ML20024C940
| ML20024C940 | |
| Person / Time | |
|---|---|
| Site: | 07109111 |
| Issue date: | 06/29/1983 |
| From: | CHEM-NUCLEAR SYSTEMS, INC. |
| To: | |
| Shared Package | |
| ML20024C939 | List: |
| References | |
| 22504, NUDOCS 8307200365 | |
| Download: ML20024C940 (57) | |
Text
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SAFETY ANALYSIS PIPORT FOR CHBI-NUCLEAR SYSTB6, INC.
g s
l0 DEL CNS 6-80-2 DOCgg i
[p AU TYPE A RADWASTE SHIPPING CASK usage z]
3 L 1 1 ggg3 8
NAfs3
!c$?g*g O
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b CHB 1-NUCLEAR SYSTB1S, INC.
l Corporate Headquarters Che Greystone West Building l
Suite 100 240 Stoneridge Drive Columbia, South Carolina 29210 i
l l
A l NN 0307200365 830629 PDR ADOCK 07109111 C
TABLE OF C0hTENTS PAGE NO.
1-1 1.0 GENERAL INFOR!RTION 1.1 Introduction.....................
1-1 1-1 1.2 Package Description 1-1 1.2.1 Pa ckaging..................
1-2 1.2.2 Operational Features 1.2.3 Contents of Packaging............
1-2 2-1 2.0 STRUCTURAL EVALUATION....................
2-1 2.1 Structural Design..................
2-1 2.1.1 Discussion.................
2-1 2.1.2 Design Criteria...............
2-1 2.2 Weights and Center of Gravity 2.3
!!cchanical Properties of flaterials..........
2-1 2.4 General Standards for all Packages..........
2-2 2.4.1 Chenical and Galvanic keactions.......
2-2 2-2 2.4.2 Positive Closure (Q>
2.4.3 Lifting Devices...............
2-2 2-6 2.4.4 Tie-Downs..................
2-8 2.5 Not Applicable....................
2-8 2.6 Normal Conditions of Transport.
2-9 2.6.1 lieat....................
2-9 2.6.2 Cold....................
2-9 2.6.3 Pressure..................
2.6.4 Vibration..................
2-11 2-11 2.6.5 Water Spray.................
2-11 2.6.6 Free Drop..................
2-11 2.6.6.1 Flat End Drop 2-19 2.6.7 Corner Drop.................
2.6.8 Penetration.................
2-19 2-19 2.7 liypothetical Accident Conditions...........
2-19 2.8 Special Foru.....................
2-20 2.9 Riel Rods 2-20 2.10 Appendix.......................
O.
i
TABLE OF CONTENTS (CONT.)
V(~h PAGE h0.
3-1 s
3.0 111ERMAL EVALUATION.....................
3.1 Discussion........'..............
'3-1 3.2 Summary of termal Properties of mterials......-
3-1.
3-2 3.3 Technical Specification of Components 3.4 Wernal Evaluation'for Normal Conditions of Transport 3-2 3.4.1 Wermal flodel................
3-2 3-2 3.4.2 4xitum Tenperatures 3-2 3.4.3 liinimun Temperatures 3.4.4 hximuu Internal Pressures '. a.......
3-2.
3.4.5 Maxinua 1hermal Stresses 3-3 3.4.6 Evaluation of Package Performance for Norcal-Conditions of Transport........
3-3 3
3-3 3.5 Hypothetical 11iermal Accident Evaluation.......
3-4 3.6 Appendix........................
3.6.1 W ermal Analysis - Normal Conditions of 3-4 Transport..
3.6.2 Geometry Assumption.,............
3-4 3.6.3
' External Convection and Radiant Heat pd 3-4 Transfer 3.6.3.1 Convection............
3-5 3.6.3.2 Radiation 3-5 3.6.4 HeatLoads-SolarandInternali.......
3:5 3.6.4.1 Solar Ioads
~
3-5 3-7
-3.6.4.2 Internal lieat 3-7 3.6.5 Steady State Solution............
3-7 3.6.6 Wall termal Gradient,
4 -1 4.0 CONTAINMENT.........................
4 -1 4.1 Containment Boundary.................
4-1 4.1.1 Containment Vessel 4-1 4.1.2 Containment Penetration...........
4-1 4.1.3 Seals and Welds...............
4-1 4.1.4 Closure...................
4-1 4.2 Requirements for Normal Conditions of Transport l 0 ii l
l h
j.
t
TABLE OF CONTBTS (CONT. )
(
PAGE NO.
4.2.1 Release of Radioactive h terial.......
4-1 4.2.2 Pressurization of' Contairment Vessel 4-1 4.2.3 Coolant Contamination............
4-1 4-2 4.2.4 Coolant loss................
4.3 Containment Requirements for the Hypothetical 4-2 Accident Conditions 5-1 5.0 SilIELDING EVALUATION....................
5.1 Discussion and Results................
5-1 6-1
6.0 CRITICALITY EVALUATION
7-1 7.0 OPERATING PROCEDURES....................
7.1 Procedures for loading the Package..........
7-1 7.2 Procedures for Unloading the Package.........
7-1 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGW1 8-1 8-1 Q
8.1 Acceptance Tests...................
8-2 V
8.2 Maintenance Prograu.................
9-1 9.0 QUALITY ASSURANCE......................
I i
i,f s
i O
iii I
I
~
- ~ ~
' - ~ ~
1 1.0 GENERAL INFOR!& TION O
1.1 Introduction
%e Model CNS 6-80-2 packaging is a reusable shipping package developed as a safe means of transporting Type "A" quantities of radioactive materials meeting the definition of "Iow Specific Activity." Fissile material is limited to those exempt quanti-ties licensed under 10 CFR 71.7.
Authorization is sougnt for shipment by cargo vessel, motor vehicle and rail.
1.2 Package Description 1.2.1 Packaging We package consists of a one-inch (1-1/8" for casks fabricated after October 31, 1980) external steel shell and a 3/8-inch internal steel shell.
Le annulus between sheels is filled with 4-1/4" of lead.
Equivalent lead shielding is 5.00 inches for Cobalt 60.
We top and bottom of the cylindrical cask are con-structed from a ' pair of stacked four-inch thick steel plates.
