ML20128B602
| ML20128B602 | |
| Person / Time | |
|---|---|
| Site: | 07109192 |
| Issue date: | 06/12/1985 |
| From: | ANEFCO, INC. |
| To: | |
| Shared Package | |
| ML20128B585 | List: |
| References | |
| NUDOCS 8507030300 | |
| Download: ML20128B602 (56) | |
Text
3
,o DESIGN SAFETY ANALYSIS REPORT O
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ANEFCO INC.
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DOCUMENT APPROVAL SIGNATURE SHEET DOCUMENT NO.
WPE OF DOCUMENT SAFETY ANALYSIS REPORT AP-300 g
DESIGN AND SAFETY ANALYSIS REPORT ANEFC0 AP-300 Greater Than Type A - LSA Dated 3/1 /84 EXT.
5 PREPARED BY: _ John D. Murphy Jr.
ORIGINATED BY:
John D. Murphy Jr.
EXT.
5 APPROVAL & REVIEW SIGNATURES ORGANIZATION DATE J,
Technical Raview Comittee j
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TABLE OF CONTENTS em N-1.
GENERAL INFORMATION 1.1 Introduction 1.2 Package Description 1.2.1 Packaging 1.2.2 Operational Features 1.2.3 Contents of Packaging 1.3 Appendix 2.-
STRUCTURAL EVALUATION 2.1 Structural Design 2.1.1 Discussion 2.1.2 Design Criteria 2.2 Weights and Centers of Gravity 2.3 Mechanical Properties of Materials 2.4 General Standards for All Packages 2.4.1 Chemical and Galvanic Reactions
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2.4.2 Positive Closure 2.4.3 Lifting Devices 2.4.4 Tiedown Devices 2.5 Standards for Greater Than. Type A Packaaing 2.5.1 Load Resistan ce 2.5.2 External Pressure
' 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 O
V V
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 3.4.3 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 lll 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 i
O ii
TABLE OF CONTENTS (Con't)
W'b.
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
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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 P,ROGRAM 8.1 Acceptance Tests 8.1.1 Visual Inspection 8.1.2 Structural and Pressure Tests 8.1.3 Leak Tests 8.1.4. Component Tests 8.1.5 Test for shielding Integrity (n_j 8.1.6 Thermal Acceptance Tests lii
TABLE OF CONTENTS (Con't) h
-B.2 Maintenace Tests 8.2.1 Structural and Pressure Tests 8.2.2 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 1.0 GENERAL INFOR5ATION'#
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1.1 Introduction
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V The AP-300 A ir a ferritic steel shielded shipping cask designed to meet the criteria cf greater than Type A low specific activity (LSA) packages (as defined'.in10CFR 71.4). 'The container is built to comply with Title r.
10 Code of Federal Regulations (as amended September 6, 1983), Subpart E, parts 71. U, 71.43, 71.45, 71.47 and 71.51.
In addition, it has been cvaluated 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 i
Number 71-0001 and is labeled and marked in accordance with Title 49 Code i
of Federal Regulations Parts 176.350, 173.24 and Part 72.
1 i j' The" specifications for this cask are as follows:
(
MODEL AP-300 A (referred to as AP-300 in remainder of the text.)
l Classification:
" Greater Than Type A LSA" Overall DLeensions:
83 " dia. x 96_ " high Shielding:'
3" lead equivalent (Cobalt 60)
Il Cask Weight:
46,720 lbs.
l Capacity:
76" dia. x 82" high Max. Quantity /Pkg:
20,000 lbs., not to exceed 20 curies of Cobalt 60 s
l The'AP-300 is a steel encased, lea 6' shielded cask. The cask consists of
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two concentric cylindrical shells.- The inner shell is h inch thick by 76" l Cl
.I.DJ, made of ASTM A240 Type 304 S.S. material. The outer shell is ik l~_),
. inches > Lhick by 83.625 inches 0.D., made of ASTM A516 Grade 70 steel.
-The annulus between the two concentric shells is filled with 2 inches of
[t poured lea'dito'act ay,a shield. The base has 2 inches of poured lead and is the same totalfthickness as the vertical walls of the cask. The flanged lid con'sists of three ASTM-A240 Type 304 S.S. plates attached to f
,4 a riser ring. Concrete is placed between the two upper plates, and lead shielding 1,s placed between the ryo lower plates.
A positive closure -is provided by thirty-six (36) 3/4 inch diameter hex
.A socket bolts and a J.M. " Red' Devil" (or Neoprene equivalent) compressed sheet gasket. The cask is equipped /with four independent (2 redundant pairs) liftting 1u's.
These lugs sre also used to tie the cask down during 3
g 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 torcidal ring is welded to the top of the l,
ca A to act as a crash barrier.
Ie A
. A double bolted seal test port fr provided in the lid. This allows test j
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 uot Icak during accidents.
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-fN 1.1-1 Revision 5 - 6/10/85
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1.1 Introduction (Con't)
The AP-300 cask is desianed to transport areater than rvna a y.llh wasbe wdd1 an approximate curie level of.09 curies /cu f t of
~~~ Cobalt 60 or a total of 20 curies Cobalt 60.
The waste The AP-300 form may be solid, dewatered or solidified.
one liner / catch tank up to 74" diameter can acm.oodate by 80" high or ten (10) DOT 17-H 55 gallon drums.
i 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 Weight The weight breakdown ~of the AP-300 cask is as follows:
Weicht (1bs.)
Components Cask Body 37,255 9,462 Cask Lid 4
Total Cask (Empty) 46,717 20,000 Cask Contents Total Cask & Contents 66,717 l
1.2.1.4 General Construction stainless steel (used Materials of construction are:
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 ASTM - J.240, Type 304 stainless steel.
The inner and outer stells of the cask body are both weldedtotheclosureringatthetopofthecavityflange.O 1.2-1 Revision 4 - 4/15/85
1.2.1.4 General Construction (con't)
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 Icad for GAMMA 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 lifting eye pads (redundant pairs for those sites requiring four-f point lifts) 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:
An outer plate with provisions to attach lifting eye bolts, which f
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.
1 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, b 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 b 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 limited Transportation of the AP-300 cask is normally by (although not 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.
bd 1 2-2 Revision 5 6/10/85
1.2.1.7 shipping Confiouration (Con't)
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 Ring The closure ring is fabricated from ASTM A240, Type 304 stainless steel and is 81.125 inch O.D.,
76 inch 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 1.id to the ring.
1.2.1.10 Lid Closure Seal The seal between the closure lid and ring is made of high temperature, compressed SBR (neoprene blend), flange gasket of Johnsfamvule, 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 O.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 V-
~ 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" O.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 located 2" below the outer surface of the lid. The seal test connection is in turn sealed by a inch hex socket, ASTM 320 stainless steel bolt and a 1/8" thick Johns-O)
Manville Red Devil gasket. The seal test connection and plug are in
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turn protected by a second seal plug in a h" ASTM A320 hex socket bolt lb" 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 Gasket. 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,10k inches high by 20 inches long by 4 inches f
thick, fabricated from ASTM A516, Grade 70, are located on the side of the outer shell of the cask body. Each pair of opposite lifting eyes are designed in accordance with the regulations and may be used independently of each other. The four lifting eyes design is used to meet the requirements of those reactor sites which require independent four point lifts. The lifting pad eyes are used during I
transport as tie down points during shipment.
.A 1.2-4 Revision 5 -6/10/85
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 material;in 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.
Maximum 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 yy 8
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2.0 STRUCTURAL EVALUATION g
U 2.1 STRUCTURAL DESIGN 2.1.1 Discussion The principal structural members of the package consists of two major structural systems and other components.
The 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 cavity pressure and temperature and prevent puncture from the top.
The next 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 tic it dowr. Curing transport.
2.1.2 Design Criteria
)
The design conditions used to evaluate the structural integrity of the packaging are specified in 10 CFR 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, the cask is evaluated in accordance with NUREG-CR-1815, "Recommandations for Protection Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers up to 4 Inches Thick" and Rep. Guide., Task P.S 144-4, June, 1983, Draft.
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, 1974 Edition, were sed to size components, obtain material Both properties, and evaluate design safety margins.
operating and accident conditions were evaluated and compared Division 2.
with the stress and f atigue limits of Section VIII, 2.1-1 Revision 5 - 6/10/85 a
When specific design formulae were avai3able, such as presented in ORNL-68, these were used to either size or lh evaluate components and parts.
Design criteria used to evaluate stresses and strains caused by the 3 foot free drop and the 6 inch bar puncture were either the static yie3d, or where appro-priate by comparison with the dynamic yie3d or ultimate tensile strength.
Permanent deformations were allowed to occur provided that the u3timate strain was not reached and the primary containment seals remained operable.
WEIGHTS AND CENTERS OF GRAVITY 2,2 The individual weights of the major individual sub-assemblies are tabulated in the table of cask weights and outers of gravity.
Each sub-assemb3y is referenced to the cask assembly Drawing No.133 respectively.
The tota) empty cask weight is 46,717 pounds.
The loaded g
cask weight, with maximum design load is 66,717 j
pounds.
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The center of gravity of the Joaded cask is 47.66 inches above the bottom of the cask at the center axis of the O.
cask.
O 2.2-1 Revision 4 - 4/15/85
TABLE 2-1 CASK WEICHTS & CENTERS OF ORAVITY i
,O PART W LBS.
Y IN.
WY 4l Cask Lid Concrete 1462 92.09 1.35 x 10 l
Cask Lid Assembly 8000 89.06 7.19 x 105 Cask Outer Shell 8925 48.0 4.28 x 105 Closure Ring 405 45.375
.18 x 105 l
Inner Shell 3070 43.75 1.34 x 105 Inner Shell Bottom Plate 655 4
.03 x 1055 l
Outer Shell Bottom Plate 1825 1.12
.02 x 10 5 Gamma shield 18560 44.5 8.26 x 10 5 Bottom Shield 3815 2.75
.10 x 10 3
4,;
46717 22.75 x 10 L ?W 4!
CG = t W 48.70" 5
Contents 20,000 45.25 9.05 x 10 5
4!
Loaded Wft WL 66,717 31.80 x 10 t iW 4l Loaded C.G.
(R,1 ?W )
(41.75", 47.66")
i 2.2-2 Revision 4 - 4/15/85
O 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 1
4.
