD M LUG Revision 7 - 8/22/85 i
Tie-Down Pads As shown in the drawing, four tie-down pads are provided to attach..the shipping cask to the truck bed.
Each pad, a plate 24" square and 1" thick, is formed with the curvature of the vessel in the vertical direction.
The lug, a plate 4" thick, 22" long and 8" high, is welded at right angles to the pad with a 1" fillet weld all around.
The pad is welded to the cask body using a 1" fillet weld all around.
A 3" diameter hole provided in the lug is used to enable; tie-down.
Both g
plates will be fabricated from a-steel having a minimum, Fy T
= 38 ksi and the lug plate will be welded using a E70 ksi low hydrogen electrode.
The cask will be installed on the truck bed so that the center line of che'110' angle between adjacent pads is parallel with the direction of travel.
The transverse line is parallel to the center line of the 70" angle between adjacent pads.
The lifting / tie-down pads and the welds that attach them to the cask'shell are therefore adequate with a safety factor in excess of 1.43 to resist the assumed simultaneous maximum g loading during transportation.
2.4.4.5.5 Excessive Loading of the Tie-Down i
/
.. s,.
y
~
c.e Q a.I
', W,
~
l'
\\,
g, y
F= 3Sa. 8 WW.,
Tie-Down Fitting (Stresses in Shell)
The stresses induced into the outer shell of the vessel by the forces, calculated in Section 2.4.4.1 due to loadings of 2, 10g 9
and Sg in the vertical, forward horizontal and sideward horizontal-Cdirect_ionsrespectively, are very localized in the vicinity of the fitting.
It is conservatively assumed that only the outer shell will react ~tcthe maximum tie-down fitting load of 390.8 kip.
The g
analysis approach is taken from Welding Research Council Bulletin W
2.4-14 Revision 7 - 8/22/85
A No. 107* which is based on the classic analytical studies of V
P.P. Biglaard.
f 1
c.ew=bW dueelvm ( essq9 a
, a y v v e v As it e t xA xi v 4. w 4
s I
p 4
<ff f
a A
a
~
, :& %e,re.%st.
--~~ j A.w s
f VeA M
~.
1,Z Lv3 x
J J
oxvw q q n v 7/.nn f
4 3:~
.I n
p H A
,y*#
~
O E 'V fad v
44 yMov' W A
t gu) n v eTs The bending moment and shears in the shell circumferential(c) and longitudial (L) directions due to the maximum resultant force of 390.8 kip.will be assumed to react into the shell by the pad attachments.
n X4 7
.Ni Y'
Vs u
e M
.J j
A er a Vu M.
t U
- " Local Stresses in Spherical and cylindrical Shells due to Dcternal Loadings", by Wichman, Hopper, and Mershon, NRC Bulletin No. 187, August 1965.
"evision 7 8/22/85
O\\
The shear forces are:
V
= 390.8 sin 47.7 289.05 kip
=
c 263.01 kip V
= 390.8 cos 47.7
=
The bending moments are:
1183.5 in-kip g
4.5V3 4.5V
= 1300.7 in-kip M
=
c c
The shell geometric parameter used is:
[=R
,41.1875 32.95
=
1.25 T
The pad geometric parameter used is:
1 = 24.0 therefore, C
= 12.0 h,
1
= 24.0 2
therefore, C2 = 12.0 The combined shell/ pad geometric parameters used are:
1 12.0 E
= 0.29 l
R 41.1875 m
2 41.
h5
= 0.29 E
m The constants for the circumferential moment (M ) for this design are:
fy p2)Ys p=
For membrane forces
= 0.29
=
y For bending moments p=K El E
= 0.32
=
c 2
)
(K = 1.1)
The constants for the longitudial m8 ment (P ) for this design 7
are:
hl 2 '/3 p=
pE
= 0.29 For membrane forces
=
y2 2
0'29 For bending moments E=
g p p2
=
(
2.4-14b nevision 7 8/22/85
-)
Stresses resulting from the circumferential moment, Mc The circumferential stresses (6g )at Point A are obtained as follows :
Step 1 -
Read from graph in reference the value for NL (M I EI c
m Step 2 -
Read from graph in reference the value for 4
= 0.07 (M /R,p) c 1
Step 3 -
Circumferential membrane stress:
N M
}
3 4
c 1300.~7
=(1.3)
T 2
(41.1875 f(. 29) (1. 25 )
gg jg B)
R BT O
C m
2.75 ksi
=
e Step 4 -
Circumferential bending stress:
M 6M 6H 4 g
c
-(6)'1300.7
(
}
2 41.1875(1.25)*(.32)
T M /R,p RTp c
m 6M4 26.53 ksi
=
2 T
Step 5 -
Combine the circumferentiil membrane and bending stress-h +
6M4 k
=
T 2
T h
6
= 2.75 + 26.53
= 29.28 ksi g
l 2.4-14c Revision 7 - 8/22/85
The longitsdinal stresses (6 y ) at Point A are obtained as follows:
h The same steps are repeated using different graphs from the reference.
N M
x xg
= 0.03 M /R p c
c N
N M
-1300.7 x
x c
7 M!mE N
c m
N[
6.98 ksi
=
6 "x
6M x
c 6(1300.7)
T "c
E m
RT y (41.1875)(1.25)2(.32) m O
6M 11.37 ksi
=
2 T
N 6M 18.35 ksi
6.98 + 11.37 fx
T 2
=
T The shear stress resulting from the longitudinal load at Point A is:
VL 263.01 7"
4.38 ksi
=
1A 4C T
- 4 (12) (1. 25) 2 The combined stress intensity at Point A is calculated:
1/
}6 - 64 )
S=
( 6, + 6 +
f
+ 4Z 3
ax
-t S=
(29.28 + 18.35 +
29.28 - 18.35)
+ 4(4438)2
)
t S = 30.82 ksi Material yield stress
= 38 ksi g
1.23 (FS)
=
=
0 2
2.4-14d Pavision 7 - 8/22/85
The shell material can resist the stresses due to the maximum
. (O tie-down circumferential moment with a. factor of safety of 1.23.
' i Stresses Resulting'From the Longitudinal Moment, Mg The circumferential stresses h at Point B are obtained as follows:
The above steps are repeated using the appropriate graphs from
.the reference..
"0 4
From Graphs:
= 3.0
= 0.015 LY
- M /R, p g
N N
M 4
L 1183.5 (3. 0) (41.1875)'(1.25)(.29)
=
(2Ty Mg/R,2p N4 y
y = 5.77 ksi 6M 4
Ok 6(1183.5)
=
= ( 0. 015 )
T M /R p 2
(41.1875)(.29)(1.25) g B
T 6M4=
5.71 ksi 2
T h
= 5.77 + 5.71
= 11.'48 ksi The longitudinal stresses 6 x at Point B are obtained as follows:
The above steps are repeated using_the appropriate graphs from the reference.
N M
1*4
=.025 M /R,p Fron' Graphs:
2 jp g
N
%a 1183.5-h, x
y,4 M /R, p R, pT (41.1875)2(.29)(1.25)
T 3
N l = 2.69 ksi O
2.4-14e Revis3xm 7 - 8/22/85 i
x, x
L 6(1183.5 h
6M M
6M
= 0.25 2
M /R,p R
T (41.1875)(.29)(1.25)2 T
L 6M
= 9.51 ksi 2
T
{
= 2.69 + 9.51 = 12.2 ksi The shear stress resulting from the circumferential load at Point B is:
= 4.82 ksi d
" 4C T (4
2
) (1. 2 5)
The combined stress intensity at Point B is calculated:
'zI,
~
9
(% d)
+ 4[q (7 + 6x +
S=
?
-v g z
(11.48 + 12.2
+
(11.48 - 12.20)
+ 4(4.82)2 j
S =
O S = 16.67 ksi
=}.0
= 2.28 (FS)Y 16.67 The shell material can resist the stresses due to the maximum tie-down longitudinal moment with a factor of safety of 2.28.
Therefore, the governing stress in the shell resulting from tie-down loads is the combined stress intensity at Point A due to the circumferential moment.
The stress calculations assume that there is no support from the inner shell or the lead between tie shells when the maximum tie-down loading is applied.
The factors of safety calculated are therefore conservative.
I f
O 2.4-14f Pavisico 7 - 8/22/85
2.4.4.7 CHOCKING RING
)
/s 78 c'5k ;1F hs V2 i
h' V
10 W
_ =,. [_
A a
lh Trailer Side Frame j
8' M C 8.5 l
,f FIGURE 2.4-10 FORCE DIAGRAM CHOCKING RING O
l l
l I
l l
l l
l r
1
(
2.4-15 Revision 7 - 8/22/85
,o
The chocking ring velded to the steel deck plate is designed to prevent sliding of the cask due to the forces imposed during
$I the conditions of transport stated in Title 10 of the Code of Federal Regulations 71.31 (d).
Making the conservative assumptions that the friction force between the cask and support is neglible, the maximum force that would be transferred at the base (using the analogy of a simple beam on two supports) is:
4 Max. Reaction =
102+52 373.0 kip x 66.72 kip
=
The chocking (restraining) ring consists of a 7/8 thick ring welded to the base by two inch fillet welds, one on each face of the ring.
The shear restraint of the steel. ring is:
13.3 kip /in Fv = 0.4 x 38 x 7/8 x 1
=
allow.
I The welding electrode has a tensile strength of 80 ksi.
16.97 kip /in
=
Fv
=
E O
allow.
The shear of the steel ring governs.
Width of ring, required to restrain base of cask is:
373 4
13.3 The minimum diameter of the ring = 0.D. of the cask = 83.625" the cask is safely restrained by the ring, assuming Therefore, friction is neglible.
_ 83.625" J Cask
~
~
W = 65.72 kip fD (tie dcM1)
I 10K 5w/
g Reacticn g
s (Ring) 2.4-16 Revision 4 - 4/15/85
\\
4
-,y?
3';
2 2.5' STANDARDS FOR GREATER THAN TYPE A PACKACING The' greater than. Type A-package must satisfy the requirements
~
of~10 CFR parts 71.41 - 71.47.
The ANEFCO AP-300 cask described intthis SAR will be used to
- transport low specific activity packages.
In accordance with 10 CFR.71.52, the packages need-not satisfy hypothetical accident cond.itions..
Compliance:of ANEFCO AP-30 under normal operating conditions
'is described in Sections 2.6, 3.4'and 4.2.
w' LO 4
3 4
w I
2.5-1 I
- 2. 6 Normal Conditions of Transport 2-73(*)
2.6.1 Heat Assuming an' ambient shaded temperature of 100*F'and a heat
-imput of cal 1 BTU 929 cm2 122.8 BTU 400 2
2 252 cal.
ft.2 hr-ft
=
G2h)
Assume maximum 150 watts
- watt (175.14 ft surface) 2.7 BTU
=
hr-ft Assume 126 BTU
= maximum heat that must be dissipated hrft from cask under normal conditions.
h AT
= 126 ' BTU 2
hrft!
where h
=h
+h
= total heat transfer from' cask t
r O)
= convection transfer + radiation transfer u
AT= surface temp - maximum ambient' temp Ir.cAdams 1/3 ea ransfer-h.=.18(T
~
c s
a F
4
- 4 _' l h
= 0.173 E T
T r
s a
100 100-l
Cask'_ Designer's Guide
_7 )
's a
s 1.
if T =100*F=560*R-by trial and error 3
and if T = 165"F=625*R h
= 0.72 BW T
= 1 0*F=630*R s
c s
hrft *F h
= 0.74 r-h
= 1.15 BTU h " I*17 r-c
'hrft *F
-h = 1.87 BW t
ht = 1.91 2
hrft *F
! )
h t.T = 122' BTU hga T= 133 BTU t
2 hrft hrft
,,-Surface temperature of cask will be between 165'F and l'70*F_
I..
Af.5-R
2.6.2 COLD 2.6.2.1 COLD AMBIENT TEMPERATURE (-40 ) *F. NN STILL g
AIR AND SHADE The shipping package must be able to withstand an ambient temperature of (-40)'F in still air and shade.
Assuming that the container cavities were sealed at a temperature T1 = 70'F = 530'R, and a pressure P1 = 14.7 psia and where T2 =-40*F = 420*R.
Assuming no internal heat load, then by gas laws for constant volumes, the final pressure is:
P2 = P1 T2 T1 P2 = 14.7 (420) 530 P2 = 11.65 psia The resulting pressure differential is not significant by comparison to ambient atmospheric pressure.
A temperature of (-40)'is within the operating temperature range of the materials of the g
container.
The containment vessel is fabricated of ASTM A240, Type 304 stainless steel and is not susceptible to failure by brittle fracture.
The contents are shipped in dry condition and is entirely passive and no heat transfer Jiquids are involved.
The only adverse effect occurs when the lead contracts and places the inner shel] in compression.
This differential radial contraction wil] cycle f rom (-40)'F to.180'F.
The range of 220*F will produce interference stresses between the J ead shie]d and the inner shell.
To be conservative, for design purposes, the radial interference and resulting pressure was calculated for one cycle from 600*F to (-40)' ".
This is about six times the maximum normal ex-pected alternating stress.
O 2.6-2
5 l
,w CONTRACTION OF LEAD AROUND INNER SHELL
-2.6.2.2 N
Differential thermal expansion between the j
lead shie3d and inner she31 during cooling b
4 af ter pouring of the 3ead results in compression The analysis conservatively p
of the inner shell.
i assumes a continuous cool-down'from the lead U
melt temperature for.a.long period prior to.
1 During this time some relaxation of the contact forces k
exposure to a (-40)*Ftemperature.
