ML19344B251

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SAR for Chem-Nuclear Sys,Inc,SGC-1,Type a Radwaste Shipping Cask. Drawings Encl
ML19344B251
Person / Time
Site: 07109144
Issue date: 07/24/1980
From:
CHEM-NUCLEAR SYSTEMS, INC.
To:
Shared Package
ML19344B250 List:
References
NUDOCS 8008260021
Download: ML19344B251 (82)


Text

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SAFETY ANALYSIS REPORT for CHEM-NUCLEAR SYSTEMS INC.

SGC-1 TYPE A RADWASTE SHIPPING CASK July 24, 1980 l

l l

l Chem-Nuclear Systems Inc.

Corporate Headauarters P.O. Box 1866 Bellevue, Washington 98009 (206) 827-0711 1

foO DGO O*I

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J TABLE OF CONTENTS Page Title Page Table of Contents i

1.

GENERAL INFORMATION 1-1 1.1 Introduction.

1-1 1.2 Package Description.

1-1 1.2.1 Packaging.

1-1 1.2.2 Operational Features 1-4 1.2.3 Contents of Packaging.

1-5 1.3 Appendix 1-6 Basic Nomenclature.

1-7 Drawing #900-0103-C01 -

Name Plate 1-8 Drawing #900-0102-E01 -

Flow Diagram.

1-9 Drawing #110-2700-E01 -

Cask Assembly.

1-10 Drawing #110-2700-E02, Sheet 1 Lower Shell.

1-11 Drawing #110-2700-E02, Sheet 2 Lower Shell.

1-12 Drawing #110-2700-E02, Sheet 3 Lower Shell.

1-13 Drawing #110-2700-E03 -

Upper Shell.

1-14 Drawing #112-2700-E01 -

Internal Tiedown.

1-15 Drawing #112-2700-E02 -

Outline Cask / Barge Tiedowns.

1-16 Drawing #115-0127-D01 -

Seal Gasket.

1-17 2.

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 Centers of Gravity.

2-1 2.3 Mechanical Properties of Materials.

2-3 2.4 General Standards for All Packages.

2-3 2.4.1 Chemical and Galvanic Reactions.

2-3 2.4.2 Positive Closure 2-3 2.4.3 Lifting Devices.

2-4 2.4.4 Tiedown Devices.

2-10 2.5 Standards for Type B and Large Quantity Packaging.

2-25 i

, ~ -

+

c

TABLE OF CONTENTS (Continued)

Pace 2.6 Normal Conditions of Transport 2-25 2.6.1 Heat.

2-25 2.6.2 Cold.

2-26 2.6.3 Pressure.

2-27 2.6.4 vibration 2-28 2.6.5 Water Spray.

2-28 2.6.6 Free Drop.

2-28 2.6.7 Corner Drop.

2-28 2.6.8 Penetration.

2-29 2.6.9 Compression.

2-29 2.7 Hypothetical Accident Conditions 2-29 2.8 Special Form.

2-29 2.9 Fuel Rods.

2-29 2.10 Appendix.

2-30 Figure 2-7:

Typical Marine Transport Tiedown Configuration 2-31 3.

THERMAL EVALUATION.

3-1 3.1 Discussion.

3-1 3.2 Summary of Thermal Properties of Materials 3-1 3.3 Technical Specifications of Components 3-1 3.4 Thermal Evaluation for Normal Conditions of Transport.

3-1 3.4.1 Thermal Model.

3-2 3.4.2 Maximum Temperatures.

3-2 3.4.3 Minimum Temperatures.

3-2 3.4.4 Maximum Internal Pressures.

3-2 3.4.5 Maximum Thermal Stresses.

3-3 3.4.6 Evaluation of Package Performance for Normal Conditions of Transport.

3-8 3.5 Hypothetical Accident Thermal Evaluation.

3-8 3.6 Appendix.

3-9 Figure 3-1:

Steam Generator / Cask Thermal Model.

3-11 Figure 3-2:

Thermal Resistor Model.

3-13 Table 3.6.1 Cask Segment Heat Loads 3-18 Table 3.6.2 Node Temperatures for SGC-1 3-21 4.

CONTAINMENT 4-1 ii n

2 TABLE OF CONTENTS (Continued)

Page 4.1 Containment Boundary.

4-1 4.1.1 Containment Vessel.

4-1 4.1.2 Containment Penetrations.

4-1 4.1.3 Seals and Welds 4-1 4.1.4 Closure 4-1 4.2 Requirements for Normal Conditions of Transport.

4-1 4.2.1 Release of Radioactive Material.

4-2 4.2.2 Pressurization of Containment Vessel.

4-2 4.2.3 Coolant Contamination 4-2 4.2.4 Coolant Loss.

4-2 4.3 Containment Requirements for the Hypothetical Accident Conditions.

4-2 5.

SHIELDING EVALUATION.

5-1 5.1 Discussion and Results 5-1 6.

CRITICALITY EVALUATION.

6-1 7.

OPERATING PROCEDURES.

7-1 7.1 Procedures for Loading the Package.

7-1 7.2 Procedures for Unloading the Package 7-2 7.3 Preparation of an Empty Package for Transport.

7-3 8.

ACCEPTANCE TESTS AND MAINTENANCE PROGRAM.

8-1 8.1 Acceptance Tests 8-1 8.2 Maintenance Program.

8-2 9.

QUALITY ASSURANCE 9-1 9.1 Appendix.

9-2 Approval Letter for CNSI Quality Assurance Program.

9-3 NRC Form 311 9-4 iii

1 1.0 GENERAL INFORMATION 1.1 Introduction The Model SGC-I Packaging has been developed as a safe means of transporting " Type A" quantities of radioactive materials or greater than " Type A" quantities meeting the definition of low specific activity material.

Model SGC-I is developed specifically for the shipment of steam generator components.

Fissile material is limited to those exempt quantities licensed under 10 CFR 71.7.

Authorization is sought for shipment by cargo vessel, barge, or special overland transporter.

1.2 Package 1:escription 1.2.1 Packaging 1.2.1.1 General Description Model SGC-I Packacing is a reusable shipping package designed to prevent the release of radioactive material during normal conditions of transport.

The normal material is a steam generator lower section.

1.2.1.2 Materials of Constructions, Dimens--

ions, and Fabricating Methods General arrangement drawings of Model SGC-I Packaging are included in Appendix 1.3.

They show the overall dimensions as well as the material of construction.

The cask body consists of 2 -inch steel plate rolled into a cylindrical section.

The cylinder has reinforced end plates made of 2 3/4-inch plates.

The cask is separable at the center and is sealed with a si::-inch flange made of 2 -inch plate.

The flange 1-1

=

is sealed with a neoprene gasket material and 112 two-inch diameter bolts on 12-inch centers.

The payload is secured by two internal straps and two internal saddles.

These internal tie downs carry the load directly to the cask external saddles and base plates.

1.2.1.3 Containment Vessel SGC-I cask serves as a containment vessel and the mechanical configura-tion is described in the foregoing paragraph.

A neoprene gasket is employed on the flange interface which seals the upper and lower sections of the cask together.

The radioactive material is sealed inside the cask.

1.2.1.4 Neutron Absorbers There are no materials used as neutron absorbers or moderators in the Model SGC-I Packaging.

1.2.1.5 Package Weight Package weight (empty) = 264,000 lbs.

Payload

= 446,000 lbs.

Gross weight

= 710,000 lbs.

1.2.1.6 Receptacles There are no internal or external structures supporting or protecting receptacles.

1.2.1.7 Drain Port The cask is provided with two 1-1/2 inch NPT pipe plugs.

It is used for the removal of entrapped liquids, i.e.

1-2

i rain, decontamination fluids, etc.

1.2.1.8 Tiedcwns Tiedowns are a structural part of the package and are designed for 1

G loads in all directions.

This loading is conservative and typical for this type of transport.

These tiedowns attach to the cask external saddles.

There are eight points for lateral stability - four in each direction.

There are eight tiedowns for loagitud-inal stability.