ASTM A320, Grade L7A Closure bolts, seal test connections O
2.3-1 Revision 5 - 6/10/85 k
O O
O TABLE 2J3-1 MECHANICAL PROPERTIES OF MATERIALS Coefficient Values of Yield Spec Min. /
Spec. Min.
of Linear Modulus Yield (KIPS Tens. (K PS/ Thermal of Material Temperature Matnrial sq. in.)
sq. in.
Expansion (4)
Elasticity (4)_ 100 300 400 500 600_ maferene SA-516 38.0 70.0 6.5 x 10-6 28.5 +.5 38.0 33.7 32.6 30.7 28.1 Table (in/in/*F)
~
Grcde 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
-6 ARA-l*
Type 304 Dynamic Strength - 5000 poi (1) (2) (E
-6 Lerd 0.84(4) 16.3 x 10 2
35.0 31.9 30.6 09.5 28.1 Table hA-320 105.0 125.0 AEN"2*
llGrEde L 7A
- Division 2,Section VIII, ASME Boiler & Pressure Vessel Code U
(1) " Nuclear engineering and Design". Vol. 13, 1970, North-Holland Publishing Co.,
Y P.O. Box 3489, Amsterdam, The Netherlands, u
- o (2)
Shappart, Cask Designers Guide", ORNL-NSIC-68, United States Atomic Energy Comission, Oak Ridge, Tennessee.
5'
" Impact - The Theory and Physical Behavior of Colliding Solids",
g-(3)
Goldsmith, W.,
Edwards Arnold Pub]ishers, Ltd 1960.
o (4)
American Society for Metals, " Metals Handbook", 8th Edition.
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2.4 CENEPAL 67ANDARDDR9Euacnnswam 2.4.1 Chamical nna Calvanic Reaction The cask's materials of construction, those of the disposable canister and the contents are all metals that do not produce significant chemical galvanic or other reactions.
The g
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 unscrewed. The closure assembly is secured by 36 hex socket 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 d
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 ina$iertently opened.
.The seal is made by a high temprature gasket, which is placed between the lid plate cnd the ring plate, and secured by the 36 hex socket head bolts.
The gasket is icbricated by Johns Mansville and consists of DuPont aracid fibers which are bound by styrene butadiene rubber.
Th2 stress on the gasket is determined as follows:
The gasket is compressed by the weight of the lid and the preload applied by the h tightening of the bolts to a torque of 115 ft Ibs.
The area of the gasket (81.125" OD, 16" ID 3/4" bolts) is:
2 2
} (81.125 - 76 ) in - 36 % (.75 ) in A=
632.45 - 15.90 - 616.55 in The f orce on each bolt, torqued to 115 f t lbs,can be determined f rom the 3
relationship shown in ORh*L-NSIC - 68 page 37, formula (2.9):
T = 0.2 a F T = Torque (ft Ib), a = bolt diameter (ft), F = induced force (1bs)
Where:
115 f t Ib 9200 lb
=
y=
0.2(*y ) ft The total force f rom each of the 36 bolts torqued to 115 f t Ib and the wieght of the lid is:
9200(36) + 9500 - 340,700 lbs.
g 340,000 lbs 552.6 psi Therefore, the stress on the gasket will be 2
616.55 in 2.4-1 Fevision 3 - 2/15/85
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n-b s
5 k
HOIST NG BEAM R
k z
n m
e a a
o q) e 5
E2 (f
f FOUR VIRE R0PE P
SLINGS D
CASK LIFTING f
h
/ PADS i
tn o
8 FOUR SCREL' PIN n
h 5
ANCHOR SHACKLES TOP AND BOTTOM
%y L.
A ANEFC0 MODEL AP-300
/
\\
SHIPPING CASK C?$
/
- P" 4w* It rO x F E F.
N
[n"
-w>
s i
~T n"?
f
[-
j l
3 o
5 I
5 2
U E
l
!0 5*
g FICURE 2.4 CASK LIFTING DEVICE l
w
Th2 maximum ctrats cnd ctrein th2 geck 2t-een withstcnd withtut iciluro 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
'N test and gasket replacement schedule is based on the following.
(d 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.
compressibility = 35% x Ob = 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 rw 2.4.3.1 Lifting Devices for Cask Assembly (v)
The cask lif ting 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 assumed.that the cask I
is loaded with its payload of 20,000 lbs, in evaluating the design of the lifting / tie down pad eye.
Total lifting weight is therefore:
We = 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 load.
D = 3(Wt)
Design load = 3(66,717) = 200,151 lbs.
6 Each pair of lifting / tie down pad eyes are designed to take the
(^
entire load, therefore, each ear is designed to take 31 the load or 100,075.lbs.
2.4-2 Fevision 5 - 6/10/85
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 the hole in the lifting pad for bearing and shear. (assuming 2" minimum for pin)
= 12.5 ksi (actual bearing stress)
F
=
p 2
Allowable AISC (8th edition spec. para. 1.5.1.5)
F = 1.5 F
= 1.5 x 38 =.57 ksi p
y Safety factor to allowable AISC bearing SF =
= 4.56 2.5 Check tear out of lifting device A = 2 x 3 x 4 = 24 sq. in.
y The shear capacity of structural steel is 2/3 of the tensile capacity. Therefore, the tear out capacity is:
2/3 x 38 x 24 = 608 kip SF =
= 6.07 l
0
[
Check bending of pad Sm=flh -Tir
(
}2 (1.25)3 - 348.7 in 3'
=
F = T, 3(66.72) = 100.1 kip 3W Z
Bending moment = 100.1 kip x 6" = 600.6 kip-in 1.72 ksi Bending stress =
=
348.7 in Safety factor SF =
= 22.1 A
72 Check welds bending along plane 1-2 (see Figure 2.4-2)
M = 6" x 100.1 = 600.6 kip-in Sm for 3/4" fillet veld A = 2(2(R4)(.53) = 25.5 in A
25.5
" 6.15 b " 6.15(.53) l i
i f
2.4-3 Revision 5 - 6/10/85
c i
i t.
N 2,,
0 N
N x
x
'N r-TA 4
s
'x
/
/
x
'N, N
b
/'
K
/
./ \\
S IDE E L E. VAT IO N 4
s
- g go y,
I'la n ts
,,s,.A l
6 t-t Id s>
q i
- q g a
Qi v
S Ec Tio N A-A A
1 {/
LIFTING _ TIE _-yototJ PC
~
[i o u.t, 2.4-Z
- Li f Eim, Fome
,,0.ciot..
u c
2.4 4 Revision 5 - 6/10/85
h 6
.6 Fweld
- 3.01 ksi
=
tension 3.93 ksi F
=
weld 2 5 stress
(
1 (3.012 + 3.93
4.95 ksi Combined stress
Allowable tensile stress for E70 ksi low hydrogen electrode is 21 ksi.
SF to tensile stress for lifting
- 4.24
= 4 95
~e O
2.4-5 Revision 5 - 6/10/85
/^
2.4.3.2 Cask Lid Lifting Device'.
%.)T 2.4.3.2.1 -Loading 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 lif ting system must be capable of handling three times the expected total load..
D = 3(W )
The cask lid weight is 9,462 lbs.
28,386 lbs.
Design load = (9,462)(3)
=
Each ear will carry half of the design load:
W = D /2 g
Where D = Design Load = 28,386 lbs.
g N
W = 28,386/2 = 14,193 lbs.
_34 t
N I
T
/a J
v 7 "__ __
I i
3 3/
et c \\;
b LL dX
- (-
9 9
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' apart.
Each eye bolt McMaster Carr #3013T57 or equivalent has a 3" shank arid is threaded ik" into the lid threads which are lined with helicoil inserts.
'b 2.4 '6 Revision 5 - 6/10/85
r 0
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 eyes 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.
I 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 normally be lifted by a sling that will engage all four eye bolts simulteneously, thereby doubling the safety factor to a value of 2.12.
O I
t i
4 k
l
- 2. 4-7 Revision 5 - 6/10/85 i
3.4.4 TIE-DOWN DEVICE In order to satisfy the requirements of 173.412 (d) the cask tie-down blocks were designed to meet Title 10 of the Code of qb Federal Regulations 71.31 (d) which stipulates that the tie-down structure be capable of sustaining at the center of gravity of the cask a "g" loading conponent of:
2 g's Vertical
=
10 g's Forward horizontal
=
5 g's Sideward horizontal
=
2.4.4.1 TIE-DOWN FORCES e
- 27'-.
f %
73*
t I 70' 70*
i
- 7 d' '
e f
f 14.7 5" t
a-41.81* -*
47.7*
96*
~
a g46.67 N
42.3*
42.3 \\
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.
4 Weight 66,720.
~
O 2.4-8 Revision 4-4/15/85
V I
O 4l Tor a loaded cask veight of 66720 lbs, it is considered that the following forces will act simultaneously at the center of the cask in the following h
directions:
Vertical-V 2g vill act in the upward direction and lg vill act in the downward direction 4l for a net lg f orce or 66,720 lbs upward.
Forward Horizontel - H 7 4l 10g vill act in the forward horizontal direction or 667,200 lbs.
Sidevard Horizontal - H g 4
sg will act in the sideward horizontal direction or 333,600 lbs.
Resultant Force - F R l
S The resultant force of the above three forces acting sicultaneously can be i
calculated from the following relationship:
(66,720 +667,200 +333,600 )h= 748.93 kip 2
2 2
4 F
+ "F 5
+
=
R gt The resultant force will act in a direction which is approximately:
84.89* fro = the vertical 27.02* f rom the forward (longitudinal) horizontal, and 63.55* - f rom the sidevard (lateral) horizontal The resultant force is distributed equally in each of two (2) tie-down lugs.
Therefore, each lug will be subjected to a force of 374.5 kip.
The tie-down makes an angle of 42.3' with the horizontal, as shown in Fig. 2.4-3.
F=
374.5 (cos 42.3* ) = 277 kip 5
H F=
374.5 (sin 42.3 )=252 kip y
Therefore, horizontal and vertical forces, of.277 kip _and 252 kip respectively, will be imposed on each lug.