The exerted by the lead can be expected.
h theoretical maximum contact pressure between the lead and inner shell is determined by:
- ej (e pb A s ) d "'
4 Pp3 =
'b +a2 2
-g, 4
(1/Epd)
'c2+b2 +d pb} + (1/E,)
.cZ-N FZ-a2 o
I oc pb = coef ficient of linear therma) j Where:
expansion of lead
= coefficient of linear thermal expansior of steel g pb = aodulus of elasticity of Jead
= modulus of elasticity of steel gr
= inner radius of inner shell a
r
= outer radius of inner shell b
= outer radius of lead shield c
d s " d pb = Poisson's ratio = 0.3 (36.3 - 6.5)(660)
P
=
p3 1
- 0. 31 + F
)
'(40.5) f + (38.5) Z
+
l-Y
- (4 0.5) ' - (38.5)Z
- (38.5)2 + (38)2 0.3]
(38)e (38.5)4 TimoShenko, S.
" Strength of Materials, Part II,
. Advanced Theory and Problems", third edition, Van t
Nostrand, 1956 O
2.6-3 Revision 1 7/31/84
I l
O The actual maximum contact pressure the lead is capable of exerting on the steel is the maximum equivalent hydrostatic pressure:
Using Roark Case la, page 504 Ppb (c2-b}
2 1l P
=
maxpb (c4 + be) maxpb = 511
(.0508) s' P
ll P axpb =
25.96 m
The lead will develop a circumferentia) membrane stress in the inner shell as a result of the lead contraction.
Using Roark Case *1b, page 448 8 =
gR t
Where: g = pressure exerted by the lead R = radius of the inner shell t = thickness of the inner shell O' =
25.96 (38)/.5 1
O' =
.19 7 3. 0 psi This is well below the yield stress of the inner shel) (30,000 psi) by a' factor of 15.
t
- R.J.
Roark and W.C. Young " Formulas for Stress and Strain", fifth edition, McGraw Hill, 1975.
l ID 2.6-4
. Revision 1 7/31/84
4
- ~
s Further' examination of the interference f
stresses warrants. examination of the critical
(])
pressure of the inner shell.
The critical pressure for elastic' stability for the inner shell is:
Using Roark Case 19b, page 556 2
2 2
[(1/1 -p ) 3 (t /R )] 0.25 2
P R = 0.807 (Et /LR)
C Where: E = Modulus of elasticity of inner shell jk = Poisson's ratio t = Thickness of inner shell I
R = Radius of inner shel)
L = Length of the inner shell P
= 0.807 (29 x 10 ) (.5) 2/(84) (38) 6 CR 2
2
[(1/1-(0.3) 2) 3 (.5 /38 )) 0.25 4
F
= 196 psi CR
(
Since P
= 196 psi and Pmaxpb = 25.96, the lead CR 1
contact pressure due to lead contraction will not buckle the inner shell.
l i
5 O) 2.6-5 Revision 1 7/31/84
\\-
I l-l
'\\
2.G.3 Reduced External Pressure g
The regulations for normal conditions of transport specify that the package be able to withstand an The resulting absolute atmospheric pressure of 3.5 psi.
t internal pressure is thus 11.2 psi, 3Sysi d~
00 4
Y ca4-sede ym2sws.
l;'d(cle.
r I
- f o
( 4.7 S i lMSo'd C-f yg*
W
, (g} wif )
L-pres sure COVER PLATE SECTION (1.25 + 1.562) = 39.00" R = h(83.625)
From Roark " Stress and' Strain" Sth edition case 10a page 363 for r. = 0 G
I3+ I "
(3 +.27) = 3481.6 inlb/in Mcenter "
1 2
1x2 0.67 in /in S, =
5196 psi (bending in plate) fb" 67
=
7.30
=
S.F.in bending 20 Using ASTM 516 steel having a yield of 38 k.s.i.
Only the outside cover plate will be exposed to differ-ential pressures during reduction of the external pressure.
The lead shield on the inside face of the lid and the inner plates will not be subject to bending due to a reduction of external pressure when the cask is operational.
h
- the next page is 2.6 2. 6 '6 Revision 1 7/31/84
w e
g -
s.
3 s
(-
2.6.4 Increased External Pressure, The regulations for normal conditions of transport specify that the package be able to withstand.an atmospheric pressure of 20 psi.
The r,esulting net pressuie is therefore, 6 psi.
The effect of an' increased atJoospheric pressure is to increase the external pressure to 6 psi.
For this anaylsis the internal (primary containment) vessel is considered free standing without support from the external shell.
Therefore, the primary memt.Vanef stress in the inner shell is:
Using Roark Case Ic, page 448 cR
=
04 t
r g=Pressureinlbs)in Where:
R=
Internal radius
' s, t = Tliickness of the inner shell e
g
,m 7 = 6(38) 2 n
.5 v
7 = 456 psi t
x 2
Theyieldstressfohth'dinnershellis30,000 psi, therefore, thexinner shell will suffer no. damage from a 25 psi external pressure'.
l Evaluating the lid and end plates, considering the lid'and botton plates are simply supported Using Roark Case 10a, page ' 363 (to derive the moment) 2 M = K ga m
?
t where:
K
=.20625 where R0 = 0.0 i,
m 2
s
= pressure in lbs/in r.
e a1 = radius of cask lid t
a2 = radius of end plate (inner shell) l My = moment of the cask lid
!O
,s t
d j
e s
(_
sa r
~E'~
f
. f --.
.A
.20625 (6) (40.5625)2 M
=
G ',
t 2036 lbs.
M
=
y M
= M ment of the end plate (inner shell) 2
.20625 (6) (38)2 M
=
2 M
= 1787 lbs.
y Solving for the stress in the lid and end plate (inner shell)
Using Roark Table 24, notations Page 332 The circumferential bendina stress for the lid is:
6M1 2
2 7
t b
= 6(2036) 2 1 2
2 b
= 3054 psi g
2 y The yield stress for the lid is 30,000 psi therefore the lid is sufficient.
The circumferential bending stress for the end plate (inner shell) 6M2 72 2
t
@2 6(1787)
=
2
(.5)2 T
42,900 psi 2
=
2 The yield stress for the end plate (inner shell) is 30,000 psi.
Since the inner end plate is located inside the lead and outer plate the analysis of the stress on the outer plate will be performed to determine the actual stress seen by the inner plate.
O 2.6-10
Usina.Roark:CaseJ10a, Pace 363 y y!
!s,i
-(to' determine the moment)
M = K, _. g a Where:
K,
=1.20625 when R0=0 2
3 g;
= pressure in lbs/in a - = radiusLof cask outer. bottom plate 3
M
= m ment of-the cask outer bottom plate 3
M
=: (.20625) (6) -(40.5625)2 3
s 2036 lbs.
- M
=
3 Solving-for the stress in the outer _ plate s
a
+
.Us ng Roark. Table 24,-Notations page 332 i
~
The circumferential bendino stress in the outer bottom plate is:
' 7 6F~3
-3' 2
t
- 7,
_6(2036) 3
-(1.25)2 7=
,818'ps(
~
3
. b
. The-yield: stress of the outer bottom plate-is 38,000 psi
.therefore, there will;be no stress:seen by the inner end plate due to'the external pressure of 25 psi.
k k ',
lp
+. k' '
i,.!
JO 2
2.6.
r
-3 2.6.5 Vibration The approximate natural frequency of the loaded cask is based on the concentric steel shells.
Using Roark
- page 576, Case Ib, considering the cask a uniform beam with both ends simply supported, and a uniform load w per unit length including the cask weicht.
! TI 9"
fn" l
Where:
E= Modulus of Elasticity I= Area of Moment of Inertia L= Cask height = 96 in, l= Distance between supports = 83.5 in, w= 65,710.80 (lb) 684.49 lb/in
=
96 (in) 6 E = 29 x 10 1b/in R=
Outside Radius of Cask Shell =
= 41.8125 in.
2 R = Inside Radius of Cask Shell =
R
- 1.25 = 40.5625 in.
g I
6 3
12 EI = E (R -Ry) = 29 x 10 x 274 x 10
= 7.946 x10 fn = (9.87/2gT) (7.946x 10 x 32.2 x 12/684.49 x 83.5 )b 1
4 fn = 477 HZ This natural frequency is satisfactory for truck transport, since it is well above the low frequency range of truck suspension systems (1-20 HZ)
- R.J. Roark & W.C. Young, " Formulas for Stress & Strain" i
Fifth edition, McGraw Hill, 1975 i
i t
2.6-12 Revision 1 7/31/84
.I
_.... ~
~.
2.6.61 ' WATER SPRAY-M A heavy water? spray on the package will.not harm the package because it
,VO is constructed of ASTM A516,.Crade 70 steel. Inaddition, no water will leak into the primary containment'because of the bolted closure and seals. Therefore, the only possible effect of the water spray would be to-lower 4the. cask temperature.
' 2. 6'. 7 -
FREE DROP-In designing a cask for transport 'of radioactive material _ the regulations require that a free drop of the cask through a predetermined' distance (in
~ feet) onto a flat, essentially unyielding surface must be investigated.
= A-segmented toroidali ring will-belattached - to the ANEFC0 AP-300. cask to
~
absorb the energy which-is generated by a 1 foot drop of the' cask..as shown in Figure 2.6-1.
As shown.in ORNL-NSIC-68 in Section 2.8.2, this
- ring will protect'the' cask closure not only in an end drop, but will
.' operate properly'regardless'of the angle at which the cask impacts on a horizontal' surface. The damage evaluated here is that due to-deformation at
~
the impact plane and indirect damage due to deceleration.
The- ~ toroidal ring will be a 3"-
0.D; x k" thick steel tube made from bl 1020 steel
. hot rolled
-and : electric resistance welded. Using equation 2.17 on page 67 in ORNL-NSIC-68, the energy absorbing character-
'istics in a crushing impact are correlated _by:
2 2'
g, Syt L [ A t 0.4 6 i
R R
Where:
E = Energy absorbed $(in-lb)'.
Syf= Yield strength.of steel (psi) t = Tube thickness (in) f L =. Tube length-(in)
'R = Mean radius (in)
A =-Deformation of' tube _(in)-
~
and as shom in Figsre.2.6-2.
. The ener gy which must be absorbed by the tube for a 1 foot drop
~ E =.66,720 lb x 12 in- = 800,640 in-lb For-the L3" tube described above 4
L Sy =. 38,000 psi' s t - 0.25 in :
L== 83.625
- 262.7~in:
3 +~2.5 R-=
= '1.375
- f 4
- Substituting in the above equation:
= 38,000(0.25)2(262.7) 0.4 2
F' r
c 800,640
-1.375-13
='
.6-i-
- A. - :1.28
- '(
l
- Since the I.D. of L the tube:is 2.5 -inches;hei tubeLean accommodate the '
deformation caused by;a-1-foot drop ofLthe' cask; i
[s l-
"2.6-13:
+
Revision '6 8/7/85-L m-
ToRoivat RiNs ENERGY 4BsoRSEC e
-'T J p._ qgHs WeLJ) 60'
\\
s
~.-
81% WELp Boter R mG j
C,ASK 00TER Sdst-t-FIGURE 2.6-1 TOROIDAL RING ENERGY ABSORBER l
N.
%,g %
s
\\
's,,,
'"%g FIGURE 2.6-2 DEFINITIONS OF TERMS USED IN EO. IN SEC. 2.6.7 O
2.6-13a Revision 5 - 6/10/85
The tube will be velded to the cask outside shell with two " fillet (s) welds using E70 kai Iow hydrogen electrode, which has an allowable tensile stress of 21 ksi, as shown in Figure 2.6-1.
The force due to the deceleration of the cask can be determined using equation 2.4 on page 36 of ORNL-NSIC-68 (Cask Designer's Guide)
F = 2Ng(W)
Where:
W = weight of the leaded cask Ng = the mean no. of g's the cask subject upon impact 9.375
(,
Ng = y
=
Ng can be calculated by dividing the drop height by the stopping distance in accordance with the statement in section 2.7 of the Cask Designer's Guide.
3 1.251 x 10 kip Therefore, F=
(66,720)1bs
=
This force must be resisted by the welds with which the tube is attached to the cask shell. The total area of the 3/4" weld that will resist the force can be calculated as:
A = 2 Y(D)(b)
Where:
D = 0.D. of cask b = effective throat of weld 2
A = 2W(83.625)(0.354) = 186 in The tensile stress on the veld area is:
3 6
g,1.262 x 10 kip g73 g 186 2'
4 Safety Factor = 6.73
~
Since allowable stress for the weld is 21 ksi, the tube welds'will resist the force of the drop impact with a safety factor of 3.12.
A square tube ring, f abricated from ASTM 4A500-GRB., steel, 2 inches on a side and 0.083". thick, will be installed on the bottom of the cask to absorb T
the -energy during a bottom drop of the AP-300 cask through a height of 12".
This arrangement.is shown in Fig. 2.6-2a.
O 2.6-13b Revision 7 - 6/22/85
=
l I
(
e pre Mc erg I
ese AST M A-500
(
G R R STEL 1
Figure 2.6-2A AP-300 Cask Bottom Desien 2.5"
- o.06f I
-a
-..w,.
The force on the impact ring, the stress in the wall of the ring and the stress at which the wall of the tube will buckle or crush can be expressed as follows*:
0.6[E Ng=
- F=
g
=
er Where:
Nf = Force on impact ring g -= Gravity Force
}
R
= Radius of the ring t
= thickness of the tube f
= stress in the tube of the wall C = stress at which wall tube will buckle er 6
= knockdown factor which is a function of R/t E
= Yourg 's modulus for f = 41 8
= 496.2
- [ = 0.3 0
(
I Therefore Ecr "
4 2
= 10,339 psi Under stress conditions the stress in the wall of the tube will be:
(66,720) 1
= 3106 ps1 21T141.1875)
.083 The wall will'not buckle under static load.