All sixteen tiedowns apply to the vertical stability of the system.

The tiedowns have a clevis and pin end configuration.

Also they are designed with two swivel pins and a turnbuckle rod giving the tiedowns alignment and takeup capa-bilities.

The design also includes cask to trailer tiedowns.

These tiedowns are a shear pin / bolt cortiguration that attaches the cask base plate to the trailer structure.

The pin connection plates for all tie-downs are designed to shear out prior to damaging the structural integrity of the cask.

Refer to Section 2.4.4 for the detailed structural analysis.

1.2.1.9 Lifting Devices There are no lifting devices on the Model SGC-1 cask for the complete system.

See Section 7.0 operating procedures.

There are however four lifting lugs provided on the cask upper section.

These lugs are designed to only lift the upper section.

They are designed in accordance with 10 CFR 71.

See section 2.4.3'for the structural evaluation.

~~

1-3

1.2.1.10 Pressure Relief System There are no pressure relief valves.

1.2.1.11 Heat Dissipation There are no special devices used for the transfer or dissipation of heat.

The package maximum design capacity is 20 watts, however, this value may be exceeded if it can be demonstrated that actual equilibrium temperatures with the higher heat load are still within allowable limits.

1.2.1.12 Coolants There are no coolants involved with this system.

1.2.1.13 Protrusions There are no inner or outer protrus-ions except for the two external saddles consisting of three webs with a base plate used for supporting the cask, and the sealing flange located at the center. Also, there are two small drain plugs.

1.2.1.14 Shieldinc Contents will be limited such that the radiological shielding provided will assure co=pliance with DOT and IAEA Regulatory Requiraments for transport.

1.2.2 Operational Features Refer to the General Arrangement Drawing of the Packaging in Appendix 1.3.

There are no ec= plex operational requirements for the Model SGC-I Packaging.

1-4

~

1.2.3 Contents of Packace The contents are contaminated reactor com-ponents, where the radioactive contamination is in a non-readily dispersible form.

Tge level of contamination averaged over 1 m (or the area of the surface if it is less than 2

2 1 m ) does nog exceed 20 pCi/cm and no more than 2 pCi/cm are alpha emitters other than natural or depleted uranium or natural thorium.

Contamination will consl.st of the isotopes Co-60, Co-58, Mn-54, Fe-59 and traces of Cs-137.

The total quantity of isotopes will not exceed 2300 curies.

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2.

STRUCTURAL EVALUATION i

This section identifies and describes the principle structural engineering design packaging, components and i

systems important to safety in compliance with the performance requirements of 10 CFR 71, with the exception that the one foot drop will not be met.

2.1 Structural Design j

2.1,1 Discussion The principle structural member for Model I

SGC-I Package is the primary containment i

or transport shield as described in Sections l

1.2.1.

The above components are identified on the drawing as noted in Appendix 1.3.

Details of the discussion for the structural design of the performance of these components l

are provided below.

2.1.2 Design Criteria The chield is constructed so that all wall thickness in the radial direction from the steam generator is 2\\-inches and the two end plates are 2 3/4-inch thick steel.

2.2 Weights and Center of Gravity Model SGC-1 Cask 264,000 lbs.

Steam Generator Lower Section 446,000 lbs.

Transportation Trailer 150,000 lbs.

Total 860,000 lbs.

I See Figure 2-1 for center of gravity dimensions.

2-1 4

}

l il -

v

n

~-

i l

) bY

(

.9 e i

f i

bl i

h) b_.

l l

i, l-9'-0" 13'-3" e 10'-9" ~^ 9'-6" m

\\

l

.a j

i 10'-2" 2'-8"

[

8'-8 3 A'.

(without trailer)

(with trailer) f m

p o

4

.~

Figure 2-1:

Center of Gravity Dimensions

~..

2-2

E s

2.3 Mechanical Procerties of Material SGC-1 Packaging is made of ASTM A516 Grade 70.

The steel has the following properties:

Minimum tensile strength, 70,000 psi; minimum yield strenctk 38,000 psi; minimum, 15 ft.-lb. charpy test at -40' Ftu = 70,000 psi Fty = 38,000 psi Bolting will be to ASTM A320 LC7 Ftu = 123,000 psi Fty = 105,000 psi Elongation in 2 in = 16%

The tiedown shear pin and turnbuckle material is AISI/SAE 4340 Steel, normalized and heat treated to the following properties:

Ftu = 160,000 psi Fty = 120,000 psi 2.4 General Standards for All Package This section demonstrates that the general standards for all packages are met.

2.4.1 Chemical and Galvanic Reactions The package is fabricated complete steel of the same grade, along with the contents of the package high grade alloy steel, will not cause significant chemical galvanic or other reactions in air, nitrogen or water atmosphere.

2.4.2 Positive Closure The positive closure will be two special flange I

bolts.

These bolts are located on opposite corners of the cask flange.

The bolts will be red in color to distinguish them from the other flange bolts, and will have lock wire holes.

After the bolts have been torqued they will be lock wired and lead sealed.

2-3

~

2.4.?

Lifting Devices 2.4.3.1 Upper Shell Lifting Lugs There are four lifting lugs provided for the upper shell.

i These lugs are the four 2.5" thick flange sussets with holes.

These lifting lugs are designed only to lift the upper sh' ell.

The lug material is ASTM A516 Grade 70, normalized steel.

See section 2.3 for the mechanical properties.

.1 n;

4 Y

~

nt O L

g..

M i

il '

Q.l 9

2"

'/ ;.

5

~

EM=2.5"

/ lg 1

d=2.25"

. /!

l I-t=2.5"

r,,

'I X

l ' Auf L

- l t

l

+6" m

I i

Figure 2 - 2.

Upper Shell Lifting Lug v

l 2-4

.---.----...y

-.. ~ -. _ _ -

2.4.3.1 (con't)

The lug capacity can be determined from the following set of calcula-tions.

The lug load is calculated as follows:

P=

W/N S

Where P

= Lug Load (lbs.)

n, 3

V3

~

W = Package Weight (1bs.)

P=

120,000 / 4 N = Number of Lugs 376 322 V = Vertical Length (in.)

L" ffif,l bs.

S

= Sling Length (in.)

g 0

Using the standard 40 shear out equation:

P=2F t

EM - (d cos 40 /2) a sy Where P,= Allowable Load (1b s. )

37 Allowable shear yield F

(Pty / klO (psi) t = Lug Thickness (in.)

EM = Edge Margin (in.)

dm Hole diameter (in.)

P,= 2(38,000/ kSI) 2.5 j2;5- (2.25 cos 40 /2)l 0

P = 179,705 lbs.

a 2

4

--y

^

7 i

2.4.3.1 (con't)

The shearout margin of safety is:

M.S.

=P

/P

-1

= 179,705/30,031-1

= + 4.1

=

The capacity of the lug in bending is shown as follows:

P=H (W/N) /V Where:

P=

r z ntal Load (lbs)

H 3

L H

= 195.6 (120,000/4)/322 W = Package Weight (lbs)

= 18,224 lbs.

N = Number of Lugs V = Vertical Length (in.)

H = Horizontal Length (in.)

From Formulas For Stress and Strain Roark and Young.

5th Edition Table 26, case 11 aaa.

Assume:

Load is uniform over plate from y=0 to y=l/3 b M

2-6

2.4.3.1 (con't)

The uniform load is then; 2

18,224 lbs./36 in

= 506.2 psi

-B g b /t Where:

f = maximum bending stress Max f

=

y b

b (psi) 58 j) 0

=-

B = coefficient y

3333 psi (compression) q = uniform load (psi)

=

=

b = length (in.)

t = plate thickness (in.)

The upper shell lifting lug bending margin of safety is:

(38,000/3333) - 1 = +10.4 M.S.

=

=

The weld capacity of the upper shell lifting lug is as follows:

Refer to Figure 2-2.

Assume the line of action of the load is parallel to the long weld.

Both welds are 600 groove with a 0.125" root with a 1.0" fillet weld.