De removable lid is secured to the cask body by eight 1-1/4" studs with nuts (or bolts).
A 29-inch diameter secondary cask lid is located in the center of O
the primary lid.
It is secured to the primary lid with eight 1-inch studs with nuts (or bolts).
Broughout the rest of the SAR, use of the tenn studs is meant to include bolts also.
Both primary and secondary lids are sealed with' silicone gaskets.
The secondary lid employs a
redundant neoprene gasket.
A drain line at. the base of the package penetrates the containnent vessel.
%e drain line is sealed with a 1/2-inch NPT pipe plug.
All internal cask surfaces are lined with light gauge stainless steel to facilitate decontamination.
We internal cask cavity dimensions are 59" in diaueter I
and 58" high.
We cask is used to snip disposable steel liners and 55-gallon drums.
Tie-downs and lifting devices are structurally part of the package and are shown on the general arrangement drawing included in Appendix 2.10.1.
llaterials of construction are given on the drawings in p
Appendix 2.10.1.
Nechanical properties of materials Q
are given in Section 2.3.
1-1 4
y r
.---..-r-
+m.,-
,,--,...w
--w.
--n.
1.2.2 Operational Features O
Refer to the General Arrangement Drawing in Appendix 2.10.1.
There are no complex operational requirements associated with the package.
1.2.3 Contents of Packaging The contents of this cask will consist of:
(1)
Type and form of material (i)
Greater than Type A quantities of radio-active material as process solids, either dewatered,
- solid, or solidified, in secondary container (s),
meeting the requirements for low specific activity radioactive materials as defined in 10 CFR 71.4 (g )
(ii)
Greater than Type A quantities of radio-active material as activated solid cou-ponents meeting the requirements for low specific activity radioactive material as described in 10 CFR 71.4(g).
(2)
Ihxicum quantity of material per package Not to exceed 60 thermal watts of radioactive material.
The contents may include fissile mate-rials provided the mass limits of 10 CFT( 71.7 are not exceeded.
( O 1-2 l
2.0 STRUCTURAL EVALUATION Wis section identifies and describes the principal structural engi-neering design of the packaging, components, and systems important to safety in compliance with the performance requirements of 10 CFR 71.
2.1 Structural Design 2.1.1 Discussion ne principal structural member of the Model CNS 6-80-2 package is the primary containment vessel or transport shield, as described in Section 1.2.1.
he above components are identified on the drawing as noted in Appendix 2.10.1.
A detailed discussion of tne struc-tural design and performance of these components will be provided below.
2.1.2 Design Criteria he design loads used for this safety evaluation are those specified by 10' CFR 71 for Type "A" packagings.
Acceptance criteria of 10 CFR 71 require that shielding and containment for the package be maintained.
2.2 Weights and Center of Gravity 0
he weight of the cask and liner (or payload) will not exceed 51,500 pounds.
The cask weight is approximately 44,000 pounds.
We center of gravity for the assembled package is located at the approximate geometric center.
2.3 11echanical Properties of 1.taterials
%e Model CNS 6-80-2 packaging uses an outer and inner shell fabricated of various thicknesses of low carbon hot-rolled steel conforming to AS111 A-36.
For casks fabricated after October 31, 1980, low carbon steel shall conform to ASl}l A-516, Grade 70.
Both yield 'and ultimate stresses of A-516, Grade 70, are slightly higher than those of A-36 (5% greater yield; 205 greater ultimate).
For conservatism, the lower A-36 values are used for analysis throughout this report.
Specific properties are as follows:
Per fIIL-IIDBK-V Fu=
55,000 psi t
Fty =
36,000 psi Fsu =
35,000 psi Pbrg=
90,000 psi 2-1
Imad shielding will possess those properties referenced in O
oant-"stc-68' T*ble 2.6, Page 84.
Lid studs are all of SAE Grade 5 quality possessing the follow-ing properties, per AS111 A325 and A449:
1" 1-1/4" Proof Ioad:
78,000 psi 74,000 psi Tensile Strength: 115,000 psi 105,000 psi Tie-down lugs are fabricated of U.
S.
Steel T-1 material possessing the following properties per ASHI A-514:
2" Plate 115,000 psi Fu
=
t 110,000 psi Fty
=
65,000 psi Fsu
=
2.4 General Standards for all Packages his section demonstrates that the general standards for all packages are met.
2.4.1 Otenical and Galvanic Reactions ne materials from which the packaging is fabricated (steel and lead') along with the contents of the package will not cause significant chemical, galvanic, or other reaction in air, nitrogen or water atmosphere.
2.4.2 Positive Closure he positive closure system has been previously described in Secticn 1.2.1.
In addition, each package will be sealed with an approved tamper indicating seal and suitable locks to prevent inadvertent and undetected opening.
l f
2.4.3 Lifting Devices Three lifting lugs and four tie-down lugs are pro-vided.
L e package can be lifted by either the lifting or tie-down lugs.
We lifting lugs are primarily designed for lifting the lid only; however, for conser-vatism, it is assuned the total package is lifted via these three lugs. L e lug load is calculated as:
O 2-2
4 L = Wa /N; hhere: W = Package Weight P
g load Factor
,q ag = 141ciber of lugs Q
N
=
PL = (51,500)(3)/3 = 51,500 lbs.-
The capacity of the lug can be determined from the fol-lowing:
2: /K.~
U N
eg : \\.5 a / z,
- ii J
k
\\\\ \\ \\ \\ \\ \\ A.\\ \\
f
=
i
/"'
Using the standard 400 shearcut equation:
Pa = 2 Fsut ed-d cos 400 2
2
= (2)(35,000)(1.5) 1.5
.75 cos 400
= 97174 lbs.
We shearout margin of safety is:
M.S. = (97174/51500)-1 = +0.87 The capacity of the lug-to-lid weld may be estimated as:
Pa = FsuAw Aw = 1(tn) 1 = 2(4 + 1) = 10" l
tn=(1/2")h=0.707
("V" weld)
PA = (35,000)(10)(.707) = 247487 lbs.