However, the wall will not be able to support more than:
10,339
= 3.33 g 3106 Assuming that the 12" drop will cause the tube wall to collapse, then the stopping distance will be the height of the tube minus twice its thickness.
h d = 2.5 - 2(.083) 2.334
=
- Buckling of Bars and Shells, Brush & Almroth, McGraw Hill, 1975 2.6-14 Revision 7-8/22/85
Th2 g loading on th2 cc k lid tnd:r th2 imp ct cenditicns enn b2 calculctcd by dividing th] dr:p height by th2 ctcpping dictcnce, cc chown in S;cti:n 2.7 of the Cask Designer'c Guida (CRNL-NSIC-68).
12 S " 2'.334 5.14 The g loading on the lid will therefore be b
Fg = 2Wg = (2) 9.46 kip x 5.14 = 97.2.
kip The force will be distributed on the 2.5" lip (Part No. B-5) where the lid is bolted to the cask, whose area is:
2 2
2 f(81.125 - 26 )
632.5 in
~~
A=
=
Subtracting the area of the 36 bolts, the net area is:
2 2
A,. 3e x.y(0.>e5e>
1e.e in 632.5 - 16.6 - 615.9 in The stress on the lid plate will be:
1.E 97.2 0.16 ksi
~
A 615.9
}
The SA-240 plate, with a yield strength of 30 ksi, will not bend out of shape under a stress of 0.16ksi with a safety factor of 187.5.
(*)
'" ~
= 187.5 SF
=
0.16 m
(
[ y ea % e ~ese Asim A-s'o c
L
/
G a E snt t.
Lenw re:r~
3 b
- c.ogt m.5' "
I c,
g R.4i.itw' N
Nfs/ 44*ijlf
- ff,7;o d.:
s n()
2.6-15 Revision 7 - 8/22/85 l
l
eW 6eTroe zmcr j'
o.q p,H
.-- i.e s "
,h Lesd s
/
ge d_
v1111;.i n
- k. j' c
- $, Ajg N
- .9 s \\<
\\
/
'a
~.
l-t
/
f////////////] f L
T.
2
- 6 sa I.26
[
n51.44kllAllllkllll}lllkk 4
i
?
For bottom, flat impact (g=5.14), the loading on outside bottom plate is due to the weight of the contents, and the weight of the bottom plates h
and lead.
81.125b2.0625)(710)3
= 4380 lbs.
Weight of lead
=
4 (12)
.125)2 (1.75) (.283)
Weight of steel =
= 2560 lbs.
contents = 20,000 lbs 26,940 lbs 26,940 (4)
5.21 lbs/in2 q
(81.125)4 2
at impact gi = 5.14 (5.21) = 26.78 lb/in For uniformily loaded circular plate, with fixed edges reference to Roark & Young, page 363. The edge bending moment is Mra " 8 2.6-16 Revision 7 - 8/22/85 g
A L(81.125) 2
}
}
Therefore Mg-5,508 in Ibs/in
=
r h weld stress ~ = f,
'ra =
21,150 psi
=
=
2 (1.25)2 t
I 4
i
~
3 Assume that the weld yield strength for dynamic impact is 25% greater 6
than for static loading
$}
}
b5 1*24 Thus FS =
~
1 and the bottom plate welds are adequate with a factor of' safety of 1.24.
a f.
{
h lid plate bending stress at plane A-A E
[
for 1" strip M = 160 (2.5)2 = 500~ in lbs/in i
- I 2
6M 6(*5001 f=p=
2)'.
750. psi y
Edge rotation -=
2 h
yy) 21.4 lb/in q=
(3 Z. =
0M8 radians-8(2 0 0')(1.3)
(0.3*)
There will be no releases because of compression maintained on _the seal.
4 2.6.8 p RNER DROP--
As indicated'in Section 2.6.7 the segmented toroidal ring, whose design is. evaluated above, will protect the cask closure regardless of.the angle at which the cask impacts on a horizontal-surface (Cask Designer's Guide, ORNL NSIC-68, page 66).
i -lO 2.6 Revision 7 - 8/22/85 l
q a
e
,,,,n
--r-
From a physical standpoint, the maximum direct damage in a corner drop would occur with the cask so oriented that the line passing between the center of gravity and the point of impact coincides with the direction of the fall.
The geometrical representation of the corner drop is shown in Figure 2.6-3.
The idealization of deformation, the external damage after impact, is indicated as Z.
/
Y s
4 I
1 1//HH Hr
/H/Hu //sr
~)
T FIGURE 2.6-3 CORNER DROP DEFORMATION GEOMETRY Using Figure 2.6-3, the angle A (angle of impact) can be seen to be:
Tan A = R/H Where:
R=
Cask Radius 41.8125" H=
Center of Gravity with relation to the top (lid) end = 49.33" Therefore, the angle of impact (a) is:
41.8125/49.33" Tan A
.8476
=
=
40.28' A
=
1 Impact on the top corner causes an axini force component and a lateral l
force component. The axial force acts on the cask lid in the same way as analyzed previously. The lateral force component on the contents bears against the sides of the cask before any shear load is transmitted to the bolts connecting the lid to the cask.
g The behavior response for a corner drop should result in a greater deformation of either the toroidal ring for a top drop or the square ring for the bottom drop.
It is speculated that the crushing under the point of impact will be extensive with less deformation occurring away
[
from the point of impact.
This greater deformation would result in "g" factors less than those for a flat drop.
e :,
2.6-17a Revision 6 - 8/7/85 1
i
LT TOP CORNER DROP 40.28' from vertical Drop angle A
=
Bolt Tension 9.375 (same as for flat drop. This is believed Assume g
=
to be conservative)
F = 2Ng(W1 + W ) cos 40.28' y_
e F - 2(9.375)(29,462) cos 40.28' = 421,432 lbs.
y p (from internal pressure) = 52,500 F
Therefore Fb" 6
~
F, =
= 38,726 psi Bolt Shear
)
Even though the design is such that bolt shear should not occur, we will l
assume that the bolts do take the shear induced by the in-plane component h
of"g" forces on the lid. This is very conservative.
F, = 2(9.375)9.462 sin 40.28 = 114,701 lbs 3186 lbs/ bolt F
=
=
= 7211 psi fs" 44 8 For bolts in combined tension and shear
Reference:
Guide to Design Criteria for Bolted and Riveted Joints, Fisher and Struik, John Wiley and Sons 1974.
2
+ Y (0 62)4 Where x = ratio of the shear stress on the shear plane to the tensile
- strength, y =. ratio of the tensile stress-to the tensile strength Therefore~
x=
= 0.058 1 5 000 1
38,726 Y"
= 0.310 125,000 l
2.6 17b Revision 6 - 8/7/85-T-
F Therefore
+ (.310)2 A,o 1
2 0.009 + 0.096 h-1.0 h
0.105 6. 1.0 Therefore, Bolt is 0.K.
If 50% of the tensile strength is used (62,500 psi) 0.034 + 0.384 i-1.0 0.418 4 1.0 Bolt is still 0.K.
Therefore, the lid remains in place.
2.L.E.1 holt ing De:$gn The bolts screwed into the helicoil inserts are designed to withstand the expected decelerating f orces. resulting f ro: the~ impact resulting fro: a one foot drop at the impact velocity.
t The helicoil it inserted into the bolt ring which 1s fabricated of 2
h SA-240 Type 304 with a minicut yield of 30 Kip /in. The root diarcter of the 1.5' inch long helicoil is 0.79 inches. Therefore, at yield, f
the tensile strength of the helicoil in the cetal ring is:
T = 30,000 lb/in x 1Y(1.5)(.79) = 112 kip The tensile strength of t
, helicoil assembly based on the tr.anuf acturer 's data, shown in figure 2.6.
, is 125 kip.
The bolt which will be used is a 3/4 igch SA-320 Grade L7A bolt with a cinicut tensile strength of 125 kip /in. Therefore, it will be capable of resisting a force f(.75)2 T = 125,000 lb/in x
- 55.2 kip Therefore the bolt will yield before either the helicoil, or the ring caterial when an excessive force is applied to the assembly.
This is the basis of selection of th( bolt specification.
2.6-17e Revision 6 - 8/7/85
w w -
,I n.
/
T I
/
I j
,* s /,
7 y
1 1.
/
........3....<
.-*4~~--
../.=.**.
- .*.=)+
.g
.. 4.. *. 6 o..
s'
..e-
..iv Ys 4-
...............e...
- -s*
i/
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%d FIGURE 2.6 4. TENSILE STRENGTH OF HELICOIL ASSEV.BLY Page 2.6-17d Revision 5 - 6/10/85
s 1,
2 2.6.8.3.2 BOLTS IN TENSION solving for the force in tension on the bolt 'due to the
'g' component using ORNL-NSIC-68 P.37 Fomula (2.7) the z.inimun bolt area for tensile is:
A
. FkV + FG 4 FF m.
gg Where FW = Tension on the bolts due to the decelerating drop force FG = Tension on the bolts due to the gasket using Tsg or Foc, whichever is greater Where:
Fsg = Tension due to gasket seating Foc = Tension due to maintenance of a tight seal on the gasket Fp = Tension due to internal pressure at reduced atmospheric pressure sa = Ultimate strength of the bolts Using ORNL-NSIC-68 P.36 Formula (2.4), the tension on the bolts due to the drop (FW) is found to be l
ThV = W (2Ng) htere:
W = cask lid and contents weight = 29,462 lbs.
cl Ng = "g" loading due to the drop = 9.375 Therefore:
ThV =
29,462 12 (9.375)]!
0 ThV =. 552.413 lbs.
Using ORNL-NSIC-68 P.36 Formula (2.5), the tens.bn load due to gasket seating (Fsg) is found to bet i
Fsg = b7 dy hteres l
d = Mean diameter of the gasket, in = 77.25 l
y = Minimum yield design seating streng'for self th (ASPI section VIII, Table VA-49.1 (1974) i sealing type gaskets (Neoprene), Ib/in2=0 l
b = Ef fective gasket seating width, in = 1.875 Since the y value is *0" the Tsg value is h
negligible and can be considered "0".
I 2.6 Revision 6 8/7/85
()
I-Using ORNL-NSIC-68 P.36 Formula (2.6) to determine I
the tensile load on the bolts created to maintain a tight seal on a f 3at gasket (Foc) is found to be r Toc = bSDP Where:
m = gasket factor (ASME Section VIII Tab 3e VA-49.1)=0 b = effective seating vidth in = 3.875 d = mean diameter of the gasket in = 77.25 (See Section J.5.2) p = differential pressure, psi = 13.2 Since the n value is
- 0", the Foc value is negligible and can be considered "0".
the force due to Using ORNL-NSIC-68 P.35 (Formula 2.3) the internal pressure as a result of the case given in Section 1.5.2 yields:
(
rp = Up (d) 2
~
4 O
where:
p = dif ferential pressure across the gasket psi = 11.2 d = mean diameter of the gasket, in = 77.25 Fp = if(11.2) (77.25) 2 4
g Fp =
52,500 lbs.
Substituting the derived values into the Formula (2.7) for the r.inimum bo3t area it is found to be:
AM = FWV 4 Fp sa Where S,a = Ultimate tensile strength of the bo3tr (A320-L7a from Table 1.3.1) = 125 K pri.
l l
2.6-19 Revision 5 - 6/10/85 l
h Therefore:
g,(552,500 + 52,500) lbs 125,000 lb/inZ b
AM = 5.76 sq. in.
Evaluations for the 3/4" bolts yields NB =
Where:
N = number of bolts required B
Amin = minimum bolt area due to tension
= r t Area of the bolts =.34 AB Therefore:
5 NB"
= 16.9
(,
NB=
17 bolts Since the cask uses 36 - 3/4" bolts, the lid will remain in place during the drop.
g Check load / bolt:
52,500 + 552,500
= 16,806 lbs yb 6
6
= 49,429 pai Tensile stress
=
9 From ORNL-NSIC-68, Stress should not exceed the yield strength g 50%
of the ultimate strength F.fU/2 = 62,000 psi b
FS =
1.26
=
49 Thus, 36 bolts is adequate with a 1.26 safety factor.
Check local bending of 2" thick flange of lid near a bolt.
6 6(1 g06)
= 25,209 psi bending stress in /,
f
=
=
g 1.19 (F.S.) yield =
=
Revision 6 - 8/7/85 h
2.6-20
(
Check elongation of bolt due to tensile load PL 16,806 (2.75),
0.005 in A, AE 0.34(28.5 x 10
=
Rotation at edge of plate (Roark & Young Table 24, case 10)
)g52,E 3
2,
,333,4 p,i ga q=
g
,8D(1+ )
Et3-28.5 x 10 (2)3 7
6
= 2.09 x 10 D = 12(1-g) 12(1.34) 133.4(39)3 _
8(2.09 x 10')(1.3) a 0.0364 radians a
(2.1')
NOTE: This rotation assumes no restraint from bearing of lid flange on the outer shell extension. This effect would reduce the plate edge rotation.
2.8.8.1.3 Bolts in Shear O
The plug portion of the lid has a radial clearance less thab that of the g
lid bolts clearance holes, preventing contact of the lid with the closure bolts during the hypothetical drop conditions which would put a shear load on the closure bolts.
2.6-21'
' Revision 6 - 8/7/85 O
2.6.8.1.3 Conclusions h
Since all the damage will occur in the toroidal segmented ring and the bolts are sufficient to retain the lid, 6
no release of radioactive contents will occur due to direct or indirect damage in the (1) one foot corner drop.
2.6.9 Compression The AP-300 cask w6ighs in excess of 5000 Kg.
Therefore, no compression load was considered.
2.6.10 Penetration The regulations in 49 CFR 173.465 (c) stipulate that the cask must be able to withstand the impact of a 1.25 inch diameter bar with hemispherical end weighing 13.2 lbs.
being dropped from a height ef 3.3 feet on the most vulnerable region of the cask.