The weld throat length is:

2.18 x.707 = 1.5 in.

Aa (1.5in.) (2) (61n.) =18 sq.in.) Where: A = area of weld j

x in the x direc-A=

( l. S in.' ) (2) (18in.)=54 sq.in.

tion (sq.in.)

A 31=A + A = 72 sq.in.

A = area of weld g

y y in the y direc-tion (sq.in.)

Atotal= total area (sq.in.)

2-7 e

r v

m-w-

m

~

e v

y -

2.4.3.1 (con't) x= Ax(3)

+A (6) = 18(3) + 54 (6) y A

72 E= 5.25 in.

Where:x=x dimension to the cg. (in. )

y= AY(9)

  • (18) = 54 (9) + 18 (18)

+A E=y dimension to 3

72 t

the eg.(in.)

y= 11.25 in.

Now obtain r and r :

Where:

g y

r = radius from

[6.752 + 2.252 cg. to center 7.0 in.

r=

=

x of x direction weld (in.)

[2.752 + 2.25 3.5 in, r=

=

r = radius from Y

eg. to center of y direction weld (in.)

Now obtain J and J :

Where:

Y J = polar moment x (g 1

2 h of inertia J=A x

+r x about the x x

)

direction weld 2

2)

(in )

4

= 18 6

,7 F~

)

J = polar moment 4

Y f i"*#Di" J = 936 in x

about the y direction weld

+ ry )

(in4) 2 J=A 2+3.5) total" D U"1 P 18#

2

= 54 18 moment of 12

/

inertia. (in4) 4 J = 2120 in 1 = x direction Y

weld length (ia) 4 I = y direction Jtotal = J

+J

= 3056 in y

x y

weld length (in) 2-8

I 2.4.3.1 (con't)

Now obtain S" and S":

Where: S"= secondary shear stress on x direction S" = Mry/J x

t weld (psi)

= 35,031 (2) (3.5) / 3056 S"= secondary Y

shear stress S" = 80 psi on y direction weld (psi)

S" = Mr*/J Y

M = moment (in-lbs)

= 35,031 (2) (7) / 3056 S" = 160 psi Y

Now obtain S':

Where:

S'= orimar'v shear Y

Y

' stress in the direction of S' = P/A = 35,031/72 y

t the applied load (psi)

S' = 487 psi Y

P = applied load (lbs)

Now obtain S:

Where: S = resultant stress on both welds (psi)

/

2 S=

V S" 2

+

S' + S" x

y y

[ 802+ (487 + 160)

S = 652 psi The weld margin of safety is as follows:

M.S. = 38,000 (.4) / 6 5 2 - 1 = +2 2. 3 Therefore, from the preceding analysis, it can be concluded the upper shell lifting lugs are capable of reacting the expected loads with sufficient margins of safety. And the analysis shows, based on =arcin of safety, that the edge margin will shear out while the weld integrity is maintained, since the margin of safety for edge margin is 4.1 while the margin of safety for the weld is 22.3.

2-9 L

^

2.4.4 Tiedowns There are two sets of tiedowns used for trans-porting the CGC-1 package.

One set is used for securing the cask to the barge during water transport.

The other set is used for securing cask to the trailer for land transport.

Each of the two systens have its own criteria and will be addressed separately.

2.4.4.1 Barce Tiedown System Based on previous criteria for loads of this size and nature, the applied load factors are:

a

= 1.5g longituminal x

a

= 1.5g lateral y

a

= 1.5g vertical z

These accelerations will be reacted by tiedowns indicated in Appendix 2.10.

The interface between the tiedowns and the cask are the shear pin joints indicated.

The barge tiedown system consists of eight tiedcwns in the lateral direction and eight tiedowns in the longitudi al direction.

All the tiedowns restrain the cask in the vertical direction.

The analysis of these tiedowns will be shown in two parts; (1) lateral tiedowns, (2) longitudinal tiadowns.

The analysis will show the loads, edge margin on the cask plates, weld integrity of the cask welds, the cask plates in bearing, the weld integrity 1

of the plate doublers, and the shear of the pin.

The analysis will show that the pins will shear or the edge margin will shear out while the integrity of the cask is maintained.

2-10

~

aa

2 2.4.4.1 (con't)

Lateral Tiedow.s 860,000x1.5 = 1,290,000 lbs.

- 13.2.5 '

10.~15 ' ~

-T-~R

/

__-.-------,I i

1 J

6

u I.

c I - }

I i

S 8 2

_____L__L_

~;l

(( '

~

/

\\

'1

/

. nl V

d:

\\

d Y

a R

1,7.90, OOC \\bs.

b Figure 2-3 Lateral Tiedown Leads 2M

= 0; 1,290,000 (13.25) = R.

(24) a o

g

= 712,189 lbs.

R,

= 577,812 lbs.

Therefore the design load will be 712,188 lbs. for each saddle.

~1\\?., \\ B S \\'es. Ver ic.a\\

a i

N r

7 \\7.. \\ D B WS. w -

,l '

\\.a%r.r o.\\

-t-

\\<

e 10'. 2,"

W ; + h i

r... u l

/

a'- BV" w/o 3

Tr.ter

}

i t

i l

2-11 l

\\

- =

2.4.4.1 (con't)

T 7., \\ B 8 Ws.

h V

4 0..e 54 o

y

71. $ **

The tiedown load for the vertical acceleration is as follows:

'. tension (712,188/2)(90.82) / 71.5

=

tension =

452,414 lbs.

P The tiedown load for the lateral acceleration is as follows:

l

'\\\\?.,\\SS \\bL 90.62" 5(o

, s. v.

i tension =

712,188 (90.82) / 71.5 P

Ptension =

904,628 lbs.

l 2-12

^*

1 2.4.4.1 (con't)

Therefore the load of 904,628 lbs.

is used for the analysis.

Also, a conservative approach was taken since the line of action of these lateral tiedowns is through the C.G. without the trailer at 10.17'.

The composite C.G. with the trailer is 8.7'.

Therefore the actual expected load is:

Pactual =9 0 4,6 2 8 ( 8. ; ) /10.17=773, 870lbs.

However, the design is based on the 904,628 lb. load.

Pjz P/4 UV

4 C oVBLF 9,5

,v

,v 9"a 9"= I"TH K.

(T Y PI C A L.

.W,. f.

3.50" OtA PtM 0

F M = 6. O O" TtE.DowN CLFvts O

h AND SWlVP t

(.TYPl C AL)

Figure 2-4 LATERAL TIEDQWN 2-13

'~

s 2.4.4.1 (con't)

The edge margin of the cask saddle plates is shown using the standard 400 shearout formula:

Pa= 2 Fsy t EM-(dcas 40 /

Where: Pa= allowed load (lbs.)

2

= 2 ( 38,000/VI) ( 4. 75)

Fsy= allowable shear (psi)

-(3.625 ces 40 /2 t= plate thickness (in)

Pa= 671,767 lbs.

EM= edge margin (in) d= pinhole dia(in)

The shearout margin of safety is:

M.S. = 671,767/ P/2 - 1 = 671,767/(904,628/2) - 1 M.S. =+.48 The cask saddle weld capacity is shown as follows:

The load required to shearout the edge margin is:

P = 2 Fsu t EM - (d cos 40 /2

=2 (70,000 / VI) (4.75) 6-(3.625 ces 40 /2)

P = 1,770,547 lbs.

~^

2"FilW Wa4 i

74.S' I

h l

l 1

I,TIO,947 b.

The weld configuration is a 30 groove with a 2.5' fillet for reinforcement.

2-14

g-.

2.4.4.1 (con't)

The stress in the weld is shown:

f= P/g ; A = Nhl Where:

F= stress in weld (psi) f= P/Nhl P= applied load (lbs)

A= Weld area (sq in)

= 1,770,547/(2) (2.25) n (2) (74.5/4)

N= No. of welds f= 3362 psi h= weld throat height 1= length at weld The cask saddle weld margin of safety is:

Fsu = 70,000 / VOI= 40,415 psi Where:

Fsu= material ultimate shear stress.