2.4-9 Revision 5 - 6/10/85 next page 2.4-11 e
i
2.4.4.5 TIE - DOWN PADS FOR CASK' ASSEMBLY
~2.4.4.5.1 LOADING
,.s
)
95 Two tie-down pads must be capable of sustaining the total force of the resultant force previously calculated, viz. 748.9 kip 4
~
The tie-down pads are designed to recist the resultant zorce 5
together..Each pad is designed for 374.5 kip.
O b
I o
2.4-11 Revision 5 - 6/10/85
(
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 Welding a
Code.
W Check hole for bearing and shear. (assume 2" min. for Pin) 374'5 46.8 ksi (actual bearing stress) 5 F
=-2x4
=
p Allowable AISC (8th edition specification para. 1.5.1.5)
= 1.5 F3 = 1.5 x 38 = 57 ksi Fp Safety factor to allowable AISC bearing 5
1.2'2 SF =
-=
g 46 Check tear out of hold down device along lines 1-2 and 3-4, Section A-A (page 2.4-13)
- 24. sq. in.
Av = 2 x 3 x 4
=
g The shear capacity of structural steel is 2/3 of the tensile capcity.
4 Therefore, the tear out capacity is:
608
= 1.62 2/3 x 38 x24
= 608 kip; SF,374.5 5
Bending along plane 1-2 M = 6" x 374.5 = 2247 kip-in g
Sm for 3/4" fillet weld (Stress & Strain by Roark & Young page 63)
- 25. 5 sq. in.
A=
2 (20 + 4) (.53)
=
2 2
A 25.5 199,4
=
=
3m_ 6.15 b 6.15 (.53) 2247
- 41. 3 ksi Fweld
=
y=
tension g
374.5 =
14.7 ksi Fweld
=
25.5 shear Combined Stress comb.
11.32 + 14. 72 f
18.5 ksi
=
O 2.4-12 Revision 5 - 6/10/85
o,x 0
.l
\\
s s-x,\\ \\
~
4 s
-/
,,b i
3
/
/
5 j
~
~% l
'A
- >^
j 7 r
3 &*
- 9 S \\DE g
E L EVATION 4
<l' 26
~
Shear
^
flancs s)/
h piCKg
%H id r,
I 3
s-g g
JD-v S E C Tio N A-A 1
1 i [/
LtFrir/j _T(t -yotor) PAD
, ~\\
()
2.4-13 P.evision 5 - 6/10/85
O Use E70 ksi low hydrogen electrode.
Allowabic tensile stress = 21 ksi 3
21 4l S.F. to tensile stress =
" 1.14 19.5 Tie-Down Pads As shown in the drawing, four tie-down pads are provided to attach the shipping cask to the truck bed. A 7" square, 2" high plate is welded to the cask body using a 3/4" fillet veld all around. A plate, 4"
thick, 2 0" long and 10("
high is velded at right angles to the base plate and the cask body using a g[
3/4" fillet seld all around. A 2 " diameter hole is provided in the latter plate ano used to enable tie-down.
Both plates will be fabricated from a steel having a minimum, Fy = 60 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 the 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.
O 2.4-14 Revision 5 - 6/10/85 h
- r J
E U
s 2.4.4.5.5 EXCESSIVE LOADING OF THE TIE-DOWN Itcan be seen from the previous sections that
(
extensive loading of the tie-down pad will cause failure in the tie-down pads due to bending or shear of the ear we]ds prior to any damage to the side wall of the container.
Therefore, extensive Joads wi]1 not impair the ability of the cask to meet other requirements and the conditions for 173.412 (1) are met.
'O 2.4.4.7 CHOCKING RING
/p 78 Cask 10 W j
F2 V
s E.._mm.
1 g
m m m m.
Trailer Side Frame
_l 8' MC 8.5 l
b FIGURE 2.4-10 FORCE DIAGRAM CHOCKING RING O
l 2.4-15
The chocking ring velded to the steel deck plate is designed to prevent sliding of'the cask due to the forces imposed during pL'y the conditions of transport stated in Title 10 of the Code of Federal Regulations 71.31 (d).
I 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 twc supports) is:
373.0 kip'
~
4 Max. Reaction =
102+52 x 66.72 kip
=
)
i The chocking (restraining) ring consists of a 7/8 thick ring v
v welded to the base by two inch fillet welds, one on each i
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
=
alloa.
The welding electrode has a tensile strength of 80 ksi.
Oe3 x 80 x 2 x.5 16.97 kip /in
=
Fv
=
E h
alloa.
The shear of the steel ring governs.
Width of ring, required to restrain base of cask is:
373 4
= 28.05 in 13.3 The minimum diameter of the ring = 0.D. of the cask = 83.625" Therefore, the cask is safely restrained by the ring, assuming i
l friction is neglible.
,83.<S25".
Cadc W = 66.72 kip l
Beacticn
- g.,
_s (tie down) l 1mf 1
=
/
l SW/
Reaction g
(Ring) l l
2,4-16 Revision 4 - 4/15/85
1 i
2.5 STANDARDS FOR GREATER THAN TYPE A PACKAGING
() -
The greater than Type A package must satisfy the requirements N-cf 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 conditions.
Compliance of ANEFCO AP-300 under normal operating conditions is described in Sections 2.6, 3.4 and 4.2.
(
{
O 2.5-1
2.6 Normal Conditions of Transport 2.6.1 Heat Assuming an ambient shaded temperature of 100*F and a heat imput of 9
m
.8 BTU 400 x
x 2
,2(12hr) 252 cal.
ft.2 hr-ft
=
Assume maximum 150 watts
- 3.14 BTU 2
cask watt hr (175.14 ft surface) 2.7 BTU
=
2 hr-ft Assume 126 BTU
= maximum heat that must be dissipated 7
hrft from cask under normal conditions, h AT
= 126 BTU 2
hrft where h
=h
+h
= total heat transfer from' cask t
e r
= convection transfer + radiation transfer g
aT= surface temp - maximum ambient temp ICcAdams
.18(T
- T )1/3
- Heat Transfer h
=
c s
a 1
F 4
4 0.173 E T
T h
=
r g
a 100 100
- ORNL - NSIC - 68 Cask Designer's Guide (T
-Ta) s if T,=100*F=560 R by trial and error and if T = 165 F=625 R h
= 0.72 BTU T
0 F=630 R
=
s c
s hrft F
h 0.74
=
r h
= 1.15 BTU h = 1.17 r
2 hrft F
h = 1.87 BTU t
ht = 1.91 hrft *F h t.T = 122 BTU h a T= 133 BTU t
2 hrft hrft
.', Surface temperature of cask will be between 165*F and 170*F 2.6-1
2.6.2 COLD
- 2.6.2.1 COLD AMBIENT TEMPERATURE (-40 )'F. IN STILL
- /~';
AIR AND SHADE
'\\ J 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=P3 T2 T1 P2 = 14.7 (420) 530 P2 = 11.65 psia The resu] ting 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
(~)
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 liquids are invo]ved.
The only adverse effect occurs when the lead contracts and places the inner she).] in compression.
This differential radial contraction wilJ cycle from (-40)*F to 180*F.
The range of 220*F will produce interference stresses between the Jead shieJd and the inner shell.
To be conservative, for design purposes, the radial interference and resulting pressure was calculated for one cyc]e from 600'F to (-40)* F.
This is about six times the maximum normal ex-pected alternating stress.
-O 6
2.6-2
2.6.2.2 CONTRACTION OF LEAD AROUND INNER SHELL Differential thermal expansion between the lead shie3d and inner she3 3 during cooling after pouring of the 3ead resu3ts in compression g
of the inner she31.
The analysis conservatively assumes a continuous cool-down from the lead me)t temperature for a long period prior to exposure to a (-40)*F temperature.
During this time some relaxation of the contact forces exerted by the lead can be expected.
The theoretical maximum contact pressure between the 3ead and inner she3 3 is determined by:
- el
(- pb ~ e c) d T Pp3 =
2 2
(1/Epb)
'c2+b2 + 0 pli Ib +a
+ (1/E )
s s
.bi-al
,ci-bl a
Where: oc pb = coef ficient of linear thermal expansion of lead
= coefficient of linear therma) 8s expansion of steel E pb = modulus of e3asticity of Jead
= modulus of elasticity of steel gs inner radius of inner shell h
=
a
= outer radius of inner shel) b
= outer radius of lead shield c
d s " d pb = Poisson's ratio = 0.3 (36.3 - 6.5)(660)
P
=
pb 3
'(40.5) f + (38.5) Z
+ 0.31
+
1 (38.5)Z i
29 2
,(4 0. 5 ) e i
I
- (38.5)2 + (38)2 0.3]
(3 W j(38.5)4 f
TimoShenko, S.
" Strength of Materials, Part II, Advanced Theory and Problems", third edition, Van i
Nostrand, 1956 O
2.6-3 Revision 1 7/31/84
1
.O V
/
The actua) maximum contact pressure the lead is capable of exerting on the steel is the maximum equivalent hydrostatic pressure:
Using Roark Case la, page 504 i
P
~
maxPb" (ce + be) maxpb = 511
(.0508)
P g
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
()
(/=
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 L
1 CP =
-1973.0 psi l
This is well below the yie3d stress of the
'll inner shel) (30,000 psi) by a' factor of 15.
- R. J. Roark and W.C. Young " Formulas for Stress and Strain", fifth edition, McGraw Hill, 1975.
.O 2.6-4 Revision 1 7/31/84
Further examination of tha intorforenca 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
[ (1/1 -p ) 3 (t /R ) ) 0.25 2
2 2
2 P R = 0.807 (Et /LR)
C Where: E = Modulus of elasticity of inner shell A = Poisson's ratio t = Thickness of inner shell 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- (O.3) 2) 3 (.5 /38 )] 0.25 F
= 396 psi CR Since P
= 196 psi and P pb = 25.96, the lead CR 1
contact pressure due to lead contraction will not buckle the inner shell.
17/31/84g 2.6-5 Revision
-(,m) 2.6.3 Reduced External Pressure The regulations for normal conditions of transport specify that the package be able to withstand an absolute atmosi eric pressure of 3.5 psi.
The resulting t
internal pressure is thus 11.2 psi.
35f34 dw 00 t
V colside. passws.
c.arcle.
9 I
l t
.t.,,. g
- 14.7 psi inside.
. ( a x - y w) e.
freSturc COVER PLATE SECTION (1.25 + 1.562) = 39.00" R=
(83.625)
From Roark " Stress and Strain" 5th edition case 10a page 363 for r. = 0 2
2
(?