The most vulnerable region of the cask is the 1.25 inch thick outer steel shell.
If the ASTM-A516 Grade 70 steel plate is assumed perfectly rigid, the kinetic energy of the falling bar must be absorbed by the shear deformation of the plate.
This is conservative because any bending deformation of the plate will also absorb energy and reduce the tendency for shear llh failure.
The energy required to cause shear can be expressed as:
Eg = KND t S3 Where:
K = ductility factor =.60 Sg= Ultimate strength in shear 27,000 psi D = Bar diameter = 1.25 in.
t = Plate thickness = 1.25 in.
Thus the energy the outer shell can absorb is:
Es= 99,400 in.lbs.
The kinetic energy of the falling bar is found to be Eb = Wh Eb = 13.2 (3.3 x 12)
Eb = 523 in-lbs.
O' Thus, the most vulnerable part of the cask will not be penetrated by the falling bar.
2.6-22 Revision J
. 1-n
~
.'2.7' Hypothetical Accident Conditions-1 The hypothetical accident conditions need not be considered for the AP-300' cask, when it is used to transport greater than 4
A quantity LSA waste packages, i
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THERPAL EVALUATION s
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3.0 THERMAL EVALUATION 3.1 Discussi n O*
The packaging is designed to safely contain B-type non-fissile material under the required normal and accident conditions.
The thermal analysis of the cask under the conditions outlined in 10 CFR 71 is described in this section.
These conditions include:
ambient temperatures, heat, and the hypothetical fire accident.
The only thermal limitation on the cask contents is that the maximum internal heat generation will not exceed the decay heat of 20 Ci of Co-60.
g Co-60 releases 2.5 Mev per disintegration. The decay heat released by 20 Ci of Co-60 is:
O
-13 20 Ci x 3.7 x 10 dis x 2.5 Mev x 1.602 x 10 watt-sec sec-Ci dis Mev 0.296 watt
=
Duringtheg00*Ftemperatureconditionwithaheatloadof 400 cal./cm over 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a maximum internal temperature of 250*F and a pressure of 19.3 psia is expected.
This is well below the 600*F and 100 psia design conditions for the primary containment.
The maximum suface temperature of the cask for the 100*F temperature, is 165'F.
This is below the 180*F v
maximum accessible surface temperature allowed by regulations and, therefore, cask access will not be limited by a barrier during shipment.
There are no fluids used in the cask, and therefore, the limiting cold condition is -40*F, with no decay or other heat load.
l The cask is designed to withstand the combined drop, puncture and fire accident conditions without releasing any of.its contents.
The cask is protected from the fire accident by an external fire shield which maintains the'1ead shield below its melting temperature during and following the fire.
Calculations of the cask response to the hypothetical fire accident indicate a maximum internal bulk temperature below 500*F.-
At this temperature the contents are below the temper-atures which would cause any physical changes to occur.-.
similarly, the lead will not experience temperatures which would cause it to melt.
Thus the shield integrity to reduce the gamma. dose rate is assured.
l l
The maximum internal cask pressure corresponding to the
~
calculated internal temperature during the fire accident is less than 12 psig.
Thus, any radioactive contents will be i
' O retained in the cask under the fire accident condition.
3.1-1 Revision 5 - 6/10/85
J 3.2 Summary of Thermal Properties of Materials.
f't The thermophysical properties of -the materials of construction
'd of the cask are presented in this section.
For the Steady State Thermal Calculations Material (Btu /hk-Ft*F)*
(Btu / b
- F)*
Carbon Steel 26 0.11 Stainless Steel' 10 0.11 Lead 19.5 0.03
- John H. Perry, Chemical Engincering Handbook, 5th Edition, McGraw Hill 3.3 Technical Specifications of Components This section contains a description of the technical specifi-cations and limiting conditions of those components that would be affected by the temperature reached during the fire or whose performance would be compromised by these high temperatures.
kT Two key items are the closure assembly and pressurized vent
/~
seals.
These seals are made from Johns-Manville " Red Devil" material, with a continuous operating temperature limit of 700*F.
1 l
l 3.2-1
3.4 Thermal Evaluation for Normal Conditions of Transport 3
kJ The effects of the normal thermal conditions of transport have been determined by analytical methods.
No model test will be made and there will be no thermal test of the bond between the lead and the shells.
The two extremes of thermal loading for the normal conditions are:
(1) isothermal at -40*F; and, (2) a decay heat load of 150 w with ambient air of 100 *F and 2
a heat load of 400 cal /cm over 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The bulk coolant in the cavity is air.
3.4.1 Thermal Model The maximum heat load to be carried in and dissipated by the AP-300, 150 watts or 512 BTU /hr, is very low.
Therefore, a very simple model was used.
It was first assumed that the cask with a full load was exposed to an ambient temperature of 80*F with no outside heat load.
It was then assumed that the same fully loaded cask was exposed to an ambient temperature of 100*F with a total incident heat load over a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period of 400 g cal 1475 BTU or based on the cask suface area added to 2
em cm the maximum 150 watt load.
Using the Cask Designer's Guide, by L.B.
Shappert - ORNL-NISC-68, the surface temperature of the cask necessary to dissipate the heat load, was calculated, using p-trial and error as suggested in the reference.
Using the properties of the cask materials, the temperature profile across s
the cask was also determined.
For heat removal from cask surface and to determine the cask surface temperatures, the following relationship was used.
A(T
-Tl 07=ht s
a Where:
OT = total heat transferred - BTU /hr h
= total heat transfer coefficient - BTU /hr - ft2
- F t
2 A=
surface area of cask for heat transfer - ft T=
surface temperature = *R s
T=
ambi$ent temperature = *R a
and:
ht = he +hr 2
h
= convective heat transfer coefficient = BTU /hr-ft
,.7 c
2 hr = radiation neat transfer coefficient = BTU /hr-f t
.p 3.4-1
hc = C(T -T,)
=.19(T-laI s
s
~ [Ta\\ 4 I Ts hr = 0.173 6 dOO/
\\100/. u 1
(Ts-Ta)
C= Constant Given by ORNL-68 For heat transfer through cask and to determine the temperature profile,the following relationship was used.
Q (t) kA AT T
k" t
kA QT = Total heat transferred =
BTU /hr k
thermal conductivity
BTU /(hr-ft2)(*F/ft) 2 A=
area through which heat is conducted = ft t=
thickness of solid = ft a T=
temperature drop across conductor 9
To calculate the temperature drop across the cask body, it is assumed that heat transfer is by conduction and that the area, across which it is conducted, is the average area of each solid substance, i.e. the outer shell, the inner shell and the lead, respectively.
4.3.1.1 Ambient Temperature 80*F If it is assumed that the ambient temperature is 80*F and that 150 watts or 512 BTU must be dissipated from the surface of the cask, the surface temperature for these conditions can be determined by trial and error.
U
= 512 BTU /hr T
A= (83.625) (96)T = 175f t2 144 T
= 540*R a
Assuming:
T,*R h
h h
AT Q(BTU /hr) r e
t 545 0.88 0.32 1.20 5
1050 543 0.88 0.27 1.15 3
603 542 0.88 0.24 1.12 2
392 g
The temperature at which the cask can dissipate 512 BTU /hr is about 82.6*F, by interpolation.
3.4-2
(\\ ')
To determine the A T through the conducting substances the average areas are as follows:
Area of outer shell =
(83.625 + 81.125)
)T= 172.5 ft 2 Area of inner shell =
(76 + 77)'
(87.4)_ T =
145.9 ft 2 2
144 (81.125 + 77)
(87.4) 7
=
150.8 ft2 Area of lead
=
2 144 1
A T outer shell = (512 BTU)
(1.25 ft) hr 12
= 0.01*F
[26 BTU (172.5 ft2) 2 hrft 1
(512 BTU
- 0. 5 _ f t'l A T inner shell
=
j hr 12
/
- 0.01 *F
[10 BTU h (145.9 ft2) n 2
l hrft j,7 H
)
512 BTU 2.0625 ft A T lead
=
0.03 *F
=
19.5 BTU l
(150.8ft2; 2
(hr - ft )j 7R) i I
The resulting tecperatures of the cask shells and lead are:
82.61*F l
=
outer shell 82.65'F 5,.
Tinner shell
=
<, : +.
82.64*F
-Y,
T
=
lead 1
.?
I '
C)
N. (.
3.4-3
The temperature of the inside shell surface is almost the g
same as the outside surface, therefore, the total heat transfer coefficient can be interpolated from above to be 2
about 1.13 BTU /hr ft
- F.
The heat transfer area to the inside shell ist r-A= (76)(82) ll 136.0 ft.2 ft
=
144 T = S12 BTU /hr
= 3.3*F (136 ft2) (1.13) BTU,
hrft'*F The temperature of the air inside the cask Will be 86*F.
The surface temperature of a container inside the cask can be determined similarly.
If it is assumed that the inside container is 75 in. OD and 80 in, high the surface area is:
A=
(75)(80)lf 2
130.9ft
=
144 512 BTU /Fr 3.3 *F 6T=
ggg
=
(130.9 ft ) (1.20 BTU /hrft 'F)
The maximum temperature of the inside container surface is less than 90'F.
3.4.1.2 Anbient Tempturature 100*F If it is assumed that the ambient temperature is 100*F and that, in addition to the decay heat, 122.8 BTU /hrft2 must be dissipated from the surface of the cask, the surface temperature for these conditions can also be determined by trial and error.
O
= 512 B U 2
T
+ 175 ft (122.8) BTU
= 22,000 BTU /hr 2
hr ft 2
A=
175ft T, = 560*R O
3.4-4
~_
4 j%
? *,:
e
)
. V Assuming:
J*
/-
r c
t j
Q(BTU /hr)
T,*R h
h T
i l
'?)0
'625 1.15 0.76 1.91
, 65 '
21725 630 1.17 0.78 1.95
- 70 0
23890 i
The temperature at which the surfst;e c.an dissipate 22,000 BTU /hr is about 165.6*F by interpolation.
The AT across the ca'sFTomponents can be determined as follows:
(22,000 BTU /hr)fl.25 ft AT
=
0.50*F outer shell
\\ 12
=
_(26) BTU
["
2 172.5 ft hr ftd/'F/ft (22,000 BTU /hr) 2.0625 4Tlead ft
=
1.29'F -
=
2 (19. 5) BTU (150.8 ft )
(
hr ft
- F ft s
22,000(BTU /hr) 0.5 ft a
Tinner shell "
~TI
= 0.62 tr 2
(10) BTU (145.9 ft )
f, a"
hr ft27 s
ft The resultiNg temperatures of the cask shells and lead are:
Touter shell =
166.1 *F 167.4 *F-T
=
lead Tinner shell =* 168.0 *F i
The total heat transfer coefficient at the inside shell.
surface can be assumed to be 1.94 BTU 2
hr ft *F l'
s A T = 22,000 BTO'/hr 83*F
=
(136 ftd) (1.94) BTU _
hrftF
+
The temperature of the air inside the cask will be 250*F.
The cask contents convict of dry substances which will not I
be.affected by the cask temperctures'under these conditions.
~,
i/
+
7 7
3.4.2 Maximum Temperatures e
The temperature distribution within the cask under normal operating conditions is almost uniform in all material regions with the only significant temperature difference occuring between the surf ace of the outer shell and the ambient air, and the surface of the inner shell and the air inside the cavity.
The results at 100'F ambient temperature, 150 watts internal heat generation and solar load specified in 10CFR71 for normal operation are:
Outer shell surface temperature 166*F Inner shell surface temperature 168'F Air temperature in cask 250*F 3.4.3 Minimum Temperatures This is the isothermal condition at -40*F.
3.4.4 Maximum Internal Pressure The condition of maximum internal pressure occurs when the cavity bulk coolant is at its highest temperature.
This occurs during the condition of 100'F ambient taperature, solar load a decay heat of 150 watts.
Internal pressure will be a function of the average temperature in the cavity.
Based on the results described in 3.4.2, the maximum air temperature in the cask is 250*F.
The initial loading conditions were assumed to be 80'F and 14.7 psia.
The pressure in the cask can be determined.
P2=T2 y
y = (710)*R(14.7) psia / 540*R P /T
's/
4.6 psig P2 = 19.3 psia There will be no effects due to phase change, fluid expansion, gas generation, or chemical decomposition.
3.4.5 Maximum Thermal Stresses Within the range of normal operating conditions, the worst combination of temperature distribution that occurs to produce thermal stresses, happens at the two extremes of operating conditions.
O 3.4-6
.. - -. ~ -
At the ambient condition.of -40'F, no internal heat generation or
/N ' solar load, the packaging is isothermal at -40'F.
This condition
(_)
causes-thermal stresses between the lead shield and the inner shell because of the greater contraction of the lead shield, discussed in S2ction 2.6.2.
No other components have thermal stress problems at the isothermal'-40*F condition.
At the maximum temperature condition there may be some radial inter-ference between the shells and' the lead, but this would be equal to or less than the thermal stress produced at the cold condition.
The only other thermal problem may be, caused by the higher temperature of the inner shell vis a vis the outer shell.
The calculations indicate a temperature difference of le ss 'than 2'F.
3.4.6 Evaluation of Package Performance for Normal Conditions
-of Transport The expected temperature range of the components is between
-40*F to 170*F.
This is acceptable for the-Red Devil seals.
No other materials or components have operating. temperature limits in this range.
The thermal stresses are calculated in Section 2.6.2 for the interferences.
()3.5
~
Hypothetical Accident Thermal Evaluation The hypothetical accident'cond'itions need not be considered for the AP-300 cask, when it is used to transport greater than A quantity LSA waste packages.