M.S. = 40,415/ 3362 - 1 = +11.02 The bearing stress in the cask saddles is:

f=(P/2)/A A= td Where:

f= bearing stress (psi) f = ( 904,628/2) / (4.75) (3. 5) t= plate thickness (in) f= 27,207 psi d= pin diameter (in)

The bearing stress margin of safety:

Fsy in bearing = Fty (2.25) per AISC Manual of Steel Construction Seventh Edition, page 5-129, Section 1.5.2.2.

M.S. = 38,000 (2.25)/27,207 - 1 = + 2.14 The weld capacity of the plate doublers is shown:

The doublers are 9 in. square x 1" thick 1 in, fillet welds on 3 sides and a full 45' groove weld.

f=

(P/4)/ A = (904,628/4) /.707 (1) ( 36) f = 8886 psi w

2-15

w b

-w 2.4.4.1

( con ' t)

The weld allowable is 0.40 of base metal yield, per AWS Dl.1-80, page 128, table 8.4.1.

15,200 psi f

= 3 8,000 (0. 4)

=

allowable The weld of the plate doublers margin of safety is:

M.S.

= 15,200 /

= +. 1 8886 The shear of the pin is shown as follows:

f,11c,= reu / pcr = 160,000 / par = 92,376 psi 2

f= (P/2) / A = 904,628/2 / (w3.5 74) f = 47,012 psi The shear pin margin of safety is:

M.S.

= 92,376 / 47,012 - 1 = +.96 Therefore, the above analysis shows that the pin will shear or the edge margin will tearcut while the integri-ty of the cask is maintained, since the margin of safety for the edge margin and

' ~

shear pin are.48 and.96 respectively while the margin of safety for the weld is 11.02.

Loncitudinal Tiedowns The load is calculated as follows:

x direction = 93 in.

y direction = 121.625 in.

x direction = 53 in.

I 2 2

2 Line of action = V93 +121.625 +53,

162 in.

Total load = 860,000 (1.5) = 1,290,000 lbs.

Load per tiedown =

{,290,000(162/121.625] /4 P = 429,558 lbs.

2-16

O y

2.4.4.1 (con' t)

The edge margin is calculated as follows:

(d cos 40 /25_

t 5.M i 0

P=2 (Fsy) a

2 (38,000 / VI) (4.75) 3.25- (3.625cos40/23 P,

804,836 The shearout margin of safety is:

M.S. = 804,836/429,558-1 = +.87 The weld capacity of the longitud-inal tiedown gusset plates is shown as follows:

~

- ?_3.5 ---

-X

--._ A t I

r,

?.t.2.5

  • P 3 N_l 9

p 5

F 4

3 q

1 9,

N Figure 2-5 Longitudinal Tiedowns Gusset Plate (Small Gusset for Weld Integrity) 2-17 4

i

~, _

~.

2.4.4.1 (Con't)

P/g n

a.75,,-H l--

V P/4 3 5o'oi. pin a.

1 I

EM = 5.2.5" e--

/

Doublers, Q'k 9"a l" TH K.

(T1pieel)

Tie. d own Clevis, O

(. SwWel (Typic.al)

Figure 2-6.

Longitudinal Tiedowns The load required to shear out the plate is:

P,= 2 F, t iM- (dcos40/2}

U

= 2 (70,000/ VT) (4.75) 5.25-(3.625 cos 40 /2)

P = 1,482,593 lbs.

a 2-18

5 2.4.4.1 (con't)

The weld capacity is as followg:

The weld configuration is a 60 Groove, with a 2.5 in. reinforcing fillet weld.

A

= 1. 414hl = 1. 414 ( 3. 6) ( 2 3. 5) =119. 6 sq. in.

x

1. 414hl = 1. 414 ( 3. 6) (22. 25) = 113. 3 sq. in.

A

=

A

=A+A

= 119.6 + 113.3 = 232.9 sq. in.

,1 x

y gAx(ll.75) +Ay(23.5) 119.6(11.75) + 113. 3 (23. 5)

=

A

+A 232.9 i = 17.5 in, yay (ll 1)+ A (22.5)

=

x 113.3(11.1) + 119.6(22.25)

A

+A 232.9 x

Y E = 16.8 in.

r = V5.752 + 5.42 = 7.9 in, x

r,I= V62 + 5.72 = 8 3 in.

2 J*= A*

lx

+ r*

= 119.6 23.5

+ 7.9 T2~

12 4

J= 12,968 in x

2 J = A, lv

+ ry M 113.3 22.25

+ 8.3 12

)

12 4

J = 12,479 in y

4 J

+

= 12,968 + 12,479 = 25,447 in.

total "

x y

S " = Mr / J =

,1

,323(3.5)(8.3)/25,447 x

t S " = 1271 psi g

S " = Mr

/J

= 978,291(2.75) (7.9)/25 447 t

S " = 835 psi y

2-19

-.+

y y

-..m

.-e

^

~

2. 4. 4.1

( cen ' t)

S " = F / A = 1,113,323/232.9 = 4780 psi x

t S

= F / A = 978,291/232.9 = 4200 psi y

t S=f/(S"+Sx') 2, gg

, gy )2 x

= h/ (1271 + 4 78) 2 + (835 + 4200)2 S = 5330 psi The longitudinal gusset plate weld margin of safety is:

M.S.

= 38,000 (.4) / 5330 +1.85 The bearing stress in the plates is shown as follows:

f = P/A = 429,558/(4.75) (3.5)= 25,838 psi The bearing stress margin of safety is:

M.S. = 38,000(2.25)/25,838 - 1 = +2.3 The weld capacity of the plate doub-1ers is calculated as follows:

f = P/A = (429,558/2) /.707 (1) (36) = 8,439 psi

~

The plate doublers weld margin of safety is:

M.S. = 38,000(.4) / 8,439 - 1 = +.80 2-20

2.4.4.1 (con't) s The shear of the pin is shown as follows:

f,yyg, = Ftu / V7 = 160,000/V3'= 92,376 psi f = P/A = 42?,558/ (w3.5 /4) f = 44,647 psi The shear pin margin of safety is:

M.S. = 92,376/ 44,647 - 1 = +1.06 Therefore, using similar reasoning for the lateral tie-downs, the longitudinal tiedowns will react the expected loading.

2.4.4.2 Trailer Tiedowns The cask will be tied down to the trailer for the following loais.

longitudinal 1.5 g's lateral 1.5 g's vertical 75 tons The longitudinal and lateral loadings are based on the maximum loadings that could be generated during normal conditions, (i.e.

maximum breaking force) plus a factor of safety.

No credit was taken for friction, which is considerable, due to the large mass of the cask.

These loads are the same as used for the marine tiedowns.

The vertical load is based on the weight of the trailer.

The con-2-21

2.4.4.2 (con ' t) trolling mass is the loaded cask.

The tiedowns are sized to keep the trailer with the cask.

Lateral Restraints 1.5 g x 355 ton x 2000 lb/

=

1,065,000 lbs. at CG.

EM=0

= 15 ft (1,065,000)+ 28 R.

R

= 570,536 lbs.

1 R +R = 1,065,000 lbs.

y 2

R = 494,464 lbs.

2 Two pins at each end acting in shear.

Load per pin = 570,536 = 285,2681bs.

2 f = load = 285,266

48,028 psi area (2.75/3'u M.S. = 120,000 48,028 - 1 = +.44 V3 Ultimate shear strength of bolt

Ab 160,000 = 92,376 psi (5.94)=548,674 lbs.

V3 From the 40' shear out formula:

548,674 f *2(2.75)(6.00 - 2.875 cos 40*)

s 2

f,= 20,363 psi The margin of safety is:

(70,000[V3-) 20,363-1 M.S.=

= +.98 Required weld length p =. 70 7 tl F,

F, = ultimate 'reld strength in shear = 15,200 t = thickness 548474

=25.33 in of weld

.707 2in 15,200 There are three plates with over 12ft.

of double 2 in fillet welds attach-ing the base plate to the cask.