(3d) y[39 (3 +.27) = 3481.6 inlb/in
=
M
=
center 2
3 1x2 0.67 in /in
=
S, =
348 5196 psi (bending in plate)
=
f
=
6 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.
inside face of the lid and the The lead shield on the inner plates will not be subject to bending due to a reduction of external pressure when the cask is operational.
O
- the next page is 2.6 2.6-6 Revision 1 7/31/84
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 resulting net pressure is therefore, i
6 psi.
The effect of an increased atmospheric 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 chell.
Therefore, the primary membrane stress in the inner shell is:
Using Roark Case Ic, page 448 cR 2=
t q
Where:
g = Pressure in lbs/in R=
Internal radius t = Thickness of the inner shell 7 = 6(38)
{
2 s
e; 7 = 456 psi 2
The yield stress for the inner shell is 30,000 psi, i'
therefore, the inner shell will suffer no damaae from a 25 psi external pressure.
Evaluating the lid and end plates, considering the lid and l
bottom plates are simply supported i
Using Roark Case 10a, page 363 (to derive the moment) l' = K ga m
1
.20625 where R0 = 0.0 Where:
K
=
m 2
g
= pressure in lbs/in a1 = radius of cask lid a2 = radius of end plate (inner shell) t'1 = moment of the cask lid 9
2.6-9
-M
=.20625 (6) (40.5625)2 y
.m (J
M 2036 lbs.
y-P:2 = M ment of the end plate (inner shell) 1;2 =.20625 (6) (38)2 M
= 1787 lbs.
2 Solvino for the stress in the lid and end plate (inner shell)
Usino hoark Table 24, IIotations Pace 332 The circumferential bendino stress for the lid is:
6M1 2
2 1
t b
= 6(2036) 2 1 2
2 Pd 3054 psi
=
0../
1 s
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) 6fi2 g
2 2
t 6(1787) 2
=
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.
1 2.6-10 i
i
Using Roark Case 10a, Pace 363
(,_)
(to determine the moment) v E = K, ga Where:
K
=.20625 when R
=0 0
2 e
g
= pressure in lbs/in
~
a
= radius of cask outer bottom plate 3
r M
= m ment of the cask outer bottom plate 3
(.20625) (6) (40.5625)
M
=
3 2036 lbs.
M
=
3 Solving.for the stress in the outer plate-Using Roark Table 24, Notations page 332 The circumferential bending stress in the outer bottom plate is:
OI =
6P'3
+
t 0~ =
6(2036) 3 (1.25)2 03 = 7,818 psi 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.
i OV 2.6-11
i 2.6.5 Vibration The approximate natural frequency of the loaded cask is i
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.
f
= (9.87/2 W)
(EIg/wl )0.5 n
Where:
E= Modulus of Elasticity I= Arca 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)
I 6
2 E = 29 x 10 1b/in Outside Radius of Cask Shell = 83.625"
= 41.8125 in.
G R=
R = Inside Radius of Cask Shell =
R
- 1.25 = 40.5625 in.
g 4
6 3
12 EI = E 3 - (R -Ry) = 29 x 10 x 274 x 10
= 7.946 x10 x 32.2 x 12/684.49 x 83.5 )b 4
1 fn = (9.87/2g1) (7.946x 10 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 l
l t
2.6-12 Revision 1 7/31/84 i
2.6.6 WATER SPRAY q
A heavy water spray on the package will not harm the package because it V
is constructed of ASTM A516, Grade 70 steel.
Inaldition, 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 the 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 toroidal ring will be attached 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 2 " 0.D. x h," thick steel tube made from 1020 steel cold drawn over mandrel 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:
y A + 0.4 E=
R R
Where:
E = Energy absorbed (in-lb)
Sy = Yield ^ strength of steel (psi) t - Tube thickness (in) 6' L = Tube length (in)
R = Mean radius (in)
A' = Deformation of tube (in) and as shown in Figure 2.6-2.
The energy which must be asborbed by the tube for a 1 foot drop E = 66,720 lb x 12 in = 800,640 in-lb For the 21" tube described above 3
.Sy = 60,000 psi t = 0.25 in L = 83.625
- 262.7 in R=2.5+2
" I*I 4
Substituting in the above equation:
60,000 25)2(262.7) 2 800,640
=
+
6 0 = 0.72 O
Since the I.D. of the tube is 2 inches, the tube can accommodate the deformation caused by a 1 foot drop of the cask.
2.6-13 Revision 5 - 6/10/85
Toro'pru Rina Er4ERGY /)E60R6EC O
~
Q\\NG WELp
~
v D
gf Y
\\
s 8185 U)EL) 7 BOLT R MG UiSK 00TN j
5%Lt-FIGURE 2.6-1 TOROIDAL RING ENERGY ABSORBER
'a
..' %g,-
N.
N,
\\
'%,t 4 %
FIGURE 2.6-2 DEFINITIONS OF TERMS USED IN EO. IN SEC. 2.6.7 2.6-13a Revision 5 - 6/10/85
The tube will be welded to the cask outside shell with two " fillet welds using E70 ksi Iow hydrogen electrode, which has an allowable
- p) 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 loaded cask Ng = the mean no. of g's the cask subject upon impact 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 2.224 x 10 kip Therefore, F=
(66,720)1bs
=
72 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 = 23Y(83.625)(0.354) = 186 In The tensile stress on the veld area is:
3 f, 2.225 x 10 kip
= 11.96 ksi 186
[2' 1.76 Safety Factor =
=
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 1.75.
b J
2.6-13b Revision 5 - 6/10/85
1 The calculations which follow show that the cask drop energy is readily absorbed by the deformation of a small fraction.of the surface of the cask
'l shell extension, during a bottom and drop of the AP-300 ca h through a V
height of 12 inches.
S.T. Rolfe and J.M. Barsom in their book " Fracture and Fatique Control in Structures" state on page 190 that the dynamic yield strength is approxi-mately equal to the static yield strength plus 25 ksi.
Table 1 on page 17 of the WRC Bulletin 299(11/84) lists the value for yield strength of A516 Gr70_from 38.6 ksi to 45.4 ksi.
For our calculations, we used a dynamic yield strength of 68 ksi.
The energy of the end drop is:
E= Wh = 66,720 lbs x 12 in. - 800,640 in-lb The volume of A516 Gr70 steel to absorb this energy is:
y, E_,800,640 in-Ib = 11.77 in 68,000 lb/in The surface of the shell which can be impacted by a bottom end drop is:
A = 7tf4 (83.6252 - 81.125 ) = 323.5 in 2
2 The depth.of the shell extension deformed to absorb the drop energy is:
g\\
/
3 Y
11.77 in d=A
= 0.036 in
=
323.5 in Consequently the drop energy can be absorbed in the extension of the shell in the bottom end drop.
The g loading on the cask lid under the impact conditions can be calculated by dividing the drop height by the stopping distance, as shown in Section 2.7 of the Cask Designer's Guide (ORNL-NSIC-68).
~
g=
36 I
The g loading on the lid will therefore be Fg - Wg = 9.46 kip x 333.3 = 3,150 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 f(81.125 - 76 )
632.5 in A=
=
Subtracting the area of the 36 bolts, the net area is:
A = 36 x (0.7656 ) = 16.6 in B
t J
632.5 - 16.6 = 615.9 in 2.6-14 Revision 5 - 6/10/85
The stress on the plate will be:
O
[
= 5.11 ksi
=
The SA-240 plate, with a yield strength of 30 ksi, will not bend out of shape under a stress of 5.11 ksi with a safety factor of 5.87.
SF =
= 5.87 2.6.8 CORNER 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).
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 irpact, is indicated as Z.
O t
0M FIGURE 2.6-3 CORNERDROPDEFORMATIONGEOkTERY 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:
Tan A = 41.8125/49.33" =.8476 h
A = 40.28*
2.6-15 Revision 5 - 6/10/85
e q
(
x,1 2.6.8.1 Bolting Design The bolts, screwed into the helicoil inserts are designed to withstand the expected decelerating forces.resulting from the* impact resulting from a one foot drop at the impact velocity.
[
The helicoil is inserted into the bolt ring which 1s fabricated of 2
SA-240 Type 304 with a minimum yield of 30 kip /in. The root diameter of the 1.5 inch long helicoil is 0.79 inches. Therefore, at yield, the tensile strength of the helicoil in the metal ring is:
F = 30,000 lb/in x 1Y(1.5)(.79) = 112 kip The tensile strength of the helicoil assembly based on the manufacturer's data, shown in figure 2.6.3, is 125 kip.
The bolt which will be used is a 3/4 igch SA-320 Grade L7A bolt with a minimum tensile strength of 125 kip /in. Therefore, it will be capable of resisting a force f(.75)
= 55.2 kip F = 125,000 lb/in x
Therefore the bolt will yield before either the helicoil, or the ring material when an excessive force is arglied to the assembly.
This is the basis of selection of the bolt specification.
2.6.8.1.1 Indirect Damage The indirect damage as a result of the drop would be a result of the f
vertical and horizontal "g" loadings generated by the cask lid and contents on the closure bolts. Therefore, an evaluation of the closure bolts is performed to determine the minimum bolt area and the number of bolts required to sustain these loadings.
For the corner drop, the moment produced by the payload impacting on the lid with respect to the impacted corner is shown below.
v 2.6-16 Revision 5 - 6/10/85
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3.0 THERMAL EVALUATION g
3.1 Discussion
)
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 he.at of 20 Ci of Co-60.
Co-60 releases 2.5 Mev per disintegration.
The decay heat released by 20 Ci of Co-60 is:
f 10
-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
()
maximum accessible surface temperature allowed by regulations and, therefore, cask access will not be lii..ited 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.
The cask is designed to withstand the combined drop, puncture and fire accident conditions without releasino any of its contents.
The cask is' protected from the fire accident by an external fire shield which maintains the lead 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.
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
(])
retained in the cask under the fire accident condition.
3.1,1 Revision 5 - 6/10/85
l c'
3.2 Summary of Thermal Properties of Materials i c'T The thermophysical properties of the materials 'of construction
- l,_)
of the cask are presented in this section.