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4'.0 LCONTAINMENT O
- %)'
This chapter identifies-the containment provided by.the AP-300 cask and dis. cusses the containment provided by the AP-300 cask
.under normal' operating. conditions, during cash i an ~ vt and under: hypothetical.. accident-conditions a n b 'FR Part 71,'Subpart F,'" Package and Special Form i-t y 4~.1.
Containment Boundary This section. identifies the c uirrtet ocu Q G Vrovided.by the AP-300 cask.for material
, n,apo21 4 id.sp.Leesiies the design conditions 1to assure s?d' % " of adequate contalnment.
'4.1.1.
Containment Vessel
-Thefcontainment. vessel _-for.the.AP-300 cask is designed as a free'standingEpressure vessel in, accordance with Section JVIII of the ASME B&PVC and consists of_the following elements shown in Figure'4-1 A.
The inner vessel B..
Parts of.the~ lid h
C.
The lid gasket I
l The inner vessel consists of:
1.
The inner ~ shell.(B-2)' which.is 0.5" thick andi has a' nominal inside diameter'of 76".
~2.
The' bottom plate (B-4) which is'_0.5_" thick and has a: diameter of_.76".
1 l
3..'The bolt ring (B-5)-which:-is 2.25" thick-and has i
a' nominal: inside diameter. of' 76".:
1 The-parts'of-the lidLthatl form part of the containment boundary include:.
~
11.--
The : lower plate of the : lid f (L -2) _ which!is - 0.5"-
thick:and-has a. nomina 1Ldiameterfof.76".
l2.,LTheilid plale ring,.(L-3)-which is 0.5N thick,
- /6;24" high and?has-fa4 nominal ~ diameter of176".
i
[
3b -Theiupper lid! plate'(L-1)<which.isl2.0" thick and has'an outside diameter:of181-1/8".
.The!1idl. gasket hasfa nominaliinside' diameter of'76".
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4.1.2 Containment Penetrations
-There is only one. location in the lid which penetrates primary containment of the AP-300 cask.
The penetration is closed during shipment of the cask.
The penetration is used to verify the sealing capability of the gasket before cask shipment as outlined.in section 1.1.
After seal verification, the penetration is sealed with redundant hex socket threaded bolts.
4.1.3 Seals and Welds Red Devil gaskets are used to seal the lid and tes t penetration.
The gasket material is a compressed proprietary Johns Manville formulation that exhibits good resistance to temperatures up to 370*C.
All welds are full penetration welds in accordance with the Cask Designers Guide by L.B. Shappert and the ASME B&PV Code,Section VIII, Division 2.
4.1.4 Closure A single closure assembly is provided for the AP-300 cask, It is held in place by 36-3/4" x 2-3/4" UNC 2A bolts.
The bolts are torqued to 110 ft. -lbs. to provide' sealing for s
10 psig internal pressure.
4 4.2 REQUIREMENTS FOR NORMAL CONDITIONS OF TRANSPORT 4.2.1 Release of Radioactive Materials The radioactive material that will be transported in the ANEFCO AP-300 will be solids, such as dry solid activated metallic waste, dry borosilicate material containing fission products and enclosed in its own container or similar materials'containing radioactive fission or activated products.
The maximum weight content will not exceed 20,000 pounds and will generate less than 150 watts.
Sections 2.6 and 3.4 demonstrate that, under normal transport conditions, the components-of the ANEFCO~AP-300 cask have the design capability, with margin, to retain the design solid' load.
The contents will have no radioactive gases.
Therefore, no release of radioactivity is anticipated during normal conditions'of' transport.
~V (V
s L
4. 2-l ~
4h 4.2.2 Pressurization of Containment Vessel The contents of the containment vessel will be only solids, with no possibility 6f gas release.
The only conditions for pressure formation above. ambient atomspheric pressure would be exposure of the cask to 100*F temperatures in the shade.
Assuming a maximum internal temperature of 180*F the maximum absolute pressure within the containment v'essel, assuming that it is loaded at 70*F - 530*R, is:
2 640 14.71b/in Y
= 17.7 psia 530 rhe structural analysis of the cask in Section 2 demonstrates the capacity of the AP-300 cask to withstand an internal pressure of 3 psi gauge.
4.2.3 Coolant Contamination There will be no coolant used in the AP-300 cask.
4.2.4 Coolant Loss There will be no coolant used in the AP-300 cask.
O 4.3 Containment Requirements for Hypothetical Accident Conditions The hypothetical accident conditions need not be considered for the AP-300 cask, when it is used to transport greater than A quantity LSA waste packages.
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5.
SHIELDING EVALUATION i
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5.0 SHIELDING EVALUATION 5.1 DISCUSSION AND RESULTS Type B - Curie Content The cask will handle a-maximum of 20 curies of Co-60 shown in Table 5.1,
. equivalent.
The contact' dose rates, ~
are. 8.0' and 9.2 mR/hr which is lower than the 200mR/hr contact rates allowed in 10 CFR 71.47.
-TABLE 5.1
SUMMARY
OF MAXIMUM DOSE RATES (mR/hr) 3 Feet from Packace-Surface Surface-of Packace Side Top Bottom Side Top Bottom Nor:nal Conditions Ga:ra 8.0 9.2 9.2
<8.0
<9.2 49.2 Neutron no neutron -dose rate Total
'8.0 9.2 9.2
~< 8.0
.< 9.2
<9.2 Hypothetical Accident Conditions-8.0:
9.2
- 9. 2.
<8.0
<9.2
<9.2 Neutron
'no neutron-dose rate Total
'8.0.
9.2 9.2
<8.0
<9.2
<9.2-10 CFR Part.71 Limit'~-200 200 200 1000 1000 1000 5.2 SOURCE SPECIFICATION
- 5. 2. l' Gamma Source
.For. design and analysis purposes, the activity concentration of the--radioactive material.is to be.' considered 100% Co-60,
'O
=a it e=erer, t
- 1 25 aev-
' E.Myerage)
=. ( 0. 5 x 1.17 'MeV) ' +1 ( 0. 5 x 1. 33 MeV) ' = l. 25MeV l.'
j
~
5.1 - -
(
5.2.2 Neutron Source' The AP-300 will not carry neutron sources.
P' 5.3 MODEL SPECIFICATION Ro = 37.5" Geometry vold Fe Pb Fe l
f l
(
I T
, _ i.
a a
A
-0.5' 1- 0.5" 2'
1.25' 9, - Sz Q
5.
3.1 DESCRIPTION
OF THE RADIAL AND AXIAL SHIELDING CONFIGURATION Case fl, Dose rate at the side wall (P ' contact) 1 0 = 3 7. 5 "= 95. 25 cm Where:
R h
= 7 9. 5 "= 2 03. 2 cm Void space = 0.5" = 1.27 cm Inner shell thk. = 0.5" = 1.27'em (Fe)
Lead fill = 2" = 5.08 cm (Pb)
Outer shell thk. = 1.25" = 3.18 cm
_(Fe) a = 4.25" = 10.80 cm z = Self-absorption distance 2
Volume of liner = D o h = 5.79 x 106 cm3, R
5.3.2 Shield Regional Densities The shield material provides shielding only for carna sources.
The densities of the naterials are listed belot.:
3 Steel = 7.87 gm/cm
,.s
'id -
3 Lead
= 11.34 om/cm 5.3-1
5.4 Shielding Evaluation f-In order to determine.the value of "z",
self-absorption distance, which is intrinsic to.the source material, the following calculations have to be performed:
a = 10.80 cm; Ro = 95.25 cm i
a = 10.80cm = 0.113; Ro 95.25cm The source material is assumed to behave as carbon, which has a mass absorption coeff. Jks) of 0.06 cm-1 for a gamma energy level of 1.25 MeV (Eg)
So:
j's (a + Ro) = 0.06 cm-1 (10.80cm + 95. 25cm) o
= 6.36 From Rockwell, pg. 362, with:_a = 0.13; and i
Ro b' s (a + Ro) = 6.36; m = 1.1 j
The linear attenuation coefficients jg) of the shielding O
meterie1 ere=
M Fe =.0.391 cm-l[ Pb = 0.68 cm
~
and the thicknesses are:
tFe = 4.45cm and t b = 5.08cm P
NOTE:
The thickness of the liner. has not been incorporated i
in these calculations, since neither the value of l
the thickness is-known,-nor the material of construction.
The void space (air) has also been neglected.
So: the attenuation factor; by is:
b.= jui ti y
Where:
4l i = linear attenuation coefficient ^of-the l
j "i" material (shielding).
g = thickness of the "i" material.
t LD 5.4-1
by= (0.391 cm-1) (4.4 5 cm) + (0.68 cm-1) (5.08 cm) by = 5.2 Now with _a_ and by, find (1/mpsZ, from Rockwell, pg. 363 Ro (1/m[ sz = 3. 0 (3. 0) (1.1)
= 55 cm
- z=
(3.0) (m)
=
ps 0.06 cm-1 Determination of Angle 0 I
+z a-I i
e h
}- -
P 3
l
- 2 7.-- %
O*&"
g 2
W h
a+z 100.97 cm
1.534 tan O
2
=
a+z (10. 80cm + 55cm) g
-1 0 = tan 1.534 = 56.90*
Calculation of F(0, b ) (Rockwell, pg. 386) 2
= 5.2 + (0.06cm-1) (55cm)
O = 56.90*; b2 = by +[ sz b2 = 8.5; and F (0, b ) = 8 x 10-5 2
Calculation of build-up factor B (EgA x)., For design J
purposes the build-up factor will be the one of the outermost layer; t = 3.18 cm.
1 e
- 8[
+A2 1[
T Al
- 1 -A -
B
=A 2
(Fe)
From Rockwell, pg. 418.
9 5.4-2
5 i
i A1 = 9.4-g1 = 0.0825 A2 = -8.4e(2 = 0.0525 q
O (0.0825)(0.39)(3.18)
(-0.0525)(0.39)(3.18)
B,= (9.4)e
-(8.4)e y
Bye (Selected) = 2.54 5.4.1 Gamma Flux 4
calculation of ganna flux at P1 per curie
- d = B SvRo2 [F(9)b2) }
N 2 (a+z) cmZ-sec-curie Sv = Volumetric source strength /cm3
[
Sv =/Ix3.7x1010 =
N Volume cmJ-sec-curie The volume of the liner is: 5.79 x 106 cm3 So:
Sv
= 2 x 3.7 x 1010 = 1.278 x 104 N
5.79 x 100 cm3-sec-curie (2.54) (1.278 x 10 ) (95.25) 2 (8 x 10-5) 4 nade F
=
=
N 2 - (10. 80 + 55) 2
[
1.79 x 10 l
cmd-sec-curie Determination of dose rate / curie at P1 (contact) i (1.79 x 10 ) (2.22 x 10-3) 2 Dose Rate (mR/hr/ curie)
=
Curie j
Dose Rate = 0.4 mR/hr/ curie Curie For Maximum quantity of curies Dose Kate = 0.4 mL
- 20 Ci-8 mE hr/Ci fir Case _#2.
Top & bottom shielding calculations
- 1. ' The gamma flux (pg) is = 2.1 x 102
[
cm'-sec-curie
- 2..The dose rate per curie = (2.1 x 102) (2.22 x ' 10-3)
=
0.46 mR/ curie hr
()
3.
For Maximum quantity of curies dose rate _(mR/hr =' O.46 mR curie x _ 20 Q, l
= 9.2 mR/hr_.
l' nw-
+w--+c
-~ey.-upwy ep.,e-e-ye-
5.4.2 Free Drop Gamma Shieldine hn end drop of a cask in which the 3ead is not bonded to gg) the steel she31s, can cause the lead to settle, thus creating a void in the end opposite the impact end.
According to Shappert (ORNL-NSIC-68) the change in 3ead height is:
[h H =
RWH (P2-rd) (ts 6 s + R(L)
Where:
R = outer radius of 3ead = 40.5 inches r = inner radius of Jead = 38.5 inches
- 4 W = weight of cask p3us contents = 66,720 lbs.
3.25 inches ts = thickness of outer steel she))
=
6s = dynamic f3ow stress of steel shel) = 60,000 psi (L = dynamic f3ow stress of lead = 5,000 psi H = height of drop = 32 inches () ft)
Thus: H=
(40.5) ~(66,720)
(3 2) 4 1 (40.5) 2-(38.5) 4] [ (3.25) (60,000)+ (40.5) (5,000) ]
~
4 g = o,74 inches The geometry wil3 be:
Ring
_J
, 3 7{...
0 inches y a
i t
Source Liner 80' 87' l
)
,bA v
v pb As a result, the contact dose rate wil] not be affected 4
by the.0.74" lead s3 ump; since there wi]I not be a source window without Jead shielding.
The cask is designed to withstand a lead slump of_6.71".
9 Revision 4 - 4/15/85 5.4-4
O 6.
CRITICALITY EVALUATION a
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- 6. 0 ' Criticality Evaluation No material which is subject to-criticality conditions will
-1 transported in the AP-300 cask..
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7.
OPERATING PROCEDURES
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-x-7.0 OPERATING PROCEDURES 7.1 Procedures for Loading the Package i.
7.1.1 PURPOSE The purpose and intent of this procedure is to define the safe handling and the proper radiological controls necessary for receiving, loading and dispatching of the ANEFCO AP.300 i-cask in a safe and efficient manner.
I 7.1.2 Special-Preparations for Loading 1.
Insure the cask lid gasket is in good condition prior to shipment.
2.
Insure truck / cask tie-down devices are secure and in proper working order.
}
3.
Caution: Always use a calibrated hand torque wrench
! n.
only to bolt the cover, according to the torque
!U procedure (Attachment "A")
to prevent damage to j
bolts and cask threads.
l 4.
Caution: A potential radiation streaming, hazard exists when the cask is loaded with the cask head z
l not torqued down.