We lug-to-lid weld margin of safety is:
!!.S. = (247487/51500)-1 = +3.81 2-3
Een lifted by the lid lifting lugs, each primary and Q
secondary lid stud is exposed to a load of:
Ps = Wag /N; Mere: W = Package Weight ag = Ioad Factor N = llisber of Studs Ps = (51500)(3)/8 = 19313 lbs.
L e tensile strength of the smaller secondary lid studs (1-8UNC, SAE Gr. 5) is:
A = F A = (115,000)(.563) = 64745 lbs.
P t
We secondary lid stud margin of safety is:
M.S. - (64745/19313)-1 = +2.35 loads from the lifting lugs are distriouted to tne secondary lid where they are reacted by the eight 1-inch diameter Grade 5 studs.
Le secondary lia :aust react these loads by plate bending.
From the sketcn below, it can be seen that the bolts tend to "fix" one end of the plate while the attachment to the two 4-inch plates provides the other fixity.
i y '
- 2. c u.2s'+
l l
l I
I
_l I
I#
/
/1
/
/
/
x /
N i
m P
lO 2-4 1
Bending stress is given as:
O 2
fb = 6P(L/2)/wDt
= (6)(51500)(3)(2.43/2)/w(34.25)(1)2
= 10467 psi it.S. = (36000/10467)-1 Pf.S. = +2.43 If for conservatism the same analysis was repeated assuming no fixity of the bolts, the stress would be:
fb = 20934 psi ff.S. = (36000/20934)-1 II.S. = +.71 Lifting loads from the lugs are distributed into the top plate and the lower four-inch plate by means of plug welds adjacent to each lug as well as a full perimeter weld.
Conservatively, assume only the plug welds as being effective. Capacity will be:
bd P=FAt
= 36000 psiw (1)2/4 in2
= 28274 lbs./ plug weld The margin of safety is:
Pl.S. = [(6 velds)(28274 lbs./ weld)/(3 g's)(51500 lbs.)]-1 bl.S. = +.10 Ultimate capacity of the plug weld is given as:
Pu = F uA t
= (55000 psi)(w)(1)2/4
= 43197 lbs./ plug weld or
= 86394 lbs./ lug O
2-5
tis load is (86394/51500 or) 1.67 times greater than
("]
the maxistan 3g load condition.
At loads greater than V
this, the one-inch thick top plate will locally shear from the lug, out to the adjacent studs.
Bis will leave the primary seal area uneffected and nave no detrimental effects on the packages ability to react other requirements of the subpart.
%erefore, it can concluded that the litting points are more than capable of reacting a load equal to three times the package weight.
2.4.4 Tie-Downs Four tie-down lugs are provided to resist transporta-tion induced loads. We applied load factors are:
x = 10g (longitudinal) a ay = S g (lateral) az = 2g (vertical)
Fach of the tie-down lugs is located at a 230 angle with respect to the longitudinal axis of the venicle.
Each tie-down cable is presumed to be aligned with the tie-down lug in a plane at a 230 angle witn respect O
to the longitudinal vehicle axis.
We cables are v
assumed to be tied to the vehicle bed four feet each side of the vehicle center line.
We following sketat illustrates the geometry of the tie-down scneme used for loads evaluation.
I k
l 9
l w
}
._ l
[
i su"l' g
\\
\\
/\\
./ \\
\\31k gd4 )-
\\
v I
.. N s O
2-6
o o
4*
g cram. oew ton)
O
~
n
}-OS 4237 0
9
)
x The tie-down cable geometry may be sumarized:
Direction length Direction Cosine longitudinal 1x = 77.99 Bx =.802920 Lateral ly = 33.10 By =.340819 Vertical 12 = 47.5 Bz =.489041 A vertical load produces a cable force of:
P z = Wa /43z; (4 cables acting)
T z
A longitudinal load factor produces a cable force of:
P x = Wa /2Bx (c)/(h) ; (2 cables acting)
T x
Similarly, a lateral load factor produces a cable force 1
of:
(c)/(h) ; (2 cables acting)
PTy = Way/2By For conservatism,' these three loads may be assumed to coincide for the most everely loaded cable:
Pr=Wn[g+ Y)
A A
c x
7
+nL
(-
37 10 5
2
= (51500)
-(2) (47. 5) 7079 N
(4)(.4890)
= 596726 lbs.
1 0
2-7 l
We capacity of each lug can be determined from the O
rotto ins:
4-,
Material:
d
~~ (n U. S. Steel T-1 y
d F u = 115,000 psi t
g nb.
\\
U g
Fty = 110,000 psi
\\
cL Fsu = 65,000 psi Using a 400 shearout, the lug capacity is:
d Ps = 2Fsut ed 7 cos 400j (2)(65,000)(2)(4 - f-cos 400) = 840,828 lbs.
=
We capacity of the lug-to-cask weld is:
Pw = FsuAwi Aw = 1(tn) 1 = 2(16 + 2) = 36" tn = (1") h/2 =.707" (Fillet)
Pw = (35,000)(36)(.707) = 890955 lbs.
Bus, the minimum margin of safety is associated wita shearout and is computed as:
M.S. =
0828 - 1 = +0.41 6 6 herefore, it can be concluded that the tie-downs are able to react a load greater than the combined 10, 5 and 2g tiedown loads.
Should the tie-cowns experience loads greater than 840,828 lbs., the lug will locally shearcut.
Bis will not impair the cask's ability to meet other requirements of the subsection.
2.5 Not Applicable 2.6 Normal Conditions of Transport he Model CNS 6-80-2 packaging has been designed and constructed, and the contents are so limited (as described in Section 1.2.3) that the performance requirements specified in 10 CFR 71.35 will be met when the package is subjected to the nor-mal conditions of transport specified in Appendix A of 10 CFR 71.
Re ability of the hbdel CNS 6-80-2 packaging to satis-factorily withstand the normal conditions of transport has been (e).
assessed as described below:
2-8 wa o
+y w
w 44
,,-\\-+w
+-+y m
-,e 4
,e w
,w,-
--wv, w---g-p---,ww-w wrwm-w,w
-wr
2.6.1 Heat O
A detailed thermal analysis can be found in Section 3.4
~ wherein the package was exposed to direct sunlight and 1300F still air.
De steady state analysis conserva-tively assumed a 24-hour day at maximum solar heat load.