For the Steady State Thermal Calculations C
i Material (Btu /hh-Ft*F)*
(Btu /lb
- F)*
Carbon Steel 26 0.11 Stainless Steel 10 0.11 Lead 19.5 0.03
- John H.
Perry, Chemical Engineering Handbook, 5th Edition, McGraw Hill 5
3.3 Technical Specifications of Components r
This section contain_s 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.
l Two key items are the closure assembly and pressurized vent esf)i x_
seals.
These seals are made from Johns-Manville " Red Devil" material, with a continuous operating temperature limit of 700*F.,
t l
6w
?
?
e
?
I I
a S.
b
\\~)
ev
?
3.2-1
3.4 Thermal Evaluation for Normal Conditions of Transport The effects of the normal thermal conditions of transport have llh 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 BT or based on the cask suface area added to Cm Cm the maximum 150 watt 1 cad.
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 trial and error as suggested in the reference.
Using the properties of the cask materials, the temperature profile across llI the cask was also determined.
For heat removal from cask surf ace and to determine Gae cask surface temperatures, the following relationship was used.
A(T
-T)
OT"ht s
a Where:
QT = total heat transferred - BTU /hr total heat transfer coefficient - BTU /hr - ft2 _ op h
=
t 2
A=
surface area of cask for heat transfer - ft T=
surface temperature = "R s
T=
ambient temperature =
R a
and:
ht = he +h r 2
h
= convective heat transfer coefficient = BTU /hr-ft
- F c
2 h
= radiation heat transfer coefficient = BTU /hr-f t
- F r
O 3.4-1
b) c = C (T -T,)1/3
=.19 (T -T )l/3 h
3 s
[T, Ts hr = 0.173 6
~
j a00/
200/. J (T
a)
-T s
C= Constant Given by ORNL-68 For heat transfer through cask and to determine the temperature profile,the following relationship was used.
O (t) kA aT T
O OT*
t kA O
Total heat transferred
BTU /hr T
k
thermal conductivity
BTU /(hr-ft ) (*F/ f t) 2 A=
area through which heat is conducted = ft t=
thickness of solid = ft 6 T=
temperature drop across conductor Ob To calculate the temperature drop across the cask body, it is i
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.
O
= 512 BTU /hr T
A=
(83
- 5) (96)T = 175f t T
= 540'R a
Assuming:
T R
h h
h aT O(BTU /hr) s r
c 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 The temperature at which the cask can dissipate 512 BTU /hr is about 82.6*F, by interpolation.
i 3.4-2
To determine the A T through the conducting substances the h
average areas are as follows:
Area of outer shell =
(83.625 + 81.125) (96)T _ 172.5 ft 2 2
144 Area of inner shell =
(76 + 77)
(87.4) T =
145.9 ft 2 2
144 (81.125 + 77)
(87.4) 7 2
Area of lead
=
150.8 ft
=
2 144 A T outer shell = (512 BTU)
(1.25 ft) r 12 0.01'F
=
26 BTU (172.5 ft )
hrft (512 BTU) 0.5 ft a T inner shell
=
hr 12 0.01 'F
=
[10 BTU
\\ (145.9 ft2) hrft /2 ft 512 ETU 2.0625 ft A T lead
=
hr 12 0.03 'F
=
19.5 BTU T
(150.8ft2)
(hr - ft2)j FYt ]
The resulting taperatures of the cask shells and lead are:
2.61*F
=
outer shell 82.65 F
=
inner shell 82.64*F T
=
lead h
i O
3.4-3 I
r~
The temperature of the inside shell surface is almost the C)'
same as the outside surface, therefore, the total heat transfer coefficient can be interpolated from above to be about 1.13 BTU /hr ft2 F.
The heat transfer area to the inside shell is:
rl --
136.0 ft.2 l
A= (76)(82) ft
=
144 T = 512 BTU /hr
= 3.3*F (136 ft )(1.13) BTU hrftF 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) T 2
130.9ft
=
144 512 BTU /hr 3.3
'F
=
m)
T=
(130.9 ft2) (1.20 BTU /hrft *F)
V The maximum temperature of the inside container surface is less than 90 F.
3.4.1.2 Ambient 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 discipated from the surface of the cask, the surface temperature for these conditions can also be determined by trial and error.
O
= 512 B T
+ 175 ft (122.8) BTU
22,000 BTU /hr hr ft A
175ft T
= 560*R a
3.4-4
Assuming:
h T *R h
h h
T Q(BTU /hr) g r
e t
625 1.15 0.76 1.91 65 21725 630 1.17 0.78 1.95 70 23890 The temperature at which the surface can dissipate 22,000 BTU /hr is about 165.6*F by interpolation.
The AT across the cask components can be determined as follows:
(22,000 BTU /hr) I.25 I
ft AT
=
outer shell
( 12 0.50*F
=
\\
6)
BTU 2
172.5 ft hr fte/*F/ft (22,000 BTU /hr) 2.0625 O
=
1.29'r
=
(19. 5) BTU 2 *F (150.8 ft2) hr ft ft 22,000(BTU /hr) [0.5fth h
T
=
o inner shell
\\ 12
/
= 0.62 !F (10) BTU (145.9 ft2) hr ft
- F f t' The resulting temperatures of the cask shells and lead are:
T outer shell T
lead Tinner shell =
168.0 *F The total heat transfer coefficient at the inside shell surface can be assumed to be 1.94 BTU hr ft2*F 83*F 4T= 22,000 BTU /hr
=
(136 fte) (1.94) BTU _
hrft4*F The temperature of the air inside the cask will be 250 F.
O The cask contents consist of dry substances which will not be affected by the cask temperatures under these conditions.
3.4-5
3.4.2 Maximum Temperatures
,-)'
I
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 surface of the outer shell and the ambient air, and the surface of the inner shell and the air ir. side 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 tanperature, solar load and f(,'I 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 cash can be determined.
P2=T2.P /Ty= (710)'R(14.7) psia / 540*R y
os 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.
3.4-6
At the ambient condition of -40*F, no internal heat generation or colar load, the packaging is isothermal at -40'F.
This condition causes thermal stresses between the lead shield and the inner shell lll because of the greater contraction of the lead shield, discussed in Section 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 o temperature difference of less 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 conditions need not be considered for the AP-300 cask, when it is used to transport greater than A quantity LSA waste packages.
O 3.4-7
a A -,
4.
CONTAINVENT YY 8
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4.0 CONTAINMENT 1
This chapter identifies the containment provided by the AP-300 cask and discusses the containment provided by the AP-300 cask under normal operating conditions, during cask transport and under hypothetical accident conditions as defined in 10CFR Part 71, Subpart F,
" Package and Special Form Tests".
4.1 Containment Boundary This section identifies the containment boundary provided by the AP-300 cask for material transport and specifies the design conditions to assure the presence of adeguate conteinment.
4.1.1 Containment Vessel The containment vessel for the AP-300 cask is designed as a free standing pressure vessel in accordance with Section VIII 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
(' }
C.
The lid gasket The inner vessel consists of:
1.
The inner shcIl (B-2) which is 0.5" thick and has a nominal inside diameter of 76".
2.
The bottom plate (B-4) which is 0.5" thick and has a diameter of 76".
3.
The bolt ring (B-5) which is 2.25" thick and has a nominal inside diameter of 76".
The parts of the lid that form part of the containment boundary include:
1.
The lower plate of the lid (L-2) which is 0.5" thick and has a nominal diameter of 76".
2.
The lid plate ring (L-3) which is
- 0. 9' thick,
6.24" high and has a nominal diameter of 76".
3.
The upper lid plate (L-1) which is 2.0" thick and has an outside diameter of 81-1/8".
(')
The lid gasket has a nominal inside diameter of 76".
us 4.1-1
,m
()
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 test 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 10 psig internal pressure.
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 transpprt 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.
G
-V 4.2-1
4.2.2 Pressurization of Containment Vessel lll The contents of the containment vessel will be only solids, with no possibility of 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:
5l
= 17.7 psia 2
14.71b/in The 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 Reauirements 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.
O 4.2-2
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5.
SHIELDING EVALUATION i' i' 8
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ll 5.0 SHIELDING EVALUATION wi 5.1 DISCUSSION AND RESULTS Type B - Curie Content The cask will handle a maximum of 20 curies of Co-60 equivalent.
The contact dose rates, shown in Table 5.1, 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 Packaae Surface Surface of Packace Side Top
-Bottom Side Top Bottom Normal Conditions ni,-)
Cama 8.0 9.2 9.2
<8.0 c9.2 49 2 Neutron no neutron dose rate Total 8.0-9.2 9.2
<8.0
< 9. 2
<9.2 Hypothetical Accident Conditions D3 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 5.2.1 Gamma Source For design and analysis purposes, the activity concentration of the radioactive material is to be considered 100% Co-60,
,Q and its energy, E
= 1.25 MeV.
V (0.5 x 1.17 MeV) + (0.5 x 1.33 MeV) = 1.25MeV E
=
(average) 5.1-1 g
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5.2.2 Neutron Source' O
The AP-300 will not carry neutron sources.
5.3 MODEL SPECIFICATION e
a.-
R o = 37.5a Geometry w
void Fe Pt Fe
(/
f g
/
i
- 0.5' O.5' L 2' 1.25 o> - cz 5.
3.1 DESCRIPTION
OF THE RADIAL AND AXIAL SHIELDING CONFIGURATION (P' contact)
Case fl, Dose rate at the side wall 1
l l
i Where:
R O " 7 9. 5 "= 2 0 3. 2 cm h
=
Void space = 0.5" = 1.27 cm l
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 Volume of liner = D o h = 5.79 x 106 cm3, 2
R 5.3.2 shield Regional Densities The shield material provides shielding only for car.ma sources.
The densities of the materials are listed belot.:
Steel = 7.67 gm/cm g
3 Lead
= 11.34 gm/cm 5.3-1
5.4 Shielding Evaluation
.p/
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 a = 10.80cm = 0.113; Ro 95.25cm The source material is assumed to behave as carbon, which has a mass absorption coeff. Jus) of 0.06 cm-1 for a gamma energy level of 1.25 MeV (Eg)
So:
eL s (a + Ro) = 0.06 cm-1 (10. 80cm + 95. 25cm) j
= 6.36 From Rockwell, pg. 362, with :_a = 0.13; and Ro b' s (a + Ro) = 6.36; m = 1.1 j
The linear attenuation coefficients jg) of the shieldang material are:
-{ j
-1
/AFe = 0.391 cm-1[ Pb = 0.68 cm and the thicknesses are:
tre = 4.45cm and t b = 5.0Bcm P
NOTE:
The thickness of the liner has not been incorporated in these calculations, since neither the value of the thickness is known, nor the material of construction.