Use appropriate care, and use j
shielding apparatus when necessary.1 i
- 5.. If, while detorquing the cask head, it is determined i
tlat the head has backed off unevenly'and is einding, the head must be fully retorqued-and the detorquing operation restarted, Extra care should be
+
exercised to ensure that-the head backs off evenly.
6.
CAUTION: It is recommended the cask lid gasket be replaced every-6th shipment.
i NOTE: This should notJpreclude replacement of the gasket.if any. imperfections should' appear or if it warrants the replacement due to. failure during leak testing.
t 1
7.1-1 L
__,-.._--..m
.-.~.__..,,_.._m.-,.._,_.._,,_,-,,-,-----..._...,
7..
If any abnormalities at discovered with the cask, cask head, head gasket, or the cask equipment, notify ANEFCO at the Ridgefield g
Office (telephone (203) 431-3358) obtain advice on continued use W
of the equipment and follow such advice.
8.
Caution: Lif ting assemblies for the AP-300 cask should be 4-59" long wire chokers with a minimum rated capacity of 80,000 lbs as per federal specification RR-W-410.
The wire cables must always be at an angle of 90* from the horizontal during lif ting operations.
9.
Caution: Lif ting assemblies for the AP-300 cask lid should be 4-36" minimum length wire rope slings with a minimum rated capacity of 12,000 lbs. as per federal specification RR-W-410.
7.1.3 Loading Procedure 1.
Ensure that a copy of the check list for this procedure is on hand for use during all phases of cask handling.
2.
Upon receiving the empty AP-300 cask on site, have radiation pro-tection perform a radiation survey of the cask and trailer.
3.
Visually inspect the trailer and cask cover for evidence of damage.
If any is discovered, contact ANEFCO, at the Ridgefield Office (203) 431-3358 for advice on continued use of the equipment.
4.
Position cask and trailer into handling bay.
O 5.
Set trailer brakes and place wheel chocks fore and aft of the wheels.
6.
Detach (4) four tie-down cables from the cask side. Place the main I
pin back into the cask lift / tie down point to enable its use as lifting point.
7.
Remove canvas AP-300 cask cover, fold and place in clean area away from loading area to insure it does not become contaminated.
8.
Have radiation protection perform a survey of the cask to complete their arrival survey records.
9.
Visually inspect the surface of the cask for general cleanliness and evidence of damage. If excessive road grime is present, a wash down of the cask surface prior to moving it into the loading bay may be necessary (optional). If evidence of damage is discovered, contact ANEFC0 at the Ridgefield Office for advice on continued use of the
. cask.
NOTE: Step 10 is utilized only if cask must be removed from trailer to facilitate loading.-
10.
Attach lifting assembly (4-2 " shackles and four equal length wire rope 8
slings with a minimum rated capacity of 80,000 lbs) to the AP-300 cask lifting / tie down eyes located on the side of the outer shell of the cask body. The cask empty weight is 46,720 lbs.
7.1-2 Revision
'8 10/2/85 m _
~
'i I'.-
11.
Place poly sheeting or equivalent onto bay. floor insuring an area O~..
large enough t'o place both cask and lid onto plastic (84 sq.ft.)
(optional).
12.
Caution: Using a hand torque wrench and 5/8" hex setscrew-bit J
-socket, loosen cask lid bolts. Using r6tational order.as shown in AP-300 cask " bolt torque procedure"(Attachment'A), loosen each bolt 1/16 turn per pass.
Continue until all of the bolts'are loose, indicating that.the lid. pre-load has been fully relieved.
NOTE:
This technique helps assure that the cask head backs off the-cask flange in an even and : parallel manner.
It is important that each bolt be turned by the same increment during a pass..Should the cask back off unevenly, it may bind, making it necessary to retorque the lid bolts and start over again.
13.
Remove all 36 of the lid bolts, inspect.each bolt to insure screw i
threads are undamaged,and stow the lid bolts appropriately. Bolts having damaged ~ screw threads must be appropriately repaired or replaced.
Inspect bolt holes to assure that bolt rotates freely.
Remove 4-lk" bolts from top of lid and install 4-lk" eye bolts in g
their. place, 14.
Attach lid lifting assembly to'11d lifting eye bolts (4-h" shackles g
and 4-36" long wire rope slings at a rated capacity of 12,000 lbs.)
Caution:
The lid' cables are to. remain. slack and bear no load except when the cask lid is being removed and replaced.
15.
Carefully raise the crane hook so that the 4 lid lifting assemblies become taut simultaneously. Insure that_the-cask lid lifts' evenly off the cask. -Lift the AP-300 cask' lid until there is a large enough-gap between the body and lid to allow a radiation survey of the internal cavity of the cask..(Both smear test and dose rate assess-ment).
/16..Have radiation protection ' perform the necessary surveys.
- 17. After radiation surveys-are complete lift the111d the' remaining
~
~ distance needed-and place onto plastic-previously' laid on bey floor-in step #6..
If the crane does not have-to be freed for'other duties, leave the cask lid suspended in a convenient location..
- 18. l Inspect cask ~ gasket to insure _it. is in good. condit! ion and all bolt -
1 holes.line up correctly.
If. any1 imperfection' is discovered,-
. contact ANEFC0 at.Ridgefield Office,-(203/431-3358) for. advice on-
. continued.use offthe equipment..
I19.
Inspect'the cask cavity to insure that no water is present..All
~
water.in; cavity must be removed before the liner:is installed in'
.I cavity. J Cavity walls must be ; dried, e.g.: by swabbing walls or other l
1means.
7.1-3 Revision.i5!- 6/10/85 :
L
(,
m_
20.
Perform radiation surveys of the liner to be loaded both dose rate and smear test. Decontaminate any external loose contami-g nation exterior of liner.
21.
After radiation surveys are complete and all external loose contamination is removed, lift and insure liner bottom is free of contamination, then place liner into the AP-300 cavity.
22.
Place any necessary shoring around liner if required to prevent liner from shifting during transport.
(4 1" shackles and 4-25" long wire rope 23.
Attach lifting assembly 5
g slings) with a rated capactiy of 12,000 pounds to lid lifting eye bolts located near the center of the cask lid, (if removed)...
24.
Retrieve the cask lid from its temporary placement and position it over the top of the cask. If necessary, level the head to insure proper fit.
25.
Lok'ER the cask lid slowly until it is approximately 1" down within 1
the outer cask body. Align lid seal block on lid with grooved recess in cask body.
26.
STOP L0k'ERING and make necessary adjustments to the cask lid until the bolt holes are precisely aligned up.
27.
Lubricate and install finger tight bolts 1, 2,3, and 4 (refer to g
AP-300 " Bolt Torque Proceudre" drawing Attachment "A" for W
location of bolts).
28.
Resume L0k'ERING the cask lid slowly, as the cask lid seats. OBSERVE that the lid lifting assemblies slacken simultaneously. Failure g
of this to occur may indicate that the cask head is_. misaligned.
Remove lid lifting assembly. Remove 4-lk" eye bolts and replace with 4-lk" hex bolts.
NOTE: Decontamination activities (if required) may proceed simultan-iously to torquine Caution: Radiation streamin.g may emanate from the lid to cask gap. Use appropriate care, and use shielding apparatus when necessary.
29.
Have radiation protection survey the dose rate of the outer surface (of the cask to develop stay time limits during torquing). Radiation protection should also perform swipe test of the cask's outer surface i
to determine if any loose contamination is present. External radiationdosesandsurfacecontaminationshallconformwithh71.47 andpl.87(i) respectively of 10 CFR. 30.
Lubricate ~using a suitable lubricant, and install the rethaining 32 bolts finger tight.
31.
Caution: Using a hand torque wrench only, torque the lid bolts to 22 ft. lbs. in the sequential order shown in AP-300 cask
" Bolt Torque Procedure" drawing (Attachment "A").
32.
Caution: Using a hand torque wrench only, torque the lid bolts to 44 ft, lbs. in the sequential order shown in AP-300 cask
" Bolt Torque Procudure" drawing (Attechment "A").
7.1-4 Revision 5 - 6/10/85
?-.
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_ 33.,
Caution: Using a hand torque wrench only. torque the lid bolts to V
66-ft. lbs.31n the sequential order shovn in AP-300 cask
" Bolt Torque Procedure". drawing (Attachment "A").-
4
-X
. 34. : Caution: Using=a hand torque wrench only, torque the lid bolts to 88 ft. lbs. in.the sequential order shown in AP-300' cask-
" Bolt Torque Procedure" drawing (Attachment "A").
35.
Caution: Using a' hand torque wrench'only, torque the lid bolts to I
final torque value 110'ft. lbs. in the sequential order i
shown in AP-300 cask, " Bolt Torque Procedure" drawing L
Attachment "A".
)
- 36. 1 Caution: Using a hand torque wrench-only, use rotational tightening at 110 ft. Jbs. until all bolts are stable at final torque level: (two complete turns around is usually sufficient) as
'shown in AP-300 Cask " Bolt Torque Procedure" drawing,-
j (Attachment "A").
l
[
Steps 38, 39. and 40 are u' sed only if-cask'was f.
NOTE:
removed from trailer to facilitate loading of-i liner.
s} 37. - Install security lead wire seal.
i 38f' Attach lifting assemblies (4-2"' shackles.and~4-equa171ength wire i~
rope slings with a minimum rated'capac1ty of 80,000 lbs) to the i
AP-300 cask lifting / tie'down eyes located on the side ~of the outer shell of the cask body.:
Lift cask up 1 ft. and have 'adiation protection perform a swipe
~
39.
r survey of the cask bottom surface for externa 11y' loose contamination.
i Decontaminate-cask bottom surface'if n'ecessary.
i I$
sInspect 2 " square energy absorption. tube at bottom of cask.-
If
~
tube is cracked or overall height is. deformed to less-than 2-1/8",1 g.
-repair or replace tube. '.
+
f s
140.
_ Lift and place AP-300 cask within its' transport ring located on the trailer.
e 341.
Replace canvas AP-300 cask cover over AP-300 cask and secure at'. base.c q.
i 42.
' Retrieve tie-down p' ins.
f
.-v l
43.'
Fasten the'(4);four tio-down' cables ~to'thefcask as perfAP-300 cask'
'" Tie-Down ~ Assembly - (top view)" l(Attachement B"). ; Tighten ~ ~ tie-down -
~
assembly. Torque each belt evenly to 100;fts?lbs..
~
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~
- 7.1-5' A.c
..Rebision.81 710/2/85-
. m.-
+, - -
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d 44.
Caution: Insure that all cotte,r pins are bent over to prevent loss.
Have radiation protection gl perform final survey of AP-300 cask on trailer in preparation of shipment.
Attach the appropriate l
labeling and placards.
45.
Insure driver has all necessary forms for shipment and all documents and check lists are completed.
46.
Remove the wheel chocks and release the trailer brakes.
9.-
Perform a final cursory visual inspection of the trailer.
48.
Review the check list to ensure that no items were missed.
49.
Notify ANEFCO, Inc. (203/431-3358) transportation manager that the shipment is in route to disposal site.
7.1.4 Specific Addition to ANEFCO AP-300 Loading Procedure O
The additional procedures are intended for use when transport of ANEFCO's AP-300 cask is by vessel.
Shippers / users of the AP-300 cask when the cask movement involves transport.by vessel will comply with 49 CFR, Part 176 " Carriage by Vessel" - Subpart M - " Detailed Recuirements for Radioacti"e Materials", a copy of which is shown in Section 7.4.
i 7.1-6 I
4
~.
J O 2.2 procedures for unioadin the racxaoe 7.2.1 Purpose The purpose and inte t of this procedure is to define the safe hand 3ing and the proper radiological controls mecessary for receiving, un3oading and dispatching of the ANEFCO AP-300 cask in'a safe and efficient manner.
Preparations for Unleeding the Package 7.2.2 Prior to receipt of cask, procedures shall be-in place in I
compliance with the instructions noted in 10CFR 20.205.
I Insure truck / cask tie-down devices are secure and i
1.
in proper working order.
A3 ways use a calibrated hand torque wrench 2.
Caution:
only to bolt the cover, according to the torque procedure (Attachment "A") to prevent damage to bo3 ts and cask threads.
.o Caution: A potentia) radiation streaming, hazard exists when the cask is unloaded with the cask head 3.
Use appropriate care, and use not torqued down.
shielding apparatus when necessary.
If, while detorquing the cask head, it is detemined I
4.
that the head has backed off uneven 3y and is binding, the head must be fully retorqued and the Extra care should be detorquing operation restarted.
exercised to ensure _that the head backs off evenly.
L If any abnormalities are discovered with-the 5.
cask, cask head,-head gasket, or the_ cask equipment, notify ANEFCO at,the Ridgefield Office (telephone 203/431-3358) obtain advice on continual use'of the equipment and fo31ow such advice.
1,ifting assemblies for the AP-300 cask Caution:
6.
should be 4-equal le:xyth wire rope ' slings with a muumr.
rated capacity of 80,000 lbs. as per federal i
l,,
specification RR-W-410.
.7
' Caution: Lifting _ assemblies for the AP-300 cask Q
Jid should be 4-36 " long wire rope slings wmili iEfisimum rated capacity of 12,5,00 Ibs. as per federal The wire cables must-alwaye be specification RR-W-410.
at an angle of 90' from the horizontal during lifting g
operations.
7.2-1 l
. Revisfon --
2 - 11/28/84
7.2.3 Unimding Prcendura Ensure that a copy of the check list fcr thic 3,
procedure is on hand for use during all phases of cask handling.
Upon receiving the AP-300. cask on site, have 2.
radiation protection perform a radiation survey of the cask and trailer.
Visually inspect the trailer and cask cover for 3.
evidence of damage.