We maximum steady state temperature was found to be 1740F.
Wese temperatures will have no detri-mental effects on the package.
2.6.2 Cold He materials of construction in this package are identical to those approved and used in numerous exist-ing licensed packages.
All of the following utilize the same materials:
1.
DOT 6400 Super Tiger 2.
DOT 6272 Poly Panther 3.
DOT 6679 Half Super Tiger 4.
DOT 6553 Paducah Tiger 5.
DOT 6744 Poly Tiger 6.
NRC 9069 - Model MO-1 Overpack 7.
NRC 9073 - Model 01-142 Cask herefore, on the basis of years of actual operating experience it is safe to conclude that cold will not substantially reduce the effectiveness of the package.
\\
2.6.3 Pressure 1
(
A differential pressure of
.5 atmosphere will be reacted by the lid and its associated stud closures.
I Loads on the lid studs are calculated as:
2 Ps = Ap/N; W1ere A = h p = 14.7/2 psi N=8 For the se.condary lid studs, the load is:
Ps "
j
= 607 lbs.
We tensile strength of the 1-8UNC, Gr. 5 studs is:
PA = (115,000)(.563) = 64745 lbs.
Bus, the margin of safety is:
O n.S. = c64745/6073-2 = + terse 2-9
.... ~.
For the primary lid studs, the load is:
(14.7J)T8T = 2576 lbs.
(1)
(59.75) ps "
(2)/
(4) g
'Ihe tensile strength of tne 1-1/4 - 70NC, Gr. 5 studs is:
Pa = (105,000)(.907) = 95248 lbs.
'Ihus, the margin of safety is :
li.S. = (95248/2576)-1 = +Large Stresses induced in the cylindrical portion of the cask are conservatively estimated by assuuing the pressure differential is totally borne by the 3/8-inch thick inner shell. 'Ihe hoop and longitudinal stresses are:
fn = PR/t =
= 578 psi 1*
h1 = PR/2t =
= 289 psi Assuming these biaxial stresses are additive, Od Fmax = 867 psi
'Ihe margin of safety is:
}!.S. = (36000/867)-1 = +Large Pressure across the end is carried in plate bending by the 2-4 inch thick steel plates top and bottom.
Assum-ing a circular plate, uniformally loaded and with edges simply supported, the stress can be calculated as follows:
fr = 3W(311 + 1)/8$1t2 (per "Ibranlas for Stress and Strain" by Roark)
Miere: W = (7.35)(7/)(70.25)2/4 = 28489 lbs.
t = 4" M = 1/.33 = 3 fr = (3)(28489)(10)/87/(3)(16) fr = 708 psi O
2-10
thrgin of safety:
M.S. = (36,000/708)-1 = +Large It can, therefore, be concluded that the packaging can safely react an atmospheric pressure of
.5 times standard atmospheric pressure.
2.6.4 Vibration Shock and vibration nomally incident to trasport are considered to have negligible effects on the Model CNS 6-80-2 packaging.
2.6.5 Water Spray Since the package exterior is constructed of steel, this test is not required.
2.6.6 Free Drop The Model CNS 6-80-2 shielded cask with payload weighs 51,500 lbs.
Appendix A.6 of 10 CFR 71 prescrioes a drop height of one (1) foot for packages in excess of 30,000 pounds.
Three drop orientations are possible:
flat end drop, side drop and corner drop.
For the flat end drop, the most critical condition will be set-O tlement of the unbonded lead shield at the end opposite v
the point of impact.
For the side drop, no closure or containment components are significantly stressed or deformed.
Consequently, the side drop case need not be evaluated. For the corner drop, the most critical con-dition will be lid closure.
2.6.6.1 Flat Bid Drop The evaluation of flat end impact upon set-tlement of the lead shielding closely fol-lows Shappert's approach for a cylindrical shield, outlined in Section 2.7.3 of his Cask Designer's
- Guide, ORNL-NSIC-68, February 1970.
The lead settlement distance l
is given by:
O 2-11 i
AH = RWH/g(R2 - r2)(ts s + Repb) a O
Wiere:
AH
= Settlement Depth (in)
H
= Drop fleight (in)
R
= Outer lead Radius (in)
W
= Weight of lead (1bs) r
= Inner lead Radius (in) t
= Thickness of External Steel Shell (in) s
= Steel Dynamic Flow Stress (psi) as opb = lead Dynanic Flow Stress (psi)
For the CNS 6-80-2 shielded cask, the vari-ables are:
H
= 12. inch R
= 59/2 +.375 + 4.25 = 34.125 indi r
r
= 59/2 +.375 = 29.875 inch 1
= 58 + 8-1.25 = 64.75 indi p
=.410 lbs/in3 W
= (R2 - r2)pl = 22685 lbs.
ts = 1 inch O
= 45000 psi s
o b = 5000 psi p
The predicted lead settlement is thus:
AH = (34.125)(22685)
(12)
= 0.050 inch 2
2
?f(34.125 - 29.875 ) [(1)(45000) + (34.125)(5000)]
O l
l t
2-12
This modest settlement " void" in the lead O
shie1d cannot transmit radiation because of the stepped design of the package ends.
The innemost four-inch solid steel end plates completely back (shield) lead settlement regions at both ends of the package.
- Thus, lead settlement due to a flat end drop does not compromise, nor alter, the integrity of radiation shielding in any fashion.
2.6.6.2 Corner Drop The impact energy associated with a corner drop will be absorbed by inelastic deforma-tion of the steel corner.
Using the
" dynamic flow pressure"
- concept, total defomation of the corner is estimated and used to compute package deceleration.
This deceleration is then used to check the integrity of the lid closure.