Hence the margin of safety is positive and large.

The pin will shear prior to the cask being damaged.

2-22

'~

i 2.4.4.2 (con't)

Longitudinal Restraints 1.5 g x 3.55 tons x 2000 16/ on" t

1,065,000 lbs.

The tiedowns are symetrical about the center of gravity.

Four pins act in each direction.

Load per pin =

1,065,000 lbs = 266,250 lbs.

4 f = load = 266,250 (4)=44,826 psi area (2.75)' x M.S. = 120,000

- 1 = +.546 V7r 44826 The ultimate shear strength of the bolt is the same as for the lateral load.

The attaching welds are also the same.

Therefore, the margin of safety is positive and large.

The pin will shear prior to the cask being damaged.

Vertical Fastraints The trailer center of gravity is R

R directly below the center of gravity.

,1 2

CG i

75 tons = 150,000 lbs.

15' ++

+

EM = 0 = 15 (150,000) - R 28 28'

+

2 R

= 80,357 lbs 2

R

= 69,643 lbs There are 4 bolts per end.

Load per bolt =

P

= 80,357.4 = 20,089.25 b

4 Bolt =7/8 bolt UNC Stress area =.4612 sq. in.

Stress in bolt f"

s 20,089.25 = 43,559 psi

.4612 2-23

~

2.4.4.2 (con't)

M.S.

= 105,000 - 1 = 1.41 43,559 Ultimate Failure P

= 123,000 (.4612) = 56,7281bs.

Assume bracket is a 10 in wide by 2.5 in. deep that is 12 in. long.

M = 12 x 56,728 = 68,0727 in. lbs.

3 4

I = bh

= 10(2.75)3 = 17.33 in

=

12 32 moment of inertia f = MC 680736 1.25 = 49,101 psi'

=

b I

17.33 bending stress M.S. = 70,000 - 1 = +.43 49,101

==

This analogy only considered the strength in one direction actually the plate is fixed on two sides.

The actual stresses would be much lower.

1

~ - -w/

2-24

i 2.5 Standards for Type B and Large Quantity Packaging Not applicable 2.6 Normal Conditions of Transport The Model SGC-1 packaging has been designed and the contents are so limited (described in Section 1.2.2 above) that the performance requirements specified in 10 CFR 71.35 will be met when the package is subjected to the normal conditions of transport specified in Appendix A of 10CFR70 with the exception that the free drop will not be met due to the lack of applicability.

The ability of the Model SGC-1 packaging to satisfac-tory withstand the normal conditions of transport has been assessed as described below:

2.6.1 Heat The thermal evaluation for the analytical therm-al model is reported in Section 3.4.

2.6.1.1 Summary of Pressures and Temperatures With a maximum solar heat load in 130'F air,the external maximum temperature rose to 168.7'F and the internal temp-erature rose to 149'F with an internal pressure of 5.49 psig.

These conditions had no detrimental effect on the package.

2-25

2.6.2 Cold The materials of constructio'n in this package as described in Section 2.3 have the ability to withstand a standard Charpy V notch test with a minimum of 15 ft-lbs impact energy at

-400F.

Based on that criteria, it is safe to condlude that cold will not substantially reduce the effectiveness of the package, f

6 I

i 2-26

~

i 2.6.3 Pressure

)

A differential pressure of.5 atmosphere will be reacted by the cask and its closures.

Loads on the closure bolts are calculated as follows:

The longitudinal stress and maximum hoop stress in the cylinder are:

fh = P,R/t = 14.7/2 (85/2.5) = 249.90 psi f t = PR/2t = (14.7/2) 85/(2)2.5= 124.95 psi Assuming these biaxial stresses are additive.

f,,,= 374.85 psi The margin of safety is:

M.S.

= 38,000/374.85 - 1 = 4 large At the flange joint this load is carried by the flange bolts.

f bolt = P (R) (t) (12) thy A

= stress area of the bolt 3

A

= 2.3001 sq. in.

b Fb = 14.7 (85) (12) = 3259 psi 2 (2.3001)

The margin of safety is:

M.S. = 38,000/3259 - 1 = + large l

The presstire across the end plates is carried j

in bending.

Assut6 no strength for the gussets and assume the flinge is rigid.

From Formulas for Stress and Strain Roark and Young.

5th edition page 371 table 24.

~

9 2-27

~

Assume Poisson's ratio = 0.2 Maximum stress:

2 2

f,,x =

-0. 4 2pr /t 2

f

= -0.42 (14.7) 85

= 2949 psi Compress-2 (2.75)2 ive The margin of safety for the end plates in bending is:

M.S. = 38,000/2849 - 1 = + large It can therefore be concluded the packaging can safely react an atmospheric pressure of 0.5 times the standard atmospheric pressure.

2.6.4 Vibration Shock and vibration not.nally incident to i

transport are considered to have negligible effects on the Model SGC-1 packaging.

2.6.5 Water Spray, Since the package is constructed of steel this test is not required.

2.6.6 Free Drop This requirement is not applicable to the Model SGC-1 package since the loaded cask is never lifted.

2.6.7 Corner Drop This requirement is not applicable since the Model SGC-1 packaging is fabricated of steel.

~_

i 2-28

)

)

~ -

2.6.8 Penetration From previous container tests, as well r.s engineering judgement, it can be conc 3uded that the 13 pound rod would have negligible effect on the heavy steel shell cf tne cask.

2.6.9 Compression Nc* applicable, due to the weight exceeding 10,000 lbs.

2.7 Hypothetical Accident Conditions Not applicable for Type "A: packages.

2.8 Special Form Since no special form is claimed, this section is not applicable.

2.9 Fiel Rods i

Not applicable.

l 1

w.'

2-29 1

,-.r-. -,

n

-n

E s

2.10 Appendix 9

.s 2-30

(

)

l-. -.

Lateral Tiedown

_f 4 >-

Longitudinal Tiedown N'-

Barge Deck i

l y,

,..-T-;n

_m.__

I i

i I

i i

L_._ __

- 0 Trailer

'j' kl I

k Barge Deck i

x x

v s

I l

Longitudinal Lateral Tiedown Tiedown I

Figure 2-7:

Typical Marir.e Transport Tiedown Configuration i

to i

4

~

3.

THERMAL EVALUATION 3.1 Discussion The mechanical features of the packaging have been described in Section 1.2.1.

There are no special thermal protection subsystems or features.

The external surface of the cask is predicted to exhibit a maximum temperature of 168.7'F.

This prediction is based on an internal heat load of 20 watts.

The assumed conditions are consistent with the Normal Transport " Heat" requirements, specifically:

e Direct sunlight (mid-summer) e Ambient air at 130*F.

e Still air For conservatism, the " peak" solar flux has been assumed to exist continuously.

This is equivalent to assuming 24 hr. sunlight of maximum intensity.

3.2 Summarv of Thermal Properties of Materials Thermal conductivity Steel 26.5 BTC/hr - ft - *R Table 26 ORNL - NSIC - 68 Surface emissivity / absorptivity Dirty white paint external.70 Painted surface internal.85 3.3 Technical Specification of Components Not applicable -- no special thermal subsystems.

3.4 Thermal Evaluation for Normal Conditions of Transport 3-1

'~

-.. m 3.4.1 Thermal Model As outlined in Section 2.6, the unknown external cask temperature was determined by solving for the temperature at which the heat imput to the cask system equaled the heat output.

Input heat consisted of a peak normal solar flux (from figure 5.3 of ORNL -

NSIC - 68) plus the internal decay heat.

Heat output consisted of the sum of free-convection losses and radiation losses to a prescribed ambient air heat sink Jtemperature 130 F-Heat; -400F-Cold.)

Heat loss 0

was " allowed" only over the horizontal cylindrical sides.

Convective film coefficients were taken from convection tables.

3.4.2 Maximum Temperatures Predicted maximum temperatures are:

0 External surfaces 168.7 F Internal surfaces 149 F 3.4.3 Minimum Temperatures External surfaces

- 40 F Internal surfaces

- 39.6 F 3.4.4 Maximum Internal Pressures Assuming the package contains moisture loaded 0

at 70 F.