If any is discovered, contact for j
ANEFCO, at Ridgefield Of fice -(203/431e8358)
-l advice on continued use of the equipmdnt.
Position cask and trailer into handling bay.
4.
Set trai3er brakes and place wheel chocks fore 5.
and aft of the wheels.
(4) four tie-down cables from the cask 6.
Detach the Place the main. pin back into the cask side.
lift / tie down point to enable its use as lifting' point.
f Remove canvas AP-300 cask cover, fold and place in 7.
clean area away from loading area to insure it does not become contaminated.
Have radiation protection perform a survey of the 8.
cask to complete their arrival survey records.
Visually inspect the surface of the cask for general 9.
cleanliness and evidence of damage..If evidence of damage is discovered, contact ANEFCO at Ridgefield Office for advice on contiinued use of the cask.
NOTE:
Step 10 is utilized only if cask must be removed-from trailer to facilitate unloading.
10.
Attach lifting assembly (4-2" shackles and I
4-59" chockers within minimum rated capacity of 80,000 lbs.) to the AP-300 cask liftin9/ tie down eyes g
located on the ' side of the ou'tcr shell of the cask body.
~~
The cask empty weight is 46,710 lbs.
11.
Place poly sheeting or equiva3ent onto ground floor insuring an area large enough to place both cask and lid onto plastic ( 84 sq. ft. ) (optional).
O' Revision 5 - 6/10/85 7.2.2
Caution:
Using a hand torque wrench and 5/da 12.
hex setscrew bit socket, loosen cask lid bolts.
5 * *are= wr a=h *a 22' re 26= -
u=ias ro*=tiaa 2 O
order as shown in AP-300 cask " Bolt Torque Procedure" (Attachment "A"), loosen each bolt 1/16 turn per pass.. Continue until all of the bolts are loose, indicating that the lid p e-load has been fully re3ieved.
- NOTE:
This technique helps to assure that the cask head backs off the' cask flange in an even and parallel manner. It is important that each bolt be turned by the 4
same increment during a pass.
Should the lid back off unevenly, it may bind, making it necessary to retorque the lid bolts and start over again.
13.
Remove all 36 of the lid bolts and stow the lid 1
5~
bolts appropriately. Remove 4-1k" hex bolts from lid and replace with 4-1k" eye bolts.
14.
Attach lifting assembly ( 4-1/2" shackles and O
4-36 2o s ire rove 119= with e retea cagecity of 12,000 lbs. )
CAUTION:
~<
The lid cab 3es'are to. remain slack and bear no load except when the cask lid is being removed and replaced.
I 15.
Caref611y raise the crane hook so that the 4 lid lifting assemblies become' taut simultaneously.
Insure that the cask lid lif ts evenly off the cask.
Lift the AP-300 cask lid until there is a larae enough gap between the body and lid to allow a radiation survey of' the internal cavity of the cask.
(Both smear test and dose rate assessment.)
16.
Have radiation protection perform the necessary surveys.
17.
Af ter radiation surveys-are complete lift the lid the remaining distance needed and place onto plastic previously laid on the ground:in Step i6.
If the crane does ~ not have to be freed for other duties, leave the cask lid suspended in a convenient location.
'O Revision 5 - 6/10/85 7.2-3 l
2.
18.
Inspect cask gasket to insure it is in good condition and all bolt holes line up' correctly.
If any imperfection is discovered, contact ANEFCO at Ridgefield Office,-(203/431/3358) for advice on continued use cf g
the equipment.
19.
Perform radiation surveys of the liner to be unloaded l
both dose rate and smear test.
5 20.
After radiation surveys are complete and all external loose contamination is removed, lift and insure liner bottom is free of contamination, then place liner into the burial or temporary storage area.
O I
f r
h h
(
{
t s
7.2-4
/
Preparntion of nn Empty Packnoe for Tronsport 7.3 7.3.1 Purpose p)
The purpose and intent of this trocedure is to define the L
safe handling and the proper radiologicd controls necessary for preparing the empty ANEFCO AP-300 cask for transport, af ter the load has been removed from it.
General Preparations for Empty Packpo'e
'Fr a n sport 7.3.2 r
Insure the cask lid gasket is in good cond tion prior 1.
to shipment.
/
Insure. truck / cask tie-down devices are secure and in 2
proper working order.
L Always use a calibrated hand torque wrench Caution:
3.
only to bolt thE cover, according to the torque procedure (Attachment *A") to prevent, damage to bolts and cask threed:5.
The requirements of. 49 CFR 1D.427 " Empty Radioactive Materials p
4, Packaging" shall be complied with where; applicable.
v I
4 )
5.
- r E
If any abnormalities are discovered with the cask, cask or the cask equipment, notify ANErCO 6.
head, head gasket, the Ridgefield Office (203/431'3358) obtain advice on continual use of the equipment,and follow such advi'ie.
j at s.
M' M
r s.,
Lifting assemb>ies for the AP-300 cask Caution:
7.
/r should be 4 ' equal lenath wire rope with a rrinirun rated capacity of 80,000 lbs. as per federai s The wire cables mist 'always b[-ecifications RR-W-410.at an angle of 90* frcm the horizontal durirc liftim s
y Lif tine asser.blies for the AP-300 e'dO:
lid Caution:
should be 4 36" long wire rope slings wi.th a minimum /
E.
rated capacity of 12,000 lbs. as per federal specification RR-W-410.
, ',y j
ll
/
.e, s
j J
r,
/f
?
Re. virion 8,7 10/2/85
/tj /,*,
4-a d
I b
J ge L*dty.~
I 7.3.3 Procedures to Prepare Empty Package for Transport 1.
Clean cask interior walls and perform radiation survey g
to ensure that all loose contaminaion is removed from interior walls.
Use both dose rate and smear test. Radiation 1]
shgl conform with 10CFR71.87(i)(1) for allowable non-fixed radioactive contami-2.
Inspe'et cask gasket to insure it is in good condition and all bolt holes line up correctly.
If any imperfection is discovered, contact ANEFCO at Ridgefield Office (203/431-3358) for advice on continued use of the equipment.
3.
Place any. installed shoring around liner if recuired back into cask.
4.
Attach lif ting assembly (4-1/2" shackles and 4 36 " long wire 1l rope slings with a rated capacity of 12,000 1,bs. )to lid lif ting eye bdits loca'ted in the etnter of the cask lid, g
(if removed)._
5.
Retrieve the cask lid from its temporary placement and position it over the top of the cask.
If necessary, level the head to insure a proper fit.
6.
LOWER the cask lid slowly until it is approximately 1" down within the outer cask body.
.7.
STOP LOWERING and make necessary adjustments to the cask Jid until the bolt holes are precisely aligned.
8.
Lubricate and install finger tight bolts 1, 2, 3 and 4 (refer to AP-300 " Bolt Torque Procedure" drawing Attachment "A" for locations of bolts).
- 9. -
Resume LOWERING the cask lid slowly, as the cask
'l'id. seats.
OBSERVE that the lid lifting assemblies slacken s imul taneously.
Failure of this to. occur may indicate that the cask head is misa3igned. Remove lid g
lifting assembly, remove 4-lk" eve bolts and replace with 4-1k" hex bolts.
NOTE:
Decontamination activities (if required) nay proceed simultaneously to torquing.
10.
Radiation protection should perform swipe test of the cask's outer surface to determine if any loose contamination
- l is Present. Radiation shall conform with 10CFR71.87(i)(1) for allowable non-I fixed radioactive contamination.
h
(
11 Lubricate using a suitable 3ubricant, and install the remaining 32 bolts finger tight.
[
Revision 5 - 6/10/85, 7.3-2
12.
Caution:
Using s hand torque wrench only, torque the
~
. lid bolts to 15 ft. Ibs. in the sequential order shown
'(]j.
- in AP-300. cask
" Bolt Torque' Procedure" drawing (Attachment "A").
Caution: _Using a hand torque wrench only, torque the
- 13.
lid bolts -to 30 f t.11bs. in the sequential order shown
'in AP-300 cask
" Bolt Torque Procedure".
Drawing
~
- (Attachment "A")..
14, -
Cautions-Using a hand torque wrench only, torque the lid boltsuto 45 ft. Ibs. in the segoential order shown in AP-300 cask
" Bolt Torque Procedure" drawing (Attachment ~ "A").
15
-Caution:
Using a hand torque wrench only, torque the lid bolts to 60 ft. Ibs. in the sequential order shown in AP-300 cask
" Bolt Torque Procedure" drawing (Attachment "A").
16.
Caution: Using a hand torque wrench on~1y, torque the. lid bolts to final torque value 75 ft. Ibs.
~
~in1the. sequential order shown in AP-300 cask l
"Lolt Torque Procedure" drawing (Attachment "A").
)
Caution:' Using a _ hand torque ' wrench 'only, use
' ()17'-
tightening at 75 ft. Ibs until all bolts are stable at final torque level (two complete times around is usually cufficient) as shown in AP-300 cask " Bolt Torque Procedure" drawing (Attachment "A").
NOTE:
Steps 18,19, 20 are used only if cask was removed from'trai3er i
to facilitate uhloading,0f liner.
4-18.. Attach lif ting assemblies (4-2 shackles and 4-59" long chokers with a rated' capacity of 80,000 lbs.) to' the AP-300 cask lif ting / tie down eyes located on
'g the side of!the. outer chell ofcthe cask body.
19 Lift cask up12 fts os(have radiation _protbetion l~
perform-a swirs v tv of the ' cask bottom surface for. externally loon.:onteiination.
Decontaminate-cask bottom surface as necessary.
O 7.3-3
-Rev'ision _ S - 6/10/85 L.
u.
2.
. _.,. ~. _ _ _ _ _ _.
20.
Lift cnd plCca AP-300 cock within its transport ring located.on the trailer.
O
.21.
ex1Tran 5
22.
Replace canvas AP-300 cask cover over AP-300 cask and secure at base.
23.
Retrieve tie-down pins.
24, Fasten the (4) four tie-down cables to the cask as per AP-300 cask " Tie-Down Assembly (top view)"
(Attachment "B").
Tighten tie-down assembly. Torque each bolt evenly to 100 ft. lbs.
~25.
Caution: Ensure that all cotter pins are bent over to prevent loss.
Have radiation protection perform final survey of_AP-300 cask on trailer in preparation of shipment.
Attach the appropriate labe]ing and placards.
'2 6.
Ensure driver has all necessary forms for shipment and all documents and check lists are completed.
27.
Remove the wheel chocks and release the trailer brakes.
lll 28.
Perform-a final cursory visual inspection of the trailer.
29.
Review the check list to ensure that no items were missed.
x 30.
Notify ANEFCO, Inc. (2,03/431-3358) transportation manager that the shipment is en route to generator site.
si i
dBi s
7.3-4 Revision 5 - 6/10/85
7.4-Appendix
- /~j -
N 7.4.1 References q
1.
ANSI N 14.10.1 " Administrative Guide for Packing and Transporting Radioactive Materials" 2.- 49 CFR 173.400 to 173.478 " Shippers-General Requirements for Packaging, Subpart I - Radioactive Material"
~3..
10 CFR Part=20 " Standards for Protection Against Radiation" 4..
49 CFR 172.450
" Empty-Label" 5.
'49 CFR Part 176 " Carriage by Vessel" -Subpart M
" Detailed Requirements for Radioactive Materials" O
?
l 7.4,
MIPLM9M - M d
AP-300 CASK LOADING PROCEDURE 3 176.704 Cegotismenta eetating to transport inde sea.
(a)De sum of the trnn: port indemos for all packages of radioactive materials not in freight container on board a vessel. may not exceed 200 (b) Emcept as provided in paragrsph h
[e) of this section, the sum of transport j
Indexes for pactinges hot in a freight conteiner may not exceed 50 in any hold, compartment, or defined deck area. Esch group of radioactive material
~
paclinges must be separated by a distance of atleast six meters [20 feet)
- 'i at aU tirnes.
(c) Except as provided in paragrsph
,{e) of this section. the number of freight containers with paclages of radioactive materials contained therein must be limited so that the total sum of the transport Indexes in the container 1i in any bold or defined dech ares does not
[
- PART 176-CARRIAGE BY VESSEL exceed 200, and;
- 21. In Part 176. Subpart hf is revised to D)ne surn of transport Indexes for any individual freight container, or read as follows:
. group of freight containers. does not Subpart W-Detailed Requirements for exceed 50. and Ra&oactive Materials (2) Each freigh't, container or group of,,, -
8"-
7 freight conta*iners is bandled and slowed 276.700 General stowage requirements.
176 704 Requirements relating to transpor1.
.. g,g,,,
g81 Froups are.
separated fr.orn each other by a distance.
176.70e Seg eFationifjstance table.
.Pof at least'six meters [20 feet).
176.710--Care foI)owing leal *Re or sifting of~
(d) De limitations specified in f r.6cactive materista.
sS,
,, paragraphs (a),(b). and [c) of this 176.715 Contaraination control.
section do not apply to consignments of..
~
~~
Subpar 1 M-Deta!!cd Requirements for- ' low specific activity materials if the Radioactive Materlats paclages are marked RADIOACTIVE LSA" and no Fissile Cass D or Essile 3 176.700 Ceneral stowage requirements.
[a) Radioactive materials must notbe included in the slupment.
stowed in the r.arne bold with mail beFs.-
ge) y, exclusive use shipments, the'. *
(b) A paclage of radioactsve maten,als.j;;nitations spe'cifiedin paragraphs (b)..
which in silU air has a surface and N d ghs d.e & m app)y,gg-i.
temperature more than 5*C [9'F) above' -
U3 I " P* O *8 " II" I,'8
~'
the ambient air may not be overstowed c niainm. esum 6e transpwt
~
with any other cargo. lf the pa'clage is - indemes of FissDe Cass Il packages does stowed under deck the bold or
. compartment in which it is stowed must-n i exceed 50 in each bo1d.,
(2) For packages in fre,ight conteners.