The void space (air) has also been neg3ected.
So: the attenuation factor; by is:
by = )Di ti 4here:
j0li = linear attenuation coefficient of the "i" material (shielding).
g = thickness of the "i" material.
t O
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 DetermintvLon of Ang)e 0 i
tz a-( i >.
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l
- 2
- - ~ ~)%
O=&"
e" 3
2 V
h r
a+z 100.97 cm
1.534 tan O
2
=
a+z (10.80cm + 55cm) 0
~1 0 = tan J.534 = 56.90*
Calculation of F(0, b ) (Rockwell, pg. 386) 2
= 5.2 + (0.06cm-1) (55cm) 0 = 56.90*; b2=by+[sz b2 = 8.5; and F (0, b ) = 8 x 10-5 2
Calculation of build-up factor B (Eo/L x)., For design purposes the build-up factor will be the one of the outermost layer; t= 3.18 cm.
= Ay e '# [
8
+A2
[
iA1 = 1 -A2*
B (Fe)
From Rockwcil, pg. 418.
O 5.4-2
A1 = 9.4-M1 = 0.0825 A2 = -8.4 82 = 0.0525
.O (0.0 25)<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
- Calculation of gamma flux at P1 per curie p = B SvRo2 [F(9)b2)l N
2 (a+z) cm2-sec-curie Sv = Volumetric source strength /cm3
_[
Sv
/I x 3.7 x 1010
N volume cmJ-sec-curie The volume of the liner is: 5.79 x 106 cm3 So:
Sv
= 2 x 3.7 x 1030 = 1.278 x 104 N
5.79 x 100 cm3-sec-curie (2.54) (3.278 x 10 ) (95.25) 2 (8 x 10-5) 4 and:
7
=
=
N 2 (10.80 + 55) 2 g
1.79 x 10 cmd-sec-curie Determination of dose rate / curie at P1 (contact)
(1.79 x 10 ) (2.22 x 10~3) l 2
Dose Rate (mR/hr/ curie)
=
Curie Dose Rate = 0.4 mR/hr/ curie Curie For Maxinum quantity of curies Dose Kate = 0.4 mL 20 Ci,
8 rf x
hr/Ci hr Case 92.
Top & bottom shielding calculations
[
1.
The gamraa flux (7{} 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 f
hr O
2.
ror aaximum su tiiv of curies 20 C1 dose rate (mR/hr = 0.46 mR/ curie x fir
= 9. 2 mR/hr a u
5.4.2 Free Drop Gamma Shielding in end drop of a cask in which the 3ead is not bonded to h
the steel she31s, can cause the 3ead to settle, thus creating a void in the end opposite the impact end.
According to Shappert (ORNL-NSIC-6 8 ) the change in Jead height is:
8H=
RWH (R2-r2) (ts 6 s + F(L) htere:
R = outer radius of 3ead = 40.5 inches r = inner radius of Jead = 38.5 inches
- 4l W = weight of cask plus contents = 66,720 lbs.
3.25 inches ts = thickness of outer stee) she))
=
6s = dynamic f3ow stress of stee) she13 = 60,000 psi (L = dynamic f3ow stress of lead = 5,000 psi H = height of drop = 3 2 inches (3 ft) 4 Thus: H=
(40.5) (66,720)
(3 2) 1 (40.5) 2-(38.5) 2) I (3.25) (60,000) + (40.5) (5,000) ]
4 H = 0.74 inches The geometry wil] be:
g Ring 3 7(, Inches 0
y
/
n Source Liner 80' 87'
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ei y
\\
b As a resu3t, the contact dose rate wil) not be affected by the 0.74" J ead s3 ump, since there will not be a source 4,
window without Jead shielding.
The cask is designed to withstand a Jead slump of 6.73 ".
e i
Revision 4 - 4/15/85 5.4 4
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6.
CRITICALITY EVALUATION a
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6.0 Criticality Evaluation O:
No material which is subject to criticality conditions _will' i
be transported in the AP-300 cask.
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7.
OPERATING PROCEDURES yy a
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7.0 OPERATI11G PROCEDURES 7.1 Procedures for Loading the Package 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, Joading and dispatching of the ANEFCO AP,300 cask in a safe and efficient manner.
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 only to bolt the cover, according to the torque (V
procedure (Attachment "A")
to prevent damage to
'T bolts and cask threads.
4.
Caution: A potential radiation streaming, hazard exists when the cask is loaded with the cask head not torqued down.
Use appropriate care, and use shielding apparatus when necessary.
5.
If, while detorquing the cask head, it is determined that the head has backed off unevenly and is binding, 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.
NOTE: This should not prec3ude replacement of the gasket if any imperfectio.ns should appear or if it warrants the replacement due to. failure during leak testing.
i V
7.1-1
7.
If any abnormalities are discovered with the cask, cask head, head p
gasket, or the cask equipment, notify ANEFCO at the Ridgefield d
Office (telephone (203) 431-3358) obtain advice on continued use of the equipment and follow such advice.
8.
Caution: Lifting assemblies for the AP-300 cask should be 4-59" A
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 lifting operations.
9.
Caution: Lifting 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
'l.
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 e_quipment.
~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 lif ting assembly (4-2" shackles and four equal length wire rope g
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 5 -6/10/85
I I
i 11.
Place poly sheeting or equivalent onto bay floor insuring an area large enough to place both cask and lid onto plastic (84 sq.ft.)
g (optional).
W' 12.
Caution: Using a hand torque wrench and 5/8" hex setscrew bit i
socket, loosen cask lid bolts. Using rotational 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 4-1\\" bolts from top of lid and install 4-1k" eye bolts in jr their place, 14.
Attach lid lifting assembly to lid lifting eye bolts (4 " 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 llh 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.
Af ter radiation surveys are complete lif t the lid the remaining distance needed and place onte plastic previoucly laid on bay 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.
Inspect cask gasket to insure it is in good condition and all bolt holes line up correctly.
If any imperfection is discovered, contact ANEFC0 at Ridgefield Office, (203/431-3358) for advice on continued use of the equipment.
19.
Inspect the cask cavity to insure that no water is present. All water in cavity must be removed before the liner is installed in cavity.
Cavity walls must be dried, e.g. by swabbing walls or other I
means.
7.1-3 Revision 5 - 6/10/85 L
1.
20.
Perform radiation surveys of the liner to be loaded both dose 3
rate.and smear test. Decontaminate any external loose contami-
_(V 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.
23.
Attach lifting assembly (4 " shackles and 4-25" long wire rope I
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.
LOWER the cask lid slowly until it is t.pproximately 1" down within i
the outer cask body. Align lid seal 1 lock on lid with grooved recess in cask body.
26.
STOP LOWERING 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 pV AP-300 " Bolt Torque Proceudre" drawing Attachment "A" for location of bolts).
28.
Resume LOWERING 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 4-11r." eye bolts and replace with 4-1k" hex bolts.
NOTE: Decontamination activities (if required) may proceed simultan-iously to torquing.
Caution:Radiat; ion streaming 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)respectivelyof10CFR.
30.
Lubricate using a suit'able lubricant, 'and install the remaining 32 bolts finger tight.
31.
Caution: Using a hand torque wrench only, torque the lid bolts to 22 f t. Ibs. in the sequential order shown in AP-300 cask
" Bolt Torque Procedure" drawing (Attachment "A").
bv 32.
Caution: Using a hand torque wrench only, torque the lid bolts to 44 ft. Ibs, in the sequential order shown in AP-300 cask
" Bolt Torque Procudure" drawing (Attachment "A").
7.1-4 Revision 5'- 6/10/85
h.
t 33.
Caution: Using a hand torque wrench only, torque the lid bolts to 66 ft. lbs. in the sequential order shown in AP-300 cask ll)
" Bolt Torque Procedure" drawing (Attachment "A").
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 Procedare" drawing (Attachment "A").
35.
Caution: Using a hand torque wrench only, torque the lid bolts to final torque value 110 ft. Ibs. in the sequential order shown in AP-300 cask, " Bolt Torque Procedure" drawing Attachment "A".
36.
Caution: Using a hand torque wrench only, use rotational tightening at 110 ft. ]bs. 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, (Attachment "A").
. NOTE:
Steps 38, 39, and 40 are uced only if cask was removed from trailer to facilitate loading of liner.
2 l
- 37. Install security lead wire seal.
38.
Attach lifting assemblies (4-2" shackles and 4-equal length wire rope slings with a minimum rated capacity of 80,000 lbs) to the lll 1
AP-300 cask lifting / tie down eyes located on the side of the outer shell of the cask body.
39.
Lift cask up 2 ft. and have radiation protection perform a swipe survey of the cash bottom surface for externally loose contamination.
Decontaminate cask bottom surface if necessary.
Ei 40.
Lift and place AP-300 cask within its transport ring located on the trailer.
41.
Replace canvas AP-300 cask cover over AP-300 cask and secure at base.
42.
Retrieve tie-down pins.
43.
Fasten the (4) four tie down cables to the cask as per AP-300 cask
" Tie-Down Assembly (top view)" (Attachment "E").
Tighten tie-down assembly. Torque each bolt evenly to 100 ft. Ibs.
\\
O 7.1-5 Revision 5 - 6/10/85
c 5
44.
Caution: Insure 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 labeling and placards.
- 45. -
Insure driver has all necessary forms for shipment and all documents and check lists are completed.
I 46.
Remove the wheel chocks and release the trailer brakes.
E.7.,
Perform a final cursory visual inspection of the trailer.
s 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 A5J Thejadditional 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 Requirements for Radioactive Materials", a copy of.which is shown in Section 7.4.
4 9
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7.1-6 T
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Procedures for Unloading tAe Package 7.2 7.2.1 Purpose The purpose and inte t of this procedure is to define the safe hand)ing and the proper radio 3ogical controls
'necessary for receiving, un3oading and dispatching of the ANEFCO AP-300 cask in a safe and ef ficient manner.