The volume of deformed steel is estimated by:
K. E. = hil K.E. = o Vs s
O Thus:
Vs = hlf/os hhere:
K.E. = Kinetic energy of drop (in-lb)
W
= Package Gross Weight (1b)
H
= Drop Height (in)
"s
= Dynamic Flow Pressure of Steel (psi)
Vs
= Volume of Deformed Steet (in3)
L The volume of deformed steel is thus:
Vs " (51500)(12) " 13*733 1"3 45000 l
l
! O 2-13
Deformation associated with this volume can
(
be estimated from the following geometric expression for a truncated cylinder:
s 3
2 t
r t rR w
. -1 r V = 2 sin n y + 7 7 7 - sin y
s t = (R - r )l; r = R - S 2
sin a M1ere:
S = impact deformation R = radius of package = 35.125" a = angle between package bottou and a horizontal plain = 43.50 For a
volumetric deformation of Vs
=
13.733
- in3, the corresponding corner deformation is found to be:
S = 1.26 indles The corresponding deceleration for an impact force which increases with deformation may be computed as:
. n 8 = 2(H/S) = (y
) = 19.lg's A
hhere:
Fis = Wi ag sin a Fc=Wi ag cos a i
i
= T, total package
= C, cask side and bottom
= P, payload i
= L, lid lit = Wc + Wp+W1 R
= Lid / Cask Binder Forces l
O I
2-14
O
@ *F s t
/
[= Deformation.
F tc I
h 1
suu / ymis,, /,i,,, -
[
Fts Ftc External Equilibrium Forces - Corner Impact
~
O Fcc Cask Freebody ps+k F.!/
F lR tc I
I l
pa
- l Fl F,+F s c
p vgFc t
Lid Freebody 1
[
'F Ic ts Fte-1atera 1 raui11dri==
0 Forces - Corner Impact 2-15
Bis deceleration imposes loads upon the Q
primary lid closure bolts as illustrated in the sketch on the previous page.
We total primary lid closure load may be estiuated as:
R = F c - Fcc = Fyr + F c t
p
= (WL + Wp) ag cos 43.50
= (7300 + 7500)(19.1) cos 43.50 = 205049 lbs.
Since there are eight primary lid closure studs (1-1/4-7UNC, SAE Gr. 5), each stud load is 25631 lbs.
We tensile strength of the stud is:
P =otA = (10500)(.907) = 95235 lbs.
%us, the margin of safety of tne primary lid studs is:
}!.S. = (95235/25631)-1 = +2.72
%e secondary lid closure studs are examined in a comparable fashion.
Conservatively, the total payload mass of 7500 lbs.
is assumed to be reacted by the secondary lid p>
studs.
Thus, the total secondary lid stud
~
load is estimated as:
R=(WL + Wp) ag cos a (2000 + 75000)(19.1) cos 43.50 = 131619 lbs.
=
Since there are eight secondary lid studs (1-8bNC, SAE Gr.
5), each stud load is 16,452 lbs.
The tensile strength of the stud is:
P = F A = (115,000)(.563) = 64745 lbs.
t
%us, the margin of safety of the secondary lid is:
11.S. = (64745/16452)-1 = g W erefore, it can be safely concluded tnat the package can survive a normal corner drop.
Detrimental effects resulting from a corner or side drops are limited to the closure creas.
Both primary and secondary lids are deeply stepped and manufactured l
2-16
from solid steel plates.
From the drawing, it can be O
seen that the primary 11d is desianed to be f1ush witn the external edge of the cask.
The side impact loads produce lateral shear forces that are reacted in direct compression of the lapped joint.
bolts securing the primary or secondary lids are not required to react this shear force since the radial clearance with their hole is greater than that of their stepped lid, i.e.,
lid bottoms out before bolts contact.
This joint design is identical to the one used in the 01-142 pack-age, Certificate of Compliance Number 9073.
Each stud is threaded into the top closure ring and high strength doubler.
Total thread engagement includes.75 inches for the closure ring and 1.75 inches into the doubler.
Recommended thread engagement is that equal to the thickness of a heat treated nut of the same tensile strength as the stud.
Minimum thick-ness for a 1-1/4UNC Heavy Hex N.it is 1.250 in. (max. ),
per Machinery Handbook.
Since the doubler is manu-factured from a material of greater strength than the stud, the following conservative margin of safety can be calculated.
M.S. = (1.75 in./1.25in.)-1 Q
M.S. = +.40 4
T
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O 2-17
From the figure on the previous page, tear out or shear strength at the closure ring is calculatea as follows.
{/
3 Conservatively assume that the closure ring welds are s
effective only out 4 inches on either side of the stud center line.
Pw = Fsu keld hhere:
Fsu
= 35,000 psi Aeld = [(3/4)(.707) + (3/8)] 8
= 7.24 in2 Pw = (35,000 psi)(7.24 in2)
Pw = 253,470 lbs.
Margin of safety:
M.S. = (253,470/25,631)-1 M.S. = +Iarge
'Iherefore, it can be concluded that both the stud and O
its ettachments are cagebie of reectins tne normei con-dition loads.
For end drop conditions onto the secondary lia, iupact energies will be absorbed primarily by crushing of the top lif ting lugs.
From the drawing, it can De seen that the lug is chanfered and has a 1-1/2" diameter hole.
'Ihe effective area can be approximatea oy tne following:
Ae = (3 lugs)(1-1/2 in, thick)(4 1/2 in. wide)
Ae = 11.25 in.2 Frou the standard energy relationsnips, tne crusn ueptn can be calculated as follows:
l t = (51,500 lbs.)(12 in.)/(110,000 psi)(11.25 in2) t =.50 in.
O 2-18
Acceleration is given as:
O Ay = 12 in./.50 in.
Ay = 24 g 's NOTE: 'llilS IS A CONSERVATIVE ACCELERATION SINCE IT DOES NOT TAKE IN'IO CONSIDERATION ' HIE SPRING OR ELASTIC DEFORlRTION OF' DIE LID.
Le total load transmitted to the secondary lid is given as:
6 lbs.
P = (51,500 lbs. )(24 g's) = 1.236 x 10 Bis load must be reacted in directed compression by the seal spacer block.
Commpressive stress in the block is:
6 lbs.)/(.50)(v)(30 in.)
fb = (1.236 x 10 fb = 26,200 psi lhrgin of safety:
M.S. = (36,000/26,200)-1 f t. S. = +. 37 herefore, it can be concluded that the spacer blocks do provide protection to the seal.
2.6.7 Corner Drop his requirement is not applicable since the Model CNS 6-80-2 packaging is fabricated of steel.
2.6.8 Penetration Fron previous container tests, as well as engineering judgenent, it can be concluded that the 13-pound rod would have a negligible effect on the heavy gauge steel shell of the cask.