- be ventDated.
.the radiationlevel does not exceed 200
[c) Each EssDe Class ID shipment ',
rnust be stowed in a separ'ste* bold.
I." mhm per hour at any point n &e
~
10 mhem at 1wo metm [6 8"# "C# "".k "
compartment, or defined ' deck area'aind.
~
II) "*
"C#
~ be separated by a distance of atleast -
.fre. ht contamer and the sum of..
ig six meters (2C feet) from isU other transport indexes of Fissile Cass D
~~ Radioactive Category D oilD.YeDow packages does not exceed 50in each...
-Tabeled pacleges. For a shipmeut of Ight container and 200 in each bold or
. radioactive materials requiring defined deck area: and
' supple mental operational procedures, D)Each gmup d Mssue can D
~.
the shipper must furnish the master or packages is separated from other 1
person in charge of the vessel a copy of
d' actave matenal by a distance of at the necessary operationalInstructiona.'
least six meters (20 feef) at aD times.
fraperwork requirem' nt eacepted from (f) he lim!!alions specified in -
e 05c4 of Management and Budget approva1J paragraphs [a) through [e) of this section
. [d] A person may not remain do not apply when the entire vessella
- unnecessarily in a hold or coropartrnent reserved or chartered for use by a single or in the immediate vicinity of any shipper under exclusive use conditions
, pacieze on deck containing radioactive if the number of Dssile Cass D and W
~
nssDe Cass ID packages of radic' active materials.
,f 7.4-)
y
OO h
materials clonard the trastel does not regubtly ecerphd working sp c2s.
m:y be losd:d enbn:rd o vess:1 with the cpprtprtle segrrg: lion det:nce Gtce;d the amount authoriard art op cas that m:y be continu;Ily ocevpiId established by demonstrating that direct H 173 451 through 173 459 of thts by* any person (eacept those spaces subch pler.De entire shipment esclusively reserved for couners measurement of the radiation level at glion must be approved by the specifically authorized to accompany regularly occupied working spaces and We of Hazardous Materials such packsges). and sndeveloped film living quarters is less than o.75 millirem R:gul: tion (OHMR)in advance.
than the distance specified to Table Ill per hour,provided that the vessel has
)
Where ordy one consignment of a been chartered for the e3clusive use of a 5 m.?ot Segrepetion estance tatge, redioactive substance le to be* loaded on competent person specialized In the
,4 D)Tcble m applies to the stowage of board a vessel under e3clusive use carriage of radioactive meterial.
Pac 1res:s of radioactive materials on conditions, the appropriate negregation Stowage arrangements shallbe 1
. bosrd a vess'ef with regard to transport distance may be established by predetermined for the entire voyage.
including any radioactive substances to
'a ind;3 gambers which are shown on the demonstrating that the direct.
labels EIindividual paclages
- measurement of the radiation level at be Ioeded al ports of cad enroute.De Radio:ctive Category D or III-YeDow regularly occupied working spaces and radiation level shall b'e measured by a lebehd p ckages may not be slowed living quarters is less than 0.75 millirem responsible person skilled in the use of monitoring instrurnents.
any cIIser toliving accomrnodations. -
per hour. More than one consignment N.e Tastz NI
+
a
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i 176.710 Care fotowing keope or stfting of sed.oactive materials.
($ In case of fire.coflision, ce bradcre involving any shipment of r:diozetive materials, other than rnattrir.1s oflow specific activity, the r:didactive rnaterials roust be regr Ecled from unnecessa'ry centaet q
with personnel. In case of obviEus :
led;ge, or if the inside container..,
cppecrs tobe damaged.the slowage,
crzo (h:1d. compartment or'deci area) containing this cargo must be Iso!ated as inuch es possible to prevent radioactive.
matari:1 frorn entering any person's s.*.
bdy through contact. Inhalation, or i
- g ingestian. No person may handle the- ;v.
W msttri:1 or remain *in the ncintty unless,
cupervised by a, qualified person. 2,..r.
.(b) A bold or compartment in which -
- "~
Icslege of radioactive' materials has
- occurr:d may not be wed for other &
c:rgs unG 11is decontaminate'd in O'".
,, cecord:nce with the, requirements of,.
~~
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I 17E711.-,
Ic) Fer reporting reguirements, see
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1171.15 of this subchapter :
$ 176.715 Contamination centrol.
(t)T.achhold, compartment. of deck cr:s arsed for the transportation oflow specific ccliEity radioactive materials end t c'aclusive use conditions shallbe
~
cerv yed vdth appr priate riediation det:ction Instruments after each use. -
Such bolds. compartments and deck cress mry not be used again unG the.
c r:distion doce rate at any accessible eerf:ce is less than 0.5 millirem per hour. cnd the remoratie (non-fim ed) radio:ctive surface contamination is not,*
i ~ gre l:t than the limits prescn' bed in j
i 173.443 of this subchapter.,
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DATE: 5 82 A
ATTACHENT,A:
A P -(/ '300 CASK
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AP 3Od CAS K Attachment C onAwincmuweEn LIO Q AS KET ASS E M B LY 1'39-1
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P.O. Box 433 m
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^""V'((Y SCALE: FULL SIZE
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Attachment D DRAWING NUMBER LI D SEAL WlRE 141 1'
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I APPENDIX I m
T AB L E.LU. - S L G
CAPACITI ES, P UNDS a
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FOR 7 0 TOTAL LOAO V ERTI C AL
' CHOKER B RI DAQf HIT C.H j
BASKET NOTYI f
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-(100 %) lVERTIC AL ; VERTICAL V E RTI C AL VERTIC AL l VERTICAL,
330 1,h30 j
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10,700 9,300 7,500 5,350 '
34 6,800 i, *_:c 13,600 11,700 9,600 6,800 1
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20,000 17,300 14,100 lo;ooo g 1 18 14,100,
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II 28,200 24,200 20,000 1h,100 -
I 22,000 1 14 22,000*1 *.6,5::
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-1 5 16 19,000 i li.,23 :
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39,000 31,800 26,500 19,000 i 1 12 24,500
'5,3~5 li h8,000 41,500 33,S00 24,000 [
1 34 29,500 22,12:-
j 59,000 51,000 k0,300 29,500 i 2
17.800 2Lu:
75,600 65,000 s2.000 37,800 2 1/2
- l 6),000 i sh,7%
170,000 147,000
- 2 *;, *. 0 0 l
85.003__(
8 NOTES:
1.
Capacities. foi bridal bitebes are for slings with eyes at top and bottom.
Derste slings if laid over pins or books (See Table IV).
2.
Capacities are.for hi-ply cables or equivalent.
For vin rope that has a breakina
.I strenarth areater than the breaking strength of hi-ply cable, the capacities any~ be one-sixth
- the manufacturer's listed breaking strength.
3.. Rated eaPacity is based upon a. tactor or sarety or 6.
i
. k.
Not a hi-ply cable *..-
5...
Basket bitches are.sub,)ect.v.o the diameter ratio require:se-ts of Appendix IV.
Che her httches are subject to the deractng'. requirements of Appendix IV or Coluse III above (which,ever to more restrictive).
i
1 4
8.
ACCEPTANCE TESTS AND MAINTENANCE PROGRAM O
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8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.l' Acceptance Tests The following are tests to be performed on the ANEFCO AP-300
~
cask prior to its first use:
8.1.1 Visual Inspection The cask will be checked to. confirm an acceptable exterior finish to assure compatibility with decontamination equipment.
This inspection will include weld porosity, rough surfaces, sharp. edges and other conditions to insure realistic decontamination.
Any imperfections that are found will be corrected and the external finish will be repolished prior;to painting.
8.1.2 Structural and Pressure Tests 8.1.2.1 Structural Tests The lifting pads will be tested with a load equivalent to 1-1/2 times the expected gross weight (98,567 pounds).
If any deformations of the lifting pads are found, the design will be re-evaluated, pads reinforced as necessary and the tests repeated.
8.1.2.2 Pressure Tests After fabrication is complete, the cavity will be subjected to a pressure test to demonstrate structural integrity.
~
Each chamber to be tested will be filled with water and This pressure will be maintained oressurized to 10.0 psig..
c
[h for 10 minutes.
No evidence of' leakage or' mechanical
. deformation will be.. accepted during this period.
For the purposes of this' test, gaskets other than service
-gaskets may be used.
8.1.3 Leak Test After the pressure test is complete, the cask will be assembled with a service gasket, and the cavity will be subjected to a leak test.
g5
'The cavity will be'pressuriz'd to 7-1/2 psig,.
e with.a gaseous mixture containing at least 10% of a test f-gas to which the leak detector is sensitive.
Testing may,
(_)3 ~
be done by using a helium mass spectrometer or a halogen leak detector if the testing procedure hgs been demonstrated to have a-sensitivity equivalent to l'cm (STP) of air per Revision 8 - 10/2/85
hour at the differential pressure used in the test.
All g
accessible welded and mechanical joints will be surveyed.
Any indication of leakage will require repair and retesting of the cask.
8.1.4 component Testino The installed performa.nce of the lid seals and the pressure and gamma test port are verified under the pressure test.
The AP-300 cask does not use valves, rupture disks or cooling systems.
8.1.5 Shieldino Inteerity Test The manufacturer will prepare a gamma probe procedure which g
includes information concerning: (1) the electronic equipment, (2) the radiation source and strength, (3) the calibration standard for both scanning and probing, (4) the grid pattern, (5) the scintillation crystal size, (6) the positioning equipment, (7) the method of reading and recordino the radiation detected, (6) the measuring technique, and (9) '
the acceptance requirements.
The procedure that is used must be acceptable to the Inspector prior to its application, and he will be notified so that he may audit the inspection g
if he desires.
The procedure and all the results will be made part of the fabrication record.
Scanning will be at low, middle and high bands, with sufficient overlap for the full circumference of the cask.
Scanning will l
also be on concentric circles and on radial grid lines.
Results shall verify that no void areas exist in the sidewall or lid assembly in excess of 0.25" lead.
The scanninc paths shall be reviewed to assure that 100% of 2
the external surface has been examined.
8.1.6 Thermal Acceptance Tests The AP-300 cask will require to reject less than 150 watts.
The calculations show the capability for this service by a large margin.
O P.1-2 Eevision 2 - 11/28/E4
8'.2 ' Maintenance Program
..[]
The maintenance program is established to ensure continued performance of the cask. The cask will be routinely inspected prior to each departure to the reactor site.
In addition, periodic inspections of the cask will be made requiring testing and/or replacement of. critical components as follows:
8.2.1 Structural and Presaure Tests 8.2.1.1 Structural On an annual basis, the lifting pads will be closely inspected for cracks or other signs of failure. -If cigns of failure are found, the lifting pads will be replaced and load tested. The square tube (Port g
B-9) will.be inspected for cracks and deformations and if cracked or deformation exceed 3/8" in height, replace or repair as deemed necessary.
8.2.1.2 Pressure Tests Onanannual.hasis..thecaskcavitywillbe.hhdrostaticallypressure
'8 tested to 10,psig_Should a leak be found,.it will be repaired and -
the test rerun.
8.2.2 Leak Tests Red Devil Casket (or neoprene equivalent) and pressure port plugs tests.
<f On an annual basis, the containment cavity will be peessurized to 10.psig. The s./
pressure level will be checked over a 10 minute interval ano no pressure 4
loss or evidence of leakage during this period will be accepted. Should a pressure drop be noted, the cause will be found, repaired.and the test rerun. An annual leak test withasensitivityof1x10'gilbeperformedusingaheliumleakdetector 1.l atm-cc/sec.
If leakage in excess of 10 cc/hr-is detected, the gasket will be replaced and the leak test will be repeated 6
until acceptable results are obtained.
8.2.3 Subsystem Maintenance There are no subsystems provided for the AP-300 cask which require maintenance.
8.2.4 Valves, Rupture Discs and Caskets on Containment Vessel The gaskets will be visually inspected before and after each use of the AP-300 cask. The gaskets will be tested during the annual pressure and leak tests, described in Sections 8.2.1.2'and 8.2.2.
The gaskets will be replaced after twelve (12) sequentid1 uses or if found unsatisfactory
.during the annual leak test. There are no other components of the AP-300 cask which need maintenance.
A()
Revision 8 - 10/2/85 8.2-1
Each of the 36 closure bolts will be inspected before use to insure that the screw threads are intact.
Bolts which bind when manually installed in a test tap shall be repaired or replaced.
h 1
Each bolt hole will be checked before use by manually checking bolt rotation with a test bolt.
Should test bolt bind, tap hole will be repaired before use.
8.2.5 shielding Before each shipment, a gamma radiation survey of the cask will be' conducted to verify that the cask is within acceptable limits for shipment.
8.2.6 Thermal The 150 watt thermal load capacity does not require thermal tests.
8.2.7 Cask Surface Inspection on an annual basis, the cask will be inspected visually to verify protective coating integrity.
Defects which are noted will be refurbished, in accordance with specification A83-GCPO, to restore the integrity of the protective coating.,
O i
I O'
S.2-2 Revision 1 7/31/84 l
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4 O
APPENDIX A - DRAWINGS 8
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Liquid Penetrant (' P) - ASW i s Flate 3-1 to be fillet welded using multipase string technique using SMAW & 38W processes. Croove design to be double bevel with $2' Mag in ticle (t@) ASMI 5ect'en bends and 1/8" masimum root gap. weld to be IOC: ICT esing s-ray.
Radlegraphic Inspectica (F1) /*
Plate 3-2 (laner shell) to be fillet welded using m.itipass string technique using SMAW 6 SAW processes. Croove design ts, be singIn bevel with $3' with1/8" assimum esp. Weld to be 100: 21.
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