Under maximum temperatures conditions (149oF), the pressure would increase as shown below:

The partial pressures of water and air at 700F are:

P

= 0.36 psi P

= 14.7

.36 = 14.34 psi a

3-2

l The partial pressures at 149 F are:

P

= 3.71 psi P

= 14.34 (149 + 460) / (70 + 460)

=

16.48 psi The internal pressure differential is thus:

P= 3.71 + 16.48 - 14.7 = 5.49 3.4.5 Maximum Thermal Stress Stresses in the cask are increased by two ways with the increased temperature.

1)

Stresses due to the increased pressure and 2)

Stresses due to the temperature differen-tial from the top of the cask to the bottom.

In section 2.6.3 the critical elements of the cask were evaluated for a pressure differential of 0.5 atm.

(7.35 psi).

The internal pressure due to maximum temperature therefore decreases the stresses predicted in section 2.6.3 by the factor 5.49/7.35 =.75.

The stresses due to the thermal expansion of the top of the cask in relation to the bottom can be determined by examining the restraining forces.

The largest temperature differential is between the top of the cask and the connecting flange.

The bottom half of the cask will be assumed to remain flat.

As the top half curls as indicated it will stress the flange bolts.

3-3

3.4.5 (con't)

,. /

f 7

L I

H

[b

(

R A

Where L= Length of the cask.=

41.5 ft.

excluding the flanges T= Temperature differential between the 0

cask top and the flange. = 19.9 F R= Radius of curvature formed by the expanding top flange.

H= Height of the cask assured to be uniformly 6 ft.

b= Vertical difference between the top flange and the bottom flange.

Coefficiegt of thermal expansion =

(1=

6.5 x 10-A= Angle defined by cord L and radius R.

J L= Length of top of cask = L + aTL 3-4

-r

y.

3.4.5 (con't)

L= 2R Sin A/2 L= 2 (R + b) Rad A/2 Assume A/

is small 2

Therefore sin A/

9' Rad A/

2 2

L= L + aTL L= 2R A/2 A/ " L/

2 2R L= 2RL + 12 L 2R 1R L+

aTL= L + 12 L_

2R R= 6/aT A(R+6) =L #cTL A= L + aTL R+6 A= L aT 6

b= L tan A/ 4 2

For the upper shell

-6 b= L tan A/ = 41.5 tan 41.5 6.5x10 19,9 4

2 2

6 4

-3 b= 4.641105028 x 10 ft Similarly the bottom half will bow upward.

3-5

3.4.5 (con ' t)

A'= L aT 6

b= L/

tan A/

2 4

-6 b= 41.5 tan 41.5 6.5 x 10 12.7 2

6 4

~

b= 2.961911220 x 10 ft.

The cylinder also expands in the circumferential direction.

Each quandrant increases by sat sat = v2R a?

5 4

One half of the increase is in the vertical direction and one half is in the horizontal direction.

Therefore, the flange moves down by:

c= w 2 rat = w2 (6) (6. 5x10-6)(19,9) 4(2)

(4) (2)

~4 6.095475146 x 10 ft The lower flange moves up by:

-6

~4 c'= w (2) (6) 6.5 x10 12.7=3.890077104x10 ft.

4 (2)

By summing the above according to direction the top flange moves away from the bottom flange at the center by 6.80638 x 10-4 ft. if it is not restrained.

However the flange is restrained.

3-6

3.4.5 (con't)

The strain that would be generated on the cask body is:

~4

~4 c ' 6.80638 x 10 ft = 1.1344 x 10 in/in 6

This results on a stress of

~4 6

ft= 1.1344 x10 29 x 10 psi = 3289.75 psi This would load the center bolt as follows:

P= f A

~

P= 3289.75 (2.5) (12) = 98692.59 lbs.

A = 2.3001 sq in = stress area at bolt.

b f

= 98692.54 = 42907.96 psi bol**

i 2.3001 The pressure increase due to the heat gives a pressure differential of 5.49 psi.

Using the ratio of this pressure to that of the 0.5 atmosphere condition the bolt stress can be determined.

~

f = 5.49 3260 + 42907.96 = 45343 psi b

7.35 Plus the clamping stress:

per. " Standard Handbook of Fastening and Joining."

Parmley. Page 24 P=T KD Where:

T= tightening torgue 1b'-in.

K= torque coefficient

.15

.20 D= nominal bolt diameter, inches.

P= clamp load lb.

3-7 e,

-.m-----


y

--,e

~

3.4.5 (con ' t)

~

Torque specification 1600 1 100 ft lbs P= 1700 12 68000lbs.

=

.15 (2) f = P = 68000 = 29564 psi b

A 23001 Total stress on bolt fb total = 45343 + 29564 = 74907 psi Margin of safety = 105,000 -1 = +.40 74,907 The condition of -40 F has no adverse affects

  1. on the package.

There are no large temperature gradients for this condition.

3.4.6 Evaluation 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)

There will be no release of radio-active material from the containment vessel; 2)

The effectiveness of the packaging will not be substantially reduced; 3)

There will be no mixtures of gases or vapors on the package which could, through any credible increase in pressure or an explosion, signifi-cantly reduce the effectiveness of l

the package.

3.5 Hypothetical Thermal Accident Evaluation.

Not applicable for type "A"

packages.

i i

l 3-8 l

3.6 Appendix

-- Thermal Analysis All three modes of heat transfer (conduction, convectional, radiation) were considered in the thermal model.

The model consists of two right horizontal concentric cylinders.

A one foot slice was considered since maximum solar load only was considered by symmetry only one half of the slice was examined.

The slice was segmented into 18 segments and the corresponding heat transfer was examined between each.

All the segments were ident-ical except for the ones containing the flange.

The interface between nodes 10 and 11 has an added thermal resistance due to the bolts and gasket.

This added resistance is small.

The model looked at the worst case conditions at 1300F ambient temperature in still air, with the maximum solar heat load per ORNL - NSIC - 68 Fig. 5.3. page 130.

The internal heat load is only 20 watts.

t i

{

r 3-9

E

=

3.6 Appendix (con' t)

Sector to Sector Conduction.

R i = 1,17 i/9 g

l=x=-10 2rE = 10/

2x (6.1042)=1.0654 it 360 360 2

A=

(2.5) (12) / 144 =.2083 Pt K = 26.5 BTU /HR - ft OR per 4

Table 2.6 of ORNL - NSIC - 68 (1.0654)

=.19297 hr R

R.

=

1 (26.5)(.2083)

BTU Gasket / Flange Recion, R 9 10 10 2"-8 th/in x 10" Bolt 3

W 10 R

l: !;

9 RB G

i i

6

/

i R3 f

11

/

s 4.25" x 7/8" Gasket 11 3-10 M

em

-e-

-se-4--

r-w+

-e 9----

w-g--m y--pyw

3.6 Appendix (cont'd)

Design Condition - Maximum Thermal Difference Model Depth - 12 inches 2

f.

External Shell O

6,,

10' #

s (Typ) 7, 2.5 in.

66 in.

9e 72 in.

20 11 8!

r,

\\

12

  • 15
  • Resistor Type 16 Number 17 1-17 Conduction (shell) 18 18-35 Convection 19 36-71 Radiation Figure 3-1:

Steam Generator / Cask Thermal Model 3-11

3.6 Appendix (con'td)

The model is set up as a thermal resistor model see Tigure 3-2.

The resistor types are as shown in table 3.6.1 Re.e,1stor Number Type 1-17 Conduction 18-35 Convection 36-71 Radiation Conduction heat transfer is considered betweenishell segments and through the flange bolts.

Convenction heat transfer is considered between the external environment and the outer shell.

Radiation heat transfer is considered between the external environment and the outer shell and between the cask shell and the payload.

Conduction Resistors.

q = KAT x

2 q = Heat Transferred = BTU / Er - ft Time Area K = Thermal conducting coefficient = BTU /HR-ft. OF T = Change in temperature A = Area x = Change in position in the direction of heat transfer.

q=T R

R = Thermal resistance R = _x KA 3-12

-w.