2.7 Ifypothetical Accident Conditions Not applicable for Type "A" packages.
2.8 Special Form Since no special form is claimed, this section is not applicable.
O 2-19
2.9 Riel Rods O
Not applicable.
2.10 Appendix 2.10.1 General arrangement drawing of Model CNS 6-80-2 packag-ing.
O l
O 2-20
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STUD. NLITg DETAIL -C LDCKWA5HER 4' FLA1 WASHER l'4 I uur. S. A.t.. couteC. 5 3 p,x crit.
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=
TNIS LOCATION, THEY SELL BE EX. HD CAP SCREV,
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PAINT ALL' EXTERIOR SURFACES WITH CE (1) COAT g
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SEC.TIOM A-A
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3.0
'HERMAL EVALUATION
<s-c pd A thermal analysis for the Model.CNS (6-bO-2, packagibg has f teen con-ducted for normal transport conditions, he performance of ta'e packag-ing under normal conditions of transport is described below:
3
- y, s
+
3.1 Discussion 1
We mechanical features of the pa'ckagin'g have been described,in g _ 9, Bere are,no spe, ial thermal protection subsf(- Q' ; M g; c
Section 1.2.1.
g tems or features.
s 4'
q _
A.
\\,
,-~
N
%e external hurface of,.the cash i's predicted to exhibit maximum c
s temperatures ranging' from 1690 to 1740F, ' depending upon the quantity of internal oecay heat assumed.
he'1 wer teuperature prediction assumes no internal heat whereas the higher tempera-ture assumes an internal decay heat load'of 400 watts.
Rese maximum temperature prediction assume conditions donsi' stent with N
the Normal Transport " Heat" requirements, specifically:
sc y
s Direct sunlight (mid-summer) i t '-
e w
'~
e Ambient air at 1300F % ;
,a s
\\
x.
e Still air.
w
'x4 s
s
\\
x x
',[,
a; For conservatism, the " peak", ' solar flux ~ has bewsssumed,to -
C O
exist continuously. %fs:'is equivale'nt' to' assyming 24-hour son-
~ g light, of maximum intensity,'t _. Further conservatism' is incor-5?j porated in the analysis by assuming the cask base is an adiabatic boundary -(no heat loss).
fi D
i 8
,\\,
We analysis also shcws Wat the internal' decay heat f400 watts) raises inside surface tapet atures, above' the external "teupera-
_t s tures by only 0.30F.
a s
s.
s
,,N 3.2 Sucuaary of %ermal Properties of Materials -
(
s Only three basic properties of the, cask materials were etaployed A '-
in this analysis.
Wey were obtairit;d sfroml corventional hand-l 2' '
l
\\
_y's
- +
books as follows:
e e.
a (o\\
g
'1 1
%ermal Conductivity s
s s
~
s Steel 25 Btu /hr ft OF lead 18.6. Btu /hr"ft oF
~'
J, s, x Surface Dnissiirity/ Absorptivity
'\\
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v
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4 5
1 1
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.N b
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3.3 Technical Specification of Components O
Not applicable -- no special themal subsystems.
3.4
%ermal Evaluation for Normal Conditions of Transport The thermal analysis for Normal Transport "Ibat" and " Cold" con-ditions is presented in Section 3.6, Appendix.
1 s
1 3.4.1 W ernal Model As outlined in Section 3.6, the unknown external cask temperature was determined by solving for the tempera-ture at which the heat input to the cask system equaled heat output.
Input heat consisted of a peak normal solar flux (from Figure 5.3 of ORNL-NSIC-68) plus the internal decay heat.
Ibat rejection mechanisms consist i
of the sum of free-convection losses and radiation losses to the prescribed ambient air sink temperature 7
(1300F "Ibat",
-400F " Cold").
Ibat losses were
" allowed" only over the vertical cylindrical sides and the top.
Convective film coefficients were taken from empirical equations for free convection found in 11cAdam's "Ibat Transmission"..
3.4.2 Wximum Temperatures V
Predicted maximum temperatures are:
External Internal Surfaces Surfaces s,-
No Internal lleat 1690F 1690F 400 Watts Internal Ibat 1740F 174.30F m_
i 3.4.3 Minimum Temperatures l
External Internal
[
Surfaces Surfaces l
No Internal lieat
-400F
-400F 400 Fatts Internal lieat
-27.30F
-27.00F s
3.4.4 2ximum Internal Pressures c
~~
0 70 F.
Assuming the package contains water loaded at Under maximum temperature conditions (174.30F), the pressure would increase as shown below:
l The partial pressures of water and air at 700F are:
s s
Pwe = 0.36 psi O
Pac = 14.7
.36 = 14.34 psi 3-2 i
i
.__..__m...
h e partial pressures at 1730 are:
O Pwh = 6.75 psi Pc n 14.34(175 + 460)/(70 + 460) = 17.18 psi A
% e internal pressure differential is thus:
P = 6.75 o 17.18 - 14.7 = 9.23 psi 3.4.5 4ximum termal Stresses In Section 2.6.3, the critical elements of the cask were evaluated for a pressure differential of 0.5 atm (7.35 psi).
%e internal pressure due to maximum temperature, therefore, increases stresses predicted in Section 2.6.3 by the factor:
9.23/7.35 = 1.26.
We loads and margins of safety thus become:
load /
Allowable Item Stress Ioad/ Stress W rgin Secondary Lid Stud 762 64785 Iarge Primary Lid Stud 3235 95248 Large Shell 1089 36000 Iarge Lid 889 36000 Large 3.4.6 LValuation of Package Performance for Normal Conditions of Transport As the result of the above assessment, it is concluded that under normal conditions of transport:
(1)
%ere will be no release of radioactive material from the containment vessel; (2)
We effectiveness of the packaging will not be substantially reduced; (3)
Were will be no mixture of gases or vapors in the package which could, through any credible increase in pressure or an explosion, signifi-cantly reduce the effectiveness of the package.
3.5 INpothetical termal Accident LValuation Not applicable for Type "A" packages.
l O
3-3
3.6 Appendix O
3.6.1 1hermal Analysis - Normal Conditions of Transport - No Overpack (CNS 6-80-2 Cask)
'No cases are specified by Appendix A,10 CFR 71.