Preparations for Unloeding 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.
g i
Insure truck / cask tie-down devices are secure and 1.
in proper working order.
Always use a calibrated hand torque wrench Caution:
- 2. on3y to bolt the cover, according to the torque procedure (Attachment "A") to prevent damage to bo3 ts and cask threads.
Caution: A potentia) radiation streaming, hazard exists when the cask is unloaded with the cask heed (gp 3.
Use appropriate care, and use not torqued down.
shie3 ding apparatus when necessary.
If, while detorquing the cask head, it is determined the head has backed off uneven 3y and is 4.
binding, the head must be fu]Iy retorqued and the that Extra care should be detorquing operation restarted.
exercised to ensure that the head backs off evenly.
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 follow such advice.
Caution: Lifting assemb3ies for the AP-300 cask should be 4-equal lergth wire rope slings with a r~.uunu.
6.
rated capacity of 80,000 lbs. as per federal specification RR-W-410.
Lifting assemblies for the AP-300 cask 7
Caution:
Jid should be 4-36 ' long wire rope slings witn a kh Einimum rated capacity of 12,500 lbs. as per federal The wire cables must alwaye be smcification RR-W-410.
at an angle of 90* from the horizontal during lifting operations.
7.2-1 P.evision 2 - 11/28/g4
7.2.3 Unionding ProcOdurp Ensure that a copy of tha chock liot for this 1,,
procedure is on hand for use during all phases of cask handling.
O Upon receiving the AP-300. E:ask 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 ANEFCO, at Ridgefield Office (203/431-8358) for advice on continued use of the equipmdnt.
Position cask and trailer into handling bay.
4.
Set trailer brakes and place wheel chocks fore 5.
and aft of the wheels.
6.
Detach the (4) four tie-down cables from the cask side.
Place the main. pin back into the cask lif t/ tie down point to enable its use as lif ting" point.
p 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 lif ting assembly (4-2' shackles and 3
4-59" chockers within minimum rated capacity of 80,000 lbs.) to the AP-300 cask lifting / tie down eyes g
located on the " side of the ou'ter shell of the cask body.
The cask empty weight is 46,710 lbs.
l Place poly sheeting or equivalent onto ground floor l
11.
insuring an area large enough to place both cask and lid onto plastic ( 84 sq. ft. ) (optional).
Q Revision 5 - 6/10/85 7.2.2
12.
caution:
Using a h2nd torqua wrcnch cnd 5/8o hex setscrew bit socket, loosen cask lid bolts.
Set torque wrench to 110 ft. Ibs.
Using rotational order as shown in AP-300 cask " Bolt Torque a
W Procedure" (Attachment "A*), loosen each bolt 1/16 Continue until all of the bolts turn per pass.
are loose, indicating that the lid p e-load has been fully relieved.
NOTE:
This technique he3ps 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 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 I
bolts appropriately. Remove 4-ik" hex bolts from lid and replace with 4-lk" eye bolts. ~
14.
Attach lif ting assembly ( 4-1/2" shackles and 4-36
- long wire rope slings with a rated capacity of 12,000 lbs. )
gg)
CAUTION:
The lid cab 3cs 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 assessment.)
16.
Have radiation protection perform the necessary surveys.
17.
Af ter radiation surveys are complete lif t the lid the remaining distance needed and place onto plastic If the crane previously laid on the ground in Step $6.
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
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 of the equipment.
19.
Perform radiation surveys of the liner to be unloaded both dose rate and smear test.
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 7.2-4
Prop 7rntion of nn Dmpty Pocknga for Trnnsport 7.3 7.3.1 Purpose The purpose and intent of this procedure is to define the g
safe handling and the proper radiological controls necessary for preparing the empty ANEFCO AP-300 cask for transport, after the load has been removed from it.
General Preparations for Empty Package Transport 7.3.2 is in good condition prior Insure the cask lid gasket 1.
to shipment.
Insure truck / cask tie-down devices are secure and in 2.
proper working order.
Always use a calibrated hand torque wrench 3.
Caution:
only to bolt the cover, according to the torque procedure (Attachment "A*) to prevent damage to bolts and cask threads.
4.
l O
s.
If any abnormalities are discovered with the cask, cask or the cask equipment, notify ANEFCO 6.
head, head gasket, the Ridgefield Office (203/431-3358) obtain advice on continual use of the equipment and follow such advice.
at Lifting assemblies for the AP-300 cask Caution:
7.
should be 4 'apal lend wire rope with a rdnirum as per federal rated capacity of 80,000 lbs.The wire cables must always b[ecifications RR-W-410.at an angle of 90* frcn the horizontal during liftinc o s
7 Lifting assemblies for the AP-300 cask lid Caution:
E.
should be 44 36" long wire rope slings with a minimum j
rated capacity of 12,000 lbs. as per federal f
specification RR-K-410.
l G
l Revision 2 - 11/28/84 7.3-1
7.3.3 ' Procedures to Prepare Empty Package for Transport
(#
l.
Clean' cask interior walls and perform radiation survey to ensure that all loose contaminaion is removed from interior walls.
Use both dose rate and smear test. Radiation 1) ggconform with 10CFR71.87(i)(1) for allowable non-fixed radioactive contami-2.
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 of the equipment.
3.
Place any. installed shoring around liner if required back into cask.
4.
Attach lif ting assembly (4-1/2" shackles and 4 36 " long wire l\\
rope slings with a rated capacity of 12,000 lbs.)to lid lif ting eye bdits loca'ted in the etnter of the cask lid, 0
(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 3id 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).
Resume LOWERING the cask lid slowly, as the cask 9.
'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 misaligned. Remove lid g
lifting assembly, remove 4-lh;" eye bolts and replace with 4 -l h;" h e x bolts.
i NOTE:
Decontamination activities (if required) may proceed simultaneously to torquing.
10.
Radiation protection should perform swipe test of the
~
cask's outer surface to determine if any loose contamination j
is present. Radiation shall conform with 10CFR71.87(i)(1) for allowable non-O"ll.
Lubricate using a suitable Jubricant, and instal) the fixed radioactive contamination.
remaining 32 bolts finger tight.
Revision 5 - 6/10/85 7.3-2
}
1.
12.
Caution:
Using a hand torque wrench only, torque the lid bolts to 15 ft. Ibs. in the sequential order shown in AP-300 cask
" Bolt Torque Procedure" drawing g
(Attachment "A").
13 Caution:
Using a hand torque wrench only, torque the 3id bolts to 30 ft. Jbs. in the sequential order shown in AP-300 cask
" Bolt Torque Procedure".
Drawing (Attachment "A").
14,
Caution:
Using a hand torque wrench only, torque the lid bolts to 45 ft. Ibs. in the sequential 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 only, torque the lid bolts to fin ~al torque value 75 f t.
Ibs.
~
in the sequential order shown in AP-300 cask
" Bolt Torque Procedure" drawing (Attachment "A").
17 '.
Caution:' Using a _ hand torque' wrench ~only, use tightening at 75 ft. lbs. until all bolts are stable at final torque level (two complete times lll around is usually sufficient) 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 trai)er to facilitate uhloading of liner.
18 Attach lifting assemb]ies (4-2" shack]es and 4-59" long chokers with a rated capacity of 80,000 lbs.) to the AP-300 cask lif ting / t ie down eyes located on
- g the side of the outer shell of the cask body.
19 Lift cask up 2 ft. and have radiation protection perform a swipe survey of the cask bottom surface for externally loose contamination.
Decontaminate cask bottom surface as necessary.
O 7.3-3 Revision 5 - 6/10/85
20.
Lif t cnd p3cca AP-300 cock within its trenoport ring located on the trailer.
O 21.
o::tiran V5 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. Ibs.
'2 5.
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 labeling and placards.
'26.
Ensure driver has all necessary forms for shipment and all documents and check lists are completed.
27.
Remove the wheel chocks and re3 ease the trailer brakes.
O V
28.
Perform-a final cursory visual inspection of the trailer.
29.
Review the check list to ensure that no items were missed.
30.
Notify ANEFCO, Inc. (2,03/431-3358) transportation manager that the shipment is en route to generator site.
l i
l
,O V
7.3-4 Revision 5 - 6/10/85
7.4 Appendix 7.4.1 References 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
O 7.4-1
N AP-300 CASK LOADING PROCEDURE i 176.704 Oceaementa ertatwo se t,cn: port taxe e n.
(a) The sum cf the tr:nsport Inden:s for a!! pactinges of radioactive materiala not in freight container on board a vessel. may not e nceed 200 (Oj (b) Encept as provided in peregraph (e)of this section the sum of transport Indenes for packages hot in a freight container may not exceed 50 in any hold compartrnent. or defined deck area Each group of radioactive materfal packages mu'st be separated by a distance of at least six meters (20 feet) e.
at all tirnes.
(c) Emcept as provided in paragraph (e) of this section, the nurnber of freight containers with packages of radioactive snaterials contained therein rnust be lirnited so that the total surn of the transport indenes in the containers in any bold or defined deck area does not PART 17C -CARRIAGE BY VESSEL enceed 200, and;
- 21. In Part 176. Subpart hf is revised to (1)
- Die sum of transport indenes for read as follows:
any individual freight container.or
.gmup of freight containers. does nol Sutepart W--Detahed Requirements for exceed 50. and (2) Each freigh't" container or gr' up of *,
- Rad.oactJve Materials
." ~
o fre ght c ntainers is handied and stowed Ceneral stows'ge reg'uirernenta.
~.In such a manner that Fmups am.
,f 2 700 176 704 Requirements relating to transport separated from each other by a distance. -
17(.708 Segregation' distance table.
fof at least'six meters (20 feet) 176.710 'Cair fo!)oMrg leakage or s fting of (d) The limitations specified in.'
s.6osetsve materials.
., paragraphs (a). (b). and (c) of this 276 725 Contamination control.
section do not apply to consi nments of.
F
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Subpart M-Detatted Requirernents for' ' low specific actMty rnaterials if the
(_/
Radioactive Materials packages are roarked
- RADIOACTIVE LSA. and no Mssile Cass, 'or fissile D
g 176.700 ceneral stowage requirementa.
(a).Radinactive materi41s must not be Incluaed in the shipment.
slowed in the same hold with maU bags.'