3.6 Appendix (cont'd)

R18 Node R54 W

2 R36 0

W W

R$

19 y

p w

5 55 R

J W

37 Noce W

3 R3 0 Node 4 Typical 9

Node

" Node 1 0 20 y

R16 R

W 70 Node 18 w

W W

17 R77 W

W Node 19 Node 1 External Environment Nodes 2-19 Cask Shell Segments Node 20 Payload Figure 3-2:

Thermal Resistor Model 3-13

i 3.6 Arpendix (con ' t)

A = 2.3001 in.'

A = 4.25 in ft.1 ft.= 4.25 ft b

9 12 in 12 K

= 0.087 8 Btu per table A-2,page 635, Ne0prene hr-ft OF Krei th, 3rd Ed., Principles of Heat Transfer.

From above R

=.19297/2 s

1

= 10/12 R

1.96874 Hr -

R b = KA

=

(26.5)(2.3001/144)

BTU b

R

=_1 = ( 7/8) /12

= 2.36650 Hr -

R KA

(.083(4.25/12' BTU 66 Hr UR R9=2R

=

s b

q R +R s

g Convection Resistors R

-R yg 35 Assuming still air, free convection will be the mode of heat transfer.

Free convection is governed by:

q = BTU / r h

h = convective heat transfer coefficient

= BTU / hr = ft F

Tw = Wall temperature F

U T= = Environment temperature F

For horizontal cylinders b

h = 0.27 T

for laminar flow 4

10

<Gr Pr

<10 per Heat Transfer Second Edition by J.P. Holman, page 185, Reference 10.

3-14

1

_s 3.6 Appendix ( con ' t) or h = 0.18 (7)1/3 for turbulent flow Gr Pr

>10' Gr = Grashof's number Pr = Prandtl's number Gr = 5 g L T/Y Where:

S = Volume coefficient of expansion _1 R

g = gravity ft/

2 sec 2

Y = Kinematic Viscosity ft /see T = Change in temperature R

0 Assume approximately 50 R L =-Characteristic length 12 ft.

From Table A-3, Kreith, 3rd Ed. " Principles of Heat Transfer the product Sg/Y for air is:

6 1.76x10 at 100 F 6

0.85 x 10 at'200 F

-1

-3 6

Use 1 x 10.

R ft 0

3 Gr = (1 x 10 ) LT Pr =.699 for air at atmospheric pressure table A-5 page 378 Holman, 2nd Ed.

" Heat Transfer" 6

3 0-Gr Pr = (1 x 10 ) (12 ) (50) (.699) = 6.04 x 10 s-3-15

3.6 Appendix (con ' t)

Therefore the correct mode of heat transfer is turbulent convective heat transfer.

The area associated with this convection mode is:

A = 2wR 27 (72+25) = 1.0836 ft

=

36 36 12 Radiation Resistors a)

External R

-R 36 53 The heat transfered by radiation is governed by 4

4 q = cAc (T

-T2) y Where: c = S tef an - Boltzman constant

-8 BTU / r-ft

= 0.1714 x 10 R

h A = Area ft

1.0836 ft c = Emissivity of the surface For various segments ij * # ^ij 'i c

.95 at 100 F

.18 at solar temperatures

(.1714 x 10~9) (1.0836) (.95)

K..

=

=

13

~9 1.7644 x 10 BTU hr OR b)

Internal Resistors R

~

54 71 K..= c^i

-1+pf,+gb h~"

g, 1

/

13 3

J

-9 1.5670 x 10 BTU hr -

R u

3-16 3

E 3.6 Appendix (con ' t)

II)/

2n (6) 2sR =

A.

1.0472 ft

=

=

1 II-2rR = 2x(5.5)

A.

34.5575 ft

=

=

3 R

F42=

i, 5.5 = 0.9167

'J R.

6 1

From Shappert, " Cask Designers Guide" ORNL-NSIC-68 Table 5.2 page 133 c =. 95 White zine paint g

.94 Roagh steel plate r$

=

Heat Loads a)

Decay heat - Node 20 Assume that the decay heat is spread uniformily through a 30 ft section of the payload.

Decay heat = 20 watts.

q 20 = 20-watts 3.41 BTU / att = 2.27 BTU /,,

W 30 ft b)

Solar Load - Nodes 2-19

Reference:

Shappert, " Cask Designers Guide" ORNL-NSIC-68 Fig. 5.3 page 130 Max solar load 310 BTU /ft -hr 12 noon at latitude 420 Solar heat load for cask.

Horizontal Elements (facing up) l 310 BTU /ft2 - hr Q

=

l u

Vertical Elements O

= 25 BTU /ft2 - hr y

I Horizontal Elements (facing down)

Q

= 0 BTU /ft2 - hr d

l l

l 3-17

[

2 3.6 Appendix (con't) ge = A, (O

cose + O sine)0<0< 90 y

q, = A Q

sine e>90 g

y A = 1.836 ft c =.70 (Dirty white paint)

Table 3.6.1 Cask segment Heat Loads Node 0

q BTU / hr.

2 5

60.66 3

15 59.67 4

25 56.86 5

35 52.33 6

45 46.20 7

55 38.68 8

65 29.97 9

75 20.36 10 85 10.13 11 95 4.86 12 105 4.71 13 115 4.42 14 125 3.99 15 135 3.45 16 145 2.80 i

17 155 2.06 18 165 1.26 19 175 0.42 The above data is used in thermal analyzer computer program called TRAN.

The TRAN thermal analyzer is a lumped parameter analysis method based upon an electrical analogy.

For steady state analysis, a Newtonian iteration method is employed to achieve heat flow balance at a node.

Typically three distinct types of heat transfer must be considered.

s.

3-18

i 3.6.1 (con't)

Conduction:

i 913 =

Rij Where:

g ) = the heat flow from node i to g

node 3 Tg = the temperature at node i.

3 = the temperature at node j T

R.= the linear conduction " resistor" f3 linking nodes i and j.

Convection:

A (T

-T) 9 )= hg3 13 g

3 1

hg3= the convective film coefficient =

GK (T

-T) g 3

K=S iTj

A tabular function of T

y 2

mean film temperature G = A constant for steady state analysis Radiation:

4 4

913 = Kg3 (T1

-Tg)

Where:

K..

= a radiation coefficient of the form 13 Kf3 = Af a or A

a g

1) 1 1

A1 [1

_ y,F..

A.

V ].

/

c.1 1]

]

3-19

~

3.6.1 ijon't)

A.

= Area of Node i 1

1 = Emissivity of Node i c

F )= the view factor from node i to j f

Mathematical Solution Process The steady state solution c;proach simultan-eously " relaxes" all nodes using a Jacobian specifically includes terms for the highly non-linear radiation heat flows.

The mildly non-linear convection heat flows are treated as linear elements subjected to periodic updates once convergence is achieved for the radiation elements.

Specifically the steady state problem can be defined for node i as:

N I

(q13) 0

=

j=1 Using the above process the steady state temperatures were calculated as shown in table 3.6.2.

4

=

I I'

3-20

(

~

Table 3.6.2 Node Temperatures for SGC-1 Conditions 0

Node

-40 F 130 F c=

.70 1

-40.00 130.00 2

-39.88 168.73 3

-39.88 168.14 4

-39.88 166.76 5

-39.88 154.57 6

-39.88 161.58 7

-39.88 157.84 8

-39.88 153.48 9

-39.88 148.84 10

-39.88 144.83 11

-39.88 139.26 12

-39.88 138.86 13

-39.88 138.56 14

-39.88 138.24 15

-39.88 137.87 16

-39.88 137.44 17

-39.88 136.97 18

-39.88 136.50 19

-39.88 136.14 20

-39.63 149.00

\\ _.