Key assumptions for these cases include:
IEAT - direct sunlight (sumer, latitude 420N) o ambient air at 1300F internal hest load = 0 and 400 watts e
00LD - shade ambient air at -400F internal heat load = 0 and 400 watts 3.6.2 Geometry Assumptions (Simplified) l$n R4tY,
4 1
to J. i m
k
)
p p,
.L M %
/"fK Ndfm O
%"in w m
.k=
Je#
Y T
l fff" I
ks,,
M L l
////
N _.. _ \\.
S9'b j
7?MA 3.6.3 External Connection and Radiant Ileat Transfer Heat leaves the package via combined convection and radiant heat transfer to the ambient air at T=T Heat is lost only on top and sides; adiabatic asstsap-tions are applied to the base.
3-4
3.6.3.1 Convection O
qc = hAAT; AT = Text - T,; T, = 1300F and
-400F For free convection, McAdams gives:
h =.29
- vertical cyl. (L = f t)
.27
- horizontal plate (up-heated)
'Ihus :
qc=(hss+h'h)aT=liXAT A
T As = wDis = w (
){
= 113.41 ft2 144 2
T " wD,w(70.25)2 = 26.92 ft2 A
4 4(144) 2 Ls = 74/12 = 6.17 ft.; AE = 140.33 f t LT = 70.25/12 = 5.85 ft.
Therefore:
g, 3y
(.29)(113.41). (.27)(26.92)
(6.17)I (5.85)I I
x AT, Btu /hr OF
= 25.5435 3.6.3.2 Radiation qR " A c(T
- T ") = K(T
~
r ext ext
=.1714 x 10-8 o
e =.8 Ag = 140.33 Therefore:
K = (.1714 x 10-8)(140.33)(.8) = 192.42 x 10-9 3.6.4 Heat loads - Solar and Internal 3.6.4.1 Solar Loads, Solar loads are estimated by use of Stappert 's normal incident solar energy curve given in Figure 5.3, ORNL-NSIC-68, 3-5
" Cask Designer's Gilde."
Assumptions i
include:
clear sky, mid-sumer, latitude fs
'd 4 20N.
The total solar load absorbed by a body is:
Q=AN X 9si x a lh = normal X-set area qsi = solar intensity (norm)
= surface absorbtivity (.8) a For a right circular cylinder:
An=AT cos + + As sin +,
(e- = ) wrt vert. )
2 2
A
= 26.92 ft T " 4( 4) 2
= 36.10 ft A
=
s Thus:
si * "(A;, cos e + A sin e) = q i * (14b 3) 9 s
s x [(26.92) cos e + (36.10) sin 0]
~
Evaluating using Shappert's variation of qsi versus 4:
Btu /hr-ft2 Eley.
Solar Solar Solar Angle Intensity load A = 140.33 f t2 7
Time 4( )
4si (Q/A )r 8 Ag 48 250 63.9 8:30 42 260 9
36 270 6.
Q/A M x. S lar E
9:30 30 275 64.8 Load 10 24 280 62.7 10:30 18 285 59.7 O
3-6
3.6.4.2 Intern 1 lbat Internal heat is assumed to be 400 watts.
'Ihus:
Qy = (400)(3.41) = 1364 Btu /hr Total heat load is the stai of internal and external (solar) heats:
9T X QI + At x (Q/Ar)
Case (Q/Ar)
QT 9T (Btu /hr) 10T 1
66.2 1364 10654 2
66.2 0
9290 (1)LD 3
0 1364 1304 4
0 0
0 3.6.5 Steady State Solution Newton's method is used to solve for cask external temperature T = Text' 0
P(T) = qin - 9out
- K(T" - T,") - M(T-T,)
= qT - R ~9C"9T F(T) = 1 b,9 (T" - T ")
9 (T-T ) M 0 9T Q
T bxT 1+bT"+-T bxTS
=
9T 9T 9T 9T m,
r r
r5 6
7 g
M R
T lbat load 9
T (OF)
Case (Btu /hr)
AT = 40*
TEXT = T
(*R) (Ext. Wall Temp.)
1.
Hot-Int. Heat 10b54 64.24 65.78 633.7 174i0"F 2.
Hot-No Int Ibat 9290
/
63.85 628.7 169.0*
T = 13 3.
Cold-Int. Ibat 1364
/
48.19 432.4
-27.3*
T = -4
-40*F 4.
Cold-No Int lieat 0
3.6.6 Wall W ermal Gradient:
ATw = (Tinterint - Tnytnri nt)
We conductive properties of the cask wall and the internal heat determine steady state wall temperature l
gradients:
O 3-7
AT Nw"EEFF
- 91 9I" O
Where:
[qy = 1364 Btu /hr]
RTor h%
^
N 6"-
Rsnout R uro R st ut M- -M%';%%iuv.--. r)
- ,uM4 V-*
1 1
1 Q"Q*R WALL = RSTL OUT + RLEAD + RSTL IN ggg K = 25 Btu /hr-f
- F (Steel)
R
=
TOP A
wD w(59) ; t = 8/12 4
4(144) l
=
.4 6 x 10 f
ETOF " (Z 8 99)
.499 x 10 N
=
STL OUT " T " (25)[w(7
)(58)/144]
STL IN " { " TITf[w(3/8 t
/12)
-6
= 16.743 x 10 R
(59)(58)/144]
l u(d / i), In1TB.6)(58/12)l (68.25/59.75) = 235 47 x 10 d
-6 u
R
=
LEAD 2n k 1
R
= 289.71 x 10-6 ggg 1
1 1
-6
+
R
= 240.4 x 10 R
EFF " 1.4046 x 10-3 289.71 x 10-6 EFF THEREFORE:
AT = (240.4 x 10-6)(1364) = 0.33*F y
[@ 400 watts]
O 3-8
4.0 CONTAIMIENT Os Ris chapter identifies the package containment for the normal con-ditions of transport.
4.1 Containment Boundary 4.1.1 Containnent Vessel W e containment vessel claimed for the Model CNS 6-80-2 package is the shielded transportation cask as described in Section 1.2 and the general arrangement drawing in Appendix 2.10.1.