-(e) For' exclusive use shipments, the'. '
~
(b) A package of radioactne'matenals.);mitations sp.e'cified in paragraphs (b).
which in still air has a surface and (c) of this section do not applyi!-
i temperature more than 5 C(9'F) abov.
- (1) For packages not in freight -
~
e.
the arnbier}t att may not be overstowed containers, the sum of the transport '
with any other carEo. If the pa'ckage is -
indenes of Fassue Class flpackages does stowed under deck, the hold or en in which 11 is stowed must-not esceed 50 in each bold.
g3 g,,; g g p
,.co
. the radiation level does not exceed 200 (c) Each MssUr Class ID shipment ' :.,
must be stowed in a separ' ate' bold.- '. mulirem per hour at any point on the sudace and 2 mhem at two meters (6 compartment. or defined deck area'and.
I"t) Emm ty outside sudace of the be separated by a distance of at least
.I. ht contamer and the sum of
'g six meters (20 feet) from all other transport indexes of Mesite Cass D..
' Radioactive Category D or'ID.YeDow packages does not eaceed 50 m each..,-
. labeled pacieges.For a shipment of I#sht cootamer and 200 in each hold or i
radioactive materials requiring defined deck area: and j
supplement al opera tional procedures.
W Each smup'of Mssue Cass D the shipper must fumish the master or P**lages is separated hom oGer person in charge of the vessel a copy of redioactive malen,al by a distance of at 3
the necessary operationalinstructions.-
least alx sneters (20 feet) at aD times.
I (Paperwork regu'vement encepted from
([) Ihe limitations specified in l
Oh, of Manegement and Edget approval) paragraphs (a) through [e) of this section f
(dj A persoo may not remain do not apply when the entire vessella l unnecessarily in a hold or cormpartment reserved or chartered for use by a sine e p) or in the immediate vicinity of any shipper under exclusive use conditions
'(
paclare on deci containing radioactive if the number of Fissile Cass D and l
materials.
/
MssDe Cass ID packages of radio' ctive i
a i
~
7.4-g y
i
/
.J en terials cbnerd the tess:el does not argul rly occepIId w:rliing sp:c:s.
incy be Io:did enbn:rd a veerel with the cppr priate orgreg. tion dist:nce C ce:d the cmrent cuthoriard m ep:ces th",1 rn;y be continu-Ily ocevpi:d cal:blish:d by demtnstr: ling th:1 direct il173 451 through 1H 459 of this bf any person (escept those sp;cca rnessurement of the radiation level at s:bch:pter.The entire shiprnent
- esclusively reserved for couners oper: lion enust be approved by the specifically suthorized to accompany regularly occupied working spaces and Offsc:of Harardous Materists such pacliages). and undeveloped film living quarters is less than c.75 millitem Regul: tion (OHMR)in advance.
than the distance specified soTable 11L per hour,provided that the vessel bas g
Where only one consignment of a been chartered for the exclusive use CI S l 176.708 $,egergetion estarste tatde.
radioactive substance is to be' loaded on compefent person specialized In the (s)Tchle 177 applies to the stowage of board a vessel under exclusive use carriage of radioactive material.
padr 31s of radioactive rnsterials on conditions. the appropriate segregation Stowage arrangements sha!! be predelermined for the entire voyage.
. board a vess'el with reEard to transport distance snay be established by
- including any radioactive substances to Indea numb' rs which are shown on the demonstrating that the direct.
Isbels Of individual paclages
- rnessurement of the radiation Icvel af be loaded al ports of call enroute.De e
R:deo:ctive Category D or ID Yeflow regularly occupied working spaces and radiation level shall b'e measured by a I;beled packages may not be stowed living quarters is less than 0.75 millirem responsible person skilled in the use of cny c1:ser to hving accorninodations.
per hour. More than one consignment rnonitoring instruments.
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(l ln CJ se of l' art, coIlision, or bredcge Involving any shipment of F dsolclive materials. Other than mat:rtls oflow specific activity. the r dici:ctive rnaterials roust be segryst:d frogn urmecessa'ry contad with personnel. Iri c.ase of obviiius :
lealtage. or if the inside conta*tner..,
cppeirs to be damaged, the ston age Cr:a (h:Id. compartment. or' deck area) cont:Ining this carro must be isolated as snuch ts possible to present radio.ective.
rnal:rtl from entering any person's % *.
through contact. irdalation. or, -
tiort No person may handle the-rna :ri:1 or remain *m the sTicinity unless,
supervis;d by a, qualified person. *.',..
.[b] A bold or compartment in which*"*
ledge cf radioactive'rr.aterials has occur 72d sna) not be used for other i
O'*
cargo untilit is decontamir. ate'd in
, tcturd;nce with the, requirements of,
114715.
(c) Ter itporting require me nts. s ee I
[ 171.15 of this subchapter. '.
$ 17L.7t$ Contamination contret E..
(:) Tach hold, compartment, or deck crn tied for the transportation oflow specific cclisity radioactise rnalertals end:t cactusive use conditions shat! be s reyed with appr prkte ridiation det:ction instruments after each use..
Such b: Ids. compartments, and deck Crrcs rn y not be used again until the,
r:de.lin dose rate at any accessible carf:ce is less than 0.5 rni!! ire to per ho r.cnd the removable [non timed) redinetive surface contamination is not _*
great:t Dan the L: nits prescribed in i 173 443 of this subchapte.r.,
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.f DRAWNSY C.Ce DATE: 10-20-82
//kYW AP 3Od CASK Attachment C DRAWING NUM8E R LIO Q AS KET A SS E M B LY 1'39-1
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' DsET2 GEN MASTER FORMiteMF g
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APPENDIX I
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TABLE ill - SLING CAPACITI ES., P UNDS OM LOAD N. #O LEGS V ERTI C AL CHOKER BASKET l
BRIDALI HITCH L
NOT I
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INCHES - (100 %) 17.5"7e OF ji2OO 7o OF 8 73 Vo O F I 41 % O F l 100 7. O F,
SLING.DI A V ERTIC AL I
'VERTIC All ; V E RTICAL V E RTI C AL VERTIC AL l VERTICAL,
1/4 830 622 5 1,k30 i
1,'71 l
330 1,660 2,000 l y
L 9/32 1,000 1 1,730 l
1,410 -
1,000
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.,4 :
. 3,760 3,250 2,d50 1,380 1/2 3,5ho 2,655 3,5ho i 7,000 6,100 3,000 9/16
~4,000 3,::c I
8,000
-6,900 5,640 k, coo -
5/8~
5,350 g h, n2 5, ll-10,700 9,300 7,500 5,350 '
3/4 6,800 y,.:c 13,600 11,700 9,600 6,800 1
10,000 !
'I:
20,000 17,300 1k,100 10;ooo ;
1 1/8 14,10o,
- ,5 5 i
28,200 24,200 20,000 1k,100 -
1 1 1/4 22,000
- i _i,5::
Il hk,ooo 38,000 31.000 22,000 1 5/16 19,000 i.6,23:
'li 39,000 31,800 26,500 19,000 1 1/2 2h,500
_i,3'I ji h8,ooo kl,500 33,800 24,000 [
1 3/4
- 29,500 22, 2:-
j; 59,000 51,000 1
40,600 29,500 i 22,i::
75,600 65,000 52.000 37,800 2
37,600 J
d 1/2 " l
_ 63,000 i 5h,7%
170,000 l 147,000
- 22,,02 _i 85,003]
f e
g 8
NOTES:
1.
Capacities foi bridal bitebes are for slings vlth 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 wire rcpe that has a breaking I
strenath greater than the breaking strength of hi-ply cable, the capacities any be one-sixth,
- the manufacturer's listed breaking strength.
3*
Rated enpacity is based upon a factor of safety of 6.
4.
Not a hi-ply cable *..-
5..
Basket bitenes are subject to diameter ratio requireme-ts of Appendix IV.
c her httches are subject t'o the 'de ra t ng, rements of Appendix IV or Column III above (w i, eve r t s mo re restrictive).
O 8.
ACCEPTANCE TESTS AND MAINTENANCE PROGRAM O
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8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM
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8.1 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 necescary and the tests repeated.
O 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 pressurized to twice the maximum normal operating pressure or 10.0 psig, whichever is greater.
This pressure will be maintained 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.
i The cavity will be pressurized to 1-1/2 times the maximum f
normal operating pressure or 7-1/2 psig, whichever is greater, with a gaseous mixture containing at least 10% of a test gas to which the leak detector is sensitive.
Testing may
{/1 be done by using a helium mass spectrometer or a halogen l
i leak detector if the testing procedure hgs been demonstrated l
to have a sensitivity equivalent to 1 cm (STP) of air per 1
i I
L 8.1-1
()
hour at the dif ferential pressure used in the test.
All em 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 performance 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 includes information concerning: (1) the electronic (2) the radiation source and strength, (3) the equipment, 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 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 h, ands, 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 exis~t in the sidewali or lid assembly in excess of 0.25" lead.
The scanning paths shall be reviewes 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 cargin.
()
8.1 2 Eevision 2 - 11/28/84
8.2 Maintenance Program The maintenance program is established to ensure continued performance of g
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 Pressure 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 signs of failure are found, the lifting pads will be replaced and load tested.
8.2.1.2 Pressure Tests On an annual basis, the cask cavity will be hydrostatically pressure tested to one and one half (1 ) times the maximum normal operating pressure.
Should a leak be found, it will be repaired and the test rerun.
8.2.2 Leak Tests Red Devil Gasket (or neoprene equivalent) and pressure port plugs tests.
t on an annual basis, the containment cavity will be pressurized to 1.5 the maximum pressure of the containment cavity during design conditions.
The pressure level will b_ checked over a 10 minute interval and no pressure llh 4
loss or evidence of Icakage during this period will be accepted. Should a pressure drop be noted, the cause will be found, repaired and the test with a sensitivity of 1x10-yyg11 be performed using a helium leak detector rerun.
An annual leak test d
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) sequential uses or if found unsatisfactory 4
during the annual Icak test.
There are no other components of the AP-300 cask which need maintenance.
O 8.2-1 Revision 5 - 6/10/85
Each of the 36 closure bolts will be inepscted 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.
p Each bolt hole will he 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 V
O c.2-2 Revision 1 7/31/84
O APPENDIX A - DRAWINGS V y' 8
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