3-21

4.0 CONTAINMENT This chapter identifies the package containment for the normal conditions of transport.

4.1 Containment Boundary 4.1.1 Containment Vessel The containment vessel claimed for the Model SGC-1 package is the shielded transportation cask as described in Section 1.2.1.3 and the general arrangement drawing in Appendix 1.3.

4.1.2 Containment Penetration There are no penetrations into the contain-ment vessel.

4.1.3 Seals and Welds A neoprene seal,is placed between the upper shell and lower shell interface flanges.

It is described in Section 1.2.1.3 above.

All joints are arc we?ied.

4.1.4 Closure The closure devices for the lid consist of 112 2-inch diameter high strength bolts as described in Section 1.2.1.2 above.

These bolts will be torqued to 1600 ft-lb. 1100 ft.-lb.

4.2 Requirements for Normal Conditions of Transport The following is an assessment of the package containment under normal conditions of transport as a result of the analysis performed in Sections 2.0 and 3.0 above.

In summary, the containment vessel is not effected by these conditions.

(Refer to Section 2.6 above).

a 4-1

n l

4.2.1 Release of Radioactive Material There is no release of radioactive material from the 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 Contamination This section is not applicable since there are no coolants involved.

i 4.2.4 Coolant Loss Not applicable.

4.3 Containment Requirements for the Hypothetical Accident Conditions Not applicable for Type "A: packages.

1

  • w 4-2

~

5.0 SHIELDING EVALUATION 5.1 Discussion and Results The Model SGC-1 packaging consists of a steel containment 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).

Analysis performed under Chapters 2.0 and 3.0 above 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 individ-ual loadings to assure compliance with applicable regulations.

(.

Q!

5-1

6.0 CRITICALITY EVALUATIOf{

Not applicable for the Model SGC-1 packaging.

l 4

{

s 6-1

2

=

(

7.0 OPERATING PROCEDURES This chapter generally describes the procedures to be used for loading and unloading the Model SGC-1 packaging.

7.1 Procedure for Loading the Package 1)

At the time of loading the package, the lower half of the cask will be secured to the trailer.

The upper half will be on the ground beside the cask.

(For upper half reinoval, see unloading procedures).

2)

Inspect the inside of the shielded cask to assure there are no loose articles within the packaging and assure the cask is not damaged.

3)

Inspect and clean thetflange surface of the lower half.

4)

Lift the contents into the cask and secure it by the use of the tiedowns to the internal saddles.

( '-

5)

Inspect and clean the gasket thoroughly.

Replace the gasket upon signs of wear or deterioration.

6)

Lift the top half to inspect and clean the flange surface.

7)

Place the top half of the cask on the lower half.

Carefr.lly align the bolt holes before final placement.

8)

Secure the top half by fastening the 112 bolts and install the upper half lifting lug hole bolts.

9)

Inspect the package for proper labeling necessary to meet all applicable regulations.

10)

Install an approved securing seal.

l l

l 1"

7-1

I M

7.2 Procedure For Unloading The Package 1)

Move the unopened package to the appropriate unloading area.

2)

Perform an external inspection of the unopened package.

Record any significant or potentially significant observations.

3)

Remove the security seal.

4)

Remove the flange bolts.

5)

Remove the upper half lifting lug hole bolts.

6)

Attach slings and lift the upper half off the cask.

7)

Move the lower half / payload and trailer to the final unloading area under the lifting device.

8)

Remove the internal tiedowns.

l 9)

Lift the payload out of the lower half.

10)

Move the trailer and lower half of the cask out k

from under the payload.

11)

Set the payload down.

12)

Inspect the cask and take any necessary surveys.

13)

Reassemble cask internal tiedowns.

aw 14)

Place the upper half on the lower half per the procedures set forth in Section 7.1.

7.3 Preparation of an Empty Package for Transport i

1)

Follow the same steps as set forth in Section 7.1, except omit the steps involving the contents.

(

7-2 r-w.

-w

~

8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 1

S.1 Acceptance Tests Model SGC-1 pac? caging shall be inrpected and released for use by responsible operating personnel prior to loading.

The following will be included in such inspections:

1)

The entire package, both inside and out, shall be visually inspected and assured that it has not been significantly damaged (no cracks, puncture, holes, nor broken welds).

2)

The exterior stencils must be in place and legible.

3)

All bolts and gaskets must be present and free of defects.

4)

Follow all applicable operating procedures and complete all necessary work fur the handling and operation of the Model SGC-1 Packaging.

8.2 Maintenance Procram k_.

A sound industrial maintenance program shall be followed to insure the integrity of the Model SGC-1 integrity.

Components such as gaskets, bolts and other equipment necessary for the safe and easy operation of the cask should be given regular inspections and repaired or replaced as necessary.

,J 8-1 8

i e

l 9.

QUALITY ASSURANCE The Quality Assurance Program to be applied to the design, fabrication, purchasing, assembly, handling, shipping, inspections, testing use, modification and maintenance of the.Model SGC-1 Packaging will be the the approved Chem-Nuclear Systems Inc.

(CNSI) quality assurance program (See Appendix 9.1) CNSI's top management has approved and fully supports adherence to the policies and procedures contained in the quality assurance program.

The intent of the program is to meet or exceed the requirements of Appendix E of 10 CFR 71.

6 u.

s m

9-1 n

e 6

s 4

A APPENDIX 9.1 og #

9-2 e-

0

(

&S 80 C0 ff o,

UNITED STATES y g. 7,{j[ %

NUCLEAR REGULATORY COMMISSION

_gg c

WASHINGTON, D. C. 20555 y (m\\,i 'T-~%lJ' t

3 OCT 2 1973 FCTR: RHO 71-0231 Chem-Nuclear Systems, Inc.

ATTt!:

fir.. Louis E. Reynolds P.O. Box 1855 Bellevue, WA 99009 Gentlemen:

Enclosed is Quality Assurance Prograr Approval for Radioactive flaterial Packages No. 0231', Revision No. O.

Sincerely,

((~ ~

b

.A Cha/les E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and f4aterial Safety, NMSS

Enclosure:

As stated IG 'LLl' #

3 H h o 9o* 3 M

9-3

~

--,m m

g e

,e

-,,---g

--o-w,_,

w---t-

.s, e

~

(

f Np; pgau 3)g U.S. tvuCLEAR REGULATORY COMrAl"010r.

A P P a o.s A... *.* s t a

  • i:-78' QUALITY ASSURANCE PROGRAM APPROVAL pC
  • 1 FOR RADIOACTIVE MATERIAL PACKAGES O

Pars. ant t tne Ats.e Erer;y Act of 1954. as an enced.the Energy Reorgani:stior* Act of 1974, as amended, am Title 10.

Co:e of Cececal Re;.,:st.:.s. Cha:ter 1. Part 71, and in ret:ance on statements and representations heretofore r. ace in item 5 b, tne ;e son,amec in item 2.the Quality Assurance Pro; ram identif;ec in Item 5 is he'ety approved. This acproval is issued to satisfy the recw.re rents of Section 71.51 of 10 CFR Part 71. This approval is subject to all applicaole rules, regu!ations, and orders of t*.e Nw:Isar negalatory Commission now or hereafter in effe:: and to any conditions specified below.

saug

3. E x *I A ATsON D AT E Che'-Muci ar Systems, Inc.

t staa:T A::nass Januarv 31, 1985 P.O. Sex 1866

  • oo:At7 ~uusta jstATs j zi, caos cit.

Bellevue WA 98009 71-0231 5 o y A 6.T V Ass'uM ANOL P aoO" AM AP'LICATloN OAT EIS)

Sectember 6. 1979

6. C o N Gt T ao Ns A:tivities cenducted under applicable criteria of Appendip E of 10 CFR Part 71 to be exechted with regard to transportation packages by January ', 1950.

i l

(

f.

hpf*bh i

]C}ggIt r i

i j

aenm. r0FTat u s wktsaa ascutATCav covwssion AWUJ a k.hd kDM[ y C(.arlest. MacCo.ald, Chief, Transpectation Certification Branch ' O I373 rs... e4.. e.. g,....,.,,,,,,,,,,,,.g 9-4 .}}