4.1.2 Containment Penetration ne drain line is the only penetration of the contain-ment vessel.
4.1.3 Seals and Welds A silicone seal is placed between the primary lid to body interface.
It is described in Section 1.2.1.
All joints are arc welded.
The secondary lid employs a silicone seal and a redundant neoprene seal.
4.1.4 Closure Q
he closure devices for the lid consist of eight 1-1/4 inch diameter studs (or bolts) in the primary lid and eight 1-inch diameter studs (or bolts) in the secondary lid as described in Section 1.2.
4.2 Requirements for Normal Conditions of Transport
%e following is an assessment of the package containment unaer normal conditions of transport as a result of the analysis per-formed in Chapters 2.0 and 3.0.
In summary, the containment vessel was not effected by these tests.
(Itefer to Section 2.6) 4.2.1 Release of Radioactive Nterial Were was no release of radiaactive material from the I
containment vessel.
4.2.2 Pressurization of Containment Vessel Normal conditions of transport will have no effect on pressurizing the containment vessel.
4.2.3 Coolant Contanination This section is not applicable since there are no cool-ants involved.
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4.2.4 Coolant loss Not applicable.
4.3 containment Requirements for the Hypothetical Accident Conditions Not applicable for Type "A" packages.
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5.0 SHIELDING EVALUATION 5.1 Discussion and Results
'Ihe Model Cl4S 6-80-2 packaging consists of a lead and steel con-tainment vessel which provides the necessary shielding for the various radioactive materials to be shipped within the package.
(Refer to Section 1.2.3 for packaging contents.)
Tests and analysis performed under Chapters 2.0 and 3.0 have demonstrated the ability of the containment vessel to maintain its shielding integrity under normal conditions of transport.
Prior to each shipment, radiation readings will be taken based on individual loadings to assure compliance with applicable regulations.
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6.0 CRITICALITY EVALUATION
O Not applicable for the Model CNS 6-80-2 packaging.
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7.0 OPERATING PROCEDURES 3b This chapter generally describes the procedures to be used for loaaing and unloading the Ndel CNS 6-80-2 packaging.
7.1 Procedures for Loading the Package (1)
Inosen and remove the bolts which secures the priuary lid.
(2)
Remove the lid by attaching suitable hooks to the lid lifting lugs.
Care should be taken during the operation so as not to damage the lid to body interface sesl while setting the lid down.
(3)
Inspect the inside of the shielded cask to assure there are no loose articles within the packaging.
(4)
Place the disposable steel liner, druns, or other packag-ing into the cask.
Contents shoulo fit snuggly witnin tne cask body using shoring or bracing when requirea.
(5)
Inspect and clean seals attached to underside of lid.
Brush off and clean thoroughly the seal to body inter-face.
Replace seals upon signs of wear and deteriora-tion.
Replace the lid and secure it to tne body by fastening the eight bolts.
(6)
Inspect the package for proper labeling necessary to meet all applicable regulations.
(7)
Install an approved security seal.
(8)
Using suitable material handling equipment, transfer tne package to the transport vehicle.
(9)
Secure package to the transport vehicle using the appro-priate tie-down devices.
7.2 Procedures for thloading the Package (1)
Move the unopened package to the appropriate unloading Place it in a suitable unloading attitude.
area.
(2)
Perforu an external inspection of the unopened package.
Record any significant or potentially sionificant observa-tions.
(3)
Remove the security seal.
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(A)
Repeat Steps 1 and 2 in Section 7.1, above, for resx>ving O
the lid.
(5)
Remove the contents.
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8.0 ACCEPTANCE TESTS AND FRINTENANCE PROG #1 8.1 Acceptance Test Prior to the first use of the CNS 6-80-2 package, the following test and evaluations will be performed.
8.1.1 Visual Examination The package will be examined visually for any adverse conditicn in materials or fabrication using applicable codes, standards, and drawings.
8.1.2 Structural Tests No structural testing is required.
8.1.3 Ieak Tests The package will be subjected to a Design and Fabrica-tion Verification Soap Ribble leak Test prior to first Cask cavity pressure shall be 14.0 psig (= 1.5 x use.
maximum normal operating pressure).
(See Section 3.4.4.)
Any condition resulting in a detectable leak will be corrected.
8.1.4 Component Tests 8.1.4.1 Gaskets Gaskets and seals will be procured and examined in accordance with the ChS1 Quality Assurance Program.
leak testing of the package will be the final acceptance for gaskets' design.
8.1.5 Tests for Shielding Integrity Shielding integrity of the package will be verified by gamma scan or gamma probe methods to assure package is free of significant voids in the poured lead shield annulus.
Voidt resulting in shield loss in excess of 10 percent shall not be acceptable.
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8.1.6 Thermal Acceptance Tests r'3 v
No thermal acceptance testing will be performed on the CNS 6-80-2 package.
Refer to the Thermal Evaluation, Section 3.0 of this report.
8.2 Maintenance Program' CNSI is committed to an ongoing preventative maintenance program for all shipping packages.
The 6-80-2 package will be subjected to routine and periodic inspections and tests as outlined in this section and CNSI approved procedures.
8.2.1 Structural and Pressure Tests Routine visual examinations will be performed to detect damage or defects significant to package condi-tion.
Exterior stencils, nameplates, seals and bolts will be verified in place.
8.2.2 Icak Tests No leak tests are performed.
8.2.3
_ Subsystem Maintenance A
The CNS 6-80-2 package contains no subsystem assen-V blies.
8.2.4 Valves, Rupture Discs, and Gaskets on Contairuaent Ves-sel Gaskets shall be replaced when visual examination under Section 8.2.1 shows damage or deterioration of the gasket material.
8.2.5 Shielding Shielding tests will be performed if damage has required repairs affecting shield integrity.
Any additional shield testing shall be in accordance with the original criteria specified in Section 8.1.5.
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9.0 QUALITY ASSURANCE O
CNSI's Quality Assurance Program used for the design, fabrication, assembly, testing, use and maintenance of the ChS 6-80-2 cask is designed and administered to meet the 18 criteria of 10 CFR 71, Appendix E.
A description of this program has been submitted to the NRC. CNSI has received Quality Assurance Program Approval No. 0231.
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